Insights About Emergency Diesel Generator Failures from the USNRC's Common Cause Failure Database (English)
- New search for: Marshall, F. M.
- New search for: Wierman, T. E.
- New search for: Rasmuson, D. M.
- New search for: Mosleh, A.
- New search for: Marshall, F. M.
- New search for: Wierman, T. E.
- New search for: Rasmuson, D. M.
- New search for: Mosleh, A.
- New search for: Modarres, M.
In:
Probabilistic safety assessment
;
297-304
;
1999
-
ISBN:
- Conference paper / Print
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Title:Insights About Emergency Diesel Generator Failures from the USNRC's Common Cause Failure Database
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Contributors:Marshall, F. M. ( author ) / Wierman, T. E. ( author ) / Rasmuson, D. M. ( author ) / Mosleh, A. ( author ) / Modarres, M.
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Conference:International meeting; 6th, Probabilistic safety assessment ; 1999 ; Washington, DC
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Published in:Probabilistic safety assessment ; 297-304
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Publisher:
- New search for: American Nuclear Society
-
Publication date:1999-01-01
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Size:8 pages
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ISBN:
-
Type of media:Conference paper
-
Type of material:Print
-
Language:English
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Keywords:
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Source:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Table of contents conference proceedings
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 3
-
Level 1 PSA for Japanese Light Water Reactors with Domestic Component Failure Rate DataSugawara, M. / Takahashi, H. / Hirano, M. et al. | 1999
- 11
-
Progress Toward a Component Failure Rate Data Bank for Magnetic Fusion SafetyCadwallader, L. C. / Pinna, T. et al. | 1999
- 21
-
Insights from Level 1 PSA for Novovoronezh NPP (Unit 5) and PSA-Based ModificationsLioubarski, A. / Kouzmina, I. / Gordon, B. / Rozin, V. et al. | 1999
- 29
-
Organization and Management of the Plant Safety Evaluation of the VVER-440/230 Units at NovovoronezhRozin, V. / Puglia, W. J. / Afshar, C. M. / Pizzica, P. et al. | 1999
- 38
-
The Role of PRA in the Safety Assessment of VVER Nuclear Power Plants in UkraineKot, C. A. / Dickerman, C. E. / Binder, J. L. et al. | 1999
- 45
-
Application of European Utility Requirements (EUR) for the Development of the PSA for the European Passive PlantBassanelli, A. / Schulz, T. et al. | 1999
- 55
-
A Guided Tour of Minimal Cutsets Handling By Means of Binary Decision DiagramsDutuit, Y. / Rauzy, A. et al. | 1999
- 63
-
The Stand-By Failure Analysis in Bayesian ExperimentWang, H.-J. / Fang, G. / Chien, C.-F. et al. | 1999
- 70
-
Using Fuzzy Arithemetic in Containment Event TreesRivera, S. S. / Baron, J. H. et al. | 1999
- 77
-
Insights from the Seismic PSA of the BWR Model Plant at JAERIOikawa, T. / Kondo, M. / Watanabe, Y. / Shiraishi, I. / Hirose, J. / Muramatsu, K. et al. | 1999
- 85
-
Internal Flooding Analyses Results of Slovak NPPSSopira, V. et al. | 1999
- 97
-
Black Start-Based Recovery of Offsite Power to SONGSMoieni, P. / Henneke, D. / Shepherd, S. / Save, P. / Mansell, M. / Reny, D. / Stekar, J. / Rao, S. et al. | 1999
- 105
-
