APOSS was involved in a number of projects in different countries, either as a member of consortium or subcontracted to one of the partners and associates, or implementing them on its own. The end users or beneficiaries are from the four continents (Europe, Asia, Americas and Africa). The projects included safety analyses implementation, safety analysis reviews, assessments and evaluation, consulting in the field of nuclear safety, as well as training, workshops and consulting in the capacity building in these areas. The services provided were described and documented in numerous technical documents, in the form of studies, evaluations or review reports. Following below is a selection of specific topics covered by those documents which were either completely written by the APOSS staff or were by them considerably contributed.

2020

  • Industry Contribution to Final report on Decommissioning Plan, EUROfusion – IFMIF / DONES Draft Report
  • Interim Executive Summary Report on NPP Seismic Probabilistic Safety Analysis
  • Interim Technical Report on NPP Seismic Probabilistic Safety Analysis: Main Report
  • Interim Executive Summary Report on NPP Low Power and Shutdown PSA
  • Interim Technical Report on NPP Low Power and Shutdown Probabilistic Safety Analysis: Human Reliability Analysis
  • Interim Technical Report on NPP Low Power and Shutdown Probabilistic Safety Analysis: Systems Analysis and Fault Tree Modeling
  • Interim Technical Report on NPP Low Power and Shutdown Probabilistic Safety Analysis: Accident Sequences and Event Tree Modeling
  • Interim Technical Report on NPP Low Power and Shutdown Probabilistic Safety Analysis: Main Report

2019

  • Interim Executive Summary Report on NPP Level 2 PSA
  • Interim Technical Report on NPP Level 2 PSA: Risk Model Integration and Quantification
  • Interim Technical Report on NPP Level 2 PSA: Human Reliability Analysis for Level 1 – Level 2 PSA Interface
  • Interim Technical Report on Angra 1 Level 2 PSA: Level 1 – Level 2 PSA Interface
  • Supporting Tool for Severe Accident Management, D5.3 – Definition of Hazard-Induced Damage States and Development of State-Specific APETs for Demonstration Purposes”, NARSIS, Horizon 2020, Euratom research and training programme 2014-2018 under Grant Agreement No. 755439

2018

  • Industry Contribution to Final report on Decommissioning Plan, Update, EUROfusion – IFMIF / DONES Draft Report
  • Supporting Tool for Severe Accident Management, D 5.1 Characterization of the referential NPP for severe accident management analyses”, NARSIS, Horizon 2020, Euratom research and training programme 2014-2018 under Grant Agreement No. 755439
  • NPP SAMG User Guide
  • Insights from NNP Plant Specific PSA (for SAMG development)
  • NPP Validation and Verification Procedure
  • NPP SAMG Verification Report
  • NPP SAMG Validation Report
  • NPP SAMG Instrumentation

2017

  • Criteria for Incident Investigation Response
  • NPP Level 2 PSA Containment Event Tree Notebook – CET Development Principles
  • Evaluation of NPP ECR Habitability per RG 1.78 Requirements
  • NPP SAMG Writter’s Guide

2016

  • Industry Contribution to Preliminary Report on the Decommissioning Plan, EUROfusion – IFMIF / DONES Draft Report
  • Spent Fuel Pool PSA for Internal Fire, Internal Flooding and Seismic Events
  • NPP SAMG Setpoint Study Procedure
  • “The assessment of environmental conditions after LOCA with equivalent diameter 100 and break of PRZ surge line”
  • Review Report on “Justification of selection of initial states in performing the safety analyses”, NPP Project
  • Review Report of “Classification of transients and accidents”, NPP Project
  • Review report of “Development of the list of initiating events for deterministic safety analysis”, NPP Project
  • Review Report of “Description of code “SOKRAT/B3”, NPP Project
  • Review Report of “Validation of code SOCRAT/B3”, NPP Project
  • Review Report “Description of SOKRAT/В3 code (extended version of SOKRAT/В1 code): Aerosol kinetic program unit, NPP Project
  • Review Report of “Validation of SOKRAT/B3 code (extended version of SOKRAT/В1 code): Aerosol kinetic unit”, NPP Project
  • Review Report of NPP PSAR Chapter 15.6
  • Review Report of NPP PSAR Chapter 15.7

2015

  • Spent Fuel Pool PSA for Internal Initiating Events
  • Proposals for Revision E of EUR Chapter 2.17 (European Utility Requirements for LWR Nuclear Power Plants)
  • Assessing Regulatory Requirements and Guidelines for the Single Failure Criterion
  • Izračun verjetnosti za nastanek nesreče v železniškem prometu na relaciji Trst – Divača (slovenski del odseka)” (in Slovenian, Assessment of Accident Probability in Railway Traffic at Line Trst – Divaca (Slovenian Part))
  • Consultation on the Development of the Safety Analysis Methodology complying with European Requirements Technical Report
  • Description of software package KORSAR GP Review Report, NPP Project
  • Description of software package SOCRAT B1 Review Report, NPP Project
  • Verification of software package SOKRAT/B1, NPP Project

