| | Site | Start date | Reporting criterion |
|---|
| WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term | Wolf Creek | 15 November 2018 | |
| WO 08-0001, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process | Wolf Creek | 15 January 2008 | |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions | Wolf Creek | 31 May 2016 | |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls | Wolf Creek | 31 May 2016 | |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements | Wolf Creek | 31 May 2016 | |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 14.0 - Initial Test Program | Wolf Creek | 31 May 2016 | |
| WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 10.0 - Steam and Power Conversion System | Wolf Creek | 31 May 2016 | |
| WM 06-0033, Revision to Technical Specification (TS) 3.7.2, Main Steam Isolation Valves (Msivs), and TS 3.7.3, Main Feedwater Isolation Valves (Mfivs) | Wolf Creek | 25 August 2006 | |
| WBL-25-026, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual | Watts Bar | 5 June 2025 | |
| WBL-23-045, 10 CFR 50.59 Summary Report | Watts Bar | 7 November 2023 | |
| WBL-22-008, 10 CFR 50.59 Summary Report | Watts Bar | 27 April 2022 | |
| WBL-20-049, Augmented Inservice Test Program, Revision 2 | Watts Bar | 21 October 2020 | |
| WBL-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual | Watts Bar | 19 March 2019 | |
| WBL-19-013, 10 CFR 50.59 Summary Report | Watts Bar | 11 April 2019 | |
| W3P89-2163, Responds to Violations Noted in NRC Enforcement Action 89-192 Re Inoperable Main Steam Line Code Safety Valve. Corrective Actions:Mgt Directive Issued Providing Guidance Re Instrumentation Malfunctions During Surveillance Testing | Waterford | 14 December 1989 | |
| W3P85-2115, Forwards Depressurization Capability W/Degraded Auxiliary Pressurizer Spray, Satisfying License Condition 12.Analysis Demonstrates That Sys Can Perform Necessary Depressurization W/Isolation Valve Failing to Open | Waterford | 13 June 1985 | |
| W3P85-1413, Forwards Response to NRC Re Enforcement Action 85-10 Concerning Failure to Perform Hydrostatic Test Per Fsar.Corrective Actions:Field Change Request Initiated on 800806 to Cover Deletion of Use of High Point Vents | Waterford | 21 June 1985 | |
| W3P84-1805, Forwards Proposed FSAR Chapter 14 Changes Re Venting of Sys During Hydrostatic Testing & Testing of nonsafety-related Supplementary Chilled Water Sys.Changes Will Be Incorporated in Future FSAR Amend | Waterford | 29 June 1984 | |
| W3P84-1257, Advises That Main Steam Flow Recorders on Main Steam Lines Between Steam Generators & Main Steam Safety Valves Will Be Used to Record Flow Following Detection of Accident Condition & Closure of Msivs.Procedure Will Be Revised | Waterford | 8 May 1984 | |
| W3P82-3017, Forwards Effects of Vessel Head Voiding During Transients & Accidents in C-E NSSS, in Response to NUREG-0737,Item II.K.2.17 Re Potential for Voiding RCS During Anticipated Transients | Waterford | 2 November 1982 | |
| W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors | Waterford | 25 April 2022 | |
| W3F1-2017-0075, Submittal of the Inservice Testing Plan for the Fourth 10-Year Interval | Waterford | 4 December 2017 | |
| W3F1-2017-0046, Relief Requests Associated with the Fourth Inservice Testing Interval | Waterford | 13 June 2017 | |
| W3F1-2015-0040, License Amendment Request to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.4 | Waterford | 2 July 2015 | |
| W3F1-2011-0010, Submittal of an Update to All Changes Made to Technical Specification Bases for the Period May 25, 2010 Through January 24, 2011 | Waterford | 24 January 2011 | |
| W3F1-2010-0058, WT-2010-10-Draft Outlines | Waterford | 7 July 2010 | |
| W3F1-2010-0047, License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System | Waterford | 20 July 2010 | |
| W3F1-2009-0045, License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-1 | Waterford | 22 October 2009 | |
| W3F1-2007-0031, Technical Specification Bases Update to the NRC for the Period 07/02/2006 Through 06/01/2007 | Waterford | 13 June 2007 | |
| W3F1-2006-0016, To Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program | Waterford | 3 May 2006 | |
| W3F1-2006-0007, Supplement to Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program | Waterford | 15 February 2006 | |
| W3F1-2005-0062, Technical Specification Bases Update to the NRC for the Period October 1, 2004 Through October 31, 2005 | Waterford | 1 December 2005 | |
| W3F1-2005-0040, License Amendment Request NPF-38-262 Proposed Technical Specification Change to Steam Generator Tube Inservice Inspection Program Using Consolidated Line Item Improvement Process | Waterford | 21 July 2005 | |
| W3F1-2004-0095, To Amendment Request NPF-38-256 Alternate Source Term | Waterford | 13 October 2004 | |
| W3F1-2004-0071, Supplement to Alternate Source Term Submittal | Waterford | 19 August 2004 | |
| W3F1-2004-0068, Supplement to Amendment Request NPF-38-249 Extended Power Uprate | Waterford | 10 August 2004 | |
| W3F1-2004-0061, Supplement to Amendment Request NPF-38-249, Extended Power Uprate | Waterford | 28 July 2004 | |
| W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate | Waterford | 14 July 2004 | |
| W3F1-2004-0044, Small Break Loss-of-Coolant Accident Emergency Core Cooling System Performance Analysis | Waterford | 26 May 2004 | |
| W3F1-2004-0017, Supplement to Amendment Request NPF-38-249 Regarding Extended Power Uprate | Waterford | 4 March 2004 | |
| W3F1-2004-0004, Supplemental Information Extended Power Uprate - Power Ascension Testing | Waterford | 29 January 2004 | |
| W3F1-2003-0079, 6 to EP-002-050, Offsite Dose Assessment (Manual) | Waterford | 29 September 2003 | |
| W3F1-2003-0067, Supplement to Amendment Request Main Steam Line Isolation Valves | Waterford | 11 September 2003 | |
| W3F1-2003-0031, Ses Annual Radioactive Effluent Release Report - 2002, Section 3/4.11 - 9.0 Attachments | Waterford | 23 April 2003 | |
| W3F1-2002-0106, Extended Power Uprate Methodologies | Waterford | 16 December 2002 | |
| W3F1-2002-0101, License Amendment Request NPF-38-246 Main Steam Line Isolation Valves | Waterford | 16 December 2002 | |
| W3F1-2002-0005, Ses, Technical Specification Bases Update to NRC for Period September 1, 2002 Through January 15, 2002 | Waterford | 16 January 2002 | |
| ULNRC-06651, License Amendment Request for Risk-Informed Approach to Resolution of Generic Letter 2004-02 | Callaway | 22 July 2021 | |
| ULNRC-06547, Technical Specifications Bases, Chapter B 3.7, Plant Systems | Callaway | 13 November 2019 | |
| ULNRC-06442, 4 to Technical Specification Bases, Table of Contents | Callaway | 19 June 2018 | |
| ULNRC-06414, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado . | Callaway | 23 March 2018 | |
| ULNRC-06174, Licensing Document Change Notice (LDCN)14-0014 Application to Revise TS to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process | Callaway | 9 March 2015 | |
| ULNRC-05947, License Renewal Application, Clarification of Responses to SAMA RAIs to the License Renewal Application | Callaway | 15 January 2013 | |
| ULNRC-05908, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives | Callaway | 24 September 2012 | |
| ULNRC-05808, Facility Operating License NPF-30, License Amendment Application Supplement for a Technical Specification Change That Would Relocate Specific Surveillance Frequencies to a Licensee Controlled Program (LDCN 10-0020) | Callaway | 25 July 2011 | |
| ULNRC-05627, License Amendment Request OL-1253 Elimination of Technical Specification Requirements for Hydrogen Recombiners and Monitors Using the Consolidated Line Item Improvement Process | Callaway | 10 July 2009 | |
| ULNRC-05608, ULNRC-05608, Revision of Technical Specification 3.3.2 and 3.7.3 (License Amendment Request OL-1289) | Callaway | 4 May 2009 | |
| ULNRC-05566, Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised) | Callaway | 4 May 2009 | |
| ULNRC-05463, Revision to Technical Specification Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process (License Amendment Request OL-1287) | Callaway | 14 January 2008 | |
| ULNRC-05445, One-Time Completion Time Extension for Essential Service Water (ESW) System | Callaway | 31 October 2007 | |
| ULNRC-05322, Application for Amendment to License No. NPF-30, Relocation of Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report Adoption of Industry Travelers TSTS-339 and TSTS-363 | Callaway | 17 August 2006 | |
| ULNRC-05280, Proposed Revision to Technical Specification 3.7.2 Main Steam Isolation Valves and Revision to Technical Specification 3.7.3 Main Feedwater Isolation Valves and Main Feedwater Regulating Valve Bypass Valves to Remove Valve Isolation Time | Callaway | 11 May 2006 | |
| ULNRC-05129, Union Electric Company Amended 10 CFR 50.46 Thirty Day Report ECCS Evaluation Model Revisions | Callaway | 9 March 2005 | |
| ULNRC-05123, Transmittal of 10CFR50.46 Thirty-Day Report Regarding ECCS Evaluation Model Revision | Callaway | 8 March 2005 | |
| ULNRC-05056, Technical Specification Revisions Associated with Steam Generator Replacement Project | Callaway | 17 September 2004 | |
| ULNRC-04949, License Amendment Request OL-1251, Emergency Technical Specification Change to Permit One-Time Extension of Required Action Completion Time for Inoperable Turbine Drive Auxiliary Feedwater Pump | Callaway | 5 February 2004 | |
