NUREG-0945

Vol. 3

Final ;

Environmental Impact Statement

on 10 CFR Part- 61 "Licensing Requirements for'Land Disposal of Radiodactive Waste"

: Appendices C-F

U.S. Nuclear Regulatory Commission

Office of Nuclear Material Safety and Safeguards

November 1982

.~ ~ z.; .

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I I . , : :

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Reprinted January 1986
NOTICE

Availability of Reference Materials Cited in NRC Publications

Most documents cited in NRC publications will be available from one of the following sources:

1. The NRC Public Document Room, 1717 H Street, N.W.

Washington, DC 20555

2. The Superintendent of Documents, U.S. Government Printing Office, Post Office Box 37082,

Washington, DC 20013-7082

3. The National Technical Information Service, Springfield, VA 22161

Although. the listing that follows represents the majority of documents cited in NRC publications,

it is not intended to be exhaustive.

Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC Office of Inspection

and Enforcement bulletins, circulars, information notices, inspection' and investigation notices;

Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicant and

licensee documents and correspondence.

The following documents in the NUREG series are available for purchase from the GPO Sales

Program: formal NRC staff and contractor reports, NRC-sponsored conference proceedings, and

NRC booklets and brochures. Also available are Regulatory Guides, NRC regulations in the Code of

-Federal Regulations, and Nuclear Regulatory Commission Issuances.

Documents available from the National Technical Information' Service include NUREG series,

reports and technical reports prepared by other federal agencies and reports prepared by the Atomic

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Documents available from public and special technical libraries include all open literature items,

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Single copies of NRC draft reports are available free, to the extent of supply, upon written request

to the Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, Washington, DC 20555.

Copies of industry codes and standards used in a substantive manner in the NRC regulatory process

are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, and are available

there for reference use by the public. Codes and standards are usually copyrighted and may be

purchased from the originating organization or, if they are American National Standards, from the

American National Standards Institute, 1430 Broadway, New York, NY 10018.
NUREG-0945

Vol. 3

Final

Environmental Impact Statement

on 10 CFR Part 61 "Licensing Requirements for Land Disposal of Radioactive Waste"

Appendices C-F

U.S. Nuclear Regulatory

Commission

Office of Nuclear Material Safety and Safeguards

November 1982
ABSTRACT

The three-volume final environmental impact statement (FEIS) is

prepared to guide and support publication of a final regulation,

10 CFR Part 61, for the land disposal of low-level radioactive

waste. The FEIS is prepared in response to public comments received

on the draft environmental impact statement (DEIS) on the proposed

Part 61 regulation. The DEIS was published in September 1981 as NUREG0782. Public comments received on the proposed Part 61 regulation

separate from the DEIS are also considered in the FEIS. The FEIS is

not a rewritten version of the DEIS, which contains an exhaustive and

detailed analysis of alternatives, but rather references the DEIS and

presents the final decision bases and conclusions (costs and impacts)

which are reflected in the Part 61 requirements. Four cases are

specifically considered in the FEIS representing the following: past

disposal practice, existing disposal practice, Part 61 requirements,

and an upper bound example.

The Summary and Main Report are contained in Volume 1. Volume 2

consists of Appendices A - Staff Analysis of Public Comments on the

DEIS for 10 CFR Part 61, and Appendices B - Staff Analysis of Public

Comments on Proposed 10 CFR Part 61 Rulemaking. Volume 3 contains

Appendices C-F, entitled as follows: Appendix C - Revisions to

Impact Analysis Methodology, Appendix D - Computer Codes Used for

FEIS Calculations, Appendix E - Errata for the DEIS for 10 CFR Part 61

and last, Appendix F - Final Rule and Supplementary Information.

i
FOREWARD

In September 1981, NRC published the Draft Environmental Impact

Statement on 10 CFR Part .61:. "Licensing Requirements, for. Land Disposal 'of Radioactive Waste". (NUREG-0782). This draft' environmental

impact statement (EIS) contains-'an exhaustive and detailed analysis

of a wide'range of alternatives. Basedupon NRC -analysis of public

comments on both the draft..EIS and upon the proposed Part-61 regulation'itself (Federal Register Notice 46 FR 38081, July'24, 1981), no

new alternatives or principles were identified which required analysis. No major changes were required for several requirements of the

Part 6L regulation, including the overall performance objectives

which should be achieved in the land disposal of low-level radioactive

waste, administrative and procedural requirements for licensing a land

disposal facility, and the requirements for financial assurance. Many

clarifying and explanatory changes were, however, required-with

respect to specific rule provisions. .

Given this conclusion and public comments suggesting that the number

of alternatives considered in the EIS be reduced to a smaller, more

understandable number, NRC has chosen not to republish the extensive

analysis of alternatives as presented in the draft EIS. Rather, NRC

has refined the EIS impact analysis methodology based upon public

comments and has grouped the alternatives analyzed onto four major

alternatives which present the basis for decisions made regarding the

Part 61 requirements.

This final EIS is therefore not a revision of the -draft EIS but a

stand-alone statement which uses the draft EIS as. a -resource, and

reference document. Refinements made to the draft EIS assumptions and

impact analysis methodology are noted and used in the final EIS. NRC

hopes that in this way, the final EIS will be of a more managable size

and the alternatives analyzed and conclusions reached presented in

more of a concise, understandable manner. .

.:

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-Iiii
List of Preparers

The overall responsibility for the preparation of this draft environmental

impact statement was assigned to the Low-Level Waste Licensing Branch, Division

of Waste Management, Of fice of Nucl ear Material Safety and Safeguards, U.S.

'Nuclear Regulatory Commission. The statement was prepared with technical

assistance from the' firm of Dames and Moore, White Plains, New York.

Nuclear Regulatory Commission Staff

Preparers

R. Dale Smith, Chief

Low-Level Waste Licensing Branch

Kitty S. Dragonette

Paul H. Lohaus

George C. Pangburn

G. W. Roles

Contributors

Timothy C. Johnson

Mary Jo Seemann

James A. Shaffner

David L. Siefken

Derek Widmayer

Special Contributors

Willste CRESS Central Dictation Unit

Carole Finan

Jeannette Kiminas

Pauline Rock

Charline Simon

Irene Suissa

Cathy S. Bromberg, Secretary, Low-Level Waste Licensing Branch

Robert Fonner, Attorney, Office of the Executive Legal Director

iv
Dames and Moore Staff

Others contributing significantly to this environmental impact statement

included personnel of the firm of Dames and Moore, Inc. (D&M) of White Plains,

New York. The D&M contribution was directed by Dr. Oktay I. Oztunali.

OPTIONR & GRWATRR Codes

Oktay I. Oztunali

C. Joseph Pitt

Input on I-129 & C-14

Oktay I. Oztunali

Leslie Skoski

Kim D. Petschek

v
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APPENDIX C

REVISIONS TO IMPACT ANALYSIS METHODOLOGY
TABLE OF CONTENTS

Page

1. INTRODUCTION.. .......................................... C-1

2. MODIFICATIONS TO METHODOLOGY USED TO CALCULATE DISPOSAL COSTS.. C-1

3. MODIFICATIONS-TO COST DATA ..................... C-7

4. MODIFICATIONS TO THE WASTE SOURCE DATA BASE . C-70

5. MODIFICATIONS TO THE IMPACT ANALYSES METHODOLOGY . .C-97

5.1 Revised-Methodology to Consider Waste Classification

Impacts................................................. C-103

5.2 'Treatment-of Decay Chains .C-106

5.3 Radiological Impacts from Trench Overflow and Leachate

Evaporation ......................... 1-C-107

-5.4 Revised&Pathway'Dose Conversion'Factors ................... C-109

5.5 Revised Methodology to Consider Potential Operational

Accidents ............ C-109

6. IMPACT OF DISPOSAL OF C-14 AND I-129 . . . C-111

6.1 Isotope Characteristics and Generation . .. C-120

6.2 Review of Available Information ... C-122

6.2.1 Iodine-129 . ' C-122

6.2.2 Carbon-14 .C-128

6.3 Discussion and Conclusions .. C-130

6.3.1 Iodine-129 .C-130

6.3.2 Carbon-14 . C-133

7. DISPOSAL LIMITS FOR TRANSURANIC ISOTOPES .C-134

REFERENCES......................................................... C-139
I 11!r!I

TABLE OF CONTENTS (Continued)

Page

C.16 Revised DEIS Table F.8 - Differential Costs for-Slit

Trench Operations (Ten Percent of Waste Volume) ........... C-36

C.17 Revised DEIS Table F.9 - Differential Costs for Caisson

Disposal (Ten Percent of Waste Volume) ...................... C-38

C.18 Revised DEIS Table F.10 - Differential Costs for Concrete

Walled Trench (Ten Percent of Waste Volume) ............... C-41

C.19 Revised DEIS Table F.11 - Differential Costs for Concrete

Walled Trench (Entire Waste Volume) ....................... C-44

C.20 Revised DEIS Table F.12 - Differential Costs for Grouting. C-47

C.21 Revised DEIS Table F.13 - Differential Costs for Installation of an Engineered Human IntruderBarrier .............. C-49

C.22 Revised DEIS Table F.14 - Differential Costs for Improved

Monitoring ....... C-51

C.23 Revised DEIS Table F.15 - Differential Costs for Improved

Compaction ....... C-52

C.24 Revised DEIS Table F.16 - Differential Costs for Improved

Thicker Cap ........ C-53

C.25 Revised DEIS Table F.17 - Differential Costs for

Moisture Barriers. ............. C-55

C.26 Revised DEIS Table F.18 - Differential Costs for Use

of a Sand Backfill .............. C-57

C.27 Revised DEIS Table F.19 - Differential Costs for a

Surface Water Drainage System ......................... C-58

C.28 Revised DEIS Table F.20 - Differential Costs for

Weather Shielding ............. C-60

C.29 Revised DEIS Table F.21 - Differential Costs for Stacked

Waste Emplacement ............. C-61

C.30 Revised DEIS Table F.22 - Differential Costs for Waste

Segregation ........ C-63

C.31 Revised DEIS Table F.23 - Differential Costs for

Decontainerized Disposal .................... C-64

C.32 Revised DEIS Table F.24 - Differential Costs for In-Situ

Dynamic Compaction of Compressible Waste .................. C-66
LIST OF TABLES

Page

C.1 Revised DEIS Table Q.1 - Administrative Costs During

Siting, Licensing and Construction ........................ C-12

C.2 Revised DEIS Table Q.4 - Reference Disposal Facility

'Payroll .... C-13

- C.3 Revised DEIS Table Q.5 - Reference Facility Operational

Monitoring Program ................. C-14 '. 

* . . F... . . . . .. .. ,

-C.4 Revised DEIS Table Q.7'-'Estimated Closure Costs - Low

Scenario ..... C-16

C.5 Revised DEIS Table Q.8 - Estimated Closure Costs'- High

Scenario . C-18

C.6 Revised DEIS Table Q.9 - Personnel Requirements for

Institutional Control .. C-20

C.7 Revised'DEIS Table Q.11 - Estimated Long-Term'

Environmental Monitoring Activities ....................... C-21

C.8 Revised DEIS Table Q.12 - Estimated Annual Institutional

Control Base Costs .............. C-22

C.9 Revised'DEIS Table Q.13 - Small to Moderate Water

Accumulation Costs ......................................... C-24

C.10 Revised DEIS Table Q.14 - Pumping, Processing, and

Solidifying Costs for One Million Gallons of Contaminated

Liquid Per Year ........................................... C-26

C.l1 Revised DEIS Table Q.15 - Site Restabilization Program.... C-28

C.12 Revised DEIS Table F.4,- Differential Costs for Deep

Trench Disposal ................-... ' ' .' C-29

C.13 Revised DEIS Table F.5'-iDifferential Costs for'Thicker

Trench Covers ......... C-32

C.14 Revised DEIS Table F.6 - Differential Costs for'Increasing

the Distance Between the Waste and the Top of- the Disposal

Cell . .. ............. 'C-33

C.15 Revised DEIS Table F.7 - Differential Costs for Layering

Operations .........-... ... C-35
I I!D I t

TABLE OF CONTENTS (Continued)

Page

C.33 Revised DEIS Table G.16 -Unit'Rates for Impact Measures.. C-68

C.34 Reprinted DEIS Table D.11 - Group 1: Untreated Isotopic

Concentrations .......... C-72

C.35 Volume Percent and Average Concentration (Ci/ft3) in

Range . C-73

C.36 Distribution of Gross Activity in LWR Process Waste

Streams .... C-74

C.37 Revised Waste Processing Indices .......................... .C-76

C.38 Revised Waste Form, Processing, and Volume Change Indices

for Waste Spectrum 1 . C-77

C.39 Revised Waste Form, Processing, and Volume Change Indices

for Waste Spectrum 2 . C-79

C.40 Revised Waste Form, Processing, and Volume Change Indices

for Waste Spectrum 3 . C-81

C.41 Revised Waste Form, Processing, and'Voilume Change Indices

for Waste Spectrum 4 . C-83

C.42 Waste Form, Processing, and Volume Change Indices for

Waste Spectrum 5 . C-86

C.43 Waste Form, Processing, and Volume Change Indices for

Waste Spectrum 6 ........................................... C-88

C.44 Wastes from Clean-up of MOX Research Facilities ............ C-92

C.45 Estimated Annual Waste Volumes and RadionuclideConcentrations Generated from Assumed Operation'of a 3,000 MTHM

Spent. Fuel Storage Facility . C-96

C.46 Waste Streams From Reference 2,000 MTHM/yr Fuel Reprocessing

Plant . C-98

C.47 Waste Streams From Reference 400 MTHM/yr MOX Fuel

Fabrication Plant .............................. C-102

C.48 Pathway Dose Conversion Factor 1 .......................... C-112

C.49 Pathway Dose Conversion Factor 2 .......................... C-113

C.50 Pathway Dose Conversion Factor 3 ........................... C-114

C.51 Pathway Dose Conversion Factor 4 .......................... C-115
-TABLE OF CONTENTS (Continued)

Page

C.52 Pathway Dose Conversion Factor 5 .......................... C-116

C.53 Pathway Dose Conversion Factor 6 ....... ; .................. C-117

C.54 Pathway Dose Conversion Factor.7 .......................... C-118

C.55 Pathway Dose Conversion Factor 8 .......................... C-119

C.56 Waste Streams Considered in Analyses ...................... C-121

C.57 Estimated 1-129 Generation Rates .......................... C-123

C.58 Estimated C-14 Generation Rates ........................... C-124

C.59 Iodine in Sedimentary Rocks ............................... C-125

LIST OF FIGURES

C.1 Revised Waste Classification Test Procedure ............... C-104

C.2 Details of Uptake Pathways ................................ C-l1
APPENDIX C

REVISIONS TO IMPACT ANALYSES METHODOLOGY

1. INTRODUCTION

In the draft environmental impact statement (EIS) on 10 CFR 61, "Licensing

Requirements for Land Disposal of'Radioactive Waste," a description of the

alternatives, cost data, and methodology for calculating impacts was presented

in a number-of appendices to the statement. These appendices included:

o Appendix D:

o Appendix E:

o Appendix F:

o 'Appendix G:

o Appendix H:

Low-Level Waste Sources and Processing Options

Description of a Reference Disposal Facility

Alternative Disposal Technologies

Impact Analysis Methodology

Alternative Analysis Codes

o~' -Appendix J:

6 Appendix Q:

Regional'Case Studies

Calculation of Pre-operational,-Operational,

and Institutional Control Costs

Closure

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Since the publication of the draft EIS, the alternatives, cost data, and

methodology for calculating impacts have been reviewed by the public and-various

comments have'been received.. Based upon these comments as well:as upon review

by NRC staff, some modifications to the alternatives, cost data, and impact

calculational methodology have been made. These modifications are summarized

in-the remainder-of this -appendix. - -

The modifications are discussed as follows.- First, modifications to the

methodology used to determine unit-disposal costs 'are discussed. Seco'nd', any

modifications to any cost data which may be contained 'in'the EIS are discussed.

Third, modifications to the waste source data base are discussed. Finally,

modifications to the calculational procedure used to determine radiological

and other impacts are presented.

Listings of the computer codes used.to calculate impact measures for this final

EIS are presented in Appendix D.

Based upon the impact analyses methodology presented in the draft EIS, and upon

the modifications to that impact analyses methodology 'as discussed in this

appendix, the analysis for the final EIS was performed.

2. MODIFICATIONS TO METHODOLOGY USED TO CALCULATE DISPOSAL COSTS

In the draft EIS, the costs for siting, designing, constructing, operating,

and closing a near-surface disposal facility, as well as institutional control

costs, were summarized as three types of-costs: total capital (pre-operational)

costs, total operational costs, and closure and institutional control costs.

C-1
Total capital and operational costs were calculated by first calculating base

capital and operational costs and then applying a series of multipliers to the

base costs as follows: -

Total capital and operational costs = MULT, x CAP-+ MULT2 x OP, where

CAP = direct capital costs in 1980 dollars

OP = direct operational.costs in 1980 dollars

MULT, = interest during construction x contingency x other costs x annual

fixed capital charge x operating life of site x profit

MULT 2 = contingency x profit.

Comments on this approach were received from two commentors. One commentor

(Ref. 1) suggested that a time-value-of-money approach would be more realistic

than a cost-plus-fixed-fee approach, while another commentor (Ref. 2) questioned the use of constant dollars for operational costs and inflated dollars

for closure and long-term care costs. These comments are reasonable, yet there

are a couple of points worth remembering. One is that the actual-costs of

operating a disposal facility are very complicated and are furthermore sitespecific, depending upon the manner~in which the facility~was originally

financed as well as upon many other factors. Many of the costs would depend

upon economic-and business decisions-which a disposal facility would make on a

casa basis given the overall economic conditions at the time the decisions are

made. The best can be done here is an approximation which covers the high points.

In addition, one of the reasons that.aperational costs were left in 1980 dollars

wds that although operational costs would tend to rise every year due to inflation,

these inflated costs would rise irrespective of any additional NRC requirements.

In any case, a simplified.present value approach is taken in. the final.EIS to

estimate base disposal charges (prior to consideration of additional-charges

for closure, disposal facility observation, and institutional control). Basically,

the approach inccrporates the concept- that the summation of the yearly discounted

capital expenditures should be equal to the yearly discounted net cash inflows.

For purpose of this. EIS:

PVout PVi where

N PVut = X yearly pre-operational expense

n(1 +dY), nc

ITo + N

PV I yyearly net cash. inflow

in n = 1 + N (1 + d)n

where both the yearly pre-operational expense and the yearly net cash

inflow are functions of time (in), and

N = length of pre-operational period (years)

C-2
IT0 = operating life of the disposal facility (years)

d = discount rate.

The yearly pre-operational expense is the cost required'to site, design,

license, and construct the disposal facility. The net cash inflow for. a given

year is simply the total revenues received for the waste disposal service

minus the operating and fixed costs. Operating costsinclude costs for dis-k

posal trench construction,' personnel salaries, environmental monitoring,-and

so forth.- 'For..this EIS, fixed costs are assumed to include recovery of equity

capital,' amortization of debt capital, and taxes on income.

Calculating the present value of the pre-operational costs involves consideration of the timing of the expenditures. Initially, expenses would involve those

associated with site selection, obtaining environmental samples, and preparation

of environmental reports. Expenses would then shift to those associated with

facility licensing, which could include costs associated with possible hearings

and possible acquisition of additional information. Finally, expenses would

shift to those associated with disposal facility construction, where most of

.the construction is assumed to take place after issuance of the disposal

facility license. For the reference disposal facility, a total base capital

cost of $7.87 million is calculated in 1980 dollars prior to consideration of

contingency and other overhead expenses (see the discussion in the following

Section 3 on "Total Direct Capital Costs"). Assuming that the preoperational

period lasts 5 years, the following approximate yearly capital expenses'are

estimated in 1980 dollars:

Expense

Year (1980 $ x 106)

1 1.2

2 1.2

3 0.75

4 0.75

5 3.97

As for the draft EIS, these base capital costs would be multiplied by a factor

which would consider contingency and other overhead expenses. As in the draft

EIS, a 30% contingency charge is assumed, as well as a 10% charge to cover other

miscellaneous overhead expenses. Combining these two charges results in a multiplier equal to 1.43.

Of these expenses, part would'probably be covered by the firm's equity and part

would be covered through debt financing. Financing for most' utilities, for

example, is generally about half equity-and half debt financing. Financing

for large private companies is often in the range of.75%.equity and 25% debt

financing.

For consistency, the effect of inflation should also be considered. For the

,purposes of this EIS, and given the need to correspond to the currently available

data on waste projections, the fifth year of pre-operational activities is

assumed to correspond to 1980 costs. Earlier pre-operational costs are then

C-3
I TH

deflated yearly. Operational costs are then inflated over the assumed 20 year

life of the disposal facility so that the 20th year of facility operating life

corresponds to the year 2000. This is. equivalent to discounting all costs to

the year 1975. Discounting to 1975 is expected'to result in slightly lower

costs' than would be the'case if a potential applicant instituted a siting. procedure today in 1982 for a new disposal facility, since costs would be discounted

to 1982 rather than.1975. Nonetheless, discounting to 1975 is-believed to give

acceptable results since the main purpose of the EIS is to'compare one' alternative against another rather than to precisely calculate the actual costs of

disposal at a particular existing or new disposal facility.

In any case, PVout may be approximated as follows:

n- - PVout n 1 CAP(n) (1+j) * (1+d) , where

CAP(n) = annual capital charge, including'contingency and overhead costs'($)

j = average inflation rate

d = discount rate.

In this simplified analysis, the yearly net cash inflow is given by the

following:

yearly net cash inflow = revenues - operating expenses - fixed charges.

At an actual disposal facility, an expense would be probably included to cover

costs of a capital nature incurred during operations, a principal component of

which would be heavy equipment replacement. To reduce the complexity of the

analysis in this EIS, however, all heavy equipment is assumed to be leased.

This assumption is expected to somewhat overstate heavy equipment costs compared to such costs at an actual disposal facility.

For this EIS, an average disposal charge ($/m3) over the operating life of the

site is determined, and so the yearly revenues are given by:

0 * VY(n), where

D = average disposal charge ($/m3)

VY(n) = yearly volume of waste received (m3).

An alternative approach could have been to calculate a yearly disposal charge

D(n), where 0(n) would vary in a manner related to (but not necessarily proportional to) the inflation rate. The above should suffice for this EIS, however.

Operating expenses are simply given as the yearly charge in 1980 dollars as

appropriately inflated for the year considered. Total operating expenses over

the operating life of the site are then given by:

ITo + 5 nI OPY(n) * (1 + j) where

n = 6

C-4
OPY(n) = total (base plus contingency) operating costs for the year (n)

"Fixed charges include recovery of equity and debt capital as well as taxes on

income. 'Annual capital recovery costs are given by'the product of the capital

recovery factor (CRF) with the'total Investment (TCAP), or CRF x TCAP. The

capital recovery factor is given by:

CRF = d (1 + d) ITo (1 + ITo (1 +d) -1

The total

TCAP

TCAP

CAPE

investment is given by:

= CAPE + CAPD * (1 + id), where

= total investment

= equity portion of capital

5 = I EDR * CAP(n) * (1 + j)n-5

n=1

CAPD = debt portion of capital

5 = 1 (1 - EDR) * CAP(n) * (1 + j)n-5

n=1

id = cost of debt (%)

EDR = fraction of financing provided by equity.

For this EIS, the yearly tax on'income is assumed to be given by:

TAX(n) = TR * IGNI(n)) - IDP - DEPY(n)), where

TR = TS + TF * (1 TS)

TS = state and/or local tax rate

GH

TF = federal income tax rate

1I(n) = gross net income 5

= D * VY(n) - OPY(n) * (1 + j)

IDP = interest component of the yearly return on debt i

= (CAPD/ITo) * id

'Y(n) = yearly depreciation of depreciable capital items

C-5

capital

DEF
Typically, the federal tax rate for a corporationwould be in the neighborhood

of 48%, while state/local income tax rates would be in the neighborhood of 6-7%.

It is also possible that some manner of property.tax would: be assessed even

though the disposal facility would be located on land'owned by either the state

or federal government, or some sort of other arrangement would be made so that

the disposal facility operator contributes to the county or local tax base.

This is already the case in at least one existing disposal facility.

Deductions from the gross net income include the yearly interest on recovery of

the debt capital (IDP) and depreciation. For the reference disposal facility,

the depreciable portion of the capital expense is considerably less than the

total capital expense. Much of the capital expense consists of nondepreciable

items such as environmental studies, legal expense, and so forth. For this

EIS, depreciable items are assumed to include roads, fences, buildings, office

equipment, etc., but does not include heavy equipment. No salvage value is

assumed. Depreciation is calculated using a sum-of-the-digits approach. In

this approach, yearly depreciation is calculated-as follows:

DEPY(n) = 2 * DEP * (ITo + 6 - n)/((ITo) * (ITo - 1)), where

DEP = total value of depreciable items in 1980 dollars.

In this equation, n varies from 6 to ITo + 5.

Combining terms and solving for D, one can obtain:

A

A where D= ITo + 5 ,h

(1 - TR) * [ {VY(n) * (1 +d) -n

n = 6

A= n-5 (+ 1 d)-n +

A = CAP(n) (1-' j)

n = 1

ITo + 5

X [CRF * TCAP + (1 TR) * OPY(n) * (1 + j)n-5 -TR *IDPn = 6

TR * DEPY(n)) * (1 + d)n

As an example, the above equation is solved for the reference disposal facility

assuming the above yearly capital expenses (in 1980 dollars) plus the following

parameters:

ITo = 20 years

OPY = $5.46 million

DEP = $2.12 million

j = 9%

EDR = 75%

C-6
TS = 6.5%

TF =48%

MVY = 50,000 mr3/yr

In this exampie, the equation is solved for various values of the cost of debt,

as well as various values of the discount rate (d). The results of this analysis

are as follows:

Cost of Discount' Disposal Costdebt (%) rate (%) $/m= $/fti

10 10 307.70 8.71

10 15 325.20 9.21

10 20 355.50 10.07

12 10 312.40 8.85

12 15 300.00 9.35

12 20 360.40 10.21

14 10 315.80 8.94

14 15 333.50 9.45

14 20 364.00 10.31

16 10 318.40 9.02

16 15 336.20 9.52

16 20 366.80 10.39

As shown, economic factors at the time that the disposal facility is originally

sited, as well as the discount rate chosen, can have a moderately significant

effect on the disposal costs calculated. In economic calculations for an actual

disposal facility, the disposal facility operator would choose a value for the

discount rate which would result in the desired compensation for his efforts.

Economic calculations by others for other types of (non-nuclear) businesses

have often assumed a discount rate of 10%. The actual discount rates' used by

existing disposal facility operators'are considered proprietary business information.:' However, as discussed in the draft EIS, NRC staff regard operating a

disposal facility as a high risk business venture. One of the commenters on

the draft EIS, who is an operator of an-existing disposal facility, agreed with

this statement and stated in his 'comments that the discount rate used should

consider this high level of risk. A 10% discount rate is, therefore,'considered

by NRC staff to be unrealisticly low for a low level waste disposal facility.

A discount rate of 15% is assumed for the EIS. A cost of debt of 10% is assumed.

3. MODIFICATIONS TO COST DATA

Based upon comments upon the draift-EIS and upon additional input from these

commenters in clarification of their comments,' .a number of modifications have

been made to the cost data presented in'Appendix Q. 'These modifications are

presented as follows. First, specific changes to assumed 'values are discussed.

Then the results of these changes on direct capital', direct operating, and

closure and institutional costs are-presented.

C-7
Land Acquisition.

One commenter suggested that NRC's assumed cost for land acquisition were too

low (Ref. 1). In the draft EIS, NRC assumed that 200 acres would be purchased,

of which about 140 acres would be actually used for the disposal facility, at

a cost of $1200/acre. The commenter suggested that a disposal facility operator

would actually probably purchase 400-500 acres of land (to allow for contingencies, possible future expansion, or unsuitable portions of land) and that

land costs would be expected to be somewhat higher.

Land acquisition costs are therefore recalculated assuming acquisition of

400 acres at a cost of $1400/acre. This results in land acquisition capital

costs of $560,000 for the reference disposal facility.

Base Personnel Occupations and Salaries. -

In comments on the draft EIS, one commenter'suggested that some of the base

personnel salaries appeared-low (Ref. 1). These comments were clarified in

subsequent conversations with the commenter (Ref. 3). Based upon these conversations, the following modifications were made:

Assumed annual

salary ($ x 1000)

Job Draft EIS Final EIS

Site manager 40 45

Assistant sitemanager 35 40

Operations manager 26 38

QA and safety supervisor -26 30

Office manager 24 38

Waste shipment schedules 16 20

Security personnel 12 18

QA technician 14 25

Radiation safety technician 15 25

In addition, one commenter, who is an operator of a disposal facility, suggested

that the assumed number of personnel at-the reference disposal facility appeared

low (Ref. 1). Based, upon staff discussions with this commenter (Ref. 4), the

number of personnel assumed for the reference facility was raised by 10 over the

70 assumed in the draft EIS. Assumed occupations for these additional personnel

were also based upon these discussions. The additional personnel and annual

salaries are as follows:

Annual salary

Job ($ x 1000)

1 Personnel manager 32

1 Regulatory affairs manager 35

1 Site engineer 35

.2 Junior engineers 24

3 ''Billing/accounting personnel 12

2 Secretarial personnel 9

TO

C-8
Building Costs.

As discussed above, the base-number of personnel at the reference disposal facility has been raised by 10. Since all 10 would be expected'to be administrative

in'nature,,the size of the administration building at the reference disposal.

facility has been increased from.625 m2 (6,725 ft )'to 750 m2 (8,075 ft2). At

an assumed average cost of $35/ft2, 'the cost of the administrative'building is

raised from $235,400 to $282,600. Total building costs were therefore.calculated for the final EIS asfollows: .

Building 1980 $

Administration- '' $ 282,600

Health physics/security 387,500

Warehouse 126,500

Garage 113,000

Waste activities 302,250

Storage shed 8,600

$1,220,450

Environmental Monitoring Costs.

As suggested by a contractor, environmental monitoring costs for the reference

disposal facility were calculated in the draft EIS based upon an assumed average

cost of $50 per sample. This resulted in a yearly environmental monitoring cost

for the reference disposal facility of $26,700 per.year... Some;.commenters'questioned this cost, however, saying that they would expect the costs to be considerably higher (Ref. 1, 5). Upon NRC staff request,' the-bases for these' comments

were provided by the commenters (Ref. 3, 6). Based upon this'input and upon consideration of references 7 and 8, the following sample analysis costs are assumed:

Sample

Type of

Analysis

Unit

,Costs Cs -)

TLD

Atmospheric

Soil and vegetation

.Exposure 12,

Gamma isotopic 165

I-131

Gamma isotopic

Gross alpha

Tritium

235 -

Water : ' Gamma isotopic 200

' ^ Gross alpha

Tritium

*thermoluminescent-dosimeter

This resulted (see

$60,740.

below) in a total yearly environmental monitoring cost of

C-9,
Personnel Monitoring.

In the draft EIS,',the costs for monitoring of site personnel were not included.

These are so included in the'final EIS'based upon data received from a disposal facility operator (Refs. 1, 3). For this EIS, 50 of the 80 base personnel

are assumed to have duties which would require reasonably routine access to

the restricted area of the disposal facility. Personnel monitoring costs

are based upon these 50. The remaining 30 personnel have' duties which are

administrative in nature (e.g., secretarial personnel, billing/accounting personnel) and would rarely need to enter the restricted area.

Yearly personnel monitoring costs per person are assumed to include costs for

12 TLD analyses, 1 whole .body scan, and 2 bioassays per year. Costs per person

are calculated (Ref. 3) to be the following:

Sample Cost/sample ($) Total costs ($)

TLD* analysis 12 144

Whole body scan 200 200

Bioassay lo 200

$544/person

Ithermoluminescent dosimeter

Total Direct Capital Costs.

Total direct capital costs for the final EIS are calculated,

,following items:

to include the

. i

Capital cutlay 1980 $ (X 1000)

1. Site selection

2. Environmental impact studies

3. NRC licensing fees

4. Other licenses and permits

5. Land acquisition (400 acres @ $1400/acre) 6. Corporate administration

7. Construction administration

8. Legal fees

9. Road construction

10. Initial land preparation (40 acres @ $1145/acre) 11. Office and other miscellaneous light equipment 12. Building construction

13. Utilities and supplies during construction

14. Peripheral systems (fencing, lighting utilities

installation, telephone, etc.) 15. Engineering and design (10% of items 9, 12, and 14)

$ 500

600

325

250

560

1,625.25

496.65

1,000

200

45.8

400

1,220.45

175

300

172.05

' $ 7,870.2

C-10
These costs are accumulated over five years and are further assumed to be multiplied by a factor equal to 1.3 x 1.1 = 1.43 to account for contingency and

miscellaneous other overhead costs. Updated costs for land acquisition (item 5)

and building construction (item 12) have been discussed previously. Engineering

and design costs (item 15) have also been updated 'to reflect theincrease in

land acquisition costs. Construction administrat-ion costs have been modified

to be. consistent with the increase in personnel salaries-for some site personnel

as discussed above. Total construction administration costs are calculated to

be $496,650 as calculated in the following Table C.1.

Total Direct Operating Costs.

Total, direct operating costs over 20 years for the final EIS are calculated to

include the following items:

Operating Costs Over 20 years (X 1000)

1. Operations and maintenance (10% of buildings, grounds, 5,360.9

facilities, and light equipment over 20 years)

2.^' Disposal cell materials (58 trenches) 124.2

3.- Heavy equipment 12,228

4. Payroll:

o Base 30,500

o Fringe 3,050

o Overhead 16,775.

5. Corporate administration (@ $300 k/yr) 6,000.

6.^ Legal fees (@ $150 k/yr) 3,000

7.:. Environmental monitoring 1,214.8

8. Personnel monitoring 544

9. Regulatory costs 1,138_

10. Consumables (utilities, fuel, supplies, etc.) 4,000

- (@ $200 k/yr) $83,934.9

Changes from the draft EIS include revised costs for operations and maintenance

(item 1), payroll (item 4), and environmental monitoring (item 7), plus an

additional item 8 reflecting pers'snnel monitoring costs. Revised operations

and-maintenance costs reflect additional capital costs for building construction and land acquisition. Payroll costs include a base salary, a 10% fringe,

and a:50% overhead. The annual reference disposal facility base payroll is

summarized-on the following Table C.2.

Revised costs for the reference facility environmental monitoring program are

summarized in Table C.3. Assumed unit costs per analysis have been discussed

previously. Total costs for analysis of possible traces of. accumulated water

in filled disposal trench sumps are difficult to estimate and have therefore

been estimated in a conservative manner. Costs for trench sump analyses can be

(in effect) considered as a contingency cost. Assuming a total of 58 disposal

trenches constructed over 20 years, this results in approximately 3 trenches

C-li
11-

Table C.1 Revised DEIS Table Q.1 - Administrative

Siting, Licensing, and Construction

Costs During

Corporate Personnel (annual for 5 years):

1 Project Leader

2 Senior Engineers

3 Engineers

2 Clerical

@ 55 k

@ 35 k

@ 24 k

@ 12 k

Costs ($ x 1000)

55.00

70.00

48.00

24.00

$ 197.00

+ 19.70

$ 216.70

+ 108.35

$ 325.05

10 % Fring"

50 % Overhead

Legal Fees (annual for 5 years):

Site Administration (during one year construction period)

1 Site Manager

1 Assistant Site Manager

1 Foreman

1 Site Radiation Safety Officer

1 Contracts Coordinator

1 Radiation Safety Technician

1 QA and Safety Supervisor

1 Customer Service Coordinator

1 Waste Shipment Scheduler

1 Billing/Accounting Personnel

2 Secretarial

@ 45 k

@ 40 k

@ 28 k

@ 35 k

@ 24 k

@ 25 k

@ 30 k

@ 24 k

@ 20 k

@ 12 k

@ 9k

$ 200.00

45.00

40.00

28.00

35.00

24.00

25.00

30.00

24.00

20. 00

12.00

18.00

$ 301.00

+ 30.10,.

$ 331.10

+ 165.55

$ 496.65

I

10 % Fringe

50 % Overhead

C-12
Table C.2 Revised DEIS Table Q.4

Facility Payroll - Reference Disposal

No. Job Annual Salary($) Extended Total($)

Senior Staff

*1 -

. 1

*1

*1

*1

*1-

*1

1

*1

1

^ 1 , .- 1

*1

*1

*1

Site Manager 45,000

Executive Secretary 12,000

Site Radiation Safety Officer -35,000

Assistant Site Manager 40,000

Foreman -: -28,000

Operations Manager 38,000

QA & Safety Supervisor 30,000

Office Manager 38,000

Security Chief 25,000

-Librarian (Records) 12,000

Customer Service Coordinator 24,000

Contracts Coordinator 24,000

-Personnel Manager 32,000

Regulatory Affairs Manager 35,000

Site Engineer 35,000

- 45,000

12,000

35,000 ;

40,000,

28,000

38,000 -

30,000

38,000

25,000 -- 12,000 --,--

24,000 - -

24,000.

-32,000 - :.

35,000

35,000

Support Staff

4 --Waste Shipment Schedulers

5 ::Billing/Accounting Personnel

*4 Security Personnel

6 Secretarial Personnel

*2 Junior Engineers

20,000

12,000

18,000

9,000

24,000

- 80,000

60,000

72,000

54,000

48,000

-1

*3

*8*8

*13

*12

Staff

QA Technicians

Radiation Safety Technicians

Heavy Equipment Operators

Semi-Skilled Laborers

(includes mechanics)

Unskilled Laborers

25,000

25,000

21,000

15,000

75,000

200,000

168,000.

195,000.-

10,000 120,000

80 $1,525,000

*Personnel contributing to annual personnel monitoring costs. ;

C-13
Table C.3 Revised DEIS Table Q.5 - Reference Facility Operational Monitoring Programs

No. of Frequency of -Unit Annual

Sample Description Locations Type Media Analysis Type of Analysis Cost ($) Cost ($)

External Gamma 50 Continuous TLD Quarterly Exposure

Gross Beta-Gamma

12 2,400

Atmosphere 3 Continuous Particulate

Filter

Daily

Particulate

Fi l ter

Charcoal

Cartridge

Weekly*

Weekly*

Gamma Isotopic

1-131

165 25,740

Soil & Vegetation 10 Grab Soil &

Vegetation

Quarterly

e-) .I

Gross Beta-Gamma

Gamma Isotopic

Gross Alpha

Tritium

235 9,400

Offsite Wells

Site Boundary Wells

Disposal Area Wells

5 Grab

10 Grab

H2 0

H2 0

H2 0

Semiannual

Semiannual

Quarterly.

Quarterly

Gamma Isotopic

Gross Alpha

Tritium

Gamma Isotopic

Gross Alpha

Tritium

Gamma Isotopic

Gross Alpha

Tritium

200

200

200

2,000

4,000

15 Grab 12,000

Filled Disposal"

Trench Sumps

As

Constructed

Grab H2 0 Monthly Gamma Isotopic

Gross Alpha

Tritium

200 5,200

*Ahssume52 operating weeks/yr.

**Trench sumps are surveyed on a monthly basis. Analysis would only take place if water was determined to

be present in a sump. Conservatively assuming that analysis takes place 10% of the time that sumps are

surveyed results in an "av3rage" of about 26 analyses/year.
-

constructed per year. If disposal trench sumps are surveyed for water on a

monthly basis, this results in 5133 such surveys over 20 years. Conservatively

assuming for the purposes of the EIS that 10% of the sump surveys results in

sample analyses,' this results in an "average" of 26 such analyses per year.

Personnel monitoring costs are calculated based upon 50 personnel so monitored

per year over a 20 year operating'life 'at-a cost of $544 per'person.

Base Closure Costs.

In this EIS, two possible site closure scenarios are assumed: a low scenario

and a high scenario. Revised costs for these two scenarios are presented in

Tables C.4 and C.5. Revisions from the draft EIS include updated costs for

building demolition, personnel salaries, personnel monitoring, consumables,

and environmental monitoring.

In their comments on the draft EIS, two disposal facility'operators (Ref. 1,9)

commented that they believed that the assumed cost for facility building decontamination and demolition was excessive. Based upon these two comments, decontamination and demolition costs have been reduced from $300,000 to $200,000

for the final EIS. Other costs for personnel salaries, personnel monitoring,

environmental monitoring, and consumables have been revised from the draft EIS

to be-consistent with the earlier revisions to site operational costs.

Base Institutional Control Costs.

In this EIS, annual institutional control base costs are'calculated assuming

that a contractor is hired by the site owner to maintain the site. These costs

include the following:

o administrative costs to the site owner

o contractor personnel costs

o supplies

o equipment

o environmental monitoring

o contractor's fee.

Modifications to the above costs for the final EIS are made for personnel,

supplies, and environmental costs, as well as the contractor's fee. Revised

personnel salaries are summarized in Table C.6. These updated costs reflect

revised salaries for individual occupations as well as yearly personnel monitoring costs. Yearly environmental monitoring costs are summarized in

Table C.7, assuming similar sample analysis costs as previously. However,

atmospheric sampling costs are reduced by $30/sample over that cost assumed

previously to reflect a lesser need to perform I-131 analyses. For the high

and moderate care scenarios, costs for disposal trench sump water analysis are

based upon an assumed 10% of sump surveys being subjected to further analysis.

For the low care scenario, costs are based upon an assumed 1% of sump surveys

being subjected to additional analysis.

Supply costs and the contractor's fee are calculated in the same manner as the

draft EIS. Supply costs are calculated as 10% of the base personnel costs.

The contractor fee is calculated as 10% of the total costs for personnel,

supplies, equipment and monitoring. Total estimated annual institutional

control base costs are presented in Table C.8.

C-15
11ML

Table C.4 Revised DEIS Table Q.7 - Estimated Closure Costs--

Low Scenario -

I. Building Demolition

II. Waste Disposal Materials and Survey

40,000 ft3 = 1133 m3 of waste, need 22,700 m3

disposal space, assuming 50% efficiency.

Assume one 7m X 47m X 8m trench

a) Standpipes

30 ft of. 6" p.v.c. standpipe @ $2.45/ft

2 standpipes per trench = $300/trench

well casings @ $150/pipe = $300/trench

b) French drain

(.6m x .6m x 47m) = 17m3 = 22 yd3

22 yd3 @ $5/yd3

c) Seed and mulch

0.12 acres@ $295/acre

d) Cornermarkers &'monuments

6.67 ft2 x $18. 30/ft2

e) Surveyor

Surveys @ $60/hr

Assume 8 hrs/trench

$200,000

of

$ 547

$ 2,582

$ -35

III. Personnel

1st year: 1 Site Manager

1 Foreman

2 Security

1 Radiation safety officer

1 Radiation safety

technician

5 Semiskilled laborer

2 Unskilled laborer

$ 480

$ 480

$1,2 94

45,000

28,000

36,000

35,000

25,000

75,000

20,000

$264,000

26,400

145,200

$435,600

45,000

25,000

* 15,000

85,000

8,500

46,750

$140,250

Fringe

Overhead

2nd year: 1 Site manager

1 Radiation safety

technician

1 Semiskilled laborer

Fringe

Overhead

Personnel monitoring

16 person-years @ $544/person-year $ 8,704

C-16
Table C. 4 (continued)

IV. Consumables

(10% of base personnel costs)

2 years:

V. Equipment

$ 34,900

1 4WD vehicle

1 Crawler tractor

1 Farm tractor

1 Pan scraper

1 Pickup

24 months

6 months

24 months

12 months

12 months

@ $ 800/mo

@ $4200/mo

@ $ 800/mo

@ $750/mo

@'$750/mo -

19,200

25,200

19,200

48,000

9,000

$120,600

VI. Environmental Monitoring

2 years',@ $60,740/yr $121,480

Total $1,062,828

C-17
Table C.5 Revised DEIS Table Q.8 - Estimated Closure Costs--

High Scenario

I. Building Demolition

II. Waste Disposal (Survey and Materials)

III. Restabilization.

Total disposal area: 86 acres = 348,000 m2

$ 200,000

1,294

a) Strip cap (1 m)

348,000 M3 = 455,000 yd3

b) Vibratory compaction

assume one week per

trench

1 vibratory compactor

3 man crew

c) Replace cap (1.15 m)

400,200/m7 = 523,380 yd3

d) Compact Ca

@$0.55/mJ

e) Vegetate

3-@$5007acre

@ $0.75/yd3 341,250

= 58 weeks

= 13 months, 2 weeks

@ $1,950/mo, $675/wk

@ $15/hr x 40 hr/wk

@ $0.75/yd3

131,100

392,438

220,100

43,000

$1,127,888

IV. Personnel

Year 1: $ 435,600

Years 2-3:

1 Site manager

1 Foreman

1 Radiation safety officer

2 Radiation safety technician

3 Semi-skilled laborer

3 Unskilled laborer

Fringe:

Overhead:

x 2 years

45,000

28,000

35,000

50,000

45,000

30,000

233,000

23,300

128,150

384,450

768,900

140,250

$1,344,750

Year 4:

Personnel monitoring

38 person-years @ $544/person-yr

C-18
Table C.5 (continued)

IV. Consumables

(@ 10% of base personnel costs)

YV. Equipment

$ 81,500

-1 Crawler tractor 6

.* 1 Farm tractor 48

1 Pan scraper 6

* 1 4WD vehicle 48

1 Pickup 36

mo @ $4200/mo

mO @ $800/mo

mo @ $8000/mo

mO @ $800/mo

mo @ $750/mo

25,200

38,400

48,000

38,400

27,000

$ 177,000

'-VI Environmental monitoring

4 years @ $60,740/yr

air, sampler purchase and install

10 samplers @ $900/sampler

- air sampler analyses

10 samplers x 52 samples/yr x $135/sample

2 years @ $70,200/yr

$ 242,960

9,000

140,400

$ 392,360

Total: $3,345,464

C-19
. I 'I!I

Table C.6 Revised DEIS Table Q.9 - Personnel Requirements

for Institutional Control

Level of Effort Personnel

High (6-man crew) 1 Site manager $ 45,000

1 Health physics technician 25,000

3 Semi-skilled laborer 45,000

1 Unskilled laborer 10,000

$125,000

Fringe 12,500

Overhead: 68,750

$206,250

personnel monitoring: $ 3,264

Moderate (4-man crew) 1 Site manager ' $ 45,000

1 Health physics technician 25,000

1 Semi-skilled laborer 15,000

1 Unskilled laborer 10,000

$ 95 000

Fringe :9 SO

Overhead: 52,250

$156,750

personnel monitoring: $ 2,176

Low (2-man crew) 1 Foreman $ 28,000

1 Semi-skilled laborer 15,000

$ 43,000

Fringe : 4,300

Overhead: 23,650

$ 70,950

personnel monitoring $ 1,088

Very Low (1-man) 1 Caretaker $ 20,000

Fringe 2,000

Overhead: 11,000

$ 33,000

personnel monitoring: $ 544

C-20
Table C.7 Revised DEIS Table Q.11 - Estimated Long-Term Environmental Monitoring Activities

High Moderate Low

Sample Unit No. of Annual No. of No. of Annual

Description Cost Loc. Frequency Costs Loc. Frequency Cost Loc. Frequency Cost

TLD*

Atmospheric

12

135

30

3

Soil and

Vegetation

. Offsite

Wells

Boundary

Wells

Disposal

Area Wells

Disposal

Trench Sumps

235 10

200 5

200 10

200 15

200 58

quarterly

daily gross

beta-gamma

weekly gamma

isotopic

* quarterly

semiannual

semiannual

quarterly

monthly

1,440

21,060

10

I

9,400

2,000

4,000

10

2

5

quarterlydaily gross

beta-gamma

weekly gamma

isotopic

semi- l

annual

semiannual

semiannual

semiannual.

semiannual

480

7,020

0

0

0

0

0

0

4,700

800

2,000

6,000

2,400

(10% of

samples)

$23,400

10

2

5

5

58

annual

annual

annual

I

semiannual

semiannual

2,350

400

1,000

2,000

200

(1% of

samples)

$5,950

12,000 15

14,000

(10% of

samples)

$63,900

58

Estimated total

annual costs

*Thermoluminescent dosimeter. , ~. . I
'Tm

Table C.8 Revised DEIS Table Q.12 - Estimated Annual Institutional

Control Base Costs

Contractor Costs ($ x 1000 per year)

Level of

Effort Adm Personnel Supplies Equipment Monitoring Fee Total

High

0-10 150 209.51 12.5 53.4 63.9 33.93 523.24

(high) (high) (high)

11-25 100 158.93 9.5 26.4 63.9 25.87 384.60

(mod) (mod) (high)

26-100 50 72.04 4.3 6.9 23.4 10.66 167.30

(low) (low) (mod)

Moderate

0-10 100 158.93 9.5 26.4 63.9 25.87 384.60

(mod) (mod) (high)

11-25 50 72.04 4.3 6.9 23.4 10.66 167.30

(low) (low) (mod)

26-100 50 33.54 2.0 - 5.95 - 91.49

(care) (nil) (low)

Low

0-10 50 72.04 4.3 6.9 23.4 10.66 167.30

(low) (low) (mod)

11-25 25 33.54 2.0 - 5.95 - 66.49

(care) (nil) (low)

26-100 12.5 33.54 2.0 - 5.95 - 53.99

(care) (nil) (low)

C-22
Institutional Control Contingency Costs.

In the draft DEIS, institutional control contingency costs were calculated for

3 contingencies:

o small to moderate water accumulation problem

o large scale water accumulation problem'

o site restabilization program.

For:the final EIS, costs for these scenarios have been revised based upon updated

cost estimates for personnel salaries, personnel monitoring, and environmental

monitoring. These revised costs are presented in the following Tables C.9,

C.10, and C.11.

Modifications to Cost Analysis for Alternatives to the Reference-Disposal Facility.

Revisions have been made to the cost analysis performed in Appendix F of the draft

EIS for alternative disposal technologies to the reference disposal facility.

Revisions have been made to be consistent with assumptions'and calculations

for the reference disposal facility and are in two areas: (1) revisions to

specific cost parameters, and (2) revisions to the'methodology.usedto calculate

total costs. The former includes revisions to costs for personnel salaries,

consumables, and environmental monitoring. This is to be 'consistent with previous

revised calculations for-the reference'disposal facility. 'Costs for personnel

monitoring have been added. Costs for additional 'land acquisition, which were

included in the draft EIS for some of the alternatives, have been eliminated.

This is because the assumed increase in land acquisition for the reference case

from 200 acres to 400 acres'eliminates'need to purchase additional land for

the-alternatives involving significantly reduced'land'use 'efficiency.

In Appendix F of the draft EIS, capital and operational costs associated with

alternative disposal technologies to the reference facility were presented in

Tables F.4 through F.24. Revised capital and operational costs for these tables

are presented in 1980 dollars in the following Tables'C.12'through C.32.

Similarly to the draft EIS, many of these alternativestwere then selected for

inclusion into the computer codes,;thus providing for further analysis in the

EIS. The capital and operational costs for selected alternatives were converted

into unit rates for use in the codes as summarized in Table:C.33, which is a

revision of Table G.16 of the draft EIS. Unit rates for closure and institutional

control are also listed in Table C.33.

Based upon the data presented in Table C.33, unit disposal costs ($ per m3 of

waste) may be determined using the revised methodology presented in Section 2

of this appendix. The additional capital costs associated with the selected

alternative disposal technologies are assumed to be incurred in the fifth year

of construction. The depreciable portions of the alternative disposal capital

costs are assumed to be equal to the capital costs minus engineering design fees.

These depreciable costs for the selected disposal technologies are as follows:

C-23
Table C.9 Revised DEIS Table Q.13 - Small to Moderate Water

Accumulation Costs

I. Personnel

1 additional semi-skilled laborer:@ $15,000/yr $ 15,0.00

Fringe & Overhead

Personnel Monitoring

Supplies @ 10%

$ 9 750

$ 544

II. Solidification Equipment

Cement solidify into 55 gallon drums

@ 25,000 gallons per year, 1.4 VIF, $2.50/gal

637 drums @ $20/drum

(Price includes equipment, cement, labor & fuel)

III. Disposal Trench Materials Costs

Continuously operated trench for 10 years

(2650 m3 disp. space). Trench dimensions = 8 m x 47 m x 8 m = 3008 m3 = 3934 yd3

$ 62,500

$ 12,740

a) Standpipes

30 ft. of 6" p.v.c standpipe @ $7/ft

2 standpipes per trench @ $210/pipe

standpipe casings @ $150/casing

b) French drain'

(.6m'x .6m x 47m) = 17m3 = 22 yd3

gravel fill'@ $5/yd3

c) Seed and mulch

550.m2 = .14 acres @ $295/acre

$ 420

$ 300

$* 177

$ 40.

d) Cornermarkers and monuments

-Polished red granite: 6.7 ft2 @

e) Surveyor

$60/hr @ 8 hr/trench

$18. 30/ft 2 $ '122"

$ 480.

$ 1,539

$ ~154

Total:

Cost per year:

IV. Disposal equipment

1 panscraper, 6 months @ $8000/mo

pumping equipment, 12 months @ $500/mo

$ 48,000.

6,000

$ 54,000

C-24
Table C.9 (continued)

V. Additional environmental monitoring

10 extra atm. samplers, 52 samples/yr, $135/sample

100 extra water samples/yr. @ $200/sample

Subtotal:

$ 70,200

20,000

$ 90,200

$246,388

VI. Contractor's Fee

10% $ 24 639

Total per yr: $271,027

Total operating costs over 10 years =

Purchase and install 10 atm. samplers

@ $900 apiece = $9,000

I..

$2,710,270

Total cost = $2,719,270

...

.. . . .

e t

; . . .

., A*

. . .

.. ..

. ,

.. . a* ..

.. . ... .

.. . .. .

.. . . . . . .

, . . ..

... . . .

C-25
Table C.10 Revised DEIS'Table Q.14 -. Pumping, Processing, and Solidifying

Costs for One Million Gallons of Contaminated Liquid Per Year

I. Capital Costs

Purchase evaporator

Purchase ion-exchange pre-treatment system

Purchase and install 10 atm. samplers @ $900

apiece

II. Yearly Costs

1) Equipment

Lease pump & hose @ $500/month

2) Labor Costs

2 semi-skilled laborers @ $15,000

2 unskilled laborers @ $10,000

30,000 + 20,000 =

$1,000,000

$ 750,000

9, 000

$1,759,000

$ 6,000

$ 50,000

Fringe

Overhead

Personnel

Supplies

5,000

27,500

2,176

5,000

Monitoring

3) Treatment Costs

Volume reduction factor = 200

Ion exchange 1.E+6 gal/yr @ $0.10/gallon

Evaporate 1.E+6 gal/year @ $0.35/gallon

$ 100,000

$ 350,000

4) Solidification

Solidify 5,000 gallons of concentrated

bottoms per year. Assume cement solidification, with 1.4 VIF, @ $2.50/gallon

and $20 per 55-gallon drum

728 drums

Solidification:

Drum Charge:

$ 12,500

$ 2,545

5) Disposal Costs

7,000 gal solidified waste per year requires

53 m3 of disposal space per year or 530 m3

of disposal space over 10 years. Assume

continuously operated 4 m x 19 m x 8 m trench.

a) Standpipes

30 ft. of 6" pvc pipe @ $7/ft

2 standpipes per trench @ $210/pipe

Standpipe casings @ $150/casing

$ 420

$ 300

C-26
Table C.10 (continued)

b) French drain

(.6m x .6m x 19m) = 7m3 = 9 yd3

gravel fill @ $5/yd3

c) Seed and mulch

154 m2 = 0.04 acre @ $295/acre

$ 72

12

d) Cornermarkers and monuments

Polished red granite: 6.7 ft2 @ $18.30/ft2 $ 122

e) Surveyor

$60/hr @ 8hr/trench

480

Total: $ 1406

Cost per year:

6) Disposal Equipment Lease

1 pan scraper: 12 months @ $800/mo

7) Additional Environmental Monitorinq

10 samplers x 52 samples/yr @ $135/sample

300 extra water samples/yr @ $200/sample

$ 141

$ 9,600

$ 70,200

$ 60,000

$ 130,200

Subtotal: $ 700,662

Contractor's Fee @ 10%

Total Yearly Costs

Total Operating

Costs Over 10 Years:

Total Capital Costs:

Total Costs Over 10 Years

$ 70,066

$ 770,728

$ 7,707,280

$ 1,759,000

$ 9,466,280

C-27
Table C.11 Revised DEIS Table Q.15 - Site Restabilization Program

I. Restabilization

(from Table Q.8) $1,127,888

II. Additional Personnel

1 Foreman

1 Radiation safety officer

1 Radiation safety technician

2 Unskilled laborer

$ 28,000

35,000

25,000

20,000

$ 108,000

10,800

59 400

$ 178 200

$ 356,400

$ 5,440

x2 years

Personnel Monitoring @ $544/person-yr

III. Additional Equipment

0

IV. Additional Supplies $ 21,600

V. Additional Environmental Monitoring

10 samplers @ 52 samples/yr

$135/sample x 2 years

$1,651,728

Contractors Fee: $ 165,173

Purchase and install 10 atm

samplers @ $900/sampler

$1,816,901

9,000

$1,825 ,901*

`If the restabilization program is combined with a moderate to large water

accumulation program, then additional atmospheric samplers are already

included. In this case, total costs = $1,671,461.

C-28
Table C.12 Revised DEIS Table F.4 - Differential Costs

for Deep Trench Disposal

Assumptions:

'-o Total volume input of 1 million m3/20 years, or 50,000 m3/year

o 30 deep trenches (approximate dimensions: 180 m

58 reference trenches

x 30 m x 16m) replace

o Random disposal of waste

o Waste volume capacity of deeper trench = 33,600 m3

o Costs are calculated with and without shoring

ADDITIONAL CAPITAL COSTS

- A. Without Shoring $ 0

B. With Shoring

(1) Increase health physics/security building by 4,000 ft2

@ $45/ft 2

i(2) Increase warehouse bye10,000 ft2 @ $42/ft2

Engineering and Design:

$180,000

250,000

$430,000

$473,000

i

ADDITIONAL OPERATIONAL COSTS

A. Additional Trench Construction Materials

(1) Standpipes and Casings

58 reference trenches @ $670.50/trench

30 deep trenches

56 ft of 6" pvc standpipe @,$2.45/ft

3 standpipes/trench = $411.60/trench

3 standpipe casings @ $150/standpipe = $45C

30 trenches @ $861.60/trench

(2) French Drain

58 reference trenches @ $425/trench

30 deep trenches @ $425/trench

$ 38,889

I/trench

$ 25,848

-$ 13,041

$ 24,650

$ 12,750

-$ 11,900

C-29
.JluffTable C.12 (continued)

(3) Seed and Mulch

1.5 acres/trench @ $295/acre

58 reterence trenches

30 deep trenches'

(4) Corner Markers and Monuments

6.7 ft2 of granite corner markers and monuments

per trench @ $18.30/ft2 = $122/trench

58 reference trenches

30 deep trenches

(5) Surveyor

$60/hr and 8 hrs/trench

58 reference trenches

30 deep trenches

(6) Shoring (optional)

58 reference trenches

30 deep trenches

wall area/trench = 6720 m2 = 72,334 ft2

material charge $2.40/ft2 . 30 trenches x 72,334 ft2 x $2.40

$ 25,665

$ 13 275

-$ 12 390

$ 7,076

$ 3,662

-$ 3,414

$ 27,840

$ 14,400

-$ 13,440

$ 0

$5,208,050

+ $5,208,050

B. Additional Personnel

(1) With No Shoring

1 heavy equipment operator @ $21,000 $ 21,000

Fringe:

Overhead:

2,100

$ 11,550

$ 34,650

$ 693,000

$ 10,880

x 20 yrs

personnel monitoring:

(2) With Shoring

1 heavy equipment operator @ 21,000

5 semiskilled laborers @ $15,000

10 unskilled laborers @ $10,000

21,000

75,000

100, 000

$ 196,000

Fringe:

Overhead:

19,600

107,800

$ 323,400

$6,468,000

$ 174,080

x 20 yrs

personnel monitoring:

C-30
Table C.12 (continued)

C.. Additional Consumables

With no shoring

With shoring

,D. Additional Equipment

1 - drag-line excavator for 240 months @ $8,000/mo

E; Additional Monitoring

'Total additional operational charges

-- With shoring:

Without shoring:

$ - 42,000

$ 392,000

$ 1,920,000

0

$14,107,945

$ 2,566,687

C-31
Table C.13 Revised DEIS Table F.5 - Differential Costs for

Thicker Trench Covers

Assumptions:

o Costs are estimated based upon the equivalent construction costs of

$0.75/yd3 to excavate, haul, and spread earth using scrapers at an average

haul distance of 1,500 ft and an average rate of 5,500 yd3/day

o Fill required = disposal area x cover thickness, where the disposal area =

vol/(EMP x EFF x SEFF); Vol = waste volume (m3); EMP = emplacement efficiency;

EFF = volumetric disposal efficiency (m3/m2); SEFF = surface use efficiency

o Example calculations are developed for Vol = 1,000,000 m3; EMP = 0.5 (random

disposal); EFF= 6.4 m3/M2 (reference trench); SEFF = 0.9 (reference trench);

and a cover thickness = 3m.

ADDITIONAL CAPITAL COSTS $ 0

ADDITIONAL OPERATIONAL COSTS

Excavation, haul, and spread of fill

volume required = 1,000,000/(.5 x 6.4 x .9)

= 347,222 m3/m2 of cover

3 meters cover: 1,041,667 m3 = 1,362,500 yd3

Costs = 1,362,500 yd3 @ $0.75/yd3 $1,021,875

Total additional operational costs $1,021,875

C-32
Table C.14 Revised DEIS Table F.6 - Differential Costs for Increasing the

Distance Between the Waste and the Top of the Disposal Cell

.'Assumptions:

o Costs are calculated on the basis of 1,000,000 m3 of waste randomly

disposed into reference disposal trenches.

o The bottom 4 m (rather than the bottom 7 meters)-is used for waste disposal,

resulting in a reduction in trench waste capacity (50% disposal efficiency)

from about 17,230 m3 to about 9,524 m3. The number of trenches required is

increased from 58 to 105, and the number of disposal trenches that need to

be constructed per year is raised from about 3 to 5-6.

.o The land area commited for disposal is raised from about 87 acre'sto about

157 acres, or an additional 70 acres.

o Additional costs involve additional material costs such as standpipes and

markers, as well as additional land. -Also, since the number of trenches

that must be excavated is increased, additional machinery and personnel

are assumed to be required.

ADDITIONAL CAPITAL COSTS

.$ 0

ADDITIONAL OPERATIONAL COSTS

A. Additional Trench Construction Materials

1. Standpipes and Casing

58 reference trenches @ $670.50/trench $ 38,889

105 reference trenches @ 670.50/trench 70,403

+ $ 31,514

2. Gravel Drain

58 reference trenches @ $425/trench $ 24,650

105 reference trenches @ $425/trench 44,625

+ $ 19,975

3. Seed and Mulch

87 acres'@ $295/acre $ 25,665

157 acres @ $295/acre 46,315

+ $ 20,650

C-.33
Table C.14 (Continued)

4. Corner markers and monuments

58 reference trenches @ $122/trench

105 reference trenches @ $122/trench

$ 7,076

12 810

+ $ 5,734

5. Surveyor

58 reference trenches @ $480/trench

105 reference trenches @ $480/trench

$ 27,840

50,400

+ $ 22,560

B. Additional Personnel

1-heavy equipment operator @ $21,000

Fringe:

Overhead:

$ 21,000

2,100

11,550

x 20 yr

personnel monitoring

$. 693,000

$ 10,880

C. Additional Consumables $ 42,000

D. Additional Equipment

1 - panscraper for 24 mo. @ $8,000/mo $ 1,920,000

E. Additional Monitoring 0

Total additional operational costs $ 2,724,313

C-34
Table C.15 Revised DEIS Table F.7 - Differential Costs for

Layering Operations

Assumptions:

o 10% of the one million m3 (100,000 m3) requires layering

o Layering requires a waste storage building and additional labor

ADDITIONAL CAPITAL COSTS

Building Construction-add 6,000 ft2 storage building @ $20/ft2 $ ;120,000

Engineering and Design $ 12,000

$ 132,000

ADDITIONAL OPERATIONAL COSTS

A. Additional Trench Construction Materials

B. Additional Personnel

1 Radiation.safety technician @ $25,000

1 Semiskilled laborer @ $15,000

1 Quality assurance technician @ $25,000

$ 0

Fringe:

Overhead:

x 20 yrs

. $ 25,000

$ 15,000

$ 25,000

$ 65,000

$ - 6,500

$ 35,750 ----- '-107,250

$2,145,000

$ 32,640

- -$ '-130, 000

0

0

$2,307,640

personnel monitoring

C. Additional Consumables

D. Additional Equipment

E. Additional Monitoring

Total additional operational costs:-

.

C-35
I I [Ills

Table C.16 Revised DEIS Table F.8 - Differential Costs for Silt

Trench Operations (Ten Percent of Waste Volume)

Assumptions:

o About ten percent of 1,000,000 m3 of waste is disposed in slit trenches,

which replace an equivalent volume of randomly disposed waste in reference

trenches.

o Slit trench dimensions: 20m x 3m x 8m, of-which the bottom 7m is used for

aaste disposal. Spacing between trenches = 2m. Disposal efficiency = 50%.

o Slit trench waste capacity = 210 m3 , reference trench waste capacity = 17,230 m,3 . Therefore, 492 slit trenches (disposal volume = 100,320 m3)

replace 6 reference trenches.

o Unit area of slit trench = (22m x 5m) = JJOM 2 = 1184 ft2. Surface area

of 492 slit trenches = 582,528 ft2. Surface area of 6 reference trenches =

6 x (183m x 33m) = 36,234 m2 = 390,057 ft2 = 8.95 acres.

o Use of slit trenches for 10% of waste requires additional 517,518 ft2 =

11.88 acres.

o Construct approximately 25 trenches/yr, or one every 2 weeks

o Assume deletion of standpipe and gravel drain. ; Emplacement

require trench shoring at considerable additional expense.

would otherwise

ADDITIONAL CAPITAL COSTS

Add atmospheric sampler @ $900

Engineering and Design

$ 900

90

$ 990

ADDITIONAL OPERATIONAL COSTS

A. Additional Materials

(1) Standpipes

6 reference trenches @ $670.50/trench

492 slit trenches assume no stand pipes

$ 4,023

0

-$ 4,023

(2) French Drain

6 reference trenches @ $425/trench

492 slit trenches assume no installed drain

$ 2,550

0 . -$ 2,550

(3) Seed and mulch

6 reference trenches x 1.5 acres/trench x $295/acre

492 slit trenches require 12 acres

12 acres x $295/acre

$ 2,655

38540

+$ 88-5

C-36
Table C.16 (continued),

(4) Corner Markers and Monuments

6.7 ft2 of granite corner markers

trench @ $18.30/ft2

6 reference trenches

492 slit trenches

and monuments per

$I 1 732

*. I 60,054

* +$ 59,322

(5) Surveyor.

-$60/hr and 8 hrs/trench

6 reference trenches .- 492 slit trenches

$ 2,880

236,160

+$ 233,280

B. Additional Personnel

1-heavy equipment operator @ $21,000

2-semiskilled laborers @ $15,000

2-unskilled laborers @ $10,000

1-radiation safety technician @ $25,000

l-quality-assurance technician @ $25,000

$ 21,000

30,000

20,000

.. . . 25,000

25,000

$ 121,000

* Fringe: 12,100 . Overhead:. . : 66,550

$ 199,650

x 20 yrs $3,993,000

personnel monitoring $ 76,160

C. Additional Consumables $ 242,000

D. Additional Equipment

E.

l-backhoe for 240 mo @ $4,000/mo

1-40 ton crane for 240 mo @.$4,5SOO/mo

Additional Monitoring

52 sample analyses/yr @ average

$165/sample x 20 years .*-

960,000

: 1,080,000

$2,040,000

1.,

$ 171,600

Total additional operational costs $6,809,674

C-37
Table C.17 Revised DEIS Table F.9 - Dfferential Costs for Caisson

Disposal (Ten Percent of Waste Volume)

Assumptions:

o About ten percent of 1,000,000 m3 of waste is disposed in caissons, which

replace an equivalent volume of randomly disposed waste in reference

trenches.

o Assume caissons consist of 30" concrete culvert pipes 24 ft in length,

placed in slit trenches constructed 15m x 1.5m x 8m, 16 caissons per trench.

Average spacing between trench = 1m.

o Assume deletion of standpipes and gravel drain. Emplacement would otherwise

require trench shoring at considerable additional expense.

o Disposal capacity is 40m3/trench, assuming stacked disposal at 75%

efficiency. Reference trench waste capacity = 17,230m3 . Therefore,

2,585 caisson trenches (disposal volume = 103,400) replace 6 reference

trenches.

o Unit area of caisson trench = (16m x 2.5m) =40 im2 = 430.6 ft2. area of 2,585 caisson trenches = 1,113,100 ft2. Surface area of

trenches = 390,060 ft2.

Surface

6 reference

o Use of slit trenches for 10% of waste requires additional 723,040 ft2 =

16.6 acres.

o Construct approximately 129 caisson trenches, or 2.5/week.

o After waste placement, backfill with concrete (0.6 m thick

plus overburden.

concrete cap)

ADDITIONAL CAPITAL COSTS

(1) 3-atmospheric samplers @ $900 each

(2) increase health physics/security building

by 4,000 ft2 @ $45/ft2

(3) increase garage by 1000 ft2 @ $25/ft2

(4) increase warehouse by 1000 ft2 @$25/ft2

Engineering and Design:

$ 2,700

180,000

25,000

25,000

*$ 232,700

23,270

$ 255,970

ADDITIONAL OPERATIONAL COSTS

A. Additional Construction Materials

(1) Standpipes

6 reference trenches @ $670.50/trench

2585 caisson trenches assume no standpipes

$ 4,023

0

-$ 4,023

C-38
Table C. 17 (continued)

(2) French Drain

6 reference trenches @

2,585 caisson trenches

$425/trench

assume no gravel required

$ 2,550

0

-$ 2,550

(3) Seed and Mulch

6 reference trenches x

2,585 caisson trenches

24 acres x $295/acre

1.5 acres/trench

require 24 acres

x $295/acre $ 2,655

7 ,080

+$ 4;425

(4) Corner Markers and Monuments

6 reference trenches @ $122/trench

2,585 caisson trenches @ $122/trench

$ 732

315,528

+$ 314,796

(5) Surveyor

6 reference trenches @ $480/trench

Surveyor consulting fees @ $120,000/yr

$ 2,880

240,000

+$ 237,120

(6) Concrete Backfill (cap)

fill/trench = (15m x 1.5m x 0.6m) = 17.7 yd3 @ $45/yd3 x 2,585 trenches

13.50 m3 = 17.7 yd3

+$2,054,067

B. Additional Personnel

2-heavy equipment operators @ $21,000

4-semiskilled laborers @ $15,000

2-unskilled laborers @ $10,000

2-radiation safety technicians @ $25,000

1-quality assurance technician @ $25,000

$ 42,000

60,000

20,000

50,000

25,000

$ 197,000

Fringe:

Overhead:

x 20 yrs

19,700

108,350

$ 325,050

$6,501,000

personnel monitoring $ 119,680

C. Additional Consumables $ 394,000

C-39
l slim

Table C.17 (continued)

D. Additional Equipment

2-backhoes for 240 mo @ $4,000/mo $ 1,920,000

2-40 ton cranes for 240 mo @ $4500/mo 2,160,000

+$ 4,080,000

E. Additional Monitoring

156 sample analyses/yr

@ average $165/sample x 20 years $ 514,800

Total additional operational costs $14,213,315

V

C-40
Table C.18 Revised DEIS Table F.10 - Differential Costs for Concrete Walled

Trench (Ten Percent of Waste Volume)

Assumptions:

o About ten percent of 1,000,000 M3'of waste is disposed in walled trenches,

which replace an equivalent volume of waste randomly disposed in reference

trenches

o Walled trench inside dimensions: 12 m x 3 m x 8.3 m, of which the bottom

7.3 m is used for waste disposal. The thickness of walls and slab = 0.3 m.

A 0.3 m-thick gravel base is placed on the bottom of the trench. Spacing

between trenches = 3 m. Disposal efficiency = 75% (stacked disposal).

- o Concrete walled trench waste capacity = 189 m3; reference trench waste

capacity = 17,230 i 3 . Therefore, 547 walled trenches replace 6 reference ! trenches (disposal volume = 103,400 m3).

o Unit area of walled trench = (15.3 m x 6.3 m) = 96.4 'm2 - 1,038 ft2. Surface area of 6 reference tren'ches' 390,060 ft2 = 9 acres. Surface

area of 547 walled trenches = 567,645 ft2'= 13 acres.

o Use of concrete walled trenches for 10% of waste requires an additional

177,585 ft2 = 4 acres

o Construct approximately 27 walled trenches/yr or about one every two weeks.

ADDITIONAL CAPITAL COSTS

(1) add 1 atmospheric sampler @ $900

(2) increase health physic/security building''

by 4,000 ft2 @ $45/ft2

(3) increase garage by 1,000 ft2 @ $25/ft2

(4) increase warehouse'by 1,000 ft2 @$25/ft2

Design and Engineering:

ADDITIONAL OPERATIONAL COSTS

A.- Additional Construction Materials

(1) Standpipes and Casings

6 reference trenches @ $670.50/trench

547 walled trenches with one standpipe/trench

547 trenches @ $223.50/trench

$ 900

$

180,000

25,000

25,000

230,900

23,090

253,990

$ 4,023

$ 122,255

+$ 118,232

C-41
I I I1 IMI

Table C.18 (continued)

(2) Gravel Drain

reference trenches E

547 walled trenches.

= (12m x 3m x 1.3m)

547 trenches x

R $425/trench

= Gravel volume/trench

= 10.8 m3 = 14.13 yd3

14.13 yd3/trench x $5/yd3

(3) Seed and Mulch

6 reference trenches x 1.5 acres/trench x $295/acr547 walled trenches require 13 acres

13 acres @ $295/acre

(4) Corner Marker and Monuments

6 reference trenches @ $122/trench

547 walled trenches @ $122/trench

(5) Surveyor

6 reference trenches $$480/trench

Surveyor consulting fees

(6) Additional Material

Form work

30 m x 8.6m = 258m2 = 2777 ft2/trench. Form

work = $0.68/ft2 for 3 uses prior to replacement

2777 ft2/trench x 547 trenches x $0.68/ft2

$ 2,550

$ 38,636

+ $ 36,086

$ 2,655

$ 2,835

+$ 1,180

$ 732

$ 66,734

+$ -66,002

$ 2,880

$ 240,000

+$ 237,120

$1,032,933

Concrete

124.2 m3/trench = 162.45 yd3 x 547 trenches @ $45/yd3 $3,998,795

Reinforcing Steel

0.74 tons/trench x 547 trenches @ $430/ton

B. Additional Personnel

4-semiskilled laborers @ 15,000

4-unskilled laborers @ $10,000

1-heavy equipment operator @ $21,000

1-radiation safety technician @ $25,000

l-quality assurance technician @ $25,000

$ 174,055

$ 60,000

40,000

21,000

25,000

25,000

$ 171,000

$ 17,100

94,050

282,150

$5,643,000

$ 119,680

Fri nge:

Overhead:

x 20 yrs

personnel monitoring

C-42
Table C.18 (continued)

C. Additional Consumables $ .342,000

D. Additional Equipment

2-40 ton cranes for 240 mo @ $4,500/mo

1-concrete pump for 240 mo @ $5,000/mo

1-backhoe for 240 mo @ $4,000/mo

E. -Additional Monitoring

52 offsite sample analyses/yr @ average

$165/sample x 20 yrs

Total additional operational costs

;$ 2,160,000

1,200,000

960,000

$ 4,320,000

$ 171,600

$16,260,683

- .

. I_ .

C-43
Table C.19 Revised DEIS Table F.11 - Differential Costs for Concrete

Walled Trench (Entire Waste Volume)

Assumptions:

o Disposal of 1,000,000 m3 of waste entirely in walled trenches.

o Walled trench capacity = 189 m3 , requires 5,291 trenches.

o Surface area of 5,291 trenches = 5,492,000 ft2 = 126.08 acres. Surface

area of 58 reference trenches = 3,770,000 ft2 = 87 acres. Use of walled

trenches requires additional 39.5 acres.

o Construct 265 trenches/yr or about 5 trenches/week.

ADDITIONAL CAPITAL COSTS

(1) Add five atmospheric samplers @ $900

(2) Increase health physics/security building

by 8,000 ft2 @ $45/ft2

(3) Increase garage by 2,000 ft2 @ 25/ft2

(4) Increase warehouse by 5,000 ft2 @ $25/ft2

Engineering and Design:

ADDITIONAL OPERATIONAL COSTS

A. Additional Trench Constructional Materials

(1) Standpipes and Casings

58 reference trenches @ $670.50/trench

5,291 walled trenches with one standpipe/trench

5,291 trenches @ $223.50/trench

(2) Gravel Drain

58 reference trenches @ $425/trench

5,291 walled trenches. 5,291 trenches

x 14.13 yd3/trench x $5/yd 3

(3) Seed and Mulch

58 reference trenches x 1.5 acres/trench

@ $295/acre

5,291 walled trenches 126 acres @ $295/acre

$ 4,500

360,000

50,000

$ 125,000

539,500

53,950

$ 593,450

$ 38,889

$1,182,539

+$1,143,650

$ 24,650

$ 373,809

+$ 349,159

$ 25,665

$ 37,170

+$ 11,505

C-44
Table C.19 (continued)

(4) Corner Markers and Monuments

58 reference trenches @ $122/trench

5,291 walled trenches @ $122/trench

* $ 7,076

$ 645,502

+$ 638,426

(5)- Surveyor .

58 reference trenches @ $480/trench

Surveying consultant costs,@ $120,000/yr

$ 27,840

$ 2,400,000

+$ 2,372,160

(6) Additional Material

Formwork - 2777 ft2/trench x 5291 trenches

@ $0.68/ft 2

Concrete - 162.45 yd3/trench x 5291 trenches @ $45/yd3

$ 9,991,313

$38,678,533

Reinforcing Steel - 0.74 tons/trench

@ $430/ton

x 5291 trenches

$ 1,683,596

B. Additional Personnel

3-radiation safety technicians @ $25,000

30-semiskilled laborers @ $15,000

30-unskilled laborers @ $10,000

3-heavy equipment operators @ $21,000

3-quality assurance technicans @ $25,000

1-foreman @ $28,000

$ 75,000

450,000

300,000

63,000

75,000

28,000

$ 991,000

99,100

$ 545,050

$ 1,635,150

$32,703,000

$ 761,600

Fringe:

Overhead:

x 20 yrs

personnel monitoring

C. Additional Consumables $ 1,982,000

D. Additional Equipment

4-concrete pumps 240 mo @ $5,000/mo

3-backhoes for 240 mo @ $4,000/mo

3-40 ton cranes for 200 mo @ $4,500/mo

3-pickup trucks for 240 mo @ $750/mo

1-farm tractor for 240 mo @ $800/mo

$ 4,800,000

2,880,000

3,240,000

540,000

192,000

$11,652,000

C-45
Table C.19 (continued)

E. Additional Monitoring

260 offsite sample analyses/yr

@ average $165/sample x 20 yrs. $ 858,000

Total additional operational costs: $102,824,942

,'

C-46
- -

Table C.20 Revised DEIS Table F.12 - Differential Costs for Grouting

-Assumption:

o Costs based upon 1,000,000 m3 of waste disposed by stacking into

reference trenches. (75% efficiency). Available disposal volume per

trench = 2 x 17,230 m3 = 34,460 m3. At 75% efficiency, have'25,845 m3

of waste and 8,615 m3 of void space per trench (not counting 1 m backfill

between top of waste and trench). 'Disposal of 1,000,000'm 3 of waste by

stacking therefore requires 1E+6/25,845 = 39 trenches having 333,000 M3

' '(1- EFF) of void space. Grout volume therefore equals waste-volume x EF

o Differential costs for stacking included elsewhere

Costs are for grouting alone.

(see Table F.21).

o Case A: cement

Case B: low strength (200 psi) cement)

ADDITIONAL CAPITAL COSTS

(1) Increase garage by 1,000 ft2 @ $25/ft2 $ 25,000

(2) Increase warehouse by 1,000 ft2 @ $25/ft2

Engineering and Design:

25,000

$ 50,000

5,000

$ 55,000

ADDITIONAL OPERATIONAL COSTS

A. Additional Materials

Grout

Case A. 333,000 M3 = 436,000 yd3

Case B. 436,000 yd3 @ $25/yd3

B. Additional Personnel

1-semiskilled laborer @ $15,000

2-unskilled laborers @ $10,000

1-quality assurance technician @ $25,000

@ $45/yd3 $19,619,980

$10,900,000

Fri nge:

Overhead:

x 20 yrs

$ 15,000

20,000

25,000

$ 60,000

6,000

33,000

$ 99,000

$ 1,980,000

personnel monitoring $ 43,520

C. Additional Consumables $ 120,000

C-47
. I WIN

Table C.20 (continued)

D. Additional Equipment

2-cement pumps for 240 mo @ $5,000/mo $ 2,400,000

2-tremie pipe and hose systems 400,000

$ 2,800,000

E. Additional Monitoring $ 0

Total additional operational costs

Case A $24,563,500

Case B $15,843,520

C-48
Table C.21 Revised DEIS Table F.13 - Differential Costs for

Installation of an Engineered Human Intruder Barrier

Assumptions:

o, Costs based upon 1,000,000 m3 of waste randomly disposed int6 reference

trenches. This results in a total disposal area ='vol/(EMP X EFF X SEFF) =

347,000 m2, where EMP 0.5, EFF =-6.4, and SEFF 0.9.

o The engineered intruder barrier is 5.5 m thick and consists of layers of

sand, clay, gravel, cobbles, boulders,'asphaltic concrete, and'topsoil,

and is installed on top of existing 1 m thick backfill and 1 m thick cap.

o The engineered intruder barrier consists of 43,511 yd3 of material per

; trench at an average cost of $6.00/yd3

CAPITAL COSTS:

Increase health physics/security building by 4,000 ft2 @ $45/ft2

Increase garage by 2,000 ft2 @ $25/ft2

Increase warehouse by 1000 ft2 @ $25/ft2

Engineering and Design:

$ 180,000

50,000

25,000

$ 255,000

25,500

$ 280,500

OPERATIONAL COSTS

A. Additional Materials

(1) Standpipes

add 20 ft to each standpipe.

3 standpipes/trench x 20 ft @

58 trenches x

$2.45/ft $ 8,526

(2) Barrier material

43,511 yd3/trench x 58 trenches @ $6/yd3 $15,141,828

B. Additional Personnel

4-heavy equipment operators @ 21,000/yr

4-semiskilled laborers @ $15,000/yr

2-unskilled laborers @ $10,000/yr

2-quality assurance technicians @ $25,000

Fringe:

Overhead:

x 20 yrs

$ 84,000

60,000

20,000

50,000

$ 214,000

21,400

117,700

$353,100

$ 7,062,000

personnel monitoring $ 130,560

C-49
Table C.21 (Continued)

C. Consumables $ 428,000

D. Additional Equipment

2-pan scrapers for 240 months @ $8,000/mo.

1-asphalt paver for 240' months @ $3,775/mo

1-crawler tractors for 240 months @ $4,200/mo

1-vibratory compactor for 240 months @ $6,000/mo

5-dump trucks for 240 months @ $6,000/mo

1-motor grader for 240 months @ $3,200/mo

$ 3,840,000

906,000

1,008,000

468,000

.7,200,000

768,000

$14,190,000

E. Additional Monitoring 0

Total additional operational costs $36,960,914

C-50
Table C.22 Revised DEIS Table F.14 - Differential Costs for Improved Monitoring

Assumptions:

o Improved monitoring consists of 25 additional wells at an average depth of

60 ft, 10 particulate air samplers, and (optional) one automatic runoff

sampler.

o Well construction: '1,500 total feet at'$15/ft.= $22,500.

o - Cost of consulting services for well location selection-= $20,000.

o Purchase and installation of 10 particulate air samplers @ $900/sampler =

$9,000.

o Purchase and installation of automatic runoff sampler $7,000.

o Construction of WEIR for sampler = $10,000.

CAPITAL COSTS

Monitoring systems purchase and installation $ 48,500

Engineering and design fees

Consulting fees

4,850

20,000

$ 73,350

Without runoff sampler $ 54,650

OPERATIONAL COSTS

- A. Additional Trench Construction Materials 0

B. Additional Personnel

1-radiation safety technician @ $25,000

Fringe:

- -- 'Overhead:

. ~~ . ..

' x20 yrs

personnel monitoring

$ 25,000

2,500

13,750

41,250

$ 825,000

$ 10,880

C. Additional Consumables

D. Additional Equipment

E. Additional Monitoring

25 wells, quarterly samples, @ $200/sample

10 air samples, 52 each/yr, @ $165/sample

runoff samples, 52/yr, @ $200/sample

50,000

0

20,000

85,800

10,400

$ 116,200

$ 2,324,000

$ 3,209,880

$ 3,001,880

x 20 yrs

Total additional operational costs:

Without runoff samples

C-51
Table C.23 Revised DEIS Table F.15 - Differential Costs for

Improved Compaction

Assumptions:

o The costs are a function of the area compacted, which is Vol/(EMP x EFF x

SEFF). Costs are estimated based upon 1,000,000 m3 of randomly disposed

waste, where EMP = 0.5, EFF = 6.4 m, and SEFF = 0.9.

ADDITIONAL CAPITAL COSTS

ADDITIONAL OPERATIONAL COSTS

A. Additional Materials

B. Additional personnel

1-heavy equipment operator @ $21,000

$ 0

$W 0

Fringe:

Overhead:

x 20 yrs

personnel monitoring

C. Additional Consumables

D. Additional Equipment

1-vibratory compactor for 240 mo @ $1,950/mo

E. Additional Monitoring

Total additional operational costs

$ 21,000

$ 2,100

$ 11,550

$ 34,650

$ 693,000

$ 10,880

$ 42,000

$ 468,000

0

$1,213,880

C-52
- -

Table C.24 Revised DEIS Table F.16 - Differential Costs for

Improved Thicker Cap

Assumptions:

o Thicker Cap Case A. Two meters of imported clay compacted to 95% of

maximum density.

o Thicker Cap Case B. Three meters of imported clay compacted to 95% of

maximum density.

o Fill required = disposal area x cover thickness, where the disposal area =

Vol/(EMP x EFF x SEFF), and

Vol = waste volume (m3)

EMP = emplacement efficiency

EFF = volumetric disposal efficiency (m3/m2)

SEFF = surface use efficiency

o Example calculation for vol = 1 million m3, EMP = 0.5 (random

EFF = 6.4 m3/M2 (reference trench), and SEFF = 0.9 (reference

disposal),

trench)

ADDITIONAL CAPITAL COSTS $ 0

ADDITIONAL OPERATIONAL COSTS

A. Additional Trench Construction Materials

Case A: 2 meter cap

disposal area = 1,000,000/(.5 x 6.4 x .9) =

347,222 m2. Fill required = 694,444 m3 =

908,333 yd3

Purchase and haul fill @ $3.50/yd3

Case B: 3 meter cap

fill required = 1,041,666m3 = 1,362,499 yd3

Purchase and haul fill @ $3.50/yd3

$ 3,179,165

$ 4,768,747

B. Additional Personnel

1-heavy equipment operator @ $21,000

Fringe:

Overhead:

x 20

$ 21,000

$ 2,100

11,550

$ 34,650

$ 693,000

personnel monitoring $ 10,880

C. Additional Consumables $ 42,000

D. Additional Equipment

1-crawler tractor for 240 mo @ $4200/mo

1-vibratory compactor for 240 mo @ $1950/mo

$ 1,008,000

$ 468,000

$ 1,476,000

C-53
I I IN

Table C.24 (continued)

E. Additional Monitoring $ 0

Total additional operational costs:-

Case A:

Case B:

$ 5,401,045

$ 6,990,627

C-54
Table C.25 Revised DEIS Table F.17 - Differential Costs for

Moisture Barriers

Assumptions:

.0 Costs based upon random disposal of 1,000,000 m3 of waste into 58

reference disposal trenches.

0 Barrier options: A = one bentonite layer

B = one polymer membrane layer

C = one polymer membrane layer plus one bentonite layer

D = two polymer membrane layers

o Bentonite is used as a rate of 4 lbs/ft2

o Costs in addition to those for 2 m-thick compacted clay caps (Table F.16).

ADDITIONAL CAPITAL COSTS $ 0

ADDITIONAL OPERATIONAL COSTS

A. Additional Trench Construction Materials

Two meter thick clay cap (from Table F.16)

Case A 86 acres (3,746,160 ft2) of bentonite

7,492 tons @ $260/ton

Case B 3,746,160 ft2 of 36 mil reinforced hypalon

@ $0.60/ft2

Case C Material Cost of Case A plus Case B.

Case D Twice additional material cost of Case B.

B. Additional Personnel

1-heavy equipment operator @ $21,000

Fringe:

Overhead:

x 20

$ 3,179,165

$ 1,948,003

$ 2,247,696

$ 4,195,699

$ 4,495,392

$ 21,000

2,100

11,550

$ 34,650

$ 693,000

$ 10,880

$ 42,000

personnel monitoring

C. Additional Consumables

D. Additional Equipment

1-crawler tractor for $240 mo @ $4200/mo

1-vibratory compactor for $240 mo @ $1950/mo

$ 1,008,000

$ 468,000

$ 1,476,000

C-55
Table C.25 (Continued)

E. Additional Monitoring $ 0

Total additional operational costs:

Case A: $ 7,349,048

Case B: $ 7,648,741

Case C: $ 9,596,744

Case D: $ 9,896,437

C-56
Table C.26 Revised DEIS Table F.18 - Differential Costs for Use

of a Sand Backfill

Assumptions:

o Costs estimated based upon disposal of 1,000,000 m3 of waste -into

reference disposal trenches.

o Sand backfill is assumed to be procured, trucked to the disposal facility,

and stockpiled for use at an average cost of $2.50/yd3. '

o Costs are calculated for both random and stacked disposal, and include an

equivalent of a 1 m thick backfill;between the waste and the top of the

trench. For random disposal, required sand volume ='1,000,000 i 3 + 58 x

(180 m x 30 m x I m) = 1,313,200 m3. For stacked disposal, required sand

.volume = 333,333 m3 + 39 x (180 m x 30 m x lm).= 543,933

ADDITIONAL CAPITAL COSTS $ 0

ADDITIONAL OPERATIONAL COSTS

A.' - Additional Materials

*:1 - .

Random disposal

1,313,200 m3 = 1,717,666 yd3 @ $2.50/yd3

Stacked disposal

543,933 m3 = 711,464 yd3 @ $2.50/yd3

B. Additional Personnel

C. Additional Consumables

D. Additional Equipment

$ 4,294,164

$ 1,778,661

$ 0

$

$

$

0

0

' E. -Additional Monitoring 0'

*~ I

. I . . . .

Total-additional operational costs:

random disposal

stacked disposal

$ 4,294,164

$ 1,778,661

C-57
-_ -

Table C.27 Revised DEIS Table F.19 - Differential Costs for a Surface

Water Drainage SystemAssumptions:

o Primary system, discharge channel, and run-off monitor installed during facility construction, secondary system installed in stages during

facility operations.

o Primary system runs entirely around 60

2 north-south site access roads. (See

total length)

ha state-owned land plus along

Figure E.11) (system 5200 m in

o Secondary system runs between trenches (along lengths and ends) and carries

discharge to primary system (system 10,900'm in total length).

o Drainage channel carries discharge from primary system to an offsite

publicly owned drainage-channel which empties into a nearby stream.

o Primary system consists of 1/3 section of 24" radius galvanized pipe;

secondary system consists of 1/3 section of 15" radius galvanized pipe;

discharge channel consists of trapezoidal sectioned gravel channel

500 m long. Gravel layer 3.5 m wide and 0.6 in thick.

CAPITAL COSTS

(1) Primary system: 5200 m = 17,061 ft @ $19.43 ft

(2) Discharge channel: gravel (3.5 m x 500m) = 1050m3 =

1,373 yd3 @ $10/yd3

(3) Purchase and install automatic runoff sampler

(4) Construction of WEIR for sampler

$ 331,499

$ 13,730

$ 7,000

$ 25,000

(5) Increase warehouse by 1,000 ft2 @ $25/ft2 $ 25,000

$ 387,229

$ 38,723

$ 425,952

Engineering and Design

Total additional capital costs

C-58
Table C.27 (continued)

OPERATIONAL COSTS

A. Additional Materials

(1) Secondary System

10,900 m = 35,763 ft @ $10.25/ft $ 366,570

(2) System Maintenance Contingency

5 maintenance operations @ $1.19/ft for 52,824 ft

of system $ 314,303

(3) Additional Personnel

1-semiskilled laborer @ $15,000 $ 15,000

2-unskilled laborers @ $10,000 20 000

$ 35,000

Fringe: $ 3,500

Overhead $ 19,250

$ 57,750

x 20 years -X$1,I55,000

personnel monitoring $ 32,640

C. Additional Consumables $ 70,000

D. Additional Equipment 0

E. Additional Monitoring

Offsite sample analysis @ average

$200/sample, 52 samples/yr $ 208,000

Total additional operational costs: $ 2,146,513

C-59
. . lUll

Table C.28 Revised DEIS Table F.20 - Differential Costs

for Weather Shielding

Assumptions:

o Tension structures employed.

o Purchase 3 tension structures having dimensions 36.6m x 190m @ $100/m2 =

$695,400 apiece

o Weather shield moves during operations cost 1.5% of total capital cost and

include costs for temporary help, repairs, etc.

o Costs calculated on basis of 1,000,000 m3 of waste.

CAPITAL COSTS

3 tension structures @ $695,400 apiece

Engineering and Design

OPERATIONAL COSTS

Weather shield moves

55 moves at 1.5% of $2,294,800

$2,086,200

208,620

$2,294,820

$1,893,210

C-60
- - -

Table C.29 Revised DEIS Table F.21 - Differential Costs for

Stacked Waste Emplacement - - :

Assumptions:

-I

o Costs based upon 1,000,000 m3 of waste disposed by stacking into reference

trenches at 75% efficiency. Thesavailable disposal-volume per trench is

34,460 m3. At 75% efficiency, can dispose of 25,845 m3 per trench. The

number of disposal trenches is reduced from 58 to 39.

^ ADDITIONAL CAPITAL COSTS

- iIncrease health physics/security building by 4,000 ft2 @ $45/ft2

I Increase garage by 1,000 ft2@ $25/ft2 -

Engineering and Design'

$ 180,000

$ 25,000

$ 205,000

20,500

$ 225,500

ADDITIONAL OPERATIONAL COSTS

A. Additional Materials

I - ' - .-

1. Standpipes

58 trenches @$670.50/trench

39 trenches @$670.50/trench

$ 38,889

.+j $ 26,150

-$ 12,739

2. French Drain'-

58 trenches with 85 yd3/trench

39 trenches with 85 yd3/trench

@ $5/yd

@ $5/yd

3. Seed and Mulch

58 trenches = 87 acres @ $295/acre

39 trenches = 58.5 acres @ $295/acre

$ 24,650

$ 16,575

-$ 8,075

$ 25,665

$ 17,258

S$ 8,407

$ 7,076

$ 4,758

_$ 2,318

4. Monuments and Markers

58 trenches @ $122/trench

39 trenches @ $122/trench

5. Surveyor

$60/hr @ 8 hrs/trench

58 trenches @ $480/trench

39 trenches @ $480/trench

$ 27,840

$ 18,720

-$ 9,120

C-61
I I lift"

Table C.29 (continued)

B. Additional Personnel

4-Radiation safety technicians @ $25,000

4-Heavy equipment operators @ $21,000

5-Semiskilled laborers @ $15,000

6-Unskilled laborers @ $10,000

1-Quality assurance technician @ $25,000

Fringe:

Overhead:

x 20 yrs

personnel monitoring

C. Consumables

$ 100,000

84,000

75,000

10,000

25,000

$ 294,000

$ 29,400

$ 161,700

$ :485,100

$9,702,000

$ 217,600

$ 588,000

D. Additional Equipment

4-forklifts for 240 months @ $1,000/mo

1-40 ton crane for 240 months,@ 4,500/mo

1-onsite transport vehicle 240 months

@ $2,100/mo

$ 960,000

$ 1,080,000

$ 504,000

$ 2,544,000

E. Additional Monitoring 0

Total additional operational costs: $13,010,941

C-62
Table C.30 Revised DEIS Table F.22 - Differ'ential Costs for Waste Segregation

Assumptions:

o Waste segregation requires additional labor and.additional equipment

o Costs calculated based on 1,000,000 m3 of randomly disposal waste

- -ADDITIONAL CAPITAL COSTS

Add atmospheric sampler @ $900

Engineering and Design

$ 900

90

$ 990

ADDITIONAL OPERATIONAL COSTS

A. Additional Trench Construction Materials

B. Additional Personnel

1-radiation safety technician @ $25,000

1-semiskilled laborer @ $15,000

3-unskilled laborers @ $10,000

1-quality assurance technician @ $25,000

$ 0

Fringe: .

Overhead:

x 20 yrs

$ 25,000

$ 15,000

$ 30,000

$ 25,000

$ 95,000

9,500

52,250

$- 156,750

$ 3,135,000

$ 65,280

$ 190,000

personnel monitoring

C. Additional Consumables

D. Additional Equipment

1-40-ton boom crane for 240 mo. @ $4,500/mo.

1-forklift for 240 mo. @ $1,000/mo

---$ 1,008,000

240,000

$ 1,248,000

E. Additional Monitoring

52 offsite analyses/yr @ $165/sample x20.yrs $ 171,600

Total additional operational costs: $ 4,809,880

C-63
Table C.31 Revised DEIS Table F.23 - Differential Costs for

Decontainerized Disposal

Assumptions:

o Costs based upon decontainerized disposal of lower'activity compressible

unstable waste, assumed to be about 56% of 1,000,000 m3, or 560,000 m3

for waste spectrum 1 (50% disposal efficiency).'

o Operations require additional personnel, increased storage space, increased

facility building sizes and increased airborne sampling.

o Operations. require segregated waste disposal and use of weather shielding;

however, costs calculated here do not include costs for segregation.

CAPITAL COSTS:

1. Add 10 atmospheric samplers @ $900

2. Increase health physics/security building by

8,000 ft2 @ $45/ft2

3. Increase garage by 1,000 ft2 @4$25/ft2

4. Increase warehouse by 1,000 ft2 @ $25/ft2

5. Construct additional storage area covering

6,000 ft2 @ $20/ft2

6. Increase waste activities building

by 6,025 ft2 @ $50/ft2

Engineering and Design

$ .9,000

$ 360,000

$ 25,000

$ 25,000

$ 120,000

$ 301,250

$ 840,250

$ 84,025

$ 924,275

ADDITIONAL OPERATIONAL COSTS

A. Additional Construction Materials

B. Additional Personnel

$ 0

6-Radiation safety technicians @ $25,000

6-Heavy equipment operators @ $21,000

12-Semiskilled laborers @ $15,000

25-Unskilled laborers @ $10,000

2-Quality assurance technicians @ $25,000

$ 150,000

$ 126,000

$ 180,000

$ 250,000

$ 50,000

$ 756,000

$ 75,600

$ '415,800

$ 1,247,400

$24,948,000

$ 554,880

Fringe:

Overhead:

x 20 yrs

personnel monitoring:

C-64
Table C.31 (continued)

*- - C.- Additional -Consumables $ 1,512,000

D. Additional Equipment

1-four wheel.drive vehicle for 240 months @ $800/mo

1-pickup for 240 months @ $750/mo

..2-forklifts for 240 months:@-$1;000/mo.

1-crawler tractor for 240 months @ $4,200/mo

1-vibratory compactor for 240 months @ $1,950/mo

1-;farm tractor.for 240 months @:$2,100/mo

1-onsite transport vehicle 240 months @$2,100/mo

4 192,000

180,000

480,000

1,008,000

468,000

504,000

504,000

$ 3,336,000

E. Additional Monitoring

520 offsite sample analyses per year @ $165/analysis

x 20 years

Total additional operational costs:

$ 1,716,000

$32,066,880

- .1 . "

, -. * ~ i - A. -

i . . ,

C-65
Table C.32 Revised DEIS Table F.24 - Differential Costs for In-Situ

Dynamic Compaction of Compressible Waste

Assumptions:

o Costs based upon dynamic

wastes, or 1,000,000 m3,

consolidation of trenches containing unstable

if no waste segregation is performed.

o Dynamic consolidation costs calculated as if performed by outside firm

under contract.

o Compacted area = Vol/(EMP x EFF) 312,500 m2, where EMP = 0.5 and

EFF = 6.4.

o Disposal area (347,222 m2) requires additional clayey cover averaging

3 meters thick.

CAPITAL COSTS

Add 10 atmospheric samplers @ $900

Engineering and Design:

$ 9,000

$ 900

$ 9,900

ADDITIONAL OPERATIONAL COSTS

A. Additional Materials

1. Additional Clay Soil

3m x 347,222 m4 = 1,041,666

1,362,499 yd3 @ $3.50/yd3

m3 = 1,362,499 yd3

$ 4,768,747

2. Standpipes

Repair one standpipe/trench

58 trenches @ $223.5/trench $ 12,963

B. Dynamic Compaction Costs

1. Dynamic consolidation @ $6.50/M2

312,500 m2 x $6.50/M2 $ 2,031,250

2. Install new fill and compact, move, spread, and

backfill earth into trenches, plus compaction of

1,362,499 yd3 at approximately $2.00/yd3 $ 2,724,998

C-66
Table C.32 (continued)

C. Additional Personnel

2-radiation safety technicians @ $25,000

1-quality assurance technician @ $25,000

Fringe:

Overhead:

x 20 yrs

personnel monitoring

D. Additional Consumables

E. Additional Equipment

F. Additional Monitoring

520 offsite sample analyses

@ $135/analysis x 20 yrs

Total additional operational costs:

$ 50,000

25,000

$ 75,000

7,500 . : 41,250

$ -123,750

$ 2,475,000

-$ 32,640

-$ 150,000

0

1:

-$ 1,404,000

-$13,599,598

.1.

. .. I - .

. . . :1 r4 ' ; -.

. i,  1 -, ,

. .. - .

i I., .. .

. r

.I

. i I :

C-67
Table C.33 Revised DEIS Table G.16 - Unit

Impact Measures

Rates for

Cost Occupational a Energy Use

(thousand Exposure (thousand b

Activity 1980 $) (person-rem) gallons) Units

Capital

Reference Base Case

(total)

Additive AlternativesC

Walled Trench

Stacking

Segregation of Unstable

Waste

Segregation of Chemical

Waste

Layering

Decontainerized Disposal

Hot Waste Facility

Grouting

Intruder Barrier

Extreme Stabilization

7,870 212 Lump Sum

594

226

is Il

I. II.

1 Il Il

1

132

924

260

55

281

10

It It

it II

II It

is ..

Operational

Reference Base Case

Trench (-Cover)

Regular Cover

Other Costs

2,341

1,420

78,760

300

2400

1000

200

100

200

Disposal Vol.

Disposal Area

Lump Sum

Additive Alternativesc

Walled Trench

Stacking

Segregation of Unstable

Waste

Segregation of Chemical

Waste

Layering

Decontainerized

Disposal

Hot Waste Facility

Grouting

Sand Backfill

Cover Options

Thick

Intruder Barrier

Moderate Stabilization

Extreme Stabilization

77,119

13,011

4,810

4,810

23,076

57,262

181,823

73,691

3,270

15,555

106,447

3,496

39,167

700

100

300

100

100 30

100

-100

30

30

400

-200

2550

2400

2400

4800

4800

100

450

800

185

150

300

300

600

Disposal Vol.

Waste Volume

Il Il

Chemical Wast

Vol.

Layered Vol.

Decont. Vol.

Hot Waste Vol

Grout Volume

Sand Volume

Disposal Area

I, I

Il II

of Il

C-68
-

Table C.33 (Continued)

I

-a Cost Occupational Energy Use

(thousand Exposure ' " (thousand

Activity 1980 $) (person-rem) '"gallons) Unitsb

Post-Operational

Closure Period

Regular Closure

Extensive Closure

Institutional Periode

Low Care Level

Years 1-10

Years 11-25

Years 26-100

Medium Care Level

Years 1-10

Years 11-25

Years 26-100

High Care Level

Years 1-10

Years 11-25

'Years 26-100

1,063

3,345

50 0 d

1000

15

60

Lump Sum ,, it

Per Year il II

Il Il

167

66

54

385

167

.91

523f '

385

167

2

2

2

6

'6

6

II

It

II

- it

It

-10

10,

10o 

,. ...

Il II

II. It

(a) Occupational exposures associated with operations other than waste unloading and

disposal.-

(b) Lump sum items' are assumed to'be' independent of''the waste'volume; disposal volume

dependency is for 1 million mr3'of disposal '(not'waste)'volume;'layered volume

dependency is for 1 million m3 of layered waste disposed; analogously, chemical,

decontainerized, hot waste,'grout, and 'sand volume dependencies are for 1 million

m3 of waste/material of concern; disposal area dependency is'for 1 million m2 of

trench cover area.

(c) All these rates for alternatives are incremental rates in addition'to the rates

given for the reference system.

(d) Regular closure is assumed to last 2 years; extensive closure is assumed to

last four years. Both cases assume 5000 person-hours of field work per year in

an average radiation field of 0.05 mR/hr. ur of f w:r p e

(e) These costsare basic costs not considering inflation or interest.. Details

for 'complete' calculation of the institutional period costs,; including consideration of inflation and interest, ,cancbe found in Appendix Q of the draft EIS as

revised by this Appendix.

(f) To this cost, a ten-year annual contingency cost is added whiich depends on the

soil conditions: $439,000 for.medium-permeability-soils, $183,000 for highpermeability soils, and $1,114,000 for low-permeability, soils.

' ' '; . . .

. - l, . .- I :

C-69
- -, , 11112

Technology Cost (thousand 1980 $)

Reference Base Case 3,120

Additive Alternatives

Walled Trench 540

Stacking 205

Segregation of Unstable Waste 0.9

Segregation of Chemical Waste 0.9

Layering 120

Decontainerized Disposal 840

Hot Waste Facility 236

Grouting 50

Intruder Barrier 255

Extreme Stabilization 9

4. MODIFICATIONS TO THE WASTE SOURCE DATA BASE

Relative to the draft EIS, modifications to the waste source data base (presented

in Appendix D of the draft EIS) include the following:

o Use of a distributed source term for certain LWR process wastes.

o Modified waste spectral files.

o Addition of a waste stream representing wastes from clean-up. and

decommissioning of small scale mixed oxide fuel research facilities.

o Estimated radioisotope concentrations in waste streams generated from

possible future fuel storage and recycle activities.

o Other minor modifications.

These are discussed below:

Distributed Source Term.

In the draft EIS, LWR process waste streams included the following streams:

o PWR ion exchange resins (P-IXRESIN)

o PWR concentrated liquids (P-CONCLIQ

o PWR filter sludge (P-FSLUDGE)

o PWR cartridge.filters (P-FCARTRG)

o BWR ion exchange resins (B-IXRESIN)

o BWR concentrated liquids (B-CONCLIQ)

o BWR filter sludge (B-FSLUDGE)

The average concentration of 23 different radionuclides were determined based

upon extrapolations of experimental data as discussed in the draft EIS and

reference 10. These average concentrations, as well as the total concentrations obtained from summing the concentrations over all 23 radionuclides, are

C-70
presented in Tables D.11 and D.27 of Appendix D to the draft EIS. For illustration, Table D.11 is reprinted here as Table C.34. In the final EIS, however,

a distributed source term is used for all ,LWR process streams except filter

cartridges based uponnew.data obtained from a survey -of records of waste. -

shipments to disposal sites (Ref. 11).

Distribution data obtained from the records (in units of Ci/ft3 as directly

obtained from the data) are presented in Table C.35 and show the volume-percent

distribution of gross concentration in LWR-wet wastes.- The records reviewed

to obtain the data-cover waste shipments for the years'1978 and 1979 and include

79% and 77%, respectively,-of the total volume of waste disposed in the country

for the two years considered. Six different LWR waste~streams are shown:- PWR

resins, PWR sludges,'PWR concentrated liquids, BWR resins, BWR sludges, and

BWR concentrated liquids. The concentrations are separated into 14 ranges from

.000005 Ci/ft. to 10+ Ci/ft3. Within each range, the-percentage of the total

volume of the particular stream found to be'within the range is indicated, as

well as the average concentration (in Ci/ft3) of the wastes within the concentration range. Also shown are the'total number of data'points (shipments) found

for each waste stream as well as the total waste volumes. In the table, resins

and sludges are shown as dewatered, while concentrated liquids are shown prior

to solidification.,.

The data obtained' require some interpretation. For-exanmple, the distinction

in the shipment records between'-resins and sludges was often unclear. Some of

the data points were listed as "resins + diatomaceous earth" (counted as sludge)

while others were listed as "powdex resin" (counted as resin). Many'other

potential data points, which were disregarded for purposes of constructing the

table, were described in vague terms such as "solidified product" or:"radwaste

solidified in concrete." Several other potentialidata points (also disregarded)

were listed in the shipment records'as "evaporator bottoms plus dry waste."

Another factor was that the distribution of data points was uneven. 'While over

a thousand data points were available for BWR resin waste, only 10 data points,

for example, were found for PWR sludge.- Given the above, -theresults for-LWR

resins and sludges are also presented in the table:as:combined (resin + sludge)

streams. Support for this action is' indicated by the similar concentration

distribution shown for BWR resins and BWR sludges.-

Based upon this data, and converting from Ci/ft3 to Ci/m3, the distribution of

gross radioactivity in LWR resins, filter'-'sludge', and concentrated liquids was

taken to be as shown in'Table.C.'36. 'Concentrations of individual radionuclides

in each rangeiare'obtained by first determining'the-ratio'of the average activity

in a range to the'activity obtained from the sum of the' 23 individual radionuclides (e.g., in Table C.34, the summed activity for PWR ion exchange resins

is 3.36E-2 Ci/m3). This ratio is then multiplied by the individual radionuclide

concentration listed. For example, 22.1% of PWR resins have a gross activity

in the range of 0.01 to 0.05 Ci/ft3. The concentration of Co-60 in this range

is taken to be (.85/3.36E-2) x 4.53 E-3 '0.11'Ci/mS. This procedure, which

assumes a fixed'fractional distribution of individual radionuclides within each

range, is conservative (by an approximate-factor of-between 'land 2) since it

disregards the contribution of many short-lived radionuclides.

The use of this data on waste activity distributions in the impact analyses

methodology and computer codes is presented in Section 2, Appendix D, of this

final EIS.

