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Appendix E

SECTION 1

WATER RESOURCES

Table E.1-1. 1993 analytical data for National Pollutant Discharge Elimination System Outfall M¡004 (M-Area Liquid Effluent Treatment Facility)-Permit SC#0000175.a,b

			DMRe results
Parameter	Unitsc	Permit limitsd	Minimumf	Maximumf
pH	Standard unit	6.0-10.0g	6.8	7.8
Nitrate (as N)	mg/L	RRh	51.1	1,700
Phosphate	mg/L	RR	0.238	17.3
Suspended solids	mg/L	31/60i	1	14
Oil and Grease	mg/L	RR	<1	11.9
Uranium	mg/L	RR	<0.02	0.128
Lead	mg/L	0.43/0.69i	<0.0012	0.0225
Nickel	mg/L	1.23/2.46i	<0.012	<0.3
Silver	mg/L	0.009/0.018i	<0.0005	<0.0025
Chromium	mg/L	0.62/1.24i	<0.02	<0.1
Aluminum	mg/L	3.2/6.43i	<0.05	1.3
Copper	mg/L	0.21/0.42i	<0.004	0.03
Zinc	mg/L	0.32/0.64i	<0.01	0.085
Cyanide	mg/L	0.62/1.24i	<0.005	<0.005
Cadmium	mg/L	0.05/0.1i	<0.01	<0.05
Gross Alpha Radioactivity	pCi/L	---------- j	0.306k	4.99k
Nonvolatile (dissolved) Beta Radioactivity	pCi/L	---------- j	0.408k	5.33k
Tritium	pCi/L	---------- j	303k	1,560k

a. Source: Arnett (1994).

b. Parameters are those DOE routinely measures as a regulatory requirement or as a part of ongoing monitoring programs.

c. mg/L = milligrams per liter; a measure of concentration equivalent to the weight/volume ratio.
pCi/L = picocuries per liter; a unit of radioactivity; one trillionth of a curie.

d. Limits imposed by SCDHEC NPDES Permit SC#0000175.

e. 1993 results reported to SCDHEC on the monthly Discharge Monitoring Report (DMR).

f. The minimum concentration was the minimum concentration found in samples analyzed in 1993. The maximum concentration is the highest single result found during the 1993 sampling events.

g. First number is the minimum acceptable pH while the second number is the maximum acceptable pH.

h. RR = measure and report.

i. First number represents the daily average limit while the second number represents the daily maximum limit.

j. Radioactive limits are not included on the NPDES Permit.

k. Collected near the mouth of Tim's Branch, downstream of M-Area.

---

Table E.1-2. 1993 analytical data for National Pollutant Discharge Elimination System Outfall H¡016 (F/H-Area Effluent Treatment Facility)-Permit SC#0000175.a,b

---

			DMRe results
Parameters	unitsc	Permit limitsd	Minimumf	Maximumf
pH	Standard units	6.0-9.0g	6.4	9.0
Temperature	ºC	32.2	14	30
BOD5	mg/L	20/40h,i	<1	5
Nitrate (as N)	mg/L	RRj	1.78	66
Ammonia as Nitrogen	mg/L	20/RR	<0.01	0.15
Suspended Solids	mg/L	30/60i	<1	2
Oil and Grease	mg/L	10/15i	<1	10.1
Uranium	mg/L	RR	<0.02	<0.1
Lead	mg/L	0.29/0.58i	<0.0005	0.0094
Nickel	mg/L	RR	<0.03	<0.05
Mercury	mg/L	0.045/0.175i	<0.0001	<0.0005
Chromium	mg/L	1.71/2.77i	<0.02	<0.03
Aluminum	mg/L	RR	<0.05	0.053
Copper	mg/L	1.45/2.07i	<0.01	0.013
Zinc	mg/L	1.48/2.61i	<0.01	0.414
Manganese	mg/L	RR	<0.005	0.0343
Total Chlorine	mg/L	RR	<0.01	0.37
Gross Alpha Radioactivity	pCi/L	------ k	0.53h	3.90h
Nonvolatile (dissolved) Beta Radioactivity	pCi/L	------ k	0.497h	3.94h
Tritium	pCi/L	------- k	607h	13,200h
Strontium-89,90	pCi/L	------- k	<DLl	0.783h
Uranium/Plutonium	pCi/L	------- k	<DL	0.298h

a. Source: Arnett (1994).

b. Parameters are those DOE routinely measures as a regulatory requirement or as a part of ongoing monitoring programs.

c. mg/L= milligrams per liter; a measure of concentration equivalent to the weight/volume ratio.
pCi/L= picocuries per liter; a unit of radioactivity; one trillionth of a curie.

d. Limits imposed by the SCDHEC NPDES Permit SC#0000175.

e. 1993 results reported to SCDHEC on the monthly Discharge Monitoring Report (DMR).

f. The minimum concentration is the minimum concentration found in samples analyzed in 1993. The maximum concentration is the highest single result found during the 1993 sampling events.

g First number is the minimum acceptable pH while the second number is the maximum acceptable pH.

h. Collected downstream of Outfall H-016 on Upper Three Runs near Road C.

i. First number represents the monthly average limit while the second number represents the daily maximum limit.

j. RR = measure and report.

k. Radioactive limits are not included on the NPDES Permit.

l. <DL = analytical result less than the test procedure detection limit.

---

Table E.1-3. Water quality in Beaver Creek Dam on SRS (calendar year 1992).a,b

---

Parameter	Unit of measurec	MCLd,e or DCGf	Minimumg	Maximumg
Aluminum	mg/L	0.05-0.2h	3.59	4.14
Ammonia	mg/L	NAi,j	0.048	0.40
Cadmium	mg/L	0.005d	<0.00004	0.0025
Calcium	mg/L	NA	2.68	4.41
Cesium-137	pCi/L	120
Chloride	mg/L	250h	2.4	8.6
Chromium	mg/L	0.1d	<0.0004	0.0668
Copper	mg/L	1.3k	<0.0004	0.014
Dissolved oxygen	mg/L	>5.0l	5.8	10.0
Fecal coliform	Colonies per 100 ml	1,000l	3	22
Gross alpha radioactivity	pCi/L	15d	<DL	1.15
Iron	mg/L	0.3h	0.567	3.81
Lead	mg/L	0.015k	<0.0004	0.015
Magnesium	mg/L	NA	1.02	1.82
Manganese	mg/L	0.05h	<0.0004	0.412
Nickel	mg/L	0.1d,e	<0.0004	0.015
Nonvolatile (dissolved) beta radioactivity	pCi/L	50d	0.5	5.8
pH	pH units	6.5-8.5h	6.2	7.6
Phosphate	mg/L	NA	<0.01	1.5
Sodium	mg/L	NA	3.83	10.6
Sulfate	mg/L	250h	3.98	13.1
Suspended solids	mg/L	NA	1.0	31.8
Temperature	°C	32.2m	14.5	34
Tritium	pCi/L	20,000d,e	0.05	228
Zinc	mg/L	5h	<0.0004	0.017

a. Sources: Wike et al. (1994); Cummins, Martin, and Todd (1991).

b. Parameters are those DOE routinely measures as a regulatory requirement or as part of ongoing monitoring programs.

c. mg/L = milligrams per liter; a measure of concentration equivalent to the weight/volume ratio.

pCi/L = picocuries per liter; a picocurie is a unit of radioactivity; one trillionth of a curie.

d. Maximum Contaminant Level (MCL), EPA National Primary Drinking Water Standards (40 CFR Part 141).
See glossary.

e. Maximum Contaminant Level, SCDHEC (1976). See glossary.

f. DOE Derived Concentration Guides (DCGs) for water (DOE Order 5400.5). DCG values are based on committed effective doses of 4 millirem per year for consistency with drinking water MCL of 4 millirem per year. See glossary.

g. Minimum concentrations of samples taken at the downstream monitoring station. The maximum listed concentration is the highest single result found during one sampling event. Less than (<) indicates concentration below analysis detection limit (DL).

h. Secondary Maximum Contaminant Level (SMCL), EPA National Secondary Drinking Water Regulations
(40 CFR Part 143).

i. NA = none applicable.

j. Depends on pH and temperature.

k. Action level for lead and copper.

l. WQS = water quality standard. See glossary.

m. Shall not exceed weekly average of 32.2°C (90°F) after mixing nor rise more than 2.8°C (5°F) in 1 week unless appropriate temperature criterion mixing zone has been established.

---

Table E.1-4. Water quality in Fourmile Branch on SRS (calendar year 1993).a,b

---

Parameter	Unit of measurec	MCLd,e or DCGf	Minimumg	Maximumg
Aluminum	mg/L	0.05-0.2h	0.08	0.34
Ammonia	mg/L	NAi,j	NDk	0.04
Cadmium	mg/L	0.005d	ND	ND
Calcium	mg/L	NA	2.24	3.35
Cesium-137	pCi/L	120	8.44	19.4
Chemical oxygen demand	mg/L	NA	ND	ND
Chloride	mg/L	250h	2	5
Chromium	mg/L	0.1d	ND	ND
Copper	mg/L	1.3l	ND	ND
Dissolved oxygen	mg/L	>5.0m	6.4	11.3
Fecal coliform	Colonies per 100 ml	1,000m	23	440
Gross alpha radioactivity	pCi/L	15d	0.073	2.68
Iron	mg/L	0.3h	0.364	1.14
Lead	mg/L	0.015l	ND	0.003
Magnesium	mg/L	NA	0.565	0.636
Manganese	mg/L	0.05h	0.079	0.104
Mercury	mg/L	0.002d,e	ND	ND
Nickel	mg/L	0.1d	ND	ND
Nitrite/Nitrate (as nitrogen)	mg/L	10d	1.42	2.85
Nonvolatile (dissolved) beta radioactivity	pCi/L	50d	20.5	43.5
pH	pH units	6.5-8.5h	5.7	7.7
Phosphate	mg/L	NA	ND	ND
Sodium	mg/L	NA	6.29	10.6
Strontium-89/90	pCi/L	-	10.3	15.3
Sulfate	mg/L	250h	4	9
Suspended solids	mg/L	NA	2	9
Temperature	°C	32.2n	10	25.5
Total dissolved solids	mg/L	500h	40	78
Tritium	pCi/L	20,000d,e	33,600	68,900
Zinc	mg/L	5h	ND	0.011

a. Source: Arnett (1994).

b. Parameters are those DOE routinely measures as a regulatory requirement or as part of ongoing monitoring programs.

c. mg/L = milligrams per liter; a measure of concentration equivalent to the weight/volume ratio.

pCi/L = picocuries per liter; a picocurie is a unit of radioactivity; one trillionth of a curie.

d. Maximum Contaminant Level (MCL), EPA National Primary Drinking Water Standards (40 CFR Part 141).
See glossary.

e. Maximum Contaminant Level, SCDHEC (1976). See glossary.

f. DOE Derived Concentration Guides (DCGs) for water (DOE Order 5400.5). DCG values are based on committed effective doses of 4 millirem per year for consistency with drinking water MCL of 4 millirem per year. See glossary.

g. Minimum concentrations of samples taken at the downstream monitoring station. The maximum listed concentration is the highest single result found during one sampling event.

h. Secondary Maximum Contaminant Level (SMCL), EPA National Secondary Drinking Water Regulations
(40 CFR Part 143).

i. NA = none applicable.

j. Depends on pH and temperature.

k. ND = none detected.

l. Action level for lead and copper.

m. WQS = water quality standard. See glossary.

n. Shall not exceed weekly average of 32.2°C (90°F) after mixing nor rise more than 2.8°C (5°F) in 1 week unless appropriate temperature criterion mixing zone has been established.

