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

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Comment<br />

Number<br />

2-3<br />

Comment<br />

Number<br />

from plutonium recycle as compared with U0 2 -enriched uranium only fuel. c.2 p. 2.1.22<br />

As averaged over the entire time span to the year 2040, the MOX to 2 The assumption that spent fuel will be stored after packaging rather than<br />

fuel ratio we calculate is 60/40. Please provide your basis for this<br />

el ate.<br />

prior to packaging while awaiting shipment to a respository should be<br />

justified. Economics may dictate this procedure and it should be based on<br />

estimate a cost effectiveness analysis.<br />

2.b.8 p. A.49<br />

Table A.43, presents the inventories <strong>of</strong> spent fuel in storage and isolation<br />

for the delayed repository availability. By taking the difference between<br />

the entries for succeeding years, one should be able to determine the<br />

tonnage <strong>of</strong> spent fuel that is discharged for each year, and from that, the<br />

total number <strong>of</strong> canisters discharged for each year. The following results<br />

2.c.3<br />

2.<br />

2.c.4<br />

pp. 2.1, 2.2<br />

pp. 2,<br />

The NRC Final EIS on spent fuel storage, NUREG-0575, should be cited. The<br />

NRC Draft GEIS on Uranium Milling, NUREG-0511, April 1979, has been issued<br />

or comment.<br />

p. 3.1.184<br />

were obtained: On page 3.1.184, the following statement is made: "During planned operation<br />

Year MTHM Canisters* <strong>of</strong> the ESFSF (dry caisson option) no releases <strong>of</strong> radioactivity would<br />

1983 1669 5,619 occur." Provide support for this statement.<br />

1985 2979 10,030<br />

1986 1960 6,599 2.c.5 It appears that all <strong>of</strong> the below terms refer to the same facility. Terms<br />

1987 2950 9,932<br />

1988 3430 11,548 should be used consistently throughout to avoid confusion and to facilitate<br />

comparisons.<br />

*Using 0.297 M M per Table 2.1.8<br />

CAN packaged spent fuel storage facility (p. 2.1.22)<br />

Explain the erratic discharge rates.<br />

2-4<br />

storage (p. 2.1.22)<br />

<strong>of</strong>fsite storage facilities (p. 2.1.22)<br />

Detailed information on the nuclear growth scenario assumed should be extended storage facility (p. 2.1.25)<br />

provided, including; numbers and types <strong>of</strong> reactors that come on line<br />

storage facility (p. 2.1.25)<br />

each year; and the annual waste streams from the plants, including<br />

(ESFSF) Extended Spent Fuel Storage Facilities (p. 3.1.181)<br />

spent fuel, and low-level waste (volume and activity).<br />

dry caisson storage facility (p. 2.1.184)<br />

SURF (p. 3.1.184), (p. 3.1.186)<br />

c. <strong>Waste</strong> Storage and Treatment<br />

2.c.6 The basis for assuming that two Independent Retrievable <strong>Waste</strong> Storage<br />

2.c.1 p. 1 Facilities would be needed to serve the needs <strong>of</strong> the reprocessing industry<br />

The GEIS should include interim storage facilities in the general if repositories are available beginning in the year 2000 should be given.<br />

description <strong>of</strong> the fuel cycle since it is apparent from the discussions in In particular, if economics is the basis, i.e., facility versus transportation<br />

the statement that these facilities will be built,<br />

costs, such a discussion would assist in any cost/benefit analysis.

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