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(Chemical Forms of Uranium

Form Code Form Code Form Code
U (metal) 1 UO3 0.83 UF6 0.68
Uo2 0.88 UF4 0.76 UO2F2 0.77
U308 0.85 UCcI4 0.63 U02(NO3)2 0.6
% U-235___ U SpecAct uCi/g U
U Enrichment (% U-235) = 3.75E+01 Ratio
Code DAC Value Actto DAC
Chemical Form of U code = 6E-10  6.25E+10
[SUM Constituent Actto DAC= 4.19E+10 [Fraction Dose from Constituents = | 0.6696
Constituent Data Units uCi/g sample uCiig U DACValue Actto DAC
Pu-238 0.00E+00 3.00E-12 0.00E+00
Pu-239 0.00E+00 2.00E-12 0.00E+00
Pu-240 0.00E+00 2.00E-12 0.00E+00
Np-237 0.00E+00 2.00E-12 0.00E+00
Am-241 0.00E+00 2.00E-12 0.00E+00
U-236 0.00E+00 6.00E-10 0.00E+00
Te-99 0.00E+00 3.00E-07 0,00E+00
_uCiig U DAC Value Act to DAC
Pu-238 5.17E-03) 3.00E-12  1.72E+09
. Pu-239 3.12E-06' 2.00E-12 1.56E+06
Pu-240 1.63E-06) 2,00E-12 8.17E+05
Np-237 2.03E-02) 2.00E-12 1.02E+10
Am-241 0.00E+00) 2.00E-12 0.00E+00
U-236 4.80E+01 6.00E-10 3.00E+10
Te-99 4.39E+00} 3.00E-07 4.65E+06

9212 HEU Process Stream 5 (Y-12 & SRS Data)

Assume
Pu ppb
Np ppb
Te ppm
U-236 ppm

0.36
28,800
82

278,000
Assume U @ 62.5% U-235

Assume Weapons Pu Dist
Pu-238
Pu-239
Pu-240
Pu-241
Pu-242

oonks

sg



Table ES-1 Estimated Mass Balance for Highly Enriched RU

RU Inventory (as of 3/31/99) 13,082
ne “

* This difference is due to the inability to precisely distinguish between RU and non-RU shipments.

IV. CONSTITUENTS (PU, NP, AND TC) IN RU

The overall mass balance for highly enriched RU and constituent flow through the
Y-12 Complex is summarized in Table ES-2. This table compiles quantities of each
constituent based upon the estimating logic presented in Chapter 5.

Table ES-2 Overall Mass Balance for Y-12 Complex Highly Enriched RU

150,857

Be
6

RU (kg U)

Creek Burial Grounds as solid waste or shipped off site to another DOE facility.
1 The Te difference is 340 g if it is assumed that most Tc found in the southeast S-3 Pond came from
ORGDP and that Te is not included in receipts.

Based upon Y-12 Complex records of highly enriched RU receipts and shipments,
material remaining in inventory, and determinations regarding quantities in disposal, there
remain no more than trace quantities of Pu not accounted for.

In contrast, the overall mass balance cannot account for 2,200 g of Np. In the historical
plant record, reference is made to discharge of 2,500 g (1.75 Ci) of Np to the S-3 Ponds.
However, the amount of Np that can be accounted for by sampling and analysis of pond
sludge is only 145 g. A similar quantity was found in the WETF sludge. It is known by a ~
few individuals in the plant that an ion exchange column was installed in the uranyl nitrate
feed stream to specifically remove Np from the incoming SRS RU for use in another
program. The spent or loaded ion exchange columns were removéd from the feed line and
sent off-site for Np recovery. Since there was little residual uranéum contained on the ion ;
exchange resin, this transaction was not listed as an RU transfer and was not placed in the
plant uranium accountability record. Assuming that the 2,500 g of Np identified in the waste

ES-5


(Chemical Forms of Uranium

Form Code Form Code Form Code
U (metal) 1 UO3 0.83 UF6 0.68

uo2 0.88 UF4 0.76 UO2F2 0.77

U308 0.85 UCI4 0.63 U02(NO3)2 0.6

% U-235 _U SpecAct uCi/g U
U Enrichment (% U-235) = 5.09E+01 Ratio
Code DAC Value Actto DAC
Chemical Form of U code = 3E10 © 1.70E+11

0.1369

SUM Constituent Act to DAC= 2.32E+10 [Fraction Dose from Constituents =
Constituent Data Units uCi/g sample uCig U DAC Value Actto DAC
Pu-238 0.00E+00 3.00E-12 0.00E+00
Pu-239 0.00E+00 2.00E-12 0.00E+00
Pu-240 0.00E+00 2.00E-12 0.00E+00
Np-237 0.00E+00 2.00E-12 0.00E+00
Am-241 0.00E+00 2.00E-12 0.00E+00
U-236 0.00E+00 3.00E-10 0,00E+00
Te-99 0.00E+00 3.00E-07 0.00E+00
uCi/g U DAC Value Act to DAC
Pu-238 1.88E-06| 3.00E-12  6.27E+05
Pu-239 5.87E-06| 2.00E-12 2.94E+06
Pu-240 3.00E-06) 2.00E-12  1.50E+06
Np-237 3.31E-03) 2.00E-12 1.66E+09
Am-241 0.00E+00) 2.00E-12 0.00E+00
U-236 6.47E+00) 3.00E-10 2.16E+10
Tc-99 2.21E-03) 3.00E-07 7.37E+03