---

Table E.1-5. Water quality in Pen Branch on SRS (calendar year 1993).a,b

---

Parameter	Unit of measurec	MCLd,e or DCGf	Minimumg	Maximumg
Aluminum	mg/L	0.05-0.2h	0.096	0.398
Ammonia	mg/L	NAi,j	NDk	0.09
Cadmium	mg/L	0.005d	ND	ND
Calcium	mg/L	NA	0.976	5.03
Chemical oxygen demand	mg/L	NA	ND	ND
Chloride	mg/L	250h	3	10
Chromium	mg/L	0.1d	ND	ND
Copper	mg/L	1.3l	0.041	0.098
Dissolved oxygen	mg/L	>5.0m	6.3	10.6
Fecal coliform	Colonies per 100 ml	1,000m	18	320
Gross alpha radioactivity	pCi/L	15d	<DLn	1.27
Iron	mg/L	0.3h	0.361	0.705
Lead	mg/L	0.015l	ND	0.002
Magnesium	mg/L	NA	0.71	1.08
Manganese	mg/L	0.05h	0.038	0.096
Mercury	mg/L	0.002d,e	ND	ND
Nickel	mg/L	0.1d	ND	ND
Nitrite/Nitrate (as nitrogen)	mg/L	10d	0.15	0.26
Nonvolatile (dissolved) beta radioactivity	pCi/L	50d	0.368	2.86
pH	pH units	6.5-8.5h	5.9	7.8
Phosphate	mg/L	NA	ND	0.04
Sodium	mg/L	NA	3.49	9.35
Strontium-89/90	pCi/L	-	<DL	0.49
Sulfate	mg/L	250h	4	7
Suspended solids	mg/L	NA	2	12
Temperature	°C	32.2o	10.3	26.5
Total dissolved solids	mg/L	500h	42	79
Tritium	pCi/L	20,000d,e	17,200	65,000
Zinc	mg/L	5h	ND	0.012

a. Source: Arnett (1994).

b. Parameters are those DOE routinely measures as a regulatory requirement or as part of ongoing monitoring programs.

c. mg/L = milligrams per liter; a measure of concentration equivalent to the weight/volume ratio.

pCi/L = picocuries per liter; a picocurie is a unit of radioactivity; one trillionth of a curie.

d. Maximum Contaminant Level (MCL), EPA National Primary Drinking Water Standards ( 40 CFR Part 141).
See glossary.

e. Maximum Contaminant Level, SCDHEC (1976). See glossary.

f. DOE Derived Concentration Guides (DCGs) for water (DOE Order 5400.5). DCG values are based on committed effective doses of 4 millirem per year for consistency with drinking water MCL of 4 millirem per year. See glossary.

g. Minimum concentrations of samples taken at the downstream monitoring station. The maximum listed concentration is the highest single result found during one sampling event.

h. Secondary Maximum Contaminant Level (SMCL). EPA National Secondary Drinking Water Regulations
(40 CFR Part 143).

i. NA = none applicable.

j. Depends on pH and temperature.

k. ND = none detected.

l. Action level for lead and copper.

m. WQS = water quality standard. See glossary.

n. Less than (<) indicates concentration below analysis detection limit (DL).

o. Shall not exceed weekly average of 32.2°C (90°F) after mixing nor rise more than 2.8°C (5°F) in 1 week unless appropriate temperature criterion mixing zone has been established.

---

Table E.1-6. Water quality in Steel Creek on SRS (calendar year 1993).a,b

---

Parameter	Unit of measurec	MCLd,e or DCGf	Minimumg	Maximumg
Aluminum	mg/L	0.05-0.2h	NDi	0.138
Ammonia	mg/L	NAj,k	ND	0.05
Cadmium	mg/L	0.005d	ND	ND
Calcium	mg/L	NA	1.92	2.28
Cesium-137	pCi/L	120	3.75	3.75
Chemical oxygen demand	mg/L	NA	ND	ND
Chloride	mg/L	250h	4	9
Chromium	mg/L	0.1d	ND	ND
Copper	mg/L	1.3l	ND	ND
Dissolved oxygen	mg/L	>5.0m	6.4	11.4
Fecal coliform	Colonies per 100 ml	1,000m	2	142
Gross alpha radioactivity	pCi/L	15d	<DLn	1.22
Iron	mg/L	0.3h	0.053	0.224
Lead	mg/L	0.015l	ND	0.004
Magnesium	mg/L	NA	0.947	1.16
Manganese	mg/L	0.05k	ND	0.024
Mercury	mg/L	0.002d,e	ND	ND
Nickel	mg/L	0.1d	ND	ND
Nitrite/Nitrate (as nitrogen)	mg/L	10d	ND	0.17
Nonvolatile (dissolved) beta radioactivity	pCi/L	50d	0.688	2.79
pH	pH units	6.5-8.5h	5.9	7.9
Phosphate	mg/L	NA	ND	ND
Sodium	mg/L	NA	5.44	8.53
Strontium-90	pCi/L	8f	<DL	0.818
Sulfate	mg/L	250h	4	6
Suspended solids	mg/L	NA	ND	5
Temperature	°C	32.2o	10.2	29.6
Total dissolved solids	mg/L	500h	39	67
Tritium	pCi/L	20,000d,e	4,130	6,200
Zinc	mg/L	5h	ND	0.014

a. Source: Arnett (1994).

b. Parameters are those DOE routinely measures as a regulatory requirement or as part of ongoing monitoring programs.

c. mg/L = milligrams per liter; a measure of concentration equivalent to the weight/volume ratio.

pCi/L = picocuries per liter; a picocuries is a unit of radioactivity; one trillionth of a curie.

d. Maximum Contaminant Level (MCL), EPA National Primary Drinking Water Standards (40 CFR Part 141).
See glossary.

e. Maximum Contaminant Level, SCDHEC (1976). See glossary.

f. DOE Derived Concentration Guides (DCGs) for water (DOE Order 5400.5). DCG values are based on committed effective doses of 4 millirem per year for consistency with drinking water MCL of 4 millirem per year. See glossary.

g. Minimum concentrations of samples taken at the downstream monitoring station. The maximum listed concentration is the highest single result found during one sampling event.

h. Secondary Maximum Contaminant Level (SMCL), EPA National Secondary Drinking Water Regulations
(40 CFR Part 143).

i. ND = none detected.

j. NA = none applicable.

k. Depends on pH and temperature.

l. Action level for lead and copper.

m. WQS = water quality standard. See glossary.

n. Less than (<) indicates concentration below analysis detection limit (DL).

o. Shall not exceed weekly average of 32.2°C (90°F) after mixing nor rise more than 2.8°C (5°F) in 1 week unless appropriate temperature criterion mixing zone has been established.

---

Table E.1-7. Water quality in Lower Three Runs on SRS (calendar year 1993).a,b

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Parameter	Unit of measurec	MCLd,e or DCGf	Minimumg	Maximumg
Aluminum	mg/L	0.05-0.2h	NDi	0.092
Ammonia	mg/L	NAj,k	ND	0.06
Cadmium	mg/L	0.005d	ND	ND
Calcium	mg/L	NA	5.63	12.8
Chemical oxygen demand	mg/L	NA	ND	ND
Chloride	mg/L	250h	3	5
Chromium	mg/L	0.1d	ND	ND
Copper	mg/L	1.3l	ND	ND
Dissolved oxygen	mg/L	>5.0m	6.7	10.2
Fecal coliform	pCi/L	1,000m	72	12,200
Gross alpha radioactivity	mg/L	15d	<DLn	0.69
Iron	mg/L	0.3h	0.138	0.275
Lead	mg/L	0.015l	ND	0.002
Magnesium	mg/L	NA	0.553	0.79
Manganese	mg/L	0.05h	ND	0.024
Mercury	mg/L	0.002d,e	ND	ND
Nickel	mg/L	0.1d	ND	ND
Nitrite/Nitrate (as nitrogen)	mg/L	10d	ND	0.18
Nonvolatile (dissolved) beta radioactivity	pCi/L	50d	1.16	3.43
pH	pH units	6.5-8.5h	5.9	7.5
Phosphate	mg/L	NA	ND	ND
Sodium	mg/L	NA	1.97	2.98
Strontium-90	pCi/L	8f	<DL	0.048
Sulfate	mg/L	250h	2	4
Suspended solids	mg/L	NA	ND	10
Temperature	°C	32.2o	10.3	26.0
Total dissolved solids	mg/L	500h	33	69
Tritium	pCi/L	20,000d,e	131	907
Zinc	mg/L	5h	ND	0.031

a. Source: Arnett (1994).

b. Parameters are those DOE routinely measures as a regulatory requirement or as part of ongoing monitoring programs.

c. mg/L = milligrams per liter; a measure of concentration equivalent to the weight/volume ratio.

pCi/L = picocuries per liter; a picocurie is a unit of radioactivity; one trillionth of a curie.

d. Maximum Contaminant Level (MCL), EPA National Primary Drinking Water Standards (40 CFR Part 141).
See glossary.

e. Maximum Contaminant Level, SCDHEC (1976). See glossary.

f. DOE Derived Concentration Guides (DCGs) for water (DOE 5400.5). DCG values are based on committed effective doses of 4 millirem per year for consistency with drinking water MCL of 4 millirem per year. See glossary.

g. Minimum concentrations of samples taken at the downstream monitoring station. The maximum listed concentration is the highest single result found during one sampling event.

h. Secondary Maximum Contaminant Level (SMCL), EPA National Secondary Drinking Water Regulations
(40 CFR Part 143).

i. ND = none detected.

j. NA = none applicable.

k. Depends on pH and temperature.

l. Action level for lead and copper.

m. WQS = water quality standard. See glossary.

n. Less than (<) indicates concentration below analysis detection limit (DL).

o. Shall not exceed weekly average of 32.2°C (90°F) after mixing nor rise more than 2.8°C (5°F) in 1 week unless appropriate temperature criterion mixing zone has been established.

