TNAG-1506-FCO40-2064-Guangdong-nuclear-power-station-project-at-Daya-Bay-safety-c-1986 — Page 147

FCO40 Hong Kong Department Records 聯邦事務部香港部檔案 All

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Information Requirements

Generic Information on the PWR

Since the engineering of a typical PWR power plant is well understood at SRD, there is no requirement to provide information related to the general prop- erties and safety approach for the PWR.

Generic information on safety standards

Information is requested concerning the safety standards which will be used in the design and operation of the plant. In particular, a brief statement of the French safety targets which will be used for the design, and likewise of any Chinese standards which will be applied instead of, or overriding, the French standards.

Design safety guidelines concerning the application of the Single Failure Criterion, or more stringent criteria such as Common Cause Failure criteria and diversity requirements will be useful to indicate the safety standards which are likely to be achieved.

Plant specific information

The study will require specific information on a number of safety systems, so that the probabilities of the multiple failures necessary for a severe accident can be estimated. Information is required on both front line systems which actually carry out the safety functions, support systems which provide electric power, cooling and other necessary services, and

'procedures which are involved in carrying out any safety functions not carried out by authomatic actions. A list of the systems and possible procedures on which information is desirable follows :

Reactor protection system, including the specifications of the methods of reactivity control (particularly the matter of an emergency boration system ).

Emergency core cooling system

-

actuation ( safety injection signal ) accumulator system

low pressure injection system

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low pressure recirculation system

-

high pressure injection system

Auxiliary feedwater system

-

high pressure recirculation system

(or procedure for transition from

HPI to LP recirc. )

procedures for recirculation (if not automated ).

Main feedwater system acting to provide AFW function post-trip Containment spray system

Containment fan cooler system

Containment isolation system

Primary circuit relief and isolation system (automatic/manual ? ) Secondary circuit (steam generator) relief system

Main steam isolation system

Interfaces between primary circuit and RHR / ECCS circuits Reactor coolant pump seal protection systems

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