a n n u a l m e e t i n g o n t h e s a f e t y a n d l i
play

A n n u a l M e e t i n g o n t h e S a f e t y a n d L i c e n - PowerPoint PPT Presentation

Dec 26, 2023 •108 likes •320 views

A n n u a l M e e t i n g o n t h e S a f e t y a n d L i c e n s i n g o f R e s e a r c h R e a c t o r s ENRRA Cairo, Egypt 28 August 01 September 2016 State te O Offi ffice f for Nucle lear S Saf afety Czec ech R Repu

  1. A n n u a l M e e t i n g o n t h e S a f e t y a n d L i c e n s i n g o f R e s e a r c h R e a c t o r s ENRRA Cairo, Egypt 28 August – 01 September 2016 State te O Offi ffice f for Nucle lear S Saf afety Czec ech R Repu epublic Periodic Safety Review Process for Research Reactors

  2. Objectives • PSR on Research Reactors – the reason? • Regulatory requirements for Periodic Safety Review (PSR) – current status • PSR process on Nuclear Power Plants • Graded approach for PSR application on Research Reactors • New regulatory requirements for PSR and their application on Research Reactors • Conclusion Periodic Safety Review Process for Research Reactors 2

  3. Overview of Research Reactors Training Reactor VR-1 Vrabec Nominal power: 1 kW thermal Nuclear fuel: type IRT-4M, enrichment 19,75 % U 235 Utilization: training tasks Research Reactor LR-0 Nominal power: 1 kW thermal VVER-1000 / VVER-440 Nuclear fuel: Utilization: core physics and shielding of VVER experiments Research Reactor LVR-15 Nominal power: 10 MW thermal Nuclear fuel: type IRT-4M, enrichment 19,75 % U 235 Utilization: material research and corrosion tests of I. circuit of NPPs radiopharmaceuticals and radioisotopes production silicone doping Periodic Safety Review Process for Research Reactors 3

  4. PSR on Research Reactors – WHY? • PSR is a standard requirement for security assessment on nuclear installations, which is conventionally provided on both - the power reactors and on the Research Reactors nuclear installations. Outputs from the PSR serve as a basis for an application for a permit to operate license. • Based on the experience of participating countries presented at the IAEA workshop on PSR, which was held in Vienna, they are carrying the PSR on their research reactors and they have highlighted positive results from the view of improving nuclear safety and radiation protection, as well as demonstrable detecting deviations from current good practice in terms of safety of Research Reactors. Workshop therefore recommended that all Research Reactors operating organizations who have not established the PSR for their research reactors should do so. • PSR will be legislatively required as a condition for the granting of permits to operating license in all nuclear installations, including Research Reactors in Czech Republic. Periodic Safety Review Process for Research Reactors 4

  5. Regulatory requirements for PSR – current situation ATOMIC ACT General Requirements and obligations: • Activities relating to nuclear energy or radiation utilization shall be justified and nuclear safety and radiation protection shall be ensured as a matter of priority. • A licensee shall assess in a systematic and comprehensive manner the fulfilment of requirements, from the aspect of the current level of science and technology, and ensure that the assessment results are put into practice. CONDITIONS OF OPERATING LICENSE (applied for NPPs only) Operating license for Dukovany NPP, 1. Unit (LTO), issued by SÚJB 30.3.2016 • The Applicant shall submit the methodology and criteria of PSR to SÚJB, T:30.6.2020 • The Applicant shall perform PSR and submit the final report to SÚJB, T: 30.4.2025 • The Applicant shall submit the results of meeting the schedule of completing corrective actions to SÚJB, T: annually REGULATORY GUIDE: • Regulatory guide BN-JB-1.2, Rev. 1 – Safety Instructions for Periodic Safety Review INTERNATIONAL STANDARDS: • IAEA Safety Standards Series No. SSG-25 - Periodic Safety Review for Nuclear Power Plants • WENRA Safety Reference Levels for Existing Reactors - Issue P (Periodic safety review), 2014 Periodic Safety Review Process for Research Reactors 5

  6. WENRA Safety Reference Levels for Existing Reactors Issue P - Periodic Safety Review, 2014 Periodic Safety Review Process for Research Reactors 6