9212 HEU Process Stream 4 (ICPP + Data)

Assume
Pu ppb 0.11
Np ppb 4,700
Te ppm 0.13

U-236 ppm 100,000

Assume U @ 62.5% U-235

Assume Weapons Pu Dist
Pu-238 0.1
Pu-239 86.1
Pu-240 12
Pu-241 16 .
Pu-242 0.2

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(Chemical Forms of Uranium

Form Code
U (metal) 1

Uo2 0.88

U308 0.85

U Enrichment (% U-235) =

Chemical Form of U code =

Form
UO3
UF4
UCI4

Code Form
0.83 UF6
0.76 UO2F2

0.63 U02(NO3)2

% U-235_U SpecAct uCiig U
3.75E+01 Ratio

Code

DAC Value Actto DAC

3E-10 © 1.25E+11

Code
0.68
0.77

0.6

SUM Constituent Act to DAC= 6,95E+10 [Fraction Dose from Constituents = L_ 0.5558
Constituent Data Units uCi/g sample uCig U DAC Value ActtoDAC
Pu-238 0.00E+00 3.00E-12 0.00E+00
Pu-239 0.00E+00 2.00E-12. 0.00E+00
Pu-240 0.00E+00 2.00E-12 0.00E+00
Np-237 0.00E+00 2.00E-12 0.00E+00
Am-241 0.00E+00 2.00E-12 0.00E+00
U-236 0.00E+00 3.00E-10 0.00E+00
Te-99 0.00E+00 3.00E-07 0.00E+00
uCi/lg U DAC Value Act to DAC
Pu-238 3.45E-03) 3.00E-12  1.15E+09
Pu-239 2.08E-06) 2.00E-12  1.04E+06
Pu-240 1.09E-06 2.00E-12 5.45E+05
Np-237 1.68E-02 2.00E-12 8.39E+09
Am-241 0.00E+00| 2.00E-12 0.00E+00
U-236 1.80E+01 3.00E-10 6.00E+10
Te-99 1.45E+00} 3.00E-07 4.82E+06
9212 HEU Process Stream 19 (Y-12 & SRS Data)
Assume
Pu ppb 0.24
Np ppb 23,800
Te ppm 85
U-236 ppm 278,000
Assume U @ 62.5% U-235
Assume Weapons Pu Dist
Pu-238 84
Pu-239 14
Pu-240 2
Pu-241 0 “
Pu-242 0
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(Chemical Forms of Uranium

SUM Constituent Act to DAC= 1.24E+10

Form Code Form Code Form
U (metal) 1 U03 0.83 UF6
uo2 0.88 UF4 0.76 UO2F2
U308 0.85 UCI4 0.63 U02(NO3)2
% U-235___U SpecAct uCi/g U
U Enrichment (% U-235) = 5.09E+01 Ratio
Code DAC Value Act to DAC
Chemical Form of U code = 6E-10 8.48E+10

Code
0.68
0.77

06

[Fraction Dose from Constituents _=

0.1467

Constituent Data Units uCi/g sample uCi/ig U DAC Value
Pu-238 0.00E+00 3.00E-12
Pu-239 0.00E+00 2.00E-12
Pu-240 0.00E+00 2.00E-12
Np-237 0.00E+00 2.00E-12
Am-241 0.00E+00 2.00E-12
U-236 0.00E+00 6.00E-10

Te-99 0.00E+00 3.00E-07
uCi/g U DAC Value
Pu-238 1.88E-06) 3.00E-12
Pu-239 5.87E-06) 2.00E-12
Pu-240 3.00E-06) 2.00E-12
Np-237 3.31E-03} 2.00E-12
Am-241 0.00E+00! 2.00E-12
U-236 6.47E+00) 6.00E-10
Te-99 2.21E-03) 3.00E-07

Act to DAC
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00

Act to DAC
6.27E+05
2.94E+06
1,50E+06
1.66E+09
0.00E+00
1.08E+10
7.37E+03

9212 HEU Process Stream 5 (ICPP + Data)
Assume

Pu ppb 0.11

Np ppb 4,700

Te ppm 0.13

U-236 ppm 100,000
Assume U @ 62.5% U-235
Assume Weapons Pu Dist

Pu-238 0.1

Pu-239 86.1

Pu-240 12

Pu-241 1.6

Pu-242 0.2

B-26



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However, dose assessment studies may be warranted as a follow-on activity to provide a
more detailed assessment of worker exposure.

Potential Environmental Releases

Soil and groundwater around the Y-12 Complex is contaminated with various
radionuclides as a direct result of the nature of the Y-12 Complex work and past disposal
practices. However, the quantities of RU constituents in and around the plant are very small
and pose no threat to the immediate environment or the surrounding communities. A clear
understanding of the contamination exists, and ongoing environmental programs continue to
verify this conclusion. The report of the joint task force assembled by DOE in 1985 to study
past and (then) current practices related to the processing of RU reflected similar
conclusions. The task force did not disclose any instance at the Y-12 Complex in which the
environment was jeopardized or compromised.

An Oak Ridge Dose Reconstruction Project was initiated in 1994 as follow-up to the
Oak Ridge Dose Reconstruction Feasibility Study, which recommended a closer examination
of past uranium emissions and potential resulting exposures. The Task 6 component of the
project involved further evaluation of Oak Ridge uranium operations and effluent monitoring
records to determine if uranium releases from the Oak Ridge Reservation likely resulted in
off-site doses that warranted further study. The results were documented in the July 1999
Task 6 report. The Task 6 team concluded that earlier estimates of uranium releases had
been underestimated. However, based on the decision guidelines from the Oak Ridge Health
Agreement Steering Panel, the Task 6 team concluded that while Y-12 Complex uranium
teleases are candidates for further study, they are not high-priority candidates.

The Task 7 component of the project involved performing qualitative and quantitative
screening of various materials of concern at the Y-12 Complex and the other DOE Oak
Ridge sites. Materials screened included Np and Tc. Results were reported in the Task 7
report. Based on the analysis of data, the Task 7 team determined that Np did not warrant
further study. Although Tc was identified as one of the potential candidates for further study,
it was not determined to be a high-priority candidate.

These analyses, along with other information on environmental consequences from
Y-12 Complex operations, identify candidate environmental issues for additional study.
However, candidate issues related to the processing of RU have not been determined to be
high-priority candidates for further study.

ae

ES-10


(Chemical Forms of Uranium

Form Code Form Code Form Code
U (metal) 1 U03 0.83 UF6 0.68

u02 0.88 UF4 0.76 UO2F2 0.77

U308 0.85 UCI4 0.63 U02(NO3)2 0.6

%U-235 _U SpecAct uCi/g U
U Enrichment (% U-235) = 3.75E+01 Ratio
Code DAC Value Actto DAC
Chemical Form of U code = 6E-10  6.25E+10

SUM Constituent Act to DAC= 1.38E+12 [Fraction Dose from Constituents = | 22.0674

Constituent Data Units uCi/g sample uCig U DACValue ActtoDAC
Pu-238 0.00E+00 3.00E-12  0.00E+00
Pu-239 0.00E+00 2.00E-12 0.00E+00
Pu-240 0.00E+00 2.00E-12 0.00E+00
Np-237 0.00E+00 2.00E-12 0.00E+00
Am-241 0.00E+00 2.00E-12 0.00E+00
U-236 0.00E+00 6.00E-10 0,00E+00

Tc-99 0.00E+00 3.00E-07 0.00E+00
uCi/g U DAC Value Actto DAC

Pu-238 8.96E-01 3.00E-12 2.99E+11
Pu-239 §.42E-04) 2.00E-12 2.71E+08
Pu-240 2.83E-04} 2.00E-12 1.42E+08
Np-237 2,10E+00; 2.00E-12  1.05E+12
Am-241 0.00E+00! 2.00E-12 0,00E+00
U-236 1.80E+01 6.00E-10 3.00E+10
Tc-99 1,09E+01 3.00E-07 3.63E+07

9212 HEU Process Stream 30 (Y-12 & SRS Data)

Assume
Pu ppb 62.4
Np ppb 2,980,000
Te ppm 641
U-236 ppm 278,000

Assume U @ 62.5% U-235

Assume Weapons Pu Dist

Pu-238 84
Pu-239 14
Pu-240 2
Pu-241 tt)
Pu-242 0 “

on.

