Proceedingsof the

1996 American Nuclear SocietyInternational Topical Meeting

on

Nuclear PlantInstrumentation, Control

and Human-Machine InterfaceTechnologies, NPIC&HMIT'96

Sponsored by:

Cosponsored by:

The Nittany Lion Inn,The Pennsylvania State University, USA

May 6-9,1996

The Power, Nuclear Operations and Human Factors Divisions andThe Pittsburgh Section of The American Nuclear Society (ANS)

The Electric Power Research Institute (EPRI),US Department of Energy (DOE),

US Nuclear Regulatory Commission (NRC),Three Rivers Chapter of the Human Factors and Ergonomics Society (HFES),

Institute of Electrical and Electronics Engineers (IEEE),IEEE Power Engineering Society Nuclear PowerEngineering Committee (IEEE PES NPEC),

Sociedad Nuclear Mexicans (SNM),Canadian Nuclear Society (CNS),

Atomic Energy Council (AEC) Republic of China,Atomic Energy Society of Japan (AESJ),

European Nuclear Society (ENS, Overseas Co-sponsorship),Korean Nuclear Society (KNS).

Published by theAmerican Nuclear Society, Inc. UB/TIB Hannover 89

La Grange Park, Illinois 60525 USA U 5 m m

HMI Performance in I&C HMI

Session Chair: 5. A. Brown-VanHoozer (ANL West)Topic Organizer Don W. Miller (Ohio State)

Towards the Optimum Automation Level in N.P.P.Operation and Control the Escrime Project / BernardPapin and Charles Fiche (C. E. Cadarache SSAE/LCSR).. 795

Base Principles and Approach at Design of GeneralizedOperator Support System (GOSS) / A. S. Stebenev, A. P.Eperin, M. M. Khoudiakov (Leningrad NPP), and I. D.Rakitin (RRC Kurchatov Institute) 803

Complex Methodology of Safety Regulation-System ofDynamic Barriers (SDB) Preventing the Development ofEmergency Transients at Nuclear Power Plants / A. S.Stebenev, A. P.Eperin, M. M. Khoudiakov (LeningradNPP), and 1. D. Rakitin (RRC Kurchatov Institute) 811

Ergonomic Analysis of Nuclear Plant Operator Activity /Alexey N. Anokhin (Obninsk Institute of Nuclear PowerEngineering) 817

Advanced I&C Technology

Session Chair and Topic Organizer:S. A. Brown-VanHoozer (ANL West)

A Conceptual Design of the Digital Nuclear PowerControl System by the Order Increased LQR Method /Yoon Joon Lee (Cheju National University) 827

Enhancing an Intelligent Reconfigurable Reactor PowerController / Stephen J. Kenney and Robert M. Edwards(Penn State) 835

Toward Autonomous Control of Nuclear Power SystemsUsing Supervisory Reconfigurable Control / Phillip B.Walter and Robert M. Edwards (Penn State) 843

Development of a UNIX Network Compatible ReactivityComputer / Roberto F. Sanchez and Robert M. Edwards(Penn State) 851

Reactor Temperature Control Experiments Using ModernDesign Tools with Automated Program Generation / GaryL Meyers, Richard M. Johns, and Robert M. Edwards(Penn State) 859

Design of a Fuzzy Logic Controller for the ITU TRIGAMark-n Reactor / A. Fevzi Baba, Burhanettin Can, IhsanGSk, and Erbil Akbay (Marmara University) 867

Failure Detection in Control Systems Using PrincipalComponents / Wayne C. Jouse and RadjakicheninRadjassamy (Univeristy of Arizona) 873

Noise Analysis Applications in Nuclear Plants #1

Session Chair and Topic Organizer:O. Glockler (Ontario Hydro Nuclear)

Feasibility of Subcriticality and NDA Measurements forSpent Fuel by Frequency Analysis Techniques with M2Cf/ / T. Mihalczo, T. E. Valentine, and J. K. Mattingly(ORNL) (Invited) 883

Study of a Cross Correlation Technique for LeakLocalization on PWR Primary Circuits by AcousticEmission / Cic'ue Comu (Commissariat a I'EnergieAtomique) 893

