Main Steam Safety Valve

	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-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
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
W3F1-2018-0015, Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 30, 2018	Waterford	30 April 2018
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
W3F1-2016-0012, License Renewal Application Waterford Steam Electric Station, Unit 3 (Waterford 3) (Part 9 of 9)	Waterford	23 March 2016
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
W3F1-2015-0039, Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period April 28,2014 Through April 28,2016	Waterford	28 April 2016
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, Supplement 2 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
W3F1-2004-0110, Report of Facility Changes, Tests and Experiments and Commitment Changes	Waterford	29 November 2004
W3F1-2004-0095, Supplement 3 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, Revision 16 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-06445, Revised Emergency Action Level Technical Basis Document	Callaway	9 July 2018
ULNRC-06442, Revision 14 to Technical Specification Bases, Table of Contents	Callaway	19 June 2018
ULNRC-06433, License Amendment Request for Emergency Action Level (EAL) Changes	Callaway	4 September 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-05725, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (LDCN 10-0020)	Callaway	5 August 2010
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-604633, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 1	Clinton	23 May 2021
U-604555, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 0	Clinton	13 July 2020
U-604457, Third Ten-Year Interval Inservice Testing Program Plan Revision 9	Clinton	21 November 2018
U-604359, Third Ten-Year Interval Lnservice Testing Program Plan, Revision 8	Clinton	20 July 2017
U-604326, Third Ten-Year Interval Inservice Testing Program Plan Revision 7	Clinton	8 March 2017
U-604262, Third Ten-Year Interval Inservice Testing Program Plan, Revision 6	Clinton	15 February 2016
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
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-17-035, Submittal of Changes to Technical Specifications Bases	Three Mile Island	13 April 2017
TMI-16-016, Combined 2015 Annual Radioactive Effluent Release Report	Three Mile Island	29 April 2016
TMI-15-049, Submittal of Changes to Technical Specifications Bases	Three Mile Island	14 April 2015
TMI-15-048, Submittal of the Update to the Fifth Ten-Year Interval Lnservice Testing Program	Three Mile Island	13 April 2015
TMI-14-069, Submittal of the Fifth Ten-Year Interval Inservice Testing Program	Three Mile Island	16 May 2014
TMI-14-055, Submittal of Changes to Technical Specifications Bases	Three Mile Island	10 April 2014
TMI-14-002, Draft - Outlines (Folder 2)	Three Mile Island	7 January 2014
TMI-13-064, Submittal of Changes to Technical Specifications Bases	Three Mile Island	10 April 2013
TMI-12-168, Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval	Three Mile Island	7 November 2012
TMI-12-068, Submittal of Changes to Technical Specifications Bases	Three Mile Island	12 April 2012
TMI-12-047, (TMI-1), Biennial 10 CFR 50.59 and Commitment Revision Reports for 2010 and 2011	Three Mile Island	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.	Three Mile Island	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	Three Mile Island	21 April 2011
TMI-11-064, Submittal of Changes to Technical Specifications Bases	Three Mile Island	15 April 2011
TMI-11-055, PSC Procedure Sq 6.0, Grease Cap Removal Data Sheet 6.0, July 31, 2009, Rev. 0	Three Mile Island	31 July 2009
TMI-10-046, Submittal of Changes to Technical Specifications Bases	Three Mile Island	22 April 2010
TMI-10-035, Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves	Three Mile Island	24 September 2010
TMI-10-033, TMI Unit 1 T1 R18 Outage ASME Code Section XI Inservice Inspection (ISI) Form NIS-1 Owner'S Report for Inservice Inspections, Part I, TMI Unit 1 Form NIS-2 Owner'S Report for Repairs or Replacements, and Topical Report Number 203, Part 2	Three Mile Island	21 April 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....	Three Mile Island	2 July 2009
TMI-09-052, Submittal of Changes to Technical Specifications Bases	Three Mile Island	17 April 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-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-20132, Fourth Interval Inservice Testing (IST) Program	Seabrook	21 October 2020
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-16100, Inservice Testing Program for the Third 10-Year Interval	Seabrook	21 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, Llc'S 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-1	Seabrook	27 February 2015
SBK-L-14229, Expedited Seismic Evaluation Process Report (CEUS Sites) Related to the 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...	Seabrook	19 December 2014