C-71
Table C.34- Repri.nted DEIS Table D.11 - Group 1: Untreated Isotopic Concentrations (Ci/m 3)

P-IXRESIN P-CONCLIQ P-FSLUDGE P-FCARTRG B-IXRESIN B-CONCLIQ B-FSLUDGE

TOTAL 3.36E-02 1.09E-01 1.06E+00 1.86+00 4.63E+00 2.77E-01 5.24E+OO

H-3 2.66E-03 3.45E-03 2.59E-03 1.15E-03 1.92E-02 6.24E-04 1.26E-02

C-14 9.74E-05 1.27E-04 9.55E-05 4.25E-05 1.19E-03 3.89E-05 -7.78E-04

FE-55 2.34E-03 2.27E-02.. 3.10E-01 5.55E-01 9.48E-01. 7.60E-02 1.44E+O0

NI-59- 2.79E-06 2.71E-05 3.71E-04 6.60E-04 9.80E-04 7.85E-05 1.49E-03

CO-60 4.53E-03 4.40E-02- 6.OOE-01 1.07E+00 1.59E+00 1.27E-01 2.41E+OO

NI-63 8.61E-04 8.36E-03' 1.14E-O1 2.04E-01 2.15E-02 1.72E-03 3.25E-02

NB-94- 8.84E-08 8.58E-07' 1.17E-05 2.09E-05. 3.09E-05 2.48E-06 4.70E-05

SR-90 1.94E-04 2.52E-04' 1.89E-04 8.40E-05 3.64E-03 1.18E-03 2.37E-03

TC-99 8.23E-07 1.07E-06 8.03E-07 3.58E-07 7.65E-05 2.50E-06 5.OOE-05

I-129 2.44E-06 3.16E-06 2.37E-06 1.06E-06 2.04E-04 6.65E-06 1.33E-04

CS-135 8.23E-07 1.07E-06 8.03E-07 .3.58E-07 7.65E-05 2.50E-06 5.OOE-05

CS-137 2.19E-02 2.85E-02 2.14E-02 9.54E-03- 2.04E+00 6.65E-02 1.33E+O0 -

U-235 4.71E-08 6.15E-08 1.46E-07 3.64E-07 5.33E-08 3.44E-08 3.32E-07

U-238 3.71E-07 4.84E-07 1.15E-06 2.87E-06 4.20E-07 2.71E-07 2.61E-06

NP-237 9.06E-12 1.18E-11 2.81E-11 7.02E-11 1.02E-11 6.61E-12 6.38E-11

PU-238 2.60E-05 5.12E-05 4.76E-05 2.51E-04 8.34E-05 1.99E-04 4.66E-04

PU-239/240 1.82E-05 3.31E-05 1.55E-04 3.80E-04 5.34E-05 9.43E-05 --2.36E-04

PU-241 7.94E-04 1.44E-03 6.75E-03- 1.66E-02 2.60E-03 4.60E-03 1.15E-02

PU-242 3.99E-08 7.25E-08 3.39E-07- 8.34E-07 1.17E-07 2.06E-07 5.18E-07

AM-241 1.87E-05- 2.99E-05 2.64E-04 1.64E-04 2.32E-05 1.20E-04 1.56E-04

AM-243 1.26E-06 2.02E-06 1.78E-05 1.1OE-05 1.57E-06 8.10E-06 1.05E-05

CM-243 9.92E-09 1.17E-08 3.10E-07 1.93E-07 2.70E-08 2.59E-07 2.97E-07

CM-244 1.38E-05 1.92E-05 1.77E-04 1.10E-04 1.82E-05 2.05E-04 2.24E-04

c,
Table C.35 Volume Percent and Average Concentration (Ci/ft3) in Range

wC

PWR RESIN BWR RESIN -PWR RESIN PWR SLUDGE PWR CONC LIQ BWR RESIN BWR SLUDGE BWR CONC LIQ + SLUDGE + SLUDGE

Range (Ci/ft3) Vol% Conc. Vol%,- Conc Vol% Conc Vol% Conc Vol% Conc Vol% Conc Vol% Conc Vol% Conc

.000005 - .00001 0.2 .0000071 0.1 .0000071

.00001 - .00005 0.8 .000032 0.4 .000048 0 -- 0.7 .000032 0 -

.00005 - .0001 5.2 .000064 ' 0.6 .000068 0.2 .000059 1.2 .000060 4.8 .000064 0.4 .000060

.0001 - -.0005 8.4 .00025 ' a 4.3 .00033 3.7 .00028 3.5 .00025 7.5 .00027 '7.8 .00025 3.7 .00027

.0005 - -.001 5.9 .00071V 8.1' .00071 9.1 '.00067 3.2 .00061 1.1 .00092 0 - 6.1 .00071 2.9 .00070

.001- - -.005' 15.5' .0026 67.8 .0019 28.6' .0028 9.7 .0030 19.4 .0028 45.7 '.0030 .19.3 .0025 11.4 .0029

.005 - .01 '' 8.2 - .0074 9.3 '.0076' 20.4' .0077 7.2 .0076 7.3 .0072 22.3 .0072 8.3 .0074 7.2 .0075

.01 ' --. 05 23.0-- .024 10.9 .018'' 30.4 ; .024 31.0 .024 ^ 29.0 .025 *8.8 .027 ''22.1 :'.024 30.6 .024

.05 - .1 8.9 .074 3.9 .084 3.2 .067 11.6 .076 12.3 .070 6.1 .075 8.5 .074 11.8 .075

.1 - .5 15.4'- .22 2.6' .16 26.9 .21 20.0 .21 9.7 .15 14.3 .21 25.7 .21

.5 - 1.0 4.2 .71 0.1 .51' 3.6 .72 3.8 .75 3.9 .71 3.6 .73

1.0 - 5.0 3.5- 2.08' 0.3 2.45 2.4 1.69 2.3 1.81 3.2 2.08 2.4 1.72

5.0 -10 0.9 7.37 { . - 0.1 7.17 - 0.8 7.37 0.1 7.17

10+ 0.2 11.19 -. . . .0.1 13.08 - 0.2 11.19 0.1 13.08

Data Points (1818) 254 10 286 - 1024 181 - - 63 . 264 1205

Total Volume (ft3) 39,924 . 3121 55,081 .142,097 30,044 71,790 43,045 172,141
Table C.36 Distribution of Gross Activity in LWR Process Waste Streams

Range P-IXRESIN P-CONCLIQ P-FSLUDGE B-IXRESIN B-CONCLIQ B-FSLUDGE

Cf/ft3 . Cf/M 3 Vol% Conc VolX Conc VolX Conc Vol% Conc VolX Conc Vol% Conc

.000005 - .00001 .00018 - .00035 0.1 .00025 0.1 .00025

.00001 - .00005 .00035 - .0018 0.7 .0011 0.4 .0017 0.7 .0011 0 - 0 -

.00005 - .0001 .0018 - .0035 4.8 .0023 0.6 .0024 4.8 .0023 0.4 .0021 0.4 .0021

.0001 - .0005 .0035 - .018 7.8 .0088 4.3 .0012 7.8 .0088 3.7 .0096 7.5 .0095 3.7 .0096

.0005 - .001 .018 - .035 6.1 .025 9.1 .024 6.1 .025 2.9 .025 0 - 2.9 .025

.001 - .005 .035 - .18 19.3 .088 28.6 .099 19.3 .088 11.4 .10 45.7 .10 11.4 .10

.005 - .01 .18 - .35 8.3 .26 20.4 .27 8.3 .26 7.2 .26 22.3 .26 7.2 .26

.01 - .05 .35 - 1.8 22.1 .85 30.4 .84 22.1 .85 30.6 .86 8.8 .96 30.6 .86

.05 - .1 1.8 - 3.5 8.5 2.61 3.2 2.37 8.5 2.61 11.8 2.65 6.1 2.63 11.8 2.65

.1 - .5 3.5 - 18 14.3 7.47 2.6 5.65 14.3 7.47 25.7 7.38 9.7 5.33 25.7 7.38

.5 - 1 18 - 35 3.9 25.02 0.1 17.97 3.9 25.02 3.6 25.67 3.6 25.67

1 - 5 35 - 180 3.2 73.28 0.3 86.55 3.2 73.28 2.4 60.63 2.4 60.63

5 * 10 180 - 350 <0.8 260.34 0.8 260.34 0.1 253.17 0.1 253.17

10+ 350+ 0.2 395.17 0.2 395.17 0.1 461.96 0.1 461.96.

-P
Modified Waste Spectral Files

Since publication of the draft EIS, some relatively minor modifications have

been made to the waste spectral files (for background, see sections 5.1 and

5.2 of Appeendix D 'of the draft EIS.).' 'These modifications have been made to

allow increased flexibility and expanded consideration of the use of high

integrity containers (HIC). _.These [include changes to the waste stability index

(18) and waste processing index (110) for some of the waste streams, as well

as the addition of a fifth and sixth waste spectrum.

For the draft EIS, the waste stability index (I8) could have two values: zero

or one. A value I8=0 signified an unstable waste stream while a value I8=1

signified a stable waste stream. For the final EIS, I8 may have the following

values:

Index Value Meaning

0 Unstable waste form

1 -. Inherently stable waste form

2 Stabilized by placement into HIC

3 'Stabilized by another means

As indicated above, all index values greater than 0 indicate a stable waste

form. However, 'the revised'values'provide some additional information as to

how stability has been achieved and could be used, for example, if one wished

to consider a time limit for waste stability. An "inherently" stable waste

form is one in-which either the waste form itself may be considered stable or

current packaging techniques typically already achieve a stable waste form.

An example'of an"inherently" stable waste form is waste solidified in a media

such as cement or vinyl ester styrene. A value of I8=2 indicates that stability

is achieved through placement of thiewaste into a high integrity container (HIC).

A value of I8=3 indicates that-processing is performed to achieve stability in

addition to current waste packaging techniques and other than solidification

or placement into an HIC. An example would be a waste package containing miscellaneous'activated-metals' in which'_'the6inters'tital voids are filled with an inert

incompressible material such as sand.

In the same vein, the values assigned to the waste processing index (110) have

been modified to allow consideration of stabilization using an HIC or by other

means. As before, the waste processing index is a four digit number of which

the first digit signifies processing resulting in volume reduction, the second

digit signifies the type of solidification agent used, the third digit indicates

the location of the processing activity, and the fourth digit signifies whether

incineration is performed. The modified waste processing index adds two potential values to the second (solidification) digit as shown in Table C.37.

The modified waste spectral file for each of the four waste spectra considered

in the draft EIS are presented in the following Tables C.38 through C.41. These

modified spectral files reflect the modifications to the I8 and I10 indices as

discussed above.

C-75
Table C.37 Revised Waste Processing

Indices

Value Meaning

First Digit

Second Digit

Third Digit

Fourth Digit

o No Volume Reduction

1 Regular Compaction

2 Improved Compaction

3 Hydraulic Press

4 Evaporation

5 Pathological Incineration

6 Small Calciner

7 Large Calciner

o No Solidification

1 Solidification Scenario A

2 Solidification Scenario B

3 Solidification Scenario C

4 High Integrity Container

5 Stabilize by another means

o No Processing

1 Processing at the Generator

2 Processing at the Disposal Site

O No Incineration

1 Urban Environment

2 Rural' Environment

C-76
Table C.38 Revised Waste Form, Processing, and Volume -

Change Indices for Waste Spectrum 1

-Waste

Stream VRF

Flam i:Disp Leach 'Chem''Stab

VIF I4 I5 I6 I7 I8

:. Acc -Process

I9. ,I10

-'P-IXRESIN

P-CONCLIQ

-':P-FSLUDGE

P-FCARTRG

B-IXRESIN

B-CONCLIQ

B-FSLUDGE

P-COTRASH

P-NCTRASH

B-COTRASH

B-NCTRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

N+LOTRASH

F-PROCESS

U-PROCESS

I-LQSCNVL

I+LQSCNVL

I-ABSLIQD

I+ABSLIQD

I-BIOWAST

I+BIOWAST

N-SSWASTE

N-LOWASTE

1.00

1.00

1.00

1.00

1. 00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.40

:1.00

1.00

1.00

.1.40

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

3.00

3.00

3.00

3.00

1.92

1.92

1.00

1.00

2

1

1

2

2

1

1

3

0

3

0

3

0

3

3

2

2

3

3

0

0

3

3

3

3

2

2

0

3

1 1 0 0

1 2 0 1

3 100

'2 1 0 0

1 1 0 0

1 2 0 1

3 1 0 0

2 1 0 0

O 1 0 0

2 1 0 0

0 1 0 0

2 1 0 0

0 1 0 0

2 1 0 0

2 1 0 0

2 1 0 0

2 1 0 0

2 1 0 0

2 1 0 0

3 1 0 1

3 1 0 1

3 1 1 0

3 1 1 0

3 1 1 1

3 1 1 1

3 1 1 0

3 1 1 0

3 1 0 1

3 1 1 0

1 ''0010

1 -'0110

1 '0010

1 0110

1 0010

1 0110

1 0010

1 0000

2 0000

1 0000

2 0000

1 0000

2 0000

1 0000

1 0000

1 0000

1 0000

1 0000

1 0000

1 0000

1 0000

1 0010

1 0010

1 0010

1 0010

1 0010

1 0010

1 0000

1 0000

C-77
I line

Table C.38 (Continued)

Waste Flam Disp Leach Chem Stab Acc Process

Stream VRF VIF I4 15 I6 I7 I8 I9 I10

N-NFRCOMP 1.00 1.00 0 0 1 0 0 2 0000

L-DECONRS 1.00 2.00 2 0 4 1 1 1 0310

N-ISOPROD 1.00 1.30 1 1 3 1 0 1 0210

N-HIGHACT 1.00 1.00 0 0 1 0 0 3 0000

N-TRITIUM 1.00 1.00 3 3 1 1 1 1 0000

N-SOURCES 1.00 1.00 0 0 1 0 1 2 0000

N-TARGETS 1.00 1.00 0 0 1 0 1 1 0000

C-78
Table C.39 Revised Waste Form, Processing, and Volume

Change Indices for Waste Spectrum 2

Waste

..Stream

P-IXRESIN

P-CONCLIQ

P-FSLUDGE

?P-FCARTRG

B-IXRESIN

B-CONCLIQ

B-FSLUDGE

P-COTRASH

P-NCTRASH

B-COTRASH

B-NCTRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

N+LOTRASH

F-PROCESS

U-PROCESS

I-LQSCNVL

I+LQSCNVL

I-ABSLIQD

I+ABSLIQD

I-BIOWAST

I+BIOWAST

N-SSWASTE

N-LOWASTE

L-NFRCOMP

I .

VRF VIF

1.00

6.00

1.00

1.00

1.00

2.40

1.00

2.00

1.00

2.00

1.00

1.50

1.00

2.00

4.00

1.50

3.00

2.00

4.00

1.00

1.00

1.28

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.65

1;82

1.65

1.00

1.65

1.56

1.65

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

3.00

3.00

1.65

3.00

1.92

1.92

1.00

1.00

1.00

Flam - Disp

14 15

1 - 1

1 1

1 1

1 1

1 1

1 1

1 1

3 2

O 0

3 2

0 0

3 2

O 0

3 2

3 2

2 2

2 2

3 2

3 2

0 3

0 3

3 3

3 3

3 1

3 3

2. 3

2 3

0 3

3 3

0 .0

Leach Chem Stab Acc Process

16 I7 18, 19 I10

3 0 1;' 1 0210

3 0 1. 1 .74210

3 0 1 1 0210

3 O :1 1 0210

3 0 1 1 -0210

3 0 1 1 0420

3 0 1 1 0210

1 0 0 1 1010

1 0 3 2 0510

1 0 0 1 1010

1 0 0 2 0510

1 0 0 1 1010

1 0 0 2 0000

1 0 0 1 1010

1 0 0 1 2020

1 0 0 1 1010

1 0 0 1 2020

1 0 0 1 1010

1 0 0 1 2020

1 0 1 1 0000

1 0 1 1 0000

1 1 1 1 1010

1 1 0 1 0210

3 1 1 1 0210

1 1 1 1 0010

1 1 0 1 0010

1 1 0 1 0010

1 0 1 1 0000

1 1 0 1 0000

1 0 3 2 0510

.C-79
J

Table C.39 (Continued)

Waste Flam Disp Leach Chem Stab Acc Process

Stream VRF VIF I4 I5 I6 I7 I8 I9 I10

L-DECONRS 1.00 2.00 2 0 4 1 1 1 0310

N-ISOPROD 1.00 2.00 1 0 4 1 1 1 0310

N-HIGHACT 1.00 1.00 0 0 1 0 3 3 0510

N-TRITIUM 1.00 1.00 3 3 1. 1 1 1 0000

N-SOURCES 1.00 1.00 0 0 1 0 1 2 0000

N-TARGETS 1.00 1.00 0 0 1 0 1 1 0000

C-80
Table C.40 Revised Waste Form, Processing, and Volume

Change Indices for Waste Spectrum-3 -

-Waste

Stream

P-IXRESIN

P-CONCLIQ

P-FSLUDGE

P-FCARTRG

B-IXRESIN

B-CONCLIQ

B-FSLUDGE

P-COTRASH

P-NCTRASH

B-COTRASH

B-NCTRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

N+LOTRASH

F-PROCESS

U-PROCESS

I-LQSCNVL

I+LQSCNVL

I-ABSLIQD

I+ABSLIQD

I-BIOWAST

I+BIOWAST

N-SSWASTE

N-LOWASTE

L-NFRCOMP

Fl am

VRF VIF I4

Disp

I5

Leach Chem Stab

I6 I7 18

Acc

I9

Process

I10

1.00

6.00

1.00

1.00

1.00

2.40

1.00

80.00

1.00

80.00

1.00

40.00

1.00

20.00

80.00

10.00

40.00

20.00

80.00

1.00

1.00

4.52

1.00

1.00

1.00

15.00

1.00

1.00

1.00

1.00

2.00

2.00

2.00

1.00

2.00

2.00

2.00

2.00

1.00

2.00

1.00

2.00

1.00

2.00

2.00

2.00

2.00

2.00

2.00

1.00

1.00

2.00

3.00

2.00

3.00

2.00

1.92

1.00

1.00

1.00

0 4 0

,0 4 0

0 4 0

0 4 0

0 4 0

O 4 0

0 4 0

0 4 0

0 1 0

0 4 0

0 1 0

0 4 0

0 1 0

0 4 0

0 4 0

0 4 0

0 4 0

0 4 0

0 4 0

1 1 0310

.1 1 :4310

.1 1-0310

1 0310

1 1 0310

1 1 4310

1 1 0310

1 1 6312

3 2 0510

1 1 6312

3 2 0510

1 1 6311

0 2 0000

1 1 5311

1 1 7322

1 1 5311

1 1 7322

1 1 5311

1 1 7322

0

0

1

3

1

3

1

2

0

3

0

3 1 0 1 1 0000

3 1 0 1 1 0000

0 4 0 1 1 5311

3 1 1 0 1 0010

0 4 1 1 1 0310

3 1 1 1 1 0010

0 4 0 1 1 5311

3 1 1 0 1 0010

3 1 0 1 1 0000

3 1 1 0 1 0000

0 1 0 3 2 0510

C-81
I |.-

Table C.40 (Continued)

I .1! u . . I

Waste Flam Disp Leach Chem Stab Acc Process

Stream VRF VIF I4 I5 I6 I7 I8 I9 I10

L-DECONRS

N-ISOPROD

N-HIGHACT

N-TRITIUM

N-SOURCES

N-TARGETS

18.00

1.00

1.00

1.00

1.00

2.00

2.00

1.00

1.00

1.00

1

1

0

3

0

O 4 0 1 1 6312

0 4 1 1 1 0310

0 1 0 3 3 0510

3 1 1 1 1 0000

0 1 0 1 2 0000

1.00 1.00 0 0 1 0 1 1 0000

C-82
Table C.41 Revised Waste Form, Processing, and Volume

Change Indices for:Waste Spectrum 4- -

Waste

Stream

P-IXRESIN

P-CONCLIQ

P-FSLUDGE

P-FCARTRG

B-IXRESIN

B-CONCLIQ

B-FSLUDGE

P-COTRASH

P-NCTRASH

B-COTRASH

B-NCTRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

N+LOTRASH

F-PROCESS

U-PROCESS

I-LQSCNVL

I+LQSCNVL

I-ABSLIQD

I+ABSLIQD

I-BIOWAST

I+BIOWAST

N-SSWASTE

N-LOWASTE

L-NFRCOMP

Flam Disp Leach Chem Stab Acc Process

VRF VIF I4 I5 I6 I7 I8 I9 I10

18.00

8.00

5.00

1.00

18.00

6.40

5.00

80.00

6.00

80.00

6.00

40.00

6.00

20.00

80.00

10.00

40.00

20.00

80.00

1.00

1.00

4.52

1.00

100.00

1.00

15.00

1.00

1.00

1.00

1.00

2.00

2.00

2.00

1.00

2.00

2.00

2.00

2.00

1.00

2.00

1.00

2.00

1.00

2.00

2.00

2.00

2.00

2.00

2.00

1.00

1.00

2.00

3.00

2.00

3.00

2.00

1.92

1.00

1.00

1.00

1

1

1

2

1

1

1

1

0

1

0

1

0

1

1

1

1

1

1

0

0

1

3

1

3

1

2

0

3

0

4. 0 1 -.1

4 0 1 1

4 0 1 1

4 0 1 1

0 1 1

4 0 1 1

4 0 1 1

4 0 1 1

1 0 1 2

4 0 1 1

1 0 1 2

4 0 1 1

1 0 0 2

4 0 1 1

4 0 1 1

4 0 1 1

4 0 1 1

4 0 1 1

4 0 1 1

1 0 1 1

1 0 1 1

4 0 1 1

1 1 0 1

4 1 1 1

1 1 1 1

4 0 1 1

1 1 0 1

1 0 1 1

1 1 0 1

6312

: 6312

6312

. 0310

6312

6312

6312

6312

3010

6312

3010

6311

3020

5311

7322

5311

7322

5311

7322

0000

0000

5311

0010

5311

0010

5311

0010

0000

0000

1 0 3 2 0510

C-83
.1.1

Table C.41 (Continued)

Waste Flam Disp Leach Chem Stab Acc Process

Stream VRF VIF I4 I5 I6 I7 I8 I9 I10

L-DECONRS

N-ISOPROD

N-HIGHACT

N-TRITIUM

N-SOURCES

N-TARGETS

18.00 2.00 1

1.00 2.00 1

1.00 1.00 0

0 4 0 1 1 6312

0 4 1 1 1 0310

0 1 0 3 3 0510

3 1 1 1 1 0000

0 1 0 1 2 0000

0 1 0 1 1 0000

1.00

1.00

1.00

1.00

1.00

1.00

3

0

0

C-84
- - -

For the final EIS, two additional waste spectra are considered. The fifth waste

spectra incorporates high integrity containers-to achieve a stabilized waste

form. Relative to waste spectrum 1, waste streams other than activated metals

which had previously been in an unstable form are stabilized using HICs. Activated metals-are assumed to'be stabilized by 'filling interstitial voids in a

waste container-with a noncompressible material.. This could occur either at

the waste generator's facility or at the disposal facility. ThelN-TRITIUM waste

stream is already assumed to-be-stableinh waste spectrum 1, but is assumed to

be placed into an HIC to help further reduce potential ground water impacts.

Since HIC's are more expensive than normal waste containers, all compressible

waste streams are assumed to be subjected to compaction Waste streams I+COTRASH,

N+SSTRASH, N+LOTRASH, and I+LIQSCVL are assumed to be compacted at a centralized

processing facility which is assumed to be colocated with the disposal facility.

The remainding compressible waste streams are assumed to be compacted at the

-waste generator's site. These include the P-COTRASH, B-COTRASH, I-COTRASH,

N-SSTRASH, and N-LOTRASH waste streams.

Waste spectra processing indices as well as volume reduction and volume increase

factors are presented for waste spectrum 5 in Table C.42.

The sixth waste spectrum is a combination of waste spectra 1 and 2, and is used

to represent overall waste characteristics that are projected to result without

requirements for waste stability and considering the increasing costs' for disposal. In this waste spectrum, light water reactor (LWR) process waste streams

are disposed in an unstable manner. For example, LWR,ion exchange resins and

filter sludge are disposed in a dewatered form. Other high activity waste

streams such as pressurized water reactor (PWR) cartridge filters, LWR nonfuel

reactor core components, and LWR noncompressible trash are also packaged in a

manner which could result in disposal cell slumping and other' subsidence problems.' The waste form and packaging conditions for the above waste 'streams are

the same as those assumed for waste spectrum 1.

Similarly, to waste spectrum 2, however, all compressible waste streams are

assumed to be compacted. Given the greatly increased costs for disposal that

have been experienced over the last few years, 'and the expectation that disposal costs will probably continue to increase in the future, there has been a

great interest in volume reduction technologies such as compaction. In waste

spectrum 6, waste streams I+COTRASH, N+SSTRASH, N+LOTRASH, and +LIQSCVL are

assumed to be compated at a centralized processing facility which is assumed

to be colocated with the disposal facility. The remaining compressible waste

streams are assumed to be compacted at the waste generator's site. These

include the P-COTRASH, B-COTRASH, I-COTRASH, N-SSTRASH, and N-LOTRASH waste

streams.

Waste spectra processing indices as well as volume reduction and volume increase

factors are presented for waste spectrum 6 in Table C.43.

C-85
Table C.42 Waste Form Processing, and Volume Change

Indices for Waste Spectrum 5

Waste Flam Disp Leach Chem Stab Acc Process

Stream VRF VIF 14 I5 I6 17 18 I9 I10

P-IXRESIN

P-CONCLIQ

P-FSLUDGE

P-FCARTRG

B-IXRESIN

B-CONCLIQ

B-FSLUDGE

P-COTRASH

P-NCTRASH

B-COTRASH

B-NCTRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

N+LOTRASH

1.00

1.00

1.00

1.00

1.00

1.00

1.00

2.00

1o00

2.00

1.00

1.50

1.00

2.00

4.00

1.50

3.00

2.00

4.00

1,00

1.40

1.00

1.00

1.00

1.40

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

2, - 1 1 0 2

1 1 2 0 1

1 3 1.0 2

2 2 1 0 2

2 1 1 0 2

1 1 2 0 1

1 3 1 0 2

3 2 1 0 1

0 0 1 0 3

3 2 1 0 2

0 0 1 0 3

3 2 1 0 2

0 0 1 0 3

3 2 1 0 2

3 2 1 0 2

2 2 1 0 2

2 2 1 0 2

3 2 1 0 2

3 2 1 0 2

1 0410

1 0110

1 0410

1 0410

1 0410

1 '0110

1 0410

2 1410

2 0510

1 1410

2 0510

1 1410

2 0510

1 1410

1 -2420

1 1410

1 2420

1 1410

1 2420

C-86
.- -

Table C.42 (Continued)

...waste

Stream

Flam. Disp - Leach Chem Stab Acc Process

VRF VIF I4 -I5 I6 I7 -.I8 I9 : 110

F-PROCESS 1.00 1.00 0

U-PROCESS 1.00 1.00 0

I-LQSCNVL 1.28 3.00 3

: I+LQSCNVL 1.00 3.00 3

I-ABSLIQD 1.00 1.65 3

I+ABSLIQD. 1.00 3.00 3

I-BIOWAST 1.00 1.92 2

I+BIOWAST 1.00 1.92 2

. N-SSWASTE 1.00 1.00 0

N-LOWASTE 1.00 1.00 3

3 1 0 0

3 1 0

3 1 1

3 1 1

3 1 1

3 1 . 1

3 1 1

3 1 1

3 1 0

3 1 1

1

1

2

2

1

1

.2

2

1

2

1

1

1

:1

.1

1.

1

1

. I ,; 

.2

1,.

1

.3

1,,

2

1

0000

*0000

1410

0420

0010

0010

0410

0420

0000

0410

L-NFRCOMP 1.00 1.00 0

L-DECONRS 1.00 2.00 2

N-ISOPROD 1.00 2.00 1

N-HIGHACT 1.00 1.00 0

N-TRITIUM 1.00 1.00 3

N-SOURCES 1.00 1.00 0

N-TARGETS 1.00 1.00 0

0 1 0 3

0 4 1 1

1 3 1 2

0 1 0 3

3 1 1 2

0 1 0 1

0 1 0 2

0510

0310

0410

0510

0410

0000

0410

C-87
11LML

Table C.43 Waste Form, Processing, and Volume

for Waste Spectrum 6

Change Indices

Waste Flam Disp Leach Chem Stab Acc Process

Stream VRF VIF I4 I5 16 I7 I8 19 I10

P-IXRESIN

P-CONCLIQ

P-FSLUDGE

P-FCARTRG

B-IXRESIN

B-CONCLIQ

B-SLUDGE

P-COTRASH

P-NCTRASH

B-COTRASH

B-NCTRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

N+LOTRASH

F-PROCESS

U-PROCESS

I-LQSCNVL

I+LQSCNVL

I-ABSLIQD

I+ABSLIQD

I-BIOWAST

I+BIOWAST

N-SSWASTE

N-LOWASTE

1.00

6.00

1.00

1.00

1.00

2.40

1.00

2.00

1.00

* 2.00

1.00

1.50

1.00

2.00

4.00

1.50

3.00

2.00

4.00

1.00

1.00

1.28

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.82

1.00

1.00

1.00

1.56

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

1.00

3.00

3.00

1.65

3.00

1.92

1.92

1.00

1.00

2 1 1 0

1 1 3 0

1 3 1 0

2 2 1 0

2 1 1 0

1 1 3 0

1 3 1 0

3 2 1 0

0 0 1 0

3 2 1 0

0 0 1 0

3 2 1 0

0 0 1 0

3 2 1 0

3 2 1 0

2 2 1 0

2 2 1 0

3 2 1 0

3 2 1 0

0 3 1 0

0 3 1 0

1 0010

1 4210

1 0010

1 0110

1 0010

1 4210

1 0010

1 1010

2 0000

1 1010

2 0000

1 1010

2 0000

1 1010

1 2020

1 1010

1 2020

1 1010

1 2020

1 0000

1 0000

1 1010

1 0010

1 0210

1 0010

1 0010

1 0010

1 0000

1 0000

3

3

3

3

2

2

0

3

3 1 1 1

3 1 1 0

1 3 1 1

3 1 1 1

3 1 1 0

3 1 1 0

3 1 0 1

3 1 1 0

C-88
Table C.43 (Continued)

Waste Flam -Disp Leach Chem Stab., Acc .Process

rIJ VTF ITF TA T1 TA' T7 TR 1Q Ain

L-NFRCOMP 1.00 1.00 .0 0 1 0 0 2 . 0000

L-DECONRS 1.00 2.00 2: -0 :4 1 1 1 0310

N-ISOPROD 1.00 1.30 1 1 3 1 0 1 0210

N-HIGHACT 1.00 1.00 0 0 1 0 0- 3- 0000

N-TRITIUM 1.00 1.00 3 3 1 1 1 i 0000

N-SOURCES 1.00 1.00 0 0 1 0 1 2 0000

N-TARGETS 1.00 1.00 0 o 1 0 1 1 0000

I . .

. I . I

.. . ,

. . I

I . .;

. L

. i

. I -

C-89
Wastes From Clean-up of MOX Research Facilities.

To improve the EIS analysis of impacts of transuranic waste disposal, an additional waste stream (F-PUDECON) is added to the 36 considered in the draft EIS.

This additional waste stream considers the generation of transuranic-contaminated

waste from decontamination-of mixed oxide (MOX) fuel research facilities and

from burnup studies of' irradiated LWR fuel rods.

A brief background of past and possible future transuranic waste generation and

disposal practices has been provided in Appendix D of the draft EIS. As discussed in Appendix D, compared to operations conducted by DOE, there, have been

only relatively small quantities of transuranic (TRU) waste generated by the

commercial sector. Major sources of TRU wastes that have been delivered in

the past to commercial disposal facilities have included waste from:

o DOE and its predecessors, the Energy Research and Development

Administration (ERDA) and the Atomic Energy Commission (AEC);

o DOE, ERDA, and AEC contractors;

o Reprocessing of spent uranium fuel at the West Valley, New York

commercial fuel reprocessing plant.

o Research and development of plutonium fuels, including fabrication

of small quantities of mixed-oxide (MOX) fuels for test purposes in

light water reactors; and

o Research studies of irradiated reactor fuel.

Within the last few years, the amount of transuranic waste delivered to commercial waste disposal facilities has been further reduced to even lower levels

and has been finally all but discontinued. This has been caused by a number

of factors. One factor was the policy announced by AEC in 1970 whereby AECproduced TRU waste in concentrations greater than 10 nanocuries per gram (nCi/gm)

were consigned to retrievable storage at AEC facilities pending the availability

of a repository for the ultimate disposition of the waste. (Some TRU waste

generated as a result of AEC (and later DOE) contracts with private companies,

however, was still sent to commercial disposal sites.) The only commercial

reprocessing facility ever to operate in the United States was the facility

operated by Nuclear Fuel Services (NFS) near West Valley, New York. In 1972,

this facility was shut down and has not operated since. In 1976, President

Carter announced a national policy of deferment of commerical fuel reprocessing.

This policy of deferring fuel reprocessing halted most of the mixed oxide fuel

research and development work in the commercial sector. (Some research is still

being carried on, however, either by or under contract to DOE.) Most commercial

mixed oxide fuel fabrication test facilities implemented a program for facility

clean-up and decontamination.

In addition, there is currently a lack of disposal capacity for TRU waste disposal. Individual disposal facility license conditions impose a 10 nanocurie

per gram disposal limit for TRU waste at all operating commercial low-level

C-90
waste disposal facilities.* Although at one time five of the six commercial

LLW disposal sites accepted TRU wastes for disposal (the Barnwell, South

Carolina facility has never accepted TRU wastes for disposal), this practice

has been discontinued. The last commercial facility to accept TRU waste for

disposal was the facility located in the center of the Hanford Reservation

near 1Rich1and, Washirnton anrd operated by the Nuclear Engineering Company

(NECO, now U.S. Ecology, Inc.). From'1976 to 1979, this facility was the only

commercial disposal facility accepting TRU waste for-disposal. TRU waste

acceptance at this facility 'in concentrations exceeding 10 nCi/gm was prohibited by the'state of Washington'in November 1979. This prohibition has

severely curtailed decontamination activities'at the MOX fuel research facilities discussed above.

Future generations of TRU waste may arise from three basic sources: (1) 'recycle

of spent uranium fuel, (2) decontamination of the existing small plutonium

research and'fuel fabrication facilities, and (3) burnup'studies of irradiated

LWR fuel.' For a number of reasons.which have been discussed in Appendix D of

the draft EIS, NRC staff do not expect significant quantities of waste-from

commercial fuel recycle activities prior to the year 2000. The remainder of

this discussion, therefore, addresses the latter two TRU waste sources.''

Following' the November'1979 prohibition of TRU disposal 'at the NECO-Richland

disposal facility, estimates were made of the volumes of transuranic waste that

would be generated from decontamination activities and burnup studies. (Ref. 12,

13). In these estimates, about 4960 m3 of decontamination waste was projected

to be generated over a three-year period, after which about 75 m3 from burnup

studies was.projected annually. Since that time, DOE has accepted some of this

waste for retrievable storage at DOE surface storage facilities. This includes

waste contaminated with plutonium -owned by DOE and which has been generated as

a result of an ongoing contract with DOE. (Waste generated as a result of previous contracts with AEC, ERDA, or DOE has not been so accepted.) Thus, an

updated estimate of the waste projections was required.Y This was accomplished

by means of a survey of NRC licensees potentially generating TRU waste (Ref. 14).

Based upon written responses to this-survey (Refs. 15-22), previous projections

(Ref. 12, 13) and other data (Ref.'23, 24),7the projections used for the final

EIS were'made.

Waste volume projections for the-F-PUDECON waste stream are summarized on

Table-C.44.-- Shown are the-volumes projected-to-be generated to the year 2000

in each of the 4 regions considered in the EIS, the total volume projected to

be generated in the country, and an "average" regional volume for purposes of

generic analysis. The projections assume that at present, a negligible quanity

of transuranic waste is shipped to disposal facilities. This waste is all less

than 10 nCi/gm in TRU activity. However, following the promulgation of the

Part 61 rule and assuming that disposal capacity is available, relatively large

volumes of waste are shipped over a three-year time period. During this time

period, decontamination of the MOX fuel research facilities is assumed to be

*The 10 nCi/gm limitation has been interpreted very strictly by the states.

It has been interpreted to include, for example Pu-241 (a beta-emitter) and

Cm-244 (a very short lived alpha emitter) in the 10 nCi/gm accounting.

C-91
II

Table C.44 Projected Regional Volumes to the

of F-PUDECON Waste Stream

Year 2000

(volumes in ft3)

Year Region 1 Region 2 Region 3 Region 4 Total Reference

1983 8,400 24,600' 4,300 16,500 53,800. 13,450

1984 6,200 16,800 1,150 14,500 38,650 9,663

1985 6,200 16,800 1,150 14,500 38,650 9,663

1986 1,500 160 1,150 160 2,970 743

1987 1,530 163 1,173 163 3,030 758

1988 1,561 166 1,196 166 3,090 773

1989 1,591 170 1,220 170 3,150 788

1990 1,621 173 1,243 173 3,210 8Q3

1991 1,652 176 1,266 176 3,270 818

1992 1,682 179 1,289 179 3,330 833

1993 1,712 . 183 1,313 183 3,390 848

1994 1,742 186 1,336 186 3,450 - 863

1995 1,773 189 1,359 189 3,510 878

1996 1,803 192 1,382 192 3,570 893

1997 1,833 196 1,406 196 3,630 908

1998 1,864 199 1,429 199 3,690 923

1999 1,894 202 1,452 202 3,750 938

2000 1,924 205 1,475 205 3,810 953

Total (ft3) 46,482 60,939 26,290 48,239 181,950 45,488

Total Wm3) 1,316 1,726 745' 1,366 5,153 1,288

C-92
completed. Also shipped during the first year are quantities of waste which

have been accumulated and stored at the waste generator's site.- Following this,

waste volumes drop to very low levels and are principally due' to assumed'continued

small scale burnup studies of.occasional spent fuel rods.'U-Projections of volumes

beyond the next few years" are rsomewhat specultive,-and are6conservatively assumed

to increase in a linear manner proportional to the projected increase in LWR electric generating capacity assumed inrthe EIS to the year 2000. ''This-is likely to

be conservative since current indications are that-the actual LWRelectric generating capacity by'the'year 2000'will be less than that projected in the EIS.

The radiological, physical, and chemical characteristics of the waste so~generated

are expected to be quite-varied. Waste generated from decontamination operations

:are expected to be a mixture of compressible and noncompressible material, including such material as paper, miscellaneous trash, glove boxes and concreterubble.

Such waste would be expected to contain at least some quantities of chelating and

other decontamination chemicals. <Waste'from'burnup studies would be expected to

'mainly~consist'of compressible trash, with smaller traces of oxide residues. The

waste form and processing-indices assumed for-this streamare presented below for

each of the 6 waste spectra:

Spec. VRF VIF i4 1- 5 I6 .I7 I8 I9 I10

1 1.0 1.0 2 2 1 1 0 1 0000

2 1.0 1.0 2 2 1 1 2 1 0410

3 1.0 1.0 2 2 1 1 2 1 0410

4 1.0 1.0 2 2 1 1 2 1 0410

5 1.0 1.0 2 2 1 1 2 1 0410

6 1.0 1.0 2 2 1' 1 0 1 0000

As shown, no processing is projected for the waste other than emplacement of the

waste ,into high integrity containers. This is mainly due to the heterogenity of

the expected waste mixture. Much of'the' waste from'the decontamination operations

is- not'expected'to be in'a form readily'.amenable to volume reduction through such

techniques as compaction or incineration. The overall'volumesiofwaste''that would

be amenable to further volume reduction are expected to be quite small in comparison

with other waste streams (e.g., P-COTRASH) investigated in this EIS.

Based upon-information received in response-to the survey of-licensees, the

activity in the F-PUDECON waste stream is projected in this EIS to be distributed into 3 groups: low, moderate and high. These three groups are listed

below, assuming a waste'density of 1 gm/cc.

Volume percent Average activity

Range in range in range

0-10 nCi/cc 40 5 nCi/cc -

10-100 nCi/cc 15 50 nCi/cc

100+ nCi/cc 45 500 nCi/cc

C-93
This distribution is believed to be conservative, as, it is believed to somewhat

exaggerate the percentage of the waste occurring in higher'!activity levels'.

In addition-, the average activity in the waste, in the 0 to 10 nCi/cc group is

realistically probably much less than: 5 nCi/cc. This distribution results in

an average activity across the waste stream of 235 nCi/cm3.

Since most of the waste in this waste stream will be generated from decontamination of MOX research facilities, the' isotopic distribution within most of the

waste is expected to be similar to that within the fabricated MOX fuel. Burnup

studies would generate waste having the same basic plutonium isotopes as the

MOX fuel, but in a somewhat different isotopic distribution. A very small

volume of waste (about 6 m3 per year) will be 'generated from manufacture of

plutonium heat sources for use in batteries. This waste will be principally

contaminated with Pu-238.

For use in the EIS, then the F-PUDECON waste stream is estimated to have an.

isotopic distribution similar to that in fuel for the Fast Flux Test Facility

(FFTF). This distribution is as follows (Ref. 15):

Isotope Weight percent

Pu-238 .05

Pu-239 86.8

Pu-240 11.35

Pu-241 1.2

Pu-242 0.3

Am-241 0.3

100

This distribution was then converted

Assuming an average waste density of

gross activity of 0.235 pCi/cm3, one

distribution:

to an equivalent activity per volume.

1 gm/cm3, and normalizing to the average

arrives at the following radionuclide

Isotope Concentration (pCi/cm3)

Pu-238 1.355E-3

Pu-239/40 1.280E-2

Pu-241 2.188 E-1

Pu-242 1.893E-6

Am-241 1.559E-3

2.345E-1

C-94
s - .

Wastes From Spent Light Water Reactor Fuel Storage.

Section'6.4 of Appendix 0 of the draft EIS discussed wastes which could possibly

result from construction and use of an independent facility for storage of light

water reactor fuel. As discussed in the draft EIS, wastes generated at an independent spent fuel storage facility would primarily arise from treatment of

storage basin water,-receiving and unloading spent fuel, and maintenance-ofplant ventilation-systems. These wastes would include'spent resins, filter

sludges and miscellaneous trash, and would be similar in composition'to wastes

produced from light'water reactor operations.

At this time, NRC has not received any application for construction of an.independent spent fuel storage facility. The timing for future construction of a.-

storage facility (and associated waste volume generation) is difficult to determine. The Department of Energy (DOE),.-however, has developed an estimate of

the annual volumes and radionuclide concentrations of. wastes that could be

generated from operation of a large' (3000 MTHM) independent spent fuel storage

installation, assuming that one is constructed (Ref. 25). These volumes and

radionuclide concentrations are listed in Table C.45, and are based upon an

operating mode (conservative for purposes of waste generation) in which onesixth of-the storage-capacity is replaced each year. In the table, all volumes

'and concentrations are shown as generated--i.e., trash streams are shown prior

to compaction, resins are shown in-a dewatered form, and concentrated liquids

are shown prior to solidification.. As shown, the total volume of waste from a

-large independent spent fuel storage facility is comparable to the annual'

:generation.rate of a single 1000 MW(e) light water reactor. Table C.45 serves

to expand the information previously given in Table D.33 of the draft EIS.

Comparison of the radionuclide concentrations in Table C.45 with-the radio- ¶

nuclide limits established in the final Part 61 regulation indicates that about

-96% of,~the.waste would be classified.as Class A while only 4% would be classified as Class B. ..Class A waste includes combustible trash, ventilation filters,

noncombustible trash'; and failed equipment. Class C-waste includes'bead resins,

filt'er'ip'r-'c`atsludge,6 sulfate concentrate, an'd miscellianeous solution'-cnc en-''

-trates. This is only an estimate since the activity in the waste streams generated by' anfactual' facility would actually be expected-to exhibit a distribution.

For example, some fraction 'of'the volume of the filter precoat sludge, sulfate

concentrate, and miscellaneous solution concentrate waste strais would probably

be classed as Class C waste. No waste, however, is at this time projected to

'be'determined"to 'be unacceptable for nhear-.surface disposal.

Wastes From Recycle of Uranium Fuel.

One'-potential'source of additional:wastes could result from recycle of uranium

.fuel.' (Currently, spent uraniui'fu'l removed from nuclear power reactors is

'stored.) Such wastes could result'from reprocessing the spent fuel to recover

plutonium and uranium and.-converting 'the recovered plutonium into an

oxide powder. Recovered plutonium'oxide could then be'mixed'with fresh uranium

and fabricated into mixed oxide'fuel rods':for aggregation into fuel assemblies

and reuse in nuclear power plants., For a:variety of reasons, NRC staff believe

"that it is unlikely, that significant volumes of waste from commercial recycle

'of uranium will be generated over the next 20 years. It'may be of interest,

C-95
Table C.45 Estimated Annual Waste Volumes and Radionuclide

Concentrations Generated from Assumed Operation of

a 3,000 MTHM Spent Fuel Storage Facility

Concentration of some

Gross concen- individual nuclides (Ci/m3)

Waste Category Volume (m3) tration (Ci/m3)* Fe-55 Co-60 Sr-90 Cs-137

Compactible and

Combustible Wastes:

* Combustible trash 630 5.9E-2 1.7E-3 1.2E-3 1.BE-4 1.1E-2

* Ventilation filters 23 2.3E-2 6.6E-4 4.8E-4 7.OE-5 4.2E-3

Liquids and Other

Wet Wastes

* Bead resins 2 8.OE+O 2.1E-1 1.5E-1 2.2E-2 1.3E+O

* Filter precoat sludge 8 2.OE+2 6.OE+O 4.4E+O 6.4E-1 3.8E+1

* Sulfate concentrate 7 2.3E+2 6.5E+O 4.8E+O 7.0E-1 4.1E+1

* Miscellaneous solu- 10 2.1E+2 6.3E+0 4.6E+O 6.7E-1 4.0E+1

tion concentrates

Noncombustible Material:

* Noncombustible trash 51 6.2E-2 1.8E-3 1.3E-3 1.9E-4 1.1E-2

Failed equipment 19 2.2E-3 6.3E-5 2.7E-5 6.8E-6 4.OE-4

Total Volume 750

zIncludes a number of otner, mostly snort lived, isotopes.

however, to obtain a rough comparison of radionuclide concentrations'in'potential waste streams with the limits for near-surface disposal developed as part

of the Part 61 rulemaking action.

DOE has prepared an estimate of the volumes and contained radionuclidefconcentrations in waste streams that could'be generated from' recycle of uranium fuel.

Wastes from reprocessing activities are'assumed to be'generated by a 2000 MTHM/yr

plant in which input fuel is'assumed to be aged 1.5 years out'of reacto'r; (Note:

2,000 MTHM/yr means a processing capability of 2,000 metric tons of heavy metal

(uranium and.plutonium) per' year.) Wastes from mixed oxide (MOX)'fuel fabrication are assumed to be generated by a 400 MTHM/yr plant for which there is

assumed to be a one year decay between plutonium recovery'at the reprocessing

plant and fabrication'of MOX fuel. Both plants are of fairly large capacity

and are based upon currently available technology. (Ref. 25)

C-96
Table C.46 lists annual volumes and associated radionuclide concentrations of

30 waste streams estimated to be generated by the reference 2000 MTHM/yr

reprocessing plant. All wastes are shown as generated prior to' further processing. Such processing could take the form of incineration or compaction of

compressible trash and solidification of liquids. Such processing operations

could produce further (relatively smaller) volumes of secondary wastes.

Table C.47 lists annual volumes and associated radionuclide concentrations of

six waste streams estimated to be generated by the reference 400 MTHM/yr fuel

fabrication facility. Again, all wastes are shown prior to further processing.

Estimated waste concentrations obtained from Tables C.46 and C.47 may be compared

against the waste classification limits in the final Part 61 'regulation. Based

upon this rough comparison, only about 17% (1400 m3) of the waste generated by

the 2000 MTHM/yr reprocessing plant would be classed as being unacceptable for

near-surface disposal. This is assuming a limit of 100 nCi/gm -fornear-surface

disposal of alpha-emitting transuranic nuclides (except fori'Cm-242). Corresponding amounts of other waste classes include Class A: 59% (5030 m3 ),

Class B: 9% (804 m3), and Class C: 15% (1200 M3 ). If the near-surface disposal limit were 10 nCi/gm for alpha-emitting transuranic radionuclides, however, an additional 1200 m3 would be classed as unacceptable. ' The''amount'

determined to be unacceptable would be 31% of the waste volume,(2600 m3). 'The

Class A and B waste volumes would remain the same but the Class .C waste volume

would be reduced to 44 m3. All of the waste generated by the 400 MTHM/yr MOX

fuel fabrication facility would be classed as being unacceptable for nearsurface disposal, whether the transuranic limit is 10 nCi/gm or:100 nCi/gm;

5. MODIFICATIONS TO THE IMPACT ANALYSES METHODOLOGY

* This section summarizes the changes to the environmental impact analyses

methodology that have been made for the final EIS. In the draft EIS, the

impact'analysis methbdology'was Presented in'Appendix G.' The changes dis-'

cussed mainly involve additions (rather'than alterations) to the information

contained'in Appendix G and in reference 26. Items discussed herein include:

o revised methodology to consider waste classification impacts;

:o revised :treatment of decay chains;-

o addition of a methodology to consider impacts of potential trench

overflow and operation of a leachate evaporator;

o revised pathway dose conversion factors;'

o revised methodology to consider potential-operational accidents;

o additional insights into impacts of disposal of carbon-14 and

iodine-129.

C-97
Table C.46 Waste Streams From

Plant -

Reference 2000 MTHM/yr Fuel Reprocessing

(Ci/m 3)

Fuel assy

hardware

Fuel

residue

(hulls)

Main

plant

I LLW

(TRU)

Main Plant

silica gel

(TRU)

Storage

basin bead

resins

(Non-TRU)

Storage

basin filter

precoat

sludge

(Non-TRU)

Storage

basin sulfate concentrate

(Non-TRU)

Storage

basin

misc.

sol-s.

(Non-TRU) Isotope

H-3

C- 14

Fe-55

Co-60

Ni-59

Ni-63

Sr-90

Nb-94

Tc-99

I-129

Cs-135

to Cs-137

U-234

U-235

U-236

U-238

Np-237

Pu-236

Pu-238

Pu-239

Pu-240

Pu-241

Pu-242

Am-241

Am-243

Cm-242

Cm-243

Cm-244

8.9E-1

7.1E+4

7.1E+4

5.4E+1

7.4E+3

1.8E-2

1.8E-3

1.3E-1

2. 4E+2

2.3E-1

3.4E+2

3.8E+2

1.1E-1

1. 5E+1

1.2E+2

2.4E-2

5.8E-4

1.8E+2.

6.4E-4

3.OE-5

4.9E-4

6.OE-4

7.5E-4

6.OE-4

1.OE+1

6.8E-1

1.4E+O

3.4E+2

7.3E-3

1.3E+O

8.8E-2

1.9E+1

1.8E-2

1.4E+1

3.8E+O

5.1E-5

5.6E+O

1.3E-4

9.6E-4

2.8E-5

8.5E+O

3.1E-3

1.5E-4

2.4E-3

2. 9E-3

3.6E-5

2.9E-3 6.4E-6

5.1E+1 1.1E-1

3.3E+0 7.2E-3

6.6E+0 1.5E-2

1.6E+3 3.6E+O

3.6E-2 7.8E-5

6.5E-2

4.5E-3

9.OE-1

8.8E-4"

6.6E-1

3.5E-1J

2.2E-1

2.8E-2

1. 7E+O

9.9E+O

6.2E+O

-7.9E-1

4.7E+1

1.4E+1

8.7E+O

1.1E+O

6.6E+1

9.2E+O

*5.8E+O

7.4E-1

4.4E+1

Vol (m3/yr) 112 532 220 10 4 14 10 20

Vol (m3/MTHM) 056 .266 .11 5E-3 2E-3 7E-3 5E-3 1E-2

U + Pu Recycle Fuel aged 1.5 yrs,
-K: '

I .1

r I

Table C.46 (Continued) ''

Concentration (Ci/m 3)'.-

. - I 

I I. I

I

U F6 plant

,' ' fluorinator

bed residues

Isotope (TRU)

UF6 plant

fluorinator

fines

(TRU)

UF6 plant

K2UO4

mud

UF6 plant

waste dryer

discharge

(NR)*

Storage

basin

combustible trash

(Non-TRU)

Main plant

combustibl'e trash

(TRU)

Pu02 conversion

combustible trash

(TRU) '

UF6 plant

combustible trash

(Non-TRU)

H-3 2.7E-3

C-14

Fe-55

Co-60

Ni-59

Ni-63,

Sr-90

Nb-94

Tc-99

I-129

Cs-135

Cs-137

U-234

U-235

U-236

U-238

Np-237

Pu-236

Pu-238

Pu-239

Pu-240

Pu-241

Pu-242

Am-241

Am-243

Cm-242

Cm-243

Cm-244

2.7E-3

1.7E-3

2. 2E-4

1.4E-6

1.5E-1

3.3E-5

1. 3E-2

5.1E-4

2.4E-5

3.9E-4

4.8E-4

1. 6E-5

2.8E-1

1.8E-2

3.7E-2

9.OE+O

2.OE-4

1. 7E-2

8.OE-4

1.3E-2

1.6E-2

6.3E-3

3. OE-4

4.8E-3

5.9E-3

1.1E-5

1.8E-1

1.2E-2

2.5E-2

6.OE+O

1.3E-4

7.8E-7

2.3E-1

8.5E-7

4. OE-8

6.5E-7

8.OE-7

1.OE-6

8.OE-7

1.4E-2.,

9.OE-4

1. 8E-3

4.5E-1

9.8E-6

1.8E-3

1.2E-4

2.5E-2

2.4E-5

1.8E-2

5.5E-3

9.2E+1

6.OE+O

1.2E+1

2.8E+3

6.5E-2

3.4E-3

1.6E-4

2.6E-3

3.2E-3

Vol (m3/yr) 8 60 140 1000 1200 800 60 100

Vol (m3/MTHM) 4E-3 3E-2 7E-2 5E-1 0.6 0.4 3E-2 5E-2

XExpected to contain insignificant quantities of radioactive isotopes.
- - -

Table C.46 (Continued)

Concentration (Ci/m 3)

Storage

basin ventilation

filters

(Non-TRU)

Main plant

ventilation

filters

(TRU)

UF6 plant

ventilation

filters

(Non-TRU)

Pu02 conversion ventilation filters

(TRU)

Isotope

IX bead

resins

(TRU)

Degraded

extractant

(TRU)

Main plant

combustible

trash

(TRU)

Main plant

noncombustible

trash

H-3

C-14

Fe-55

Co-60

Ni-59

Ni-63

Sr-90

Nb-94

Tc-99

C) I-129

o Cs-135

Cs-137

U-234

U-235

U-236

U-238

Np-237

Pu-236

Pu-238

Pu-239

Pu-240

Pu-241

Pu-242

Am-241

Am-243

Cm-242

Cm-243

Cm-244

4.OE-5 1.1E-5

1.6E-1

1. OE-1

1. 3E-2

7.7E-1

4.4E+O

9.3E-4

2.2E-5

6.6E+O

2.4E-5

1.1E-6

1. 9E-5

2.3E-5

2.9E-5

2.3E-5

3.9E-1

2.6E-2

5.2E-2

1.3E+1

2.8E-4

5.1E-2

3.4E-3

7.1E-1

6.9E-4

5.1E-1

6.8E-4

3.2E-5

5.2E-4

6.4E-4

1.2E+O

2.6E-4

1.4E-2

6.2E-6

1.9E+O

6.8E-4

3.2E-5

5.2E-4

6.4E-4

8.OE-6

6.4E-4

1.1E+1

7.2E-1

1.5E+O

3.6E+2

7.8E-3

1.4E-2

9.4E-4

2.OE-1

1.9E-4

1. 4E-1

7.OE-9

7.6E-4

1. 6E-7

4.4E-4

3.9E-9

1.2E-3

4.3E-5

2.OE-6

3.3E-5

4.OE-5

5.OE-5

4.OE-3-

6.9E+1

4.5E+O

9. 1E+O

2.3E+3

4.9E-2

8.9E-2

5.9E-3

1.2E+O

1.2E-3

9.OE-1

4.7E-10

5.1E-5

1.1E-8

0

2. 6E-10

7.8E-5

2.8E-10

1. 3E-11

2.2E-10

2. 7E-10

3.3E-10

2.7E-10

4.6E-6

3.OE-7

6.1E-7

1.5E-4

3.3E-9

5.9E-7

3.9E-8

8.3E-6

8.1E-9

6. OE-6

1.4E-6

1.5E-1

3.3E-5

0

7.8E-7

2.3E-1

8.5E-7

4.OE-8

6.5E-7

8.OE-7

1.OE-6

8.OE-7

1. 4E-2

9.OE-4

1.8E-3

4.5E-1

9.8E-6

1. 8E-4

1.2E-4

2.5E-2

2.4E-5

1.8E-2

3.3E-2

5.5E+2

3.6E+1

7.3E+1

1.7E+4

3.9E-1

Vol (m3/yr) 20 2.80 10 40 10 16 2400 800

Vol (m3/MTHM) 1E-2 1.4E-1 5E-3 2E-2 5E-3 8E-3 1.2 4E-1
Table C.46 (Continued)

Concentration (Ci/m3)

UF6 plant

Inoncombus-

.,tible trash

Pu06 conversion-noncom- Main plant--

bustible -' failed

trash -,equipment

UFj plant- PuO2 converfailed ''sion failed

equipment equipment

Storage

basin noncombustible

trash

Storage

,basin

failed

Istope equipment

H-3 1.8E-4

C-14

Fe-55

Co-60

Ni-59

Ni-63

Sr-90

Nb-94

Tc-99

I-129

o Cs-135

Cs-137

U-234

U-235

U-236

U-238

Np-237

Pu-236

Pu-238

Pu-239

Pu-240

Pu-241

Pu-242

Am-241

Am-243

Cm-242

Cm-243

Cm- 9AA

... . . . .

2.8E-6

2.8E-3

1. 7E-3

I .1. 8E-4

1.2E-4

3.1E-1 2.2E-4 I 1. 5E-5

6.5E-5

3.4E-3

!1. 6E-4

2.6E-3

* 3.2E-3

5.5E9.2E+

6.0E,+

1.2E+E

2. 8E+

6.5E1.6E-6 - 4.7E-1

1.7E-6

8.OE-8

1.3E-6

1. 6E-6

2.OE-6

3 1.6E-6

'1 2.8E-2

.0 1.8E-3

.1 3.6E-3

.3 9.OE-1

2 2.OE-5

3.6E-3

2.4E-4

5.OE-2

4.9E-5''

3- :fF-2

3.4E-4

1.6E-5

2.6E-4

3.2E-4

-1.-3E-2 ,8.8E-4

1.7E-3

2.8E+1

1.8E+O

3.7E+O

'8.5E+2

2.OE-2

-. 11 - . v, -

Vol (m0/yr) 20 '12 ' '400 ' -- '20- ' 40' * 100 *; - 20

Vol (mS/MTHM) 1E-2 6E-3 0.2 1E-2 2E-2 5E-2 1E-2
- - - .

Table C.47 Waste Streams from Reference 400 MTHM MOX Fuel Fabrication Plant

(1 year decay from reprocessing plant assumed,

corresponding to DOE's reference plant)

Concentration

(Ci/m 3)

HEPA Combustible

filters trash

Process

solutions

Scrap.

recovery

solutions

Non-combustible trash

Failed

equipment

0

U-234

U-235

U-236

U-237

U-238

Np-237

Pu-236

Pu-238

Pu-239

Pu-240

Pu-241

Pu-242

Am-241

2.7E-3

1.lE-4

5.3E-7

1.lE-1

2.2E-3

1.1E-6

6.3E-3

1.3E+2

9.1E+O

1.8E+1

4.1E+3

9.8E-2

6.7E+O

2.3E-4

9. OE-6

4.5E-8

9.OE-3

1.9E-4

9.6E-8

5.4E-4

1.1E+l

7.8E-1

1.6E+O

3.5E+2

8.4E-3

5.8E-1

2.OE-4

7.5E-6

3.8E-8

7.5E-3

1.6E-4

8.OE-8

4.5E-4

9.5E+O

6.5E-1

1. 3E+O

2.9E+2

7.OE-3

4.8E-1

1.lE-4

4.3E-6

2.1E-8

4.3E-3

9.1E-5

4.6E-8

2.6E-4

5.4E+O

3.7E-1

7.4E-1

1.7E+2

4.OE-3

5. 5E+1

2.OE-4

7.5E-6

3.8E-8

7.5E-3

1.6E-4

8.OE-8

4.5E-4

9.5E+O

6.5E-1

1.3E+O

2.9E+2

7.OE-3-

4.8E-1

2.OE-5

7.5E-7

3.8E-9

7.5E-4

1.6E-5

8.OE-9

4.5E-5

9.5E-1

6.5E-2

1.3E-1

2.9E+1

7.OE-4

4.8E-2

Vol (Total in m3) 40 200 8 140 80 80

Vol (m3/MTHM) 0.1 0.5 .02 0.35 0.2 0.2

i
5.1 Revised Methodology to Consider Waste Classification Impacts

During the preparation of the draft EIS, several computer programs were written

to calculate impact measures associated with the management of low-level radioactive waste. These computer codes are discussed in Appendix H of the draft

EIS and include the codes OPTIONS, GRWATER, INTRUDE, INVERSI, and INVERSW.

Three phases of waste management whichvmay-result in impacts were considered:

waste processing, waste transportation, and waste disposal. ''The impact measures

were calculated utilizing: (1) information on waste characteristics, (2) alternative waste processing and packaging technologies, (3) data and assumptions on

alternative disposal technologies and disposal facility site environments,

(4) the impact calculational methodologies presented in Reference 26.

For the 'draftEIS, a waste classification procedure was adopted in the OPTIONS

and GRWATER codes in which the characteristics of individual waste streams are

fixed (through a choice of a waste spectrum), the intruder impacts of each of

the waste streams are calculated and compared to a set of numerical dose limitation criteria (e.g., 500 mrem/year whole body), and then the waste streams are

classified.: -Following this,-impact 'measures such as costs, volume-averaged

intruder-impacts, and groundwater impacts are'determined. The waste classification requirements in the Part 61 rule, however, are presented not in terms

of dose limitation criteria, but in terms of radionuclide concentration limits

for various waste classes. Depending upon the concentrations of the radionuclides within a particular waste stream, a waste generator may be required

toprocess the:waste into a stable form, dispose of it in a stabilized manner

at the disposal-facility, and possibly stabilize it and dispose of it using

an intruder barrier. The waste may even be considered not generally acceptable

for near-surface disposal.

A revised waste classification test procedure was therefore developed for the

final EIS and incorporated into the OPTIONS and GRWATER computer codes. These

modified computer codes have been titled'the OPTIONR and GRWATRR codes,

respectively.'

A flow diagram of the revised waste classification test procedure is provided

as Figure C.1L Briefly, the revised waste classification test procedure for a

-given waste stream operates~as follows. First, a waste spectrum is chosen which

establi'she's'part'icular characteristics (particularly radionuclide concentrations

and whether-the waste stream is in a stable form) for the stream.. Thesradionuclide concentrations are then compared against a set of limiting concentrations

for Class A waste disposal. If the waste" stream'c6ncentrat'ions are less than

the limiting Class A concentrations, then a determination is made whether the

waste stream (which has been determined to be Class A waste) is stable or

unstable. If unstable, it is disposed'of in a'Class A (unstable) disposal unit.

If stable, it is disposed of in a disp6sil'unit along with 'stable Class B and

C wastes. (This is a desirable practice since it increases-overall site

stability, helps to further reduce potential groundwater migration, and also

reduces potential personnel exposures at a disposal facility.).

C-103
Start

0D

:Class A, unstable'

® :Class A, waste form or packaging stable

(I :Class B. stabilized through disposal facility design

(I:Class B, waste form or packaging stable

:Class C. stabilized through disposal facility design

'IV :Class C, waste form or packaging stable

7 :Hot waste, stabilized through disposal facility design

:Hat o waste, waste form or packaging stable

( Waste spectrum must be changed and the testing procedure restarted

Figure C.1 Revised Waste Classification Test Procedure

C-104
f

If the radionuclide concentrations in the waste stream exceed the limiting

Class A waste concentrations, then the waste stream must be stabilized and -

tested to determine if it meets limiting concentrations for Class B and C

'wastes. -Such waste.-stabilization may be accomplished for a given waste stream

by either specifying a particular improvement.in waste form and packaging.or

by a particular disposal facility design. The test-procedure compares thevwaste

radionuclide concentrations against the Class B and C limits using a number of

possible stable waste forms and packages or facility designs which achieve

stabilization. If there are no such waste forms or packaging'techniques which

can achieve a stable waste having-radionuclide concentrations-less 'than-theClass C values, then (with the exception discussed-below) the waste stream is

considered not acceptable for near-surface disposal. .:

..It may~be noted that if the waste stream exceeds the Class C waste limits, then

the testing procedure.includes:the provisions-for optional disposal-by 'a disposal

method giving greater confinement than near-surface disposal. In the draft

EIS and data base, this hasbeen generically referred to as a "hot waste:facility."

To date,'no disposal -criteria have-been developed by.NRC for disposal by such ' improved methods over near-surface disposal. However, inclusion of.this-option

in the codes at this time-will help to develop such future criteria as is neces-

.sary in a rapid manner. ' -

'As an~option, an alternative procedure is also included for determining limiting

concentrationsfor Class A (and other) waste. This alternative is included to

provide an assessment of the impacts of existing license conditions. at LLW disposal facilities.- In this alternative, the normal sum-of-the-fractions-rule

is not applied..-.Rather, a limit of 1 pci/cm3 of nontransuranic isotopes having

half-lives greater.than 5 years -is applied to light water reactor:process waste

streams (filter.sludges, ion.exchange resins,.solidified concentrated liquids

and 'cartridge filters) as well'as waste from isotope.production facilities..

For.such waste streams, if the concentration of. any nontransuranic isotope having

a half-life.greater than 5 years exceeds 1 pCi/cm3, then the waste stream is

not acceptable as Class A waste and must-be stabilized prior-to disposal.--, For

all other waste streams, no Class A concentration limits are imposed.

Under this alternative, classification of transuranic radionuclides is also

modified to conform with existing license conditions.: Current license conditions impose a 10 nCi/gm limit on transuranic waste disposal. These license

conditions generally allow disposal ofitransuranics up.to the 10 nCi/gm limit

as long as the transuranics are homogeneously distributed through'the waste.

Surface contaminated materials are often prohibited., Occasionally, homogeneously contaminated waste streams such as ion exchange resins are-found to

exceed the 10 nCi/gm limit, almost always due to 'short-lived alpha emitters

such 'as Cm-242 (163-day half-life) or. to Pu-241, which. is a beta-emitter having

a 13.2-year half-life. In such cases,.waste generators will-either dilute such

waste with lower activity waste (still retaining a homogeneous mixture) or allow

the short-lived radionuclides to decay'prior'to shipment.

Not to account for the above practicesiwouldlincorrectly'skew the resultsof

the cost-benefit analysis -in favor of the final Part 61 requirements. 'To'provide a more accurate analysis under this alternative classification scheme,

therefore, the Pu-241 concentrations within LWR process waste streams and isotope

production waste are decayed to their alpha-emitting equivalents. No such decay

C-105
I---

is performed-for trash or other waste streams which may be composed of surfacecontaminated materials. '' ; ,' 1 :' - -

The operational mechanics of the waste classification test procedure involves

a number of additional concepts. These are discussed in Section 2 of Appendix D of this final EIS.

5.2 Treatment of Decay Chains

The existing impact analysis methodology calculates radiological impacts to a

potential inadvertent intruder as a function of time. Offsite impacts from

such intrusion as well as hypothetical impacts from erosion-are also calculated.

For the final EIS, this impact analysis methodology has been revised to include

an improved method of determining radiological impacts associated with certain

heavy metal radioisotopes having daughters which are also radioactive.

Basically, the methodology for determining radiological impacts starts by considering, for a given'isotope; the concentration of that nuclide in waste.

This concentration is multiplied byfactors that correspond to radioactive decay

and to the transfer of the nuclide through the environment to a biota access

location. Given a unit concentration of the nuclide at a biota access location,

resulting dose equivalents are determined using "pathway dose conversion factors"

(PDCFs). For radioisotopes!belonging to decay chains, the revised methodology

determines for a given decay time the fractional amounts of respective daughter

radionuclides which would be ingrown during the decay time-period. These fractions are then multiplied by the respective pathway dose conversion factors

for the daughter nuclides, the products summed,';nd the total added to the pathway dose conversion factor for the parent nuclide. 'This calculational technique is identical to that used to calculate ingrowth of daughters of the nuclide

Rn-222 in the NRC uranium tailings impact code MILDOS (Ref. 27). That is, for

nuclides that do not belong to heavy metal decay chains, an entity f x PDCF

is used in the calculations. For nuclides which do belong to decay 8hains, this

entity is replaced by the following:

f x PDCF + (fdl x PDCFdl) + (fd2 x PDCRd2) + (fd3 x PDCF d3) -

f = exp (-X T) 0 p.

Ap = decay constant of parent

p

T = decay time period

PDCF = PDCF of parent p

f = fractional quantity of a given daughter generated from a unit

quantity of the parent at a given time

PDCFd = PDCF for a given daughter.

This additional treatment of decaydaughters is discussed in somewhat more

detail in Section 3, Appendix D, of this final EIS.

C-106
5.3 Radiological Impacts from Trench Overflow'and Leachate'Evaporation

As part of the work performed in the draft EIS, scenarios were considered in

which a disposal facility experiences severe water accumulation problems within

' diiposal'trenches.' Such water accumulation, it is'recognized, could fill upon

some of the trenches and overflow, resulting in environmental releases and

potential public impacts. It was recognized in the draft EIS that environmental

impacts from.such overland flow would'not be likely'to continue for.a great

' ttime period,-if at all. Rather, the pjprincipal'impacts would most probably

result from treatmentof leachate p'umped from inundated trenches--for example,

from leachage evaporation. The long-term economic impacts to the disposal site

owner that would result from' such leachate treatment activities were'emphasized.

Commenters on the draft EIS, however, have suggested that it would be useful

to calculate the-potential-environmental impacts that could result from trench

overflow or leachate treatment activities. A calculational procedure has been,

therefore, added to the impact analysis methodology to provide an order of

magnitude estimate of such'impacts.

In this final EIS, impacts from overflow are calculated assuming that each year,

a certain activity is released from the disposal trenches and flows into a nearby

stream, where contaminated stream water is consumed by an individual. Thus,

exposures due to overland flow are calculated as exposures to an individual

(in millirem/yr). In addition, the subroutine calculates exposures to the

surrounding population (in man-millirem/yr) that could result from pumping

leachate from the inundated trenches and processing the leachate through an

evaporator. In both cases, one must start with determining the activity

released. This is approximated using a method similar to the 'one [described in

Appendix G of. the'draft ,EIS for calculating a source term for groundwater

migration.' That is, the total activity released (A..) is given by '-

, NSTR NNUC

ij i-i I Cij x fi x V1 x fc(i,) where

- NSTR number of waste streams considered

'NNUC = number of radioisotopes considered -

C.- concentration (Ci/m3) of jth radionuclidei in ith waste stream 1.

fraction of waste volume in-ith waste stream

V1 =Volume Cm3) 6'f leachate annually' released or processed

' fc ~ Mo x tc x MULT (I6,I7,IS)'x 10,.9

M =,leach fraction of jth radionuclide

' -tc = fraction of year that leachate is in contact with the waste,

assumed to be equal to 1

C-107
MULT (I6,I7,IS) = a multiplier which accounts for reduced leaching of

some waste streams due to specific waste stream properties (See

Section 3.2.4 of Appendix G of the draft EIS)

o(-19) .= a correction factor for radioisotopes contained in activated

metals. --

For overland flow to a stream, the calculated released'activity is divided by

the flow rate of the stream (4,500,000'm3/yr for'the reference disposal facility),

and multiplied by PDCF-7 (see Appendix G of the draft'EIS) to obtain a total

individual dose in millirem/yr. For airborne'impacts to a population, the calculated activity is multiplied by the assumed individual isotope release fractions for the evaporator. These are:

Radionuclide Release Fractions

H-3 0.90

C-14 0.25

Tc-99 0.001

1-129 0.001 '

All Others 2.5E-6

This activity released from the evaporator is then multiplied by a factor

corresponding to atmospheric dispersion (see section 3.6 of Appendix G of the

draft EIS) and finally by PDCF-8 to obtain a population dose in man-millirem/yr.

In the above calculations, the activity released is assumed to be proportional

to the volume (V ) of leachate annually released overland or processed. In

this EIS, V is waste volume prorated from a base of one million gallons of

leachate, wiich is the approximate volume of leachate and other contaminated

liquids annually processed at the Maxey Flats disposal facility, and from one

million m3 of waste disposed. One million gallons is also the annual volume

of leachate assumed for the high cost institutional care'scenario (i.e., ICL=13

or 23) discussed in Appendix Q of the draft EIS. In the methodology, V is

assumed to be greater than zero only for the condition of a high level lf institutional control, and only for very impermeable site soil conditions. For such

conditions and if there is no segregation of stable'and'unstable waste, then

V is equal to one gallon per m3 of waste multiplied by the total volume of

waste (in m3) delivered to the disposal facility. In addition, the leachate

is assumed to contact both the stable and unstable waste streams. If there is

segregation of stable and unstable waste, then V1 is taken to be one gallon

per m of waste multiplied by the unstable waste volume. In this case, the

leachate only contacts the unstable waste streams.

Besides the radiological impact measures, three additional impact measures

associated with evaporator operations are calculated. These include annual

occupational exposures (in whole body man-rem), evaporator operation costs,

C-108
and gallons of propane. These impact measures were determined based upon

experience at the Maxey Flats disposal facility (Ref. 28).

5.4 Revised Pathway Dose Conversion Factors

As'discussed in the draft EIS,' eight sets of pathway dose conversion factors

(PDCF) are used to determine potential radiological dose equivalents based

upoi'a''unit concentratio'n' of a radionuclide at a biota access location. That

is, assuming that there exists a unit concentration of a radionuclide at a

biota access location (e.g., 1 Ci/m3"in water obtained from a well), there may

be a number of pathways by .which'exposures to an individual could occur. These

could include direct' consumption of the water or consumption of food which has

been irrigated by the contaminated well water. Airborne resuspension of the

contaminated irrigated-soil is another potential pathway. PDCFs are used to

-reduce to 'a s'ingle set of numbers all of the potential pathways from a biota

access location and-the-transfer of radionuclide's through these pathways. This

:--is preferable to repetatively calculating all of the pathways and transfer

mechanisms" through each-stage of the impact analysis methodology.

The eight basic groups. of uptake pathways leading to human exposures, and the

PDCFs corresponding to these pathways', are as follows:-

PDCF-1 :Accident

PDCF-2 Intruder-construction-air

PDCF-3 Intruder-agriculture-air

PDCF-4 :,Food

PDCF-5 : Direct 'Gamma

PDCF-6 : Well Water. -

PDCF-7 : Open Water

-PDCF-8 : Atmo'spheric Transport

These groups of-uptake pathways and the associated PDCFs are illustrated in

Figure C.2., ' '. '' -

The PDCFs are calculated using the computer code DOSE (Ref. 26). For the draft

EIS,-PDCFs'were calculatedjfor 7'body organs and 23 radionuclides. For the

final EIS, PDCFs for an-'additional 13 radionuclides were determined. All such

nuclides are members of heavy metal decay chains as discussed in Section 5.2.

Data for''dete'rminaition-of'the-.updated PDCFs were obtained using the same sources

as those listed as-references'in Appendix:.B-of-reference 26.

The PDCFs used in'the -final EIS 'are summarized in Tables C.48 through C.55.

5.5 Revised Methodology to Consider Potential Operational Accidents

The Part 61-rulemaking'action'has-emphasized generic requirements which would

involve'redu6tionr-of:-Iong-term radiological exposures and costs to a site owner.

Operational safety is'already addressed in the Commission's'regulations in

10 CFR Part.2C and relatively few additional requirements aimed at genericly

improving operational safety have been implemented. Once sound health physics

practices are established at a disposal facility, some flexibility in practices must be maintained so that operational safety may be continuously improved

over the operation of the site. In addition, operational impacts are relatively

short lived.

C-109
Figure C.2 Details of Uptake Pathways

t .

Scenario

Accident

(Acute)

Biota Acces!

Location

Offsite Air

s

Uptake Pathways

T 4 .6. .f4I

PDCF

Symbol

Ddiation area .

Direct Radiation air)

Inhalation (air) air - PDCF-1 PCDirect Radiation air)

DInhalation (atir)

Fod arF-2

adiation (volume) PDCF-5

Inhalation (air)

_~DJetRdjto ar v_IPnrcr_i

Intruder-,

Construction unsite Soil

(Acute)

IntruderAgriculture

(Chronic)

Onsite Soil - \ Food (air) j . W. __

- Food (soil) - PDCF-4

Direct Radiation volume PDCF-5

Leaching &

Migration

(Chronic)

Inhalation (soil)

I Well Wat e \Direct Radiation (air) PDCF-6

Leaching &

Migration

(Chronic)

Inhalation (soil)-

Sol 0 Db irect Radiation (area)

iOpen Water (>Drc Rdiation ~air)

Food (water)

Inh'alation (soil)

Surface . : .O~rc ~daton.

Water Runoffl Open

(Chronic)

n rect Radiation (air)sh

Fod (water)

- 5 Lgestion (fish)

'~PDCF-7

POCF-7

PDCF-8

Inhalation (soil)

Atmospheric

Transport

(Chronic)

I~ Of si t eA Air'. \DOirect Radiation (air)

\ ~Inhalation (air)-

,,-"Direct Radiation (a-ir)T

I

C-110
Operational safety was not ignored in the draft EIS, however, and an analysis

was performed to determine the effect on operational safety of requirements

intended to reduce long-term costs and radiological impacts. In general, it

was determined that 'requirements intended,to reduce long-term costs and radiological impacts also tended to'improve operational'safety.

In the draft EIS,,a scenario was considered in.which a waste container is

assumed to be' dropped from a significant height so that the waste container

breaks open. A portion of the radioactive contents'of the waste package is

assumed to be released into-'the-air where it is transported offsite, leading

to subsequent potential human exposure. The *fraction released was assumed to

be given by the following: ' '

-| ~ '' "' f x10(l-I9) x lo(1-I6)

This'was meant to reflect the'fact that the fraction released would be greatly

reduced for improved waste -forms. The factor f 'was' taken to be equal to '.1%,

which is a worst case condition. This factor of .1% was obtained from experimental data involving release of powdered PuO under transportation accident

conditions. --

It'was determined that the above relationship did not adequately reflect the

variation in waste forms. For the final EIS, the above relationship was replaced by the relationship f 'x.Mult. -As before, f is taken to be equal to

O.1%., Depending upon the'waste'form, Mult is taken to be the following:-.'

Mult' Waste form

1 dewatered sludge and other misc. powders

.1 trash

.1 dewatered resins

.01 waste solidified in cement

.001 waste solidified in' vinyl ester styrene

0 activated metals ' -

' 6. "IMPACTS OF-DISPOSAL OF C-14 AND I-129

Two radionuclides considered in the impact analysis methodology and draft EIS

included carbon-14 (C-14) and iodine-129 (1-129). Both isotopes are longlived and both decay by emination of beta particles. Both are believed to

be present in a number of LLW streams and are also believed to be fairly mobile

in the environment. By far the principal pathways by which humans could receive

radiation exposures from these two isotopes involve ingestion. That is, through

consumption of contaminated food. Given such ingestion, the principal organ

impacted by carbon-14 is the bone. Conversely, the thyroid is the principal

organ impacted by ingestion of iodine-129. In fact, the relative dose to the

thyroid for a ingestion of a unit concentration of iodine-129 is about 1000 times

that for the whole body.

C-lll
'Table C.48 Pathway Dose Conversion Factor 1

Total Body Bone Liver Thyroid Kidney. Lung GI-LLI

H-3 1.25E+09 5.19E+07 1.25E+09 1.25E+09 1.25E+09 1.25E+09 5.19E+07

C-14 3.17E+09"' 1.40E+10 3.17E+09 3.17E+09 , 3.17E+09 3.17E+09' 2.53E+09

Fe-55 1.81E+10 1.89E+10 2.41E+10 1.61E+10 1.61E+10 2.08E+11 1.93E+10

Co-60 2.36E+12 2.34E+12 2.35E+12 2.34E+12' 2.34E+12 2.63E+13 2.50E+12

Ni-59 3.70E+10 9.38E+10 5.06E+1O' 2.58E+10 2.58E+10 5.78E+10 2.85E+10 Ni-63 3.06E+10 9.60E+11 6.58E+10 1.56E+08 1.56E+08 8.82E+10 7.44E+09

Sr-90 2.42E+13 9.62E+13 1.67E+11 1.67E+11 1.67E+11 1.98E+11 1.89E+11

Nb-94 6.10E+11 6.11E+11 6.11E+11 6.10E+11 6.11E+10 1.33E+12 6.84E+11

Tc-99 1.18E+09 9.68E+08 2.28E+09 7.60E+08 2.OOE+10 7.40E+09 7.88E+09

I-129 9.14E+11 8.52E+11 8.52E+11 5.13E+13- 8.52E+11 8.57E+11 8.52E+11

Cs-135 2.37E+10 9.65E+10 8.85E+10 5.08E+08 3.33E+10 1.49E+10 1.OOE+09

Cs-137 4.50E+11 6.34E+11 7.78E+11 2.42E+11 4.26E+11 3.30E+11 2.44E+11

Pb-210 8.04E+12 2.56E+14 6.56E+13 3.84E+10 2.08E+14 -. 04E+14 4.72E+10

Ra-226 1.52E+15 2.16E+15 8.94E+09 8.94E+09 8.94E+09 8.00E+14 1.77E+11

Ra-228 6.88E+14 6.48E+14 1.14E+08 1.14E+08 1.14E+08 8.80E+15 1.87E+09 Ac-227 3.60E+14 5.68E+15 8.OOE+14 1.OOE+09 2.56E+14 2.16E+16 1.14E+10

Th-228 2.40E+13 7.12E+14 1.20E+13 1.80E+10 6.80E+13 1.44E+16 2.98E+11

Th-229 1.36E+15 2.80E+16 4.24E+14 ', 2.55E+11 2.08E+15 2.OOE+16 2.49E+12

Th-230 5.36E+14 -1.76E+16 1.12E+15 1,.43E+10 5.28E+15 3.52E+14 2.46E+11

Th-232 2.56E+14 7.44E+15 3.52E+14 1.38E+10 1.68E+15 4.72E+15 2.38E+11

Pa-231 5.60E+14 1.36E+16 5.44E+14 1.10E+11 3.04E+15 5.12E+15 4.22E+11

U-233 2.01E+12 3.28E+13 1.08E+10 1.08E+10 7.69E+12 3.68E+15 2.91E+11

U-234 1.94E+12 3.12E+13 1.75E+10 1.75E+10 7.54E+12 3.60E+15 2.89E+11

U-235 2.06E+12 3.06E+13 2.21E+11 2.21E+11 7.26E+12 3.36E+15 5.17E+11

U-236 1.86E+12 3.04E+13 1.65E+10 1.65E+10 7.30E+12 3.44E+15 2.72E+11

U-238 1.69E+12 2.88E+13 1.45E+10 1.45E+10 6.57E+12 3.12E+15 2.55E+11

Np-237 5.20E+14 1.20E+16 1.12E+15 1.34E+11 3.84E+15 3.60E+14 3.74E+11

Pu-238 2.OOE+14 4.08E+15 2.80E+15 1.92E+10 8.80E+14 4.08E+15 3.31E+11

Pu-239 2.24E+14 4.80E+15 3.12E+15 7.40E+09 9.60E+14 3.84E+15 3.03E+11

Pu-240 2.24E+14 4.80E+15 3.12E+15 7.40E+09 9.60E+14 3.84E+15 3.03E+11

Pu-241 3.04E+12 7.44E+13 4.56E+13 4.78E+07 1.44E+13 6.80E+12 5.57E+09

Pu-242 2.16E+14 4.48E+15 3.04E+15 1.44E+10 9.60E+14 3;68E+15 2.94E+11

Am-241 5.04E+14 7.12E+15 6.64E+15 7.87E+10 3.84E+15 4.24E+14 3.59E+11

Am-243 4.96E+14 7.04E+16 6.48E+15 9.10E+10 3.76E+15 4.OOE+14 3.63E+11

Cm-243 3.84E+14 6.16E+15 5.60E+15 2.44E+11 1.76E+15 4.40E+14 5.48E+11 Cm-244 2.80E+14 4.40E+15 4.16E+15 1.71E+10 1.28E+15 4.40E+14 3.05E+11

C- 112
> '.: 555-. ¢¢ r

Table C.49 Pathway Dose Conversion Factor 2

Total Body: .Bone Liver Thyroid - Kidney . Lung GI-LLI

H-3- - 1J.17E+10- 5.19E+07 1.17E+10! .1.17E+10

C-14: 6.68E+10- 3.32E+11 .6.68E+102 .6.68E+10

j Fe-55 ,9.28E+09 - £4.82E+10 3.94E+10 5.08E+07

Co-60 ; 1.24E+11 2.28E+10 7.60E+10-2.28E+10

-,Ni-59 -. 3 3.87E+lO. 2.33E+11- 8.13E+10 *5.98E+07

Ni-63 1.04E+11 3.15E+12: ~,2.18E+11 1.56E+08-

Sr-90 6.39E+13 2.59E+14 1.76E+09. 1.76E+09'

Nb-94 1.39E+10 -1.51E+10, 1.45E+10 .1.32E+10: . Tc-99 2.96E+09 * 5.41E+09- 8.89E+09 7.60E+08,

1-129 2.07E+12 * 7.12E+11 6.12E+11 .1.62E+15 -

Cs-135 1.57E+11:- 4.21E+11 3.88E+11; .5.08E+08

Cs-137 - 1.40E+12 : 1.72E+12 2.35E+12 .1.53E+09

Pb-210 1.70E+13- 5.09E+14. 1.38E+14 3.51E+08

Ra-226 .1.65E+15 2.53E+15 5.01E+12 5.01E+12

Ra-228 7.60E+14 ,8.32E+14 6.51E+12 6.68E+12

-Ac-227- 3.62E+14 ,5.71E+15 8.04E+14 1.19E+08

Th-,228 ,2;43E+13 -7.20E+14 1.21E+13 1.98E+08

Th-229 .1.37E+15 2.81E+16 4.26E+14 1.79E+09

Th-230 5.37E+14 1.76E+16 1.12E+15 1.30E+08

Th-232 2.58E+14 7.48E+15 3.54E+14, 1.08E+08

Pa-231 5.63E+14 1.37E+16 5.47E+14 6.59E+08

U-233--- 2.87E+12-- 4.72E+13 5.16E+07 5.16E+07

U-234 ,2.77E+12 4.50E+13 1.14E+08 1.14E+08 ' .U-235 2.64E+12 -4.36E+13 1.59E+09 1.59E+09.-

U-236 2.66E+12- 4.36E+12 - 9.67E+07 9.67E+07

U-238 2.43E+12 , 4.15E+13 8.57E+07- 8.57E+07,

Np-237 5.21E+14 * 1.20E+16, 1.12E+15 8.40E+08

Pu-238:-, 2.00E+14, 4.09E+15 2.80E+15;,8.87E+07

Pu-239 2.24E+14 4.81E+15 3.12E+155 5.17E+07-

Pu-240 >. 2.24E+14 4.81E+15. ,3.12E+15 ,5.17E+07

Pu-241 3.05E+12 - 7.47E+13, 4.56E+13 4.78E+07,

Pu-242 2.16E+14 4.49E+15 3.04E+15 ,6.93E+07,,

Am-241 5.05E+14 7.13E+15 6.64E+15- 3.80E+08

Am-243 4.97E+14 7.05E+15 6.48E+15 6.09E+08

Cm-243 . 3.85E+14, ,6.17E+15 5.60E+15 .2.26E+O9

Cm-244. 2.80E+14 4.41E+15 4.16E+15 7.23E+07

1.17E+10 1.17E+10' 1.05E+10

6.68E+10 - 6.68E+10 6.61E+10

5.08E+07 2.10E+11 2.12E+10

2.28E+10 2.40E+13- 8.59E+11

5.98E+07.. 3.21E+10 .1.44E+10

1.56E+08 -:8.82E+10 3.91E+10

1.76E+09: 3.30E+10 ..4.73E+12

1.45E+10 -7.33E+11 4.43E+11

1.03E+11 6.36E+10 -'2.24E+11

1.32E+12 6.37E+09 ,9.79E+10

1..47E+11 4.88E+10- ::8.1E+09

,-8.01E+11 2.94E+11- 3.92E+10

4.11E+14 1.04E+14 -9.05E+11

-5.O1E+12. .8.OOE+14 '4.24E+12

,,6.51E+12 -8.80E+15 1.69E+12

:2.57E+14-- -2.16E+16 - 1.36E+12

.6.88E+13 1.44E+16 9.58E+12

-2.09E+15 2.OOE+16 ' 1.07E+13

;5.29E+15 3.52E+14-,- 1.23E+12

-1.69E+15- 4.72E+15 ''1.07E+12

,3.05E+15 5.12E+15 ;1.50E+12

,:1.10E+13 3.68E+15 1.31E+12

-1.08E+13 '3.60E+15 :1.28E+12

1.01E+13 3.36E+15 .1.59E+12

1.04E+13 3.44E+15. 1.21E+12

9.45E+12 3.12E+15 1.15E+12

3.85E+15, 3.60E+14 1.55E+12

8.81E+14 -4.08E+15 1.51E+12

9.61E+14 3.84E+15. 1.39E+12 , 9.61E+14 3.84E+15 ,;1.39E+12

, 1.44E+13 - 6.80E+12 '2.86E+10

9.61E+14 3.68E+15 --1.35E+12 -3.85E+15 4.24E+14 1.51E+12

;3.77E+15 , 4.OOE+14 1.71E+12

-,1.76E+15 4.40E+14 ,1.59E+12

.1.28E+15 4.40E+14 -:1.53E+12

, C-113
Table C.50 Patnway Dose Conversion Factor 3

Total Body Bone Liver Thyroid Kidney Lung GI-LLI

H-3 4.45E+10 5.19E+07 4.45E+10 4.45E+10 4.45E+10 '4.45E+10 - 4.33E+10

C-14 2.66E+11 1.33E+12 2.66E+11- 2.66E+11 2.66E+11 2.66E+11 2.65E+11

'Fe-55 3.22E+10 1.90E+11 1.38E+11- 5.08E+07: 5.08E+07 2.64E+11 '7.75E+10

Co-60 3.70E+11 2.28E+10 1.87E+11' 2.28E+10; 2.28E+10 '2.40E+13 -2.95E+12

Ni-59 1.25E+11- 7.48E+11 2.58E+11 5.98E+07 5.98E+07 '3.21E+10 ;:5.08E+10

Ni-63 3.34E+11 1.OOE+13 6.93E+11 1.56E+08 1.56E+08 8.82E+10 1.38E+11

Sr-90 1.89E+14 7.69E+14 1.76E+09' 1.76E+09 1.76E+09 3.30E+10 1.95E+13

Nb-94 1.40E+10 1.55E+10 .1.47E+10 1.32E+10 1.46E+10 7.33E+11 1.56E+12

Tc-99 8.55E+09 1.93E+10 2.96E+10 7.60E+08' 3.64E+11 2.39E+11 9.01E+11

I-129 8.35E+12 2.94E+12 2.53E+12 6.55E+15 5.43E+12- 6.37E+09 -4.01E+11

Cs-135 .5.73E+11 1.44E+12 1.33E+12 5.08E+08 5.01E+11 1.55E+11 2.99E+10

Cs-137 5.12E+12 5.87E+12 8.03E+12 1.53E+09 2.73E+12 9.35E+11 1.49E+11

Pb-210 4.51E+13 - 1.30E+15 3.64E+14 3.51E+08 1.05E+15 1.04E+14 3.71E+12

Ra-226 2.07E+15 3.68E+15 2.07E+13 2.07E+13' 2.07E+13 8.OOE+14 1.70E+13

Ra-228 9.85E+14 1.41E+15 2.69E+13 2.76E+13' 2.69E+13 8.80E+15 6.97E+12

Ac-227 3.68E+14- 5.81E+15 8.17E+14 1.19E+08 2.61E+14 2.16E+16 5.59E+12

Th-228 2.51E+13 7.46E+14 1.26E+13 1.98E+08' 7.12E+13 1.44E+15 3.87E+13

Th-229 1.39E+15 2.85E+16 4.32E+14 1.79E+09 2.12E+15 2.OOE+16 3.72E+13

Th-230 5.40E+14 1.77E+16 1.13E+15 1.30E+08 5.32E+15 3.52E+14 4.34E+12

Th-232 2.66E+14 -7.60E+15 3.59E+14 1.08E+08 1.71E+15 4.72E+15 3.72E+12

Pa-231 4.71E+14 ;1.39E+16 3.54E+14 6.59E+08 3.10E+15 5.12E+15 5.20E+12

U-233 5.60E+12 '-9.22E+13 5.16E+07 5.16E+07 2.15E+13 3.68E+15' 4.55E+12

U-234 5.44E+12 8.82E+13 1.14E+08' 1.14E+08 2.11E+13 3.60E+15 4.46E+12

U-235 5.15E+12 8.50E+13 1.59E+09 1.59E+09 1.98E+13 3.36E+15 5.62E+12

U-236 5.22E+12 8.50E+13 9.67E+07 9.67E+07 2.03E+13 3.44E+15 4.18E+12

U-238 4.77E+12 8.11E+03 8.57E+07 8.57E+07- 1.85E+13 3.12E+15 3.99E+12

Np-237 5.24E+14 1.21E+16 1.13E+15 8.40E+08"- 3.87E+15 3.60E+14- 5.65E+12

Pu-238 2.01E+14 4.13E+15 2.81E+15 8.87E+07 8.85E+14' 4.08E+15 5.28E+12

Pu-239 2.25E+14- 4.85E+13 3.13E+15 5.17E+07 9.66E+14 3.84E+15 4.83E+12

Pu-240 2.25E+14 4.85E+15 3.13E+15 5.17E+07 9.66E+14 3.84E+15 ' 4.83E+12

Pu-241 3.06E+12 7.55E+13 4.57E+13 4.78E+0" 1.45E+13 6.80E+12' 1.01E+11

Pu-242 2.17E+14 4.53E+15 3.05E+15 6.93E+07' 9.65E+14 3.68E+15 4.72E+12

Am-241 5.08E+14 7.18E+15 6.66E+15 3.80E+08 3.87E+15 4.24E+14 5.36E+12

'Am-243 5.OOE+14 7.10E+15 6.50E+15' 6.09E+08 3.79E+15 4.OOE+14 6.22E+12

Cm-243 3.87E+14 6.20E+15 5.62E+15 2.26E+09 1.77E+15 4.40E+14- 5.63E+12

Cm-244 2.82E+14 4.43E+15 4.17E+15 7.23E+07 1.29E+15 4.40E+14 5.43E+12

C-114
Table C.51 Pathway Dose Conversion Factor 4

Total Body Bone Liver. Thyroid Kidney Lung . - .GI-LLI

H-3

C-14

Fe-55

Co-60

Ni-59

Ni-63

Sr-90

Nb-94

Tc-99

.1-129

Cs-135

Cs-137

Pb-210

Ra-226 . Ra-228

Ac-227

Th-228

Th-229

Th-230

Th-232

* Pa-231

U-233

U-234

U-235

U-236

U-238

Np-237

Pu-238

Pu-239

Pu-240

Pu-241

Pu-242

Am-241

Am-243

Cm-243

Cm-244

5. 99E+04

3. 72E+05

3. 48E+01

5. 27E+03

3.69E+03

:9.88E+03

,6. 41E+07

2. 12E+00

6. 57E+03

6. 02E+04

8.84E+03

7.90E+04

,2.58E+07

71. 33E+07

>7.15E+06

-3. 30E+04

8.38E+03

1. 95E+05

2. 84E+04

-7.48E+04

4. 72E+04

-1. 57E+04

1.53E+04

1. 44E+04

-1.47E+04

,1. 35E+05

1. 64E+04

1. 14E+03

1.27E+03

1. 27E+03

2. 21E+01

1.22E+03

3.60E+04

,3.53E+04

1. 11E+04

-8.52E+03 -

O.OOE+00 -5.99E+04,.5.99E+04 5.99E+04

1.86E+06 ,3.72E+05, 3.72E+05 3.72E+05

2.16E+02 1.49E+021 0.OOE+00 -.-OOE+00

9.00E+00. 2.39E+03 O.OOE+OO -OOOE+00

2.21E+04 7.59E+03,;,O.00E+00 O.OOE+0O

2.95E+05 2.04E+04 -O.OOE+00 O.OOE+00

2.61E+08 O.OOE+00 O.OOE+00 3.OOE+00

7.08E+00- 3.94E+00 O.OOE+00 3.89E+00

1.64E+04 2.43E+04 0.00E+00 * 3.06E+05

2.14E+04. ' 1.84E+04, 4.72E+07 3.95E+04

2.16E+04 1.99E+04 O.OOE+00 7.53E+03

.8.81E+04 1.21E+05 'O.OOE+00 4.09E+04

7;27E+06 2.08E+06' O.OOE+00 5.84E+06

3.66E+07 .4.99E+05 4.99E+05 4.99E+05

1.83E+07 6.48E+05 6.-65E+05 6.48E+05

5.55E+05 7.36E+04- O.OOE+00 2.38E+04

.2.47E+05 4.19E+03 '0.OOE+00 , 2.33E+04

-3.98E+06 5.94E+04 .O.OOE+00 --.,2.87E+05

:1.03E+06 5.84E+04 O.OOE+00 , 2.82E+05

1.15E+06 4.99E+04 0.OOE+00 2.40E+05

1.22E+06- 4.57E+04 O;OOE+OO , 2.57E+05

2.59E+05 O.OOE+00 O.OOE+00 6.03E+04

.2.48E+05 O.OOE+00. O;OOE+00 - 5.91E+04

2;38E+05. O.OOE+00 ;,O.OOE+00 5.55E+04

2.38E+05. . O.OOE+00 ,O.OOE+00 5.67E+04

.2.28E+05 , O.OOE+OO;-,O.OOE+00 . .5.20E+04

4.07E+05 .3.53E+05 .O.OOE+OO ,.1 22E+05

4.52E+04 6.37E+03. ,0.00E+00 4.87E+03

1.5.23E+04 7.05E+03- O.OOE+00 *5.39E+03

-5.23E+04' 7.05E+03 -O.OOE+00 ,- .5.39E+03

1.1OE+03 5.61E+01- O.OOE+00 1.02E+02

4.85E+04,. ,6.78E+03 ;O.OOE+00 :*5.19E+03 - 5.45E+05_,, 1.92E+05,;0.OOE+00 ;2.71E+05

5.44E+05 ,1.85E+05- 0.OOE+00 ; 2.65E+05

.1.90E+05: ,-7.15E+04,-O.OOE+00 ji 5.20E+04

1.43E+05 6.15E+04 .O.OOE+00 -- 3.98E+04,

5.99E+04

3. 72E+05

8.33E+01

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

0. OOE+00

:2. 07E+05

:O. OOE+00

2.26E+03

1. 36E+04

0. OOE+00

,.2. 93E+03

4. O1E+03

0. OOE+00

0. OOE+O0

0. OOE+00

O.OOE+00

-0.OOE+00

.O. OOE+00

,0.OOE+00

0.OOE+00

,. OOE+00

0.OOE+00

0. OOE+00

0. OOE+00

0.OOE+00

-0. OOE. 00 0.OOE+00

O.OOE+00

.O.OOE+00

O.OOE+00

0. OOE+00

O.OOE+,00

O0.OOE+0OO

5. 99E+04

3.72E+05

8. 57E+01

4.49E+04

1. 56E+03

4. 26E+03

7. 54E+06

2. 39E+04

7. 95E+05

-2. 90E+03

,4.66E+02

2. 33E+03

2. 57E+04

4. 06E+05

I;68E+05

,2.43E+04

2.81E+05

2.55E+05

3. OOE+04

:2. 55E+04

2.13E+04

1. 86E+04

.1. 82E+04

2. 32E+04

1. 71E+04

-1.63E+04

2 36E+04

4.85E+03

4.43E+03

44.43E+03

9.31E+01

4.34E+03

4.94E+04

5.79E+04

2.32E+04

2.24E+04

C-115
Table C.52 Pathway Dose Conversion Factor 5

Total Body - Bone Liver Thyroid Kidney Lung GI-LLI

H-3

C-14

Fe-55

Co-60

Ni-59

Ni-63

Sr-90

Nb-94

Tc-99

I-129

Cs-135

Cs-137

Pb-210

Ra-226

Ra-228

Ac-227

Th-228

Th-229

Th-230

Th-232

Pa-231

U-233

U-234

U-235

U-236

U-238

Np-'237

Pu-238

Pu-239

Pu-240

Pu-241

Pu-242

Am-241

Am-243

Cm-243

Cm-244

0. OOE+00

0.OOE+00

0. OOE+00

1. 54E+07

6.20E+03

0. OOE+00

3. 06E+04

9. 63E+06

0. OOE+00

1. 92E+04

0. OOE+00

3.50E+06

6. 58E+05

2. 94E+07

5. OOE+06

1. 39E+07

2.22E+07

1.45E+07

2. 13E+03

4.92E+04

4.56E+05

4.16E+06

3. 98E+05

1.50E+05

5.56E+05

5.16E+03

6.56E+04

1.93E+01

9.39E+01

9.39E+01

3.43E-01

0. OOE+00

7. 71E+04

1.86E+05

3.82E+05

5. 64E+01

0. OOE+00

0. OOE400

0. OOE+00

1. 54E+07

6.20E+03

0. OOE+00

3. 06E+04

9.63E+06

O.OOE+00

1. 92E+04

0.OOE+00

3. 50E+06

6. 58E+05

2.94E+07

5. OOE+06

1. 39E+07

2. 22E+07

1.45E+07

2.13E+03

4.92E+04

4.56E+05

4.16E+06

3.98E+05

1.50E+05

5.56E+05

5.16E+03

6.56E+04

1 .93E+01

9.39E+01

9.39E+01

3.43E-01

O.OOE+00

7. 71E+04

1.86E+05

3. 82E+05

5.64E+01

0. OOE+00

0.OOE+00

0. OOE+00

1. 54E+07

6. 20E+03

0. OOE+00

3.06E+04

9.63E+06

0. OOE+00

1. 92E+04

0.OOE+00

3. 50E+06

6. 58E+05

2. 94E+07

5. OOE+06

1.39E+07

2.22E+07

1. 45E+07

2.13E+03

4.92E+04

4.56E+05

4.16E+06:

3. 98E+05

1. 50E+05

5.56E+05

5.16E+03

6. 56E+04

1. 93E+01

9. 39E+01

9.39E+01

3.43E-01

0. OOE+00

7. 71E+04

1. 86E+05

3.82E+05

5.64E+01

0.OOE+00

0.OOE+000 - 0.OOE+00

1. 54E+07

6.03E+03

0.OOE+00

3.06E+04

9.63E+05

0. OOE+00

1. 92E+04

0. OOE+00

3. 50E+06

6. 58E+05

2.94E+07

5. OOE+06

1.39E+07

2. 22E+07

1. 45E+07

2.13E+03

4.92E+04

4.56E+05

4.16E+06

3.98E+05

1.50E+05

5.56E+05

5. 16E+03

6.56E+04

1. 93E+01

9. 39E+01

9.39E+01

3.43E-01

0. OOE+00

7.17E+04

1.86E+05:

3.82E+05

5.64E+01

0. OOE+00

O. OOE+00

0. OOE+00

1.54E+07

6.03E+03

0.OOE+00

3.06E+04

9. 63E+06

0. OOE+00

1. 92E+04

O. OOE+00

3. 50E+06

6. 58E+05

2. 94E+07

5. OOE+06

1.39E+07

2. 22E+07

1. 45E+07

2. 13E+03

4 92E+04

4.56E+05

4. 16E+06

3.98E+05

1. 50E+05

5. 56E+05

5. 16E+03

6.56E+04

1.93E+01

9.39E+01

9. 39E+01

3.43E-01

0. OOE+00

7. 71E+04

1. 86E+05

3. 82E+05

5.64E+01

0. OOE+00

0. OOE+00

0. OOE+00

1.54E+07

6.03E+03

0.OOE+00

3.06E+04

9.63E+06

0. OOE+00

1.92E+04

0. OOE+00

3. 50E+06

6. 58E+05

2.94E+07

5. OOE+06

1.39E+07

2.22E+07

1.45E+07

.2.13E+03

4.92E+04

4.56E+05

4.16E+06

3.98E+05

1.50E+05

5.56E+05

5.16E+03

6.56E+04

1. 93E+01

9.39E+01

9.39E+01

3.43E-01

0. OOE+00

7. 71E+04

1.86E+05

3.82E+05

5. 64E+01

0. OOE+00

0. OOE+00

0. OOE+00

1. 54E+07

6.03E+03

0. OOE+00

3.06E+04

9.63E+06

0. OOE+00

1.92E+04

0 OOE+00

3.50E+06

6. 58E+05

2. 94E+07

5. OOE+06

1. 39E+07

2.22E+07

1. 45E+07

2. 13E+03

4. 92E+04

4. 56E+05

4.16E+06

3. 98E+05

1. 50E+05

5.56E+05

5. 16E+03

6.56E+04

1. 93E+01

9. 39E+01

9. 39E+01

3.43E-01

0. OOE+00

7. 71E+04

1.86E+05

3. 82E+05

5.64E+01

C-116
O 

. -

I,.

Table C.53' Pathway Dose Conversion Factor 6

Total Body Bone'' Liver' ' Thyroid' Kidney Lung. GI-LLI

H-3 '2.37E,+06 1.42E-01 2.37E+06 2.37E+06 2.37E+06 2.37E+06§ 2.37E+06

C-14' 1.44E+07, 7.21E+07 1.44E+07 1.44E+07 1.44E+07'- 1.44E+07j' 1.44E+07

Fe-55 2.73E+06 - 1.24E+07 8.86E+06 8.61E+05 8.61E+05 ' 5.33E+06,. 5.45E+06

Co-60 1.43E+08 - 1.24E+08 1.33E+08 1.24E+08 1.24E+08 1. 24E+08 2.89E+08

Hi-59 8.54E+06 ~. 4.42E+07 1.61E+07 1.38E+06 131.38E+6 1.38E06j 4.41E+06

Ni-63: 1.92E+07 5.71E+08 3.96E+07 4.28E-01 4.28E-01 --2.42E+02'' 8.26E+06

Sr-90 9.56E+09 3.90E+10 8.83E+06 8.83E+06 8.83E+06 8.83E+06' 1.13E+09

Nb-94 . 3.19E+07 ' 3.20E+07 3.19E+07 3.19E+07 3.19E+07 '3.19E+07' 1.47E+08

Tc-99, , 4.19E+05 1.04E+06 1.55E+06 2.08E+00 1.95E+07.- 1.32E+07 ' 5.07E+07

I-129-' 4.29E+07 1.76E+07 1.56E+07 3.08E+10 2.94E+07 3.64E+06.- 5.54E+06

Cs-135 3.32E+07x- 8.1OE+07 7.48E+07 1.39E+00 2.83E+07 8.47E+06. 1.75E+06

Cs-137- 3.09E+08 3.44E+08 4.66E+08" 1.29E+07 1.67E+08 6.39E+07.- 2.16E+07

Pb-210 2.19E+09 6.16E+10 1.76E+10 2.03E+06 4.96E+10, 2.32E+06' 2.20E+08

Ra-226 3.26E+10 ' 8.95E+10 1.22E+09 1.22E+09 1.22E+09-. 9.83E+06'- 9.93E+08

Ra-228 -1.75E+10 4.48E+10 1.59E+09 1.63E+09 1.59E+09- 3.39E+07' 4.11E+08

Ac-227 4.48E+08 7.54E+09 1.OOE+09 4.74E+04 3.23E+08 '5.92E+07 3.30E+08

Th-,228 6.87E+07 2.OOE+09 ' 3.48E+07 9.51E+05 1.89E+08 '4.04E+O7i 2.27E+09

Th'229, i'1.59E+09 3.22E+10 4.94E+08 1.35E+07 2.33E+09 6.48E+07,- 2.07E+09

Th-230 2.32E+08 ' 8.34E+09 4.75E+08 7.61E+'05 2.29E+09' 1.73E+06 '- 2.43E+08

Th-232 6.05E+08 9.28E+09 4.04E+08 7.35E+05 ' 1.95E+09 1.37E+07'' 2.07E+08

Pa-231 6.47E+08- 1.65E+10 6.27E+08 5.84E+06 3.49E+09 1.99E+07 . 2.94E+08

U-233, ,-2.13E+08 3.51E+09 5.74E+05 5.74E+05 8.18E+08 1.07E+07i 2.33E+08

U-234 2.09E+08 3.37E+09 9.29E+05 9.29E+05 8.02E+08- 1.08E+07 2.48E+08

U-235 2.07E+08 3.24E+09 1.18E+07 1.18E+07 7.64E+08 .2.10E+07 , 3.26E+08

U-236 2.00E+08 3.22E+09 8.77E+05 8.,77E+05 7.70E+08 1.03E+07 2.33E+08

U-238 1.83E+08 3.09E+09 7.74E+05 7.74E+05 7.05E+08 - 9.32E+06 2.22E+08

Np-237 2.31E+08 5.55E+09 4.88E+08 7.13E+06 ' 1.67E+09 8.11E+06 3.26E+08

Pu-238 7.02E+07 2.74E+09 3.93E+08 1.03E+06 2.97E+08 1.22E+07 2.94E+08

Pu-239 7.77E+07 ' 3.17E+09 4.34E+08 3.93E+05 3.28E+08-''1.09E+07 2.68E+08

Pu-240 ,7.77E+07 3.17E+09 4.34E+08 3.93E+05 3.28E+08 '1.09E+07 2.68E+08

Pu-241 1.34E+06 6.64E+07 3.51E+06 1.31E-01 6.18E+06 ''1.86E+04 5.62E+06

Pu-242 7.52E+07 2.'94E+09 4.18E+08 7.67E+05 3.17E+08 1.09E+07' 2.63E+08

Am-241 '2.25E+08 ' 3.34E+09 1.19E+09 4.19E+06 - 1.66E+09 5.35E+O5<- 3.05E+08

Am-243 2. 21E+08' 3.34E+09 ' 1.15E+09' 4.84E+06 ' 1.63E+09 .5.93E+06 3.57E+08

Cm-243 1.65E+08 2.60E409, 9.97E+08 1.30E+07 7.21E+08 1.42E+07 3.27E+08

Cm-244 -1.17E+08'~' 1.'95E+09 8.44E+08 9.09E+05 5.43E+08 ' 2.12E+06 ' 3.04E+08

C-117
I IN1

Table C.54 Pathway Dose Conversion Factor 7

Total Body Bone Liver Thyroid Kidney Lung GI-LLI

H-3 2.37E+06 1.42E-01 2.37E+06 2.37E+06 2.37E+06 2.37E+06 2.37E+06

C-14 3.76E+07 1.88E+08 3.76E+07 3.76E+07 3.76E+07 3.76E+07 3.76E+07

Fe-55 4.45E+06 2.31E+07 1.63E+07, 8.61E+05 8.61E+05 9.45E+06 9.69E+06 Co-60 1.46E+08 1.24E+08 1.34E+08 1..24E+08 1.24E+08 1.23E+08' 3.11E+08 Ni-59 9.82E+06 5.20E+07 1.87E+07 1.38E+06 l.38E+06 1.38E+06 4.95E+06 Ni-63 2.26E+07 6.74E+08 4.67E+07 4.28E-01 4.28E-01 2.42E+02 9.74E+06

Sr-90 1.01E+10 4.13E+10 8.83E+06 8.83E+06 8.83E+06 8.83E+06 1.20E+09

Nb-94 3.32E+07 3.32E+07 3.27E+07 3.19E+07 3.26E+07 3.19E+07 4.50E+09

Tc-99 4.24E+05' 1.06E+06 1.57E+06 2.08E+00 1.98E+07 1.33E+07 5.14E+07

I-129 4.39E+07 1.79E+07 1.59E+07 3.16E+10 3.OOE+07 3.64E+06 5.58E+06

Cs-135 1.44E+08 3.52E+08 3.25E+08 1.39E+00 1.23E+08 3.68E+07 7.60E+06

Cs-137 1.30E+09 1.45E+09 1.98E+09 1.29E+07 6.81E+08 2.35E+08 5.1OE+07

Pb-210 2.62E+09 7.37E+10 2.11E+10 2.03E+06 5.93E+10 2.32E+06 2.63E+08

Ra-226 3.73E+10 1.03E+11 1.40E+09 1.40E+09 1.40E+09 1.09E+07 1.14E+09

Ra-228 2.01E+10 5.13E+10 1.82E+09 1.87E+09 1.82E+09 3.54E+07 4.71E+08

Ac-227 4.56E+08 7.68E+09 1.02E+09 4.74E+04 3.29E+08 5.92E+07 3.36E+08

Th-228 8.05E+07 2.35E+09 4.07E+07' 9.51E+05' 2.22E+08 4.04E+07 2.67E+09

Th-229 1.87E+09 3.79E+10 5.78E+08 1.35E+07' 2.74E+09 6.84E+07 2.44E+09

Th-230 2.72E+08 9.80E+09 5.58E+08 7.61E+05 2.69E+09 1.73E+06 2.86E+08

Th-232 7.11E+08 1.09E+10 4.75E+08 7.35E+05 2.29E+09 1.37E+07' 2.43E+08

Pa-231 6.59E+08 1.68E+10 6.38E+08 5.84E+06 3.55E+09 1.99E+07 3.OOE+08

U-233 2.17E+08 3.57E+09 5.74E+05 5.74E+05 8.32E+08 1.07E+07 2.58E+08

U-234 2.13E+08 3.43E+09 9.29E+05 9.29E+05 8.16E+08 1.08E+07 2.53E+08

U-235 2.11E+08 3.29E+09 1.18E+07 1.18E+07' 7.78E+08 2.1OE+07 3.32E+08

U-236 2.04E+08 3.28E+09 8.77E+05 8.77E+05 7.84E+08 1.03E+07 2.37E+08

U-238 1.87E+08 3.14E+09 7.74E+05 7.74E+,05 7.18E+08 9.32E+06 2.26E+08

Np-237 2.57E+08 6.19E+09 5.44E+08 7.13E+06 1.87E+09 8.11E+06 3.63E+08

Pu-238 7.49E+07 2.93E+09 4.19E+08 1.03E+06' 3.17E+08 1.22E+07 3.14E+08

Pu-239 8.29E+07 3.39E+09 4.63E+08 3.93E+05 3.51E+08 1.09E+07 2.86E+08

Pu-240 8.29E+07 3.39E+09 4.63E+08 3.93E+05 3.51E+08 1.09E+07 2.86E+08

Pu-241 1.43E+06 7.09E+07 3.74E+O6 1.31E-01 6.60E+06 1.86E+04 6.OOE+06

Pu-242 8.02E+07, 3.14E+09 4.46E+08 7.67E+05 3.38E+08 1.09E+07 2.81E+08

Am'241 3.72E+08, 5.57E+09 1.97E+09 4.19E+06 2.77E+09 5.35E+06 5.07E+08

Am-243 3.65E+08 5.57E+09 1.91E+09 4.84E+06 2.72E+09 5.93E+06 5.94E+08

Cm-243 2.09E+08 3.35E+09 1.28E+09 1.30E+07 9.26E+08 1.42E+07 4. 18E+08

Cm-244 1.51E+08 2.52E+09 1.09E+09 9.09E+05 7.OOE+08 2.12E+06 3.93E+08

i

ii

I

II, ,,

1,

C-118
nr! s rs r

Table C.55, Pathway Dose Conversion Factor 8 ,

- , .; . I .