B-23


(Chemical Forms of Uranium

[161.3840

Form Code Form Code Form Code
U (metal) 1 uUo3 0.83 UF6 0.68
U02 0.88 UF4 0.76 UO2F2 0.77
U308 0.85 UCK 0.63 U02(NO3)2 06
%_U-235___ U SpecAct uCi/g U
U Enrichment (% U-235) = 3.75E+01 Ratio
Code DAC Value Act to DAC
Chemical Form of U code = 6E-10  6.25E+10
SUM Constituent Act to DAC= 1.01E+13 [Fraction Dose from Constituents =
Constituent Data Units uCi/g sample uCivg U DACValue ActtoDAC
Pu-238 0.00E+00 3.00E-12 0.00E+00
Pu-239 0.00E+00 2.00E-12 0.00E+00
Pu-240 0.00E+00 2.00E-12 0.00E+00
Np-237 0.00E+00 2.00E-12 0.00E+00
Am-241 0.00E+00 2.00E-12 0.00E+00
U-236 0.00E+00 6.00E-10 0.00E+00
Te-99 0.00E+00 3.00E-07 0.00E+00
uCi/g_U DAC Value Act to DAC
Pu-238 5.21E+00 3.00E-12  1.74E+12
Pu-239 3.15E-03} 2.00E-12 1.58E+09
Pu-240 1.65E-03 2.00E-12 8.24E+08
Np-237 4.66E+01 2.00E-12  8.32E+12
Am-241 0.00E+00) 2.00E-12  0.00E+00
U-236 1.80E+01 6.00E-10 3.00E+10
Te-99 7.55E+01 3.00E-07 2.52E+08

9212 HEU Process Stream 25 (Y-12 & SRS Data)

Assume
Pu ppb 363
Np ppb 23,600,000
Te ppm 4,440

U-236 ppm 278,000

Assume U @ 62.5% U-235

Assume Weapons Pu Dist
Pu-238 84
Pu-239 14
Pu-240 2
Pu-241 )
Pu-242 0

B-20



Building 9212 Complex Processes
Building 9212 complex processes involved the following pathways:

receiving UN solution from ICPP (in safe bottles) and from SRS (in tanker trucks)
weighing SRS tanker trucks (at Building 9929-1)
sampling UN solution
pouring UN solution from ICPP safe bottles into “pour-up” stations for transfer to
intermediate storage tanks
pumping UN solution from SRS tanker trucks to 9212
e UN evaporated and concentrated
manual filling and loading of UN into safe bottles for transfer to 9206 (in the period after
9206 assumed responsibility for certain recovery operations from 9212)
© ICPP UO; received and dissolved to produce UN (in the period after ICPP began
sending UO; instead of UN)
purification of UN via solvent extraction (primary and secondary extraction)
pumping of solvent extraction raffinate to S-3 Ponds
feeding of solvent extraction raffinate to 9212 bioreactor
transporting of solvent extraction raffinate to WETF
denitration of uranyl nitrate hexahydrate (UNH) to UO;
maintenance on denitrator or fluid beds
conversion of UO3to uranium tetrafluoride (UF.) in converted lab muffle furnaces
removal of dry UF, from process
“bomb” reduction of UF, to uranium metal
sampling, fracturing, and packaging of uranium metal buttons
salvage operations for uranium-aluminum (U-Al) alloy from SRS
metal product shipped from Building 9720-5

Building 9206 Processes
Building 9206 processes involved the following pathways:

UN solution “poured-up” into safe tanks

U-AI ingots received from SRS at Building 9720-5

dross and sweepings received

U-AI ingots (or dross/sweepings) dissolved in NaOH to remove Al; sodium
diuranate produced

sodium diuranate dissolved in nitric acid to produce UN

UOs received and dissolved to form UN

purification of UN via solvent extraction (primary and secondary extraction)
isolation and transport of raffinateto9212 .

denitration of UNH to UO3 a
maintenance on denitrator or fluid beds s

conversion of UO; to UF, 3

ES-7


management record was indeed separated from the RU stream as suspected and either sent
off-site for use elsewhere or buried as a solid waste in the Bear Creek Burial Grounds, the
overall mass balance shows 300 g more Np than can be accounted for.

The overall Y-12 Complex mass balance shows 2,345 grams more Tc on the plant site
than can be accounted for, based on the mass difference between the uranium feed, product,
and waste streams. It should be noted that the normal flow of acid waste from the 9212 and
9206 HEU operations to the S-3 Ponds went first into the NE basin. The flow was then
touted by overflow pipe to the NW basin, then to the SW basin, and finally into the SE basin.
Under this normal design flow pattern, one would expect to find the greatest concentration of
Tc in the NE basin and the least in the SE basin. Sludge analysis, however, shows 179 g of
Tc in the NE basin, 184 g in the NW, 89 g in the SW, and 2,680 g in the SE. The apparent
discrepancy was explained by a former S-3 Pond manager, who stated that on several
occasions Tc liquid waste was discharged directly to the SE basin from 5-gal waste drums
received from ORGDP. These Tc residues were removed from the gaseous diffusion cascade
from time to time during certain maintenance activities. If it is assumed that essentially all of
the Tc in the SE basin came from ORGDP and was not included in the Y-12 Complex RU
database, the mass balance difference is 340 g Tc, or 2% of the estimated total receipt.

V. POTENTIAL FLOW PATHS OF RU WITHIN THE Y-12 COMPLEX

The processing of RU at the Y-12 Complex impacted a number of facilities and
locations at the’plant site. The primary facilities with significant involvement in processing
RU were:

e Building 9212, a large uranium processing complex that performed uranium recovery
operations on RU materials and produced RU metal product,

e Building 9206, a large uranium processing facility that also performed uranium recovery
operations on RU materials.and produced RU metal product,

© Building 9720-5, the Y-12 Complex “warehouse,” which received, stored, and shipped
uranium materials, including RU,

e §-3 Ponds, four holding ponds for liquid and sludge wastes resulting from processes
involving uranium, including both unirradiated and recycled uranium (prior to WETF
operation beginning in 1986),

e West End Treatment Facility (WETF), a group of nine tanks/bioreactors for holding and
treating Y-12 Complex aqueous nitrate wastes (after the S-3 Ponds were taken out of
service) plus four sludge storage tanks, and

© New Hope Pond, a large surface water impoundment designed to capture and retain coal
fines and other entrained solids from rainwater and plant secondary wastewaters.