Linked Fault Tree Methodology as Applied to ComEd PSA'sKalache, M. et al. | 1999
- 108
-
Loss of Offsite Power Recovery Factors and Diesel Generator Mission Times: A Suggested ApproachCanavan, K. et al. | 1999
- 115
-
Application of Piping Reliability Models and Service Data to Evaluate Large Service Water System Pipe Break FrequenciesMelnicoff, M. A. / Bidwell, D. A. / Fleming, K. N. et al. | 1999
- 125
-
Development of Maintenance Software for PRA ModelsLin, T.-J. / Wang, H.-J. / Peng, C.-M. / Li, G.-D. et al. | 1999
- 128
-
On-Line Operation Support Modeling: Common Cause DependencySimic, Z. / Mikulicic, V. et al. | 1999
- 135
-
The Distinction Between Aleatory and Epistemic Uncertainties is Important: An Example from the Inclusion of Aging Effects into PSAApostolakis, G. et al. | 1999
- 143
-
Severe Accident Phenomenological Uncertainty: Risk and Accident Management ImpactsBirchley, J. / Jackel, B. et al. | 1999
- 151
-
Modeling and Measuring the Effects of Imprecision in Severe Accident ManagementYu, D. et al. | 1999
- 161
-
Applying a Fire IPEEE: Hot Shorts and Appendix R VerificationGallucci, R. H. V. / Flaherty, M. D. / Wilson, D. F. / Jorgenson, E. J. et al. | 1999
- 169
-
Description of a Fire Hazard Screening MethodologyJoglar-Billoch, F. / Mowrer, F. W. / Modarres, M. et al. | 1999
- 175
-
Quad Cities Fire Risk AssessmentBurchill, W. E. / Zee, K. et al. | 1999
- 183
-
Risk Insights Gained From Fire IncidentsNowlen, S. P. / Kazarians, M. et al. | 1999
- 191
-
Test Interval Analysis for the Isolation Valves at Olkiluoto Nuclear Power PlantYli-Kauhaluoma, M. / Himanen, R. et al. | 1999
- 195
-
Insights into the Risk Characteristics Derived From the Application of a Computerized On-Line Configuration ManagerPong, L. T. et al. | 1999
- 202
-
Simplified Risk Model Version II (SRM-II) Structure and ApplicationEide, S. / Wierman, T. et al. | 1999
- 213
-
A Quality Assurance Handbook for Probabilistic Safety AssessmentHolmberg, J. et al. | 1999
- 217
-
Assessment of PRA QualityKrueger, G. A. / Burns, E. T. / Hill, R. A. et al. | 1999
- 225
-
Insights from the Development of a Reliability Assurance Programme (RAP) Guidebook for Advanced Light Water ReactorsCho, B. O. / Hunt, R. N. M. et al. | 1999
- 235
-
A Probabilistic Approach of Incorporating Safety and Reliability in System Designs for a Manned Mission to MarsRailsback, J. W. / Simion, G. P. et al. | 1999
- 241
-
Space Shuttle Multiple-Phase Integrated Probabilistic Risk AssessmentWoods, K. S. et al. | 1999
- 249
-
Safety Factor of a Helicopter Exposed to Ground Fire with Failure Probability EstimationNiezgoda, T. / Jazwinski, J. / Zurek, J. / Woropay, M. et al. | 1999
- 254
-
The Integration of Probabilistic Tools into the Aeronautics Risk Management Program at the NASA Glenn Research CenterRusick, J. J. / Pai, S. S. / Lalli, V. R. / Packard, M. H. et al. | 1999
- 262
-
Estimation of Risk Trends in Shuttle Failure DataHeydorn, R. P. / Railsback, J. W. / Adams, T. C. et al. | 1999
- 271
-
Simple Measure of Uncertainty Importance Using Entire Change of Cumulative Distribution FunctionsChun, M.-H. / Han, S.-J. / Tak, N.-I. et al. | 1999
- 279
-
Different Sources of Uncertainty in Level 2 PSA: Their Characterization and PropagationAhn, K.-I. / Kim, D.-H. et al. | 1999
- 287
-
Sensitivity Analysis for Embedded Computer-Based SystemsMeshkat, L. / Dugan, J. B. / Andrews, J. D. et al. | 1999
