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

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6<br />

Spec c The hazard indices discussed in Section 3.1.3.4 and mentioned here<br />

1. (Page 1.5, last paragraph, line 8) The bentonites referred to are at best crude estimates. estiates The hazard hazard the <strong>of</strong> <strong>of</strong> a material materials avail is based on<br />

sodium montmorillonites t<br />

which lose water when heated to 100oc<br />

factos--(a) the quantity <strong>of</strong> the materials available, (b) the<br />

Although the adsorption <strong>of</strong> metals is high in bentonites the water toxicity <strong>of</strong> the materials,<br />

release<br />

and<br />

is<br />

(c)<br />

an<br />

the<br />

undesirable<br />

pathways between<br />

property<br />

the materials<br />

in p mity to aniste<br />

release<br />

Per<br />

is an undesirable<br />

and<br />

property<br />

human beings.<br />

in proximity<br />

Hazard indices<br />

to canisters.<br />

which do not consider<br />

Perhaps<br />

all <strong>of</strong> these<br />

illlte could be utilized in lieu <strong>of</strong> bentonite to the assured 1000C<br />

(and it is difficult to think <strong>of</strong> a generic hazard index which would be<br />

isotherm. useful for specific pathways) are not particularly useful.<br />

2. (Page 1.9) Why is the statement made that "in either event th 6. (Page 1.19)-Accident analysis: The impacts associated with<br />

HL2 contains fission products, uranium, plutonum and ther event, e accidents after closure <strong>of</strong> the repository have been improperly<br />

HLW contaUs? I b n oth recycle the options most <strong>of</strong> the um, and the alance <strong>of</strong> assessed. The most suitable assessment<br />

and<br />

measure<br />

in the<br />

is<br />

U-Pu<br />

the time-integrated<br />

recycle most options lutoniums <strong>of</strong> the uranium removed, population dose over the time<br />

and<br />

<strong>of</strong><br />

in<br />

interest<br />

thermore, U-Pu<br />

which,<br />

recycle<br />

for many<br />

most<br />

accidents<br />

<strong>of</strong> the lutonium is removed as eel. involving ground water flow, would be a very long time. Maximum<br />

reaches the point where fuel elements no<br />

no<br />

longr<br />

longer have<br />

asooner or<br />

sufficient<br />

ter one<br />

fuel<br />

individual doses would probably be associated<br />

use<br />

with the<br />

<strong>of</strong><br />

ingestion<br />

ground<br />

and<br />

value to be worth recycling. This case should be considered.e <strong>of</strong><br />

water;<br />

und ater<br />

this<br />

ths<br />

was<br />

was not<br />

not calculated. calculted<br />

The volatile materials and TRU elements separated in fuel<br />

processing<br />

est<br />

and captured<br />

andards<br />

in<br />

(<br />

accordance with<br />

C capture<br />

the uranium fuel<br />

1 od acco in e thshe uranium ful cycle<br />

included cussion. They should be<br />

The chemical nature <strong>of</strong> the waste and <strong>of</strong> the geosphere appears to<br />

be largely ignored. Much <strong>of</strong> the reduction <strong>of</strong> radiation dose appears to<br />

occur as a result <strong>of</strong> the delay <strong>of</strong> radionuclides by sorption from the<br />

ground water. The sorption <strong>of</strong> radionuclides depends on several<br />

3. (Page 1.11) In comparing natural and manmade doses prson- i<br />

the sum <strong>of</strong> doses to individuals in the population and is-a function<br />

<strong>of</strong> both individual doses and population size The extra 260000tion<br />

person-rem in Colorado comoared to Louisiana is meaninle s in that<br />

population Population size selection -was as arbitrary.<br />

arbitrary. Why<br />

Why<br />

not<br />

not<br />

use<br />

use<br />

Newss<br />

New<br />

in that<br />

York and<br />

Hawaii? Moreover, the data base is now obsolescent, see NCRP-45.<br />

factors, including the oxidation-reduction state <strong>of</strong> the nuclide, the<br />

presence or absence <strong>of</strong> complexing or chelating agents, and the nature<br />

<strong>of</strong> the specific geological materials present. In some cases,<br />

particularly if large and rather exotic containment canisters are<br />

postulated, the ion exchange requirements <strong>of</strong> the canister materials may<br />

be quite significant and might overload the exchange<br />

media<br />

capacity<br />

in<br />

<strong>of</strong> the<br />

which the waste<br />

edia<br />

was<br />

in whi<br />

emplaced.<br />

c h t h e wa s t e w s em ced.<br />

S(Page 1.12) Media properties: This section appears t conside<br />

only the properties Properties <strong>of</strong> a medium which make it<br />

it oapper<br />

possible to<br />

to<br />

construct<br />

consider<br />

a<br />

mine in it. For example, ground water is discussed only in terms o<br />

the necessity to remove water from repository shafts and rooms. Ground<br />

water is more important as a potential way for the radionuclides to<br />

move in the geosphere.<br />

7. (Page 2.2.1, Section 2.2.1.1) The document neglects to mention<br />

overall guidance provided<br />

for<br />

by the FRC:<br />

Federal<br />

Radiation Protection<br />

Agencies,<br />

Guidance<br />

or Fedeal<br />

25 F.R.<br />

Agencies, 25 F.R.<br />

4402<br />

402 et<br />

et seq.<br />

.<br />

(5/18/60),<br />

(5/18/60), for which<br />

10 CFR 20 is one <strong>of</strong> several implementing regulations.<br />

8. (Section 2.2.1.2, page<br />

8. (Section 2.2.1.2,<br />

22.3<br />

page 2.2.3 et<br />

se.)<br />

seq.)<br />

There<br />

There<br />

is<br />

is<br />

no<br />

no<br />

mention<br />

mention <strong>of</strong><br />

5. (Page 1.15) Again bentonite is considered despite the limitations<br />

expressed above. limitations<br />

EPA's regulations developed under the regulatory authority <strong>of</strong> the<br />

Marine Protection, Research and Sanctuaries Act <strong>of</strong> 1972 (Public Law<br />

92-532). This authority should be referenced in this section.<br />

Under human institutions: Human back-up <strong>of</strong> the "carefull<br />

engineered geologic system" for eriods <strong>of</strong> hundreds <strong>of</strong> ear<br />

engineered<br />

enough. Back-up<br />

geologic<br />

for<br />

system"<br />

thousands<br />

for periousan<br />

ds years <strong>of</strong><br />

<strong>of</strong> years, if not<br />

is not<br />

many thousands, would<br />

be necessary. It is for this reason that the roosed PA criteriashould<br />

9. (Page 2.2.3) Under EPA Uranium Fuel Cycle Standards, the last<br />

sentence in this section is in error. The effective date for<br />

application <strong>of</strong> 40 CFR 190 can be found in 40 CFR 190.12.<br />

should<br />

This error<br />

be corrected.<br />

e corrected<br />

3 F.tt. 53262a et seq., November St, 1978) recommend against reliance 10. (Page 2.2.3) The way in which the EPA drinking water regulations<br />

would be applied, if at all, is not made clear. These regulations are<br />

not directly appropriate to the disposal <strong>of</strong> radioactive waste since<br />

they do not control the contamination <strong>of</strong> the environment. They are<br />

7

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