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I&C Modeling in SPAR Models

Description: The Standardized Plant Analysis Risk (SPAR) models for the U.S. commercial nuclear power plants currently have very limited instrumentation and control (I&C) modeling [1]. Most of the I&C components in the operating plant SPAR models are related to the reactor protection system. This was identified as a finding during the industry peer review of SPAR models. While the Emergency Safeguard Features (ESF) actuation and control system was incorporated into the Peach Bottom Unit 2 SPAR model… more
Date: June 1, 2012
Creator: Schroeder, John A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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LWRS II&C Industry and Regulatory Engagement Activities for FY 11

Description: To ensure broad industry support and coordination for the Advanced Instrumentation, Information, and Controls (II&C) Systems Technologies research pathway, an engagement process will be continually pursued with nuclear asset owners, vendors, and suppliers, Nuclear Regulatory Commission (NRC), and the major industry support organizations of Electric Power Research Institute (EPRI), Institute of Nuclear Power Operations (INPO), and Nuclear Energy Institute (NEI). Nuclear asset owner engagemen… more
Date: September 1, 2011
Creator: Thomas, Ken
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Next Generation Nuclear Plant Resilient Control System Functional Analysis

Description: Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generat… more
Date: July 1, 2010
Creator: Stevens, Lynne M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effects of Degraded Digital Instrumentation and Control Systems on Human-system Interfaces and Operator Performance: HFE Review Guidance and Technical Basis

Description: New and advanced reactors will use integrated digital instrumentation and control (I&C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission (NRC) supported this research project to investigate the effects of degraded I&C systems on human perf… more
Date: February 26, 2010
Creator: O'Hara, J. M. & W. Gunther, G. Martinez-Guridi
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Framework for Evaluating the Effects of Degraded Digital I and C Systems on Human Performance

Description: New and advanced reactors will use integrated digital instrumentation and control (I&C) systems to support operators in their monitoring and control functions. Even though digital systems are typically highly reliable, their potential for degradation or failure could significantly affect operator situation awareness and performance and, consequently, impact plant safety. The U.S. Nuclear Regulatory Commission has initiated a research project to investigate the effects of degraded I&C sy… more
Date: April 9, 2009
Creator: O'Hara, John; Gunther, Bill; Hughes, N. & Barnes, V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Instrumentation Needs for Integral Primary System Reactors (IPSRs) - Task 1 Final Report

Description: This report presents the results of the Westinghouse work performed under Task 1 of this Financial Assistance Award and satisfies a Level 2 Milestone for the project. While most of the signals required for control of IPSRs are typical of other PWRs, the integral configuration poses some new challenges in the design or deployment of the sensors/instrumentation and, in some cases, requires completely new approaches. In response to this consideration, the overall objective of Task 1 was to establi… more
Date: September 30, 2005
Creator: Storrick, Gary D.; Petrovic, Bojan; Oriani, Luca; Conway, Lawrence E. & Conti, Diego
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prometheus Reactor I&C Software Development Methodology, for Action

Description: The purpose of this letter is to submit the Reactor Instrumentation and Control (I&C) software life cycle, development methodology, and programming language selections and rationale for project Prometheus to NR for approval. This letter also provides the draft Reactor I&C Software Development Process Manual and Reactor Module Software Development Plan to NR for information.
Date: July 30, 2005
Creator: Hamilton, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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UPGRADE OF INSTRUMENTATION FOR PURDUE REACTOR PUR-1, PHASE 3

Description: The major objective of this program is to upgrade and replace instruments and equipment that significantly improve the performance, control and operational capability of the Purdue University nuclear reactor (PUR-1). Under this major objective one project on design and installation of interface cards for channel four detector was considered. This report is the final report and gives the efforts and progress achieved on these projects from August 2002 to July 2004.
Date: September 24, 2004
Creator: Revankar, S. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Issues Associated With Probabilistic Failure Modeling of Digital Systems

Description: The current U.S. Nuclear Regulatory Commission (NRC) licensing process of instrumentation and control (I&C) systems is based on deterministic requirements, e.g., single failure criteria, and defense in depth and diversity. Probabilistic considerations can be used as supplements to the deterministic process. The National Research Council has recommended development of methods for estimating failure probabilities of digital systems, including commercial off-the-shelf (COTS) equipment, for use… more
Date: September 19, 2004
Creator: Chu, T. L.; Martinez-Guridi,G.; Lehner, J. & Overland, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Ion Chamber Compensation Tests

Description: The purpose of this report is to present the results of a series of tests performed to determine the need for gamma compensation of the ion chambers used to monitor the neutron flux in the 100 Area reactors.
Date: February 14, 2003
Creator: Mallard, R. L., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Pattern Recognition Methodology for Determining Operationally Optimal Heat Balance Instrumentation Calibration Schedules

Description: The goal of the project is to enable plant operators to detect with high sensitivity and reliability the onset of decalibration drifts in all of the instrumentation used as input to the reactor heat balance calculations. To achieve this objective, the collaborators developed and implemented at DBNPS an extension of the Multivariate State Estimation Technique (MSET) pattern recognition methodology pioneered by ANAL. The extension was implemented during the second phase of the project and fully a… more
Date: December 15, 2002
Creator: Beran, Kurt; Christenson, John; Nica, Dragos & Gross, Kenny
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Synergistic Use of IEEE and IEC Nuclear Power Plant Standards

