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-06392, LER 17-002-00 for Callaway Plant, Unit 1, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming DesignCallaway13 October 2017
ULNRC-06258, LER 15-004-00 for Callaway, Unit 1, Regarding Auxiliary Feedwater Control Valve Inoperable Due to Faulty Electronic Positioner CardCallaway12 October 2015
ULNRC-06174, Callaway, Unit 1 - 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 ImprovemCallaway9 March 2015
ULNRC-05947, Callaway Plant, Unit 1, License Renewal Application, Clarification of Responses to SAMA RAIs to the License Renewal ApplicationCallaway15 January 2013
ULNRC-05908, Callaway, Unit 1, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation AlternativesCallaway24 September 2012
ULNRC-05830, Callaway, Unit 1, Environmental Report; Operating License Renewal Stage Final, Attachment E Through EndCallaway15 December 2011
ULNRC-05808, Callaway Plant, Unit 1 - 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 10-002Callaway25 July 2011
ULNRC-05774, Attachment 1 - Technical Specification Page Mark UpCallaway3 November 2011
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, Callaway Plant, Unit 1, ULNRC-05608, Revision of Technical Specification 3.3.2 and 3.7.3 (License Amendment Request OL-1289)Callaway4 May 2009
ULNRC-05566, Callaway, Unit 1, 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, Callaway Plant Unit 1, 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-05-18, 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 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
Regulatory Guide 1.3331 January 1977
Regulatory Guide 1.1941 June 2003
RS-18-016, Braidwood Station, Units 1 and 2 - 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, Byron, Units 1 and 2 - 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 27Byron
Braidwood
07200068
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 GuidesByron
Braidwood
07200068
07200073
15 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, Byron Station, Units 1 and 2 - License Amendment Request to Utilize the Tormis Computer Code MethodologyByron7 October 2016
RS-16-088, Byron, Unit 2, 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, Byron, Unit 2 - 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, Braidwood, Unit 1 - 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, Braidwood, Unit 2 - 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, Byron 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)Byron30 November 2015
RS-15-253, Byron Station, Units 1 and 2 - 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, Byron Station, Units 1 and 2 - 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-1Byron28 August 2015
RS-15-170, Byron Station, Units 1 and 2 - Submittal of Relief Requests Associated with the Fourth Inservice Testing IntervalByron22 June 2015
RS-15-084, Braidwood Station, Units 1 and 2, 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)Byron
Braidwood
07200068
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, Byron Station, Units 1 and 2 - 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-Byron28 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, Dresden Nuclear Power Station, Units 2 and 3, 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, Quad Cities, Units 1 and 2, Fifth Ten-Year Interval Inservice Testing ProgramQuad Cities25 February 2013
RS-13-045, Quad Cities, Units 1 and 2, 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 BasesByron
07200068
14 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
Byron
07200068
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, Dresden, Units 2 and 3 - Submittal of Relief Requests Associated with the Fifth Lnservice Testing IntervalDresden30 October 2012
RS-12-149, Quad Cities, Units 1 and 2, Response to Request for Additional Information Regarding Relief Requests Associated with the Fifth Inservice Testing IntervalQuad Cities13 September 2012
