Download Anticipated and Abnormal Plant Transients in Light Water by Joseph M. Hendrie (auth.), Pamela L. Lassahn, Debu Majumdar, PDF

By Joseph M. Hendrie (auth.), Pamela L. Lassahn, Debu Majumdar, George F. Brockett (eds.)

Over the final 30 years, reactor protection know-how has developed now not lots from a necessity to get over injuries or incidents, yet basically from many teams within the nuclear group asking hypo­ thetical, looking (what if) ~uestions. This ~uestioning has certainly paid off in developing preventive measures for lots of sorts of occasions and strength injuries. stipulations, comparable to reactivity tours, huge holiday, lack of coolant, middle soften, and comprise­ ment integrity loss, to call a number of, have been all at one time subject matters of protracted discussions on hypothesized occasions. traditionally, lots of those became multiyear, large-scale learn courses aimed toward resolving the "what ifs. " For the subject of expected and irregular plant transients, how­ ever, the looking out ~uestions and the learn weren't so prolific till the mid-1970s. at the moment, probabilistic threat methodolo­ gies started to let us know we must always switch our emphasis in reactor security examine and improvement and concentration extra on small pipe breaks and plant transients. 3 Mile Island punctuated that message in 1979. The plant temporary subject region is a multidisciplinary topic related to not just the nuclear, fluid circulate, and warmth move applied sciences, but additionally the synergistics of those with the reactor keep watch over structures, the protection s;,"stems, operator activities, upkeep or even administration and the industrial concerns of a given plant.

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Extra resources for Anticipated and Abnormal Plant Transients in Light Water Reactors: Volume 1

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When the exact sequence is ambiguous, define the possible alternates and discriminators. Preliminary dynamic analysis using the simplest applicable methods. Use more sophisticated methods selectively. Explore sensitivity to plausible ranges of parameters; self-consistent, plant-specific parameters. SENSITIVITY AND RISK ANALYSIS In the first item in Table 4, the "plausible variations" can be derived from at least three sources. The first is simply to take account of added fault conditions which are known to occur at reasonable frequencies.

These incidents might occur once during the lifetime of the unit. Limiting Faults include events such as large break LOCA, steamline break, and control rod ejection. These events, although of low probability of occurrence, have the potential for releasing significant amounts of radioactivity. They are not expected to occur. This category is used for the deterministic design of mitigating systems. The fifth category deals with a degraded core and the potential for radioactive releases much greater than those which would result from a limiting fault.

The conditional probability to core damage is a measure of the safety margin remaining, given that the event has occurred or is repeated. This method complements PRAs as a continuing source of potential "outliers" which need attention or remedy. s A paper later in this conference describes the process of sequence risk analysis in detail. B. Robinson Haddam Neck Haddam Neck 9 Kewaunee 10 Millstone 2 11 Humboldt Bay 12 Point Beach 1 13 Rancho Seco 14 Davis Bessee 15 Turkey Point 3 Loss of feedwater; open PORV Stuck-open PORV Cable tray fire HPCI fails to start Loss of feedwater control RCP seal failure Loss of offsite power Trip with loss of offsite power Auxiliary feedwater inoperable Load shedding on safety buses Loss of offsite power Inoperable auxiliary feedwater pumps NNI failure; excess-feedwater Auxiliary feedwater pumps inoperable Failure of three auxiliary feedwater pumps 3/28/79 9/24/77 3/22/75 6/3/79 8/31/77 5/1/75 1/19/74 7/15/69 11/5/75 7/20/76 7/17/70 4/7/74 3/20/78 12/11/77 5/8/74 EVALUATION OF OPTIONS FOR IMPROVEMENTS Table 6 lists four of the activities important in the evaluation of options.

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