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Identify and discuss key significant issues associated with current guidance for license amendments that include digital instrumentation and control in order to scope and plan activities to produce appropriate technical guidance.
Public teleconference meeting to discuss technical issues that need to be resolved associated with the NuScale Design Certification Application review in progress and to promote a common understanding of the technical issues associated with staff RAIs.
To discuss plant-specific technical and administrative issues in support of the pilot TMRE submittals for Shearon Harris Nuclear Power Plant and Vogtle Electric Generating Plant. The applicability of issues to the TMRE guidance and the pilot TMRE submittal for Grand Gulf Nuclear…
The U.S. Nuclear Regulatory Commission (NRC) staff and Korea Hydro and Nuclear Power Co., Ltd. (KHNP), will conduct a public meeting to discuss proprietary and non-proprietary topics of the Advanced Power Reactor 1400 related to probabilistic risk assessment (PRA), severe…
The U.S. Nuclear Regulatory Commission (NRC) staff and Korea Hydro and Nuclear Power Co., Ltd. (KHNP), will conduct a public meeting to discuss proprietary and non-proprietary topics of the Advanced Power Reactor 1400 (APR1400) related to Instrumentation and Controls (I&C).…
The purpose of this teleconference is to discuss DNC's planned license amendment request (LAR) for Millstone Power Station (Millstone), Unit No. 3. The proposed amendment would revise the Spent Fuel Pool Criticality Safety Analysis. DNC will discuss the scope and proposed…
The purpose of the teleconference is to discuss the James A. Fitzpatrick Nuclear Power Plant, proposed license amendment request to adopt TSTF-542, Revision 2.
The U.S. Nuclear Regulatory Commission (NRC) staff and Korea Hydro and Nuclear Power Co., Ltd. (KHNP), will conduct a series of public meetings to discuss proprietary and non-proprietary topics of the Advanced Power Reactor 1400 related to probabilistic risk assessment (PRA),…
To discuss the draft responses to the NRC staff requests for additional information on MRP-227, Rev 1, “Materials Reliability Program: Pressurized Water Reactor Internals Inspection And Evaluations Guideline"
The purpose of this meeting is to discuss NEI's model 10 CFR 50.69 license amendment request. This meeting will focus on a proposed approach to account for fire risk in 50.69 applications for plants that have not implemented National Fire Protection Association (NFPA)-805…
To discuss draft Fire Probabilistic Risk Assessment (FPRA) Frequently Asked Question (FAQ) 17-0012 Regarding Incipient Detection For Fire Prevention and Suppression