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, Supplement 3 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, Supplement 2 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-09118, License Amendment Request 09-03, Revision to Technical Specification 6.7.6.k, Steam Generator (SG) Program, for Permanent Alternate Repair Criteria (H)	Seabrook	28 May 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 1.194		1 June 2003
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-16-087, 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)	Three Mile Island	29 June 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-13-062, Fifth Ten-Year Interval Inservice Testing Program	Quad Cities	25 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-12-175, Report No. 12Q0108.70-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Three Mile Island Unit 1, Cover Through Page B-209	Three Mile Island	7 November 2012
RS-12-155, Submittal of Relief Requests Associated with the Fifth Lnservice 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-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-10-030, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)	Byron	15 February 2010
RS-10-029, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program	Braidwood	15 February 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, Technical Specification Bases	Byron	15 December 2008
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 Three Mile Island Braidwood	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-05-130, Fourth Ten-Year Interval Inservice Testing Program	Quad Cities	29 September 2005
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/13-0117, License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation	Robinson	10 February 2014
RNP-RA/12-0064, Response to NRC Request for Additional Information Related to Relief Requests (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program Plan	Robinson	4 June 2012
RNP-RA/12-0056, Response to NRC Request for Additional Information for the Fifth Ten-Year Interval Inservice Testing Program Plan	Robinson	10 May 2012
RNP-RA/12-0017, Inservice Testing Program Plan for the Fifth-Ten Year Interval	Robinson	16 March 2012
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/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-09-0004, License Amendment Request - LAR 04-02911 License Amendment and Related Technical Specification Changes to Implement Full-scope Alternative Source Term in Accordance with 10 CFR 50.67	Summer	17 February 2009
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
RA07-045, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report	LaSalle	1 June 2007
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-20-0032, License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits	Harris	6 March 2020
RA-19-0144, License Amendment Request for Measurement Uncertainty Recapture Power Uprate	Oconee	19 February 2020
RA-18-0219, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes	Catawba	4 December 2018
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-18-0106, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement and Request for Additional Information Response	Harris	19 September 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-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P	Harris Robinson	3 October 2016
RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.	Harris Robinson	19 November 2015
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 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 2019-004, License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b	Palisades	28 March 2019
PNP 2017-067, Submittal of Changes to Palisades Nuclear Plant Technical Specifications Bases	Palisades	8 November 2017
PNP 2016-006, Inservice Testing Program Plan Fifth 10-Year Interval	Palisades	28 April 2016
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 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-89-007, 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-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-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-2015-071, Submittal of Emergency Plan Revision 2015-004	Oconee	25 June 2015
ONS-2015-050, Emergency Plan Revision 2015-003	Oconee	20 May 2015
ONS-2014-165, Emergency Plan Revision 2014-003	Oconee	19 January 2015
ONS-2014-146, Emergency Plan Revision 2014-002	Oconee	10 November 2014
ONS-2014-086, Updated Final Safety Analysis Report, Revision 23, Chapter 9, Auxiliary Systems	Oconee	30 June 2014
ONS-2014-065, Emergency Plan Implementing Procedures Manual Volume a, Revision 2014-001	Oconee	22 May 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-2103, Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000 Pressurized Water Reactors Final Report		31 January 2021
NUREG-1231, Forwards NUREG-1231, SER Re B&W Owners Group Plant Reassessment Program. NRC Unable to Reach Final Conclusion on Acceptability of Human Factors Portion of Program. Consideration of NRC Recommendations Requested	Davis Besse Oconee Arkansas Nuclear Three Mile Island Crystal River Rancho Seco Bellefonte 05000000	6 November 1987
NUREG-1122, Rev. 3 Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors		30 September 2020