Reconstruction Process Algorithm of the CorruptedMetal Impact Signal Based on the Adaptive Filtering inNuclear Power Plant / D. I. Kim, W. K. Shin, S. H. Oh,and W. Y. Yun (Korea Institute of Nuclear Safety) 901

Digital Ratemeter / CJaudio A. Verrastw (CentroAtomico Ezeiza, Argentina) 905

Advanced Process Sensor Technology #2

Session Chair: 0. Glockler (Ontario Hydro Nuclear)Topic Organizers: David E. Holcomb (ORNL) and Revis James

(EPRI)

System Behavior Detection Using Parameter TransferFunctions / Igor Salamun, Borut Mavko, and AndrejStritar (University of Ljubljana, "Joief Stefan"Institute) 915

Recurrent Neural Network for Fault Detection andIsolation / T. M. Tsai (Industrial Technology ResearchInstitute) and H. P. Chou (National Tsing HuaUniversity) 921

Inferential Neural Networks for Nuclear Power PlantSensor Channel Drift Monitoring / Chris L. Black, J.Wesley Hines, and Robert E. Uhrig (University ofTennessee) 927

Smart System Application to Nuclear Reactor CoolantTemperature Measurement / Jan Tomlk and StanislavStanc (Nuclear Power Plant Research Institute) 935

Operating Longevity of Thermocouples in WERReactor / Alexandre S. Timonin and Lev I. Firsov (RRCKurchatov Institute) 943

Commercial Dedication of Software-BasedEquipment

Session Chair and Topic OrganizerRay Torok (EPRI)

Evaluation and Acceptance of Commercial Software-Based Equipment In Nuclear Power Plant Safety SystemsIR. T. Fink (MPR Associates, Inc.), C. M. Waite (PublicService Electric and Gas), and R. C. Torok (EPRI). 949

Commercial Dedication of Computer Based SystemsApproach in the EPR Basic Design / Giuseppe Skull andGeorg Winded (Siemens KWU) 9 5 7

Functional Evaluation of Digital Control System(DCS's) for Nuclear Power Plant / Patrick Salaun(Electricixi de France) 9 6 5

ANRC Perspective on the Revised 10CFR Part 21 Rulefor the Procurement of Commercial Digital ComputersSystems for use in Safety System Applications inNuclear Power Facilities / James C. Stewart (U.S. NRC).. 971

A Procurement Engineering View of Commercial GradeDigital Equipment / Rory M. Mackie (Houston Lighting& Power) 975

A Buyer's Guide to Digital Systems the Good System:Fact or Fiction? / Charles M. Waite (Kemper-Masterson,Inc.) (Invited) 979

Commercial Grade Dedication of a Digital Single LoopController / Bruce Geddes and Doug Lenker (BaltimoreGas & Electric Company) 987

Panel Discussion:Evaluation of Commercial Equipment

How Much is Enough?

Moderated by Ray Torok (EPRI)

Safety Critical Software #3

Session Chair. Robert Brill (U.S. NRC)Topic Organizer: Leo Beltracchi (U.S. NRC)

An Integrated Formal Approach for Developing HighQuality Software for Safety-Critical Systems / MengOuyang, Michael W. Golay (MIT), and Michael S. Novak(ABB Combustion Engineering Inc.) 995

A Safety Kernel Approach to Critical Real-timeController / Jang S. Lee and Kee C. Kwon (KAERI) 1003

Analysis and Design of a Licensable Computing Systemfor Safety-Critical Applications / Swu Yih (SouthernMethodist University), Behrooz Shirazi (University ofTexas at Arlington), and Chin-Feng Fan (Yan-ZeInstitute of Technology) 1011

Validation and Reliability Testing of Safety-CriticalSoftware for Wolsong NPP Units 2, 3 and 4 / J. S.Baxter, A.M. McDonald, F.Y. Lam, N.D. Thai (AtomicEnergy Canada Limited), H.B. Kim, J.H. Kim, J.M. Koo,and C.S. Chun (KAERI). 1019