---

SECTION 2

AIR QUALITY

Table E.2-1. Results of SRS modeling for toxic air pollutants (micrograms per cubic meter of air).a,b

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Pollutant	Maximum allowable concentration (µg/m3)	Concentration at SRS boundary (µg/m3)	Percent of standardc
Low Toxicity Category
Acetonitrile	1,750.00	0.00018	0.00
Ammonium Chloride	250.00	0.02379	0.01
Antimony	2.50	0.00112	0.04
Chlorine	75.00	7.63023	10.17
Cyanide	125.00	0.00000	0.00
Ethanolamine	200.00	0.00101	0.00
Formic Acid	225.00	2.41990	1.08
Furfural	200.00	0.00180	0.00
Hydrochloric Acid (Hydrogen Chloride)	175.00	1.05622	0.60
Hydrogen Cyanide	250.00	0.12935	0.05
Methyl Ethyl Ketone (2-Butone)	14,750.00	5.12159	0.03
Methyl Methacrylate	10,250.00	0.00002	0.00
Methylene Chloride	8,750.00	10.46781	0.12
Methyl Tert-Butyl Ether	(d)	0.49390	NAe
Naphthalene	1,250.00	0.00452	0.00
Nitric Acid	125.00	50.95952	40.77
Phosphoric Acid	25.00	0.46236	1.85
Styrene	5,325.00	0.00079	0.00
Trichloroethylene	6,750.00	6.43130	0.10
Moderate Toxicity Category
Acetaldehyde	1,800.00	0.00180	0.00
Acrylamide	0.30	0.00180	0.60
Aldicarb	6.00	0.00737	0.12
Cresol	220.00	0.00180	0.00
Cumene	9.00	0.00110	0.01
p-Dichlorobenzene	4,500.00	0.00180	0.00
Diethanaolamine	129.00	0.00364	0.00
Dioctyl Phthalate	50.00	0.02569	0.05
Ethyl Benzene	4,350.00	0.58773	0.01
Ethyl Chloride	26,400.00	0.00007	0.00
Ethylene Dibromide	770.00	0.00180	0.00
Furfuryl Alcohol	400.00	0.00037	0.00
1,6-Diisocyanatehexamethylene	0.34	0.00110	0.32
Hydrogen Sulfide	140.00	0.20149	0.14
Hydroquinone	20.00	0.00010	0.00
Isophorone	250.00	0.00154	0.00
Maleic Anhydride	10.00	0.00180	0.02

Table E.2-1. (continued).

---

Pollutant	Maximum allowable concentration (µg/m3)	Concentration at SRS boundary (µg/m3)	Percent of standardc
Methyl Isobutyl Ketone	2,050.00	2.96016	0.14
Oxalic Acid	10.00	0.00026	0.00
Pentachlorophenol	5.00	0.00180	0.04
Phenol	190.00	0.02745	0.01
Phosgene (Carbonyl Chloride)	4.00	0.00180	0.05
Phosphorus (Yellow or White)	0.50	0.00013	0.03
Sodium Hydroxide	20.00	0.00940	0.05
Sulfuric Acid	10.00	0.00951	0.10
Tetrachloroethylene	3,350.00	2.00935	0.06
Xylene	4,350.00	39.36740	0.90
m-Xylene	4,350.00	0.00180	0.00
o-Xylene	4,350.00	0.00181	0.00
p-Xylene	4,350.00	0.00180	0.00
High Toxicity Category
Acetophenone	(d)	0.00180	NA
Acrolein	1.25	0.01585	1.27
Acrylic Acid	147.50	0.00182	0.00
Acrylonitrile	22.50	0.01646	0.07
Aniline	50.00	0.00180	0.00
Arsenic	1.00	0.00191	0.19
Benzene	150.00	31.71134	21.14
Benzidine	(d)	0.00180	NA
Benzotrichloride	300.00	0.00180	0.00
Benzyl Chloride	25.00	0.00180	0.01
Beryllium	0.01	0.00000	0.00
Biphenyl	6.00	0.00138	0.02
Bis (chloromethyl) Ether	0.03	0.00180	6.00
Bromoform	25.85	0.00475	0.02
Cadmium Oxide	0.25	0.02136	8.54
Cadmium	0.25	0.00028	0.11
Carbon Disulfide	150.00	0.00208	0.00
Carbon Tetrachloride	150.00	0.00209	0.00
Catechol	297.00	0.00009	0.00
Chlordane	2.50	0.00181	0.07
Chlorobenzene	1,725.00	0.00209	0.00
Chloroform	250.00	4.95658	1.98
Chloromethyl Methyl Ether	(d)	0.00180	NA
Cobalt	0.25	0.20628	82.51
2,4-Dichlorphenoxy Acetic Acid	50.00	0.00180	0.00

Table E.2-1. (continued).

---

Pollutant	Maximum allowable concentration (µg/m3)	Concentration at SRS boundary (µg/m3)	Percent of standardc
Dibutyl Phthalate	25.00	0.13246	0.53
3,3-Dichlorobenzidine	0.15	0.00180	1.20
1,3-Dichloropropene	7.00	0.00208	0.03
Diethyl Phthalate	25.00	0.00000	0.00
3,3-Dimethoxybenzidene	0.30	0.00180	0.60
3,3-Dimethylbenzidine	(d)	0.00180	NA
Dimethylformamide	149.50	0.00024	0.00
Dimethyl Phthalate	25.00	0.00180	0.01
Dimethyl Sulfate	2.50	0.00180	0.07
2,4-Dinitrophenol	(d)	0.00180	NA
2,4-Dinitrotoluene	1.50	0.00180	0.12
Dioxane	450.00	0.00184	0.00
1,2-Diphenyl Hydrazine	(d)	0.00180	NA
Epichlorohydrin	50.00	0.00180	0.00
1,2-Butylene Oxide	(d)	0.00877	NA
Ethylene Dichloride	200.00	0.00183	0.00
Ethylene Glycol	650.00	0.19536	0.03
Ethylene Oxide	10.00	0.00180	0.02
Ethylene Thiourea	(d)	0.00180	NA
Ethylenimine	5.00	0.01802	0.36
1,1-Dichloroethane	2,025.00	0.00116	0.00
Formaldehyde	7.50	0.00269	0.04
Glycol Ethers	(d)	0.00031	NA
Heptachlor	2.50	0.00737	0.29
Hexachlorobenzene	(d)	0.00180	NA
Hexachlorobutadiene	1.20	0.00180	0.15
Hexachlorocylopentadiene	0.50	0.00180	0.36
Hexachloroethane	48.50	0.00180	0.00
Hexachloronapthalene	1.00	0.00000	0.00
Hexane	200.00	0.20551	0.10
Hydrazine	0.50	0.00180	0.36
Lindane	2.50	0.00180	0.07
Manganese Oxide	25.00	0.00066	0.00
Manganese	25.00	0.82129	3.29
Mercury	0.25	0.01393	5.57
Methyl Alcohol	1,310.00	2.87804	0.22
Methoxychlor	50.00	0.00180	0.00
Methyl Bromide	100.00	0.00158	0.00
Methyl Chloride	515.00	0.00200	0.00

Table E.2-1. (continued).

---

Pollutant	Maximum allowable concentration (µg/m3)	Concentration at SRS boundary (µg/m3)	Percent of standardc
1,1,1-Trichloroethane	9,550.00	80.83216	0.85
Methyl Hydrazine	1.75	0.00180	0.10
Methyl Iodide	58.00	0.00180	0.00
Curene	1.10	0.00180	0.16
Nickel Oxide	5.00	0.00183	0.04
Nickel	0.50	0.27106	54.21
Nitrobenzene	25.00	0.00314	0.01
p-Nitrophenol	0.00	0.00180	NA
2-Nitropropane	182.00	0.00180	0.00
Parathion	0.50	0.00737	1.47
Pentachloronitrobenzene	(d)	0.00180	NA
Phthalic Anhydride	30.30	0.00180	0.01
Polycyclic Organic Matter	160.00	0.00000	0.00
Propylene Dichloride	1,750.00	0.00079	0.00
Selenium	1.00	0.00000	0.00
Tetrachlorinated Dibenzo-p-Dioxins	0.00	0.00000	NA
1,1,2,2-Tetrachloroethane	35.00	0.00208	0.01
Toluene	200.00	9.27688	0.46
Toxaphene	2.50	0.00737	0.29
1,1,2-Trichloroethane	273.00	0.01646	0.01
2,4,6-Trichlorophenol	(d)	0.00180	NA
Triethylamine	207.00	0.00010	0.00
Vinyl Acetate	176.00	0.05518	0.03
Vinyl Chloride	50.00	0.00183	0.00
1,1-Dichloroethylene	99.00	0.00180	0.00

a. Source: WSRC (1993).

b. Concentrations are based on maximum potential emissions.

c. Percent of standard =

d. No standard established by regulatory agency.

e. NA - not applicable.

---

Table E.2-2. Comparison of potential worker annual exposure to OSHA permissible exposure limits under alternative A (micrograms per cubic meter of air).a

---

		Expected forecast receptor locations			Minimum forecast receptor locations				Maximum forecast receptor locations
Pollutant	OSHA PELb	100 metersc	640 meters			100 meters	640 meters			100 meters	640 meters
M-Area Vendor
Nitrogen dioxide	9,000	37.45	43.70			37.45	43.70			37.45	43.70
Sulfur dioxide	1.3´104	1.65	1.92			1.65	1.92			1.65	1.92
PM10d	5,000	1.97	2.30			1.97	2.30			1.97	2.30
Bld waste hazardous waste storage)
Total suspended particulates	1.5×104	25.13	10.56			13.10	5.51			41.28	17.36
PM10	5,000	8.79	3.70			4.49	1.89			14.54	6.11
Bldg. 645-2N (mixed waste mixed waste storage)
Total suspended particulates	1.5×104	6.60	2.78			1.78	0.75			32.84	13.81
PM10	5,000	2.32	0.97			0.62	0.26			11.50	4.84
Soil sort facilities
Total suspended particulates	1.5×104	11.00	4.63			0.31	0.13			54.74	23.02
PM10	5,000	3.84	1.61			0.11	0.05			1.92	0.81
(Four) new solvent tanks
Vinyl chloride	2,600	5.08	3.95			3.78	2.94			4.29	3.34
1,1 Dichloroethane	N/Ae	0.38	0.30			0.29	0.22			0.33	0.25
Methyl ethyl Ketone	5.9×105	22.00	17.11			16.39	12.75			18.61	14.48
Chloroform	9,780	2.36	1.84			1.76	1.37			2.00	1.56
Carbon tetrachloride	1.26×104	0.19	0.15			0.14	0.11			0.16	0.13
Benzene	3,250	3.08	2.40			2.29	1.78			2.61	2.03
1,2 Dichloroethane	N/A	0.13	0.10			0.09	0.07			0.11	0.08
Trichloroethane	2.7×105	0.12	0.09			0.09	0.07			0.10	0.08
Tetrachloroethylene	1.7×105	0.03	0.02			0.02	0.02			0.02	0.02
Chlorobenzene	3.5×105	0.02	0.01			0.01	0.01			0.01	0.01
Transuranic waste characterization/ certification facility
Vinyl chloride	2,600	0.02	0.01			0.01	0.01			0.39	0.34
1,1 Dichloroethane	N/A	0.001	9.8×10-4			8.1×10-4	7.0×10-4			0.30	0.25
Methyl ethyl ketone	5.9×105	0.07	0.06			0.05	0.04			1.70	1.46
Chloroform	9,780	0.01	0.01			0.01	0.00			0.18	0.16
Carbon tetrachloride	1.26×104	5.6×10-4	4.8×10-4			4.0×10-4	3.5×10-4			0.015	0.013
Benzene	3,250	0.009	0.008			0.007	0.006			0.237	0.204
1,2 Dichloroethane	N/A	3.8×10-4	3.2×10-4			2.7×10-4	2.3×10-4			0.010	0.008
Trichloroethane	2.7×105	3.6×10-4	3.1×10-4			2.5×10-4	2.2×10-4			0.009	0.008
Tetrachloroethylene	1.7×105	7.9×10-5	6.8×10-5			5.6×10-5	4.8×10-5			0.002	0.002
Chlorobenzene	3.5×105	5.0×10-5	4.3×10-5			3.5×10-5	3.0×10-5			0.001	0.001
Containment building
Total suspended particulates	1.5×104	4.34	2.64			2.28	1.38			15.41	9.36
PM10	5,000	4.34	2.64			2.28	1.38			15.41	9.36

Table E.2-2. (continued).

