The Nuclear Safety Authority in France: A Dogma of “Independence” and Institutional Fragility

2017 ◽  
Vol 22 (1) ◽  
pp. 119
Author(s):  
Saliha Hadna
Keyword(s):  
Nuclear Safety ◽  
Nuclear Safety Authority

Quality Assurance in the ITER Construction

2010 ◽  
Author(s):  
Sungkook Park ◽  
David Sands ◽  
Carlos Alejaldre
Keyword(s):  
Quality Assurance ◽  
Nuclear Safety ◽  
Quality Assurance Program ◽  
Roles And Responsibilities ◽  
Fusion Device ◽  
Safety Regulations ◽  
Nuclear Safety Authority ◽  
And Performance ◽  
Experimental Fusion ◽  
Iter Project

The ITER project is basically an engineering and construction project in order to build the ITER machine which is a scientific experimental fusion device. The seven members of the project have all created legal entities called Domestic Agencies to provide in-kind contributions to the ITER Organization (IO) for the supply of components which are manufactured by their suppliers. According to ITER agreement and due to nuclear safety involved in the fusion process, the project requires a license from the French Nuclear Safety Authority. One of nuclear safety regulations is the French Quality Order. The IO has established a Quality Assurance Program for the construction of the ITER machine to meet the requirements of the Order and to ensure that ITER activities are performed to achieve the safety and performance objectives of the ITER machine. The requirements in the program shall be followed by all performers involved in the project not only the IO, but DAs and their suppliers and subcontractors. This paper represents the quality requirements from the Order, and roles and responsibilities between each performer involved in the project. The paper also shows the main characteristics of the ITER Quality Assurance Program ensuring that all activities performed for the project conform to established and documented requirements.

RCCE-E 2005 Creator of Confidence Between Nuclear Safety Authority, Owner, and Suppliers

2010 ◽  
Author(s):  
J. M. Haure
Keyword(s):  
Environmental Conditions ◽  
Nuclear Safety ◽  
Severe Accident ◽  
Frequency Variation ◽  
Electrical Networks ◽  
French Society ◽  
Low Frequencies ◽  
Custom Made ◽  
Nuclear Safety Authority ◽  
Design And Construction

The paper deals with the design rules included in the RCCE code applicable to electrical, and instrumentation and control systems and components contributing to safety-class functions. It is a major document in the relationships between the Owner and its suppliers and the safety authorities. The code is periodically submitted to the Nuclear Safety Authority Assessment. Initially used for the French PWR program and published by the French Society for Design and Construction rules for Nuclear Island Components (AFCEN), the code evolves to comply with third generation PWR nuclear islands and aims to comply with national regulations if needed in addition to French regulations. It gathers within one set of rules, the design and construction practices of, the electrical and I&C systems and components, and installation engineering documents. Brief presentation of some items is proposed: - Relationships between Safety Analyses Report plant system and installation engineering; - Off-site and on-site sources requirements; - Periodic tests and permanent monitoring requirements to guarantee the safety function availability; - I&C architecture and Human Machine Interfaces; - Digital I&C systems requirements; - Establishing qualification to ambience conditions, that includes normal and mild conditions and, harsh and severe accident conditions. Custom-made approach based on the families of ambience defined as a combination of equipment mission time, and normal and abnormal conditions (pressure, temperature, radiation) enabling to cope better with environmental conditions; - High and Low frequencies disturbances protections (Lightning, GSM, DECT, WiFi); - Project data used by any supplier or designer such as site data, temperature of rooms, maximum design temperature of equipment, the voltages and frequency variation range and tolerances of the alternative current and direct current electrical networks, the decoupling data of environmental conditions; - Electrical equipment separation requirements and isolation and decoupling solutions designs; - Electrical enclosures design requirements. A conclusion on the evolution of AFCEN organization in charge of comprehensive set of technical codes on the design, construction and surveillance of civil work structures, fire protection, mechanical structures, the core and fuel design, the electrical and I&C equipment and systems of PWR nuclear island.

Statement of the French Safety Authority Concerning the Behaviour of 900 MWe PWR RPV Between 30 and 40 Years in Operation

2011 ◽  
Author(s):  
L. Monin
Keyword(s):  
Radiation Protection ◽  
Pressure Vessel ◽  
Technical Support ◽  
Nuclear Safety ◽  
Reactor Pressure Vessel ◽  
Regulatory Requirements ◽  
Safety Margins ◽  
Calculation Step ◽  
Nuclear Safety Authority ◽  
Reactor Pressure

The French 900 MWe reactor pressure vessel (RPV) integrity demonstration was reviewed in 2010 by the French Nuclear Safety Authority (ASN), together with its technical support organisation, the French Institute for Radiation Protection and Nuclear Safety (IRSN). The purpose was to decide whether these 3-loop PWR RPV’s are able to remain in service for ten years after their third decennial outage (VD3). ASN and IRSN examined the demonstration developed by Electricite´ De France (EDF) in order to ensure the compliance of in-service RPV behaviour with regulatory requirements and to check the validity of the calculations and hypotheses that were used for that purpose. The analysis aimed notably at ensuring that the results of every calculation step were conservative and that regulatory safety margins were applied. The calculations made by EDF showed that regulatory criteria were met until the provisional deadline of their fourth decennial outage (VD4). Thus ASN considered that the serviceability of all 900 MWe PWR RPV’s is guaranteed throughout the decade following the VD3 of the reactors, considering that EDF respects ASN demands with a view to comfort safety margins.

Improving Research Reactor Accident Response Capability at the Hungarian Nuclear Safety Authority

2015 ◽  
Vol 62 (1) ◽  
pp. 187-194 ◽  
Author(s):  
Janos Vegh ◽  
Ferenc Gajdos ◽  
Csaba Horvath ◽  
Attila Matisz ◽  
Daniel Nyisztor
Keyword(s):  
Research Reactor ◽  
Nuclear Safety ◽  
Reactor Accident ◽  
Nuclear Safety Authority ◽  
Accident Response ◽  
Response Capability

scholarly journals Dynamics of agency governance: Evidence from the Nuclear safety sector

2021 ◽  
pp. 095207672110195
Author(s):  
Kjerstin Kjøndal ◽  
Jarle Trondal
Keyword(s):  
Public Policy ◽  
Organizational Factors ◽  
Public Organizations ◽  
Nuclear Safety ◽  
Core State ◽  
Nuclear Safety Authority ◽  
Organizational Approach

Public organizations are compound bodies characterized by competing endogenous dynamics of governance. This study makes two main contributions. First, it contributes to an organizational approach to studies of public policy and administration by conceptualizing compound agency governance. Second, by determining how variation in agency governance reflects endogenous organizational factors. Based on a study of the Norwegian Radiation and Nuclear Safety Authority (DSA), two observations are highlighted: Firstly, DSA staff are torn between two competing behavioural logics: A governmental and a transnational logic. Moreover, portfolios of core state powers are more closely monitored by parent ministries than portfolios that relate to non-core state powers. Secondly, the study suggests that organizational factors are vital determents in balancing behavioral logics in agency governance.

Sign in / Sign up

Export Citation Format

Share Document