- 297
-
Insights About Emergency Diesel Generator Failures from the USNRC's Common Cause Failure DatabaseMarshall, F. M. / Wierman, T. E. / Rasmuson, D. M. / Mosleh, A. et al. | 1999
- 305
-
Insights from the Application of INEL's Common Cause Database at Commonwealth Edison's Byron and BraidwoodBidwell, D. A. / In, Y. H. et al. | 1999
- 310
-
Common-Cause Failure Analysis for Reactor Protection System Reliability StudiesWierman, T. / Eide, S. / Gentillon, C. / Rasmuson, D. et al. | 1999
- 318
-
Common Cause Failure Analysis of Hydraulic Scram and Control Rod Systems in the Swedish and Finnish BWR PlantsMankamo, T. et al. | 1999
- 327
-
Common Cause Failure Modeling in CANDU Design Probabilistic Safety AssessmentVesik, W. et al. | 1999
- 343
-
Fire Risk Analysis for Loviisa 1 Turbine HallLehto, M. / Vaurio, J. K. et al. | 1999
- 350
-
Estimation of the Frequency of Fire Scenario by Means of Improved Apportionment of the Frequency of Fires Associated with Engulfed Ignition SourcesArgirov, J. P. et al. | 1999
- 356
-
Cable Hot Shorts and Circuit Analysis in Fire Risk AssessmentLaChance, J. / Nowlen, S. P. / Wyant, F. et al. | 1999
- 363
-
Lessons Learned from an Uncertainty and Sensitivity Analysis of a Transient Simulation for a PSAHofer, E. / Kloos, M. et al. | 1999
- 369
-
Selection of the Appropriate Technique for Sensitivity/Uncertainty Analysis: A Decision Tree ApproachRocco, C. M. / Miller, S. A. J. et al. | 1999
- 376
-
A Treatment of Uncertainties for Component Reliability or Initiator Frequency Estimates Based on Combining Data Sources with the Potential of Non-HomogeneityMorozov, V. et al. | 1999
- 385
-
Probabilistic Risk Assessment as a Forensic Science: The Effect of Daubert and Kumho Tire on PRAs as EvidenceBrannigan, V. M. / Smidts, C. et al. | 1999
- 391
-
The Results of Probability Analysis of the First-Level Safety for the Bilibino NPPAntonov, A. V. / Volnikov, I. S. / Dagaev, A. V. / Dolgov, V. V. / Ilyin, Y. V. / Shvedenko, I. M. et al. | 1999
- 401
-
PSA Applications: Safety Goals and Acceptance GuidelinesCunningham, M. A. / Holahan, G. M. / King, T. L. / Murphy, J. A. / Parry, G. W. et al. | 1999
- 408
-
On the Role of Defense in Depth in Risk Informed RegulationSorensen, J. N. / Apostolakis, G. E. / Kress, T. S. / Powers, D. A. et al. | 1999
- 414
-
Development of Risk-Based Performance IndicatorsBaranowsky, P. W. / Mays, S. E. / Wolf, T. R. et al. | 1999
- 422
-
A Pilot Study on Risk-Informed In-Service InspectionMononen, J. / Julin, A. / Hinttala, J. / Niemela, I. / Rantala, R. / Valkeajarvi, O. / Virolainen, R. et al. | 1999
- 435
-
New LOCA Frequencies in Barseback-1 PSA Update-An Application of a Piping Failure DatabaseLydell, B. / Ingemarson, I. / Nyman, R. et al. | 1999
- 443
-
Innovative Use of EPRI Loss of Offsite Power Data for Dual-Unit Plant Frequency and RecoveryPolanski, X. et al. | 1999
- 450
-
Engineering and Safety Assessment of Field Experience Related to Pressurized Water Reactor Primary System LeaksShah, V. N. / Sattison, M. B. / Ware, A. G. / Atwood, C. L. / Hartley, R. S. / Hsu, C. et al. | 1999
- 458
-
Bayesian Modeling of Failure Rates and Initiating Event FrequenciesHofer, E. / Peschke, J. et al. | 1999
- 467
-
Regulatory Treatment of Non-Safety Systems for Passive Plants: Application to the AP600Levin, A. E. / Saltos, N. T. / Tzanos, C. P. et al. | 1999
- 474