| ULNRC-04928, Responses to RAIs on the Proposed Revision to Technical Specification (TS) 1.1, Definitions, TS 3.7.3, Main Feedwater Isolation Valves (Mfivs), and Steam Generator Tube Rupture with Overfill Re-Analysis | Callaway | 12 December 2003 | |
| ULNRC-04721, Technical Specification Bases Revision 3 | Callaway | 30 August 2002 | |
| ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis | Callaway | 27 June 2003 | |
| ULNRC-03854, Application for Amend to License NPF-30,revising TS 3.7.1.7 Re SG Atmospheric Steam Dump Lines | Callaway | 29 June 1998 | |
| ULNRC-03747, Forwards Responses to Request for Addl Info Re MSSV Setpoint Tolerance Change.W/One Oversize Drawing | Callaway | 4 March 1998 | |
| ULNRC-03696, Forwards Responses to NRC 971113 RAI Re Licensee 970808 Application for Amend to TS Table 3.7-2 to Specify That Lift Valves Be Changed to +3/-1% as-found.Marked-up STS Pages Encl | Callaway | 16 December 1997 | |
| U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval | Clinton | 12 July 2010 | |
| TXX-9826, Application for Amends to Licenses NPF-87 & NPF-89,proposing Increase in Licensed Power for Operation of Cpses,Unit 2 to 3445 Mwt (Approx 1%) & Changes Administratively for Unit 1.Supporting TSs & TR WCAP-10263,encl | Comanche Peak | 21 December 1998 | |
| TXX-9711, Application for Amends to Licenses NPF-87 & NPF-89, Consisting of Change Request 97-002 Re Rev to Unit 2 RT Setpoint | Comanche Peak | 16 May 1997 | |
| TXX-9501, CPSES Annual Operating Rept for 1994 | Comanche Peak | 31 December 1994 | |
| TXX-9109, Annual Operating Rept & Annual 10CFR50.59 Rept for 1990 | Comanche Peak | 31 December 1990 | |
| TXX-8965, Forwards Amend 77 to FSAR W/Typo Corrections Made to Numerical Values in Tables 6.2.1-94 & 6.2.1-95 & Inserting Description of Change Re Main Steam Safety Valves in Table 140.1-1 | Comanche Peak | 8 September 1989 | |
| TXX-8877, Forwards Draft Rev 0 to Comanche Peak Steam Electric Station Tech Spec Improvement Program Tech Spec Requirements, Per NRC Rev 4a of Sts,For Review | Comanche Peak | 17 November 1988 | |
| TXX-6912, Forwards Description of Amend 65 to Fsar.Amend,Transmitted Under Separate Cover,Includes Listed Revs,Including Fire Protection,Electrical Separation,Power Sys,Testing,Util Organization & Electrical Grounding | Comanche Peak | 20 November 1987 | |
| TXX-6468, Responds to NRC Re Violations Noted in Insp Repts 50-445/86-22 & 50-446/86-20.Corrective Actions:Documentation Supplied W/Purchase Order CP-0077 Reviewed for Compliance & Receipt Insp Program Reviewed for Adequacy of Instruction | Comanche Peak | 15 June 1987 | |
| TXX-6396, Responds to NRC Re Violations & Deviations Noted in Insp Repts 50-445/86-22 & 50-446/86-20.Corrective Actions:Required Certification for Valve Bonnet Received from Vendor & Placed in Appropriate Receipt Insp Package | Comanche Peak | 27 April 1987 | |
| TXX-6070, Suppls Response to NRC Re Violation & Deviation Noted in Insp Repts 50-445/86-01 & 50-446/86-01.Corrective Actions:Test Procedures & Data Reviewed & Evaluated to Ensure Adequacy of Auxiliary Feedwater Sys | Comanche Peak | 4 November 1986 | |
| TXX-5048, Responds to NRC Re Violations & Deviations Noted in Insp Repts 50-445/86-01 & 50-446/86-01.Corrective Actions:Nonconformance Repts Issued for All Deviation Repts Not Previously Documented | Comanche Peak | 13 October 1986 | |
| TXX-4382, Forwards Addl Info to Justify Acceptability of Plant Design for Several Accident Monitoring Parameters.Commitment Provided to Modify Design Re Safety Injection Accumulator Pressure & Pressurizer Heater Status | Comanche Peak | 28 January 1985 | |
| TXX-4306, Forwards Addl Info for Resolution of Open Items Re Handling of Heavy Loads,Per NRC 840830 & 0906 Requests Re NUREG-0612, Phase II | Comanche Peak | 24 September 1984 | |
| TXX-4223, Forwards Request for Change to FSAR Table 17A-1 to Satisfy 10CFR50.55(f)(3).Change Clarifies Performance of Leak Tests on Instrument Tubing Between Instrument Isolation Valves & Instruments | Comanche Peak | 13 July 1984 | |
| TXX-3659, Forwards Final Response to NUREG-0612, Control of Heavy Loads at Nuclear Power Plants | Comanche Peak | 8 June 1983 | |
| TXX-3486, Forwards Response to 801222 Generic Ltr Encl 3 Re Design & Operation of Load Handling Sys in Area of Stored Spent Fuel, Reactor Core & Equipment Components for Safe Shutdown,Per NUREG-0612 & SER,NUREG-0797,Suppl 2 Confirmatory Issue 11 | Comanche Peak | 1 March 1982 | |
| TXX-0518, License Amendment Request (LAR) 04-010, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity | Comanche Peak | 16 December 2005 | |
| TXX-0502, Submittal of Txu Powers Application of Non-LOCA Transient Analysis Methodologies to a Feed Ring Steam Generator Design - Topical Report ERX-04-005, Revision 0 | Comanche Peak | 25 January 2005 | |
| TSTF-17-04, Technical Specifications Task Force - Transmittal of TSTF-567, Add Containment Sump TS to Address GSI-191 Issues | Technical Specifications Task Force | 30 March 2017 | |
| TSTF-07-05, TSTF-412, Revision 3, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable | Technical Specifications Task Force | 10 January 2007 | |
| TSTF-06-01, TSTF-412, Revision 2, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable | | 31 January 2006 | |
| TSTF-05-21, TSTF-05-21, Transmittal of TSTF-491, Revision 1, Removal of Main Steam & Main Feedwater Valve Isolation Times from Technical Specifications | | 13 October 2005 | |
| TSTF-05-18, Transmittal of TSTF-491, Revision 0, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications | | 13 September 2005 | |
| TSTF-05-16, TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec | Technical Specifications Task Force | 13 September 2005 | |
| TSTF-04-09, TSTF-426, Revision 0, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c | | 30 August 2004 | |
| TMI-14-002, Draft - Outlines (Folder 2) | Crane | 7 January 2014 | |
| TMI-12-168, Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval | Crane | 7 November 2012 | |
| TMI-12-047, (TMI-1), Biennial 10 CFR 50.59 and Commitment Revision Reports for 2010 and 2011 | Crane | 16 April 2012 | |
| 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 | Crane | 27 May 2011 | |
| 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 | Crane | 21 April 2011 | |
| TMI-10-035, Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves | Crane | 24 September 2010 | |
| 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.. | Crane | 2 July 2009 | |
| SVP-99-032, Application for Amend to License DPR-29,changing SR 4.6.E.2 to Allow one-time Extension of 18-month Requirement to Pressure Set Test or Replace One Half of MSSVs to Interval of 24 Months | Quad Cities | 30 March 1999 | |
| SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With | Quad Cities | 31 January 1999 | |
| SVP-07-001, CFR 50.59/10 CFR 72.48 Summary Report for January 2004 to December 31, 2006 | Quad Cities | 3 January 2007 | |
| SVP-05-082, Main Steam Safety Valve Performance | Quad Cities | 30 December 2005 | |
| SVP-03-096, Submittal of Proposed Relief Requests to the Requirements of 10 CFR 50.55a Concerning the Fourth Ten-Year Interval Inservice Testing Program | Quad Cities | 11 September 2003 | |
| ST-HL-AE-5689, Application for Amend to License NPF-76,incorporating Revs to TS 3.7.1.6, Atmospheric Steam Relief Valves, to Ensure Automatic Feature of SG Power Operated Relief Valve Remains Operable During Modes 1 & 2 | South Texas | 18 August 1997 | |
| ST-HL-AE-5675, Supplement to Application for Amends to Licenses NPF-76 & NPF-80,dtd 960604,requesting Conversion to Improved Std Tss, Per NUREG-1431 | South Texas | 22 July 1997 | |
| ST-HL-AE-5077, Application for Amend to Licenses NPF-76 & NPF-80,revising LCO 3.4.2.2 & Table 3.7-2 of TSs by Relaxing Lift Setting Tolerance of Pressurizer Safety Valves from +1% to +2% & MSSV from +1% to +3% | South Texas | 2 May 1995 | |
| ST-HL-AE-5042, MSSV & Pressurizer Safety Valve Setpoints Discovered Outside Required Tolerances | South Texas | 29 March 1995 | |
| ST-HL-AE-4887, Forwards Requested Summary of Calculation NC-7104,used as Basis for 940429 Proposed TS Amend,Revising TS 3.7.1.1, Turbine Cycle - Safety Valves | South Texas | 8 September 1994 | |
| ST-HL-AE-4750, Application for Amends to Licenses NPF-76 & NPF-80,revising Max Allowable Power Range Neutron Flux High Setpoint When One or More Main Steam Safety Valves Inoperable | South Texas | 29 April 1994 | |
| ST-HL-AE-4166, Special Rept:On 920630,CR Annunciator Lamp 22M01 Window F-1, Isolation Valve Cubicle Temp High Alarmed.Caused by Train D Cubicle Temp.Investigation Into Root Cause Ongoing | South Texas | 29 July 1992 | |
| ST-HL-AE-2279, Forwards Revised Pages 3.6.A-1,3.6.A-2,9.2.9 & 9.2.10 from FSAR Amend 61.Pages Revised to Correct Misprinting of Obverse Pages.Replacement Pages Will Be Included in Future Amend | South Texas | 25 June 1987 | |
| ST-HL-AE-1993, Forwards Annotated Revised Response to NRC Question 122.1 Re Ferritic Matls Used in Fabrication of Safety Class 2 & 3 Components.Rev Will Be Incorporated in Future FSAR Amend | South Texas | 13 April 1987 | |
| ST-HL-AE-1971, Forwards Annotated Revs to FSAR App 3.6.A Re Isolation Valve Cubicle (Ivc) Subcompartment Analysis.Changes Update Ivc Pressure & Temp Analysis Results.Revs Will Be Incorporated in Future FSAR Amend | South Texas | 9 March 1987 | |