Description: Many organizations worldwide develop standards that affect nuclear instrumentation and control (I and C). Two of the primary standards organizations are the US IEEE's Nuclear Power Engineering Committee (NPEC), and the IEC subcommittee on Reactor Instrumentation (SC45A). This paper surveys the contents of the two sets of standards. Opportunities for complementary use of IEEE and IEC standards are discussed. The collections of IEEE. and IEC standards have some overlap, but in many cases cover si… more
Date: December 19, 2001
Creator: Johnson, G
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EMI/RFI and Power Surge Withstand Guidance for the U.S. Nuclear Regulatory Commission

Description: This paper discusses the regulatory guidance implemented by U.S. NRC for minimizing malfunctions and upsets in safety-related instrumentation and control (I and C) systems in nuclear power plants caused by electromagnetic interference (EMI), radio-frequency interference (RFI), and power surges. The engineering design, installation, and testing practices deemed acceptable to U.S. NRC are described in Regulatory Guide (RG) 1.180, ''Guidelines for Evaluating Electromagnetic and Radio-Frequency in … more
Date: September 7, 2001
Creator: Ewing, P. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

Description: This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I&C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I&C system upgrades of present-day nuclear pow… more
Date: August 24, 2001
Creator: Korsah, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Upgrade of Instrumentation for Purdue Reactor PUR-1

Description: The major objective of this program was to upgrade and replace instruments and equipment that significantly improve the performance, control and operational capability of the Purdue University nuclear reactor (PUR-1). Under this major objective two projects on instrument upgrade were implemented. The first one was to convert the vacuum tube control and safety amplifiers (CSA) to solid state electronics, and the other was to upgrade the electrical and electronic shielding. This report is the ann… more
Date: August 28, 2000
Creator: Revankar, S. T.; Merritt, E. & Bean, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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University Reactor Instrumentation Grant

Description: A noble gas air monitoring system was purchased through the University Reactor Instrumentation Grant Program. This monitor was installed in the Kansas State TRIGA reactor bay at a location near the top surface of the reactor pool according to recommendation by the supplier. This system is now functional and has been incorporated into the facility license.
Date: February 2000
Creator: Bajorek, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NSTX High Temperature Sensor Systems

Description: The design of the more than 300 in-vessel sensor systems for the National Spherical Torus Experiment (NSTX) has encountered several challenging fusion reactor diagnostic issues involving high temperatures and space constraints. This has resulted in unique miniature, high temperature in-vessel sensor systems mounted in small spaces behind plasma facing armor tiles, and they are prototypical of possible high power reactor first-wall applications. In the Center Stack, Divertor, Passive Plate, and … more
Date: November 1, 1999
Creator: B.McCormack; Kugel, H.W.; Goranson, P.; Kaita, R. & al, et
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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U.S. Department of Energy University Reactor Instrumentation Program Final Report for 1992-94 Grant for the University of Florida Training Reactor

Description: Overall, the instrumentation obtained under the first year 1992-93 University Reactor Instrumentation Program grant assured that the goals of the program were well understood and met as well as possible at the level of support provided for the University of Florida Training Reactor facility. Though the initial grant support of $21,000 provided toward the purchase of $23,865 of proposed instrumentation certainly did not meet many of the facility's needs, the instrumentation items obtained and im… more
Date: April 1, 1999
Creator: Vernetson, William G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurements of the Effects of Smoke on Active Circuits

Description: Smoke has long been recognized as the most common source of fire damage to electrical equipment; however, most failures have been analyzed after the fire was out and the smoke vented. The effects caused while the smoke is still in the air have not been explored. Such effects have implications for new digital equipment being installed in nuclear reactors. The U.S. Nuclear Regulatory Commission is sponsoring work to determine the impact of smoke on digital instrumentation and control. As part of … more
Date: February 9, 1999
Creator: Tanaka, T. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Upgrade of the NCSU PULSTAR instrumentation power channels. Final technical report, September 1, 1992--August 31, 1994

Description: The Nuclear Reactor Program at North Carolina State University initiated an upgrade program at the NCSU PULSTAR Reactor in 1990. The originally supplied instrumentation has been replaced with solid-state and current technology equipment. The financial assistance from the US Department of Energy has been the primary source of support. This is the final report for the Instrumentation Upgrade.
Date: November 13, 1998
Creator: Perez, P. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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University Reactor Instrumentation grant program. Final report, September 7, 1990--August 31, 1995

Description: The Ohio State University Nuclear Reactor Laboratory (OSU NRL) participated in the Department of Energy (DOE) grant program commonly denoted as the University Reactor Instrumentation (URI) program from the period September 1990 through August 1995, after which funding was terminated on a programmatic basis by DOE. This program provided funding support for acquisition of capital equipment targeted for facility upgrades and improvements, including modernizing reactor systems and instrumentation, … more
Date: June 17, 1998
Creator: Talnagi, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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