-
Regulatory Experience with Blending of Deterministic and Probabilistic Information in Risk-Informed ApplicationsLee, S. S. / Cheok, M. C. / Barrett, R. J. et al. | 1999
- 481
-
Dynamic Reliability Analysis with Monte Carlo Simulation and First Order Reliability MethodsWoltereck, M. M. et al. | 1999
- 489
-
Integrated Thermal Hydraulic Analysis and Probabilistic Assessment for Safety Evaluation and Scenario Screening of the Westinghouse AP600 ReactorLi, F. / Guan, Y. / Modarres, M. et al. | 1999
- 499
-
Dependability Estimation of Digital System by Operational Profile-Based Fault InjectionChoi, J. G. / Seong, P. H. et al. | 1999
- 507
-
Qualitative Analysis of Petri NetsPoint, G. et al. | 1999
- 513
-
Development of Markov Model for Emergency Diesel Generators Based on Causal Loop DiagramChoi, S.-Y. / Yang, J.-E. et al. | 1999
- 521
-
Evaluation of Systems Reliability by Means of Binary Decision DiagramDutuit, Y. / Rauzy, A. / Signoret, J.-P. et al. | 1999
- 529
-
A Risk-Informed Regulation Pilot Project-Exemption from the Hydrogen Control Requirements at SONGSMoieni, P. / Hook, T. G. / Christie, B. et al. | 1999
- 537
-
Pilot Programs for Risk-Informed, Performance-Based RegulationChristie, B. et al. | 1999
- 545
-
Using Individual Plant Examination Data to Derive the Individual Risk of Early Fatalities: Preliminary Results, Insights, and Limitations of ApproachMubayi, V. / Pratt, T. / Drouin, M. et al. | 1999
- 551
-
An Approach to Study the Effectiveness of Mitigation Accident Management in a Probabilistic FrameKawabata, O. / Tanaka, N. et al. | 1999
- 559
-
The Characteristics and Construction of CANDU CETSong, Y.-M. / Kim, D. H. / Choi, Y. / Jin, Y. H. / Ahn, K. I. et al. | 1999
- 567
-
Accident Management Insights from the Level 2 PSA for the Kernkraftwerk LeibstadtTorri, A. / Zeller, M. / Pokorny, V. / Luettringhaus, U. et al. | 1999
- 577
-
Rates of Initiating Events at U.S. Nuclear Power Plants, 1987-1995Poloski, J. P. / Atwood, C. L. / Galyean, W. J. / Marksberry, D. G. / Mays, S. E. et al. | 1999
- 585
-
Evaluation of Loss of Offsite Power Events at Nuclear Power Plants: 1980-1996Marshall, F. M. / Atwood, C. L. / Kelly, D. L. / Prawdzik, D. A. / Stetkar, J. W. et al. | 1999
- 593
-
Westinghouse Reactor Protection System Unavailability, 1984-1995Eide, S. / Calley, M. / Gentillon, C. / Wierman, T. / Rasmuson, D. / Marksberry, D. et al. | 1999
- 601
-
General Electric Reactor Protection System Unavailability, 1984-1995Eide, S. / Calley, M. / Gentillon, C. / Wierman, T. / Hamzehee, H. / Rasmuson, D. et al. | 1999
- 608
-
Auxiliary/Emergency Feedwater System Reliability, 1987-1995Galyean, W. J. / Poloski, J. P. / Gentillon, C. D. / Knudsen, J. K. / Rasmuson, D. M. / Marksberry, D. G. et al. | 1999
- 619
-
Safety Analysis System Using Thermo-Hydrodynamic Simulation of Accident Sequences in Event Tree/Go-FlowMatsuoka, T. / Ida, T. / Nakamura, H. et al. | 1999
- 624
-
RBMK-1500 Core Lifetime-Gas Gap Closure Probabilistic AssessmentLiaukonis, M. / Uspuras, E. / Augutis, J. / Kopustinskas, V. et al. | 1999
- 631
-
Incorporating Aging Effects into Probabilistic Risk AssessmentSmith, C. L. / Apostolakis, G. / Kao, T.-M. / Shah, V. et al. | 1999
- 641
-
EISTRAM-Experimental Investigation of the Pie-TechniqueThunem, H. / Gran, B. A. et al. | 1999
- 649
-
A Challenge for Software Reliability Analysis: Descriptive Parameters in Concurrent Real-Time Software SystemsJalashgar, A. et al. | 1999
