CNSC RD-337 PDF
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.
|Published (Last):||9 December 2017|
|PDF File Size:||20.57 Mb|
|ePub File Size:||20.99 Mb|
|Price:||Free* [*Free Regsitration Required]|
Such attributes include different principles of operation, different physical variables, different conditions of operation, or production by different manufacturers.
RD-337: Design of New Nuclear Power Plants
Stationary equipment and laboratory facilities are to be provided to determine the concentration of selected radionuclides in fluid process systems as appropriate, and in gas and liquid samples taken from plant systems or the environment.
Fuel assembly design includes all components in the assembly, such as the fuel matrix, cladding, spacers, support plates, movable rods inside the assembly, etc. The design provides facilities for monitoring chemical conditions of fluids, and of metallic and non-metallic materials. The design of the SCR ensures that appropriate lighting levels and thermal environment are maintained, and noise levels align with applicable standards and codes.
The design provides for an emergency support centre that is separate from the plant control rooms, for use by the emergency support staff in the event of an emergency. Accidents exclude anticipated operational occurrences, which have negligible consequences from the perspective of protection or safety. Risk significant system Any plant system whose failure to meet design and performance specifications could result in unreasonable risk to the health and safety of persons, to national security, or to the environment.
Appropriate quality assurance also facilitates identification and control of design interfaces. Direct trip parameter A value based on direct measurement of a specific challenge to the derived acceptance criteria and, if applicable, a direct measure of the event. Such assessments are most useful in assessing the relative level of safety. The reactor control mechanisms limit the positive reactivity insertion rate to a level required to control reactivity changes and power manoeuvring.
The single failure criterion requires that each safety group perform all safety functions required for a PIE in the presence of any single component failure, and:. 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.
If operator intervention is required to keep the reactor in a shutdown state, the feasibility, timeliness, and effectiveness of such intervention is demonstrated. Cnsf revised requirements and new guidance also take into account findings from a cns study, which compared RD against the design requirements of the United States, the United Kingdom, France, Finland and the Western European Regulators Association to identify differences in objective, scope and level of detail.
The re-337 of the turbine generators are to be oriented in such a rd-37 as to minimize the potential for any missiles gd-337 result from a turbine break-up striking the containment, or striking other SSCs important to safety.
Heat sink A system or component that provides a path for heat-transfer from a source such as heat generated in the fuel, to a large heat absorbing medium. The design provides a means for allowing reliable detection of fuel defects in the reactor, and subsequent removal of failed fuel if action levels are exceeded.
The design authority identifies the modern standards and codes that will be used for the plant design, and evaluates those standards and codes for applicability, adequacy, and sufficiency to the design of SSCs important to safety.
These activities are performed to standards commensurate with the importance of the respective safety functions of the SSCs, with no significant reduction in system availability or undue exposure of the site personnel to radiation. All plant systems are designed such that, to the greatest extent practicable, tests of the equipment can be performed to cbsc that rd-37 requirements have been achieved prior to the first criticality.
In addition, the choice of materials inside containment takes into account the impact on post-accident containment conditions, including fission product behaviour, acidity, equipment fouling, radiolysis, fires, and other factors that may affect containment performance and integrity, and fission product release. Mission time The duration of time within which a system or component is required to operate or be available to operate and fulfill its function following an event.
The human factors engineering program also facilitates the interface between the operating personnel and the plant by promoting attention to plant layout and procedures, maintenance, inspection, training, and the application of ergonomic principles to the design of working areas and working environments.
The design facilitates safe operation of the plant within a defined range of parameters, with an assumed availability of a minimum set of specified support features for safety systems. The containment structure and the equipment and components affecting the leak tightness of the containment system are designed to allow leak rate testing:.
The design provides for ample flow routes between separate compartments inside the containment.
The design is expected to provide for ready and reliable detection of any significant breach cnsd the containment envelope. Systems directly connected to the reactor coolant system that may be open during normal operation are subject to the same isolation expectations as the normally closed system, with the exception that manual isolating valves inside the containment structure will not be used.
The shutdown margin for GSS is such that the core will remain subcritical for any credible changes in the core configuration and reactivity addition. These levels are introduced in general terms below, and are discussed in greater detail in subsection 6. The design minimizes the likelihood of operator action defeating the effectiveness of safety and control systems in normal operation and AOOs, without negating correct operator actions following a DBA. The design specifications also define all loads and load combinations, with due consideration given to concurrence probability and loading time history.
In cases where SSCs important to safety cannot be designed to support the desirable testing, inspection, or monitoring schedules, the following approach is taken:.
The design supports maintenance of full functionality following a DBE of all parts of the containment system credited in the safety analysis. The design provides over-speed protection systems for the turbine generators to minimize the probability of turbine disk failure leading to generation of missiles.
During normal operation, including maintenance and decommissioning, doses are regulated by the limits prescribed in the Radiation Protection Regulations. Fail-safe design Design whose most probable failure modes do not result in a reduction of safety.
The design considers the effect on core reactivity of the mixing of ECCS water with reactor coolant water, including possible mixing due to in-leakage. The means of removing residual heat meets reliability requirements on the assumptions of a single failure and the loss of off-site power, by incorporating suitable redundancy, diversity, and independence. Interconnections and isolation capabilities have a degree of reliability that is commensurate with system design requirements.
This includes the use of complementary design features to prevent accident progression and to mitigate the consequences of selected severe accidents. Related considerations include facility access, as well as lifting and packaging capabilities.
RD Design of New Nuclear Power Plants – Canadian Nuclear Safety Commission
Cnssc design provides the type of information that enables an individual in an equipment operator role to identify the parameters associated with individual plant systems and equipment, and to confirm that the necessary safety actions can be initiated safely. The containment design incorporates systems to assist in controlling internal pressure and the release of radioactive material to the environment following an accident.
Where space sharing is necessary, services for safety and for other important process systems are arranged in a manner that incorporates the following considerations:.