Guideline on Application Process of Techniques Developed for Repair, Replacement and Mitigation Activities

2018 ◽  
Author(s):  
Koji Koyama ◽  
Hiroyuki Kobayashi ◽  
Kiminobu Hojo
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Development Stage ◽  
Standard Formulation ◽  
Application Process ◽  
New Techniques ◽  
Engineering Development ◽  
Actual Application ◽  
Maintenance Activities ◽  
Code Standard

The process from the engineering development to actual application of the new techniques used for the maintenance activities for Japanese nuclear power plants’ (NPPs) component in operation, the JANTI Guideline, “Guideline on Application Process of Techniques Developed for Maintenance Activities” was developed to propose clarification activities to be checked or examined in each stage throughout process. The guideline focuses on techniques used for especially such remedial activities as repair, replacement and mitigation of ageing. In engineering development stage, all information on the new techniques are provided to be checked or examined at each stage of the process followed further, such as code/standard formulation stage. It is important to carry out share recognition for the activities, which should be performed in each process in the prompt application to the actual plant system efficiently, among the persons or organizations concerned.

A Study on Maintenance Rule Application in VVER NPP

2017 ◽  
Author(s):  
Ma Chao ◽  
Deng Wei ◽  
An Jin
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Power Production ◽  
Nuclear Regulatory Commission ◽  
Application Process ◽  
The Us ◽  
Rule Application ◽  
Maintenance Activities ◽  
Regulatory Commission ◽  
Wide Usage

Maintenance effectiveness is important for the safety and power production of Nuclear Power Plants (NPP). U.S. Nuclear Regulatory Commission (NRC) Maintenance Rule (10CFR50.65, MR) became effective in 1996, and it is mandatory for all the US plants to use Maintenance Rule in their daily maintenance activities. With the development and wide usage of Probabilistic Risk Assessment (PRA) technique in China, China regulator and utilities are trying to adopt MR in maintenance activities. Brief study on application of MR in some VVER-typed China nuclear plant is carried out and some main results are shown. All the application process and results will be useful for later official application of MR in China.

scholarly journals Spesifikasi, Kode dan Standar Baja Nasional dan Potensinya untuk Mendukung Program PLTN Tipe LWR di Indonesia

2019 ◽  
Vol 20 (2) ◽  
pp. 111 ◽  
Author(s):  
Dharu Dewi ◽  
Sriyana Sriyana
Keyword(s):  
Literature Review ◽  
Structural Steel ◽  
Research Methodology ◽  
Steel Industry ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
International Standards ◽  
Code Standard ◽  
Standard Steel

SPESIFIKASI, KODE DAN STANDAR BAJA NASIONAL DAN POTENSINYA UNTUK MENDUKUNG PROGRAM PLTN TIPE LWR DI INDONESIA. Spesifikasi, kode dan standar baja nasional sangat penting diidentifkasi agar dapat dicocokkan atau dibandingkan  dengan spesifikasi, kode dan standar internasional untuk komponen PLTN sehingga industri baja diharapkan dapat berpartisipasi dalam pembangunan Pembangkit Listrik Tenaga Nuklir (PLTN). Spesifikasi kode dan standar  baja mengacu pada ASTM, ASME, AISC dan lain - lain. Tujuan studi ini adalah mengidentifikasi  spesifikasi, kode dan standar baja yang dimiliki industri nasional dan kemudian dicocokkan dengan spesifikasi, kode dan standar baja sesuai standar internasional untuk PLTN. Metodologi penelitian adalah kajian literatur, pengiriman kuesioner, survei dan kunjungan teknis ke industri baja. Disimpulkan bahwa baja struktur pada dasarnya memenuhi persyaratan untuk konstruksi PLTN.Kata kunci: spesifikasi, kode, standar, baja, industriSPECIFICATION, CODE AND STANDARD OF NATIONAL STEEL AND THE POTENCY TO SUPPORT THE NUCLEAR POWER PROGRAMME OF LWR TYPE IN INDONESIA. Specification, codes and standards are important to identify in order to be matched or compared to international specifications, codes and standards for NPP components so that the steel industry is expected to participate in the construction of Nuclear Power Plants (NPPs). The specifications, code and standards of steel refer to ASTM, ASME, AISC and others. The purpose of this study is to identify specifications, codes and steel standards owned by national industries and then compared it to international standards for nuclear power plants. The research methodology is literature review, questionnaire submission, surveys and technical visits to the steel industry. It was concluded that the structural steel basically meets the requirements for NPP construction.Keywords: specification, code, standard, steel, industry