2014

  • Review of the Partial NPP Fire PSA
  • NPP Periodic Safety Review, Summary Report and Global Assessment of Plant Status
  • NPP Periodic Safety Review, Implementation Action Plan (IAP)
  • NPP Periodic Safety Review, Final Broad and Detailed Ranking of Safety Issues with Identification and Prioritization of Corrective Measures
  • Counting Lines of Defense (CLOD) Ranking Approach
  • Incorporating Ageing Effects into PSA Applications
  • Risk Based Event Analysis
  • Description of software package TRAP KS Review Report, NPP Project
  • Verification of software package TRAP-KS Review Report, NPP Project
  • Description of safety analysis calculation procedures Review Report
  • Procedure of preparation and performance of calculation in safety analyses, NPP Project
  • Verification of software package KORSAR-GP Review Report

2013

  • Safety Assessment of Human Factors Engineering for NPP, Preparation of FSAR Chapter 18
  • Safety Assessment of Human Factors Engineering for NPP, Supporting Document for Preparation of FSAR Chapter 18
  • Safety Assessment of Human Factors Engineering for NPP, Fulfillment of NUREG-0711 Elements Evaluation Report
  • NPP Periodic Safety Review – Procedures
  • NPP Periodic Safety Review – Emergency Planning (Safety Factor 13)
  • NPP Periodic Safety Review – Equipment Qualification (Safety Factor 3)
  • NPP Periodic Safety Review – Aging (Safety Factor 4)
  • NPP Plant Specific SEOPs Validation
  • NPP Training on SEOPs

2012

  • Time Schedule for Obtaining of Permits for a New NPP
  • NPP Spent Fuel Pool Risk Significance Evaluation
  • NPP Analyses of Potential Safety Improvements

2011

  • Application of Risk-Informed In-service Inspection at NPP, Risk Impact Evaluation
  • Application of Risk-Informed In-service Inspection at NPP, Consequence Evaluation
  • Accident Management Guidelines and Procedures: Improvement of the Emergency Documentation, Review of the Best International Practice and Situation in a Country (EUROPEAID)
  • Evaluation of Seismic and Flooding Margins for NPP
  • NPP Symptom Oriented Emergency Operating Procedures: T-H Analyses Summary Report

2010

  • Evaluation of PSA Impact of Expansion of Airport
  • NPP PSA Update with SG BD System Modification
  • The Second NPP Periodic Safety Review Program
  • Assessment of Accident Probability in Railway Traffic Line (Prepared for Ministry of Transport)
  • IPSART Mission to NPP Level 1 Internal Initiating Events Probabilistic Safety Assessment (IAEA report)
  • NPP Symptom Oriented Emergency Operating Procedures: PTS Summary Report
  • NPP Symptom Oriented Emergency Operating Procedures: Containment Analysis and Evaluation

2009

  • Risk Assessment of Scenarios Involving Potential for Pressure Locking of Pressurizer PORV Block Valves
  • Development of the NPP EQ Master Equipment List (EQMEL), Summary Report (with 14 system related EQ reports)
  • Overview of Existing Systems for the Response to Emergency Situation Involving the Nuclear Material Trafficking in EU Countries
  • Aircraft Crash Frequency Estimation for the Site of Nuclear Power Plant
  • Enhancement of Nuclear Regulatory Authority capabilities with regard to assessment of NPP Periodic Safety Review – Procedure for regulatory assessment of Periodic Safety Review
  • Identification, Evaluation and Corrective Action Proposal for the Valves from MOV Program Susceptible to the Pressure Locking (PL) Phenomena
  • Enhancement of Nuclear Regulatory Authority capabilities with regard to assessment of NPP Periodic Safety Review – Specifications for a Tool for Monitoring of Aging Management Program (AMP) at the Licensing Organization
  • Enhancement of Nuclear Regulatory Authority capabilities with regard to assessment of NPP Periodic Safety Review – Specifications for a Database Tool for the Management of PSR Insights
  • Assistance at Nuclear Power Plant – Environmental Conditions Evaluation due to the Postulated High Energy Lines Breaks in Turbine Hall at Elevation 14.7m
  • Enhancement of Nuclear Regulatory Authority capabilities with regard to assessment of NPP Periodic Safety Review – Procedure for regulatory assessment of Ageing Management Program
  • NPP Symptom Oriented Emergency Operating Procedures and Associated Background Writers Guide
  • NPP Symptom Oriented Emergency Operating Procedures Setpoint Study Background (Review of Applicable Instrumentation for Usage in NPP Symptom Oriented Emergency Operating Procedures)
  • Consulting Assignment for Nuclear Safety Administration – Recommended Elements for Upgrade of Regulatory PSR Requirements in the Light of Ageing Management and Methodology for Identification of Important Equipment for Life Extension Review