«

pa

ES-6


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consequences as can be seen by comparing uranium DAC values. Monitoring, both in the
field and through bioassay, accounts for its presence and correctly assigns dose or risk.
Other constituents, such as plutonium, are fundamentally different in that they do not have
the same chemical behavior or risk. Their presence could alter the intrinsic risk of handling
recycled uranium. Because “°U was monitored at the Y-12 Complex, the analysis presented
here, which used the DOE Mass Balance Project de minimis calculation methodology,
estimates the Occupational Exposure Potential (the implied hazard) to be higher than it
actually is. A calculation that considers the non-uranium, potentially unmonitored
component would at times lead to the conclusion of “No Significant Occupational Exposure
Potential” when “°U is more appropriately considered.

VII. EVALUATION OF PROCESSES OR FACILITIES THAT INVOLVED
POTENTIAL ENVIRONMENTAL RELEASES

Various sources that documented the potential environmental impact of RU components
from the Y-12 Complex and the Oak Ridge Reservation were identified and reviewed by the
Project Team. These reports are summarized in Chapter 2.

Solvent raffinate streams from Building 9212 and 9206 extraction systems—as well as
condensed acid streams from the various UN solution evaporators and denitrators—were
ultimately discharged to the unlined S-3 Ponds. Chemical analysis of the S-3 Pond sludge
indicated the presence of 3,140 g of Tc, 145 g of Np, and <0.1 g of Pu. The S-3 Ponds were
capped in 1986, with the sludge left in place under EPA oversight. Uranium has been
detected in groundwater monitoring wells around the S-3 Ponds. Therefore, one can infer
that RU constituents also leached into the nearby environment from the ponds. Data from
other locations, such as the WETF and New Hope Pond, were analyzed and indicated these
sites have no significant potential for environmental releases.

VIII. CONCLUSIONS
Potential Personnel Exposure

Although the Project Team identified 36 activities as having potential for worker
exposure, in no instance did any identified activity produce an OEP score in the
“High” range. As a result, the potential for worker exposure to TRU elements and fission
products at the Y-12 Complex is considered low to moderate.

Early in its existence, the Y-12 Complex implemented a worker protection program that
included worker radiological protection (see Section 2.7). This program incorporated such
elements as personnel protective equipment, personnel mgnitoring, environmental
monitoring, work location surveys, work-time limits on jobs with penetrating radiation,
excretion rate limits, periodic examinations of personnel, and Plant Action Level limits. The
inhalation of radioactive materials was recognized as the most important source of possible
exposure at the Y-12 Complex. Consequently, administrative controls were primarily
designed to guard against associated hazards. &

Worker protection measures in place at the Y-12 Complex likely provided substantial
mitigation to the risks introduced by the activities rated as moderate to low in OEP.

ES-9


(Chemical Forms of Uranium

Form Code Form Code Form Code
U (metal) 1 U03 0.83 UF6 0.68

uU02 0.88 UF4 0.76 UO02F2 0.77

U308 0.85 UCH. 0.63 U02(NO3)2 06

%U-235__U SpecAct uCi/g U
U Enrichment (% U-235) = 3.75E+01 Ratio
; Code DAC Value Act to DAC
Chemical Form of U code = 6E-10  6.25E+10

SUM Constituent Act to DAC= 1.04E+12 [Fraction Dose from Constituents = | 16.5699
Constituent Data Units uCi/g sample uCig U DAC Value ActtoDAC
Pu-238 0.00E+00 3.00E-12 0.00E+00
Pu-239 0.00E+00 2.00E-12 0.00E+00
Pu-240 0.00E+00 2.00E-12 0.00E+00
Np-237 0.00E+00 2.00E-12 0.00E+00
Am-241 0.00E+00 2.00E-12 0.00E+00
U-236 0.00E+00 6.00E-10 0.00E+00
Te-99 0.00E+00 3.00E-07 0.00E+00
uCi/g U DAC Value Act to DAC
Pu-238 5.21E-01 3.00E-12  1.74E+11
Pu-239 3.15E-04) 2.00E-12  1.58E+08
Pu-240 1.65E-04! 2.00E-12  8.24E+07
Np-237 1.66E+00} 2.00E-12 8.32E+11
Am-241 0.00E+00| 2.00E-12 0.00E+00
U-236 1.80E+01 6.00E-10 3.00E+10
Te-99 7.55E+00} 3.00E-07 2.52E+07

9212 HEU Process Stream 11 (Y-12 & SRS Data)

Assume
Pu ppb 36.3
Np ppb 2,360,000
Te ppm 444
U-236 ppm 278,000

Assume U @ 62.5% U-235

Assume Weapons Pu Dist

Pu-238 84
Pu-239 14
Pu-240 2
Pu-241 1)
Pu-242 to) “



EXECUTIVE SUMMARY

I. INTRODUCTION

This report has been prepared to summarize the findings of the Y-12 National Security
Complex (Y-12 Complex) Mass Balance Project and to support preparation of associated
U. S. Department of Energy (DOE) site reports. The project was conducted in support of
DOE efforts to assess the potential for health and environmental issues resulting from the
presence of transuranic (TRU) elements and fission products in recycled uranium (RU)
processed by DOE and its predecessor agencies. The United States government used
uranium in fission reactors to produce plutonium and tritium for nuclear weapons production.
Because uranium was considered scarce relative to demand when these operations began
almost 50 years ago, the spent fuel from U.S. fission reactors was processed to recover
uranium for recycling.

Uranium that has been irradiated in reactors contains TRU elements [e.g., plutonium
(Pu) and neptunium-237 (Np)], fission products [e.g., technetium-99 (Tc)], and reactor-
generated uranium products [e.g., uranium-236 ( )]. Following chemical processing to
extract various isotopes of Pu and tritium, as well as to recover uranium for reuse, trace
quantities of Pu, Np, Tc, and ”°°U remain in the RU stream. These constituents make the RU
stream more radioactive than natural uranium. Thus, the processing and re-enrichment of
RU may present an increased potential for personnel and environmental exposure greater
than that normally associated with the processing of unirradiated uranium.