NUREG-0787, Safety Evaluation Report Related to the Operation of Waterford Steam Electric Station, Unit 3 (Redacted)	Waterford	31 July 1981
NUREG-0750 Volume 87, Nuclear Regulatory Commission Issuances: Opinions and Decisions of the Nuclear Regulatory Commission with Selected Orders (January 1, 2018 - June 30, 2018).		10 May 2019
NUREG-0544, Forwards Revised Draft NUREG-0544,Rev 4, NRC Collection of Abbreviations. Requests Comments & Concurrence by 970930		2 September 1997
NSD-NRC-98-5788, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided	05200003	15 September 1998
NSD-NRC-98-5719, Forwards Comments on AP600 Advanced Final Safety Evaluation Rept	05200003	19 June 1998
NSD-NRC-98-5695, Forwards Markup of AP600 TSs for Review.Markup Will Be Incorporated in Ssar,Rev 23.Encl Table Provides Summary of Changes	05200003	15 May 1998
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-98-5613, Forwards Markup of AP600 TSs Which Will Be Incorporated in Ssar Rev 22 & Includes All Open Items Which Have Been Resolved to Date for NRC Review.Summary of Changes & Open Items Which Directed Change,Encl in Table 1	05200003	13 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-97-5153, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 970423-0512	05200003	27 May 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-97-5031, Forwards Formal Transmittal of mark-up Ssar Sections Open Items & Draft Responses to NRC Questions Previously Submitted Informerly	05200003	1 April 1997
NSD-NRC-97-5029, Forwards Response to NRC Re TS Comments	05200003	27 March 1997
NSD-NRC-97-4998, Forwards Informal Correspondence Previously Sent to NRC Re Ssar	05200003	25 February 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 Three Mile Island Susquehanna Surry North Anna Waterford Duane Arnold Clinton Cook Comanche Peak Yankee Rowe McGuire	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 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 2017-0041, to License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors	Point Beach	21 August 2017
NRC 2017-0028, License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.	Point Beach	23 June 2017
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 2015-0072, Notification of Full Compliance with Order EA-12-049, Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events and Submittal of Final Integrated Plan	Point Beach	16 December 2015
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. Llc'S 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, Llc'S 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 2010-0105, License Amendment Request 261, Supplement 6 Extended Power Uprate	Point Beach	28 July 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 2009-0030, License Amendment Request 261, Extended Power Uprate	Point Beach	7 April 2009
NRC 2008-0081, Submittal of License Amendment Request 241, Alternative Source Term	Point Beach	8 December 2008
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-15003311, Notification of Full Compliance with Order EA-12-049 for Mitigation Strategies for Beyond Design Basis External Events and Update for Order EA-12-051 for Reliable Spent Fuel Pool Instrumentation	South Texas	17 February 2016
NOC-AE-14003116, 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-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
NLS8400169, Rev 3 to Inservice Testing Program	Cooper	30 June 1984
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
NLS2016012, Fifth Ten-Year Interval Inservice Testing Program	Cooper	9 March 2016
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-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-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications	Indian Point	28 April 2020
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-19-026, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications	Indian Point	15 April 2019
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-18-0815, Tornado Missile Risk Evaluator: SNC Response to NRC Request for Additional Information	Vogtle	26 July 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-17-1197, Fourth Ten-Year Interval Lnservice Testing Program Update	Vogtle	23 October 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 Lnservice 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-16-0388, Draft License Amendment Request Regarding Alternative Source Team	Farley	15 October 2016
NL-16-0388, Alternative Source Term License Amendment Request	Farley	22 November 2016
NL-16-0228, Notification of Full Compliance of Required Action for NRC Order EA-12-049, Mitigation Strategies for Beyond-Design-Basis External Events	Vogtle	23 May 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 Entergy'S 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, Entergy'S 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-14-0706, Application to Revise Technical Specifications to Adopt Previously NRC-Approved Generic Technical Specification Changes	Vogtle	18 July 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
... further results