RS-12-039, Braidwood Station, Units 1 & 2, 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, Quad Cities, Units 1 and 2, 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, Quad Cities, Units 1 and 2, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, Annual ReportQuad Cities7 May 2010
RS-10-029, Braidwood, Units 1 & 2, 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, Quad Cities, Units 1 and 2 - 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, Byron, Units 1 and 2 - Technical Specification BasesByron15 December 2008
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification BasesBraidwood15 December 2008
RS-08-144, Clinton, Unit 1, 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, Braidwood, Units 1 and 2, 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, Quad Cities, Unit 1, 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, Quad Cities Units 1 & 2, 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, Dresden, Units 2 and 3, 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, Quad Cities, Units 1 and 2 - 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, Dresden, Units 2 and 3, 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, Quad Cities, Units 1 and 2, Response to Request for Additional Information Related to Relief Request RV-30EQuad Cities30 October 2007
RS-07-126, Quad Cities, Units 1 and 2 - 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, Dresden, Unit 2, Response to Request for Additional Information Related to Relief Request RV-02BDresden27 July 2007
RS-07-104, Dresden Unit 2, 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, Quad Cities Nuclear Power Station, Units 1 and 2, 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, Braidwood, Units 1 and 2, 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, Quad Cities, Units 1 & 2, 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, Dresden, Unit 2 and 3, 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, Dresden Nuclear Power Station, Units 2 & 3, 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, Quad Cities, Units 1 & 2 - Startup and Power Ascension Testing Following Installation of Acoustic Side Branch ModificationsQuad Cities2 August 2006
RS-06-087, Dresden, Units 2 & 3 - Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System EnrichmentDresden2 June 2006
RS-06-067, Quad Cities, Unit 1 & 2, Startup and Power Ascension Testing Following Installation of Acoustic Side Branch ModificationsQuad Cities3 May 2006
RS-06-064, Quad Cities, Unit 1 & 2, 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, H.B. Robinson, Unit 2 - 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 (ORobinson19 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, H.B. Robinson, Unit 2 - Transmittal of Technical Specifications Bases RevisionsRobinson29 April 2014
RNP-RA/13-0117, H.B. Robinson Unit 2, 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, 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, H.B. Robinson, Unit 2, 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, Virgil C. Summer Nuclear Station, Unit 1, 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, Virgil C. Summer, Unit 1 - Technical Specification Bases Revision Updated Through May 2014Summer12 June 2014
RC-13-0028, Virgil C. Summer, Unit 1, 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-11-0052, 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-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
RA07-045, LaSalle, Unit 2, Post-Outage 90-Day Inservice Inspection (ISI) Summary ReportLaSalle1 June 2007
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-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-16-094, LER 2016-004-00 for Oyster Creek Nuclear Generating Station, Regarding Technical Specification Violation Due to Main Steam Safety Valve Setpoint Discovered Out of ToleranceOyster Creek16 November 2016
RA-16-0024, 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-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, Shearon Harris, Unit 1, 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, Oconee, Units 1, 2, and 3 - 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, Oconee Nuclear Station, Units 1, 2, and 3 - Submittal of Emergency Plan Revision 2015-004Oconee25 June 2015
ONS-2015-050, Oconee Nuclear Station, Units 1, 2 and 3 - Emergency Plan Revision 2015-003Oconee20 May 2015
ONS-2014-165, Oconee, Units 1, 2, and 3 - Emergency Plan Revision 2014-003Oconee19 January 2015
ONS-2014-146, Oconee, Units 1, 2, and 3, Emergency Plan Revision 2014-002Oconee10 November 2014
ONS-2014-065, Oconee Nuclear Station, Units 1, 2 and 3 - Emergency Plan Implementing Procedures Manual Volume a, Revision 2014-001Oconee22 May 2014
ONS-2014-007, Oconee Nuclear Station, Units 1, 2 and 3, Emergency Plan Implementing Procedures Manual, Volume C, Revision 2014-003Oconee4 February 2014
ONS-2013-015, Oconee Nuclear Station, Units 1, 2, and 3 - Emergency Plan, Volume a, Revision 2013-01Oconee14 November 2013
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, Point Beach, Units 1 and 2, 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 2015-0056, Point Beach, Units 1 and 2 - 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 EAPoint 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, Point Beach, Units 1 and 2 - 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, Point Beach, Units 1 and 2, 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-BasisPoint Beach28 February 2014
NRC 2013-0024, Point Beach, Units 1 and 2 - 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 ExtePoint 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, Point Beach, Units 1 & 2, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional InformationPoint Beach13 January 2011
NRC 2010-0145, Point Beach Nuclear Plant, Units 1 & 2, License Amendment Request 261, Supplement 9 Extended Power UpratePoint Beach21 September 2010
NRC 2010-0136, Point Beach Nuclear Plant, Units 1 and 2 - License Amendment Request 261 Extended Response to Request for Additional InformationPoint Beach8 September 2010
NRC 2010-0129, Point Beach, Units 1 and 2, License Amendment Request 261, Supplement 7, Extended Power UpratePoint Beach24 August 2010
NRC 2010-0105, Point Beach, Units 1 and 2 - License Amendment Request 261, Supplement 6 Extended Power UpratePoint Beach28 July 2010
NRC 2010-0097, Point Beach, Units 1 & 2, Response to Request for Additional Information on License Amendment Request 261, Supplement 5, 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, Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional InformationPoint Beach6 May 2010
NRC 2010-0023, Point Beach, Units 1 & 2 - License Amendment Request 261 Extended Power Uprate Response to Request for Additional InformationPoint Beach12 February 2010
NRC 2010-0005, Point Beach, Units 1 and 2 - License Amendment Request 261 Extended Power Uprate Response to Request for Additional InformationPoint Beach13 January 2010
NRC 2009-0120, Point Beach Nuclear Plant, Units 1 and 2, License Amendment Request 261, Supplement 3 Extended Power UpratePoint Beach8 December 2009
NRC 2009-0094, Point Beach Nuclear Plant, Units 1 & 2 - License Amendment Request 261 Extended Power Uprate Expedited Review RequestPoint Beach11 September 2009
NRC 2009-0085, Point Beach, Units 1 & 2 - License Amendment Request 241 Alternative Source Term Response to Request for Additional InformationPoint Beach4 September 2009
NRC 2009-0066, Point Beach Nuclear Plant, Units 1 and 2, License Amendment Request 261 Supplement 1 Extended Power UpratePoint Beach17 June 2009
NRC 2009-0045, Point Beach, Units 1 and 2 - Supplement to License Amendment Request 241, Proposed Technical Specifications for Primary Auxiliary Building Ventilation (Vnpab)Point Beach17 April 2009
NRC 2009-0030, Point Beach, Units 1 and 2 - License Amendment Request 261, Extended Power UpratePoint Beach7 April 2009
NRC 2008-0081, Point Beach, Units 1 and 2 - Submittal of License Amendment Request 241, Alternative Source TermPoint Beach8 December 2008
NL-18-0541, Edwin I. Hatch Nuclear Plant, Unit 2 - Response to Request for Additional Information for Alternative RR-V-11 Regarding Main Steam Safety Valve Testing RequirementsHatch17 April 2018