Total Body 'Bone Liver' Thyroid : Kidney ' Lung' , GI-LLI

H-3 4.45E+10

C-14 2.66E+11

Fe-55 4.83E+10

Co-60 2.68E+12

Ni-59 1.50E+11

Ni-63 3.34E+11

Sr-90 1.89E+14

Nb-94 6.10E+11

Tc-99 8.55E+09

1-129 - 9.20E+12

'Cs-135 5.73E+11

Cs-137 5.36E+12

Pb-210 4.52E+13

Ra-226 2.07E+15

,Ra-228 9.85E+14 --Ac-227' 3.68E+14

Th-228 2.52E+13

Th-229 1.39E+15

Th-230 5.40E+14

'Th=232 2.'66E+14'

'Pa-231' 5.71E+14

U-233 5.61E+12

U-234 -5.46E+12

U-235 5.37E+12

U-236 5.24E+12

U-238 4.79E+12

,Np-237 5.24E+34

'Pu-238'7 2.01E+14

Pu-239' 2.25E+14

Pu-240 -2.25E+14

Pu-241 ;-,3.06E+12

.Pu-242 "2;17E+14

Am-241 '5.'08E+14

Am-243 5.OOE+14

Cm-243 3.87E+14

Cm-244 2.82E+14

5. 19E+07

1. 33E+12

2.06E+11

2. 34E+12

7.73E+11

1.OOE+13

7.69E+14

6. 12E+11

1. 93E+10

3. 79E+12

1. 44E+12

6. 11E+12

1. 30E+15

'3.68E+15

1. 41E+15

5.81E+15

'7.46E+14

2.85E+16

1.77E+16

7. 60E+15

1.39E+16

:9.22E+13

8.82E+13

8.52E+13

8.50E+13

8. 11E+13

1. 21E+16

4.13E+15

4.85E+15

4. 85E+15

7.55E+13

4.'53E+15

'7.18E+15

7. 10E+15

6. 20E+15

-'"4.43E+15

4.45E+10

2.66E+11

1.54E+11

2. 50E+12

2. 84E+11

6.93E+11

1.67E+11

6.11E+11'

2. 96E+10

3.38E+12

1. 33E+12

8.27E+12

3. 64E+14

2.07E+13

2.69E+13

8. 17E+14

1.26E+13

4. 32E+14

1. 13E+15

3.59E+14

5.55E+14

1.08E+10

1.'75E+10

2. 21E+11

1. 65E+10

1. 45E+10

1. 13E+15

2. 81E+15

3. 13E+15

3.'13E+15,

4. 57E+13

3.-05E+15 -- 6.66E+15

6.50E+15

5. 62E+15

4. 17E+15

'4;45E+10

2. 66E+11

1.16E+10'

2.34E+12

2. 58E+10

1. 56E+08

1.'67E+11

6. 10E+11

7.60E+08

6. 55E+15

5.08E+08

2.42E+11

3. 84E+10

2. 07E+13'

2.76E+13

1. OOE+09

1. 80E+10

2.55E+11

1. 43E+10

1. 38E+10

1. 1OE+11

1. 08E+10

' 1.75E+10

2. 21E+11

1. 65E+10

''1.45E+10

1. 34E+11

1. 92E+10

'7.40E+09

7.40E+09

'4:78E+07

1.44E+10

7.'87E+10

9. 10E+10

2.44E+11

1.71E+10

I 

A 

Arr.IA A AEr ., Id% . A -%,sr, I t%

. .

4.45E+10

,2.66E+11

1. 61E+10

2.34E+12

2. 58E+10

1. 56E+08

1.67E+11

6. 11E+11

3. 64E+11

6. 28E+12

5.01E+11

'2.97E+12

1. 05E+15

2.07E+13

2.69E+13

2.61E+14

7.'12E+13

2. 12E+15

5. 32E+15

1. 71E+15

3.10E+15

'2.15E+13

' 2. 11E+13

'2.OOE+13

2. 03E+13

1.85E+13

3. 87E+15

8.85E+14

'9. 66E+14

9.66E+14

1.'45E+13

9.65E+14

-3.87E+15

3.79E+15

1. 77E+15

1.29E+15

4.45E+10-

2. 66E+11

2.80E+11'

2.63E+12

5. 78E+10

8.82E+10

1. 98E+11

1. 33E+12

2.39E+11

8.57E+11

1. 55E+11

1. 18E+12

1. 04E+14

-8. OOE+14

8.80E+15

2. 16E+16

1. 44E+16

2. OOE+16

3. 52E+14

4.72E+15

5. 12E+15

3. 68E+15

3. 60E+15

3 36E+15

3.44E+15

3.12E+15

3. 60E+14

4.08E+15

3.84E+15

3.84E+15

6.80E+12

3. 68E+15

4. 24E+14

4. OOE+14

4.40E+14

4. 40E+14

4. 33E+10

2. 65E+11

9.36E+10

5. 27E+12

7.65E+10

1. 38E+11

1. 96E+13

2.15E+12

9. 01E+11

1. 25E+12

2.99E+10

3.89E+11

3. 75E+12

1. 70E+13

6.97E+12

5.59E+12

3.87E+13

3.75E+13

4. 36E+12

3.73E+12

5..31E+12

4. 56E+12

4.47E+12

5.84E+12

4. 20E+12

4. OOE+12

5. 79E+12

5.30E+12

4.83E+12

4.83E+12

1. 01E+11

4. 74E+12

5.43E+12

6. 31E+12

5. 87E+12

5.45E+12

C-119
I I i11

In the comments on the draft EIS and proposed Part 61 regulation, there was

some interest'in the concentration'limits for and impact calculations involving these- two nuclides. Based upon this interest NRC staff determined that a

reexamination of the potential radiotoxicity of the two nuclides was warrented.

This reexamination was carried out by a contractor (Ref. 29) and the results

of this reexamination are summaried here.

In this effort, two basic questions regarding iodine-129 disposal were

addressed:

* whether natural iodine will provide a-means of limiting exposures

(especially thyroid exposures) which may result from the nearsurface disposal of waste containing I-129; and

* whether it is possible to provide artificial dilution by disposing

certain waste streams together with material containing high concentrations of natural iodine.

Regarding carbon-14, the basic question addressed was:

* whether the exposures calculated through consumption of food (which

are dominated by a pathway involving root uptake of C-14 out of

soil) are over-conservative.

The remainder of this section is divided as follows. First, C-14 and-I-129

isotopic characteristics and projected generation rates are discussed. Second,

a short review of available information of environmental characteristics,

chemistry, and uptake of these two isotopes is presented. This is followed by

a discussion and conclusions.

6.1. Isotope Characteristics and Generation

This section presents a brief discussion of the radio-characteristics of the

above two isotopes plus an estimate of their occurrence in waste streams. As

discussed elsewhere in this EIS, routine radioactive waste expected to-'be-generated between the years 1980-,and 2000 has been separated into 37 waste, streams

and each waste stream has been characterized in terms of its physical,

chemical and radiological properties. These waste streams are summarized in

Table C.56.

The concentrations of I-129 and C-14 in the waste streams utilized in the radiological impact assessment's performed for.the draft EIS were calculated using

the methodologies presented in reference 10. Since the publication of reference 10, however, additional information has been compiled on the total radioactivity content of process waste streams generated by light water power reactors (i.e., Group I waste streams in Table C.56). This new information has

been discussed in Section 4 of this appendix (Ref. 11). This new information

does not alter the comparative concentrations of the radionuclides considered

(e.g., the percent of the total activity that is I-129). However, it does

indicate an upward adjustment of the average radioactive concentrations presented in reference 10. Both the previous and the updated concentrations of

I-129 and C-14 are summarized below.

C-120
Table C.56 Waste Streams Considered in Analyses

.Waste'Stream

*;~ .p - G ro LR P r .,. .':;'.Gro'up 'I:LWR* rc ess Wastes"

I - -I.

PWR** Ion Exchange Resins

PWR Concentrated Liquids

,PWR Filter.Sludges

PWR Filter Cartridges

BWR**, Ion Exchange Resins.. .:

BWR. Concentrated Liquids

BWR Filter Sludges

. I I

I  ..,

I

* Group II: Trash

PWR Compactible Trash .

PWR Noncompactible Trash .-.BWR Compactible Trash

BWR Noncompactible Trash

Fuel Fabrication Compactible Trash

Fuel Fabrication Noncompactible Trash

. Institutional-Trash (large facilities)a, c

Institutional Trash-(small facilities)

IndustrialSS# Trash (large facilities).

Industrial SS Trash (small facilities)

Industrial,-Low Act. Trash (large facilities):-

Industrial Low Act. Trash (small facilities)

Symbol.

P-IXRESIN

P-CONCLIQ

, P-FSLUDGE

P-FCARTRGIB-IXRESIN,.

,;:B-CONCLIQ

B-FSLUDGE,,

:,P-.COTRASH

-P-NCTRASH;,

.,...B-'COTRASH.

B-NCTRASH

F-COTRASH

F-NCTRASH'

.,.-,I-COTRASH

..-I+COTRASH

;N-SSTRASH.;

-N+SSTRASH

-N-LOTRASH-.-

N+LOTRASH

i Group III: Low Specific Act'ivity Wastes ;

..-. Fuel Fabrication Process Wastes F

UF6 Process Wastes. - - - U

Institutional ,LSV## Waste (large facilities) ., Institutional LSV Waste (small facilities)..,., I

Institutional Liquid Waste (large facilities) I

--Institutional -Liquid Waste,(small,facilities) I .:Institutional , Biowaste, (smallfacilities) -.I

Institutional Biowaste (small f acilities)

Industrial SS Waste. N

Industrial Low Activity ,Waste.+-- N

Group:IV: Special':Wastes

LWR.Nonfuel Reactor CoreComponents L

LWR Decontamination.Resins . - L

Waste from Isotope Production Facilities' N

Tritium Production Waste ,.N

Accelerator Targets N

Sealed Sources . N 

Industrial High Activity Waste :-N

MOXt Facility Decontamination Waste F

-PROCESS -

-PROCESS

-LIQSCVL

+LIQSCVL

-ABSLIQD

+ABSLIQD .

-BIOWAST

+BIOWAST-

-SSWASTE.

N-LOWASTE,;

L-NFRCOMP

.-DECONRS',-

N-ISOPROD

N-TRITIUM .

I-TARGETS

1-SOURCES

N-NIGHACT

F-PUDECON

XLWR: Light Water Reactor

**PWR: Pressurized Water Reactor

***BWR:'Boiling Water Reactor - -#SS:' Source and Special Nuclear Material'' '

##LSV: Liquid Scintillation Vial

tMOX: Mixed Oxide (PuO 2+UO2 )

C-121
IIodine-129

Iodine-129 is produced by fission. It decays by beta emission to xenon-129

with a half-life of 1.7x107 years. The emitted beta particles have a maximum

energy of 0.150 MeV. The beta decay is accompanied by the emission of xenon

x-rays and conversion electrons with enerqies of 0.005 MeV and 0.034 MeV,

respectively (Ref. 10).

Fission of U-128, U-235, and Pu-239 is the principal means through which I-129

is generated. Consequently, only wastes associated with light water reactors

and wastes "generated by medical isotope production facilities are expected to

contain significant amounts of I-129. These concentrations'and expected generation rates are presented in Table C.57 (Refs. 10, 11).

Utilizing the information in Table C.57 and the I-129 specific activity of

1.63 x 10 4 Ci/g, expected I-129 generation rates may be estimated. These are

about 83.44 grams of I-129 per GW(e)-yr for PWRs, 379.75 grams of I-129 per

GW(e)-yr for BWRs, and 343.56 grams of I-129 per year from other sources.

Carbon-14

Carbon-14 is produced by neutron capture from nitrogen-14 -- i.e., the reaction

[N-14 (n, p) C-14]. Naturallyroccuring-C-147is produced by cosmic radiation

in the upper atmosphere. Carbon-14 decays by beta'emission to N-14 with a

half-life of 5730 years.' The maximum energy of'the emitted beta particles is

0.156 MeV. No other radiations are produced (Ref. 10).'

Carbon-14 is estimated to be present in most of the waste streams considered

in reference 10 and the draft EIS. In addition to waste-routinely generated

by light-water reactors, it is projected to be present in 'significant quantities in several institutional waste streams as'well as waste streams from

industrial sources.' These concentrations and expected generation rates are

presented in Table C.58.

This table can be utilized to calculate the generation rates of C-14 in

routine radioactive waste. Using the specific activity-of C-14 of 4.46 Ci/g,

assuming that the same L-NFRCOMP volume is generated in both PWRs and BWRs

(there is insufficient data for a more accurate estimate), and ignoring the

N-SOURCES waste stream since its physical', chemical, and radiological properties are very unrepresentative of the properties of other streams in the

group, expected C-14 generation rates may be-estimated. These are about 0.8

Ci (0.18 g) per GW(e)-yr for PWRs', 0.575 Ci (0.13 g) per GW(e)-yr for BWRs,

and 33.1 Ci (7.46 g) per year from other sources.

6.2 Review of Available Information

This section presents a very brief review of the environmental characteristics,

chemistry, and uptake of I-129 and C-14.

6.2.1 Iodine-129

Two matters herein discussed include: (1) the environmental concentrations of

natural stable and radioactive iodine, and (2) iodine chemistry and uptake.

C-122
Table C.57 tstimated I-129 Generation Rates

-- Total

Waste Activities (Ci/m3) Volumes (m3 Activity

stream (Ref. 10) (Ref.-11) per GW(e)-yr) (Ci/GW(e)-yr)

-P-IXRESIN

'P-CONCLIQ

-:P-FSLUDGE

-'P-FCARTRG

'P-COTRASH

,P-NCTRASH

2.44E-06.

3.16E-06

2.37E-06

1. 06E-06

2.78E-07'

6.41E-06-

5.

2.

1.

NC

NC

NC

60E-04 17.6

43E-05- 123.0

72E-05 2.2

* 11.0

215.0,

110.0.

Totals 478.

9.85E-03

' 2.99E-03

-' 3.79E-05

'1.17E-05

*6. OOE-05

6.75E-04

1. 36E-02

B-IXRESIN

B-CONCLIQ

B-FSLUDGE

'B-COTRASH

, ., 

2.04E-04

6. 65E-06

1. 33E-06

7.14E-07

1. 15E-04

2.47E-04

2. OOE-05:

1.42E-04

NC

NC

Totals

80.7

223.0

179.0-

221.0

105.0

808.7

1.99E-02 - 4.47E-03

2.54E-02

1.58E-04 , 1.20E-02

5.37E-02

I: 

Total

Waste Activities (Ci/m 3) Volumes** Activity

stream (Ref. 10) (Ref. -11) (m3/year) (Ci/year)

L-DECONRS 3.34E-05 NC - 1666 5.56E-02

N-ISOPROD 2.72E-06 NC 148 4.03E-04

Totals 1814 - 5.60E-02

Source: References 10 and 11.

*NC: No change.

**Volumes are for the year 1980.-

*C-123
.Table C.58 Estimated C-14 Generation Rates

Total

Waste Activities (Ci/m3) Volumes (m3 Activity

stream (Ref. 10) (Ref. 11) per GW(e)-yr) (Ci/GW(e)-yr)

P-IXRESIN 9.74E-05 2.23E-02 17.6 3.92E-01

P-CONCLIQ 1.27E-04 9.77E-04 123.0 1.20E-01

P-FSLUDGE 9.55E-05 6.93E-04 2.2 1.53E-03

P-FCARTRG 4.25E-05 NC 11.0 4.68E-04

P-COTRASH 1.12E-05 NC 215.0 2.40E-03

P-NCTRASH 2.57E-04 NC 110.0 2.83E-02

Subtotals 478-.8 5.45E-O

B-IXRESIN 1.19E-03 1.44E-03 80.7 1.16E-01

B-CONCLIQ 3.89E-05 1.17E-04 223.0- 2.60E-02

B-FSLUDGE 7.78E-06 8.31E-04 179.0 1.49E-01

B-COTRASH 1.12E-07 NC 221.0 2.48E-03

B-NCTRASH 2.57E-04 NC 105.0 2.70E-02

Subtotals 808.7 3.19E-01

L-NFRCOMP 2.59E-01 NC 0.99 2.56E-01

Total

Waste Activities (Ci/m 3) Volumes** Activity

stream (Ref. 10) (Ref. 11) (m3/year) (Ci/year)

L-DECONRS 5.12E-05 NC 1666 8.53E-01

N-ISOPROD 4.51E-05 NC 148 6.68E-03

I-COTRASH 5.26E-03 NC 4014 2.11E+01

N-LOTRASH*** 1.64E-03 NC 1445 2.37E+00

I-LQSCNVL*** 2.51E-04 NC 1402 3.50E-01

I-ABSLIQD*** 8.15E-03 NC 159 1.29E+O0

I-BIOWAST*** 1.01E-02 NC 448 4.52E+00

N-LOWASTE 9.35E-04 NC 1719 1.61E+00

N-HIGHACT 1.32E-02 NC 74.4 9.82E-01

Subtotals 11075.4 3.31E+01

N-SOURCES 5.75E+01 NC 5.3 304.75

Source: References 10 and 11.

*NC: No change

**Volumes are for the year 1980.

***Includes wastes from both large and small facilities.

C-124
* Environmental Concentrations

.The ' distribution of iodine within.natural soil and rock;.is.discussed.in refer- ,. ence 30. -It pointed out inthis reference that-the averageiodineconcentrations in volcanic rocks range from 22 to 1900 parts per billion,:(ppb),.and that

the average value for igneous rocks probably falls-within the range of 75 to

150 ppb., Experiments to leach thisiodine from volcanic-rocks usually-removed

bless than 20,percent of.the total iodine in the rock.

The abundance of iodine in:sedimentary rocks,. however, isonAhe -order of about

1000. times that of igneous rocks. Table C.59 presentsvalues for iodine as

obtained from reference 30. It is also pointed out in reference 30 that while

the Iodine content of:marine sediments depends to:a large extent on-the carbon ..content , of theusediments, marine sediments,are~much.richer in iodine than .sedimentary . rocks.. Experiments that examined iodine'bonding determined that

most of.,the iodine in marine sediments was surface-adsorbed.or covalent-bonded

to carbon, and that about 23 percent could be extracted with organic solvents

(Ref. 30).

I I . .. ., -

1 '.

. - 1 ,

. . I i j ,

I.. ;--1 ,; -: . , 

!: - . I

:. Table C.59 Iodine in Sedimentary Rocks ,. 'I.T

Sedimentary Rock I, ppm

* Sandstones, 11, Bashkiria, USSR 0.15-1.5

Sandstone, white,

Klondyke, MO

Sandstone, red,

Potsdam, NY

Argillaceous sandstone,

Portageville, NY

0.068

0.14

37.6

Argillaceous shale,

' Rochester, NY.

Calcareous-shale,.

*Lima, NY

Limestones, -6,. . Paleozoic;,:OK

Sediments,''>-

SW Barents Sea

.13,0

: ' 38:0 '''

. 3.

; 4.2 -

405

; Source: - Reference 30. -' ' *~~1 * -A - - * -. Of

I

C-125
There appears to be a marked increase in soil iodine content compared to the

rocks that they are derived from. Reference 30 quotes an investigation by

Vinogradov (1959)' who estimates the average iodine'content'of'soils as being

about 5 ppm,:and who also suggests that much of the soil iodine is atmospherically derived.-

The iodine'concentration within surface and groundwaters-is also a variable

and, except for highly mineralized water or brines, is normally found in tiny

concentrations. For example, reference 31 classifies iodine as being a minor

constituent in potable water, where in the listed classification system a

"minor constituent'!" is one that falls within a range of 0.0001 to:0.1 ppm.

Measurements-of preatomic age materials indicate I-129/I-127 ratios of about

2x10 15 forvery:oldiodine rich ores, 3x10 12.for-chemicals and lxlO 10 for

biological materials..-According to reference 32, a nominal base-figure value

of 3x1O 12 for pre-1945 potassium iodine appears to be in good agreement with

the values used by other investigators.

During the early 1950's, the I-129/I-127 radio in the biosphere increased from

3x10' 2 to lxlO 6, or by about a factor of a million. This was due to atmospheric testing and to insufficient time for I-129 released from this source to

come to equilibrium with I-127 in the environment. By the late 1950's and

early 1960's, samples of various biological materials gave values for the

I-129/I-127 ratios in the range of 1xlO 10 to 1x1O 8 (Ref. 32). A more recent

EPA measurement of bovine thyroids from Vermont and New Hampshire gave results

on the order of 5x10 5 uCi/gm of total iodine which equates to an I-129/I-127

ratio of 3x10 7 (Ref. 33).

Similar measurements of iodines have been made in more recent studies. One

study indicates that around existing nuclear facilities, the-atom ratio of

I-129 to that of I-127 measured in biota ranges up to 3.9x10 5 in thyroid

tissues of animals other than bovine.(deer around the Hanford Reservation),

and up to 1.7x1O 6 in bovine thyroid tissues (around Northeastern Oregon)

(Ref. 34). In yet another study, bovine thyrod tissues have been observed to

have an I-129/I-127 atom ratio of 4.5xlO 7 around the Savannah River Plant

(Ref. 35).

Iodine Chemistry and Uptake

Iodine is a nonmetallic element belonging to the halogen family. There are 24

known isotopes of iodine with 18 of these isotopes having half-lives of less

than 1 day. The only stable isotope is I-127. Although iodine is known in

the -1, +1, +3, +5, and +7 oxidation states', its ususal occurrance is in the

-1 (iodide, I ) state in fresh waters and as .iodate (IO) in marine or similar

aqueous environments (Refs. 30, 36). Iodine, like the other halogens, is very

active chemically, but is usually less violent in its action. Iodine is also

a volatile element, subliming at atmospheric pressures without melting.

A considerable proportion of iodine occurs in organic forms which are much

less reactive than elemental iodine (Ref. 37). Most compounds of iodine are

very soluble. Some of the insoluble or sparingly soluble compounds include

iodides of Pb and Pd, the hypoiodites of Ag and Hg, and Ba periodates (Ref. 30).

In normal soils, the concentration of most of the elements (Pb, Pd, Ag, Hg, and

Ba) with which iodine forms insoluble compounds is very low. Iodine in aqueous

solutions free from oxidizing agents generally exists as iodide (Ref. 30).

C-126
.-

Soil-to-plant concentration factors (uptake factors) are obtained from

experiments on nts ts grown in the laboratory or in the field. Concentration

*factors are'also estimated from the statistical correlation between the con-

'centration 'in a crop and the cumulative' ground deposition. The' uptake factor

of an isotope in a given crop varies in a very complex manner with soil

texture' and other soil -properties such as cation'exchange capacity, exchangeable'calcium, 'exchangeable potassium,',pH, and organic'matter content. It will

vary with crop'variety, stage of growth, and plant part as well as with

experimental conditions such as the manner in which the isotope was introduced

into soil.

I

In general, ions of any element present in the soil will pass into the root

system whether or not they are essential for plant growth (Ref. 38). The

major factor' governing the availability, of radionuclides to plants in soils is

the'solubility of the nuclides in the soil matrix. Plant'roots-absorb only

the'soluble 'species 'of metals'(Ref. 37). Iodine is not concentrated by

vegetation 'and is 'classified by Menzel (Ref. 39),as in 'the, "not 'concentrated"

class. That is, the ratio of ppm in 'dry plant material to ppm'dry soil is

0.1-10.0. 'In addition, 'iodine is not listed among the trace elements (micronutrients)' necessary for plant'growth (Ref. 39).

The radioiodine uptake by plants'from soil is influenced by several factors

as with any element.' It has been shown with stable iodine that uptake

increases with increasing concentration in the substrate, that uptake

increases when soil pH was reduced down to about 4 from a higher pH, and that

the relative order of uptake by plant species is bean '> tomato > barley >

Russian thistle (Ref. 38).

5

'' Elevated levels'of soil iodine have also'been shown to be toxic to plants.

',:.The most s'ensitive-studied'was' lettuce which was drastically affected at all

levels of applied :iodine'above 10 ppm. Spinach and 'radish were also -studied

and'showed~a slightdepression'of shoot growth 'with' added iodine-(Ref.. 29).

In general, airborne release of '-129 has been considered'to b6e'an insignificant

-,source'of'hazar'd . from the root uptake pathway becaus`e6of its low activity.

However,'because of its extremely 'long 'half-life, 'it has'the potential for

| *accumulation-1'in~'t environme'nt from,long-'term chroniczrel ases (Rf3)

Generally the root uptake of 1-129 from soils by vegetation.is considered to

"be minor relative to that obtained from direct foliar deposition.' The contribu-

'tionof "soil' I-129 -to 'c6ncentrations' of 'radioiodine in vegetables growing in

such contaminated soils'would-not be'significant'until several tens of years

deposited iodine had accumulated in the soil (Ref. 40).

Also of interest is the amount of iodine that can be-present in the thyroid and

the exposures resulting from'the radioactive component of this iodine. Normally

the adultthyroid has 'an'iodine content "of 7 to `8 milligrams although this

varies greatlyin individuals' (Ref. 41-43). The' normal thyroid 'takes up approx-

'imately,80-100 micrograms of'iodide'per day(Ref.[47). Most of-this iodine in

thyroid'is expected to be 'iatural iodine-which would,,not result in exposures.

A study on I-129 dosages to thyroid as a function of -'the total I-129 administered indicated that dosages up to 1 nCi resulted in doses of 7 mrem/nCi;

however, there was a marked reduction in dose'between'10nCi'(5.8 mrem/nCi)

and 1000 nCi (0.8 mrem/nCi) (Ref. 44).

C-127
I T

It is known that insufficient thyroid iodine content is undesirable and that

humans in many parts of, the world' suffer from goiters due to. deficiencies in

iodine ingestion-from available food. sources (Ref. 45)' The' inverse, of this

condition (i.e.,'administration'of large amounts of iodine) may also have an

upper bound. For many years, one of the mitigative measures used to reduce

thyroid exposures to persons potentially exposed to releases of radiolodine

has been to administer large amounts of stable iodine, usually in the form of

potassium iodine (KI) tablets. The National Council on Radiation Protection

and Measurements (NCRP) has published reports on the function of stable iodine

as a blocking mechanism, including recommended dosages and possible side

effects (Refs. 46, 47).

For example, Ref. 47 states that "toxic reactions from a brief course of

iodide treatment should be rare. A few individuals, however', are.sensitive

and may develop angioedema. Chronic iodide poisoning, or iodism, can also

occur but only after ingesting iodides for'several weeks or longer. 'Symptoms

and signs include sialadenitis, rhinitis, conjunctivitis, headache, drug

fever, and skin rashes. In either acute or chronic toxicity reactions,

withdrawal of the medication and supportive care is all that is necessary and

symptoms disappear with a few days." Reference 46 states that it has been

determined that toxic effects of iodide are not noted with doses of 100 mg of

iodine (130 mg of KI) per day given to children over a course of years and

that iodide goiter will result only after daily doses of several hundred

milligrams of iodide administered for years.

6.2.2 Carbon-14

To calculate impacts from ingestion of carbon-14 through food pathways, two

basic mechanism for transfer of C-14 into and onto plants must be considered:

(1) airborne settling of C'14 onto plant' surfaces and' uptake through photosynthesis, and' (2) uptake through'plant 'roots. Numerical factors used in the

EIS to estimate transfer, into plants by these mechanisms we're those taken from

U.S. NRC Regulatory Guide 1.109 (Ref. 48)'. A 'review'was' made of current work

on these pathway mechanisms to determine whether updated transfer factors were

appropriate for use'within the impacts analysis methodology.' This review

suggested that a newer "specific activity model" may be a more appropriate

model to use in connection with atmospheric releases of carbon-14 (Ref. 29).

The review also suggested that the soil-to-plant uptake factors in Regulatory

Guide 1.109 (Ref. 48) should be updated but that little or no work was being

performed to determine more appropriate uptake factors (Ref. 29). A brief

description of the result's of this review follows:

Specific Activity Model

The specific activity model (Refs. 49, 50)' is a more recent model used by some

investigators, to calculate total body exposure:iresulting from all pathways due

to airborne C-14.' The' basic assumption of the model is that the fraction of

-the carbon pool in man's tissues which is maintained by ingestion approaches

equilibrium consistent with the concentrations of airborne carbon at all sites

of food production.

The basic structure of the specifc activity model is a multiplicative chain

of parameters which relate the atmospheric specific activity (activity of the

C-128
radionuclide per mass of stable element) to the,'specific activity in the body.

Dose equivalents are predicted using a dose rate factorappropriate for steadystate conditions when the'body specific activity has approached equilibrium

(Ref. '50). Under conditions of complete equilibrium:

Annual Dose j = (SpA)Y(DFR)i. .

where (SpA). is the atmosphere specdific~activity relative to the radionuclide

i of concerA and its stable element', and (DFR).. is the conversion'factor that

relates-the body specific activty of radionuclide i and its stable element to

a dose equivalent rate at equilibrium for a given organ tissue-or the whole body

(g). For C-14 the specific activity may be estimated using:

SpA = x/c

where x is the ground-level air concentration of.C-14 (pCi/m 3),'and c-is the

concentration of airborne-carbon,0g/m3). The factor (DFR).. for C-14 for

total-body ingestion is given as 2.1x1O 1 mrem/yr per pCi/O3 carbon.,

A comparison between the whole body dose equivalent estimates for C-14 is made

using the. specific activity approach (Ref. 50) and the terrestrial pathway

models 'inRegulatory Guide,1.109 (Ref. 48).' A concentration of 1 pCi/m 3 was

assumed for ground level atmosphere-having a carbon content of,0.16 gm/m3. This results inm'a ground level atmospheric'specific activity of 6.25;pCi of

C-14 per~gram carbon. The maximum dose equivalent then becomes 1.3 mrem.

In Regulatory Guide 1.109 (Ref. 48) the specific activity approach is'used to

estimate the transfer' of C-14 from air to vegetation. The concentration of C-14

per mass of vegetation (C. ) is estimated'in Regulatory Guide 1.109 by multiplying the vegetation specifc activity by the fraction'of the total'mass' of the

edible tissue of .vegetation.assumed.to be composed of carbon. -For vegetation, -. -,,11% of the total fresh mass-of~edible'.tis'sue'is assumed to-be carbon.7 1Using the

Regulatory Guide'1.109 approach, a 1 pCi/i 3, concentration'of Ct14 inthe aboveground atmosphere would result min'a calculated vegetation-concentratidn of:

C-14 (1 pCi/m3)(1/0.16 g/m3)(0.11)(100.g/kg), ,

= 690 pCi/kg fresh weight. '

The terrestrial pathway models addressed in'Regu'atory'Guide-1 109 include:

air-vegetables-man, air-vegetation-milk-man, air-vegetation-meat-man, air-all

terrestrial pathways-man. The results of these calculations-are summarized

below along with calculated the dose from the specific acivity model.

Pathway , , Annual doseequivalent.

Air-vegetables-man ' ' 2.3x10 1 -

Air-vegetation-milk-man 7.3x10. 2

Air-vegetation-meat-man 6.7x10 2

Air-all terrestrial pathways-man 3.7x10

All pathways 1.3

C-129
The above assumes a 1 pCi/M 3 concentration of C-14 in aboveground air. The

last entry in the table is the'specific'activity model'estimate which assumes

complete'equilibrium between the'atmospheric specific activity and'the human

body. Thus', the calculated dose equivalent represents a maximum upper-limit

estimate.

The above comparison indicates that the calculated annual dose for all

terrestrial pathways using the Regulatory Guide approach is approximately 28%

of that using the specific activty model.

The second question which must be addressed, the accuracy and the viability of

the soil-to-plant uptake'factor utilized in the impact analyses, is not

answered by the specific activity' model. This uptake factor is implicitly

included in the model.

Uptake Through Plant Roots

One of'the difficulties in addressing exposures resulting from near-surface

disposal of C-14 is that much of the uptake of carbon by'a plant is assumed to

occur through root uptake and utilizes a conservative soil-to-plant transfer

factor (B. ) factor set forth-'in Regulatory Guide 1.109 (Ref. 48). The soilto-plant transfer factors (B. ) in' Regulatory Guide 1.109 were mainly calculated

from the handbook assembled y Ng, et al. (Ref. 51). They were calculated as

the ratio of the average coucentratfionin food derived from plants to that in

dry soil.' While correct for the overwhelming majority of elements for which

the soil-root system is the primary pathway (for most, the only pathway) for

incorporation of radionuclides into the plant system, the primary pathway for

incorporation of carbon in plants is the photosynthesis of CO2 in air (Ref. 45).

Thus, this "transfer factor" for carbon-14 simply represents a ratio of plant

carbon to soil-carbon and nothing more.

References 52 and 53 confirm that most carbon is obtained by higher plants from

the air in the form'of CO2. Reference 53 further quotes a reference (Livingston

and Beall 1934) that concludes that as much as 5 percent or more of the CO2

used by plant's'came from the soil. In 'ancther quote, reference 53 points out

that investigations by Kursanov (1954) estimated that under their conditions,

the abount of CO2 absorbed by the roots is as much as 25 percent of that taken

up from the atmosphere by the leaves.

6.3 Discussion and Conclusions

6.3.1 Iodine-129

Discussion

As discussed in the introduction to Section 5.6, there are two basic questions

herein addressed. These questions are:

C-130
(1) Whether natural iodine will provide a means of limiting exposures

(especially thyroid exposures) which may result from thie near-surface

disposal of waste containing I-129; and

. ' (2). Whether'it is possible to provide artificial dilution by disposing

certain wastes-together-with material containing high concentrations of

natural'iodine.

In'addition to-the above two questibns,.tthere are two additional-questions

that have an important'bearing on the issue of concern. These two questions

. are:

(3) Whether natural and/or.artificially introduced stable iodine will behave

chemically in a manner similar to radioiodine.in.the pathways of concern; .. - ,, and

(4) Assuming'that stable and radioactive iodine chemically behave'identically,

whether the atom ratio 1-129/1-127 resulting from either natural or

artificially introduced stable iodine will remain approximately constant

along the.pathways of.concern and thereby provide dilution.

" ,Regarding the-first question, some interest was raised by Appendix B of reference,54.which 'stated that provided.that the atom ratio of, I-129 to.natural .iodine in'the tnyroid was le'ss than about',1/48 (0:02), exposures to the thyroid

'would be inherently limited to levels less than 1500 mrem/yr. .'Reference 54 ..then performed a calculation assuming a natural iodine concentration in soil of

1 ppm and 'delivery of 175 grams of I-129 shipped to a disposal site per year,

and concluded'that thyroid exposures due to I-129 would be. indeed 'limited to -

levels less than 1500,mrem/yr.: This calculation has been used as a basis by

.some for stating that I-129 need never be considered a problem in low-level

waste disposal.

- A calculation similar to the above may be performed using data assembled for .the EIS.' It was calculated in Section 5.6.1 that the expected generation

rates.of I-129 'in routine radioactive'waste are about 83.44-grams of I-129 . per GW(e)-yr for PWRs, 379.75.grams of I-129 perGW(e)-yr. for BWRs, and

343;56 grams.of.I-129 per year from'other sources'. Utilizing the'estimated

average capacity during the'yeais'1980 to 2000 of 87,798 MW(e).for PWRs and

.41,612 MW(e) for BWRs, and accounting for the contrib'utioh.bf other waste

sources (a factor 'of 1.72 is incorporated to account.for the 'assumied linear

increase in the generation rate' of waste from other 'sources), an average total

generation rate of about 23,718 grams of 1-129 per year can be calculated.

. This value corresponds to an activity of about 3.78 Ci/year. Normalizing

these generation rates to the waste volumes assumed in waste spectrum 1 for

the 'reference disposal facility results in a value of 6552 gm/yr (1.04 Ci/yr).

If'one assumes that the wastes containing.iodine'are disposed together, and

''considering the-average annual waste volumes of 42,038 m3/year from'all PWRs,

33,652 m3/year from all BWRs, and'an average of 3120 m3/year (1814 x 1.72)

'from other sources (totaling 78,810 m3/year), one may calculate an average concentration of. about 0.30 g/m3 of 1-129 or 4.91x10 5 Ci/m3. This value is about

X 150 'time 'less than the concentration 'limit of 0.008 Ci/m 3 for Class 'A wastes

given in the proposed Part 61 rule. However, if the average annual generation

rate of all wastes (including those that are not expected to contain I-129) is

C-131
f ill

considered (about 1.72x1O5 m3/year), this yields an average concentration of

0.14 g/m3 of I-129, or 2.24x10 5 Ci/m 3.

Soldat (Ref. 43) agrees that an atom ratio of 1:48 for I-129/I-127 is-required

to limit thyroid exposures to 1500 mrem/year. This results in a'concentration

of 3.6 pCi of I-129'per gram of total iodine. Utilizing the specific activity

of I-129 of 1.63x10 4 Ci/g, this yields a ratio of about 22 mg of I-129 per

gram of total, iodine. It would also be reasonable to assume that if this ratio

were 1:960, the thyroid exposures would be limited to 75 mrem/year.

For purposes of illustration, assume an average concentration of total iodine

in a soil/waste mixture of 5 ppm (i.e., 5x1O grams iodine per gram of soil/

waste mixture which is'not a conservative assumption) and a soil/waste mixture

density of 1.6 g/cm3. This yields a concentration of total iodine of about

8 g/m3. This value, when used in conjunction with the values previously calculated for I-129 of 0.30 g/m3 for wastes expected to contain I-129 and -

0.14 g/m3 for all wastes, would result in I-129/I-127 ratios of about 37.5 mg

and 17.5 mg of I-129 per gram of stable iodine, respectively.

Further, assuming that I-127'in the soil/waste mixture behaves in a manner

chemically similar-to the I-129 in the waste,,this calculation implies that

natural dilution of iodine will not limit exposures to thyroid to levels below

1500 mrem/year if I-129 is assumed to be distributed throughout the wastes

expected to contain I-129. However, it will limit exposures to below 1500 mrem/

year if it is assumed to be distributed throughout all the wastes expected to

be generated, which is a questionable premise'. In neither case will natural

dilution limit exposures to'levels below 75 mrem/yr. Moreover, the assumption

that the average concentration of natural iodine in the soil/waste mixture

will be as high as 5 ppm is not conservative. The'average concentration of

natural iodine in soil is highly variable and the actual value is likely to

be lower.

One big difference between the above calculation and the one in reference 54

is the assumed amount of I-129 delivered to'the disposal site. Appendix B of

reference'54 contains an assumption'that 175 grams of I-129 is shipped to a

disposal site per year. This is considerably different than the above calculated value of 6552 g/year shipped to the reference disposal site., Given this

difference, additional information is needed on the actual content of I-129

within waste streams. This is being accomplished through an ongoing NRC contract involving measurements of a number of specific radionuclides (including

1-129) within several waste streams.

Another problem is that both the above analysis and the one in reference 54

assume that the I-127 in the soil/waste mixture behaves in a chemically similar

manner to the I-129 in the waste. This is a questionable premise since neither

the chemical form of the I-129 in the waste nor the chemical form of the I-127

in the waste and soil are known. Assuming that stable iodine is to dilute

uptake of I-129, then the stable iodine must be in a form which will dissolve

at the same rate as the I-129 in waste and thus pass into groundwater for

direct consumption or uptake by plant roots. There is no experimental

evidence to support this supposition. In the case of'natural iodine:in soil,

one can't help but suspect that the natural iodine is mostly in an insoluble

form, since if it was in a soluble form it would have been long ago 'leached

out of soils. As'noted in Section 6.2.1, experiments to leach natural iodine

C-132
would have tojleach at the same rate and pass through groundwater at the same

speed as the radioactive iodine in order to arrive'at the biota access.loca-

'tion'at the' same time.'Assuming that"this is the' case, about 15 grams of

..,natural iodine-127 per m3 of waste would be required to.reduce the.estimated

average6'-129 concentrations (about 0.30 ,grams per m3 'of waste.expected to

containA -129) to an I-129/I-127 atom r'atio dilution of 1:48,(i.e. a dose

'limit of 1500 mrem/year). .About '300 grams of natrual iodine per m, of waste

would requiredd'to 'reduce exposur'es-to .75 mrem/yr.

However,' the natural iodine thus' employed would have to behave in a chemical

manner-similar to the'I-129 contained 16 the waste. ' The''chemical :form of 1-129

in the waste is not known at the present time. It appears that due'to the

..complex behavior.of.iodine both in the plants and soil and the various organic

and.inorganic.'comrpounds it frms, a.controlled'series of experiments 'would be

'useful as'a means of testing this, approach..

Concl usion ., -

II

It;'ithus,'appears from.the preceeding disc'ussiontha he'answer to''thet'first

question-posed above is 'probably negative, and 'the answer .to th6 second question

is maybe. 'It''cannot be assumed that 'natural iodine'within wast6 and'soil will

automatically'in''all cases limit thryoid exposuresito 'levels less than 1500

mrem/yr. However, if the chemical form of I-129 in the' waste' is'deter'mined, and

if a chemically compatible artificial .iodine dilution.material is employed, it

may be possible to limit thyroid exposures'fromi 1-129-to' levels consistent with ,- --. ... A .- - C. - '-- .. III--

The'answer to the..thir"d and'fourth-questions'posed'above are implicit'in the

above conclusions., Itjis.unlikely''that natural.'iodine'insoil 'will'.behave in

a chemically s'imilar'"mannerto'I-129'in'7the was'te (natural-iodine w6uld likely

: 'have been leached,-outof the soil ..long'ago if it were-easily soluble'in water;

.; alsos'ee' Section'6.2.1.and'the solubility'of natural iodine). -It may'be'

poss'ible, however,'to add'cobmpounds'of iodine'that 'will'behave in'alchemically

similar manner to the contained I-129. The answer to the fourth question is

-believed to~be positive; no evidence would be located-to ascertain the opposite

conclusion., As long'as the solubility and.chemical'behavior of'iodine in the

waste and-outside the waste are'.compatible, it'is'i'easonable to.ass'um'e that . they will be,present'in'the pthwys'to 'biota('including groundwater)- in the

same proportion. . .

In the impact analyses methodologies.' ut'ilized in this-EIS, no criedit'was assumed

due to the presence of stable iodine in'the soil/waste mixture. 'As it is pointed

-out above, NRC staff be'lieves that''prior to taking such'credit,'the 'chemical

'form' of. the 1-129.in the waste and'of.the.I-127 .in''the soil'sh'ould'be ascertained.

.Consequently, ,this que'stion can .not'b'e addressed and resolved 'in'Ithis.EIS.

However, if a fraction'of.thte natural 'stable' iodine in'the soil is demonstrated

to be similar in sblubility and chemic'al behaviorto' the.I-129 i'n the waste,

then this ratio may be utilized'to reducie the' calculated ;exposures..,,,

6.3.2 Carbon-14 ' '

Incorporating the specific activity model into the impacts analysis methodology

used for this EIS is expected to have a negligible effect on the exposures

.C-133
calculated for carbon-14. This is because the calculated exposures due to

carbon-14'are dominated (by about a factor of 100) by'the' root-uptake pathway.

Unfortunately' there has been relatively little interest by' investigators to

provide an updated soil-to-plant root transfer factor. Although it is known

that most carbon'taken up by plants is through leaves, little data could be

found to be able' to predict the relative fractional amount' that would be taken

up by roots, and under what physical and chemical conditions. For example, it

is known that carbon dioxide will dissolve in groundwater (Ref. 55) (and thus

become available for root uptake), but it is difficult to predict the extent

of this occurrence.

The limited data that could be collected suggests that from 5 to 25 percent of

plant carbon'is taken'up by plant''roots. 'Assuming that the soil-to-plant

transfer factor for C-14 was reduced by a factor of 10, then C-14' exposures

due to food pathways would also be reduced by a factor of 10. Similarly,

groundwater impacts at the well water access points would be reduced by a

factor of 4 while surface water impacts would be reduced by a factor of 1.5.

Given the limited data;'available, however, no credit for theepotential reduction in the 'root-uptake transfer factor was taken at this time. 'It appears

that a more detailed study on C-14 uptake under different environmental conditions is warrented.'

7. DISPOSAL LIMITS FOR TRANSURANIC ISOTOPES

As part of the work performed for the draft EIS 'and proposed Part 61 regulation,

a waste classification system was developed.which.involved 3 waste classes:

Class A, Class B, and Class'C. Limits fo'r a'number of individual transuranic

isotopes were calculated.' These.individual isotopic limits were then reduced

to a limit for the isotope Pu-241 (a beta emitter) plus a cumulative limit for

all alpha emitting transuranic isotopes having half-lives greater than 5 years.

These limits were 350 nCi/gm for Pu-241 and 10 nCi/gm for the alpha-emitting

nuclides.

For the final EIS and-Part 61 rule'tfie limits calculated for the''classification system have been"'reassessed. In particular, a more refined method for

considering'the ingrowth of transuranic daughter. products (see Section 5.2)

has been incorporated into the impact analysis methodology. In'addition, commenters to the proposed Part 61 rule have offered a suggestion-'that waste which

> has been disposed as Class C waste will be covered by at least 5 meters of earth

' -;' ~ and loiqer'activity Class B'waste a'nd'therefore--should'still b'e difficult to con-

|-'' ' tact even after 500 years. Other commenters have suggested that NRC consider

'dilution by lower activity waste''strea'ms. To determine impacts of disposal of

'larger'amounts-of transuranic waste,''after calculating'classification limits

based 'upon the more refined method for determining decay chain ingrowth, the

calculated Class C waste disposal limits have been raised by a factor of 10.

'This additional''factor of 10 credit has been assumed for Class C waste disposal to'account for the dilution provided by the earth and other waste. The

disposal limits thus obtained are listed below in units of nCi/cm3 for individual radionuclides.

C-134
TRU classification limits (nCi/cm3)

Isotope Class A Class B Class C

Np-237 4.1 340 41

Pu-238 28 2300 6800

Pu-239/40 10.4 860 105

Pu-241 270 22,300 4900

Pu-242 11 610 110

Am-241 7.9 920 140

Am-243 6.6 550 68

Cm-243 62 5,100 78,000

Cm-244 540 45,000 41,000

As shown, for many isotopes the limits calculated for Class B disposal exceed

those calculated for Class C disposal. These isotopes include Np-237,: Pu-239/40,

Pu-242, Am-241, Am-243, and Cm-244. ,This is because the potential hazard of

these isotopes outlasts the assumed effectiveness of the improved waste form

or packaging. Reliance is instead placed upon the 5 meter (or equivalent)

intruder barrier to limit impacts. This means that for these isotopes (and

for most waste containing TRU nuclides in concentrations exceeding the Class A

limit), there are really no Class B limits. The classification system for

transuranics and other lonc-lived isotopes can be thus simplified to.two

classes: Class A and Class C. This will ease the effort on the part of

licensees to comply with the waste classification system.

Another way to ease the process of compliance with the waste classification

system would be to combine-the individual isotopic limits into a single limit

to be complied with.:' In general, it is-believed that fewer individual limits

to compare against--(fewpr specific isotopes to determine) will result in

easier compliance. As before, it is believed that the easiest approach will

be to separate the limit for Pu-241 from the limit for the longer-lived transuranic isotopes. Plutonium-241 is a beta emitter having a 13.2 year halflife and decaying to Am-241. It comprises a significant fraction of the transuranic activity observed in waste streams generated by nuclear power plants

and other NRC licensees. Another short-lived isotope comprising a significant

fraction of the activity observed in the above waste streams is Cm-242. This

is an alpha emitter having a 162.5 day half-life and decaying to Pu-238.

Setting separate limits for Pu-241 and Cm-242 is expected to ease compliance

for most NRC licensees. Setting out separate limits for other isotopes is not

believed at this time to be generally cost effective for most NRC licensees.

The isotopic limits for the remaining longer-lived transuranic isotopes are as

follows (in nCi/cm3):

C-135
Concentration limits for alphaemitting TRU isotopes (nCi/cm3)

Isotope Class A Class C

Np-237 4.1 41

Pu-238 28 6800

Pu-239/40 10.4 105

Pu-242 11 110

Am-241 7.9 140

Am-243 6.6 68

Cm-243 62 78,000

Cm-244 540 41,000

One option for reducing the above list of nuclides to a single gross alpha

limit would be to assume the limit for the most restrictive isotope. This

would be Np-237. This is believed to be overly restrictive, however, since

Np-237 is' projected to be contained in-low-level waste in only very tiny

quantities. A better approach would be to consider the isotopic distribution

expected to be in typical low-level waste streams. This distribution is

expected to be different for individual waste streams. Based upon the data

base assembled for the Part 61 EIS, the equivalent gross alpha limits for both

waste classes for the waste streams expected to contain the above transuranic

nuclides are as follows:

Equivalent gross alpha

concentration limits (nCi/cm3)

Waste stream Class A Class C

P-IXRESIN 14.6 230

P-CONCLIQ 14.6 233

P-FSLUDGE 9.6 178

P-FCARTRG 13.1 177

B-IXRESIN 15.6 244

B-CONCLIQ 18.8 571

B-FSLUDGE 17.6 295

P-COTRASH 14.0 207

P-NCTRASH 14.0 207

B-COTRASH 18.1 300

B-NCTRASH 18.1 300

L-DECONRS 13.8 173

N-ISOPROD 25.4 621

F-PUDECON 10.3 113

C-136
These numbers were calculated from the relationship:

isotopic fraction

7- isotopic-class Imit

-In this relationship, the "isotopic fraction As the,..fractional amount-of a

.Particula'r-iso'tope'across the total.-alpha-emitting transuranic Jsotooe,,distributionwithinthe waste-stream-considered., The "isotopiccl 'ass-limit" is

the classification limit obtained for thatparticularisotope as summarized

above.

As shown,,theequivalent Class A gross alphalimit for the..wastestreams

-contain-transu'anics is ina fairly'narrow-ran e--i expected to 3 e.,,from about .10 to about.,20 nCi/cm Only.onestream-exceeds 20 nCi/cm The spread for

Class C waste streams is larger,.,-How'ever,,'only two waste.sireams are above

300 nCi/cm3. The other 12 streams range from 100 to 300 nCi/CM3. Given the

ranges calculated, it is apparent that some judgment is required in converting

to working gross alpha limits for the two classes.

Historically, limits for transuranic waste disposal have been given in units

of nCi/gm rather than nCi/cm3. The density of waste streams expected to

contain transuranics will fluctuate. This range in densities may be possibly

as much as one to six gm/cm3, but are believed to be typically in the range of

one to two gM/CM3. This would result in a range of 5-20 nCi/gm for Class A

waste and 50-300 nCi/gm for Class C waste. An average value of 1.6 gm/cm3

would result in a range of about 6 to 13 nCi/gm3 for Class A waste and 60 to

190 nCi/gm for Class C waste.

Thus, it appears from the above considerations that a reasonable generic grossalpha limit for commercial waste disposal would be 10 nCi/gm for Class A waste

and 100 nCi/gm for Class C waste. There may be a number of other considerations which could be cited as rationales for raising or lowering the above

limits. These can include differences in waste masses, dilution by lower

activity wastes, increased use of volume reduction techniques, "de minimus"

waste disposal, improvements in health physics considerations, and sitespecific environmental conditions. However, it would appear that there are

about an equal number of tendencies one way as another. For example, the

potential for dilution by lower activity waste streams may be offset by

improvements in health physics, site-specific environmental conditions and

increased use of volume reduction.

In the analysis for the Part 61 EIS, NRC staff have determined that the 10 nCi/gm

limit for Class A waste and the 100 nCi/gm limit for Class C waste will result

in a high probability that the intruder performance objective will not be

exceeded at any new site. With the above limits, the waste volume-averaged

intruder impacts calculated at 500 years after facility closure ranged in the

final EIS from about 8 to 170 mrem per year to bone over the 4 regional disposal sites. The calculated impacts appear to be sufficiently below the

500 mrem/year limit that the intruder performance objective should be achievable at all new disposal sites considering uncertainties.

C-137
- - -

The 10 and 100 nCi/gmlimits also appearto be'reasonable from institutional

considerations. Commercial disposal sites will De generally located on land

owned by the States. Unlike federal installations, the disposal sites will

probably not be part of a nuge nuclear installation'or a national laboratory,

but will be a few hundred acres existing by themselves.' Thus, inadvertent

intrusion may be more likely at commercial sites. The sentiment has been

expressed by'several persons that the states should really only be responsible

,for disposal of.wastes which-are expected to-be fairly innocuous after a few

'hundred years.: This means that' the sites would be mainly restricted to short

to moderately-lived-radionuclides and contain only small quantities of longlived toxic radionuclides. The 10 and 100 nCi/gm limits are in keeping with

this sentiment. Ten nCi/gm would be the limit for disposal within a very few

feet of the earth's surface;. where contact by humans has a reasonable possibility of occurrence. An 'extra requirement of 5 meters disposal depth for

Class C waste provides additional protection in compensation for the higher

allowable Class C waste transuranic limit.

C-138
-

REFERENCES

1. February 9, 1982 letter fromiLeslie.Poppe, Corporate Health Physicist,

Chem-Nuclear.Systems, Inc.,' to R. Dale Smith, U.S. NRC.

-2. March'18, 1982 letter ,from Paul 'Cahill, Director, Office-of Federal

Activities, U.S. Environmental Protection Agency, to Samuel'Chilk,

Secretary of the Commission, U.S. NRC.

3. March 10, 1982 telephone conversation between -Leslie7Poppe, Corporate

Health Physicist, Chem-Nuclear Systems, Inc., and G. W. Roles, U.S. NRC.

4. March 17, 1982 telephone conversation between'Leslie Poppe, Corporate

Health Physicist, Chem-Nuclear Systems, Inc., and G. W. Roles, U.S. NRC.

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NRC6. March 4, 1982 letter from J. Howard Kittel, Manager, Office of Waste

*' '--Management Programs, Argonne-National Laboratory, to G. W. Roles, U.S.

NRC. -'

7. Denhem, D. H., et al., Technology, Safety and Costs of Decommissioning a

Reference Low-Level Waste Burial Ground: Environmental Surveillance

Programs, NUREG/CR-0570 Addendum, Pacific Northwest Laboratory for U.S.

NRC, July 1981.

8. Witherspoon, J. P., Technoloqy and Cost of Termination Surveys :

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9. January 13, 1982 letter from J. Scoville, President, U.S. Ecology, to

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10. Wild, R. E., et. al., Data-Base for Radioactive Waste Management,

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Transuranic Waste,- hTbruary 1980. -. -

13. February 14, 1980 Memo from W. J. Dircks, NRC Executive Director for

Operations;-to the Commission. - - '

14. March 10, 1982 survey letter from Leland C. Rouse, Chief, Advanced Fuel

and Spent Fuel Licensing Branch, U.S. NRC.

C-139
l Al! n

15. March 29, 1982 letter from Michael A. Austin, Manager, Technical Control,

Babcock and Wilcox, to G. W. Roles, U.S. NRC.

16. March 25, 1982 letter from M. E. Remley, Director, Health, Safety and

Radiation Services, Rockwell International, to G. W. Roles, U.S. NRC.

17. March 26, 1982 letter from R. Nilson, Manager, Corporate Licensing, Exxon

Nuclear Company, Inc., to G. W. Roles, U.S. NRC.

18. March 31, 1982 letter from C. J. Michel, Administrative Manager, Nuclear

Fuel Services, Inc., to G. W. Roles, U.S. NRC.

19. March 17, 1982 letter from Steve Hoadley, Radiation Safety Officer,

Monsanto Research Corporation, to G. W. Roles, U.S. NRC.

20. April 2, 1982 letter from G. E. Cunningham, Senior Licensing Engineer,

General Electric Company, to G. W. Roles, U.S. NRC.

21. April 8, 1982 letter from W. J. Shelley, Vice-President, Nuclear Licensing

and Regulation, Kerr-McGee Corporation, to L. C. Rouse, U.S. NRC.

22. April 21, 1982 letter from J. D. Yesso, Group Leader, Nuclear Materials

Technology Section, Battelle Columbus Laboratories, to G. W. Roles, U.S.

NRC.

23. March 25, 1980 Memo from W. J. Dircks, NRC Executive Director for

Operations, to the Commission.

24. February 12, 1982 telephone conversation between A. J. Nardi, Westinghouse,

and G. W. Roles, U.S. NRC.

25. U. S. Department of Energy, Technology for Commercial Radioactive Waste

Management, DOE/ET-0028, May 1979.

26. Oztunali, 0. I., et. al., Data Base for Radioactive Waste Management,

Volume 3: Impacts AnaTyses Methodology Report, NUREG/CR-1759, Dames and

Mo-ore, Inc. for U.S. NRC, November 1981.-

27. Strenge, D. L., T. J. Bander, MILDOS - A Computer Program for Calculating

Environmental Radiation Doses from Uranium Recovery Operations, NUREG!

CR-2011, Pacific Northwest Laboratory for U.S. NRC, April 1981.

28. Picazo, E. D., et. al., Specification Report for Evaporator Concentrate

Solidification at the Maxey Flats Low-Level Radioactive Waste Disposal

Site, Dames and Moore, Inc. for Kentucky Department for National

Resources and Environment Protection, April 2, 1981.

29. Oztunali, O.I., et al., Report on Reexamination of C-14 and I-129

Radiotoxicity, Dames and Moore, Inc. report, June 1982.

30. Ames, L.L., and D. Rai, Radionuclide Interactions with Soil and

Rock Media, Vol. 1, EPA 520/6-78-007, 1978.

C-140
31. Todd, K.D. (ed), The Water Encyclopedia, 1970.;

32. Nuclear Fuel Services, Inc., Environmental Report, NFS Reprocessing

Plant, U.S NRC Docket Number 50-201, 1973.

33. Magno, P. J., et. al., Iodine-129 in'the Environment Around a Nuclear

-- Fuel Reprocessing Plant,4Off~ice of Radiation Programs,-.Environmental

Protection Agency, 1972.

34. Brauer, J. K., et. al.,!"Natural Iodine and Iodine-129 in Mammalian

*Thyroids and Environmental Samples"Taken From-Sites in the USA'"

Environmental Surveillance Around Nuclear Installations, Vol. II,

Proceedings of a Symposium Warsaw 5-9 November 1973, IAEA Publication,

IAEA-TM-180/34, 1974.--

35. Palms, J.-M., and V. R. Veluri, Summary of-the Analysis Associated

with the Environmental Impact of 'TeI Released by the Barnwell Nuclear

Fuel-Plant, Emory University.Report EMP-122, July_1974. ;

36. Kirk-Othmer, Encyclopedia of Chemical Technology, John Wiley:& Sons, Inc.,

1966.

37. McKay, HA.C., Background Considerations in the Immobilization-of

Volatile Radionuclides," International Atomic Agency, IAEA-SAM-245/8,

pp. 59-78, 1980.

38. Nishita, H. et. al., Radionuclide Uptake by Plants, USNRC Report

NUREG/CR-0336, 1978.

39.' Menzel, R.-G., "Radioactivity'in Plants," in Disposal of Residues on

Land, Proceedings of the National Conference of Disposal of Residues on

Land, EPA, 1976.

: 40. Book, S. A. et al., "Thyroidal'Burdens of I-129 From Various Dietary

Sources," Health Physics, 32, 143-148, 1977.

41. Shaprio, J., Radiation Protection: A Guide for Scientists and

Physicians, Harvard University Press, Cambridge, Massachusetts, 1981.

42. UNSCEAR, Sources and Effects of Ionizing Radiation, United Nations Publication, E.77IX.1, 1977.

43. Soldat, J. K., "Radiation Doses from Iodine-129 in the Environment,"

Health Physics, 30, 61, 1976.

44. Book, S. A., "Iodine 129: Limits to Radiological Dose," Health Physics,

32, 321, 1977.

45. Bidwell, R. G. S., Plant Physiology, MacMillan Publishing Co., Inc.,

New York, 1974.

46. National Council on Radiation Protection and Measurements, Protection

of the Thyroid Gland in the Event of Releases of Radioiodine, NCRP

Report No. 55, August 1977.

C-141
47. National Council on Radiation Protection and Measurements; Management of

Persons Accidentally Contaminated-with Radionuclides, NCRP Report No.65,

Apri l 1980.-

43. U.S. Nuclear Regulatory Commission, Calculations of Annual Doses to Man

from Routine Releases of Reactor Effluents for the Purpose of Evaluating

Compliance with 10 CFR Part 50, Appendix I, Draft Regulatory Guide 1.109,

March 1976.

49. Killough, G. G. and P. S. Rohwer, "A New Look at the Dosimetry of 14C

Released to the Atomosohere as Carbon Dioxide," Health Physics, 34,

141-159, 1978.

50. Hoffman, F. 0., R. H. Gardner and K. F. Eckerman, Variability in Dose

Estimates Associated with the Food Chain Transport and Ingestion of

Selected Radionuclides, Draft Report NUREG/CR-2612, 1982.

51. Ng, Y. C., et al., Prediction of the Maximum Dosage to-Man from the

Fallout of Nuclear Devices Handbook for Estimating the Maximum Internal

Dose from Radionuclides-Released to the Biosphere, USAEC Report,

UCRL-5013, Part IV, 1968.

52. Cronquist, A., Basic Botany, Harper & Row, Publishers, New York,- 1973.

53. Gibbs, M., "Radioisotopes in Plants: Absorption and Incorporation of 14C

in Cell Metabolism," in A Symposium on Radioisotopes in the Biosphere,

Univeristy of Minnesota, 1960.

54. Leddicotte, G. W., et al., "Suggested Quantity and Concentration Limits

to be Applied to Key Isotopes in Shallow Land Burial," Management of

Low-Level Radioactive Waste, Volume 2, Pergamon Press, New York, 1979.

55. U. S. Environmental Protection Agency, Draft Environmental Impact Statement on the Proposed Guidelines for the Landfill Disposal of Solid Waste,

Office of So-ird Waste, March 1979.

C-142
APPENDIX D

COMPUTER CODES USED FOR FINAL ENVIRONMENTAL

IMPACT STATEMENT CALCULATIONS
TABLE OF CONTENTS

Page

1. i-INTRODUCTION ................. D

2.'' -REVISED WASTE CLASSIFICATION TESTPROCEDURE . D-1

3. 'OTHER FEATURES OF THE COMPUTER CODES ........... ................... D-13

4. -'STRUCTURE OF INPUT AND OUTPUT FILES ......... ........ D-18

5. -INPUT .................................... D-18

6. .,INPUT INDICES... i D-18

7. INPUT FORMATS............................ D-25

8. LISTING OF COMPUTER CODES AND DATA FILES . .............. D-32
. I May

LIST OF TABLES

Page

D.1 Assignments for Logical Units .D-18

D.2 Disposal Technology Indices (IRDC)..-19

D.3 Waste Form Behavior Indices (ISPC) ......................... D-20

D.4 Other Indices for Impact Codes ............................ D-22

D.5 Waste Streams ............................. D-24

D.6 List of Reference CLST Sets ............................. D-26
LIST OF FIGURES

Page

0.1 Revised Waste Classification Test Procedure ............... D-3

D.2 Example Total Activity Distribution ......................... D-8
- - -

'APPENDIX D '"

COMPUTER CODES USED FOR FINAL.ENVIRONMENTAL IMPACT

-STATEMENT CALCULATIONS '

1. 'INTRODUCTION - , ,-.

This'appendix presents two 'computier code'-th'at we're used to perform cakulations

for the final EIS, as well"as the' data files used to provide input parameters

to the codes.' Five computer codes--INTRUDE,"OPTIONS,'GRWATER,' INVERSI, 'andr

INVERSW--were prepared and used'ih'the draft EIS and a description'of these''

codes is provided in Appendix'H to the draft EIS.- Th is'appendix 'discusses

revised versions of the OPTIONS and GRWATER'code's, termed the OPTIONR and

GRWATRR codes," respectiv'ely.' Theise''two revised codes- are very similar to the

existing 'OPTIONS and GRWATER codes in-terms'of subroutines, variable names`,'

and calculational procedures. The principal difference from the existing . OPTIONS and GRWATER'codes 'is-in the manner in which'the wa'ste classification'

test' rocedure is handled.' 'Another difference is the ability'in the two

revised codes to address'w'astes having distributed 'activities.~''

The remainder'of'this 'appendix discusses in more detail the'waste classifica-

"tion test procedure' used in' the two 'revised codes, 'followed'by 'a' brief discussion of other.'features' of the revised code's' The~ structure 'of 'the''data 'files'

read'to 'both'codes is 'then 'discussed, followed by 'a presentation 'of .the input

variables requiredto 'run the c'ode's. Finally', listings 'of the codes and accompanying' data' files are presented.-. ' . i

2. REVISED WASTE CLASSIFICATION TEST PROCEDURE

In'the-'existing'OPTIONS and'GRWATER c'omputer codes, a waste classification test

procedure':is 'use"d -'in which the characteristics of individual waste streams are

first'fixed (through a"choice''of a'waste 'spectrum), the intrudgr impacts of-'

each'of the' waste streams are calculated for different disposal 'technologies'

(e.g., regular disposal, la'e'ring',Uuse of a hdt'waste facility), 'the resulting

impacts compared to 'a numerical dose'-limitation crite'rion'(e-.'g.,'-500 mrem/yr

'whole 'body), the''waste'stream'fifirnally ''and clas'sifie'd'- 'Following this, impact

measures such as costs, volume-averaged intruder impacts, and"groundwater impacts

are calculated. Thisywaste classification test procedure is described in Sect'ion' 14, Appendix"'H, of'fthe''draft'EIS,'and-was particularly useful during the

analyses performed in the draft EIS to determine performance objectives for

low-level waste'dispoial: "' -I - '

''Thee t'wo~'rvised ~computer 1codes--OPTIONR' and'GRWATRR--are ve'ry similar to'<OPTIONS

and GRWATER but utilize a different waste-classification test-procedure. This

was done to increase the flexibility of the.impact analysis methodology and to

provide a mor6'`'fined analysis 'ofparticular Part'61'technical-'criteria. Rather

than comparing potential inadvertent intruder exposures to a set of dose limitation criteria, 'the'revised test procedure compares-individuai-radionuclide concentrations in waste streams toa set of limiting radionuclide concentrations

in'particulaitwaste';cl'a'sses." The Wdist'e'streami is"then classified (e.g.,' as

Class A, Class B, or Class C). Depending upon the classificatibon'status of

D-1'
film

the waste, there may be a requirement to process the waste into a stable form,

dispose of it in a stabilized manner at a disposal facility, or stabilize the

waste and dispose of it uising an intruder barrier. The waste stream may even

be classified as being not generally acceptable for near-surface disposal.

A flow diagram of the waste classification test procedure used in the OPTIONR

and GRWATRR computer codes is provided as Figure D.1. Briefly, the test procedure operates as follows. First, a waste spectrum is chosen which establishes particular characteristics for each waste stream, particularly'the

radionuclide concentrations and whether the waste stream is in a stable.form..:

The radionuclide.concentrations for each waste stream-are then compared against

a set of limiting concentrations for Class A waste disposal. If the waste

stream concentrations are less than the limiting Class A waste concentrations,

then the waste stream-is.classified as Class A~waste and a determination must.

be made as to whether the waste-. stream is' stable or, unstable... If unstable, it

is disposed of into a Class.A'unstable.waste disposal unit.., If stable, it is

disposed of into a disposal unit along with stable Class B and C wastes.:

If the radionuclide concentrations i'n the- waste stream.exceed1 the limiting

Class A waste concentrations, then the waste stream must be stabilized and -

tested to determine if it meets limiting concentrations for Class B and C wastes.

Such waste stabilization may be accomplished for a given waste stream by either

specifying a particular improvement in waste form and packaging or by a particular disposal facility, design.. 'The. test procedure compares the waste radionuclide concentrationsagainst the Class B and C.limits,using a number of

possible stable-waste forms and packages or facility designs which.achieve.

stabilization. If there are no such waste forms, packaging techniques,. or

facility designs which can achieve a stable waste having radionuclide concentrations less than the Class C values, then the waste stream is considered

not acceptable for near-surface disposal;..

It may be noted.that if the waste.stream exceeds the Class C waste limits,.then

the testing procedure includes the.provision' for~optional disposal by a disposal

method giving greater confinement than near-surface disposal. In the draft

EIS.and data base, this has been generically referred to as a "hot waste facility."

To date, no disposal criteria has been-developed-by NRC for disposal by such,

improved methods'over near-surface disposal. However,.inclusion of this option

in the codes at this time will help to develop future such criteria (as necessary)

in a rapid manner.

The mechanisms of the test procedure involves a-number of concepts, including:

o The use of lists of limiting'radionuclide concentrations.

o Use of a waste classification alternative based upon existing disposal

facility license conditions.

o Optional stabilization through disposal facility design.

o Optional stabilization through waste form or packaging.

o Use-of-the IMOD array to track the classification status of waste

streams.

D- 2
+ - # # 4 j s

; ' Start ' . .

'\ III

 119>N_ '.

* Accept as Accept as 3

Class C? CasB

Accetpas

:Class A. unstable

(3 :Class A. wasteformor packagingstable

© :Class B. stabilized through disposal facility design

(i) :Class'B. waste form or vackaging stable

( :Class C, stabilized through disposal facility design

. . (:Class,C; waste form or packaging stable

( :Hot waste, stabilized through disposal facility design

(a) :Hot waste, waste form or packaging stable

* :Waste spectrum must be changed and the testing

procedure restarted

Figure D.1 Revised Waste Classification Test Procedure

D-3
a Waste streams having distributed activities.

o Use of two different disposal technologies at the same disposal

facility.

Lists of Radionuclide Concentrations. As discussed above, the revised waste

classification test procedure compares radionuclide concentrations in waste

streams against lists of limiting radionuclide concentrations in each waste

class. An alternative approach which could have been incorporated into the

classification scheme would be to conmare-potential inadvertent intruder

impacts against a set of limiting dose'limitation criteria. (This latter

approach was used in the draft EIS in order to arrive at preferred overall

performance objectives for waste disposal.) The former approach has been

used, however, since it allows more precise consideration of potential

impacts of different waste classification values for different radionuclides

and it is also more directly related'to requirements to be met by a waste

generator.

In practice, the limiting concentrations are stored within the codes using the

array CLST(4,16). The four rows of the array signify limiting concentrations

of Class A, Class B, Class C, and hot waste facility waste, respectively. (If

there is no hot waste facility--i.e.,' IH-0-'-then the fourth row is ignored.)

The 16 columns signify the limiting radionuclide concentrations for each waste

class. The first 14 columns correspond to'the first 14 radionuclides of the

23 considered in the EIS impacts analysis methodology. These are, in order,

H-3, C-14, Fe-55, Ni-59, Co-60, Ni-63, Nb-94, Sr-90, Tc-99, I-129, Cs-135,

Cs-137, U-235, and U-238. The 15th column corresponds to the limit (in pCi/cm3)

for alpha-emitting transuranic nuclides. (Generally an assumption is made that

the waste density is equal to 1.6 gm/cm3.) The 16th column corresponds to the

limit (in pCi/cm3) for Pu-241.

The decision as to whether a particular waste stream falls within a particular

waste class is made using a sum-of-the-fractions rule similar to that described

in Table II of 10 CFR Part 20. This rule"states that the sum of the ratios of

the isotopic concentrations in a particular waste stream to the limiting concentrations in a'particular waste class shall not exceed unity. That is, a value

Al is calculated which is equal to:

Ca Cb Cc

A1l + + U + ..., where

Ca b~ b

Ca' Cb, and Cc = concentrations in waste of isotopes a, b, and c; and'

Ca, C1, and Cc = limiting concentrations in.a given waste class for

isotopes a, b, and c.

If Al < 1, then the waste stream is classified as being acceptable for'the waste

class considered. If Al > 1, then the waste stream is classified as being

unacceptable for the waste class considered.

Use of a Waste Classification Alternative. As an option, an alternative procedure is ircluded for determining limiting concentrations for Class A waste.

This alteriative is included to provide an assessment of the impacts of existing

license ccnditions at LLW disposal facilities. In this alternative, the normal

D-4
sum-of-the-fractions rule is not. applied.- Rather, a limit of 1 PCi/cm3 of nontransuranic isotopes having half lives:greater than 5 years.is applied to light

water reactor (LWR) process waste streams (filter sludges,-ion exchange resins,

,solidified-concentrated liquids, and cartridge:filters) as.well as waste from.

isotope-production facilities. For such waste 'streams, if,.the concentration

of any nontransuranic isotope having a half life greater than 5.years exceeds-:

1 PCi/cm3, then-the waste stream.,is-.not.acceptable..as Class A waste and must--

be stabilized prior to disposal. For'all.other waste-streams, no Class A con--.

centration limits are imposed. s. 3 . '' -

Under this alternative,-classification of transuranic radionuclides.is also;.'-

modified. Current license conditions impose a 10 nCi/gm limit on transuranic

waste disposal. .-These license conditions generally. allow' disposal of trans-.

uranics up to the 10 nCi/gm limit as.long-as-the transifranics are homogeneously

distributed through the.waste., Surface contaminated-materials are often-pro--

hibited.. Occasionally,- homogeneously-contaminated waste streams such as ion, 2

'exchange:resins are;generated which'exceed the 1O.nCi/gm limit, almost always-;.

due to short-lived alpha emitters such.as Cm-242 (163 day half life) or.to Pu-241,

which is a-beta-emitter having a 13.2 year half life... In'such cases,'waste ...-

generators-wil~l either. dilute such waste'with.lower activity waste (still retaining a homogeneous mixture) or allow the short lived radionuclides to decay to.'

levels less than 10 nCi/gm prior to shipment.

Not.to account-for.the above practices would incorrectly-skew the, results ofthe cost-benefittanalysis in favor-of the final Part.61 requirements.: To pro-.

vide asmore accurate analysis under this alternative classification scheme,

therefore, the Pu-241 concentrations within LWR process-waste-streams and

isotope production waste are..decayed to their alpha-emitting equivalents.. 'No

such decay is performed for trash or other'waste streams which cannot be

assumed to be homogeneously.contaminated and may be composed of surface-.-

contaminated materials. -.

The manner in which the above classification alternative is triggered in.the

computer codes is discussed in Section 6 of this Appendix (See Table D.2).

Stabilization through dis'osal facilitj.design_. One option forwaste stabilization is through disposal facility design--for example, by grouting'the waste

mass, using extreme compaction techniques 'on the disposed waste, or by disfosal'.

into a hot waste'facility--rather than the more common method of improved waste'

form and packaging. This option may be specified for a particular waste stream

through use of an array, NDXS(I), which is read into the program and which has

a number of other, functions besides signifying stabilization through facility

design. A valve'for NDXS is assigned to each waste stream as follows:

-NDXS (ISTR) --- - Meaning-- -

2 .- . Normaltwaste stream, 'stabilize through disposal

-. ' . ' facility design , ' -

-'1 . Normal waste stream.

O O Exclude stream from-analysis .-

-1 - Distributed waste stream

i . -2. -Distributed-waste stream, stabilize-through

' disposal facility design' -

D-5'.
As shown, if a waste- stream has a value NDXS (ISTR) = ±2,- then it is to be

stabilized through a special disposal- facility'design (e.g., setting the stable

waste IRDC indices'ID=2, or IG=1,- or IX=3, or IH=1). If no such' design is -'

specified, the programs will automatically-fall back on the procedure (discussed

below) of achieving waste stabilization through waste form and packaging. Asshown, the NDXS. array'has other functions which consist of (1) flagging waste

streams for which the radionuclide' concentrations- are given as' a distribution

rather than an average across the stream (NDXS < 0), and (2) flagging waste

streams which are to be excluded from analysis. The former function is discussed in more detail below. This latter function is useful for assessing the

relative impacts of one or a group of selected waste streams.

Stabilization Through Waste Form or Packaging. As discussed above, if a waste

stream is in an unstable form and exceeds Class A-waste limitations, it must

be placed into a stable form and tested against' the Class B and-Class C limits.

This is accomplished in the codes by changing the waste spectrum for the: stream

and comparing the resulting waste radionuclide concentrations which would result

from the processing option associated with the new waste spectrum against theclass limits. The order in which the successive waste spectra are considered

is read into the codes as an input variable. This procedure can be illustrated

by using an example.

Consider the possible processing options considered in the EIS for PWR ion

exchange resins. In waste spectra 1 and 6, the resins are-dewatered, in waste

spectrum 2 half of the resin volume is solidified in cement and half in vinyl

ester styrene, and in waste spectrum 3 the resins are all solidified in vinyl

ester styrene. In waste -spectrum 4 the resins are. incincerated prior to solidification in vinyl- ester styrene, and in waste spectrum 5 the resins-are placed

into high integrity containers (HICs). Now assume that when the. resins are in

an unstable dewatered form (waste spectrum 1) the concentration of a particular

radionuclide is 100 Ci/m3. The concentration of this radionuclide in each of

the other spectra is, after the appropriate waste processing techniques are

employed:

Spectrum 1 Spectrum 2 Spectrum 3 Spectrum 4 Spectrum.5 Spectrum 6

Stability: unstable stable stable stable stable Unstable

VRF:* 1.0 1.0 1.0 18.0 1.0 1.0

VIF: 1.0 1.65 2.0 2.0 1.0 1.0

Conc. (Ci/m3) 100 61 50 900 100 100

*VRF: Volume reduction factor

VIF: Volume increase factor

Further assume that the limiting concentrations for this radionuclide are

Class A: 0.1 Ci/m3, Class B: 55 Ci/m3, and Class C: 800 Ci/m, and that there

is no "hot waste facility" at the disposal site. For this example, the order

of the waste spectra to be considered is taken to be spectrum 1 followed by

spectra 2, 3, 4, 5, and 6. Now using the classification test procedure shown

in Figure D.1,. the classification procedure would first determine that the waste

stream is unstable and furthermore, exceeds the radionuclide concentration limit

D-6
for Class A waste. The program would then switch to waste spectrum 2 for this

stream and determine that it qualifies as Class C waste. An alternative example

waste spectra order could have been 1, 3, 2, 4, 5, and 6. In this case, the

waste stream would have been disposed as Class B waste according to the waste

concentration given by waste spectrum 3. Finally, consider the waste spectrum

order 4, 1, 5, 2, 3, 6. In this case, the waste stream would have initially

(waste spectrum 4) exceeded Class C concentrations. The program would have

switched to waste spectrum 1, only to determine that the waste stream exceeds

Class A concentrations. The program would have then switched to waste spectrum 5 and determined that the waste could be disposed in ..n HIC as Class C

waste.

This test procedure is carried out for each waste stream. The waste spectrum

that each waste stream eventually falls into is retained and used when determining overall impact measures.

In the OPTIONR and GRWATRR codes, the order that the waste spectra are considered

is provided as an input variable through use of the six-member integer array

IORDD.

The IMOD Array. The IMOD array is an array used to keep track of the classification status of a given waste stream within the OPTIONR and GRWATRR codes.

Values assigned to the array are integers ranging from 1 to 9 as shown on Figure G.1. An IMOD value equal to zero signifies that the waste stream has been

determined to'be unacceptable for near-surface disposal.

Distributions. It is recognized in the draft EIS and the accompanying data

base that in practice there exists a wide variation in the average total activity.of almost all of the waste streams shipped for.disposal. This variation

results'from many factors including different waste management practices by

the waste generator, different ages and designs of waste generating facilities,

and so forth. One of the more desirable changes to.the .impact calculation codes

would be the capability to consider an arbitrary variation in .the total activity

of individual waste streams (as opposed to the technique of assuming a fixed

average radionuclide activity over a waste stream).

The variation in these waste streams can be expected to follow a rough gaussianor poisson-type distribution with less waste at the extreme high and low ends

of the total activity, and an aggregation of the waste volumes at the middle

of the distribution. The significance of this distribution is the-fact that

some portion of the waste (at the lower end) may be acceptable for disposal as

unstable Class A waste, some portion of the waste may be acceptable as Class B

waste, another portion of the waste may be-acceptable as Class C waste, and

some may not be considered generally acceptable for near-surface disposal.

To illustrate' the data needed to determine 'activity distributions', as well as

to illustrate how the activity distributions are stored and used in the OPTIONR

and GRWATRR codes, a hypothetical example distribution is presented in Figure D.2. For this hypothetical example, data are assumed to have been collected

which show that the gross activity of the waste stream ranges from 1 to

10 Ci/m3. Based upon this data, the range of possible activities has been

divided into 10 increments--e.g., 1-2 Ci/m3, 2-3 Ci/m3, etc. For each increment

the fraction of. the total waste volume which has an activity falling within

the increment is determined, as well as the average activity of the waste'within

D-7
- Average Activity (Cl/m 3)

Denoted inside

the rectangles

0.24 1-

0.20 FC

0

U

to

U.

E

0.16 I0.12 -

0.081-

0.04 _ 1.3 2.6 3.5 4.2 5.5 6.6 7.6 8.7 Tfl

0 '1 2 3 4 5 6

Total Activity (CU/M3)

I ,I &

7 8 9 10

ARRAYS

CL 0 1 2 3 4 5 6 7 8 9 10

PV 0 0 .04 .12

AA 0 0 1.3 2.17

.28 .40 .64

2.93 3.31 4.13

.76 .84

4.52 4.81

.96

5.30

1.0

5.46

Figure D.2 Example Total Activity Distribution

D-8
the'increment. For example,..24% of the waste is shown to fall within an increment of between'5 and 6 Ci/m3 and have an average activity'of 5.5 Ci/m3.

Based upon this data, three one-dimensional arrays"are specified which contain

the following information: .

(1) The array 'CL', which.conta'ins for each increment the' upper .value of the.'

activity within the 'increment;

(2) The array PV, which contains for each increment the cumulative fraction

of the waste which have'activities.less than the upper value of the particular increment; and '

(3) The array AA, which contains for each increment the average activity across

the cumulative fraction of waste defined by the array PV.

These three arrays, and the values assigned to the arrays according to the

example, are shown in Figure D.2.

This procedure is general--that is, it can be applied to any waste stream for

which an activity distribution is known. For the final EIS, such information

is available for 6 light water reactor (LWR) process waste streams: pressurized water reactor (PWR) ion-exchange resins, PWR filter sludge, PWR concentrated liquids, boiling water reactor (BWR).ion-exchange resins, BWR filter

sludge, and BWRconcentrated liquids.' Distribution'data used for the 6;LWR'

waste streams are presented in Table C.36 (see Appendix C). Using this data,

14 activity increments are used from 0.00018 Ci/m3 to 350+ Ci/m3. A distributed waste source is also assumed for the mixed oxide (MOX) facility decontamination stream (F-PUDECON). Data for this MOX'facilitydecontamination

stream are presented in Section 4 of Appendix C.' Three activity increments

are assumed for this stream ranging from 0.001 Ci/m3 to 0.1+ ti/r 3.

The fact that the activity of some of the waste streams is given as a distribution rather than-as an average over the stream complicates' the waste classification test procedure described above. This results from the likelihood that

a certain fraction of a distributed waste stream may be determined to be Class A,

another fraction may be determined tobe'Class'B, and so forth`. In addition,

each time that a fraction of a waste stream is classified, the distribution of

activity across the remaining fraction must be recalculated..

Briefly, the classification test procedure for distributed waste streams works

as follows:.

(1) obtain an upper total activity value by comparing to-a set of radionuclide concentrations which-will permit disposal of the waste in

the waste class for which it is being considered,

(2) based on the array CL defined above, identify the fraction of the

waste acceptable in this class (interpolating where necessary),

(3) take-out the' fraction which has been found to be acceptable from the

distribution and redefine'the waste distributions, and

(4) reconsider the new distribution for further classification.

- D-9
One point of note concerns the. manner in which the fraction of the waste volumes

in a distribution' that are found to be unacceptable during a given classification

test are considered. These unacceptable waste-volumes are classified as an'

additional new waste stream and considered separately.

The interpolation and redistribution scheme can be mathematically illustrated

in the following manner. Assume that the following data exists regarding the

distribution of activity within a given waste stream:

Volume Avg.. Activity

Range Fraction in Range

0-C1 v1 a1

c1-c 2 v 2 a2

c2-C3 v3 a3

c3-c.4 ev 4 a4

etc. etc. etc.

As discussed above, this data may be stored

AA(I)--in the following manner:

in 3 arrays--CL(I), PV(I), and

Maximum in Cumulative Average Activity to

Range Fraction Maximum in Range

CL(1) 0 PV(1) 0 AA(1) 0

CL(2) C1 PV(2) V AA(2) Al-al

v a v a

CL(3) C2 PV(3) V2 v+V 2 AA(3) A = 1 1 + 2 2

2.2 122 V 1 + V2

(C*) (V*) (A*)

3

3 I v.a.

CL(4) C3 PV(4) V3 = X v; AA(4) A3 =

i=l X v.

i=1 1

4

4 X v iai

CL(4) C4 PV(5) V4 = X v; AA(5) A4 = 1

i=1 I v

i.=1 1

etc. etc. etc.

D-10
As shown, the first member in each array is equal to zero, and the total number

of members in each array is 16.

Over all levels of activity, -the ratio of the concentration of one isotope to

the next is-assumed to be constant. -Given this,-assume-that the concentration

of a given isotope is given by Xi and the limiting concentration of that isotope

for a given waste class is gienb Y.. Then the limiting gross activity of

that stream for the given wastelclass1 i found by,-the following:,

NNUC

I X

i=1 Y

NNUC =number of radioi sotopes.

The range into which C* falls may be then determined and the corresponding

cumulative fraction and average activity upto' the'value CAmay be determined

through interpolation.

..For example, assumie* that C <- c*C <.

tion (V*) up to CA is gives by: 3

Then, the corresponding cumulative frac-

(V V C.* C V* V + 3 2 2

(C C 3 2

The average activity (A*) up to C* is given by:

I- I .A '=CAtI 2)(CA 2). ')

I 2 - (CR .7 .C9) I : I

, 2 I

I 7

The f ractio6n' of the waste-stream hKavin'g'an activity between zero and CA Ci/m 3

is removed and classified as falling into the waste class tested for. The

,average concentration of individual radionuclides within this fraction may be

.readily determined and environmental-impacts calculated. However;- prior to

,testing the remaining fraction of~the waste stream again'sit the radionuclide

'concentration limits for a higher waste class, the' activity' distribution across

the emanin fratio ofthe waste stre'am' is reca'lculated. Again usingth

above'exam-les, the values for the CL, PV,''and AAarrays are 'recalculated as

follows:

D-11.
Maximum in Cumulative Average Activity to

Range Fraction Maximum in Range

CL(1) 0 PV(1) 0 AA(1) 0

CL(2) 0 PV(2) 0 AA(2) 0

CL(3) C* PV(3) V* AA(3) A*

VV 3A3- V*A*

CL(4) C3 PV(4) V3- AA(4) V*

CL(5) C4 PV(5) V4-V AA(5) 4A4 A

The above process is repeated for the next classification text.

For calculational convenience in the computer codes, the above three onedimensional arrays are merged into a single three-dimensional array DIST(I,J,K).

Different Disposal Technologies

This feature involves the practical fact that unstable wastes (i.e., that portion

of the Class A group that are unstable) may be disposed of using different disposal practices than stable wastes, and will likely involve different levels

of long-term environmental releases and site maintenance. The primary effect

of considering two different disposal technologies at the same disposal facility

is during the calculation of certain impact measures such as costs, transportation impacts, etc.

In the GRWATRR and OPTIONR codes two different sets of disposal technology

indices (see Table D.2) are read in, and two different sets of impact measures

are calculated. For example; in the GRWATRR code, groundwater migration impacts

are first calculated for unstable waste streams and then for stable waste streams;

finally total impacts over all waste streams are calculated. A similar

approach is taken in the OPTIONR code for impact measures such as occupational

exposures, transportation impacts, land use, costs, and so forth. In particular,

disposal and post-operational costs are calculated according to the following

procedure:

(1) All the lump-sum capital expenditure items for the disposal technologies

are waste volume prorated into two waste groups: stable and unstable

waste. For example, if there are 600,000 m3 of unstable waste acceptable

for disposal using the unstable disposal technology indices, and if there

are 400,000 m3 of waste acceptable for disposal using the stable disposal

technology indices, then the base capital expenditure (not the alternative

disposal technologies which are considered below) is divided 60 percent and

40 percent between the two cases.

D-12
(2) The capital expenditures involving the alternative disposal technologies

(e.g., grouting option; segregation option, etc.) arexvolume prorated-if

iboth sets of disposal technology indices include the'option; if-onlylone

' ofthe'disposal technology sets include the option,ithe capital expenditure is included entirely in that portion of the impact measures.

(3) The base-dcase-operational impact measures are-volume prorated similar-to

the capital expenditures base-case example-given above.'

-(4) Additional 'operational alternatives depend'on the waste~volume or parameters suchias'the disposed waste-surface'?area.; -It is straightforward to

consider these additional impact measures for each disposal technology

cases.

(5);

. . I

Postoperational impacts'are also"volume prorated in an exclusionary mode--

i.'e.-, in the-above example, if the first disposaltechnology requires-a

high level of institutional care, only 40 percent-of'the base impact

measures are included as part of'the'impacts'due to the first disposal

technology. Contingency costs are also volume prorated even though they

may be relatively independent of the fraction of the disposed volume that

require emergency actions. ,, , ,., ..

-(6)- Radiological and other impact measures (e.g., ground water migration;

transportation impact measures,.waste processing impact measures,'etc.)

arecalculated for each waste'stream. Therefore the calculation of these

impact-measures into two groups'is-straightforward.' -

3! OTHER FEATURES OFITHE-COMPUTER CODES--

As discussed above, the most significant feature of the-revised OPTIONR and

GRWATRR codes compared to the OPTIONS and GRWATER computer codes is the test

procedure by which waste streams are classified. A number of other features

have also been incorporated into the OPTIONR and GRWATRR codes in order' to

increase the accuracy of the analysis,-increase the flexibility of the codes,

and in response to-comments made on'the draft EIS. ;These features include the

following: - - -

a revised method to determine unit disposal costs;

- revised costs for alternative disposal technologies and post-operational - activities; '

- calculation of impacts from decay chain daughters;

trench overflow and leachate treatment impacts;

a revised method to calculate'operat'ional 'impacts from -accidents; and

* revised data files.

Unit disposal costs.

As discussed in Section 2 of Appendix C of this final EIS, the methodology used

to calculate unit disposal costs ($/m3 of waste disposed) has been altered since

D-13
the draft EIS. To these unit disposal, costs would be added costs for disposal

-facility closure, observation and maintenance, and institutional control. The

calculational routine presented in Section 2, Appendix C, uses a-present value

analysis to determine unit disposal costs and has been implemented in the OPTIONR

computer code.

In the code, calculations are performed by the subroutine COSTS which is called

from the subroutine ECON. ECON calculates total capital, operational, and depreciable costs in 1980 dollars, and passes these costs to COSTS. COSTS returns

with unit disposal costs. Constants which are used in COSTS, such as tax rates

and interest rates, are provided as data statements. in COSTS.

Revised unit costs for alternative disposal technologies.

The basis for the revised-unit costs for the reference disposal facility, alternative disposal technologies, and post-operational costs is set forth in Section 3, Appendix C, of this final EIS. These revised costs are incorporated

into the ECON subroutine of the OPTIONR code.

Calculation of impacts from decay chain daughters.

The existing computer codes INTRUDE and OPTIONS include subroutines which calculate radiological impacts to a potential inadvertent intruder as a function

of time. The revised code OPTIONR, which incorporates a revised logic for

classifying wastes for disposal, also calculates potential inadvertent intruder

exposures as a function of time. For the final EIS, OPTIONR includes an

improved method of determining radiological impacts associated with certain

heavy metal radioisotopes having daughters-which are also radioactive. This

methodology is applied to calculations involving exposures to individual inadvertent intruders, off-site exposures to populations due to the intrusion, and

hypothetical impacts from erosion. -

Basically, the methodology for determining radiological impacts starts by considering, for a given, nuclide, the-concentration of that nuclide in waste.

This concentration is multiplied by factors that correspond to radioactive decay

and to the transfer of the nuclide through the environment to a biota access

location. Given a unit concentration of the nuclide at a biota access location,

resulting dose equivalents are determined usingt"pathway dose conversion factors"

(PDCFs). For radioisotopes belonging to decay chains, the revised methodology

determines for a given decay time the fractional amounts of respective daughter

radionuclides which would be ingrown during the decay time periods. 'These fractions are then multiplied by the respective pathway dose conversion factors

for the daughter nuclides, the products summed, and the total added to the pathway dose conversion factor for the parent nuclide.

That is, for nuclides that do not belong to heavy metal decay chains, an entity

f x PDCF is used in the calculations, where f is the time delay factor. (See

Appendix G of the draft EIS.) For nuclides belonging to decay chains, this

entity is replaced by the following:

D-14
f x PDCF + (fd1 x PDCFdl) + (fd2 x PDCFd2) + (fd3 x PDCF + where

f = exp (-XAT)_

A decay constantof'parent .P

T = decay time periodPDCF = PDCF of parent

= fractionalquantity-of a given daughter generated-from a unit

quantity of the parent at a given time

PDCFd = PDCF for a given daughter.

In the analysis, the following radionuclides are set out into four'-decay chains:

Decay chains

4n 4n+1 4n+2 4n+3

Cm-244 Pu-241 Pu-242 Cm-243

, Pu-240 . Am-241 Pu-238 Am-243-

. U-236 Np-237 U-238 Pu-,239

Th-232 U-233 U-234 U-235 .

Ra-228 Th-239 Th-230 Pa-231

Th-228 / Ra-226 Ac-227

,-, Pb-2- - , - . . . -

Use of 'the decay'chain methodology in'volved only-relativel minor changes'to

the existing calculational procedure, prin~cipally the addition'of two small subroutines.CHNS and CALC. Incorporating.the-chain calculations has also involved

modifying the'data files:used for thedraft EIS " This involved determining additional values for the'decay constants"(AL), leachate partitionrations (FMF),

retardation coei T(INUC,1ahdRET(INUC,4)),'"and pathway dose conversion factors.(PDCF). The first' three' items are..presented below. Pathway dose

''.;conversion factosfor all'isotopes are listed in Section 8 of this'appendix.

~~ * . - . -.,...

, ; .:,- : . . --. I *, ,

D-15
Isotope INUC* AL(INUC)** FMF(INUC) RET(INUC,1) RET(INUC,4)

Pb-210 24 3.40E-2 4.11E-3 840 7200

Ac-227 25 3.21E-2 4.11E-3 300 2500

Ra-226 26 4.33E-4 4.11E-3 30 250

Th-228 27 3.63E-1 4.11E-3 840 7200

Ra-228 28 1.03E-1 4.11E-3 30 250

Th-229 29 9.44E-5 4.11E-3 840 7200

Th-230 30 8.66E-6 4.11E-3 840 7200

Pa-231 31 2.13E-5 4.11E-3 840 7200

Th-232 32 4.92E-11 4.11E-3 840 7200

U-233 33 4.28E-6 1.25E-4 840 7200

U-234 34 2.81E-6 1.25E-4 840 7200

U-236 35 2.90E-8 1.25E-4 840 7200

Pu-240 36 1.05E-4 4.67E-4 840 7200

*Indicates the order in which the isotopic information is stored in

the data files and considered in the codes. The first 23 values

of INUC correspond to the 23 other isotopes considered in the data

base.

**In yr- 1

Trench Overflow and Leachate Treatment Impacts

In the OPTIONR code, the subroutine OVERFLO is used to provide an order of

magnitude analysis of the impacts that could result from trench overflow and

leachate evaporation at a disposal facility having severe water accumulation

problems. The calculational methodology used by the subroutine is described

in Section 5.3, Appendix C, of this final EIS.

In the subroutine, impacts from'overflow are calculated assuming that each year,

a certain activity is released from the disposal trenches and'flows into a nearby:stream, where contaminated stream water is consumed byan individual. Thus,

exposures due to overland flow are calculated'as'exposures to an individual (in

millirem). In addition, the subroutine calculates exposures to the surrounding

population (in man-millirem/yr) that could result from pumping leachate from the

inundated trenches and processing the leachate through an evaporator.

In the calculations, one of the critical parameters is the volume (V ) of

leachate annually released overland or processed. In this EIS, V is waste

volume prorated from a base of one million gallons of leachate, wiich is the

approximate volume of leachate and other contaminated liquids annually processed

at the Maxey Flats disposal facility, and from one million m3 of waste disposed.

One million gallons is also the annual volume of leachate assumed for the high

D-16
cost institutional care scenario (i.e., ICL=3). In the methodology, V1 is

assumed to be greater than zero onlytfor the condition'of-a.high level of

institutional control, and only for very impermeable disposal site soil conditions (IR=1 or1IR=6). 'If ICL=3 and there is no segregation of stable and

' unstable waste, then V :is equal to one gallon per m3 of waste-times the:total

'.:' :-volume of'waste (in m33'delivered to the disposal-facility. 'If there 'is segre-

- gation of stable'and unstable waste,-then V is taken to be one gallon per m3

of waste multiplied by the unstable waste vblume.

Besides the'radiological impact measures,:three-additional'impact measures

associated with evaporator operations-are'calculated. 'These include-annual

occupational exposures (in whole body man-millirem), evaporator operation

costs, and gallons of propane. These impact measures were determined based

upon experience at the Maxey Flats disposal-facility.

Revised Methodology to Consider Potential Operational Accidents

The OPTIONR computer code contains a subr6utine`ACCEXP which (among other things)

calculates potential impacts from operational accidents at the reference disposal

facility. The operational accidents-considered in'the subroutine include a

scenario in-which a waste container is assumed to be dropped from a significant

height so that the waste container breaks open. A portion of the~radioactive

contents of the waste package is assumed to be released into the air where it

is transported offsite, leading to subsequent potential human exposure. For

the final'EIS, ACCEXP incorporates a.revised technique to estimate the fraction

of the waste contents released from this accident. The assumed release functions are given in Section 5.5, Appendix C, of this final EIS.

Revised data files.

Revisions have been made to the data files used for the dr'aft'EIS.' One 'reason

for these revisions is to minimize the number of different data files required

'for operating the codes. "'For example, the codes may be used to perform' impact

- calculations on either a generic 'or on a regional basis'. -'In the draft EIS, a

separate set of data files were required for each region.' For the'final EIS,

the'different:information 'contained -in 'these files has"bee'n incorporated -into

three data files (INIFIL, GW2FIL, IN2FIL) which are input into'the'two computer

programs used in the final EIS. These files are modified versions of the DATA,

DATAD, and SPECTRUMS files used for the draft EIS. Other changes awere made to

accommodate the expanded calculational methodology. These include, for example,

additional pathway dose conversion'factdrs-for decay daughters (INIFIL-file),

a 37th waste 'stream '(F-PUDECON) "considering waste from decontamination of mixed

oxide (MOX) fuel research 'facilitie-s (INIFIL, GW2FIL files), and addition of a.

' 5th and 6th waste spectra'(IN2FIL file). ''A number of alternative'lists.of waste

classification limiting concentraitions;'are' also read in through 'the IN2FIL file.

To summarizee input datafefo:'the computer codesFused iN'ihefinal EIS ared con

:'' tained inthree data files':f INlFILt-GW2FILd and IN FhIL e' IN2FIL is used by

both codes.' IN1FIL is used by the'OPTIONR code while'GW2FIL-is used'by-the

GRWATRR code. Listings of the'three''datafiles are provided in Section 8 of

this appendix.

-. . ' , .t.*.

D-17
4. STRUCTURE OF INPUT AND OUTPUT FILES

The two impact analysis programs used in the final EIS utilize the logical

units 1 through 5 according to the assignments in Table D.1.- Logical unit 1

is used for inputting the contents of either the INIFIL or GW2FIL file. Logical

unit 2 is used for inputting the contents of the IN2FIL file. Output in a summary form is printed onto paper using logical unit 4. Logical unit 5 is-used

for inputting data other than that contained in logical units 1 and 2. The

format for inputting data through logical unit 5 is discussed in the following

Sections 5 through 7 of-this appendix.

Table D.1 Assignments for Logical Units

Logical unit Logical unit Logical unit Logical unit

1 2' 4 5

Code name: (TAPE1) (TAPE2) (TAPE4) (TAPE5)

GRWATRR GW2FIL IN2FIL OUTPUT INPUT

OPTIONR IN1FIL' IN2FIL OUTPUT INPUT

5. INPUT

Input for the five programs is read in in "sets." Each "set" consists of the

necessary input to execute the program one time.,

Input for an execution of the GRWATRR and OPTIONR codes generally consists of

(1) a title for the execution, (2) several input indices, (3) two sets of disposal technology indices (IRDC) as described in Appendix G of the draft EIS

and updated in Appendix C of this final EIS, and (4) the order of the waste

spectra considered in the programs.

6. INPUT INDICES

Table D.2 snows the IRDC (disposal technology indices) parameters, optional

values to choose. from, and the explanation of each. These thirteen indices

are the major inputs for both codes. Appendix D of. the draft EIS presents

information explaining further what each index means. Two sets of IRDC indices

are read in for both the OPTIONR and GRWATRR codes.

Table D.3 shows ISPC (waste form behavior indices) parameters 14 through 19,

optional values to chooseffrom, and an explanation of each. These six-indices

are input through the IN2FIL file but are included here as background. Appenddix D of the DEIS and Appendix C of this final EIS explain further the meanings

of the index values.

Additional variables read into the GRWATRR and OPTIONR codes include the IORDD

array and the CLST array. IORDD is a six member integer array presenting the

order in which waste spectra are considered in the codes. Integer values in

D-18
Table D.2 Disposal Technology:Indices (IRDC)

. ., I .I I I , ....

*Variable -Parameter Optional Explanation -

v a . ... -

IR* - - REGION 1

2

3

4

5

Northeast regional'site

Southeast regional site

Midwest regional site

Southwest regional site

Southeast site with sandy soil (faster

ground water velocity)

Southeast site with clayey soil (slower

groundwater velocity)

6

ID

IC

IX

--IE -

! I IDESIGN

COVER

STABILIZATION

1

2

1

2

3

1

2

3

* EMPLACEMENT 1

32 

4

.5

IS SEGREGATION 0 0

..- 1

2

3

Regular shallow land burial'trenches

"Concrete-walled" trenches

Regular cover

"Thick" cover

"Intruder barrier" cover

No special procedures

Moderately extensive procedures

Very extensive procedures

-Random

Stacked

Decontainerized

Random with sand backfill

Stacked with sand backfill

No segregation

Segregation of unstable waste

Segregation of waste containing chemical

agents

Segregation of unstable waste as well

as waste containing chemical agents

No layering

Layering of waste streams

No grouting Grouting of interstices between disposed

waste packages

No special disposal of high-activity

waste

Special disposal operations for high

activity waste

2 year modest closure effort

4 year closure period incorporating

complete site restabilization program

Low care level

Moderate care level

High care level

IL LAYERING

IG GROUTING

0

1'

0

1

. 0

I1

.

IH I HOT WASTE

FACILITY

IQ

ICL

CLOSURE

CARE LEVEL

1,

;2

. .1

L1

'2

3

D-19
Table D.2 (continued)

Variable Parameter Optional Explanation

values

IPO POST-OPERATIONAL PERIOD

INSTITUTIONAL

CONTROL PERIOD

2-99**

0-999

Number of years between cessation of

waste disposal of waste and transfer

of title to site owner

Number of years between transfer of

title to site owner and the assumed

loss of institutional controls

IIC

*In the codes, two sets of IRDC indices are read in. Setting IR=O in the

second set of IRDC'indices signifies using an alternative method for classifying waste based upon existing license conditions at disposal facilities.

**IPO must be greater than

greater than or equal to

or equal to 2 when IQ is equal to 1 and must be

4 when IQ is equal to 2.

Table D.3 Waste Form Behavior Indices (ISPC)

Variable Parameter Optional Explanation

values

I4 FLAMMABILITY 0 Non-flammable

1 Low flammability

2 Burns if heat supplied

3 Flammable

I5 DISPERSIBILITY 0 Near zero

1 Slight'to moderate

2 Moderate

3 Severe

I6 LEACHABILITY 1 Unsolidified waste form

2 Type A solidification

3 Type B solidification

4 Type C solidification

I7 CHEMICAL CONTENT 0 No chelating agents or organic

chemicals

1 Chelating agents or organic chemicals

likely present

I8 STABILITY 0 Structurally unstable waste form

1 Structurally stable waste form

(inherent to waste form)

2 Stabilized using a high intensity

container

3 Stabilized by other means

I9 ACCESSIBILITY 1 Readily accessible

2 Moderately accessible,

3 Accessible with difficulty

D-20
each member of the array may be 1, 2, 3, 4, 5, or 6, corresponding to the

identification numbers of the waste spectra. Normally, all waste streams are

considered in the order given by IORDD. However, an option is provided by which

a different order may be imposed for given waste streams. This option is

triggered by setting the variable-.NORD greater than zero,-where the value of

NORD-indicates the number of waste streams for which this option is implemented.

,If,,NORD is greater than zero, then the appropriate stream identification number

'(NK) is read in. This is -followed by 6 -integer values of-the-index-NORDD(I)

giving'the order in which!the waste spectra are considered for the particular

waste stream.

The CLST(4,16) array is used to read in limiting waste classification radionuclide concentrations. Each of the four rows correspond to a set of limiting

concentrations for a particular waste class (i.e., for CLST(I,J), I = I corresponds to Class A waste limits'; I '2;'Class B limits'; I = 3, Class C limits;

and I = 4, "hot waste facility" limits'). The116 columns correspond to limiting

values for the'following radionuclides (in order): H-3, C-14, Fe-55, Ni-59,

Co-60, Ni-63, Nb-94, Sr-90,'Tc-99,'I-129, Cs-135, Cs-137, U-235, U-238, alpha

emitting long-lived transuranic nuclides, and Pu-241. Reading in the CLST array

is optional and is implemented only when NLST'= 0. Otherwise, a reference set

of CLST concentrations are used corresponding to the'value of NLST.

The other indices needed to execute the impact analysis codes are explained

.below and summarized in Table D.4. Each code does not need every index for

execution. Therefore, with each explanation below, the code(s) that use(s)

the index is(are)'listed, and the-table shows the codes that use each index.

The input formats in-the next section will demonstrate the location of each

index in the input fields. -;

The NBEST index is used to take credit in certain calculations within the OPTIONR

code for improvements in the waste form for reducing impacts to-inadvertent

intruders. ,NBEST = 1 results'-in taking the credit, NBEST = 0 does not (refer

to Vol. 2 of'the draft EIS, Section 4.3.4.1). NBEST is only used in the OPTIONR

code. -

The NTHIC index is used in the GRWATRR code and is the number of years. of

,expected lifetime of a high integrity container.'' 'j

TheNOPTW index is-usedriin-the GRWATRR code)and'indicates whether the'boundary

well (NOPTW = 1) or the intruder well (NOPTW;=-O)lis to be analyzed. The

resultant output will indicate which well -was, chosen. . I; .nd.N*,C* Sar6,u*e* -

In the codes, two input indices (NNDXand!NHIC) ar6 used which signify the total

'number of waste streams-to be-treated;differently--than the regular analysis.

-In'all the codes, each of the 37 waste streams is'identified by an integer

corresponding to its position in~the data file. Table D.5 shows the identification number for the waste streamsland-the description of the streams. An index

value is then assigned to-each stream identifying the treatment it is to receive.

In the codes, an array NDXS is'-maintained';in which'an index value equal to 1

is automatically assigned for each waste stream except for distributed waste

streams. These latter waste streams (P-IXRESIN, P-CONCLIQ, P-FSLUDGE, B-IXRESIN,

B-CONCLIQ, B-FSLUDGE, F-PUDECON) are automatically assigned an index value equal

D-21
Table D.4 Other Indices forImpacts Codes

Optional Codes

Index values Explanation where'used

genre - bi - _ :._o . _. .__._.. nsl Nrib I U NO credit in waste Torm tar reducing intruder

impacts

Take credit

UP I 1UNK

1

NOPR 0-6

NLST 0-6

O = perform generic analysis

1 = perform regional analysis

2 = perform regional analysis

3 = perform regional analysis

4 = perform regional analysis

5 = perform regional analysis

assuming sandy soil

6 =,perform regional analysis

assuming clayey soil

for

for

for

for

for

region 1

region 2

region 3

region 4

region 2

,GRWATRR

OPTIONR

for region 2

o = read in a set of waste classification

lists

GRWATRR

OPTIONR

1 = use

2 = use

3 = use

4 = use

5 = use

6 = use

reference

reference

reference

reference

reference

reference

waste

waste

waste

waste

waste

waste

classification

classification

classification

classification

classification

classification

list 1

list 2

list 3

list 4

list 5

list 6

NORD 0-37

NNDX 0-37

NHIC 0-37

NTHIC 0-1000

NOPTW 0

1

-NDXS -2, -1, 0,

1, or 2

Total 'number of waste streams for which

classification will be tested in a

different order than that given by IORDD

Total number of waste streams to treat

differently from the regular analysis

Total number of waste streams to place in a

high integrity container or stabilize

Lifetime (in years) of high integrity

container

Intruder well case

Boundary well case

2 = normal waste stream, stabilize'through

disposal facility design

1 = normal waste stream

0 = remove from analysis

-1 = distributed waste stream

-2 = distributed waste stream, stabilize

through disposal facility design

GRWATRR

OPTIONR

GRWATRR

OPTIONR

GRWATRR

OPTIONR

GRWATRR

GRWATRR

GRWATRR

OPTIONR

D-22
Table D.4 (continued)

Optional ' Codes

Index, values Explanation where used

If NNDX > 0:

IDIFF... 1-37 Identification number of waste streams to GRWATRR

treat differently OPTIONR

NDXD -2, -1, 0, Index value identifying special treatment

1, or 2 2 = normal waste stream, stabilize through

disposal facility design

*; 1 = normal waste stream

o = remove from analysis

-1 = distributed waste stream

-2 = distributed waste stream, .stabilize

through disposal facility design

If NHIC > O:

IDIF. :.,1-37 . Identification number of waste streams to GRWATRR

place in a high.integrity container or OPTIONR

'stabilize

NHCD .- 1-or 2 Index value identifying stream treatment

1.= place in a high integrity container

2 = stabilize byrother means

If.NORD > 0:

NK: 1-37 Identification number of waste stream GRWATRR

for which-waste classification spectrum ..OPTIONR

order will be different than given'by

IORDD

NORDD 1-6 Index values '(6 will .e read) giving

spectral order considered by waste

stream . '

I:!-. .

