Main Steam Safety Valve

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 SiteStart dateReporting criterion
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC QuestionsWolf Creek31 May 2016
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and ControlsWolf Creek31 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 RequirementsWolf Creek31 May 2016
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 14.0 - Initial Test ProgramWolf Creek31 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 SystemWolf Creek31 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 Creek25 August 2006
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 ProcessCallaway9 March 2015
ULNRC-05947, License Renewal Application, Clarification of Responses to SAMA RAIs to the License Renewal ApplicationCallaway15 January 2013
ULNRC-05908, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation AlternativesCallaway24 September 2012
ULNRC-05908, Callaway, Unit 1, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation AlternativesCallaway24 September 2012
ULNRC-05830, Environmental Report; Operating License Renewal Stage Final, Attachment E Through EndCallaway15 December 2011
ULNRC-05830, Callaway, Unit 1, Environmental Report; Operating License Renewal Stage Final, Attachment E Through EndCallaway15 December 2011
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)Callaway25 July 2011
ULNRC-05774, Attachment 1 - Technical Specification Page Mark UpCallaway3 November 2011
ULNRC-05627, License Amendment Request OL-1253 Elimination of Technical Specification Requirements for Hydrogen Recombiners and Monitors Using the Consolidated Line Item Improvement ProcessCallaway10 July 2009
ULNRC-05627, Callaway, Unit 1 - License Amendment Request OL-1253 Elimination of Technical Specification Requirements for Hydrogen Recombiners and Monitors Using the Consolidated Line Item Improvement ProcessCallaway10 July 2009
ULNRC-05608, ULNRC-05608, Revision of Technical Specification 3.3.2 and 3.7.3 (License Amendment Request OL-1289)Callaway4 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)Callaway4 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)Callaway14 January 2008
ULNRC-05445, Callaway - One-Time Completion Time Extension for Essential Service Water (ESW) SystemCallaway31 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-363Callaway17 August 2006
ULNRC-05280, Callaway 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 IsolaCallaway11 May 2006
TSTF-07-05, TSTF-412, Revision 3, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable.Technical Specifications Task Force10 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-05-16, TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec.Technical Specifications Task Force13 September 2005
TSTF-04-09, TSTF-426, Revision 0, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c30 August 2004
TMI-16-016, Combined 2015 Annual Radioactive Effluent Release ReportThree Mile Island29 April 2016
TMI-15-049, Submittal of Changes to Technical Specifications BasesThree Mile Island14 April 2015
TMI-15-048, Submittal of the Update to the Fifth Ten-Year Interval Lnservice Testing ProgramThree Mile Island13 April 2015
TMI-14-069, Submittal of the Fifth Ten-Year Interval Inservice Testing ProgramThree Mile Island16 May 2014
TMI-14-055, Submittal of Changes to Technical Specifications BasesThree Mile Island10 April 2014
TMI-14-002, Draft - Outlines (Folder 2)Three Mile Island7 January 2014
TMI-13-064, Submittal of Changes to Technical Specifications BasesThree Mile Island10 April 2013
TMI-12-168, Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) IntervalThree Mile Island7 November 2012
TMI-12-068, Submittal of Changes to Technical Specifications BasesThree Mile Island12 April 2012
TMI-12-047, Three Mile Island Nuclear Station, Unit 1 (TMI-1), Biennial 10 CFR 50.59 and Commitment Revision Reports for 2010 and 2011Three Mile Island16 April 2012
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 ValvesThree Mile Island21 April 2011
TMI-11-064, Submittal of Changes to Technical Specifications BasesThree Mile Island15 April 2011
TMI-10-046, Submittal of Changes to Technical Specifications BasesThree Mile Island22 April 2010
TMI-10-035, Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety ValvesThree Mile Island24 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 2Three Mile Island21 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 Island2 July 2009
TMI-09-052, Submittal of Changes to Technical Specifications BasesThree Mile Island17 April 2009
SVP-05-082, Quad Cities, Units 1 & 2 Main Steam Safety Valve PerformanceQuad Cities30 December 2005
SBK-L-16108, Seabrook, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External EventsSeabrook26 July 2016
SBK-L-16100, Seabrook Station - Inservice Testing Program for the Third 10-Year IntervalSeabrook21 July 2016
