10556oam 2200553zu 450 991100655820332120230725052318.01-5231-3000-81-282-99143-49786612991431(CKB)3390000000015337(SSID)ssj0000671272(PQKBManifestationID)12276193(PQKBTitleCode)TC0000671272(PQKBWorkID)10614286(PQKB)10090945(MiAaPQ)EBC5266439(Au-PeEL)EBL5266439(CaONFJC)MIL299143(OCoLC)1027143651(Exl-AI)5266439(EXLCZ)99339000000001533720160829d2010 uy engurcnu||||||||txtccrGood practices in heavy water reactor Operation1st ed.[Place of publication not identified]International Atomic Energy Agency20101 online resource (201 pages)Bibliographic Level Mode of Issuance: Monograph92-0-105710-5 Cover -- Foreword -- Contents -- Summary -- Session I. Regulatory Aspects -- Regulatory Assessment Of Nuclear Power Plant Safety Performance In Canada -- 1. Introduction -- 2. Report Content -- 3. Rating Process and Rating System -- 4. Report Card -- 5. Informing Canadians and Cnsc Activities -- 6. Continuous Improvement -- Evolution Of Regulatory Requirements For Hwrs In Romania -- 1. Introduction -- 2. Legislative Framework and Evolution of the Regulatory Body -- 3. Evolution of Hwr Regulatory Requirements in Romania -- 4. Hwr Licensing Practices in Romania -- 5. Conclusions -- Development Of Risk-Informed Regulatory Positions On Candu Safety Issues, Part I: Methodology Development For Risk Estimation And Evaluation -- 1. Introduction -- 2. Risk-Informed Decision Making Process -- 3. Methodology for Risk Estimation and Risk Evaluation -- 3.1. Underlying Principles -- 3.2. Risk Tolerability Scale and Risk Significance Levels -- 3.3. Risk Matrices -- 3.4. Risk Matrices for Risk Estimation and Evaluation in Selected Risk Areas -- 4. Summary -- Acknowledgements -- References -- Development Of Risk-Informed Regulatory Positions On Candu Safetyissues, Part Ii: Application Of Risk-Informed Decision Making Forcategorization Of Safety Issues -- 1. Introduction -- 2. Identification of Safety Issues, and the Process for Development of the Path Forward for Resolution of Issues -- 2.1. Issue Identification -- 2.2. An Approach for Initial Categorization of Safety Issues -- 2.3. Process for Determining the Risk Significance of Safety Issues -- 3. Application of the Rdim Process to Safety Issues for Pressurized Heavy Water Reactors -- 3.1. Adequacy of Eccs Sump Screen -- 3.2. Moderator Temperature Predictions -- 4. Conclusions -- Acknowledgments -- References -- Session II. Reduction In Occupational Dose Exposure.Pickering B Nuclear Dose Reduction Through Innovative Shielding And Mock-Up Training -- 1. Reactor Face Dose Rate Challenge -- 2. The Employment of Radiation Protection Measures -- 2.1. Alara Oversight -- 2.2. Innovative Shielding -- 2.3. Timeline - Development and Implementation -- 2.4. Leadership Role of Radiation Protection and Ims Management -- 2.5. Mock-Up Training - Team Building -- 3. Success and Results -- 4. Empowered Future Performance -- Best Practices In Management Of Heavy Water And Tritium -- 1. Introduction -- 2. GE's Experience -- 3. Impact of Tritium for An Operational Phwr -- 4. Lower Vault Tritium Concentrations -- 5. Achieving Low Pht Heavy Water Tritium Concentrations -- 6. Conclusion -- References -- Reduction In Tritium Emissions And Worker Internal Uptakes Through Source Term Reduction, Dryer Performance And Online Tritium Monitoring -- 1. Identification of Problem -- 2. Action Plan -- 3. Success and Results -- Systematic Collective Dose Reduction -- 1. Introduction -- 2. Safety Review of Existing Nuclear Installations -- 3. Collective Dose Reduction Programme -- 4. Area Identification -- 5. Development of Corrective Actions -- 5.1. Administrative Measures -- 5.2. Work Practices -- 5.3. Design Modifications/Improvements -- 5.4. Improvements to Reduce Internal Doses -- 5.5. Upgrades in Radiological Monitoring/Protection -- 5.6. Reinforcement of Other Areas -- 6. Conclusion -- Downsizing Of The Pht Purification Filter Cartridge In Wolsong Unit 1 -- 1. Introduction -- 2. History of Changing the Pht Purification System Filter Cartridges -- 3. Evaluation of the Changing Filter -- 3.1. A Transition of the Crud1 Concentration in the Pht System -- 3.2. Analysis of Crud Constituents in the Pht System -- 3.3. Evaluation of Steam Generator Worker Dose Rates -- 4. Conclusions -- Portable Dryer Used At Candu Stations -- 1. Introduction.2. Standard Desiccant Dehumidification Design -- 3. Powerpurge™ Desiccant Dehumidification Design -- 4. Portable Vapour Recovery Dryers (Vrds) -- 5. Minimize Ingress of H2O in the Reactor Building -- 6. Application of the Portable Dryers At Candu Stations -- 7. Conclusions -- Dose Reduction Initiatives At Darlington Nuclear -- 1. Introduction -- 2. Dose Reduction Initiatives -- 2.1. Installation of Submicron Filtration -- 2.2. Remote Monitoring -- 2.3. Shielding Applications -- 2.4. Decontamination -- 2.5. Characterization of Dose and Dose Rates -- 2.6. Internal Dose Reduction -- 3. Human