Exploring the Use of Cognitive Work Analysis in Developing a Nuclear Power Plant New-State Vision

Author(s):  
Casey R. Kovesdi ◽  
Zachary A. Spielman

The United States nuclear industry needs to identify and implement a new strategy that will lower operating and maintenance costs while maintaining safety for existing plants. The industry must also have a clear and strategic vision of this transformative new state that focuses on ways in which technologies can be integrated to maximize the benefits of technology and people. While there are ongoing efforts in this area, this work discusses how the use of cognitive work analysis may offer further support. This paper provides an overview of cognitive work analysis, as well as the state of current new-state development efforts. The use of cognitive work analysis as a tool to enhance existing practices is presented to ensure the systematic and complete development of a new state vision.

2003 ◽  
Author(s):  
Michelle Rogers ◽  
Marta L. Render ◽  
Richard I. Cook ◽  
Robert Bower ◽  
Mark Molloy

Author(s):  
Thierry Morineau ◽  
Mounia Djenidi-Delfour ◽  
Fabrice Arnault

This study describes the concept of affordance-based procedure and its implementation in a triage station in a hospital emergency department. Rather than seeking to increase operators’ adherence to procedures, an affordance-based procedure (1) aims to induce task steps using affordances that also (2) support degrees of freedom for action. The design of this procedure was guided by the application of an extended version of cognitive work analysis, named “heuristic cognitive work analysis.” This design process produced a new procedural document: a reception card. Ten months after its implementation, a qualitative evaluation with 10 triage nurses shows that the reception card is viewed as supporting coordination between the different nurses’ tasks and providing an external memory to cope with frequent interruptions during high patient inflow, even though the document is used for convenience and with unexpected and partial uses of its items. The document assessed also afforded emerging benefits, that is, acceleration of ambulance release, higher level of confidentiality, assistance for staff hand-overs. Finally, novice triage nurses are particularly sensitive to the benefits brought by this affordance-based procedure.


Author(s):  
Ronald C. Lippy

The nuclear industry is preparing for the licensing and construction of new nuclear power plants in the United States. Several new designs have been developed and approved, including the “traditional” reactor designs, the passive safe shutdown designs and the small modular reactors (SMRs). The American Society of Mechanical Engineers (ASME) provides specific Codes used to perform preservice inspection/testing and inservice inspection/testing for many of the components used in the new reactor designs. The U.S. Nuclear Regulatory Commission (NRC) reviews information provided by applicants related to inservice testing (IST) programs for Design Certifications and Combined Licenses (COLs) under Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” in Title 10 of the Code of Federal Regulations (10 CFR Part 52) (Reference 1). The 2012 Edition of the ASME OM Code defines a post-2000 plant as a nuclear power plant that was issued (or will be issued) its construction permit, or combined license for construction and operation, by the applicable regulatory authority on or following January 1, 2000. The New Reactors OM Code (NROMC) Task Group (TG) of the ASME Code for Operation and Maintenance of Nuclear Power Plants (NROMC TG) is assigned the task of ensuring that the preservice testing (PST) and IST provisions in the ASME OM Code to address pumps, valves, and dynamic restraints (snubbers) in post-2000 nuclear power plants are adequate to provide reasonable assurance that the components will operate as needed when called upon. Currently, the NROMC TG is preparing proposed guidance for the treatment of active pumps, valves, and dynamic restraints with high safety significance in non-safety systems in passive post-2000 reactors including SMRs.


2013 ◽  
Vol 8 (1) ◽  
pp. 3-22 ◽  
Author(s):  
Tizneem Jiancaro ◽  
Greg A. Jamieson ◽  
Alex Mihailidis

2011 ◽  
Vol 21 (1) ◽  
pp. 62-84 ◽  
Author(s):  
Laura Millen ◽  
Tamsyn Edwards ◽  
David Golightly ◽  
Sarah Sharples ◽  
John R. Wilson ◽  
...  

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