PRIORITIZING FEEDERS FOR MAINTENANCE ACTIVITIES USING AHP IN NUCLEAR POWER PLANTS

2007 ◽  
Vol 14 (03) ◽  
pp. 275-282 ◽  
Author(s):  
A. SRIVIDYA ◽  
H. N. SURESH
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Decision Making Process ◽  
Decision Criteria ◽  
Analytic Hierarchy ◽  
Qualitative And Quantitative ◽  
Prioritization Process ◽  
Maintenance Activities ◽  
Hierarchy Process ◽  
Pair Wise Comparison

The Analytic Hierarchy Process (AHP) is a powerful and flexible decision making process to help people set priorities and make the best decision when both qualitative and quantitative aspects are to be considered. In this paper, a procedure of prioritizing the outlet feeders under multiple criteria using Saaty's priority theory is presented. In priority theory, weights are assigned to the decision criteria via pair wise comparison of criteria. Seven outlet feeders (alternatives) and three decision criteria have been considered and the prioritization process is illustrated with an example case.

scholarly journals Proof of Concept for a Human Reliability Analysis Method for Heuristic Usability Evaluation of Software

2005 ◽  
Vol 49 (5) ◽  
pp. 676-680 ◽  
Author(s):  
Ronald L. Boring ◽  
David I. Gertman ◽  
Jeffrey C. Joe ◽  
Julie L. Marble
Keyword(s):  
Reliability Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Cost Effective ◽  
Usability Evaluation ◽  
Analysis Method ◽  
Human Reliability ◽  
Human Reliability Analysis ◽  
New Techniques ◽  
Innovative Methods

An ongoing issue within human-computer interaction (HCI) is the need for simplified or “discount” methods. The current economic slowdown has necessitated innovative methods that are results driven and cost effective. The myriad methods of design and usability are currently being cost-justified, and new techniques are actively being explored that meet current budgets and needs. Recent efforts in human reliability analysis (HRA) are highlighted by the ten-year development of the Standardized Plant Analysis Risk HRA (SPAR-H) method. The SPAR-H method has been used primarily for determining humancentered risk at nuclear power plants. The SPAR-H method, however, shares task analysis underpinnings with HCI. Despite this methodological overlap, there is currently no HRA approach deployed in heuristic usability evaluation. This paper presents an extension of the existing SPAR-H method to be used as part of heuristic usability evaluation in HCI.

scholarly journals Nuclear Power Plant Maintenance Optimization with Heuristic Algorithm

2014 ◽  
Vol 2014 ◽  
pp. 1-13 ◽  
Author(s):  
Andrija Volkanovski ◽  
Leon Cizelj
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Objective Function ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Risk Measure ◽  
Plant Safety ◽  
Maintenance Activities ◽  
Probabilistic Safety

The test and maintenance activities are conducted in the nuclear power plants in order to prevent or limit failures resulting from the ageing or deterioration. The components and systems are partially or fully unavailable during the maintenance activities. This is especially important for the safety systems and corresponding equipment because they are important contributors to the overall nuclear power plant safety. A novel method for optimization of the maintenance activities in the nuclear power plant considering the plant safety is developed and presented. The objective function of the optimization is the mean value of the selected risk measure. The risk measure is assessed from the minimal cut sets identified in the Probabilistic Safety Assessment. The optimal solution of the objective function is estimated with genetic algorithm. The proposed method is applied on probabilistic safety analysis model of the selected safety system of the reference nuclear power plant. Obtained results show that optimization of maintenance decreases the risk and thus improves the plant safety. The implications of the consideration of different constraints on the obtained results are investigated and presented. The future prospects for the optimization of the maintenance activities in the nuclear power plants with the presented method are discussed.

Decommissioning: An Approach to Predict the Amount of Radioactive Waste Arisings

2007 ◽  
Author(s):  
K. Kugel ◽  
P. Brennecke ◽  
W. Koch
Keyword(s):  
Radioactive Waste ◽  
Federal Government ◽  
Heat Generation ◽  
Electricity Generation ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Energy Use ◽  
New Techniques ◽  
Phase Out

In the next decades many facilities are going to be decommissioned in Germany. On the basis of the agreement between the utilities and the Federal Government on the phase out of nuclear energy use for commercial electricity generation predictions can be made on the schedule of the shut down of nuclear installations in Germany and a prognosis might be given for the complete amount of decommissioning waste that will arise. 17 nuclear power plants and other nuclear installations are to be shut down and decommissioned within the next 2 decades. An approach for the prediction of the amount of radioactive waste and an overview on the underlying assumptions is given. The prognosis for the expected radioactive waste in Germany depends on several assumptions. Utilities in Germany expect approx. 5000 m3 of radioactive waste with negligible heat-generation from decommissioning per reactor. New inquiries seem to indicate that less radioactive waste may arise due to new techniques in decontamination and conditioning. Nevertheless, there will be limits due to costs and physical properties.

scholarly journals Analyzing alpha emitting isotopes of Pu, Am and Cm from NPP water samples: an intercomparison of Nordic radiochemical laboratories