SBK-L-16082, Seabrook Station - Supplement to License Amendment Request 16-01 Request to Extend Containment Leakage Test FrequencySeabrook31 May 2016
SBK-L-15025, Seabrook, 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 (OrdeSeabrook27 February 2015
SBK-L-14229, Seabrook Station, 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 froSeabrook19 December 2014
SBK-L-14202, Seabrook - Response to Request for Additional Information Regarding License Amendment 14-03 Changes to Technical Specification 3.3.3.1, Radiation Monitoring for Plant OperationsSeabrook11 December 2014
SBK-L-14007, Seabrook Station - 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 SurveillancSeabrook29 January 2014
SBK-L-13030, Seabrook Station, 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 ProcessSeabrook27 March 2013
SBK-L-12265, Seabrook Station - Submittal of Changes to the Technical Specification BasesSeabrook19 December 2012
SBK-L-12185, Seabrook Station, Supplement 3 to Severe Accident Mitigation Alternatives Analysis Response to RAI Request Dated July 16, 2012, NextEra Energy Seabrook License Renewal ApplicationSeabrook13 September 2012
SBK-L-12053, Seabrook Station, Supplement 2 to Severe Accident Mitigation Alternatives Analysis, License Renewal ApplicationSeabrook19 March 2012
SBK-L-11132, Seabrook, Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection ProgramSeabrook22 June 2011
SBK-L-11067, Seabrook Station - Response to Request for Additional Information, NextEra Energy Seabrook License Renewal ApplicationSeabrook18 April 2011
SBK-L-11001, Seabrook - Response to Request for Additional Information, NextEra Energy License Renewal ApplicationSeabrook13 January 2011
SBK-L-09269, Seabrook Station, Submittal of Changes to Technical Specification BasesSeabrook30 December 2009
SBK-L-08216, Seabrook Station Submittal of Changes to Technical Specification BasesSeabrook16 December 2008
SBK-L-06243, Seabrook Station - Response to Request for Additional Information Regarding License Amendment Request 06-03, Application for Amendment to Technical Specifications for Miscellaneous ChangesSeabrook22 January 2007
SBK-L-06214, Seabrook - Clarification of Response to RAI Regarding LAR 06-02, Application for Technical Specification Improvement Regarding Steam Generator Integrity Using Consolidated Line Item Improvement Process.Seabrook28 November 2006
SBK-L-06158, Seabrook Station - 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 ImprovemSeabrook16 August 2006
SBK-L-06072, Seabrook, 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.Seabrook30 March 2006
SBK-L-06064, Seabrook Station, License Amendment Request 06-02, Application for Technical Specification Improvement Regarding Steam Generator Integrity Using the Consolidated Line Item Improvement ProcessSeabrook23 March 2006
Regulatory Guide 1.3331 January 1977
Regulatory Guide 1.1941 June 2003
RS-18-016, License Amendment Request to Utilize the Tormis Computer Code MethodologyBraidwood1 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 AnalysisQuad Cities19 October 2017
RS-17-125, Relief Request RV-2 Associated with the Fourth Inservice Testing IntervalByron25 September 2017
RS-17-119, Byron, Units 1 and 2 - Full Action Request Report AR 1284054, Legacy Issues with Main Steam Tunnel Pressurization Calculation, RedactedByron31 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 RoomByron
Braidwood
1 September 2017
RS-17-061, Quad Cities and R.E. Ginna - Exelon Nuclear Radiological Emergency Plan Addendum Revisions, Including Revision 3 to EP-AA-1006, Addendum 3 and Revision 4 to EP-AA-1012, Addendum 3Ginna
Quad Cities
07200067
3 May 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 27Braidwood
07200073
15 December 2016
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory GuidesBraidwood
07200073
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)Braidwood7 December 2016
RS-16-223, Braidwood Station, Unit 1 - 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)Braidwood7 December 2016
RS-16-205, LaSalle County Station, Units 1 and 2 - Relief Requests Associated with the Fourth Interval Inservice Testing ProgramLaSalle17 October 2016
RS-16-118, License Amendment Request to Utilize the Tormis Computer Code MethodologyByron7 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)Byron15 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)Byron26 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)Braidwood26 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)Braidwood16 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)Byron30 November 2015
RS-15-253, Withdrawal of Relief Request RV-1 and Revision to Relief Request RG-1 Associated with the Fourth Inservice Testing IntervalByron21 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)Byron28 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)Braidwood28 August 2015
