CNSC welcomes feedback on any regulatory document at any time REGDOC- supersedes RD, Design of New Nuclear Power. CNSC has issued its Fukushima report – posted on the CNSC website on that the design intent complies with CNSC design requirements (RD, RD-. Re: The Approvals Process for New Reactors in Canada – RD & RD ( CNSC) request for feedback on the comments received on the.
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In addition, the means for adding or modifying the chemical constituents of fluid streams are specified.
Leak-before-break A situation where leakage from a flaw is detected during normal operation, allowing the reactor to be shut down and depressurized before the flaw grows to the critical size for rupture. The safety assessment is part of the design process, with iteration between the design and analyses, and increases in scope and level of detail as the design process progresses.
Hazards analysis is the process of collecting and evaluating information about the NPP to identify the associated hazards and determine those that are significant and must be addressed.
RD Design of New Nuclear Power Plants – Canadian Nuclear Safety Commission
Internal event An event internal to the nuclear power plant that results from human error or failure in a system, structure, or component. Threats identified as DBTs have credible attributes and characteristics of a potential insider or external adversaries, who might attempt unauthorized removal of nuclear material or sabotage against which a physical protection system is designed and evaluated.
The ECCS recovery flow path is such that impediment to the recovery of coolant following a loss of coolant accident by debris or other material is avoided. The aim of the fourth level of defence is to ensure that radioactive releases caused by severe accidents are kept as low as practicable. The design provides a means i. This document is part of the physical design series of the CNSC’s regulatory framework. The design provides sufficient physical separation between redundant divisions of safety support systems and process systems.
The design also allows for the display of information needed to monitor the effects of the automatic actions of all control, safety, and safety support system. The positive and negative design pressures within each part of the containment boundary include the highest and lowest pressures that could be generated in the respective parts as a result of any DBA.
Where space sharing is necessary, services for safety and for other important process systems are arranged in a manner that incorporates the following considerations:. The design of internal structures considers any hydrogen control strategy, and assists in the effectiveness of that strategy.
The technical safety objective is interdependent with administrative and procedural measures that are taken to ensure defence against hazards due to ionizing radiation. This source term is referred to as the reference source term, and is based on a set of representative core damage accidents established by the design authority. The sum of rd-3337 of all event sequences that can lead to significant core degradation rs-337 less than 10 -5 per reactor year. Where the design has to accommodate an SSC failure, preference is given to equipment that exhibits known and predictable modes of failure, and that facilitates repair or replacement.
Document History of REGDOC-2.5.2, Design of Reactor Facilities: Nuclear Power Plants
The design authority classifies SSCs in a consistent and clearly defined classification scheme. Similar to NS-R-1, RD considers all licensing phases, because information from the design process feeds into the processes for reviewing an application for a Licence to Construct an NPP, and other licence applications.
The design provides facilities for monitoring chemical conditions of fluids, and of metallic and non-metallic materials. Diversity Xnsc presence of two or more redundant systems or components to perform an identified function, where the different systems or components have different attributes so as to reduce the possibility of common-cause failure.
If a design other than a water-cooled reactor is to be considered for licensing in Canada, the design is subject to the safety objectives, high level safety concepts and safety management expectations associated with this regulatory document.
RD-337: Design of New Nuclear Power Plants
To the greatest extent cnsv, application of this principle enables plant systems to pass into a safe state if a system or component fails, with no necessity for any action to be taken. The design authority establishes initial severe accident management guidelines, taking into account the plant design features and the understanding of accident progression and associated phenomena. The design establishes a set of requirements and limitations for safe normal operation, including:.
It may include certain safety and safety support systems, and any interacting process system.
The design includes an emergency heat removal system EHRS which provides for removal of residual heat in order to meet fuel design limits and reactor coolant boundary condition limits. This includes instrumentation for measuring variables that can affect the fission process, the integrity of the reactor core, the reactor cooling systems, and containment, as well as instrumentation for obtaining xnsc information rs-337 the plant that is necessary for its reliable and safe operation.
Missile generation The internal hazard associated with the sudden high-speed propulsion of debris.
The design includes a clearly defined continuous leak-tight containment envelope, the boundaries of which are defined for all conditions that could exist in the operation or maintenance of the reactor, or following an accident. Consistent with the concept of defence-in-depth, the design provides multiple barriers for protection against malevolent acts, including physical protection systems, engineered safety provisions, and measures for post-event management, as appropriate.
These include hardwired display panels as well as computerized displays that are as user friendly as possible.
External events include, but are not limited to, earthquakes, floods, and hurricanes. Where two fluid systems operating at different pressures are interconnected, failure of the interconnection is considered.
The seismic design of the concrete containment structure has an elastic response when subjected to seismic ground motions. This includes provision of appropriate permanent layout and shielding of SSCs cnac radioactive materials, and the use of temporary shielding for maintenance and inspection work.
The first step of each part of the safety analysis is to identify PIEs using a systematic methodology such as failure modes and effects analysis. Systems designed for this purpose are considered part of the containment system, and are capable of:.