| ST-HL-AE-1440, Forwards Responses to Draft SER Open Items 14.2-1,14.2-5, 14.2-6,14.2-7,14.2-9,14.2-12 & 14.2-15.Changes to FSAR Section 14.2 Also Encl | South Texas | 18 October 1985 | |
| ST-HL-AE-1316, Forwards Corrected Notes from Portion of 850626 Meeting W/Mechanical Engineering Branch Re Review of ASME Documentation & Compliance for Selected Mechanical Features. W/One Oversize Drawing.Aperture Card Available in PDR | South Texas | 2 August 1985 | |
| SNRC-1078, Forwards Revs to FSAR Chapter 13, Conduct of Operations & Section 17.2, QA During Operations Phase, Reflecting Operational Readiness.Revs Will Be Included in Forthcoming Rev 33 to FSAR | Shoreham | 5 September 1984 | |
| SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan | Seabrook | 4 January 2022 | |
| SBK-L-18089, License Amendment Request 17-06, Change to the Technical Specification Requirements for Reactor Trip System Instrumentation and Engineered Safety Features Actuation System Instrumentation to Implement WCAP-14333 and WCAP-15376 | Seabrook | 1 November 2019 | |
| SBK-L-16108, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events | Seabrook | 26 July 2016 | |
| SBK-L-16082, Supplement to License Amendment Request 16-01 Request to Extend Containment Leakage Test Frequency | Seabrook | 31 May 2016 | |
| SBK-L-15025, NextEra Energy Seabrook, LLCs Fourth Six-Month 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 | Seabrook | 27 February 2015 | |
| SBK-L-14202, Response to Request for Additional Information Regarding License Amendment 14-03 Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant Operations | Seabrook | 11 December 2014 | |
| SBK-L-14007, Response to Request for Additional Information Regarding License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency. | Seabrook | 29 January 2014 | |
| SBK-L-13030, LAR 13-02 - 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 | Seabrook | 27 March 2013 | |
| SBK-L-12265, Submittal of Changes to the Technical Specification Bases | Seabrook | 19 December 2012 | |
| SBK-L-12185, To Severe Accident Mitigation Alternatives Analysis Response to RAI Request Dated July 16, 2012, NextEra Energy Seabrook License Renewal Application | Seabrook | 13 September 2012 | |
| SBK-L-12053, To Severe Accident Mitigation Alternatives Analysis, License Renewal Application | Seabrook | 19 March 2012 | |
| SBK-L-11132, Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program | Seabrook | 22 June 2011 | |
| SBK-L-11067, Response to Request for Additional Information, NextEra Energy Seabrook License Renewal Application | Seabrook | 18 April 2011 | |
| SBK-L-11001, Response to Request for Additional Information, NextEra Energy License Renewal Application | Seabrook | 13 January 2011 | |
| SBK-L-09269, Submittal of Changes to Technical Specification Bases | Seabrook | 30 December 2009 | |
| SBK-L-08216, Submittal of Changes to Technical Specification Bases | Seabrook | 16 December 2008 | |
| SBK-L-06243, Response to Request for Additional Information Regarding License Amendment Request 06-03, Application for Amendment to Technical Specifications for Miscellaneous Changes | Seabrook | 22 January 2007 | |
| SBK-L-06214, Clarification of Response to RAI Regarding LAR 06-02, Application for Technical Specification Improvement Regarding Steam Generator Integrity Using Consolidated Line Item Improvement Process | Seabrook | 28 November 2006 | |
| SBK-L-06158, Response to Request for Additional Information Regarding License Amendment Request 06-02 Application for Technical Specification Improvement Regarding Steam Generator Integrity Using the Consolidated Line Item Improvement Process | Seabrook | 16 August 2006 | |
| SBK-L-06072, Response to Request for Additional Information Regarding License Amendment Request 05-11, Changes to Technical Specification 3.8.3.1, Onsite Power Distribution, for Vital Inverter Allowed Outage Time | Seabrook | 30 March 2006 | |
| SBK-L-06064, License Amendment Request 06-02, Application for Technical Specification Improvement Regarding Steam Generator Integrity Using the Consolidated Line Item Improvement Process | Seabrook | 23 March 2006 | |
| SBK-L-05054, Supplemental Response to Request for Additional Information Regarding License Amendment Request 04-03, Application for Stretch Power Uprate | Seabrook | 25 February 2005 | |
| SBK-L-05032, Supplemental Response to Request for Additional Information Regarding License Amendment Request 04-03, Application for Stretch Power Uprate | Seabrook | 9 February 2005 | |
| SBK-L-04155, Response to Request for Additional Information Regarding License Amendment Request 03-02 Implementation of Alternate Source Term | Seabrook | 13 January 2005 | |
| SBK-L-04050, Submittal of Changes to the Plant Technical Specification Bases | Seabrook | 2 September 2004 | |
| Regulatory Guide 1.33 | | 28 February 1978 | |
| Regulatory Guide 1.194 | | 1 June 2003 | |
| RS-25-088, Response to Request for Additional Information Related to License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2 to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 | Byron
Braidwood | 21 April 2025 | |
| RS-24-106, Request RV-04, Proposed Alternative to Modify Reactor Pressure Vessel Safety Relief Valve Testing Sampling Requirements Per Inservice Test Program | LaSalle | 25 November 2024 | |
| RS-22-011, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval | Quad Cities | 17 February 2022 | |
| RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements | Peach Bottom
Nine Mile Point
Byron
Braidwood
Limerick
Ginna
Clinton
Quad Cities
FitzPatrick
LaSalle | 30 June 2021 | |
| RS-18-016, License Amendment Request to Utilize the TORMIS Computer Code Methodology | Braidwood | 1 February 2018 | |
| RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 15, Accident and Transient Analysis | Quad Cities | 19 October 2017 | |
| RS-17-125, Relief Request RV-2 Associated with the Fourth Inservice Testing Interval | Byron | 25 September 2017 | |
| RS-17-119, Byron, Units 1 and 2 - Full Action Request Report AR 1284054, Legacy Issues with Main Steam Tunnel Pressurization Calculation, Redacted | Byron | 31 October 2011 | |
| RS-17-119, Braidwood and Byron, Units 1 and 2 - Response to Request for Voluntary Response to Petition Re High Energy Line Break in Main Stream Isolation Value Room | Byron
Braidwood | 1 September 2017 | |
| RS-16-248, Byron/Braidwood Nuclear Stations, Submittal of Revision 16 to Updated Final Safety Analysis Report and Updated Fire Protection Report (Fpr), Amendment 27 | Byron
Braidwood | 15 December 2016 | |
| RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides | Byron
Braidwood | 15 December 2016 | |
| RS-16-223, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | Braidwood | 7 December 2016 | |
| RS-16-205, Relief Requests Associated with the Fourth Interval Inservice Testing Program | LaSalle | 17 October 2016 | |
| RS-16-118, License Amendment Request to Utilize the TORMIS Computer Code Methodology | Byron | 7 October 2016 | |
| RS-16-088, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | Byron | 15 July 2016 | |
| RS-16-021, Sixth Six-Month 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 Number EA-12-049) | Byron | 26 February 2016 | |
| RS-16-020, Sixth Six-Month 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 Number EA-12-049) | Braidwood | 26 February 2016 | |
| RS-15-276, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | Braidwood | 16 December 2015 | |
| RS-15-267, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | Byron | 30 November 2015 | |
| RS-15-253, Withdrawal of Relief Request RV-1 and Revision to Relief Request RG-1 Associated with the Fourth Inservice Testing Interval | Byron | 21 September 2015 | |
| RS-15-209, Fifth Six-Month 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 Number EA-12-049) | Byron | 28 August 2015 | |
| RS-15-208, Fifth Six-Month 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 Number EA-12-049) | Braidwood | 28 August 2015 | |
| RS-15-170, Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval | Byron | 22 June 2015 | |
| RS-15-084, Request for Exemption from 10 CFR 50.55a, Codes and Standards, Paragrapgh (h)(2), Protection Systems | Byron
Braidwood | 6 April 2015 | |
| RS-14-338, Braidwood, Units 1 and 2, Byron, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26. (Redacted Version) | Byron
Braidwood | 15 December 2014 | |
| RS-14-033, Response to NRC Requests for Additional Information for the Severe Accident Mitigation Alternatives Review, Dated January 6, 2014 License Renewal Application | Byron
Braidwood | 4 February 2014 | |
| RS-14-008, Second Six-Month 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 Number EA-12-049) | Byron | 28 February 2014 | |
| RS-14-007, Second Six-Month 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 Number EA-12-049) | Braidwood | 28 February 2014 | |
| RS-13-175, Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs) | Byron
Braidwood | 21 August 2013 | |
| RS-13-098, Response to Request for Additional Information Related to Request for NRC Approval of Relief Requests for Fifth Inservice Testing Interval | Dresden | 1 April 2013 | |
| RS-13-045, Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing Interval | Quad Cities | 25 January 2013 | |
| RS-13-018, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | Byron | 28 February 2013 | |
| RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases | Byron | 14 December 2012 | |
| RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases | Braidwood | 14 December 2012 | |
| RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 15.0 - Accident Analyses | Byron
Braidwood | 14 December 2012 | |
| RS-12-155, Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval | Dresden | 30 October 2012 | |
| RS-12-149, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing Interval | Quad Cities | 13 September 2012 | |
| RS-12-039, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate | Byron
Braidwood | 5 March 2012 | |
| RS-12-026, Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval | Quad Cities | 15 February 2012 | |
| RS-12-006, Units 1 & 2 - License Amendment Request for the Use of an Auxiliary Feedwater Cross-tie Between Units | Byron
Braidwood | 31 January 2012 | |
| RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses | Quad Cities | 19 October 2011 | |
| RS-11-077, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report | Quad Cities | 6 May 2011 | |
| RS-10-087, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report | Quad Cities | 7 May 2010 | |
| RS-09-059, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report | Quad Cities | 7 May 2009 | |
| RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases | Braidwood | 15 December 2008 | |
| RS-08-144, Request for Relief from ASME OM Code 5-Year Test Interval for Safety Relief Valves (Relief Request No. 2210) | Clinton | 3 November 2008 | |
| RS-08-087, License Amendment Request to Administratively Clarify the Operating Licenses and Technical Specifications | Byron
Braidwood | 29 July 2008 | |
| RS-08-080, Request for One-Time Relief from ASME OM Code 5-year Test Interval for Main Steam Electromatic Relief Valve (Relief Request RV-30G, Revision 0) | Quad Cities | 19 June 2008 | |
| RS-08-064, CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors Annual Report | Quad Cities | 7 May 2008 | |
| RS-08-057, Supplemental Information Concerning Requests for Relief from ASME OM Code 5-year Test Interval for Main Steam Safety Valves | Dresden
Quad Cities | 18 April 2008 | |
| RS-08-033, Request for Relief from ASME OM Code 5-year Test Interval for Main Steam Safety Valves (Relief Request RV-30F, Revision 0) and Partial Withdrawal of Relief Request RV-30E, Revision 0 | Quad Cities | 6 March 2008 | |
| RS-08-013, Request for Relief from ASME OM Code 5-year Test Interval for Main Steam Safety Valves (Relief Request RV-02C, Revision 0) | Dresden | 8 February 2008 | |
| RS-07-146, Response to Request for Additional Information Related to Relief Request RV-30E | Quad Cities | 30 October 2007 | |
| RS-07-126, Request for Relief from ASME OM Code 5-year Test Interval for Main Steam Safety Valves (Relief Request RV-30E) | Quad Cities | 7 September 2007 | |
| RS-07-111, Response to Request for Additional Information Related to Relief Request RV-02B | Dresden | 27 July 2007 | |
| RS-07-104, Request for Relief from ASME OM Code 5-Year Test Interval for Two Main Steam Valves (Relief Request RV-02B) | Dresden | 3 July 2007 | |
| RS-07-070, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report | Quad Cities | 7 May 2007 | |
| RS-07-027, Supplemental Response Regarding Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds | Byron
Braidwood
Crane | 21 February 2007 | |
| RS-07-007, Additional Information Supporting Request for License Amendment to Increase Main Steam Safety Valve Life Setpoint Tolerance and Standby Liquid Control System Enrichment | Quad Cities | 24 January 2007 | |
| RS-07-003, Additional Information Supporting Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment | Dresden | 11 January 2007 | |
| RS-06-147, Quad, Units 1 & 2 - Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment | Quad Cities | 7 November 2006 | |
| RS-06-122, Additional Information Supporting Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment | Dresden | 18 August 2006 | |
| RS-06-113, Startup and Power Ascension Testing Following Installation of Acoustic Side Branch Modifications | Quad Cities | 2 August 2006 | |
| RS-06-087, Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment | Dresden | 2 June 2006 | |
| RS-06-067, Startup and Power Ascension Testing Following Installation of Acoustic Side Branch Modifications | Quad Cities | 3 May 2006 | |
| RS-06-064, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual Report | Quad Cities | 5 May 2006 | |
| RS-05-072, Additional Information Supporting Main Steam Safety Valve Setpoint Tolerances and Tolerance Uncertainty Treatment Methodology for Dresden Nuclear Power Station, Units 2 and 3 | Dresden | 26 May 2005 | |
| RS-05-048, Additional Information Supporting Main Steam Safety Valve Setpoint Tolerances and Tolerance Uncertainty Treatment Methodology | Dresden | 15 April 2005 | |
| RS-04-166, Letter Transmitting Dresden, Units 1 and 2 - Main Steam Safety Valve Setpoint Tolerances and Tolerance Uncertainty Treatment Methodology | Dresden | 29 October 2004 | |
| RS-04-111, Additional Information Regarding Request for Technical Specifications Changes Related to Main Steam Safety Valve Operability Requirements | Dresden | 23 July 2004 | |
| RS-04-102, Additional Information Regarding Request for Technical Specifications Changes Related to Main Steam Safety Valve Operability Requirements | Dresden | 8 July 2004 | |
| RS-04-003, Additional Information Regarding Request for Technical Specifications Changes Related to Main Steam Safety Valve Operability Requirements | Dresden | 13 January 2004 | |
| RS-03-224, Additional Information Regarding Request for Technical Specifications Changes Related to Main Steam Safety Valve Operability Requirements | Dresden | 21 November 2003 | |
| RS-03-193, Additional Information Regarding Request for Technical Specifications Changes Related to Main Steam Safety Valve Operability Requirements | Dresden | 10 October 2003 | |
| RS-03-097, Units 1 & 2 - Response to RAI Technical Specifications Change Request - Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) | Byron
Braidwood | 27 May 2003 | |
| RS-03-064, Request for a License Amendment to Revise the Pressurizer Safety Valves Lift Settings | Byron
Braidwood | 27 June 2003 | |
| RS-03-047, Response to a Request for Additional Information Regarding a Technical Specifications Change Request - Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) | Byron
Braidwood | 28 February 2003 | |
| RS-02-175, Request for Technical Specification Changes Related to Main Steam Safety Valve Operability Requirements | Dresden | 10 October 2002 | |
| RS-02-173, Request for License Amendment to Add Technical Specification Surveillance Requirement for Diesel Driven Auxiliary Feedwater Pump | Byron
Braidwood | 12 December 2002 | |
| RS-02-027, Request for Technical Specifications Change, Revision to Technical Specification 3.7.1, Main Steam Safety Valve (Mssvs) | Byron
Braidwood | 7 August 2002 | |
| RNP-RA/15-0053, Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04) | Robinson | 19 August 2015 | |
| RNP-RA/14-0129, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima | Robinson | 17 December 2014 | |
| RNP-RA/14-0042, Transmittal of Technical Specifications Bases Revisions | Robinson | 29 April 2014 | |
| RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions | Robinson | 30 October 2007 | |
| RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions | Robinson | 6 April 2006 | |
| RNP-RA/06-0028, Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process | Robinson | 30 May 2006 | |
| RNP-RA/06-0027, ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis | Robinson | 31 March 2006 | |
| RNP-RA/04-0090, Supplement to Amendment Request Regarding Full Implementation of the Alternative Source Term | Robinson | 22 July 2004 | |
| RNP-RA/04-0014, Supplement to Amendment Request Regarding Full Implementation of the Alternative Source Term | Robinson | 5 March 2004 | |
| RNP-RA/02-0115, Supplement to Amendment Request Regarding Increase of Authorized Reactor Power Level | Robinson | 12 August 2002 | |
| RNP-RA/02-0067, Request for Technical Specifications Change, Full Implementation of Alternative Radiological Source Term | Robinson | 10 May 2002 | |
| RNP-RA/02-0066, Request for Amendment Re Increase Authorized Reactor Core Power Level from 2399 Mwt to 2339 Mwt (Approximately 1.7 Percent) | Robinson | 16 May 2002 | |
| RIS 2000-05, Resolution of Generic Safety Issue 165, Spring-Actuated Safety and Relief Valve Reliability | | 16 March 2000 | |
| RC-99-0147, Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-1988 | Summer | 26 July 1999 | |
| RC-93-0037, Forwards Revised Tech Spec Re Main Steam Safety Valves,Per NRC Request | Summer | 10 February 1993 | |
| RC-18-0091, License Amendment Request - LAR-16-01490 National Fire Protection Association Standard 805 Program Revisions | Summer | 29 August 2018 | |
| RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 12.0, Radiation Protection | Summer | 31 May 2018 | |
| RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System | Summer | 31 May 2018 | |
| RC-16-0143, (VCSNS) Unit 1 - Report of Full Compliance and Final Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design. | Summer | 31 October 2016 | |
| RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System | Summer | 25 May 2016 | |