D-23
Table D.5 Waste Streams

Identi fication Data file

Number Stream name

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

19

20

21

22

23

24

25

26

27

28

29

30

31

32

33

34

35

36

37

**LSV = I

PWR Ion Exchange Resins

PWR Concentrated Liquids'

PWR Filter Sludges

PWR Filter Cartridges

BWR Ion Exchange Resins

BWR Concentrated Liquids

BWR Filter Sludges

PWR Compactible Trash

PWR Noncompactible Trash

BWR Compactible Trash

BWR Noncompactible Trash

Fuel Fabrication Compactible Trash

Fuel Fabrication Noncompactible Trash

Institutional Trash (large facilities)

Institutional Trash (small facilities)

Industrial SS* Trash (large facilities)

Industrial SS* Trash (small facilities)

Industrial Low Trash: (large facilities)

Industrial Low Trash (small facilities)

Fuel Fabrication Process Wastes

UF6 Process Wastes

Institutional LSV** Waste (large facilities)

Institutional LSV** Waste (small facilities)

Institutional Liquid Waste (large facilities)

Institutional Liquid Waste (small-facilities)

Institutional Biowaste (large facilities)

Institutional Biowaste (small facilities)

Industrial SS* Waste

Industrial Low Activity Waste

LWR Nonfuel Reactor Core Components

LWR Decontamination Resins

Waste from Isotope Production Facilities

Tritium Production Waste

Accelerator Targets

Sealed Sources

High Activity Waste

MOX Research Facility Decontamination Waste#

P-IXRESIN

P-CONCLIQ

P-FSLUDGE

P-FCARTRG

B-IXRESIN

B-CONCLIQ

B-FSLUDGE

P-COTRASH

P-NCTRASH

B-COTRASH

B-NCTRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

N+LOTRASH

F-PROCESS

U-PROCESS'

I-LIQSCVL

I+LIQSCVL

I-ABSLIQD

I+ABSLIQD

I-BIOWAST

I+BIOWAST

N-SSWASTE

N-LOWASTE

L-NFRCOMP

L-OECONRS

N-ISOPROD

N-TRITIUM

N-TARGETS

N-SOURCES

N-HIGHACT

F-PUDECON

ource and special nuclear i

iquid scintillation vial.

material.

#Waste streams for which the contained activities are given as

distributions rather than averages.

D-24
to -1. The total number of waste'streams' which will be assigned different index

values is equal to NNDX;- If NNDX is greater than zero, the identification number

of each waste stream:receiving a&'different index value is input, followed by

the value of the index. Possible index values are as follows:

"-2" = normal waste str'eam, stab'ilize through disposal facility design

"-1" = normal waste stream

"0" = exclude waste stream~from analysis

"1" = distributed'waste. sti'eam n i>, '!

"2" = distributed waste'stream,)stabilize through disposal facility design

Waste streams initially.assigned;;an -index equal to 1 may only be reassigned a

value of 0 or 2.: Similarly, waste streams initially assigned an index equal

to -1 may only be reassigned a value of 0 or -2.

The option to place a stream in a high integrity container or to stabilize by

some other means is.handled by the NHIC variable and the following procedure.

The index value'of '"'O" is automatically assigned to every stream in OPTIONR

and GRWATRR. If NHIC is greater'than zero (0), the appropriate stream identification number is input'together with an index value of "1" to identify that

the stream is to be placed into a high integrity container or a value of "2"

identifying that the stream is to be stabilized by some other means.

When NNDX is greater'than zero (O), the identification number of the streams

to receive special treatment is input by the index named IDIFF and the index

value identifying the new treatment is input by NDXD (see Table D.4).

When NHIC is greater than zero.(O), the identification number of the streams

to be placed in a-high integrity container or otherwise stabilized is input by

* the index named IDIF, and the index value is read in by NHCD (see Table D.4).

The NOPR index is used in all five codes and is used to distinguish whether a

generic or regional-analysis is to-be performed. Possible values for and consequences of this'index are listed in Table D.4.

The NLST index is used in'the GRWATRR and OPTIONR codes to specify which set

of reference waste classification limitsare used in the analysis. In the codes

the reference sets of cla'ssification -zlimits are read in through the IN2FIL file

and stored in the array FLST(6,4,16).' Index values of 1 through 6 correspond

to the sets listed in TableD.6. .An index value equal to zero indicates that

the reference sets 6of'w 'st'e"class'ification limits are ignored. Rather, the

classification limits.are read in by thet user.

7. INPUT FORMATS. . -

7.1 GRWATRR

Input for the GRWATRR cEode consists.of the desired number of data sets. Each

data set consists of a minimum of 5 cards as follows:

D-25
Table 0.6 LUst of Reference CLST sets

Set 1 Set 2 Set 3 Set 4 Set S Set 6

A B C HWF A B C HWF A B C HWF A B C fIF A B C HWF A B C HWF

H-3 109 109 109 10' 10' 10' 10' 109 1. 10' 109 109 4.E+1 10' 109 109 4.E.1 10' 10' 10' .0. 10' 10' 109

O C-14 109 109 10' 10' 10' 10' 10' 109 1. 10' 109 109 - 8.E-1 S.E-I 8.E-1 B.E'0 8.E-1 8.E-1 8.E40 8.E.1 0. 8.E-1 8.E+O 8.E+1

\ Fe-SS 10' 10' 109 109 10' 109 10' 10' 109 109 10 10' 7.E+2 7.E+4 10' 10' - 7. E2 10' 10' 10' 0. 10' 10' 10' on NI-59 10' 10' 109 1o' 10'. 109 10' 10 1. 10' 109 109 2.2E*0 2.2E+O 2.2E+0 2.ZE+1. 2.2E*0 2.2E+0 2.2E*1 2.2E+2 0. 2.2E.0 2.2E*1 2.2E+2

Co-60 10' 10' 10' 10' 109 109 10' 109 1. 10'. 109 109 7.E+2 7.E+4 10* 10' 7.E+2 10' 10' 10' 0. - 10' 10' 10'

Nl-63 lO 10' 10' 10' 10' 109 109 109 1. 10' 109 109 3.5E*0 7.E+1 7.E*1 7.E*2 3.5E40 7.E+1 7.E+2 7.E+3 0. 7.E+1 7.E+2 7.E+3

Nb-94 109 109 109 109 109 109 10' 109 1. 109 10' 109 2.E-3 2.E-3 . 2.E-3 2.E-2 2.E-3 2.E-3 2.E-2 2.E-1 0. 2.E-3 2.E-2 2.E-1

Sr-90 109. 109 109 10' 10' 10' 10' 109 1. 10' -10 109 4.E-2 1.5E42 7.E,2 7.E+3 4.E-2 1.5E+2 7.E+3 7.E.4 0. 1.5E+2 7.E+3 7.E*4

Tc-99 10' 10' 10' 109 109' 109 109 10' 1. 10' 109 109 3.E-I 3.E-1 3.E-1- 3.E+0 3.E-1 3.E-1 3.E40 -3.E41 0. 3.E-1 3.E*O 3.E+1

1-129 109' 109 109 109 10. 10' 109- 109 1. 109 . 109 109 8.E-3 8;E-3 8.E-3 8.E-2 8.E-3 8.E-3 8.E-2 8.E-1 0. 8.E-3 8.E-2 8.E-1

Cs-135 10' 10' 10' 10' 109 109 109 109 1. 10' 109 109 8.4E+1; 8.4E+1 ,8.4E'1 8.4E+2 8.4E+1 8.4E*1 8.4E+2 8.4E43 0. 8.4E+1 8.4E+2 8.4E+3

Cs-137 10' 10' 10' 10' 10' 10' 109 109 1. lo 109 109 -1.E +I - 4.4E+1 4.6E+3 4.6E+4 I.E+0 4.4E41 4,6E+3 4.6E+4 0. 4.4E+1 4.6E+3 4.6E+4

U-235 10' 109 109 109 109 10' 109 109 1. 109 10' 10' 4.E-2 4E-2 4.E-2 4.E-1 ..'4.E-2 4.E-2 4;E-1 4.E*0 0. 4.E-2 4.E-1 4.E O

U-238 10' 10' 10' 109 lo 10' 109 10' 1. 109 10' 109 5.E-2 5.E-2 5.E-2 5.E-1 5.E-2 S.E-2 5.E-1 5 5.E+1 0. 5.E-2 S.E-1 5.E+1

TRU 10' 10' 10' 109 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-1 1.6E-2 1.6E-2 1.6E-1-1.6E40 0. 1.6E-2 1.6E-1 0.6E+0

Pu-241 109 109 109 109 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 1.6E-2 5.6E-1 5.6E-1 5.6E-1 5.6E+tO 5.6E-1 S.6E-1 5.6E*0 5.6E+1 0. 5.6E-1 5.6E+0 5.6E.1
Card Columns Format Index Definition

I . . .. I . . . I

1 1-20

.1-2

3-4

2A10 NOTE Title of execution

5-6

7-8

9L10

11-12

13-16

3 1-2

3-4

5-6

7-8

9-10

11-12

13-14

15-16

17-18

19-20

21-22

23-27

28-32

4 1-2

3-4

5-6

7-8

9-10

11-12

13-14

15-16

17-18

19-20

21-22

23-27

28-32

5 1-2

* . 3-4

5-6

7-8,

9-10

11-12

12 -. I2

I2

I2

I2

I2

I4

I2

I2

12

I2

I2

I2

I2

I2

12

I2

I2

I5

I5

12

12

I2

I2

I2

I2

12

12

I2

12

I2

I5

I5

I2

I2

I2

I2:

I2

I2

NOPR

NNDX.

NORD

N LST

NHIC

NOPTW

NTHIC

IR1

IDI

IC1

IX1

IE1

IS1

IL1

IG1

IH1

IQ1

ICLI

IP01

IIC1

IR2

ID2

IC2

IX2

IE2

IS2

IL2

IG2

IH2

IQ2

ICL2

IP02

TIC2

.Generic or-regional analysis

Number of streams excluded,

distributed,.or-stabilized.through

facility design

Number of waste streams considered

in a different order than that

given by IORDD D

Identity of reference waste

classification list set

Number of streams to go into HIC or

stabilized'-

Choice of well, boundary or intruder

Lifetime of HIC (years)

IRDC values for-set 1

I RDC values for set 2

!

I

I

.,I. I

IORDD(1)Order of considering

IORDD(2)- ----

IORDD(3)

IORDD(4).

IORDD(5)

IORDD(6)

waste spectra

D-27
However, if NLST = 0, NNDX > 0, NHIC > 0, or NORD > 0 for a given set, then

additional cards will be read for that-set as follows:

If NLST = 0, then 8 cards follow with the format:

Card Columns Format Variable Definition

1 1-10

11-20

21-30

31-40

41-50

51-60

61-70

71-80

2 1-10

11-20

21-30

31-40

41-50

51-60

61-70

71-80

E10. 3

E10. 3

E10. 3

E10. 3

E10. 3

E10.3

E10.3

E10. 3

E10.3

E10.3

E10.3

E10. 3

E10.3

E10. 3

E10. 3

E10. 3

E10.3

E10. 3

E10.3

E10.3

E1O.3

E1O.3

E10.3

E10.3

E10.3

E10. 3

E10.3

E10.3

E10.3

E1O. 3

E10. 3

E10. 3

CLST(1,1-8) Waste classification limits

3 1-10

11-20

21-30

31-40

41-50

51-60

61-70

71-80

CLST(1, 9-16)

CLST(1, 1-8)

4 1-10 CLST(2, 9-16)

11-20

21-30

31-40

41-50

51-60

61-70

71-80

cards 5-8 are read similarly

If NNDX > 0; then NNDX cards follow'with the following format:

D-28
Card Columns Format. Index Definiti6n- .

.. .- _ _ -- --- . . . . . . . - . . ... - .... -.. .. . . ..... . . ..

All 1-2 I2 IDIFF ? Identification number of stream '

3-4 12 . 'NDXD

.' .; r. I

. Option to exclude from analysis,

treat as a distributed waste

stream, or stabilize only using . : disposal facility design.

(-2 < NDXD < 2)

I ..

: ., -.; ;

If NHIC > O, then NHIC cards follow with the format:,

Card Columns 'Format Index Definition

All 1-2 12 IDIF Identification number of stream

3-4 I2 NHCD Index to identify treatment (I or 2)

If NORD > 0, then NORD cards follow with the following format:

Card Columns Format Index DefinitionAll 1-2 12 NK Identification number of waste

stream

3-4 I2 NORDD(1) border in which waste spectra are

5-6 I2 NORDD(6) considered for the particular

7-8 I2 NORDD(6) stream. :

9-10 I2 NORDD(6)

11-12 I2 NORDD(6)

13-14 I2 NORDD(6) ;

7.2 OPTIONR

Input for the OPTIONR code consists of the desired number of data sets. Each

data set consists of a minimum of 5,cards as follows:
II

Card Columns Format Index Definition'

1I

2

1-20

1-2

3-4

5-6

7-8

9-10

11-12

3

4

1-2

3-4

5-6

7-8

9-10

11-12

13-14

15-16

17-18

19-20

21-22

23-27

28-32

1-2

3-4

5-6

7-8

9-10

11-12

13-14

15-16

17-18

19-20

21-22

23-27

28-32

1-2

3-4

5-6

7-8

9-10

11-12

2A10

I2

I2

I2

I2

I2

I2

I2

I2

I2

I2

I2

I2

I2

I2

I2

I2

I2

I5

I5

I2

I2

I2

I2

I2

I2

I2

I2

I2

12

12

I5

15

I2

I2

I2

I2

I2

I2

NOTE

NOPR

NNDX

NORD

N LST

NHIC

NBEST

IR1

ID1

IC1

IXl

IEl

IS1

ILI

IG1

IH1

IQ1

ICL1

IP01

IIC1

IR2

ID2

IC2

IX2

IE2

IS2

IL2

IG2

IH2

IQ2

ICL2

IP02

IIC2

IORDD(1)

IORDD(2)

IORDD(3)

IORDD(4)

IORDD(5)

IORDD(6)

Title of execution

Generic or regional analysis

Number of streams excluded,

distributed, or stabilized through

facility design

Number of waste streams considered

in a different order than that

given by-IORDDIdentity of reference waste

classification list set

Number of streams to go into HIC

or stabilized

Credit for waste form to reduce

intruder impacts

IRDC values for set 1

IRDC values for set 2

5 Order of considering waste spectra

'D-30
However, if NLST = 0, NNDX > 0, NHIC > 0, or NORD > 0 for a given set, then

- additional cards will be-read for'that set as follows: --

---'If-NLST = 0. then 8-'cards follow with the format:

Card ' Columns

1 ' 1-10

11-20 -.- -- .- '''---'-21-30

41-50

51-60

61-70

71-80

Format Index Definition

,E10.3,-

E10.3

E1O. 3

E10.3

E10. 3

E10. 3

E10. 3

CLST(1,1-8) Waste classification limits

2 1-10

11-20

21-30.,

,: - 31-40,

41-50

51-60

61-70

71-80

3 1-10

11-20

21-30

'31-40

' 41-50

51-60 -. . - 61-70

71-80

4 1-10

11-20

21-30

31-40

41-50

51-60

61-70

71-80

E10. 3

E10. 3

E10.3

E1O.3

E10. 3

E10.3

E10.3 E10. 3 E10.3

E10.3

E1O. 3

E1O.3

E10.3 -

E10.3

E10.3

E10.3

E10.3

E1O.3

E10.3

E10.3

E10.3

E10.3

E10.3

E10.3

CLST(1,9-16)

CLST(2,1-8)

CLST(2,9-16)

. I-'

Cards 5-8 are read similarly

If NNDX > 0, then NNDX cards follow with the following format:

D-31
.U-MCard Columns Format Index Definition

All 1-2 I2 IDIFF Identification number of stream

3-4 I2 NDXD Option to exclude from analysis

treat as a distributed waste

stream, or stabilize only using

disposal facility design.

(-2 < NDXD < 2)

If NHIC > 0, then NHIC cards follow with the format:

Card Columns Format Index Definition

All 1-2 I2 IDIF Identification number of stream

3-4 I2 NHCD Index to identify treatment (1 or 2)

If NORD > 0, then NORD cards follow with the following format:

Card Columns Format Index Definition

All 1-2 I2 NK Identification number of waste

stream

3-4 I2 NORDD(1) Order in which waste spectra are

considered for the particular

stream

5-6 I2 NORDD(2)

7-8 I2 NORDD(3)

9-10 I2 NORDD(4)

11-12 I2 NORDD(5)

13-14 I2 NORDD(6)

8. LISTING OF COMPUTER CODES AND DATA FILES

This section presents a listing of the computer codes and data files used in

the final EIS. The computer codes are listed in the following order:

* GRWATRR

* OPTIONR

The data files follow in the following order:

* IN1FIL

* GW2FIL

* IN2FIL

D-32
GRWATRR Code

PROGRAM GRWATRR

C*****4***{***f4.*4****u .** ***.*******a**444*********4**4**4*

C THIS IS THE MODIFIED GROUNDWATER IMPACTS CODE. IT FINDS *

C THE DOSE FROM GROUNDWATER MIGRATION OF RADIONUCLIDES FOR *

C THREE CASES: THE INTRUDER WELL. THE POPULATION WELL. AND *

C SURFACE WATER.-HOWEVER. WHEN NOPTW-1. THE BOUNDARY WELL *

C IS SUBTITUTED FOR THE INTRUDER WELL. SEE APPENDIX D OF * C FEIS FOR DETAILS

Co** .*,**.*.*..*..**.u. *444#.**.4**4***44*.4*.w*.****.*

C

CHARACTER*10 BASNC90),NUC(36).NOTE(2).DES(3),

COtMON/BAST/DAS(90.32.2).ISPC(6.90.10).DCF(36.7.9).FICRP(7)

* /CHRC/DASN.NUC

* /NVCS/AL(36).F "F(36).RET(36.5)

+ /DTNXI/IRDCI(13)/DTNX2/IRDC2(13)

* /DTIS/FSC(6).FSA(6),PRC(6,2).GFC(6.3).TTM(6.3).TPC(6.3).

-RGF(6.3).POP(6.3).DTTh(6).DTPC(6).TPO(6.2).NRET(6)

+ /VOLS/VRGI.VRG2,VLAY.VHOT.VNOT.RVOL(4.36)

- , /IMPS/DZD(23,22,21).DZ(71 3.22).DZT(7.3,22)

/NBAS/NSTR.NNUC.NDXS(9O).IMOD(90).ISPEC(90).IHIC(90)

+ /LSTS/CLSTC4.I6),DIST(3.16.7),IORD(6.90).FLST(6,4,16)sNLST

DIMENSION IORDD(6).TNM(22).NORDD(6)

C .,'

C4**N4**4*****4******42**4.)4N*4*4.**********44***1********1*4*4**4**

C THE ABOVE MATRICES AND ARRAYS ARE BRIEFLY EXPLAINED BELOW.*

C MORE DETAILED EXPLANATIONS CAN BE FOUND IN THE DEIS&FEIS. 4

C,. .

C BASN - NAME OF THE WASTE STREAMS *

C NUC - NAME OF THE RADIONUCLIDES CONSIDERED *

C NOTE - TITLE OF TIIE PROBLEM -

C DES - DESCRIPTIONS OF PATHWAYS *

C BAS - BASIC DATA MATRIX OF VOLUMES & CONCENTRATIONS *

C ISPC - WASTE SPECTRUM INFORMATION.

C DCF - PATHWAY DOSE CONVERSION FACTORS , ,

C FICRP - ICRP WEIGHTING FACTORS FOR ORGANS *

C AL - DECAY CONSTANTS OF RADIONUCLIDES *

C FnF - PARTITION RATIOS BETWEEN WASTE AND LEACHATE *

C RET - RETARDATION COEFFICIENTS OF RADIONUCLIDES 4

C IRDC1 - DISPOSAL TECHNOLOGY INDICES FORUNSTABLE WASTES * C IRDC2 - DISPOSAL TECHNOLCOY.INDICES -FOR STABLE WASTES *

C FSC - SOIL-TO-AIR TRANSFER FACTOR:- CONSTRUCTION

A FSA - SOIL-TO-AIR TRANSFER FACTOR - AGRICULTURE 4

C GFC - DILUTION FACTORS FOR GROUNDWATER SCENARIOS

C TTh - TRAVEL TIME(YEARS) FOR GW SCENARIOS *

C TPC - PECLET NUMBERS FOR CW SCENARIOS

C ROF - GEOMETRIC REDUCTION FACTORS FOR.'CW SCENARIOS *

C POP - POPULATION FACTORS FOR.ACCIDENT SCENARIOS *

C DTTM - TRAVEL TIME BETWEEN DISPOSAL SITE SECTORS *

C DTPC - PECLET NUMBER BETWEEN DISPOSAL SITE SECTORS *

C TPO - X/O WEIGHTED POPULATION SUM-DISTRIBUTIONS *

C NRET - RETARDATION COEFFICIENT.SET FOR THE'DISPOSAL SITE*

C RVOL w REGIONAL VOLUMES-OF'WASTE GENERATED. *

C DZD - DUMMY DOSE MATRIX,CALCULATED INrERNALLY *

C DZ - DUMMY DOSE MATRIX CALCULATED INTERNALLY *

C DZT - DUMMY DOSE MATRIXCALCULATED INTERNALLY *

C NDXS - INDEX ON STATUS OF WASTE STREAM - - *

C IMOD - CALCULATED DISPOSAL MODE OF WASTE, STREAM *

C ISPEC - CURRENT SPECTRUM FOR THE 'WASTE-STREAM *

C IHIC - HIGH INTEGRITY CONTAINER INDEX , > *

C CLST - LISTS OFUASTE.CLASSIFICATION CONCENTRATIONS *

C DIST - ACTIVITY DISTRIBUTIONS OF CERTAIN WASTE STREAMS *

C IORD - ORDER IN WHICH WASTE SPECTRUMS-ARE CONSIDERED *

D-33
GRWATRR Code (cont'd)

C FLST - GENERAL LISTS OF WASTE CLASS CONCENTRATIONS *

C TYM - YEARS AT WHICH THE IMPACTS ARE CALCULATED *

C IORDD - BASIC ORDER FOR SPECTRUM CONSIDERATION *

C NORDD * DUMMY ORDER FOR SPECTRUM CONSIDERATION *

C

DATA NTYM/22/

DATA TYM/40. * 50. * 60. 70. 80. 90. 100., 120. . 200. s 300. e 400..

5 500. # 600.' .700. e900. go900. 1000. . 2000. i 4000. a 6000..

* 8000. 0 10000. /

DATA DES/' BOU-WELL '.' POP-WELL ,' POP-SURF I

C

C NEXT SECTION READU. ALL THE BASIC INFORMATION

C

10 REWIND I

REWIUD 2

CALL READIN

C

C NEXT SECTION READS BASIC AND CONDITIONAL INFORMATION

C FROM TAPES. PROORAM QUITS WHEN.,THERE ARE NO MORE CASES

C TO BE CONSIDERED. CONDITIONAL INFORMATION IS USED TO

C ALTER THE BASIC INFORMATION DEPENDING ON THE CASE.

C .

READtS.102.END-IOO)IOTE

12 READC5.103)NOPRNNDXsNORDNLST.NHICNOPTWNTHIC

READ(5.104)CIRDCItI),I-1.13)

READC5s104)CIRDC2CI).o11.13)

READCS.104)(IORD0CI).1-1,6)

IF(NLST.EG.O)READ(5,105)(CCLST(IJ). J-1.16),1-1.4)

102 FORMAT(2A10)

103 FORMAT(612.14)

104 FORMATIL12, 215)

105 FORMAT(SE10.3)

DO 14 I-1.NSTR

ISPECCI)-l

14 NDXSCI)-l

DO 16 I-1.3

, NDXStI)--l

16 NDXS(r+4)--1

IF(NNDX.EQ O)GO TO 20

DO 19 I-1.NNDX

READ(5.104) IDIFFNDXD

19 NDXStIDIFF)nNDXD

20 DO 2V I-1.NSTR

20 IHICtI)-O

IF(NHIC.EQ.0)0O TO 26

DO 24 I-1.NHIC

READS.S104) IDIFNHCD

24 IHICCIDIF)-NHCD

26 DO 28 I-I.NSTR

DO 28 J-1.6

28 IORDtJ.I)-IORDDtJ)

IF(NORD. EQ. O)GO TO034

DO 32. 1-1,NORD

READ(5.104) NK.(NORDDCJ).J-l,6)

DO 30 Ju1;6

30 IORDtJ.NK)-NORDD(J)

32 CONTINUE

34,IFCNLST.EQ.O)0 TO 39

DO 36 J-1,4

DO.36 K-1.16

IF(FLST(NLST.J.K).LT.1.E-7)FLST(NLSTJ.K)-l.E-7

36 CLST(J.K)nFLST(NLST.J.K)

D-34
GRWATRR Code (cont d)

38 IF(NOPR. EQ. O)CO TO 42

IRR-IRDC1(1)

-IF(IRR.CT.4)IRR-2

DO 40 ISTR-1.NSTR

BAS(ISTR.3,'l)RVOL(IRR.ISTR),

40 BASCISTR.3.21-RVOLCIRR.ISTR)

C

C THIS IS THE REAL 8ECINNINO OF THE CODE.

C FIRST BASIC INFO IS PRINTED. THEN ARRAYS ARE ZEROED OUT.

42 WRITEC4o1001) NOTE.

NI-I

.WRITE(4.1002) Nl.IRDCl

N1-2 .7-

WRITEC4.1002) Nl.IRDC2

WRITE(4,1003) NOPR.NNDX.NORD.NLST.NHICNOPTW.NTHIC.

(IORDD(I.I-1.6)

VNOTO.0

VRC1-O.0

VRC2-0.0

VLAY-O.0

VHOT-0.0

THIC-NTHIC

C

C NEXT SECTION IS THE OPEN DO LOOPTHAT DETERMINES THE

C STATUS OF THE WASTE STREAMS.

C

ISTR-O

4-¶ ISTR-ISTR+-

IF(ISTR.CT.NSTR) CO TO 66

IF(NDXS(ISTR).NE.0) GO TO 46

WRITE(4#1009)BASN(ISTR)

IMODCISTR)-O

CO TO 44

46 IHC-IHICCISTR)

IF(IHC.NE.O)WRITE(4.1011)BASN(ISTR)

IF(IRDC(l1).NE.4.OR.ISTR.CT.37) CO TO 50

DO 4E J-1.6

48 ISPC(JISTR.5)-ISPC(J.ISTR.5)-l

50 IMOD(ISTR)-l

CALL RCLAIM(ISTR.NOPR)

Ir-IMODCISTR)+l

C AFTER DETERMININC THE STATUS AND IMPACTS OF THE WASTE

C STREAMS, VOLUMES ARE STORED APPROPRIATELY.

C

CO TO (52.54.56.56.56.58.'5.62.62).II

52 VNOT-VNOT+BAS(ISTR.3,1)

CO TO 44

54 VRCl-VROl+BAS(ISTR,3,1)

CO TO 44

56 VRC2-VRG2+BAS(ISTR.3.1)

00 TO 44

59 VLAY-VLAY+BASCISTR,3.1)

CO TO 44

62 VHOT-VHOT+BAS(ISTR.3.1)

CO TO 44

C 4

C THIS IS THE END OF THE OPEN DO LOOP TO CLASSIFY THE

C WASTE STREAMS. NEXT SECTION PRINTS WASTE VOLUMES

C.

66 IF(NHIC.NE.O)WRITE(4.1012) NrHIC

WRITE(4,1004) VRCI.VRC2,VLAY.VHOT.VNOT

D-35
GRWATRR Code (cont'd)

DO 70 I-I.NSTR

70 WRITE(4r1007) BASN(I).BAS(I,3.1).BAS(I.3.2).IMOD(I).ISPEC(I)

AFTER CLASSIFICATION BASED ON THE PROPERTIES OF THE

WASTE STREAM, THE CLASSIFICATION STATUS MAY BE CHANCED

IN SUBROUTINE MCODIF DEPENDING ON THE DISPOSAL TECHNOLOGY

INDICES.

CALL MODIF

WRITE(4,1008)

DO 72 I-I1.tSTR

72 WRITEC4.1007) BASN(I).BAS(I.3.1).DAS(I.3.2).IMOD(I).ISPEC(I)

68 CALL ZEROCDZT.462)

NEXT SECTION CALCULATES AND PRINTS IN TWO STEPS (UNSTABLE

AND STABLE WASTES) GROUNDWATER MICRATION IMPACTS

DO 92 ICN-1.2

CALL ZERO(DZD,10626)

CALL GWATER(NTYM.TYM.THIC.ICN.NOPTW)

CALL ZERO(DZ. 462)

LOOP 85 SUMS THE DOSES OVER ALL NUCLIDES

DO 84 ITYMuI.NTYM

DO 84 K-1.3

KK-(K-1)*7

DO 84 J-1,7

DO 82 INUC-INNUC

82 DZ(J.KITYM)-DZ(J.K.ITYM)+DZD(INUC.ITYM.KK+J)

94 DZT(JK, ITYM)-DZTCJ#K.ITYM)+DZ(J.IKITYrI)

LOOP 90 OUTPUTS GROUNDWATER DOSES FOR 7 ORGANS. 3 PATHWAYS,

AND 22 TIMESTEPS.

IFCICN.EQ.I)WRITE(4.v0I3)

IF(ICN.EQ.2)WRITE(4.1014)

DO 90 ITYMI.sNTYM

TYMD-TYM(ITYM)

WRITE(4.1005)TYMD

DO 89 K-1.3

Al-0.0

DO 86 Jw1.7

86 Al-Al+DZCJ.K.ITYM)4FICRP(J)

89 WRITE(4.1006) DES(K).(DZ(J.K.ITYM).J-1.7).A1

90 CONTINUE

92 CONTINUE

WRITEC4.1015)

DO 99 ITYM-1,NTYM

TYMD-TYM(ITYM)

WRITE(4.1005) TY1ID

DO 96 K-I1.3

AI=O.

DO 94 J-1.7

94 Al-AI+FICRP(J)*DZT(JKITYM)

96 WRITE(4.1006) DES(K).(DZT(J.K.ITYM).J-1,7).AI

98 CONTINUE

CO TO 10

100 STOP

001 FORMATCIHl/2X.2A10)

002 FORMAT(//2X'IRDC GRP 'I2/Z2X'DISPOSAL TECHNOLOGY INDICES'/21

* 'IR -'12' ID -'12' IC -'12' IX -'12/2X

* 'IE -'I2' IS -'12' IL -'12' IO -'12/2X

I'

I c

D-36
i

GRWATRR Code (cont'd)

* 'IH -'12' ICL-'12' INS-'2'. IPO-'I2' IIC-'I5)

1003 FORMAT(//2X'NOPR-'l2.2X'NNDX-1.2.2X'NORD-'I2.2X/

* 2X'NLST-'12.2X'NHIC-'12.2X'NOPT-'12.2X'NTHIC-'14/

* 2X'IORD 1-6 ARE:'612) -

1004 FORMAT(/lP.2X' VRC1 -'E9.2' VRC2 - 'E9.2' VLAY -'E9.2.

+' VHOT -'E9.2' VNOT -'E9.2)

1005 FORMAT(/2X'YR .-'F6.0' BODY BONE -LIVER'

*2X' THYROID KIDNEY LUNG 0-I TRACT- ^-ICRP')

1006 FORMAT(lP.2X.A1O.8E10.3)

1007 FORMAT(2X.A1O2E10.3,215)

1008 FORMAT(//2X'RECLASSIFIED WASTE STREAMS')

1009 FORMAT(/2X'WASTE STREAM NOT INCLUDED IS :'2X.A10)

1011 FORMAT(/2X'WASTE STHEAM USING H.-I.C. IS :'2X.A10)

1012 FORMAT(2X.'H.I.C. HAS A LIFE OF '14' YEARS')

1013 FORMAT(//2X.'IMPACTS FROM UNSTABLE WASTE STREAMS')

1014 FORMAT(//2X,'IMPACTS FROM STABLE WASTE STREAMS')

1015 FORMAT(//2X.'TOTAL IMPACTS')

END

C~

CO*O******4**{***4*z**4********O*4**44**.*****W*-4*4*W** **********#******

C

SUBROUTINE READIN

C

- C ALL THE BASIC INFORMATION CONTAINED IN TAPES 1 AND 2

C IS READ IN THROUGH THIS SUBROUTINE.

C

CHARACTER*10 BASNC90).NUC(36)

COMMON/BAST/BAS(90,32o2),ISPC(6,90,10).DCF(36.7.8).FICRP(7)

* /CHRC/BASN.NUC - -

* /NUCS/AL(36).FMF(36).RET(36#5)

* /DTIS/FSC(6).FSA(6).PRC(6,2)#.FC(6.3).TTI(6.3),TPC(6.3). + RGF(6.3).PQP(6.3).DTTh(6).DTPC(6).TPO(6.2).NRET(6) + /VOLS/VRGI.VRG2,VLAY.V8OT, VNOT.RVOL(4.36)

/NBAS/NSTR.NNJCNDXS(90).IMOD(90).ISPEC(90).IHIC(90)

* LSTS/CLST(4,16),DIST(3;16.7).IORD(6,90),FLST(6,4,16)

READ(1,101) NSTR.NNUC.FICRP

DO 20 I-t.NSTR

20 READ(1,102)BASN(I),(BAS(I.Jl),Ji2,27)

DO 25 I-1.NSTR : 25 READ(I.102)BASN(I).aBAS(IeJ.2).J-2.27)

NN-NNUC+13 -

DO 40 I-1.NS

READ(1.104)NUC(I).AL(I).Fr (I).RET(Il).RET(IU4)

DO 30 K-1.8

30 READ(1.106)(DCF(I.J.K).J-1.7) -

40 CONTINUE

DO 50 1-1.6 -- READe1. 105)FSC 1). FSAC I)# tPRC (I#J)* J-lo2). (GFC(I.J).J-1l.3)t

+ (TTM(I.J)*J21.3). (TPC(I.J).J'1.3). + (RGF(I*J)*J-1.3)t(POP(I.J).J=1l3),NRET(I)#

* DTTM(I).DTPC(I).(TPO(I.J).J1.2)

50 CONTINUE -

DO 55 I-1.4

55 READ(1.108) (RVOLCI.J).J-1.NSTR)

DO 60 K-1.6 -

DO 60 I-1.NSTR * -

60 READC2.103) (ISPC(K.I.J).J-l.10)

DO 70 K-1.7

DO 70 1-1.3

70 READ(2.107) (DIST(I.J.K).J=1.16) -

DO 80 1-1.6 -

DO 80 K-1.16

80 READ(2.109) (FLST(IoJ.K)sJ-1.4)

D-37 I
GRWATRR Code (cont'd)

DO 85 INUC-I.NNUC

A2-RET(INUC.4)

Al-(A2/RET(INUC.1))**0.334

RET(INUC.5)-A2*Al

RET(INUC.3)-A2/AI

e5 RET(INUC.2)-RETCINUC.1)*A.

101 FORMAT(215,7F5.2)

102 FORMAT(AO. 2E10.3/lOX.6E10.3/lOX,6E10.3/lOX.6E10.3/lOX.6E10.3)

103 FORMAT(1OX. 1015)

104 FORMAT(AIO.4E10.3)

105 FORMATClOX.7E10.3/lOX.6E10.3/lOX.6E10. 3. I/lOX.4E10.3)

106 FORMAT(IOX#7E10.3)

107 FORMAT(SE10.3)

109 FORMAT(lOX.6EI0.3/lOX.6E10.3/lOX,6E10.3/lOX. 6E10.3/

lOX.o6E10.3/lOX.6E10.3)

109 FORMAT(lOX.4E10.3)

RETURN

END

C

C****h*** i***+ X** **<*w*#****** I**************

C

SUBROUTINE COMBYN(ISTR.NOPR)

C

C THIS SUBROUTINE IS CALLED FRCM SUBROUTINE RCLAIM AND

C CHANCES WASTE SPECTRUMS & MODIFIES ACTIVITY DISTRIBUTIONS

C

CHARACTER*10 BASN(90).NUC(36)

COMMON/BAST/BAS(90.32,2).ISPCC6.90.10),DCF(36.7.8).FICRP(7)

+ /CHRC/BASN.NU* + /NUCS/AL(36).FMF(36).RET(36.5)

+ /NBAS/NSTR.NNUC.NOXS(90). IMOD(90). ISPECC90)

+ /LSTS/CLST(4, l6).DIST(3.16.7).IORD(6.90).FLST6,4. 16)

DIMENSION DEC(2.2)

DATA DEC/.9..75. 9.. 25/

AA5-3.62

IFCN0PR.OT.0)AA5-1.0

IDR-ISPEC(ISTR)

NSPC-IORD(IDR.ISTR)

C

C IF THIS IS CALLED FOR THE FIRST TIME (IDR-l) THEN THE ROUTINE

C PROCEEDS TO STATEMENT 20 (THE MAIN SECTION). HOWEVER. IF

C IDR > I. THEN IT MUST FIRST UNDO THE PREVIOUS MODIFICATION.

C

IFtIDR.EO.l)CO TO 20

ISP-IORD(IDR-1.ISTR)

A1-ISPC(ISP.ISTR.2)

Al-A1/ISPCCISP.ISTR.3)

BAS(ISTR.3.1)-BAS(ISTR.3.1)*A1*AA5

BAS(ISTR. 3.2)-BAS(ISTR.3,2)*AI*AAS

DO 12 1-4.27

DO 12 J-1.2

12 BASCISTR, I.J)-AS(ISTR.I.J)/Al

IF(NDXS(ISTR).CE.O)CO TO 16

IJK-BASCISTR.2.#1 +0.

DO 14 I-1.16

DIST(l.I.IJK)-DIST(1.I.IJK)/AL

14 DIST(3.I.IJK)-DIST(3.I.IJK)/Al

16 IP-ISPC(ISP.ISTR.l0)/1000

IF(IP.LT.5) CO TO 20

J-2

IF(IP.EQ.5) J-1

BAS(ISTR.5,1)-BAS(ISTR.5.1)/C1.-DEC(1,J))

BAS(ISTR.6.1)-BAS(ISTR,6.1)/CI.-DEC(2.J))

D-38
GRWATRR Code (cont'.d)

BAS(ISTR,5,2)=BAS(ISTR,5,2)/C1 -DEC(C1J))

BAS(ISTR.6.2)-BAS(ISTR.6,2)/(1.-DEC(2,J))

C .R .. 'T . ':ST GEERTO

C MAIN SECTION STARTS HERE. FIRST THE UASTE CENERATOR

C IMPACTS ARE SET-EQUAL TO ZERO, THEN THE VOLUMES AND

C CONCENTRATIONS ARE MODIFIED.

C

20 Al-ISPC(NSPC.ISTR.2)

Al-A2/ISPC(NSPC.ISTR#3)

A2-BAS(ISTR.3 I)IAA5

A3-A2/AI .

BAStISTR.3,1)-A3

BAS(ISTR.3.2)-A3

DO 22 1-4.27

DO 22 J-1.2

22 BASCISTR#I.J)-BAS(ISTR.I.J)*Al

IF(NDXS(ISTR).CE.0)GO TO 26

IJK-BAS(ISTR.2,1)+0.1

DO 24 1-1.16

DIST(I.I.IJK)-DIST(l.I.IJK)*Al

24 DISTC3,I. IJK)DIST(3 I.IJK)*A1

26 IP-ISPC(NSPC.ISTR.10)11000

IF(IP.LT.5)RETURN

J-2

IF(IP.EG.5) J-1

BAS(ISTR.5.1)-(1.-DEC(l.J) )*BAS(ISTR.5.1)

BAS(ISTR.6.1)-(1.-DEC(2.,J))BAS(ISTR.6.1)

BAS(ISTR,5,2)-(1.-DEC(l.J))*BAS(ISTR,5.2)

BAS(ISTR.6.2)-Cl.-DEC(2.J))*BAS(ISTR,6,2)

RETURN

END

C

C .

SUBROUTINE RCLAIM(ISTR.NOPR)

C

C THIS SUBROUTINE CLASSIFIES THE WASTE STREAMS IF THEY DONT

C HAVE A DISTRIBUTION, ANO CLASSIFIES THE PORTION OF THE

C DISTRIBUTION (AS APPROPRIATE).

C

CHARACTER10 BASN(90). NUC(36)

COMMON/BAST/BAS(90.32.2).ISPC(6.90.10).DCF(36;7.8).FICRPC7)

+ /CHRC/DASN.NUC

+ /NUCS/AL(36).FMF(36).RET(36,5)

+ /DTNXI/IRI.IDI. ICI. IXI. IEl. ISl. ILl. IGl,.IHlIQ1S1. ICLI. IPOl. IICI + /DTNX2/IR2.ID2.IC2.IX2.IE2.rS2.IL2,IC2.'IH2.102.ICL2.IP02.IIC2

+ /NBAS/NSTRNNVC.NDXS(90).IMOD(90).ISPEC(90).IHIC(90) + /LSTSICLST(4.16).DIST(3.16,7),IORD(6.90).FLST(6.4.16)

NFC-O

C,

C -NEXT STATEMENT IS THE STARTING POINT AFTER EACH SPECTRUM

C CHANGE AS WELL AS FOR THE FIRST TIME - IN EFFECT AN OPEN

C ENDED DO-LOOP UNTIL- ALL. SOME. OR NONE OF THE WASTE IS

C CLASSIFIED. SEE COMMENTS UNDER STATEHENT 29.

C THE LOGIC OF THE SECTION FOLLOWS FIGURE 3 OF APPENDIX C

C OF THE FEIS.

C

10 IF(NUXS(ISTR).EQ.O)GO TO 34

IF(ISTR.LE.37JCALL COMSYNCISTR.NOPR)

IDR-ISPEC(ISTR)

ISP-IORDtIDR.ISTR)

IS-ISPC(ISP.ISTR,.)

IF(IHrCCISTR).CT.0)I8-1+XHIC(ISTR)

D-39
GRWATRR Code (cont'd)

IF(ISTR.GT.37.AND.NFG.EQ.O)CO TO 29

CALL LISTSCISTR.1.NX)

IF(NXX.EQ.t) GO TO 21

IF(IS.GT.O)0O TO 16

IF(IABS(NDXS(ISTR)).NE.2) CO TO 29

IF(IG2.EO.1.OR.IX2.EQ.3) CO TO 12

IF(IH2.EQ.l) CO TO 14

00 TO 29

12 CALL LISTS(ISTR.2.NX)

IFCNX.EQ.I) CO TO 23

IFCIL2.EQ.O)CO TO 13

CALL LISTSCISTR.3.tlX)

IF(NX.EQ.1) CO TO 25

13 IF(IH2.EQ.0) CO TO 29

14 CALL LISTS(ISTR.4.tX)

IF(NX.EQ.I) CO TO 27

OO TO 29

16 CALL LISTS(ISTR.2#NX)

IFCNX.EQ.1) CO TO 24

IF(IL2.EQ.O0)O TO 17

CALL LISTS(ISTR.3.NX)

IFCNX.EQ.l) CO TO 26

17 IFCIH2.EQ.O) CO TO 29

CALL LISTS(ISTR.4.NX)

IF(NX.EQ.1) CO TO 28

CO TO 29

21 IMODCISTR)-l

IF(18.NE.0) IMODCISTR)-2

CO TO 36

23 IMoDCISTR)-3

CO TO 36

24 IMOD(ISTR)-4

OO TO 36

25 IMODCISTR)-5

CO TO 36

26 IMODCISTR)-6

CO TO 36

27 IMODCISTR)-7

GO TO 36

28 IMOD(ISTR)-8

OO TO 36

29 IF(IDR.EQ.6) CO TO 34

*NFGCI..

IDR-IDR+I

ISPECtISTR)-IDR -

IF(ISTR.GT.37)CALL COMBYN(ISTR.NOPR)

CO TO 10

C

C THIS IS THE END OF THE OPEN ENDED DO LOOP TO CLASSIFY

C ALL'OR SOME OF THE WASTE STREAMS. IF THE WASTE .S NOT

C ACCEPTABLE. THEN STATEMENT 34 IS CALLED. IF SOME OF

C THE WASTE IS ACCEPTABLE, THE ACCEPTABLE PORTICN IS LEFT

C IN ITS ORIGINAL ORDER.- AND THE REST OF THE STREAM IS

C DESIGNATED AS THE NSTR+1 STREAM. SEE SUBROUTINE LISTS.

C

34 IMOD(ISTR)mO

36 RETUHN

END

C

C

SUBROUTINE LISTS(ISTR.NO.NX)

C

D-40
GRWATRR Code (cont'd)

C THIS SUBROUTINE COMPARES THE CONCENTRATIONS OF THE ISTR WASTE

C STREAM WITH THE CONCENIRATION FOR REGULAR (NG-I). STABLE

C (NO-2). LAYERED (NO-3). OR HOT (NO-4) WASTE DISPOSAL. AND

C MANIPULATES THE WASTE ACTIVITY DISTRIBUTIONS, IF NECESSARY.

C

- CHARACTER*10 BASN(90).NUC(36) -

COMMON/BAST/BAS(90.32.2).ISPC(6.90.l0).DCF(36.7.G8)FICRP(7)

+ /CHRC/BASN.NUC/DTNX2/IR2 + /NUCS/ALC36).FMFC36).RET(36.5)

+ /NBAS/NSTR.NNUC.NDXS(90).IMOD(90)sISPEC(90).IHIC(90)

+ --/LSTS/CLST(4.16).DIST(3.16.7).IORD(6.90).FLST(6.4.16).NLST

NX-0 :

INDEX-O ,

IF(IR2.NE.0.OR.NO.NE.1)GO TO 4

IF(ISTR.CT.7.AND.ISTR.NE.32)CO TO 4

INDEX-IC THE SECTION BETWEEN HERE AND STATEMENT 16 IS FOR WASTE

C STREAMS WITHOUT AN ACTIVITY DISTRIBUTION.

C

4 IDR-ISPEC(ISTR)

ISP-IORD(IDR.ISTR)

19-ISPC(ISPISTR,9)

A1-CLST(NO.16)

IF(XR2.NE.O0CO TO 6

IF(NLST.CT.3.AND.NO.NE.l)CO TO 6

IJK-BAS(ISTR.2.1)+0.1

IFCISTR.LE.7.OR.ISTR.EO.32.OR.ISTR.CT.37)AlI-A11*35.0

IF(IJK.EG.7)AI1-CLST(NG.16)

6 IF(NDXS(ISTR).LT.0) CO TO 16

IF(INDEX.EQ.O))O TO 8

C

C SUBROUTINE BARN PERFORMS A SPECIAL SUMMATION OF THE

C ACTIVITIES AND CLASSIFICATICN BASED ON THE CURRENT

C LLW DISPOSAL FACILITY LICENSE CONDITIONS.

C 3NLY UNSTABLE WASTES ARE SUBJECTED TO THIS TEST.

C -AND ONLY IF SR2-0.

C

- CALL BARN(ISTRaA2.A3.NX)

RETURN - DO 10 1-19.27

10 Al-A1+BAS(ISTR.1.1)

Al-AI-BAS(ISTR,2Z, I))/CLST(NO.15)+BAS(ISTQ.22.1)/AlI

IF(IR2.EO.O.AND.NQ.EG.I)C0 TO 14

10 12 1-1.14

A2-1.0

IF(I9.EQ.1)0O TO 12

IF(I.EQ.2.OR. I. EQ. 4.OR. I.EQ.6. OR. I.EQ.7)Ae-10.

12 Al-AI+BAS(ISTR.I+441),/(CLST(NQ. )*A2)

14 IF(AI.CT.1.0) RETURN

NX- ,

RETURN

C

C THIS SECTION STARTS THE TESTINO AND CLASSIFICATION FOR

C WASTE STREAMS WITH AN ACTIVITY DISTRIBUTION. FIRST THE

C TOTAL ACTIVITY THAT WOULD PERMIT A PORTION OF THE WASTE

C TO BE DISPOSED AS CLASS NOIS DETERMINED, THEN THE VOLUME

C OF THE WASTE CORRESPONDINO TO.THATACTIVITY IS CLASSIFIED.

C

16 IFCINDEX.EO.0)0O0TO 193,

CALL BARN(ISTR.A2,A3.NX)

00 TO 2

D-41
I aI!Q

GRWATRR Code (cont'd)

A-1S DO 20 1-19.27

20 Al-Al+BAS(ISTR,.11)

A2-Al

AlI-AI-BAS(ISTR.22.1))/CLST(NQ. 15)+BAS(ISTR.22,1)/All

IFtSR2.EO.O.AND.NQ.EO.1)OO TO 23

DO 22 1-.114

A3-1.0

IFCt9.EQ.1)CO T0 22

IF(I. EQ. 2. OR. r. EQ. 4. OR. I. EO. 6. OR. I. EQ. 7)A3-10.

22 Al-A1+BAS(ISTR,34. l)/(CLST(NQ. I)*A3)

23 DO 24 1-1.14

24 A2-A2+BASCISTR*1+4.1)

A3-A2/Al

C -

C AT THIS POINT A3 IS THE MAXIMUM PERMISSIBLE TOTAL ACT

C FOR WASTE CLASS NO. IT IS TESTED AGAINST DIST(1.I.IJI

C AND THE FRACTION OF UASTE VOLUME DETERMINED.

IVITY

J.).

C

26 IJK-BASCISTR.2.1)+0.l

DO 28 1-2.16

IF(A3.LT.DIST(1.IvIJK)) 00 TO 30

29 CONTINUE

SUCCESS OF DO LOOP 30 MEANS ALL OF THE WASTE IS ACCEPTABLE

UNDER THE CLASSIFICATION NO.

NX-1

Al-l.

A5-DISTC3,16,IJK)

CO TO 38

30 A4-CA3-DIST(t, I-. I.JK))/(DIST(IlI lIJK)-DIST(l. I-I. IJK))

Al-DIST(2.I-I.IJK)+A4*(DIST(2,1,IJK)-DIST(2.I-lIJAM))

IF(A1.LT .l.E-3) RETURN

IF(AI.OT.0.999) CO TO 36

AT THIS POINT SOME OF THE WASTE IS FOUND TO BE ACCEPTABLE

UNDER CLASSIFICATION NG3 THE PORTION THAT IS FOUND USACCEPTABLE MUST BE DESIGNATED AS A NEW WASTE STREAM. THUS. A NEW

WASTE STREAM DENOTED NSTR+l IS CREATED. AND PROPERTIES OF

THE ISTR WASTE STREAM IS STORED ONTO THE PROPERTIES OF NSTR.

NSTR-NSTR+I

BASN(NSTR)-3ASN(ISTR)

BAS(NSTR,2.1)wBAS(ISTR.2.1)

BAS(NSTR,2,2)-BAS(ISTR.2.2)

BAS(NSTR,3,1)-BAS(ISTR.3.,)*(1.-Al)

BAS(NSTR.3,2)-BAS(ISTR.3;2)'(1.-Al)

DO 32 J-4.27

DO 32 K-1.2

32 BAS(NSTR,J.K)-BASCISTR.J,K)

DO 34 K-l.6

IORD(K.NSTR)nIORDCKISTR)

DO 34 J-1.1O

34 ISPC(K.NSTR.J)-ISPCtK.ISTR.J)

ISPEC(NSTR)-ISPECCISTR)

NDXS(NSTR)-NDXS(ISTR)

IHIC(NSTR)-IHICCISTR)

THE FINAL STEPS IN THE CLASSIFICATION OF THE DISTRIBUTION

WASTE STREAM CONSIST OF ADJUSTING THE VCLUMES, TOTAL AND

RADIONUCLIDE ACTIVITIES, WASTE GENERATOR IMPACTS. AND

MODIFYING THE DIST (DISTRIBUTIONS) TO REFLECT THAT A

FRACTION HAS BEEN CLASSIFIED.

D-42
-

GRWATRR Code (cont'd)

C

36 AS-DIST(3. I-1. IJK)+A4*(DIST(3,I. IJK)-DIST(3.1-1.I1K))

38 A6-A5*Al

A7-A5/A2

BAS(ISTR3. 1)-BASCISTR*3. 1)*AI

BASCISTR. 3.2)cBASCISTR. 3, 2)*A1

BAS(ISTR.4,1)-A5

BASCISTR.4.2)-A5

DO 46 J-5,27

DO 46 KI1.2

46 BAS(ISTR. J.K)-BASCISTR. J. K)*A7

IF(NX. EQ. 1)RETURN

DO 50 J-1.16

A7-DIST(2.J, IJK)JDISTt3.J. IJ.)-A6

AS-DZST(2. J. IJK)-AS

DIST(2.J. IJK)-AS

SO DIST(3.J. IJK)-A7/AB

DO 55 J-2,I

DIST(2. J-1. IJK)-O.

55 DISTl3.J1.IJK)-O.

DIST(1.I-I. IJK)-A3

DO 65 J-1.16

65 DIST(2. J. IJK)-DIST(2.J, IJK)/DISTC2.16. IJK)

NX-1

RETURN

END

C

C

SUBROUTINE MODIF

C

C THIS ROUTINE MODIFIES THE DISPOSAL-STATUS OF THE WASTE

C (WHICH IS BASED ON WASTE PROPERTIES) BY TAKINO INTO

C ACCOUNT THE DISPOSAL PRACTICES

C

COMMON/DTNXIIR1. ID1. IC1. IXi. IEi; ISI

* /DTNX2/IR2. ID2. IC2# IX2, IE2. IS2. IL2. 1C2, IH2

* /NBAS/NSTR.NNUC.NDXS(90),.IMOD(90)-

IF(IS1. EQ. 1.OR. IS1.EQ.3)RETURN

DO 30 ISTR-1,NSTR

I11-IMOD(ISTR)

IF(IR2. NE. 0)00 TO 10

IF(I11. CT. 1.AND. I11.LT.7)I1l1-

CO TO 30

10 IF(IH2.EQ.1)0O TO 20

IF(I11. CT.2.AND. I11.LT.7)111-0

IF(I11. E0.2)I11-1

00 TO 30

20 IF(Ill.EQ.3.0R.It1.EQ.5)I11-7

IF(Ill. EQ. 4. OR. Ill. EQ. 6)111-8

30 IMOD(ISTR)-Ill

RETURN

END

C

C

SUBROUTINE BARN(ISTR.A2. A3. NX)

C

C THIS ROUTINE PERFORMS ASPECIAL CLASSIFICATION TEST

C FOR UNSTABLE WASTES BASED ON EXISTING DISPOSAL FACILITY

C LICENSE CONDiiIONS. BOTH NON-DISTRIBUTIONAL AND DISTRIC BUTIONAL-WASTE STREAMS CAN BE SUBJECTED TO THIS TEST.

C

D-43
. I I i t

GRWATRR Code (cont'd)

COtiCINJ/AST/BAS(90.32,2)/N3AS/NSTRNNUC.NOXS(90)

Al-0.

DO 10 1-19.27

10 A1 AI+BAS(ISTR.I.1)

A2-AI

A1 AI-BAS(ISTR. 22. 1)-(. -1./35.)'

IF(NDXSCISTR).LT.0)CO TO 20

IF(AI.CT.0.016)RETUHN

DO 12 I-5.6

IF(BASCISTR.1S).GCT.1.0)RETURN

12 CONTINUE

DO 14 I-9. 19

IF(BASCISTR.I.l).GT.1.O)RETURN

14 CONTINUE

NX-1

RETURN

20 'DO 22 I-5.18

22 A2nA2+BASCISTR,1.1)

A4-AMAXI(DAS(ISTR.5.1).BAS(iSTR.6.1))

DO 24 I-S.18

IF(A4.LT. BAS(ISTR., 1))A4-BASCISTR.3.1)

24 CONTINUE

A3-A/0. 016

IFCA4.LT.A3)A4-A3

A3-A2/A4

RETUmN

END

C

C.. N4*4**4**#**p*****4-}*I*e*N*I4s*******************

C

FUNCTION ERFS(Al.A2)

A3-0.5*4SQRT(A2/AI)

A4-A3uC1.-Al)

A5-A3*tl.+A1)

IF(A4.CT.0)00 TO 10

ERFS-2.+EXl(A4*A4)*(POLY(A5)-POLY(-A4))

RETURNt

10 ERFS-EXI(A4*A4)*CPOLY(A4)+POLY(A5))

RETURN

END

C

FUNCTION POLY(XI)

DATA AI.A2.A3.A4.A5,P/.254929592,-.264496736.1.421413741.

-1.453152027.1.061405429..3275911/

TX-I./C1.4P*Xl)

POLY-T1*(Al+TI.(A2+Tl*(A3+TI*(A4+TI*A5))))

RETUMN

END

C

FUNCTION EXM(AI)

A2-0:0

IF(AI. LT. 85.)A2-EXPC-Al)

EXM-A2

RETURN

END

C

C.44444 ******44..**4*4*4***i*.***4*****.*~4 I *************

C

SUBROUTINE CWATER(NTYf.TYO.THIC.ICN.NOPTW)

C

CHARACTER4io BASN(90),NUC(36)

COMMON/BAST/BAS(90.32.2).ISPC(6.90.10),DCF(36.7.8).FICRPC7)

+ /CHRC/BASN.NUC

D-44
GRWATRR Co'de (cont'd)

C

C

C

C

C

C

C

C

C

C

_-C

C r ' C

C

/NUCS/AL(36).FMF(36),RET(36.5)

+ /DTNXlIIR1. IDl. IdC.Xl.IEl.ISlILtl..tHl~.O11. ICLI.IPOl.lICI + /DTNX2/IR2.ID2.IC2.IX2.IE2.IS2.IL2,102.IH2,102.ICL2.IP02.IIC2

+ /DTIS/FSCC6).FSA (6).PRC(6,2).QFC(6.3).TTh(6.3).TPC(6.3).

+ R0F(6,3).POP(6.3).DTTM(6).DTPC(6).TPO(6.2).NRET(6)

+ /IlPS/DZ(23o22.21)

+ /NBAS/NSTR.NtiUC.NDXS(90). IOD(90)sISPEC(90).IHIC(90)

+ /LSTS/CLSTC4sl6).DIST(3.16.7).IORD(6.90).FLSTC6.4.16)

DIMENSION EMP(5).EFF(2).SEFF(2).TYMDC22).RES(22.3) DATA EMP/. 5.. 75. S.. 5,. 75/

DATA EFF/6.4,7. O/

DATA BEFF/0.9.0.35/

DATA NOPT/l/

THE ABOVE MATRICES AND ARRAYS ARE

EMP(S) VOLUME EKPLACEKENT EFFICIENCIES

EFF(2) LAND USE VOLUME EFFICIENCIES

SEFF(2) LAND USE SURFACE AREA EFFICIENCIES

TYMD(22) THE 22 TIIESTEPS

RES(22.3) WILL CONTAIN RESULTS FROM SUBROUTINE RTIJ

IHIC(90) INDEX FOR INTERNMENT IN HIGH INTEGRITY CONT.

IF(ICN.EQ.2) CO TO I

IR-IRI

ID-ID1*

IC-ICI

IX-IXI

IE-IEI

IS-IS1

IL-IL1

IC-101.

IH-IH1

10-I1t

ICL-ICL.

IPO-IPO1

IIC-2IC1

CO TO 2

1 IR-IRI

ID-ID2

IC-IC2

IX-IX2

IE-IE2

IS-1S2

IL-IL2

IH-IH2

I0-102

ICL-ICL2

IPO-IP02 -

IIC-IIC2

2 TVOL-O.0

CINStIPO+IIC

NSEC-10

NEXT SECTION DETERMINES PERCOLATION VALUE AND LOWER

LIMIT FORTHEEDILUTION-FACTOR. -

PRCl-PRCCIR. ,, PRC2-PRCCIR.2)

IFCI0.EQ.1.OR.ID.EQ.2) 0O TO .5

IF(IE.EG.4.OR.IE.EQ.5) PRCInPRC(IR.,1)/10.

IFCIE.EQ.4.OR.IE.EQ.5) PRC2-PRC(IR.2)/10.

D-45
GRWATRR Code (cont'd)

S CONTINUE -

IFCIC.EQ. I)PRCD-PRCIIF( IC. Ct I )PRCD-PRC2

IF(IX. EQ. I)PRCD-4. O4PRCI

IFtIC. EQ.1.AND.IX. EQO2)PRCD-2.25*PRC1

IF(IC.EQ.2.AND. IX. EQ. 2)PRCD-4.00PRC2

TVOL-352000.*SQRT(PRC( IR. 1)*27.8)

IF(TVOL. LT. 7700. )TVCL-7700.

C

C LOOP 90 IS THE MAIN LOOP OF CROUNDUATER PATHWAY EQUATION

C

DO 90 ISTR-lvNSTR

III-IMOD(ISTR)

IFCIII. EQ.0)CO TO 90

IFC11l.Ea.1.AND.ICN.NE.1) CO TO 90

IFCI11.¢T.1.AND.ICN.NE.2) CO TO 90

IDR-ISPEC(ISTR)-

NSPC-IORD(IDR.ISTR)

I6-ISPC(NSPC. ISTR.6)

VUR-O.9/(EKP(IE)*EFF(ID))

I7-ISPC(NSPC.ISTRD7)

IF(I11. CT. 6)VUR-0.19

18-ISPC(NSPCISTRS)

IF(IS.LT.2.OR.I7.EQ.1)I6=I6-l

IF(IHICCISTR). CT. OI)8-1+IHIC(ISTR)

CDELO.

IF(IHIC(ISTR).EQ. l.OR. I..EO.2)CDEL-THIC

I9-ISPC(NSPC.ISTR.9)

PERC-PRCD

IF(I8.LT.I.OR.IS1.EQ.O.OR.ISI.EQ.2)CO TO 10

IF(IC. EQ.1)PERC-PRCI

IF( IC. CT. .1 )PERC-PRC2

10 IF(II.CT.6.OR.ID.EQ.2)PERC-PRC2/16.

PERCoPERC4(1.0-0.9410)

PER2-3.6*PERC+O. IPRCI

IF(ID. EQ. 2)PER2-0. 9*PERC+O.1*PRC2

NX-0

IF(PERC.LT.PRC1)NX-1

A&-1. 0

IF(I6. CT. I)A6-4.** (1-I6)

A9-1.0

IF(I9. CT. 1)A9-1O. **(1-19)

I1-NRET( IR)

IF( IS. LT. 2. OR.I7.EO. t)Il-Il-1

TDUM-1.0/(PERC*VIR*A6*A9)

IF(I1.LE. 0)I11

DO 90 INUCI.lNNUC

IF(BAS(ISTR.INUC+4.2).LT.1.E-14)CO TO e0

TDUR-TDUM/FMFCINUC)

C1-TDUR

IF(NX.EQ.0.OR.NOPT.EQ.0)CO TO 15

IF(CI.LT. CINS)CI-OINS

C

15 CALL RTIJtTYMD.NTYM. INUC.IR. I1.CI.O.O.RES.CDEL.NOPTW)

C

C RESULTS FROM SUBROUTINE RTIJ ARE RETURNED IN RES MATRIX

C

B1-BAS(ISTR.3.2))BAS(ISTR. INUC+4. 2)/TDUR

DO 30 IPTH-1.3

B2-B1*RCF(IR.IPTH)/(GFC(IRIPTH)*NSEC)

IF(TVOL. CT. OFC C IR. IPTH))B2-B2'QFCCIR.IPTH)/TVOL

13-CIPTH-1)47

12-6

D-46
GRWATRR Code (cont'd)

IF(IPTH.EG.3)12&7

DO 25 ITYM-I.NTYM

A3-EXM(AL(INUC).TYMD(ITYM))

DO 20 1-1.7

A4-A34RES(ITYMIPTH)*B2.DCF(INUC.I.12)

20 DZ(INUCITYM.I3+I)-DZCINUCITYM,13+I)+A4

25 CONTINUE

30 CONTINUE

C

C THE NEXT SECTION CONSIDERS (NOPT-O CANCELS THIS CONSIDERC ATION) THE SECOND SOURCE TERM OF THE 2-STEP ANALYSIS WITH

C AN INCREASED SOURCE TERM (PER2) AFTER THE INSTITUTIONAL

C CONTROL PERIOD.

C

IF(NX.EQ.O.OR.NNOPT.EG.0)0O TO 60

IF(TUUR.LE.CINSCO TO 60

TI-GINS

T2-Tl+PERC*CTDUR-TI)IPER2

C

CALL RTIJ(TYI.DNTYM. INUC.IR.I1.T2,Tl.RES.CDEL.NOPTW)

C

I-Bl *PER2/PERC

DO 50 IPTH-I.3

-B2-nl*RCF(IRIPTH)/(OFC(IR.IPTH)*NSEC)

IF(TVOL.CT.GFC(IRIPTH))B2-B2.QFC(IRIPTH)/TVOL

13-(IPTH-2)*7

12-6

IF(IPTH.EQ.3)I2w7

DO 45 ITYMVlNTYM

A3-EXM(AL(INUC)*TYMD(ITYM))

DO 40 1-1.7

A4-A3'RES(ITYM.IPTH).B2.DCF(INUC.I.12)

40 DZCINUC.ITYM.13+I)-DZCINUC.ITYM. 3+.Iv)A4

45 CONTINUE

50 CONTINUE

60 CONTINUE

eo CONTINUE

90 CONTINUE

RETURN

END

C

C

SUBROUTINE RTIJ(TYMDNTYM. INUC. IR.I1,TDURTrIN.RES.CDEL.NOPTW)

C

C SUBROUTINE RTIJ CALCULATES THE MIGRATION REDUCTION FACTORS

C

COMMON/NUCS/AL(36).FMF(36).RET(36.5)

* /DTIS/FSC(6),FSA(6).PRC(6.2),GFC(6,3),TTt'(6.3).TPC(6.3).

* ROF(6.3).POP(6,3),DTTM(6).DTFC(6).TPC(6,2),NRET(6)

DIMENlSlON TYMD(NTY?1),RESt22.3).BTTM(6).BTFC(6)

DATA BTTR/350..66..175..2e3..56. .116./

DATA BTPC/700..1900..700.,16CO. *1Q00..1900./

C

C THE ABOVE ARRAYS ARE DTTM AND DTPC ARRAYS FOR

C THE BOUNDARY WELL CASE (NOPTW-1)

C

CALL ZERO(RES.66)

C

DO 30 IPTH-I.3

Al-RET(INUCI1)2TTM(IRIPTH)4lDEL

IF(NOPTW. EO I.AND.IPTH.EQ .)AI-RET(INU:.Il)*BTTM(IR)+CDEL

DO 20 ITYMWINTYM

D-47
I INL

GRWATRR Code (cont'd)

TYM-TYHD(ITYM)-TMIN

A2-TYIDCITYM)-TDUR

DO 10 ISEC-1.10

B3-1.0/CAI+RETcINUC.11C*!ISEC-I)vDTTM(IR))

IF(TYM*I. 193.LT.1.0) CO TO 20

B4-TPC(!RIPTH)+tISEC-1)*DTPCCIR)

IF(NOPTW.EQ. .AND.IPTH.EQ.l)B4wBTPC(IR)-(ISEC-1)*DTPCCIR)

A3=0.5*ERFSCB3*TYM.B4)

IF(A2.CT.O.O)A3-A3-0.5*ERFS(83*A2.34)

IF(A3.LT.O.OIA3-0.0

10 RESCITYM.IPTH)-RES(ITYM.IPTH)+A3

20 CONTINUE

30 CONTINUE

RETURN

END

C

C

SUBROUTINE ZEROCA.N)

C

DIMENSION A(N)

DO 10 I-1,N

10 ACI)U0.O

RETURN

END

0-48
OPTIONR Code

PROGRAM OPTICNR

C*>^*E#d******** >***4 * **4z**E4tI4*455*4*****4*X*Z44 2*4*(**4**********

C- THIS IST::E REVISED OPTIONS IMPACTS CODE. IT-FINDS THE *

C DISPOSAL PRACTICES FOR PROPER-INTERNMENT OF WASTE STREAMS. *

C :WA-ST -VOLUME-AVERAG-fn INTRUDER.IMPACTS, EXPOSED WASTE *

C - I'fPACTS, IMPACTS FROM-SITE-CPERATIChAL ACCIDENTS. POTENTIAL *

C ;-TRENCH OVERFLOW A1ND LEACHATE -TREATMENT Il;ACTS, Al;D COSTS,.

C -^Et EqGY USE. LAt4D USE. OCCUPATIONAL EXPOSURES. AND POPULATION*

C EXPOSURES ASSOCIATEVUIJITH ,4ANACAGEMENT, TPL!JSPORT. AND

C - DISPOSAL OF WASTE. *

C

CHARACTER*iO BDASWC903),NUC(36).NOTE(2),DESt9)

COMXHON/TSAST/BAS(90. 13) .ISPC (6. 90. 10). DCF(36. 7. 8) .FICRP (7), AZP (90)

/CHRC/BASN. NW: -

+ ./NJCSIAL(36). F-F(i36),RET(36.5)/COMB/TPOP(2),DEC(36o2)

+ /DTNXI/IRDC1t13)/L'TrX2/IRDC2(13)

+ /DTIS/FSC(6),FSRA(6),PRC(6,2), FC(6.3).TTM(6.3).TPC(6.3).

+ , RGFio.63).PO-P(6.3).DTTM(6).DTPC(6)hTPO(6.2).NRET(6)

+ /VOLS/VRC1. fR.2, VLAY. VHDT, VNOT. RVOL(4.37)

* /IMPF/DZCS. 7, 2). DZ0(4. 7.2), DZA(7. 7). DZS(90. 7.2)

/NBAS/NSTR. rN-JC NDXS(90), It40D(90), ISPEC (90)s IHIC(90)

-* . . /LSTSfCLST(C4,16).DIST(3,116.7).IORD(6,90),FLST(6. 4,16),NLST

* /CSTS/TIt1PC6), COST(S). GD(B), UN(S)i TCU(30)

/CHY:./NXUC(c6),ICH(7,6),LCH(6),ACT(7)

+ /CHIN/BCT(7. 2)

-DI MENSICN IGON 1 (,lOl90), IOR2(90). IGL(90)b IOH(90).

* DZUS(3.7.2),DZST(4.7.2),IORDD(6), NORDDC6)

C

C*.%.*4 *4 4*4-**444:4*44z*4*.s44********x**4****4

C THE ABOVE MATRICES AND ARRAYS -ARE ERIEFLY EXPLAINED BELOW.*

C MORE DETAILFD EXPLANATrOr'S CA"J SE FOUrND IN THE DFTIStFFIS :

: _ 7 ,. 'C 

* C :BAS! - NAME OF THE UASTE STREAMS - 4

C -NU - NAME OF THE RADIONUJCLIDES CCNSIDEREV

C - N3TE : TITLE OF T;:E PROBLEM *

C DES - DESCRIPTICNS OF PAT:IWAYS *

C BAS. BASIC DATA-MATKIX OF:VOLUMESCCNCENTRATICNS *

C ISPC - WASTE.SPECTkUM It'FCRMATION .

C VCF - PATHWAY DOSE CONVERSICN FACTORS 4

C FICRP - ICRP WEIGHTIt, FACTCRS FOR ORGANS *

C AZR - VRF/VIF FCR THc FIRST., SPECTRUm 4

C AL - DECAY, CONSTANTS OF RADIONUCLIDES

C FM. - PARTITICN RATIOS BETWEEN WASTEAND LEACHATE *

C RET - RETARDATION COEFFICIENTS OF RADION'JCLIDES *

C TPOP - RURAL AND URBAN X/Q WEICHTED POPULATION FACTORS 4

C DEC - DECONTAMUIt.ATION FACTORS FOR INCINERATORS *

C IRDC1 - DISPOSAL TLCHNOLOGY INDICES FOR UNSTABLE WASTES *

C IRDC2 - DISPOSAL TECHNOLOCYINDICES FOR STABLE WASTEC t

C FSC - SOIL-TO-AIR TRANSFER FACTOR - CCNSTRUCTION 4

C FSA - SOIL-TO-AIR TRANSFER FACTOR- AGRICULTURE 4

C OPC w DILUTION FACTORS FOR CROUNDWATER SCENARIOS *

C TTM - ThAVEL TIMECYLAF.S) FOR CWSCENARIOS 4

C TPC - PECLEr NWUMERS FCR CW SCENARIOS .

C ROF w GFOMETRIC REDU:TION FACTORS FOR CW SCENARIOS 4

C FOP - POPULATION FACTORS FOR ACCIDENT SCENARIOS 4

C DTTI - TRAVEL TSIME BEIWEEN DISPOSAL SITE SECTORS *

C DTPC - PECLET NIJMBER SETWEtN DISPOSAL SITE SECTCRS *

C TPO - XXG WEIGHTED POPULATION SUM-DISTRIBUTION 4

C INRET a RE1ARDATION COEFFICIENT SET FOR THE DISPOSAL SITE*

C RVOL - RECIONAL VOLU.'IES OF WASTE GENERATED 4

C DZ - DUMnY DOSE HATMIX CALCULATED INTERNALLY 4

D-49
OPTIONR Code (cont'd)

C DZQ - DUMMY DOSE MATRIX CALCULATED INTERNALLY

C DZA - DUMMY DOSE MATRIX CALCULATED INTERNALLY

C DZS - DUMMY DOSE MATRIX CALCULATED INTERNALLY

C NDXS - INDEX ON STATUS OF WASTE STREAM *

C IMOD - CALCULATED DISPOSAL MODE OF WASTE STREAM *

C ISPEC - CURRENT SPECTRUM FOR THE WASTE STREAM

C IHIC - HICH INTEGRITY CONTAINER INDEX

C CLST - LISTS OF WASTE CLASSIFICATION CONCENTRATIONS *

C DIST - ACTIVITY DISTRIBUTIONS OF CERTAIN WASTE STREAMS *

C IORD *- ORDER IN WHICH WASTE'SPECTRUMS ARE CONSIDERED a

C FLST --GENERAL LISTS OF WASTE CLAS. CONCENTRATIONS

C- CSTS _- IMPACTS RELATED ARRAYS -

C NXUC - INDEX DENOTING WHETHER MEMBER OF CHAIN

C -ICH - CRDER OF TH- FOUR CHAINS-CONSIDERED

C LCH - NUMBER OF MEMBERS IN FOUR CHAINS CONSIDERED 4

C ACT * FRACTIONAL ACTIVITIES OF CHAIN MEMBERS *

C BCT - INTERMEDIATE ARRAY USED IN CHAIN CALCULATIONS *

C IGN - NUMBERS OF NOT-ACCEPTABLE WASTE STREAMS 4

C IGRI - NUMBERS OF UNSTABLE-REGULAR WASTE STREAMS

C IQR2 - NUMBERS OF STABLE-REGULAR WASTE STREAMS 4

C IOL - NUMBERS OF LAYERED WASTE STREAMS *

C IGH - NUMBERS OF HOT-WASTE FACILITY WASTE STREAMS

C DZUS - INTERMEDIATE INTRUDER IMPACTS-UNSTABLE WASTES *

C DZST - INTERMEDIATE INTRUDER-IMPACTS-STABLE WASTES

C IORDD - BASIC ORDER FOR SPECTRUM CONSIDERATION *

C NORDD - DUMMY ORDER FOR SPECTRUM CONSIDERATION *

C

DATA DES/' INT-CONS ". INT-AGRI . INT-AIR

* ERO-AIR INT-WAT . ERO-WAT .

* ACC-SNGC . ACC-FIRE . ACC-AVG / DATA RI.RJ/. 1.09/

DATA AZR/1..1.4.3*1. 1.4,15*1. 4*3.,2*1.92.3*1. 2..1.3. 5*1./

C

C NEXT SECTION READS ALL THE BASIC INFORMATION

C

10 REWIND I

REWIND 2

CALL READIN

C

C NEXT SECTION READS BASIC AND CONDITIONAL INFORMATION

C FROM TAPE5. PROGRAM QUITS WHEN THERE ARE NO MORE CASES

C TO BE CONSIDERED. CONDITIONAL INFORMATION IS USED TO

C ALTER THE BASIC INFORMATInN DEPENDING ON THE CASE.

C

READC5.i020.ENDOXOO)NOTE

12 READ(5, 1022)NOPRNNOX.NORD.NLSTNHIC.NBEST

READ(5.1022)(IRDCI(C).I-1.13)2

READ(5.1022)(CRDC2(I).I-I.13)

READC5.1022)(roRDD(i).I-I.6)

IF(NLST.EQ.O)READ(5.1025)((CLST(CIJ)J-1.16).lul. 4)

DO 14 I-1.NSTR

ISPEC(I)-l

1' NDXS(I)-l

D0-16 1-1.3

NDXSCI) -1

16 NDXS(1+4)--1

NDXSC37)=--

IF(NNDX.EQ.0)GO TO 20

DO ISI-1.NNDX

READ(5.1022) IDIFF.IJDXD

1S NDXSCIDIFF)-NDXD

20 DO 22 Im1.NSTR

D-50
,.;i - 1 '

OPTIONR Code (cont'd)

22 IHICCI)0O

IF(NHIC.EQ.0)O TO 26

DO 24 I-1,NHIC

READ(5,1022) IDIF.NHCD

24 IHICCIDIF)-NHCD

26 DO 28 I-1,NSTR

DO 28 J-1.6

28 IORD(J.Z)-IORDD(J)

IFCNORD.EQ. 0)O TO 34

DO 32 I-1.NORD

READS. 1022) NK.(NORDD(J).J-1.6)

DO 30 J-1.6

30 IORD(NK.J)mNORDD(J)

32 CONTINUE

34 IF(NLST.EQ.0)00 TO 33

DO 36 J-1.4

DO 36 K-1.16

IF(FLST(NLST.J.K).LT.l.E-7)FLST(NLST.J.K)=1.E-7

36 CLSTCJ.K)-FLST(NLST.J.K)

IRR-IRDCl~l) --

39 IF(N0PR.EQ 0)0O TO 43

IF(IRR.CT.4)IRRm2-

40 DO 41 ISTR-1.NSTR

41 DAS(ISTR.3)-RVOL(IRR.ISTR)

43 IF(IRR.NE. 4)O TO 42

DO 39 1-1.6

DO 39 ISTR-l.NSTR

39 ISPCCI.ISTR.5)-ISPC(I.ISTR.5)-1

CC THIS IS THE REAL BEGINNING OF THE CODE.

C FIRST BASIC INFO IS PRINTED. THEN ARRAYS ARE ZEROED OUT.

C

42 WRITE(4.1002) NOTE

N-1

WRITE(4.1003) N.IRDCI

N-2

WRITE(4.1003) N.IRDC2

WRITE(4.1032)NOPR# N.NDX, NORD.NLST.tNHIC.NBEST. (IORDD(I). 1-1.6)

1032 FORMAT(/2X'NOPR-'I2,2X'JNDX-'I2,2X'NORD-'I2.2X/

* 2X'NLST-'I2,2X'NHIC''2,2X'N3ES-'I2,2X/

+ 2X'IORD 1-6-ARE:'6I2)

CALL ZERO(DZ.1477)

CALL ZERO(DZUS.42)

CALL ZERD(DZST.56)

VRGI-O.0

VRC2-0.0

VLAY-O. 0

VHOT-O. 0

VNOTO.0

NNOT-O

NHOTwO

NLAY-O

NROI--

NRC2-0

C

C NEXT SECTION IS THE OPEN ENDED DO LOOP THAT DETERMINES

C THE STATUS OF THE WASTE STREAMS.

C

ISTR-O

44 ISTR=ISTR+l

IFtISTR.CT.NSTR) CO TO 66'

IF(NDXS(ISTR).NE.O) CO TO 46

WRITE(4,1006)BASN(ISTR)

D-51
__I IU

OPTIONR Code (cont'd)

IMOD(ISTR)-O

CO TO 44

46 IMOD(ISTR)-1

IHC-IHIC(ISTR)

C

CALL RCLAIM(ISTR.INDX.NOPRoNBEST)

C

IX-IMOD(ISTR)+a

C

C AFTER DETERMININO THE STATUS AND IMPACTS OF THE WASTE

C STREAMS, IMPACTS AND VOLUMES ARE STORED APPROPRIATELY.

C

CO TO t48.50.54.54.54.58. S.62.62).11

48 NNOT-NNOT+1

ION(NNOT) ISTR

VNOT-VNOT+BAS(ISTR,3)

CO TO 44

50 NRCl-NRC1+1

IGRl(NRQl)-ISTR

DO 52 1-1,7

DO 52 J-1.2

DZUS(I.1J)-DZUS(1.1.J)+BAS(ISTR.3)*DZ(INDX.I.J)

DZUS(2.I.J)-DZUS(2.IJ).3AS(ISTR.3)*DZ(3.,.J)

52 DZUSC3,IJ)-DZUS(3,I.J)+3AS(ISTR.3)*DZ(8.I.J)

VRGI-VRCG+BAS(ISTR.3)

CO TO 44

5+ NRC2-NRC2+1

IQR2(NRC2)-ISTR

DO 56 I-1.7

DO 56 J41.2

DZST(l. I.)-DZST(.I.IJ)+BAS( ISTR.3)*DZ(INDXI.J)

DZST(2.I.J)-DZST(2.I.J)+BAS(ISTR.3)*DZ(3, 1J)

56 DZST(3.I.J)-DZST(3.I.J)+3AS(ISTR.3)*DZ(6.I.J)

VRG2-VR02.BASCISTR,3)

CO TO 44

56 NLAY-NLAY+1

IQL(NLAY)mISTR

DO 60 I-1.7

DO 60 J-1.2

DZST(4,I.J)-DZST(4.I.J)+BAS(ISTR.3)*DZ(INDXI.J)

DZST(2.1.J)-DZST(2.IJ)+DAS(ISTR.3)*DZ(3I.4J)

60 DZSTC3.I.J)-DZST(3.I.J)+BAS(ISTR.3).DZCS.I.J)

VLAY-VLAY+BAS(ISTR,3)

CO TO 44

62 NHOT-NHOT+l

IGH(NHOT)-ISTR

DO 64 1-1.7

DO 64 J-1.2

DZST(1.I.J)-DZST(.I. J)+BAS(ISTR.3)*DZ(INDX.I.J)

64 DZSTC3.I.j)-DZST(3.I.J)+3ASCISTR.3)*DZ(6.I.J)

VHOT-VHOT+BAS(ISTR.3)

GO TO 44

C

C THIS IS THE END OF THE OPEN DO LOOP TO CLASSIFY THE

C WASTE STREAMS NEXT SECTION CALCULATES AND PRINTS

C WASTE VOLUMES AND VGLUME-AVERAGED INTRUDER IMPACTS.

C

66 VlVRG2+Ynmo

V2-VRG2+VLAY

V3-VRG2+VLAY+VHOT

V4-VRCI+VI

V5-VRGI+V2

V6-VRGI+V3

D-52
OPTIONR Code (cont'd)

DO 70 J-1f,7

DO 70 K-1.2

DO 6E I-1.3

68 DZQ(IJK)-DZUS(I,J.K)+DZSTCI, JK)

IF(V1.CT. .)DZST(1.J.K)-DZST(l.JK)/VI

IF(V2.CT.1.)DZSTC2.J.K)-DZST(2.JK)/V2

IF(V3.CT.1.)DZST(3.J.K)-DZST(3.J.K)/V3

DZQC ,J,K)-DZO(iJ,.K)/V4

DZOC2,J.K)-DZO(2.J.K)/V5

DZQC3,J.K)-DZQ(3.J.K)/V6 -

IF(VLAY.CT.1.)DZST(1.J.K)-DZSTC1,J,-K)+DZST(4.JK)/VLAY

* IF(VLAY. CT.1.)DZO(I.J.K)-DZOC1.J.K)+DZQ(4 .J.K)/VLAY

IF(NRGI.LT.l)CG TO 70-

DZUSC.J.K)iNDZUS(C#J#K)/VRGI

DZUSC2..JoKv DZUSC2.,JK)/VRGI

DZUS(3oJ#K)B-DZUS(3,J.K)/VROI

70 CONTINUE

WRITE(4.1026)

WRITE4, 1027)(NUC(I).(CLST(J.I).J-1,4).l 1114)

WRITE(4, 1028)(CLST(JI),J-1.4).1-15,16)

IF(NRGI.CT.0) CALL PRT(VRGI.IGRINRG1.1)

IF(NRC2.CT.0) CALL PRT(VRG2,I0R2.NRG2.2)

IF(NLAY.CT.0) CALL PRT(VLAYsIQLNLAYo3)

IF(NHOT.CT.0) CALL PRT(VHOT#IQH.NHOT.4)

IF(NNOT.CT.0) CALL PRT(VNOTIONNNOT.5)

WRITE(4.1008)

DO 76 IK-1.3

IF(IK.EQ.1) WRITE(4.1029)

IF(IK.EQ.2) WRITE(4,1030)

IF(IK.EO.3) WRITE(4.1031)

DO 76 1-1.3

DO 74 K-1,2

A1=0.0

DO 72 J-1.7

IF(IK.EQ. )AI-A1+DZUS(IJK)*FICRP(J)

IFCIK.EQ.2)AI-A1+DZST(I,J.K)*FICRP(J)

IF(IK.EQ.3)AI-Af+DZO(I,J.K)*FICRP(J)

72 CONTINUE

IF(IK.EO.1)WRITE(4.I0U9) DES(K).(DZUS(I#J.K).J-1.7).AI

IFCIK.EO.2)WRITEC4,1009) DES(K).(DZST(I.J.K),.J-1.7).AI

IF(IK.EQ.3)WRITE(4,1009) DES(K).(DZG(I.J.K).J1.7).Al

74 CONTINUE

76 CONTINUE

C

C: NEXT SECTION CALCULATES AND PRINTS ACCIDENT. EROSIONt

C AND INTRUDER INITIATED POPULATION EXPOSURE IMPACTS.

C

DO 82 ICN-1,2

CALL ACCEXP(NDESTICN)

IF(ICN.EO.1) CO TO E2

WRITE(4.1014)

DO eo K-1.7

KK-K+2

A1-0.0

D' 78 J-1.7

78 A1-AI+DZA(J,K)*FICRPCJ)-

E0 WRITE(4,1015)DES(KK), (DZA(J.K).J-1,7),AI

82 CONTINUE

C .

C NEXT SECTION CALCULATES AND PRINTS IN TWO STEPS (UNSTABLE

C AND STADLE WASTES)' IMPACTS RESULTING FROM MANAGEMENT.

C TRANSPORT, AND DISPOSAL OF WASTES OTHER THAN THOSE

C RADIOLOGICAL IMPACTS PRINTED ABOVE.

D-53
OPTIONR Code (cont'd)

C

CALL ZEROtTIMP.60)

WRITEt4.1010)

DO E8 ICN-1.2

C

CALL TRANSP(TIMP.ICN)

C

CALL ZEROtCD.8)

DO 84 ISTR-1.NSTR

IF(ICN.EQ.l.AND.IMDD(ISTR).NE.1)0O TO 84

IF(ICN.EQ.2.AND. IMOD(ISTR).EO.1)GO TO 64

IDR-ISPECCISTR)

NSPC-IORD(IDR.ISTR)

I1ISPC(NSPC.ISTR.10)

12-11/100

13-(I1/10)-12*10

IFtl3 EQ.O) GO TO 84

14-0

IF(13.EG.2) 14-4

CD(I4+1)-GDC14+1)+BASCISTR.29)

CD( I42)-GDCI4+2)+8AS(ISTR.30)

CD14+33)-CDtI4+3)+EAS(ISTR.31)

CDO14+4)-GCD(4.4)+BASCISTR,32)

84 CONTINUE

C

CALL ECON(RI.RJCOST.ICN)

C

VT-VRO1

IF(ICN.EQ.2) VT-VRG2+VLAY+VHOT

CALL ZEROtUN.8)

IFtVT.LT.O.1) GO TO 85

UNC1)uGD( )/VT

UN(2)=GCD5)/VT

UN(3)-TIMPtl)/VT

UN(4)-COSTC1)/VT

UN(5)-COST(5)/VT

UN(6)-COST6) /VT

UNC7)-COST(7)/VT

UN(8)COST(S)/VT

85 COST(2)wCOST(2)+TIMP(5)

X=O. O

TIMP(3)-TImP(3)+TIMP(6)

WRITEt4 1013)ICN. Dtl).GCD5).TIMPCl),COSTC1).COST(5)#

+ COST(6).COSTC7).COSTC6).UN(1).UN(2).UNC3).

+ UN(4). UN(S).UN(6).UN(7).UN(8).GD(4) GD(S).

+ TIXP(4).X.GD(3).CD(7).TIMP(3).COST(2).X.X.X.

+ COST(4).GD(2).0D(6).TIMP(2).COST(3).RI.RJ

DO E6 1-1.22

86 TCU(I)-TCUCI)+TIMPCI)

ES CONTINUE

C

C NEXT SECTIONS SUMS AND PRINTS THE TOTAL IMPACTS.

C

VT-VR01YVRG2+VLAY+VHOT

TCU(23)-TCU(15)/VT

TCU(24)-TCV(19)/VT

TCU(25)-TCU( 1)/VT

TCU(26)-TCUC 7)/VT

TCU(27)-TCU(11)/VT

TCU(28)-TCU(12)/VT

TCU(29)TCU( 13)/VT

TCU(30)-TCU(14)/VT

WRITE(4.1013)ICN TCU(15).TCU( l1).TCUV().TCU(7), TCU(I1).

D-54
''OPTIONR Code (cont'd)

* TCU(12).TCU(13),TCU(14).TCUC23).TCU(24).TCU(25).

* TCU(26).TCU(27).TCV(2B).TCU(29),TCU(30).TCU(18).

* TCU(22).TCU(4).X,TCU(17).TCU(21).TCU(3).TCU(B).

* X. X. X. TCUCIO). TCUC16). TCU(20).TCU(2). TCU(9). RI.RJ

C

CALL OVERFLO

:C

DO 92 K-1.2

IF(K.lEQ.1)WRITE(4 1016) -

IF(K. EQ.2)WRITE(4.1017)

WRITE(4.1018)

DO 92 1In*.NSTR

Al-0. 0

DO 90 J-1,7

90 Al-Al+DZS(I.J.K)*FICRP(J)

WRITE(4.1009)IASNCI), DZS(I J. K) P.J=1 7).Al

92 CONTINUE

GO TO 10

100 STOP

C

1002 FORMAT(lHl/2X.2Al0)

1003 FORMAT(//.2X.'DISPOSAL TECHNOLOGY INDICES GRP`;I2/2X.

'IR =-I2' ID -'I2' IC -'I2' IX -'I2/2X

+ 'IE -1I2'- IS -'I2' IL ='12' IG -'12/2X

* 'IH -'12' 10 -'12' INS='I2' IPO='I2/2X

* 'IIC-'I5)

1006 FORMAT(/.2X'WASTE STREAM NOT INCLUDED:'.2X.A1O)

1008 FORMAT(IHI/2X.'INTRUDER IM 0 ACTS',7X#'BODY BONE LIVE

+' THYROID KIDNEY LUNG G-I TRACT ICRP')

1009 FORMAT(IP. 12X.Aio.eEiO.3)

1010 FORMAT(IHI)

1013 FORMAT(/2X.'OTHER IMPACTS IRDC',12/20X.

+' WASTE PROCESSING: - TRANSP ',

+'DISPOSAL POST OPERATIONAL COSTS'.

+/16X' CENERAT DISPOSAL'20X' TOTAL CLOSURE

+'OBSERVE INSTITUT.

+/2X'COST CS) 6X.1P.E'lO.2/2X'UNIT COST (s/M3)'eE1O.2.

- 2XVPoP DOSE (MREM) '4E10.2/2X'OCC DOSE (MREM) '4E10.2.

#/2X'LAND USE (M2) '4E10.2/2X'ENERGY USE CGAL)'4E10.2.

+/2X'INTEREST RATE 'OP.sF5.3/2X'INFLATION RATE 'IFS.3)

1014 FORMATC/2X'EXPOSE/ACC IMPACTS')

1015 FORMATCIP.I 2X#AI0. 510.3)

1016 FORMAT(//2X'SINGLE CONTAINER ACCIDENT - bLL STREAMS')

1017 FORMAT(//2X'ACCIDENT BY FIRE - ALL STREAMS')

1018 FORMAT(14X.'STREAM'.SX. 'BODY BONE LIVER THYROID

+'KIDNEY LUNG C-I TRACT ICRP')

1020 FORMAT(2A10)

1022 FORMAT(1112.215)

1024 FORMAT(IOX.4E1O.3)

1025 FORMAT(SE10.3)

1026 FORMAT(//2X,'LISTS A B C HW

1027 FORMAT(2X.AlO. 1P. 4E10 3)

1028 FORMATC2X'TRU'7x,lP,4E10.3/2X'PU-241'4X. IP,4E10.3)

1029 FORMAT(/IOX,'VOLUIE' WEIGHTED IMPACTS - UNSTABLE WASTES')

1030 FORMAT(/lOX. 'VOLUM1E WEIGHTED IMPACTS - STABLE WASTES')

1031 FORMAT(/1OX.'VOLUME WEIGHTED IMPACTS - ALL WASTES')

END

I. -o -

'ER'

. .

C

C . . . .I.

SUBROUTINE READIN . ;

c1 .1 . . 1 - . I

I C ALL THE BASIC INFORMATION CONTAINED IN TAPES 1 AND 2 ARE

D-55
- - - 'ILML

OPTIONR Code (cont'd)

C READ IN THROUGH THIS SUBROUTINE.

C

CHARACTER*10 BASN(90).NJC(36)

COMMON/BAST/BAS(90,32). ISPC6.690, 10),DCF(36.7.o ). FICRPt7). AZR(90)

+ /CHRC/3ASN.NUC

+ /NUCS/AL(36).FMF(36).RET(36.s)

+ /DTIS/FSC(6).FSA(6).PRC(6.2).QFC(6.3).TTM(6.3).TPC(6,3).

+ RGF(6.3),POP(6.3)1DTTM(6).DTPC(6).TPO(6.2).NRET(6)

+ /VOLS/VRGI VRG2.VLAY VHOT.VtqOT RVOL(4,37)

+ /NBAS/NSTR.NNUC.t4DXS(90).IMOD(90).ISPEC(90).IHIC(90)

+ /LSTS/CLST(4,16).DXST(3.16.7)1IORD(6.90).FLST(6.4.16)

READ(C.101) NSTR.NNU_.FlCRP

DO 20 I-1,NSTR

20 READ(I.102IBASNCI).(BAS(1.J).J-2.27)

NNIJttJC+13

DO 40 I-I.NN

READ(1, 104)NUC(I).AL(I. FMF I).RET I. I.RET(I.4)

DO 30 K-1.8

30 READCl.106)(DCF(I.J.K).J-1.7)

40 CONTINUE

DO 50 1-1.6

READ(l.lO5)FSC(I).FSAI). (PRC(I.J),J-1.2). CFCCI.J).J-1.3).

+ (TTM(I.J).J-1.3).(TPC(I.J),J=1.3).

+ (RGF(I.J).J1.3).(POP(I.J).J-1,3).NRETCI).

+ DTTM(I),DTPC(I).(TPOCI.J).J-1.2)

50 CONTINUE

DO 53 I-1.4

55 READ(I.109) (RVOL(I.J).J-1.NSTR)

DO 60 K-1.6

DO 60 I-S.NSTR

60 READ(2.103) CISPC(KI.J).J-1, 10)

DO 70 K-1,7

70 READ(2.107) (CDIST(I.J.K).J-I.16).I-1.3)

DO 75 I-1.6

- DO 75 K-1,16

75 READ(2.1091 (FLST(I,.J.K).J-1.4)

101 FORMAT(2I5.7F5.2)

102 FORMATCA10,2E10. 3/1OX.6E10. 3/lOX. 6E10. 3/10X. 6E10. 3/IOX.6E10. 3)

103 FOR.MAT(lOX. 1013)

104 FORMATCA10.4E10.3)

105 FORMATC1OX.7E10.3/lOX.6E10.3/IOX.6EO.3.3I5/IOX.4E10.3)

106 FORMAT(lOX.7EO0.3)

107 FORMAT(SE10.3)

109 FORMAT(0OX,6E10.3)

109 FORMAT(IOX.4E10.3)

RETURN

END

C

C

SUBROUTINE COMBYNCISTR.NOPR)

C

C THIS SUBROUTINE IS CALLED FROM SUBR. RCLAIM AND CHANCES

C WASTE SPECTRUMS. MODIFIES ACTIVITY DISTRIBUTIONS (DIST).

C AND CALCULATES WASTE GENERATOR IMPACTS.

C

CHARACTER*10 BASNC90). NUC(36)

COMMON/BAST/3AS(90. 32). ISPC(6. 90. 10). DCF(36. 7. 8). FICRP(7). AZR(90)

+ 'CHRC/BASN.NUC.

+ /NtUCS/AL(36).FMFC36).RET(36.5)

+ /DTNX1/IRI. IDI. ICI. IXI. lEI, ISI, ILlI, G10 IHI4 101, ICLI. IPOl. IICl

+ /DTNX2/IR2, ID2Z IC2. IX2. IE2. IS2. IL2Z I02. IH2. 102. ICL2. IP02. IXC2

+ /DTIS/FSC(6).FSA(6).PRC(6.2).GFC(6.3),TTM(6,3).TPC(6.3).

D-56
OPTIONR Code (cont'd)

+ RCF(6.3).PO'c6.3).DTTM(6).DTPC(6).TPO(6.2),NRET(6)

* /VOLS/VRC1,VRC2.VLAY,VHOT,VNOT

* - /NBAS/NSTRNNUCNOXS(90),IMOD(90)hISPEC(90),IHIC(90)

+ /LSTS/CLST(4.16).DIST(3.16.7),IORD(6.90)

* /COMB/TPOP(2).DEC(36.2)

DIMENSION UPRS(7.3).USOL(5.3).USAV(3)

DATA UPRS/335..503.'.-1006..690..2060. .1938. .1039. .3*4.6.

S6.3.116..129..72..3*15..4. 42.B.. 6. 125. 35/

DATA USAV/210.,.4,4./.TPOP/1.56E-B'.1.56E-10/

DATA USOL/1282..1873..'2445..2*450.,3*40..2*15..3*24. .0. 10.1

DATA DEC/. 9. 75. 6.2. 5E-3. 21. E-2. 26.2. 5E-3.. 9. 25. 6*2. 5E-5.

* 2*1.E-4,13*2.'5E-5.13*2.~5E-5/

AA5-3. 62

IF(NOPR.GT.O)AA5-1.0

IDR-ISPECCISTR)

NSPC-IORD(IDR.ISTR)

C

C IF THIS IS CALLED FOR THE FIRST TIME (IDRWI) THEN ROUTINE

C PROCEEDS TO STATEMENT 8 (THE MAIN SECTION). HOWEVER. IF

C IDR > 1, THEN IT MUST FIRST UNDO THE PREVIOUS MODIFICATION.

C

IF(IDR.EG.1) CO TO 8

ISP-IORD(IDR-1.-ISTR)

AI-ISPCCISP.ISTR,2)

Al-Al/ISPC(ISP.ISTR.3)

BAS(ISTR.3)=BAS(ISTR.3)*Al*AA5

DO 4 1-4.27

4 BAS(ISTR.I)=BAS(ISTR.1)/Al

IF(NDXSCISTR).CE.0)CO TO 7

IJK-BAS(ISTR.2)*0. 1

DO 6 1-1.16

DIST(1.I.IJK)=DIST(lIIJK)/Al

6 DIST(3.,1.IJK)-DIST(3,I.IJK)/A1

7 IP-ISPC(ISP.ISTR.10)/1000

IF(IP.LT.5) CO TO S

J=2

IF(IP.EG.5) J-I

" DAS(ISTR.5)=BAS(ISTR.5)/(1.-DEC(1.J))

BAS(ISTR,6)-BAS(ISTR,6)/(l;-DEC(2.J))

C

C MAIN SECTION STARTS HERE. FIRST THE WASTE:.GENERATOR

*C IMPACTS ARE SET EOUAL TO ZERO. THEN THE VOLUMES AND

C CONCENTRATIONS ARE r.ODIFIED.

C

E DO 10 J-26.32

IBAS(ISTR.J)O.O10 CONTINUE

A1-ISPC(NSPC.ISTR.2)

Al-A1/ISPC(NSPC.ISTR.3)

A2 BAS(ISTR.3)/AA5

C

A3=A2/AI

BASCISTR.3)-A3

DO 12 1=5.27

12 BAS(ISTR. I)-AS(ISTR. I)Al -

IF(NDXS(ISTR). CE.0)GO TO 16

IJK-BAS(ISTR.2)+0. 1

DO 14 I-1.16 ,

DIST(1. I. IJKA)DIST(1,II..JK)*A1

14 DIST(3.IIJK(=DIST(3, IIJK)*A2

16 BAS(ISTR.28)5BAS(ISTR.3) -

- , : . -.

D-57
OPTIONR Code (cont'd)

C NEXT SECTION UNSCRAI1BLES THE WASTE PROCESSING INDEX.

C AND CALCULATES THE WASTE GEt:ERATOR IMPACTS (IF ANY).

C

J-ISPC(NSPC. ISTR, 10)

9AS(ISTR.4)-BAS(ISTR.4)*A1

;P JO1000

IS-tJX100)-IP*10

IL-(J10)-IP*100-IS*10

-IH-J-IP*1000-IS*100-IL*10

IF(IHIC(ISTR). CT. 0. At4D. IL. EQ. 0) IL-1

IF(IL. EQ. O)RETURN

IF(IL. NE. 2) GO TO 20

BAS( ISTR. 2)-A2

BAS(ISTR. 4)-BAS(ISTR. 4)/Al

20 A5-O.

IF( ISTR. LE. 11. OR. ISTR. GT. 37) A50. 5

IF( ISTR. EG. 30. OR. ISTR. EQ. 31) A5-0. 5

DO 25 J-1.3 :

A4--A3*(AZR(ISTR)*A1-1. )*USAV(J)

IF( IP. CT. O)A4-A4+A2*UPRS( IP. J)

IF(IS. GT. O)A4-A4+A3*USOL(IS.J)

IHC-IHIC C ISTR)

IF(IHC. GT. O. AND. IS. LT. 4)A4=A4+A3*USOL(3+IHC. J)

IF(J. EQ. 3)A4wA4.A5

25 BASC ISTR. 28+J)-A4

C

C NEXT SECTION IS USED TO CALCULATE POPULATION IMPACTS

C FROM ATMOSPHERIC RELEASES IF THE WASTE IS INCINERATED.

C

IF( IP. LT. 5)RETURN

A5=0. 0

J=2

IFCIP.EQ.5) J-1

IF( IH. NE. 1.AND. IH. NE. 2) IH1

DO 40 INUC-1.NNUC

A4-BASCISTR,3)*BASCISTR. INUC+4)*DEC(INUC.J)*TPOPCIH)

40 A5=AS+A4*DCF(INUC. 1.8)

BAS(ISTR. 32)-A5

BAS(ISTR.5)=(l.-DECC(l..J))*I3AS(ISTR.5)

BAS(ISTR.6)-(I.-DECC2.J))*BAS(ISTR.6)

RETURN

END

C

C

SUBROUTINE RCLAIM(ISTR. INDX. NOPR. NBEST)

C

C THIS SUBROUTINE CLASSIFIES THE WASTE STREAMS IF THEY DONT

C HAVE A DISTRIBUTION. CLASSIFIES THE PORTION OF THE

C DISTRIBUTION (AS APPROPRIATE). AND COMPUTES THE IMPACTS

C RESULTING FROM THE INTRUCER-INITIATED SCENARIOS.

C

CHARACTER*10 BASNl90). NUC(36)

COMMONIBAST/BAS(90, 32). ISPC(6. 90, 10). DCF(36. 7.8). FICRP(7). AZR(90) + /CHRC/BASN.NUC

+ /NUCS/AL(36).FMF(36).RET(36.5)

+ /DTNXI/IRI. ID1. IC1. lX1. IEI. ISI. IL1. IC1. IH1. IQ0. ICLI. IPOl. IIC1

+ /DTNX2/IR2. ID2. IC2. IX2. IE2. IS2. IL2. IC2. IH2. 102. ICL2. IP02. IIC2

+ /DTIS/FSC(6).FSA(6).PRC(6.2),GFC(6,3).TTMC6.3).TPC(6.3).

+ RCF(6. 3). POP(6. 3). DTTM(6). DTPC(6). TPO(6. 2). NRET(6)

+ /IMPS/DZ(8.7.2).DZQC4,7.2)

+ /NBAS/NSTR. NNUC. NDXS(90). IMOD(90). ISPEC(90). IHIG(90)

+ /LSTS/CLST(4. 16). DIST(3. 16. 7). IORDC6. 90)

D- 58
OPTIONR Code (cont'd)

DIMENSION EMP(5)

DATA EMP/.5..75-.5..5..75/

NFG-O

C

C NEXT STATEMENT IS THE STARTING POINT AFTER EACH SPECTRUM

C CHANGE AS WELL AS FOR THE FIRST TIME - IN EFFECT AN OPEN

C ENDED DO-LCOP UNTIL ALL. SOME. OR NONE OF THE WASTE IS

C CLASSIFIED.' SEE COMM1ENTS UNDER STATEMENT 29.

C THE LOGIC OF THE SECTION FOLLOWS FIGURE 3 OF APPENDIX C.

C

'10 IF(NDXS(ISTR).EO.OCO TO 30

IF(ISTR.LE.37)CALL'COMBYNCISTR.NOPR)

IDR-ISPEC(ISTR)

ISP=IORD(IDR.ISTR)

'I=ISPC(ISP.ZSTR#8)

IFCIHIC(ISTR).GT.0)I8-1+IHIC(ISTR)'

IF(ISTR. CT.37. AND. NFG.EQ. 0)00 TO 29

.ALL LISTSCISTR.I.NX)

:F(NX.EQ.1) GO TO 21

IF(IE.GT.O)0O TO 16

IF(IABS(NDXS(ISTR)).NE.2) GO TO 29

IF(IC2.EG.I.OR.IX2.EG.3) GO TO 12

IF(IH2.EG.1) GO TO 14

CO TO 29

12 CALL LISTS(ISTR.2.NX)

IF(NX.EG.I) CO TO 23

IF(IL2.EQ.O) GD TO 13

' CALL LISTS(ISTR.3.NX)

'' IF(NX.EG.l)'O TO 25

13 IF(IH2.EO.O) GO TO 29

.14 CALL LISTS(ISTR#4,NX)

IFCNX.EQ.1) CO TO'27'

GO TO 29

16 CALL LISTS(ISTR.2.NX)

IF(NX.EG.1) CO TO 24

IF(IL2.EQ.0) GO TO 17'

CALL LISTS(ISTR.3,'NX)

IF(NJX.EG.1)G-CO TO 26

17 IF(IH2.EQ.O) CO TO 29

CALL LISTS(ISTR.4itJX)

IF(NX.EQ.1) CO TO 26

CO TO 29

21 IMOD(ISTR)-l

INDX-1

IFCIB.E. 0) CO TO 32

IMOD(2STR)-2

INDX-2

CO TO 32

23 IMOD(ISTR)=3

INDX-2

GO TO 32

24 IMOD(ISTR)-4

INDX-2

CO TO 32

25 IMOD(ISTR)-5

INDX-4

GO TO 32

26 IMOD(ISTR)-6

INDX-5

GO TO 32

27 IMOD(ISTR)-7

INDX-7

GO TO 32

D-59
I IIMIL

OPTIONR Code (cont'd)

28 IMOD(ISTR)-B

INDX-7

00 TO 32

29 IF(IDR. EQ. 6) GO TO 30

NFGmt

IDR-IDR+I

ISPEC(ISTR)-IDR

IF(ISTR.OT.37)CALL COMBYNCISTR.NOPR)

GO TO 10

C

C THIS IS THE END OF THE OPEN ENDEDDO LOOP TO CLASSIFY

C ALL OR SOME OF THE WASTE'STREAMS. IF THE WASTE IS NOT

C ACCEPTABLE. THEN STATEMENT 30 IS CALLED. IF SOME OF

C THE WASTE IS ACCEPTABLE. THE ACCEPTABLE PORTION IS LEFT

C IN ITS ORIGINAL ORDER. AND THE REST OF THE STREAM IS

C DESIGNATED AS NSTR+1 STREAM. SEE SUBROUTINE LISTS.

C

30 .MOD(ISTR)-O

RETURN

C

C AFTER CLASSIFICATION BASED ON THE PROPERTIES OF THE

C WASTE STREAM. THE CLASSIFICATION STATUS MAY BE CHANCED

C IN SUBROUTINE MODIF DEPENDING ON THE DISPOSAL TECHNOLOGY.

C INDICES.

C

32 CALL MODIF(ISTR.INDX)

C

C NEXT SECTION STARTS THE CALCULATION OF THE INTRUDER

C IMPACTS FOR VARIOUS TIMES: AT IIC YEARS FOR UNSTABLE (41)

C RECULAR-STABLE (42). LAYERED-UNSTABLE (44). LAYERED-STABLE (45)

C AND HOT (47) WASTES; AT 500 YEARS FOR REGULAR-STABLE (43) AND

C LAYERED (46) WASTES; AND AT 1000 YEARS FOR HOT (48) WASTES.

C

31 I5-ISPC(ISP.ISTR..5)

I6-ISPC(ISP.ISTR.6)

17ISPC(ISP.ISTR,7)

I9-ISPC(ISP.ISTR.9)

IF(IMOD(ISTR).GT.I.AND.I8.EG.O) I8-1

A7-1.0

IF(16.EQ.2.OR. I6.EQ.3) A7-0.80

IF(IMOD(ISTR).CT.1) GO TO 38

IR-IRI

ID-lDI

IC-ICI

IXUIXI

IE-IEl

IS ISI

IL ILI

IC-Id1

IH IHI

10-I0

ICL-ICL1

IPO=IPO1

IIC"IIC1

GO TO 40

33 IR-IRI

ID-ID2

IC-IC2

IX-1X2

IE IE2

IS-1S2

IL-IL2

IC-IC2

D-60
OPTIONR Code (cont'd)

IH=IH2

IO 102

, . *ICL-ICL2

IPO-IP02

,- . *~ . IIC-IIC2

40 CALL ZERO(DZ..112)

IF(17. Ml. OR. IS. EQ.0),:16I6-

FDES-EMP(IE)*(1.-.9*IC)

IF(19.EQ.3):A7-A7*1O.

A5-1.0

IF(I5.LT.3) A5-10.**(15-3)

A6-1.0

IF(I6. CT. 1).:A6-4. ** C1-16)

A9-1.0

IF(I9. CT. 1) A9-10. C(1-19)

DO 60 m3a1i8

CDEL-IPO+IIC

IF(IC.EO.3) CDEL-IPO+5OO.

CO TO C41.42.43.44.45.46,47.48).I3

41 A4C-l-O

A4A-1.0

ABC-A7 -

ABA-A7

CO TO 50.