- 657
-
Fault Tree Qualitatively Improve REliability of Safety-Related SoftwareCepin, M. / Mavko, B. et al. | 1999
- 657
-
Fault Tree Qualitatively Improves Reliability of Safety-Related SoftwareCepin, M. / Mavko, B. et al. | 1999
- 665
-
Function Point Analysis: An Application to a Nuclear Reactor Protection SystemKececi, N. / Li, M. / Smidts, C. et al. | 1999
- 672
-
Software Reliability Test in Nuclear Power Plant Uljin Units 3, 4Oh, T.-K. / Kim, D.-I. / Park, J.-W. et al. | 1999
- 683
-
Evaluation of Surveillance Test Arrangement of BWR Using Time-Dependent ModelHisamochi, K. / Suzuki, H. / Oda, S. et al. | 1999
- 690
-
Advanced On-Line and Shutdown Safety Monitor at San Onofre Nuclear Generating StationHenneke, D. W. / Hook, T. G. et al. | 1999
- 695
-
Risk-Informed IST PRA Results for San Onofre (SONGS), Including Fire, Seismic and Shutdown Quantitative PRAHenneke, D. W. / Chung, G. / Coveney, M. et al. | 1999
- 699
-
Progressively Improving Technical Specifications with Risk Information History-Current-FutureReinhart, M. et al. | 1999
- 705
-
Paper: Chemical Safety Assessment: Use in Food Additives, Superfund, and Other DecisionsWilson, J. D. et al. | 1999
- 717
-
Sophistication of SGTR Event Tree for Accident Sequence Precursor AnalysisWatanabe, N. / Hirano, M. / Takahashi, H. et al. | 1999
- 725
-
Comparison of Some Precursor-Based Core-Melt Frequency EstimatorsCollet, J. / Francois, P. / Jourdain, B. / Lapeyre, B. et al. | 1999
- 731
-
Results of the Precursor Analysis for German Nuclear Power PlantsHoertner, H. / Babst, S. et al. | 1999
- 738
-
French Precursor Studies: Methods and InsightsFauchille, V. / Lanore, J. M. / Pichereau, F. / Tirira, J. et al. | 1999
- 747
-
Enhanced Generalized Performance Assessment of Near-Optimized Pressurized Water Reactor Core Configurations by Multi-Valued Possibilistic ProcessingMironidis, A. / Lidofsky, L. / Tsoukalas, L. et al. | 1999
- 755
-
Effects of SCDAP/RELAP5 Hot Leg Modeling on Prediction of the Risk of Steam Generator Tube RuptureKnudson, D. L. / Dobbe, C. A. et al. | 1999
- 765
-
Improving Risk Insight Utilization and Communication in the Inspection, Assessment, and Enforcement Programs of the Nuclear Regulatory CommissionCoe, D. H. et al. | 1999
- 773
-
The Technical Basis for Off-Site Emergency PlanningPerryman, L. J. / Magugumela, M. T. et al. | 1999
- 781
-
Risk Analysis Based on Acceleration MeasurementsVladicescu, F. P. / Mihaela, R. / Friedman, E. et al. | 1999
- 793
-
PSA Support of Implementation of the Maintenance Rule at ComEdMelnicoff, M. A. et al. | 1999
- 809
-
Probabilistic Risk Assessment and Slaughterhouse Practices: Modelling Contamination Process Control in Beef Destined for HamburgerRoberts, T. / Malcolm, S. A. / Narrod, C. A. et al. | 1999
- 816
-
The Creation of Regional Safety Management System Structure: Bashkortostan Republic ExperienceKhamitov, R. Z. / Krymsky, V. G. / Akhmedjanov, F. M. / Yunusov, A. R. et al. | 1999
- 823
-
Use of an Interactive Matrix Approach for Safety Analysis of the Initial Operations Phase of the National Ignition FacilityBrereton, S. / Ma, C. et al. | 1999
- 831
-
Effective Risk Based Methods for Management of Safety, Health and Environment in Small and Medium Sized EnterprisesBodsberg, L. et al. | 1999
- 839
-