---

		Expected forecast receptor locations			Minimum forecast receptor locations				Maximum forecast receptor locations
Pollutant	OSHA PELb	100 metersc	640 meters			100 meters	640 meters			100 meters	640 meters
Vinyl chloride	2,600	0.24	0.15			0.13	0.08			1.08	0.66
1,1 Dichloroethane	N/A	0.02	0.01			0.01	0.01			0.08	0.05
Methyl ethyl ketone	5.9×105	26.40	16.04			25.46	15.47			32.38	19.68
Chloroform	9,780	0.11	0.07			0.06	0.04			0.50	0.31
Carbon tetrachloride	1.26×104	0.01	0.01			0.005	0.003			0.04	0.02
Benzene	3,250	0.15	0.08			0.06	0.04			0.66	0.40
1,2 Dichloroethane	N/A	0.006	0.004			0.003	0.002			0.03	0.02
Trichloroethane	2.7×105	0.006	0.004			0.003	0.002			0.03	0.02
Tetrachloroethylene	1.7×105	0.001	7.4×10-4			5.4×10-4	3.3×10-4			0.006	0.003
Chlorobenzene	3.5×105	7.6×10-4	4.6×10-4			3.4×10-4	2.1×10-4			0.004	0.002

a. Source: NIOSH (1990).

b. OSHA PEL - Occupational Safety and Health Administration Permissible Exposure Limits.

c. To convert to feet multiply by 3.281.

d. Particulate matter less than 10 microns in diameter.

e. Not Applicable - No OSHA PEL assigned - Exposure should be kept as low as possible.

---

Table E.2-3. Comparison of potential worker exposure to OSHA permissible exposure limits under alternative C (micrograms per cubic meter of air).a

---

			Expected forecast receptor locations						Minimum forecast receptor locations						Maximum forecast receptor locations
Facility/Pollutant	OSHA PELb		100 metersc		640 meters				100 meters		640 meters				100 meters	640 meters
M-Area Vendor
Nitrogen dioxide		9,000		37.45		43.70				37.45			43.70		37.30	43.52
Sulfur dioxide		1.3×104		1.65		1.92				1.65			1.92		1.65	1.92
PM10d		5,000		1.97		2.30				1.97			2.30		1.97	2.30
Bldg. 645-2N (mixed waste mixed waste storage)
Total suspended particulates		15,000		6.60		2.78				1.78			0.75		32.84	13.81
PM10		5,000		2.32		0.97				0.62			0.26		11.50	4.84
Soil sort facilities
Total suspended particulates		15,000		15.63		6.57				4.34			1.83		75.38	31.69
PM10		5,000		5.47		2.30				1.52			0.64		26.38	11.09
(Four) new solvent tanks
Vinyl chloride		2,600		3.99		3.10				3.92			3.05		4.17	3.24
1,1 Dichloroethane		N/Ae		0.30		0.23				0.30			0.23		0.32	0.25
Methyl ethyl ketone		5.9×105		17.28		13.44				17.00			13.22		18.06	14.04
Chloroform		9,780		1.86		1.44				1.82			1.42		1.94	1.51
Carbon tetrachloride		1.26×104		0.15		0.12				0.15			0.11		0.16	0.12
Benzene		3,250		2.42		1.88				2.38			1.85		2.53	1.97
1,2 Dichloroethane		N/A		0.10		0.08				0.10			0.08		0.10	0.08
Trichloroethane		2.7×105		0.09		0.07				0.09			0.07		0.10	0.08
Tetrachloroethylene		1.7×105		0.02		0.02				0.02			0.02		0.02	0.02
Chlorobenzene		3.5×105		0.01		0.01				0.01			0.01		0.01	0.01
Transuranic waste characterization/ certification facility
Vinyl chloride		2,600		0.015		0.013				0.011			0.009		0.389	0.335
1,1 Dichloroethane		N/A		0.001		0.001				0.001			0.001		0.029	0.025
Methyl ethyl ketone		5.9×105		0.065		0.056				0.046			0.040		1.687	1.450
Chloroform		9,780		0.007		0.006				0.005			0.004		0.181	0.155
Carbon tetrachloride		1.26×104		5.6×10-4		4.8×10-4				4.0×10-4			3.4×10-4		0.015	0.013
Benzene		3,250		0.009		0.008				0.006			0.006		0.236	0.203
1,2 Dichloroethane		N/A		3.7×10-4		3.2×10-4				2.7×10-4			2.3×10-4		0.010	0.008
Trichloroethane		2.7×105		3.5×10-4		3.0×10-4				2.5×10-4			2.2×10-4		0.009	0.008
Tetrachloroethylene		1.7×105		7.9×10-5		6.8×10-5				5.6×10-5			4.8×10-5		0.002	0.002
Chlorobenzene		3.5×105		4.9×10-5		4.2×10-5				3.5×10-5			3.0×10-5		0.001	0.001
Containment building
Vinyl chloride		2,600		0.059		0.036				0.028			0.017		0.219	0.133
1,1 Dichloroethane		N/A		0.004		0.003				0.002			0.001		0.017	0.010
Methyl ethyl ketone		5.9×105		24.91		15.13				24.65			14.98		26.21	15.92
Chloroform		9,780		0.028		0.017				0.013			0.008		0.102	0.062
Carbon tetrachloride		1.26×104		0.002		0.001				0.001			6.5×10-4		0.008	0.005
Benzene		3,250		0.036		0.022				0.017			0.010		0.133	0.081
1,2 Dichloroethane		N/A		0.001		9.0×10-4				7.1×10-4			4.3×10-4		0.005	0.003
Trichloroethane		2.7×105		0.004		0.002				0.002			9.2×10-4		0.011	0.007
Tetrachloroethylene		1.7×105		8.1×10-4		4.9×10-4				3.4×10-4			2.1×10-4		0.002	0.001
Chlorobenzene		3.5×105		5.1×10-4		3.1×10-4				2.1×10-4			1.3×10-4		0.002	9.3×10-4

Table E.2-3. (continued).

---

		Expected forecast receptor locations			Minimum forecast receptor locations			Maximum forecast receptor locations
Facility/Pollutant	OSHA PELb	100 metersc	640 meters		100 meters	640 meters		100 meters	640 meters
Non-alpha vitrification
Total suspended particulates	1.5×104	1.5×10-9	0.215		4.4×10-10	0.065		7.2×10-9	1.056
PM10	5,000	1.5×10-9	0.215		4.4×10-10	0.065		7.2×10-9	1.056
Nitrogen oxides	9,000	3.2×10-9	0.478		9.7×10-10	0.143		1.6×10-8	2.344
Sulfur dioxide	1.3×104	2.0×10-11	0.003		6.1×10-12	9.0×10-4		1.0×10-10	0.015
Carbon monoxide	4.0×104	2.9×10-12	4.3×10-4		8.7×10-13	1.3×10-4		1.4×10-11	0.002
Lead	100	3.0×10-12	4.4×10-4		8.9×10-13	1.3×10-4		1.5×10-11	0.002
Acetaldehyde	1.8×105	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Acrylamide	30	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Acrylonitrile	4,420	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Arsenic pentoxide	10	2.9×10-12	4.3×10-4		1.5×10-12	2.2×10-4		6.5×10-12	9.6×10-4
Asbestos	0.2 fibers/m3	6.6×10-14	9.8×10-6		1.6×10-14	2.3×10-6		1.8×10-13	2.6×10-5
Benzene	3,250	7.1×10-11	0.010		3.6×10-11	0.005		1.6×10-10	0.023
Benzidine	N/A	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Bis(chloromethyl)ether	N/A	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Bromoform	5,000	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Carbon tetrachloride	1.2×6104	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Chlordane	500f	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Chloroform	9,780	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Cr(+6) Compounds	50f	2.0×10-14	2.9×10-6		1.0×10-14	1.5×10-6		4.4×10-14	6.5×10-6
Formaldehyde	1,224	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Heptachlor	500	1.5×10-12	2.2×10-4		7.6×10-13	1.1×10-4		2.2×10-12	4.8×10-4
Hexachlorobenzene	N/A	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Hexachlorobutadiene	210f	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Hydrazine	100	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Nickel oxide	1,000	3.3×10-11	0.005		7.9×10-12	0.001		8.9×10-11	0.013
1,1,2,2-Tetrachloroethane	7,000	1.2×10-11	0.002		6.1×10-12	8.9×10-4		2.6×10-11	0.004
1,1,2-Trichloroethane	4.5×104	5.9×10-13	8.7×10-5		3.0×10-13	4.5×10-5		1.3×10-12	1.9×10-4
Toxaphene	500	1.5×10-12	2.2×10-4		7.6×10-13	1.1×10-4		3.2×10-12	4.8×10-4
Alpha vitrification
Total suspended particulates	1.5×104	8.2×10-10	0.12		4.9×10-10	0.07		2.1×10-8	3.06
PM10	5,000	8.2×10-10	0.12		4.9×10-10	0.07		2.1×10-8	3.06
Nitrogen oxides	9,000	1.8×10-9	0.27		1.1×10-9	0.16		4.6×10-8	6.78
Sulfur dioxide	1.3×104	1.1×10-11	0.002		6.8×10-12	0.001		2.9×10-11	0.004
Carbon monoxide	4.0×104	1.6×10-12	2.4×10-4		9.7×10-13	1.44×10-4		4.1×10-11	0.01
Lead	100	1.7×10-12	2.45×10-4		1.0×10-12	1.47×10-4		4.2×10-11	0.01
Asbestos	0.2 fibers/m3	6.6×10-15	9.8×10-7		4.0×10-15	5.9×10-7		1.7×10-13	2.5×10-5
Nickel oxide	1,000	3.3×10-12	4.9×10-4		2.0×10-12	2.93×10-4		8.4×10-10	0.01

a. Source: NIOSH (1990).

b. OSHA PEL - Occupational Safety and Health Administration permissible exposure limits.

c. To convert to feet multiply by 3.281.

d. Particulate matter less than 10 microns in diameter.

e. N/A = not applicable. No OSHA PEL assigned. Exposure should be kept as low as possible.

f. Threshold limit value, time-weighted average (ACGIH 1993).

