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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The design provides for the ongoing availability of fundamental safety functions during BDBTs; these provisions will depend on the severity of the threat.

The design provides for ample flow routes between separate compartments inside the containment. The extent of trip coverage provided by all available parameters is documented for the entire spectrum of failures for each set of PIEs.

RD-337: Design of New Nuclear Power Plants

Nothing contained in this document is to be construed as relieving any applicant or licensee from requirements associated with conventional codes and standards.

This documentation is maintained in a dynamic suite of documents to reflect changes in design as the plant evolves. Such operator actions are facilitated by the provision of adequate instrumentation to monitor plant status, and controls for manual operation of equipment.

Jet impact The potential internal hazard associated with high pressure fluid released from a pressure-retaining component. Where water is required for the EHRS, it comes from a source that is independent of normal supplies.

To the extent practicable, penetrations are to be designed to allow individual testing of each penetration.

RD Design of New Nuclear Power Plants – Canadian Nuclear Safety Commission

Reliability and effectiveness of a safety system will not be impaired by normal operation, by partial or complete failure in other systems, or by any cross-link generated by the proposed sharing. The event or cause may be a design deficiency, a manufacturing deficiency, an operating or maintenance error, a natural phenomenon, a human-induced event, or an unintended cascading effect from any other operation or failure within the plant.


The design applies the principle that plant states that could result in high radiation doses or radioactive releases have a very low frequency of occurrence, and plant states with significant frequency of occurrence have only minimal, if any, potential radiological consequences.

Shutdown state Characterized by subcriticality of the reactor. This consideration continues in an iterative way throughout the entire design process. Any alternative approach should demonstrate equivalence to the outcomes associated with the use of the expectations set out in this regulatory document. The design therefore reflects an assessment of options, demonstrating that an optimized configuration has been sought for the facility layout.

That report identified improvements to the CNSC’s regulatory framework to strengthen the oversight of existing programs, including those for the design of new NPPs. Intermediate or secondary cooling piping loops have leak detection, whether the ECCS recovery system is inside or outside of containment, with the leak detection being such that on detection of radioactivity from the ECCS recovery flow, the loops can be isolated as per the requirements for containment isolation.

A review of the design confirms that this provision has been met. The rx-337 system and the td-337 reactor characteristics keep all critical reactor parameters within the specified limits for a wide range of AOOs.

Correct operation of the EHRS equipment following an accident is not dependent on power supplies from the electrical grid or from the turbine generators associated with any reactor unit that is located on the same site as the reactor involved in the accident. All pressure-retaining SSCs are protected against overpressure conditions, and are classified, designed, fabricated, erected, inspected, and tested in accordance with established standards.

Management arrangements The means by which an organization functions to achieve its objectives, including:. Where physical separation is not possible, safety support system equipment may share physical space.


The plant design considers the role of structures, pathways, equipment, and instrumentation in providing detection, delay, and response to threats.

The design provides for periodic testing of the entire channel of instrumentation logic, from sensing device to actuating rd337. All pressure-retaining SSCs of the reactor coolant system and auxiliaries are designed with an appropriate safety margin to ensure that the pressure boundary will not be breached, and that fuel design limits will not be exceeded in normal operation, AOOs, or DBA conditions.

All equipment required for correct operation of the ECCS is considered part of the system or its safety support system s. For the purposes of this document, accidents include design basis accidents and beyond design basis accidents.

Damage to the containment structure is limited to prevent uncontrolled releases of radioactivity, and to maintain the integrity of structures that support internal components.

Practicable Technically feasible and justifiable while taking cost-benefit considerations into account. This is ensured by providing additional trip parameters if necessary. The design authority establishes an adequate qualification program to verify that the new design meets all applicable safety design requirements. All systems that contribute to the transport of heat by conveying heat, providing power, or supplying fluids to the heat transport systems, are therefore designed in accordance with the importance of their contribution to the function of heat transfer as a whole.

Personnel access to the containment is through airlocks that are equipped with doors that are interlocked to ensure that at least one of the doors is closed during normal operation, AOOs, and DBAs.

Pressure and leak testing is conducted on applicable structures to demonstrate that the respective design parameters comply with cnsf.