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

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Lines & 6: Did this result take 2-14 into account the growth <strong>of</strong> population<br />

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derived from experience rather than<br />

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.d.18 p. N.4<br />

Lines 5 & 6: Did this result take into account the growth <strong>of</strong> population<br />

along the transport route during the 70 year period?<br />

_. r n < 2.d.19 p. Paragraphs<br />

N.4<br />

3& 4: An inconsistency exists between these two paragraphs.<br />

SParagraphs 3 & 4: An inconsistency exists between these two paragraphs.<br />

SmaIn the third paragraph, it is stated that population doses are calculated<br />

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rn<br />

R based on the permissible limit <strong>of</strong> radiation. Individual doses given in<br />

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the fourth paragraph are taken from WASH-1238 which used dose rate values<br />

derived from experience rather than permissible limits. In addition,<br />

V r- these Ro WASH-1238 numbers were obtained from considering average exposures<br />

w resulting from the transport <strong>of</strong> fuel and waste from a power reactor.<br />

z Since the discussion on page N.4 <strong>of</strong> t the GES concerns transportation <strong>of</strong><br />

Sspent fuel, it would be better to examine the WASH-1238 analysis <strong>of</strong> exposures<br />

due to transport <strong>of</strong>.spent fuel which can be found on pages 40-42.<br />

2.d.20 p. N.4<br />

.2. SA reference to NRC/OOT/State surveillance program results would be useful<br />

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w . Sfor adding realistic perspective and credibility to the estimates <strong>of</strong><br />

ni maximum driver and handler exposure in transportation. See "Summary<br />

r Report <strong>of</strong> the State Surveillance Program on the Transportation <strong>of</strong> Radio-<br />

0 active Materials," NUREG-0393.<br />

%o<br />

S« c - - < o t2.d.21 p. N.4<br />

S The transportation accident consequences presented on page N-4 <strong>of</strong> the GEIS<br />

are based on accident number 6.2.8 described in Table 6.2.6 <strong>of</strong> DOE/ET-0028.<br />

Releases <strong>of</strong> cesium are based on vaporization mechanisms as reported in<br />

Supplement II to WASH-1238. A study conducted by Battelle's Pacific<br />

Northwest Laboratory, "An Assessment <strong>of</strong> the Risk <strong>of</strong> Transporting Spent<br />

§ Nuclear Fuel by Truck," PNL-2588 indicates that other mechanisms can cause<br />

-oo a.o > additional releases <strong>of</strong> cesium and other isotopes. These mechanisms involve<br />

0 m .either oxidation or leaching <strong>of</strong> the fuel. Releases <strong>of</strong> radioactive material<br />

o S c>-1 . m resulting from these mechanisms can occur in addition to the releases used<br />

nu o =r<br />

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-4-

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