---

Table E.2-4. Comparison of potential worker exposure to OSHA permissible exposure limits under alternative B (micrograms per cubic meter of air).

---

			Expected forecast receptor locations					Minimum forecast receptor locations			Maximum forecast receptor locations
Pollutant	OSHA PELb		100 metersc		640 meters			100 meters	640 meters		100 meters	640 meters
M-Area Vendor
Nitrogen dioxide		9,000		37.45	43.70			37.45	43.70		37.30	43.52
Sulfur dioxide		1.3×10-4		1.65	1.92			1.65	1.92		1.65	1.92
PM10d		5,000		1.97	2.30			1.97	2.30		1.97	2.30
Bldg. 645-N (hazardous waste storage)
Total suspended particulates		1.5×104		25.13	10.56			13.10	5.51		41.28	17.36
PM10		5,000		8.79	3.70			4.49	1.89		14.54	6.11
Bldg. 645-2N (mixed waste mixed waste storage)
Total suspended particulates		15,000		6.60	2.78			1.78	0.75		32.84	13.81
PM10		5,000		2.32	0.97			0.62	0.26		11.50	4.84
Soil sort facilities
Total suspended particulates		15,000		10.79	4.54			3.39	1.43		64.79	27.24
PM10		5,000		3.77	1.58			1.19	0.50		22.61	9.51
(Four) new solvent tanks
Vinyl chloride		2,600		4.71	3.66			4.28	3.33		4.25	3.31
1,1 Dichloroethane		N/Ae		0.36	0.28			0.32	0.25		0.32	0.25
Methyl ethyl ketone		5.9×105		20.39	15.86			18.56	14.43		18.39	14.30
Chloroform		9,780		2.19	1.70			1.99	1.55		1.98	1.54
Carbon tetrachloride		1.26×104		0.18	0.14			0.16	0.12		0.16	0.12
Benzene		3,250		2.86	2.22			2.60	2.02		2.58	2.00
1,2 Dichloroethane		N/A		0.12	0.09			0.11	0.08		0.11	0.08
Trichloroethane		2.7×105		0.11	0.09			0.10	0.08		0.10	0.08
Tetrachloroethylene		1.7×105		0.02	0.02			0.02	0.02		0.02	0.02
Chlorobenzene		3.5×105		0.02	0.01			0.01	0.01		0.01	0.01
Transuranic waste characterization/ certification facility
Vinyl chloride		2,600		0.02	0.01			0.01	0.009		0.39	0.33
1,1 Dichloroethane		N/A		0.001	9.7×10-4			8.0×10-4	6.9×10-4		0.29	0.25
Methyl ethyl Ketone		5.9×105		0.07	0.06			0.05	0.04		1.69	1.45
Chloroform		9,780		0.007	0.006			0.005	0.004		0.18	0.16
Carbon tetrachloride		1.26×104		5.6×10-4	4.8×10-4			3.9×10-4	3.4×10-4		0.01	0.01
Benzene		3,250		0.009	0.008			0.006	0.006		0.24	0.20
1,2 Dichloroethane		N/A		3.7×10-4	3.2×10-4			2.7×10-4	2.3×10-4		0.010	0.008
Trichloroethane		2.7×105		3.5×10-4	3.1×10-4			2.5×10-4	2.2×10-4		0.009	0.008
Tetrachloroethylene		1.7×105		7.9×10-5	6.8×10-5			5.6×10-5	4.8×10-5		0.002	0.002
Chlorobenzene		3.5×105		5.0×10-5	4.3×10-5			3.5×10-5	3.0×10-5		0.001	0.001
Containment building
Total suspended particulates		1.5×104		2.96	1.80			1.48	0.90		10.26	6.23
PM10		5,000		2.96	1.80			1.48	0.90		10.26	6.23
Vinyl chloride		2,600		0.17	0.10			0.08	0.05		0.74	0.45
1,1 Dichloroethane		N/A		0.01	0.01			0.01	15.25		29.82	0.03
Methyl ethyl Ketone		5.9×105		25.77	15.66			25.10	0.22		3.22	18.12
Chloroform		9,780		0.08	0.05			0.04	0.02		0.34	0.21
Carbon tetrachloride		1.26×104		0.01	0.004			0.003	0.002		0.03	0.02
Benzene		3,250		0.10	0.06			0.05	0.03		0.45	0.27
1,2 Dichloroethane		N/A		0.004	0.003			0.002	0.001		0.02	0.01
Trichloroethane		2.7×105		0.004	0.002			0.002	0.001		0.02	0.01
Tetrachloroethylene		1.7×105		7.8×10-4	4.7×10-4			3.7×10-4	2.2×10-4		3.9×10-3	2.4×10-3
Chlorobenzene		3.5×105		4.9×10-4	3.0×10-4			2.3×10-4	1.4×10-4		2.4×10-3	1.5×10-3

Table E.2-4. (continued).

---

Expected forecast receptor locations

Minimum forecast receptor locations

Maximum forecast receptor locations

Pollutant

OSHA PELb

100 metersc

640 meters

100 meters

640 meters

100 meters

640 meters

Non-alpha vitrification

Total suspended particulates

1.5×104

1.5×10-9

0.23

no vitf

no vit.

7.6×10-9

1.11

PM10

5,000

1.5×10-9

0.23

no vit.

no vit.

7.6×10-9

1.11

Nitrogen oxides

9,000

3.4×10-9

0.50

no vit.

no vit.

1.7×10-8

2.47

Sulfur dioxide

1.3×104

2.1×10-11

0.003

no vit.

no vit.

1.1×10-10

0.02

Carbon monoxide

4.0×104

3.1×10-12

4.5×10-4

no vit.

no vit.

1.5×10-11

0.002

Lead

100

3.1×10-12

4.6×10-4

no vit.

no vit.

1.5×10-11

0.002

Acetaldehyde

1.8×105

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Acrylamide

30

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Acrylonitrile

4,420

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Arsenic pentoxide

10

1.9×10-13

2.8×10-5

no vit.

no vit.

2.5×10-13

3.7×10-5

Asbestos

0.2 fibers/ m3

1.3×10-14

1.9×10-6

no vit.

no vit.

6.1×10-14

9.1×10-6

Benzene

3,250

4.5×10-12

6.7×10-4

no vit.

no vit.

6.0×10-12

8.9×10-4

Benzidine

N/A

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Bis(chloromethyl)ether

N/A

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Bromoform

5,000

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Carbon tetrachloride

1.26×104

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Chlordane

500g

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Chloroform

9,780

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Cr(+6) Compounds

50g

1.3×10-15

1.9×10-7

no vit.

no vit.

1.7×10-15

2.5×10-7

Formadelhyde

1,224

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Heptachlor

500

9.4×10-14

1.4×10-5

no vit.

no vit.

1.3×10-13

1.8×10-5

Hexachlorobenzene

N/A

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Hexachlorobutadiene

210f

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Hydrazine

100

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Nickel oxide

1,000

6.3×10-12

9.3×10-4

no vit.

no vit.

3.1×10-11

4.5×10-3

1,1,2,2-Tetrachloroethane

7,000

7.5×10-13

1.1×10-4

no vit.

no vit.

1.0×10-12

1.5×10-3

1,1,2-Trichloroethane

4.5×104

3.8×10-14

5.6×10-6

no vit.

no vit.

5.0×10-14

7.4×10-6

Toxaphene

500

9.4×10-14

1.4×10-5

no vit.

no vit.

1.3×10-13

1.8×10-5

Alpha vitrification

Total suspended particulates

1.5×104

3.3×10-10

0.05

3.3×10-10

0.05

1.2×10-8

1.78

PM10

5,000

3.3×10-10

0.05

3.3×10-10

0.05

1.2×10-8

1.78

Nitrogen oxides

9,000

7.2×10-10

0.11

7.2×10-10

0.11

2.7×10-8

3.97

Sulfur dioxide

1.3×104

4.5×10-12

6.7×10-4

4.5×10-12

6.1×10-4

1.7×10-10

0.02

Carbon monoxide

4.0×104

6.5×10-13

9.6×10-5

6.5×10-13

9.6×10-5

2.4×10-11

0.004

Lead

100

6.6×10-13

9.8×10-5

6.6×10-13

9.8×10-5

2.5×10-11

0.004

Asbestos

0.2 fibers/ m3

2.7×10-15

3.9×10-7

2.7×10-15

3.9×10-7

9.8×10-14

1.4×10-5

Nickel oxide

1,000

1.3×10-12

2.0×10-4

1.3×10-12

2.0×10-4

4.9×10-11

0.007

a. Source: NIOSH (1990).

b. OSHA PEL - Occupational Safety and Health Administration Permissible Exposure Limits.

c. To convert to feet multiply by 3.281.

d. Particulate matter less than 10 microns in diameter.

e. N/A = Not Applicable. No OSHA PEL assigned. Exposure should be kept as low as possible.

f. no vit. = no non-alpha vitrification occurring.

g. Threshold limit value, time-weighted average (ACGIH 1993).

---

Table E.2-5. Maximum SRS boundary-line concentrations of carcinogens without risk factors (micrograms per cubic meter).

---

Alternative A

Alternative B

Alternative C

Expected

Minimum

Maximum

Expected

Minimum

Maximum

Expected

Minimum

Maximum

Lead

1.0E-05

1.0E-05

1.0E-05

3.0E-05

3.0E-05

6.0E-05

2.5E-05

1.9E-05

6.6E-05

Dioxane

1.6E-07

9.9E-08

1.2E-07

1.4E-07

6.8E-08

1.2E-07

4.6E-07

2.4E-07

1.0E-06

Ethylene dibromide

4.1E-07

2.5E-07

3.1E-07

3.5E-07

1.7E-07

3.0E-07

1.1E-06

5.9E-07

2.5E-06

Ethylene dichloride

4.1E-07

2.5E-07

3.1E-07

3.5E-07

1.7E-07

3.0E-07

1.1E-06

5.9E-07

2.5E-06

Parathion

4.1E-07

2.5E-07

3.1E-07

3.5E-07

1.7E-07

3.0E-07

1.1E-06

5.9E-07

2.5E-06

Aniline

1.6E-07

9.9E-08

1.2E-07

1.4E-07

6.8E-08

1.2E-07

4.6E-07

2.4E-07

1.0E-06

Cresols

1.6E-07

9.9E-08

1.2E-07

1.4E-07

6.8E-08

1.2E-07

4.6E-07

2.4E-07

1.0E-06

Chloromethyl methyl Ether

1.45E-07

2.41E-08

8.77E-08

1.4E-07

6.8E-08

1.2E-07

4.6E-07

2.4E-07

1.0E-06

3, 3-Dichlorobenzidene

1.6E-07

9.9E-08

1.2E-07

1.4E-07

6.8E-08

1.2E-07

4.6E-07

2.4E-07

1.0E-06

1, 2-Diphenylhydrazine

1.6E-07

9.9E-08

1.2E-07

1.4E-07

6.8E-08

1.2E-07

4.6E-07

2.4E-07

1.0E-06

2, 4-Dinitrotoluene

1.6E-07

9.9E-08

1.2E-07

1.4E-07

6.8E-08

1.2E-07

4.6E-07

2.4E-07

1.0E-06

Methyl iodide

1.45E-07

2.41E-08

8.77E-08

1.4E-07

6.8E-08

1.2E-07

4.6E-07

2.4E-07

1.0E-06

Pentachlorophenol

1.6E-07

9.9E-08

1.2E-07

1.4E-07

6.8E-08

1.2E-07

4.6E-07

2.4E-07

1.0E-06

Benzyl chloride

1.0E-04

1.0E-04

1.0E-04

8.0E-08

4.1E-08

4.4E-07

4.6E-07

2.4E-07

1.0E-06

a. Source: EPA (1994).

b. Integrated Risk Information System (IRIS) contains EPA health risk information for Class A, B, and C (suspected, probable, and possible) carcinogens.