In response to these concerns, DOE initiated an effort to identify all situations in which
the processing of RU by DOE and its predecessor agencies could have created an increased
potential for exposure of workers and/or significant increased environmental exposure. The
first step in this process involves the “mass balance review.”

The Y-12 Complex Mass Balance Project represents an effort to collect, verify, analyze,
and interpret available data to provide an overall accounting, or site mass balance, for
Y-12 Complex RU streams. In addition, data on related Y-12 Complex processes and
activities and data on Pu, Np, Tc, and °U —the primary constituents of concern in the RU
streams—have also been collected, analyzed, and interpreted. Based on available
Y-12 Complex records and information about processes and methods of operation and
maintenance, the Project Team has identified essentially all those plant activities that (1)
created a likelihood of Y-12 Complex workers coming into contact with significant levels of
RU constituents through direct physical contact or via airborne dust and/or (2) caused
reportable environmental releases of concentrated RU constituents.

The Project Team analyzed data on receipts, shipments, inventories, product, releases,
and other categories—along with available analytical data—in the context of documented
historical information on Y-12 Complex processes and activities. Understanding of processes
known to concentrate Pu, Np, and Tc and of activities known to create potential for exposure
to these RU constituents provided additional context for analysis. By correlating mass
balance data, analytical data, and historical information on Y-12 Complex processes, the
team was able to identify specific processes, locations, and time periods of importance for
potential worker exposure or environmental releases. These professes, locations, and time

ES-1


Value Likelihood

0 Sum of constituents clearly below de minimis levels (clearly less
than 10% additional dose)

1 Sum of constituents likely to cause up to 20% total dose

2 Sum of constituents likely to cause more than 20% but less than
50% total dose

3 Sum of constituents likely to cause 50% or more of total dose

Exposure Duration

This parameter considers the time of worker exposure on the job. As such, it
considers whether or not a particular activity was conducted infrequently or was carried
out on a daily basis. Exposure duration was also based upon a set of criteria to arrive at a
numeric value:

Value Likelihood
1 50 hours per year or less
2 More than 50 hours per year but less than 500 hours per year
3 500 or more hours per year
OEP Ratings

Multiplying the three values for airborne potential, constituent level, and exposure
duration produces an overall value that falls within a range that determines the OEP
score: -

Score Product Range Likelihood
0 0 “No significant” occupational exposure potential
1 1 “Low” occupational exposure potential
2 2-9 “Moderate” occupational exposure potential
3 >10 “High” occupational exposure potential

The results of this rating system for Y-12 Complex activities are presented in the
following charts and tables, which were used to provide the OEP ratings presented in
Table 2.6.

ad

B-2


APPENDIX B

OCCUPATIONAL EXPOSURE POTENTIAL METHODOLOGY

The Occupational Exposure Potential (OEP), shown in Table 2.6, is a score derived
from the product of three parameters qualitatively assigned by the Project Team. The
parameters are airborne potential, constituent level, and exposure duration. Each
parameter is assigned a numeric value according to prescribed criteria.

Airborne Potential

This parameter is a subjective assignment of the likelihood of the contaminant to
become airbome or concentrated in air. The judgment is largely based upon the form of
the material and the nature of the particular operation. An associated numeric value is
based on the following criteria:

Value Likelihood
0 No likelihood of being airborne
1 Low airborne potential
2 Moderate airborne potential
3 High airborne potential

Constituent Level

Calculations for each of the various product streams were performed to estimate the
additional dose presented by constituents present in irradiated uranium over that of the
uranium alone. The DOE EH-3 team provided a standardized tool, in the form of an
electronic spreadsheet, to perform the dose fraction calculations. The calculation and its
technical basis are described in detail in the Historical Generation and Flow of Recycled
Uranium in the DOE Complex Project Plan. To use the tool, the following information
about the process stream being considered was determined and entered in the
spreadsheet:

chemical form
level of enrichment in the “SU isotope
mass fraction of the constituents "Pu, 7°Pu, “°Pu, 77Np, “!Am, “°U, and °Te

The required information was determined by assuming estimates based on available
analytical data, process knowledge, and engineering judgment, and calculations were
performed for the streams of interest. Assumptions for the calculations and the results
are summarized in the accompanying tables.

The calculated fractional dose was then compared against critetia for assignment of a
respective numeric value: >

B-1


Chemical Forms of Uranium

Form Code Form Code Form Code
U (metal) 1 UO3 0.83 UF6 0.68
uo2 0.88 UF4 0.76 UO2F2 0.77
U308 0.85 uciK4 0.63 U02(NO3)2 0.6
%_U-235__U SpecAct uCi/g U
U Enrichment (% U-235) = 3.75E+01 Ratio
Code DAC Value Act to DAC
Chemical Form of U code = 6E-10 6.25E+10
SUM Constituent Act to DAC= 2.27E+11 [Fraction Dose from Constituents = | 3.6319
Constituent Data Units uCi/g sample uCi/g U DAC Value ActtoDAC
Pu-238 0.00E+00 3.00E-12 0.00E+00
Pu-239 0.00E+00 2.00E-12 0.00E+00
Pu-240 0.00E+00 2.00E-12 0.00E+00
Np-237 0.00E+00 2.00E-12 0,00E+00
Am-241 0.00E+00 2.00E-12 0.00E+00
U-236 0.00E+00 6.00E-10 0.00E+00
Te-99 0.00E+00 3.00E-07 0.00E+00
uCi/g U DAC Value Act to DAC
Pu-238 8.76E-02 3.00E-12 2.92E+10
Pu-239 5.29E-05 2.00E-12 2.65E+07
Pu-240 2.77E-05' 2.00E-12  1.38E+07
Np-237 3.36E-01 2.00E-12  1.68E+11
Am-241 0.00E+00) 2.00E-12 0.00E+00
U-236 4.80E+01 6.00E-10  3.00E+10
Tc-99 1,52E+01 3.00E-07 5.08E+07
9212 HEU Process Stream 27 (Y-12 & SRS Data)
Assume
Pu ppb 641
Np ppb 476,000
Te ppm 896
U-236 ppm 278,000
Assume U @ 62.5% U-235
Assume Weapons Pu Dist
Pu-238 84
Pu-239 14
Pu-240 2
Pu-241 0
Pu-242 0 .
>
+

B-22



(Chemical Forms of Uranium

Form Code Form Code Form Code
U (metal) 4 UO3 0.83 UF6 0.68

U02 0.88 UF4 0.76 UO2F2 0.77

U308 0.85 UCI4 0.63 U02(NO3)2 0.6

%U-235 _U SpecAct uCi/g U
U Enrichment (% U-235) = 3.75E+01 Ratio
Code DAC Value Act to DAC
Chemical Form of U code = 6E-10 6.25E+10

