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Extra resources for Accid. Anal. - Nuclear Powerplants with PHWRs
ASME Level C (emergency) both with and without the LRVs being credited. The first trip parameter may be credited in the case where this trip parameter is high pressure. Systematic fuel failures are prevented. It is sufficient to prevent prolonged periods in dryout or in stratified flow before reactor trip. Relevant event combinations Since there is no fuel damage for these events, there are no relevant event combinations with impairments of ECC or containment. 9. 1. Initiating events This event class includes rupture of the steam piping inside or outside the reactor building, up to the complete guillotine rupture of the steam balance header.
Each event class has its own public dose acceptance criterion. See Fig. 1. feeder pipe. Small pipes connecting each channel to the inlet and outlet headers at each end of the core. figure-of-eight loop. See core pass. Group 1. Systems used for power production that also have a safety function. Group 1 systems by themselves must be able to shut down the plant, remove decay heat, keep radioactivity contained and monitor the state of the plant. Group 2. Seismically qualified emergency systems, including AC power (Group 2 diesels), feedwater (Group 2 auxiliary feedwater), service water, instrument air and secondary control area systems.
Normal operation of the RRS can delay a reactor trip or make one unnecessary; shutdown system effectiveness must be shown whether the RRS operates normally or fails to respond. 3. Acceptance criteria The following acceptance criteria apply: (1) Dose to the most exposed individual in the critical group is below the limits listed below: (i) Loss of Class IV power: Event Class 1 limit in Fig. 1; (ii) Pump seizure: Event Class 2 limit in Fig. 1. (2) The heat transport system must remain intact. Thus it must not fail due to: (i) Overpressure; 24 (ii) Overheating of the pressure tubes.
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