Analysis of Control Software in Advanced ReactorsUsing the Dynamic Flowgraph Methodology (DFM) /Sergio B. Guam and Michael K. You (ASCA Inc)(Invited) 1025

Using A Program Slicing CASE Tool for EvaluatingHigh Integrity Software Systems / Leo Beltracchi (U.S.NRC), James R. Lyle, and Dolores R. Wallace (NIST). .. 1033

A Case Study of Structured Analysis and StructuredDesign Methodology for Safety-Related SoftwareDevelopment / Jang-Yeol Kim and Ki-Choon Kwon(KAERI). 1041

Project Data to Support High Integrity Software Methods/ Herbert Hecht (SoHaR Inc.) and Dolores Wallace(NIST) 1047

Noise Analysis Applications in Nuclear Plants #2

Session Chair: Josi March-Leuba (ORNL)Topic Organizer: O. Glockler (Ontario Hydro Nuclear)

Experience with Noise Analysis in German PWRs andBWRs / J. Runkel and D. Stegemann (University ofHanover) (Invited) 1057

Reactor Noise Analysis Applications in WWER-440 andWWER-1000 Type PWRs / G. Por (Technical Universityof Budapest) (Invited) 1069

Reactor Noise Analysis Applications in Ontario Hydro'sCANDU Stations / O. Glockler, D. F. Cooke, and M. V.Tulettx (Ontario Hydro Nuclear) 1077

Portable System for Reactor Noise Data Acquisition / S.T. Craig, P. D. Tonner, J. P. Johnston, L E. Nicholson(AECL), O. Glockler, and D. Williams (Ontario HydroNuclear) 1085

Sensor Diagnostics in a BWR Based on Noise Analysis /Bengt-Goran Bergdahl, Bohao LJao, Ritsuo Oguma(EuroSim AB), and Herbert Schwaninger (BKW EnergieAG) (Invited) 1091

On-Line Parameter Estimation for a Nuclear ReactorUsing an Extended Kalman Filter / Miguel Cecenas-Falcdn and Robert M. Edwards (Penn State) 1099

Boiling Water Reactor Stability Analysis via KalmanFilter-Based State Estimation and Maximum a PosterioriProbability Detection / James A. Turso, R. M. Edwards,and Thomas W. Hilands (Penn State) 1107

A Core Stability Monitor for the Laguna Verde NuclearPower Station / Hfctor Ocampo, Pedro Rafael Mendoza,and Jaime B. Morales (Instituto de InvestigacionesElictrias) 1117

Modeling Operator Behaviors

Session Chair: Greg Galetti (U.S. NRC)Topic Organizer Douglas G. Hoecker (Westinghouse)

How Do Operators Monitor a Nuclear Power Plant?: AField Study / Kim J. Vicente, Catherine M. Burns(University of Toronto), Randall J. Mumaw, and EmilieM. Roth (Westinghouse STC) 1127

Using Models of Operator Performance to Support MMISDesign: An Example in the Use of Procedural Aids /Douglas G. Hoecker and Emilie M. Roth (WestinghouseSTC). 1135

Using Simulated Human Model for Evaluating Human-Machine Interfaces: Validation of CAMEO / HiroshiSakuda, Tomihiko Furuta (Institute of Human Factors),Ichiro Yanagisawa, Kazuo Tanaka, and Yushi Fujita(Mitsubishi Heavy Industries, Ltd.) 1141

Validating Physiological Measures for the CognitiveBehavior Analysis Using Neural Network / MakotoTakahashi, Osamu Kubo, Akira Yasuta, HidekazuYoshikawa (Kyoto University), Kazunori Sasaki, TomItoh, Masayuki Matsumiya, Yoshinobu Yamanaka(Mitsubishi Electric Co. Ltd.), Kazuhiro Kiyokawa, andAkira Hasegawa (Nuclear Power EngineeringCorporation) 1147

MMI Evaluation

Session Chair Mark Feher (AECL)Topic Organizer Douglas G. Hoecker (Westinghouse STC)

Human Factors Issues in Digital System Design andImplementation / Greg S. Galletti (U.S. NRC) 1157