  7. PSR structure and methodology on Nuclear Power Plants According to the IAEA Safety Standards Series No. SSG-25 - Periodic Safety Review for Nuclear Power Plants and defined PSR safety factors which are divided into five subject areas to facilitate the review and IAEA-TECDOC (under development) for Periodic Safety Reviews for Research Reactors Basis for PSR • National Legal Requirements • WENRA Reference Levels • IAEA Safety guides and international best practice • Regulatory guides, Normative documentation, ... Methodology • Collecting of documents and information relating to the criteria • Evaluate and compare the information on the actual status with the requirements of criteria (Best Practice) • Identify strengths • Identify deviations and propose corrective measures Source for evaluation consist of design and licensing documentation (especially Safety Report Analysis), control and work documentation, reports of the findings of internal and external audits and controls (OSART, WANO Peer Review, SÚJB inspections and other), records of the procedures and other documents, which are demanded for assessment purpose. Periodic Safety Review Process for Research Reactors 7

  8. Phases of PSR 1. Phase – preparation of PSR • Specifications of the scope of assessments, defining legislative and normative base • Outputs: Strategy of Approach to PSR, the Methodology and Criteria, a draft schedule of each stage of PSR. 2. Phase – execution (perform) of the PSR Assessment • Systematic evaluation (detailed comparison of the actual state, with the requirements of the applicable criteria) • Outputs: Reports on evaluation of individual thematic areas of PSR, a list of strengths and a list of deviations ranked and sorted by severity. 3. Phase – corrective actions from findings in PSR • Formulation of safety deviations findings and setting the method of implementing corrective actions • Outputs: Schedule of corrective actions on safety findings and final report of the PSR preparation. Periodic Safety Review Process for Research Reactors 8

  9. PSR Schedule Plan on NPP Agreement between Submission of PSR results to operating organization and SÚJB regulatory body on general latest in term stated in License scope and requirements for PSR and its expected outcome 6 months - 6 months 12 months 6 months PSR starting phase PSR performing phase PSR reports PSR finalization finalization phase phase PSR Reviews Preparation of the Answering SÚJB Action Plan of comments, PSR Final Corrective Actions Report finalization PSR preparation phase Methodology and Criteria, Strategy of Approval of an Action PSR Plan of Corrective Actions Periodic Safety Review Process for Research Reactors 9

  10. Evaluation Sheet PSR EDU 30 No and version of AS OXFYKZN(WIJ)(S,SK)v0 PSR Evaluation Sheet and Area X Name of the area Factor Y Name of the factor process of verification Criteria Z The overall text of criteria Documentation used for the evaluation of criteria (Unique identification of used documentation, including revision / date of issue) • Reviewer have to cover all criteria for Background Commentary particular factor before evaluating it. Descriptive part of the evaluation of criteria: (describing how was the criteria evaluated, how is the criteria • Reviewer should be experienced in particular fulfilled, whether are there deviations or suspected non-fulfillment of criteria, which one? Whether is current status better than Best Practice, in which area and in what way?). area for its evaluating. Evaluation of Block differences: (differences among blocks will be listed with a brief commentary only in case they would lead to the deviations or strengths) Other insights, comments and suggestions: (Mention important facts related to the evaluation, including feedback and recommendations useful in future assessments of criteria. In case of unavailability of necessary documents for criteria assessment, state: CRITERIUM CAN NOT BE ASSESSED) Were identified strengths? (Individual strengths will be listed and numbered. The facts leading to their formulation must be listed with description. In case they were not identified put NOT). Were identified deviations in criteria fulfillment? (All deviations will be listed and numbered. . The facts leading to their formulation must be listed with description. In case they were not identified put NOT, CRITERIUM IS FULFILLED) Proposal for recommendations for corrective actions to resolve deviations: (Corrective actions to resolve the deviations will be listed there). Name and surname of the reviewer: Date of evaluation completing: Name and surname of the Date of validation: guarantee: Name and surname of the opponent: Date of opponency: Periodic Safety Review Process for Research Reactors 10

Recommend

More recommend