| RC-16-0048, Submittal of Annual Operating Report for 2015 | Summer | 30 March 2016 | |
| RC-16-0035, (VCSNS) Unit 1 - Exigent License Amendment Request - LAR (16-00848) Technical Specification Change Request for the Emergency Feedwater System Limiting Condition for Operation 3.7.1.2 Action B | Summer | 1 March 2016 | |
| RC-14-0086, Technical Specification Bases Revision Updated Through May 2014 | Summer | 12 June 2014 | |
| RC-13-0069, Request Relief from ASME Code Requirements in VCSNS 4th Ten Year Inservice Inspection Interval | Summer | 16 May 2013 | |
| RC-13-0047, License Amendment Request - LAR 12-03567, Application to Revise Tech Specs to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using Consolidated Line Item Improvement | Summer | 2 April 2013 | |
| RC-13-0028, Overall Integrated Plan as Required by March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Event( Order EA-12-049) | Summer | 28 February 2013 | |
| RC-11-0094, Technical Specification Bases Revision Updated Through June 2011 | Summer | 31 August 2011 | |
| RC-11-0052, License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation | Summer | 2 May 2011 | |
| RC-07-0025, License Amendment Request - LAR 05-3594 Steam Generator Tube Integrity | Summer | 15 February 2007 | |
| RC-06-0084, License Amendment Request - LAR 05-3594, Steam Generator Tube Integrity | Summer | 24 May 2006 | |
| RC-03-0230, October 2003 Monthly Operating Report for Virgil C. Summer | Summer | 6 November 2003 | |
| RBG-47737, Relief Requests for 10-year Updates to the 120-Month Inservice Testing Intervals | River Bend | 27 February 2017 | |
| RBG-47456, Relief Request; ASME Code Case OMN-17, Alternative Rules for Testing ASME Class 1 Pressure Relief/Safety Valves | River Bend | 14 May 2014 | |
| RAIO-1118-63021, LLC Supplemental Response to NRC Request for Additional Information No. 468 (Erai No. 9420) on the Nuscale Design Certification Application | NuScale | 20 November 2018 | |
| RAIO-0818-61360, LLC - Response to NRC Request for Additional Information No. 410 (Erai No. 9310) on the NuScale Design Certification Application | NuScale | 10 August 2018 | |
| RAIO-0718-60804, LLC Response to NRC Request for Additional Information No. 468 (Erai No. 9420) on the NuScale Design Certification Application | NuScale | 9 July 2018 | |
| RAIO-0418-59506, LLC Response to NRC Request for Additional Information No. 368 (Erai No. 9242) on the NuScale Design Certification Application | NuScale | 11 April 2018 | |
| RAIO-0118-58116, LLC Supplemental Response to NRC Request for Additional Information No. 171 (Erai No. 9032) on the NuScale Design Certification Application | NuScale | 10 January 2018 | |
| RA07-045, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report | LaSalle | 1 June 2007 | |
| RA-25-0014, License Amendment Request to Adopt the Full Spectrum Loss of Coolant Accident Methodology and Axiom Fuel Cladding Topical Reports and Associated 10 CFR 50.46 Exemption Request for Use of Axiom Fuel Cladding | Mcguire
Catawba
McGuire | 18 August 2025 | |
| RA-24-0286, Transmittal of Core Operating Limits Report | Robinson | 27 November 2024 | |
| RA-21-0240, Supplement to Relief Requests for Inservice Testing Plan - Sixth Interval | Oconee | 19 August 2021 | |
| RA-21-0169, Relief Requests for Inservice Testing Plan - Sixth Interval | Oconee | 29 July 2021 | |
| RA-21-0095, Relief Requests for Inservice Testing Program Plan - Sixth Ten-Year Interval | Robinson | 29 March 2021 | |
| RA-20-0382, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model | Robinson | 17 December 2020 | |
| RA-20-0223, Supplement to Application to Revise Harris Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b | Harris | 27 July 2020 | |
| RA-18-0213, Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles | Mcguire
McGuire | 1 November 2018 | |
| RA-17-0048, Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2) | Harris
Robinson | 30 October 2017 | |
| RA-14-092, Supplemental Response to RAI Re Request for Extension to Comply with NRC Order EA-13-109: Order Modifying License with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | Oyster Creek | 25 November 2014 | |
| RA-11-089, Submittal of Relief Requests for the Fifth Inservice Testing (IST) Interval | Oyster Creek | 17 November 2011 | |
| Press Release-I-05-028, NRC to Present Preliminary Findings of Millstone 3 Special Inspection | Millstone | 11 May 2005 | |
| Press Release-I-05-022, NRC Begins Special Inspection at Millstone Unit 3 Nuclear Power Plant | Millstone | 20 April 2005 | |
| PNP 2025-003, License Amendment Request to Revise Selected Permanently Defueled Technical Specifications to Support Repairing of Steam Generator Tubes by Sleeving | Palisades | 11 February 2025 | |
| PNP 2021-008, 5 to Updated Final Safety Analysis Report, Chapter 14, Safety Analysis | Palisades | 14 April 2021 | |
| PNP 2019-017, Submittal of Changes to Technical Specifications Bases | Palisades | 21 March 2019 | |
| PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases | Palisades | 8 November 2017 | |
| PNP 2016-005, License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing | Palisades | 11 July 2016 | |
| PNP 2014-074, Relief Request Number RR 4-20 Proposed Alternative, Use of Alternate ASME Code Case N-716 | Palisades | 14 August 2014 | |
| PNP 2013-010, Overall Integrated Plan in Response to March 12, 2012 Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) | Palisades | 28 February 2013 | |
| PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases | Palisades | 9 November 2012 | |
| PNP 2011-032, Report to NRC of Changes of Technical Specifications Bases | Palisades | 25 April 2011 | |
| PNO-V-89-055, on 890906,reactor Shut Down for Greater than 48 H.Test Results Revealed That Valve Blowdown Setting as-found Varied from Required Settings.Licensee Plans to Commence 30-day Outage to Correct Noted Problem | Palo Verde | 6 September 1989 | |
| PNO-V-89-007A, update on PNO-V-89-007 Re Unusual Event Due to Grid Disturbance.Augmented Insp Team (AST) Assembled Onsite on 890304.AST Understanding of Sequence of Events Discussed | Palo Verde | 6 March 1989 | |
| PNO-V-89-007, on 890303,main Generator Tripped Followed by Reactor Power Cutback Due to Main Generator Trip & Reactor Trip on Low Steam Generator 2 Pressure.Increase in One Containment Sump Level Was Noted | Palo Verde | 3 March 1989 | |
| PNO-V-88-058, on 881014,reactor Tripped from Phase Imbalance on 6.9 Kv Power to Four Operating Reactor Coolant Pumps.Grid Disturbance,Which Affected Startup & Auxiliary Transformer Power Sources on One Offsite Power Line,Possible Initiator | Rancho Seco | 14 October 1988 | |
| PNO-V-84-017, on 840331-0401,licensee Discussed Main Steam Safety Valve Failure,Inoperable Radwaste Valve & Loss of Control Room Annunciation | Diablo Canyon | 2 April 1984 | |
| PNO-IV-98-060, on 981201,potential for Reactor SD Greater than 72 H Occurred.Licensee Has Initiated Action to Inspect or Evaluate All of Remaining Flexible Couplings as Result of Failures.Licensee Completing Maint on Balance of Plant | Diablo Canyon | 3 December 1998 | |
| PNO-IV-97-059, on 971024,Unit 2 Experienced Reactor Trip & Safety Injection from 100% Power After Main Steam Isolation Valve Closed.All Plant Safety Sys Operated as Designed During Event.State of CA Notified of Event | Diablo Canyon | 27 October 1997 | |
| PNO-IV-96-062, on 961122,unit 1 Tripped Due to Electrical Fault in Fuse Box Located Between Unit Auxiliary Transformer & Associated Grounding Transformer.Fault Created Fire in Fuse Box.Fire Extinguished.Root Cause Under Investigation | Diablo Canyon | 26 November 1996 | |
| PNO-III-87-118, on 870906,reactor Shut Down.Caused by Reactor Trip Due to Various Equipment Malfunctions.Two Valves Removed for Insp & Events & Malfunctions Under Evaluation. Confirmatory Action Ltr Re Plant Startup Will Be Issued | Davis Besse | 8 September 1987 | |
| PNO-III-85-086, on 850923 & 24,seven of Eight Main Steam Safety Valves Failed to Meet Criteria During Testing at Wylie Labs.Four Valves Leaked After Reseating & Lift Setpoints of Three Lower than Specs.Valves Will Be Reset | Davis Besse | 26 September 1985 | |
| PNO-III-85-045, on 850602,reactor Trip & Main Feedwater Pump Trip Occurred.Caused by High Turbine Vibration.Cause of Main Feedwater Pump Trip Under Investigation.Plant in Hot Standby Mode | Davis Besse | 3 June 1985 | |
| PNO-II-96-060A, on 961004,licensee Notified NRC That Extended Shutdown Was Being Initiated to Accomplish Design Mod to Increase Safety Margins.On 960902,plant Was Shutdown Due to Problem W/Turbine Oil Sys.Meeting Scheduled on 961009 | Crystal River | 4 October 1996 | |
| PNO-I-98-062, on 981211,Millstone Unit 3 Tripped from 100% Reactor Power During MSIV Partial Stroke Testing.Solenoid Valve Integral to MSIV Failed to Reopen When Licensed Operator Released Test Switch | Millstone | 15 December 1998 | |
| PNO-I-89-029, on 890411,unit Tripped from lo-lo Level in Steam Generator as Result of Closure of Msiv.Caused by Faulty Relay in Test Circuitry During Main Steam Valve Cycling Surveillance & Severe Seat Damage.Valves Replaced | Salem | 13 April 1989 | |
| PNO-I-05-017, Alert Declared at Millstone 3 Due to Main Steam Safety Valve Not Reseating After an SI Actuation on Low Main Steam Line Pressure | Millstone | 18 April 2005 | |