NL-17-2107, LER 17-002-00 for Joseph M. Farley, Unit 2, Regarding Main Steam Safety Valve Lift Pressure Outside of Technical Specifications LimitsFarley19 December 2017
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, Vogtle, Units 1 and 2, 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, Indian Point Nuclear Generating, Units 2 and 3, 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, 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-16-109, 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, Indian Point, Unit 2, 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 RIndian Point12 August 2016
NL-16-074, LER 15-006-01 for Indian Point Unit No. 3 Regarding Technical Specification Prohibited Condition Due to Two Pressurizer Code Safety Valves Discovered Outside Their As-Found Lift Setpoint Test Acceptance CriteriaIndian Point8 August 2016
NL-16-045, LER 16-001-00 for Indian Point 2 Technical Specification Prohibited Condition Caused by One Main Steam Safety Valve Outside Its As-Found Lift Set Point Test Acceptance CriteriaIndian Point2 May 2016
NL-16-0388, Joseph M. Farley Nuclear Plant, Units 1 and 2, Alternative Source Term License Amendment RequestFarley22 November 2016
NL-16-0388, Draft License Amendment Request Regarding Alternative Source TeamFarley15 October 2016
NL-16-0228, Vogtle, Units 1 and 2 - 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, Farley, Unit 1 - 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-15-108, LER 15-006-00 for Indian Point Unit No. 3 Regarding Technical Specification Prohibited Condition Due to Two Pressurizer Code Safety Valves Discovered Outside Their As-Found Lift Setpoint Test Acceptance CriteriaIndian Point28 August 2015
NL-15-086, LER 15-002-01 for Indian Point 3, Regarding Technical Specification Prohibited Condition Caused by Four Main Steam Safety Valves Outside Their As-Found Lift Set Point Test Acceptance CriteriaIndian Point7 July 2015
NL-15-081, Indian Point, Unit 3 - 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 ForceIndian Point25 June 2015
NL-15-062, Indian Point, Unit 2 - 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, Vogtle, Units 1 and 2 - Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.1Vogtle30 December 2014
NL-14-1703, Vogtle, Units 1 and 2 - 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 GuVogtle11 November 2014
NL-14-154, Watts Bar - Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 12 (TAC No. MD8314)Watts Bar2 September 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-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-13-149, Watts Bar Nuclear Plant, Units 1 and 2, Updated Inservice Test (IST) Program (Unit 1) and Ist/Preservice Test (Pst) ProgramWatts Bar12 December 2013
NL-13-131, Indian Point Nuclear Generating, Unit No. 2 - 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, Indian Point, Units 2 and 3, 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-13-088, LER 12-003-01 for Indian Point, Unit 3, Regarding Technical Specification Prohibited Condition Due to a Pressurizer Safety Valve Discovered Outside Its As-Found Lift Set Point Test Acceptance CriteriaIndian Point20 June 2013
NL-13-0213, Joseph M. Farley, Units 1 & 2, 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 EventsFarley27 February 2013
NL-13-0081, Joseph M. Farley, Units 1 & 2, 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 ImFarley
Vogtle
23 January 2013
NL-12-1344, Vogtle, Units 1 and 2, 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, Indian Point, Unit 3 - Proposed License Amendment Regarding Atmospheric Dump ValvesIndian Point23 May 2012
NL-11-1297, Vogtle, Units 1 and 2, Methods to Be Used in the Implementation of Risk-Informed Technical Specifications Initiative 4bVogtle27 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, Vogtle Units 1 & 2 - 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 ControVogtle7 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, Joseph M. Farley, Units 1 and 2, 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 CFarley29 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, Indian Point Nuclear Generating, Units 2 & 3 - 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, Indian Point Nuclear Generating, Units 2 and 3 - Response to Safety Evaluation Report with Open Items Related to the License RenewalIndian Point12 March 2009