42 A4C-0.012

A4A0. 0

A8C-0.012*A7

A8AwO.O

CO TO 50

43 CDEL-IPO+500.

A4C-1.0

A4A-1.0

ASC-A7

.ABA-A7

CO-TO 50

- 44 A4C-O.1

- A4A-O 0

ABC-A7/1200.

A8A-O.0

.COTOSO

45 A4C-0.0012

A4A-O. 0

, . * , * - ABC-0-.0012*A7/1200: - , - , ,~A8A-O.O0 , CO TO SO0

46 CDEL=IPO+500.

A4C1. 0,

A4A-l.-O

A8C-A7

A8A-A7,.

CO TO 50

47 ABC-O.1*A7/1.44E6

IF(IC.EQ.O) A8C-A8C*O.i

A4C0. 01.

- A4A-O. 0

ABA-0. 0

CO TO 50

-48 CDEL=IPO'1000..-

,. :ABC-A7 :.

IF(IC.EO.O ABC-O.1*A7

A4C1.0 :

A4A-1.0

ABA-ABC

D- 61
OPTIONR Code (cont'd)

O0 111-IMOD(ISTR)

DO 58 INUC-I.NNUC

A1-A9*FDES*BAS(ISTR.INUC+4)

C

C IF(C13.E0.3.OR. 13.EO.8).AND. (Ill.EO.5.OR.1I11.EO.6))AI-0.1*Al

C EFFECT OF CHAIN DSCAY 'ARE HANDLED THROUGH CHNS AND CALC.

C CHNS CALCULATES THE FRACTION OF EACH MEMBER OF 'THE CHAIN

C AT TIME CDELP AND CALC MULTIPLIES THESE FRACTIONS WITH

C THE DOSE CONVERSION FACTmRS AND SUMS.

CALL CHNS(INUC.GDEL.IENjIBG#NCH)

DO 56 1-1.7.

CALL CALC(INUC.I.C1.C2.,i6.C4.IEN.IBsNCH)

A2-C1

1B5-0.2S*A1*A8A*A2*0.27

B2-A1*ABC*A2*0.057

IF(NBEST.EQ.O) 00 TO 52

BI-Al*A4C*A5*FSC(IR)*C2

B3-0.25*Al*A4A*A5*FSA(IR)*C3

B4-0.5*0.25*Al*A4A*A6*C4

CO TO 54

52 B3-0.25*AI*A4A*FSACIR)*C3

B4-0.5*0.225*A1A4A*C4

Bl-Al*A4C*FSCtIR)*C2

51 DZtI3.I.1)-DZtI3.I.l)+Bl+B2

56 DZ(I3.I.2)-DZ(I3.r.2)-B3.B4+9B

59 CONTINUE

60 CONTINUE

RETURN

END

C

C

SUBROUTINE LISTS(ISTR.NQsNX)

C

C THIS SUBROUTINE COMPARES THE C014CENTRATIONS OF THE ISTR WASTE

C STREAM WITH THE CONCENTRATION-FOR REGULAR (NO-I). STABLE

C (NO-2). LAYERED (NO-3). OR HOT (NO-4) WASTE DISPOSAL. AND

C MANIPULATES THE WASTE ACTIVITY DISTRIBUTIONS. IF NECESSARY.

C

CHARACTER*10 BASNC9O).NUCC3bI

COMMON/BAST/3AS(90.32).ISPC(6.90. 10),DCFC36.7.8).FICRP( .iAZR(90)

+ /CHRC/BASN.NUC

+ /NUCS/AL(36)F.FMF(36).RET(36. D

+ fDTNX1lIRl. 1D0. ICI.lIXI. IEl. ISI. ILl. I11. IHl. 101 ICLI. IPOI. IIC1

+ /DTNX2/IR2. ID2. IC2. IX2. IE2. IS2, IL2, IC2.IH2,102, ICL2. IP02. IIC2

* /DTIS/FSC(6).FSA(6),PRC(6.2).0FC(6.3).TTM(6.3).TPCC6.3).

+ RGF(6,3).POP(6,3).DTTM (6).DTPCC6).TPO(6.2).NRETC6)

+ /VOLS/VRGI.VRG2.VLAY.VHOT. VNOT

+ /IMPS/DZ(8#7.2).DZQ(4.7.2)

+ /NBAS/NSTR.NNUC.NDXS(90).IMOD(90).ISPEC(90).IHIC(90)

+ /LSTS/CLSTC4.16),DISTC3,16.7).IORD 26.90).FLST(6,4.16).NLST

N O0

Al-0.

INDEX-0O

IF(IR2.NE.0.OR.N0.NE.l)CO TO 4

IF(ISTR.CT.7.AND.ISTR.NE.32)CO TO 4

INDEX-1

C

C THE SECTION BETWEEN HERE AND STATEIMENT 16 IS FOm WASTE

C STREAMS WITHOUT AN ACTIVITY DISTRIBUTION.

C

4 IDR-ISPEC(ISTR)

D-62
OPTIONR Code (cont'd)

ISP IORD(IDR.ISTR)

t9=XSPC(ZSP.ISTR.9)

AllCLST(NO.16)

IF(IR2.NE.O)CO TO 6

IF(NLST.CT.3.AND.NQ.NE.1)CO TO 6

IJK-BAS(ISTR.2)+O.1

IF(ISTR.LE.7.OR.ISTR.EQ.32.OR.ISTR.CT.37)A11-A11*35.

IF(IJK.EO.7)A1I-CLST(NO.16)

6 IFCNDXS(ISTR).LT.0) CO TO 16

IF(INDEX.EG.O)GO TO E

C SUBROUTINE BARN PERFORMS A SPECIAL SUMMATION OF THE

C .,ACTIVITIES AND CLASSIFICATION BASED ON THE EXISTING

C DISPOSAL FACILITY LICENSE CONDITIONS. ONLY UNSTABLE

*C WASTES ARE SUBJECTED TO THIS TEST. AND ONLY IF IR2-0

C

CALL BARN(ISTR.A2,A3.NX)-

C

RETURN

8 DO 10.1I19.27.

10 AlAl+BAS(ISTRI)

Al-(AI-BAS(ISTR.22))/CLST(N,15)+EAS(ISTR,22)/AlI

IF(IR2.EG.O.AND.NG.EQ.l)GO TO 14

DO 12 1-1,14

A2-1.0

IF(19.EQ.1)GO TO 12

IF(I. EQ. 2. OR...I. EQ. 4. OR. I. EQ. 6. OR. I. EQ.7)A2=10. 0

12 AlmAl+BAS(ISTRI+4)/(CLST(N0. I)*A2)

14 IF(A1.CT.1.0) RETURN

NX-1

RETURN

C

C THIS SECTION STARTSTHE TESTING AND CLASSIFICATION FOR

C WASTE STREAMS WITH AN ACTIVITY DISTRIBUTION. FIRST THE

-C TOTAL ACTIVITY THAT WO'J..D PERMIT A PORTION OF THE WASTE

C TO BE DISPOSED AS CLASS NO IS DETERMINED, THEN THE VOLUME

C OF THE WASTE CORRESPONDING TO THAT ACTIVITY IS CLASSIFIED.

.- C

16 IF(INDEX.EO.O)CO TO 1E

CALL EARN(ISTR.A2.A3.NX)

GO TO 28

18 DO 20 1-i9.27

20 Al-Al+BAS(ISTR.I)

A2-A1 . -

Al-Al-BAS(ISTR,22))/CLST(NrO,15)+BAS(ISTR.22)/AlI

DO 22 1-1.14

22 A2=A2+BAS(ISTR,1+4).

IF(IR2. EQ. O. AND.7NO..EO.-I)CO TO 26

DO 24 Im1.14

A3-1.0

IF(I9.EQ.1)GO TO 24

IF(U.EO 2.OR.1.EQ.4.OR.I.EQ.e OR.;.EQ 7)A-10. 0

24 Al-Ai-BASCISTR.1-4)/(CLST(NO.I)*A3)

26 A3-A2/AI -

C

C AT THIS POINT A3 IS THE MAX!MJr. PERM.ISSIBLE TOTAL ACTIVITY

C FOR WASTE CLASS NO. IT IS TESTED ASAINST DIST(1.I.IJK).

C AND THE FRACTION OF UASTE vOC-_ME DETERMINED

C . - .

28 IJKwEAS(ISTR.2).0.I

DO 30 12.16

IF(A3.LT.DIST(1,I1IJKi) GO TC 32

3D CONTINUE

D-63
OPTIONR Code (cont'd)

c

C SUCCESS OF DO LOOP 30 MEANS ALL OF THE WASTE IS ACCEPTABLE

C UNDER THE CLASSIFICATION NO.

C

NX-1

Al-I

AS-DIST(3l6.IIJK)

CO TO 44

32 A4-(A3-DIST(l. r-11 IJ.K))/(DIST(i. I. IJK)-DIST(l. -is IJK))

Al-DIST(2.I-1.IJK)+A4*(DIST(21. IJK)-DIST(2,I-IIJK))

IF(AI.LT.I.E-3) RETURN

IFCAI.CT.0.999) CO TO 42

C

C AT THIS POINT SOME OF THE WASTE IS FOUND TO BE ACCEPTABLE

C UNDER CLASSIFICATION NO. THE PORTION THAT IS FOUND UNACCEPTC ABLE MUST BE DESIGNATED AS A liEW WASTE STREAM. THUS, A NEW

C WASTE STREAM DENOTED NSTR+l IS CREATED. AND PROPERTIES OF THE

C ISTR WASTE STREAM IS STORED ONTO THE PROPERTIES OF NSTR.

C

NSTR-NSTR.1

BASN(NSTR)-BASN(ISTR)

3AS(NSTR,2)-3AS(ISTR.2)

BAS(NSTR.3)-3AS(ISTR.3)*(l.-Al)

BAS(NSTR,4)-BAS(ISTR.4)

DO 36 J-5.27

36 BAS(NSTRJ)-BASCISTR.J)

DO 38 J-23,32

33 BAS(NSTR,J)w0AS(ISTR.J)*(l.-Al)

DO 40 K-1.6

IORD(KNSTR)-IORD(KISTR)

DO 40 Jul.10

40 ISPC(KNSTRJ)-ISPC(K.ISTR.J)

ISPEC(NSTR)-ISPEC(ISTR)

NDXSCNSTR)-NDXS(ISTR)

IHIC(NSTR)-IHICCISTR)

AZR(NSTR)-AZR rISTR)

C

C THE FINAL STEPS IN THE CLASSIFICATION OF THE DISTRIBUTION

C WASTE STREAM CONSIST OF ADJUSTING THE VOLUMES. TOTAL AND

C RADIONUCLIDE ACTIVITIES. WASTE GENERATOR IMPACTS. AND

C MODIFYI14G THE DIST (DISTRIBUTIONS) TO REFLECT THAT A

C FRACTION HAS BEEN CLASSIFIED.

C

42 A5-DIST(3.I-1.IJK).A4*(DIST(3.I.IJK)-DIST(3.I-I.IJK))

44 A6-A5*AI

A7=A5/A2

BAS(ISTR.3)-3AS(ISTR.3)*Al

BAS(ISTR.4)-A5

DO 46 J-5.27

46 BASCISTRJ)-BAS(ISTRJ)*A7

IF(NX.EQ.1)RETURN

DO 48 J-28,32

48 BAS(ISTR.J)-BAS(ISTRJ)*Al

DO 50 qJ-I.16

A7-DIST(2. J, IJK)*DIST(3. J. IJK)-A6

AB3DIST(2.J.IJK)-Al

DIST(2, J. IJK)-A3

50 DIST(3.J.IJK)-A7/AS

DO 55 J-2.I

DIST(2.J-l.IJK)iO.

55 DIST(2.J-1.IJK)"O.

DIST(l.I-IlIJK)-A3

A5-O.

D- 64
: . r '. -. ! .i I .,

I C

IOPTIONR Code (cont'd)

DO 65 J1.l6

65 DIST(2.J,IJK)mDIST(2,J,IJK)/DIST(2,16.IJK)

NX-1

RETURN

END

C

C

SUBROUTINE TRANSPCTIMPINX)

C.

C THIS SUBROUTINE DETERMINES THE TRANSPORTATION SCHEME FOR

C ALL THE WASTE STREAMS BASED ON THE PACKAGING INDEX OF THE

C SPECTRUM FILES AND THE CONCENTRATIONS OF THE INDIVIDUAL

C WASTE STREAMS. ULTIMATE RESULT IS THE TRANSP IMPACTS (TIMP).

C

COMMON/DAST/DAS(90.32).ISPC(6.90.10)

+ /DTNXIIIRl.IDljICl.IXl;IEI

+ /DTNX2/1R2.ID2.1C2,1X2,.E2

+ /NBAS/NSTRNNUC.NDXS(90),IMOD(90),ISPEC(90),IHIC(90)

+ /LSTS/CLST(4.16).DUJY(3. 16.7).IORD(6,90)

DIMENSION PCAR(6.3),PPAK(8.6).KON(I9).TYM(2.1),TCST(2.3).

+ RDZ(2. 3)TDZ(2. 2).PKV(5).KWT(I1).DIST(6).STPS(6).

* CASK(6).DU:l(3). DUM2(3).DUM33.33),TIMP(6).TVOL(5,3)

DATA PCAR/l.,.8..4..2.1.0. 0.,.2..5..56..5.2,0.. 0...1..2../4..

DATA PPAK/0...23.540..1..O.,.8.o.025; '50. i;69,.69t.975..2, 1..

3*0.. .50.. . .. E. 0...5.2*0 ;.16.4*0. .5.1..0.,

4 3.a1. 2..4*3..

DATA KON/1103024.1104076,1236100,1370100,1411100.-1501100.

* 2103100.2236096.-2206004.2370048.-2314051.-2306001.

* -2402100.-2501100.-3306051.-3301049o-3402100.-3501100/

DATA TYM/200. 240. 74..120..16.,24..6.,24..136..165.,1200..1440.,

* 300 .360. .26. .39. .250. .300. . 10. .24. .86. S 175. .200. .312.,

* 600 .720. 1200. 1440. .200. .312., 600. .720. s 600. .720.,

4. 1500..1800./

DATA TCST/1.69,1.25.1.47,1.14,1.17.1.08/

DATA RDZ/500. O 750. .1200. *1 00 . .2200.,2200./

DATA TDZ/1.8E-2/2.0E-2,2 .2./

DATA PKV/3.625,.453,.208,1.416.4.814/

DATA KWT/16*0.2*1/ -

DATA DIST/300..400..600.,1000..2.400.1

DATA STPS/2*1..2..3..2*1./

DATA CASK/2. , 3. * 5. S. # 2*3./

ABOVE ARRAYS AND MATRICES ARE AS FOLLOWS:

PCAR - CONTAINS 6 DISTRIBUTIONS OF 3 CARE LEVELS

PPAK - CONTAINS 8 DISTRIBUTIONS OF 5 PACKAGING

CONTAINERS. AND A POSITIONING INDEX

KON D MULTIPLE INDEX DESCRIBINC THE PACKINC PROPERTIES

FOR 3 CARE LEVELS AND 5 CONTAINERS

TYM - TIME (MIN) FOR UNLOADINC OF WASTE CORRESPONDING

TO 1E VALUES CF KON FOR RANDOM AND STACKED DISPOSAL

TCST - TRANSPORTATION COST '(5) PER mILE'

RDZ - DOSE PER HOUR OF CONTACT TIME WITH WASTE

TDZ - UNIT DOSES DUE TO TRANSPORTATION -

PKV - VO.urE CAPACITY FOR 5 TYPES OF CONTAINERS

KWT - OVERWEIGHT STATUS FOR EACH OVERPACK TYPE (KON)

DIST - REGION DEPENDENT TRAVEL DISTANCE TO DISPOSAL SITE

STPS - REGION DEPENDENT STOPS ALONG EACH ROUTE

CASK - REGION DEPENDENT NUMBER OF CASK DAYS ON THE ROAD.

C

C

C

C

C

C

C

C

C

C

C

C

C

C

C

C

C

C

C

CALL ZEROMTIMP.6)

CALL ZERO(TVOL.15) - . . .

D-65
OPTIONR Code (cont'd)

IR-IRi

IE-IEl

IF(INX.EO.1) GO TO 10

IR-IRi

IE-IE2

10 CONTINUE

C

C DO LOOP 160 DISTRIBUTES THE WASTE INTO THREE CARE LEVELS

C AND AMONG 5. TYPES OF CONTAINERS.

C

DO 160 IPAK-1.8

NX-0

CALL ZERO(DUMI.3)

C

C DO LOOP 70 DISTRIBUTES WASTE AMONG CARE LEVELS

C

DO 70 ISTR-1,NSTR.

IF(IMOD(lSTR).EO.0) CO TO 70

IF(INX.EG.1.AND.IMOD(ISTR).NE.1) GO TO 70

IF(INX.EG.2.AND.IMOD(ISTR).EO.1)0CO TO 70

IDR-ISPEC(ISTR)

NSPC-IORD(IDRISTR)

12-IABS(ISPC(NSPC#ISTR.1))

I1-I12/10

IF(I1.NE.IPAK) CO TO 70

13.12-I1*10

AI-BAS(ISTR,28)

A2-BAS(ISTR.4)*100.

IF(13. E£.2) A2=BAS(ISTR.4)*10.

NX-1

IF(13.GT.2) GO TO 40

15-ALOGIO(A2)

IF(13.EQ.2) CO TO 30

IF(A2.LT.1.) 14=1

IF(AZ.GE.1.) 14-15+2

IF(14.GT.6) I4-6

GO TO 50

30 IF(A2.LT.1.) 14-1

IF(A2.GE.1.) 14-15+2

IF(I4.GT.4) I4x4

GO TO 50

40 14-13-2

50 DO 60 11.3

60 DUMI(I)-DUM1lI)+PCAR(I4.,I)*Al

70 CONTINUE

C

C DUMI CONTAINS WASTE VOLUME IN EACH OF 3 CARE LEVELS

C

IF(NX.E0.0) GO TO 160

AI=DUMlC1)+DUMI(2)+DUMI(3)

I2-PPAK(IPAA. 6)+0. 1

DO 80 1-1.3 I I-I-I

80 DUM2(I)xPPAK(IPAK.I2+II)*Al

C

C DUM2 CONTAINS WASTE VOLUME IN EACH OF 3 CONTAINER TYPES

C

CALL ZERO(DUM3.9)

C

C DO LOOP 130 DETERMINX-S PACKAGINC STRATEGY FOR THIS LOOP

C OF IPAK, AND ACCORDINGLY DUKI AND DUM2 ARE DISTRIBUTED

C AND STORED INTO DUM3 OVERALL DISTRIBUTION FOR THIS STREAM.

D-66
OPTIONR Code (cont'd)

DO 130 J-1..3

DO 120 a1.3

IF(DUMI(W).LE.O.0) GO TO 130

IF(DUM.2(I).LE.O.0) CO TO 120

IF(DUMI(1J)-DUM2(I))90.100.110

90 DUM3(IJ)-DUMI(J) - -

%'.'M2(.) DUM2 C I)-DYM IC(JI

DUM I (--1.0

CO TO 130

-100 DUM3(I.J)-DUM(J)-

DUM2(I)--1.0 -

DUM1(J)s-l.0

GO TO 130

110 DUM3CI.J)-DUM2(I) .

DUM1(J)-DUM1(.')-DUM.2(I)

DUM2(I)--1.0

120 CONTINUE

130.CONTINUE

DO 150 1.1.3

II-I-1

DO 150 J-1.3

150 -TVOL(12+II.J)-TVOL(I2+II.J)+DUM3(I.J)

160 CONTINUE

C

C AT THIS POINT TVOL CONTAINS TOTAL-UNSTABLE OR STABLE

C WASTE DISTRIBUTED FOR 3 CARE LEVELS AND 5 CONTAINERS.

C ! '

C THE NEXT SECTION. DO LOOP 240. COMPUTES THE TRANSPORTATION

C IMPACTS FOR THE TVOL. AND STORES IN TIMP. WHICH ARE:

C TIMP(I) -. DOLLAR COSTS

C TIMP(2) - ENERGY USE

C TIMP(3) - TRANSP OCCUPATIONAL DOSE

C TIMP(4) - TRANSP POPULATION DOSE

C - TIMP(S) -- DISPOSAL-SITE UNLOADING OCCUPATIONAL DOSE

C TIMP(6) -TRANSPORTATION LOADING OCCUPATIONAL DOSE

C

DO 240 IKON-I6lE

II-KON(IKON)

NX-1

FRC-1.0

IF(II.CT.0) GO TO 210

C

C IF KON INDEX IS NEGATIVE. THEN RETURN TRIP IS NECESSARY

C

lS--II -

NX-2

210 13-II/100000 -

12-13/10 - w - ~II1 3-12*10 --

I5=II-13.100000-

13-15/1000 -

I4mI5-13*1000 -;

C IN AgOVE SECTION..KON INDEX IS BROKEN UP INTO:

C Il - PACKAGE TYPE I3 1 NO. OF PACKAGES PER SHIPMENT

C 12 - CARE LEVEL -A PCT OF WASTF IN KON MODE

C

IF((12.EG.1).OR. (12.EO.2.AND.NX.EG.2)l.FRC-0.1

FRSI4/100. - *

Al-TVOL(I1.12)*FRS

IF(AI.LT.1.E-06) CO TO 240

KSHP-AI/(13*PKV(II))+1.0-

A2-KSHP*DIST(IR)

D-67
f lmt

OPTIONR Code (cont'd)

A3=A24NX

TIMP(2)-TI.MP(2)+A3/6.

TIMP(4)-TIMP(4)+(A2*TDZ(1.1)+KSHP*TDZ(1l2)*STPS(IR))*FRC

TIMP(3)-TIMP(3)+(A2.TDZ(2,1)+KSHP*TDZ(2.2)*STPS(IR))*FRC

NC-3

IF(DIST(IR).GT.400.AtJD.DIST(IR).LT.1000.) NC-2

IF(DIST(IR).LE.400.) NC-1

TIMP(l)-TIMP(1)+A3*TCST(NX.NC)*1.1S

C

C CASK RENTAL FEE. AND OVERWEIGHT FEE ARE ADDED IN THE

C NEXT SECTION IF APPLICABLE.

C

IF(NX.EQ.1) GO TO 220

TIMPCl)-TIMP(1)+KSHP*CASKCIR)*250.

IF(KWT(IKON).CT.O)TIrIP(l)-TIM.P(1)+A240.76+60.*STPSCIR)

220 KPAK-Al/PKV(Il)+I.O

NX-2

ZF(IE.EQ. I.OR.IE.EQ.4) NX-1

FRC-1.0

IF(IE.EQ.3) FRC-2.0

A2-KPAK*I.E-3/60.

TIMP(5)-TIMP(S)+A2*TYM(NX.IKON)*RDZ(NX.I2)*FRC

TIMP(6)-TIMP(6)+A2*TYM(2.IKON)*RDZ(2.I2)

240 CONTINUE

3002 FORMATCIP.'TVOL '3E10.2)

3003 FORMAT(1P. 'TIMPS '6EI0.2)

RETURN

END

C

C.*.......****. X*X***.+*.s.****.*******+444I*4444***{***444*4**4**4***4*+*

C

SUBROUTINE ECON(RI.RJ.COST.ICN)

C

C THIS ROUTINE CALCULATES THE DISPOSAL IMPACTS BASED ON

C THE WASTE VOLUMES AND THE DISPOSAL TECHNOLOGY INDICES.

C THE RESULTS ARE PLACED IN ARRAY COST, WHERE:

C

C COST(I) - PRE-CP AND OPERATIONAL COST

C COST(2) - OCCUPATIONAL DOSE

C COST(3) - ENERGY USE

C COST(4) - LAND USE

C COST(S) - TOTAL POST OPERATIONAL COST

C COST(6) - COST FOR CLOSURE PERIOD

C COST(7) - COST FOR OBSERVATION PERIOD

C COST(S) - COST FOR INSTITUTIONAL CONTROL PERIOD

C

COMMON/BAST/BAS(90.32).ISPC(6.90,10)

+ /DTNXI/IR1. IDI. ICi. IXXI IEI. ISle ILl.I 11. IHI. 101. ICLI. IPOI. IICI

+ /DTNX2/IR2.ID2. IC2. IX2. IE2, IS2. IL2. 1C2. 1H2. I02. ICL2. IP02. IIC2

+ /VOLS/VRGl.VRG2.VL.VH.VN

+ XNBASXNSTR.NNUC.NOXS(90).IMODI90) ISPEC(9O).IHIC(90)

+ /LSTS/CLST(4.16).DIST(3.16.7).IORD(6.90)

DIMENSION EMP(5).EFF(2).SEFF(2).AI;ULT(2).CONT(6)s

+ IMA(2).COST(8).XCAPC4).CAP(S)

DATA EMP/.5..75 .. 5..S.75/

DATA EFF/6.4.7.0/

DATA SEFF/0. 9.0.35/

DATA AMULT/1.43.1.30/

DATA CONT/1114..439..439..0..1S3..1114.X

DATA XCAP/2*1200..2-750./

DATA IMA/2.4/

DATA ITO/20/

DATA F/.015/

D-68
OPTIONRCode (cont'd)

ARRAYS NEWLY INTRODUCED ABOVE ARE THE FOLLOWING:

AMULT - CAPITAL AND OPERATIONAL COST.MULTIPLIERS

CONT - CONTINGENCY FOR DIFFERENT SOIL CONDITIONS

XCAP - (ALSO CAP);ARE THE BASE ANNUAL CAPITAL COSTS

FOR SITING AND CONSTRUCTION OF A FACILITY

C

C

C

C

C

C

C

C

CALL ZEROKCOST.e8),;.

I VSTAB-O.0

VUNS-O. 0

VCHM-O. 0

VCON-O. 0

IF(ICN. EQ. 2) CO TO 2

IR-IRI

ID-IDI

IC-IC1

IX-IXI

IE IEI

IS-ISIL-IL1

IG-101

IH-IHI

IOIO1-

ICL-ICL1

IPO'IPO1

IIC-IIC1

CO TO 5

2 IR-IR1

ID=ID2

IC-IC2

IX-IX2

IE-IE2

IS-IS2

IL-IL2

IC-IC2

IH-IH2

IQ-102

ICL-ICL2

IPO-IP02

IIC-IIC2

C

C NEXT SECTION CALCULATES VARIOUS

C

VOLUMES AND AREAS-SEE BELOW.

5DO 10 ISTR-1.NSTR

I11-"ISOD(ISTR)

IF(Ill.NE.1) CO TO 6

IF(ICN.EG.l.AND.IE.EQ.3) VCON-VCON+3AS(ISTR,3)

6 IDR ISPECCISTR)

NSPCIORD(IDR.ISTR)

I7-ISPC(NSPC.ISTR.7)

IF(ICN.EG.2)00 TO 7

IF(I 11. EG.1.AND.I7.EG.1)VCHM-VCHM1+BAS(ISTR.3)

CO TO'10 . ;- . . I 

7 IF(CIl1.CE.2.AND.Ill.LT.7).AND.17.EQ.l)VCHM=VCHM+BAS(ISTR.3)

10 CONTINUE -

IF(ICN.EG.2) CO TO 12

VREC-VRCI

VLAY-O. 0

VHOT-O.O

VUNS-VRC -

CO TO 15

12 VREC-VRC2

D-69
IOPTIONR Code (cont'd)

VLAY-VL

VHOT-VH

VSTAB-VREG+VLAY+VHOT

15 CONTINUE

DLAY-VLAY1. OOE-ob

DREG-CVREC+VLAYl*l.OE-6

DHOT-VHOT*I.OE-6'-

DCHM-VCHM*I.OE-6

SV-DRE0*(U1.1567/EMP(IE))-l.)

DCON-VCON*1.OE-06

DVOL-DREC/EMP(IE)

DAREA-DVOL/(EFF(ID)*SEFF(ID)l

GVC(l.-EP(CIE))*DVOL

VTOT-VREC+VLAY+VHOT

DTOT-DREG+DHOT

C

C AT THIS POINT THE VARIOUS VARIABLES ARE AS FOLLOWS:

C

C VREG x REGULAR WASTE VOLUME

C VLAY a LAYERED WASTE VOLUME

C VHOT - HOT WASTE VOLUME

C VUNS a UNSTABLE WASTE VOLUME

C VSTAB- STABLE WASTE VOLUME

C VCHM a CHEMICAL WASTE VOLUME

C VCON - DECONTAINERIZED DISPOSAL WASTE VOLUME

C

C AFTER THE INITIAL CALCULATION. THESE ARE MULTIPLIED BY

C 1.CE-6 TO CONVERT THEM INTO MEGA UNITS DLAY. DHOT.

C DCHM AND DCON ARE ALL CONVERTED UNITS. IN ADDITION

C

C DVCL u DISPOSAL VOLUME

C DAREA- DISPOSAL AREA

C VTOT a TOTAL VOLUME (IN STANDARD UNITS)

C SV - SAND VOLUME

C CV - GROUT VOLUME

C

IF(VTOT.LT.0.1)RETURN

VTOTT-VRGC+VRC2+VL+VH

RATIO-VTOT/VTOTT

COST(4)-DAREA*1.OEO6(DHOT/1.84)*l.OE+06

C

C IN WHAT FOLLOWS. Cl. C2. AND C3 ACCUMULATE THE DOLLAR

C COSTS. DOSE. AND ENERGY USE THROUGH VARIOUS PHASES

C OF THE DISPOSAL FACILITY LIFE.

C

C PRE-OPERATIONAL (CAPITAL) COSTS

C

C ******* REFERENCE BASE CASE *****.

C

C1-3970.2*RATIO

DEP-2120.5*RATIO

ZOSTC3)-212.*RATIO

C

C *.....* ADDITIVE ALTERNATIVES ****.

C

1B IF(ID.NE.2) GO TO 98

Al-593.5

D1-539.5

IF(IDl.EQ.2.AND.ID2.EQ.2) AIAI*RATIO

IF( ID1. EQ. 2. AND. ID2. EQ. 2) DI-DI*RATIO

Cl1C1+AI

DEP-DEP+DI

98 IF(IS.LT.2.OR.VCHM.LT.O.1)0O TO 100

D-70
OPTIONR Code (cont'd)

A10.99

D1-0.9

IF(ISI.CE.2.AND.IS2.CE.2)AI-Al*RATIO

IF(IS1.CE.2.AND.IS2.CE.2)Dl-D1*RATIO

Cl-C 1A1

DEP-DEP+D1

100 IF(IE.NE. 2. AND.IE.NE.5) CO TO 101

Al-225. S

DI 205.

IF((IEI. EQ. 2.OR. IEM.EO.5).AND. CIE2.EQ. 2. OR. IE2.Ea. 5))AI-A1*RATIO

IF((IE1. EO. 2. OR. IE1.EQ.5).AND. (IE2.EQ.2.DR.IE2.EQ. 5))D1=DI*RATIO

C1-C1 +A

DEP-DEP+DI

101 IF(IS.EQ.O.OR.IS.EQ.2) CO TO 102

IF(VRG1.LT.0.1)CO TO 102

A1-0.99

I ~D1-0.9-.

IF((IS1.EQ. 1.OR. IS1.EQ.3).AND. (IS2.E.1. OR.IS2.EQ.3))Al-AI*RATIO

IF((IS1.EQ.1.OR.ISI.E0.3).AND. (IS2.EO.1.OR.IS2.EQ.3))DI=Dl*RATIO

DEP-DEP+D1

102 IFIL. NE.1.0R.ICN.EQ.1) CO TO 103

A1-132.

D1-120.

Cl-CI+A1

DEP-DEP+D1

103 IF(IE.NE.3) CO TO 104

A1-924.3

D1-840.25

IF(IE1.EQ.3.AND.IE2.EQ.3) A1-AI*RATIO

IF(IE1.EQ.3.AND.IE2.EQ.3) D1-DI*RATIO

C1-C1+A1

DEP-DEP+D1

104 IF(IH.NE.1) CO TO 105

A1-259.5

D1-235.9

IF(IHI.EQ.1.AND. H2.EQ.1) AI=AI*RATIO

IF(IH1.EQ.1.AND.IH2.EQ.1) D1=DI*RATIO

Cl-Cl+Al

DEP-DEP+Dl

105 IF(IC.NE.1) CO TO 106

A1-55.

D1-S50.

IF(ICI.EQ.1.AND.IC2.EO;.1) AI-Al*RATIO

IF(ICI.EQ.1.AND.IC2.EO.1) D1-Dl*RATIO

Cl-C1+A1

DEP-DEP+Dl

106 IF(IC.NE.3) CO TO 107 -

A1=280. 5

D1 255.

IF(ICI.EQ.3.AND.IC2.-EQ.3) A1-A1§RATIO

IF(ICI:EG.3.AND.IC2.EQ.3) DI-DI*RATIO

CI=CI+A1

DEP-DEP+D1

107 IFCIX.NE.3) CO TO 10S

Al-9. 9

D1-9.

IF(IX1. EO.3. AND.IX2.E0.3) A1-Al*RATIO

IFC IX1. E.3. AND. IX2. EO.3) D I=DI*RATIO

C1CI+A1-

DEP-DEP+D1

10S CONTINUE

DEP-DEP*1.3

D-71
OPTIONR Code (cont'd)

CAP(5)-Cl*AKULT(l)

DO 110 1-1,4

110 CAP(I)-XCAP(I)*AMULT(CIIRATIO

C

C OPERATIONAL COSTS

C

C ***4 REFERENCE DASE CASE **444

C

C1-2341.*DVOL

C2-300.*DVOL

C3i200.*DVOL

Cl-CI+1420.*DAREA

C2-C2+2400.*DAREA

C3-C3+100.*DAREA

Cl-Cl+78759.*RAT2O

C2-C2+1000.*RATIO

C3-C3+200.*RATIO

C

C ****o ADDITIVE ALTERNATIVES ***

C

IF(ID.NE.2) CO TO 20

Cl-Cl+77118.*DVOL

C2-C2+700.*DVOL

C3-C3+300.*DVOL

20 IF(IE. NE. 2) CO TO 24

Cl-CI+13010.*DREG

C2-C2+100. *DREC

C3-C3+100.*DREC

24 IF(IE.NE.5) CO TO 25

Cl-Cl+13010.*DREG

C2-C2+100.*DREG

C3-C3+100.*DREO

25 IF(IS.EQ.0.OR.IS.EQ.2) CO TO 26

IF(VRCI..LT.0.1)CO TO 26

ClmCI+4809.9*DREO

C2-C2+100.*DREG

C3-C3+30.*DREC

26 IF(IS.LT.2)CO TO 30

Cl-Cl+4809.9*DCHM

C2-C2+100.*DCHM

C33C3+30.*DCHM

30 IF(IL.NE.1) CO TO 35

ClmCI+23076.*DLAY

C2-C2+(-100.)*DLAY

C3-C3+30.*DLAY

35 IF(IE.NE.3) CO TO 40

Cl-Cl+57262.3*DCON

C2-C2+400.*DCON

C3-C3+100.*DCON

40 IF(IH.NE.1) GO TO 45

Cl-Cl+181823.*DHOT

C2-C2+(-200.)*DHOT

C3-C3+450.*DHOT

A5 IF(IG.NE.1) CO TO 46

C2-C2+2250.*CV

C3-C3+800.*GV

46 IF(IE.LT.4) CO TO 50

Cl-CI+3270.*SV

C3-C3+185.*SV

50 IF(IC.NE.2) CO TO 55

Cl-Cl+15555.*DAREA

C2-C2+2400.*DAREA

D-72
OPTIONR Code (cont'd)

C3-C3+150.*DAREA.

55 IF(IC.NE.3) CO TO 60

Cl-CI+106447.*DAREA

C2-C2+2400.*DAREA

C3-C3+300.*DAREA

60 IF(IX.EO.1) CO TO 75

S3-DAREA

IXX-IX-1

CO TO (65.70).IXX

65 Cl-CI+3496.*S3

C2-C2+4eoo.*S3

C3-C3+300.*53

CO TO 75

70 Cl-CI+39167.*S3

C2-C2+4800.*S3

C3-C3+600.*S3

75 OP-CI*AMULT(2)

COST(2)-COST(2).C2

COST(3)-COST(3)+C3

C

C

C

C

C

C

C

C

C

C

C

CALL COSTS(CAP.DEP.OP.DTOT.DC)

POST-OPERATIONAL COSTS -

******* CLOSURE PERIOD ***.***

I Cl-1063.*RATIO

C2-500.*RATIO

C3-15.*RATIO

IF(IQ.NE.2) CO

Cl-3345. *RATIO

C2- 1000.*RATIO

C3-60.*RATIO

TO 76

*****+* INSTTTUTICNAL PERIOD **.***

DOLLAR COST SECTION -.

:. e,.

76 CA-RATIO*167.3

CB-RATIO*66.5

CC-RATIO*54.

COM-RATIO*106.6

IF(ICL.NE.2) CO TO 77

CA-RATIO*384.6-

CB-RATIO*167.3

CC-RATIO*91.5

COM-RATIO*258.7

77 IF(ICL.NE.3) CO-TO 78

CA-RATIO*(523.2+CONT(IR))

CB-RATI0*384.6

CC-RATIO.167.3

COM-RATIO*339.3

76 Sl-0.O

- S2-0.t0 -

S3-0.0

Dl-l. i - D2-(1.+RJ)/(C.+RI)

DO 80 N-I.10

DI-Dl*D2 -

DO 85 N=11.25

Dl=DI4D2

85 S2-52+D1

D-73
13L

OPTIONR Code (cont'd)

DO 90 N-26.XIC

D1DI4D2

90 S3-S3+DS

IMI-IMACI0)

IM1P0-IP.I

S4-0.0

IF(IM.LT.1) CO TO 95

DO 93 N-1.IM

E-N

D1-tl +RJ)**E

D2i(l.+RI)**E

93 S4-S4+DI/D2

95 CONTINUE

PV80-CA*SI+CB*S2+CC*S3

M-IPO+ITO

MI-ITO+IMI

EM-M

EITOWITO

EIPO-IPO

EM1-M

Dl-Cl. +RJ)**EITO

D2-Cl.+RJ)**EM

D3CIl.+RI)**EITO

D4-Cl.+RJ)**EIPO

D5.Cl.+RJ)**EMI

D6-CCI..RI)**EMI)-l.)

COST(9)-(EITO*PV80*D2*RI)/CCD3-l.)*D4)

COST(7)-EITO*COM*D*S44*RI/D6

COST(6)=EITO*D1Cl*(F+tRI/(D3-1.)))

COSTtl)-DC*DTOT I

COST(5)-COST(6)+COST(7)+COSTCS3

C

C ENERGY USE SECTION

C

IICC-CIIC-26)+1

CO TO t200.210.220).ICL

200 C3-C3+C1O*5.+15*3.+IICC*l. *RATIO

CO TO 225

210 C3-C3+C10*10.+15*5.+IICC*3.)*RATIO

CO TO 225

220 C3-C3+t10*12.+15*10.+IICC*5.)*RATIO

225 CONTINUE

COSTl)-COSTt 1)*1000.

COSTt2)-COSTt2)+C2

COST(5)-COST(5)*1000.

COST(3)-COST(3)+C3

COST(3)-COST(3)*1000.,

COST(6)-COST(6I*1000.

COST(7)-COST(7)*1000.

COSTC8)=COST(B)*1000.

RETURN

END

C

C

SUBROUTINE ZEROCA.N)

C

DIMENSION AtN)

DI 10 1J1.l4

10 AcI)-O.O

RETURN

END

C

D-74
OPTIONR Code (cont'd)

C

FUNCTION EXM(Al)

C

A2-0.0

IF(AZ.LT.85.) A2-EXP(-AI)

EXM-A2 -

RETURN

END - -

CC .. .

SUBROUTINE PRT(VI0.4.UID) -

C

C SUBROUTINE PRT IDENrIFIES AND PRINTS OUT WASTE VOLUIIES.

C DISPOSAL MODE. SPECTRUM. AND STREAM NUMBER IN FIVE TYPES:

C UNSTABLE-RECULAR. STABLE-REGULAR. LAYERED. HOT. AND

C UNACCEPTABLE. CHEMICAL AND NON-CHEMICAL PORTION OF EACH

C CROUP IS PRINTED SEPARATELY.

C

CHARACTER*10 BASN(90).LAB(2)

COMMON/BAST/3AS(90.32).ISPC(6,90.10)

:./CHRC/BASN

+ /NBAS/NSTR.NNUC.NDXS(90).IMODC9O).ISPEC(90).IHIC(90)

+ /LSTS/CLST(4.16).DIST(3.16.7).IORD(6.90)

DIMENSION 10(90)

DATA LAB/'N-CHEMICAL'. 'CHEMICAL

IFCN.EQ.O)RETURN

CO TO (10. 10. 10. 50 70); ID,

10 lF(ID.EO.1)WRlTE(4o4l0)V

-IF(ID.EG.2)WRITE(4,420)V

IF(ID.EQ.3)WRITE(4.425)V

DO 40 K-1.2 ,

IT-0

VTOT-0. 0

DO 20 InlN

J-IQ(I)

IDR-ISPECCJ)

NSPC IORD(IDR.J) -

17=ISPC(NSPC.J.7)

IF(K.E0.l.AND.17.NE.O) GO TO 20

IF(K.E0.2.AND.17.NE.1) GO TO 20

IF(IT.EQ.O)WRITE(4.430)LAB(K)iBASN(J).BAS(J.3).J.IMODCJ).IDR.NSPC

IF(IT.EO.I)WRITE(4.440)BASNCJ).BAS(J.3).J.IMOD(J).IDR.NSPC

IT-I

VTOT-VTOT+BAS(J.3)

20 CONTINUE

IF(IT.EO.1) WRITEC4.470)VTOT

40 CONTINUE

RETURN

50 WRITE(4.450)V

DO 55 11.N

J-IQC I)

IDR-ISPEC(J)

NSPC-IORD(IDR.J -)

55 WRITE(4.440)BASN(J).BAS(J.3).J.IMOD(J),IDR.NSPC

RETURN

70 WRITE(4.460)V

DO 75 I-1.N

J-ICI} )

IDR-ISPEC(J)

NSPC-IORD(IDR.J)

75 WRITE(4.440)BASN(J),BAS(J.3).J.IMOD(J).IDR.NSPC

D-75
OPTIONR Code-(cont'd)

410 FCRMAT(lP*/2X'REC-VNSTA8LE :'21X.10.3,5H M**3)

420 FCRMAT(lP,/2X'REC-STABLE : '2IXE£10.3.5H M**3)

42 FCRMAT(IP#/2X'LAYEREV WASTE :'21X#EIO.3. H M443)

430 FORMAT(lPs 7X# 2AlO. E10.3 4.15)

440 FORMAT(IP 17X.A1O.E10.3.415)

450 FORMAT(1P./2X'HOT WASTE :'21X.E;10.3,5H M**3)

460 FORXAT(IP,/2X'NOT ACCEPTABLE:. 21X*EX10.3.5H M*43)

470 FORMAT(IP.1SX'TOTAL VOLUME : 5XE10.3#5H M**3)

RETURN

END

C

C*42 .~*-P4*X-*4*q4**4*4 I 2*4A4*4U**^>***44*4NEW >4X<§441***

C

SJBROUTINE ACCEXP(NEEST.ICrJ

C

C THIS ROUTINE CALCULATES IIIPACTS FRCOM OPERATIOMAL

C ACCIDENTS. AND IMeACTS FRO1 ATMOSPHERIC AND SURFACE

C WATER TRAt4SPORT CF WASTt EXPOSED THROUGH SCME MEANS.

C I.E.. THE SO CALLED EXPOSED-WASTE SCENARIOS.

C

COMMON/BAST/3AS(90.32).ISPC(6,90#10).DCF(36,7.5)

+ /NUCS/AL(36)

+ /DTNXlIRlo IDI* ICIP Ixt IEl. IS1 ILlt 101, IHIs 101. ICLI. 1POlsI.IC1

+ /DTIJXZ/IR2i 12, IC2. IX2. IE2, IS2. IL2.102,1H12.102. ICL2, IPOZ2 IIC2

+ /DTIS/FSC(6).FSA(6).PRCC6.2).GFCC6,3),TTh(6.3),TPCC6.3).

+ RCFC6,3).POPC(63).DTTM(6).DTPC(6)0TPC(6#2),NRET(6)

+ /VOLS/VRGI.VR02#VLoVHVN

* /IMPS/DZ(S,7,2).DZG(4.7.2),DZA(7.7),DZS(90,7.2) + /NIEAS/NSTR#1Q.fUCotJDXS(90)# IMOD(90). ISPEC(90)o IHIC(90)

+ /LSTS/CLST(4.16).DIST(3.16,7).IORD(6. o)

+ /CHYW/NXUC(i6).ICH(7.6).LCH(6).ACT(7)

i ;lNiBC;7 i2

DIMENSION EKP(5).EFF(2)*SEFFC2)

DATA EMP/. 5.. 75s.. 5.. 5. 75/

DATA EFF/6.4.7.0/

DATA SEFF/0. 9. 0. 35/

IF(ICN.EG.2) GO TO 5

IR-IRI

IDD101

IC-ICl

IE-IEl

IS-IS1

IPO=IPOI

IIC-IIC1

VTOP-VRG1

VTOT-VRGI

VLAYuO.

VHOT=O.

CO TO 10

5 IR-IR1

IDwID2

IC-IC2

IE-IE2

IS-Ib2

IPOwIP02

IIC-IIC2

VTOP-VRQ2

VTOT-VRC2+VL

VHOT-VH

C

C EXFOSED WASTE SCENARIOS ARE HANDLED FIRST. CREC AND CERO

C ARE THE TIMrFS INTHUDER-INITIATED AND EROSION-INITIATEO

C SCENA.RIOS ARE INITIATED.

D-76
OPTIONR Code (cont;d)

C

10 CREC-IPO+IJC

CERO-IP0+2000.

IF(IC.EQ.2) GERO=IPO+3COOr

IF(IC.EQ.3) CERO-IPO+CO0OO.

IF(ID.EG.2) GERO-IPO+10300.

FRA5.72E-5*POP(IRI )4.E3E+3

VUR-E.lP(IE).EI-F(ID)*SEFF(ID)

FEA-9.09E-6*POP(IR.2)*VTOT/VU!4

FRW=l.15E-4*POP(IR.3)-1.eE+3

FEIJ=1.15E-4*FOPCJR.3)*VTOT/VUR

C

C FRA - FACTCR FOR INrTUDER-ATMOSPHERIC

C FRW - FACTOR FOR INrRUDER-SURFACE WATER

C FEA - FACTOR FOR ERDSION-ATKOSPHERIC

C FEW - FACTOR FOR EROSION-SURFACE WATER

C

DO 40 ISTR=1NSTR

A1'0.25

IIlI-IrlOD(ISTR)

IF(Ill.EG.0) CO TO 40

IF(ICN.EQ.1.AND.111.NE.l)CO TO 40

IF(ICN.EG.2.AND.Il1.EO.1)CO TO 40

IDR-ISPEC(ISTR)

t4SPC=IORD(IDR, ISTK)

15I1PC(NSPCISTH -5)

A5-1.0

IF(15.LT.3) A51IO.-%xtI5-3)

I9-IFSPC(NEPC, ISTR.9)

A9-1.0

I8ISPC(NSPCISTR8-)

IFt~l.OD(ISTF0.CT.2) 18-1

IFCIHIC(ISTK).CT.0) I8-1*XHIC(ISTR)

IF(18. CT. 0. AND. IS. EG. 1) A1-0.012/9.

IFtI8.CT.O.AND.IS.EO.3) Al-O.012/9.

IF(IXI.EG.5.OR.Ill.EO.6.OR.ID.EG.2) Al-Al*O.01

IF(I1l.EG.7.OR.Ill.EQ.8) Al-1.2E-5/9.

A2-0

A3 O. -

A4-ErP(IE)*SEFI(ID)43AS(ISTR,3)

IF(VTOP.CT.0.1)A2-A4/VrOP-

- IF(VTOT+VHOT.CT.O.l)A3-A4/(VIOT+VHOT)

IF(I11.CT.4) A2-O.0 -

IF(ID.EG.2.ANlD. (III.NE. 5.CR.-Ill.NE.6)) A.2-A3

CDO 30 INUC=INN'UC

CALL CHNS(INUC. CREC. IEN. IBG. NCH)

DO 12 1-1,7

12 BCT(IXl)=ACT(r)

-CALL CHNS(INUCCERD, ZEN. IBO, NCH)

DO 14 1-1,7

14 BCT(I.2)-ACT(I)

A8SBAS(ISTRIN'JC+4)

IFlN3EST.EQ.O) 00 TO 15

Bl-FRA*AA*A3*A9)A5*A9- -

B2-FEA*A2*A8

CO TO 20

I5 Bl'FRA*Al*A3*A9*A8

B2-FEA*A24AS

20 B3=FHW*A1*A3AA8*A9

B4-FEW*A2*AS

DO 25 IORC-1#7

CALL CALC2(INUC.IORG.CI.C2.C3sC4,IEN.IBCotJCH)

D-77
I LLN

OPTIONR Code (cont'd)

DZA(IORO.1)-DZACIORCl)+Bl4CI

DZA(IORG.2)-DZACICORC.2)+B2*C2

DZA(IORG.3)-DZACIORG.3)493*C3

DZAtIORG.4)-DZACIORO.4)+B4iC4

25 CCNTINUE

30 CONTINUE

40 CONTINUE

IF( ICN. EQ. 2)RETURIJ

C

C ACCInENT SECTION IS EMPLOYED ONLY FOR UNSTABLE WASTES

C

VSC-D. 0

VFR=0.0

DO 80 ISTR-1.NSTR

13-IlOiDtISTR)

IF(13.EQ.O.OR.13.EQ.7.CR.13.EQ.8) GO TO eo

IDR-ISPEC(ISTR)

.NSPC-IORD(IDR.ISTR)

14-ISPC(NSPC.ISTR.4)

I5-ISPCtNSPCISTR.5)

I6-ISPCtNSPC.ISTR.6)

I9 ISPCCNSPC.ISTR.9)

A5-3AS(ISTR.3)

IF(19.CT.1) GO TO 80

IF(A5.EQ.0.0) CO TO eo

FAF-TPOCIR, 1)*O. 1

FAS-TPO IR. 2)

A6-1.0

IFCI3.EQ.3) mo1.0

IFCI5.LT.3.AND. I6.EQ. 1) A60. l

IF(I6.EQ.2.0R.I6.EO.3) A6-0.01

IFCIA.EQ.4) A6-0.001

IF(14.LT.3) FAF-FAF*(20.**(I4-3))

IFtIS.EQ. 1.AND. I4.NE.3) FAP-O.0

IFtIS. EQ. 3. AND. 14. NE.3) FA=-D.0

VFR-VFR+AS

VSC-VSC+A5

DO 70 INUC-I.NNUC

AlSuFAS*BAS(ISTR.INUC+4 )'A5

AlF=FAF*BAS(ISTRINUC+4)*AS

DO 70 IORO-1.7

DZSCISTR.IORO. )-DZSCISTRIORO,1)+AlS*DCFCINUC.IORO.R1)/A

DZSCISTRICRO.2)-DZS(ISTR.ICRGC2)+A1F*DCFCIN'JCIOR. 1)/AS

DZACIORG, )-DZA(IORC.5)+AlS*DCF(INUCIOR. 1)

70 DZA(IORC.6)-DZA(IORG.6)+AIF*DCF(INUCIORGl)

SD CONTINUE

CO 90 IORG1l.7

DZA(IORC.7)-CDZACIORG,5)+DZA(IORG.6))/(VSC+VFR)

IF(VSC.GO.O.) DZACICRQ.5)-DZA(IORC.3)/VSC

IF(VFH.cT.O.) DZACIV.RC.6)-DZA(IORG.6)/VFR

90 CONTINUE

RETU4N

EIwo

C

C{*4§*.*...'.***.**.**: X*-tU*Zs***4*****x*Z4**w**X**A*****4*4****

C

SUBROUTINE CHNSCINUC.GDEL. IEN.3 130. lCH)

C

C THIS ROUTINE IS IDENIICAL IN LOOIC WITH THE ACTDR

C SUBROUTINE OF MILDOS CODE. HOIIEVER. HERE FIRST THE

C CHAIN MEMBERS ARE DEIERMINED. THEN THE ACTDR CALCULATIONS

C ARE APPLEIE. SMALL DIFFERENCES ARE DUE TO UTILIZATION

D-78
OPTIONR Code (cont'd)

C OF DOUBLE PRECISION TO INCREASE ACCURACY OF RESULTS.

C

COMMON/CHYN/NXUC(36).ICH(7,6),LCH(6).ACT(7) -

* /NUCS(AL(36),FMF(36)

REAL*8 Y. Z. DACT(7).H M(7).EHLMt7)

DATA ICH/23.36.35.32.28.27. 0.18.20.15.33.29. 0. 0.

* 19.14.34.30.26.24,0.16.34.30.26.24.0,0. -

* 2-. 17. 13.31.27.0.0.21.17.13.31.27.0.0/

DATA LCH16. 5. 6. 5. 5. 5/

DATA N XUC/12*0. 11*1. 13/ 0

CALL ZERO(ACT.7)

IF(NXUC(INJC).NE.O)CO TO 12

10 ACT()i-EXt(AL(INVC)*GCEL)

RETUHtJ

17 CO 16 NCH-1,6

IEtJ=LCHtNCH)

DO 14 IEC=1.IEN

IF(IW"JC. EQ. ICH(IDG1.NCH))CO TO 19

14 CONTINUE

16 CONTINUE

STOP

IS IF(ISG.EQ.IEN)1O TO 10

IEND-IEN-IBG+1

DO 20 I-1sIEND

J-ICHCIBG+I-1.NCH,

HLMCI)-AL(J)

Y-HLtMCI)*GDEL

2-0.

IF(Y.LT.'85.)Z DEXP(-Y)-

20 EH KM(l)-Z tlL.C.T ( I I=UW Mu (I

DO 60 I2.IEND

PD 30 J-2.1

30 YNY*HLM(J)

DACT(I) O.

DO 50 K-1.I

Z EHLM (K)

DO 40 J-1.I

IF(K.N -JZ (PILM(J) -HI-MtK})

40 COGNTINUE

DACT(l)=DACTCI)+Z

50 CONTINUE

DACT(Ir-DACT(I).Y

IF(DACT(I).LT.O.)DACT(I)=O.

60 CCOJTINUE

DO 70 1-1.IlEND

70 ACT(l)-DACT(I)

RETUxN

END

C

C* * 44 * * * 24* * 4*4 **4* *:*z**4***X *4 {4Z£4 *t* 44* 4 .t X*44 t4** * * ** * * ** * *

C

SUBROUTINE CALC(INUC.IPC1,C2.C3.C4.IEN;IONCH)

C

C THIS ROUTINE OBTAINS THE C1.C2.C3.C4 COEFFICIENTS USED IN

C THE INTRUDEN IMPACT CAlCULATIONS. IF:INUJ IS NOT A M'EMBER

C OF A CHAIN THEN THE SECTION BEFORE STATEMENT 15 IS USED.

C IF IT IS A CHAIN MEIBEN, SECTION AFTER 15 IS USED.

C

COc3M-N/BAST/3ASC90.32). ISPC(6.90. 10).CCF(36,7.8)

* /CHYN/NXUC(36).ICHC7s6).LCH(6).ACT(7)

* /NUCS/ALC36).FMF(36)

D-79
film

OPTIONR Code (cont'd)

IF(NXUC(ItUC).NE.0)CO TO 15

10 A1'ACT(l)

Cl-AI*DCF(INUC.IP 5)

C2-AI*DCFtINUC*IP.2i

C3AA1*DCi( INUC. IP, 3)

C4-AI*DCFCINUC. IP 4)4FtF(IN'JUC)

RETURN

15 IEND IEN-I3C+1

Cl-a.

C2a0.

C3-0.

C4-0.

DO 20 I-1.IEND

NIJZICH(IBG+I-1- NCH)

ClCl+ACTCI)*DCF(NN. IP#5)

C2*C2+AcrcI)*DCF(NN. IP.2)

C3-C3+ACT(I)*DCFCNN. IP*3)

C4-C4+ACT(I)*DCF(riN.IP.4)4FM=(Nt4)

20 CCNTINUE

RETURN

END

C

C

SU3ROUTINE OVERFLO

C

C THIS ROUTINE CALCULATES AN1b PRINTS RADIOLOGICAL AND VONC RADIOLOGICAL IMPACTS IF TH, DISPOSAL CELLS ARE PERMiITrED

C TO FILL WI1H WATER 'JNDSE TWO COURSES OF ACTION: LETTING

C TH- THENCH OVERFLOW, AND TREATING AND EVAOORATING THE

C TRENCH LEACHATE. I:4 TH- OVERFLCW CASE. SUJRFACE WATFR

C IMPACTS TO THE MAXIMUM ivnIVIDUAL ARE CALCULATED, AND IN

C THE EVAPC ATCN:: CA-- r-rn AV;_.: EXPCSUnES AnE CALCULATED.

C IN ACDITIONt COSTSt AND ENERGY USE ARE ESTIMATED BASSD ON

C THE EXPERIENCE AT THE MAXEY FLATS EVAPORATOR.

C

COMMGDN/3AST/3AS(9032).ISPC(6,90.i10).DCF(36,7.S),FICRP(7)

+ /NUCS/ALC(6),Fr&F(36)

+ /DTNYI/IR, ID, IC. IX. IE# IS. IL. 10, INH 10, ICL

+ /VOLS/VRG1 VRw22tVLAYV;'OTVN3T

+ /NBAS/NSTRNNUCtf.DXS(q'O), IMOD(90). ISPECC90)fIHIC(90)

+ /LSTS/CLST(4,16).DIST(3#16,7).IORD(6.50)

+ /COMB/TPOP(2).t EC(36.2)

DIMENSION OINPC5).TAC(23),DZFLO(2,7)

IF(IR.EQ. 1.OR. IR.EG.6.C*R. ICL.NE.3)RETURN

CALL ZERO(OINP.5)

CALL ZERO(TAC.23)

CALL ZERO(DZFLO.14)

VL-O.

IF(IX.EO.3.OR.I0.EQ. .OR.ID.EQ.2)00 TO 45

VTOT-VRGI+VRC2+VLAY+VHDT

CO 20 ISTR-INSTR

IF(IrQOD(lSTR).NE.1) GO TO 20

IDR-ISPEC(ISTR)

ISP=IORD(IDRR ISTR)

16-IbPC(ISP.ISTR.6)

I7-ISPC(ISP.ISTR,7)

I9aISPC(ISP.ISTR,9)

110ISPC(ISP.ISTK.10)

IP-IIO/SOO

IESC(I10/100)-IP*10

IFCIES.EG.4.CR.IHIC(ISTR).EQ. 1)00 TO 20

IF(I7.EG.1.OR.IS.LT.2) 16I16-1

D-80
OPTIONR Code (cont'd)

A6-1. 0

A9-1. 0

IF(16.GT.1) A6=4.**t1-16)

IF(19.GT.1) A9=10.**(1-19.)

AI-A6*A9*3AS(ISTR,3)/VTOT

DO 10 INUC-I.t.NUC

10 TAC(INUC)=TAC(l.NJC).AlFM(It4tUC)*DAS(ISTR, INUC+4)

-.CONTINUE

VL-VR21/264.17205

DO 40 INUC-l.NNU

A1-VL*TAC(INUC)*D-C(INUJC.2)*TPOP(2)

A2-VL*TAC(IN'UC)/4.5E+6

DO 30 1-1.7

DZFLO(l.1)=DZFLOC.1)+fA14DCF(INtJCIse) --.

DZFLO(2.I)-DZFLO(2,1)+A2-DCF(INUC.1.7)

0It1P(1)uOINP()+Al.FICRP C)*DCF(IlJC.I S8)

30 0114PC5)-OINP(5).A2*FICRP(I)*DCF(INUC.1.7)

40 CONTINUE - -

45 VL-VLa264.17205

OINP(2)-0.4*VL/208.

OINP(3)-VL*300000./1.3E+6

OINP(4)-VL*2.4E+5/1.3E+6 .

WRITE(4 100)VL.OXNPtl),OlNP(5),OINP(2),OlIJP(3),01NP(4)

DO 50 I-1.2

50 WRITt(4101 )(DZFLOCIJ)J 1,7) -

100 FCRMAT(/2X. 'TRENCH OVERFLOW IMPACTS : (`IPElO.3. GALS )'/2X.

+'RADIOLOGICAL POPULATION DOSE (PERSON-rREM) !:'E0.3/2X*

+ INDIVIDUAL DOSE t ?iREM/YR ) : E1O.3/2X.

+1 OCCUPATIONAL DOSE ( 11REK ) :'E10.3/2X.

*'FItJNACIAL COST C S/YR ):E1O.3/2X#

*'EIERGY USE PRC?AhIE 1 CALS/YR ':10.3/)

101: R TCMAT .1I. 71 0. :)

RETURN

END

C

C

SUBROUTINE COSTS(CAP.DEP.OP.V.DC)

C

C THIS ROUTINE CALCULATES THP DISPOSAL COSTS ACCORDING

C TO THE ALGORITHM PRESEN;ED IN APPENDIX C OF THE FEIS.

C

DIMENSION CAP(5)

DATA ITO/20/.EJ/.09/,EOR/.75/.TF/.48/.TS/.065/

DATA D/.15/.EID/.10/ I

EITO-ITO -

oPY-OP/SEITO

VY-V/EITO

.CRF-(D*Cl.+D)**rITO)/(((I.+D)**ITO)-l.) *

. TR-TS+TF*(1.-TS) . '

A-O. O

CAPD-0.0

TCAP-D. 0

DO 30 N-1.. -

CAPD-CAPD+CAP(N)*(l.-EDR)*((1.+EJ)**(N-5))

TCAP-TCAP+CCAP(N)*EDRICAP(N)*Cl.-EDR)m(1.+EID))*

+ (1.+EJ) ** (I-5)) -

30 AI-A1+CAP(N)*(Cl.+EJ)4*(N-5))/(C1.+D)**N)

XIDP-(CAPD/EITO)/EID -

A2-0.0 .

A3-0 0

IIUITO+5

XI I-II

D-81
OPTIONR Code (cont'd)

A6zEITO*(EITO+l.)/2.

DO 40 N-6.11

EU-N

DEPY-(XII-EN+1.)*DEP/A6

A4=tl.+D)*.(-N)

A2mA2+(CRF*TCAP+((1.-TR)*CPY*C1.+EJ)u*(14-5))-TR*XIDP-TR*DEPY)*A4

40 A3-A3+tC.-Tf ){VY*A4

CC-CAI.A2)/A3

RETUXN

END

C

C

SUBROUTINE MODIF(ISTR.INDX)

C

C THIS ROUTINE MODIFIES THE DISPOSAL STATUS OF THE 1JASTE

C (WHICH WAS DETERMINE,, BASED CN WASTE PRCPERTIES)-TO TAKEC INTO ACCOUNT THE DISPOSAL PRACTICES.

C

CCMMON/DT:!Xt/IRIIDIICt. IXl# Elt IS%

+ /DTNX2IR2.D2, IC2. X2. 1E2.IS2.1L2. 1G2,H2

/NI3AS/NSTR. NNUCe ).XS(90), IMODC90)

IF(ISI.EQ. l.OR. ISI.EQ.3)RErux,:

111-111ODCISTR)

IFtIR2.NE.O);GO TO 20

IFtIl1. Ea. 1. OR. Ill. GE. 7)RETURtJ

IriODDlSTR)-I

INOXut

RETURN

20 IFtIH2.EO.t)CO TO 30

I .F MNDX _I. . I SREQ. _4_. O. .11. EQ_ ) 1

ISOD(ISTR)-I1I

INOX-l

RETU8N

30 IFtIlt.EO.3 OR.Itt.EQ.5)111-7

IFtItI.EQ.4.0R.Ilt.Ea.6)Iltl=3

IXODtISTR)-Ttt

I.:OX-7

RETUHN

END

C

C*4414 -4o4*44*.44§^t4{ {<{4{**4 X>.{Z*{4}4X*R4 E{*.*44{4 1*4**4444*4*

C

SUBROUTINE 3ARNCISTR#A>.A3.tJX)

C

C THIS ROUTINE PERFORMS A SPECIAL CLASSIFICATION TEST

C FOR UNSTABLF WASTES BASED ON EXISTING DISPOSAL FACILITY

C LICENSE CONDITICNS. BOTH NON-DISTRIBUTIONAL ANID DISTRIBUC TIONAL WASTE STREAKS CAN 3E SUBJECTED TO THIS TEST.

C

COMMON/3AST/3AS(90.32)/NBAS/X!STR, WNUC.NDXS(90)

A1-O.

DO 10 1-19.27

10 AI-Al+3ASCISTRI)

A2-Al

Al-At-3AStISTR.22){(t.-l./35.)

IF(NDXS(ISTR).LT.O)CO TO 20

IF(Al.OT.0.016)RElUmN

DO 12 1-5.6

IF(3AS(ISTR.I).CT.1.O)RETURN

12 CONTINUE

00 14 I-8.lS

D-82
OPTIONR Code (cont'd)

IF(DASCISTR1 ICT. 1. . ,RETURN14 CONTINUE .

RETURN

20 DO 22 I-5. 18

2I A2-A2+AS(ISTR.I)

A4-AIIAXI(B3AS(ISTR, 5), DAS(ISTR, 6))

DO024 XinS.12

IF(A4. LT.ZAS( ISTR, I) )A4-I3A,( ISTR. 1)

24 CONTINUE

A3-A l/.016

IF(A'!.LT.A3)A4uA3

A3xA2/A4

RETURN

END

C

SUBROUTINE CALC2CtINUC. IP.Cl.C2.C3,C4, lEN. IBG.NCH)

C

C THIS -ROUTINE PERFORMS THE SAME FUNCTION THAT SUBROUTINE

C CALC DID FOR RCLAIKI FCR ACCEXP. CHAI1N EFFECTS FOR

C - INTRUDER- AND E-OcTn!J-1TJTTTAT iY fncn UASTE

C- SCENARIOS ARE CALCULATeD IN THIS ROUTINE.

CC IFMCN/3AST/IAS(90.32).ISPC(6,9010.).DCF(36.7.8)

/CHYN'./NXUC(36),ICHC7,6),LCH(6).ACT(7)

4 /CHIN-./BCT(7, 2)

* /NUCS/AL(36).FMF(36)

IFCNXUCEINUC).NE.O)0OTO 15

10 CI-3CT(1.1)*DCFCINUC.IP.s)

C2-ECTi1,'2)*DCF(IKU!'IP,8)

;C-CTI -2 FA.TA)*DFA4 A3 C - , 7-

- - RETURN

15 IEIID-IEN-IEG+1

CI-O.

C2-0.

C3-0.

C4-0.

-020 EN1 TEND

* NrjuIcH(IBO.I-1 t~Icm)

CI-CI+BCTU1.1)*DCF(N'NIp,g)

C2CC24CT(I. 2)DCF(t!N. IP- 13)

C3=C3+BCTCI, 1)*DCF(Il.V# IP. 73

C4-C4O3CT(I. 2)*DCF(N-4, IP, 7)

20 CONTINUE -

RETURN *

END

D-83
I li

IN1FIL File

37 231.000 .120

P-IXRESIN 1.OOOE+00

1 3.360E-02

1 8.610E-04

1 2.190E-02

I 7.94CE-04

P-CONCLIO 2.000E+00

2 1.090E-01

2 8.360E-03

2 2.850E-02

2 1.440E-03

P-FSLUDGE 3.000E+00

3 1.060E+00

3 1.140E-01

3 2.140E-02

3 6.750E-03

P-FCARTRO 1.100E-01

4 1.860E+00

4 2.040E-01

4 9.540E-03

4 1.660E-02

B-IXRESIN 4.OOOE+00

5 4.630E+00

5 2.150E-02

S 2.040E+00

5 2.600E-03

3-CONCLI 5.OOOE+00

6 2.870E-01

6 1.800E-03

6 6.650E-02

6 4.600E-03

B-FSLUDGE 6.000E+00

7 5.240E+00

7 3.250E-02

7 1.330E+00

7 1.150E-02

P-COTRASH 2.100E-01

8 2.280E-02

8 2.190E-03

8 2.510E-03

8 2.410E-04

P-NCTRASH 2.100E-01

9 5.250E-01

9 5.050E-02

9 5.780E-02

9 5.550E-03

B-COTRASH 2.200E-01

10 2.350E-02

10 1.360E-04

10.7.140E-03

10 5.630E-05

B-NCTRASH 2.200E-01

St 3.790E+00

11 2.190E-02

11 1. 150E+00

11 9.080E-03

F-COTRASH 2.110E-01

12 5.580E-06

12 0.

12 0.

12 0.

F-NCTRASH 2.110E-01

13 5.330E-06

.060 . 030

3.463E404

2.660E-03

8.840E-08

4.710E-08

3.990E-08

2.435E+05

3.450E-03

8.580E-07

6.15CE-09

7.250E-0O

4.279E403

2.590E-03

1.170E-05

1.460E-07

3.390E-07

2.177E+04

1.150E-03

2.090E-05

3.640E-07

8.340E-07

7.623E+04

1.920E-02

3.090E-05

5.330E-08

1.170E-07

2.102E+05

6.240E-04

2.590E-06

3.440E-03

2.0602-07

1.690E+05

1.260E-02

4.700E-05

3.320E-07

5.180E-07

4.244E+05

3.040E-04

2.250E-07

7.890E-09

1.210E-09

.060 .120 . 060

9. 740E-05

1. 940E-04

3. 710E-07

4. 154E-05

1.270E-04

2. 520E-04

4. 840E-07

7. 132E-05

9. 550E-05

1.890E-04

1. 150E-06

4. 581E-04

2. 340E-03

8. 230E-07

9. 060E-12

1.260E-06

2. 270E-02

1.070E-06

1. 180E-11

2. 020E-06

3. 1OOE-01

8. 030E-07

2.810E-11

1.780E-05

4. 250E-05. 5. 550E-01

8.400E-05 3.580E-07

2.870E-06 7.020E-11

6.414E-04 1.100E-05

1.190E-03 9.480E-01

3. 640E-03

4. 200E-07

9. 798E-05

3. 890E-05

1. 180E-04

2. 71OE-07

2. 523E-04

7. 780E-04

2. 370E-03

2. 610E-06

4. 868E-04

7. 650E-05

1. 020E-11

1. 570E-06

7. 940E-02

2. 5OOE-06

6. 610E-12

8. 100E-Ob

1. 440E+00

5. COOE-05

6. 380E-11

1. 050E-05

2. 790E-06

2. 440E-06

2. 600E-05

9. 920E-09

2. 710E-05

3. 160E-06

5. 120E-05

1. 170E-08

3. 710E-04

2. 370E-06

4. 760E-05

3. 100E-07

6. 600E-04

1. 060E-06

2. 510E-04

1. 930E-07

9. 800E-04

2. 040E-04

8. 340E-05

2. 700E-08

8. 210E-05

6. 650E-06

1. 990E-04

2. 590E-07

1. 490E-03

1. 330E-04

4. 660E-04

2. 970E-07

7. 110E-06

2. 780E-07

5. 970E-06

2. 740E-09

1. 640E-04

6. 4SOE-06

1. 380E-04

6. 300E-08

6. 210E-06

7. 140E-07

2. 300E-06

1. 930E-09

1. OOOE-03

1. 150E-04

3. 710E-04

3. 120E-07

0.

0.

0.

0.

0.

4. 530E-03

8. 230E-07

1. 820E-05

1. 380E-05

4. 400E-02

1. 070E-06

3. 310E-05

1. 920E-05

6. 000E-01

8. 030E-07

1. 550E-04

1.770E-04

1. 070E+00

3. 580E-07

3. 800E-04

1. 100E-04

1. 590E+OO

7. 650E-05

5. 340E-05

1. 820E-05

1. 330E-01

2. 500E-06

9. 430E-05

2. 050E-04

2. 4 10E+00

5. 000E-05

2. 360E-04

2. 240E-04

1. 150E-02

9. 420E-08

5. 530E-06

2. 610E-06

2. 650E-01

2. 170E-06

1. 270E-04

6. 000E-05

1. 01OE-02

2. 680E-07

1. 160E-06

1. 490E-06

1.620E+00

4. 330E-05

1. 860E-04

2. 410E-04

0.

0.

0.

0.

0.

1.120E-05 5.970E-03

2.220E-05 9.420E-08

6.220E-08. 1.520E-12

1.089E-05 2.670E-07

2.178E405- -

6.990E-03 2.570E-04

5. 180E-06 5.S1OE-04

1. 820E-07 1.430E-06

2.790E-07 2.508E-04

2.086E+05

6.750E-05 4.170E-06

1.960E-07 1.270E-05

1.220E-09 9.600E-09

2.530E-09 2.586E-06

9.896E+04

1.090E-02 6. 730E-04

3.160E-05 2.0SOE0-03

1.970E-07 1.550E-06

4.080E-07 4.172E-04

2.359E+05

0. 0.

0. 0.

1.180E-06 4.400E-06

0. 0.

4.171E+04

0. 0.

1. 370E-01

i2. 170E-06

3. 490E-11

6. 150E-06

6. 01OE-03

2. 68CE-07

2. 350E-13

6. 520E-08

9. 690E-01

4. 330E-05

I3. 780E-S1

1. 050E-05

0.

0.

0.

0.

0.

D-84
X! FI File - I.,.

INIFIL File (6ont'd)

i'

13 0. 0. 0.

13 0. '1.130E-06 4.200E-06

13 0. 0. . 0.

I-COTRASH 2.030E-01 1.407E+05 - 14 1.130E-01 9.130E-02 5.260E-03

14 0. 0. .- :1.450E-03:

14 4.560E-03 0. - - 0.

14 0. . 0. 4.820E-06

I+COTRASH 2.030E-01 1.407E*05 ''

15 1.130E-01 9.130E-02 5.260E-03-

15 0. 0. 1.450E-03

15 4.560E-03 0. 0.

15 0. 0. -. 4.620E-06

N-SSTRASH 2.060E-01 1.796E+05

16 1.120E-05 0. 0.

' 16 0. 0. 0.

16 0. 2.360E-06'8.BOOE-06

16 0. 0. 0.

N+SSTRASH 2.060E-01 1.796E+05

17 1.120E-05 0. 0.

17 0. 0. - 0.

17 0. 2.360E-06 B.BOOE-06

17. 0. 0. ' 0.

N-LOTRASH 2.070E-01 5.064E+04

1B 3.530E-02 2.850E^02 1.640E-03

18''' 0. 0. -4.-530E-04

'- e18 1.420E-03 0. . 0.

1.:e 0. 0. 1.SlOE-06

N+LOTRASH 2.07CE-01 5.064E+04'

19 3.530E-02 2.850E-02 1.640E-03

19 0. 0. 4.530E-04

-19 1.420E-03 0. - 0.

.19 0. '. 0 1.'510E-06

F-PROCESS 3.110E-01 7.816E+04'

20 l.OBOE-04 0. 0.

20 0. 0. ' 0.

20 0. 2.300E-05 B.540E-05

20 0. 0. 0.

U-PROCESS 3.120E-01 2.B61E+04

21 3.800E-04 0. 0.

21 0. 0. 0.

21 0. 1.650E-05 3.640E-04

21 0. - 0. 0.

I-LOSCNVL 3.030E-01 4.914E+04 ';

22 9.600E-03 5.010E-03 2.510E-04

22 0. 0. 4.340E-03

22 0. 0. - O.

22 0. 0. 0.

I+LGSCNVL 3.030E-01 4.914E+043': -

23-9.600E-03 5.010E-03 2.510E-04

23 0. 0. -4.340E-03

23 0. 0. 0.

23 0. 0. 0.

I-ARSLIOD 3.030E-01 5.585E6+03

24 1.990E-01 1.420E-01 8.160E-03

24 0. 0. 4.340E-03

24 1.370E-02 0. 0.

24 - 0. 0. 0.

I+ARSLIOD 3.030E-01 5.585E+03

25 1.990E-01'1.4202-01 8.160E-03

--25 O. 0. -'4.340E-03

25'1.370E-02 0. 0.-

25 0. 0. 0.

.O.

0.

0.

0.

3. 390E-09

0.

0.

- 0.

3.390E-09'.

0.

0.

0.

0.

0.

0.

0.

0.

0-O. '- 1.'040E-02

0. 0.

0. - 0.

0. 0.

.0.

0. '- 0.

0.

-1. 040E-02

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.060E-

- 0.

0.

0.

1. 0602-

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

: 0.

0.

0.

0.

0. ' 0.

0. 0.

0. 0.

0. - 0.

.0. 0.

0. 0.

0. 0.

0. - 0.

0. 3. 250E-03

_09 0. 0.

0. 0.

0 0.

0. 3. 250E-03

_09. n0. 0.

0. 0.

0. 0.

0. * 0.

0. 0.

0. 0.

0. 0.

*0. -0.

0. 0.

0.- 0.

0.' 0.

0. O.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 3. 1202-02

-06 O.- - 0.

0. 0. O. 0.

0.

1. 020E0.

0.

0. _

1. 020E-08'

0. !

0.

0.

0.

0.

0.

3. 120E-02

0.

0.

0.

D-85
I II Its

IN1FIL File (cont'd)

I-SSOWAST

26

26

26

26

I+3IOWAST

27

27

27

27

N-SSWASTE

28

2z

28

28

N-LOWASTE

29

29

29

29

L-N>RCOMP

30

30

30

30

L-DECONRS

31

31

31

31

N-ISOPROD

32

32

32

32

N-HICHACT

33

33

33

33

N-TRITIUM

34

34

34

34

N-SOURCES

35

35

35

35

N-TARGETS

36

36

36

36

F-PUDECON

37

37

37

37

H-3

H-3 /ACC

H-3 /CON

3. 030E-01

2. 06CE-01

0.

8.760E-03

0.

3. 030E-01

2.060E-01

0.

8. 760E-03

0.

3. 060E-01

2. 170E-04

0.

0.

0.

3. 070E-01

2. 110E-02

0.

1. 040E-03

0.

4. 300E-01

4. 040E+03

2. 090E+02

0.

0.

4. 40CE-01

1. 560E+02

3. 690E+00

3. 18E-Ol

3. 550E+01

4. 040E-01

1. 500E+01

0.

6. 730E+00

7. 100E-03

4. 030E-01

2. 100E+02

1. 060E+01

0.

0.

4. 050E-01

2. 330E+03

0.

- 0.

0.

4. 030E-01

5. 760E+03

1. 050E+01

3. 540E+03

0.

4. 030E-01

S. 040E+01

0.

0.

0.

7. 000E+00

2. 345E-01

- 0.

0.

2. 188E-01

5. 630E-02

1. 252E+09

1. 172E+10

1. 571E204

1. 750E-01

0.

0.

0.

1. 571E+04

1. 750E-01

0.

0.

0.

6. 339E+04

0.

0. a 600E-05

0.

6. 027E+04

1. 630E-02

0.

0.

0.

2. 887E+03

0.

8. 190E-03

0.

0.

3. 498E+04

1. 060E-02

1. 420E-03

6. 84C0-05

3. 870E-03

5. 196E+03

4. 2C0E-02

0.

1. 020E-05

9. 370E-09

2. 602E+03

0.

4. 470E-04

0.

0.

3. 481E+03

2. 330E+03

0.

0.

0.

1. 866E+02

2. 090E+03

0.

0.

0.

1. 340E+03

6. 040E+01

0.

0.

0.

4. 663E+03

0.

0.

0.

1. 893=-Ob

1. 10+OO

5. 190E+07

5. 190E+07

1. OOE-02

6. 330E-03

0.

0.

l. OlOE-02

8. 330E-03

0.

0.

0.

0.

1. 710E-04

0.

9. 360E-04

1. 310E-03

0.

0.

2. 590E-01

0.

0.

0.

6. 880E-04

4. 260E-02

5. 400E-04

1. 026F+O0

4. 510E-05

6. 270E+00

3. 810E-05

2. 152E-04

1. 320E-02

0.

0.

0.

0.

0.

0.

0.

3. 190E-03

2. 870E+01

0.

1. 600E+01

0.

0.

0.

0.

0.

6. 510E-09

0.

I,. -. --

0.

0.

0.

0.

0. 0.

6. 510E-09 0.

0. 0.

0. . 0.

0.

0.

0.

0.

0.

7. 760E-10

0.

0.

2. 230E+03

0.

0.

0.

4. 050E+01

1.200E-05

1. 320E-08

3. 590E-04

0.

3. 270E-04

5.330E-13

1. 250E-06

1. 150E+02

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.4002E00

0.

0.

0.

4.490E-02

3.340E-05

1.340E+00

3.460E-04

0.

2.720E-06

1.970E-04

1.650E-04

6.560E-02

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.355E-03

0.

1.252E+09

3. 990E-03

0.

0.

0.

3. 990E-03

0.

0.

0.

0.

0.

0.

0.

1. 470E-03

0.

0.

0.

1. 600E+03

0.

0.

0.

7. 280E+01

1. 200E-05

1. 770E+00

3.270E-O0.

3. 270E-04

5. 550E-05

2. 860E-07

8. 480E+01

0.

0.

0.

0.

0.

0.

0.

8. 120E+01

0.

0.

0.

0.

0.

0

0

0.

0.

1. 260E-02

0.

1.252E+09 5.190E+07

0. 0.

0 0.

0. 0.

1. 559E-03 0.,

1.000E+OO l.OOOE+00

1.252E+09 1.252E+09

1. 172E+10 1. 172E+10 1. 172E+10 1. 172E+10 1. 0W2E+10

D-86
INlFIL File (cont'd)

H-3' /ACR 4.451E+10 5.190E+07-4.'451E+10:4.451E+10 4.451E+10 4.451E+10 4.331E+10

H-3 ,,/FOO 5.995E+04.- 0. 5.995E+04 5.995E+04 5.995E404 5.995E+04 5.995E+04

'H-3- /D W 0, . '- 0 , ., ,,_ 0. . 0 .

H-3 /JWWT 2.367E+06,1.422E-01 .2:367E+06 2.367E+06'2.367E+06 2.367E+06 2.367E+06

' H-3 /SUT,2.368E+06 1. 422E-01 .2.'368E+06,2.3&SE+06'2.36EE4 06 2.368E+06 2.368E+06

-H-3 /AIR'4.'451E+10',5.'190E+07:4.451E+10 4.451E+10'4:451E+10 4.451E+10 4.331E+10

IC-14 , 1.210E-04 5.'760E-03,1:OOOE+011.'OOOE+01,

,C-14 /ACC,3.166E+09 1.405E+10:3.,166E+09 3.166E+09 3.-166E+09 3.'166E+09 2.526E+09

' C-14' /CON 6.678E+10 3.321E+1'.667BE+10 6.678E+10;6.678E+10 6.678E+10 6.614E+10

C-14 /ACR 2.660E+11 1.32aE+12 2.660E+11 2.660E+11 2.660E+11 2.660E+11 2.654E+11

'C-14 /FOO 3.721E+05 1.861E406'3.721E+05 3.721E+O5 3.721E+05 3.721E+05 3.721E+05

C-14, /DGM 0. 0. ;0. 0. 0. ' 0. 0.

C-14 '/WWT'1.441E+07 7.205E+07.1.441E+07,.1.441E+07 1.'441E+07 1.441E+07 1.441E+07

C-14 /SWT 3. 761E+07 1. BODE+08 3. '761E+07-3.'761E+07 3.761E+07 3.761E+07 3.761E+07

C-14 /AIR 2.-66CE+11 1.328E+12 2.660E+11,'2.660E+11'2.660E+11 2.660E+11 2.654E+11

IFE-55, 2.670E-01 1.480E-02 6.300E+02 5.400E+03

FE-S5 /ACC'1.8O'E+10 1.885E+10 2.413E+10 1.613E+10 1.613E+10 2. OSE+11 1.925E+10

FE-55 /CON 9. 23E+09 4.'816E+10'3. 941E+10 5.02OE+07 5.080E407 2.095E+11 2.116E+10

FE-55 /AOR 3.219E+1O 1.-903E+11'1.376E+11 5.080E+07-5.080E407'2.644E+11 7.752E+10'

FE-55 /FOO 3.482E+01 2.161E402,1.493E+02 - 0. '. 8.331E+01 8.566E+01

'FE-55 /DOM :0. 0. - ',0. ,0. 0.. 0. . 0.

FE-55 /WWT 2.727E+06 1.244E+07 'E. 63E+06 8.609E+05 8.609E+05 5.326E+06 5.452E+06

: FE-55/SWT 4.450E+06 2.314E407 1.625E+07 8.609E+05'8.609E+05''9.449E+06 9.692E406

'''FE-5S /AIR 4.E27E+10 2.064E+ll l.S37E+11 1.613E+10 1.613E+10 2.8304E+11 9.360E+10

iNI-9 , 8.660E-06 1.'480E-02.4;200E+02 3.600E+03,

NI-59 /ACC'3.698E+10 9.378E+10 5.058E+10.2.57EE+10,2.57EE+10 5.778E+10 2.850E+10

NI-59 /CON 3.872E+10 2.325E+11 B.,130E+10:5.9aOE+075. 980E+07 3.206E+10 1.441E+10

NI-59 /AGR 1.247E+11 7.476E+11 2..591E+11 5.980E+07-5:980E+07 3.206E+10 5.082E+10

NI-S9 /FOO 3.693E+03 2.211E404'7.590E+03 0. 0. 0 1.563E+03

NI-59 /DGM 6.200E+03 6.200E+03 .6.200E+03 6.200E+03 6.200E+03 6.200E+03 6.200E+03

NI-59 /WWT 8.537E+06 4.425E407 1.609E+07 1.377E+06 1.377E406 1.377E+06 4.408E+06

NI-59 /SWT 9.825E+06 5.196E+07 1.874E+07 1.377E+06;1.377E+06 1.377E+06 4.9S3E+06

NI-59 /AIR 1.50'E+11 7.'733E+11 2.-e3BE+l1 2.578E+10:2.578E+105.778E+10 7.654E+10

,CO-60 - ,1.320E-01.1.480E-02 4.200E+02 3.600E+03'

- CO-60'/ACC'2.358E+12 2.'336E+12 2.353E+12 2.336E+12 2.336E+12 2.634E+13 2.504E+12

CO-60 /CON 1.237E+11 2.280E+10 7.'599E+10 2.280E+10'2.280E+10 2.402E+13 8.593E+11

CO-60 /AGR 3.695E+11 2.280E+10 1.874E+11 2.280E+10t2.2S0E+10 2.402E+13 2.953E+12

, CO-60 /FOO'5.274E+03 ',0. ' 2.391E+03 0. 0. 0. 4.492E+04

C0-60 /DM 1.540E+07 1.540E:07 1;540E+07 1.540E+07 1.540E+07 1.S40E0707 ' 060UT .42E0 123E0 .-3Z6E+08 1.238E+08 1.2383E+08 1.239E+08 2.893E+08

;C-60 /SWT 1.458E+08'1. 232E+08 1. 338E+08 1.23BE+08 1. 236E+08 1.239E+08 3.112E+08

C0-60 lAIR 2.6B3E+12 2.335E+12 2.SOOE+12 2.336E+12 2.336E+12 2.634E+13 5.266E+12

r NI-63 ,7.530E-03 1.480E-02 4.200E+02 3.600E+03 - , -

14-63 /ACC 3.056E+10 9.602E+11'6.576E+10 1.560E+08 1.560E+08-8.816E+10 7.436E+09

NI-63 /CON 1.040E+11 3.150E+12 2.176E+11 1.560E+08 1.560E+08 8.816E+10 3.911E+10

NI-63 /ACR 3.341E+11 l.'OOlE+13 6.931E+111.560E+08 1.560E+08 8.816E+10 1.383E+11

NI-63 /FOO 9. 878E+03 2.945E+05 2.041E+04 0. 0. 0. 4.259E+03

NI-63 /DCM 0. 0. .- 0. 0.. 0. 0.

, NI-63 /WWT 1.915E+07 6.711E40o 3.958E+07 4.276E-0 76E-01-2.416E+02 8.258E+06

NI-63 /SWT-2.260E+07 6.:73E2+08 4.670E+07 4.276E-01 4.276E-01,2.416E+02 9.743E+06

-NI-63 AIR 3.341E+11 1;001E+13 6.931E+11,-1.560E+08 1.560E+O8 8.816E+10 1.383E+11

NB-94 3. 470E-05 1.110E-02 1.'000E+03 1.000E+04

NB-94 jACC 6.;102E+11 6.114E+11 6.108E+11 6.095E+11- 6. 107E+11.i. 3;0E+12 6.839E+11

`45-94 /CON 1.389E+1O 1.515E+1O 1:.454E+10 1:320E+10 1.446E+10 7.332E+11 4.432E+11

-NB-94 /ACR 1.399E+10 1:54eE+10 1.;472E+10 1.320E+210'1.464E+10 7.332E+11 1.557E+12

,NB-94 /FOO 2.'116E+00 7.,076C+00 3.937E+00 0. '3.892E+00 -O. 2.390E+04

NB-94 /DOt 9.630E+06 9.630E2O6 9.630E+06 9.630E+06 9.630E+06 9.630E+06 9.630E+06

NB-94 1UWWT 3.l93E+O7 3.196E40T 3.194E+O7 3.192E+O7 3.9EO .92E+O7 1.466E+O8

NB-94 /SWT 3.232E+07 3. 324E+07 '3. 266E+07 3.192E+O; 3.265E+07 3.192E+07 4.496E+09

NB-94 /AIR 6.103E+11 6. l1EE+11 6.111E+11 6.095E+11 '6. 11OE+1 1.330E+12 2.153E+12

SR-90 2.,470E-02 9.860E-03 9.OOOE+00 7.300E+01

-SR-/90 ACC 2.417E+13 9.617E+131.668E+11 1.668E+11 1.668E+11 1.980E+11 1.892E4-11

SR-90 /CON 6.394E+13 2.58SE+14 1.760E+09 1.760E+09 '1.760E+09 3.296E+10 4.727E+12

D-87
INIFIL File (cont'd)

SR-90 /AGR 1. 891E+14 7.686E+14 1.760E+09 1.760E+09 1.760E+09 3.296E+10 1.946E+13

SR-90 /FOO 6.407E+07 2.611E+08. 0. 0. 0. . 0. 7.543E+06

SR-90 /DCM 3.060E+04 3.060E+04 3. 060E+04 3.060E+04,3.060E+04 3.060E+04 3.060E+04

SR-90 /WWT 9.564E+09 3.895E+10 8.835E+06 8.B35E+06 8.835E+06. 8.835E+06 1.134E+09

SR-90 ISWT 1.'014E+10 4.12EE+10 8.835E+06 8.835E+06 8.835E+06 8.835E+06 1.201E+09

SR-90 7AIR I1.892E+14 7.688E+14 1.668E+11.1.66EE+11 1.668E+11' 1.980E+11 1.962E+13

TC-99 3. 270E-06 1. 150E-01 2.000E+00 5. 000E+00. ,

TC-99 /ACC 1.176E+09 9. 680E+09 2.280E+09 7.600E+08 1.996E+10.7.400E+09 7.880E+09

TC-99 ICON 2. 960E+09 5. 411E409 8.890E+09 7.600E+08 1.031E+11 7.962E+09 2.240E+11

TC-99 /AGR 9.548E+09 1.933E+10 2.960E+10 7.600E+08 3.636E+11 9.720E+09 9.008E+11

TC-99 /F00 6.560E+03 1.635E+04 2.433E+04 0. 3.061E+05 2.067E+03 7.933E+05

TC-99 /DCM 0. 0. 0. 0. 0. 0. 0.

TC-99 /WWT 4.186E+05 1.042E406 1.551E+06 2.083E+00 1.951E+07 1.318E+05 5.069E+07

TC-997/SWT 4.24CE+05 1.056E+06 1.571E+06 2.083E+00 1.976E+07 1.335E+05 5.135E+07

TC-99 /AIR 8.-548E+09 1.933E+10 2.960E+10 7.600E+08 3.636E+11 9.721E+09 9.008E+11

1-129 4.08CE-08 '1.150E-01 2.000E+00. 5.OOOE+00

1-129 /ACC,9.139E+11 8.515E+11 8.515E+11 5.128E+13 8.515E+11 8.572E+11 8.521E+11

1-129 /CON 2.068E+12 7.124E+11 6.123E+11 1.624E+15 1.315E+12 6.366E+09 9.787E+10

1-129 /ACR 8.346E+12 2.942E+12 2.528E+12 6.S53E+15 5.433E+12 6.366E+09 4.006E+11

1-129 /FOO 6.019E+04 2.137E404 1.836E+04'4.725E+07.3.947E+04 0. 2.901E+03

1-129 /DCM 1.9202E+04 1.920E+04 1.920E+04 1.920E+04 1:920E+04 1.920E+04 1.920E+04

1-129 /WWT,4.289E+07 1.75EE+07 1.562E+07 3.081E+10 2.938E+07 3.644E+06 5.536EtO6

1-129 /SWT.4.389E+07 1.793E+07 1.592E+07 3.160E+10.3.004E+07 3.644E+06 5.584E+06

1-129 /AIR 9.197E+12 3.792E+12 3.379E+12 6.554E+15 6.284E+12 8.572E+11 1.251E+12

CS-135 2.310E-07 1.620E-04 8.5002E01 7.200E+02,

CS-135/ACC 2.371E+10 9.651E+10 8.851E+10 5.080E+08 3.331E+10 1.491E+10 1.004E+09

CS-135/CON 1.566E+11 4.209E+11 3.879E+11 5.030E+08 1.466E+11 4.884E+10 8.007E+09

CS-135/AGR,5.729E+11 1.439E+12 1.326E+12 5.080E+08 5.014E+11 1.551E+11 2.994E+10

CS-13S/FOO 8.836E+03 2.157E+04 1.991E+04 0. 7.531E+03 2.256E+03 4.656E+02

CS-135/DCM 0 . 0. o 0. 0. 0. , 0.

CS-133/WWT 3.316E+07 8.09eE+07 7. 475E+07 1.392E+00. 2.828E+07 8.472E+06 1.748E+06

CS-133/SWT 1.442E+08.3.520E+08 3.250E+08 1.392E+00 1.229E+08 3.683E+07 7.600E+06

CS-135/AIR 5.729E+11 1.437E+12,1.326E+12 5.08CE+08 5.014E+11 1.551E+11 2.994E+10

CS-137 2.310E-02 1;620E-04 8.500E+01 7.200E+02

CS-137/ACC 4.499E+11 6.339E+11 7.779E+11,2.419E+11,4.259E+11-3.299E+l 2.444E+11

CS-137/CON 1.397E+12 1. 7192+12 2.351E+12 1.530E+09 8.010E+11 2.941E+11 3.919E+10

CS-137/AGR S. 117E212 5.872E+12 3.030E+12 1.530E+092.;729E+12 9.350E+11 1.491E+11

CS-137/F0O 7. 896E204 8.814E+04 1.205E+05 0. 4.092E+04 .1.360E+04 2.333E+03

CS-137/DGM 3.500E+06 3.500E+06 3.500E+06 3. 00E+06 3.500E+06 3.500E+06 3.500E+06

CS-137/WWT 3.094E+08 3.438E+05 4.655E+08 1.287E+07 1.665E+08 6.394E+07 2. 1632+07

CS-137/SWT 1.302E+09 1.452E+09 1.981E+09 1.287E+07 6.80HE+08 2.349E+08 5.096E+07

CS-137/AIR 5.358E+12 6.112E+12*8.270E+12 2.419E+11 '2.969E+12 1. 175E+12 3.895E+11

U-235 9.760E-10 1.250E-04 8.400E+02,7.20CE+03.

U-23S /ACC 2.062E+12 3.062E+13 2.214E+11 2.214E+11. 7.262E+12 3.360E+15 5.175E+11

U-235 ICON 2;643E+12 4.361E+13 1.590E+09 1.590E+09' 1.013E+13 3.360E+15 1.586E+12

U-235 /AGR 3.154E+12 8.500E+13 1. 590E+09 1.590E+09 1.979E+13 3.360E+15 5.621E+12

U-23S /FOO 1.443E+04 2.378E+05 .,; 0. 0. -5.552E404 0., 2.319E+04

U-235 /DCG 1.500E+05 1.500E+05 1.500E+05 1.500E+05 1.500E+05 1.500E+05 1.500E+05

U-23S /WWT 2.073E+08 3.235E+09 1.177E+07 1.177E+07 7.643E+08 2.098E+07 3.261E+08

U-235 /SWT 2.109E+08 3.294E+09.1.177E+07 1.177E+07 7.781E+05 2.098E+07 3.318E+08

U-235 /AIR S.374E+12 8.522E+13 2.214E+11 2.214E+11 2.001E+13 3.360E+15 5.841E+12

U-238 1.540E-10 1.2502-04 8.400E+02 7.200E+03. -

U-238 /ACC 1.695E+12 2.882E+13 1.454E+10 1.454E+10 6.575E+12 3.120E+15 2.546E+11

U-238 ICON 2.429E+12 4.145E+13 8. 570E+07 8.570E+07 9.447E+12 3.120E+15 1.147E+12

U-238 /AGR 4.774E+12 8.108E+13 8.570E+07 8.570E+07 1.849E+13 3.120E+15 3.989E+12

U-238 /FOO 1.348E+04 2.277E+05 O. 0. 5.196E+04. 0. 1.633E+04

U-238 /DCM 5.160E+03 5.160E+03 5.160E+03 5. 1602+03 5.1602+03 5.160E+03 5.160E+03

U-238 /WWT, 1.835E+08 3.087E+09 7.739E+05 7.739E+03 7.050E+08 9.325E+06 2.221E+08

U-238 /SUT-1.86862+08 3.144E209 7.739E+05 7 739E+05 7.179E+08 9.325E+06 2.262E+08

U-238 /AIR 4.789E+12 8.109E+13 1.454E+10 1.454E+10 1.850E+13 3.120E+15 4.003E+12

NP-237 3.240E-07 4.670E-04 3 000E+02 2.500E+03

NP-237/ACC 5.202E+14 1.200E+16 1.120E+15 1.340E+11 3.840E+1S 3.602E+14 3.740E+11

NP-237/CON 5.209E+14 1.202E+16 1.122E+15 8.400E+08 3.847E+15 3.600E+14 1.550E+12

D-88
INIFIL File (cont'd)

NP-237/ACR 5.238E+14 1.209E+16 1.12BE+15 8.400E+08 3.868E+15 3.600E+14 5.652E+12

NP-237/FDO 1.645E+04 4.067E+05'3.533E+04 0. 1. 223E405 0. : 2..357E+04

NP-237/DCO 6.560E+04 6.-560E+04 6 560E+04 6.560E+04 6.560E+04 6' 560E+04 6.560E+04

NP-237/WWT 2.312E+08 5.546E+O094:8850E+8 7.126E+06 1.674E+09 8.:113E+06 3.263E+06

NP-237/SWT 2.572E+08 6.189+09' 5.-443E+08 7. 126E206 1.867E+09.8. 113E+06 3.635E+08

NP-237/AIR Z.239E+14 1.209E+16 1.-128E+15 1.'340E+11 3.868E+I5:3..602E+14 5.785E+12

- - PU-238 -6. 020E-03 4.670E-04E.'400E+027.200E+03':,

PU-238/ACC 2.000E+14 4.080E+15 2.800E+15 1.-924E+10 8.'801E+14 4.060E+15 3.313E+11

PU-238/CON 2.003E+14 4.091E+152.802E+15 8.870E+07 E.812E+14 4.'080E+15 1.514E+12

P,- PU-238/AR 2.012E+14'4.126E+15' 2.807E+15 8.87CE+07 8.850E+14 4:'080E+15 5.277E+12

PU-238/FOO 1.137E+03 4.522E+04 6.371E+03' 0. 4.866E403, O.' 4.E55E+03

PL:, -238/DQM 1. 930E+01 1.930E+S01 l.930E+01 1.930E+01 1.930E401 1.930E+01 1.930E+01

PU-238/WWT 7.019E+07 2.741E+09.3.931E.08 1.025E+06 2.972E+08 1.221E+07 2.940E+.0

PU-238/SWT7.485E+07 2.9262E+094.192E+08 1.7025E+06 3.171E+08 1 221E+07 3.139E+08

PV-238/AIR 2.012E+14 4.126E+15 2.807E+15 1.924E+10 8.850E+14 4.080E+15 5.297E+12

PU-239 2.84CE-O5 4.670E-04 8.400E+02 7.200E+03 -

PU-239/ACC 2.240E+14 4.800E+15 3. 120E+15 7.400E+09 9.601E+14 3.8402+15 3.034E+11

PU-239/CON 2.243E+14 4.813E+15,3.122E+15 5.170E+07 9.613E+14 3.840E+15 1.392E+12

PU-23?/AGR 2.253E+14 4.854E+15 3.-127E+15 5. 170E+07 9.655E+14-3.-840E+15 4.826E+12

PU-239 FOO 1.270E+03 5.234E404'7.049E+03 0. 5.393E+03 ,0. 4.429E+03

PU-239/DGM 9.390E+01 9.390E+01 9.390E+01 9.390E+01 9.390E+01 9.,390E+01 9.390E+01

PU-239/WWT 7.765E+07 3.172E409 4.343E+08 3.934E+05 3.285E408 1.092E+07 2.676E+08

;PU-239/SWT,8.286E+07 3.386E+09 4:632E+08 3.934E+05,3.506E+08 1.092E+07 2.858E+08

PU-239/AIR 2.253E+14 4.854E+15 3.127E+15 7.400E+09 9.656E+14.3.840E+15 4.833E+12

PU-241 5.250E-02 4.670E-04 8.400E202 7.200E+03:

PU-241/ACC 3.040E+12 7.440E+13 4.560E+13 4.7BOE+07 1.440E+13 6.600E+12 5.568E+09

,PU-241/CON 3.046E+12 7.467E+13 4.561E+13 4.780E+07 1.443E+13 6.600E+12 2.861E+10

,-PU-241/AGR 3.'063E+12 7.552E+13,4.566E+13 4.780E+07 1.450E+13 6.600E+12 1.008E+11

*.PU-241/FOO 2.202E+01 1;097E+03 5.613E201 O 0 1.017E+02 0. 9.310E+01

- PU-241/DGM,3.430E-01 3.430E-01 3.430E-01,3.430E-01 3.430E-01 3.430E-01 3.430E-01

, ,PU-241/WWT 1.341E+06 6.642E+07.3.512E206 1.310E-01 6. 179E+06 1. 864E+04 5.618E+06

PU-241/SWT 1.431E+06 7.091E407 3.742E+06 1.310E-01 6.596E+06 1:864E+04 5.999E+06

P1-241/AIR,3.063E+12 7.553E+13 4.566E+13 4.780E+07 1.450E+13 6:800E+12 1.008E+11

PU-242 2.480E-06 4.670E-04 8.400E+02 7.200E+03

PU-242/ACC 2.160E+14 4.480E+15 3.040E+15 1.441E+10 9.601E+14 3.680E+15 2.944E+11

-PU-242/CON 2.163E+14'4.492E+15 3.042E+15 6.930E+07 9.613E+14 3.680E+15 1.355E+12

PU-242/AOR.2.173E+14 4.530E+15,3.047E+15 6.930E+07 9.653E+14 3.680E+15 4.722E+12

PU-242/FOO 1.224E+03 4.84eE+04 6.783E+03 0. 5.'194E+03. 0.. 4.343E+03

PU-242/DCM 0. . 0. O0. 0.. - ° . 0. 0-

, PU-242/WWT 7.520E+07 2.932E409 4.184E+08 7.674E+05 3.'168E+08 1.085E+07 2.628E+06

; PU-242/SWT 8.021E+07 3.137E409 4.462E+08 7.674E+05 3.381E+08,1.085E+07 2.806E+08

PU-242/AIR 2.173E+14 4.530E+15 3.047E+15 1.441E+10 9.654E+14 3.680E+15 4.736E+12

AM-241 1.510E-03 4.'110E-03 3. 000E+02 2.500E+03

AM-241/ACC 5.041E+14 7.120E+15 6.640E+15 7.869E+.10 3.840E+15 4.241E+14 3.587E+11

-,AM-241/CON 5.049E+14;7.134E+15 6.645E+15 3.800E+08 3.847E+15,4.240E+14 1.S508E+12

AAM-241/AGR 5. 077E+14,7.176E+15 6.660E+15 3.800E+08 3. 8682E15 4. 240E+14 5.355E+12

AM-241/FOD 3.599E+04 5.44eE405 1.916E+05 0; 2.707E+05 O. 4.936E+04

AP-241/DGK 7.710E+04 7.710E+04 7.710E+04 7.71CE+04 7.710E+04 7.710E+04 7.710E+04

AM-241/WWT 2.247E+08 3.340E409 1. 189E+09 4.192E+06 1;663E+09 5.354E+06 3.047E+08

AM-241/SWT 3.721E+08 5.'572E+09 1.974E+09 4.192E+06 2.772E+09 5.354E+06 5.069E+08

AM-241/AIR 5.078E+14 7.176E+15 6.660E+15 7.869E+10 3.868E+15 4.,241E+14 5.434E+12

AM-243 8.72CE-05 4.110E-03 3. 000E+02 2.500E+03

AM-243/ACC 4.961E+14 7.040E+15 6 480E+15 9.096E+10 3.760E+15 4.001E+14 3.630E+11

AM-243/CON 4.969E+14 7.054E+15 6.485E+15 6.090E+08 3.767E+15 4.000E+14 1.713E+12

AM-243/AGR 4.996E214 7.096E+15 6;.499E+15 6.090E+08 3.787E+15 4.000E+14 6.223E+12

-, AM-243/FOO 3.525E+04 5.441E205 1.849E+05 0. . 2.654E+05.. O. 5.787E+04

AM-243/DGM 1.860E+05 1.860E+05 1.860E+05 1.860E+05 1.860E+05 1.860E+05 1.860E+05

,AM-243/WWT 2.208E+08 3.337E209 1. 148E+09 4.837E+06 1.6312E09,5.933E+06 3.572E+08

A1-243/SWT 3.653E+08 5.566E409 .1.906E+09 4.E37E+06 2.7182409 5.9332+06 5.9422+08

AM-243/AIR 4.997E+14 7.096E+15 6.499E+15 9.096E410 3.,788E+15'4.,001E+14 6.313E+12

CM-243 2.'170E-02 4.670E-04 3.000E+02 2.500E+03

CM-243/ACC 3.843E+14 6.161E+15 5.601E+15 2.444E+11 1.760E+15 4.403E+14 5.464E+11

CM-243/CON 3.846E+14 6.171E+15 5.604E+15 2.260E+09 1.763E+15 4. 400E+14 1.594E+12

D-89
ULMILINIFIL File (cont'd)

CM-243/ACR,3.866E+14 6.204E+15 5.616E+15 2.260E+09 1.772E+15 4.400E+14

CM-243/FOO.1.113E+04 1.897E+057.155E+04 O.. 5.195E+04- 0.

CM-243/DGM 3.820E+09 3.820E+05 3;820E+05 3.820E+05 3.'820E+05 3.820E+05

CM-243/WWT 1.647E+08 2.59EE+09 9.-970E+08 1.296E+07 7.212E+08 1. 417E+07

CM-243/SWT,2.087E+08 3.347E409 1.280E+09 1.296E+07+9.264E208 1.417E+07

CH-243/AIR 3.868E+14 6.204E+15,5.617E+15 2.444E+11 1.772E+15 4.403E+14

Cn-244,, , 3.940E-02 4.670E-04 3;000E+02 2.500E+03

CM-244/ACC 2.800E+14 4.400E+15 4.160E+15 1.706E+10 1.280E219 4.400E+14

CI-244/CON 2.805E+14 4.40oE+15 4..163E+15 7.Z230E+07 1. 282E+15 4.400E+14

CM-244/AOR 2.820E+14 4. 433E+15 4.'174E+15 7.230E+07 1.289E+15 4.400E+14

CM-244/FOO 8.520E+03 1.434E+05 6:145E+04, 0; 3.978E+04 0.

CM-241/DGM 5.640E+01 5.640E+Oi,5.640E+01 5.640E+01 5.640E+01 5.640E+01

CM-244/WWT I.17CE+08, 1;954E+09 8.443E+08 9.093E+05 5. 430E+08. 2.115E+06

CM-244/SWT 1.507E+08 2.521E+09 l.'087E+09 9.0932+05 7.001E+08 2.115E+06

CM-244/AIR 2.820E+14 4.433E+15 4.174E+15 1.706E+10 1.289E+1 '4.4002+14

P9-210 3.398E-02 4.110E-03 8:400E+02 7.200E+03

PB-210/ACC 8. 039E+12 2.561E+14 6.564E+13 3.836E+10 2080E+14 1.040E+14

P9-210/CON 1.699E+13 5.0&EE+14 1.378E+14 3.510E+08 4.112E+14 1.040E+14

PB-210/ACR 4.514E+13 1.300E+15 3.639E+14 3.510E+08 1.048E+15 1.040E+14

PB-210/FOO 2.584E+05 7.268E+06 2.076E+06 O.COCE+00 5.843E+06 O.OOOE+00

PB-210/0W 6. 502+05 6.558C+05 6. 580E+05 6.58CE+05-6.580E+05 6.580E+05

PB-210/WWT 2.194E+09 6.164E+10 1.761E+10 2.035E+06 4.955E+10 2.320E+06

PB-210/SWT 2.6232+09 7.372E+10 2.106E+10 2.035E+06 5.927E+10 2.320E206

PB-210/ATR 4.S18E+13 1.301E+15 3.640E+14 3.836E+10 1.048E+15 1.040E+14

AC-227, 3.209E-02 4.110E-03 3.000E+02 2.500E+02

AC-227/ACC 3.600E+14 5.680E+15 8.000E+14 1.004E+09 2.56CE+14 2.160E+16

AC-227/CON 3.618E+14 5.711E+15 8.041E+14 1.190E+08 2.573E214 2.160E+16

AC-227/AGR 3.676E214 5.807E+15 8.169E+14 1.190E+08 2.61SE+14 2.160E+16

AC-227/F00 3.296E+04 5.552E+05 7.363E+04 O.OOOE+00 2..375E+04 O.OOOE+00

AC-227/DGM 1.390E+07 1.390E+07 1.390E+07 1.390E+07 1.390E+07 1.390E+07

AC-227/WWT 4.477E+08 7.541E+09 l.OOOE+09 4.740E+04 3.227E+08 5.925E+07

AC-227/SWT 4.559E+08 7.679E409 1.019E+09 4.'740E+04 3.286E208 5.925E+07

AC-227/AIR 3.676E+14 5.s80E+15 8.169E+14 1.004E+09 2.615E+14 2.160E+16

RA-226 4.327E-04 4.110E-03 3.000E+01 2.500E+02

RA-226/ACC 1.520E+15 2.160E+15 8.944E+09 8.944E+09 8.944E+09,8.000E+14

RA-226/CON 1.654E+15 2.527E+15 5.008E+12 5.008E+12 5.008E+12:. OOOE+14

RA-226/AGR 2.072E+15 3.678E+15 2.069E+13'2.069E+13 2.069E+13 8.0012+14

RA-226/FOO 1.330E+07 3.6582+07 4.988E+05 4.988E+05 4.988E+05 2.926E+03

RA-226/DGr 2.940E+07 2.940E+07 2.940E+07 2. 940E+07 2.940E+07 2.940E+07

RA-226/WWT 3.256E+10.8.952E+10 1.221E+09 1.221E+09 1.221E+09 9.828E+06

RA-226/SWT 3.732E+10 1.026E+11 1.400E+09 1.400E+09 1.400E+09 1.098E+07

RA-226/AIR 2.072E+15 3.67&E+15 2.070E+13 2.070E+13 2.070E+13 8.002E+14

TH-228 3.629E-01 4.110E-03 8.400E+02 7.200E+03

TH-228/ACC 2.402E+13 7.121E+14 1.202E+13 1.797E+10 6.802E+13 1.440E+16

TH-228/CON 2.428E+13 7.202E+14 1.214E+13 1. 980E+08 6.877E+13 l.440E+16

TH-228/AGR 2.515E+13 7.459E+14 1.257E+13 1.980E+08' 7.119E+13 1.440E+16

TH-228/FO0 8.379E+03 2.474E+05 4.190E+03 O.OOOE+00 2.329E+04 O.OOOE+00

TH-228/DGM,2.220E+07 2. 22CE+07 2.220E+07 2.220E+07 2.220E+07 2.220E+07

TH-228/WWT 6.865E+07 2.000E+09 3. 480+E07 9.512E+05 1. 891E+08 4.042E+07

TH-228/SWT-18.053E+07 2.350E+09 4. 074E+07 9.512E+05 2.222E+03 4.042E+07

TH-228/AIR 2.517E+13 7.459E+14 1.259E+13 1.797E+10 7.121E+13 1.4402+16

RA-228 1.035E-01 4.110E-03 3.000E+01 2.500E+02

RA-228/ACC 6.880E+14 6.480E+14 1.140E+08 1.140E+08 1.140E+08 8.800E+15

RA-278/CON 7.598E+14 8.316E+14 6.511E+12 6.67eE+12 6.511E+12 8.OOE+15

RA-228/AGR 9.846E+14 1.407E+15 2.690E+13 2.759E+13 2.690E+13.8.800E+15

RA-228/FOO 7.149E+06 1.829E+07 6.484E+05 6.651E+05 6.484E+05 4.007E+03

RA-278/DGM 5.000E+06 5.00OE406 5.000E+06 5.COCE+06 5.OOOE+06 5.OOOE+06

RA-228/WWT 1.750E+10 4.476E+10 1.597E+09 1.628E+09 1.587E209.3.392E+07

RA-228/SWT 2.006E+10 5.130E+10 1.819E+09 1.866E+09 1.819E+09 3. 536E+07

RA-278/AIR 9.847E+14 1.407E+15 2.690e+13 2.759E+13 2.690E+13 8. 801E+15

TH-229 9.443E-05 4.110E-03 8.400E+02 7.200E+03

TH-229/ACC 1.360E+15. 2.800E+16 4.243E+14 2.548E+11 2.080E+15 2.000E+16

TH-229/CON 1.366E+15 2.813F+16 4.260E+14 1.790E+09 2.090E+15 2.000E+16

5. 629E+12

2. 319E+04

3. 820E+03

3.269E+08

4. 184E+08

5. 871E+12

3. 031E+11

1. 533E+12

5. 434E+12

2. 241E+04

5. 640E+01

3. 044E+08

3. 99E29208

5. 451E+12

4. 716E+10

9. 045E+11

3.709E+12'

2. 575E+04

6. 580E+05

2. 204E+08

2. 632E+08

3. 747E212

1. 140E+10

1. 361E+12

3. 593E+12

2. 432E+04

1. 390E+07

3. 296E+08

3. 357E+08

5. 594E+12

1.770E+ 11

4. 241E+12

1. 700E+13

4. 037E+05

2. 940E+07

9. 933E+08

1. 138E+09

1. 701E+13

2.980E+11

9.583E+12

3. 872E+13

2. 808E+05

2. 220E+07

2. 267E+09

2. 666E+09

3. 874E+13

1. 874E+09

1. 688E+12

6. 969E+12

1. 679E+OU

5. OOOE+06

4. 110E+08

4. 711E+08

6. 969E+12

2.495E+12

1. 070E 13

D-90
7 1 7vr * , 7

1 INFIL File (cont'd)

TH-29/AGR 1. 2.E+15 7 2.854E+16 4.321E+14 1.79CE+09 2.1192+15 2.000E+16 3.720E+13

.TH-229/FD0 .. 950E+05 3. 930E+06 5. 935E+04 O669E05 0. 0402+00 2. 0. OO2E+00 2. 554E+05

s TT-2290 1.5E0 14502+07 1. 450E+ 1T450++077 l'450E+07.,l. 450E+07 1. 450+07E+1. 4502+07

'TH-229/WWT 1. 591E+09 3.222E+108 1.935E+08' 7 2.334E+096.836E+372.0752.0 0

T-229/SWT.1.8692+09 3:7863+10 5. 779S+08 3435 4E+07 2.741E+0 68.37E+07 9. 