---

SECTION 3

TRAFFIC AND TRANSPORTATION

Table E.3-1. Hazardous waste shipments during 30-year period of interest.

---

			Waste forecast				Alternative A					Alternative B					Alternative C
Waste	Shipping container	Containers per truck	Min. volume (m3)a	Exp.b volume (m3)	Max. volume (m3)		Min. shipments		Exp. shipments	Max. shipments		Min. shipments		Exp. shipments	Max. shipments		Min. shipments	Exp. shipments	Max. shipments
ONSITE SHIPMENTSc
Inorganic debris	90 cu. ft. box	6	4,280	8,283	11,489		280		541	751		280		541	751		280	541	751
Soils	45 cu. ft. box	10	146,784	282,935	465,392		11,468		22,106	36,361		11,468		22,106	36,361		11,468	22,106	36,361
Filters	45 cu. ft. box	1	2,267	4,285	6,495		17,71		3,348	5,074		1,771		3,348	5,074		1,771	3,348	5,074
Aqueous liquids	3000 gal. truck	1	8,206	35,943	38,345		714		3,142	3,376		714		3,142	3,376		714	3,142	3,376
Organic debris	90 cu. ft. box	1	28	28	28		11		11	11		11		11	11		11	11	11
Organic sludge	55 gal. drum	1	2,327	4,545	6,867		11,635		22,725	34,335		11,635		22,725	34,335		11,635	22,725	34,335
Heterogeneous debris	90 cu. ft. box	2	6,188	11,690	15,642		1,213		2,292	3,067		1,213		2,292	3,067		1,213	2,292	3,067
Lead	22.5 cu. ft. box	1	2,764	5,266	7,725		4,339		8,267	12,127		4,339		8,267	12,127		4,339	8,267	12,127
Organic liquids	3000 gal. truck	1	2,238	4,523	6,495		197		398	572		197		398	572		197	398	572
CIF ashcreted	55 gal. drum	48	(e)	(e)	(e)		72		132	198		72		132	198		55	66	73
Bulk	Bulk box	1	3,389	6,642	9,474		62		122	174		62		122	174		62	122	174
Inorganic sludge	55 gal. drum	30	2,327	4,545	6,867		388		758	1,145		388		758	1,145		388	758	1,145
Metal debris	90 cu. ft. box	4	7,800	14,220	20,974		765		1,394	2,056		765		1,394	2,056		765	1,394	2,056
Sand/rock/gravel	45 cu. ft. box	6	19,698	38,060	62,091		2,565		4,956	8,085		2,565		4,956	8,085		2,565	4,956	8,085
Paint waste	55 gal. drum	4	2,294	4,062	6,122		2,868		5,078	7,653		2,868		5,078	7,653		2,868	5,078	7,653
Glass debris	55 gal. drum	60	4,297	7,999	12,245		358		667	1,020		358		667	1,020		358	667	1,020
PCBs	55 gal. drum	1	2,437	2,437	2,280		12,185		12,185	11,400		12,185		12,185	11,400		12,185	12,185	11,400
OFFSITE SHIPMENTSf
Various typesg	40 foot van	25 m3	(h)	(h)	(h)		8,093		14,745	24,843		7,713		14,725	23,780		6,558	7,944	9,233
Average daily shipmentsi				(No-Action)
Hazardous waste				14				8	14	20	8		14			20	8	13		18

Source: Rollins (1995).

a. Cubic meters.

b. Expected waste volume is assumed to be the same as for the no-action alternative.

c. Onsite shipments average 8 kilometers (5 miles) each.

d. CIF = Consolidated Incineration Facility. Volumes from the Consolidated Incineration Facility vary depending on alternative. Source: Hess (1994a, b, c, and d).

e. Ashcrete volume varies depending on alternative (Ashcrete is not a hazardous waste).

f. Offsite shipments average 1,609 kilometers (1,000 miles) each.

g. Offsite shipments of hazardous waste types vary depending on alternative.

h. Hazardous waste volume varies depending on alternatives.

i. Daily shipments are estimated by totaling all shipments for each alternative/forecast and dividing this sum by 30 years and 250 working days per year.

---

Table E.3-2. Low-level and transuranic (TRU) waste shipments during the 30-year period of interest.

---

			Waste forecast					Alternative A						Alternative B						Alternative C
Waste	Shipping container	Containers per truck	Min. volume (m3)a	Exp.b volume (m3)		Max. volume (m3)		Min. shipments		Exp. shipments		Max. shipments		Min. shipments		Exp. shipments		Max. shipments		Min. shipments		Exp. shipments		Max. shipments
ONSITE SHIPMENTSc
Tritiated equipment	90 cu. ft. box	10	461	1,184		1,622		18		46		64		18		46		64		18		46		64
Spent deionizers	Liner	1	30	30		30		11		11		11		11		11		11		11		11		11
LLW job-controld	90 cu. ft. box	6	309,115	366,285		413,812		21,375		25,112		28,218		20,204		23,940		27,047		20,204		23,940		27,047
Offsite job-control	90 cu. ft. box	10	12,600	12,600		25,200		494		494		988		494		494		988		494		494		988
LLW equipment	90 cu. ft. box	6	(e)	(e)		(e)		2,220		4,543		15,386		1,707		3,319		10,525		1,177		2,089		5,471
ILW job-controlf	90 cu. ft. box	2	12,477	22,335		28,111		2,446		4,449		5,512		2,446		4,449		5,512		2,446		4,449		5,512
Long-lived waste	55 gal. drum	1	1,003	3,302		4,643		5,015		16,510		23,215		5,015		16,510		23,215		5,015		16,510		23,215
Tritiated job-control	90 cu. ft. box	10	1,558	3,860		133,994		61		151		5,255		61		151		5,255		61		151		5,255
Low-level soils	45 cu. ft. box	10	8,068	19,791		311,923		630		1,548		24,371		630		1,548		24,371		630		1,548		24,371
Suspect soils	45 cu. ft. box	10	12,102	29,669		467,884		946		2,318		36,556		946		2,318		36,556		946		2,318		36,556
Tritiated soils	45 cu. ft. box	10	575	1,532		2,492		45		119		195		45		119		195		45		119		195
CIF ashcreteg	55 gal. drum	48	(h)	(h)		(h)		0		0		0		1,922		1,527		3,471		737		947		1,033
TRU wastei 10­100 nCij	55 gal. drum	15	3,164	4,400		252,919		1,055		1,467		84,298		1,055		1,467		84,298		1,055		1,467		84,298
TRU wastei>100 nCi, <0.5 Cik	55 gal. drum	15	2,165	3,112		51,295		722		1,036		17,097		722		1,036		17,097		722		1,036		17,097
TRU wastei>0.5 Cil	55 gal. drum	15	2,228	3,202		52,780		742		1,066		17,591		742		1,066		17,591		742		1,066		17,591
TRU wastei bulk	Bulk box	1	8,146	11,707		192,989		150		215		3,547		150		215		3,547		150		215		3,547
TRU wastei remote	Bulk box	1	146	209		3,449		3		4		63		3		4		63		3		4		63
OFFSITE SHIPMENTSm
Offsite smelter	Railroad Car	NA	(n)	(n)		(n)		0		0		0		54		762		332		37		479		173
LLW offsiteo	40 ft van	25m3	(p)	(p)		(p)		0		0		0		18,540		30,525		77,815		0		0		0
Average daily shipmentsq				(No-Action)
Transuranic waste				1			<1		1		16		<1		1		16		<1		1		16
Low-level waste				7			4		7		19		6		9		20		4		7		17

Source: Rollins (1995).

a. Cubic meters.

b. Expected waste volume is assumed to be the same as for the no-action alternative.

c. Onsite shipments average 8 kilometers (5 miles) each.

d. LLW = low-level waste.

e. Volumes of low-level equipment vary with alternative.

f. ILW = intermediate-level waste.

g. CIF = Consolidated Incineration Facility.

h. Volumes from the Consolidated Incineration Facility vary depending on alternative. Source: Hess (1994a, b, c, and d).

i. TRU = transuranic.

j. Includes mixed and nonmixed transuranic waste at 10-100 nanocuries per drum.

k. Includes mixed and nonmixed transuranic waste between 100 nanocuries and 0.5 curies per drum.

l. Includes mixed and nonmixed transuranic waste greater than 0.5 curies per drum.

m. Offsite shipments average 541 kilometers (336 miles) each.

n. Volumes to Offsite Smelter Facility vary with alternative.

o. Includes return shipments of processed waste.

p. Offsite low-level waste shipments vary by alternative.

q. Daily shipments are estimated by totaling all shipments for each alternative/forecast and dividing this sum by 30 years and 250 working days per year.

---

Table E.3-3. Mixed waste shipments during the 30-year period of interest.

