Orange County NC Website
<br />Official estimates indicate that this exposure will cause 50-100 thousand extra cancer <br />fatalities worldwide over the next 70 yeazs.19 <br />28. The core of the Harris reactor contains 157 PWR fuel assemblies. At shutdown, this <br />core contains about 155,000 TBq (47 kg) of cesium-137.20 When a spent fuel assembly is <br />discharged from the reactor, it will contain more cesium-137 than the average assembly at <br />shutdown. CP&L plans an eventual, aggregate capacity in the Harris pools of 3,080 <br />PWR assemblies and 5,304 BWR assemblies. Note that the cesium-137 content in each <br />BWR assembly will be about one. quarter the cesium-137 content in each PWR assembly, <br />if both assemblies have been dischazged for an equal period.21 After dischazge, the <br />content of cesium-137 in a fuel assembly will decay exponentially with ahalf--life of 30 <br />years. <br />29. As a simplified illustration, assume that all fuel assemblies in the Harris pools have <br />been discharged for an equal period. Further assume that all four pools are full and <br />contain 3,080 PWR assemblies and 5,304 BWR assemblies. The pools will then contain <br />as much cesium-137 as 4,406 PWR assemblies. (3,080 + 5,304 x 1/4 = 4,406) Note that <br />4,406 PWR assemblies represent 28 cores of the Harris reactor. <br />30. If an accident can be postulated that releases to the environment a significant fraction <br />of the cesium-137 in the Harris pools, then it is clear that the consequences of this <br />accident would be large. The offsite radiation exposure could be an order of magnitude <br />larger-than the exposure from the Chernobyl accident. Activation of pools C and D could <br />lead to an accident which creates offsite radiation exposure as much as two times higher <br />than the exposure that would arise from a similar accident involving only pools A and B. <br />H. Loss of Water from Spent Fuel Pools at Harris <br />31. Loss of water from one or more of the Harris pools could initiate a release to the <br />environment of a significant fraction of the cesium-137 in the pools. This potential exists <br />because the cladding of PWR or BWR fuel is a zirconium alloy which can react <br />exothermically with air or steam. Thus, if the water in a fuel pool is removed and the fuel <br />is partially or totally uncovered, one must be concerned about the possibility of a <br />runawayair-zircomum or steam-zirconium reaction. Such a reaction could release <br />cesium-137 and other radioisotopes from affected fuel-into the fuel building. That <br />building was not designed to contain radioisotopes released during a vigorous exothermic <br />reaction in the pools, and it can be assumed that most of the volatile radioisotopes <br />entering the building from the affected fuel would be released from the building as an <br />atmospheric plume. <br />32. Several reports prepared by or for the NRC have examined the conditions under <br />which a runaway zirconium reaction might occur.22 However, these reports have <br />~9 Allan S Krass, Consequences of the Chernobyl Accident (Cambridge, Massachusetts: Institute for <br />~ Resource and Security Studies, December 1991). <br />20 NRC, Final Environmental Statement, page 5-50. <br />21 The ratio of one quarter derives from the parameters shown in the license amendment application, <br />~ Enclosure 7, page 5-15. <br />22 Relevant reports include: V L Sailor et al, Severe Accidents in Spent Fuel Pools in Support of Generic <br />Safety Issue 82, NUREG/CR-4982, July 1987; E D Throm, Regulatory Analysis for the Resolution of <br />Generic Issue 82, "Beyond Design Basis Accidents in Spent Fuel Pools", NUREG-1353, April 1989; and R <br />