RS-15-170, Submittal of Relief Requests Associated with the Fourth Inservice Testing IntervalByron22 June 2015
RS-15-084, Byron Station, Units 1 and 2 - 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)Braidwood
07200073
15 December 2014
RS-14-033, Braidwood, Units 1 & 2 and Byron Units 1 & 2, Response to NRC Requests for Additional Information for the Severe Accident Mitigation Alternatives Review, Dated January 6, 2014 License Renewal ApplicationByron
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)Byron28 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)Braidwood28 February 2014
RS-13-175, Braidwood, Units 1 and 2 and 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 (TAC Nos. ME9871 and ME9872)Dresden1 April 2013
RS-13-062, Fifth Ten-Year Interval Inservice Testing ProgramQuad Cities25 February 2013
RS-13-045, Additional Information Regarding Relief Request RV-06 Associated with the Fifth Inservice Testing IntervalQuad Cities25 January 2013
RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases14 December 2012
RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications BasesBraidwood
07200073
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 AnalysesBraidwood
07200073
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-209Three Mile Island7 November 2012
RS-12-155, Submittal of Relief Requests Associated with the Fifth Lnservice Testing IntervalDresden30 October 2012
RS-12-149, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing IntervalQuad Cities13 September 2012
RS-12-039, Byron Station, Units 1 & 2, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power UprateByron
Braidwood
5 March 2012
RS-12-026, Quad Cities, Units 1 and 2- Submittal of Relief Requests Associated with the Fifth Inservice Testing IntervalQuad Cities15 February 2012
RS-12-006, Braidwood and Byron Station, Units 1 & 2 - License Amendment Request for the Use of an Auxiliary Feedwater Cross-tie Between UnitsByron
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 AnalysesQuad Cities19 October 2011
RS-11-077, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual ReportQuad Cities6 May 2011
RS-10-087, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual ReportQuad Cities7 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)Byron15 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 ProgramBraidwood15 February 2010
RS-09-059, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual ReportQuad Cities7 May 2009
RS-08-161, Technical Specification BasesByron15 December 2008
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification BasesBraidwood15 December 2008
RS-08-144, Request for Relief from ASME OM Code 5-Year Test Interval for Safety Relief Valves (Relief Request No. 2210)Clinton3 November 2008
RS-08-087, and Byron Station, Units 1 and 2, License Amendment Request to Administratively Clarify the Operating Licenses and Technical SpecificationsByron
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 Cities19 June 2008
RS-08-064, 10 CFR 50.46 Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors Annual ReportQuad Cities7 May 2008
RS-08-057, Quad Cities, Units 1 and 2 - Supplemental Information Concerning Requests for Relief from ASME OM Code 5-year Test Interval for Main Steam Safety ValvesDresden
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 0Quad Cities6 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)Dresden8 February 2008
RS-07-146, Response to Request for Additional Information Related to Relief Request RV-30EQuad Cities30 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 Cities7 September 2007
RS-07-111, Response to Request for Additional Information Related to Relief Request RV-02BDresden27 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)Dresden3 July 2007
RS-07-070, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual ReportQuad Cities7 May 2007
RS-07-027, Byron, Unit 2 and Three Mile Island, Unit 1, Supplemental Response Regarding Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt WeldsThree Mile Island
Byron
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 EnrichmentQuad Cities24 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 EnrichmentDresden11 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 EnrichmentQuad Cities7 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 EnrichmentDresden18 August 2006
RS-06-113, Startup and Power Ascension Testing Following Installation of Acoustic Side Branch ModificationsQuad Cities2 August 2006
RS-06-087, Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System EnrichmentDresden2 June 2006
RS-06-067, Startup and Power Ascension Testing Following Installation of Acoustic Side Branch ModificationsQuad Cities3 May 2006
RS-06-064, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual ReportQuad Cities5 May 2006