---

				Waste forecast					Alternative A							Alternative B						Alternative C
Waste	Shipping container	Containers per truck		Min. volume (m3)a	Exp.b volume (m3)		Max. volume (m3)		Min. shipments		Exp. shipments		Max. shipments			Min. shipments		Exp. shipments		Max. shipments		Min. shipments			Exp. shipments		Max. shipments
ONSITE SHIPMENTSc
Inorganic debris	90 cu. ft. box	6		6,240	15,170		23,516		408		992		1,537			408		992		1537		408			992		1,537
Waste filters	45 cu. ft. box	1		1,256	2,851		3,858		981		2,227		3,014			981		2,236		3,014		981			2,227		3,014
Aqueous liquids	3000 gal. truck	1		8,957	32,862		51,026		788		2,893		4,492			788		2,893		4,492		788			2,893		4,492
Organic debris	90 cu. ft. box	1		242	241		27,769		95		95		10,890			95		95		10,890		95			95		10,890
Organic sludge	55 gal. drum	1		1,335	3,672		5,113		6,675		18,360		25,565			6,675		18,360		25,565		6,675			18,360		25,565
Heterogenous debris	90 cu. ft. box	2		10,594	25,699		126,967		2,077		5,039		24,896			2,077		5,039		24,896		2,077			5,039		24,896
Gold traps	55 gal. drum	1		3	3		3		14		14		14			14		14		14		14			14		14
M-Area glass	71 gal. drum	3		2,058	2,058		2,058		2,618		2,618		2,618			2,618		2,618		2,618		2,618			2,618		2,618
Lead	22.5 cu. ft. box	1		1,280	5,956		7,677		2,009		4,675		12,052			2,009		4,675		12,052		2,009			4,675		12,052
PUREX solvents	3000 gal. truck	1		345	345		345		30		30		30			30		30		30		30			30		30
Organic liquids	3000 gal. truck	1		1,149	2,879		7,873		101		253		693			101		253		693		101			253		693
CIF ashcreted	55 gal. drum	48		(e)	(e)		(e)		4,941		13,301		82,407			4,897		445		1,331		62			109		849
Bulk	Bulk box	1		4,202	10,358		32,295		77		190		594			77		190		594		77			190		594
Inorganic sludge	55 gal. drum	30		1,299	3,636		5,046		217		606		841			217		606		841		217			606		841
Metal debris	90 cu. ft. box	4		6,768	12,897		53,719		664		1,264		5,267			664		1,264		5,267		664			1,264		5,267
Soils/sand/rock/gravel	45 cu. ft. box	6		22,186	88,329		440,062		2,889		11,501		57,300			2,889		11,501		57,300		2,889			11,501		57,300
Paint waste	55 gal. drum	4		1,468	2,133		2,598		1,835		2,666		3,248			1,835		2,666		3,248		1,835			2,666		3,248
Glass debris	55 gal. drum	60		1,652	2,997		7,558		138		250		630			138		250		630		138			250		630
OFFSITE SHIPMENTSf
Lead	22.5 cu. ft. box	1		(g)	(g)		(g)		2,115		4,802		12,237			2,115		4,802		12,237		2,112			4,799		12,234
Average daily shipmentsh						(No-Action)
Mixed waste						8		4		10		33			4		8		22		3			8		22

Source: Rollins (1995).

a. Cubic meters.

b. Expected waste volume is assumed to be the same as for the no-action alternative.

c. Onsite shipments average 8 kilometers (5 miles) each.

d. CIF = Consolidated Incineration Facility.

e. Volumes from the Consolidated Incineration Facility vary depending on alternative. Source: Hess (1994a, b, c, and d).

f. Offsite shipments average 541 kilometers (336 miles) each.

g. Volumes to offsite treatment facilities vary with alternative.

h. Daily shipments are estimated by totaling all shipments for each alternative and forecast and dividing this sum by 30 years and 250 working days per year.

---

Table E.3-4. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste under the no-action alternative.

---

	Dose from incident-free transportation
Waste stream	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	2.37E-11	2.10E-06	4.56E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	9.27E-05	7.28E+00	1.80E-01
4. Offsite job-control	2.03E-06	2.47E-01	3.94E-03
5. Low-activity equip.	2.39E-06	3.24E+01	4.64E-03
6. Inter.-level job-control	9.23E-03	7.52E+01	1.04E+00
7. Long-lived	1.83E-03	3.10E+01	7.43E-01
8. Tritiated job-control	3.08E-08	2.30E-03	5.95E-05
9. Low-level waste soils	1.26E-07	1.33E-02	2.43E-04
10. Suspect soils	1.90E-07	1.96E-02	3.68E-04
11. Tritiated soils	9.72E-08	1.03E-02	1.88E-04
12. MW inorganic debris	9.06E-06	6.82E-01	1.76E-02
13. Mixed waste soil	1.08E-05	1.14E+00	2.09E-02
14. MW comp. filters	1.51E-06	1.36E-01	2.92E-03
15a. 0.01 Ci/m3 TRU wastec,d	1.07E-10	3.92E-06	2.07E-07
15b. 1.5 Ci/m3 TRU waste	1.18E-08	4.14E-04	2.29E-05
15c. 208 Ci/m3 TRU waste	1.61E-06	5.91E-02	3.11E-03
15d. Bulk eq. TRU waste	9.23E-09	2.46E-04	1.79E-05
15e. Bulk eq. Rmt. TRUe	1.28E-04	8.58E-02	6.32E-03
16. MW aqueous liquids	8.37E-06	4.24E-03	1.37E-02
17. MW organic debris	1.28E-07	1.11E-02	3.33E-04
18. Organic sludge	1.19E-06	1.20E-01	3.07E-03
19. Heterogeneous debris	9.07E-06	1.37E+00	2.35E-02
19a. Lead	6.33E-08	1.02E-02	1.64E-04
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	2.29E-06	1.15E-03	3.75E-03
22. Ashcreteg	0.00E+00	0.00E+00	0.00E+00
23. Bulk waste	2.80E-06	8.00E-02	7.28E-03
24. Inorganic sludge	2.24E-06	1.08E-01	5.82E-03
25. Metal debris	2.58E-06	2.73E-01	6.70E-03
26. Sand/rock/gravel	1.80E-06	1.94E-01	4.66E-03
27. Paint waste	2.87E-07	6.13E-02	7.44E-04
28. Glass debris	3.18E-06	1.18E-01	8.25E-03
Totals:h
Low-level	1.1E-02	1.5E+02	2.0E+00
Mixed	5.5E-05	4.3E+00	1.2E-01
Transuranic	1.3E-04	1.5E-01	9.5E-03

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction.

g. Consolidated Incineration Facility does not operate under the no-action alternative so there would be no ashcrete.

h. For incident-free dose, the sum of waste streams 1 through 11 are used to calculate the corresponding dose of low level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitute the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-5. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste for alternative A - expected waste forecast.

---

	Dose from incident-free transportation
Waste stream	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	2.37E-11	2.10E-06	4.56E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	9.27E-05	7.28E+00	1.80E-01
4. Offsite job-control	2.03E-06	2.47E-01	3.94E-03
5. Low-activity equip.	1.25E-05	1.69E+02	2.42E-02
6. Inter.-level job-control	9.23E-03	7.52E+01	1.04E+00
7. Long-lived	1.83E-03	3.10E+01	7.43E-01
8. Tritiated job-control	3.08E-08	2.30E-03	5.95E-05
9. Low-level waste soils	1.26E-07	1.33E-02	2.43E-04
10. Suspect soils	1.90E-07	1.96E-02	3.68E-04
11. Tritiated soils	9.72E-08	1.03E-02	1.88E-04
12. MW inorganic debrisb	9.06E-06	6.82E-01	1.76E-02
13. Mixed waste soil	1.08E-05	1.14E+00	2.09E-02
14. MW comp. filters	1.51E-06	1.36E-01	2.92E-03
15a. 0.01 Ci/m3 TRU wastec,d	1.07E-10	3.92E-06	2.07E-07
15b. 1.5 Ci/m3 TRU waste	1.18E-08	4.14E-04	2.29E-05
15c. 208 Ci/m3 TRU waste	1.61E-06	5.91E-02	3.11E-03
15d. Bulk eq. TRU waste	9.23E-09	2.46E-04	1.79E-05
15e. Bulk eq. Rmt. TRUe	1.28E-04	8.58E-02	6.32E-03
16. MW aqueous liquids	8.37E-06	4.24E-03	1.37E-02
17. MW organic debris	1.28E-07	1.11E-02	3.33E-04
18. Organic sludge	1.19E-06	1.20E-01	3.07E-03
19. Heterogeneous debris	9.07E-06	1.37E+00	2.35E-02
19a. Lead	3.16E-08	5.11E-03	8.20E-05
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	2.29E-06	1.15E-03	3.75E-03
22. Ashcrete	4.1E-05	1.4E+00	7.9E-02
23. Bulk waste	2.80E-06	8.00E-02	7.28E-03
24. Inorganic sludge	2.24E-06	1.08E-01	5.82E-03
25. Metal debris	2.58E-06	2.73E-01	6.70E-03
26. Sand/rock/gravel	1.80E-06	1.94E-01	4.67E-03
27. Paint waste	2.87E-07	6.13E-02	7.44E-04
28. Glass debris	3.18E-06	1.18E-01	8.25E-03
Totals:g
Low-level	1.1E-02	2.8E+02	2.0E+00
Mixed	8.4E-05	5.3E+00	1.7E-01
Transuranic	1.3E-04	1.5E-01	9.5E-03

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction..

g. For incident-free dose, the sum of waste streams 1 through 12 are used to calculate the corresponding dose of low-level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitutes the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-6. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste for alternative A - minimum waste forecast.

---

	Dose from incident-free transportation
Waste	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	9.21E-12	8.19E-07	1.78E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	7.82E-05	6.14E+00	1.52E-01
4. Offsite job-control	2.03E-06	2.47E-01	3.94E-03
5. Low-activity equip.	6.10E-06	8.28E+01	1.18E-02
6. Inter.-level job-control	5.07E-03	4.14E+01	5.72E-01
7. Long-lived	5.56E-04	9.41E+00	2.26E-01
8. Tritiated job-control	1.25E-08	9.29E-04	2.40E-05
9. Low-level waste soils	5.11E-08	5.43E-03	9.91E-05
10. Suspect soils	7.75E-08	7.98E-03	1.50E-04
11. Tritiated soils	3.66E-08	3.89E-03	7.09E-05
12. MW inorganic debrisb	3.73E-06	2.81E-01	7.22E-03
13. Mixed waste soil	2.71E-06	2.87E-01	5.25E-03
14. MW comp. filters	6.64E-07	6.01E-02	1.29E-03
15a. 0.01 Ci/m3 TRU wastec,d	7.70E-11	2.81E-06	1.49E-07
15b. 1.5 Ci/m3 TRU waste	8.25E-09	2.88E-04	1.60E-05
15c. 208 Ci/m3 TRU waste	1.12E-06	4.12E-02	2.17E-03
15d. Bulk eq. TRU waste	6.43E-09	1.71E-04	1.24E-05
15e. Bulk eq. Rmt. TRUe	8.91E-05	5.97E-02	4.40E-03
16. MW aqueous liquids	2.25E-06	1.14E-03	3.69E-03
17. MW organic debris	1.28E-07	1.11E-02	3.33E-04
18. Organic sludge	4.32E-07	4.37E-02	1.12E-03
19. Heterogeneous debris	3.74E-06	5.65E-01	9.69E-03
19a. Lead	1.36E-08	2.20E-03	3.52E-05
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	1.82E-06	9.18E-04	2.98E-03
22. Ashcrete	1.5E-05	5.9E-01	3.0E-02
23. Bulk waste	1.14E-06	3.25E-02	2.95E-03
24. Inorganic sludge	8.01E-07	3.86E-02	2.08E-03
25. Metal debris	1.35E-06	1.44E-01	3.52E-03
26. Sand/rock/gravel	4.53E-07	4.87E-02	1.17E-03
27. Paint waste	1.98E-07	4.22E-02	5.12E-04
28. Glass debris	1.75E-06	6.51E-02	4.55E-03
Totals:g
Low-level	5.7E-03	1.4E+02	9.8E-01
Mixed	3.2E-05	2.0E+00	6.7E-02
Transuranic	9.0E-05	1.0E-01	6.6E-03

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction..

g. For incident-free dose, the sum of waste streams 1 through 12 are used to calculate the corresponding dose of low-level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitutes the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-7. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste for alternativeA - maximum waste forecast.