2008

  • NPP PSA Internal Flooding Update
  • PBMR – Fire Probabilistic Risk Assessment Tasks Outline, FIPRA Tasks Specification in Accordance to State of the Art Practices
  • Establishment of realistic source term for NPPs in neighboring countries;  Phase 1-Pilot Project – The assessment of the Level 2 PSA and estimate of source term for two NPPs, Status of Level 2 PSA studies for 6 selected NPP sites and the availability of source term data
  • Establishment of realistic source term for NPPs in neighboring countries;  Phase 1-Pilot Project – The assessment of the Level 2 PSA and estimate of source term for two NPPs, Source term data for two selected NPPs
  • Analiza osnovnih pogonskih događaja kao podloga upravljanju rizicima u Hrvatskoj elektroprivredi (Analysis of Basic Operational Events as a Basis for the Risk Management in the Croatian Electrical Utility)
  • Seismic PSA for NPP, Evaluation of Selected Plant Improvements
  • Seismic PSA for Armenian, Quantification of Seismic CDF
  • Review of NPP’s Environmental Qualification (EQ) Program
  • Consulting Assignment for Nuclear Safety Administration – Review of starting points for PSR program and identification of useful elements for upgrade in the light of ageing management program
  • Development of the method for performance of risk analysis of maintenance performance
  • Consulting Assignment for Nuclear Safety Administration -Review and comparison of approaches on lifetime extension and identification of useful elements for PSR upgrade
  • Screening of potential time-limited aging analyses in the NPP’s Current Licensing Basis
  • Review of NPP’s Plant Specific TLAAs Related to Civil Structures
  • Definition of the Transients and Accidents Scenarios (for RELAP Calculations) Not Covered by NPP’s Design Bases Documentation

2007

  • Seismic PSA for NPP, Fault Tree Modeling
  • Seismic PSA for NPP, Accident Sequence Modeling
  • High Wind Probabilistic Risk Assessment for NPP – Analysis of Core Damage Frequency
  • High Wind Probabilistic Risk Assessment for NPP – Level 2 Analysis
  • Evaluation of the Design Bases Documentation and Their Applicability for Development of Symptom Oriented Emergency Operating Procedures Documentation
  • General Overview of the List of Necessary Transients and Accidents Evaluations Required for the Development of the NPP Symptom Oriented Emergency Operating Procedures Background Documentation
  • Task3: The Assessment of environmental conditions after LOCA 100mm diameter break

2006

  • Guidelines for using PSA in the evaluation of inspection findings – Significance Determination Process” with “Appendix A – Risk-informed Inspection Notebook for NPP 1 and Appendix B – Risk-Informed Inspection Notebook for NPP 2
  • Risk-Informed Categorization of Structures, Systems and Components – Results for NPP 1
  • Risk-Informed Categorization of Structures, Systems and Components – Results for NPP 2
  • Update of Plant-Specific Worksheets for Significance Determination Process
  • Risk-Informed Categorization of Structures, Systems and Components – Methodological approach
  • Review of the Methodology for Risk-Informed In-Service Inspection for Piping
  • NPP Ultimate Heat Sink (UHS) Design Bases Review – Revision 1
  • IAEA Technical report – Review of the Preliminary Safety Analysis Report of NPP
  • IAEA Technical Report – “Review of the Final Safety Analysis Report of NPP, Chapter 14

2005

  • Assessment of Ageing Management Program and Adequacy of Existing Programs at NPP
  • Software, Methodology and Data Requirement for the Seismic PSA for NPP
  • Basis for Regulatory Guidelines for Assessment and Approval of Risk-Informed Requests for Changes in Technical Specifications
  • Review of NPP’s Submittal for Risk-Oriented Change in TS AOTs (PSA-related Part)
  • Review of NPP PSA with Regard to Its Scope and General Quality (NPP 1)
  • Review of NPP PSA with regard to its scope and general quality (NPP 2)
  • Significance Determination of Inspection Findings at NPP
  • Plant-Specific Worksheets for Significance Determination Process
  • Methodology for development of aging management procedure for Nuclear Safety Administartion
  • Management of aging effects in NPP
  • NPP Ultimate Heat Sink (UHS) Design Bases Review

 

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APOSS – System Reliability and Safety Analyses Inc. for services and engineering