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Title: Executive Summary: Prototype Design, Analysis, and Results for a Liquid Radiological Waste Control Room

Abstract

Under the United States Department of Energy Light Water Sustainability Program (LWRS), Idaho National Laboratory (INL) is collaborating with Palo Verde Generating Station (PVGS) to support human factors engineering efforts in the modernization of PVNGS’ radiological waste system (LRS) control room. The studies proposed and/or conducted by INL are designed to address the inconsistency between different human factors standards, guidance, and conventions. Guidance such as NUREG-0700 leave much of the information open to interpretation. INL will identify whether maintaining a design that is consistent with population stereotypes actually enhances performance, or whether there are alternative designs that yield performance that is better than the designs that maintain those stereotypes. The overall design concept for the LRS workstation includes system overview displays for the Evaporator system and the Boric Acid Concentrator system. A third display contains overview information for the rest of the LRS. The forth display contains alarm information. Each display will be presented on one of four monitors in the control room. The system overview displays contain embedded controls for valves and pumps, mini-trends, and micro-trends. The mini-trends present data for the controllers and contain alarm set point information as well as trending. All other relevant system parameters aremore » shown on micro-trends. The semi-dull screen approach utilized present dynamic data in green, active components are white (gray when closed or off). The product stream flow paths are indicated by different colors. Alarm states are presented in saturated red and selected components are indicated by bright blue. In addition to the micro task study described below, the INL researchers also conducted an evaluation of the semi-dull screen approach as well as an ergonomic evaluation of the suggested upgrades in the local control room. A detailed report of all INL’s activities related to the modernization of the LRS conducted between October 2016 and September 2017 are found in these two reports; • INL-EXT-17-43226, Prototype Design, Analysis, and Results for a Liquid Radiological Waste Control Room, and • INL-EXT-17-43250, Evaluation of Control Room Interface Designs to Support Modernization in Nuclear Power Plants.« less

Authors:
 [1];  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1466992
Report Number(s):
INL/EXT-17-44135
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United Kingdom
Language:
English
Subject:
47 OTHER INSTRUMENTATION; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; Radiological Waste Control Room

Citation Formats

Oxstrand, Johanna, and Le Blanc, Katya. Executive Summary: Prototype Design, Analysis, and Results for a Liquid Radiological Waste Control Room. United Kingdom: N. p., 2018. Web. doi:10.2172/1466992.
Oxstrand, Johanna, & Le Blanc, Katya. Executive Summary: Prototype Design, Analysis, and Results for a Liquid Radiological Waste Control Room. United Kingdom. doi:10.2172/1466992.
Oxstrand, Johanna, and Le Blanc, Katya. Mon . "Executive Summary: Prototype Design, Analysis, and Results for a Liquid Radiological Waste Control Room". United Kingdom. doi:10.2172/1466992. https://www.osti.gov/servlets/purl/1466992.
@article{osti_1466992,
title = {Executive Summary: Prototype Design, Analysis, and Results for a Liquid Radiological Waste Control Room},
author = {Oxstrand, Johanna and Le Blanc, Katya},
abstractNote = {Under the United States Department of Energy Light Water Sustainability Program (LWRS), Idaho National Laboratory (INL) is collaborating with Palo Verde Generating Station (PVGS) to support human factors engineering efforts in the modernization of PVNGS’ radiological waste system (LRS) control room. The studies proposed and/or conducted by INL are designed to address the inconsistency between different human factors standards, guidance, and conventions. Guidance such as NUREG-0700 leave much of the information open to interpretation. INL will identify whether maintaining a design that is consistent with population stereotypes actually enhances performance, or whether there are alternative designs that yield performance that is better than the designs that maintain those stereotypes. The overall design concept for the LRS workstation includes system overview displays for the Evaporator system and the Boric Acid Concentrator system. A third display contains overview information for the rest of the LRS. The forth display contains alarm information. Each display will be presented on one of four monitors in the control room. The system overview displays contain embedded controls for valves and pumps, mini-trends, and micro-trends. The mini-trends present data for the controllers and contain alarm set point information as well as trending. All other relevant system parameters are shown on micro-trends. The semi-dull screen approach utilized present dynamic data in green, active components are white (gray when closed or off). The product stream flow paths are indicated by different colors. Alarm states are presented in saturated red and selected components are indicated by bright blue. In addition to the micro task study described below, the INL researchers also conducted an evaluation of the semi-dull screen approach as well as an ergonomic evaluation of the suggested upgrades in the local control room. A detailed report of all INL’s activities related to the modernization of the LRS conducted between October 2016 and September 2017 are found in these two reports; • INL-EXT-17-43226, Prototype Design, Analysis, and Results for a Liquid Radiological Waste Control Room, and • INL-EXT-17-43250, Evaluation of Control Room Interface Designs to Support Modernization in Nuclear Power Plants.},
doi = {10.2172/1466992},
journal = {},
number = ,
volume = ,
place = {United Kingdom},
year = {2018},
month = {1}
}

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