SUM Constituent Actto DAC= 3.97E+15 [Fraction Dose from Constituents = [63516.2677
Constituent Data Units uCi/g sample uCi/g U DAC Value Actto DAC
Pu-238 0.00E+00 3.00E-12 0.00E+00
Pu-239 0.00E+00 2.00E-12 0.00E+00
Pu-240 0.00E+00 2.00E-12 0.00E+00
Np-237 0.00E+00 2.00E-12 0.00E+00
Am-241 0.00E+00 2.00E-12 0.00E+00
U-236 0.00E+00 6.00E-10 0.00E+00
Tc-99 0.00E+00 3.00E-07 0.00E+00
uCi/g U DAC Value Actto DAC
Pu-238 2.77E+03} 3.00E-12  9.24E+14
Pu-239 1.68E+00 2.00E-12 8.38E+11
Pu-240 8.76E-01 2.00E-12 4.38E+11
Np-237 6.09E+03, 2.00E-12 3.05E+15
Am-241 0.00E+00; 2.00E-12 0.00E+00
U-236 1,80E+01 6.00E-10 3.00E+10
Te-99 7.34E+03} 3.00E-07 2.45E+10

9212 HEU Process Stream 26 (Y-12 & SRS Data)

Assume
Pu ppb 193,000
Np ppb 8,640,000,000
Te ppm 432,000

U-236 ppm 278,000

Assume U @ 62.5% U-235

Assume Weapons Pu Dist
Pu-238 84
Pu-239 14
Pu-240 2
Pu-241 i)
Pu-242 0 ial

B-21



e removal of dry UF, from process
e “bomb” reduction of UF, to uranium metal

Processes Associated with Other Y-12 Complex Facilities

© capping and closure of S-3 Ponds and sludge removal and closure of New Hope Pond
¢ treatment of nitrate waste at WETF
« — storage of RU materials at Building 9720-5

VI. EVALUATION OF ACTIVITIES THAT INVOLVED POTENTIAL WORKER
EXPOSURE TO RU CONSTITUENTS

Prior to and during the processing of RU, the Y-12 Complex also operated as a uranium-
processing facility. Careful consideration for worker protection was given to the introduction
of RU for processing. A criterion for acceptance was based upon DOE/OR-859,° which in
turn was derived from an informal agreement between the Y-12 Complex and SRS. The
intent of this criterion was to maintain the relative hazard potential of all non-uranium alpha
emitters to less than 7% of the relative hazard potential of uranium.’ With this limitation, it
was expected that RU could be safely managed by the measures already in place for
processing uranium.

The Project Team carefully analyzed and evaluated 36 activities identified as involving
potential for worker exposure. The team assigned the following Occupational Exposure
Potential (OEP) scores:

No Significant OEP 8 activities
Low OEP 1 activity
Moderate OEP 27 activities

Most of the potential exposure activities at the Y-12 Complex were found to have a
“Moderate” OEP rating as a result of the combined product of a constituent level value of 3
for Savannah River RU or a value of 2 for Idaho RU with a value of 1 or 2 for airborne
potential and exposure duration. Certain maintenance activities involving equipment that
contained finely divided RU solids were assigned a value of 3 for airborne potential.
However, because these types of maintenance activities were not performed very often, the
overall OEP was rated “Moderate,” with a cumulative score of 9.

In no instance did any identified activity involve a combination of airborne potential,
constituent level, and exposure duration that produced an OEP score in the “High” range.
Although some activities presented moderate OEP scores, the average derived air
concentrations (DAC) for the areas associated with RU was on the order of only 3% of the
plant action level (PAL).

The methodology established for the DOE Mass Balance Project considered 7°U an
unmonitored isotope, along with Pu, Np, and Tc. In fact, ”°U is, generally indistinguishable
from other uranium isotopes; it has the same chemical behavior and the same dose
3 Beli, D. et al., The Report of the Joint Task Force on Uranium Recycle MateFials Processing, 1985.

‘Vath and Duerksen, Criteria for Acceptance and Technical Assessment for Acceptance of Enriched Uranium
at the ¥-12 Plant, April 25, 1996.

ES~8


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(Chemical Forms of Uranium

Form Code Form Code Form

U (metal) 1 UO3 0.83 UF6
uo2 0.88 UF4 0.76 UO2F2
U308 0.85 UCI4 0.63 U02(NO3)2

% U-235 _U SpecAct uCi/g U
U Enrichment (% U-235) = 3.75E+01 Ratio
Code DAC Value Actto DAC
Chemical Form of U code = 3E-10  1.25E+11

Code
0.68
0.77

06

SUM Constituent Act to DAC= 6.95E+10 [Fraction Dose from Constituents =

0.5555

Constituent Data Units uCi/g sample uCi/g U DAC Value
Pu-238 0.00E+00 3.00E-12
Pu-239 0.00E+00 2.00E-12
Pu-240 0.00E+00 2.00E-12
Np-237 0.00E+00 2.00E-12
Am-241 0.00E+00 2.00E-12
U-236 0.00E+00 3.00E-10

Te-99 0.00E+00 3.00E-07
uCi/g U DAC Value
Pu-238 3.45E-03 3.00E-12
Pu-239 2.08E-06) 2.00E-12
Pu-240 1.09E-06 2.00E-12
Np-237 4.67E-02 2.00E-12
Am-241 0.00E+00} 2.00E-12
U-236 1.80E+01 3.00E-10
Te-99 1.45E+00) 3.00E-07

Act to DAC
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00

Act to DAC
1.15E+09
1.04E+06
5.45E+05
8.35E+09
0.00E+00
6.00E+10
4.82E+06

9212 HEU Process Stream 22 (Y-12 & SRS Data)

Assume
Pu ppb 0.24
Np ppb 23,700
Tc ppm 85
U-236 ppm 278,000

Assume U @ 62.5% U-235

Assume Weapons Pu Dist

Pu-238 84
Pu-239 14
Pu-240 2
Pu-241 0 .
Pu-242 te)

B-18



e = receipts of 192,836 kg of slightly depleted RU from ORGDP; this material is believed to
have been stored at the Y-12 Complex temporarily and returned to ORGDP and

© = receipts of 38,423 kg of slightly depieted RU as fluorination tower ash from PGDP; this
material is believed to have been disposed of on the Oak Ridge Reservation or returned
to PGDP without any processing in Y-12 Complex facilities.

