CNSC RD-337 PDF

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.

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In the event of an accident when injection of emergency coolant is required, it is not readily possible for an operator to prevent the injection from taking place. A quality assurance program is established as part of the overall management arrangements by which the plant will function to achieve objectives.

Nothing contained in this document is to be construed as chsc any applicant or licensee from requirements associated with conventional codes and standards. It establishes a set of comprehensive design expectations that are risk-informed and align with accepted international codes and practices. The sum of frequencies of all event sequences that can lead to a release to the environment of more than 10 15 becquerel of iodine is less than 10 -5 per reactor year.

The design ensures that diverse methods of communication are available within the NPP and in the immediate vicinity, and also to off-site agencies, in accordance with the emergency response plan. A safety analysis of the plant design includes hazards analysis, deterministic safety analysis, and probabilistic safety assessment techniques.

Settlement analysis and evaluation of soil capacity includes consideration of the effects cnsf fluctuating ground water on the foundations, and identification and evaluation of potential dd-337 soil strata and slope failure. Achievement of the general nuclear safety objective discussed in subsection 4. In DBAs, the fuel assembly and its component parts remain in position with no distortion that would prevent effective post-accident core cooling or interfere with the actions of reactivity control devices or mechanisms.

The need for operator intervention on a short time scale is kept to a minimum. Seismic fragility levels should be evaluated for SSCs important to safety by analysis or, where possible, by testing. 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.

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Defence-in-depth level four is achieved by providing equipment and procedures to manage accidents and mitigate their consequences as far as practicable.

During normal operation, including maintenance and decommissioning, doses are regulated by the limits prescribed in the Radiation Protection Regulations. All closed piping service systems have at least one single isolation valve on each line penetrating the containment, with the valve being ncsc outside of, but as close as practicable to, the containment structure.

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

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. Safety support systems provide services such as electrical, compressed air, and water to systems important cnsv safety. The design provides appropriate means for access control and detection, and for minimizing the number of access and egress points to protected areas.

Human factors Factors that influence human performance as it relates to the safety of the nuclear power plant, including activities during design, construction, and commissioning, operation, maintenance and decommissioning phases.

System control interlocks are designed to minimize the likelihood of inadvertent manual or automatic override, and to provide for situations when it is necessary to override interlocks to use equipment in a non-standard way.

All Cns important to safety are designed with sufficient quality and reliability to meet the design limits. Particular attention is placed on the prevention of potential containment bypass in accidents involving significant core degradation.

The design of the NPP, including that of external buildings and SSCs integral to plant operation, includes provisions for fire safety.

There is no gap in trip coverage for any operating condition i. Exemptions for passive components apply only to those components that are designed and manufactured to high standards of quality, that cnsd adequately inspected and maintained in service, and that remain unaffected by the PIE.

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Radiation doses to the public fd-337 to site personnel are to be as low as reasonably achievable. The adequacy of the design, including design tools and design inputs and outputs, are verified or validated by individuals or groups that are independent from those who originally performed the work.

It is also intended to provide requirements and guidance to all applicants and licensees cnzc in preparing applications for a licence to construct an NPP. The principle of fail-safe design is applied to the design of SSCs important to safety.

RD-337: Design of New Nuclear Power Plants

For example, to reduce the potential for common-cause failures, the application of diversity is examined for any similarity in fnsc, components, and manufacturing processes, or subtle similarities in operating principles or common support features. A reasonable level of confidence that this equipment will perform as intended in the case of a severe accident is demonstrated by environmental, fire, and seismic assessments.

These rules comply with appropriate accepted engineering practices. The control system, combined with the inherent characteristics of the reactor and the selected operating limits and conditions, minimize the need for shutdown action.

Periodic testing of the systems and their components is ncsc at a frequency commensurate with applicable requirements.

Document History of REGDOC-2.5.2, Design of Reactor Facilities: Nuclear Power Plants

This includes a liquid waste cndc system of sufficient capacity to collect, hold, mix, pump, test, treat, and sample liquid waste cnac discharge, taking expected waste and accidental spills or discharges into account.

Early in the design process, the various potential barriers to core degradation are identified, and features that can be incorporated to halt core degradation at those barriers are considered. To ensure that emissions and concentrations remain within prescribed limits, the design includes suitable means for controlling liquid releases to the environment in a manner that conforms to the ALARA principle.