| PMNS20241083, Pre-submittal Meeting with Tennessee Valley Authority to Discuss a Proposed Sequoyah Nuclear Plant, Unit 2, Alternative Related to Main Steam Safety Valve Surveillance Requirement 3.7.1.1 | Sequoyah | 27 August 2024 | |
| PLA-6002, Proposed License Amendment Numbers 285 for Unit 1 and 253 for Unit 2, Constant Pressure Power Uprate; Attachment 14 to PLA-6002 Steam Dryer Structural Evaluation, Non-Proprietary | Susquehanna | 31 March 2006 | |
| ONS-2015-113, Fifth 10-Year Inservice Testing Plan, Relief Request No. ON-GRR-01, Grace Period for OM Code Frequencies (Code Case OMN-20) | Oconee | 23 November 2015 | |
| ONS-2015-072, Updated Final Safety Analysis Report, Revision 24, Chapter 9 - Auxiliary Systems | Oconee | 30 June 2015 | |
| ONS-2015-050, Emergency Plan Revision 2015-003 | Oconee | 20 May 2015 | |
| ONS-2014-086, Updated Final Safety Analysis Report, Revision 23, Chapter 9, Auxiliary Systems | Oconee | 30 June 2014 | |
| ONS-2014-007, Emergency Plan Implementing Procedures Manual, Volume C, Revision 2014-003 | Oconee | 4 February 2014 | |
| ONS-2013-015, Emergency Plan, Volume a, Revision 2013-01 | Oconee | 14 November 2013 | |
| NUREG-1431, Informs Utils That Staff Has Incorporated TS Bases Provided by Ltr Into Utils Ts.Rev to TS Bases Encl | Diablo Canyon | 26 December 1995 | |
| NUREG-0857, Supplement No. 8 Safety Evaluate on Report Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 | Palo Verde | 31 May 1985 | |
| NSD-NRC-98-5640, Transmits Rev 4 of Section 3.0, Non-Sys Based Design Descriptions & ITAAC & Section 5.0, Site Parameters of AP600 Certified Design Matl.Changes Made as Result of W Responses to NRC Questions & FSER Open Items Since 970516 | 05200003 | 30 March 1998 | |
| NSD-NRC-97-5467, Forwards Westinghouse Response to RAI 640.97 Re Comments on Design Reliability Assurance Program in Rev 3 of AP600 Certified Design Matl as Requested in Ltr from Staff | 05200003 | 3 December 1997 | |
| NSD-NRC-97-5438, Forwards 3 Copies of W Responses to NRC RAIs 440.731-440.734,relating to AP600 MSSV TS 3.7.2.W Status for Open Item Tracking Sys Item 5998-6001 Are Action N.Status for Item 4464 Is Confirm W to Track Pending SSAR & TS Rev | 05200003 | 17 November 1997 | |
| NSD-NRC-97-5249, Provides Response to NRC Comment 4 Re AP600 SSAR Chapter 15 Accident Analysis, | 05200003 | 29 August 1997 | |
| NSD-NRC-97-5146, Forwards Rev 1 to RAI 440.75 Part C,Response Which Discusses Pressurizer Safety Valve Sizing Analysis to Support Completion of Chapter 5 FSER | 05200003 | 2 June 1997 | |
| NSD-NRC-97-5135, Forwards Draft of SSAR Section 15.6.5.4B.1.0, Small-Break LOCA Analysis Methodology. Markup Section Provided to Facilitate NRC Review of Chapter 15 | 05200003 | 15 May 1997 | |
| NSD-NRC-97-5122, Informs That NRC Has Taken New Position for Creation of AP600 Design Reliability Assurance Program List of Risk Significant Structures,Sys & Components.Position Requests That W Revise AP600 SSAR Section 16.2.Markup,encl | 05200003 | 26 June 1997 | |
| NSD-NRC-97-5029, Forwards Response to NRC Re TS Comments | 05200003 | 27 March 1997 | |
| NSD-NRC-97-4989, Requests Responses to NRC Request for Addl Info & Updates of Status for Several Areas Being Reviewed by Ecgb & Emeb for AP600 | 05200003 | 19 February 1997 | |
| NSD-NRC-96-4917, Forwards Responses to Open Items Re Inservice Testing | 05200003 | 17 December 1996 | |
| NSD-NRC-96-4833, Forwards Roadmap for Content of AP600 Tech Specs Vs NUREG-1431 & Description of General or Overall Changes Whose Explanations Apply to Multiple TS | 05200003 | 11 October 1996 | |
| NRC-94-4254, Forwards Response to NRC Request for Addl Info on AP600 | 05200003 | 3 August 1994 | |
| NRC-94-4249, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from Ltrs 940407,15,29,0505,11,16,23 & 0608. Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a | 05200003 | 29 July 1994 | |
| NRC-94-4234, Forwards Westinghouse Responses to Requests for Addl Info on AP600 from Ltrs of 940428,29,0502,05,11,16,18,23,24,26,0601 & 08.Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a | 05200003 | 22 July 1994 | |
| NRC-86-3112, Forwards Results of Bart Evaluation Model Large Break LOCA 10CFR50.46 Analysis,Demonstrating Acceptability of upper-head Injection Removal in Support of License Amend. Info Re Sys Behavior W/ & W/O upper-head Injection Encl | Mcguire
McGuire | 18 March 1986 | |
| NRC-2017-0197, FRN: Exemption - Millstone Power Station, Unit No. 2 - Request for Exemption from Appendix R to 10 CFR Part 50, Section Iii.G (CAC No. MF8789; EPID L-2016-LLE-0002) | Millstone | 24 October 2017 | |
| NRC-2017-0142, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: July 5, | Wolf Creek
Summer | 19 June 2017 | |
| NRC-2013-0025, Update to Next Era Energy Point Beach. LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3. Seismic | Point Beach | 3 October 2013 | |
| NRC-2012-0158, Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section lll.G.2 | Millstone | 12 July 2012 | |
| NRC-2011-0230, FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations | Calvert Cliffs
Mcguire
Palo Verde
Indian Point
Fermi
Kewaunee
Hope Creek
Grand Gulf
Susquehanna
Surry
North Anna
Waterford
Duane Arnold
Clinton
Cook
Comanche Peak
Yankee Rowe
McGuire
Crane | 22 September 2011 | |
| NRC-2009-0433, FRN: General Notice. Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations | Diablo Canyon | 25 September 2009 | |
| NRC-2002-0094, Supplement to License Amendment Request 226, Measurement Uncertainty Recapture (MUR) Power Uprate | Point Beach | 23 October 2002 | |
| NRC-19-0025, Submittal of Valve Relief Requests for the Inservice Testing Program Fourth 10-Year Interval | Fermi | 29 May 2019 | |
| NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan | Point Beach | 30 September 2022 | |
| NRC 2019-0037, Technical Specification Bases Change Summary | Point Beach | 18 October 2019 | |
| NRC 2018-0022, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Nonconformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile Protection | Point Beach | 26 April 2018 | |
| NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis | Point Beach | 1 September 2016 | |
| NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 10 - Steam and Power Conversion | Point Beach | 1 September 2016 | |
| NRC 2015-0056, Fifth Six-Month 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 Number EA-12-049) | Point Beach | 28 August 2015 | |
| NRC 2015-0025, Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B | Point Beach | 14 May 2015 | |
| NRC 2014-0088, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of | Point Beach | 22 December 2014 | |
| NRC 2014-0013, NextEra Energy Point Beach. LLCs Second Six-Month Status Report in Response to March 12 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Event | Point Beach | 28 February 2014 | |
| NRC 2013-0024, NextEra Energy Point Beach, LLCs Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External. | Point Beach | 22 February 2013 | |
| NRC 2011-0066, License Amendment Request 254, Removal of the Table of Contents from Technical Specifications | Point Beach | 23 June 2011 | |
| NRC 2011-0003, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information | Point Beach | 13 January 2011 | |
| NRC 2010-0145, License Amendment Request 261, Supplement 9 Extended Power Uprate | Point Beach | 21 September 2010 | |
| NRC 2010-0136, License Amendment Request 261 Extended Response to Request for Additional Information | Point Beach | 8 September 2010 | |
| NRC 2010-0129, License Amendment Request 261, Supplement 7, Extended Power Uprate | Point Beach | 24 August 2010 | |
| NRC 2010-0097, Response to Request for Additional Information on License Amendment Request 261, Supplement 5, Extended Power Uprate | Point Beach | 8 July 2010 | |
| NRC 2010-0065, Response to Request for Additional Information on License Amendment Request 261, Extended Power Uprate | Point Beach | 8 July 2010 | |
| NRC 2010-0049, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information | Point Beach | 6 May 2010 | |
| NRC 2010-0005, License Amendment Request 261 Extended Power Uprate Response to Request for Additional Information | Point Beach | 13 January 2010 | |
| NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate | Point Beach | 8 December 2009 | |
| NRC 2009-0094, License Amendment Request 261 Extended Power Uprate Expedited Review Request | Point Beach | 11 September 2009 | |
| NRC 2009-0085, License Amendment Request 241 Alternative Source Term Response to Request for Additional Information | Point Beach | 4 September 2009 | |
| NRC 2009-0066, License Amendment Request 261 Supplement 1 Extended Power Uprate | Point Beach | 17 June 2009 | |
| NRC 2009-0045, Supplement to License Amendment Request 241, Proposed Technical Specifications for Primary Auxiliary Building Ventilation (Vnpab) | Point Beach | 17 April 2009 | |
| NRC 2004-0064, Transmittal of Point Beach, Units 1 and 2 - Emergency Plan Implementing Procedure, Revision to Emergency Action Levels | Point Beach | 15 October 2004 | |
| NRC 2004-0025, Response to Request for Additional Information Regarding Relief Request VRR 03-01 | Point Beach | 15 March 2004 | |
| NRC 2004-0010, Emergency Plan Implementing Procedures Manual and Emergency Plan Manual Revisions | Point Beach | 16 January 2004 | |