Simulation Based MMI Evaluation Support System:SEAMAID System / Takashi Nakagawa, Yoshio Nakatani(Mitsubishi Electric Corporation), Hidekazu Yoshikawa,Makoto Takahashi (Kyoto University), TomihikoFuruta, and Akira Hasegawa (Nuclear EngineeringCorporation) 1167

Main Control Room Task Analysis in Korean NuclearPower Plant Design / Jung Chang Na (KOPEC) 1173

Electronic Environment Issues, EMI/RFI

Session Chair: Richard Wood (ORNL)Topic Organizer: Dwayne Fry (ORNL)

Understanding of EMI/RFI and Digital Updates / Eric J.Lee (U.S. NRC) 1181

Survey of EMI Ambient Levels in Nuclear Power Plants /Stephen W. Kercel (ORNL) (Invited) 1189

Advanced Digital I&C Systems in Nuclear Power Plants:Risk-Sensitivities to Environmental Stressors /Mahbubul Hassan (BNL) and William E. Vesely (ScienceApplications International Corporation) 1197

Environmental Effects Testing of an ExperimentalDigital Safety Channel / Kofi Korsah, Thomas L.Wilson, Jr., and Richard T. Wood (ORNL) (Invited) 1203

U.S. Experience in Upgrade of I&C

Session Chair Richard Wood (ORNL)Topic Organizer: Dwayne Fry (ORNL)

Electromagnetic Interference and Radio FrequencyInterference Testing at the Palo Verde Nuclear GeneratingStation / Ay D. Nguyen (Arizona Public Service) 1215

Integration of Upgraded Neutron Flux MonitoringSystems into the St. Lucie Nuclear Power Plant /Laurence D. Hiegel, Christopher Chartier (Florida Power& Light Company), Robert W. McDowell, and James F.Miller (GAMMA-METRICS) 1221

Millstone Nuclear Unit 3 Control System DigitalUpgrade / Leonid G. Meter, and Gilbert M. Olsen(Northeast Nuclear Energy Company) 1227

Panel Discussion: Inspection Insights from U.S.I&C Upgrades

Moderated by: William H. Ruland and John A. Calvert(U.S. NRC)

Use of Standards in Safety Critical Systems #2

Session Chair: Joel Kramer (US. NRC)Topic Organizer: Leo Beltracchi (U.S. NRC)

Software Quality Measures for Improving the SoftwareProcess for Digital I&C Safety Systems / John Waclo(Westinghouse Electric Corporation) 1237

Guidelines for the Use of Software Tools for theDevelopment and the Maintenance of Safety Systems /Nguyen N. Q. Thuy and Frangoise Ficheux-Vapne(Electricity de France) 1245

Development of a Software Test Case Generator forNuclear Plant I&C System Software / Han S. Son andPoong H. Seong (KAIST) 1251

A Study on Software Verification for Shutdown SystemNo. 1 of Wolsong 2, 3 and 4 in CANDU / Ki Chang Son,Chong Son Chun, Se Do Sohn, Byung Chai Lee,Byeong Joo Lee (KAERI), and Bob R.Whittall (AtomicEnergy of Canada Ltd.) 1259

Reconciling the Structured Software Design Process toLarge Scale Nuclear I&C Project Schedules / Bruce M.Cook (Westinghouse Electric Corporation) 1265

Stability Monitoring of Boiling Water Reactors /Frigyes Reisch (Swedish Nuclear Power Inspectorate(SKI)) andAdly Wahba (GRS) 1273

Maintenance and Condition Monitoring Issues #1

Session Chair and Topic Organizer:Hash M. Hashemian (AMS Inc.)