NL-08-086, Indian Point Units 2 & 3, 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-07-028, Indian Point, Unit 2 - 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-06-1707, Vogtle, Units 1 and 2, NRC Regulatory Conference July 26, 2006 Supplemental InformationVogtle31 July 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, Indian Point, Unit 2, 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, Point Beach, Units 1 & 2, 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-PPoint Beach21 December 2017
NEI 99-01, 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
MNS-18-009, McGuire Nuclear Station, Units 1 and 2, Site Emergency PlanMcGuire26 January 2018
MNS-17-026, McGuire, Units 1 and 2, Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated MissilesMcGuire8 December 2017
MNS-14-103, McGuire, Units 1 and 2 - Submittal of Emergency Plan, Revision 14-5McGuire16 December 2014
MNS-14-016, McGuire, Units 1 and 2, Emergency Plan, Revision 14-1McGuire30 January 2014
ML993630482Point Beach23 December 1999
ML18333A034Clinton21 November 2018
ML18325A145Wolf Creek15 November 2018
ML18313A005Vogtle9 November 2018
ML18304A330Surry25 October 2018
ML18291A980Braidwood8 November 2018
ML18291A834Surry15 October 2018
ML18283A775Arkansas Nuclear4 October 2018
ML18274A1154 October 2018
ML18270A130Calvert Cliffs30 October 2018
ML18269A362Palo Verde25 September 2018
ML18264A1410520004628 September 2018
ML18262A096Calvert Cliffs6 March 2018
ML18227A0610520004628 September 2018
ML18218A171Surry31 July 2018
ML18215A2420520004628 September 2018
ML18212A190Indian Point17 September 2018
ML18206A545Three Mile Island25 July 2018
ML18198A119North Anna31 May 2018
ML18193A911Palo Verde19 January 1976
ML18192B990Calvert Cliffs6 July 2018
ML18179A350Arkansas Nuclear28 June 2018
ML18176A0510520004628 September 2018
ML18173A10128 September 2018
ML18169A07515 June 2018
ML18149A276Davis Besse10 May 2018
ML18143A860Ginna24 March 1972
ML18142A599Ginna31 December 1975
ML18122A174Waterford30 April 2018
ML18117A264Calvert Cliffs10 May 2018
ML18117A238San Onofre24 April 2018
ML18108A176Three Mile Island13 April 2018
ML18108A015Point Beach1 May 2018
ML18107A79716 April 2018
ML18107A759Indian Point30 April 2018
ML18107A235Salem23 April 1999
ML18107A183Salem31 March 1999
ML18107A182Salem31 March 1999
ML18106A402Salem20 March 1998
ML18106A372Salem10 March 1998
ML18102B691Diablo Canyon31 January 1997
ML18102A421Salem20 September 1996
ML18102A141Salem17 May 1996
ML18101A748Salem19 May 1995
ML18101A236Salem20 September 1994
ML18100B128Salem31 May 1994
ML18100B086Salem13 May 1994
ML18100B083Salem29 April 1994
ML18100B082Salem25 April 1994
ML18100B063Salem10 May 1994
ML18100B061Salem6 May 1994
ML18100A797Salem23 December 1993
ML18100A421Salem31 May 1993
ML18100A291Salem31 March 1993
ML18098A046Saint Lucie1 April 1976
ML18096B043Salem30 September 1992
ML18096B011Salem24 September 1992
ML18096A888Salem31 July 1992
ML18096A870Salem31 July 1992
ML18096A352Salem31 October 1991
ML18094B224Salem28 December 1989
ML18094B222Salem28 December 1989
ML18094A578Salem30 June 1989
ML18094A577Salem30 June 1989
ML18094A560Salem7 July 1989
ML18094A520Salem31 May 1989
ML18094A115Wolf Creek28 March 2018
ML18093B560Calvert Cliffs12 May 1988
ML18093B481Salem2 March 1989
ML18093B341Salem13 December 1988
ML18093B174Salem20 September 1988
ML18093A920Wolf Creek8 March 2018
ML18093A919Wolf Creek8 March 2018
ML18093A909Wolf Creek8 March 2018
ML18093A901Wolf Creek8 March 2018
ML18093A895Wolf Creek8 March 2018
ML18093A646Salem31 January 1988
ML18093A335Palo Verde30 March 2018
ML18092A758Salem6 August 1985
ML18088B195Saint Lucie29 March 2018
ML18088A080Hatch29 March 2018
ML18087A254Arkansas Nuclear28 March 2018