What Does A MERMOS Analysis Consist in?Bieder, C. / Le Bot, P. / Cara, F. et al. | 1999
- 846
-
What are the CICAs? Retrospective Analysis of the Three-Mile Island Accident from the MERMOS ViewpointCara, F. / Le Bot, P. / Bieder, C. et al. | 1999
- 852
-
MERMOS, A Second Generation HRA Method: What It Does and Doesn't DoLe Bot, P. / Cara, F. / Bieder, C. et al. | 1999
- 861
-
Developments in the Decision Tree MethodologySpurgin, A. / Bareith, A. / Kouzmina, I. / Baumont, G. / Smoutnev, V. et al. | 1999
- 869
-
A Comparison of the Application of the CAHR Method to the Evaluation of PWR and BWR Events and Some Implications for the Methodological Development of HRAStrater, O. / Reer, B. et al. | 1999
- 879
-
Probabilistic Risk Assessment in Support of On-Line Maintenance at Virginia PowerAnderson, R. C. / John, T. P. / Shen, S.-H. / Tuley, K. D. / Bucheit, D. M. / Thomas, R. S. et al. | 1999
- 883
-
The First Feasibility Study of Maintenance Rule Application In Korean NPPKim, K. / Kim, T. / Jin, Y. et al. | 1999
- 887
-
Developing a Performance-Based Regulatory System for DOE FacilitiesRempe, J. / Leahy, T. / Knudson, D. / Wierman, T. / Apostolakis, G. / Golay, M. / Chaniotakis, E. / Borgonovo, E. / Felder, F. / Ghosh, T. et al. | 1999
- 894
-
On-Line Maintenance and Maintenance Rule Implementation at Both Turkey Point and St. Lucie Nuclear PlantsHeiba, M. / Zamanali, J. et al. | 1999
- 901
-
Risk Informed Maintenance in Support of Defense in DepthMorton, G. R. / Cramer, D. S. et al. | 1999
- 904
-
Use of PSA in Risk Management at a Research ReactorJohnson, D. H. / Wakefield, D. J. / Cameron, R. et al. | 1999
- 913
-
Facilitating Technical Risk Communication Among Non-SpecialistsBley, D. C. / Kojima, S. / Wreathall, J. et al. | 1999
- 921
-
Making the Most of Your Investment in PSA: The Role of a Documentation and Information ManagementEpstein, S. A. / Johnson, D. H. / Rao, S. B. / Lin, J. C. / Wakefield, D. J. et al. | 1999
- 925
-
PSA Documentation: Does Anybody Read What I Write?Stutzke, M. A. et al. | 1999
- 933
-
Experiences from the Safety Assessment of a Train Leader Telephone SystemDahll, G. / Thunem, H. et al. | 1999
- 941
-
Reliability of a Computer Based Transit Car Door SystemKaufman, L. M. / Giras, T. C. / Ghaly, N. et al. | 1999
- 949
-
FACE-A Framework for Analysing Commission ErrorsPyy, P. T. et al. | 1999
- 957
-
Human Reliability in Severe Accident ManagementPyy, P. T. et al. | 1999
- 964
-
Evaluation of Human Performance Issues for Fire RiskCooper, S. E. / Bley, D. C. / Forester, J. A. / Kolaczkowski, A. M. / Ramey-Smith, A. / Thompson, C. M. / Whitehead, D. W. / Wreathall, J. et al. | 1999
- 970
-
Using a Decision Tree to Estimate Human Error Probabilities in a Level 2 PSA: The HORAAM MethodMenage, F. / Vogel, A. / Chaumont, B. et al. | 1999
- 979
-
OECD Nuclear Energy Agency Activities in Risk Assessment-An International PerspectiveKaufer, B. / Murphy, J. A. et al. | 1999
- 987
-
Regulatory Use of PSA in GermanyBerg, H. P. / Gortz, R. / Schott, H. / Weil, L. et al. | 1999
- 994
-
IAEA Activities on PSACobo, A. G. / Ranguelova, V. et al. | 1999
- 1002
-
Use of PRA in the AP600 Design Certification ReviewSaltos, N. T. / El-Bassioni, A. et al. | 1999
- 1013
-
Using PSA Applications in EDF Nuclear Power PlantsPesme, H. / Francois, P. / Magne, L. et al. | 1999
- 1021
-
Commonwealth Edison Byron/Braidwood PSA UpgradeIn, Y. H. / Rodgers, S. S. et al. | 1999