TH-229AIR 1 1.377E+15 2.2.55E+16-4.324E+14 2..548E+11-2.0120l+15 2.0E+16, 3.745+13

TH-230 6. 664E-06 I 6 4. 1 8. OE-03 ..400E+02 7. 200E+03 .

TH-23O/ACC 5. 360E+14.E+1760E+16.1. 120;+15E1:435E+10 5.2 280E+15.3. 520E+14 2.464E+ 11

TH-236/CON.5.+369E+14 1 763+16 1.122E+15 1.300E+08 5.289E+15 3.520E+14 1.227+12

TH-230/AR 55.399E+14 1.774E+16 1.12aE+15 1.300E+08E5.319E+15,3.520E+1 4.34 4 2E+12

TH-230/F0 2. 6432+04 1.027E3+065. 835E+04.0.'0E000E+O02:818E+05 . 0002+00 3.0032.04

TH-230/DM 2.21303+03 2.2130+03 2.2130+03 2.2130203 2313032.0302.130E+03 2.2130003

TH-230/WWT 2.317E+08 8. 342E+09. 4.749E+08 7.610E+05 2.2 2900+09 1.7262+06 2.431E23+

TH-230/SWT. 2.720E+08 9 .799E+09 5.576E+08 7.610E+ 05 2 689E+09. 1.726+06 2.857E+08

TH-230/AR 5.5399E+14 1.774E+16 1. 1285+15.4 1.4352+1095.319E+1 3.520E+14 4.357E+ 12

PAP231 , 2. 133E-05 E 4.110E-003 400E+02 7.0 2003+03 3 1

'PA-231/ACC 5.601E+14,1.360E+16 5.441E+14 1.097E+11 3.040E+1S S .120E+15 4.217E+ll

aA-231ICON 5.626++14.61.367E+16 5.465E+14 6.5590E+08,3.0548+155. 120E+15 1.495E+1 2

PA-231/AR 5.7057.14 1.3854E+ 16 5.545E+14 6.590E+08 3.099E5 5.120E12+15 5.200S012

PA-231/FO0 4.721E+04 1 .217 E+06 4.572E+04 O.OOOE+ 00 2.565E+05 0.00+ E+00 2.129E+04

PA-P231 /D4 M 4.,560E+05' 4. 560E+05'45602+05 4.450 E+05 4.4560+05 4.E560+05 4.560E+05

PA-231/WWT 6.6472E+08-1.654E+10 .7270E+08.5.E836+06 3..491E09 1.987E+07 2.944E+08

PA-231/SWT 6.589E+08 1;684E+10 6.384E+08 5.836E+06 3.555E+09 1.9672+07 2.997E+08

PA-231/AIR 5.9710+14 1.388E+16 5.546E+1 4 1.097E+11 3.099E +15 5.120E+15 5.309E+12

TH-232 - 4.916E-11 4.11CE-03 8 .400E+02 7.2002.03 . -

TH-w2 2/ACC 2.560E+14 7.440,415 3.520E+14 1.384E+10 1 1;60E+15 4.720+15 2.379E+11

TH-T232/CN 2.2585E+14 7.7478E+15 3.5537E+14 1..0E+ E08 1.6865+15'.4.720E+15 1.070E+12

TH-232/AGR 2.662E+14 7.5972+15 3.5S8E +14 1.0O0E+08 1.713E+15 4.7202+15 .3.720E+12

TH-232/FOO 7.471241 +0 4 1.147E+06 4.98 204 O.00000 2.404E+05 0.000E+00 2.554E204

H-232/DG1 4.492092 +04 4.920E 404 4..920E+04 4.920E+04 4.920E+04, 4.9202+04 4.920E+04

TH-232/WWT 6.053E+09 9.221E+09 4.0432+06 7.3522.05 1.,946E+09 1.3672+07 2.0692.09

TH-232/SWT 7.1142+08 1.091E+10 4.750E+08 7.352E+05 2.2977+09 1.367E+07 2.4312+08

TH-232/AIR 2.663E+14 7.597E+15 3.589E+14 1.384E+10 1.713E+15 4.4720E15 3.734E+12

U-233 4.4279E-06 1.250E-04 6.400E+02 7.2002403

JJ233 /ACC 22.011E 2123.281E+13 1.077E +10 1.077E+107.691E +12 3.680E +15 2.9020 +11

U-233 /CON 2.871E+12'1r717E+13 5.1602+07 5.16CE+07 1.103E+13 3.680E+15 1.314E+12

U-233 /AGR 5.599E+ 12 9.217E+13 5.160E+07 5.126CE+07 2.152E+13 3.680E+15 4.5542.12

U-23 3 /FOO 1. 56eE+04 2.586E+05 .OOOE+OO+00 0.OOOE+00 6.027E+04 .OOOOO200 1.862E+04

U-233 -/DM 4.1 6CE+06 4.160E+ 06 4.1602+06 4.160E+06 4.160E+06 4.160E+06 4.160E+06

U-233 WWT 2.131E+08 3..6506E409 5.'739E+05 5.7392405 8.175E+08 1.066E+07 2.529E+08

U-233 /SWT 2.117CE+08 3. 570E+09 5.739E+05 5.739E+05 8.'325E+08 1.066E+07 2.575E+08

U-233 /AIR 5.610E+12 9.218E+13 1.077E+10 1.077E+10 2.153E+13 3.680E+15 4.564E+12

U-234 . 2.806E-06 1.2502-04 8.400E+02 7. 200E+03

U-234 /ACC 1.938E+12 3.122E+13 1.'746E+10 1.746E+10 7.538E+12 3.600E+15 2.895E+11

U-234 /CON 2.773E+12 4.495E+13 1.140E+09 1.140E+08 1.080E+13 3.600E+15 1.285E+12

U-234 /AGR 5.444E+12 8.612E+13 1.140E+08 1.140E+08 2.108E+13 3.600E+154.457E+12

U-234 /FOO 1.535E+04 2.492E+05 OOOOE+0 00 0.000E+00 5.908E+04 O.O000E+O0 1.23E+04

U-234 /DOM 3.980E+05 3.980E+05 3..980E+05 3.980E+05 3.-980E+ 05 3.980E+05 3.980E+05

U-234 1WWT 2. 090E+08 3.365E+09 9.286E+05 9.286E+05 8.018E+08 1.080E+07 2.480E+08

U-234 /SWT.2.128E+08 3.427E+09 9;286E+05 9.286E+05 8.164E+08 1.080E+07 2.525E+08

U-234 /AIR 5.461E+12 8.820E+13 1.746E+10 1.746E+10 2.-11CE+13 3.600E+15 4.474E+12

U-236 2.900E-08 1.250E-04 8.400E+02 7.200E+03

U-236 /ACC 1.857E+12 3.042E+13 1.648E+10 1.648E+10 7.297E+12 3.440E+15 2.725E+11

U-236 ICON 2.658E+12 4.361E+ 13 9.670E+07 9.670E+07 1.043E+13 3.440E+15 1.206E+12

U-236 /AOR 5.221E+12 8.500E+13 9:670E+07 9.670E+07 2.030E+13 3.440E+15 4.182E+12

U-236 /FOO 1.473E+04 2.37E2+05 O.OOOE+00 O.OOOE+00 5;671E+04 O.OOOE+00 1.710E+04

U-236 /DOM 5. 560E+04 5.560E404 5.560E+04 5.560E+04 5.-560E+04 5.560E+04 5.560E+04

U-236 /WWT 2,005E+08 3.224E+09 8.-770E+05 8.770E+05 7.695E+08 1.031E+07 2.327E+08

U-236 /SWT 2.041E+08 3.-283E+09 8.'770E+05 8.77CE+05 7.836E+08 1.031E+07 2.369E+08

U-236 /AIR 5.237E+12 8.501E+13 1.648E+10 1.648E+10 2.032E+13 3.440E+15 4.198E+12

PU-240 . 1.053E-04 4.670E-04 8.400E+02 7.200E+03

PU-24OACC 2.240E+14 4.8OOE+15 3.120E+15 7.400E+09 9.601E+14 3.840E+15 3.034E+11

PU-240/CON 2.243E+14 4.813E+15 3.122E+15 5.170E+07 9.613E+14 3.840E+15 1.392E+12

D- 91
I 11U3L

IN1FIL File (cont'd)

PU-240/AGR 2.253E+14 4. 854E+lS.3. 127E+15.5. 170E+07,9. 655E+14.3. 840E+15' 4.826E+12

PU-240/FOO, 1.270E-03 5.234E+04 7. 049E+03, 0; 5. 393E+03 . O. 4.429E+03

PU-240/DGM 9.390E+01.9.390E+01 9.390E+01 9.390E+01 9.390E+01 9.390E+01 9. 390E+01

PU-240/WWT.. 7. 765E+07, 3. 172E+09 4. 343E+08 3. 934E+3053 285E+08.1. 092E+07;2. 676E+06

PUJ-240/SWT 8. 286E+07 3.386E+09 4.632E+08 3: 934E+05 3. 506E+08 1. 092E+07 2.858E+08

PU-240/AIR 2.2S3E+14 4.854E+15,3.127E+1S.7.400E+09,9.656E+14 3.840E+15 4.833E+12

REGION 1 9.180E-12 2;,960E-11, 1. 970E-04'4. 930E-05 7.70CE+03 2.OOOE+05 4.S00E+06

2. 000E+025. SOOOE+03' 1. 000E+04, 4. 000E+02:1. 000E+04,2. 000E+04

.1.000E+00 1.000E40O-1.000E+00 l.OlOE-09.1.SlOE-09 1.120E-07 3

4;000E+02 8.000E+02 1.830E-10 2.610E-12.

REGION 2 2.010E-ll 3;'180E-11 1.160E-03 3.24CE-0,7;700E+03 2.0OOE+0 4.500E+06

4.200E+01 4.000E+02 8.0C0E+02 1.300E+03' 1.000E+04 2.000E+04

2.000E+001.000E+00 1.000E+00,3.:00E-10 5. 250E-10 1.120E-07 3

6.400E+01 1.600E+03 1.830E-10' 3.323E,12'

REGION 3 2.510E-11.3.280E-11 9.000E-05 2.250E-057.770E+03 2.000E+05.4.500E+06

1.400E+02 2.900E403 5.800E+03.4.'000E+02 1.250E+04 2.500E+04, -1.000E+00 1.OOOE+00 1.000E+00 3.e60E-10 5.790E-10 1.120E-07 4

1:600E+02 6.000E402 1.830E-10 2.550E-12

REGION 4 2. 640E-10 8. 060E-11 1.300E-06 3.250E-07 7.700E+03 2.000E+05 4.500E+06

1.500E+01 3.000E+02 6.000E+02 1.300E+03'3.000E+04 6.000E+04

1.000E+00 1.000E+00.000E+00 2.660E-11 3.990E-11 1.120E-07 2

8.000E+00 8.000E+02 1.830E-10 1.'790E-12.

REGICNS 2.010E-11 3.180E-11-1.160E-04 3.240E-06 7.700E+03 2.000E+05 4.500E+06

3.200E+01,3;900E+02 7.9COE+02 1.300E+03 1. OOO+04 2.000E+04

OOOE+00' 100024E+00 1.000E+00 3.500E-10 5.250E-10 1.120E-07. 2

6.'400E+00 1.600E403 1.930E-10 3.3232-12.

REGION 6 2.010E-11 3.180E-11 1.160E-02 3.240E-04 7.700E+03 2.000E+05 4.500E+06

9.200E+01 4.500E402 8.500E+02 1.300E+03 1.000E+04 2.000E+04

1.000E+00 1.OOOE+00 1.OOOE+00 3.500E-10 5.250E-10 1.1202-07 4

6.400E+01 1.600E+03 1.S30E-10 3.323E-12 ,, REGION 1 6.926E+03 4. 870E404 8.559E+02 4.3S5E+03 Z 099E404 5.786E+04

VOLUMES 4.654E+04 8:489E+04 4.356E+04 5.744E+04 2.724E404 4.719E+04

8.341E+03 4.363E+04 4.363E+04 8.978E+04 8.978E+04 1.519E+04

1. 519E+04 1.563E+04 0. 1.523E+04 1.523E404 1.713E+03

1.731E+03 4.869E+03 4.869E+03 3.169E+04 1.808E404 6.479E+02

7.346E+03 5.196E+03 6.0e6E+02 2.646E+03 5.782E+01 4.1S5E+02

1.316E+03

REGION 2 1.298E+04 9.124E404 1.604E+03 8.159E+03 2.511E+04 6.925E+04

VLOUMES 5.568E+04 1.590E+05 8.162E+04 6.872E+04,b3.260E+04 1.180E+05

2.085E+04 3.096E+04 3.096E+04 1. 796E+04 1. 796E+04 1.013E+04

1.103E+04 3.90E2+04 0. 1.081E+04 1.OE1404 1.229E+03

1.229E+03 3.456E403 3.456E+03 6.339E+03 1.205E404 1.040E+03

1.224E+04 0. 5.739E+02 2.089E+02 4.103E+01 2.949E+02

1:726E+03

REGIQN,3 6.587E+03 4.631E+04 8.140E+02 4.141E+03 2.046E+04 5.643E+04

VOLUMES 4.537E+04 9.,073E+04 4.143E+04 5.600E+04 2.656E+04 0.

0. 3. 6004E04 3.800E+04 3.591E+04 3.591E204 1.519E+04

1.519E+04 0.. 1.406E+04 1.327E+04 1.327E+04 1.506E+03

1. 506E+03 4.241E403 4.241E+03 1.266E+04 1.809E+04 6.224E+02

'8.045E+03 0. 7.043E+02 2.089E+02 5.036E+01 3.619E+02

7.450E+202

REGION 4 8.136E+03 5.720E+04 1.005E+03 5.'115E+03 9.672E+03 2.666E+04

VOLUMES 2.14.E+04 9.972E+04 5.117E+04 2.647E+04 1.256E+04 7.076E+04

1.251E+04 2.81SE404 2.815E+04 3.'591E+04 3.'591E+04 1. 10E+04

1. 103E+04 2.345E+04 1.406E+04 9.829E+03 9.-829E+03 1.117E+03

1.117E+03 3.141E403 3.141E+03 1.268E604 1.205E404 5.774E+03

7.346E+03 0. 5.217E+02 4.178E+02 3.730E+01 2.681E+02

1.366E+03

D-92
or vey' ;--

GW2FIL File

37 231.000 .120 .060 .030 .060 .120 .060

P-IXRESIN 1.OOOE+OO 3.463E 04

1 3.36CE-02 2.660E-03 9. 740E-05 2. 340E-03 2.790E-06 4. 530E-03

1 8.610E-04 E.840E-09 1.940E-04 8.230E-07 2. 440E-06.8.230E-07

1 2.190E-02 4.710E-08 3.710E-07'9.060E-12 2.600E-05 1.820E-05

1 7.940E-04 3. 990E-08 4. 154E-05 1. 260E-06-9. 920E-09 1. 380E-05

P-CONCLIO 2.000E+00-2.435E+05-

2 1.090E-01 3.450E-03 1.270E-04 2.270E-02 2.710E-05 4.400E-02

2 8.360E-03 8.580E-07 2.S520E-04 1.070E-06 3.-160E-06,1.070E-06

2 2.850E-02 6.150E-08 4.840E-07 1.lOE-11 5.120E-05 3.310E-05

2 1.440E-03 7.250E-Oa 7.132E-05 2.020E-06 1. 170E-08 1.920E-05

P-FSLUDGE 3.000E+00 4.279E+03

3 1.060E+00 2.590E-03 9.550E-05 3.100E-01 3.710E-04 6.OOOE-01

3 1.140E-01 1.170E-05 1.E90E-04 8.030E-07 2.370E-06 8.030E-07

3 2.140E-02 1.460E-07 1.150E-06 2.810E-11 4.760E-05 1.550E-04

3 6.750E-03 3.390E-07 4.581E-04 1. 780E-05 3.100E-07 1.770E-04

P-FCARTRG 1.100E-01 2.177E404

4 1.-860E+00 1.150E-03 4.250E-05 5.550E-01 6:600E-04 1.070E+00

4 2.040E-01 2.090E-05 8.400E-05 3.580E-07 1.060E-06 3.580E-07

4 9.540E-03 3.640E-07 2.870E-06 7.020E-11 2.SlOE-04 3.800E-04

4 1.660E-02 8.340E-07 6 414E-04 1.100E-05 1.930E-07 1.lOOE-04

B-IXRESIN 4.00CE+00 7.623E+04

5 4.630E+00 1; 920E-02 1.190E-03 '9.480E-01 9.800E-04 1.590E+00

5 2;150E-02 3.090E-05 3.640E-03 7.650E-05 2.040E-04 7.650E-05

5 2.040E+00 5.330E-08 4.200E-07 1.020E-11 8.340E-05 5.340E-05

5 2.600E-03 1. 170E-07 9.798E-05 1.570E-06.2.700E-08 1.820E-05

B-CQNCLIG 5.-OOOE+00 2.102E+05 -

6 2.87CE-01 6.240E-04 3.890E-05 7.940E-02 8.210E-05 1.330E-01

6 1:800E-03 2.-590E-06 1. 180E-04 2.;500E-06 6.-650E-06 2.500E-06

6 6.650E-02 3.440E-08 2.710E-07 6.610E-12 1.990E-04 9.430E-05 - 6 4.600E-03 2. 060E-07 2.;523E-04 8. 100E-06 2.590E-07 2.050E-04

B-FSLUDCE 6000E+00 1.690E.05

7 5.240E+00 1-260E-02 7.780E-04 1.440E+00 1.490E-03 2.410E+00 - 7 3.250E-02 4.;700E-05 2.370E-03 5.O0E-05 1.330E-04.,5.000E-05

7 1.330E+00 3.320E-07 2.610E-06 6.330E-11 4.-660E-04 2.360E-04

7 l:lSOE-02 5.180E-07 4.868E-04 1.050E-05 2.970E-07 2.240E-04

P-COTRASH 2.1 OOE-01-4T244E2.05

6 2.280E-02 3.040E-04 1.120E-05 5.970E-03 7.:110E-06 1.150E-02

8 2.19CE-03 2.250E-07 2.220E-05 9.'420E-08 2.7eOE-07.9. 420E-08

8 2.510E-03 7.890E-09 6.220E-08 1. 520E-12 5.970E-06 5.530E-06

8 2.41CE-04 1.210E-0 1;089E-05 2.670E-07 2.740E-09 2.610E-06

P-NCTRASH 2.10CE-01 2.17eE+05

9 5.250E-01 6.990Y-03 2.570E-04 i.370E-01 1.640E-04 2.650E-Ox

9 5.050E-02 5.18CE-06 5.110E-04 2.'170E-06 6.410E-06 2.170E-06

9 5.780E-02 1.820E-07 1.430E-06' 3.490E-11 1.380E-04' 1:270E-04

9 5.-550E-03 2.790E-07 2.508E-04 6.150E-06 6.300E-08 6.000E-05

B-COTRASH 2.200E-01 2.086E+05

* 10 2.350E-02 6.750E-05 4 170E-06 6.010E-03 6>210E-06 1.010E-02

10 1.360E-04 1.960E-07 1.270E-05 2.690E-07 7.140E-07 2.680E-07

10 7.140E-03 1.2202-09 9.600E-09 2.350E-13'2.300E-06' 1.160E-06

10-5.630E-05 2.530E-09-2.586E-06 6.520E-08 1.930E-09 1.490E-06

G-NCTRASH 2.200E-01 9.896E+04

11 3.790E+00 1.'090E-02 6.730E-04 9.690E-01 1 000E-03 1.620E+oo

11 2.190E-02 3.160E-05 2.050E-03 4.330E-05 1. 150E-04 4.330E-05

11 1.150E+00 1.970E-07 1.550E-06'3;7802-11 3.710E-04 1.860E-04

11 9.080E-03 4.080E-07 4.172E-04-1l050E-05'3.'120E-07 2.410E-04

F-COTRASH 2.110E-01 2.359E+05

12 5.580E-06 0. 0. 0. 0. 0.

12 0. 0. 0. 0. 0. 0.

12 0. 1. 180E-06 4.400E-06 0. 0. 0.

12 0. 0. . - 0. 0 0. 0.

F-NCTRASH 2.102E-01 4.171E+04'

13 5.330E-06 0. 0. 0 0. 0.

D-93
GW2FIL File (cont'd)

13

13

13

I-COTRASH

14

14

14

14

I+COTRASH

15

1s

15

1s

N-SSTRASH

16

16

16

16

N+SSTRASH

17

17

17

17

N-LOTRASH

18

18

18

18

N+LOTRASH

19

19

19

19

F-PROCESS

20

20

20

20

U-PROCESS

21

21

21

21

I-LOSCNVL

22

22

22

22

I+LOSCNVL

23

23

23

23

I-ASSLIaD

24

24

24

24

I+ARSLroD

25

25

25

25

0.

0.

0.

2. 030E-01

1. 130E-01

0.

4. 560E-03

0.

2.030E-01

1. 130E-O1

0.

4. 560E-03

0. .

2. 060E-01

1. 120E-05

0.

0.

0.

2 06QE-01

1. 120E-05

0.

0.

0.

2. 070E-01

3. 530S-02

0.

1. 420E-03

0.

2.070E-01I

3. 530E-02

0.

1. 420E-03

0. -

3. IIOE-O0

1. 080E-04

0.

0.

0.

3;120E-01

3. 800E-04

0.

0.

0.

3. 030E-01

9. 600E-03

0.

"0.

0.

3. 030E-01

9. 600E-03

0.

0.

0.

3. 030E-01

1. 990E-01

0.

1. 370E-02

0.

3. 030E-01

1. 990E-01

0.

1.370E-02

0.

0.

1. 130E-06

0.

1. 407E205

9. 130E-02

0.

0.

0.

1. 407E+05

9. 130E-02

0.

0.

0.

1. 7962.05

0.

0.

2. 360E-06

0.

1. 796E+05

0.

0.

2. 360E-06

0.

5. 064E+04

2. 850E-02

0.

0.

0.

5. 064E+04

2. 850E-02

0.

0.

0.

7.816;+04

0.

0.

2. 300E-05

0.

2. 8114E04

0.

0.

t. 65CE-05

0.

4. 914E+04

5. 010E-03

0.

0.

0.

4. 914E+04

5. O1OE-03

0.

0.

0.

5. 505E+03

1. 420E-01

0.

0.

0.

5. 585E+03

1. 420E-01

0.

0.

0.

0.

4. 2OOE-06

0.

5. 260E-03

1. 450E-03

0.

4. 820E-06

5. 260E-03

1. 450E-03

0.

4. 820E-06

0.

0.

8. 800E-06

O.

0.

0.

8. 800E-06

0.

1. 640E-03

4. 530E-04

- 0.

1. 510E-06

1. 640E-03

4. 530E-04

0.

1. 510E-06

0.

0.

8. 540E-05

0.

0.

0.

3. 640E-04

0.

2. 510E-04

4. 340E-03

0.

0.

2. 51OE-04

4. 340E-03

0.

0.

8. 160E-03

4. 340E-03

0.

0.

8. 160E-03

4. 340E-03

0.

0.

0.

0.

0.

0.

3. 390E-09

0.

0.

0.

3. 390E-09

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1. 06O0-09

0.

0.

0.

1. 06CE-09

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1. 020E-08

0.

0.

0.

1. 020E-08

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1. 040E-02

0.

0.

0.

1. 040E-02

0.

0.

0.

0.

0.

0.

0.

0. 0.

0. 0.

O. 0.

0: 0.

0. 3. 250E-03

0. 0.

0. 0.

0. 0.

0. 3. 250E-03

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0.- 0.

0. 0.

0. 0.

0. 0.

0. 3. 1202-02

0. 0.

0. 0.

0. 0.

0. 3. 120E-02 O. 0.

0. 0.

0. 0.

D- 94
- - -

GW2FIL File (cont'd)

I-BIOWAST 3.030E-01 1.571E+04

26:2.060E-01.1.75OE-01 1.

26 0. 0. S.

26 8.760E-03 0.

26 0.- 0.

I+BIOWAST 3.030E-01'1.571E+04

--27 2.060E-01 1.750E-01 1.

27 0. 0. B.

- :-27 8.760E-03 0. -. 07 -0.

N-SSWASTE 3.060E-01 6.339E+04

- 2 2. 170E-04 0. :

28 0. 0.

8- 9 0. 4.600E-05 1.

28 0. 0.

N-LOWASTE 3.070E-01 6.027E+04

29 2.110E-02 1.630E-02 9.

29 0. 0. 1.

29 1.040E-03 0.

29 0. 0.

L-UP-RCOMP 4.300E-01 2.887E+03 - 30 4.040E+03 0. 2.

30 2.090E+02 E.190E-03

30 0. 0.

30 0. 0.

L-DECONRS 4.400E-01 3.4922+04

-31 1.560E+02 1.083E-02 6.

31 3.690E+00 1.420E-03 4.

31 3.19E0-01 6.840E-05 5.

-31 3.550OE+01 3.870E-03 1.

N-ISOPROD 4.04CE-01 5.196E403

32 1.500E+01 4.200_-02 4.

32 0. 0. 6.

32 8.730E+00 1.020'-05 3.

.32.7.tO0E-03 9.570E-0 2.

N-HICHACT 4.030E-01 2.605E+03

33 2.100E+02 . 0. 1.

33 1.060E+01 4.470E-04

33 0. 0.

33 0. 0.

N-TRITrUM 4.050E-01 3.461E203

34 2.330E+03 2.330E.03

34 0. 0.

34 0. 0.

* 34 0. 0.

N-SOURCES 4.030E-01 1.865E+02

3- 5.76CE+03 2.090E+03 3.

35 1.050E+01 0. 2.

35 3.540E+03 - 0.

35. 0. - 0. 1.

N-TARCETS-4.030E-01 1. 340E+03

36,e.040E+01 8.040'+01

36 0. 0.

36 0. 0.

36 0. 0.

F-PUDECON 7.OOOE+00 4.663Ei03

37 2.345E-01 0.

37 0. 0.

37 0. 0.

37 2.18EE-01 1.8932-06 1.

P-IXRESIN l.OOOE+00 3.463E+04-

1 3.360E-02 1.840E-03 9.

1 8.150E-04 E.840E-08 1.

.OlOE-02

330E-03

0.

0.

OIOE-02

330E-03

0.

0.

0.

0.

710E-04

0.

360E-04

310E-03

0.

0.

590E-01

0.

0.

0.

880E-04

2BOE-02

400E-04

026E+00

5 10E-05

2702.00

SlOE-OS

152E-04

320E-02

0.

0.

0.

0.

0.

0.

0.

.190E-03

870E+01

0.-. -

600E+01

0.

'.0..-

0.

0.

0. . - O..

0.

559E-03

0. 0.

6.510E-09 0.

0. 0.

0. 0.

0. 0.

6. 510E-09 0.

0. . 0.

0. 0.

0. 0.

0. .- 0.

0. 0.

0. 0.

0. 0.

7.760E-10 0..

0. 0.

0. 0.

2.230E+03 1.400E+00

0. 0.

0. 0.

0. 0.

4.050E+01 4.490E-02

1.200E-05 3.340E-05

1.320E-08 1.340E200

3.590E-04 3.460E-04

0.- - 0.

3.270E-04 2.720E-06-

5.330E-13 1.970E-04

1.250E-06 1.650E-04

1.150E+02 6. 560E-02

0. - 0.

0. 0.

O. 0.

0. 0.

0. _ 0.

0. 0.

0. 0.

0. . 0.

0. - 0.. O

0. .: 0.

0. 0.

0. 0.

O.., - .

0. 0.

0. 0.

0. 0.

0. O.

0. -1. 355E-03

0. 0.

3. 990E-03

0.

0.

0.

3. 9902-03

0.

0.

0.

0.

0.

0.

0.

1. 470E-03

0.

0.

0.

l. 600E+03

0.

0.

0.

7. 280E+01

1. 200E-05

1. 770E+00

3. 270E-03

0.

3. 270E-04

5. 550E-05

2. 680E-07

8. 480E+01

0.

0.

0.

0.

0.

0.

0.

8. 120E+01

0.

0.

0.

0.

0.

0.

0.

0.

0.

1. 260E-02

0.

730E-05 7.30CE-04 2.790E-06 2.170E-03

630E-04 8.230E-07 2.440E-06 8.230E-07

D-95
- I uI' -

GW2FIL File (cont'd)

I 1.860E-02

1 5. 63CE-04

P-CONCLIa 2.000E+00

2 1.09CE-01

2 7.920E-03

2 2.43CE-02

2 1.020E-03

P-FSLUDGE 3.000E+00

3 1.060E+00

3 1.080E-01

3 1.E20E-02

3 4.790E-03

P-FCARTRO 1.lOOE-01

4 i.86CE+00

4 1.930E-01

4 8.120E-03

4 1.160E-02

3-IXRESIN 4.000E+00

5 4.630E+00

5 2.040E-02

5 1.740E+00

5 1.850E-03

B-CONCLIO 5.000Et00

6 2.870E-01

6 1.710E-03

6 5.670E-02

6 3.28CE-03

B-FSLUDCE 6.000E+00

7 5.240E+00

7 3.080E-02

7 1.1302+00

7 8.200E-03

P-COTRASH 2.100E-01

8 2.280E-02

8:2.070E-03

8 2.140E-03

8 1.71CE-04

P-NCTRASH 2.100--01

9 5.250E-01

9 4.780E-02

9 4.920E-02

9 3.930E-03

8-COTRASH 2.200E-01

10 2.3502-02

10 1.290E-04

10 6.090E-03

10 4.010E-05

B-NCTRASH 2.200E-01

11 3.79CE+00

11 2.080E-02

11-9.810E-Ol

11 6.470E-03

F-COTRASH 2. 11CE-01

12 5.58CE-06

12 0.

12 0.

12 0.

F-NCTRASH 2.110E-01

13 5.330E-06

13 0.

13 0.

13 0.

I-COTRASH 2.030E-01

4. 710E-03

3. 990E-08

2.435E+05

2.39CE-03

8.580E-07

6.150c-Oa

7. 202E-Oa

4.279E+03

1.790E-03

1.170E-05

1.460E-07

3.390E-07

2.177E+04

7. 970E-041

2.0!OE-05

3.640E-07

6.340E-07

7.623E+04

1.340--02

3.090E-05

5.33DE-08

1.170E-07

2.102E+05

4. 350-04

2.590E-06

3.440E-08

2.060E-07

1.690E+05

a. 780E-03

4.700E-05

3.320E-07

5.16OE-07

4.244E+05

2.110E-04

2.250E-07

7.890E-09

1. 210-03

2. 17E2-05

4.840E-03

5.180E-06

1.820-07

2.790E-07

2.08SE+05

4.700E-05

1.960E-07

1.220E-09

2.530E-09

9.896E+04

7.602E-03

3.160E-05

1. 97CE-07

4.080E-07

2.355E+05

0.

0.

1.180_-06

0.

4.171E204

0.

0.

1.130_-06

0.

1.407E+05

3. 710E-07 9. 060E-12 2. 450E-05 1.820E-OS

4.134E-05 1.260E-06 8.520E-09 1.060E-03

1. 270E-04

2. 120E-04

4. 640E-07

7. 102E-05

9. 540E-05

1. 590E-04

1. 150E-06

4. 551E-04

4. 250E-05

7. 070E-05

2. 870E-06

6. 394E-04

1. 190E-03

3. 080E-03

4. 200E-07

9. 768E-05

3. 890E-05

9. 970E-05

2. 71OE-07

2. 513E-04

7. 770E-04

2. 000E-03

2. 61OE-06

4. 848E-04

1. 120E-05

1. 870E-05

6. 220E-08

1.082E-05

2. 570E-04

4. 300E-04

1. 430E-06

2. 498E-04

4. 170E-06

1. 070E-05

9. 600E-09

2. 575E-06

7. 080E1.070E1. 180E2. 020E9. 670E8. 030E2. 810E1. 760E1.730E3. 560E7. 020E1. 1OOE2. 990E7. 650E1. 020E1. 570E2. 502E2. 5OOE6. 610E6. 090E4. 540E5. 0OOE6. 320E1.050E1. 860E9. 420E1. 520E2. 670E4. 27CE2. 170E3. 490E6. 140E1. 890E2. 690E2. 350E6. 510E-

'03

'06

-11

'06

2. 710E-05 2. 110E-02

3. 160E-06 1. 070E-06

4. 830E-05- 3. 310E-05

1.010E-08 1.470E-05

-02 3.710E-04

'07 2.370E-06

-11 4.490E-05

-05 2.660E-07

-01 6.600E-04

'07 1.06CE-06

-11 2.370E-04

'05 1.66CE-07

-01 9. 600E-04

'05 2.040E-04

-11 7.860E-05

-06 2.330E-08

-02 8.210E-05

-06 6.650E-06

-12 1.e80E-04

-06 2.230E-07

-01 1.490E-03

-05 1.330E-04

-11 4.400E-04

-05 2.560E-07

'03 7.110E-06

-09 2. 7OE-07

-12 5.640E-06

-07 2.35OE-09

-02 1.640E-04

-06 6.41CE-06

-11 1.300E-04

-06 5.410E-03

-03 6.210E-06

-07 7.140E-07

-13 2.17CE-06

-08 1.66CE-09

-01 1.000C-03

'05 1.150E-04

-11 3.510E-04

-05 2.69CE-07

0.

0.

0.

0.

0.

0.

0.

0.

2. 880E-01

6. 030E-07

1. 550E-04

1. 360E-04

5. 140E-01

3. 580E-07

3. 600E-04

8. 440E-05

7. 700E-01

7. 650E-05

5. 340E-05

1. 400E-05

6. 440E-02

2. 500E-06

9. 430E-05

1. 5S80E-04

1. 170E+00

5. 000E-05

2. 360E-04

1.720E-04

5. 520E-03

9. 420E-09

5. 530E-06

2. 000E-06

1. 270E-01

2. 170E-06

1. 270E-04

4. 60CE-05

4. 890E-03

2. 680E-07

1. 160E-06

1. 150E-06

7. e40E-01

4. 33CE-05

1. a60E-04

1. E6CE-04

0.

0.

0.

0.

0.

0.

0.

0.

6.720E-04 3.050E1.730E-03 4.330E1.S50OE-06 3.780E4.152E-04 1.050E0.

0.

4. 400E-06

0.

0.

0.

0.

0.

0.

0:

4. 200E-06

0.

0.

0.

0.

0.

D-96
\ , * ' ' !' .' :

* F. . . t . .

GW2FIL File (cont'd)

14

14

14

14

I+COTRASH

15

15

15

15

N-SSTRASH

16

16

16

16

N+SSTRASH

17

17

17

17

N-LOTRASH

18

-19

.18

N+LOTRASH

19

1.13CE-Oi 5.950E-02 5.250E-03

0. - 0. - 1.190E-03

3.780E-03 0. 0.

0. 0. 4. 760E-06

2.030E-01 1.407E+05

1.130E-01 5.950E-02 5 250E-03 - 0. 0. 1.190E-03

3.780E-03 0. - , 0.

0. 0. 4. 760E-06

2.060E-01 1.796E+05

1. 120E-05 O. .O.,

0. -- 0. 0.

0. 2.360E-06 8.800E-06

0. O. 0.

2.060E-01 1.796E+05

1.120E-05 0. 0.

0. 0. 0.

0. 2.360E-06 8.800E-06

0. 0. 0.

2.070E-01 5.064E+04

3.530E-02 1. 860E-02 1.640E-03

0.- I . . 3.710E-04

1.180E-03 0. 0.

0. 0. 1. 490E-06

2.070E-01 5.064E+04

3.530E-02 1.860E-02 1.640E-03

_ , _ . . 4.410E-03

3. 3S

3. 3

?OE-09

0.

0. .,

0

?OE-09

0.

0. -

0.

0.

0.

0. 0.

0. 0.

0. 0.

O.- 4.410E-03

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

-0. 0.

O. 0.

0. 0.

O0 . 0.

0. 0.

0. 0.

0. 1.380E-03

0. 0.

0: 0.

0. 0.

0. .: 1.380E-03

0.

0. --

0.

0.

'0.

1. 060E-09

0. , -

0.

0.

19 .- O. 0. .3.710E-04 1.060E-09 0.

-, 19 1.180E-03 O. O. O. 0.

19 0 O. _ 0. 1.490E-06 O. 0.

F-PROCESS 3.11OE-01 7.816E404

20 1.OBOE-04 0. : 0. 0. 0.

20 0. 0. 0. 0. . 0.

20 0. 2.300E-05 8.540E-05 0. 0.

20 0. 0. 0. 0. 0.

U-PROCESS 3.120E-01 2.811E+04

21 3.800E-04 0. 0. - 0. 0.

21 0. 0. O. 0. 0.

21 0. 1.650E-05 3.640E-04 0. 0.

21 0. 0. 0. 0. 0.

I-LOSCNVL 3.030E-01 4.914E+04

22 9.600E-03 3.270E-03 2.510E-04 0. 0.

22 0. 0.. 3.550E-03 0. 0.

22 0. 0. 0. 0. 0.

22 0. 0. ,0. 0. 0.

I+LOSCNVL 3.030E-01 4.914E+04

23 9.600E-03 3.270E-03 2.510E-,04 0. 0.

23 0. 0. 3.550E-03 0. 0.

23 0. 0. 0. 0. 0.

23 0. 0. 0. 0. 0.

I-ARSLIOD 3.030E-01 5.585E+03

24-1.990E-01 9.260E-02 a. 15oE-03 0. -. .

24 0. 0. 3.550E-03 1.020E-08 0.

24 1.140E-02 '- 0. 0. 0. 0.

24 -0. 0. 0. 0. 0.

I+A8SLIOD 3.030E-01 5. 5B5E+03 -

25 1. 990E-.01 9. 260E-02 8.150E-03 0. 0

25 0. 0. - 3. 550E-03 1. 020E-0908 0. -25 1.140E-02 -0. 0 O.

25 0.--: 0. 0- 0. 0. O.

'I-IOWAST 3.030E-01 1.571E+04 - '

26 2.060E-01 1.140E-01 1.OlOE-02 0. 0.

26 - O. 0 - 0. 6.820E-03 6.510E-09- 0.

26 7.260E-03 0. 0. 0. 0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.S32OE-02

0.

0.

0.

1. 320E-02

0.

0.

0.'

1. 690E-03

-0.

0.

D-97
I LWmGW2FIL File (cont'd)

26

I+BIOWAST

. 27

27

27

27

N-SSWASTE

28

28

28

28

N-LOWASTE

29

29

29

29

L-N9RCOMP

30

30

30

30

L-DECONRS

31

31

31

31

N-ISOPROD

32

32

32

32

N-HlCHACT

33

33

33

33

N-TRITIUM

34

34

34

34

N-SOURCES

35

35

35

35

N-TARGETS

36

36

36

36

F-PUoECON

37

37

37

37

H-3

H-3 /ACC

H-3 /CON

H-3 /AGR

H-3 /FOO

H-3 /DGM

H-3 IWWT

0.

3. 030E-01

2. 060E-01

0.

7. 260E-03

0.

3. 060E-Ol

2. 170E-04

0.

0.

0.

3. 070E-01

2. 11OE-02

0.

8. 620E-04

0.

4. 300E-01

4. 0402+03

1. 980E+02

0.

0.

4. 40CE-01

1.560E+02

3. 490E+00

2. 71CE-01

2. 520E+01

4. 040E-01

1. 500E+01

0.

7. 240E+00

4. 750E-03

4. 030E-01

2. IOCE.02

9. 950E+00

0.

0.

4. 050E-01

2. 330E+03

0.

0.

0.

4. 030E-01

5. 760E+03

2. 160E+02

9. 530E+02

0.

4. 03CE-01

S. 040E+01

0.

0.

0.

7. OOOE+00

2. 345E-01

0.

0.

2. isE-ol

5. 630E-02

1. 252E209

1. 172E+10

4. 451E+10

5.995E+04

0.

2. 367E+06

0.

1. 571E+04

1. 140E-01

0.

0.

0.

6. 339E+04

0.

0.

4. 600E-05

0. .

6.027E+04

1.060E-02

0.

0.

0.

2.887E403

0.

8. 19CE-03

0.

0.

3.498E+04

7.510E-03

1.420E-03

6. 840E-05

3.8702-03

5.196E.03

2.740E-02

0.

1.020E-05

9.570E-03

2.60SE403

0.

4.470E-04

0.

0.

3.481E+03

1. 520E.02

0.

0.

0.

1.865E+02

5.630E+02

0.

0.

0.

1.340E+03

5.2402+01

0.

0.

0.

4.66-E+03

* 0.

0.

0.

1.893=-06

l. 1o5200

5. 1902+07

5.190E407

5.190E+07

0.

0.

1.422E-01

0.

1. OOE-02

6. 920E-03

0.

0.

0.

0.

1. 710E-04

0.

9. 350E-04

1-. 070E-03

- 0.

0.

2. 590E-O1

0.

0.

0.

6. 870E-04

3. 610E-02

5. 400E-04

1.026E+00

4. 1OE-05

5. 140E+00

3. 810E-05

2. 151E-04

1. 320E-02

0.

0.

0.

0.

0.

0.

0.

5.750E+01

9. 420E+02

0.

5. 690E+02

0.

0.

0.

0. .

0.

0.

0.

1.559E-03

1.0000E+0

1.252E+09

1.172E+10

4.451E+210

5.995E+04

0.

2.367E+06

0.

0.

6. 510E-09

0.

0.

0.

0.

0.

0.

0.

7. 760E-10

0.

0.

6. 980E+02

0.

0.

0.

1. 270E+01

1.200E-05

1. 320E-08

3. 590E-04

0.

3. 270E-04

5. 330E-13

1. 250E-06

2. 970E+01

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

- . 0.

l, OOOE+00

1.252E+09

1. 172E+10

4.451E+10

5. 995E+04

0.

2. 367E+06

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1. 4002+00

0.

0.

0.

4. 49CE-02

3. 340E-05

1..260E+00

2. 9802-04

0.

2. 720E-06

1. 8402-04

1. 380E-04

6. 560E-02

0.

0.

0.

0.

0.

0.

0.

0. -

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.354E-03

0.

1.7252+09

1.1722E10

4. 4512E10

5.3995E04

0.

2. 3672.06

0.

1. 690E-03

0.

0.

0.

0.

0.

0.

0.

6. 230E-04

0.

0.

0.

7. 700E+02

0.

0.

0.

3. 500E+01

1. 200E-05

1. 770E+00

2. 51OE-03

0.

3. 270E-04

5. 550E-05

2. 110E-07

3. 600E+01

0.

0.

0.

0.

0.

0.

0.

7. 340E+02

0.

0.

0.

0.

0.

0.

0.

0.

0.

1. 280E-02

0.

1. 252E+09

1. 172E+10

4. 4512+10

5. 995E+04

0.

2. 367E+06

5. 190E+07

1. 052E+10

4. 331E+10

5. 995E+04

0.

2. 367E+06

D-98
GW2FIL File'(cont'd)

. H-3 /SWT 2. 3682.E06

H-3 /AIR 4.451E+10

C-14 1.210E-04

C-14 /ACC 3.166E+09

C-14 /CON 6.67eE+10

C-14 /ACR 2.660E+11

C-14 /FOO 3.721E+05

. , .C-14 IDGI 0.

.C-14 /IWWT 1.441E+07

C-14 /SWT 3.761E+07

C-14 /AIR 2.660E+ll

,FE-55 2.670E-01

FE-55 /ACC l.E05E+10

: FE-55 /CON 9.283E+09

FE-55 /AGR 3.219E+10

:FE-55 /FOO 3.482E+01

FE-55 /0DM - . 0. -

FE-55 /WWT 2;727E+06

FE-55 ISWT. 4.450E+06

FE-55 /AIR 4.827E410

N1-59 , S.660E-06

NI-59 /ACC 3.698E+10

NI-59 /CON 3.872E+10

NI-9 /ACR,1.247E+ll

NI-59 /FOO 3.693E+03

, NI-59 /DOM 6.200E203

. .. NI-59 /WWT 8.537E+06

; N1-59 /SWT 9.825E+06

NI-59 /AIR 1.505E+lI

CO-60 .... 1.320E-01

.C0-60 IACC 2.358E+12

r . CO-60 ICON 1.237E+ll

CO-60 /AGR 3.695E+11

,,CO-60 fFOO 5.274E+03

,CO-60 /DOM 1.540E+07

CO-60 /WWT 1.432E+08

C0-60 /SWT 1.458E+08

CO-60 /AIR 2.683E+12

NI-63 7.530E-03

NI-63 /ACC 3.056E+10

I NI-63 ICON 1.040E+11

-, NI-63 /AGR 3.341E+1I

NI-63 IFO0 9.876E+03

, .NI-63 /DGM : 0.

.I .NI-63 /WWT 1.9iSE407

,NI-63/SWT 2.2602+07

4NI-63 /AIR 3.341E+ll

N8-94 , 3.470E-05

, NB-94 /ACC 6'.102E+ll

. NB-94 /CON 1.389E+10

NB-94 /AGR 1.399E+10

!NB-94 fF00 2.116E+00

; NB-94 /DGM 9.63CE+06

-NB-94 IWWT 3.193E+07

,,NB-94 /SWT 3.232E+07

NB-94 /AIR 6.103E+ll

.SR-90 . 2.470E-02

.SR-90 /ACC 2.417E+13

SR-90 /CON 6.394E+13

-. SR-90 /AGR 1.891E+14

-SR-90 /FOO 6.407E+07

SR-90 /DGM 3.060E+04

SR-90 /WWT 9.564E+09

,1.422E-01 2.368E+06 2.368E+06 2.36EE+06 2.368E+06 2.368E+06

5.190E+07 4.451E+10 4.451E+10 4.451E+10 4.451E10 4.331E+10

5. S760E-03,1. 000E+OI 1.000E+0l: , .

1.405E+10 3.166E+09 3.166E+09, 3.166E409 3: 166E+09 2.526E+09

3.321E+11 6.678E+10 6.678E+10.6.678E+10 6.678E+10 6.614E+10

1.328E+12 2.660E+11 2.660E+11 2.660E+11 2.660E+11 2.654E+11

S1.8blE406 3.721E+05 3.721E+05 3.721E405'3.721E+05 3.721E+03

0. O. 0. 0. 0.', O.

7.205E407 1.441E+07 1. 441E+07 1;441E407 1.441E+07 1.441E+07

1.880E+08 3.761E+07 3.761E+07 3.761E407 3.761E+07 3.761E+07

1. 3282+12 2.,660E+11 2.660E+11 2.660E+11 2.660E+ll 2;654E+ll

1.480E-02 6.300E+02 5.400E+03

1.885E+10,2.413E+10 1.613E+10 1.613E+10 2.081E+11 1.925E+10

4.816E+10 3.941E+10 5.080E+07 5.060E+07 2.095E+11 2.116E+10

1.903E+11 1.376E+11 5.0 SOE.07.5.08E0+07.2.644E+I1 7. 752E+10

2.161E+02 1.493E+02

O. - . 0.

1. 244E+07 8;863E+06

2.314E407, 1.625E+07

2.064E+ll 1.537E+ll

1.48EO-02'4.200E+02

9.376E+10 5.0582E10

2.325E+ll 8.130E+10

7.47&E+11 2.581E+ll

2.211E404 7.590E+03

6.200E403 6.2002E03

4.425E+07 1.609E+07

,5.196E+07 1.874E+07

7.733E+11 2.838E+ll'

1.480E-02 4.200E+02

2.336E+12 2.353E+12

2.283E+10 7.599E+10

2.280E+10 1:874E+ll

0. 2.391E+03

1.540E+07 1.540E+07

1.233E+08 1.326E+08

3i7233E408 1.338E+08

2.336E+12 2.500E+12

1.480E-02 4.200E+02

9.602E+11 6.;576E+10

3.150E+12 2.176E+ll

1.001E+13 6.931E411

2.945E+05 2.041E404

.'.', -'.0.

5. 711E409 3.958E+07

6.7322+09 4.670E+07

1.001E+13 6.931E211

1.110E-02 1.000E+03

6.114E+11 6.108E+11

1. 515+E10 1.4S4E+10

1. 548E+10 1.472E+10

7.076+E00 3.937E+00

9.630E+06 9.630E+06

3.196E2407 3.194E+07

3.324E+07 3.266E+07

6.11E2+ll 6.111E+ll

9.860E-03 9.000E+00

9.617E+13 1.668E+11

2.58EE+14 1.760E+09

7.6e8E+14 1.760E+09

2.611E408 0.

3.060E+04 3.060E+04

3.895E+10 8.835E+06

0. 0. . 8.331E+01 8.566E+01

.0. 0. , O. 0.

8.609E+05 8.609E405

8.609E+o5 8.609E+05

1.613E+10 1.613E+10

3.600E+03

2.5782410 2.578E+10

5.980E+07 5.980E+07

5.980E+07 5.980E+07

0. , O. 0.

6.200E+03 6.2002+03

1.377E+06 1.377E+06

1.377E+06 1.377E+06

2.578E+10 2.578E+10

5.326E+06 5.452E+06

9.449E+06 9.692E+06

2.804E+11 9.360E+10

5.778E+10' 2.850E+10

3.206E+10 1.441E+10

3.206E+10 5.082E+10

0. . 1. 563E+03

6.200E+03 6.200E+03

1.377E+06 4.408E+06

1.377E+06 4.953E+06

5.778E+10 7.654E+10

3. 600E+03

2.336E+12 2.336E+12 2. 634E+13 2.504E+12

2.280E+10 2.280E+10 2.402E+13 8.593E+11

2.280E+10 2.280E+10 2.402E+13 2.953E+12

0. 0.- O. 4.492E+04

1.540E207 1.54CE007 1.540E+07.1.540E+07

1.238E2+08 1.238E+08 1.239E+08 2.893E+08

1.238E+08 1.238E+08 1.239E+08 3.112E+08

2.336E+12 2.336E+12 2.634E+13 5.266E+12

3.600E+03 -,. -. -. 

1.556OE+08 1.560E+08 8.816E+10 7.436E+09

1. 560E+08 1.560E408 8.816E+10 3.911E+10

1.560E+08 1.560E+08 6.816E+10 1.383E+ll

O.' . 0. ' ,.,0. 4..259E+03

0. 0. ' .0. '. 0.

4. 276E-01' 4.276E-01 2. 416E+02 8.258E+06

4.276E-01-4.276E-01 2.416E+02 9.743E+06

1. 560E+08 1.560E+08 8.816E+10 .1.383E+11

1.000E+04

6.095E+11 6.107E+11 1.330E+12.6.839E+11

1.320E+10 1.446E+10 7.332E+11. 4.432E+ll

1.320E+10 1.464E+10 7.332E+ll 1.557E+12

0.- -' 3.892E400 - O. -2.390E+04

9.630E+06 9.630E+06 9.630E+06 9.630E+06

3.192E407 3.194E+07 3.192E+07 1.466E+08

3.192E+07 3.265E+07 3.192E+07 4.496E+09

6.095E+11 6.110E+11 1.330E+12 2.:153E+12

7.300E+01 ; :

1.668E+11 1.668E+11 1.980E+11 1.892E+ll

1.760E+09 1.760E+09 3.296E+10 4.727E+12

1.760E+09 1.760E+09 3.296E+10 1.946E+13

20. - 0. 0. : 7.543E+06

3.060E+04 3.060E+04 3.060E+04 3.060E+04

8.835E+06 8.835E+06 8.835E+06 1.'134E+09

D-99
GW2FIL File (cont'd)

SR-90 /SWT 1.014E+10 4.12EE+10 8.835E+06 8.835E+06 8.B35E+06 8.835E+06 1.201E+09

SR-90 /AIR 1.892E+14 7.66EE+14 I.668E+11 1.668E+11 1:668E+11 1.980E+11 1.962E+13

TC-99 3.270E-06 1.150E-01 2.000E+00 5.000E+00O

TC-99 /ACC 1.176E+09 9.6e0E+Oe 2.280E+09 7:60CE+08 1.996E+10 7.400E+09 7.880E+09

TC-99 /CON 2.96CE+09 5.411E+09 8.890E+09 7.600E+08.1.031E+11 7.962E+09 2.240E+11

TC-99 /ACR 8.548E+09 1.933E+10 2.960E+10 7.600E+08 3.636E+11 9.720E+09 S.OOBE+l1

TC-99 /FOO 6.566E+03 1.635E+04 2;433E+04 0. 3.061E405 2.067E+03 7.953E+05

TC-99 /DGM 0. - 0. 0. 0. 0. 0.

TC-99 /WWT 4.186E+05 1.042E406 1.551E+06 2.093E+00. 1.951E+07 1.318E+05 a. 069E+07

TC-99 /SWT 4.240E+05 1.056E406 1.571E+O& 2;083E+00 1.976E407 1.335E+05 5.135E+07

TC-99 /AIR 8.548E+09 1.93:E+10 2.960E+10 7.600E+08:3.636E+11 9.721E+09 9.008E+11

I-129 4.080E-08 1.150E-01 2.000E+00 9.0E+O0'

1-129 /ACC 9.139E+11 8.515E+11 8.515E+11 5.128E+13 8.515E+11 8.572E+11 8.521E+1l

1-129 /CON 2.066E+12 7.124E+11 6.123E+11 1;624E+15 1.315E+12 6.366E+09 9.787E+10

1-129 /ACR B;346E+12 2.942E+12 2.528E+12 6.553E+15. 5.433E+12 6.366E+09, 4.006E+11

1-129 /FOO 6. 019E+04 2.137E404 1.836E+04 4.725E+07 3.947E404 0. 2.901E+03

I-129 /DGM 1.920E+04 1.920E404 1.920E+04 1.920E+04 1.920E+04 1.920E+04 1.920E+04

1-129 /WWT 4.289E+07 1.755E+07 1. 62E+07 3.08SE+10 2.938E+07 3.644E+06 5.536E+06

1-129 /SWT 4.389E+07 1.793E+07 1.592E+07 3.160E+10. 3.004E+07 3.644E+06,5.584E+06

1-129 /AIR 9.197E+12 3.792E+12 3.379E+12 6.554E+15 6.284E+12 8.572E+11 1.251E+12

CS-135 2.310E-07 1.620E-04 8.500E+01 7.200E+02

CS-135/ACC 2.371E+10 9.651E+10 8.851E+10 5.OSOE+08 3.331E+10 1.491E+10 1.004E+09

CS-135/CON 1.566E+11 4.209E+11 3.879E+11 5.030E+08 1.466E+11.4.884E+10 8.007E+09

CS-135/AGR 5.729E+11 1.432E+12 1.326E+12 5.080E+08 5.014E+11 1.551E+11 2.994E+10

CS-135/FOo 8.836E+03 2.157E+04 1.991E+04 0. 7.531E403 2.256E+03, 4.656E+Oi

CS-135/DCM 0. 0. :0. 0. 0. 0. O.

CS-135/WWT 3.318E+07 8.092E+07 7.475E+07 1.372E+00 2.8268E+07 8.472E+06 1.748E+06

CS-135/SWT 1.442E+08 3:520E+09 3.250E+08 1.392E+00 1.229E+09 3.683E+07 7.600E+06

CS-135/AIR 5.729E+11 1.437E+12 1; 326E+12'5.080E+08 5.014E+11 1. SlIE+11 2.994E+10

CS-137 2;310E-02 1.620E-04 8:500E+01 7.200E+02

CS-137/ACC 4.499E+11 6.339E+11 7.779E+11 2.419E+11 4.259E+11 3.299E+11 2.444E+11

CS-137/CON,1.397E+12 1.719E+12 2.351E+12 1.530E+09 8:010E+11 2.941E+11 3.919E+10

CS-137/AGR 5.117E+12 5.B72E+12 8.030E+12 1.530E+09 2.729E+12 9.350E+11 1:491E+11

CS-137/FGO 7.896E+04 8.814E+04 1.205E+05 0. 4.092E+04 1.360E+04 2.333E+03

CS-137/CGM 3.50CE+06.3.5COE+06 3.500E+06 3. 500E+06 3.50OE+06W3.500E+06 3..500E+06

CS-137/WWT 3.094E+08 3.43EE+08 4.655E+08 1.287E+07 1.665E+08 6.394E+07 2.'163E+07

CS-137/SWT 1.302E+09 1.452E409 1.981E+09 1.287E+07 6.808E+08 2.349E+08 5.096E+07

CS-137/AIR 5.358E+12 6.112E+12 8.270E+12.2.419E+11 2.969E+12 1.175E+12 3.895E+11

U-235 9.760E-10 1.25CE-04 8.4C0E+02 7.200E+03

U-235 /ACC 2.062E+12 3.062E+13.2.214E+11 2.214E+11 7.262E+12 3.360E+15 5.175E+11

U-235 /CON 2.643E+12 4.361E+13 1.590E+09 1.590E+09 1.013E+13 3.360E+15 1.586E+12

U-235 /AGR 5. 154E+12 8.500E+13 1.590E+09 1.590E+09 1.979E+13 3.360E+15 5.621E+12

U-235 /FOO 1.442E+04 2. 37S+05 0. 0. : 5.552E+04 0. 2.319E+04

U-235 /DlM 1.50CE+05 1.500E+05 1.500E+05 1. SOOE+05 1. 500E405 1.500E+05 1.'500E+05

U-235 /WWT 2.073E+08 3.235E409 1.177E+07 1. 177E+07. 7.643E+08 2.098E+07 3.261E+08

U-235 /SWT 2.109E+08 3:294E+09 1.177E+07, 1.177E+07 7.781E408 2.096E+07 3.316E+08

U-235 /AIR 5.374E+12 8.522E+13 2.214E+11 2.214E+11 2.001E+13 3.360E+15 5.841E+12

U-238 1.540E-10 1.250E-04 8.4002+02 7.200E403

U-238 /ACC 1.695E+12 2.8E2E+13 1.454E+10 1.454E+10 6.575E+12 3.120E+15 2.546E+11

U-238 /CON 2.429E+12 4 i45E+13 8.570E+07 8.570E+07 9.447E+12 3.120E+15 1..147E+12

U-238 /ACR-4.774E+12 8.106E+13 8.570E+07 8. 570E+07. 1.849E+13 3.120E+15 3.989E+12

U-238 /FOO 1. 34EE+04. 2. 277E405 0. 0. , 5.196E404 0. 1.633E+04

U-238 /DOM 5.160E+03 5.160E+03 5.160E+03 5.160E+03 5.160E+03 5.160E+03 5. 160E+03

U-238 /WWT 1.835E+08 3.087E+09 7.739E+05 7.739E+05 7.050E+0B 9.325E+06 2.221E-08

U-238 /SWT 1.868c6+08 3.144E+09 7.739E+05 7.739E+05 7.179E+08 9.325E+06 2.262E+08

U-238 /AIR 4.789E+12 8. 109E+13 1.454E+10 1.454E+10 1.850E+13 3.120E+15 4.003E+12

NP-237 3.240E-07 4.670E-04 3.OOOE+02 2.500E+03

NP-237/ACC 5.202E+14 1.200E+16 1.120E+15 1.34CE+11 3.84CE+15 3.602E+14 3.740E+11

NP-237/CON 5.209E+14 1.202E+16 1.122E+15 8.400E+08 3.847E+15 3.600E+14 1.550E+12

NP-237/AGR 5.238E+14 1.209E+16 1.128E+15 8.400E+08 3.868E+15 3.600E+14 56522E+12

NP-237/FOO 1.645E+04 4.067E+05 3.533E+04 0. 1.223E405 0. 2.;357E+04

NP-237/DGfl 6.560E+04 6.560E+04 6.560E+04 6.560E+04 6.56CE+04 6.560E+04 6.560E+04

NP-237/WWT 2.312E+08 5.546E+09 4.E85E+08 7.126E+06 1.674E+09 8.113E+06 3.263E+0B

D-100
GW2FIL File (cont'd)

NP-237/SWT 2.572E+08 6.169E409 5.443E+08 7.126E*06 1:867E09 8.113E+06 3.635E+08

NP-237/AIR 5:239E14: 1:209E 16 1 128E.15 1.340E+l 13.86eE+15 3.602E+14 5.785E+12

PU-238 8.020E-03 4.670E-04 8.400E+02 7. 200E+03

PU-238/ACC 2.OOOE+14 4.0BOE+15 2;800E+15 1.924E+10 8.BOIE+14 4.0OOE+15 3.313E+11

PV-238/CON 2.003E+14 4.091E+15 2:802E.i5 8.870E+07 8.812E+14-4.OBOE+15 1.514E+12

PU-239/AGR 2.012E+14 4.126E+15 2.-807E+15 8:B70E+07 8.8:0E+14 4:0EOE+15 5.277E+12

PU-238/FOO 1.137E+03 4.522E+04 6. 371E+03 0. 4. 86BE403 0. : 4.855E+03

PU-238/DGM 1.930E+01 1.930E401 1.930E+01 1.930E+01 1.930E+01

PU-238/WWT 7.019E+07 2.741E+09 3.931E+08 1.025E+06Z2.972E4+O 1.221E+07 2.940E.08

PU-238/SWT 7. 45E+07 2. 926E409 4.;192E+08 1.025E+06 3. 171E40j 1. 221E+07 3.139E+08

PU-238/AIR 2.012E+14 4.126E+15 2.807E+15 1.924E+10 8.850E14 4.08OE+15 5.297E+12

PU-239 2.84CE-05 4.670E-04 8.-400E+02 7. 200E+03

PV-239/ACC 2.240E+14 4.OOE+15 3.120E+15 7. 400E+09 9.601E+14 3.840E+15 3.034E+1I

PU-239/CON 2.243E.14 4.813E+15 3. 122E+15' 5. 270E+07 9.613E+14 3. 840E+15 1.392E+12

PPU-239/AGR 2.253E+14 4.854E+I5 3.127E+15 5.170E+07 9.655E+14 3.840E+15 4.826E+12

PU-239/FOO 1.270E+03 5.234E+04 7.049E+03' O. 5.393E403 - 0. 4.429E+03

Pt1-239/DCM 9.39CE+01 9.390E+01 9.390E+01 9.390E+01 9.390E+01 9.390E+01 9.390E+01

PV-239/WWT 7.765E+07 3.172E+09 4.343E+08 3.934E.05 3.285E+08 1.092E+07 2.676E*08

PU-239/SWT 9.286E.07 3.386E409 4.632E+08 3.934E+05 3.506Et08 1.092E+07 2.858E+08

PPU-239/AIR 2.253E14 4.854E+15 3.127E+15 7.400E+09 9.656E+14 3.840E+15 4.833E+12

PU-241 5.250E-02 4.670E-04 8.400E+02 7. 200E+03

PV-241/ACC-3.040E+12 7.440E+13 4:S60E+13 4. 780E+07 1.440E+13 6.0OOE+12 5.568E+09

P1-241/CON 3.046E+12'7.467E+13 4.561E+13 4.780E-07 1.443E+13 6.800E+12 2.861E+10

PV-241/AGR'3.063E+12 7.552E+13 4.566E+13 4;780E+07 1.450E+13 6.80OOE+12 1.008E+11

-- PU-241/F002.20&E+01 1.097E403 5.613E+O1 0.- 1.017E+02 '0., 9.310E+Oi

PU-241/DGM 3. 430E-01 3.430E-01 3.430E-01 3. 430E-01 3.430E-01 3 430E-01 3. 430E-01

PU-241/WWT 1. 341E+06 6.642E407 3.512E+06 1.310E-01 6.179E+06 1. 864E+04 5.618E+06

PPU-241/SWT 1.'431E+06 7.091E407 3.742E+06 1.310E-01 6.596E+06 1.864E+04 5.999E+06

P1-241:/AIR 3.063E+12 7.553E+13 4.566E+13 4.780E+07 1.450E+13'6:800E+12 1.008E+ll

PU-242 2.480E-06 4.670E-04 8.400E+02 7.200E+03

PU-242/ACC 2.160E+14 4.48vE+15'3.*040E+15 1.441E+10 9.601E+14 3.680E+15 2.944E+11

P1-242/CON 2.163E+14 4.492E+15 3.042E+15 6.930E+07 9.613E+14 3.680E+15 1.355E+12

PU-242/AGR 2.!173E+14 4.530E+15 3.047E+15 6.930E+07 9.653E+14 3.680E215 4.722E+12

PU-242/FOO 1. 224E+03 4.i84EE404 6 '783E+03 0. 5. 194E+03 0. 4. 343E+03

PPU-242/DCM 0. 0. 0. O. O. r -. 0.

PU-242/WWT 7.520E+07 2.938E+09 4.184E+08 7.674E+05 3.168E+08 1: 085E+07 2.628E+08

PU-242/SWT 8.021E+07:3.137E+09 4.462E+08 7.674E+05 3.381E+08 1.085E+07 2.806E+08

PU-242/AIR 2.1732*14 4.530E+15 3.'047E+15 1.441JE10 9.654E+14 3.680E+15 4.736E+12

AM-241 1.510E-03 4.11CE-03 3.000E+02 2.500E+03 -

AM-241/ACC 5.041E+14 7.120E+15 6.640E+15 7.869E+10 3.840E+15 4.241E+14 3.587E+l2

AM-241/CON 5.049E+14 7.134E+15 6.645E+15 3.800E408 3.847E+15 4.240E+14 1.508E+12

AM-241/AGR 5.077E+14 7.176E215 6.660E+15 3.800Et08 3.868E+15 4.240E+14'5.355E+12

AM-241/FOO 3.599E404 S.44E:405 1.916E+05 0. - 2.707E405 - 0. 4.936E+04

AM-241/DCM 7.71CE+04 7.71CE404 7:710E+04 7:710E+04 7.710E+04 7.710E+04 7.710E+04

AM-241/WWT 2.247E+O0 3.340E409 1.,'89E+09 4.'192E+06 1.663E409 5.-354E+06 -. 047E208

'A!-.-241/SWT 3.721E+08 5.572E+09 1.974E+09 4.192E+06 2.772E+09 5.354E+06 5.069E+OB

AM-241/AIR 5.078E+14 7.176E+15 6.660El15 7.869E+10 3.1868E+15 4.241E+14 5.434E+12

AM-243 8.720E-05 4.110E-03 3.OOOE+02 2.500E+03

-AM-243/ACC 4.961E+14 7.040E+15 6.480E+15 9.096E+10 3.760E+15 4.001E+14 3.630E+11

'AM-243/CON 4.969E+14 7.054Er+15 6.485E215 6.090E+08 3.:767E+15 4.000E+14 1.713E+12

* A-243/AOR-4.996E+14 7.096E215 6.!499E+15 6.b9OE+08 3.-787E+15 4.000E+14 6.223E+12

AP.-243/F0D 3.'525E+04 5.441E+05 1.849E205 0. 2.654E405 ;- 0. -5. 787Ei04

AM-243/DGM 1.860E+05 1.E60E+05 1:SeOE+05 1.860E+05 1.860E+05 1.860E+05 1. 860E+05

AM-243/WWT 2:208E+08 3.337E+09 I.'148E+09 4.837E+06 1:.631E409 5.933E+06 3.572E+09

AM.-243/SWT 3.5c0 5.566r+09 1;'90SE+09 4.837E+06 2.'718E+09 S.933E+06 5.942E+OB

AM-243/AIR 4.1997E+14 7.096E+15 6.499E+15 9.096E+10 3.788E+15 4.001E+14 6.313E+12

CM-243 2.170E-02 4.670E-04 3.000E+02 2.500E+03

CM-243/ACC 3.843E+14 6.161E+15 5.601E2+5 2.444E+11 1.760E+15 4.4032E+14.5.484E+ll

;CM-243/CON 3.846E+14 6.171E+15 5.'604E+15 2.260E+09 1.'763E+15 4.400E+14 1.594E+12

CCM-243/AGR 3.-866E+14 6.204E+15 5.616E+15 2:260E+09 1.772E+15 4.400E+14 5.629E+12

CM-243/F00 1.113E404 1.897E+05 7.155E404 0. 5.:195E404 0. 2.319E+04

:Cf-243/DGM 3.820E+05 3.820E+05 3.620E+05 3.e20E+05 3.820E+05 3.820E+05 3.820E+05

CM-243/WWT 1.'647E+08 2:59EE409 9.970E+08 1.296E+07 7.212E408 1.417E+07 3.269E+06

D-101
; 

GW2FIL File (cont'd)

CMI-243/SWT 2. 087E+08 3.347E.09 1. 2a02+09 1. 296E+07 .9. 264E408:1. 417E+07 4. 1B4E+08

CM~-243/AXR 3.868E+14 6.204E+15.5.617E.15 2.444E+11 1.7722+15 4.4032+14 5.8712+12

CM-244 3. 940E-02 4. 670E-04, 3.O000E+02 2. 500E.03

CtM-244/ACC-2.BOOE+14 4.4002-+15 4; 160E+15 1.706E+10.1.2e02+15,4.400E+14 3.051E.11

CM-244/CON 2. 80ZE2+4 4; 4082+15 4 . 163E+15 7. 23CE+07. 1.2e22+15 4.400E.14 1. 333E+12

Cr.-244/AGR 2.8202.14 4. 43:32+15 4. 174E+15 7. 230E+07 1.2e92+15 4; 400E+14 5.4342.12

CM-24-'./FOO 8. 5202403 1. 4342.05 6. 145E+04 *.0. - 3.9782404. 0. 2. 241E+04

*CM-244/DGlI 5. 640E+01 5. 6402401 5. 640E+01 5. 640E+01, 5. 640E+01* 5. 6402+01 5. 640E.01

*CM-244/WWT 1. 1702r+08 1. 9542.09 8. 443E.08 9. 093E+05 5; 4302+08 2; 1152.06 3. 044E.08

CMI-244/SWT. 1. 5072+08 2. 521E.09 1; 0872+09 9. 0932+05 7. 0012408 2. 1152+06 3. 9292+08

CM-244/AIR 2.820E+14:4.4332P+15* 4.1742+15 1. 7062+10. 1. 2892+15 4. 4002+14 5.451E+12

PB-210 3. 3982-02 4. 1102-03 ~8. 4002+02.7. 2002+03~

PB-210/ACC 8.0392+12.2. 5612+14 6. 564E+13-3. 836E+10 2.0802+14 1.0402414 4.7162+10

*P8-210/CON 1. 6992+13-, 5. 0862r+14. 1.3782+14 3.5102.06 4.1122+14 1.0402+14 9.0452+11

PB-210/ACR 4. 5142+13 1.3002.+15 3.6392+14 3.51C2+08 1.048E+15 1.0402+14,3.7092+12

P8-210/FOG 2. 584E+05 7. 26S2+06 2. 0762+06 0. 0002+00 5.e843E+06 0. 0002+00 2.'575E+04

PB-210/DGM. 6. 5802+05 6. 5802+05 6. 5802+05 6. 5902405 6. 580E+05 6. 5802.05 6. 5802+05

PB-210/WWT 2. 19-4209 6. 1642+10 1. 761E+10. 2. 035E+06 4; 955E+10 2. 3202+06 2. 204E+08

PB-210/SWT-2. 623E+09 7. 372E+10 2. 1062+10 2. 0352E+06 5. 9272+10 2. 3202+06 2. 6322+08

PB-210/AIR 4.5182.13 1.301E.15 3.6402+14 3. 8362+10 1.0482+15 1. 0402+14 3. 7472+12

AC-227 3.209E-02 4. 1102~-03 3.0002+02 2. 5002.02

AC-227/ACC 3. 600=+14 5. 6802+15 8.C0002+14. 1. 0042+09 2. 5602+14 2. 1602+16 1. 1402+10

AC-227/CON 3.618;+14~5.711E+15 8.0412+14 1. 1902+08 2.5732+14 2. 1602+16 1.3612+12

AC-2:27/AGR 3. 6762+14 5. 8072.15 8. 1692+14 1. 1902+08 2. 615E+14 2; 1602+16 5. 5932+12

AC-227/FOO 3. 296E+04 5. 552E+05 7. 363E+04 0. 0002+00 2. 375E+04 0. 0002+002. 4322.04

AC-227/DC.'1 1. 3902+07 1. 3902.07 1. 390E+07 1. 3902.07 1. 3902.07 1. 3902-+07 1. 3902+07

AC-277/WWT.4. 4772+08, 7. 5412.09 1. 0002.09. 4. 740E+04 3. 2272+08 5. 925E+07 3. 296E+08

AC-227/SWT 4. 5592-+087. 6792409 1. 019E+09~ 4. 7402.04 3. 2862+08 5. 9252+07 3. 357E.08

AC-227/AIR.3.676E.14 5.8022=+15 8.1692+14 1.004E.09 2.615E.14 2.1602.16 5. 5942+12

RA-226 4.3272-04 4. 11C2-03 3.0002+01 2.5002+02.

RA-226/ACC 1.5202+15 2. 1602+15 8.9442+09 8.9442+09 8.9442+09 8.0002+14 1.7702+11

RA-226/CON 1. 654E+15 2. 5272+15 5.003E+12-5.00eE+12 50082E+12 e.0002+14 4.2412+12

RA-226/ACR 2.072E+15 3. 6782+15 2. 0692+13 2. 0692+13 2. 0692+13 8. 0012+14 1. 7002+13

RA-226/FOO 1; 330E+07 3. 6582407 4. 988E+05 4. 9882+05. 4. 9882+05 2. 9262.03 4. 057E+05

RA-2P6/DGM 2. 9402+07 2. 9402407 2. 9402.07 2. 9402+07 2. 9402+07 2. 9402+07 2. 9402+07

RA-226/WWT: 3. 2562+ 10 8. 9522+10 1. 2212+09 1. 2212+09. 1;. 2212409. 9. 8282E+06 9. 933E+08

RA-226/SWT 3.:7322+10 1.0262+11 1. 4002+09- 1. 4002.09. 1. 4002+09 1. 0862E+07 1.21382+09

RA-226/AIR 2.0722+15 3.6782+15 2.0702+13 2.07C2+13 2.0702+13 8.0022+14 1.7012+13

TH-2218 3. 629E-01 4. 110E-03 8. 4002.02 7. 2002+03

TH-228l/ACC 2.4022+13 7. 1212+14 1.202E+13 1.7972+10 6.8022+13 1. 4402+16 2. 9802+11

TN-22S/CON 2. 4282+13 7. 2022-+14 1-. 2142+13 1..9802+08 6. 8772+13 1.4402+16 9. 583E.12

* TH-228/AGR 2. 5152+13 7. 45SP2+14 1.'2572+13 1.9802+087. 1192+13 1.'440E+16 3.8722+13

* TH-228/Foo 8. 379E+03 2. 474E+05 4. 190E+03 0. 0002+00 2. 329E+04 0. 0002+00 2.e8062+05

TH-2263/DGMI 2. 2202+07 2. 2202407 2. 220E+07 2. 2202+07, 2. 2202-+07 2. 2202-+07 2. 2202+07

TH-228/WWT 6.B6652+07 2. 0002.09 3. 4802+07 9. 5122r+05r 1. 89124083 4. 0422r+07 2. 2672+09

TH-228/SWT 8. 0532+07 2. 3502+409 4. 0742+07 9. 5122+0 5 2. 22227+02 4. 0422:+07 2. 6662.09

TH-228/AXR 2. 5172+13 7.459E214 1. 2592+13 1.7972+10 7. 121.".13 1. 4402+16 3. 8742+13

RA-228 1.0352-01 4.1102-03 3.0002+01 2.5002.02

RA-228/ACC 6. 8602+14 6..480=.14 1.-140E+08 1. 1402+08 1. 140E+08 8. 8002+15 1. 8742+09

RA-22a/CON 7.5982+14 8.3162+14 6. 51 12E+1 2 6.6782+12 6. 5112+12 8.eo0E+15.-.1.688E+12

RA-P229/AGR -9.8462+14 1.407E+15 2.6902+13 2. 7-59E+13 2. 6902+13 8.8002+15 6.9892+12

r-A-228/FDO 7.149E+06 1.8297+07 6. 4842+05 6.651E.05 6. 4842+05 4.0072+03 1.6792+05

RA-228/DCM 5. 0002=+06 5. 0002.06 5.O0002.06 5. 0002.06 5. 0002+06 5. 0002+06 3.5 000+06

RA-228/WWT 1.7505+10 4.4762+10 1. 5872+09 1.-6282+09 1. 5872+09 3.3922+07 4. 1102+08

RA-228.'SWT 2.0062+10 5.1302+10 1.8192+09 1.8662+09 1. 819E409, 3..536E.07 4.7112+08

RA-228/AIR 9. 84727+14 1.407E+15 2. 6902-+13 2.759E+13 2.690Z+13 8.18012+15 6. 9692+12

TH-2:29? 9. 4432-05 4. 1102-03 8. 4002+02 7. 200E.03

TH-229?/ACC 1. 3602+15 2.8002=.16 4.243E+14 2. 5482E+1 1 2.0802.15 2.O0002.16 2. 4952+12

TH-229/CON 1.3662+15 2.8132+16 4.2602+14 1.7902E+09 2.0902+15 2.0002+16 1.0702+13

TH-229/AGR 1.3872+15 2.8542+16 4.3212+14 1.7902+09 2. 1192+15 2.OOOE+16;3.720E+13

TH-2V9/FDOO 1; 9502+05 3. 980E.06 5. 9352+04 0.0002+00 2. 8662+05 0. 0002.00-2. 5542+05

TH-2?9/DGM1 1. 4502+07 1. 4502+07 1. 4502+07 1. 4502+07 1. 4502E+07 1. 4502+07 1. 4502+07 TH-29/WT1. 5912+09 3. 2222+10 4.938E+08 1.354E+07 2. 334E+09 6. 8362+07 2. 075E+09

D-102
-

GW2FIL File (cont'd)

TH-229/SWT

TH-229/AIR

TH-230

TH-230/ACC

TH-230/CON

TH-230/AGR

TH-230/FOO

TH-230/DCM

TH-230/WWT

TH-230/SWT

TH-230/AIR

PA-231.

PA-231/ACC

PA-231/CON

- -PA-231/AGR

PA-231/FOO

PA-231/DOM

PA-231/WWT

PA-231/SWT

PA-231/AIR

TH-232

TH-232/ACC

TH-232/CON

TH-232/AGR

TH-232/FOO

TH-232/DGM

TH-232/.WT

TH-232/SWT

TH-232/AIR

U-233

U-233 /ACC

U-233 ICON

U-233 /AOR

U-233 /FOO

U-233 /DGM

U-233 /WWT

U-233 ISWT

U-233 /AIR

U-234

U-234 /ACC

U-234 ICON

U-234 /AGR

U-234 /FOO

U-234 /DOM

U-234 /WWT

U-234 /SWT

U-234 /AIR

U-236

U-236 IACC

I

i

i

I

1.868E+09 3.786E+10 5.779E+08

1.387E+15 2.855E+16 4.324E+14

8.664E-06 4.110E-03 8.400E+02

5.360E+14 1.760E+16 1.120E+15

5.369E+14 1.763E416 J1. 122E+15

5.399E+14 1.774E+16 .1.122E+15

2.843E+04 1.027E+06 5.835E+04

2.13CE+03 2.130E+03 2.130E+03

2.317E+08 8.342E409 4.7492409

2.720E208 9. 79WE+09 5.576E+0O

5.399E+14 1.774E+16 1.128E+15

2.133E-05 4.110E-03 8.400E+02

5.601E+14 1.360E+16 5.441E+14

5.626E+14 2.367E+16 5.465E+14

5.702E+14 1.3E8E+16 5.545E+14

4.721E+04 1.217E406 4.572E+04

4.560E+05 4.560E+05 4.560E+05

6.472E+08 1.654E+10 6.270E+08

6.589E+08 1.684E+10 6.384E+08

5.710E+14 1.36aE+16 5.546E+14

4.916E-11 4.110E-03 8.400E+02

2.560E+14 -7.440E+15 3.520E+14

2.585E+14 7.478E+15 3.537E+14

2;662E+14 7.597E+15 3.588E+14

7.481E+04 1.147E+0 4. 98aE+O4

4.920E+04 4.920E+04 4.920E+04

6.053E+08 9.221E+09 4.043E+08

7.114E+08 1.091E+10 4.750E+08

2.663E+14 7.597E+15 3.589E+14

4.279E-06 1.250E-04 8.400E+02

2.01lE+12 3.281E+13 1.077E+10

2.871E+12 4.717E+13 5.160E+07

5.599E+12 9.217E+13 5.160E+07

1.5662E04 2.586E405 0.000E+00

4.16CE006 4.160E406 4.160E+06

2.131E+08 3.506E+09 5. 739E+05

2.17C0E08 3 570E+09 5.73fE+05

5.610E+12 9.218E+13 1.077E+10

2.806E-06 1.250E-04 8.400E+02

1.938E+12 3.122E+13 1.746E+10

2.773E+12 4.459E+13 1.140E+08

5.444E212 8.816E+13 1.140E+08

1.535E+04 2.482E+05 O.OCOE+00

3.98CE+05 3.9202405 3.920E+05

2.090E+08 3.365E+09 9.286E+05

2.128E+08 3.427E409 9.286E+05

5.461E+12 8.820E+13 1.746E+10

2. 900E-08 1.25OE-04 8.400E+02

1.857E+12 3.042E+13 1.648E+10

2.658E+12 4.361E+13 9.670E+07

5.221E+12 8.500E+13 9.670E+07

1.473E+04 2.376E+05 O.OOOE+00

5.560E+04 5.5602+04 5.560E+04

2.005E.*08 3.224E+09 8.770E+05

2.041E+02 3.283E+09 8.770E+05

5.237E+12 8.501E+13;1.648E+10

1.053E-04 4.670E-04 8.400E+02

2.240E+14 4.8002+15 3.120E+15

2.243E+14 4.8132E+15 3.122E+15

2.2532+14 4.854E+15 3.127E+15

1.270E+03 5.234E+04 7.D49E+03

9.390E+01 9.390E+01 9.390E+01

7.765E+07 3.172E409 4.343E+08

1.354E+07 2.741E409

2.548E+11 2.120E+15

7.200E+03

1.435E+10 5.280E+15

1.300E+08 5. 289E+15

1.300E+08-5.319E+1S

O.O00E+O0 2.818E+05

2.130E+03 2.130E+03

7.610E*05 2.290E+09

7.610E+05 2. 689E409

1.435E+10 5.319E+15

7; 200E+03 -

;.O97E+11 3.040E+15

6.590E+08 3:054E+15

6.590E+08 3:099E+15

O.OOOE+00 2:565E+05

4.560E+05 4;560E+05

5.836E+06 3.491E+09

5.836E+06 3.5S5E+09

1.097E+11 3.099E+15

7. 200E+03

1.384E+10 1.680E+15

1.090E+08 1.688E+15

1.O00E+08 1.713E+15

O.OOE+00 2.404E+05

4.920E+04 4.920E+04

7.352E+05 1.9462+09

7.352E+05 2.2272409

1.384E+10 1.713E+15

7.200E+03 -

1.077E+10 7.691E+12

5.160E+07 1:103E+13

5.160E+07 2.152E+13

O.OOOE+00 6.027E+04

4.160E+06 4.1602+06

5.739E+05 8.1752+08

5.739E+05 8.325E+08

1.077E+10 2.153E+13

7.200E+03 ; --. -

1.746E+10 7.538E+12

1.140E+08 1.080E+13

1.140E+08 2.108E+13

O.OOOE+00 5.90BE+04

3.980E+05 3.980E+05

9.226E+05 2.618E408

9.2a6E+05 8.1642+08

1;746E+10 2.110E+13

7.200E+03 . -

1.648E+10 7.297E+12

9.670E+07 1.043E+13

9. 670E+07 2.030E+13

0.000+00 5.671E404

5.560E+04 5.560E+04

8t.770E+05 7.695E402

8.770E+05 7.836E408

1.648E+10 2.032E+13

7.200E+03 -

7.400E+09.9.601E+14

5.170E+07 9.6132+14

5.170E+07 9.6s5E5+14

0. 5.393E+03

9.390E+01 9.390E+01

3.934E+05 3.285E402

6.836E+07 2.437E+09

2. 000E+16 3.745E+13

3.520E+14 2.464E+11

3.520E+14 1.227E+12

3.520E+14 4.342E+12

O.OOOE+00 3.003E+04

2.130E+03 2.130E+03

1.726E+06 2.431E+08

1.726E+06 2.857E+08

3.520E+14 4.357E+12

5.120E+15

5. 120E+15

5.120E+15

0. OOOE+00

4. 560E+05

1.987E+07

1.987E+07

5. 120E+15

4.217E+11

1. 495E+12

5. 200E+12

2. 129E+04

4. 560E+05

2.944E+08

2. 997E+08

5.309E+12

4.720E+15 2.379E+11

4.720E+15--1.070E+12

4.720E+15 3.720E+12

O.OOOE+00 2.554E+04

4.920E+04 4.920E+04

1.367E+07.2.069E+08

1.367E+07 2.431E+08

4.720E+15 3.734E+12

3.680E+15 2.902E+ll

3.680E+15 1.314E+12

3.680E+15 4.554E+12

O.OOOE+00 1.862E+04

4.160E+06 4.160E+06

1.066E+07 2.529E+08

1.066E+07 2.575E+08

3.680E+15 4.564E+12

3. 600E+15

3. 600E+15

3.600E+15

0. OOOE+00

3. 980E+05

1.080E+07

1. 080E+07

3. 600E+15

2. 895E+1l

1. 225E+12

4. 457E+12

1. 823E+04

3. 980E+05

2. 480E+08

2. 525E+08

4. 474E+12

4

U-236 /CON

U-236 IAGR

U-236 /FOO,

U-236 /DON

U-236 /WIWT

U-236 /SWT

U-236 -AIR

PU-240

PU-240/ACC

PU-240/CON

PU-240/AOR

PU-240/FOO

PU-240/DGN

PU-240/WWT

3.440E+15 2.725E+11

3.440E+15 1.206E+12

3.440E+15 4.182E+12

O.OOOE+00 1.710E+04

5.,560E+04 5.560E+04

1.031E+07 2.327E+08

1.031E+07 2.369E+08

3.440E+15 4.198E+12

3. 840E+15

3. 840E+15

3. 840E+15

0.

9.390E+01

1.092E+07

3. 034E+11

1. 392E+12

4. 826E+12

4. 429E+03

9.390E+01

2. 676E+08

. D-103
GW2FIL File (cont'd)

PU-240/SWT 8. 286E+07

PU-240/AIR 2. 253E+14

REGIOIN I 9. 190E-12

2.000E+02

I.OOOE+00

4.000E+02

REGION 2 2.-0OOE-11

4.200E+01

-.000E+OO

6.400E+01

REGICN 3 2.510E-11

1.400E+02

1.000+OO

1.600E+02

REGION 4 2.640E-10

1.500E+01

1.0002E00

8. 000E00

REGION 5 2.01CE-11

3. 200E+01

1. 0002E00

6.400E+00

REGICN 6 2.010E-11

9.200E+01

1.000E0oo

6.400E+01

REGICN I 6.926E+03

VOLUMES 4. 654E+04

8. 341E203

1.519E204

1. 731E+03

7.3462+03

1.316E+03

REGION 2 1.292E.04

VLOuVMES 5. 568E+04

2! 085E204

1. 103E+04

1. 229E+03

1.224E+04

1. 726E+03

REGION 3 6. 587E+03

VOLUMES 4. 537E+04

0.

1. 519E204

1. 508E;03

8.045E.03

7. 450E202

REGICN 4 8. 136E+03

VOLUMES 2. 145E204

1. 2512E+G4

1. 103E;04

1.117E+03

7. 346E+03

1.366E+03

3.362E+09

4. 854E+tS

2. 960E-11

5. 00OE403

1. OOO2+0O

8. 000E+02

3. 180E-11

4:0002E02

1.000E+00

1. 60OE403

3.280E-11

2.900E+03

l.OOOE400

8. OOE2.02

8.'060E-11

3.000E402

1.0000E+0

8. 000E+02

3. 180E-11

3.9002E02

1.0002E00

1. 600E+03

3. 180C-11

4. 500E*02

1. 0002.00

1.600E+03

4. 870E+04

8. 428iE404

4.363E404

1. 563E404

4. 8694 03

5. 196E203

9. 124E+04

1. 590E+05

3. 096E404

3.90E2.04

3. 456E203

0.

4. 631E404

8. 0732404

3. 802E+04

0.

4. 241E203

0.

5. 720E+04

9. 972E404

2.815E404

2. 3452.04

3.S41E403

0.

4. 632E+08

3. 127E215

1. 970E-04

1.000E+04

1.000E00

1. G30E-10'

1.160E-03

8. 000E+02

1.000E+00

1. 830E-10

9. 000E-05

5.OOE+03

1.000E00

1.'830E-10

1. 300E-06

6.000E+02

1.000E+00

1. 830E-10

1.160E-04

7.900E202

1.000E+00

1. 830E-10

1. 160E-02

8. 500E+02

1.000E+00

1. 830E-10

8. 559E+02

4. 356E+04

4. 363E+04

0.

4. e69Er03

8. 086E+02

1. 604E+03

8. 162E+04

3. 096E+04

0.

3. 4562+03

5. 739E+02

8. 140E+02

4. 143E+04

3. 8002E04

1.406E 04

4.241E.03

7. 043E+02

1.005E+03

5. 117E2.04

2. 815E+04

1.406E+04

3. 1412E03

5.217E202

3: 934E+05

7 40CE+09

4. 930E-05

4. 000E+02

1. O1OE-09

2. 610E-12

3. 240E-05

1. 300E+03

3. 500E-10

3. 323E-12

2. 250E-05

4. OOOE+02

3. 860E-10

2: 550E-12

3. 250E-07

1. 30CE+03

2. 6602E-1

1. 7902-12

3. 240E-06

1. 300E+03

3. 500E-10

3. 323E-12

3. 240E-04

1.300E203

3. 500E-10

3. 323E-12

4. 355E+03

5. 744'+04

8. 9762.+04

1. 523E+04

3. 169E204

2. 646E+03

8. 159E.03

6. 872E+04

1. 796E+04

1. 081E-04

6. 339E+03

2. 089E+02

4. 141E203

5. 600E+04

3. 591E.04

1. 327E+04

1.262E+04

2. 099E+02

5. 1152+03

2. 647E+04

3.S391E+04

9. 8292.03

1. 266E.04

4. 178E202

3; 506E+02

9. 656E+14

7. 7002E03

1;OOOE+04

1. 510E-09

7.700E+03

1.000E+04

5: 20E-10

7.770E+03

1.250E204

5.790E-10

7.700E+03

3.000E+04

3.990E-11

7.700E.03

1.000E+04

5;250E-10

7.7002+03

1.000E+04

5.2OE-10

2.099E+04

2.724E404

8.9782E04

1.523E+04

1:8082.04

5.782E+01

2.511E+04

3.2602.04

1.796E+04

1.081E204

1.205E+04

4.103E+01

2.0465404

2.656E+04

3.591E204

1.327E+04

1.BO2E+04

5. 036EO01

9:6722+03

1.256E+04

3.591E+04

9.829E+03

1.20E2.04

3. 730Ex01

1. 092E+07

3. 840E+15

2. 000E+05

2. 000E+04

1. 120E-07

2. OOOE+05

2. 000E+04

1. 120E-07

2.8958E+08

4. 833E+ 12

4. 500E+06

3

4. 500E+06

3

2.000E+05 4.500E+06

2.500E+04

1.120E-07 4

2.000E+05 4.500E+06

6.000E+04

1.120E-07 2

2. 000E+05

2. 000+E04

1. 120E-07

4. 500E+06

2

2.000E+05 4.500E+06

2.000E+04

1.120E-07 4

5.788E+04

4.719E+04

1.519E204

1.713E+03

6.479E+02

4.155E+02

6-925E204

1. 180E+05

1.013E+04

1.229E+03

1.040E+03

2.949E+02

5.643E+04

0.

1; 519E+04

1.5022+03

6.224E+02

3.619E+02

2. 6682+04:

7. 078E+04

1.103C3+04

1.117E+03

5.774E+03

2.681E+02

D-104
I ilr N F 

IN2FIL Fil e

P-IXRESIN

P-CONCLIO

P-FSLUDGE

P-FCARTRO

B-IXRESIN

' 8-CONCLIO

B-FSLUDCE

P-COTRASH

P-NCTRASH

E-COTRASH

E-NCTRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

N+LOTRASH

F-PROCESS

U-PROCESS

I-LOSCNVL

I+LOSCNVL

I-ABSLIOD

I+ABSLIOD

I-8IOWAST

I+BIOWAST

N-SSWASTE

N-LOWASTE

L-NFRCOnP

L-DECONRS

N-ISOPROD

N-HICHACT

N-TRITIUM

N-SOURCES

N-TARGETS

F-PUDECON

P-IXRESIN

P-CONCLIO

P-FSLUDGE

P-FCARTRC

B-IXRESIN

8-CCNCLIG

B-FSLUDCE

P-COTRASH

P-NCTRASH

E-COTRASH

E-N^TRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

N+LOTRASH

F-PROCESS

U-PROCESS

I-LOSCNVL'

I+LOSCNVL

I-ABSLIOD

I+ASSLIOD

I-BIOWAST

11. 100 100

II ;-' 100 140

11 100 '100

11 100 '100

11 :100 100

11 '100 140

11 100 100

21 100 :'100

91 C100 100

21 100 100

51 100 -100

22 100 : IOO

22 100 100

23 100 100

23 -100 100

22 100 100

22 100 100

22 100 100

22 100 100

52 100 100

52 100 100

33 100 '300

33 100 300

33 100 300

33 100 300

33 100 192

33 100 192

31 100 100

31 100 100

51 100 100

51 100 200

51 100 130

52 100 100

52 100 100

52 100 100

52 100 -100

11 100 100

11 100 165

11 600 182

11 100 165

11 100 100

11 100 165

11 240 156

11 100 165

21 200 - 100

51 100 100

21 200 100

51 100 -100

22 150. 100I

22 100 100

23 -200 -100

23 400 100

22 150100

22 300 100

22 200 100

22 400 100-

52 ZOO- 100 '

52 100 100 D

33 128 " 300

33 100 300

33 ' 100 - 165

33 100 300

33 100 192

2 1

1* 3

2' 2

2' 1 12 1 :

31 '2:1 3 v 32

0 20

3 '2

0' 0

O - O2

3 *2

3.;: 2

2 2

2 2'

3 --2

3 2

0 3

0 3

3 3

3 3

3 3 :

3 3'

2 3

2 3

0 3

3 3'

0 'O

2- 0

1 1. I ' :

0 0

3 3 :

0 .0

0 0

2 2

1 1

I, 1 -:

1' 1

1 1'

3 1

3 2-

0 -2"

3- 2-'-

0 *O

3 2

3 2

O~ 2

3 3-

3 3

3 1

3 3

2 ' 3

I

2

1

1'''

1*"

2-

1

1'

I

1'*

1*

1

1'-

I

1-

1'

I

I

1>

1*

1

1'

I

1

1*

1

I

I

1

4-.

3

I

1

I

1**

1

3

3

3

3

3

3

I

1

1:

1**

I

1'

I'

I

£

1

1

I

I'

I''

I

I

3.

1

1'

0 0 1

0 1 - 1

0 '0'- 1

0 0- 1

O ' '' O ' '

o 'I', o ! o -01

O O ; 2

0 O 2-

0 -0 '2

0- 0 0 -- '2I1

0 :0:X1

O '0 '1

O - '0 1

0 0 1

O 1 1

0 1 -1

1 0- 1

1 0 1

1 1 *1-

1 0 -1

I 0 1

0' 1' 1

o 1* 0 a -1 2

O O -2

1 0 *'

o 0 3

O 1 '2

0 1- 1

''0' '' 1

0 1 1

0 1I '1 0 1 1

0 '1 1

0 1 1

0 1 1

0 0 1

0 3 2

0 0 1

0 I 2

0 0 -2

0' o .o 0 "' I0 0 1

0 ' ' 0' X

0 O -0 O0 '1 O 0' 1 0 :01

0 1' 1

0 1 -1

1 10 I

... 0. 1

0010

0110

0010

0110

0010

0110

0010

0000

0000

0000

0000

0000

0000

0000

0000

0000

0000

0000

0000

0000

0000

0010

0010

0010

0010

0010

0010

0000

0000

0000

0310

0210

0000

0000

0000

0000

0000

0210

4210

0210

0210

0210

4210

0210

1010

0510

1010

0510

1010

0000

1010

2020

1010

2020

1010

2020

0000

0000

1010

0010

0210

0010

0010

D-1 05
MILIN2FIL File (cont'd)

I+BIOWAST . 33 .100 192 : 2

N-SSWASTE 31 100 100 0

N-LCWASTE 31 100 100 3

L-NFRCOMP 51 ,100 100 0

L-DECONRS 51 -100 200 2

N-ISOPROD 51 100 200 I

N-HICHACT 52 100 100 0

N-TRITIUFI 52 100 100 3

N-SOURCES 52 100 100 0

N-TARGETS . 52 100 100 0

F-PUDECON 11 .100 100 2

P-IXRESIN 11 '100 200 2

P-CONCLIO 11 600 200 2

P-FSLUDCE 11 *100 200 2

P-FCARTRO 11 100 100 2

B-IXRESIN 11 100 200 2

B-CONCLIG 11 240 200 2

B-FSLUDCE 11 100 200 2

P-COTRASH 61 8000 200 1

P-NCTRASH 51 100 100 0

B-COTRASH 61 8000 200 1

B-NCTRASH 51 100 100 0

F-COTRASH 62 4000 200 1

F-NCTRASH 22 100 100 0

I-COTRASH 23 2000 200 1

I+COTRASH 23 8000 .200 1

N-SSTRASH 22 1000 200 1

N+SSTRASH 22 4000 200 1

N-LOTRASH 22 2000 200 1

N+LOTRASH 22 8000 200 1

F-PROCESS 52 100 100 0

U-PROCESS 52 100 100 0

I-LOSCNVL 33 452 200 1

I+LGSCNVL 33 100 300 3

I-ASSLIOD 33 100 200 1

I+ABSLIOD 33 -100 300 3

I-BIOWAST 33 1500 200 1

I+BIOWAST 33 100 192 2

N-SSWASTE 31 100 100 0

N-LCWASTE 31 100 100 3

L-NFRCOMP 51 100 100 0

L-DECONRS 51 1800 200 1

N-ISOPROD 51 100 200 1

N-HICHACT 52 100 .100 0

N-TRITIUM 52 100 100 3

N-SOURCES 52 100 100 0

N-TARGETS 52 100 -.100 0

F-PUDECON- 11t 100 --100 2

3 .It I .0 10010

3 I- 0 1 10000

3 1 .I *0 10000

0 -1 0 3 20510

0. 4 1 1 10310

0 4 1 1 10310

0 1 0 3 30510

3 I--1 1 1 10000

0 I 0 1 20000

0 1 .0 1 10000

2 1 1 2 1 0410

0 4 0 I 10310

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

.0

3

3

0

.3

'0

3

0

3

3

3

0

0

0

0

3

0

0

2

4 0 I 1 4310

4 -0 1 1 0310

4 0.. 1 10310

4 0 1 1 0310

4 0 1 1 4310

4 0 1 1 0310

4 0 1 1 6312

1 0 3 2 0510

4 0 1 1 6312

1 0 3 2 0510

4 0 1 16311

1 0 0 2 0000

4 0 1 1 5311

4 0 1 1 7322

4 0 1 1 5311

4 0 1 1 7322

4 0 1 1 5311

4 0 1 1 7322

1 -0 1 1 0000

1 0 1 1 0000

4 0 1 1 5311

1 1 0 1 0010

4 1 1 1 0310

1 1 1 1 0010

4 0 1 1 5311

1 1 0 1 0010

1 0 1 1 0000

1 1 0 1 0000

1 0 3 2 0510

4 0 1 1 6312

4 1 1 1 0310

1 0 3 3 0510

1 1 1 1 0000

1 0 1 2 0000

I ,0 1 I0000

I 1 2 1 0410

4 0 1 1 6312

4 0 1 16312

4 .0 1 1 6312

4 0 1 1 0310

4 0 I 1 6312

4 0 1 1 6312

4 0 1 1 6312

4 0 1 1 6312

I O 1 .2 3010

4. 1 16312

1- 0 1 2 3010

4 0 1 1 6311

I 0 0 2 3020

4 0 1 1 5311

4 0 1 1 7322

P-IXRESIN *71 1800 - 200 1 - 0

P-CONCLIQ 71 800 200 1 0

P-FSLUDGE. 71 500 200 1 0

P-FCARTRO 71 100 100 2 0

B-IXRESIN 71 10O0 200 1 0

B-CONCLIQ 71 640 200 1 0

B-FSLUDGE 71 500 200. 1. 0

P-COTRASH 71 8000 200 1 * 0

P-NCTRASH 51 600 100 0 0

B-COTRASH 71 8000 200 1 0

B-NCTRASH 51 600 100 0 0

F-COTRASH 72 4000 200 1 0

F-NCTRASH 52 600 100 0 0

I-COTRASH 63 2000 200 1 0

I+COTRASH 73 8000 200 1 0

-

0-106
-IN2FIL File (cont'd)

N-SSTRASH 62 1000 200 1 0 4 0 .1 .1 5311

N+SSTRASH 72 4000 200 1 0 4 0 1 1 7322 N-LOTRASH 62 2000 200 -1 0 4 0 1 1 5311

N+LOTRASH 72 8000 200 .1 -0 4 0 1 1 7322

F-PROCESS 52 100 100 0 3 1 0 1 1 0000

U-PROCESS 52 100 100 0 3 1 0 1 '1°000

I-LOSCNVL 63 452 200 1 0 4 0 1 1 5311

I+LOSCNVL 33 100 300 3 3 1 1 0 1 0010

I-ABSLIOD 6310000 200 1 0 4 1 1 1 5311

1+A6SLIOD 33 100 300 3 3 1 1. 1 1 0010

I-BIOWAST 63 1500 200 1 0 4 0 1 1 5311

I+BIOWAST 73 100 192 '2 3 1 1. 0 1 0010

N-SSWASTE 31 100 100 0 3 1 0 1 1 0000

N-LOWASTE 31 100 100 3 3 1 1 0 1.0000

L-NFRCOMP 51 100 100 ,0 0 1 O 3 2 0510

L-DECONRS 71 1800 200 1 0 4 0 1 -1 6312

N-ISOPROD 51 100 200 1 0 4 :1 1 1 0310

N-HICHACT 52 100 100 :0 .0 1 0 3 3 0510

N-TRITIUM 52 100 100 3 3 1 1 1 1 0000

N-SOURCES 52 100 100 0 0 1 0 1 2,0000

N-TARGETS 52 100 100 0 0 1 0 1 1:0000

F-PUDECON 71 100 100 2 -2 1 1 2 1 0410

P-IXRESIN 11 100 100 2 1 1 0 2 1 0410

P-CONCLIG 11 100 140 1 1 2 0; 1 1.0110

P-FSLUDGE 11 100 100 1 3 1 0 .2 1 0410

P-FCARTRC 11 100 100 2 2 1 O 2 1 0410

B-IXRESIN 11 100 100 -2 1 1 0 2 1 0410

B-CCNCLIr 11 100 140 1 i 2 0 1 1 0110

E-FSLUDCE 11 100 100 :1 3 1 0 2 :1 0410

P-COTRASH 21 200 100 3 2 1 0 2 1 1410

P-NCTRASH 51 100 100 O 0 .1. -0 3 2.0510

B-COTRASH 21 200 100 3 2 1 0 .2 1 1410

B-NCTRASH 51 100 100 0 0 1 0 .3 2 0510

F-COTRASH 22 150 100 -3 2 1 'O. 2 1 1410

F-NCTRASH 22 100 .100 0 0 1 0 .3 2 0510

I-COTRASH 23 200 100 3 2 , 1 0 2 1 1410

I4COTRASH 23 400 100 '3 2 1 0 2 .1 2420

N-SSTHASH 22 .150 100 2 2 1 0 2 .1 1410

N+SSTRASH 22 300 100 2 2 1 0 .2. .1 2420

N-LOTRASH 22 :200 100 3 2 1 0 2 .1,1410

N+LOTRASH 22 400 200 3 2 1 0 2 1 2420

F-PROCESS 52 ,100 100 0 .3 1 0 1 10000

U-PROCESS 52 100 100 0 3 1 0 1 I 0000

I-LIOSCVL 33 -128 .300 3 3 1 - 2 1 1410

I+LIGSCVL 33 100 300 3 3 1 1 2 1 0420

I-ABSLIOD 33 100 165 3 3 1 1 1 I. 1 0010

I+ABSLIGD 33 100 300 3 3 1 1 1 1 0010

I-BIOWAST 33 100 192 2 3 1 1 2 1 0410-

1+BIOWAST 33 100 192 .2 3 1 1 ,2 1 0420

N-SSWASTE 31 100 100 0 3 1 0 :1 1 0000

N-LOWASTE 31 100 100 . 3 3 1 1 .2 .1 0410

L-NFRCOMP- 51 100 100 0 0 1 0 3 2 0510

L-DECONRS 51 '100 200. 2 O 4 1 1 .1 0310

N-ISOPROD 51 100 200 1 1 3 i .72 1 0410

N-HICHACT 52 ;100 100' O 0 1 O0-,: 3 3 0510,

N-TRITIUM 52 100 .100 3 3 . 1, 1 2 1 0410

N-SOURCES 52 100 300 - 0 1 0 1 :20000

N-TARCETS 52 100 100 O 0 1. 0 2 2 0410

F-PUDECON 11 100 100 2 2 1 1 2 1 0410

P-IXRESIN ,11 . 100. 100 2 . 1 0 .0 .. 10010.