RS-05-005, Exelon Letter RS-05-005, Dated 1/05/05, Submittal of Information Regarding Extended Power Uprate Vulnerability ReviewsDresden
Quad Cities
5 January 2005
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)Robinson19 August 2015
RNP-RA/14-0129, H. B. Robinson, Unit 2 - 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 thRobinson17 December 2014
RNP-RA/14-0042, Transmittal of Technical Specifications Bases RevisionsRobinson29 April 2014
RNP-RA/13-0117, License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) InstrumentationRobinson10 February 2014
RNP-RA/12-0064, H. B. Robinson - Response to NRC Request for Additional Information Related to Relief Requests (RR)-2 for the Fifth Ten-Year Interval Inservice Testing Program PlanRobinson4 June 2012
RNP-RA/12-0056, Response to NRC Request for Additional Information for the Fifth Ten-Year Interval Inservice Testing Program PlanRobinson10 May 2012
RNP-RA/12-0056, H. B. Robinson, Unit 2 - Response to NRC Request for Additional Information for the Fifth Ten-Year Interval Inservice Testing Program PlanRobinson10 May 2012
RNP-RA/12-0017, H. B. Robinson Steam Electric Plant Unit 2 - Inservice Testing Program Plan for the Fifth-Ten Year IntervalRobinson16 March 2012
RNP-RA/07-0108, H. B. Robinson, Unit 2 - Transmittal of Technical Specifications Bases RevisionsRobinson30 October 2007
RNP-RA/06-0033, Transmittal of Technical Specifications Bases RevisionsRobinson6 April 2006
RNP-RA/06-0028, H. B. Robinson - Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement ProcessRobinson30 May 2006
RNP-RA/06-0027, H. B. Robinson, Unit 2 - ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis.Robinson31 March 2006
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 12.0, Radiation ProtectionSummer31 May 2018
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion SystemSummer31 May 2018
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion SystemSummer25 May 2016
RC-16-0048, Submittal of Annual Operating Report for 2015Summer30 March 2016
RC-16-0035, Virgil C. Summer Nuclear Station (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 BSummer1 March 2016
RC-14-0086, Technical Specification Bases Revision Updated Through May 2014Summer12 June 2014
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)Summer28 February 2013
RC-11-0094, Virgil C. Summer, Unit 1 - Technical Specification Bases Revision Updated Through June 2011Summer31 August 2011
RC-11-0094, Technical Specification Bases Revision Updated Through June 2011Summer31 August 2011
RC-11-0052, Virgil C. Summer, Unit 1, License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation.Summer2 May 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.Summer2 May 2011
RC-09-0004, Virgil C. Summer - 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 50.67Summer17 February 2009
RC-07-0025, Virgil C. Summer, License Amendment Request - LAR 05-3594 Steam Generator Tube IntegritySummer15 February 2007
RC-06-0084, Virgil C. Summer, License Amendment Request - LAR 05-3594, Steam Generator Tube IntegritySummer24 May 2006
RBG-47737, Relief Requests for 10-year Updates to the 120-Month Inservice Testing IntervalsRiver Bend27 February 2017
RBG-47456, Relief Request; ASME Code Case OMN-17, Alternative Rules for Testing ASME Class 1 Pressure Relief/Safety ValvesRiver Bend14 May 2014
RA07-045, Post-Outage 90-Day Inservice Inspection (ISI) Summary ReportLaSalle1 June 2007
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 MissilesMcGuire1 November 2018
RA-18-0213, McGuire Nuclear Station, Units 1 & 2 - Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated MissilesMcGuire1 November 2018
RA-18-0106, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement and Request for Additional Information Response (EPID L-2017-LLA-0355)Harris19 September 2018
RA-18-0106, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement and Request for Additional Information ResponseHarris
RA-17-0048, Shearon Harris, Unit 1 and H.B. Robinson, Unit 2, Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2)Robinson
Harris
30 October 2017
RA-16-0024, and H.B. Robinson Steam Electric Plant, Unit 2 - Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-PRobinson
Harris
3 October 2016
RA-16-002, Shearon Harris Nuclear Power Plant, Unit 1, and H.B. Robinson Steam Electric Plant, Unit 2 - Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-PRobinson
Harris
3 October 2016
RA-15-0042, and H.B. Robinson, Unit 2 - Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.Robinson
Harris
19 November 2015
RA-14-092, Oyster Creek - 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 ConditionsOyster Creek25 November 2014
RA-11-089, Oyster Creek Nuclear Generating Station - Submittal of Relief Requests for the Fifth Inservice Testing (IST) IntervalOyster Creek17 November 2011