Transition from Prescriptive to Performance BasedRegulations / S. C. Black, R. P. Correia, and C. D.Petrone (U. S. NRC) (Invited) 1283

Reducing Outage l ime through Automated Tests to MeetTechnical Specification Requirements / H. M.Hashemian (Analysis and Measurement ServicesCorporation) 1289

Automated Reactor Internals Vibration MonitoringSystem Using Fuzzy Algorithm for Pattern Recognitionand Diagnosis / S. H. Kim, H. G. Shin, Y. B. Kim, S. J.Han, C. S. Chun (KAERI), and H. G. Kong (KAIST) 1297

Equipment Condition Diagnostics Application toWER"S / Thomas A. Kozlosky and Sam S. Palusamy(Westinghouse Electric Company) 1305

On-line Condition Monitoring of Large RotatingMachinery in NPPs / Dieter Wach and Werner Bastl(Institute for Safety Technology (ISTec) GmbH)(Invited) 1313

A Study on Improved Detection Instrumentation for theAnnulus Gas System of Wolsong 2 in CANDU / SeogNam Kim, Ik Ho Chang, Ho Chang Jung, Jun Mo Koo,and Jai Bok Han (KAERI) 1321

Statistical Analysis of the F t Calhoun Reactor CoolantPump System / Bimal Patel and Carolyn D. Heising(Iowa State University) 1329

A Fuzzy Logic Decision Making for Multi-ModuleSignal Validation Algorithms / A. S. Erbay and B. R.Upadhyaya (University of Tenneessee) 1337

Advanced Control Room Design and Upgrades #1

Session Chair and Topic Organizer:Barry Simon (GE Nuclear Energy)

Control Room I&C Upgrades, Innovations, and HMIConsiderations for the Temelin Nuclear Plant / Robert G.Orendi (Westinghouse Electric Corporation) (Invited)... 1345

A Design Basis for the Development of CANDU ControlCentres / M. P. Feher, E C. Davey, L R. Lupton, and M.J. MacBeth (AECL) 1353

Computer-Based Operator Support Systems-HungarianExperiences / Ferenc Adorjdn, Ivan Lux, and Jdnos Vigh(KFKI Atomic Energy Research Institute) (Invited). 1361

An Integrated Approach to Alarm Processing / /. S. Kim,I. K. Hwang, D. Y. Lee, J. C. Park, and C. S. Ham(KAERI) 1369

Development of a Control Room Philosophy - A Studyfor Development of an Advanced Computerised BWRControl Room Design Concept in Sweden / Conny B.O.HolmstrSm, Jon 0yen Hol, Peter Lirvall, (OECD HaldenReactor Project), Hans Carlsson, Thomas Gunnarsson,Yngve Ohlsson, Dennis Schafstrom (OskarshamnNuclear Power Plant), and Thomas Gorans son (BarsebackNuclear Power Plant) 1377

Human-Machine Interface Concepts for the ABWR /Richard Gutiirrez, Jay B. Jelinek, and Timothy O'Neil(General Electric Company). 1385

Use of Computer-Based Operator Support Systems inControl Room Upgrades and New Control Room Designsfor Nuclear Power Plants / T. J. Bj0rlo and 0. Berg(OECD Halden Reactor Project) 1397

The Concept of RBMK-1000 Operator Support Systemand Operational Experience / Vladimir E. Druzhinin,Konstantin I. Smirnov, Dmitry A. Lysov, Leonoid R.Pogosbekyan, Yury V. Shmonin, and Sergey A.Bychkov (All Russian Research Institute for NPPOperation) 1405

Model-Based Control and Diagnostics

Session Chair and Topic OrganizerS. A. Brown-VanHoozer (ANL West)

Adaptive Robust Control of the EBR-II Reactor /Michael Power (ANL) and Robert M. Edwards (PennState) 1413

Generalized Smith Predictor for Robust Control ofNuclear Reactors with Time Delays / Mohamed A.Abdelrahman, Kevin L Moore, and D. Subbaram Naidu(Idaho State University) 1421

Transients Mitigation by Qualitative And QuantitativeModel Based Predictive Control / Akira Fukumoto,Yukio Sonoda, Tetsuo Tamaoki, Tetsuo Yanai, and TakaoKageyama (Toshiba Corp.) 1429

Flexible Human Machine Interface for ProcessDiagnostics / Jaques Reifman, G. E. Graham, Thomas Y.C. Wei (ANL), Kevin R. Brown, and Ronald Y. Chin(ComEd) 1437

Maintenance and Condition Monitoring Issues #2

Session Chair and Topic Organizer:Hash M. Hashemian (AMS Inc.)