2021 ◽  
Author(s):  
Susanna Salminen-Paatero ◽  
Xiaolin Hou ◽  
Grzegorz Olszewski ◽  
Lina Ekerljung ◽  
Annika Tovedal ◽  
...  
Keyword(s):  
Water Samples ◽  
Analytical Method ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Analytical Performance ◽  
New Techniques ◽  
Intercomparison Exercises ◽  
Radioanalytical Methods

AbstractRadioanalytical methods for the determination of isotopes of Pu, Am and Cm in water samples from nuclear power plants were compared and further developed in a Nordic project (Optimethod) through two intercomparison exercises among Nordic laboratories. With this intercomparison, the analytical performance of some laboratories was improved by modification of the analytical method and adopting new techniques. The obtained results from the two intercomparisons for alpha emitting transuranium isotopes are presented, and the lessons learnt from these intercomparison exercises are discussed.

scholarly journals Multi-state Risk-Based Maintenance Analysis of Redundant Safety Systems Using the Markov Model and Fault Tree Method

2021 ◽  
Vol 9 ◽  
Author(s):  
F. Mohammadhasani ◽  
A. Pirouzmand
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Fault Tree ◽  
System Level ◽  
Aging Effects ◽  
Maintenance Activities ◽  
Maintenance Policies ◽  
Safety Systems ◽  
Tree Method

The risk-based maintenance strategy has received special attention in the safe operation of nuclear power plants. Simultaneous quantification of the positive and negative effects of maintenance activities and components degradation effect makes it possible to accurately evaluate the risk criterion for safety systems of nuclear power plants. However, it is difficult to integrate the effects of maintenance and components degradation into the standard reliability approaches. A straightforward approach for considering components degradation and different maintenance policies is to make use of Markov maintenance models. In this article, the effectiveness of maintenance activities (including changes in the surveillance test intervals and alteration in the different maintenance policies) on the components unavailability with considering aging effects is quantified using Markov maintenance models and then by coupling these models and the fault tree method, the risk measure is upgraded from the component level to the system level. The proposed models are applied to evaluate the unavailability of two safety systems of VVER-1000/V446 nuclear power plants as case studies. The results show that the Markov method due to its multi-state nature is effective in the conservative evaluation of risk measures so that the unavailability computed by the coupling process is higher than the original unavailability (calculated by system fault tree using PSA data of nuclear power plants) for all maintenance policies. In addition, this study illustrates that the developed Markov maintenance models could be applied to the large-scale whole plant level and provides a proper transition from the classical PSA methods to new techniques. This approach integrates the effects of maintenance strategies and components degradation. Also, it provides a practical and a more accurate tool to determine the technical specification of a real nuclear power plant from the risk point of view.

Veilig Werken Volgens Geschreven Procedures

1987 ◽  
Vol 28 ◽  
pp. 133-143 ◽  
Author(s):  
M.G.M. Elling
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Human Performance ◽  
Railway Track ◽  
Rule Based ◽  
Track Maintenance ◽  
Knowledge Based ◽  
Actual Application ◽  
Human Functioning ◽  
Actual Use

Research in the field of written procedures (in an industrial context) has moved along two lines: regulating the performance of operators, especially in nuclear power plants, and creating effective technical manuals. The quality of such texts has remained a problem, perhaps because research has generally concentrated on superficial text features and task analysis, thereby neglecting the actual use (or non-use) of documents in working situations and the wider interests the organisation has in writing down procedures. A more promising strategy, along the lines of a distinction made by Rasmussen, is to concentrate on the relation between written procedures and the appropriate levels of human performance: skill based, rule based or knowledge based. In a case study (procedures for railway-track maintenance with uninterrupted train service), users described their problems with the written procedures as "lack of clarity", alluding to deficiencies in content and presentation. Further analysis revealed the following more specific problems: - unclear presentation: not designed as a job performance aid, awkward phraseology, unfit for easy reference; - too many detailed procedures; - unclear working situation: users often felt compelled to choose between following the procedures to the letter and accomplishing the jobs on schedule; - resistance to the predominating "control directing" function of the procedures, to the detriment of their "action directing" function; - lack of motivation, as a result of not having been involved in the drawing up of the procedures. The procedures had been conceived by the organisation on a rule based level. Due to the modus operandi of the human cognitive system, however, actual application of the procedures often takes place on a skill based level. Accordingly, it was decided to rewrite the procedures to a skill based level, i.e. to write very explicit instructions, specifying the actions to be taken by workers at every level in the organisation. From the present study it can be concluded that the usability of safety-related written instructions is not determined predominantly by their contents and their presentation, but also by at least the following factors: organisational context (working conditions, administrative control, safety policies); task involved; risk perception; feasible level of human functioning; frequency of error types; ergonomic possibilities; motivation of the users; knowledge and experience of the users.

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