P-CONCLIO, 11 600 182- l 1 3 -0 1 14210

P-FSLUDGE 11 .100 100- 1 .3 1 0- 0 1 0010

P-FCARTRC; 11 100' 100 2 2 1 0 0 1 0110

D-107
I 

I il

IN2FIL File (cont'd)

2-IXRESlN

8-CONCLIG

B-FSLUDCE

P-COTRASH

P-NCTRASH

B-COTRASH

8-NCTRASH

F-COTRASH

F-NCTRASH

I-COTRASH

I+COTRASH

N-SSTRASH

N+SSTRASH

N-LOTRASH

4+LOTRASH

f-PROCESS

U-PROCESS

I-LOSCNVL

I+LOSCNVL

I-ABSLIOD

I+ARSLIOD

I-BIOWAST

I BIOWAST

N-SSWASTE

N-LOWASTE

L-NFRCOMP

L-DECONRS

N-ISOPROD

N-HICHACT

N-TRITIUM

N-SOURCES

N-TARGETS

F-PUDECON

O.OOOE+00

3.531E-01

O.OOOE+00

4.700E-01

O.OOOE+00

8.701E-02

O.OOOE+00

3.531E-02

3.531E+02

1.440E-01

O.OOOE+00

1.567E-02

0. 000E400

3. 531E-01

O.OOOE+00

4.700E-01

O.OOOE+00

8.701E-02

O.OOOE+00

3.531E-0O

O.OOOE+00

2.570E-01

O.OOOE+00

1.214E-01

O.OOOE+00

3.531E-03

O.OOOE+00

O.OOOE+00

O.OOOE+00

O.OOOE400

1 1 100 100 2 1 1 0 0

11 240 156 1 1 3 0 1

1 1 100 100 1 3 1 0 0

21 200 100 3 2 1 0 0

51 100 100 0 0 1 0 0

21 200 100 3 2 1 0 0

51 100 100 0 0 1 0 0

22 150 100 3 2 1 0 0

22 100 100 0 0 1 0 0

23 200 100 3 2 1 0 0

23 400 100 3 2 1 0 0

22 10 100 2 2 1 0 0

22 300 100 2 2 1 0 0

22 200 100 3 2 1 0 0

22 400 100 3 2 1 0 0

52 100 100 0 3 1 0 1

52 100 100 0 3 1 0 1

33 128 300 3 3 1 1 1

33 100 300 3 3 1 1 -0

33 100 165 3 1 3 1 1

33 100 300 3 3 1 1 1

33 100 192 2 3 1 1 0

33 100 192 2 3 1 1 0

31 100 100 0 3 1 0 1

31 100 100 3 3 1 1 0

51 100 100 0 0 1 0 0

51 100 200 2 0 4 1 1

51 100 130 1 1 3 1 0

52 100 100 0 0 1 0 0

52 100 100 3 3 1 1 1

52 100 100 0 0 1 0 1

52 100 100 0 0 1 0 1

11 100 100 2 2 1 1 0

O.OOOE+00 3.531E-04 1.766E-03 3.531E-03

1.766E+00 3.531E4C0 1.766E+02 3.531E+01

0.000E+00 O.OOOE+000 7.000E-03 5.500E-02

6.91CE-01 7.760E-01 9.190E-01 9.58CE-01

O.OOOE+000 0.000+00 1.100E-03 2.147E-03

3.31CE-01 5.807E-01 1.653E+00'2.604E+00

O.OOOE+00 O.OOOE+00 O.OOOE+00 3.531E-04

1.766E-01 3.531E-01 1.766E+00 3.531E+00

5.297E+02 O.OOOE+ 00.0.OOOE+00 O.COE+00

4.300E-01 6.34C--01 9.380E-01 9.700E-01

O.OOOE+00 O.OOOE+00 O.OCOE+00 O.OOOE+00

7.109E-02 1.351E-01 3.636E-01 4.297E-01

O.OOOE+00 3.531E-04 1.766E-03 3.531E-03

1.766E+00 3.531E200 1.766E+01 3.531E+01

O.OOOE+00 O.OOOE+00 7.000E-03 5.500E-02

6.910E-01 7.760E-01 9.190E-01 9.58CE-0l

O.OOOE+00 O.OOOE+00 1.100E-03 2.147E-03

*3.310E-01 5:807E-01 1.653E+00 2.604E+00

O.OOOE+00 3.531E-04 1.766E-03 3.531E-03

1.766E+00 3.5312E00 1.766E+01 3.531E+01

O.OOOE+00 1.OOCE-03 1.000E-03 5.OOOE-03

5.630--01 6.810E-01 9.380E-01 9.740E-01

O.OOOE+00 2.500E-04 2.500E-04 1.730E-03

5.229E-01 8.914E-01 2.669E+00 3.519E+00

O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOCE+00

1.766E-02-3.531E-02 1.766E-01 3.531E-01

O.OOOE+00 O.OOOE+000 0.000E+00 0.000E+OO

7.500E-02 7.500E-02 5.320E-01 7.550E-01

O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00

9.500E-03 9.500E-03 8.724E-02 1.383E-01

1 0010

1 4210

1 0010

1 1010

2 0000

1 1010

2 0000

1 1010

2 0000

1 1010

1 2020

1 1010

1 2020

I 1010

1 2020

1 0000

.I 0000

1 1010

1 0010

1 0210

1 0010

1 0010

1 0010

1 0000

1 0000

2 0000

1 0310

1 0210-

3 0000

1, 0000

2 0000

1 0000

I 0000

1.766E-02,3.531E-02

1.766E+02 3.531E+02

1.33CE-01 1.940E-01

9.900E-01 9.980E-01

6.049E-03 1.201E-02

4.e888E+00 6.936E+00

1.766E-03 3.531E-03

1.766E+01 3. 531E+01

4.000E-03 1.000E-02

9.960E-01 9.970E-01

1.700E-03 2.120E-03

5.660E-01 5.835E-01

1.766E-02 3.531E-02

1.766E+02 3.531E+02

1.33CE-01 1; 940E-01

9.900E-01 9. 980E-01

6.049E-03 1.201E-02

4.S99E+00 6.936E+00

1.766E-02 3.531E-02

1.766E402 3.531E+02

4.200E-02 7.100E-02

9.980E-01 9.990E-01

8.663E-03 1.534E-02

4.e83E+00 5.141E+00

O.OOOE+00 O.OOOE+00

1.'766E+00 3.531E+00

O.OOOE+00 O.OOOE+00

8.430E-01 9.040E-01

O.OOOE+00 O.OOOE+00

2.240E-01 3.864E-01

1. 766E-01

5. 297E+02

3. 870E-01

1. OOOE+00

4. 991E-02

7. 713E+00

1. 766E-02

1. 766E+02

5. 300E-02

1. OOOE+00

1.374E-03

S. 414E-01

1. 766E-01

5. 297E+02

3. 870E-01

1. OOOE+00

4. 991E-02

7. 713E+00

1. 766E-01

5. 297E+02

1. 850E-Ol

1. OOOE+00

6. 751E-02

5. 598E+00

0. OOOE+00

1. 766E+01

0. OOOE+00

1. OOOE+00

0. OOOE+00

8. 654E-01

D-108
IN2FIL File (cont'd)

0.OOOEO400 .OOOE+00 3.531E-04 1.766E-03 3.531E-03

3.531E-01 1.766E200 3.531E400 1.766E+01 3.531Et01

O.OOOE400 O.OOOE+00 1.OOOE-03 1.OOOE-03 5.000E-03

2.570E-01 5.630E-01 6.510E-01 9.380E-01 Y.740E-01

O.OOOE400 O.OOOE+00 2.500E-04 2.500E-04 1.730E-03

1.214E-01 5.229E-01 8.914E-01 2.669E+00 3.519E+00

O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE400

O.OOOE+00 O.OOOE+00 0.000E+00 O.OOOE+00 O.OOOE+00

O.000E400 0.OOOE+O00 .OOOE+000,.OOOE+00 O.OOOE+00

O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00.0.OOOE+OO

0. OOOE+00.0. OOOE+00 0. OOOE+00 0. OOOE+00 .0. O0OE+00

H-3 SETI 1.OOE+09 l.OOE+09.:1.00E+09 1.00E+09

C-14 1.OOE+09 1.00E+09 -1.OOE+09 -1.OOE+09

FE-55 - l.OOE+09 1.OOE+O? ,1.OOE+09-:1.00E+09

NI-59 1.00E+09 l.OCE409 1.OOE+09. 1:OOE+09

CO-60 1.OCE+09 1.OOE409 -1.OOE+09 1.OOE+09

NI-63 r1 OOE+09. 1.00E+09. 1.OOE+09 ,-l;OOE+09

NB-94 .- l.OOE+09 -1.00E+09 -1.OOE+09. l.OOE+09

SR-90 ; -1.OOE+09 1.OOE+09 1.OOE+09 1.OOE+09

TC-99 . .00E+09. l.OOE409 1.OOE+09 1. OOE+09

I-129 .l.OOE+09 ,1.OOE+09 1.OOE+09 l.OOE+09

CS-135 .- 1.OOE+09 1.00E+09 --1OOE+09. I.OOE+09

CS-137 ,-1.00E+09 1.OOE409 1.OOE+09 1.OOE+09

U-235 ; .OOE+09 1.OOE409 -1.OOE+09 l;OOE+09

U-238 1.OOE+09 1. OOE+09 1.OOE+09 1.OOE+09

TRU l.OOE+09 1.002409 1.OOE+09 l.OOE+09

PU-241 .1.OCE+09 1.OOE409 -1.OOE+09 l.OOE+09

H-3 SET2, :1.OOE+09- 1.OOE409 L.OOE+09 1;-OOE+09

C-14 .- -1.OOE+09 1.OOE+09 1.OOE+09 l.OOE+09

FE-55 1.OOE209 1.0409- 1. 00E+09--:1.OOE+09

NI-59 1.OOE+09 1.OOE+09 -1.OOE+09' 1.00E+09

CO-60 , 1.OOE+0009 0 9 -. OOE+09 ,1.O0E009

NI-63 - 1.00E+09 1.002409 1.OOE+09 l.OOE+09

NB-94 1.OOE+09 1.OOE+09 l.OOE+09 l.OOEt09

SR-90 1.OOE+09. 1.OOE+00 1.OOE+09 1.OOE+09

TC-99 1.OOE+09 1.OOE409 1.00E+09 1.OOE+09

1-129 1.OOE+09 1.00+09 1.OOE+09 1.OOE+09

CS-135 -- 1.OOE+09 -1. 00+09 1.OOE+09 1.OOE+09

CS-137 1.OOE+09 1.OOE+09 -1.OOE+09 1.00E+09

U-235 1.OOE+09 1.OOE+09 l.OOE+09 1.OOE+09

U-238 -1.00E+09 1.OOE409 -1.OOE+09 i1..OOE409

TRU 1.60E-02 1.60E-02 .1;60E-02 1.60E-02

PU-241 1.60E-02 1.60E-02 -1;60E-02 1.60E-02

H-3 SET3 1.00E+00 1.OOE+09 1.OOE09 I.OOE409

C-14 -. OOE+00 1.OOE409. 1.OOE+09 -1;OOE+09

FE-55 ,1.OOE+09*, 1.COE+09 1.00E+09 1.OOE+09

NI-59 L.004+00-,1.00E+09 .1.OOE+09 1OOE+09

CO-60 1;OOE+000 -1.OOE+09 1.OOE+09 J1.OOE+09

NI-63 1.OOE+0020 .OOE+009 1.002+09 .1.002409

NB-94 1.OOE+0400 1.OOE4O0? 1.OOE+09 '1.OOE+09

SR-90 , ,1.OOE+00 --I. OOE+09 1.OOE+09 1.OOE+09

TC-99 -.-l1.OOE+-00 1.OOE+09 1.00E+09 1;OOE+09

1-129 1.OCE+200 .OOE+09 1.OOE+09 1.OOE+09

CS-135 1.OOE+00 1.0409 1.OOE+209 .OOE+09

CS-137 1.OOE+000 1.00409 1.OOE+09 1.OOE+09

U-235 1.OOE+00 1.00E+09 1.OOE+09 1.OOE+09

U-238 1.OCE+00 1.OOE+09 1.OOE+09 1.OOE09

TRU 1.60E-02 1.60E-02 1.60E-02 1.60E-02

PU-241 1.60E-02 1.60E-02 1.60E-02 1.60E-02

H-3 SET4 4.00E+01 1.OOE20 1.OOE+09 I.OOE+09

C-14 B.OOE-01 8.00E-01 8.00E-01 8.00E+00

FE-55 7.00E+02 7.00E+04 1.OOE+09 1.OOE+09

1.766E-02

1.766E+02

4. 2OOE-02

9. 980E-01

8. 663E-03

4.1593E400

0. O00E+00

1. OOOE-02

0. OOOE+00

0. 000+E00

5. 000E-03

3. 531E-02

3. 531 E+02

7. 100E-02

9. 9OE-01

1. 534E-02

5. 141E+00

0. OOOE+00

1. OOOE-01

0. OOOE+00

0. OOOE+00

1.730E-02

1.766E-01

5. 297E202

1.850E-01

1.OOOE+00

6. 751E-02

5. 598E+00

0. OOOE+00

5. 000E-01

0. OOOE+00

0. OOOE+00

2.345E-01

D-109
IN2FIL File (cont'd)

NI-59

Co-d-60

NI-63

ND-94

SR-90

TC-99

1-129

CS-135

CS-137

U-235

U-238

TRU

PU-241

H-3 SEtS

C-t4

FE-55

NI-59

CO-60

NI-63

N3-94

SR-90

TC-99

1-129

CS-135

CS-137

U-235

U-238

TRU

PU-241

H-3 SET6

C-14

FE-55

NI-59

C0-60

N1-63

NIB-94

SR-90

TC-99

i-129

CS-135

CS-137

U-235

U-238

TRU

PU-241

2. 20E+00

7. OCE+02'

3. 50E+00

2. OOE-03

4.OOE-02'

3. OOE-O1 -

S. OOE-03

S. 40E+01

1. OOE+00

4. OOE-02

5. OOE-02

1. 60E-02

q AMF-O1

2.20E*C0' 2.20E+00' 2.20E+0I

7.00E404 t.OOE+09 1.OOE+09

7.00E401 7.OOE+01 7.OOE+02

2.COE-03 2.OOE-03 2.OOE-02

1.50E+02 *7.OOE+02 7.OOE+03

3.OOE-01 3.O0E-05' 3.OOE+00

8.00E-03' 8.OOE-03 9.'OOE-02

8.40E+01 8.40E+01- e.40E+02

4.40E+01' 4.60E+03 4.60E+04

4.00E-02 4.00E-02' 4.OOE-01

5.00E-02 5.OOE-02 5.OOE-01

t.60E-02''1.60E-02 1;60E-01 5;'60E-OI- S.6AO-01 5.6AOE+O

4.OCE+01 1.OCE0O4 I.OOE+09 S.OOE+09

S'. OOE-01' 3.00E-01- 8.0ooE+OO B.OOE+O

7.OOE+02 '1.OOE+09' 1.OOE+09 1t;OOE+09

2.20E+00- 2.20E400 2. 20E+01 2. 20E+02

-7.'00E+02 1.OOE+09' 1.OOE+09 l.OOE+09

3.5CE+00 7.00_+01 '7.OOE+02 7.OOE+03

2.OOE-03 2.OOE-03 2.OOE-02 2.OOE-01

4;0CE-02 t1.'OE+02 7.OOE+03 7.OOE+04

3.OOE-01 3.00E-01' 3.OOE+00 3.OOE+01

9.OOE-03 -8.00E-03 8.00E-02 8.O0E-Ot

9. 40E+01 8.4CE+O1' 8.40E+02 8.40E+03

l.OOE+00 4.40E+01'-4.60E+03 4.60E+04

4.OOE-02 4.OOE-02 4.0OE-01 4.OOE+00

5.OOE-02 5.OOE-02 5.'OOE-01 5.00E+00

1.60E-02 1.60E-02 t'.60E-01 1.60E+00

5.60E-01 5 60E-01' 5.60E+00 5.60E+01

0.00 S.OOE+09 i.OOE+09 S.OOE+09

0.00 8.00E-01- e.OOE+00 8.00E+01

0.00 S.OOE+09' t.OOE+09 1.OOE+09

0.00 2.20E+00 2.20E+01 2.20E+02

0.00 I.OOE+09 I.OOE+09 t.OOE+09

0.00 7. 00E401 7.OOE+02 7.OOE+03

0.00 2. OOE-03,- 2.OOE-02 2.OOE-01

0.00 t.50E+02 7.OOE+03 .7.OOE+04

0.00 3.OOE-01 3.00E+00 3.OOE+01

0.00 9.0OOE-03'- e. OOE-02 8.O0E-Ot

0.00 8.40E+01' 8:40E+02 8;40E+03

0.00 - 4:40E+01 4.60E+03 4.60E+04

0.00 4.COE-02 4:00E-01 4.;OOE+00

0.00 5.OOE-02 5.'O0E-01 5.OOE+00

0.00 1.60E-02 1.60E-01 1.60E+00

0.00 5.60OE-01 5.60E+00 5.60E+01

D-11 0
eras' rT.. -

APPENDIX E

ERRATA FOR THE DRAFT ENVIRONMENTAL IMPACT STATEMENT

FOR 10 CFR PART 61
APPENDIX E

ERRATA FOR THE DRAFT ENVIRONMENTAL IMPACT STATEMENT

FOR 10 CFR PART 61

Location in DEIS Errata

Volume 1, page 3,

last paragraph

Volume 2, page 20, second

and last paragraphs

.-

The reference to 40 CFR 501.7 should

read 40 CFR 1501.7

Insert after the words "site owner" the

phrase (State or Federal government).

!"Maximum annual thyroid doses are in the

range of 850 mrem at the intruder and

population wells...." should read ''Maximum

annual thyroid doses are in the range of

850 mrem at the intruder and boundary

wells...."

Volume 1,

paragraph

page 20, second

; , ,

.; .

Volume 1, page 23, third

paragraph .

volume 2, page xi, first line

I . . ., . , if

The word "quickly" should be removed from

the phrase, "Due to radioactive decay, however, the potential hazard quickly drops...."

"Chapter 10" should read "Chapter 9"

- Volume 2, page 4-8, second, "Over the next 1500 years, however, potenparagraph tial exposures are reasonably constant and

are still at about 800 mrem of 2000 years"

should read "Over the next 1500 years, however, potential exposures are reasonably

constant and are still at about 800 mrem

at 2000 years."

* E-1
Location in DEIS Errata

Volume 2,

paragraph

page 5-57, second Under Case 10A, the sentence "Waste spectrum

2 is assumed" should read "Waste spectrum 1

is assumed"

Volume 2, page 6-3 The numbers in the table at the top of the

page are in units of millirem per year or

mrem/yr

Volume 2,

paragraph

Volume 2,

paragraph

page 6-11, last

page 7-8, fourth

In the fifth line of this paragraph, the

number ".033" should be changed to ".33"

"For shorter-lived radionuclides such as

C-137...." should read "For shorter-lived

radionuclides such as Cs-137.....

Volume 2, page 7-22

Volume 2, page 9-6

The next-to-last line under Mixtures of

Radioistopes should have a closing

parenthesis after the word "...cm ... "

Since the draft environmental impact statement on 10 CFR 61 was written, the state of

Washington has increased its perpetual care

and maintenance funding. The following

revisions should be noted:

a. The Perpetual Care and Maintenance

(PC&M) Fund contribution by US' Ecology,

currently at $0.275 per cubic foot, will

increase to $1.75 per cubic foot. This

renegotiated contribution will provide

E-2
Location in DEIS Errata

-J. .

a total fund'of approximately $6 million

by July 1, 1985. The total accumulation

will be determined by the actual volume

of waste disposal.

b. In addition, US Ecology will contribute

$0.25 per cubic foot of waste disposed

to a newly established Contingency

Closure Fund. A contribution at this

rate will yield a fund of $800,000 by

July 1985, assuring that the State of

Washington will be able to adequately

close the radioactive waste disposal

operations conducted at the site if

and when needed.

I . . I ., I

.

I . f

. . .I

.I

. . . . .

j A: ,. - -;

,,, , i

1- ^ -

Voiume-3,

; O: n - .

.. , r.

... :

r "; , ,: ': '

.: . ;., .' ' .-

Appendix E! , .

C. On January 15, 1982, the company will

post a surety bond in the amount of

$500,000 for a period of one year to

* protect the state if the company

should leave the site without meeting

closure conditions as stated in the

license.

, page E-21

; .........

* ; .a i;

Concentrations listed in-Table E.2 should

be in micrograms per cubic meter (pg/m3),

not milligrams per cubic meter (mg/m 3).

Also, the EPA standard for S02 should be

80 pg/M3 as opposed to 60 pg/m3 which is

shown in the table.

i:.. ... .. .

. . .:

'- I . :. Z

E-3
_Im!

Location in DEIS Errata

Volume 3, Appendix E,

page E-47, third paragraph

Volume 3, Appendix E,

page E-50, first paragraph

The first two sentences in the third paragraph should be deleted and the following

sentences inserted as a new paragraph:

"Waste is emplaced in the trench, and backfilled with dirt removed during trench

excavation. Typically, waste packages are

emplaced with the aid of construction equipment such as cranes and forklifts, using a

combination of stacked and random disposal.

Waste packages such as wooden boxes or steel

bins having rectangular dimensions are

generally stacked in place while low activity

drummed waste is generally emplaced in a more

random manner. Special care is taken during

emplacement of higher activity waste such as

high activity ion exchange liners to ensure

operational safety. This combination of

random and stacked disposal is termed "random

disposal" in this EIS (to distinguish it from

a placement alternative of fully stacked

disposal: see Appendix F) and results in a

trench volume efficiency of about 50%."

The next-to-last sentence should be modified

to read as follows: "If through a site

accident, a worker may receive an open wound

and the wound is suspected of having become

contaminated, a radiation survey is also

performed. The survey is performed for beta

and gamma contamination, and also for alpha

contamination if alpha emitting isotopes are

suspected."

E-4
o I

Location in DEIS Errata

Volume 3, Appendix E, page E-48 The last sentence in Section

modified to read as follows:

of the survey are recorded.

5.2.3 should be

The results

Volume 4, Appendix J,

third paragraph

Volume 4, Appendix K,

page K-50, last paragraph

Volume 4, Appendix N,

page N-19, last paragraph

For the last sentence change "underlain" to

"overlain."

See the changes listed earlier in this appenddix under Volume 2, page 9-6.

The phrase "National Primary Drinking Water

Regulations" should be replaced with "Interim

National Primary Drinking Water Regulations."

Volume 4,

page Q-44

Appendix Q, The last term in the equation contains two

typographical errors. It should read as

follows:

ITo PV80 ( 1+j)m j

Vw [(l+i)ITo-1] (1+4i)TC

E-5
APPENDIX F

FINAL RULE AND SUPPLEMENTARY INFORMATION
[7590-01)

-NUCLEAR REGULATORY COMMISSION -

. ' 10 CFR PARTS' 2, 19, 20, -21, 30, 40, 51', 61, 70, 73 and 170

Licensing Requirements for Land Disposal of Radioactive Waste

AGENCY: Nuclear Regulatory Commission. -

ACTION: Final rule.

SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its regulations to provide specific requirements for licensing the land disposal

of low level radioactive wastes containing source, special nuclear, or

byproduct material. The amendments provide licensing procedures,

performance objectives, and technical criteria for licensing facilities

for the land disposal of radioactive waste. Specifically, the regulations

establish performance objectives for land disposal of waste; technical

requirements for the siting, design, operations, and closure activities 6t ; ' -. zs , w. - . ; - ' ' 6

for a near-surface disposal facility; technical requirements concerning

the waste form that waste generators must meet for the land disposal of

waste; classification of waste; institutional requirements; and admin-

-:J - - '''

istrative and procedural requirements for licensing a disposal facility.

Amendments to other parts are established to govern the certification

and use of shipping manifests to track waste shipments and clarify, but 6-, - ' [ , . ';¢ &J' ,- i ,,! . 'i

not substantially modify, the requirements of existing regulations. [i i ' < - t -wL,_I),'a* 

Provisions for consultation and participation in license reviews by State

governments and Indian tribes are also included. Specific requirements

for licensing facilities for the disposal of radioactive wnstes other than

high level waste by alternative land disposal methods will be proposed

a. 1
I JI Me

[7590-01]

in subsequent rulemakings. Disposal of radioactive wastes by an individual

licensee will continue to be governed by 10 CFR Part 20.

EFFECTIVE DATE: 10 CFR 20.311 of Part 20 effective date is 365 days

after publication in the Federal Register, 10 CFR Part 61 and all other

changes effective 30 days after publication

in the Federal Register.

FOR FURTHER INFORMATION CONTACT: Paul H. Lohaus, Low-Level Waste Licensing

Branch, Division of Waste Management, Office of Nuclear Material Safety and

Safeguards, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555,

telephone (301)427-4500.

SUPPLEMENTARY INFORMATION:

Background

On October 25, 1978, the Commission published an Advance Notice of

Proposed Rulemaking (43 FR 49811) regarding the development of specific

regulations for the disposal of low-level radioactive wastes (LLW). The

development of these regulations was in response to needs and requests

expressed by the public, the Congress, industry, the States, the Commission, and other Federal agencies for codification of regulations for the

disposal of LLW. The respondents to the advance notice strongly supported

the Commission's development of specific criteria and standards for the

disposal of low-level waste. The comments received by the Commission on

the advance notice were used by the Commission in scoping the form and

content of the draft Environmental Impact Statement (EIS) (NUREG-0782)

and the regulation.

2
[7590-01]

On February 28, 1980, the Commission also published a Notice of

Availability of.a preliminary draft regulation; dated November 5, 1979,

announcing availability-of the draft for public review.and comment (45 FR

13104). This-was done to help ensure wide.distributiontand early public

review and comment on the development of the rule. Copies of this draft

regulation were~distributed to all of the States.

-During the summer and fall of,1980, the Commission also sponsored

four regional workshops.to provide an-opportunity for open dialogue

among representatives of the States, public interest groups, industry,

and others on the issues to be addressed in the Part 61 rulemaking.

*These'workshops'were particularly useful in formulating our positions on

the more judgemental aspects of the rule and underlying assumptions (such

* as the length of'time we should assume that active'governmental'controls

could reasonably'be relied on).'

Proposed 10 CFR Part 61 and conforming amendments were published on

July 24, 1981 (46 FR 38081). The original comment period was due to

expire October 22, 1981, but was extended to January 14, 1982 to coincide

with the 90-day comment period for the supporting draft EIS (NUREG-0782).

The availability of the draft EIS was announced on October 22, 1981

(46 FR 51776). The proposed rule was sent to all Commission licensees

and copies were provided to Agreement State officials to distribute to

their licensees.

Public comments were received on both the rule and draft EIS and

may be examined at the Commission's Public Document Room (PDR) located

at 1717 H Street NW., Washington, D.C. Comments on the rule are available

at the PDR Docket No. PR-2 etfal'(46 FR 38081). Comments on the draft EIS

are available at the PDR-referencing Docket'No. PR-61 (46 FR 51776).

3
[7590-01]

A total of 42 persons commented on the draft EIS.- These commenters

represented a variety of interests'. Comments'were received'from 21 States,

8 industry/utilities, 8 Federal agencies/laboratories, 3 individuals and

2 broker/disposal firms.' The comments generally raised or echoed the

same issues raised concerning the rule except that some questions on the

methodologies and presentation of results were raised. A detailed

analysis of the "comments on the draft EIS will be included as an appendix

to the final EIS (NUREG-0945) which is being prepared.*

OVERVIEW OF COMMENTS ON 10 CFR PART 61

A total of 107 different persons submitted comments on the proposed

10 CFR Part 61. The commenters represented a variety of interests. Comments were received from: 19 industrial groups, 17 state groups, 15 individuals, 13 utilities, 9 federal agencies or laboratories, 6 universities,

4 medical groups, 4 engineering firms, 4 public interest groups, 4 professional organizations, 3 broker/disposal firms, 2 legal groups, 2 surety

groups, and 5 others. Commenters offered from one to over 20 comments

each. The topics addressed a wide range of issues and all parts of the

rule.

The general response was quite favorable. Almost half (47) expressed

explicit support of the rule or overall approach. Many of these commenters

expressed some concern about one or a few specific provisions and most

offered suggestions for improvements. Many expressed the view that the

rule provides a needed and adequate framework for establishing additional

*Copies of this report may be obtained by, written request to the Division

of Technical Information and Document Control, Washington, D.C. 20555.

Copies will also be made available for inspection or copying for a fee

at the NRC Public Document Room, 1717 H Street NW., Washington, D.C.

4
[7590-013

low-level waste disposal capacity. The importance, reasonableness, and

clarity of the rule were noted. Support was expressed by almost every

sector.

Only 15 commenters expressed any outright opposition to the rule or

some significant portion of the role. Most were individuals. No state

group or current disposal site operator expressed opposition. The

opposition expressed appeared to stem from objections to nuclear power

and use of radioactive materials, opposition to shallow land burial as a

disposal method in general and for TRU wastes in particular, opposition

to perceived increase in costs to waste generators, the regulatory burden

of the licensing process, and the technical requirements in Subpart D of

the proposed rule. Several of the commenters that expressed opposition

offered suggestions for improving the rule, however.

Most of the remaining commenters (45) offered constructive comments

without taking a general position on the rule, or offered support with

reservations about one or more aspect of the rule.

All concerns expressed by all commenters are discussed in detail in

a staff analysis of comments which is available in the PDR. Because the

volume of comments and analysis in detail occupy several hundred pages,

the following discussion summarizes and responds to all comments of major

and generic significance. For example, comments on Part 61 standard

provisions that are common to all Commission regulations are not discussed

in this summary, but are covered in the document available in the PDR.

SUMMARY OF COMMENTS FOR-PROPOSED PART 61

Subpart A:' General Prdvisions

A variety of comments were received that related to the scope of

the rule. Two clarifying changes were made to make it clearer that uranium

5
13LML

[7590-01]

and thorium tailings as defined in Section 11e(2) of the Atomic Energy Act

of 1954, as amended, are not subject to the requirements of Part 61, but

are disposed of according to requirements in 10 CFR Part 40. In addition,

clarifying changes were made to state that the requirements of Part 61 do

not apply to persons who are licensed by an Agreement State pursuant to

authority relinquished to that State by the Commission in accordance with

Section 274 of the Atomic Energy Act of 1954, as amended.

Some commenters felt that provisions should be made for an individual

to dispose of his or her own waste. Private waste disposal may be licensed

under current provisions of 10 CFR Part 20. The Commission feels that

these provisions are adequate and that no change to Part 61 to accommodate

private disposal is warranted.

At least two State commenters asked about Agreement State requirements

being compatible with Part 61. The Commission is preparing guidance for

States that will consider Section 61.2, Definitions; Subpart C, Performance

Objectives; Subpart D, Technical Requirements for Land Disposal Facilities;

those portions of Subpart B that are necessary to implement the provisions

of Subparts C and D; and Section 20.311, Transfer for disposal and manifests;

and that portion of Subpart E requiring closure funding arrangements as a

matter of compatibility for the Agreement States. Guidance will identify

those aspects where uniformity is desirable and those aspects where States

would have flexibility in establishing their own requirements.

It was suggested that construction of a disposal facility should be

permitted to begin before a license is issued. The Commission believes

that to do so would have a detrimental effect on the decision making

process and therefore no change is being made to this provision.

6
[7590-01)

In the proposed rule, near surface disposal was defined in § 61.2

and discussed in § 61.7 as disposal in the upper 15-20 meters of the

earth's surface. Based orf comments received, the wording could be

misinterpreted to mean that disposal was allowed o-nly between 15 and

20'meters or that deeper disposal was prohibited." The wording was clarifled to make it consistent withthewaste classification'requirements.

' (Class' A and B wastes' have no minimum depth requirfeme~nt and Class C

' wastes have a 5 meter depth requirement'when relying on depth alone.)

Disposal'at depth greater than5 meters would also be acceptable.

; Subpart B: Licenses

Comments received on Subpart B covered a wide range of issues. Many

} were concerned with'clarification and intent. There were, however, several

| 'issues that were more substantive and-addressed by-a large group of commenters.

Several commenters were concerned that the language in several places

required the applicant to demonstrate in the application that certain

objectives were met. Their concerns were'over what would constitute a

1demonstrationi;and'the impossibility-of meeting an objective-with complete

* certainty as implied by the language in thesrule. ThetCommission agrees

with these~commenters and~changes have been'made-in appropriate places to

- indicate that what'the-Commission wants- is information or analyses that

* ' will provide reasonable assurance that the objective or requirement will

be met. Other.minor changes were made-for purposes of clarification.

An advisory statement-in.§61.13 that the ground water pathway was

-generally the most-significant for near surface 'disposal, in terms of

releases of radioactivity, was deleted. This section requires an analyses

7
I I II!II

[7590-01)

of all potential pathways and two commentators objected to singling out

ground water.

Several commenters expressed concern over the length of time that

the licensing process might take and suggested limits be established in

the regulations. The Commission does not believe that this is practicable, considering the uncertainties in predicting the quality of future

applications, the availability of staff resources at critical times, and

the potential for hearings. The licensing process must be in accordance

with the Commission's mission to protect public health and safety but

the Commission does agree that the licensing process must be carried out

in the minimum amount of time consistent with this mission. Some changes

in the procedural aspects of the rule are being.made with this in mind

(see comments, Subpart F). The Commission staff is developing-technical

positions to assist applicants in preparing their applications and is

developing performance assessment capabilities that will enable the staff

to perform timely reviews.

Nine commenters addressed the language in §61.25 that prevents the

licensee from making any changes in the facility or procedures described

in the application except as provided for in specific license conditions.

The commenters felt that this was unnecessarily restrictive, in that there

may be aspects of the facility or procedures that were described in the

application, but which are not important to public health and safety and

the licensee should be free to change them. The Commission agrees, since

it was not intended that all changes be subject to Commission review or

approval, only those important to public health and safety. Section 61.25

is changed accordingly.

8
[7590-01]

Over a dozen commenters raised objections to the requirement that

the license be renewed on the usual five year interval with a concomitant

public notice on the opportunity to request a public hearing. The dominant

reason for these objections is the burden that is perceived if public

hearings were held every five years at the time of license renewal. The

Commission believes that a periodic reassessment by the licensee and the

Commission staff is necessary. This reassessment should factor in the

past operating experiences of the disposal facility, the results of monitoring data, changing economic conditions that might affect financial

assurances, advances in technology, etc. While there are alternatives

to license renewal in order to ensure these periodic reappraisals, the

Commission has found through its experience that periodic license renewal

is the most effective method. As for the public notice of the reniewal

and the notice of opportunity to request a public hearing, the Commission

agrees that this is not necessary and it has been deleted. Deleting this

requirement will not have an adverse effect on the public's interest and

rights. According to revised §6125, any changes to the license conditions from a license renewal process would be subject to notice and opportunity to request hearings if the conditions were in the highest category

specified in that section (paragraph 61.25(a)(1)).

Two commenters suggested not subjecting the licensee to an opportunity

for hearings at the time of site closure. The Commission believes that

this is an important and worthwhile time to provide for public participa- ,; : 'j i ' ,5 S . . :.. :t 4 ' :. a 

tion. No changes were made.

While none of the commenters took exception with the need for a period

of post-closure observation and maintenance by the licensee, a number

did object to the open-endedness of the requirements that this period be

9
-, _ _ I - I _ _ _ _ - 'U M

[7590-01]

for "a minimum of five years." This provision has been changed to state

that the period will normally be five years, but that shorter or longer

periods may be approved by the Commission in connection with the approval

of the site closure plan for a specific site.

Several commenters, including Chem-Nuclear Systems, Inc., and U.S.

Ecology, the operators of the existing disposal facilities, were concerned

about possible delays in transfer of the license to the site owner at

the end of the post-closure observation period. They foresee the possibility of more stringent requirements being imposed at this time, thereby -

delaying the transfer with an adverse effect on the ability of the

licensee to affect proper closure due to changes beyond the financial

requirements initially established. The Commission recognizes this

possibility, but it is beyond the Commission's authority to control or

regulate the site owner and force the transfer to take place. Any

requirements for transfer that are outside the public health and safety

considerations prescribed by Part 61 become a matter of contract or agreement between the site owner and the site operator. With the Low Level

Radioactive Waste Policy Act laying the responsibility for disposal of

low level waste on the States, it is obvious that the States will play

an increasingly important role. State authorities, who in all likelihood

will be the site owners, should become active participants in the disposal activities from the earliest stages of development through site

closure and stabilization so that at the time of site transfer to them

for institutional control, there are no unforeseen obstacles to the

orderly and timely transfer. Part 61 provides for this participation in

the licensing process, and as landlord, there are other avenues of

participation.

10
[7590-013

Subpart C: Performance ObjectivesA dozen commenters addressed the approach taken-in Part 61 to establish performance objectives supplemented-by some minimum technical require-

-ments..:--All commentersexcept three supported the approach of addressing

disposal from an overall systems standpoint,. i.e., establishing overall

performance objectives and minimum technical requirements and leaving

..considerable flexibility on how an applicant-or licensee would -design -

and operate a site.- Of the three who disagreed, one felt that the conicern-for~public health and safety is so great that.the rule should be

...based on prescriptive requirements; one felt that there should be no

technical requirements in the rule, only performance objectives; and the

third felt that the rule is restrictive by establishing both performance

objectives and technical requirements. The comments were judged-overall

to be-sufficiently supportive, that no changes have been made In -this

regard. - .

One commenter challenged the performance-objectives in .Part.61 as

being premature in advance of relevant-EPA-standards and beyond-the

agency's authority to the extent that they are not -already embodied in

10.CFR Part 20 and that they are unduly.stringent and unsupported. With

respect to this comment, EPA, under its ambient environmental standards

setting authority.assigned by Reorganization Plan No. 3 of 1970 has the

authority to prepare a.-standard that will-set limits-for releases of

-radioactivity.to the general .environment from disposal -facilities.

Presently therelis no such EPA standard. In-thel.absence.of such a stand-

-ard, the Commission examined a range of limitsiwhich bound that-expected

for the EPA standard and selected a-proposed performance-objective that

11
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establishes a release-limit for the site boundary, a regulatory action

within the limits of NRC authority. In a rulemaking action, the Commission is not solely limited to existing standards in Part 20 and the

Commission does not intend to withdraw any portion of the rule that may

be related to the performance objectives.

With regard to the specific performance objective for releases to

the environment, the Environmental Protection Agency commented that the

establishment of an individual exposure limit at the site boundary for

releases as proposed in §61.41 is appropriate. They stated that the

range of 1 to 25 mrem/yr analyzed by the Commission was a reasonable

range that should encompass any standard which EPA might derive for low

level waste disposal facilities. Based on the Commission's analysis,

NRC does not anticipate any need to change the technical requirements

of Part 61 to meet a future EPA standard. In their comments, EPA stated

their opinion that it was inappropriate to apply the EPA drinking water

standard as proposed in §61.41. Accordingly, this part of the performance objective has been deleted. However, this does not diminish the

Commission's concern over protecting sources of drinking water. The

Commission will assess the potential impact on drinking water supplies

as part of its licensing review.

Reaction to the proposed performance objective to protect potential

inadvertent intruders was mixed. There were some who felt the proposed

500 mrem whole body dose to the intruder was too high, some felt that it

was the right value for a standard, and others felt that higher values

were in order. Those that felt that the standard should be higher

suggested values of 5 rem or 25 rem (the Department of Energy) to correspond to limits for occupational exposure or one-time exposures to workers

12
[7590-01]

from potential accidents. A number of commenters, in their comments about

considering the probability that intrusion will occur, expressed concern

about weighting too heavily the protection against inadvertent intrusion

in determining disposal requirements for waste. Based on these comments,

the Commission believes that the primary concern of those who feel that

the intruder protection objective is too restrictive is the effect that

this has on the concentrations of certain nuclides"that are acceptable

for disposal in a near surface facility and the need to meet additional

requirements such as stability for some wastes. With this in mind, and

in response to other comments, the Commission has reevaluated the calculations that establish the waste classification concentration limits to

eliminate unnecessarily conservative assumptions with the result that

the analysis is more realistic and the limits for several important

isotopes have been raised. With this action, the Commission believes

that most of the concerns of those who encouraged higher exposure limits

or less emphasis on protection of intruders will have been met.

With respect to those who suggested that lower limits would be appropriate, there were no compelling arguments or technical demonstrations

presented that persuaded the Commission to lower the dose limit for

intruders.

The EPA recommended that the 500 mrem dose limit be deleted from

the performance objective, since the licensee would not be able to monitor or demonstrate compliance with a specific dose limit'that applies to

an event that might occur hundreds of years from'"now. They did recommend use of the 500 imem whole body dose limit coupled with ALARA as the

basis for determining the concentration limits in Table 1 of Part 61.

13
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[7590-01]

The 500 mrem dose limit has been deleted from the performance objective

but retained as the basis of the waste classification limits.

Comments were offered that more emphasis should be placed on requirements, such as the use of durable monuments to warn potential intruders.

This concept is incorporated in the regulation.

Acts of terrorism and sabotage were identified as possible intrusion

problems and suggestions were made for protecting against such acts.

The Commission does not feel that the likelihood of such events or the

magnitude of the effects of such acts are sufficient to warrant requirements in this regard.

EPA asked for a clarification of the intent of the performance objective in §61.43 as it pertains to effluents from the site. This performance

objective states that operations at the land disposal facility must be

conducted in compliance with the standards for radiation protection set

out in Part 20. Part 20 contains standards for concentrations of

radioisotopes in air and water released from a licensed facility. Section 61.41 sets forth limits on concentrations of radioisotopes released

from a land disposal facility which are lower than those in Part 20. It

is the Commission's intent that the provisions of Part 20 will apply to

all aspects of radiation protection during operation except for releases

of radioactivity from the site which will be governed by the more stringent

requirements of §61.41. The rule has been modified to clarify this point.

Commenters pointed out a need to be clearer in the rule on how the

principle of maintaining radiation exposures to a level that is as low

as reasonably achievable (ALARA) will be handled. The Commission intends

that the ALARA principle apply to the performance objectives for long-term

environmental release and protection of individuals during site operations.

14
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It cannot apply to the intruder performance objective, since Part 61 sets

out the requirements for protection and intrusion which is beyond the

disposal facility licensee's control. Appropriate changes have been made

in §§66.41 and 61.43 to reflect the ALARA principle.

Subpart D: § 61.50, Disposal Site Suitability

for Near-Surface Disposal

Approximately two dozen commenters offered comments on various

aspects of § 61.50, addressing disposal site suitability requirements.

These comments address eight subject areas which are discussed below.

Eight comments were received on the requirement that the disposal

site shall be capable of being characterized, modeled, analyzed, and

monitored. The comments were directed to the perceived vagueness of the

requirement, i.e., what does it mean to be capable of being characterized,

modeled, analyzed, and monitored? Some commenters offered suggested

rewording or examples. The Commission has issued a staff technical

position (NUREG-0902) that provides interpretation and explanation of

the meaning and intent of this requirement. In the technical position,

it is explained that the site characteristics must be such that limited

site characterization can adequately define the site characteristics

spatially across the disposal site and that site characteristics should

vary with a sufficiently narrow range so that the input to modeling is

representative of the hydrogeologic units and the assumptions underlying

the modeling are valid. Further, natural processes affecting the disposal

site should be occurring at a consistent and definable rate such that

the modeling of the site will represent both present and anticipatable

15
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[7590-01]

site conditions after closure. Finally, site characteristics must be

such that a reasonable number of monitoring points can adequately describe

the extent to which radionuclides have migrated from the waste disposal

units. In addition, the Commission's staff is developing an in-house

modeling capability and will share that capability through pre-qualification

of prospective computer codes. The Commission believes that a concise

statement in the rule along with guidance on these subjects provided by

technical position papers and Regulatory Guides is appropriate.

Several aspects related to ground water were addressed in the comments. Three commenters (Ontario Hydro, the Department of Interior, and

the Department of Energy) endorsed the provision in § 61.50(a)(7) that

permits disposal below the water table where diffusion dominated the

ground water flow system.

The Department of Interior recommended using the term, "molecular

diffusion" and both they and Ontario Hydro suggested specifying a limit

for soil hydraulic conductivity of less than 10-6 cm/sec, as appropriate.

There were several commenters who disagreed with this provision and recommended total containment or some minimum depth to the water table.

The Commission envisions a site that would satisfy the exception in

section 61.50(a)(7) as one with an inactive flow system so that the water

which would contact the wastes would move on the order of less than one

foot per year. Given the low hydraulic conductivity and effective porosity of the soils, very little water would actually contact the waste or

flow from the disposal units. The travel time will result in sufficient

reduction of concentration of the small amounts released and fine-grained

soils will typically provide significant attenuation for most radionuclides. No change has been made to this provision of the rule.

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[7590-01)

Several commenters suggested requirements on retardation properties

for soils, both impervious and porous. One suggested a leachate collection and treatment system for the impervious soils. The Commission

does not consider it appropriate to set forth specific values for characteristics which promote attenuation of radionuclides. Whereas attenuation is advantageous for some radionuclides, others such as H-3, C-14,

and I-129 may not be significantly attenuated. The Commission believes

that reliance should be placed on siting requirements which will keep

water away from wastes, result in low volumes of contaminated water being

released, and provide a long travel time for decay. The Commission takes

exception to any design which relies on a leachate collection and treatment system to reduce migration. Such a design is expected to result in

a requirement for continued active site maintenance, therefore violating

the performance objective in § 61.44.

Several comments recommended that the natural resources considered

under § 61.50(a)(4) specifically include ground water and aquifers underlying the site and that the resources of significance were not limited

to "economic" significance. Another suggested that the resources be

"known" resources so that the applicant would not have to engage in an

extensive exploration program to assure that there were no significant

natural resources. The Commission considers ground water and aquifers

to be natural resources in the context of this requirement. The Commission also agrees that it should not be necessary to conduct extensive

exploration studies to prove that no resources exist. Several changes

have been made in the sections relating to ground water to reflect these

comments.

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Commenters raised four questions on the siting requirements related

to surface water drainage. These 'can be summarized as (1) definition of

certain terms such as upstream drainage areas, coastal high-hazard area

and wetland; (2) the adequacy of the exclusion of waste disposal based

on the 100-year floodplain; (3) whether engineering drainage modifications

can be made in order to meet the requirements; and (4) the vagueness of

some terms.

With respect to the terms "coastal high-hazard area" and "wetland,"

these are defined in Executive Order 11988, Floodplain Management Guidelines which is noted in the rule. The term "upstream drainage area" can

be defined in conventional hydrologic terms as all the land surface

which drains, either by channel flow or sheetwash, across the disposal

facility.

The 100-year floodplain is that land which would be inundated by a

flood having a 1 in 100 chance of occurring in any particular year. The

Commission feels the major hazard due to flooding is associated with the

period of site operations when disposal units are open. Because of other

provisions of the rule, the disposal units will be open a comparatively

short time. Once closed, the covers and site drainage system will provide

protection against the effects of flooding. The Commission considers

300 or 500-year floodplains to be unnecessarily restrictive; and questions whether an adequate data base or standard methods of determining

such floodplains exist.

The question on engineering modifications will be addressed more

fully in staff technical positions related to site suitability, selection and characterization and to site design and operations. Engineering features may be used to improve site drainage and protect against

flooding during operations.

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With respect to the vagueness, or non-prescriptive, nature of the

requirements, the 'Commission considers 'the siting'requirements 'as site

screening tools which will be met in'most cases and which, if not met

fully, would require a site-specific evaluation to determine whether an

exemption is warranted.' The Commission finds this preferable to treating more prescriptive siting requirements as exclusionary.

Minor changes of a clarifying nature he're been made'to the requirements related to flooding.

Several commenters suggested that radioactive waste'disposal facilities could be colocated with hazardous waste disposal facilities. The

Commission-does not object to this' as long 'as' the'facilities are separated

Trom one another and the wastes 'are not comin6led.':- The provisions of

§ 61.50 pertaining to nearby facilities not adversely impacting the

ability of the site to meet the performance objectives or significantly

masking the environmental monitoring program-would'have to be met.

Several comme'nters raised the question of relevance of-seismic or

volcanic hazards to low level waste disposal, given' the orders'of magnitude

difference 'between the time frames for those geologic phenomena and the

hazard'of the low-level wastes. Concern'was als6 expressed that certain

areas, such 'as California, would have all potential' sites eliminated by

the requirement to avoid seismic areas.

- 'The requirement, as written, provides the Commission a mechanism

for site specific evaluation'of such factors'as recurrence intervals,

probabilities, liquefaction potential, and ground accelerations to compare

against'a long-term (500-year) radiological hazard and the disposal requirements of Part 61. This minimum technical requirement would not arbitrarily

eliminate potential sites'so much as it would provide a site screening

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[7590-01]

test which will be met in most cases and will mandate a thorough evaluation

of site performance in areas of known tectonic hazards.

Several persons commented on the reliability of long term projections

of population growth., The Commission recognizes such projections have a

degree of uncertainty. Part of the staff review of any projection focuses

on this uncertainty and how it has been handled by the applicant. Previous

experience witn commercial low-level disposal sites illustrate that suitable sites cpan reasonably be found in areas of low population density

and minimal population growth potential.

Two commenters suggested a siting requirement based on accessibility

to major transportation routes. This issue becomes a consideration in

site selection and the evaluation of alternatives required under NEPA

and is not necessary in the rule.

Individual comments were received suggesting siting requirements

related to mechanical and physical properties of soils to make them suitable for compaction and supporting construction equipment, and requirements to avoid areas of high natural radioactivity. Changes to the rule

were not deemed necessary. The mechanical and physical characteristics

of soils are factors to be addressed.in the site design and operations

in order to meet stabilization requirements and objectives. With respect

to areas of high natural radioactivity, these areas would be excluded if

they could be shown to violate the ability to carry out a monitoring

Drogram. Otherwise, the Commission sees no valid reason for excluding

these areas.

Several commenters raised the general question of the length of time

the various, siting or design requirements have to be satisfied. Others

requested that the design basis natural events or phenomena be identified

20
[7590-01J

and that the length of time for consideration associated with these be

stated.

The siting, design, and waste form requirements relate to both stability of the disposal site and control of releases within acceptable limits.

Reliance must be placed for a longer time on the site since the waste

form and design features will decrease in effectiveness over time. Therefore, each of the siting requirements should be considered applicable

over the indefinite future and should be evaluated for at least a 500 year

time frame. A 500-year time frame for design basis natural events or

phenomena should also be applied.

Subpart D: § 61.51, Disposal Site Design for Land Disposal

Five commenters objected to the absoluteness of the requirements in

§ 61.51 relative to preventing infiltration and eliminating the contact

of water with waste. Comments were also expressed requesting preferential

consideration be given to progressive slope design for burial and concern

was expressed that the rule does not provide specific guidance for

engineered features. Commenters also expressed concern that site areas

used for disposal of Class A waste will require more maintenance.

The requirements referred to are expressed as design objectives.

Given that these are design objectives, the actual achievement will be

to minimize, rather than absolutely prevent or eliminate. The achievement level should be as near the design objectives as is practicable.

The wording of these paragraphs has been changed to reflect this. With

respect to progressive slope design for burial, the regulation does not

specify the type of disposal unit. The site designer should give particular attention to the design of that portion of the facility used for

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[7590-01O

the disposal of Class A wastes so that the inherently unstable Class A

wastes will not interfere with the long-term stability of the site.

Four commenters recommended that warning signs or permanent identification monuments be employed as a deterrent to inadvertent intrusion.

Several suggested a design lifetime of 500 years for such markers.

Although there are few "signs" in the traditional sense that have

design lives approaching 500 years, the Commission would consider such

things as granite monuments near the survey marker control points as an

appropriate adjunct to the physical intruder barriers employed in the

disposal of the waste. A change to the rule has been made to require

such monuments at the time the license is terminated.

Subpart D: § 61.52, Land Disposal Facility Operation

and Disposal Site Closure

There were several issues related to facility operation and site

closure identified by about thirty commenters. A half dozen commenters

raised questions with respect to the requirement that Class A waste be

segregated from other classes of waste. Questions also addressed the

need for segregation during transportation, the meaning and intent of

the term "interaction," and the need for segregation in arid sites.

The intent of the rule is not to prohibit waste from more than one

class from being shipped on the same transport vehicle. Consistent with

appropriate transportation regulations, the Commission has no objection

to commingling different classes of waste in transport.

In identifying the need to clarify the term "interaction," the commenters noted that it was vague and unenforceable, could include migration, and could be physical or chemical interaction.

22
[7590-01]

The intent of the rule is to protect Class B and C wastes. Class A

wastes could interact with other wastes directly through the release of

absorbed liquids, solvents, or other mobile components that might be

present in Class A waste. Indirect interaction could result from degradation of Class A waste and its lack of stability. Consolidation of Class A

wastes would provide a less stable support which could contribute to

failure of the disposal unit cover leading to increased precipitation

infiltration and surface water intrusion. The degree to which these

interactions could occur depends to a large extent on site specific characteristics and the Commission does not believe that it is appropriate

to set a prescriptive requirement in this area in the rule. The wording

of this requirement has been changed to define the purpose for the

segregation and minimization of interaction between the segregated

wastes. The rule also permits Class A that meets the stability requirements to be placed with Class B and C wastes.

The State of Washington regulates the disposal site located in an

arid region near Richland, Washington. The state noted that without the

likelihood of ground water or surface water being factors at arid sites,

segregation of Class A wastes seems to be unnecessary. They also noted

that commingling Class A and B wastes would dilute the Class B wastes and

have potential benefit.

The State's observations may have merit for arid sites but are difficult to adopt in a rule that must address sites located in all parts of

the country. The Commission anticipated the need to consider alternative disposal requirements and included §61.54, "Alternative requirements

for design and operations" to provide for consideration of such

alternatives.

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[7590-01]

A number of commenters noted that factors other than waste form

play a role in assuring the stability of the site. In the area of site

operations, these factors are identified as the way in which waste is

emplaced and the filling of voids in between waste packages after emplacement. Several pointed out the stability problems (slumping, etc. ,) that

could still be associated with disposal units containing the segregated

and unstable Class A waste. A number of commenters objected to the

requirement that wastes must be emplaced in an orderly manner because of

perceived increased exposures. The requirement that was proposed in

paragraph (4) of § 61.52(a) was intended to assure that the placement of packages into a disposal unit did not destroy the integrity of

the package in order to minimize the possibility of releases of contamination, and also to minimize the void spaces between packages so that

this would not be a contributor to site instability. It has been a

common practice at waste disposal facilities to dump some wastes over

the edge of a disposal trench with the packages falling and tumbling to

the trench bottom where they ended up a random arrangement. This practice

jeopardizes package integrity and does not permit access to voids between

packages so that they could be backfilled. The assumption by the commentors that orderly emplacement necessitates increased handling by site

operators with resultant higher radiation exposures is not necessarily

the case. Lifting and stacking devices are currently in use for low

level waste disposal that permit remote lifting and emplacement in the

disposal trench without increased occupational exposure. The resulting

emplacement meets the intent of protection of packaging integrity and

access to void spaces. Since the term "orderly" was subject to misinterpretation, the requirement has been rewritten to remove the term

and to specify the objectives of emplacement.

24
[7590-01)

Six commenters addressed the requirement for maintaining a buffer

zone of at least 100 feet. These comments generally supported the concept

and purposes of a buffer zone, but questioned whether the specified

100 feet was sufficient. The Department of Interior suggested that the

buffer zone should be three dimensional to include some distance below

the disposal site.

In response to these comments, the Commission has restated the requirement in terms of the objective to carry out monitoring activities and

take mitigative measures if needed, and has made the buffer zone three

dimensional.

Several persons commented on the need to conduct ancillary activities at the disposal facility such as storage, waste treatment, truck

terminals, etc. Concern was expressed over the language in §61.51(a)(7)

that would seem to preclude such activities. Others felt that provisions

should be made in Part 61 for the description and licensing of such

activities.

The provisions of § 61.51 that caused the concern was that the

disposal site shall be used exclusively for the disposal of radioactive

wastes. The intent of this provision was to prevent the disposal of

wastes such as toxic or hazardous chemicals which do not contain radio-

.. . ' . ., '1- .

active material at the facility. It was not intended, as could easily

be inferred from the way the requirement was worded, that disposal is

the only activity that could take place. Corrective word changes have

- . ,i . .: .,. ,.. , , .. -. .

been made to clarify this. The purpose of Part 61 is to specify the

regulatory requirements-for;the ,disposal of radioactive waste. Existing

requirements in Parts 30, 40, 70, etal., would govern the licensing of

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[7590-01]

other activities involving licensed radioactive materials, such as waste

treatment or storage.

Several comments questioned the meaning of the term, "a few percent

above background" as applied to the requirement that limits radiation

levels at the surface of the disposal unit cover. Some suggested values

from as low as 1 percent of background to as high as 1 mrem/hour (about

5000 percent of background). One commenter suggested that the radiation

limit should not be confined to gamma radiation, but should be expressed

as a dose rate to include other types of radiation.

The rules in Part 20 contain provisions for permissible levels of

radiation in unrestricted areas in § 20.105. The Commission considers

these to be appropriate for application at the time that the disposal

facility license is transferred to the site owner for the period of

institutional control. Although access to the site will be controlled

to prevent inadvertent intrusion and the site could be viewed as a

restricted area, the Commission believes it is not proper to consider

those who do have access, such as caretakers and site maintenance personnel, as radiation workers who could receive much higher occupational

exposures. Therefore, §61.52(a)(6) has been changed to reflect the

Part 20 unrestricted limits.

A number of other individual comments and suggestions were considered and were addressed in the detailed analysis of comments. Some

clarifying changes were made to the rule as a result.

Subpart D: § 61.53, Environmental Monitoring

Only nine commenters addressed the provisions for environmental monitoring. One commenter observed that analyses of release pathways should

26
[7590-01)

be conducted so that they may be validated by data acquired from subsequent

monitoring, a point with which the Commission agrees. Two comments

addressed the 12-month preoperational monitoring requirement: one thought

it too long, the other too short. While a.one-year period of site specific

data may not provide the range of fluctuations in data expected over a

longer period, the site specific data can be augmented by reconnaissance

level data or regional data that can be correlated with the site-specific

data., These activities should be,started early enough in the site devel-

.,opment process that they do not interfere with a timely submittal of an

application.. Additional data may be obtained as the licensing process

continues which can be used to.update the application.

It was noted that the environmental monitoring requirements are not

detailed or specific and at least one commenter suggested that highly

detailed prescriptive requirements be set forth. Because of the wide

variety of site-specific conditions, and a desire to avoid overly

prescriptive requirements in Part 61, the Commission does not feel that

this suggestion is practicable. .A Branch Technical Position on monitoring

is being prepared and will provide additional guidance.-

It was pointed out-that one important purpose of a monitoring system

- is, to provide,.early warning.of~migration of radionuclides from the disposalsite.before.they leavethe site boundary. The Commission, agrees,

and has made a clarifying change to that effect.

The Department of.Interior recommended that "geochemistry" be added

to the site characteristics to.be studied. This has been done.

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Subpart D: § 61.55, Waste Classification

Over half of the commenters on Part 61 offered comments on one aspect

or another of the waste classification provisions. Nearly 20 different

issues were identified and addressed in the staff's detailed analysis of

comments. In general, there was support for the concept of identifying

wastes that were generally acceptable for near-surface disposal and

further dividing this general category into more specific classes. Most

of the comments were related to understanding how these categories were

established and the basis for them; support for further identifying a

class of waste that would not be of any regulatory concern because of

its low radioactivity, i.e., a "de minimis" level; what should the upper

limits be, particularly for certain radioisotopes such as the transuranic

elements; what provisions will be made for disposal of wastes that exceed

the limits for near-surface disposal; and'how does a waste generator show

compliance with the waste classification requirements. There were a large

number of comments requesting clarification and restructuring of the

requirements to make them more understandable, as well as a number of

miscellaneous comments.

With respect to those comments that the numbers used to define waste

classification were not adequately explained or supported in Part 61, it

should be noted that most such comments were submitted before the supporting Draft Environmental Impact Statement (DEIS) for Part 61 became generally

available. Since a considerable part of the DEIS is devoted to the derivation of the waste classification numbers, the Commission does not feel

that the basis needs to be repeated in detail in the rule. The Commission

is preparing an analysis of the comments received on the DEIS and these

28
[7590-01)

comments will be factored into the final EIS to make the basis for waste

classification values more understandable. Other commenters on the

numerical values suggested the use of values reported in an earlier NRC

contractor documenit,NUREG/CR-1005. The present waste classification

scheme proposed in Part 61 drew on this and other'earlier'work; however,

the' earlier approaches to 'waste classification'did not' considerithe effects

of stability or waste form.

Table 1 proposed values'for several radionuclides that were the same

value regardless of the class of waste. This has lead to'some confusion

and misunderstanding. In the disposal'of wastes, precautions are taken

to'provide protection against intrusion for the first several'hundred

years. These precautions include institutional controls, waste' form

requirements, and intruder barriers. There are certain radionuclides

common to waste that are of such a long half-life that they will be

present several hundred years from now in essentially the same concentration as when they were originally disposed. Therefore, the rule limits

the initial concentrations of these radionuclides to values that will be

acceptable after several hundred y'ears when the intrusion protection

measures'are not considered to. be! effective.

Over one fourth of 'all ommenters endorsed the' concept of setting

levels for wastes below which there is no regulatory concern, the so-

' called "de minimis" level. Some' of the commenters'supporting''the de

minimis concept made direct reference to the Commission's position that

exempting particular waste streams from'compliance with the:Part 61 regulations was preferable to setting'generic levels for all isotopes.

Several disagreed'with this position,'although'at least'one of these commenters remarked that as there'is not yet a consensus on a generic de

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[7590-01]

minimis level, any level chosen would be premature. A number of other

commenters suggested that a de minimis classification be added to the

Part 61 regulations, perhaps as an additional column in Table 1.

Several commenters suggested that NRC permit case-by-case review of

requests for specific application of the de minimis concept during the

period criteria are being developed. Others suggested specific values

for specific waste streams or radioisotopes.

The fundamental concern of practically all commenters was not as

much whether a generic or a case-by-case approach be taken, but rather

that action to develop de minimis standard should be taken as soon as

possible.

The Commission agrees with the importance of setting timely standards for disposal of certain wastes by less restrictive means. The

Commission agrees with the commenters that establishment of such de minimis

levels would reduce costs of disposal for many licensees and would also

conserve space in disposal faciltities which are otherwise designed for

wastes having, much higher activities. The Commission also believes that

establishment of de minimis levels is important in enhancing overall

stability of a disposal facility, and therefore in reducing potential

long-term site maintenance and corresponding costs, since de minimis

levels would reduce the volume of Class A waste. This would also tend

to reduce ground water migration impacts, since subsidence and water

infiltration would be reduced.

Regarding the issue of setting de minimis levels on a generic or on

a case-by-case basis, the Commission still believes that the current policy

of examining waste streams on a case-by-case basis will result in the

quickest and best results. It is recognized that setting generic limits

30
[7590-01]

may be a desirable goal, and'the Commission plans to work toward this

goal over the'next few years. Meanwhile, the Commission believes that

the process of examining a few specific waste streams will facilitate

the development of generic requirements and is accelerating its efforts

on setting standards for disposal of wastes by less restrictive-means.

In this regard, the Commission staff is willing to accept petitions for

rulemaking from licensees, licensee organizati6ns,' or others for declaring certain waste streams to be'of no regulatory concern. Such'petitions

should-provide at least the following information:' -

* a description of the process by which the waste is generated;

' a description of the waste generated, including chemical'

characteristics;

the radionuclide content of the waste, including principallas well

,as trace contaminants;

* a description of the potential change in the radionuclide content

as a function of process variations;

* a;description of the process control and quality control programs

by which the licensee would ensure compliance.'

Waste streams common to a number of licensees and in which the radionuclide'content is well known and relatively nonvarient are'generally

prefe~rred. Individual licensees may also continue to request amendments

for alternative disposal methods for the licensee's own waste pursuant to

§ 20.302.- -- -

'Of all the values proposed'in Table 1, the limits for contamination

'by 'alpha emitting transuranic elements received the most attention and

comments.' There were a number ofWissues raised related-to the 'allowable

concentration, ranging from its validity -to the impacts'of'meeting the

31
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[7590-01]

limit. By far the most comments were related to the magnitude of the

limit. Of the 23 commenters on the transuranic issue, four thought the

10 nCi/gm limit should be retained or lowered, while the remaining 19

suggested that the limit be raised. Those who suggested that the limit

be raised presented a number of supporting arguments. Many, if not most,

of the commenters suggested that the limit could be safely raised to

100 nCi/gm. One argument given is the advantage of enforceability of

the higher limit. With current measurement techniques, it is argued that

it is very difficult if not impossible to certify that waste contains

less than 10 nCi/gm, but much less difficult to certify that it is less

than 100 nCi/gm. Others pointed out that a 100 nCi/gm limit would

encourage volume reduction through incineration and other means while

conversely, the 10 nCi/gm limit would discourage volume reduction,

contrary to the Commission's policy on volume reduction. The commenters

cited a number of reports, documents, and ongoing activities as providing

justification for their contentions, including a proposed revision to

the Department of Energy Manual Chapter 0511. Some commenters felt that

the Commission's calculations were excessively conservative. The most

common comment in this regard was that the analysis did not consider

dilution by other wastes, and if that dilution were considered, the

allowable concentration could be increased by an order of magnitude or

more.

The commenters that supported the 10 nCi/gm limit or did not want

it raised generally made statements of endorsement for the value because

of prior use or because of the view that wastes exceeding this limit

should not be buried at commercial low-level waste disposal sites.

Concern in this regard was also expressed over the provision in § 61.58

32
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[7590-013

that the Commission could, on a case-by-case basis, grant exemptions to

the waste classification requirement, thereby permitting disposal of

higher concentrations of transuranic radionuclides.

In response to these comments, the Commission has reevaluated the

analyses for disposal of waste containing transuranic nuclides, in an

attempt to temper unnecessarily conservative assumptions, such as not

considering the dilution by other wastes that decay to essentially inert

levels with time, so that more realistic estimates of consequences will

result. As a result, disposal limits for Class C, waste have been raised

to 100 nCi/gm for long lived alpha emitting transuranic nuclides. For

Class A wastes, the limit remains at 10 nCi/gm. The details and results

of these analyses are presented in the Final Environmental Statement

supporting Part 61.

Several commenters wanted to know what to do with waste containing

Radium-226, a radioisotope which is not currently listed. It appears

that there are two types of radium wastes to be considered: (1) small

concentrated sources of radium such as radiation sources or luminescent

dials, and (2) wastes which contain small amounts of radium incidential

to other radioisotopes, such as radium contained in wastes from uranium

separation processes. The former is not subject to regulation by the

Commission, since radium is a naturally-occurring isotope and is not

included in the provisions of the Atomic Energy Act of 1954, as amended.

The Environmental Protection Agency has a program for collection of radium * .;.. .. - a. a;

sources. This program may be phased out in the next few years. Such

sources are expected to be transferred to the Department of Energy for

storage and disposal. As for radium incidental to other types of waste,

the Commission has made provisions for disposal of small quantities of

33
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[7590-01]

uranium tailings as Class A waste. For purposes of this provision, a

small quantity is defined as 10,000 kilograms containing not more than

5 millicuries of radium-226. This concentration is typical of uranium

mill tailings (0.5 nanocuries per gram). The quantity of radium-226 is

that contained in 150 pounds of natural uranium at equilibrium with its

daughter products. 10 CFR Part 40 permits any person to possess and use

under general license 150 pounds of source material per year. Permitting

the disposal of such a quantity in a near-surface disposal facility is

judged to be acceptable. For larger amounts, specific approval would be

required.

Several commenters expressed concern with a footnote in Table 1 and

§ 61.55(d) which indicate that greater concentrations than Class C limits

may be determined to be acceptable for near-surface disposal under certain conditions. Commenters were either opposed to permitting any

higher concentrations or asked for clarification of what the requirements

would be for higher concentrations.

The Commission established the Class C limits using the performance

objectives as criteria to ensure safe disposal of waste considering the

degree of protection provided by "normal" near-surface disposal. To

ensure that the performance objectives are met, disposal of higher

concentrations of isotopes than those listed in Table 1 would have to be

by disposal technologies having greater confinement capacity or protection than "normal" near-surface disposal. Such improved disposal technologies could, depending on the particular radioisotopes, involve better

waste forms or packaging, or disposal by methods having additional barriers

against intrusion (e.g., burial at depths greater than 5 meters). The

Commission believes that some flexibility should be permitted, provided

34
[7590-01]

the performance objectives are met, and therefore will evaluate exceptions

on a case-by-case basis. In the meantime, the Commission is beginning

studies to establish criteria for the disposal of wastes that are not

normally suited for near-surface disposal. These would be the subject

of future rulemaking.

Over one dozen commenters, nearly all of which were nuclear utilities

or industry groups, expressed concern with how one determines compliance

with the waste classification requirements. Most were concerned that

the regulations would require them to routinely measure for every isotope

in Table 1 within each package of waste. Many examples were given of

the difficulty that this would present, citing heterogeneous waste mixtures, difficult to measure radioisotopes, increased costs, radiation

exposures to personnel, etc. A number of suggestions were offered

related to means of classifying the waste by its source, measuring key

isotopes to infer quantities of more difficult-to-measure isotopes, and

establishing different limits for every disposal site.

The Commission expects licensees to carry out individual programs

to assure proper classification of waste. However, the Commission does

not feel that detailed measurements routinely made on all waste packages

are necessary or desirable. The Commission staff is developing guidance

to licensees on a number of alternative methods by which compliance can

be shown. At present, the Commission staff has identified four basic

programs which may be used either individually or in combination by

licensees. They are: materials accountability; classification by source;

gross radioactivity measurements; and direct measurement of individual

radionuclides including scaling some radionuclides based upon measurement

35
[7590-01]

of others. These methods are discussed in the Branch Technical Position

on Waste Classification being prepared.

Several commenters also raised the issue of averaging concentrations

to comply with the concentration limits. One expressed concern about

the potential for concentrated or "hot spots" of transuranic nuclides

permitted under the proposed provision to allow concentrations to be

averaged over the volume of the package. Since the trace transuranic

nuclides in most shipments will be homogeneously distributed and incidental

to the total activity, averaging over the packages is physically representative of the majority of wastes. Reprocessing or other future changes

in waste streams which might change the transuranic character of the waste

can be addressed in subsequent rule changes. Other commenters were

concerned about potential ground water restricted inventory limits on

radionuclides which are present in wastes in very low concentrations.

Assay of individual packages for these nuclides is difficult as discussed

in the preceding paragraph. Averaging the concentration of radionuclides

such as Tc-99 or I-129 over the waste shipment or control on a total site

inventory basis was suggested to minimize conservative over-reporting.

Such over-reporting could exhaust site inventory limits and lead to

inefficient use of the site. The Commission agrees. This issue will

also be addressed in the Branch Technical Position on Waste Classification.

The concentration averaging language in the final rule was changed to

provide additional flexibility for the specific guidance being developed

in the Branch Technical Position.

In a related issue, a few commenters remarked on the difficulty of

inspection and enforcement to ensure compliance with the Part 61 requirements, citing past history of waste shippers not complying with the

present DOT and NRC shipping requirements.

36
[7590-01]

The Commission has recognized the importance of increasing inspection and enforcement activities in the processing, packaging, and transportation of waste. A number of programs have been initiated to improve

compliance. At the present time, enforcement comes largely on the basis

of provisions in the existing regulations (e.g., 10 CFR Parts 30, 40,

and 70) that no licensee may transfer licensed material to another person

unless that person is properly licensed to receive it. Requirements on

waste form, concentrations, etc., are a part of the disposal site licensee's

license. The Commission believes that issuing regulations to which all

waste generators and disposal site operators would be subject will give

the Commission a stronger basis for inspection and enforcement. Adoption

of uniform requirements by Agreement States will greatly bolster the

effectiveness of a national system of inspection and enforcement.

There were several commenters who argued that the waste classification scheme tends to discourage volume reduction, since this increases

concentrations of radioisotopes and may result in a change in classification, or at the extreme, make the waste unacceptable for near-surface

disposal. As long as the resulting concentrations of radioisotopes are

within the limits set by Part 61, the Commission does not feel that waste

classification necessarily discourages volume reduction. While a higher

' .' -. . . I-1 t .w A

classification of waste might result in more stringent requirements on

waste form and disposal methods, there are economic considerations that

need to be considered by the waste generator. The cost of processing, , - .. .I .. . . . . . .

shipping, and disposal of a small volume of higher classification waste

needs to be compared with the transportation and disposal of a larger

, j @ . .- , tb ' , , . -.

volume of a lower classification waste. There is no reason to believe

that the balance will always be against volume reduction. For wastes ....

37
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[7590-01]

with concentrations that would place them not generally acceptable for

near-surface disposal if they were volume reduced, the provisions for

specific Commission approval of the disposal-of such wastes provides

a potential alternative for licensees considering volume reduction.

Several commenters were concerned with materials which may be present

in low level radioactive waste which may be chemically toxic or hazardous.

Some suggested that the Commission's waste classification system

incorporate a "total hazard" approach that would consider both the radiological and chemical hazard of wastes. At least one comment did not

favor the total hazard approach because of the very complex classification system that the commenter perceived would result.

The Commission has stated publicly on several occasions that if it

were technically feasible to classify waste by total hazard, then it

would make eminently good sense to do so. We do not now know of any

scheme for such classification; however, the Department of Energy intends

to support research into the development of a classification system for

hazardous waste that might be compatible with Part 61. In the meantime,

the Commission will study the chemical toxicity of low-level waste, with

special emphasis on identifying any licensees who generate hazardous wastes

subject to requirements of the Environmental Protection Agency. We will

look then at what could be done, perhaps through processing, to minimize

the hazard.

Furthermore, the Commission believes that the technical provisions

of Part 61 generally meet or exceed those expected in the Environmental

Protection Agency's rules for the disposal of hazardous wastes. Although

it is not the Commission's intent to allow disposal of hazardous wastes

in a radioactive waste disposal facility, as is noted in the regulation,

38
[7590- 01]

the Commission recognizes that such wastes may be present in low-level

radioactive wastes. It is the Commission's view that disposal of these

combined wastes' in accbrdance with the requirements of Part 61 will adequately' protect 'the public health ard safety. Such' hazardous wastes are

expected to be such'a small percentage of'the total volume that dilution

'by other wastes would greatly'minimizeany risks. The Commissionintends

t:6 work closely with'the Environ'mental Protection Agency to assure continued compatibility. Furtheri EPA in'its response to a resolution of

'the 'Conference'of Radiation Control Program Directors indicated;'their

'willingness to work with other Federal agencies to address this problem.

Several commenters raised .questions on the ba'sis or criteria for

setting site inventory limits' for certain radionuclides, as was indicated

in Table 1 of the proposed rule. Some correctly noted-that such'inventory

limits would be site specific. The Commission established concentration

limits for radionuclides based on a number of considerations, including

protection of a potential intruder, operational safety, and long-term

site stability. In'addition to concentration limits, the Commission

desires the ability to'limit maximum site inventories for some isotopes

that are of concern from a ground water point of view. Isotopes'which

are both mobile and long-lived are iodine-129, technetium-99, and

carbon-14. Tritium-is of concern due to its extreme mobility and its

presence in waste in large quantities.' Establishment of inventory limits

through site-specific license conditions for such radionuclides will help

ensure that the performance'objectives foreground water migration 'are not

exceeded. The Commissionr doesnot plan,' as was suggested by a few

commenters, to establish site invento'ry limits for every isotope to protect

against potential intrusion. Inadvertent intruder exposures are mainly

39
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[7590-01)

controlled by the concentration of a particular isotope, and to a lessor

degree by the site inventory.

Several commenters raised specific points about the cost and regulatory

burden of the waste classification requirements. Much of the concern

was related to the issue of costs for determining compliance with the

concentration limits, as discussed earlier. The basis of the concentrations, in particular the 10 nanocurie per gram limit for transuanic

nuclides was of concern and is discussed elsewhere. One commenter

expressed the view that the classification requirements would raise the

cost of disposal because of perceived increased cost for disposal of

Class A waste and the cost of quality control activities.

While some costs will be associated with. these concerns, when they

are weighed against the longer term costs and institutional burdens that

may result if the requirements are not adopted, the Commission judges

the short-term costs to be warranted.

The State of Nevada, who regulates the Beatty site, expressed the

view that the rule will increase the burden and expenses of the regulatory

agencies. Two reasons cited related to monitoring the adequacy of site

maintenance funds and inspection of waste generator packaging and classification activities.

Monitoring the adequacy of funding is already a part of the program

for regulating disposal sites and is only peripherally related to waste

classification in that stability is not assumed for Class A wastes. This

is not different from the existing situation at disposal facilities where

a large percentage of waste is not in a stable form. Thus, this does

not appear to be a significant increase in regulatory burden. Inspection

of waste generators for compliance with waste classification is more the

40
[7590-01)

responsibility of the Commission or the Agreement State regulating the

generator. Existing regulatory responsibilities include inspection of

the packaging and shipment of'radioactive'waste. The incremental'burden

-of reviewing a licensee's program'for classifying these' wastes should be

small. 7 ' '

In addition to the above is'sues; a large number of'c'ommenters offered

individual comments on a variety'of points of clarification, format,

definition, and completeness of the provisions for waste classification.

While not summarized here, they are:addressed in'-the'detailed analysis

of comments by the Commission staff; and to the extent prafticable, these

comments were-reflected in the revision of § 61.55.

'As a result of'these comments, § 61.55 has been revised to'present

-the'classification values in two tables rather tha'n one.'' Those radionuclides with long'half-lives,'along with some:shorter-lived precursors

of long-lived nuclides, are nowlisted'separately in a newTable 1. The

presence of'these long-lived radionuclides will dominate'-the classification of the waste. If waste contains le'ss than on'e-tenth'the c6ncentration of such a nuclide listed in Table 1, it is Class A waste; greater

'-than that, it'is judged to be Class'C wastet'provided the concentration

does not exceed the value shown in-Table'1. Shorter-lived radionuclides

:are listed with a range of concentrations in Table 2.' Depending on the

concentration, wastes containingronly'these shorter-lived nu'clides will

be judged to be Class A, B, or C.: Iftwaste contains nuclides listed in

both'tables,' the mixture'must be considered in determining the waste

class. If Table 1 nuclides a'r present in concentrations'less than one

tenth the Table 1 1-imits, the class is determined'by the Table 2 nuclide

concentration. If Table 1inuclides exceed one tenth of the Table 1

limits the waste is Class C regardless of the Table 2 concentrations.

41
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[7590-01O

The phrase "theoretical maximum specific activity" has been eliminated ana replaced with a notation of "no limit." A footnote to Table 2

explains that while there is no theoretical limit for concentrations of

certain nuclides in Class B and C wastes, practical considerations such

as radiation and heat generation will determine the limits.

Several radionuclides have been removed from the originally proposed

table. Cesium-135 was removed because it is present in wastes in very

small concentrations and classification will be determined by the presence

of Cs-137 and because Cs-135 is a pure beta emitter which is very difficult to measure. Similarly, the'radionuclides Ni-59 and Nb-94 have been

removed except as they may be contained in activated metals. As examined

in the draft environmental impact statement for Part 61, these nuclides

are present in reactor wastes (other than activated metals) in such small

concentrations as to be insignificant. Uranium has been removed as a

radionuclide that must be considered for waste classification. The

Commission's analysis shows that the types of uranium-bearing wastes being

disposed of do not present a sufficient hazard to warrant limitation on

the concentration of this naturally occurring material. Both depleted

and enriched uranium do not contain daughter products in any quantity

because of the relatively short time since the uranium was refined from

ore, compared to the half-lives of the uranium isotopes. The daughter

products are disposed of primarily as uranium mill tailings. Primarily

for these reasons, the uranium limits were dropped.

For a number of radionuclides, the maximum allowable concentrations

in Class C waste have been increased by a factor of ten. This came in

response to a number of comments received on the proposed rule and the

draft environmental impact statement that pointed out where unnecessarily

42
[7590-01]

conservative assumptions had been incorporated into the calculations for

intruder protection. These comments pointed out that waste disposed

beneath five meters of cover would be difficult to contact even at

500 years and that such waste would be diluted by the other wastes whose

radioactivity had decayed to extremely low levels. Additionally, the

average concentrations tend to be only a fraction of the maximum permissible. At the present time, these are recognized by the Commission as

conservative assumptions and the Commission has found that an order of

magnitude increase in Class C limits is warranted. This order of magnitude increase has not changed the established framework of factors such

.,as relying on up to 100 years of institutional control and a 500 mrem

-whole body limit for intruders.

The radionuclide, curium-242, was added to the nuclides in Table 1.

.While^.Cm-242 is a relatively short-lived nuclide (163.days) it decays to

plutonium-238,-a transuranic nuclide with a half life of nearly.90 years.

The concentration of 20,000 nanocuries per gram for Cm-242.will result

.in a concentration of 100 nanocuries per. gram of Pu-238.

To the extent practicable, the numerous footnotes originally found

! .. in theiproposed Table 1iwere eliminated~and have been incorporated, where

|; . appropriate, into the textual part of-the-section on-waste classification.

.In response to a number of-comments, a statement is.made thatrpermits

the concentrations of nuclides in waste to be determined by means other

than direct measurement., These methods may.include such things as material accountability, where records of. receipts,,shipments, and inventories

can confirm that-waste concentrationsicould not.exceed permissible-concentrations.~ Other indirect methods might include "inferential'. measurements where a ratio is established between nuclides in a mixture and the

43
film

[7590-01]

concentrations of the difficult-to-measure nuclide is inferred based on

measurement of some easier-to-measure nuclide. Whatever the indirect

method used, there should be reasonable assurance that the values determined could be correlated with actual measurements. For example, in the

case of inferential measurements, the ratio on which the value is determined should be based on previous actual measurements. In the other example

above, the receipts, shipments, and inventories should be based on measured

values.

Subpart D: § 61.56, Waste Characteristics

A large number of comments were received addressing both the minimum

and the stability requirements for waste form characteristics in § 61.56.

The following summarizes the comments on the minimum requirements.

One commenter objected to the use of absorbent material to immobilize

liquids contained in Class A waste, stating that using absorbent materials

was an obsolete technique. The State of South Carolina recommended that

this requirement apply only to institutionally generated aqueous or biological

waste forms. Since various absorbents have been shown to be effective with

liquids, such as organic solvents, oils, etc., the Commission sees no reason

to restrict the use of absorbent material to aqueous or biological waste.

The Commission does not see any reason to restrict the use of absorbents to

institutional generators.

Eighteen commenters stated that the requirement (proposed in Table 1,

§61.55) to obtain specific approval to dispose of wastes containing greater than

0.1 percent chelating agents was too restrictive, and stated that.utilities

might decide against performing decontamination operations which could reduce

Occupat.ional exposures. Several commenters requested the basis for the 0.1

percent limit. One commenter recommended that no chelating agents be permitted.

44
[7590-01J

Since chelating 'agents have been shown to increase the migration of

certain radionuclides at certain sites, the Commission desired to evaluate

the disposal of large quantities of wastes containing high'concentrations

of chelating agents on a case-by-case basis. This' approach was used when

the Commission staff reviewed the disposal of wastes that would be' generated

in the decontamination operations at the Dresden Unit 1 Station. Because

the disposal of wastes containing chelating agents is dependent 'on the

characteristics of the disposal <facility and on the properties of the

waste form, the Commission has modified the chelating agent dispos'al

requirements to reflect this. The Commission has placed on the'disposal

site-license applicant the responsibility for describing the conditions

for disposal'of waste containing chelating agents. -If approved by the

Commission, site specific requirements will be placed on the disposal

facility licensee.' At this time the waste generator will be required

only to identify such wastes in the information contained on the shipping

'manifest.

-At the request of comments, definitions have been added for the terms,

"hazardous," :"pyrophoric," and "explosive." .- iv

Of five comments received on the prohibition against-packaging waste

in cardboard or fiberboard boxes, four felt the 'prohibition is unnecessary.

One commenter supported the provision. After reviewing the comments,

including the reasons presented, the'Commission still'believes that such

a prohibition is needed., The.experience cited'by the Department of Energy,

of successfully using cardboard containers for-waste packages at their

sites, does not include extensive-handling and transportation that commercially generated wastes mighttencounter. The existing prohibition against

cardboard and fiberboard containers at existing disposal facilities came

45
[7590-01]

about as a result of unfavorable experience in receiving, handling, and

disposing of wastes in such containers. No change has been made in this

requirement.

Ten commenters addressed the requirements relating to waste in a

gaseous form. Several noted an inconsistency between the provisions in

§§ 61.56(a)(5) that prohibits wastes capable of generating toxic gases,

and 61.56(a)(7) that permits up to 100 curies of activity in waste in a

gaseous form.. Several requested the basis for the 100 curie limit.

A recommendation was made that gases should be processed into liquid or

solid forms, and another felt that gases should be limited to several

microcuries. The Department of Energy recommended that krypton 85

immobilized by zeolite encapsulation or ion implantation into metal be

permitted with concentrations up to five million curies per cubic meter.

The intent of §61.56(a)(5) is to prohibit the disposal of wastes

that are chemically reactive under ambient conditions and produce toxic

gaseous reaction products. This section is not intended to prohibit the

disposal of properly packaged gases such as H-3 or Kr-85 which occasionally require disposal. This section has been reworded to clarify

the intent. The 100 curie limit derives from the existing limits at

commercial disposal facilities. The Commission has studies underway to

determine whether. higher limits would be appropriate. Such limits, if

justified, would be proposed in 'a future rulemaking. In lieu of a requirement that gases be converted to a liquid or a solid, the Commission is

evaluating the significant generators of tritium wastes and investigating

improved package designs for tritium wastes which would be capable of

retaining the contents until they had decayed to innocuous levels. The

requirements of Part 61 do not contemplate the disposal of millions of

46
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[7590-01]

curies of Kr-85 as suggested by the Department of Energy. The Commission

is not prepared to set disposal requirements for this waste at this time,

and since this waste is not liable to be generated by Commission licensees

in the near future, the Commission believes there is ample time to assess

the still emerging technology for krypton fixation and establish suitable

disposal requirements through future technical guidance or rulemaking

action.

Some commenters felt that the requirement in § 61.56(a)(1) that

waste packages presented for disposal must comply with NRC and DOT transportation regulations implied that outer packaging such as shipping casks

must also be disposed. This was not the Commission's intent. Since

proper packaging for transportation purposes is specified in regulations

elsewhere, the Commission feels that it is not necessary to restate them

in Part 61, particularly in view of the confusion created. This requirement has been deleted.

As discussed earlier, the Commission is concerned with the possible

hazards presented by non-radiological components of the radioactive waste.

This was recognized in the requirement proposed that wastes containing

biological, pathogenic, or infectious material must be treated to reduce

the potential hazard to the maximum extent practicable. The Commission

believes it is prudent to add hazardous properties to this requirement

and has done so.

A variety of comments were received on the proposed requirements in

§61.56(b) that pertain to the stability of Class B andC wastes. These

are discussed below for the various aspects of the requirement.

Nine commenters commented on the statement that the requirements

were intended to provide stability for at least 150 years. Three thought

47
[7590-01]

that the 150 years was overly restrictive-and two recommended 100 years

to correspond to the institutional control period. Others observed that

some nuclides would not decay to low levels during the 150 years, that

Class A waste should also be stable because of the presence of Cs-137

and Sr-90, that steel drums could not be expected to last this long, and

that high integrity containers have not been tested for 150 years.

The Commission has reviewed the 150 year stability requirement with

respect to the scenarios used to calculate the waste classification values.

The property of stability contributes to meeting successfully several of

the performance objectives set forth in Part 61. A waste that is stable

for a long period helps assure the long term stability of the site, eliminating the need for active maintenance after the site is closed. This

stability helps to assure against water infiltration due to failure of

the disposal unit covers and, with the improved leaching properties

implicit in a stable waste form, minimizes the potential for radionuclide

migration in groundwater. Stability also plays an important role in

protecting an inadvertent intruder, since the stable waste form is

recognizable for a long period of time and minimizes any effects from

dispersion of the waste upon intrusion.

The 150 year period was initially chosen to approximate the active

life of a near-surface disposal facility, along with the periods of postclosure observation and institutional controls. At the end of this

period, the intrusion scenario is based on the intruder readily recognizing

any uncovered waste as something out of the ordinary with the result that

no further attempts at construction or agriculture would be attempted.

When other aspects of the performance objectives are considered, however,

a longer design life is called for. The waste should continue to maintain

48
[7590-01]

its gross physical properties and maintain a measure of its identify for

several hundred years more to provide site stability and to keep the

Class B and C waste recognizable and unsuited to the construction and

agriculture scenarios postulated. Consistent with its desire to avoid

prescriptive requirements where possible, the 150 year specification has

been removed. It is the Commission's belief, however, that to the extent

that it is practicable, waste forms or containers should be designed to

maintain gross physical properties and identity over 300 years, approximately the time required for Class B waste to decay to innocuous levels.

This is reflected in Commission staff technical positions.

Fourteen commenters indicated that the proposed requirement that a

stable waste form maintain its physical dimensions within five percent

was overly restrictive and impossible to achieve due to the impracticality of filling containers to 95 percent capacity. Commenters also noted

that asphalt and polymeric solidification agents would be incapable of

meeting this requirement because of their viscoelastic creep properties.

Commenters also observed that the limit could entail added expenses.

Upon review of the proposed requirement, the Commission has concluded

that there is not sufficient basis at this time to support a numerical

limit for deformation of stable waste. The five percent value has been

removed from this requirement. Reliance will be placed on the requirements that void spaces within packages must be minimized, that wastes

must be emplaced in a manner that permits void spaces between containers

to be filled, and that these spaces must be filled. .~ ~~ ~ ~ . r: I 

With respect to void spaces in waste containers being reduced to ; '. - .. *.;, a- . . :.-'

the extent practicable, six comments were received. Several requested

specific criteria on how this would be met and if filler materials were

49
'V1LU-

(7590-01]

needed. Two felt that economics would drive waste generators to package

the maximum volume of waste into a container and that this requirement

in the rule is unnecessary. --

Due to the highly variable nature of wastes, the Commission believes

that it is not possible or desirable to include specific criteria for

minimizing voids. To the extent that void spaces can contribute to

eventual instability of the waste, they should be eliminated or reduced

as much as possible. This might be done in some cases by filling void

spaces with other wastes or inert materials.

Eleven commenters objected to the specific requirement that the

stability of waste be maintained under a compressive load of 50 pounds

per square inch (psi). Most felt that the specific requirement should

be deleted and replaced by a more general requirement to reflect actual

disposal site conditions and operations.

In response to these comments, the 50 psi specification has been

removed from the rule. The specification was based on conservatively

assuming maximum burial depths up to 45 feet and waste or overburden

density of 150 lb/ft3 Testing performed on acceptable solidified waste

specimens indicate that 50 psi compressive strength should be easily

obtained. The Commission believes that while this is achievable, some

latitude should be allowed for the design of waste forms and containers

to reflert site conditions where burial depths may be less.

Since § 61.56(b) permits the stability of waste to be achieved by

placing the waste in a suitable container for disposal, a number of comments addressed the properties such a container should exhibit and the

uses to which it should be put. It was suggested that the Commission

50
[7590-01]

reexamine design criteria for a high integrity container for highly dispersible forms, and one suggested that such container shouldbe used for

'both high-and low'concentration wastes. A major'supplier of waste solidification technology questioned whether the use of a container reflected

the best available'technology and the concepts of ALARA.

Three commenters, two of whom are suppliers of waste solidification

'technology and services, felt that ion exchange resins should all be

'solidified and that'disposal of ion exchange media by dewatering is not

within the concepts of ALARA and use'of-the'bestiavailable technology.

The Commission 'staff is preparing a technicl position on waste form

criteria, including design criteria for a high integrity container. Draft

copies have been made available to interested parties for their'review

and-comment. In short, the technical position states that the container

must'provide as much assurance of 'stability for as long as required for

a'stable waste form or product. It should be designed, to the extent

that it is practicable, to contain the waste and maintain gross physical

pr6perties' and identity over 300 years, under the'conditions of disposal.

The Commission believes that the'use of containers to achieve stability

is consistent with the concept of ALARA and the''use of the best available

techhology. Occupational exposures in using high'integrity containers

are expected to be similar to or'-less than waste solidification, either

with mobile orinstalled systems.

Several commenters addressed the proposed limitation of free standing

liquid'%ihich would'require that such'liquids- be reduced to as low a level

as is reasonably achievable, but in no case to exceed 1 percent. Further,

the proposed rule statedihat the liquid should be non-corrosive. There

were no requests to 'increase'the'value. However, one waste'solidification

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[7590-01]

service supplier recommended a limit of zero, while the State of South

Carolina recommended implementing the limits in the license for the

Barnwell disposal facility, i.e., 0.5 percent for solidified wastes,

1 percent for waste in high integrity containers. Several commenters

asked for a definition of the term "non-corrosive."

The Commission has reexamined the proposed limit on free standing

liquid and judged that solidified wastes and wastes in high integrity

containers should be addressed separately. The Commission has concluded

that existing waste solidification technology can produce a waste form

that is essentially free of free standing liquid. In order to compensate

for potential condensation of water vapor sealed in containers, the

Commission believes that a limit of 0.5 percent by volume is appropriate

for solidified wastes. For dewatered products, such as ion exchange

resins, that are in a container designed to ensure stability, it is

very difficult to ensure that such products would meet a 0.5 percent

requirement following transport to a burial site. Therefore, for

dewatered products, 1 percent should be allowed to account for settling

during the transport period. The non-corrosive properties of the liquids

will be defined and discussed in a staff technical position, rather than

in the regulation. To provide a degree of consistency between Class A

wastes and the Class B and C wastes, the limitations on liquids in Class A

wastes have been modified. Liquid waste mustbe packaged with sufficient

absorbent material to absorb twice the volume of the liquid. Solid wastes

with incidental liquids must meet the 1 percent free standing liquid

requirement.

Two commenters pointed out what they perceived as inconsistencies

between Part 61 and other Commission rules or guides. One of the guides

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[7590-01)

' referenced is the Effluent Treatment Systems Branch Technical Position 11-3.

This document was revised in July 1981 and is consistent with Part 61

requirements. The Commission fails to see'inconsistency between Part 61

and its supporting EIS, with Appendix I of Part 50, or guidelines for

storage of waste, as claimed by the commenters.

Subpart D: § 61.57, Labeling

Several commenters offered suggestions or raised questions on the

requirement that waste packages be labeled to show the classification of

the contents.' The commenters suggested color coding, different wording,

consistency with DOT labeling, minimum standards, and asked for

clarification of responsibilities.

The requirement for labeling is to provide the'disposal 'facility

operator with information as to whether the contents are Class A, B, or

C wastes so that he will be able to dispose of'them in the'proper manner.

The'Commis'sion does not feel that a Federal standard for such labeling

is warranted, only that it be clear and legible. Indivvidual 'facility

-operators may have operating procedures that could be enhanced by label

location,'size, color, etc. Since the label is to benefit the operator,

it is more appropriate'for'him"to'set specifications'through contractual

arrangement. A suggestion to'simplify the'nomenclature on the labels

was adopted and a m'in6r-change was made 'in §-61.57.

Waste classification labeling is in addition to labels required by

DOT for transportation purposes. 'Therelis a similarity in nomenclature

between the Clas's'A and B wastes and the Type-A and'B packages used by

DOT. DOT requires 'that p'ackages'be labeled'as to whether they are Type A

or B, therefore, there could be some 'confusion'-if the packages are labeled

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[7590-01]

to indicate the waste classification. However, DOT has a variety of

numerical and alphabetical designations and it is difficult to avoid some

similarity in designation.

Subpart D: § 61.59, Institutional Requirements

There were few comments on the requirement for State or Federal

ownership of the disposal site. Those commenting expressed general

support. One commenter suggested that the State should have an option

to turn ownership and responsibility for long-term custody over to the

Federal government. Such an option is not available under current law.

In related comments, two commenters expressed concern over the State's

responsibility and liability after accepting the disposal site for custodial care. Since the State does become responsible for the site, the

State must be involved and aware of the operations and conditions at the

site during its operation. This could be done through some independent

oversight as landlord, or through participation with NRC in the review

of the initial application as provided in Subpart F of Part 61.

About twenty commenters addressed the, appropriateness of the 100 year

limit on institutional controls and its effect on wastes acceptable for

disposal under the conditions prescribed by Part 61. All commenters

expressed support in one way or another for defining a time frame for

institutional control related either to the hazard duration of the waste

or assurance of continued government stability or concern. It was

generally agreed that waste that was potentially hazardous after the end

of the assured institutional controls should be disposed of by methods

providing greater controls and assurances against potential exposure.

These comments are judged to support the provisions of Part 61 that

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combine institutional controls with waste form, site characteristics,

and site design and operations to provide assurances that potential

exposures will be within acceptable limits.- Class A waste that is potentially accessible and unrecognizable is.no longer hazardous after 100 years.

Special-provisions for waste being inma stable form and in some cases

-buried deep assure against potentially unacceptable exposures or releases

for up to 500 years.

- There were a number of suggestions that the period of institutional

control should be raised from 100 to 300 years. There appear to be two

basic reasons for these suggestions. One reason is that institutions

such as a state or the Federal government can reasonably be expected to

..survive for much longer than 100 years. A second reason is that the 100

year restriction on institutionalcare affects the waste concentrations

.acceptable for disposal as Class A waste with resultant higher costs to

-the waste generator. With respect to the first reason, the Commission

feels that it is not a question of how long the government can survive,

* but how long should they be expected to provide custodial care. Based

-on work done by EPA, public comments on a preliminary draft of Part 61

* ;and~an advanced notice of proposed rulemaking, and four regional work-

-shops, a clear consensus was developed which supported the 100 year

-limit. The Commission has not seen any compelling reasons to-change

-its view on the 100 year limit.'

- Some commenters expressed'the view that the government landowner

should have.flexibility in controlling site access during the institutional control.period and.that productive uses of-the land which would

not 'affect site integrity shouldbe permitted.:, The Commission agrees

:and words to that effect have-been added to the Concepts section, 61.7.

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Subpart E: Financial Assurances

Approximately two dozen commenters responded to the proposed financial assurance requirements for closure and post-closure care. In general,

the commenters expressed support for the rule's establishment of financial assurances for closure and for long term care of a LLW disposal site.

Commenters mentioned that the existing history of LLW disposal sites

revealed a strong need to require licensees to demonstrate evidence of

financial responsibility so that the public health and safety were protected and also so that potential liabilities do not rest with state

taxpayers.

Several commenters felt that the financial requirements should provide more detail. The Commission agrees and has prepared a draft Branch

Technical Position on Funding Arrangements for Closure and for Long-Term

Care of a LLW Disposal Site that provides definitive guidance for

evaluating all financial assurances, including surety bonds.

One of the major points raised by a variety of commenters was that

the proposed regulation failed to address financial responsibility for

unanticipated contingencies at a LLW disposal site. One group expressed

concern that the regulations set the stage for a "tax-payer funded bailout" of poorly-run disposal sites. They felt the industry should bear

these costs, and that the regulations should be written to make this

explicit. Another commenter noted that the experience of the State of

Kentucky with Maxey Flats emphasized the importance of- making contingency

funds available in the event that serious problems occur. They felt this

issue should be addressed in the rulemaking. One State further noted

that the rule failed to mention who would be financially responsible if

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[7590-01)

problems occur at the site that cost more than were budgeted on an

assumption of normal operation. These questions cover such a variety of

different scenarios (i.e., Acts of God, licensee negligence, etc.,) that U * ; , - J -

it is not possible to specifically respond to all of the potential contingencies. However, a general response to the overall issue of responsibility for contingencies at a low-level waste disposal site is possible.

These comments cover two different time periods--the post-closure period,

when the original licensee is still responsible at the site, and the

institutional control period, when the license has been transferred to

the landowner of the site for a period of up to one hundred years. In

the case of the post-closure care period, the licensee would be responsible for all activities at the site found necessary by the Commission

to protect the public health and safety. Financial responsibility for

activities during the institutional control period are a matter to be

worked out between the site owner (i.e., the State or Federal Government)

and the licensee in their lease or other legally binding arrangement.

It is possible that if the site owner were a state, they would work out

an arrangement whereby the site operator would collect a surcharge from

waste generators for the institutional control period. The rights and

responsibilities of the State and the licensee would be determined at

such a time.

With regard to contingencies, one commenter also asked who would

assume responsibility for a site and its accompanying waste when it was

closed prematurely by NRC, due to rule violation. Responsibility for a

site closed prematurely by the NRC would depend on the situation. Additionally, closure would be a last resort of the Commission, since the

agency has other authorities, such as civil penalties, to require

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licensee compliance. In the event it would become necessary to close

the site for health and safety reasons, the rule provides that the

licensee continues to be responsible until the license is terminated.

In the event that the licensee's financial condition deteriorated so

that he was unable to maintain the site to protect the public health and

safety, then the Commission would probably require the site owner (either

the State or Federal government) to assume responsibility at the site.

Regardless of who assumed responsibility for a prematurely closed

site, the rules require that a licensee have available at all times

during the site life, sufficient financial guarantees to ensure that

sufficient funds are available for site closure and decommissioning.

These funds would be available for properly maintaining the site if the

original licensee were unable to do so.

Several commenters considered that the rule should resolve the issue

of financial responsibility for contingencies by requiring liability

insurance or specific language that licensees would be required to

indemnify property owners in case of off-site migration. Although not

proposed in the original rule, the staff evaluation of these public

comments indicates there is a need for licensees to provide financial

responsibility for liability coverage for off-site bodily injury and

property damage. The Commission thinks the public health and safety and

the environment would be protected from unanticipated contingencies by

such coverage, as well as assisting the States in establishing disposal

sites. Four existing LLW disposal facilities currently carry this type

of liability coverage, and several other State and Federal agencies,

including EPA have imposed similar requirements for hazardous and radioactive waste facilities in order to protect the public health and safety

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[7590-01]

and the environment. 'However, at the present'time, the Commission's only

statutory framework for establishing such a requirement is'Section'170

of'the Atomic Energy Act, also known as the "Price-Anderson" Act. This

type of coverage is designed to cover "catastrophic events" primarily

for nuclear reactor licensees, and the'Commission feels this coverage

would be in excess of'the risk at'a-low-level'waste facility. Therefore,

the Commission has not established a third party liability requirement

in this regulation. The'Commission will strongly encourage licensees to

continue to carry third party liability insurance coverage through the

conventional insurance market.'

A variety of comments were received concerning the short term financial assurances required forIclo'sure and'decommissioning. Several commenters supported the rule's use of a variety of'different options for

' -closure','noting that flexibility was crucial if the proposedrtile was to

* ' function 'in a reasonable manner.

Other commenters *expressed support for the rule's provision rTequiring that the 'amount of surety'liability'change with changes in cost

estimates. One commenter also was concerned that the financial surety

arrangements increase in value over time' to compensate for the effects

of inflation. The rule allows the Commission to'periodically assess

the amount of funds collected for'both closure-and post-closure care of

the'site and-if necessary, the Commission could require the financial

assurances to be increased to account for'inflation, unforeseen problems,

and unanticipated costs.''

Commenters expressed support for the variety of alternatives allowed

to demonstrate short term financial responsibility.' However, several

commenters mentioned that no commercial market exists 'to provide surety

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[7590-01J

bonds of the type mentioned in the-rule. In developing the rule, the

Commission is aware that surety bonds of the type proposed in the rule

may be unavailable at this time. However, the Commission included this

alternative in the rule in the event that this type of coverage becomes

available in the insurance market at a later time.

Commenters were also divided about whether the Commission should

allow self-insurance as a financial assurance for closure. Several

commenters felt that self-insurance would not satisfy the surety requirements, and they recommended that licensees should be required to place

specific funds in escrow to cover costs of decontamination, closure and

stabilization. Another commenter suggested that self-insurance be based

on an annual submittal of financial reports, i.e., a financial test.

The Commission rejected the use of stand alone "self-insurance" based

on the Commission's lack of confidence in this method to provide adequate

assurances. Further, state officials have informally expressed the need

to have tangible funds available from the licensee for site closure, so

the State as landowner would not be left financially responsible. While

not specifically allowing its use on a generic basis in the rule, the

Commission will evaluate the use of financial tests proposed by licensees

on a case-by-case basis.

Commenters also expressed support for the need to have a long-term

care fund established at the time a license is issued. Some commenters

wanted the rule to explicitly require the licensee to set aside funds

for long-term care. However, the Commission currently lacks the authority to require a licensee to establish a fund to provide for long-term

care of the site after the license is terminated. Instead, the Commission can only require a licensee to provide evidence of entering into a

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lease or other binding arrangement with the site owner indicating that

the two parties have established financial responsibility for long-term

care between themselves. With regard to the lack of authority, one

person suggested that the Commission ask Congress for authority to

require financial assurances for licensees for the active institutional

control period. The NRC has raised.this issue with Congress both in

testimony and in a letter commenting on waste legislation.

'Subpart F: 'Pairticipation' by State Governments'and In'dian-Tribes

Many of the comments on Subpart F were concerned with interpretations and clarifications. These have been answered in the detailed analysis of comments. Two noteworthy changes were made. In §61.71, a change

was made to ensure that the Director shall make Commission staff available for discussion with the State or tribal governing body. At the

request of the Department of the Interior, a statement was added to

§ 2.101 to indicate that the Commission will inform the U.S Bureau of

Indian Affairs when tribes have been notified of the filing of an

application.

The Commission has been examining ways by which the licensing

process can be shortened in time. One way is to conduct activities in

parallel where possible, rather than sequentially. One such area is in

the submittal and evaluation of proposals by States and Indian tribes

for participation in the NRC license review, as provided by Subpart F.

As proposed, §61.72 w p u p to120 days after an application

was docketed for a State or tribe to submit a proposal for participation.

The'time from initiail submittal of the application until it has been

docketed is estimated to be 60 days or more. Thus, there is a potential

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[7590-01]

delay of 180 days between the time NRC would' receive a proposal and could

begin the serious consideration of the proposal. Until resolution were

reached on the role a State or tribe would play in the review, the NRC's

review of the application could be significantly hampered.

The Low Level Radioactive Waste Policy Act of 1980 clearly states

that it is' a State's responsibility to provide for the disposal of low

level waste. The'Act also provides for theiformation of interstate compacts for this purpose, subject to Congressional approval. Thus, any

application for a disposal facility license will have had State or compact

participation and backing for a significant period of time before submittal.

During this time, the Commission believes that the State will have had

ample opportunity to determine what role it wants to play in the review

of the application. This also holds true for other States that are

parties to an interstate compact. Therefore, §61.72 is being changed to

require that a proposal from the State in which the facility is proposed,

or from any State involved in a compact with the State, must be submitted

within 45 days after the application has been tendered. However, the

Commission notes that a more prompt submittal by .the State would help

reduce delays.

Although it is to be hoped that the States will inform Indian tribes

of plans for disposal facilities and provide them with sufficient information to permit them to make a proposal at an early time, there is no

way of ensuring this. Therefore, Indian tribes and States not covered

above will be given 120 days from the tendering of an application to submit

their proposal. It is anticipated that the participation of Indian tribes

and non-compact States will not impact the schedule of the licensing

process as much and this additional time can be accommodated.

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The Commission believes that there should be sufficient information

in the tendered application on which to base a proposal and that it is

not necessary to wait until the acceptance review is completed and the

docketing procedure carried out.

* By making these changes, review of proposals can be carried out

earlier andin parallel with, the other reviews. It is expected that

this could reduce the licensing time by up to six months.

It should be noted that participation by States and Indian tribes

pursuant to Subpart F of Part 61 is not through an adjudicatory hearing.

If an adjudicatory hearing is requested, then 10 CFR Part 2 applies.

A provision was added to §61.25 to ensure that State, local, and

Indian officials were notified of the opportunity for a hearing for certain types of amendments to the disposal facility license.

Subpart G: Records, Reports, Tests, and Inspections

Several commenters made suggestions on records and reports and the

need for resident inspectors. Comments were also offered encouraging

state involvement in records review and inspections. Two suggestions,

relative to reporting any release of radioactivity and a requirement for

maintaining duplicate sets of records were rejected as being impracticable.

The Commission, however, would encourage protection of records so that

they would not be vulnerable to loss because of fire, flood, or other

occurrence. The other suggestions did not require modification of the

regulations in order to accomplish what was suggested.

10 CFR Part 2: Rules of Practice

No major issues were raised by the several comments on the proposed

amendments to Part 2.

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10 CFR Part 20: § 20.311 Transfer for' Disposal and'Manifests

Because any licensee might make a waste shipment and thus be subject

to the proposed manifest system requirements, the Commission mailed

copies of the proposed rules to each of the Commission's approximately

9,000 licensees. In addition, some 12,000 copies were furnished to the

Agreement States for distribution to their licensees. Out of this ^large

group came a total of 29 letters commenting on the manifest system. These

comments were-wide ranging, with the majority'of questions or suggestions

being raised by only one commenter. Only a handful of issues drew'more

than one comment, with four being'the largest number of comments on any

issue. As a result of these comments, several changes were made to the

proposed requirements to clarify some aspects.

To deal with the situation where a waste'collector picks up waste

directly from the generator, provisions are made for delivering the

manifest to the collector at that time. The waste collector will not be

required to attach copies of all waste generator manifests to his, as

long as the collector's manifest has the information for each package

that is required by § 20.311(b). The person transferring wastes will be

required to maintain a signed copy of the manifest or equivalent documentation such as a computor generated printout from the transferee containing

the same information and binding acknowledgment as the record required

by Parts 30, 40 and 70 governing transfer of licensed material. This

was done to provide inspectable records at the waste generator's facility

which demonstrate compliance with the manifest requirements.

Changes were made in the requirements dealing with quality assurance.

The term quality "assurance" has been changed to quality "control" and

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[7590-01]

management's role has been modified'to require evaluation of audits rather

-than the conduct of such audits.

Of note is that-only one commenter, a midwest utility, addressed

'the' question of'the burden that the manifest would represent to small

entities.:When the manifest requirements were proposed,-the Commission

judged that they would not have significant economic impact on 'small

entities.- Pursuant to the Regulatory Flexibility Act,-the'Commission

solicited comments on this matter. -

General Comments

Seventeen commenters expressed concern with the use of absolute

terms in the rule such as "eliminate" and "prevent." One was concerned

about the lack of absoluteness of "reasonable assurance."

As discussed elsewhere, most of the places where such terms were

used were in the context of design objectives. Since total achievement

of such absolute objectives is unlikely, modifications have been made to

the requirements to require minimization or prevention to the extent

practicable.

Twelve commenters made suggestions on the kinds of additional regulatory guidance they felt was needed. The Commission agrees with the

need for regulatory guidance and has a program underway to provide such

guidance, first in the form of staff technical positions, then as Regulatory Guides. Most of the topics addressed by the commenters are already

under development. Consideration is being given to the development of

guidance on other topics suggested by the commenters.

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£7590-01]

One commenter suggested exempting wastes in storage prior to the

effective date of the regulation from the packaging and labeling requirements. This comment touches on a-subject with-broader implications, the

phasing in of the Part 61 requirements, consistent with the ability of

licensees, Agreement States, and applicants to make necessary changes to

assure compliance.

The following sections and subparts will be considered a matter of

compatibility for the Agreement States when the rule is adopted: Section 61.2, Definitions; Subpart C, Performance Objectives; Subpart D,

Technical Requirements for Land Disposal Facilities; those portions of

Subpart B that are necessary to implement the provisions of Subparts C

and D; that portion of Subpart E requiring closure funding arrangements;

and Section 20.311, Transfer for disposal and manifests. Meetings were

held with Agreement State representatives and agreement was reached on a

method for uniform implementation of the manifest requirements, waste

classification, waste form, and the effective date of Section 20.311 which

was set at 365 days after publication in the Federal Register.

Since all other provisions of the proposed rules would pertain only

to applicants for new Commission-licensed disposal facilities, there are

no reasons to delay the effective date of these requirements. The

Commission is working with the Agreement States to develop model regulations to be adopted by the Agreement States in accordance with their

agreements to maintain compatible state regulations.

Applicability of the requirements in Part 61 to Commission disposal

facility licenses in effect on the effective date of the rule will be

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[7590-01]

determined on a case-by-case basis and .implemented through terms and

conditions of the license or by orders issued by the Commission.

There were a variety of comments related to commenters questions

about the development of new sites, concerns over nuclear facilities

becoming de facto disposal sites, the need for an environmental impact

statement, and an extension of the comment period for Part 61 to correspond with that of the environmental impact statement. These comments

are addressed in the detailed analysis of comments and had no effect on

the rule. The comment period was, in fact, extended from October :22,

. 1981 to January,14, 1982 to correspond with that for the.EIS.

About one third of all commenters offered editorial suggestions

that were aimed at improving clarity, correcting grammatical errors, and

-noting typographical errors. These were very helpful in preparing the

* final version of the rule.

Employee Protection

A new 10 CFR 61.9 has been added concerning job protection for

employees who provide information~to the Commission. The new section is

included in this final rulemaking to carryout the Commission's intent

that all specific licensees will have similar responsibilities.'uder its

employee protection regulations. :See the Federal Register notice (47 FR

*30452) dated July 14, 1982 for:the-basis for this action.

'New 10.CFR-61.9-emphasizes to.employers 7 that is, licensees, applicants, and their contractors and subcontractors?-.that termination or

other acts of job discrimination.against employees who engage in activities furthering the. purposes-,of the Atomic Energy Act and the Energy

Reorganization Act is prohibited. In addition, new 10 CFR 61.9 makes

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[7590-01]

the employee aware that if'discrimination of this nature is believed to

have occurred, a remedy is available through the'Wage and Hour Division

of the Department of Labor. To ensure that employees of licensees and

applicants'are aware of these 'amendments, these organizations are

required to post their premises with explanatory material related to the

prohibition of discrimination and availability of a remedy in the event

of discrimination.

Paperwork Reduction Act

As required by the Paperwork Reduction Act, P.L. 96-511, the recordkeeping and reporting requirements in the proposed amendments to 10 CFR 20

incorporated in the 10 CFR 61 rulemaking were'submitted to the Office of

Management and Budget and were approved. The proposed amendments to

10 CFR Part 20 were not significantly altered as a result of public comments so that approval remains valid. The application, reporting, and

recordkeeping requirements contained in 10 CFR 61 apply only to land

disposal facility operators and affect fewer than 10 persons and,

therefore, are not subject to OMB clearance.

