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Management of Commercially Generated Radioactive Waste - U.S. ...

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Comment<br />

Number<br />

2-15 2-16<br />

Comment<br />

Number<br />

in accident number 6.2.8. The probability <strong>of</strong> accidents occurring where given in Table 6.2.6 for accident number 6.2.8 in 00E/ET-0028. An examinseveral<br />

release mechanisms operate is less than the probability associated ation <strong>of</strong> the release fractions and cask inventories given in DOE/ET-0028<br />

with accidents where only a few release mechanisms operate. Thus the risk indicates that the amount <strong>of</strong> radionuclides given in DOE/ET-0029 and hence<br />

may be greater for the latter accident than the one involving many release the dose reported in Appendix N are in error. There are three sources <strong>of</strong><br />

mechanisms. Recommend the GEIS address these accidents that involve error. Mixed fission products and actinides have been excluded from the<br />

several release mechanisms and show that either the risks involved are release, the amount <strong>of</strong> Kr85 released is underestimated, and the amount <strong>of</strong><br />

less than those <strong>of</strong> accident number 6.2.8 or if the risks are greater, this Cs 1 37 released has been overestimated.<br />

more severe accident should be used as the umbrella source term for severe<br />

accidents.<br />

Finally, the following discussion shows that the amount <strong>of</strong> Cs134 and Cs 137<br />

released for accident number 6.2.8 has been overestimated. The discussion<br />

2.d.22 p. N4 on page 6.2.14 <strong>of</strong> 00E/ET/0028 indicates that 6 x 10-4 <strong>of</strong> the cesium inventory<br />

Although the radiation dose to the maximum individual from postulated may be available for release as a result <strong>of</strong> fuel rod perforation in a high<br />

accidents are given, the total population dose to persons in the vicinity temperature environment. This result is taken from Supplement II to<br />

<strong>of</strong> the accident is not given. Since this is an important environmental WASH-1238. According to Table 6.2.6 <strong>of</strong> 00E/ET-0028, the availability<br />

impact, it should be included in the GEIS in context with accident frequencies. fraction is divided in half between Cs 134 and Cs 137 . Table 3.3.8 <strong>of</strong><br />

DOE/ET-0028 shows a cask inventory <strong>of</strong> 1.7 x 10 5 curies and 9.4 x 104 P<br />

The actual value for this population dose can be found on page 4.1.10 <strong>of</strong> curies per MTHM for Cs 134 and Cs 137 , respectively. Since acask contains<br />

OOE/ET-0029. The 70 year dose commitment is given as 140 man-rem. Although 4 MTHM, this results in 6.8 x 10 5 curies <strong>of</strong> Cs 134 and 3.8 x 10 5 <strong>of</strong> Cs 137<br />

the analysis uses a population density <strong>of</strong> 90 persons per square km for in a cask. Applying the availability fraction <strong>of</strong> 3 x 10-4 for each isotope<br />

routine radiological impacts, the.population density used for the accident yields 204 curies <strong>of</strong> Cs 134 and 114 curies <strong>of</strong> Cs 137 available for release.<br />

analysis is 130 person per square km. Note that population densities in Since in accident number 6.2.8, 50% <strong>of</strong> fuel rods are perforated, this results<br />

suburban or urban areas can be at least an order <strong>of</strong> magnitude higher than in 102 curies <strong>of</strong> Cs 134 and 57 curies <strong>of</strong> Cs 137 being released in this accident.<br />

this population density. A severe accident occurring in a suburban or Table 4.1.1-12 <strong>of</strong> DOE/ET-0029 shows 200 curies <strong>of</strong>Cs 134 and 110 curies <strong>of</strong><br />

urban area would, therefore, have a substantially greater environmental, Cs 137 being released. Perhaps the fact that only 50% <strong>of</strong> the rods are<br />

impact than the accident consequences presented in the GEIS. In order perforated was not taken into account.<br />

that all relevant impacts be included in the GEIS, recommend including the<br />

consequences <strong>of</strong> severe accidents in high population density areas. We recommend that the radiation dose to the maximum individual resulting<br />

from this accident be reevaluated in light <strong>of</strong> the above comments.<br />

The largest accident dose reported in the GEIS results from a severe<br />

accident involving a rail shipment <strong>of</strong> spent fuel. The resulting whole 2.d.23 p. N.4<br />

body dose to the maximum individual is given as 120 rem for a one year The consequences presented in page N.4 for severe accidents are based on<br />

period following the accident. The dose is based on the amount <strong>of</strong> the dose received by persons from radionuclides released to the atmosphere.<br />

radionuclides released to the atmosphere as given in Table 4.1.1-12 <strong>of</strong> Since severe accidents may cause a reduction in shielding efficiency,<br />

OOE/ET-0029. The amounts given in this table are based on release fractions doses resulting from radiation emanating directly from the cask should

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