PNP 2016-006, Palisades Plant - Inservice Testing Program Plan Fifth 10-Year IntervalPalisades28 April 2016
PNP 2012-106, Palisades Nuclear Plant, License Amendment Request to Adopt NFPA 805 Performance- Based Standard for Fire Protection for Light Water ReactorsPalisades12 December 2012
PNP 2012-097, Palisades Nuclear Plant - Report to NRC of Changes to Technical Specifications BasesPalisades9 November 2012
PNP 2011-032, Palisades, Report to NRC of Changes of Technical Specifications BasesPalisades25 April 2011
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)Oconee23 November 2015
ONS-2015-071, Submittal of Emergency Plan Revision 2015-004Oconee25 June 2015
ONS-2015-050, Emergency Plan Revision 2015-003Oconee20 May 2015
ONS-2014-165, Emergency Plan Revision 2014-003Oconee19 January 2015
ONS-2014-146, Emergency Plan Revision 2014-002Oconee10 November 2014
ONS-2014-065, Emergency Plan Implementing Procedures Manual Volume a, Revision 2014-001Oconee22 May 2014
ONS-2014-007, Emergency Plan Implementing Procedures Manual, Volume C, Revision 2014-003Oconee4 February 2014
ONS-2013-015, Emergency Plan, Volume a, Revision 2013-01Oconee14 November 2013
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)Millstone24 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
05200027
05200028
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. SeismicPoint Beach3 October 2013
NRC-2012-0158, Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section lll.G.2Millstone12 July 2012
NRC-2011-0230, FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations05000029
Surry
Indian Point
Three Mile Island
Kewaunee
Cook
Calvert Cliffs
Duane Arnold
North Anna
Fermi
Hope Creek
McGuire
Waterford
Susquehanna
Grand Gulf
Comanche Peak
Clinton
Palo Verde
22 September 2011
NRC-2009-0433, FRN: General Notice. Biweekly Notice Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards ConsiderationsDiablo Canyon25 September 2009
NRC 2018-0022, Point Beach - 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 MissPoint Beach26 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 ReactorsPoint Beach21 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 Beach23 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 AnalysisPoint Beach1 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 ConversionPoint Beach1 September 2016
NRC 2015-0072, Point Beach, Units 1 and 2 - 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 PlanPoint Beach16 December 2015
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 PlanPoint Beach16 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 Beach28 August 2015
NRC 2015-0025, Point Beach, Unit 1 Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763BPoint Beach14 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 Beach22 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 EventPoint Beach28 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 Beach22 February 2013
NRC 2012-0101, NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, SeismicPoint Beach26 November 2012
NRC 2011-0066, License Amendment Request 254, Removal of the Table of Contents from Technical SpecificationsPoint Beach23 June 2011
NRC 2011-0003, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional InformationPoint Beach13 January 2011
NRC 2010-0145, License Amendment Request 261, Supplement 9 Extended Power UpratePoint Beach21 September 2010
NRC 2010-0136, License Amendment Request 261 Extended Response to Request for Additional InformationPoint Beach8 September 2010
NRC 2010-0129, License Amendment Request 261, Supplement 7, Extended Power UpratePoint Beach24 August 2010
NRC 2010-0105, License Amendment Request 261, Supplement 6 Extended Power UpratePoint Beach28 July 2010
NRC 2010-0097, Response to Request for Additional Information on License Amendment Request 261, Supplement 5, Extended Power UpratePoint Beach8 July 2010
NRC 2010-0065, Response to Request for Additional Information on License Amendment Request 261, Extended Power UpratePoint Beach8 July 2010
NRC 2010-0065, Point Beach, Units 1 & 2, Response to Request for Additional Information on License Amendment Request 261, Extended Power UpratePoint Beach8 July 2010
NRC 2010-0049, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional InformationPoint Beach6 May 2010
NRC 2010-0023, License Amendment Request 261 Extended Power Uprate Response to Request for Additional InformationPoint Beach12 February 2010
NRC 2010-0005, License Amendment Request 261 Extended Power Uprate Response to Request for Additional InformationPoint Beach13 January 2010
NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power UpratePoint Beach8 December 2009
NRC 2009-0094, License Amendment Request 261 Extended Power Uprate Expedited Review RequestPoint Beach11 September 2009