Regulatory Flexibility Act

Based upon the information available and on the public comments

received on the proposed rule, and'in accordance with the Regulatory Flexibility Act of 1980, 5 U.S.C. 605(b), the Commission hereby certifies that

this rulemaking will not, if promulgated, have a significant economic

impact upon a-substantial number of small entities. -

The Regulatory Flexibility Act (Public Law 96-345) was signed into

law in September 1980. The Act's principal objective is to make certain

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[7590-01]

.that Federal agencies try, where possible, to fit regulatory requirements

to the scale of the.affected activity. Significant economic impacts on

a substantial number of small entities is a major concern. Part-61 and

accompanying rule changes will potentially impact a significant number

.of.persons -licensed by the Commission and the.Agreement States.-- The

following discussion addresses-the factors in-the analyses required by

the Act and the public comments received. The draft and final EIS's for

.Part 61 provide additional background information and~analysis of the

impacts of this rulemaking action.

Section 604 of the.Regulatory Flexibility Act requires that.the need

for the regulatory action be-clearly established. The need for standards

toogovern the disposal of low-level, radioactive wastes and. new regulations

to implement these standards was discussed in detail in the draft EIS.

The majority of the public comments supported the ruleand thus affirmed

the need for the rule and the regulatory-framework it establishes.

Section 609 of the Regulatory.Flexibility Act requires that small

entities have an opportunity to.participate in the rulemaking when the

rule will have a significant economic impact on a substantial number.

.Since the Commission's initial certification of.no significant impact

was a qualified one, special efforts to reach small, entities were made.

For-example, the proposed-rule was distributed to all Commission,

licensees.(9,000).and.made available to Agreement States (12,000

licensees)?with a cover letter highlighting the points that might impact

them. Comments were solicited from groups such as the Health.Physics

Society, a national organization of professionals concerned with

radiation safety, many of whose members will have to prepare.manifests

and coordinate compliance with the rule. The Health Physics Society

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[7590-01]

publicized the rule in its newsletters to members. Of some 107 different

commenters responding, none specifically addressed the Regulatory

Flexibility Act or the summary analysis. One 'utility (which is not a

small entity) did make a'general qualitative reference to burdens on

small entities. Twelve commenters representing a variety of sectors

(not just small entities) addressed the potential burden of the manifest

system.

Section 604 of the Regulatory Flexibility'Act further requires a

summary of the issues and a statement of any changes made in the proposed

rule as a result of the comments. Two commenters were concerned about

the burden of specifying chemical form. Four commenters objected to

shipper responsibility for tracking shipments. Three commenters including

one broker considered the system to be a paperwork burden and two, a

general burden. Three supported the system and one indicated no problems

in complying. Two objected to forwarding a copy of the manifest and one

was concerned about the implications of generator certifications.

The proposed-rule included relief language "as completely as practicable"

for specifying chemical form. Small entities generateda significant percent

of wastes and data on these wastes is needed, so no further relief was

provided. Objections to shipper tracking and forwarding manifests stemmed

primarily from the need to clarify intent'of the rule on waste broker or

collector'role and responsibility. The transfer of papers and tracking

responsibility is more clearly addressed in-the final rule. The

recommendation for simplifying the paperwork for brokers was adopted.

These issues and concerns are addressed in more detail in the staff

analysis of comments in the final EIS.

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The comments on waste classification were discussed in the preceding

summary and resulted in extensive revision of this portion of the rule

to simplify and clarify the-requirements. The'detailed staff analysis

in the'final EIS provides further'discussion of the issues raised.

Federal rules that overlap the-proposed rule are primarily those of

the Department of'Transportation (DOT). The Commission-and DOT have an

established'working relationship implemented through a formal Memorandum

of Understanding. The rule itself acknowledges the need to comply with

DOT'rules, and the Commission currently inspects licensees for compliance

with'DOT requirements. The manifest required by this rulemaking is consistent with DOT shipping'paper requirements, and-the same document may

be used by licensees to meet requirements of both agencies.' Neither NRC

nor DOT-require a specific form'and both allow such'dual use. The waste

form and packaging requirements-are in addition-to and compatible with

DOT rules. In addition, the manifest terminology and requirements were

compared to those in the proposed Uniform Hazardous Waste Manifest, the

joint EPA/DOT proposed form:published March 4, 1982 (47 FR 9336). A few

minor procedural and terminology changes were made to conform to this

proposed form. Licensees-may use the Uniform Hazardous Waste Manifest,

',once it-isimplemented,' as both'-a DOT shipping paper and a NRC manifest

for radioactive wastes'by using additional spaces-to describe wastes and

adding information to the back. These changes were made based on

consultation with EPA' and DOT staff and will help to reduce the burden

on all licensees. '

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The following comment was received from EPA on possible duplicative

requirements:

"NRC solicited comments on possible duplicative requirements for

effluent releases and broker activities under the Comprehensive

Environmental Response, Compensation and Liability Act of 1980

(CERCLA). This "Superfund" law exempts from notification "any

release of source,-special nuclear, or byproduct material ... in

compliance with a legally enforceable license, permit, regulations,

or order issued pursuant to the Atomic Energy Act of 1954" (CERCLA

Section l01(10)(K)). Radioactive releases from nuclear waste disposal

facilities which are not in compliance with an NRC license, permit,

regulation, or order fall within the reporting requirements of CERCLA.

Furthermore, as part of the notification regulations under CERCLA,

EPA is planning to develop a notification scheme for releases of

radioactive materials not licensed under the Atomic Energy Act of

1954 or the Uranium Mill Tailings Radiation Control Act of 1978.

EPA wishes to minimize duplicative reporting requirements for

releases reported to other agencies. EPA intends to work with NRC

to minimize duplicative reporting requirements to the extent possible."

The EPA also addressed the potential for duplicative costs to the

two agencies for wastes that are a mixture of hazardous chemicals and

radioactive materials. Close coordination and a memorandum of

understanding were suggested. EPA has regulatory responsibility for the

disposal of hazardous wastes under the Resource Conservation and Recovery

Act (RCRA). NRC agrees that the two regulatory programs need to be

coordinated, and will take action in that regard.

The Regulatory Flexibility Act also requires discussion of alternatives to the proposed action. The recordkeeping and reporting requirements

impose such a minor incremental burden that, no exemption was considered.

Initial estimates were that about 2,000 of the Commission's 9,000 licensees

are waste generators who might make waste shipments. Waste generators

must provide more complete information on the manifest than is currently

required to meet DOT shipping paper requirements and must report on

investigations of missing shipments. The additional information required

in the manifest includes the identities of solidification agents; presence

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of any chelating agents; whether the waste 'is Class A, B, or C; and the

total quantity of H-3, C-14, Tc-99, and I-129. The annual public burden

for all licensees should be no more than about 4,500 staff hours for the

- . . . . .

preparation of the manifest Versus DOT shipping papers and 1,000 hours

for investigating 'and reporting on late or missing shipments. Less than

half this burden should fall obnrsmall entities' base'd on relative volumes

of wastes shipped. The waste classification and characteristics portion

of the rule does provide relief for most wastes produced by the small

entities, i.e., Class A wastes. Where radiological hazard permits,

segregated disposal has been provided as an option to complying with more

restrictive waste acceptance requirements for Class B and C wastes.

The incremental burdens were initially judged small. Based on

further staff evaluations and public comments on the rule, this initial

judgment was correct and the rule will not have a significant economic

impact. The rulemaking will not affect economic factors such as employment, business viability, or ability for affected entities to compete.

The improvements in waste disposal practices and the contribution of

those improvements to establishing new disposal capacity are judged to

significantly outweigh the small economic impact on small entities.

List of Subjects in 10 CFR Parts 20 and 61

Part 20 - Byproduct material,.Licensed material, Nuclear materials,

Nuclear power plants and reactors, Occupational safety and health, Packaging and containers, Penalty, Radiation protection, Reporting requirements,

Special nuclear material, Source material, and Waste treatment and disposal. .' I.,! *'- *.'' I f . , . ,

Part '61 - Low-level waste, Nuclear materials, Penalty, waste treatment and disposal.

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Pursuant to the Atomic Energy Act of 1954, as amended, the Energy

Reorganization Act of 1974, as amended, and section 553 of title 5 of

the United States Code, the following new 10 CFR Part 61 and the following amendments to 10 CFR Parts 2, 19, 20, 21, 30, 40, 51, 70, 73, and

170 to Chapter 1 of Title 10, of the Code of Federal Regulations are

published as a document subject to codification.

A new Part 61 is added to 10 CFR to read as follows:

PART 61 - LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE

Subpart A: General Provisions

Sec.

61.1 Purpose and scope.

61.2 Definitions.

61.3 License required.

61.4 Communications.

61.5 Interpretations.

61.6 Exemptions.

61.7 Concepts.

61.8 Reporting, recordkeeping, and application requirements:

OMB approval not required.

61.9 Employee protection.

Subpart B: Licenses

61.10 Content of application.

61.11 General information.

61.12 Specific technical information.

61.13 Technical analyses.

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61.14 Institutional information.

61.15 Financial information.

61.16 Other information.

61.20 Filing and distribution of application.

61.21 Elimination of repetition.

61.22 Updating of application and environmental report.

61.23 Standards for issuance of a license.

61.24- Conditions of licenses.

61.25 Changes.

61.26 ";Amendment-of license.

61.27 Application for renewal or closure.

61.28 Contents of application for closure.

61.29,.-Post-closure observation and maintenance.

-.61.30 .Transfer of license..-

61.31 Termination of license.

Subpart C: Performance Objectives

61.40 General requirement.

61.41 Protection of the general population from releases of

radioactivity.

61.42 Protection of individuals from inadvertent intrusion. r a ** . 'ad.>; .- -

61.43 Protection of individuals during operations.

61.44 Stability of the disposal site afterclosure.

Subpart D: Technical Requirements for Land Disposal Facilities

61.50 Disposal site suitability. requirements for land disposal.

61.51 Disposal site design for land disposal.

61.52 Land disposal facility operation and disposal site closure.

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61.53 Environmental monitoring.

61.54 Alternative requirements for design and operations.

61.55 Waste classification.

61.56 Was'te characteristics.

61.57 Labeling.

61.58 Alternative requirements for waste classification and

characteristics.

61.59 Institutional requirements.

Subpart E: Financial Assurances

61.61 Applicant qualifications and assurances'.

61.62 Funding for disposal site closure-and stabilization.

61.63 Financial assurances for institutional controls.

Subpart F: Participation by State Governments and Indian Tribes

61.70 Scope.

61.71 State and Tribal government consultation.

61.72 Filing of proposals for State and Tribal participation.

61.73 Commission approval of proposals.

Subpart G: Records, Reports, Tests, and Inspections

61.80 Maintenance of records, reports, and transfers.

61.81 Tests at land disposal facilities.

61.82 Commission inspections of land disposal facilities.

61.83 Violations.

AUTHORITY: Secs. 53, 57, 62, 63, 65, 81, 161, 182, 183, 68 Stat. 930,

932, 933, 935, 948, 953, 954, as amended (42 U.S.C. 2073, 2077, 2092,

2093, 2095, 2111, 2201, 2232, 2233); Secs. 202, 206, 88 Stat. 1244, 1246

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(42 U.S.C. 5842, 5846); secs. '10 and;14, Pub. L. 95-601, 92 Stat. 2951

(42 U.S.C. 2021a and 5851).

For the purposes of sec.' 223, 68 Stat. 958, as amended, (42 U.S.C.

2273): Tables 1 and 2, §§ 61.3, 6i.24, 61.25, 61.27(a), 61.41through

.43, 61.52, 61.53, 61.55, 61.56,-and 61.61 through 61.63 issued under

sec. 161b, 68 Stat. 948 as am6nded (42 U.S.C. 2201(b)), §§ 6110 through

61.16, 61.24, and 61.80 issued under sec. 161o, 68 Stat.950, as amended

(42 U.S.C. 2201(o)).

Subpart A: General Provisions .

-§61.1 Purpose and scope.

(a) The regulations in this part establish, for land disposal of

radioactive waste, the procedures, criteria, and terms and conditions

upon which the Commission issues licenses for the disposal of radioactive wastes-containing byproduct, source and special nuclear material

received from other persons. Disposal of waste by an individual licensee

is set forth in Part 20 of this chapter. Applicability of the requirements in this Part to Commission licenses for waste disposal facilities

in effect on the effective date of this rule will be determined on a

case-by-case basis and implemented through terms and conditions of the

license or by orders issued by the Commission.

(b) Except as provided in Part 150 of this chapter, which addresses

_assumption of certain regulatory authority by Agreement States, and §61.6

"Exemptions,", the regulations.in this part apply to all persons in the

United States. The regulations in this part do not apply to (1) disposal

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of high-level waste as provided for in Part 60 of this chapter; (2) disposal of uranium or thorium tailings or wastes (byproduct material as

defined in §40.4(a-1)) as provided for in Part 40 of this chapter in

quantities greater than 10,000 kilograms and containing more than five

(5) millicuries of radium-226; or (3) disposal of licensed material as

provided for in Part 20 of this chapter.

§61.2 Definitions.

As used in this part:

"Active maintenance" means any significant remedial activity needed

during the period of institutional control to maintain a reasonable assurance that the performance objectives in §§61.41 and 61.42 are met. Such

active maintenance includes ongoing activities such as the pumping and

treatment of water from a disposal unit or one-time measures such as

replacement of a disposal unit cover. Active maintenance does not

include custodial activities such as repair of fencing, repair or

replacement of monitoring equipment, revegetation, minor additions to

soil cover, minor repair of disposal unit covers, and general disposal

site upkeep such as mowing grass.

"Buffer zone" is a portion of the disposal site' that is controlled

by the licensee and that lies under the disposal units and between the

disposal units and the boundary of the site.

"Chelating agent" means amine polycarboxylic acids (e.g., EDTA,

DTPA), hydroxy-carboxylic acids, 'and polycarboxylic acids (e.g., citric

acid, carbolic acid, and glucinic acid).

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"Commencement of construction" means any clearing of land, excavation, or other substantial action that would adversely affect the environment of a land disposal facility. The term does not mean disposal site

exploration, necessary roads for disposal site exploration, borings to

determine foundation conditions, or other preconstruction monitoring or

testing to establish background information related to the suitability of

the disposal site or the protection of environmental values.

"Commission" means the Nuclear Regulatory Commission or its duly t .- x . . -, '

authorized representatives.

"Custodial Agency" means an agency of the government designated to

act on behalf of the government owner of the disposal site.

"Director" means the Director, Office of Nuclear Material Safety and

Safeguards, U. S. Nuclear Regulatory Commission.

"Disposal" means the isolation of radioactive wastes from the

biosphere inhabited by man and containing his food chains by emplacement

in a land disposal facility.

"Disposal site" means that portion of a land disposal facility which

is used for disposal of waste. It consists of disposal units and a buffer

zone.

"Disposal unit" means a discrete portion of the disposal site into

which waste is placed for disposal. For near-surface disposal the unit

is usually a trench.

"Engineered barrier" means a man-made structure or device that is

intended to improve the land disposal facility's ability to meet the

performance objectives in Subpart C.

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"Explosive material" means any chemical compound, mixture, or device,

which produces a substantial instantaneous release of gas and heat spontaneously or by contact with sparks or flame.

"Government agency" means any executive department, commission,

independent establishment, or corporation, wholly or partly owned by the

United States of America which is an instrumentality of the United States;

or any board, bureau, division, service, office, officer, authority,

administration, or other establishment in the executive branch of the

government.

"Hazardous waste" means those wastes designated as hazardous by

Environmental Protection Agency regulations in 40 CFR Part 261.

"Hydrogeologic unit" means any soil or rock unit or zone which by

virtue of its porosity or permeability, or lack thereof, has a distinct

influence on the storage or movement of groundwater.

"Inadvertent intruder" means a person who might occupy the disposal

site after closure and engage in normal activities, such as agriculture,

dwelling construction, or other pursuits in which the person might be

unknowingly exposed to radiation from the waste.

"Indian Tribe" means an Indian tribe as defined in the Indian SelfDetermination and Education Assistance Act (25 USC 450).

"Intruder barrier" means a sufficient depth of cover over the waste

that inhibits contact with waste and helps to ensure that radiation

exposures to an inadvertent intruder will meet the performance objectives

set forth in this part, or engineered structures that provide equivalent

protection to the inadvertent intruder.

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"Land disposal facility" means the land, buildings, and equipment

which is intended to be used for the disposal of radioactive wastes into

the subsurface of the land. For purposes of this chapter, a geologic

repository as defined in Part 60 is not considered a land disposal

facility.

"License" means a license issued under the regulations in Part 61 of

this chapter. "Licensee" means the holder of such a license.

"Monitoring" means observing and making measurements to provide

data to evaluate the performance and characteristics of the disposal

site.

"Near-surface disposal facility" means a land disposal facility in

which radioactive waste is disposed of in or within the upper 30 meters

of the earth's surface.

'Person" means (1) any individual, corporation, partnership, firm.

association, trust, estate, public or private institution, group,

government agency other than the Commission or the Department of Energy,

(except that the Department of Energy is considered a person within the

meaning of the regulations in this part to the extent that its facilities

and activities are subject to the licensing and related regulatory

authority of the Commission pursuant to section 202 of the Energy

Reorganization Act of 1974 (88 Stat. 1244)), any State or any political

subdivision of or any political entity within a State, any foreign

government or nation or any political subdivision of any such government

or nation, or other entity; and (2) any legal successor, representative,

agent, or agency of the foregoing.

. *, .

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"Pyrophoric liquid" means any liquid that ignites spontaneously in

dry or moist 'air at or below 130'F (54.51C). A pyrophoric solid is any

solid material, other than one classed as an explosive, which under

normal conditions is liable to cause fires through friction, retained

heat from manufacturing or processing, or which can be ignited readily

and when ignited burns so vigorously and persistently as to create a

serious transportation, handling, or disposal hazard. Included are

spontaneously combustible and water-reactive materials.

"Site closure and stabilization" means those actions that are taken

upon completion of operations that prepare the disposal site for custodial

care and that assure that the disposal site will remain stable and will

not need ongoing active maintenance.

"State" means any State, Territory, or possession of the United

States, Puerto Rico, and the District of Columbia.

"Stability" means structural stability.

"Surveillance" means observation of the disposal site for purposes

of visual detection of need for maintenance, custodial care, evidence of

intrusion, and compliance with other license and regulatory requirements.

"Tribal Governing Body" means means a Tribal organization as defined

in the Indian Self-Determination and Education Assistance Act (25 USC 450).

"Waste", means those low-level radioactive wastes containing source,

special nuclear, or byproduct material that are acceptable for disposal

in a land disposal facility. For the purposes of this definition, lowlevel waste has the same meaning as in the Low-Level Waste Policy Act,

that is, radioactive waste not classified as high-level radioactive

waste, transuranic waste, spent nuclear fuel, or byproduct material as

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defined in section 11 e.(2) of the Atomic Energy Act (uranium or thorium

tailings and waste).

§61.3 License required.

(a) No person may receive, possess, and dispose of radioactive

waste containing source, special nuclear, or byproduct:'material at a

land-disposal facility unless authorized by a license issued-by the

--Commission pursuant to this part, or'unless exemption'has been granted

by the Commission under § 61.6 of this part.-

(b) Each person shall file an application with the-Commission and

obtain a license as provided in this part before commencing construction

of a land disposal facility. Failure to comply with this requirement

may be grounds for denial of a license.

§61.4 Communications.

Except where otherwise specified, all communications and reports

concerning the regulations in this part and applications filed under

them should be addressed to the Director, Office of Nuclear Material

Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington,

D.C; 20555. Communications, reports, and applications may be delivered

in'person 'at the Commission's offices-at 1717TH Street NW., Washington,

D.C. or'7915 Eastern:Avenue, Silver'Spring, Maryland.

§61.5 Interpretations.

Except as specifically authorized by the Commission in writing, no

interpretation of the meaning of the regulations in this part by any

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officer or employee of the Commission other than a written interpretation by the General Counsel will be considered binding upon the

Commission.

§61.6 Exemptions.

The Commission may, upon application by any interested person, or

upon its own initiative, grant any exemption from the requirements of

the regulations in this part as it determines is authorized by law, will

not endanger life or property or the common defense and security, and is -

otherwise in the public interest.

§61.7 Concepts.

(a) The disposal facility.

(1) Part 61 is intended to apply to land disposal of radioactive

waste and not to other methods such as sea or extraterrestrial disposal.

Part 61 contains procedural requirements and performance objectives

applicable to any method of land disposal. It contains specific technical requirements for near-surface disposal of radioactive waste which

involves disposal in the uppermost portion of the earth, approximately

30 meters. Burial deeper than 30 meters may also be satisfactory. Technical requirements for alternative methods will be added in the future.

(2) Near-surface disposal of radioactive waste takes place at a

near-surface disposal facility, which includes all of the land and

buildings necessary to carry out the disposal. The disposal site is

that portion of the facility which is used for disposal of waste and

consists of disposal units and a buffer zone. A disposal unit is a

discrete portion of the disposal site into which waste is placed for

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disposal. For near-surface'disrsal, the disposal unit is usually a

trench. A buffer zone is a portion of the disposal site that'is

controlled by the licensee and that lies under the'site and between

the boundary of the disposal site and any disposal unit.' It provides

controlled space to establish monitoring locations'which are intended

to provide anearly warning of radionuclide movement, and to take

mitigative measures if needed.' -In choosing a disposal'site, site characteristics should be consider~ed'in'terms of the indefinite future and

evaluated'for at least a 500 year time frame".

* (b) Waste Classification 'and Near-Surface Disposal.

(1)' Disposal of radioactive waste in near-surface disposal facilities has the following safety objectives: protection of the general

population from'releases of'radioactivity, protection of individuals

from inadvertent'intrusion, and protection-of individuals'during operations. 'A fourth objective is to'ensure'stability of the site after

closure. ' -

-(2) A cornerstone of the system is stability--stability`of the

waste and the disposal site so that once emplaced'and'covered, the access

o6f w'ater'to the waste can be' minimized. Migration of radionuclides is

thus minimized, long-term active-maintenance'can be avoided, and potential exposure's'to intruders reduced. Whiie stability is a desirable

characteristic for' all waste much radioactivewasite does not contain

sufficient amounts of radionuclides'to be of great concern 'from these

standpoints; thisviaste,'ihowever, tends to be unstable,' such as ordinary

trash type wastes. If- mixed with the higher' activ'ity 'waste, their

deterioration could lead tofailure of the system and permit water to

penetrate the disposal unit and-cause problems with the higher activity

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waste. Therefore, in order to avoid placing requirements for a stable

waste form on relatively innocuous waste, these wastes have been classed

as Class A waste. The Class A waste will be disposed of in separate

disposal units at the disposal site. However,. Class A waste that is

stable may be mixed with other classes of waste. Those higher activity

wastes that should be stable for proper disposal are classed as Class B

and C waste. To the extent that it is practicable, Class B and C waste

forms or containers should be designed to be stable, i.e., maintain

gross physical properties and identity, over 300 years. For certain

radionuclides prone to migration, a maximum disposal site inventory

based on the characteristics of the disposal site may be established

to limit potential exposure.

(3) It is possible but unlikely that persons might occupy the site

in the future and engage in normal pursuits without knowing that they

were receiving radiation exposure. These persons are referred to as

inadvertent intruders. Protection of such intruders can involve two

principal controls: institutional control over the site after operations by the site-owner to ensure that no such occupation or improper

use of the site occurs; or, designating which waste could present an

unacceptable risk to an intruder, and disposing of this waste in a

manner that.provides some form of intruder barrier that is intended

to prevent contact with the waste. This regulation incorporates both

types of protective controls.

(4) Institutional control of access to the site is required for

up to 100 years. This permits the disposal of Class A and Class B

waste without special provisions for intrusion protection, since these

classes of waste contain types and quantities of radioisotopes that will

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decay during the 100-year.period and will present an acceptable hazard

. to an intruder..,The government landowner administering the active

-institutional control program hasflexibility in-controlling site access

which may include allowing productive uses of the land provided the

integrity and long-term performance of the site arenot affected.

. .,(5) Waste that will not decay to levels.which present an acceptable

'hazard to an intruder within,lO0.years is designated as Class C waste.

This waste is disposed of at a greater depth than the other classes of

'waste so that subsequent surface activities by an intruder will not disturb the waste. Where site conditions prevent.deeper disposal, intruder

barriers such as concrete.covers may be used., The effective life of

these intruder. barriers should be 500 years. A maximum concentration of

..radionuclides is specified for all wastes so that at the end of the

,500 year period, remaining radioactivity will be at a level that does not

pose an unacceptable hazard to an intruder orpublic health and safety.

!Waste with concentrations above these limits is generally unacceptable

for near-surface disposal. There may be some instances where waste with

concentrations greater than permitted for Class C would be acceptable

for near-surface disposal with special processing or design. These

will be evaluated on a case-by-case basis. Class C waste must also be

stable.

(c). The Licensing Process.

(1) During the preoperational phase, the potential applicant goes

through..,a process of disposal site selection by selecting a region of

interest, examining a number of possible -disposal sites within the area

of interest and narrowing the choice to the proposed site. Through a

detailed investigation of the disposal site characteristics.the potential

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applicant obtains data on which to base an analysis'of the-disposal site's

suitability. Along with these data and analyses, the applicant submits

other more general information to the Commission in the form' of an application for a license for land disposal. The Commission's review of the

application is'in'accordance with administrative procedures established

by rule and may'involve participation by affected State governments or

Indian tribes. While the'proposed disposal site must be owned by a State

or the Federal government before the Commission will issue a license, it

may be privately owned during the preoperational phase if suitable

arrangements have been made with a State or the Federal government to

take ownership in fee of the land before the license is issued.

(2) During the operational phase, the licensee carries out disposal

activities in accordance with the requirements of this regulation and

any conditions on the license. Periodically, the authority to conduct

the above ground operations and dispose of waste will'be subject to a

license renewal, at which time the operating'history will be reviewed

and a decision made to permit or deny continued'operation. When disposal operations are to cease, the licensee applies for an amendment to

his license to permit site closure. After final review of the licensee's

site closure and stabilization plan, the Commission may 'approve the final

activities necessary to prepare the disposal site so that ongoing active

maintenance of the site is not required during the period of institutional control.

(3) During the period when the final site closure and stabilization activities are being carried out, the licensee is in a disposal

site closure' phase. Following that, for a period of 5 years, the

licensee must remain at the disposal site for a period of post-closure

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observation and maintenance to assure that the disposal site is stable

and ready for institutional control. The Commission may approve shorter

or require longer periods if conditions warrant. At the end ofthis

period, the licensee applies.fora license transfer to the disposal site

owner.

.(4) After a finding of. satisfactory disposal site closure, the

Commission will transfer the license to the State orFederal.,government

-that owns the disposal site. If the Department of.,Energy is the Federal

agency administering the land on behalf of -the Federal government the

license will be terminated because the Commission lacks regulatory

authority over the Department for this activity. Under the conditions

of the transferred license, theowner will carry out a program of

monitoring to assure continued satisfactory disposal -site performance,

physical surveillance to restrict access to the site and carry out minor

custodial activities. During.this.period, productive uses of the land

might bepermitted if those uses ,donot affect the stability of the site

and its ability to meet the performance objectives. At the end of the

prescribed period of institutional control, the-license will be terminated by. the Commission. .,.

§61.8 Reporting, recordkeeping, ad application'requirements''OMB

approval not required..

The information'collecti6n requirements'contained in this part

affect'fewer than'ten persons.'Therefore, under section 3506(c)(5) of

the Paperwork' Reduction Act _of 1980 (Pub. L. 96-511) i'0MB clearance

is not required'for these-information collection requirements.

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§61.9 Employee' protection.

(a) Discrimination by a Commission licensee, an applicant for a

Commission licensee, or a'contractor or subcontractor of a Commission

licensee or applicant against an employee for engaging in certain protected activities is prohibited. Discrimination includes discharge and

other actions that relate'to compensation, terms, conditions, and

privileges'of employment. The protected activities are established in

Section 210 of the Energy Reorganization Act of 1974, as amended, and in

general are related'to the administration or enforcement of a requirement imposed under the Atomic Energy Act or the Energy Reorganization

Act.

(1) The protected activities include but are not limited to -

(i) providing the Commission information about possible violations

of requirements imposed under either of the above statutes;

(ii) requesting the Commission'to institute action against his or

her employer for the administration or enforcement of these requirements;

or

(iii) testifying in any Commission proceeding.

(2) These activities are protected even if no formal proceeding is

actually initiated as a result of the employee assistance or participation.

(3) This section has no application to any employee alleging discrimination prohibited by this section who, acting without direction from

his or her employer (or the employer's agent), deliberately causes a

violation of any requirement of the Energy Reorganization Act of 1974,

as amended, or the. Atomic Energy Act of 1954, as amended.

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.(b) Any employee who believesathat he or she has been discharged

or otherwise discriminated-against by any person for engaging in the

protected-activities specified in paragraph (a)(1) of this'section may

seek a remedy for the discharge or-discrimination through an administra-

-tive~proceeding in.the Department of Labor. The'administrative proceeding

* must be initiated within 30 days after an alleged violation occurs by

erfiling'a complaint alleging the violation with the Department of Labor,

Employment Standards Administration, Wage and Hour. Division.,..The Department of Labor may order reinstatement, back pay, and compensatory damages.

(c) A violation of paragraph (a) of this section by a Commission

licensee, an applicant for a Commission license, oi'a contractor or sub-

.. '. contractor of a Commission licensee or applicant may be grounds for -

-(1) Denial, revocation, :or.suspension of .the license.

(2) Imposition of a civil penalty on the licensee or applicant.

(3). Other enforcement action. -

(d) Actions-taken by an employer, or others, which adversely affect

an employee may be predicated upon nondiscriminatory grounds. The prohibition applies when the adverse action occurs because the employee has

engaged in protected activities. An employee's engagement in protected

activities does not automatically render him or her immune from discharge

or discipline for legitimate reasons or' fromi adverse action.dictated by

non-prohibited considerations.;

'(d) 'Each licensee and each applicant'shall post Form NRC-3, "Notice

to Employees," on its' premises.' Posting must be at locations sufficient

t'o peimitemployees' protected by this section to observe a copy on the

way'to'or'from their place of work. Premises must be posted not later

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than 30ddays after an application is docketed and remain posted while

the application ispending before the Commission, during the term of

the license, and. for 30 days following license termination.

NOTE:. -Copies of Form NRC-3 may be obtained by writing to the

Regional Administrator of the appropriate U.S. Nuclear Regulatory Commission Regional Office listed in Appendix D; Part 20 of this chapter

or the Director, Office of Inspection and Enforcement, U.S. Nuclear

Regulatory Commission, Washington, D.C. 20555.

Subpart B: Licenses

§61.10 Content of application.

(a) An application to receive from others, possess and dispose

of wastes containing or contaminated with source, byproduct or special

nuclear material by land disposal must consist of general information,

specific technical information, institutional information, and financial

information as set forth in §§61.11 through 61.16. An environmental

report prepared in accordance with Part 51 of this chapter must accompany

the application.

§61.11 General information.

The general information must include each of the following:

(a) Identity of the applicant including:

(1) The full name, address, telephone number and description of

the business or occupation of the applicant;

(2) If the applicant, is a partnership, the name, and address of

each partner and the principal location where the partnership does

business;

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(3) If the applicant is a corporation or an unincorporated association, (i) the state where it is incorporated or organized and the

principal location where, it does business, and (ii) the names and

addresses of its directors andprincipal officers; and

(4) If the applicant isacting as an agent.or representative of

another person in filing the applicatioin, all information required under

this paragraph must be suppliedwith respect to the other person.

(b) Qualifications of the applicant:

'(1) 'The organizational structure of the applicant, both offsite

and onsite, including a description of lines of authority and assignments of responsibilities, whether in the form of administrative

directives, contract provisions, or otherwise;-

.(2) 'The technical qualifications, including~training and-experience,

of the'applicant and members of the applicant's staff to engage in the

proposed activities. Minimum training and experience requirements for

personnel filling key positions described in Paragraph 61;11(b)(1) must

be provided.

'(3) A description of the applicant's personnel training program;

and

(4) The plan to maintain an:adequate complement of trained personnel to.carry.out waste receipt, handling,'and-disposal operations

- in a safe manner. .

(c) A-description of.:,

(1)'..4The location of the.proposed disposal site;;

(2) The general':character ofthe proposed activities;.

(3) The types and quantities of radioactive waste to be received,

possessed, and disposed of;

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(4) Plans for use of the land disposal' facility for purposes other

than disposal of radioactive wastes; and

(5) The proposed facilities and equipment.

(d) Proposed schedules for construction,'receipt of waste, and

first emplacement of waste at the proposed land disposal facility.

§61.12 Specific technical information.

The specific technical information must include the following information needed for demonstration that the performance objectives of Subpart

C of this part and the applicable technical requirements of Subpart D of

this part will be met:

(a) A description of the natural and demographic disposal site

characteristics as determined by disposal site selection and characterization activities. The description must include geologic, geotechnical, hydrologic, meteorologic, climatologic, and biotic features of

the disposal site and vicinity.

(b) A description of the design features of the land disposal

facility and the disposal units. For near-surface disposal, the description must include those design features related to infiltration of water;

integrity of-covers for disposal units; structural stability of backfill,

-wastes, and covers; contact of wastes with standing water; disposal site

drainage; disposal site closure and stabilization; elimination to the

extent practicable of long-term disposal site maintenance; inadvertent

intrusion; occupational exposures; disposal site monitoring; and adequacy of the size of the buffer zone for monitoring and potential

mitigative measures.

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(c) A description of the principal design criteria and their

relationship to the performanceobjectives.

(d) A descriptionof the design basis natural events or phenomena

and their relationship to theprincipal design criteria.

(e) A description of codes.and standards which.the applicant has

applied.to the-design and which will apply to construction of the land

disposal facilities..

(f) A description of the construction and operation of the land

disposal facility. The description must include as a minimum the

,.methods of.constructionof disposal units; waste emplacement; the

procedures for and areas of waste segregation; types of,intruder

b.barriers; onsite traffic and drainage systems; survey control program;

methods and areas of waste storage; and methods tomcontrol surface water

and groundwater access to the wastes., The description-must also include

a description of the methods to be employed in the handling and disposal

of wastes containing chelating agents or other non-radiological substances

that might affect meeting the performance objectives in Subpart C of

"this part.

(g) A description of the.disposal site closure plan, including

those design features which are intended to facilitate.disposal site

closure and to eliminate the need for ongoing active maintenance.

. (h) An identification of the known natural.resources at the

disposal site, the exploitation of which could result in inadvertent

intrusion into the low-level wastes after-removal of 'active institutional'control.'

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(i) A description of the kind, amount, classification and specifications of the radioactive material proposed to be received, possessed,

and disposed of at the land disposal facility.

(j) A description of the quality control program for the determination of natural disposal site characteristics and for quality control

during the design, construction, operation and closure of the land disposal facility and the receipt, handling, and emplacement of waste.

Audits and managerial controls must be included.

(k) A description of the radiation safety program for control and

monitoring of radioactive effluents to ensure compliance with the performance objective in §61.41 of this part and occupational radiation exposure to ensure compliance with the requirements of Part 20 of this chapter and to control contamination of personnel, vehicles, equipment,

buildings, and the disposal site. Both routine operations and accidents

must be addressed. The program description must include procedures,

instrumentation, facilities, and equipment.

(1) A description of the environmental monitoring program to

provide data to evaluate potential health and environmental impacts and

the plan for taking corrective measures if migration of radionuclides

is indicated.

(m) A description of the administrative procedures that the

applicant will apply to control activities at the land disposal facility.

§61.13 Technical analyses.

The specific technical information must also include the following

analyses needed to demonstrate that the performance objectives of

Subpart C of this part will be met:

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(a) Pathways analyzed in demonstrating protection of the general

population from releases of radioactivity must include air, soil, groundwater, surface water, plant uptake, and exhumation by burrowing animals.

The analyses must clearly identify and differentiate between the roles

performed by the natural disposal site characteristics and design

features in isolating and segregating the wastes. The analyses must

clearly demonstrate that there is reasonable assurance that the

exposures to humans from the release of radioactivity will not exceed

the limits set forth in §61.41.

(b) Analyses of the protection of individuals from inadvertent

intrusion must include demonstration that there is reasonable assurance

the waste classification and segregation requirements will be met and

that adequate barriers to inadvertent intrusion will be provided.

(c) Analyses of the protection of individuals during operations

must include assessments of expected exposures due'toroutine:operations

andlikely-accidents during handling, storage, and disposal of waste.

The analyses must provide reasonable assurance that exposures will be

controlled to meet the requirements of Part 20 of this chapter.

(d) Analyses of the long-term stability of the disposal site and

'the need for ongoing activemaintenance afte'r'closure mrust be based upon

analyses of active natural processes such as eros'ion, mass wasting,

' slop~e failure, settlement of w-astes and backfill, infiltration through

covers over dispo-s'al areas m'and'adjacent soils,' and'surface drainage of

the disposal site. The a6nalyses must provide 'reasonable assurance that

there will 'not'be 'a ne'ed for 'ongoing active maintenance of thee disposal

site following' closure. ' -

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§61.14 Institutional information.

The institutional information must include:

(a) A certification by the Federal or State government which owns

the disposal site that the Federal or State government is prepared to

accept transfer of the license when the provisions of §61.30 are met,

and will assume responsibility for custodial care after site closure

and postclosure'observation and maintenance.

(b) Where the proposed disposal site is on land not owned by the

Federal or a State government, the applicant must submit evidence that

arrangements have been made for assumption of ownership in fee by the

Federal or a State government before the Commission issues a license.

§61.15 Financial information.

The financial information must be sufficient to demonstrate that

the financial qualifications of the applicant are adequate to carry out

the activities for which-the license is sought and meet other financial

assurance requirements as specified in Subpart E of this part.

§61.16 Other information.

Depending upon the nature of the wastes to be disposed of, and the

design and proposed operation of the land disposal facility, additional

information may be requested by the Commission including the following:

(a) Physical security measures, if appropriate. Any application

to receive and possess special nuclear material. in quantities subject to

the requirements of Part 73 of this chapter shall demonstrate how the

physical security requirements of Part 73 will De met. In determining

whether receipt and possession will be subject to the requirements of

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Part 73, the applicant shall not consider the quantity of special

nuclear material that has been disposed of.

(b) Safety information concerning'criticality, if appropriate.

(1) Any application to-receive and possess special nuclear material

in quantities that would be subject to the requirements-'of §70.-24,

"Criticality accident requirements" of Part 70 of this chapter shall

demonstrate how the requirements of that section will be met, unless the

applicant.requests an exemption pursuant to § 70.24(d). In determining

whether receipt and possession would be subject to the requirements of

§70.24, the applicant shall not consider the quantity of special nuclear

material that has been disposed of.

(2) Any application to receive and possess special nuclear material'

shall describe proposed procedures for avoiding accidental criticality,

which address both storage of special nuclear material prior to disposal

and waste emplacement for disposal.

§61.20 Filing and distribution of application.

(a) An application for a license under this part, and any amendments

thereto, shall be filed with the Director, must be signed by the applicant

or the applicant's authorized representative under oath, and must consist

of 1 signed original and 2 copies.

(b) Another 85 copies of the application and environmental report

must be retained by the applicant for distribution in accordance with

written instructions from the Director or designee. :-, ~r. .*- . *;

(c) Fees. Application, amendment, and inspection fees applicable

to a license covering the receipt and disposal of radioactive wastes in

a land disposal facility are required by Part 170 of this chapter.

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§61.21 Elimination of repetition.

In its application or environmental report, the applicant may

incorporate by reference information contained in previous applications,

statements, or reports filed with the Commission if these references are

clear and specific.

§61.22 Updating of application and environmental report.

(a) The application and environmental report must be as complete

as possible in the light of information that is available at the time of

submittal.

(b) The applicant shall supplement its application or environmental

report in a timely manner, as necessary, to permit the Commission to

review, prior to issuance of a license, any changes in the activities

proposed to be carried out or new information regarding the proposed

activities.

§61.23 Standards for issuance of a license.

A license for the receipt, possession, and disposal of waste containing or contaminated with source, special nuclear, or byproduct

material will be issued by the Commission upon finding that the issuance

of the license will not be inimical to the common defense and security

and will not constitute an unreasonable risk to the health and safety of

the public, and:

(a) The applicant is qualified by reason of training and experience

to carry out the disposal operations requested in a manner that protects

health and minimizes danger to life or property.

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(b) The applicant's proposed disposal site, disposal design, land

disposal facility operations (including equipment, facilities, and procedures), disposal site closure, and postclosure institutional control are

adequate-to protect the public health and safety.in that they provide

reasonable assurance that the general population will be-protected from

releases of radioactivity as specified in the performance objective

.- in-§6141,.Protection of the general population from.releases of

radioactivity.

-(c) The applicant's proposed disposal site, disposal site design,

land disposal facility operations (including equipment; facilities, and

procedures), disposal site closure, and postclosure institutional control

. .are-adequate-to protect the .public health and safety-in that-they will

-provide reasonable assurance that individual inadvertent intruders are

protected in accordance with the performance objective in-§61.42,

,.. .Protection.of individuals from-.inadvertent intrusion.

(d) -The applicant's proposed.land disposal facility operations,

-including equipment, facilities;,-and procedures, are adequate to protect

- the.public health and safety.in-that they will provide reasonable assurance-that the standards-for radiation protection set out.in Part 20 of

this chapter will be met.

(e). The applicant's proposed disposal site, disposal site design,

land disposal facility operations, -disposal site closure, and post-

.closure institutional control-are adequate to protect the public health

and safety in that they will provide reasonable assurance that long-term

stability of the disposed waste and the disposal site will be achieved

* - and will eliminate to the extent practicable the need for ongoing active

maintenance of the disposal site following closure.

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(f) The applicant's demonstration provides reasonable assurance

that the applicable technical requirements of Subpart D of this part

will be met.

(g) The applicant's proposal for institutional control provides

reasonable assurance that institutional control will be provided for the

length of time found necessary to ensure the findings in paragraphs

(b)-(e) of this section and that the institutional control meets the

requirements of §61.59, Institutional requirements.

(h) The information on financial assurances meets the requirements

of Subpart E of this part.

(i) The applicant's physical security information provides reasonable assurance that the requirements of Part 73 of this chapter will be

met, insofar as they are applicable to special nuclear material to be

possessed before disposal under the license.

(j) The applicant's criticality safety procedures are adequate to

protect the public health and safety and provide reasonable assurance

that the requirements of §70.24, Criticality accident requirements, of

Part 70 of this chapter will be met, insofar as they are applicable to

special nuclear material to be possessed before disposal under the

license.

(k) Any additional information submitted as requested by the

Commission pursuant to §61.16, Other information, is adequate.

(1) The requirements of Part 51 of this chapter have been met.

§61.24 Conditions of licenses.

(a) A license issued under this part, or any right thereunder, may

be transferred, assigned, or in any manner disposed of, either voluntarily

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or involuntarily, directly or indirectly, through transfer of control of

the license to any person, only if the Commission finds, after securing

full information, that the transfer -is in accordance with the provisions

of the Atomic Energy Act and gives its consent in writing in the form of

a license amendment.

(b) The licensee shall submit written statements under oath upon

request of the Commission, at any time before termination of. the- license,

to enable the Commission to determine whether or not the license should

be modified, suspended, or revoked.-

C(c) The license will be transferred to the site 'owner. only on the

full implementation of the final closure plan as approved by the Commission, including post-closure observation and maintenance.

(d) The licensee shall -be -subject to the provisions of the Atomic

-- Energy Act now or hereafter-in effect, and to all rules, regulations,

and orders of the Commission. .The terms and conditions of the license

are-subject to amendment, revision,- or modification, by reason of amend-

,ments to, or by reason of rules, regulations, and orders issued in

. accordance with the;terms of the Atomic Energy Act.,,

(e)- Any license.may be~revoked, suspended or~modified in whole or

in part for any material false statement in the application or any

. statement of fact required under Section 182 of the Act, or because of

conditions revealed by any application or statement of fact or any

report,.record, or..inspection orother means which would warrant the

-Commission to refuse-to grant a license to the original application, or

for failure to operate-the facility in accordance-with the terms of the

.. license, or for any violation of,.or failure to observe any of the terms

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and conditions of the Act, or any rule, regulation, license or order of

the Commission.

(f) Each person licensed by the Commission pursuant to the regulations in this part shall confine possession and use of materials to the

locations and purposes authorized in the license.

(g) No radioactive waste may be disposed of until the Commission

has inspected the land disposal facility and has found it to be in

conformance with the description, design, and construction described in

the application for a license.

(h) The Commission may incorporate in any license at the time of

issuance, or thereafter, by appropriate rule, regulation or order,

additional requirements and conditions with respect to the licensee's

receipt, possession, and disposal of source, special nuclear or

byproduct material as it deems appropriate or necessary in order to:

(1) Promote the common defense and security;

(2) Protect health or to minimize danger to life or property;

(3) Require reports and the keeping of records, and to provide for

inspections of activities under the license that may be necessary or

appropriate to effectuate the purposes of the Act and regulations

thereunder.

(i) Any licensee who receives and possesses special nuclear material under this part in quantities that-would-be subject to the requirements of §70.24 of Part 70 of this chapter shall comply with the requirements of that section. The licensee shall not consider the quantity of

special nuclear material that has been disposed of.

(j) The authority to dispose of wastes expires on the date stated

in the license except as provided in § 61.27(a) of this part.

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§61.25 Changes.

(a) Except as provided for in specific license conditions, the

licensee shalinot make changes in the land disposal facility'or procedures described in the license application. The license will include

conditions 'restricting subsequent changes to the facility' and 'the procedures authorized which are important to public health and safety. These.

license restrictions will fall into three categories of descending

importance to public health and safety as follows: (1) those features

and procedures which may not be changed without (i) 60 days prior notice

to the Commision, (ii) 30 days notice of opportunity for a prior hearing,

and (iii) prior Commission approval; (2) those features and procedures

which may not be changed without (i) 60 days prior notice to the Commission, and (ii) prior Commission approval; and (3) those features and

procedures which may not be .changed without 60 days prior notice to the

Commission. Features and procedures falling in paragraph (a)(3) of this

section may not be changed without prior Commission approval if the

Commission, after having received the required notice, so orders.

(b) Amendments authorizing site closure, license transfer, or

license termination shall be included in paragraph (a)(1) of this

section.

(c) The Commission shall provide a copy of the notice for oppore tunity for hearings provided in paragraph (a)(1) of this section to

State and local officials or tribal governing bodies specified in

§ 2.104(e) of Part 2 of this chapter.

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§61.26 Amendment of license.

(a) An application for amendment of a license must be filed in

accordance with §61.20 and shall fully describe the changes desired.

(b) In determining whether an amendment to a license will be

approved, the Commission wil~l apply the criteria set forth in §61.23.

§61.27 Application for renewal or closure.

(a) Any expiration date on a license applies only to the above

ground activities and to the authority to dispose of waste. Failure to

renew the license shall not relieve the licensee of responsibility for

carrying out site closure, postclosure observation and transfer of the

license to the site owner. An application for renewal or an application

for closure under §61.28 must be filed at least 30 days prior to license

expiration.

(b) Applications for renewal of a license must be filed in accordance with §§61.10 through 61.16 and 61.20. Applications for closure

must be filed in accordance with §§61.20 and 61.28. Information contained in previous applications, statements or reports filed with the

Commission under the license may be incorporated by reference if the

references are clear and specific.

(c) In any case in which a licensee has timely filed an application for renewal of a license, the license for continued receipt and

disposal of licensed materials does not expire until the Commission has

taken final action on the application for renewal.

(d) In determining whether a license will be renewed, the Commission will apply the criteria set forth in §61.23.

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[7590-01)

§61.28 Contents of application for closure.

(a) Prior to final closure of the disposal site, or as otherwise

directed by the Commission, the applicant shall submit an application to

amend the license for closure. This closure application must include a

final revision and specific details of the disposal site closure plan

included as part of the license application submitted under §61.12(g)

that includes each of the following:

(1) Any additional geologic, hydrologic, or other disposal site

data pertinent to the long-term containment of emplaced radioactive

wastes obtained during the operational period.

(2) The results of tests, experiments, or any other analyses

relating to backfill of excavated areas, closure and sealing, waste

migration and interaction with emplacement media, or any other, tests,

* experiments, or analysis pertinent to the long-term containment of

emplaced waste within the disposal site.

(3) Any proposed revision of plans for:

(i) Decontamination and/or dismantlement of surface facilities;

(ii) Backfilling of excavated areas; or

(iii) Stabilization of the disposal site for post-closure care.

(4) Any significant new information regarding the environmental

,impact of closure activities and long-term performance of the disposal

site.

(b) Upon review and consideration of an application to amend the

license for closure submitted in accordance with paragraph (a) of this

section, the Commission shall issue an amendment authorizing closure if

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[7590-01)

there is reasonable assurance that the long-term performance objectives

of Subpart C of this part will be met.

§61.29 Post-closure observation and maintenance.

Following completion of closure authorized in §61.28, the licensee

shall observe, monitor, and carry out necessary maintenance and repairs

at the disposal site until the license is transferred by the Commission in

accordance with §61.30. Responsibility for the disposal site must be

maintained by the licensee for 5 years. A shorter or longer time period

for post-closure observation and maintenance may be established and

approved as part of the site closure plan, based on site-specific

conditions.

§61.30 Transfer of license.

(a) Following closure and the period of post-closure observation

and maintenance, the licensee may apply for an amendment to transfer the

license to the disposal site owner. The license shall be transferred

when the Commission finds:

(1) That the closure of the disposal site has been made in conformance with the licensee's disposal site closure plan, as amended and

approved as part of the license;

(2) That reasonable assurance has been provided by the licensee

that the performance objectives of Subpart C of this part are met;

(3) That any funds and necessary records for care will be

transferred to the disposal site owner;

(4) That the post-closure monitoring program is operational for

implementation by the disposal site owner; and

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(5) That the-Federal or State government agency which will assume

responsibility for institutional control of the disposal siteis prepared

to assume responsibility and ensure-that the institutional requirements

found necessary,under §61.23(g) will be met.

§61.31 Termination of license.

(a) Following any period of institutional control needed to meet

the requirements found necessary under §61.23, the licensee may apply

for an amendment to terminate the license.'

(b) This application must,,be:.filed,.andwill be reviewed, in

accordance.with the provision.of §61.20 and of..this section...-

(c) .A.license is terminated only, when the Commission finds:

_(1) That the institutional control requirements found necessary

under §61.23(g) have been met; and

(2) That any additiornal requirement's resulting from new information-developed during the institutional control period have been met,

and that permanent monuments or'markers warning against intrusion have

been installed. '

Subpart C: Performance Objectives

§61.40 General requirement., ..

Land disposal facilities must be sited, designed, operated, closed,

and controlled after closure so that reasonable assurance exists that

exposures'to humans'are within the'limits established'in the performance

objectives in'§§61.41 through 61.44.

§61.41 Protection of the.general population from releases of radioactivity.

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Concentrations of radioactive material which may be released to the

general environment in ground water', surface water, air, soil, plants,

or animals must not'result in an annual dose exceeding an equivalent of

25 millirems to the whole'body, 75 millirems to the thyroid, and

25 millirems to any other organ of any member of the public. Reasonable effort should be made to maintain releases of radioactivity in

effluents to the general environment as low as is reasonably achievable.

§61.42 Protection of individuals from inadvertent intrusion.

Design, operation, and closure of the land' disposal facility must

ensure protection of'any individual inadvertently intruding'into the disposal site and occupying the site or'contacting'dthe waste at any time

after active institutional controls over the disposal site are removed.

§61.43 Protection of individuals during operations.

Operations at the land disposal facility must be-conducted in compliance with the standards for. radiation protection set out in Part 20

of this chapter, except for releases of radioactivity in effluents from

the land disposal facility, which shall be governed by § 61.41 of this

part. Every reasonable effort shall be made to maintain radiation exposures as low as is reasonably achievable.

§61.44 Stability of the disposal site after closure.

The disposal facility must be sited, designed, used, operated, and

closed to achieve long-term stability of the disposal site and to eliminate to the extent practicable the need for ongoing active maintenance

of the disposal site following closure so that only surveillance, monitoring, or minor custodial care are required.

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Subpart D: Technical Requirements for Land Disposal Facilities

§61.50 Disposal site suitability requirements for land disposal.

(a) Disposal site suitability for near-surface disposal.

(1) The purpose of this section is to specify the minimum

characteristics a disposal site must have to be acceptable for use as a

near-surface disposal facility. The primary emphasis in disposal site

suitability is given to isolation of wastes, a matter having long-term ,'] . a ': * i - ' 2

impacts, and to disposal site features that ensure that the long-term

performance objectives of Subpart C of this part are met, as opposed

to short-term convenience or benefits.

(2) The disposal site shall be capable of being characterized,

modeled, analyzed and monitored.

(3) Within the region or state where the facility is to be located,

a disposal site should be selected so that projected population growth

and future developments are not likely to affect the ability of the

disposal facility to meet the performance objectives of Subpart C of

this part.

(4) Areas must be avoided having known natural resources which,

if exploited, would result in failure to meet the performance objectives of Subpart C of this part.

(5) The disposal site must be generally well drained and free of

areas of flooding or frequent ponding. Waste disposal shall not take

place in a 100-year flood plain, coastal high-hazard area or wetland, as

defined in Executive Order 11988, "Floodplain Management Guidelines'."

(6) Upstream drainage areas must be minimized to decrease the

amount of runoff which could erode or inundate waste disposal units.

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(7) The disposal site must provide sufficient depth to the water

table that ground water intrusion, perennial or otherwise, into the

waste will not occur. The Commission will consider an exception to

this requirement to allow disposal below the water table if it can be

conclusively shown that disposal site characteristics will result in

molecular diffusion being the predominant means of radionuclide movement

and the rate of movement will result in the performance objectives of

Subpart C of this part being met. In no case will waste disposal be

permitted in the zone of fluctuation of the water table.

(8) The hydrogeologic unit used for disposal shall not discharge

ground water to the surface within the disposal site.

(9) Areas must be avoided where tectonic processes such as

faulting, folding, seismic activity, or vulcanism ma y occur with such

frequency and extent to significantly affect the ability of the

disposal site to meet the performance objectives of Subpart C of this

part, or may preclude defensible modeling and prediction of long-term

impacts.

(10) Areas must be avoided where surface geologic processes such

as mass wasting, erosion, slumping, landsliding, or weathering occur

with such frequency and extent to significantly affect the ability of

the disposal site to meet the performance objectives of Subpart C of

this part, or may preclude defensible modeling and prediction of longterm impacts.

(11) The disposal site must not be located where nearby facilities

or activities could adversely impact the ability of the site to meet the

performance objectives of Subpart C of this part or significantly mask

the environmental monitoring program.

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(b) Disposal site suitability requirements for land disposal other

than near-surface (reserved).

§61.51 Disposal site designfor land disposal.

(a) Disposal site design for near-surface disposal.

(1) Site design features must be directed toward long-term

isolation and avoidance of the need for continuing active maintenance

after site closure.

(2) The disposal site design and operation must be compatible with

the disposal, site closure and stabilization plan and lead to disposal

-site closure that provides reasonable assurance that the performance

objectives of Subpart C of this part will be met.

(3) The disposal site must be designed to complement and improve,

where appropriate, the ability of the disposal. site's natural characteristics to assure that the performance objectives of Subpart Cof. this

part will,be met.

,(4) ,.Covers must be designed to minimize to the extent practicable

water infiltration, to direct percolating or surface water away from the

disposed waste, and to resist degradation by surface geologic processes

and biotic activity.

(5) Surface features must direct surface water drainage away from

disposal units at velocities and gradients which will not result in

erosion that will require ongoing active maintenance in the.future.

(6), The disposal site must be designed to minimize to the extent

practicable the contact ofwater with waste during storage, the contact

of standing water with.waste:during disposal, and the contact of percolating or standing water with wastes after disposal.

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(b) Disposal site design for' other than near-surface disposal

(reserved).

§61.52 Land disposal facility operation and disposal site closure.

(a) Near-surface disposal facility'operation and disposal site

closure.

(1) Wastes designated as Class A pursuant to §61.55, must be

segregated from other wastes by placing in disposal units which are sufficiently separated from disposal units for the other waste classes so that

any interaction between Class A wastes and other wastes will not result

in the failure to meet the performance objectives in Subpart C of this

Part. This segregation is not necessary for Class A'wastes if they meet

the stability requirements in § 61.56(b) of this part.

(2) Wastes designated as Class C pursuant to §61.55, must be disposed of so that the top of the waste is a minimum of 5 meters below the

top surface of the cover or must be disposed of with intruder barriers

that are designed to protect against an inadvertent intrusion for at

least 500 years.

(3) All wastes shall be disposed of in accordance with the requirements of paragraphs (a)(4) through (11) of this section.

(4) Wastes must be emplaced in a manner that maintains the package

integrity during emplacement, minimizes the void spaces between packages,

and permits the void spaces to be filled.'

(5) Void spaces between waste packages must be filled with earth

or other material to reduce future subsidence within the fill.

(6)' Waste must be placed and covered in a manner that limits the

radiation dose rate at the surface of the cover to levels that at a

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minimum will permit the licensee to comply with all provisions of

§ 20.105 of this chapter at the time the license is transferred pursuant

to § 61.30 of this part.

(7) The boundaries and locations of each disposal unit (e.g.,

trenches) must De accurately located and mapped by means of a land

survey. Near-surface disposal units must be marked in such a way that

the boundaries of each unit can be easily defined. Three permanent

survey marker control points, referenced to United States Geological

Survey (USGS) or National Geodetic Survey (NGS) survey control stations,

must be established on the site to facilitate surveys. The USGS or NGS

control stations must provide horizontal and vertical controls as

checked against USGS or NGS record files.

(8) A buffer zone of land must be maintained between any buried

waste and the disposal site boundary and beneath the disposed waste.

The buffer zone shall be of adequate dimensions to carry out environmental monitoring activities specified in § 61.53(d) of this part and

take mitigative measures if needed.

(9) Closure and stabilization measures as set forth in the approved

site closure plan must be carried out as each disposal unit (e.g., each

trench) is filled and covered.

(10) Active waste disposal operations must not have an adverse

effect on completed closure and stabilization measures.

(11) Only wastes containing or contaminated with radioactive materials shall be disposed of at the disposal site.

(b) Facility operation and disposal site closure for land disposal

facilities other than near-surface (reserved).

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§61.53 Environmental monitoring.

(a) At the time a license application is submitted, the applicant

shall have conducted a preoperational monitoring program to provide

basic environmental data on the disposal site characteristics. The

applicant shall obtain information about the ecology, meteorology,

climate, hydrology, geology, geochemistry, and seismology of the disposal

site. For those characteristics that are subject to seasonal variation,

data must cover at least a twelve month period.

(b) The licensee must have plans for taking corrective measures if

migration of radionuclides would indicate that the performance objectives

of Subpart C may not be met.

(c) During the land disposal facility site construction and operation, the licensee shall maintain a monitoring program. Measurements

and observations must be made and recorded to provide data to evaluate

the potential health and environmental impacts during both the construction and the operation of the facility and to enable the evaluation of

long-term effects and the need for mitigative measures. The monitoring

system must be capable of providing early warning of releases of radionuclides from the disposal site before they leave the site boundary.

(d) After the disposal site is closed, the licensee responsible

for post-operational surveillance of the disposal site shall maintain a

monitoring system based on the operating history and the closure and

stabilization of the disposal site. The monitoring system must be

capable of providing early warning of releases of radionuclides from the

disposal site before they leave the site boundary.

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§61.54 -Alternative requirements for design and operations.

The Commission'may, upon request or on its own initiative, authorize

provisions other than those set forth in §§61.51 through 61.53 for the

segregation and disposal of waste and for the design'and operation of a

land disposal facility on a specific basis, if it finds reasonable assurance of compliance with the performance objectives of Subpart C of this

part.

§61.55 Waste classification.

(a) Classification of waste for near surface disposal.

(1) Considerations. Determination of the classification'of radioactive waste involves two considerations. First, consideration must be

given to the concentration of long-lived radionuclides'-(and their

-shorter-lived precursors) whose potential hazard will persist long after

such precautions as institutional controls, improved waste form',and

deeper disposal have ceased to be effective. These precautions'delay

the time when long-lived radionuclides could cause exposures. In

addition, the magnitude of the potential dose is limited by the concentration and availability of the radionuclide at the time of exposure.

Second, consideration must be given to the concentration of shorterlived radionuclides for which requirements on institutional controls,

waste form, and disposal methods-are effective.-

(2) Classes of waste.

(i) Class A wasteis waste that is usually segregated from other

waste classes at the disposal site. The physical form and characteristics of Class A waste must meet the minimum requirements set forth

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in §61.56(a). If Class A waste also meets, the stability requirements

set forth in §61.56(b), it is not necessary to segregate the waste for

disposal.

(ii) Class B waste is waste that must meet more rigorous requirements on waste form to ensure stability after disposal. The physical

form and characteristics of Class B waste must meet both the minimum

and stability requirements set forth in §61.56.

(iii) Class C waste is waste that not only must meet more rigorous

requirements on waste form to ensure stability but also requires additional measures at the disposal facility to protect against inadvertent

intrusion. The physical form and characteristics of Class C waste must

meet both the minimum and stability requirements set forth in §61.56.

(iv) Waste that is not generally acceptable for near-surface

disposal is waste for which waste form and-disposal methods must be

different, and in general more stringent, than those specified for

Class C waste. In the absence of specific requirements in this part,

proposals for disposal of this waste may be submitted to the Commission for approval, pursuant to §61.58 of this part.

(3) Classification'determined by long-lived radionuclides. If

radioactive waste contains only radionuclides listed in Table 1,

classification shall be determined as follows:

(i) If the concentration does not exceed 0.1 times the value in

Table 1, the waste is Class A.

(ii) If the concentration exceeds 0.1 times the value in Table 1

but does not exceed the value in Table 1, the waste is Class C.

(iii) If the concentration exceeds the value in Table 1, the waste

is not generally acceptable for near-surface disposal.

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(iv) For wastes containing mixtures of radionuclides listed in

Table 1, the total concentration shall be determined by the sum of

fractions rule described in paragraph (a)(7) of. this section.

Table 1

Radionuclide

C-14

C-14 in activated metal

Ni-59 in activated metal

.Nb-94 in activated metal

Tc-99

I-129

Alpha emitting transuranic

nuclides with half-life

greater than five years

Pu-241

Cm-242

Concentration

Curies/cubic meter

8

80

220

0.2

3

0.08

100*

3,500*

20,000*

Units are nanocuries per gram

(4) Classification determined by short-lived radionuclides. If

radioactive waste does not contain' any of the radionuclides listed in

Table 1, classification shall be determined based on the concentrations

shown in Table 2. However, as specified in paragraph (6) of this section,

if radioactive waste does not contain any nuclides listed in either

Table 1 or 2, it is Class A.

(i) If the concentration does not exceed the value in Column 1,

the waste is Class A.

(ii) If the concentration exceeds the value in Column 1, but does

not exceed the value in Column 2, the waste is Class B.

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(iii) If.the concentration exceeds the value in Column 2, but does

not exceed the value in Column 3, the waste is Class C.

(iv) If the concentration exceeds the value in Column 3, the waste

is not generally acceptable for near-surface disposal.

(v) For wastes containing mixtures of the nuclides listed in

Table 2, the total concentration shall be determined by the sum of

fractions rule described in paragraph (a)(7) of this section.

Table 2

Concentration, Curies/cubic meter

Radionuclide Column 1 Column 2 Column 3

Total of all nuclides with

less than 5 year half life 700 ** **

H-3 40 **

Co-60 700 **

Ni-63 3.5 70 700

Ni-63 in activated metal 35 700 7000

Sr-90 0.04 150 7000

Cs-137 1 44 4600

There are no limits established for these radionuclides in Class B

or C wastes. Practical considerations such as the effects of

external radiation and internal heat generation on transportation,

handling, and disposal will limit the concentrations for these

wastes. These wastes shall be Class B unless the concentrations

of other nuclides in Table 2 determine the waste to the Class C

independent of these nuclides.

(5) Classification determined by both long- and short-lived radionuclides. If radioactive waste contains a mixture of radionuclides,

some of which are listed in Table 1, and some of which are listed in

Table 2, classification shall be determined as follows:

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(i), If the concentration of, a nuclide listed in Table 1 does not

exceed 0.1 times the value listed in Table 1, the class shall be that

determined by the concentration of nuclides listed in Table 2.

(ii) If the concentration of-a nuclide listed in Table 1 exceeds 0.1

times the value listed in Table 1 but does not exceed the value in Table 1,

the waste shall be Class C, provided the concentration of nuclides listed

in Table 2 does not exceed the value shown in Column 3 of Table 2.

(6) Classification of wastes with radionuclides'other than those

Listed in Tables 1 and 2. ;If. radioactive waste 'does not contain any

nuclides listed in either Table 1 or 2, it is Class A.

(7) The sum of the'fractions rule for mixtures of radionuclides.

For determining classification for waste that contains a mixture

of radionuclides, it is necessary-to determine the sum of fractions by

dividing each nuclide's concentration by the appropriate limit and

adding the resulting values.' The appropriate limits must all be taken

from the same column of the same table. The' sum of the fractions for

the column must be less than 1.0 if the waste class is to be'determined

'by that column. Example: *A waste contains Sr-90 in'a concentration of

50 Ci/m3 -and Cs-137 -in a concentration of 22 Ci/m3. Since the concentrati ons both exceed the values'.in Col umn 1, Table 2, they must be compared

to Column 2 values. For Sr-90 fraction, 50/150 = 0.33; for Cs-137

fraction, 22/44 ='0.5; the-sum-of the fractions = 0.83. Since the sum

is less than 1.0, the-waste is Class B.'

(8) Determination of:concentrations-in wastes. The concentration

of a radionuclide may be determined by indirect methods such as use of

-.scaling factors which relate the inferred concentration of one radionuclide to another that is measured, or radionuclide material

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accountability, if there is reasonable assurance that the indirect

methods can be correlated with 'actual measurements. The concentration

of a radionuclide may be averaged over the volume of the waste, or

weight of the waste if the units are expressed as nanocuries per gram.

§61.56 Waste characteristics.

(a) The following requirements are minimum requirements for all

classes of waste and are intended to facilitate handling at the disposal

site and provide protection of health and safety of personnel at

the disposal site.

(1) Wastes must not be packaged for disposal in cardboard or

fiberboard boxes.

(2) Liquid waste must be solidified or packaged in sufficient

absorbent material to absorb twice the volume of the liquid.

(3) Solid wastes containing liquid shall contain as little free

standing and non corrosive liquid as is reasonably achievable, but in no

case shall the liquid exceed 1% of the volume.

(4) Waste must not be readily capable of detonation or of

explosive decomposition or reaction at normal pressures and temperatures, or of explosive reaction with water.

(5) Waste must not contain, or be capable of generating, quantities

of toxic gases, vapors, or fumes harmful to persons transporting, handling,

or disposing of the waste. This does not apply to radioactive gaseous

waste packaged in accordance with paragraph (a)(7) of this section.

(6). Wastes must not be pyrophoric. Pyrophoric materials contained in

wastes shall be treated, prepared, and packaged to be nonflammable.

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(7) Wastes in a gaseous form must be packaged at a pressure that does

not exceed 1.5 atmospheres at 20'C. Total activity must not exceed

100 curies per container.

(8) Wastes containing hazardous, biological, pathogenic, or infectious

material must be treated to reduce to the maximum extent practicable the

potential hazard from the non-radiological materials.

(b) The requirements in this section are intended to provide

stability of the waste. Stability is intended to ensure that the waste

does not structurally degrade and affect overall stability of the site

through slumping, collapse, .or other failure of the disposal unit and

thereby lead to water infiltration. Stability is-also a factor in limiting exposure to an inadvertent intruder, since it provides a recognizable

and nondispersible waste.

(1) Waste must have structural stability. A structurally stable

waste form will generally maintain its physical dimensions and its form,

under the expected disposal conditions such as weight of overburden and

compaction equipment, the presence of moisture, and microbial activity,

and internal factors such as radiation effects and chemical changes.

Structural stability can be provided by the waste form itself, processing

.the waste to a stable form, or placing the waste in a disposal container

or structure that provides stability after disposal.

(2) Notwithstanding the provisions in.§§61.56(a)(2) and (3), liquid

wastes, or wastes containing liquid, must be converted into a form that

contains as little free standing and noncorrosive liquid as is reasonably

achievable, but in no case shall the liquid exceed 1% of the volume of

the waste when the waste is in a disposal container designed to

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ensure stability, or 0.5% of the volume of the waste for waste processed

to a stable form.,

(3) Void spaces within the waste and between the waste and its

package must be reduced to the extent practicable.

§61.57 Labeling.

Each package of waste must be clearly labeled to identify whether

it is Class A waste, Class B waste, or Class C waste, in accordance

with §61.55.

§61.58 Alternative requirements for waste classification and

characteristics.

The Commission may, upon request or on its own initiative, authorize

other provisions for the classification and characteristics of waste on a

specific basis, if, after evaluation, of the specific characteristics of

the waste, disposal site, and method of disposal, it finds reasonable

assurance of compliance with the performance objectives in Subpart C

of this part.

§61.59 Institutional requirements

(a) Land ownership. Disposal of radioactive waste received from

other persons may be permitted only on land owned in fee by the Federal

or a State government.

(b) Institutional control. The land owner or custodial agency

shall carry out an institutional control program to physically control

access to the disposal site following transfer of control of the disposal site from the disposal site operator. The institutional control

program must also include, but not be limited to, carrying out an

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environmental monitoring program at the disposal site, periodic surveillance, minor custodial care, and other requirements as determined by

the Commission;,and administration of funds to cover the costs for these

activities. The period of institutional controls will.be determined by

the Commission, but institutional controls may not be relied upon for

more than 100 years following transfer of control of the disposal site

to the owner.

Subpart E: Financial Assurances

§61.61 Applicant qualifications and assurances.

Each applicant shall show that it either possesses the necessary

funds or has.reasonable assurance of obtaining the necessary funds, or

by a combination of the two, to cover the estimated costs of conducting

all licensed activities over the planned operating life of the project,

including costs of construction and disposal.

§61.62 Funding for disposal site closure and stabilization.

(a) The applicant shall provide assurances that sufficient funds

will be available to carry out disposal site closure and stabilization,

including: (1) decontamination or dismantlement of land disposal facility structures; and (2) closure and stabilization of the disposal site

so that following transfer of the disposal site to the site owner, the

need for ongoing active maintenance is eliminated to the extent . . - ' - -

practicable and only minor custodial care, surveillance, and monitoring

are required. These assurances shall be based on Commission-approved

cost estimates reflecting the Commission-approved plan for disposal site

closure and stabilization. The applicant's cost estimates must take

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into account total capital costs that would be incurred if an independent

contractor were hired'to perform the closure and'stabilization work.

(b) In order to avoid unnecessary duplication and expense, the

Commission will accept financial sureties that have been consolidated

with earmarked financial or surety arrangements established to meet

requirements of other Federal or State agencies and/or local governing

bodies for such decontamination, closure and stabilization. The Commission will accept this arrangement only if they are considered adequate

to satisfy these requirements and that the portion of the surety which

covers the closure of the disposal site is clearly identified and

committed for use in accomplishing these activities.

(c) The licensee's surety mechanism will be annually reviewed by

the Commission to assure that sufficient funds are available for completion of the closure plan, assuming that the work has to be performed by

an independent contractor.

(d) The amount of surety liability should change in accordance with

the predicted cost of future closure and stabilization. Factors affecting

closure and stabilization cost estimates include: inflation; increases

in the amount of disturbed land; changes in engineering plans; closure

and stabilization that has already been accomplished and any other conditions affecting costs. This will yield a surety that is at least sufficient at all times to cover the costs of closure of the disposal units

that are expected to be used before the next license renewal.

(e) The term of the surety mechanism must be open ended unless it

can be demonstrated that another arrangement would provide an equivalent

level of assurance. This assurance could be provided with a surety

mechanism which is written for a specified period of time (e.g., five

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years) yet which must be automatically renewed unless the party who

issues the surety notifies the Commission and the beneficiary (the

site owner) and the principal (the licensee) not less than 90 days

prior to the renewal date of its intention not to renew. In such a

situation the licensee must submit a replacement surety within 30 days

after notification of cancellation. If the licensee fails to provide

a replacement surety acceptable to the Commission, the site owner may

collect on the original surety.

(f) Proof of forfeiture must not be necesssary to collect the

surety so that in the event that the licensee could not provide an acceptable replacement surety within the required time, the surety shall be

automatically collected prior to its expiration. The conditions described

above would have to be clearly stated on any surety instrument which is

not open-ended, and must be agreed to by all parties. Liability under

the surety mechanism must remain in effect until the closure and stabilization program has been completed and approved by the Commission and

the license has been transferred to the site owner.

(g) Financial surety arrangements generally acceptable to the

Commission include: surety bonds, cash deposits, certificates of deposit,

deposits of government securities, escrow accounts, irrevocable letters

or lines of credit, trust funds, and combinations of the above or such

other types of airrangements as may be approved by the Commission.

However, self-insurance, or any arrangement which essentially constitutes

pledging the assets of the licensee, will-not satisfy the surety requirement for private sector applicants since this provides no additional

assurance other than that which already exists through license re -ureen

requirements.

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§61.63 Financial assurances for institutional controls.

(a) Prior to the issuance of the license, the applicant shall

provide for Commission review and approval a copy of a binding arrangement, such as a lease, between the applicant and the disposal site owner

that ensures that sufficient funds will be available to cover the costs

of monitoring and any required maintenance during the institutional

control period. The binding arrangement will be reviewed periodically

by the Commission to ensure that changes in inflation, technology and

disposal facility operations are reflected in the arrangements.

(b) Subsequent changes to the binding arrangement specified in

paragraph (a) of this section relevant to institutional control shall be

submitted to the Commission for approval.

Subpart F: Participation by State Governments and Indian Tribes

§61.70 Scope.

This subpart describes mechanisms through which the Commission will

implement a formal request from a State or tribal government to participate

in the review of a license application for a land disposal facility.

Nothing in this subpart may be construed to bar the State or tribal

governing body from participating in subsequent Commission proceedings

concerning the license application as provided under Federal law and

regulations.

§61.71 State and Tribal government consultation.

Upon request of a State or tribal governing body, the Director shall

make available Commission staff to discuss with representatives of the

State or tribal governing body information submitted by the applicant,

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applicable Commission regulations,- licensing procedures, potential schedules, and the type and scope of State activities in the license review

permitted by law. In addition, staff shall be made available to;consult

and cooperate with the State or tribal governing body in developing proposals for participation ih the.license review.

§61.72 Filing of proposals for State dnd tribal participation.

(a) A State or tribal governing body whose interest is affected

by a near-surface disposal facility at the proposed site may submit to

the Director a proposal for participation in the review of a license

application. Proposals must be submitted within the following time

periods:

(1) For the State in which the disposal facility will be located,

or any State that is member of an interstate compact that includes the

State in which the disposal facility is located, no later than 45 days

following publication in the Federal Register of the notice of tendering

of an application submitted under'§61.20.

(2) For any other State,'or for a tribal governing body, no later

than 120 days'following'publication in the Federal Register of the

notice of tendering of an application submitted under'§61:20.

(b) Proposals for participation'in the licensing process must

be made in writing and'must'b'esignedby the Governor of the'State or

the official"oth'erwise provided for by State or tribal law.

(c) -At a minimum, proposals must contain each of-the'following

items of information:

' (1) A general description of'how the'State or tribe wishes to

participate in the licensing process specifically identifying those

issues it wishes to review.

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* (2) A description of material and information which the State or

*tribe plans to submit to the Commission for consideration in the licensing

process. A tentative schedule referencing steps in the review and calendar

dates for planned submittals should be included.

(3) A description of any work that the State or tribe proposes to

perform for the Commission in support of the licensing process.

(4) A description of State or tribal plans to facilitate local

government and citizen participation.

(5) A preliminary estimate of the types and extent of impacts

which the State expects, should a disposal facility be located as

proposed.

(6) If desired, any requests for educational or information

services (seminars, public meetings) or other actions from the Commission such as establishment of additional Public Document Rooms or

exchange of State personnel under the Intergovernmental Personnel Act.

§61.73 Commission approval of proposals.,

(a) Upon receipt of a proposal submitted in accordance with § 61.72,

the Director shall arrange for a meeting between the representatives of

the State or tribal governing body and the Commission staff to discuss

the proposal and to ensure full and effective participation by the State

or tribe in the Commission's license review.

(b) If requested by a State or tribal governing body, the Director

may approve all or any part of a proposal if the Director determines that:

(1) The proposed activities are within the, scope of Commission

statutory responsibility and the type and magnitude of impacts which the

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State or tribe may bear are sufficient to justify their participation;

and

(2) The proposed activities will contribute productively to the

licensing review.

(c) The decision of the Director will be transmitted in writing to

the governor or the designated official of the tribal governing body.

(d) Participation by a State or Indian tribe shall.not affect

-their rights to participate.in.an adjudicatory hearing as provided by

Part 2 of this chapter.

Subpart G: Records, Reports, Tests, and Inspections

§61.80 Maintenance of records, reports, and transfers.

(a) Each licensee shall maintain any records and make any reports

in connection with the licensed activities as may be required by the conditions of the license or by the rules, regulations, and orders of the

Commission.

(b) Records which are required by the regulations in this part or

by license conditions must be maintained for a period specified by the

appropriate regulations.in this chapter or by license condition. If a

retention period is not otherwise specified, these records must be maintained and transferred to the officials specified in paragraph (e) of

this section as a condition of license termination unlessthe Commission

otherwise authorizes their disposition.

(c) Records which must be maintained pursuant to this part may be

the original or a reproduced copy or microfilm if this-reproduced copy

or microfilm is capable of producing copy that is clear and legible at

the end of the required retention period.

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(d) If there is a conflict between the Commission's regulations in

this part, license condition, or other written Commission approval or

authorization pertaining to the retention period for the same type of

record, the longest retention period specified takes precedence.

(e) Notwithstanding paragraphs (a) through (d) of this section,

copies of records of the location and the quantity of radioactive wastes

contained in the disposal site must be transferred upon license termination to the chief executive of the nearest municipality, the chief

executive of the county in which the facility is located, the county

zoning board or land development and planning agency, the state governor

and other State, local and Federal governmental agencies as designated

by the Commission at the time of license termination.

(f) Following receipt and acceptancerof a shipment of radioactive

waste, the licensee shall record the date of disposal of the waste, the

location in the disposal site, the condition of the waste packages as

received, any discrepancies between materials listed on the manifest

and those received, and any evidence of leaking or'damaged packages

or radiation or contamination levels in excess of limits specified in

Department of Transportation and Commission regulations. The licensee

shall briefly describe any repackaging operations of any of the waste

packages included in the shipment, plus any other information required

by the Commission as a license condition.

(g) Each licensee shall comply with the safeguards reporting

requirements of §§30.55, 40.64, 70.53 and 70.54 of this chapter if

the quantities or activities of materials received or transferred

exceed the limits of these sections. Inventory reports required by

these sections are not required for materials after disposal.

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(h) Each licensee authorized to dispose of radioactive waste

received from other persons shall file a copy of its financial report

or a certified financial statement annually with the Commission in order

to update the information base for determining financial qualifications.

(i)(1) Each licensee authorized to dispose of waste materials

received from other persons, !pursuant to this part, shall submit annual

reports to the appropriate Commission regional office shown in Appendix D of Part 20 of this chapter, with copies to the Director of the

Office of Inspection and Enforcement and the Director of the Division

of Waste Management, USNRC, Washington, D.C., 20555... Reports shall be

submitted by the end of the first calendar quarter of each year for the

preceding year; (2) The reports shall include (i) specification of the

quantity of each of the principal radionuclides released to unrestricted

areas in liquid and in airborne effluents during the'preceding year,

(ii) the results of the environmental monitoring program, (iii) a summary

of licensee'disposal unit survey and maintenance activities, (iv) a summary,' by waste class, of activities and quantities of radionuclides disposed of, .(v) any instances in which observed site characteristics were

.,significantly different-from those described inWthe application for a

license; and (vi) any'other -information the.Commission may require. If

the quantities of radioactive materials released during the reporting

period, monitoring results, or maintenance performed are significantly

different from those expected in the materials previously reviewed as

part of the;licensing action, the report must.cover this specifically.

(j) Each licensee shall report in accordance with the requirements of §70.52 of this chapter.

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(k) Any transfer of byproduct, source, and special nuclear

materials by the licensee is subject to the requirements in §§30.41,

40.51, and 70.42 of this chapter. Byproduct-, source and special

nuclear material means materials as defined in these parts, respectively.

§61.81 Tests at land disposal facilities.

(a) Each licensee shall perform, or permit the Commission to perform,

any tests as the Commission deems' appropriate or necessary for the administration of the regulations in this part,'including tests of:

(1) Radioactive wastes and facilities used for the receipt,' storage,

treatment, handling 'and disposal of radioactive wastes.

(2) Radiation detection and monitoring instruments; and

(3) Other equipment and devices- used in connection with the receipt,

possession, handling, treatment, storage, or disposal of radioactive waste.

§61.82 Commission inspections of land disposal facilities.

(a) Each licensee shall afford to the Commission at all reasonable

.times opportunity to inspect radioactive waste not yet disposed of, and

the premises, equipment, operations, and facilities in which radioactive

wastes are received, possessed, handled, treated, stored, or disposed of.

(b) Each licensee shall make available to the Commission for inspection, upon reasonable notice, records kept by it pursuant to the regulations in this chapter. Authorized representatives of the Commission may

copy and take away copies of, for the Commission's use,'any record

required to be kept pursuant to this part.

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§61.83 Violations.

An injunction or other court'order'nay be-obtained'prohibiting any

violationof'any provision of the'Atomic Energ'yAct of 1954, as amended,

or any regulation or order'issued thereunder."A court order may be

'obtained for the payment of a civil penalty imposed pursuant to'section 234 of the Act for violation of section 53, 57, 62, 63, 81, 82,

101, 103, 104, 107, or 109 of the Act, or section 206 of the Energy

Reorganization Act of 1974, or,'any rule.

The following amendments are also made to existing parts

of the regulations in this chapter

PART 2 - RULES OF PRACTICE

2. In §2.101, paragraph'(a)(2), (b),-and (d) are'revised to read

as follows:

§2.101 Filing of application.

(a)*

(2) Each application for a license for a facility will be assigned

a docket number. However, to allow a determination as .to whether an

application for a construction permit or operating license for a production or utilization facility is complete and acceptable for docketing,

it will be initially treated as a tendered application after it is

received and a copy of the ,tendered application will be available for

public inspection in the Commission's Public Document Room, 1717 H Street

NW., Washington, D.C. Generally, that determination will be made within

a period of thirty (30) days. However, in selected construction permit

applications, the Commission may decide to determine acceptability on

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[7590-01]

the basis of the technical adequacy of the application as well as its

completeness. In such cases, the Commission, pursuant to §2.104(a),

will direct that the notice of hearing.be issued as soon as practicable

after the application has been tendered, and the determination of

acceptability will generally be made within a period of sixty (60) days.

* .* * * *

(b) Each application for a license to receive radioactive waste

from other persons for disposal under Part 61 of this chapter and the

accompanying environmental report shall be processed in accordance with

the provisions of this paragraph.

(1) To allow a determination as to whether the application or

environmental report is complete and'acceptable for docketing, it will

be initially treated as a tendered document, and a copy will be available for public inspection in the Commission's Public Document Room

1717 H Street NW., Washington D.C; One original and two copies shall

be filed to enable this determination to be made.

(i) Upon receipt of a tendered application, the Commission will

publish in the Federal Register notice of the- filed application and will

notify the governors, legislatures and other appropriate State, county,

and municipal officials and tribal governing bodies of the States and

areas containing or potentially affected by the activities at the proposed site and the alternative sites. The Commission will inform these

officials that the Commission staff will be available for consultation

pursuant to §61.71 of this chapter. The Federal Register notice will

note the opportunity for interested persons to submit views and comments

on the tendered application for consideration by the Commission and

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[7590-01]

applicant. The Commission will also notify the U.S. Bureau of Indian

Affairs when tribal governing bodies are notified.

(ii) The Commission will also post a public notice in a newspaper

or newspapers of general circulation in the affected States and areas

summarizing information contained in the applicant's tendered application and noting the opportunity to submit views and comments.

(iii) When the Director of Nuclear Material Safety and Safeguards

determines that the tendered document'is complete and acceptable for

docketing, a docket number will be assigned 'and the applicant will be

notified of the determination. If it is determined that all or any part

of the tendered document is incomplete and therefore not acceptable for

processing, the applicant will be informed of this determination and the

aspects in which the document is deficient.

(2) With respect to any tendered document that is acceptable for

docketing, the applicant will be requested to (i) submit to the Director

of Nuclear Material Safety and Safeguards such additional copies as the

regulations in Parts 61 and 51 of this chapter require, (ii) serve a

copy on the chief executive of the municipality in which the waste is to

be disposed of or, if the waste is not to be disposed of within a

municipality, serve a copy on the-chief executive of the county in which

the waste is to be disposed of, (iii) make direct distribution of additional copies to Federal, State, Indian Tribe, and local officials in

accordance with the requirements of this Lhapter and written instructions from tne Director of Nuclear Material Safety and Safeguards, and

(iv) serve a notice of availability of the application and environmental

report on the chief executives or governing bodies of the municipalities

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[7590-01]

or counties which have been identified in the application and environmental report as the location of all or part of the alternative sites if

copies are not distributed under paragraph (b)(2)(iii) of this section

to t~he executives or bodies. All distributed copies shall be completely

assembled documents identified by docket number. Subsequently distributed

amendments, however, may include revised pages to previous submittals

and, in such cases, the recipients will be responsible for inserting the

revised pages. In complying with the requirements of paragraph (b) of

this section the applicant shall not make public distribution of those

parts of the application subject to §2.790(d).

(3) The tendered document will be formally docketed upon receipt

by the Director of Nuclear Material Safety and Safeguards of the

required additional copies. Distribution of the additional copies shall

be deemed to be complete as of the time the copies are deposited in the

mail or with a carrier prepaid for delivery to the designated addressees.

The date of docketing shall be the date when the required copies are

received by the Director of Nuclear Material Safety and Safeguards.

Within ten (10) days after docketing, the. applicant shall submit to the

Director of Nuclear Material Safety and Safeguards a written statement

that distribution of the additional copies to Federal, State, Indian

Tribe, and local officials has been completed in accordance with

requirements of this section and written instructions furnished to the

applicant by the Director of Nuclear Material Safety and Safeguards.

(4) Amendments to the application and environmental report shall

be filed and distributed and a written statement shall be furnished to

the Director of Nuclear Material Safety and Safeguards in the same

manner as for the initial application and environmental report.

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[7590-01)

(5) The Director of Nuclear Material Safety and Safeguards will

cause to be published in the Federal Register a notice of docketing

which identifies the State and location of the proposed waste disposal

facility and will give notice of docketing to the governor of that State

and other officials listed in paragraph (b)(3) of this section and, in a

reasonable period thereafter, publish in the Federal Register a notice

pursuant to §2.105 offering opportunity for a hearing to the applicant

and other affected persons.

* A * *

(d) The Director of Nuclear Reactor Regulation or Director of

Nuclear Material Safety and Safeguards, as appropriate, will give notice

of the docketing of the public health and safety, common defense and

security, and environmental parts of an application for a license for a

.'waste disposal facility to the Governor or other appropriate official of

the State in which the facility is to be located or the activity is to

be conducted and will cause to be published in the Federal:Register a

notice of docketing of the application which states the purpose of the

application and specifies the location at which the proposed activity

would be conducted.

3. Section 2.103 (a) is-revised to read as'follows:

§2.103 Action on applications for byproduct, source, special nuclear

material, and operator licenses.

(a) If the Director-of Nuclear Reactor Regulation or the Director

of Nuclear Material Safety and Safeguards, as appropriate, finds that an

application for a byproduct, source, special nuclear material, or operator

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[7590-01J

license complies with the requirements of the Act, the Energy Reorganization Act, and this chapter, he will issue a license. If the license is

for a facility or if it is to receive and possess high-level radioactive

waste at a geologic repository operations area pursuant to Part 60 of

this chapter, the Director of Nuclear Reactor Regulation or the Director

of Nuclear Material Safety and Safeguards, as appropriate, will inform the

State, tribal and local officials specified in §2.104(e) of the issuance

of the license. For notice of issuance requirements for licenses issued

pursuant to Part 61 of this chapter, see paragraph 2.106(d) of this part.

* * *A *

4. Section 2.104(e) is revised to read as follows:

§2.104 Notice of hearing.

* * *A. * *

(e) The Secretary will give timely notice of the hearing to all

parties and to other persons, if any, entitled by law to notice. The

Secretary will transmit a notice of hearing on an application for a

facility license or for a license for receipt of waste radioactive material from other persons for the purpose of disposal under Part 61 of this

chapter or for a license to receive and possess high-level radioactive

waste at a geologic repository operations area pursuant to Part 60 of this

chapter to the governor or other appropriate official of the State and to

the chief executive of the municipality in which the facility is to be

located or the activity is to be conducted or, if the facility is not to

be located or the activity conducted within a municipality, to the chief

executive of-the county (or to the Tribal organization, if it is to be

so located or conducted within an Indian reservation).

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[7590-01]

5. Section 2.105(a)(2) is revised to read as follows:

§2.105 Notice of proposed action.

(a) A *

(2) A license for receipt of waste radioactive material from other

persons for disposal by the waste disposal licensee under Part 61 of this

chapter.

A - A

6. Section 2.106 is amended by adding a new paragraph,(d) to read

as follows:

§2.106 Notice of issuance.

* * * *i *

(d) The Director of Nuclear Material Safety and Safeguards will also

cause to be published in the Federal Register notice of, and will inform

the State and local officials or'tribal'governing body specified in

§2.104(e) of any licensing action with respect to a license to-receive

radioactive waste from other persons for disposal under Part 61 of this

chapter or the amendment of such a license for which a notice of proposed

action has been previously published.

7. A new Section 2.765 is added to read as follows:

§2.765 Immediate effectiveness of initial decision directing issuance or

amendment of licenses under Part 61 of this chapter.

An initial decision directing the issuance of a license under

Part 61 of this chapter (relating to land disposal of radioactive waste)

or any amendment to such a license authorizing actions which-may significantly affect the health and safety of the public, will become effective

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[7590-01]

only upon order of the Commission. The Director of Nuclear Material

Safety and Safeguards may not issue a license under Part 61 of this

chapter, or any amendment to such a license which may significantly

affect the health and safety of the public, until expressly authorized

to do so by the Commission.

* * * * *

PART 19 - NOTICES, INSTRUCTIONS AND REPORTS TO WORKERS; INSPECTIONS

§19.2 [Amended]

8. Section 19.2 is amended by adding "61," following "40, 60."

§19.3 [Amended]

9. In §19.3, paragraph (d) is amended by adding "61," following

"40, 60."

PART 20 - STANDARDS FOR PROTECTION AGAINST RADIATION

§20.2 [Amended]

10. Section 20.2 is amended by adding "61," following "40, 60."

§20.3 [Amended]

11. In §20.3, paragraph (a)(9) is amended by adding "61,"

following 40, 60."

12. In §20.301 paragraph (a) is amended by adding "61," following

"40, 60," and paragraph (b) is revised to read as follows:

§20.301 General requirement.

A * * A *

(b) As authorized under §20. 302 or Part 61 of this chapter; or

A A A A

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[7590-01]

§20.302 [Amended]

13. In §20.302, paragraph (b) is removed and paragraph (c) is

redesignated as paragraph (b).'

14. A new §20.311 is added to read as follows:

§ 20.311 Transfer for disposal and manifests.

(a) 'Purpose. 'The requirements of this section are designed to

control transfers of radioactive waste intended for disposal atia land

disposal facility and establish a manifest tracking system and supplement

existing requirements concerning transfers and recordkeeping for such

wastes. The reporting and recordkeeping requirements 'contained 'in this

section have been approved by the Office of Management and Budget; OMB

,approval No. 3150-0014.

(b) Each shipment of radioactive waste to-a licensed land'disposal

facility must be accompanied by a shipment manifest that contains the

name, address, and telephone'number of the person generating the waste.

The'manifest shall also include the name, address, and telephone number

or the name and EPA hazardous waste identification number of the person

transporting the waste to the land disposal facility. The manifest must

also indicate as completely.as practicable: a physical description of

the waste; the volume; radionuclide identity and'quantity; the total

radioactivity; and the.principal chemical form. The solidification agent

must be specified. Wastes containing more than 0.1% chelating agents by

weight must be identified and the weight percentage of the chelating agent

estimated. Wastes classified'as Class A, Class-B. or.Class C in §61.55

of this chapter must be-clearly identified as such in the manifest. The

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[7590-01]

total quantity of the radionuclides H-3, C-14, Tc-99 and I-129 must be

shown. The manifest required by this paragraph may be shipping papers

used to meet Department of Transportation or Environmental Protection

Agency regulations or requirements of the receiver, provided all the

required information is included. Copies of manifests required by

this section may be legible carbon copies or legible photocopies.

(c) Each manifest must include a certification by the waste generator that the transported materials are properly classified, described,

packaged, marked, and labeled and are in proper condition for transportation according to the applicable regulations of-the Department of

Transportation and the Commission. An authorized representative of the

waste generator shall sign and date the manifest.

(d) Any generating licensee who transfers radioactive waste to a

land disposal facility or a licensed waste collector shall comply with

the requirements in subparagraphs (1) through (8). Any generating

licensee who transfers waste to a licensed waste processor who treats

or repackages waste shall comply with the requirements of subparagraphs

(4) through (8). A licensee shall:

(1) Prepare all wastes so that the waste is classified according

to §61.55 and meets the waste characteristics requirements in §61.56 of

this chapter;

(2) Label each package of waste to identify whether it is Class A

waste, Class B waste, or Class C waste, in accordance with §61.55 of

this chapter;

(3) Conduct a quality control program to assure compliance with

§§61.55 and-61.56 of this chapter; the program must include management

evaluation of audits;

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[7590-01]

(4) Prepare shipping manifests to meet the'`'equirements of §§20.311(b)

and (c) of this part;

(5) Forward a copy of the manifest to the intended recipient, at

the time of -shipment; 'or, deliver to a collector at-the time the waste

is collected, obtaining acknowledgement of receipt'in:the formbof a

signed copy of the manifest or equivalent documentation from the collector;

(6) Include one copy of the'manifest with the shipment,'

(7) Retain a copy of the manifest and documentation of acknowledgement'of receipt as the record of 'transfe'r of licensed material as required -

by Parts 30, 40,'and 70 of this chapter; and,

'(8) For any shipments or any part of a shipment for which acknowledgement of receipt has not been received within the'times set forth in

this section,' conduct an investigation in accordance with paragraph (h)

of this section.

(e) Any waste collector licensee who handles only prepackaged waste

shall:

(1) Acknowledge receipt of the waste from the generator within one

week of receipt by returning a signed copy of the manifest or equivalent

documentation;

(2) Prepare a new manifest-to reflect consolidated shipments; the

-new manifest shall serve as a listing or-index for the detailed generator

manifests. Copies of the;generator manifests shall be a-part of the new

manifest. The waste collector may prepare a new manifest-without attach-

'ing the generator manifests, provided the-new manifest contains for each

-'package the information'specified in-paragraph (b) of this section. The

collector licensee shall certify that nothing has-been'done'to'the waste

which would invalidate the generator's certification.

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[7590-01]

(3),. Forward a copy of the new manifest to the land disposal facility

operator at the time of shipment;

(4) Include the new manifest with the shipment to the disposal site;

(5) Retain a copy of the manifest and documentation of acknowledgement of receipt as the record of transfer of licensed material as required

by Parts 30, 40,- and 70 of this chapter, and retain information from

generator manifests until disposition is authorized by the Commission;

and,

(6) For any shipments or any part of a shipment for which acknowledgement of receipt is not received within the times set forth in this

section, conduct an investigation in accordance with paragraph (h) of

this section.

(f) Any licensed waste processor who treats or repackages wastes

shall:

(1) Acknowledge receipt of the waste from the generator within one

week of receipt by returning a signed copy of the manifest or equivalent

documentation.

(2) Prepare a new manifest that meets the requirements of paragraphs (b) and (c) of this section. Preparation of the new manifest

reflects that the processor is responsible for the waste;

(3) Prepare all wastes so that the waste is classified according

to §61.55 and meets the waste characteristics requirements in §61.56 of

this chapter.

(4) Label each package of waste to identify whether it is Class A

waste, Class B waste, -or Class C waste, in accordance with §§61.55 and

61.57 of this chapter.

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[7590-01)

(5) Conduct a quality control program to assure compliance with

§§61.55' and 61.56 of this chapter.' The program shall include management

evaluation 'of 'audits;

(6) Forward a copy of the new manifest to the disposal'site operator

or waste collector at the tim'e'of shipment, or deliver to a' collector at

the time the waste is collected,-obtaining acknowledgement of receipt in

the form of a signed copy of the manifest or equivalent documentation by

the collector.

'(7) Include the new manifest with' the shipment;

' (8) Retain copies of original-manifests and new manifests and documentation of acknowledgement of receipt as the record of transfer of

--licensed material required by' Parts 30, 40, and 70 of this chapter.

(9) For any' shipment or part of'a shipment for which'acknowledgement is 'not received within the times 'set forth in this section, conduct

an investigation in accordance with paragraph (h) of this section.

(g) The land disposal facility operator shall:

(1) Acknowledge receipt of the waste within one week of receipt

by returning a signed copy of the manifest or equivalent documentation

to the shipper. The shipper to be notified is the licensee who last

possessed the waste and transferred the waste to the operator. The

returned copy of the manifest or equivalent documentation shall indicate

any discrepancies between materials listed on the manifest and materials

received.

(2) Maintain copies of all completed manifests or equivalent documentation until the Commission authorizes their disposition; and

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[7590-01]

(3) Notify the shipper (i.e., the generator, the collector, or

processor) and the Director of the nearest Commission Regional Office

listed in Appendix D of this part when any shipment or part of a shipment

has not arrived within 60 days after the advance manifest was received.

(h) Any shipment or part of a shipment for which acknowledgement

is not received within the times set forth in this.section, must:

(1) Be investigated by the shipper if the shipper has not received

notification of receipt within 20 days after transfer; and

(2) Be traced and reported. , The investigation shall include tracing

the shipment and filinga report with the nearest Commission Regional

Office listed in Appendix D of this part. Each licensee who conducts a

trace investigation shall file a written report with the nearest Commission's Regional office within 2 weeks of completion of the investigation.

15. In §20.401, paragraphs (b) and (c)(3) are revised to read as

follows:

§20.401. Records of surveys, radiation monitoring, and disposal.

** * * *

(b) Each licensee shall maintain records in the same units used in

this part, showing the results of surveys required by §20.201(b),

monitoring required by §§20.205(b) and 20.205(c), and disposals made under

§§20.302, 20.303, deleted §20.3041, and Part 61 of this chapter.

(c) * * *

(3) Records of disposal of licensed materials made pursuant to

§§20.302, 20.303, deleted § 20.3041, and Part 61 of this chapter are

to be maintained until the Commission authorizes their disposition.

x * * * *

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[7590-01]

16. Section 20.408 -is amended by adding a new paragraph (a)(7) to

read as follows:

§20.408 Reports of personnel monitoring on termination of employment

or work.

(a) * *

(7) Receive radioactive waste from other.persons for disposal

under Part 61 of this chapter.

. . ** *, *

PART 21 - REPORTING OF DEFECTS AND NONCOMPLIANCE

§21.2 [Amended]

17. Section 21.2 is amended by inserting "61," after "40, 60," in

the third line, and after "40, 60" in both the first and second sentences.

§21.3 [Amended]

18. In §21.3, paragraphs (a)(2), (a) (a-1)(1), (a) (a-1)(2), and

,(k) are amended by adding "61," after "50,,60."

19. Section 21.21 is revised by adding "61," after "50, 60," in

paragraphs (b)(1)(i) and (b)(1)(ii). 4,.

PART 30 RULES OF GENERAL APPLICABILITY TO DOMESTIC LICENSING

OF BYPRODUCT MATERIAL

20. A new paragraph (d) is added to Section 30.11 to read as

follows:

§30.11 Specific exemptions.>;

* .. * * -* -*

(d) Except as specifically provided in Part 61 of this chapter,

any licensee is exempt from the requirements of this part to the extent

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[7590-01)

that its activities are subject to the requirements of Part 61 of this

chapter,

21. In §30.32, paragraph 30.32(f) is amended to read as follows:

§30.32 Application for specific licenses.

** * * *

(f) An application for a license to receive and possess byproduct

material for the conduct of any activity which the Commission determines

will significantly affect the quality of the environment shall be filed

at least 9 months prior to commencement of construction of the plant or

facility in which the activity will be conducted and shall be accompanied

by any Environmental Report required pursuant to Part 51 of this chapter.

22. In §30.33, paragraph (a)(5) is revised to read as follows:

§30.33 General requirements for issuance of specific licenses.

(a) * * *

(5) In the case of an application for a license to receive and

possess byproduct material for the conduct of any activity which the

Commission determines will significantly affect the quality of the

environment, the Director of Nuclear Material Safety and Safeguards or

his designee, before commencement of construction of the plant or facility in which the activity will be conducted, on the basis of information

filed and evaluations made pursuant to Part 51 of this chapter, has concluded, after weighing the environmental, economic, technical, and other

benefits against environmental costs and considering available alternatives,

that the action called for is the issuance of the proposed license, with

any appropriate conditions to protect environmental values. Commencement

of construction prior to such conclusion shall be grounds for denial of a

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[7590-01)

license to receive and possess byproduct material in such plant or facility.

As used in this paragraph the term "commencement of construction" means

any clearing of land, excavation, or other substantial action that would

adversely affect the environment of a'site. The term does not mean site

exploration, necessary roads,for site exploration, borings to determine

foundation conditions, or other preconstruction monitoring or testing to

establish background information related to the suitability of the site

or the protection of environmental values.

* ** * *

PART 40 - DOMESTIC LICENSING OF SOURCE-MATERIAL

23.' In §40.14, a new paragraph (d) is added to read as'follows:

§40.14 Specific exemptions.

* * * * *

(d) Except as specifically provided in Part 61 of this chapter

any licensee is exempt from the requirements of this part to the extent

that its activities are subject to the requirements of Part 61 of this

chapter,

24. In §40.31, paragraph (f) is revised to read as follows:

§40.31 Applications for specific licenses.

* *. , * ...* . * .. . . *

(f) Anrapplication for-a-license to possess and use source material

for uranium milling,b<production of uranium hexafluoride, or for the conduct

of any'other activity which the Commission determines will significantly

affect'the'quality of the environment'shall be filed at: least 9 months

prior to commencement of construction of the plant or facility in which the

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[7590-01]

activity will be conducted and shall be accompanied by any Environmental

Report required pursuant to Part 51 of this chapter.

* * * *, *

25. In.§40.32, paragraph (e) is revised to read as follows:

§40.32 General requirements for issuance of specific licenses.

A * * * *

(e) In the case of an application for a license to possess and use

source and byproduct material for uranium milling, production of uranium

hexafluoride, or for the conduct of any other activity which the Commission

determines will significantly affect the quality of the environment, the

Director of Nuclear Material Safety and Safeguards or his designee, before

commencement of construction of the plant or facility in which the activity

will be conducted, on the basis of information filed and evaluations made

pursuant to Part 51 of this chapter, has concluded, after weighing the

environmental, economic, technical and other benefits against environmental

costs and considering available alternatives, that the action called for

is the issuance of the proposed license, with any appropriate conditions

to protect environmental values. Commencement of construction prior to

such a conclusion shall be grounds for denial of a license to possess

and use source and byproduct material in such plant or facility. As used

in this paragraph the term "commencement of construction" means any

clearing of land, excavation, or other substantial action that would

adversely affect the environment of a site-. The term does not mean site

exploration, necessary roads for site exploration, borings to determine

foundation conditions, or other preconstruction monitoring or testing to

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[7590-01]

establish background information related to the suitability of the site

or the'protection of environmental values.

. .*. *-* *

PART 51 - LICENSING AND REGULATORY POLICY AND PROCEDURES

FOR ENVIRONMENTAL PROTECTION

26. In'§51.5, paragraphs (a)(6) and (b)(4)(iii) are revised,

paragraph (b)(6) is amended-by inserting "61" following "50, 60,", and

(d)(3) is amended by 'inserting "61" following "50, '60." The revised

paragraphs read as follows:

§51.5 Actions requiring preparation of environmental impact statements,

negative declarations, environmental impact appraisals; actions

excluded.

(a) * * *

(6) Issuance of a license authorizing receiptiand disposal of radioactive waste from other persons under Part 61 of this chapter;

: * * .* . * *- *

(b) * * *

(4)* * -

(iii) Authorizing receipt and disposal of radioactive waste from other

persons under Part 61 of this chapter.

* * .* * *

§51.40 [Amended)

27.- ! In §51.40, paragraph (c) is amended by inserting "61" after

"30, 40.11

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PART 70 - DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL

28. In §70.14, a new paragraph (d) is added to read as follows:

§70.14 Specific exemptions.

* * * * *

(d) Except as specifically provided in Part 61 of this chapter,

any licensee is exempt from the requirements of the regulations in this

part to the extent that its activities are subject to the requirements of

Part 61 of this chapter,

29. In §70.21, paragraph (f) is revised to read as follows:

§70.21 Filing.

* * * * *

(f) An application for a license to possess and use special nuclear

material for processing and fuel fabrication, scrap recovery or conversion

of uranium hexafluoride, or for the conduct of any other activity which the

Commission determines will significantly affect the quality of the environment

shall be filed at least 9 months prior to commencment of construction of the

plant or facility in which the activity will be conducted, and shall be

accompanied by an Environmental Report required under Part 51*** of this

chapter.

* * *

30. In §70.23, paragraph (a)(7) is revised to read as follows:

§70.23 Requirements for the approval of applications.

(a) * * *

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[7590-01)

(7) Where the proposed activity is processing and fuel fabrication,

scrap recovery, conversion of. uranium hexatluoride, or any other activity

which the Commission determines will significantly affect the quality of

the environment, the Director of Nuclear Material Safety and Safeguards

or his designee, before commencement of construction of the plant or

facility in which the activity will be conducted, on the basis of information filed and evaluations made pursuant to Part 51 of this chapter, has

concluded, after weighing the environmental, economic, technical, and

other benefits against environmental costs and considering available

alternatives, that the action called for is the issuance of the proposed

license, with any appropriate conditions to protect environmental values.

Commencement of construction prior to such conclusions shall be grounds

for denial to possess and use special nuclear material in such plant or

facility. As used in this paragraph the term "commmencement of construction" means any clearing of land, excavation, or other substantial action

that would adversely affect the environment of a site. The term does

not mean site exploration, necessary roads for site exploration, borings

to determine foundation conditions, or other preconstruction monitoring

or testing to establish background information related to the suitability

of the site or the protection of environmental values.

* * * * *

PART 73 - PHYSICAL PROTECTION OF PLANTS AND MATERIALS

31. -In §73.1, paragraph (b)(1)(iii) is revised to read as follows:

§73.1 Purpose and scope.

* * * * *

(b) * * *

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[7590-01]

(1) * * *

(iii) the physical protection of special nuclear material by any

person who, pursuant to the regulations in' Parts 61 or 70 of this chapter,

possesses or uses at any site or contiguous sites subject to the control

by the licensee, formula quantities of strategic special nuclear material

or special nuclear material of moderate strategic significance or special

nuclear material of low strategic significance.

A * ,* * *

PART 170 - FEES FOR FACILITIES AND MATERIALS LICENSES AND OTHER

REGULATORY SERVICES UNDER THE ATOMIC ENERGY ACT OF 1954, AS AMENDED*

32. Section 170.2 is revised to read as follows:

§170.2 Scope.

Except for persons who apply for or hold the permits, licenses, or

approvals exempted in §170.11, the regulations in this part apply to a

person who is an applicant for, or holder of, a specific byproduct material license issued pursuant to Parts 30 and 32-35 of this chapter, a

specific source material license issued pursuant to Part 40 of this

chapter, a specific materials license issued under Part 61 of this chapter,

a specific special nuclear material license issued pursuant to Part 70 of

this chapter, a specific license for the storage of spent fuel issued

pursuant to Part 72 of this Chapter, a specific approval of spent fuel

casks and shipping containers issued pursuant to Part 71 of this chapter,

a specific request for approval of sealed sources and devices containing

byproduct material, source material, or special nuclear material, or a

production or utilization facility construction permit and operating

156
[7590-01]

'icense issued pursuant to Part 50 of this chapter, to routine satety

and safeguards inspections of a licensed person, to a person who applies

for approval of a reference standardized design of a nuclear steam

supply system or balance of plant, for review of a facility site prior

to the submission of an application for a construction permit, for review

of an independent spent fuel storage installation pursuant to Part 72 of

this chapter, and for a special project review which the Commission completes or makes whether or not in conjunction with a license application

on file or which may be filed.

(Amendments to all parts are issued pursuant to citations of authority

presently codified or, in the case of 10 CFR Part 61, as set out after

the list of sections in the new Part 61.)

Dated at Washington, D.C. this day of , 1982.

For the U.S. Nuclear Regulatory Commission.

Samuel J. Chilk

Secretary of the Commission.

157
NRC FORM 335 1. REPORT NUMBER (4ssigred by DDCJ (7-77) ~U.S. NUCLEAR REGULATORY COMMISSIONNUE095,Vl3

BIBLIOGRAPHIC DATA SHEET NUREG-0945 , Vol. 3

4. TITLE AND SUBTITLE (Add Volume No., if appropriate) 2. (Leave blank)

Final Environmental Impact Statement on 10 CFR Part 61:

"Licensing Requirements for Land Disposal of Radioactive 3. RECIPIENT'S ACCESSION NO.

Waste" Vol. 3: Appendices C-F

7. AUTHORIS) 5. DATE REPORT COMPLETED

NRC Staff MONTH May YEAR 1982

9. PERFORMING ORGANIZATION NAME AND MAILING ADDRESS (Include Zip Code) DATE REPORT ISSUED

Low-Level Waste Licensing Branch, Division of Waste Manage- MONTH YEAR 1982

ment, Office of Nuclear Material Safety and Safeguards, ov.

Nuclear Regulatory Commission, Washington, DC 20555 6. (Leave blank)

B. (Leave blank)

12. SPONSORING ORGANIZATION NAME AND MAILING ADDRESS (Include Zip Code) . 10. PROJECT/TASK/WORK UNIT NO.

Same as item 9. 11. CONTRACT NO.

13. TYPE OF REPORT PERIOD COVERED (Inclusive dates)

Final Environmental Impact Statement

15. SUPPLEMENTARY NOTES 14. (Leave olank)

16. ABSTRACT (200 words or less)

The three-volume final environmental impact statement (FEIS) is prepared to guide and

support publication of a final regulation, 10 CFR Part 61, for the land disposal of lowlevel radioactive waste. The FEIS is prepared in response to public comments received

on the draft environmental impact statement (DEIS) on the proposed Part 61 regulation.

The DEIS was published in September 1981 as NUREG-0782. Public comments received on the

proposed Part 61 regulation separate from the DEIS are also considered in the FEIS. The

FEIS is not'a rewritten version of the DEIS, which contains an exhaustive and detailed

analysis of alternatives, but rather references the DEIS and presents the final decision

bases and conclusions (costs and impacts) which are reflected in the Part 61 requirements.

Four cases are specifically considered in the FEIS representing the following: past

disposal practice, existing disposal practice, Part 61 requirements, and an upper bound

example.

17. KEY WORDS AND DOCUMENT ANALYSIS 17.,. DESCRIPTORS

low-level waste financial assurances

land disposal institutional controls

social commitment radioactive waste

groundwater migration disposal technologies

inadvertent intrusion cost-benefit analysis

10 CFR Part 61

waste form

17h. IDENTIFIERS'OPEN-ENDED TERMS

18. AVAILABILITY STATEMENT

Unlimited

NUREG-0945, Vol. 3 FEIS ON 10 CFR PART 61 "LICENSING REQUIREMENTS FOR LAND DISPOSAL

OF RADIOACTIVE WASTE"

NOVEMBER 1982

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