| NRC 2003-0106, Response to RAI Regarding License Amendment Request 234, Selective Scope Implementation of Alternative Source Term for Fuel Handling Accident | Point Beach | 30 October 2003 | |
| NRC 2003-0081, Revised Emergency Plan Implementing Procedures | Point Beach | 10 September 2003 | |
| NRC 2003-0046, Annual 10 CFR 50.59 Summary Report for 2002 | Point Beach | 30 June 2003 | |
| NRC 2003-0035, Emergency Plan Implementing Procedure Revisions Point Beach Nuclear Plant, Units 1 & 2 | Point Beach | 14 April 2003 | |
| NRC 2003-0033, Technical Specification Bases Revisions | Point Beach | 9 April 2003 | |
| NRC 2002-0108, Technical Specification Bases Revisions | Point Beach | 10 November 2002 | |
| NRC 2002-0075, Responses to Request for Additional Information License Amendment Request 226, Measurement Uncertainty Recapture Power Uprate | Point Beach | 29 August 2002 | |
| NRC 2002-0030, License Amendment Request 226, Measurement Uncertainty Recapture Power Uprate | Point Beach | 30 April 2002 | |
| NRC 2002-0019, License Amendment Request 224 Control Room Habitability | Point Beach | 28 February 2002 | |
| NPL-98-0110, 1997 Annual Results & Data Rept for Pbnp,Units 1 & 2. W/ | Point Beach | 31 December 1997 | |
| NPL-97-0144, Provides Supplemental Info to TS Change Requests 188 & 189, Requesting Amend to TSs Identified by Analyses Performed in Support of Operations Following Replacement of Steam Generators.Revised TS 14.2.4,encl | Point Beach | 2 April 1997 | |
| NPL-97-0127, Forwards Documentation for Review by NRC to Support Restart Issues as Identified on Unit 2 Startup Commitment List.Items Are Listed | Point Beach | 1 April 1997 | |
| NPL-96-0055, 1995 Annual Results & Data Rept, for Point Beach Nuclear Plant Units 1 & 2 | Point Beach | 31 December 1995 | |
| NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval | South Texas | 28 October 2020 | |
| NOC-AE-17003501, Technical Specification Bases Control Program | South Texas | 3 July 2017 | |
| NOC-AE-140031, Application to Revise Technical Specifications to Adopt TSTF-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, Using the Consolidated Line Item Improvement Process | South Texas | 23 April 2015 | |
| NOC-AE-05001847, Technical Specification Bases Change | South Texas | 15 February 2005 | |
| NOC-AE-04001794, License Amendment Request Revision to Proposed Amendment to Technical Specifications for Steam Generators | South Texas | 5 October 2004 | |
| NOC-AE-04001765, License Amendment Request - Proposed Amendment to Technical Specifications for Steam Generators | South Texas | 12 August 2004 | |
| NOC-AE-04001668, License Amendment Request, Proposed Revision to Technical Specifications Regarding Mode Change Using the Consolidated Line Item Improvement Process | South Texas | 3 February 2004 | |
| NOC-AE-02001333, License Amendment Request, Proposed Changes to Technical Specifications 3.7.1.5 & 3.7.1.7 | South Texas | 23 May 2002 | |
| NOC-AE-02001259, Additional Information to Support Request for Approval of Power Uprate & Revision to Technical Specifications | South Texas | 5 February 2002 | |
| NOC-AE-000565, Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b | South Texas | 16 June 1999 | |
| NOC-AE-000462, Application for Amends to Licenses NPF-76 & NPF-80, Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves | South Texas | 22 March 1999 | |
| NOC-AE-000391, Requests NRC Authorization to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).STP Previously Requested Approval to Incorporate risk-informed Criteria in ISI & IST Programs.Relief Request RR-17 Encl | South Texas | 1 February 1999 | |
| NOC-AE-000213, Informs of Planned Long Term Corrective Actions for Performance During Each Units Next Refueling Outage to Prevent Recurrence of Main Steam Safety Valve Inoperability | South Texas | 2 July 1998 | |
| NOC-AE-00018, Provides 10CFR50.46(a)(3)(ii) Rept as Notification That Complete Reanalysis of Small Break LOCA Was Performed Using Approved ECCS Evaluation Model for Stp,Units 1 & 2.Revised UFSAR Pages Encl | South Texas | 7 July 1998 | |
| NOC-AE-000148, Submits Info Re Operability of Main Steam Safety Valves,Per NRC Request During 980403 Telcon.Response & Commitments Encl | South Texas | 4 May 1998 | |
| NLS8900291, Forwards Response to Generic Ltr 89-06 Re Spds,Including Responses to Checklist Questions & SPDS Photographs.Spds Will Be Modified to Fully Meet NUREG-0737,Suppl 1 & NUREG-1342 Requirements | Cooper | 7 August 1989 | |
| NLS8800365, Forwards Responses to 880422 Request for Addl Info Re Spds. W/One Oversize Drawing | Cooper | 21 July 1988 | |
| NLS2019039, Request for Exception from Certain Leak Testing Interval Requirements of the Cooper Nuclear Station Primary Containment Leakage Rate Testing Program, Docket No. 50-298, License No. DPR-46 | Cooper | 19 August 2019 | |
| NLS2015026, Fifth Ten-Year Interval Pump and Valve Inservice Testing Program Relief Requests | Cooper | 19 March 2015 | |
| NL-89-517, Monthly Operating Rept for May 1989 for Rancho Seco Nuclear Generating Station | Rancho Seco | 31 May 1989 | |
| NL-25-0306, Southern Nuclear Operating Company Vogtle Electric Generating Plant Units 3 and 4, License Amendment Request: Remove Technical Specifications Table of Contents (NL-25-0306) | Vogtle | 27 February 2025 | |
| NL-24-0412, License Amendment Request to Increase Flexibility in Mode Restraints | Vogtle | 19 December 2024 | |
| NL-24-0325, License Amendment Request: Move Surveillance Requirements from Technical Specifications (TS) 3.3.15 and 3.3.16 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic | Vogtle | 24 January 2025 | |
| NL-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) | Vogtle | 24 March 2023 | |
| NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 | Vogtle | 11 April 2023 | |
| NL-21-0845, License Amendment Request: Revise Technical Specification 3.7.2 Limiting Condition for Operation to Remove One Main Steam Isolation Valve System | Vogtle | 30 September 2021 | |
| NL-21-0160, License Amendment Request to Remove Table of Contents from Technical Specifications | Hatch
Vogtle
Farley | 22 June 2021 | |
| NL-20-0275, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues | Farley | 29 May 2020 | |
| NL-19-013, Proposed Technical Specifications Change - Administrative Controls for Permanently Defueled Condition | Indian Point | 15 April 2019 | |
| NL-18-1302, License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line . | Vogtle | 19 December 2018 | |
| NL-18-0541, Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing Requirements | Hatch | 17 April 2018 | |
| NL-18-0408, Proposed Alternative RR-V-12 Regarding Main Steam Safety Relief Valve Testing | Hatch | 9 April 2018 | |
| NL-17-155, Re-Submittal of Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) | Indian Point | 14 December 2017 | |
| NL-17-1367, Response to the Second Request for Additional Information Regarding Alternative Source Term License Amendment Request | Farley | 7 September 2017 | |
| NL-17-0643, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request | Farley | 23 May 2017 | |
| NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 8 Through Chapter 10 | Farley | 20 April 2017 | |
| NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases | Farley | 20 April 2017 | |
| NL-17-0190, Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidate Line Item Improvement Process | Farley | 21 December 2017 | |
| NL-17-0082, Submittal of the Inservice Testing Program Alternatives for the Fifth Ten-Year Interval | Farley | 6 February 2017 | |
| NL-17-002, Response to Request for Additional Information for Review of the License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives | Indian Point | 1 February 2017 | |
| NL-16-2384, Non-Voluntary License Amendment Request to Correct Non-Conservative Technical Specification 3.7.1 | Farley | 22 March 2017 | |
| NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65) | Vogtle | 2 November 2016 | |
| NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2 | Vogtle | 2 November 2016 | |
| NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 10.3 Through Section 15.1 | Vogtle | 2 November 2016 | |
| NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications | Vogtle | 2 November 2016 | |
| NL-16-1431, Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events | Farley | 13 December 2016 | |
| NL-16-1242, Submittal of the Inservice Testing Program Relief Request and Alternatives for Pumps and Valves - Fourth Ten-Year Interval | Vogtle | 28 July 2016 | |
| NL-16-115, Response to Request for Additional Information Regarding Review of Compliance with Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, | Indian Point | 2 December 2016 | |
| NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis | Indian Point | 19 September 2016 | |
| NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 10, Steam and Power Conversion System | Indian Point | 19 September 2016 | |
| NL-16-109, Indian Point 2 Improved Technical Specifications Bases | Indian Point | 19 September 2016 | |
| NL-16-0388, Draft License Amendment Request Regarding Alternative Source Team | Farley | 15 October 2016 | |
| NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 9.0 - Auxiliary Systems, Pages 9.4-1 - 9.5-66 | Watts Bar | 11 September 2015 | |
| NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 7.0 - Instrumentation and Controls | Watts Bar | 11 September 2015 | |
| NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant System | Watts Bar | 11 September 2015 | |
| NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 15.0 - Accident Analyses, Pages 15-i - 15.3-76 | Watts Bar | 11 September 2015 | |
| NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 14.0 - Initial Test Program | Watts Bar | 11 September 2015 | |
| NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 10.0 - Main Steam and Power Conversion System | Watts Bar | 11 September 2015 | |
| NL-15-183, Submittal of Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report | Watts Bar | 11 September 2015 | |
| NL-15-181, Watts Bar Unit 1, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mod | Watts Bar | 3 September 2015 | |
| NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 6 of 9 | Sequoyah | 24 July 2015 | |
| NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 5 of 9 | Sequoyah | 24 July 2015 | |
| NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 4 of 9 | Sequoyah | 24 July 2015 | |
| NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9 | Sequoyah | 24 July 2015 | |
| NL-15-1483, Refueling Outage 1R26 Inservice Inspection Report | Farley | 4 August 2015 | |
| NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8 | Sequoyah | 19 June 2015 | |
| NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8 | Sequoyah | 19 June 2015 | |
| NL-15-081, Additional Information Regarding Entergys Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of | Indian Point | 25 June 2015 | |
| NL-15-062, Response to Request for Additional Information Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years | Indian Point | 20 May 2015 | |
| NL-14-1996, Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.1 | Vogtle | 30 December 2014 | |
| NL-14-1703, Response to Request for Additional Information on LAR to Revise Technical Specifications to Implement NEI-06-09, Rev 0, Risk Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications Guidelines | Vogtle | 11 November 2014 | |
| NL-14-152, Entergys Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From. | Indian Point | 22 December 2014 | |
| NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report, (Ufsar), Revision 25, Chapter 10, Steam and Power Conversion System | Indian Point | 17 September 2014 | |
| NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections | Indian Point | 17 September 2014 | |
| NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 14 - Safety Analysis | Indian Point | 17 September 2014 | |
| NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Appendix a, Introduction | Indian Point | 17 September 2014 | |
| NL-13-1540, Response to Request for Additional Information on License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Rev. 0, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications | Vogtle | 2 August 2013 | |
| NL-13-131, Amendment 14 to License Renewal Application (LRA) | Indian Point | 26 September 2013 | |
| NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 24, Chapter 10 - Steam and Power Conversion System | Indian Point | 26 September 2013 | |
| NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 14, Safety Analysis | Indian Point | 26 September 2013 | |
| NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Appendix a | Indian Point | 26 September 2013 | |
| NL-13-098, Response to Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application | Indian Point | 24 July 2013 | |
| NL-13-0213, Southern Nuclear Operating Co.S Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Re to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049) | Farley | 27 February 2013 | |
| NL-13-0081, 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. | Vogtle
Farley | 23 January 2013 | |
| NL-12-123, Official Exhibit - ENT000580-00-BD01 - NL-12-123, Correction to Previous Responses Regarding Unit 1 Buried Piping and Unit 2 Auxiliary Feedwater Pump Room Fire Event (Sept. 26, 2012) | Indian Point | 26 September 2012 | |
| NL-12-123, Indian Point Nuclear Generating Units 1, 2 & 3 - Correction to Previous Responses Regarding Unit 1 Buried Piping and Unit 2 Auxiliary Feedwater Pump Room Fire Event | Indian Point | 26 September 2012 | |
| NL-12-123, Entergy Pre-Filed Evidentiary Hearing Exhibit ENT000580, NL-12-123, Correction to Previous Responses Regarding Unit 1 Buried Piping and Unit 2 Auxiliary Feedwater Pump Room Fire Event (Sept. 26, 2012) | Indian Point | 26 September 2012 | |
| NL-12-039, Proposed License Amendment Regarding Atmospheric Dump Valves | Indian Point | 23 May 2012 | |
| NL-11-1297, Methods to Be Used in the Implementation of Risk-Informed Technical Specifications Initiative 4b | Vogtle | 27 September 2011 | |
| NL-11-087, Proposed License Amendment Regarding Travelers - TSTF-479-A and TSTF-497-A | Indian Point | 16 September 2011 | |
| NL-10-2375, Page Numbering Scheme Clarification for License Amendment Request for Adoption of TSTF-425-A, Rev. 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program | Vogtle | 7 January 2011 | |
| NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases | Indian Point | 6 October 2010 | |
| NL-09-165, Response to Request for Additional Information on License Renewal Application - SAMA Reanalysis Using Alternate Meteorological Tower Data | Indian Point | 11 December 2009 | |
| NL-09-1510, Vogtle Electric Generation Plant, Unit 2 - 3rd Interval VOGTLE-2 ISI Plan, Version 3.0 | Vogtle | 12 October 2009 | |
| NL-09-1510, Vogtle Electric Generation Plant, Unit 1 - Third 10-Year Interval ISI Plan, Version 3.0 | Vogtle | 12 October 2009 | |
| NL-09-079, Reply to Request for Additional Information Regarding Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire Event | Indian Point | 12 June 2009 | |
| NL-09-076, Indian Point, Units 2 and 3 - Application for Unit 2 Operating License Condition Change and Units 2 and 3 Technical Specification Changes to Add Inter-Unit Spent Fuel Transfer Requirements | Indian Point | 8 July 2009 | |
| NL-09-033, Response to Safety Evaluation Report with Open Items Related to the License Renewal | Indian Point | 12 March 2009 | |
| NL-08-086, Supplemental Reply to Request for Additional Information Regarding License Renewal Application - Severe Accident Mitigation Alternatives Analysis | Indian Point | 22 May 2008 | |
| NL-08-028, Reply to Request for Additional Information Regarding License Renewal Application - Severe Accident Mitigation Alternatives Analysis | Indian Point | 5 February 2008 | |
| NL-07-2168, License Amendment Request to Revise Technical Specifications (TS) 3.3.2, ESFAS Instrumentation, and TS 3.5.4, Refueling Water Storage Tank (Rwst) | Vogtle | 9 January 2008 | |
| NL-07-1760, J. M. Farley, Units 1 and 2 - Relief Request Q1/2B13-RR-V-2, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) | Hope Creek
Farley | 17 September 2007 | |
| NL-07-028, Inservice Testing Program Summary for 4th Interval, Revision 0 | Indian Point | 28 February 2007 | |
| NL-06-1707, NRC Regulatory Conference July 26, 2006 Supplemental Information | Vogtle | 31 July 2006 | |
| NL-06-089, Reply to Request for Additional Information Regarding Proposed License Amendment for Adoption of TSTF 449 | Indian Point | 30 August 2006 | |
| NL-06-020, Application for a Technical Specification Change to Add Spent Fuel Cask Loading Requirements | Indian Point | 10 July 2006 | |
| NL-06-0124, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity | Vogtle | 29 March 2006 | |
| NL-05-0856, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process | Farley | 2 November 2005 | |
| NL-05-045, March 2005 Monthly Operating Report for Indian Point Units, 2 and 3 | Indian Point | 15 April 2005 | |
| NL-05-0211, Inservice Testing Program Summary for the Interval July 1, 1994 Through April 6.2006. Revision 3 | Indian Point | 22 February 2005 | |
| NL-05-013, Reply to RAI Regarding Indian Point Unit 3 Amendment Application for Alternate Source Term | Indian Point | 28 January 2005 | |
| NL-04-1746, Response to Request for Additional Information Related to Request to Revise Technical Specifications - Control Room Habitability | Farley | 27 September 2004 | |
| NL-04-155, Supporting Information for License Amendment Request Regarding Indian Point 3 Stretch Power Uprate | Indian Point | 15 December 2004 | |
| NL-04-1408, Request for Technical Specifications Change Steam Generator Program - Revision I | Farley | 5 August 2004 | |
| NL-04-095, Reply to Supplemental Request for Additional Information Regarding Indian Point 2 Stretch Power Uprate | Indian Point | 3 August 2004 | |
| NL-04-068, Proposed Change to Technical Specifications Regarding Full Scope Adoption of Alternate Source Term | Indian Point | 2 June 2004 | |
| NL-04-0564, And Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors | Hatch
Vogtle
Farley | 21 May 2004 | |
| NL-04-0548, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process | Vogtle | 26 October 2004 | |
| NL-04-0383, Application for License Renewal - February 13, 2004 Requests for Additional Information | Farley | 12 March 2004 | |
| NL-04-005, Supporting Information for License Amendment Request Regarding Indian Point 2 Stretch Power Uprate (TAC Mc 1865) | Indian Point | 12 April 2004 | |
| NL-03-154, To the Indian Point, Unit 2, License Amendment Request for Conversion to Improved Standard Technical Specifications | Indian Point | 8 October 2003 | |