Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
CNRO-2020-00006, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 2 | 24 January 2020 | Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 2 |
ML19066A008 | 29 April 2019 | Issuance of Amendment Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3 |
ML18099A071 | 16 April 2018 | March 20, 2018, Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding the Surveillance Frequency Control Program |
ML17237C041 | 15 September 2017 | Documentation of the Completion of Required Actions Taken in Response to Fukushima Lessons Learned |
ML15174A257 | 1 September 2015 | Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events |
ML14106A167 | 27 February 2015 | Issuance of Amendment No. 185, Adopt TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A Using Consolidated Line Item Improvement Process |
ML14211A129 | 29 July 2014 | NRR E-mail Capture - River Bend Station, Unit 1, Request for Additional Information Regarding Technical Specification Task Force Traveler (TSTF) - 423 |
ML14111A147 | 9 May 2014 | Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights |
ML14030A046 | 20 February 2014 | Letter from Eric J. Leeds Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 |
ML12118A567 | 27 April 2012 | Entergy'S Answer to Pilgrim Watch Request for Hearing Regarding Insufficiency of Order Modifying Licenses with Regard to Spent Reliable Spent Fuel Pool Instrumentation |
ML12054A735 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12054A679 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation |
ML12056A045 | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12056A044 | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status |
NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status |
NRC-2012-0068, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML060720430 | 1 March 2006 | March 1, 2006 Public Meeting Slides for Proposed Generic Letter Post-Fire Safe-Shutdown Circuit Analysis Spurious Actuations. |
ML032940104 | 7 October 2003 | Riv Backfit Status |
ML032940098 | 27 March 2003 | Riv Backfit Status |
CNRO-2002-00060, Comment of Michael A. Krupa on Behalf of Entergy Nuclear South on the Third Year of Implementation of Reactor Oversight Process | 19 December 2002 | Comment of Michael A. Krupa on Behalf of Entergy Nuclear South on the Third Year of Implementation of Reactor Oversight Process |
ML022120583 | 31 July 2002 | EA-02-036: Entergy Operations, Inc, River Bend Station, Final Significance Determination for a White Finding and Notice of Violation (IR 05000458-02-005) |
RBG-45976, Entergy Owner Controlled Area Public Notification, River Bend Station - Unit I, License No. NPF-47, Docket No. 50-458. Letter Provided as Supplement to 05/31/2002 Submittal Re Preliminary Finding Associated with Owner Controlled Area Evacu | 7 June 2002 | Entergy Owner Controlled Area Public Notification, River Bend Station - Unit I, License No. NPF-47, Docket No. 50-458. Letter Provided as Supplement to 05/31/2002 Submittal Re Preliminary Finding Associated with Owner Controlled Area Evacua |
ML021790123 | 7 June 2002 | Regulatory Conference with Entergy Operations, Inc., (River Bend Station) (Part 2) |
ML031110449 | 13 October 1999 | Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes |
RIS 1999-02, Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes | 13 October 1999 | Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes |
RBG-45094, Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation | 25 August 1999 | Responds to NRC Re Violations Noted in Insp Rept 50-458/98-16 Between 990720 & 0807.Corrective Actions:River Bend Will Submit Changes Associated with Lcn 15.06-006 & Accompanying Evaluation |
ML20210K472 | 3 August 1999 | SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves |
ML20196K685 | 30 June 1999 | Ack Receipt of & Denial of NOV in Response to Transmitting NOV & Insp Rept 50-458/98-16.Listed Info Documents Results of Review of Response to Violation Re fire-induced Circuit Faults |
NRC Generic Letter 1983-11 | 24 June 1999 | NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis |
NRC Generic Letter 1998-01 | 14 January 1999 | NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants |
ML20198G550 | 18 December 1998 | Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl |
NRC Generic Letter 1998-04 | 14 July 1998 | NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i |
RBG-44551, Responds to NRC Re Fire Protection Functional Insp Rept 50-458/97-201 on 970616-20 & 0630-0703.Requested Addl Info in Re Review of Certain Issues Found During Insp,Also Included | 30 June 1998 | Responds to NRC Re Fire Protection Functional Insp Rept 50-458/97-201 on 970616-20 & 0630-0703.Requested Addl Info in Re Review of Certain Issues Found During Insp,Also Included |
NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
NRC Generic Letter 1997-06 | 30 December 1997 | NRC Generic Letter 1997-006: Degradation of Steam Generator Internals |
NRC Generic Letter 1997-05 | 17 December 1997 | NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques |
NRC Generic Letter 1997-04 | 30 September 1997 | NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules |
ML20140D823 | 5 June 1997 | Provides Draft Fire Protection Functional Insp Procedure to Be Used to Conduct Upcoming NRR Lead Pilot Team Insp at Plant |
NRC Generic Letter 1997-02 | 15 May 1997 | NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report |
ML20135F061 | 7 March 1997 | Comments on GL 96-XX, Effectiveness of Ultrasonic Testing Sys in ISI Program |
Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents | 24 February 1997 | Implementation of a New Constraint on Radioactive Air Effluents |
NRC Generic Letter 1995-06 | 31 January 1997 | NRC Generic Letter 1995-006: Changes in Operator Licensing Program |
ML20133G218 | 9 January 1997 | Discusses Approval of ISI Program Plans for Listed Entergy Sites.Notice for Opportunity for Public Comment & Generic Communication on Effectiveness of Ultrasonic Testing Sys in ISI Programs Encl for Info |
RBG-43371, Forwards Response to NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Boiling Water Reactors | 4 November 1996 | Forwards Response to NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Boiling Water Reactors |
ML20129G311 | 28 October 1996 | Requests Exemption from 10CFR50.55a Requiring Licensee to Adopt Specific Procedures for Isi,Repair & Replacement of Class Mc & Class CC Metallic & Concrete Containment Components |
ML20134C905 | 8 October 1996 | Forwards Final Rept Re Spent Fuel Storage Pool Safety Issues |
NRC Generic Letter 1996-05 | 18 September 1996 | NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves |
ML20134C908 | 25 July 1996 | Discusses 960201 Meeting W/Sa Jackson Re Spent Fuel Pool Issues |
RBG-43070, Forwards Supplementary Info Re ISI Update for Ak Nuclear One Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station | 12 July 1996 | Forwards Supplementary Info Re ISI Update for Ak Nuclear One Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station |
NRC Generic Letter 1996-04 | 26 June 1996 | NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks |