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| Issue date | Site | Title | |
|---|---|---|---|
| ML24115A066 | 23 April 2024 | Correct-by-Construction Reactor Protection Systems-WORD Document | |
| ML24115A065 | 23 April 2024 | Correct-by-Construction Reactor Protection Systems-PowerPoint Presentation | |
| ML23081A462 | 24 March 2023 | Rev 3 Periodic Review | |
| ML23075A072 | 23 March 2023 | Rev 0 Periodic Review | |
| ML22140A311 | 8 March 2022 | coffins-hv-t7 | |
| ML22277A013 | 30 September 2021 | Investigation of the Use of Causal Analysis Based on System Theory (CAST) at the NRC | |
| SECY-18-0090, Enclosure 1 - Plan for Addressing Potential Common Cause Failure in Digital Instrumentation and Controls | 12 September 2018 | SECY-18-0090: Enclosure 1 - Plan for Addressing Potential Common Cause Failure in Digital Instrumentation and Controls | |
| ML18143A006 | 24 May 2018 | Path Forward on Protection Against Common Cause Failure (Staff Presentation - May 24, 2018) | |
| ML17313A110 | 9 November 2017 | CCF Definition and Notes in NEI 16-16 (Draft 2) | |
| ML17257A412 | 14 September 2017 | NRC Follow-up Action to Sept 7 Meeting-Common Cause Failure Definitions | |
| ML24177A278 | 30 November 2012 | Evaluating the Safety of Digital Instrumentation and Control Systems in Nuclear Power Plants | |
| ML12088A497 | 28 March 2012 | Indian Point | Entergy Pre-Filed Hearing Exhibit ENT000109, a Method for Constructing Reduced Order Transformer Models for System Studies from Detailed Lumped Parameter Models. |
| ML12338A490 | 28 March 2012 | Indian Point | Official Exhibit - ENT000109-00-BD01 - a Method for Constructing Reduced Order Transformer Models for System Studies from Detailed Lumped Parameter Models. |
| ML072060123 | 25 July 2007 | Wolf Creek | Summary of Category 2 Public Meeting Between the Nuclear Regulatory Commission Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) |
| ML072060229 | 24 July 2007 | Wolf Creek | Summary of the July 12, 2007 Category 2 Public Meeting Between the Nuclear Regulatory Commission Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) |
| ML071860672 | 5 July 2007 | Wolf Creek | 06/19-20/2007 Summary of Category 2 Public Meeting Between the NRC Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) Regarding the Likelihood That Pressurizer Nozzle Dissimilar Metal Welds Will Leak Before |
| ML071800457 | 29 June 2007 | Wolf Creek | Notice of Meeting Between the Nuclear Regulatory Commission Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analysis |
| ML071570611 | 12 June 2007 | Wolf Creek | Summary of Category 2 Public Meeting with Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) Regarding the NRC Staff'S Questions About the Likelihood That Rupture May Occur Without Prior Evidence of Leakage in Pressurize |
| ML071350527 | 15 May 2007 | Wolf Creek | 06/01/07 - Meeting Between the Nuclear Regulatory Commission Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses |
| ML071350538 | 14 May 2007 | Wolf Creek | Summary of the May 1, 2007, Category 2 Public Meeting Between the Nuclear Regulatory Commission Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) |
| ML071020308 | 11 April 2007 | Wolf Creek | Notice of Meeting Between the Nuclear Regulatory Commission Staff and the Expert Panel for the Wolf Creek Advanced Fea Analyses |
| ML070890431 | 30 March 2007 | Point Beach | Steam Generator Program Amendment Need for Discussion |
| ML070740149 | 15 March 2007 | Browns Ferry Zion | Notice of Meeting with the Tennessee Valley Authority (TVA) Concerning the Status of Browns Ferry Nuclear Plant, Units 1, 2, and 3 Extended Power Uprate |
| ML070710427 | 12 March 2007 | Browns Ferry Zion | Notice of Meeting with the Tennessee Valley Authority Concerning the Status of Browns Ferry Nuclear Plant, Units 1, 2, and 3 Extended Power Uprate |
| ML070330429 | 15 February 2007 | Browns Ferry PROJ0710 | BFN Meeting Summary, Meeting with GE and TVA on Void Correlation Methods Ltr NEDC-33173P |
| ML070230095 | 29 January 2007 | Browns Ferry | Summary of Meeting with Tennessee Valey Authority to Discuss Various Topics Regarding Tva'S Power Uprate Amendment Request for Browns Ferry Nuclear Plant |
| ML063380112 | 28 December 2006 | Browns Ferry | Meeting Summary, Status of Unit 1 Power Uprate (TAC MC8312 and MD3048) (TS-418) |
| ML061280089 | 24 February 2005 | Waterford | ER-W3-2004-0478-000, Steam Generator Sub-Compartment Platforms Addition Impact |
| ML20045F034 | 31 May 1993 | Waterford | Basemat Monitoring Program Rept 5. |
| ML20095L102 | 1 May 1992 | Waterford | Basemat Monitoring Program Rept 4 |