NRC 2009-0085, License Amendment Request 241 Alternative Source Term Response to Request for Additional InformationPoint Beach4 September 2009
NRC 2009-0066, License Amendment Request 261 Supplement 1 Extended Power UpratePoint Beach17 June 2009
NRC 2009-0045, Supplement to License Amendment Request 241, Proposed Technical Specifications for Primary Auxiliary Building Ventilation (Vnpab)Point Beach17 April 2009
NRC 2009-0030, License Amendment Request 261, Extended Power UpratePoint Beach7 April 2009
NRC 2008-0081, Submittal of License Amendment Request 241, Alternative Source TermPoint Beach8 December 2008
NRC 2008-0081, Point Beach, Units 1 and 2 - Submittal of License Amendment Request 241, Alternative Source TermPoint Beach8 December 2008
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 ...Vogtle19 December 2018
NL-18-0541, Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing RequirementsHatch17 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 Point14 December 2017
NL-17-1197, Fourth Ten-Year Interval Lnservice Testing Program UpdateVogtle23 October 2017
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 8 Through Chapter 10Farley20 April 2017
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications BasesFarley20 April 2017
NL-17-039, Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017)Indian Point23 March 2017
NL-17-002, IP-RPT-16-00078, RAI CLI-16-07 SAMA Cost-Benefit Sensitivities, Rev. 0 (Jan. 4, 2017)Indian Point4 January 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)Vogtle2 November 2016
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2Vogtle2 November 2016
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 10.3 Through Section 15.1Vogtle2 November 2016
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical SpecificationsVogtle2 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 EventsFarley13 December 2016
NL-16-1431, Joseph M. Farley Nuclear Plant, Units 1 and 2 - Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External EventsFarley13 December 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 Point2 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 AnalysisIndian Point19 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 SystemIndian Point19 September 2016
NL-16-109, Indian Point 2 Improved Technical Specifications BasesIndian Point19 September 2016
NL-16-089, Notification of Full Compliance with Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and Order EA-12-051 Modifying Licenses with Regard ...Indian Point12 August 2016
NL-16-0388, Draft License Amendment Request Regarding Alternative Source TeamFarley15 October 2016
NL-16-0388, Alternative Source Term License Amendment RequestFarley22 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 EventsVogtle23 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 - 9.5-66Watts Bar11 September 2015
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 7.0 - Instrumentation and ControlsWatts Bar11 September 2015
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant SystemWatts Bar11 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 - 15.3-76Watts Bar11 September 2015
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 14.0 - Initial Test ProgramWatts Bar11 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 SystemWatts Bar11 September 2015
NL-15-183, Submittal of Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis ReportWatts Bar11 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 - ModWatts Bar3 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 9Sequoyah24 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 9Sequoyah24 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 9Sequoyah24 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 9Sequoyah24 July 2015
NL-15-1483, Refueling Outage 1R26 Inservice Inspection ReportFarley4 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 8Sequoyah19 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 8Sequoyah19 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 Point25 June 2015
NL-15-062, Response to Request for Additional Information Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 YearsIndian Point20 May 2015
NL-15-045, LER 15-002-00 for Indian Point, Unit 3, Regarding Technical Specification Prohibited Condition Caused by Three Main Steam Safety Valves Outside Their As-Found Lift Set Point Test Acceptance CriteriaIndian Point27 April 2015
NL-14-1996, Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.1Vogtle30 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.Vogtle11 November 2014
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report, (Ufsar), Revision 25, Chapter 10, Steam and Power Conversion SystemIndian Point17 September 2014
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective SectionsIndian Point17 September 2014
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 14 - Safety AnalysisIndian Point17 September 2014
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Appendix a, IntroductionIndian Point17 September 2014
NL-14-0706, Vogtle, Units 1 and 2 - Application to Revise Technical Specifications to Adopt Previously NRC-Approved Generic Technical Specification ChangesVogtle18 July 2014
NL-14-0706, Application to Revise Technical Specifications to Adopt Previously NRC-Approved Generic Technical Specification ChangesVogtle18 July 2014
NL-13-1540, Vogtle, 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 SpecificatVogtle2 August 2013
NL-13-131, Amendment 14 to License Renewal Application (LRA)Indian Point26 September 2013
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 24, Chapter 10 - Steam and Power Conversion SystemIndian Point26 September 2013
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 14, Safety AnalysisIndian Point26 September 2013
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Appendix aIndian Point26 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 ApplicationIndian Point24 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)Farley27 February 2013
NL-13-0081, Vogtle, Units 1 & 2, 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...Farley
Vogtle
23 January 2013
NL-12-1344, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (Rmts) Guidelines.Vogtle13 September 2012
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 Point26 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 EventIndian Point26 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 Point26 September 2012
NL-12-039, Proposed License Amendment Regarding Atmospheric Dump ValvesIndian Point23 May 2012
NL-11-1297, Methods to Be Used in the Implementation of Risk-Informed Technical Specifications Initiative 4bVogtle27 September 2011
NL-11-087, Proposed License Amendment Regarding Travelers - TSTF-479-A and TSTF-497-AIndian Point16 September 2011
NL-11-087, Indian Point, Units 2 and 3, Proposed License Amendment Regarding Travelers - TSTF-479-A and TSTF-497-AIndian Point16 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 ProgramVogtle7 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 BasesIndian Point6 October 2010
NL-10-0272, License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated..Farley29 October 2010
NL-09-165, Official Exhibit - ENT000009-00-BD01 - NL-09-165, Letter from Fred Dacimo, Entergy, to NRC, License Renewal Application - SAMA Reanalysis Using Alternate Meteorological Tower Data, Indian Point, Unit 2 & 3.Indian Point11 December 2009
NL-09-1510, Vogtle Electric Generation Plant, Unit 2 - 3rd Interval VOGTLE-2 ISI Plan, Version 3.0Vogtle12 October 2009
NL-09-1510, Vogtle Electric Generation Plant, Unit 1 - Third 10-Year Interval ISI Plan, Version 3.0Vogtle12 October 2009
NL-09-079, Reply to Request for Additional Information Regarding Offsite Power, Refueling Cavity, and Unit 2 Auxiliary Feedwater Pump Room Fire EventIndian Point12 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 RequirementsIndian Point8 July 2009
NL-09-033, Response to Safety Evaluation Report with Open Items Related to the License RenewalIndian Point12 March 2009
NL-08-086, Supplemental Reply to Request for Additional Information Regarding License Renewal Application - Severe Accident Mitigation Alternatives AnalysisIndian Point22 May 2008
NL-08-028, Official Exhibit - ENT000460-00-BD01 - NL-08-028, Letter from Fred Dacimo, Entergy, to NRC Reply to Request for Additional Information Regarding License Renewal Application - Severe Accident Mitigation Alternatives Analysis (Feb. 5, 2008)Indian Point5 February 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)Farley
Hope Creek
17 September 2007
NL-07-1418, Joseph M. Farley, Units 1 & 2 - Fourth Ten-Year Interval Inservice Testing Program UpdateFarley14 August 2007
NL-07-1418, Fourth Ten-Year Interval Inservice Testing Program UpdateFarley14 August 2007
NL-07-028, Inservice Testing Program Summary for 4th Interval, Revision 0Indian Point28 February 2007
NL-07-0153, Vogtle Electric Generating Plant, Units 1 and 2, Third Interval Inservice Testing (IST) Program UpdateVogtle16 April 2007
NL-07-0153, Third Interval Inservice Testing (IST) Program UpdateVogtle16 April 2007
NL-06-1707, NRC Regulatory Conference July 26, 2006 Supplemental InformationVogtle31 July 2006
NL-06-089, Reply to Request for Additional Information Regarding Proposed License Amendment for Adoption of TSTF 449Indian Point30 August 2006
NL-06-089, Indian Point, Units 2 and 3, Reply to Request for Additional Information Regarding Proposed License Amendment for Adoption of TSTF 449Indian Point30 August 2006
NL-06-020, Application for a Technical Specification Change to Add Spent Fuel Cask Loading RequirementsIndian Point10 July 2006
