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By Daniel A. Murray

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The quickopening valves are arranged in three parallel pairs. Two of the three channels mustfail to detect the need for a reactor trip or fail to respond to the trip signal to prevent poison injection, 39 NtIREG/CR-6065 Systems NUREG/CR-6065 40 Systems o cq I-LU ZE< Z ', o _ >-_0 ! L_ _ :1 _ v, .... _. li , tt ! _v? o ' t_J__iZ I w ml-- 7 WZn'< Z _: o. U rr 0 O0 >. _. • . P-IV MLP system fault tree supply and requires operator action to refill the tank when empty.

These representative events were selected based upon PRA experience and operational information of the CANDU plant and were judged to adequately address the remaining initiators. 3. Detailed plant analysis was conducted for these IEs. 2. 4 presents the justification for the RIEs selected for each PRC. 2. U. S. Nuclear Regulatory Commission, "Standard Review Plan," USNRC Report NUREG-0800, Rev. * *Available for pm-chasefromtheNational Technical Infatuation Service,Springfield, VA22161. 4 Justification for PLIEs PRC RTE Justification LBLOCA Breakin feeder tube header Large volume of coolant inventoryloss Requiresimmediate ECCS response SBLOCA Liquid relief valve failure Requires elements of other SBLOCAs such as crash cooling Requires isolation of the bleed condenser Reactor regulatingsystem not credited for reactor shutdown Feeder tubebreak Demonstratesplantresponse to a small loss of coolant that cannot be isolated Loss of Essential Power Supplies LOP Designed plantto feed power to itself upon loss of off-site power oz stationload Requires operationof diesel generators Undercooling Event Feedwaterpiping breakin reactorbuilding Loss of coolant supply to the steam generators Poses potentialchallenge to the containment Poses a direct challenge to the Group 2 feedwater system Feedwaterpiping breakin turbine building Does not requirethe operator to isolate a draining boiler Initiating frequency is estimated to be 2 orders of magnitude greater than feedwater piping breaks in the reactor building Reactivity Transient SCRAM Requires the reactor to be shut down Other reactivity initiators result in a SCRAM-type event Overcooling Event SCRAM Overcooling of the core not a direct concern except that it forces the reactor to be shut down, which then closely follows a SCRAM sequence Loss of Heat Transport LOP The heat transport pumps trip on a LOP, resulting in loss of forced flow through the core, which looks like a LOP event except that loss of power implies that other equipment also is unavailable.

3) were analyzed using event trees as discussed in Chap. 3. The event tree branch points represent success or failure of systems designed to mitigate the initiator. Fault trees were used to model these systems to demonstrate how failure of the systems could occur. Many of the same systems would be used to mitigate different IEs and, therefore, are present in branch point calling for the FW function. In those cases where a specific system is needed, only the appropriate portion(s) of the fault tree would be called upon in the event.

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