Shipments
RU streams exited the Y-12 Complex via:

© shipments of 120,384 kg of highly enriched RU as metal product to SRS,

e shipments of 29,614 kg of RU as slightly depleted fluorination tower ash to PGDP (this
material was apparently the ash that had been shipped from PGDP to the Y-12 Complex
and stored at the plant), and

© — shipments of 192,836 kg of slightly depleted RU to ORGDP (these represent the return
of material to ORGDP).

Inventory

As of March 31, 1999, approximately 13 MT of highly enriched RU remained in the
Y-12 Complex inventory.

Summary

The estimated mass balance for highly enriched RU, which is of most concern for
worker exposure and is the primary focus of this project, is summarized in Table ES-1. A
discrepancy in the mass balance between receipts and shipments (plus inventory and waste)
reflects an inability to precisely distinguish between RU and non-RU shipments and receipts
involving the Y-12 Complex and Savannah River. Shipments of fresh fuel (non-RU) and
sweetener (also non-RU) were made from the Y-12 Complex to Savannah River along with
RU shipments. The only way to distinguish between these RU and non-RU streams using
available records is by enrichment level. Shipments of <90% enrichment were assumed to be
RU. Shipments of >90% enrichment were assumed to be non-RU fresh fuel or sweetener.
This methodology using enrichment level to distinguish between RU and non-RU results in
good estimates of RU flows that are reasonably consistent with Savannah River estimates.
Although this is the best available means of distinguishing RU streams, this method does
leave a difference of approximately 17.3 MTU between receipts and shipments.

Slightly depleted RU streams received by the Y-12 Complex from ORGDP and PGDP
are believed to have been returned to the shipping site or disposed of as waste on the Oak
Ridge Reservation. No evidence of Y-12 Complex processing of this material was identified
in the historical records reviewed by the Project Team.

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ES—4


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Depleted uranium metal primarily from Fernald, produced from gaseous diffusion plant
tails, has been used extensively in weapons and defense programs at Idaho, Rocky Flats, the
Y-12 Complex, and other sites. Identical material received at Idaho was analyzed in the
Report on Mass Balance at the Specific Manufacturing Capability Project where it was
determined that the fractional dose resulting from the RU constituents is less than 10% of
that of the uranium itself. The ORGDP Mass Balance Report also confirms very low levels
of transuranics and Tc in the tails streams. Processing of this material in a manner that
concentrated the RU constituents was not performed at the Y-12 Complex; rather, the
material was fabricated as is into an end-use form. For this reason, and in accordance with
the DOE Project Plan, this depleted uranium metal stream was excluded from further
consideration. -

II. RECYCLED URANIUM AT THE Y-12 COMPLEX

For purposes of the DOE recycled uranium mass balance project, RU has been defined as
any uranium that has been irradiated in a reactor and, as a result, contains TRU material (e.g.,
Pu and Np), fission products (e.g., Tc), and reactor-generated uranium products 7°°U). The
methodology applied in this Y-12 Complex project for identifying the flow of RU materials
includes the criteria of (1) the source site, (2) the isotopic constituents, and (3) the wt-%
assays of the material. Sites identified as RU source sites are the U.S. government facilities
that operated production reactors and/or used chemical separation processes to extract
uranium from irradiated fuel. Primary source sites are SRS, ICPP, and Hanford. The
majority of Y-12 Complex transfers with SRS and ICPP have involved RU (although
significant quantities of fresh fuel and sweetener’ were also shipped to Savannah River).
Secondary source sites providing RU materials to the Y-12 Complex are ORGDP and PGDP.
The project identified and reviewed RU streams at the Y-12 Complex from the initial
introduction of RU into the plant in 1953 until March 31, 1999.

Receipts
RU was received at the Y-12 Complex from three primary source sites:

© receipts of 125,161 kg of highly enriched RU as UN solution or U-Al ingots from SRS;
this material was processed in the plant’s 9212 and/or 9206 facilities,

e receipts of 25,696 kg of highly enriched RU as UN solution or oxide from ICPP; this
material was processed in the plant’s 9212 and/or 9206 facilities.

e receipts of 1,502 kg of slightly depleted RU as oxide from Hanford; the assay associated
with this material indicates that it was slightly depleted uranium (DU); this material is
believed to have been disposed of on the Oak Ridge Reservation without any processing
in Y-12 Complex facilities.

The Y-12 Complex also received RU from the following secondary sites:

a

? HEU used to blend with recycled uranium fuel feed to increase its enrichment is referred to as “sweetener.”

ES-3


Chemical Forms of Uranium

Form Code
U (metal) 1

uo2 0.88

U308 0.85

U Enrichment (% U-235) =
Chemical Form of U code =
SUM Constituent Act to DAC=

Constituent Data Units

Pu-238

Pu-239

Pu-240

Np-237
Am-241

U-236

Te-99

Pu-238
Pu-239
Pu-240
Np-237
Am-241
U-236
Tc-99

Form Code Form Code
UO03 0.83 UF6 0.68
UF4 0.76 UO2F2 0.77
UCHK 0.63 U02(NO3)2 0.6
% U-235__U SpecAct uCi/g U
3.75E+01 Ratio
Code DAC Value Act to DAC
6E-10  6.25E+10
1.74E+11 [Fraction Dose from Constituents = | 2.7756
uCi/gsample uCiig U DAC Value ActtoDAC
0.00E+00 3.00E-12 0.00E+00
0.00E+00. 2.00E-12 0.00E+00
0.00E+00 2.00E-12 0.00E+00
0.00E+00 2.00E-12 0.00E+00
0.00E+00 2.00E-12 0.00E+00
0.00E+00 6.00E-10 0.00E+00
0.00E+00 3.00E-07 - 0.00E+00
uCi/g U DAC Value ActtoDAC
6.46E-02) 3.00E-12  2.15E+10
3.91E-05) 2.00E-12  1.95E+07
2.04E-05 2.00E-12  1.02E+07
2.44E-01 2.00E-12  1.22E+11
0.00E+00} 2.00E-12 0.00E+00
4.80E+01 6.00E-10 3.00E+10
3.59E+00} 3.00E-07 1.20E+07

9212 HEU Process Stream 14
Assume

Pu ppb 45
Np ppb 346,000
Tc ppm 211
U-236 ppm 278,000
Assume U @ 62.5% U-235
Assume Weapons Pu Dist
Pu-238 84
Pu-239 14
Pu-240 2
Pu-241 0
Pu-242 i)

(¥-12 & SRS Data)

B-16



periods became the focus of additional assessment to determine the situations that had the
potential to create exposure hazards for workers and/or significant environmental release.