A Method of Knowledge Base Verification for NPPExpert Systems Using Extended Petri Nets IIIW. Kwonand Poong H. Seong (KAJST) 1447

Automated Digital Testing and Calibration for AnalogReactor Protection Systems / H. Gordon Shugars, JamesD. Simpson (GAMMA-METRICS), James J. Galligan(VECTRA), and Steven Hedden (ComEd) 1455

Automated Rod Drop Time Testing and Diagnostics inSoviet Designed RBMK and WER Reactors / H. M.Hashemian andR. E. Fain (Analysis and MeasurementServices Corporation) 1461

I&C/HMI in Advanced Light Water Reactors

Session Chair and Topic Organizer:G. Remley (Westinghouse)

Advanced Main Control Boards for Japanese APWRPlants / Takashi Ohno (Mitsubishi Heavy Industries,Ltd) and Masayuki Matsumiya (Mitsubishi ElectricCorp.) (Invited) 1471

The Use of an Integrated Test Environment in the Designand Verification of Digital Closed Loop AutomaticControl Systems for the Sizewell B Pressurized WaterReactor / Gregory P. Paulson, Albert G. Feczko(Westinghouse Electric Corporation), Kevin Drury, andAndrew Johnson (Nuclear Electric Ltd.) 1479

Multiplexed Plant Data System Design Considerationsfor Advanced Nuclear Power Plants / Joseph J. Birsa(Westinghouse Electric Corporation) 1489

Application of Advanced Plant-Wide Data Networks inthe ABWR First-of-a-Kind Engineering (FOAKE)Program / Barry Simon and Leslie J. Birch (GE NuclearEnergy) 1495

An Optimization Tool for Configuration ofInstrumentation and Control Cabinets in the French N4Nuclear Power Plant/ Tanguy Le Quenven (Electriciti deFrance) (Invited) 1497

Development Strategies of an Intelligent Human-Machine Interface for Next Generation Nuclear PowerPlants / Soon Heung Chang, Seong Soo Choi, Jin KyunPark, Jin Hyuk Hong, and Han Gon Kim (KAIST) 1503

Virtual Environment for Integrated Design Support(VTNDS) for Conceptual Design of Advanced ReactorSystems / Hidekazu Yoshikawa, Makoto Takahashi,Takashi Nagamatsu, and Satoshi Takeoka (KyotoUniversity) 1511

Advances in I&C-HMI with Potential NuclearPlant Application #2

Session Chair and Topic Organizer:H. Meieran (PHD Technologies)

Upgrade of the Los Alamos Plutonium Facility ControlSystem /Noah G. Pope, Willie Jim Turner, and Ryan E.Brown, Roland A. Bibeau, Robert R. Davis, and KevinHogan (Los Alamos National Laboratory) 1521

A Perception System for Advanced Human RobotInteraction I Jim Osborn (Carnegie Mellon University). 1529

Real-Time Monitoring and Control of the Plasma HearthProcess / Michael Power, Kevin P. Carney, and GregoryG. Peters (ANL). 1531

The 10-Year Old U/M Rug (Utility/Manufacturers RobotUsers Group) Keeps on Going and Going and Going .... /Harvey B. Meieran (PHD Technologies Inc.) 1535

Advanced Control Room Design and Upgrades #2

Session Chair and Topic OrganizerBarry Simon (GE Nuclear Energy)

Formal Specification of a User Interface / Susan S.Brilliant (Virginia Commonwealth University), John C.Knight, and Matthew C. Elder (University of Virginia) . . 1545

Plant Information Processing System for Korean FutureNuclear Power Plants / Yong Suk Suh, Gwi Sook Jang,Tai Hoon Lee, In Soo Koo, and Jong Kyun Park(KAERI) 1553

Development of a New Indicator and Alarm System inNPPs / Cheol Kwon Lee, Seop Hur, Hae Gon Shin, HeuiYoun Park, and In Soo Koo (KAERI) 1561