- 1025
-
"Back of the Envelope" Risk Assessment TechniquesPage, E. M. et al. | 1999
- 1035
-
The Idaho National Engineering and Environmental Risk and Reliability Information BaseSmith, C. L. et al. | 1999
- 1042
-
PSAINFOSYS, A PC Based Structured Knowledge BaseErikson, H. / Kaufer, B. / Werner, W. et al. | 1999
- 1050
-
Relational Databases for Probabilistic Risk Assessment Configuration ControlLiming, J. K. / Hook, T. G. et al. | 1999
- 1061
-
Benefits Expected from Automatic Studies with KB3 in PSAs at EDFGallois, M. / Pilliere, M. et al. | 1999
- 1068
-
Development of an Emergency Response Support System for the Fugen NPSSotsu, M. / Iguchi, Y. / Mizuno, K. / Kumasaka, K. / Shimozaki, H. / Kozaki, T. / Raines, J. C. / Deitke, B. et al. | 1999
- 1076
-
The Application of GUI Based Computer Package to TIRMPeng, C.-M. / Huang, S.-H. et al. | 1999
- 1080
-
The Development of Tai-Power Integrated Risk Monitor (TIRM)Huang, Y. / Hsu, H.-C. / Yao, C.-C. et al. | 1999
- 1087
-
Software for Living PSA on Levels 1 and 2Niemela, I. / Virolainen, R. et al. | 1999
- 1097
-
Probabilistic Safety Analysis for Storage Facility of VVER-1000 Spent FuelIslamov, R. T. / Papushkin, V. N. / Ivanchikov, M. D. et al. | 1999
- 1100
-
Frequency of Misloading Spent Nuclear Fuel into a Waste PackageLevinson, S. H. / Massari, J. R. et al. | 1999
- 1108
-
Probabilistic Safety Assessment of IFMIF PlantBurgazzi, L. / Bianchi, F. et al. | 1999
- 1119
-
Proposal of Performance Influencing Factors for the Assessment of Human Error Under Accident Management SituationsKim, J. / Jung, W. et al. | 1999
- 1125
-
Dynamic Human Interaction Models for Risk MonitoringJulius, J. A. et al. | 1999
- 1133
-
Human Model Simulation to Deduce Human Cognitive Reliability Curves for PSA/HRA PracticeWu, W. / Nakagawa, T. / Yoshikiawa, H. et al. | 1999
- 1143
-
Rapid Risk-Based Evaluation of Competing Conceptual DesignsBott, T. F. / Butner, J. M. et al. | 1999
- 1151
-
Study on Risk Ranking Method to Optimize Plant Design and ManagementNarumiya, Y. / Yonebayashi, K. / Ushijima, K. / Kuramoto, T. / Toyoshima, K. et al. | 1999
- 1155
-
Optimization of Surveillance Test Interval in Nuclear Power Plants Based on Analytic Unavailability Model and Genetic AlgorithmYang, J.-E. / Sung, T.-Y. / Jin, Y. et al. | 1999
- 1163
-
Genetic Algorithm Application in Maintenance Scheduling Optimization: Cost and Risk ModelsHadavi, M. H. / Modarres, M. et al. | 1999
- 1179
-
Representing Dynamic System Behaviors Through A Hierarchic ModelHu, Y.-S. / Modarres, M. et al. | 1999
- 1188
-
RAMAS Risk Calc: A Microcomputer Environment for Probabilistic ArithmeticFerson, S. et al. | 1999
- 1195
-
New Faster and Complete Approach to Quantify PRABanov, R. / Simic, Z. / Mikulicic, V. et al. | 1999
- 1203
-
On the Inclusion of Organizational Factors in Incident InvestigationWeil, R. / Apostolakis, G. et al. | 1999
- 1211
-
Assessing Safety Perception in Risky Industries: A Support to ManagementSchram, J. / Fourest, B. et al. | 1999
- 1217
-
The Use of Stakeholder Archetypes in Modeling the Evolution of Perceived RisksGratton, L. J. / Kastenberg, W. E. et al. | 1999
- 1227
-
Cofrentes NPP Risk-Informed Inservice Testing Project ResultsSuarez, J. / de Gregorio, S. / Parkinson, W. J. et al. | 1999
- 1233
-
Use of Living PSA in Regulatory Decision-MakingJulin, A. / Niemela, I. / Virolainen, R. et al. | 1999