II. CHARACTERIZATION OF RU STREAMS RECEIVED AT THE
Y-12 COMPLEX

Uranium streams received at the Y-12 Complex that contained or may have contained
RU constituents included:

e highly enriched RU material in the form of uranyl nitrate (UN) solutions or uranium
oxide (UO3) received from the Savannah River Site (SRS) and the Idaho Chemical
Processing Plant (ICPP) and

¢ slightly depleted RU’ oxide (including ash and scrap) from the Oak Ridge Gaseous
Diffusion Plant (ORGDP), Hanford, and the Paducah Gaseous Diffusion Plant (PGDP.

In accordance with the methodology prescribed by the DOE Project Plan, calculations
were performed to estimate for these streams the additional dose presented by constituents in
irradiated uranium over that of unirradiated uranium. A fractional dose calculation with a
result of <0.1 indicates that the additional dose presented by the RU constituents is less than
10% of the dose expected from doing similar work with uncontaminated weapons-grade
uranium. RU streams characterized by a dose fraction of <0.1 were deemed de minimis in
accordance with the definition established by DOE for the Recycled Uranium Mass Balance
Project. For those streams, the radiation-protection measures in place for the presence of
uranium are considered adequate for worker protection.

The highly enriched RU from Savannah River and Idaho in the form of uranyl nitrate and
uranium oxide was processed at the Y-12 Complex and shipped to Savannah River as highly
enriched uranium (HEU) metal for fabrication of production reactor fuel. The primary focus
of this document is on the facilities and processes that had the potential for concentrating the
RU constituents, relative to the uranium flow, and so presented the greatest potential for
increased worker exposure.

Five shipments of slightly enriched RU (0.74% 235) were received from SRS; however,
they were transferred to Fernald within one day to one month of receipt. Since the material
was not repackaged, it is not considered to contribute to an increase in personnel exposure.

Slightly depleted RU oxide was received by the Y-12 Complex from ORGDP, Hanford,
and PGDP (including fluorination tower ash from PGDP). Documentation and discussion
with many individuals who worked at the Y-12 Complex from the 1950s onward indicated
that the plant did not have the need for nor the capability of chemically processing this
material. Therefore, it is assumed this material was sent to the plant for storage prior to
burial or further disposition to other Oak Ridge Operations sites; most of the ash was
returned to ORGDP and PDGP. Since these materials were apparently not processed or
handled directly at the Y-12 Complex, they are not at this time considered to be potential
sources of increased personnel exposure or significant environniental release. Further
analysis may be warranted in the future if these materials are detepmined to have been

processed at the Y-12 Complex. %
t

' Slightly depleted RU recovered from production reactor spent fuel is generally in the range of 0.6 to 0.71%
enrichment.

ES-2


(Chemical Forms of Uranium

Form Code
U (metal) 4
Uo2 0.88
U308 0.85
U Enrichment (% U-235) =

(Chemical Form of U code =
SUM Constituent Act to DAC=

Constituent Data Units

Pu-238

Pu-239

Pu-240

Np-237
Am-241

U-236

Te-99

Pu-238

Form
UO3
UF4

uUCcI4

% U-235

Code

Code Form
0.83 UF6
0.76 UO02F2
0.63 U02(NO3)2

U SpecAct uCi/g U
3.75E+01 Ratio
DAC Value Act to DAC

6E-10 6.25E+10

Code
0.68
0.77

0.6

3.29E+10 [Fraction Dose from Constituents =

0.5270

uCi/g sample

uCi/g U

1,.94E-02)

Pu-239
Pu-240
Np-237
Am-241
U-236
Te-99

1.17E-05)

6.13E-06)

4.65E-02

0.00E+00}

1.94E+00

3.40E+00}

uCilg U DAC Value

0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00

3.00E-12
2.00E-12
2.00E-12
2.00E-12
2.00E-12
6.00E-10
3.00E-07

DAC Value

3.00E-12
2.00E-12
2.00E-12
2.00E-12
2.00E-12
6.00E-10
3.00E-07

Act to DAC

0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00

Act to DAC

6.46E+09
5.86E+06
3.06E+06
2.32E+10
0.00E+00
3.24E+09
1.13E+07

9212 HEU Process Stream 33 (Y-12 & SRS Data)

Assume
Pu ppb 1.35
Np ppb 65,900
Te ppm 200
U-236 ppm 30,000 °

Assume U @ 62.5% U-235

Assume Weapons Pu Dist
Pu-238 ©
Pu-239
Pu-240
Pu-241
Pu-242

Cones

B-24

ay



Chemical Forms of Uranium

Form Code Form Code Form Code
U (metal) 4 UO03 0.83 UF6 0.68
u02 0.88 UF4 0.76 U02F2 0.77
U308 0.85 UCI4 0.63 U02(NO3)2 0.6
% U-235__U SpecAct uCi/g U
U Enrichment (% U-235) = 3.75E+01 Ratio’
Code DAC Value Act to DAC
Chemical Form of U code = 3E-10 9 1.25E+11
[SUM Constituent Actto DAC= 7.90E+10 [Fraction Dose from Constituents = | 0.6319
Constituent Data Units uCi/g sample uCiig U DAC Value Actto DAC
Pu-238 0.00E+00 3.00E-12 0.00E+00
Pu-239 0.00E+00 2.00E-12 0.00E+00
Pu-240 0.00E+00 2.00E-12 0.00E+00
Np-237 0.00E+00 2.00E-12 0.00E+00
Am-241 0.00E+00 2.00E-12 0.00E+00
U-236 0.00E+00 3.00E-10 0.00E+00
Tc-99 0.00E+00 3.00E-07 0.00E+00
uCi/g U DAC Value Act to DAC
Pu-238 7.01E-03} 3.00E-12 2.34E+09
Pu-239 4.24E-06) 2.00E-12 2.12E+06
Pu-240 2.22E-06 2.00E-12  1:11E+06
Np-237 3.34E-02) 2.00E-12  1.67E+10
Am-241 0,00E+00} 2.00E-12 0.00E+00
U-236 1,80E+01 3.00E-10 6.00E+10
Tc-99 2.89E+00} 3.00E-07 9.63E+06
9212 HEU Process Stream 23 (Y-12 & SRS Data)
Assume
Pu ppb 0.488
Np ppb 47,400
Tc ppm 170
U-236 ppm 278,000
Assume U @ 62.5% U-235
Assume Weapons Pu Dist
Pu-238 84
Pu-239 14
Pu-240 2
Pu-241 0 x
Pu-242 0
na
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