ML18087A158Byron
Braidwood
24 April 2018
ML18086B509Salem28 May 1982
ML18081A538Salem9 November 1979
ML18079A563Salem17 July 1979
ML18072A27119 March 2018
ML18071A169Beaver Valley22 March 2018
ML18068A470Palisades31 May 1998
ML18066A754Palisades8 June 1996
ML18066A647Palisades17 September 1999
ML18066A501Palisades11 June 1999
ML18066A443Palisades30 March 1999
ML18066A441Palisades30 March 1999
ML18066A341Palisades22 April 1998
ML18066A328Palisades9 November 1998
ML18066A078Millstone1 March 2018
ML18065A601Palisades22 March 1996
ML18065A586Palisades29 March 1996
ML18065A403Beaver Valley5 April 2018
ML18064A736Palisades27 April 1995
ML18064A698Palisades31 March 1995
ML18064A584Palisades13 January 1995
ML18060A401Robinson
Harris
10 April 2018
ML18059A694Palisades22 February 1994
ML18058B744Palisades29 March 1993
ML18058B350Palisades19 January 1993
ML18057B021Palisades1 February 1991
ML18057A810Palisades30 January 1991
ML18057A278Palisades15 June 1990
ML18054A893Palisades2 August 1989
ML18052B3160520004619 March 2018
ML18052A486Dresden12 February 2017
ML18052A136Palisades28 October 1985
ML18051B069Palisades17 September 1984
ML18047A555Palisades30 August 1982
ML18047A457Palisades28 February 1982
ML18047A453Palisades31 March 1982
ML18046B091Palisades17 November 1981
ML18044A898Palisades14 May 1980
ML18044A1850520004628 September 2018
ML18043B089Palisades9 October 1979
ML18043A896Palisades31 July 1979
ML18043A2609990205822 February 2018
ML18041A135050000291 July 1986
ML18041A134Point Beach3 July 1986
ML18041A123Saint Lucie30 December 1985
ML18038A353Nine Mile Point1 May 1991
ML18038A102Nine Mile Point17 December 1985
ML18038A092Nine Mile Point27 November 1985
ML18038A065Nine Mile Point15 October 1985
ML18036B286Browns Ferry12 May 1993
ML18036A156Peach Bottom7 February 2018
ML18025B469Browns Ferry6 April 1981
ML18025A950Browns Ferry30 June 1980
ML18025A941Browns Ferry30 June 1980
ML18024A413Browns Ferry5 October 2017
ML18022A753Harris31 December 1989
ML18022A729Harris3 November 1988
ML18022A606Harris11 January 1988
ML18022A207Browns Ferry5 October 2017
ML18019A818Harris14 May 1986
ML18018B909Harris7 May 1985
ML18018B641Harris
05000401
05000402
05000403
30 January 1981
ML18018A961Nine Mile Point18 January 2018
ML18018A575Harris
05000401
30 June 1983
ML18018A549Harris
05000401
13 May 1983
ML18016A973Harris28 November 1998
ML18016A236Quad Cities19 October 2017
ML18012A531Harris18 February 1997
ML18012A468Harris20 January 1997
ML18011A665Calvert Cliffs11 January 2018
ML18011A111Harris7 July 1993
ML18010A719Harris14 August 1992
ML18010A087Fort Calhoun6 March 2018
ML18009A408Harris19 March 1990
ML18005B056Harris3 November 1988
ML18005A563Harris24 August 1988
ML18004B620Harris15 November 1986
ML18004A15718 October 2017
ML17354A984Turkey Point18 June 1998
ML17354A885Turkey Point13 October 1997
ML17354A844Turkey Point18 March 1998
ML17354A681Turkey Point30 September 1997
ML17354A612Turkey Point29 August 1997
ML17354A514Turkey Point22 May 1997
ML17354A411Turkey Point12 February 1997
ML17354A284Turkey Point7 April 1996
ML17353A506Turkey Point31 December 1995
ML17353A501Turkey Point18 December 1995
ML17352B036Turkey Point20 February 1995
ML17352A832Turkey Point20 October 1994
ML17352A732Turkey Point19 July 1994
ML17352A731
ML17352A730Turkey Point19 July 1994
ML17352A447Turkey Point15 December 1993
ML17352A359Turkey Point28 December 1993
ML17352A259Turkey Point
Saint Lucie
28 September 1993
ML17349A681Turkey Point
Saint Lucie
16 February 1993
ML17349A236Turkey Point
Saint Lucie
19 May 1992
ML17348B093Turkey Point30 June 1991
ML17348A917Turkey Point2 May 1991
ML17348A542Turkey Point30 June 1990
ML17347B302Turkey Point29 August 1989
ML17347A730Turkey Point13 April 1988
ML17347A59305000000
Turkey Point
Saint Lucie
31 July 1987
ML17347A116Waterford4 December 2017
ML17346B17105000000
Turkey Point
Saint Lucie
31 July 1985
ML17346A631Turkey Point16 November 1984
ML17346A248Turkey Point2 April 1984
ML17346A233Turkey Point14 March 1984
ML17346A232Turkey Point14 March 1984
ML17345B218Turkey Point18 August 1983
... further results