NL-06-0124, Vogtle Electric Generating Plant Application for Technical Specification Improvement Regarding Steam Generator Tube IntegrityVogtle29 March 2006
NL-04-1408, Joseph M. Farley - Request for Technical Specifications Change Steam Generator Program - Revision IFarley5 August 2004
NEI 99-06, Response to Request for Additional Information Regarding 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 ReactorPoint Beach21 December 2017
MNS-18-009, Site Emergency PlanMcGuire26 January 2018
MNS-17-026, Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated MissilesMcGuire8 December 2017
MNS-14-103, Submittal of Emergency Plan, Revision 14-5McGuire16 December 2014
MNS-14-016, Emergency Plan, Revision 14-1McGuire30 January 2014
ML993630482Point Beach23 December 1999
ML19058A583Surry27 September 2018
ML19058A442Surry27 September 2018
ML19056A189Beaver Valley20 February 2019
ML19052A161Millstone14 February 2019
ML19039A049Watts Bar8 February 2019
ML19036A523Davis Besse5 February 2019
ML19029A010Crystal River28 June 2016
ML19003A196Diablo Canyon26 December 2018
ML18355A610McGuire25 January 2019
ML18353B056Vogtle19 December 2018
ML18341A159Palo Verde6 December 2018
ML18334A363Watts Bar
07201000
29 November 2018
ML18334A124Hope Creek12 November 2018
ML18333A034Clinton21 November 2018
ML18325A145Wolf Creek15 November 2018
ML18313A133McGuire1 November 2018
ML18313A005Vogtle9 November 2018
ML18312A077Farley30 October 2018
ML18312A074Farley30 October 2018
ML18304A394Vogtle11 January 2019
ML18304A330Surry25 October 2018
ML18291A980Braidwood8 November 2018
ML18291A834Surry15 October 2018
ML18285A595Limerick19 September 2018
ML18283A775Arkansas Nuclear4 October 2018
ML18282A055Saint Lucie2 October 2018
ML18274A1154 October 2018
ML18270A130Calvert Cliffs30 October 2018
ML18269A362Palo Verde25 September 2018
ML18264A1410520004628 September 2018
ML18262A328Harris19 September 2018
ML18262A096Calvert Cliffs6 March 2018
ML18262A094Diablo Canyon11 September 2018
ML18241A088Arkansas Nuclear27 August 2018
ML18227A0610520004628 September 2018
ML18221A182Summer31 May 2018
ML18221A180Summer31 May 2018
ML18218A171Surry31 July 2018
ML18215A2420520004628 September 2018
ML18212A190Indian Point17 September 2018
ML18207A591Callaway19 June 2018
ML18206A545Three Mile Island25 July 2018
ML18198A119North Anna31 May 2018
ML18193A911Palo Verde19 January 1976
ML18193A552Palo Verde28 February 1975
ML18193A069Palo Verde12 July 2018
ML18192B990Calvert Cliffs6 July 2018
ML18179A350Arkansas Nuclear28 June 2018
ML18176A0510520004628 September 2018
ML18173A10128 September 2018
ML18169A07515 June 2018
ML18166A211Prairie Island18 May 2018
ML18166A204Prairie Island18 May 2018
ML18153D279Surry19 March 1993
ML18153D214Surry14 January 1993
ML18153C999Surry30 April 1992
ML18153C608Surry23 April 1991
ML18153C599Surry31 March 1991
ML18153C441Surry31 October 1990
ML18153C426Surry2 November 1990
ML18153B925Surry12 October 1989
ML18153B863Surry31 July 1989
ML18153B731Surry30 April 1989
ML18153B725Surry12 May 1989
ML18153B350Surry19 October 1993
ML18153B285Surry11 August 1993
ML18153B249Surry9 March 1995
ML18153A629Surry12 November 1996
ML18153A628Surry12 November 1996
ML18153A469Surry28 February 1994
ML18153A465Surry7 June 1996
ML18153A348Surry18 December 1997
ML18153A145Surry18 June 1997
ML18153A129Surry18 April 1997
ML18153A128Surry15 April 1997
ML18152B418Surry18 May 1999
ML18152A822Surry
Calvert Cliffs
11 April 1988
ML18152A447Surry6 May 1993
ML18152A391Surry24 September 1992
ML18152A383Surry30 June 1990
ML18152A290Surry30 September 1988
ML18152A182Surry9 June 1994
ML18152A119Surry30 August 1994
ML18152A036Surry4 August 1992
ML18151A935Surry
North Anna
10 February 1992
ML18151A714Surry7 August 1992
ML18151A713Surry28 November 1990
ML18151A669Surry26 January 1993
ML18151A628Surry23 July 1999
ML18151A623Surry13 January 1998
ML18151A183Surry31 August 1994
ML18151A081Surry25 September 1987
ML18150A459Surry30 June 1994
ML18150A433Surry30 September 1988
ML18150A021Surry27 March 1987
ML18149A276Davis Besse10 May 2018
ML18143B449Surry30 August 1985
ML18143A860Ginna24 March 1972
ML18143A815Ginna15 March 1973
ML18142A599Ginna31 December 1975
ML18142A057Surry19 September 1984
ML18141A021Surry16 June 1983
ML18139C030Surry21 September 1982
ML18139B504Surry21 August 1981
ML18139A906Surry15 December 1980
ML18139A900Surry15 December 1980
ML18139A832Surry14 November 1980
ML18136A392Surry
North Anna
10 January 1980
ML18130A444Surry1 April 1987
ML18130A440Surry27 March 1987
ML18130A383Surry22 December 1982
ML18130A376Surry21 September 1982
ML18130A321Surry
North Anna
15 December 1980
ML18122A174Waterford30 April 2018
ML18117A264Calvert Cliffs10 May 2018
ML18117A238San Onofre24 April 2018
ML18117A116Turkey Point26 April 2018
ML18117A101Turkey Point26 April 2018
ML18117A099Turkey Point26 April 2018
ML18117A094Turkey Point26 April 2018
ML18116A306Point Beach26 April 2018
... further results