Performance Improvement -- 3.1. Impact of Worker Practice -- 3.2. Coaching, Monitoring & Follow-Up -- 4. Future Challenges -- 5. Alara Achievements and Recognition -- Session III. Performance Improvements -- Use Of Human Performance Field Simulator At Pickering Ngs, Practising Event Prevention - Driving Culture Change -- 1. Background -- 2. Objective -- 3. Facility & Process -- 4. Programme -- 5. Summary -- Plgs Level 2 Psa -- 1. Introduction -- 2. Safety Goals -- 3. Overall Psa Results -- 4. Mitigating System Fault Tree Development -- 5. Linkage to Plant Processes -- 6. Use of Site-Specific Data -- 7. Fault Tree Multiple Top Approach -- 8. Model Integration -- 9. Plant Response Simulation -- 10. Treatment of Uncertainty (Error Factor) -- 11. Fire Psa - Cable Routing -- 12. Conclusions -- Improvement Of Power Measurement And Plant Efficiency At Atucha 1 Npp -- 1. Brief Description of Atucha I Npp -- 2. Atucha I Instrumentation and Control Technology -- 3. Using Process Characteristics to Improve Accuracy of Process Measurements and Maintenance Performance -- 3.1. Process Measurements -- 3.2. Example 1 - Pt100 Temperature Measurements -- 3.2. Example 2 - Feedwater Flow Measurements.3.3. Example 3 - Main Coolant Pump Flows As a Method of Checking the Overall Reliability and Surveillance of Instrumentation Used to Calculate Reactor Power. -- 3.4. Example 4 - Turbine-Generator Output As a Method of Checking the Reliability of Reactor Output Measurement -- 4. Instrumentation Maintenance Improvements -- Evolution Of The Wolsong Npp F/M D2O Pressure Control System -- 1. Introduction. -- 2. System Description -- 3. Design and Limitations -- 3.1. D2O Supply Pressure Control -- 3.2. F/M Magazine and C-Ram Pressure Control System -- 4. Design Considerations -- 5. New Design/Development -- 5.1. D2O Supply Pressure Control System -- 5.2. F/M Magazine Pressure Control System -- 5.3. F/M C-Ram Pressure Control System -- 6. Summary -- Platon And Spv Programme - Means Of Improving Reliability Of Cernavoda Npps -- 1. Cernavoda Npp Plant Information System -- 2. Single Point of Vulnerability Project Cernavoda Npp -- 2.1. Spv Initiative Goals -- 2.2. Spv Initiative Summary of Main Steps -- 2.3. Spv Identification -- 2.4. Establish Necessary Pm Tasks for Spv -- 2.5. Determine the Gap and Required Actions -- 2.6. Perform Feedback Analysis and Establish Future Actions -- 3. Other Proposals to Improve the Spv Initiative -- 4. Conclusions -- Review Of Candu Plant Performance -- 1. Overall Fleet Performance -- 2. Causal Factor Analysis - Flr -- 3. Cog Initiatives on Key Focus Areas -- 3.1. Materials and Equipment Performance -- 3.2. Human Performance -- 4. Conclusions -- References -- Review Of The Performance And Best Practices Of The Wolsong Nuclear Power Stations -- 1. Introduction -- 2. Forced Outage Reduction Programmes -- 2.1. Human Factors Studies and Developments -- 2.2. Minimizing Equipment Failure Trips -- 3. Good Maintenance Practices and Maintenance Management -- 3.1. Operating Ranges.3.2. Efficient Management of Maintenance Activities/Reduced Maintenance Backlogs -- 4. Lessons Learned and Opex -- 4.1. Management of Operating Experience -- 4.2. Feedforward of Opex -- 5. Research and Development -- 6. Summary and Conclusions -- References -- Session IV. Reduction In Operating And Maintenance Costs -- Cleanup And Recovery Of High Toc (Total Organic Carbon) D2O Atpickering Ngs -- 1. Summary -- 2. Background -- 3. Drum Control Process -- 4. Key Message -- Fuel Handling Benchmarking -- 1. Introduction -- 2. Project Description -- 3. Project Results -- 4. General Observations -- 5. Conclusions and Recommendations -- 6. Path Forward -- 7. Lessons Learned -- Appendix. Candu Fh Best Practices -- Development Of Consolidated Spent Fuel Dry Storage System -- 1. Introduction -- 2. Configuration of Macstor/Kn-400 Module -- 3. Design Requirement of Macstor/Kn-400 Module -- 4. Design Description of Macstor/Kn-400 -- 5. Conclusions -- Rod-Based Guaranteed Shutdown States (Rbgss) Implementation At Pickering B -- 1. Technical Considerations -- 1.1. Safety Analysis -- 1.2. Common Mode Failure Analysis -- 2. Regulatory Perspective -- 3. Implementation -- 3.1. Rbgss Application -- 3.2. Maintain Rbgss -- 3.3. Exit From Rbgss -- 4. Conclusions -- Abbreviations -- List Of Participants.This publication reports on the outcome of an IAEA workshop on heavy water reactor operation. It summarizes the material presented at the workshop and discusses a broad range of operational practices, including regulatory aspects, the reduction of occupational dose, performance improvements, and reduction of operating and maintenance costs.Heavy water reactorsGenerated by AINuclear power plantsSafety measuresGenerated by AIHeavy water reactorsNuclear power plantsSafety measuresPQKBBOOK9911006558203321Good practices in heavy water reactor Operation4391691UNINA