- 1239
-
Viewpoints of the Hungarian Nuclear Safety Authority on Application of PSA in Regulatory Decision MakingMacsuga, G. / Hollo, E. / Siklossy, P. et al. | 1999
- 1245
-
Incorporation of PRA into the Regulatory Decision and Policy Making in SlovakiaKubanyi, J. / Duca, A. et al. | 1999
- 1251
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Probabilistic Safety Assessment for Integrated Design Process for KNGR DevelopmentNa, J. H. / Oh, H. C. / Lee, J. S. / Lee, B. S. et al. | 1999
- 1261
-
Outage Schedule Cost-Benefit-Risk Analysis: A PRA Technology ApplicationLiming, J. K. / Grantom, C. R. et al. | 1999
- 1269
-
The Relationship of Deterministic and Probabilistic Analyses in Establishing the Basis for Technical SpecificationsDykes, A. A. / Johnson, D. H. et al. | 1999
- 1275
-
Creating Guidelines for a Contemporary Risk Management ProgramSteinmetz, J. E. / Burchill, W. E. / Fleming, K. N. et al. | 1999
- 1280
-
Managing Simultaneous PRA UpgradesBurchill, W. E. / True, D. et al. | 1999
- 1284
-
Quality Assurance for Probabilistic Safety AssessmentsFerson, S. et al. | 1999
- 1291
-
Insights from Developing Shutdown Risk Monitor ModelsJulius, J. A. / Jones, D. M. et al. | 1999
- 1300
-
Evaluation of Refueling Outage Core Damage Frequency for a PWR PlantWu, C.-H. / Ko, C.-M. et al. | 1999
- 1306
-
Evaluation of Refueling Outage Core Damage Frequency for a BWR-4 PlantLin, J.-D. / Chang, Y.-J. et al. | 1999
- 1311
-
Safety Monitor Implementation for Dual Units, at Surry Power StationTuley, K. D. / Morgan, T. A. / Leary, J. D. et al. | 1999
- 1321
-
Managing the Living PRA During TransitionBych, K. H. et al. | 1999
- 1326
-
Risk Impact of Electric Grid Deregulation: A Scoping StudySaltos, N. T. / O'Neal, D. M. / El-Bassioni, A. et al. | 1999
- 1337
-
Retrospective Event Analysis Using CODA and Perspectives on Human Error PredictionReer, B. et al. | 1999
- 1346
-
Human Reliability Analysis in Novovoronezh NPP Unit 5 PSAKouzmina, I. / Lioubarski, A. / Smoutnev, V. / Spurgin, A. J. et al. | 1999
- 1354
-
Human Reliability Assessment in Loviisa NPP Refueling OutageKattainen, M. / Vaurio, J. K. et al. | 1999
- 1362
-
New Emergency Procedures of Westinghouse Type from Point of View of Human Factors and Human ReliabilityHoly, J. et al. | 1999
- 1375
-
Automated Shutdown PSA Model Development for the Peach Bottom Atomic Power StationWilson, J. T. / MacLeod, D. E. / Shanley, L. B. / Vanover, D. E. et al. | 1999
- 1383
-
Modeling Techniques and Insights from the Shutdown PSA for the Kernkraftwerk MuhlebergTorri, A. / Haschke, D. et al. | 1999
- 1393
-
Internal Fire Analysis for J. Bohunice V2 NPP Within the Full Power and Shutdown PSAKovacs, Z. / Spenlinger, R. / Rydzi, S. et al. | 1999
- 1397
-
Operational Data Collection Elaboration and Reliability Parameters Calculation for V-1 and V-2 NPPS J. Bohunice PSA PurposesCillik, I. / Dana, S. et al. | 1999
- 1402
-
Differences in Approaches Used to Develop PSA Study for Different CANDU PlantsComanescu, L. et al. | 1999
- 1409
-
Preliminary Master Logic Diagram for Personnel SafetyCadwallader, L. C. et al. | 1999
- 1417
-
A Hazard Analysis Technique for Human-Computer Interface DesignFan, C.-F. / Chen, W.-H. / Yih, S. et al. | 1999
- 1425
-
A Technical Approach for Controlling Human Error in the Disassembly of Nuclear WeaponsGilmore, W. E. / Houghton, F. K. et al. | 1999