---

	Dose from incident-free transportation
Waste stream	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	3.24E-11	2.88E-06	6.25E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	1.05E-04	8.22E+00	2.03E-01
4. Offsite job-control	4.06E-06	4.95E-01	7.88E-03
5. Low-activity equip.	4.23E-05	5.74E+02	8.21E-02
6. Inter.-level job-control	1.14E-02	9.32E+01	1.29E+00
7. Long-lived	2.58E-03	4.36E+01	1.04E+00
8. Tritiated job-control	1.07E-06	7.99E-02	2.07E-03
9. Low-level waste soils	1.98E-06	2.10E-01	3.83E-03
10. Suspect soils	3.00E-06	3.09E-01	5.81E-03
11. Tritiated soils	1.59E-07	1.68E-02	3.07E-04
12. MW inorganic debrisb	1.40E-05	1.06E+00	2.72E-02
13. Mixed waste soil	5.37E-05	5.70E+00	1.04E-01
14. MW comp. filters	2.04E-06	1.85E-01	3.95E-03
15a. 0.01 Ci/m3 TRU wastec,d	6.15E-09	2.25E-04	1.19E-05
15b. 1.5 Ci/m3 TRU waste	1.95E-07	6.83E-03	3.78E-04
15c. 208 Ci/m3 TRU waste	2.66E-05	9.75E-01	5.13E-02
15d. Bulk eq. TRU waste	1.52E-07	4.06E-03	2.95E-04
15e. Bulk eq. Rmt. TRUe	2.11E-03	1.42E+00	1.04E-01
16. MW aqueous liquids	1.30E-05	6.60E-03	2.13E-02
17. MW organic debris	1.47E-05	1.27E+00	3.82E-02
18. Organic sludge	1.65E-06	1.68E-01	4.28E-03
19. Heterogeneous debris	4.48E-05	6.77E+00	1.16E-01
19a. Lead	8.16E-08	1.32E-02	2.11E-04
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	3.64E-06	1.84E-03	5.96E-03
22. Ashcrete	2.0E-04	7.8E+00	3.9E-01
23. Bulk waste	8.73E-06	2.50E-01	2.27E-02
24. Inorganic sludge	3.11E-06	1.50E-01	8.07E-03
25. Metal debris	1.07E-05	1.14E+00	2.79E-02
26. Sand/rock/gravel	8.98E-06	9.65E-01	2.32E-02
27. Paint waste	3.50E-07	7.47E-02	9.06E-04
28. Glass debris	8.03E-06	2.98E-01	2.08E-02
Totals:g
Low-level	1.4E-02	7.2E+02	2.8E+00
Mixed	3.3E-04	2.4E+01	7.0E-01
Transuranic	2.1E-03	2.4E+00	1.6E-01

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction.

g. For incident-free dose, the sum of waste streams 1 through 12 are used to calculate the corresponding dose of low-level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitutes the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-8. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste for alternative B - expected waste forecast.

---

	Dose from incident-free transportation
Waste stream	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	2.37E-11	2.10E-06	4.56E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	9.27E-05	7.28E+00	1.80E-01
4. Offsite job-control	2.03E-06	2.47E-01	3.94E-03
5. Low-activity equip.	9.12E-06	1.24E+02	1.77E-02
6. Inter.-level job-control	9.23E-03	7.52E+01	1.04E+00
7. Long-lived	1.83E-03	3.10E+01	7.43E-01
8. Tritiated job-control	3.08E-08	2.30E-03	5.95E-05
9. Low-level waste soils	1.26E-07	1.33E-02	2.43E-04
10. Suspect soils	1.90E-07	1.96E-02	3.68E-04
11. Tritiated soils	9.72E-08	1.03E-02	1.88E-04
12. MW inorganic debrisb	9.06E-06	6.82E-01	1.76E-02
13. Mixed waste soil	1.08E-05	1.14E+00	2.09E-02
14. MW comp. filters	1.51E-06	1.36E-01	2.92E-03
15a. 0.01 Ci/m3 TRU wastec,d	1.07E-10	3.92E-06	2.07E-07
15b. 1.5 Ci/m3 TRU waste	1.18E-08	4.14E-04	2.29E-05
15c. 208 Ci/m3 TRU waste	1.61E-06	5.91E-02	3.11E-03
15d. Bulk eq. TRU waste	9.23E-09	2.46E-04	1.79E-05
15e. Bulk eq. Rmt. TRUe	1.28E-04	8.58E-02	6.32E-03
16. MW aqueous liquids	8.37E-06	4.24E-03	1.37E-02
17. MW organic debris	1.28E-07	1.11E-02	3.33E-04
18. Organic sludge	1.19E-06	1.20E-01	3.07E-03
19. Heterogeneous debris	9.07E-06	1.37E+00	2.35E-02
19a. Lead	3.16E-08	5.11E-03	8.20E-05
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	2.29E-06	1.15E-03	3.75E-03
22. Ashcrete	5.5E-05	2.1E+00	1.1E-01
23. Bulk waste	2.80E-06	8.00E-02	7.28E-03
24. Inorganic sludge	2.24E-06	1.08E-01	5.82E-03
25. Metal debris	2.58E-06	2.73E-01	6.70E-03
26. Sand/rock/gravel	1.80E-06	1.94E-01	4.67E-03
27. Paint waste	2.87E-07	6.13E-02	7.44E-04
28. Glass debris	3.18E-06	1.18E-01	8.25E-03
Totals:g
Low-level	1.1E-02	2.4E+02	2.1E+00
Mixed	6.7E-05	4.8E+00	1.4E-01
Transuranic	1.3E-04	1.5E-01	9.5E-03

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction.

g. For incident-free dose, the sum of waste streams 1 through 12 are used to calculate the corresponding dose of low-level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitutes the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-9. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste for alternative B - minimum waste forecast.

---

	Dose from incident-free transportation
Waste stream	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	9.21E-12	8.19E-07	1.78E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	7.82E-05	6.14E+00	1.52E-01
4. Offsite job-control	2.03E-06	2.47E-01	3.94E-03
5. Low-activity equip.	4.69E-06	6.37E+01	9.10E-03
6. Inter.-level job-control	5.07E-03	4.14E+01	5.72E-01
7. Long-lived	5.56E-04	9.41E+00	2.26E-01
8. Tritiated job-control	1.25E-08	9.29E-04	2.40E-05
9. Low-level waste soils	5.11E-08	5.43E-03	9.91E-05
10. Suspect soils	7.75E-08	7.98E-03	1.50E-04
11. Tritiated soils	3.66E-08	3.89E-03	7.09E-05
12. MW inorganic debrisb	3.73E-06	2.81E-01	7.22E-03
13. Mixed waste soil	2.71E-06	2.87E-01	5.25E-03
14. MW comp. filters	6.64E-07	6.01E-02	1.29E-03
15a. 0.01 Ci/m3 TRU wastec,d	7.70E-11	2.81E-06	1.49E-07
15b. 1.5 Ci/m3 TRU waste	8.25E-09	2.88E-04	1.60E-05
15c. 208 Ci/m3 TRU waste	1.12E-06	4.12E-02	2.17E-03
15d. Bulk eq. TRU waste	6.43E-09	1.71E-04	1.24E-05
15e. Bulk eq. Rmt. TRUe	8.91E-05	5.97E-02	4.40E-03
16. MW aqueous liquids	2.25E-06	1.14E-03	3.69E-03
17. MW organic debris	1.28E-07	1.11E-02	3.33E-04
18. Organic sludge	4.32E-07	4.37E-02	1.12E-03
19. Heterogeneous debris	3.74E-06	5.65E-01	9.69E-03
19a. Lead	1.36E-08	2.20E-03	3.52E-05
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	1.82E-06	9.18E-04	2.98E-03
22. Ashcrete	4.4E-05	1.7E+00	8.6E-02
23. Bulk waste	1.14E-06	3.25E-02	2.95E-03
24. Inorganic sludge	8.01E-07	3.86E-02	2.08E-03
25. Metal debris	1.35E-06	1.44E-01	3.52E-03
26. Sand/rock/gravel	4.53E-07	4.87E-02	1.17E-03
27. Paint waste	1.98E-07	4.22E-02	5.12E-04
28. Glass debris	1.75E-06	6.51E-02	4.55E-03
Totals:g
Low-level	5.7E-03	1.2E+02	1.0E+00
Mixed	4.4E-05	2.5E+00	9.1E-02
Transuranic	9.0E-05	1.0E-01	6.6E-03

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction..

g. For incident-free dose, the sum of waste streams 1 through 12 are used to calculate the corresponding dose of low-level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitutes the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-10. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste for alternative B - maximum waste forecast.

---

	Dose from incident-free transportation
Waste stream	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	3.24E-11	2.88E-06	6.25E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	1.05E-04	8.22E+00	2.03E-01
4. Offsite job-control	4.06E-06	4.95E-01	7.88E-03
5. Low-activity equip.	2.89E-05	3.93E+02	5.61E-02
6. Inter.-level job-control	1.14E-02	9.32E+01	1.29E+00
7. Long-lived	2.58E-03	4.36E+01	1.04E+00
8. Tritiated job-control	1.07E-06	7.99E-02	2.07E-03
9. Low-level waste soils	1.98E-06	2.10E-01	3.83E-03
10. Suspect soils	3.00E-06	3.09E-01	5.81E-03
11. Tritiated soils	1.59E-07	1.68E-02	3.07E-04
12. MW inorganic debrisb	1.40E-05	1.06E+00	2.72E-02
13. Mixed waste soil	5.37E-05	5.70E+00	1.04E-01
14. MW comp. filters	2.04E-06	1.85E-01	3.95E-03
15a. 0.01 Ci/m3 TRU wastec,d	6.15E-09	2.25E-04	1.19E-05
15b. 1.5 Ci/m3 TRU waste	1.95E-07	6.83E-03	3.78E-04
15c. 208 Ci/m3 TRU waste	2.66E-05	9.75E-01	5.13E-02
15d. Bulk eq. TRU waste	1.52E-07	4.06E-03	2.95E-04
15e. Bulk eq. Rmt. TRUe	2.11E-03	1.42E+00	1.04E-01
16. MW aqueous liquids	1.30E-05	6.60E-03	2.13E-02
17. MW organic debris	1.47E-05	1.27E+00	3.82E-02
18. Organic sludge	1.65E-06	1.68E-01	4.28E-03
19. Heterogeneous debris	4.48E-05	6.77E+00	1.16E-01
19a. Lead	8.16E-08	1.32E-02	2.11E-04
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	3.64E-06	1.84E-03	5.96E-03
22. Ashcrete	7.6E-05	3.0E+00	1.5E-01
23. Bulk waste	8.73E-06	2.50E-01	2.27E-02
24. Inorganic sludge	3.11E-06	1.50E-01	8.07E-03
25. Metal debris	1.07E-05	1.14E+00	2.79E-02
26. Sand/rock/gravel	8.98E-06	9.65E-01	2.32E-02
27. Paint waste	3.50E-07	7.47E-02	9.06E-04
28. Glass debris	8.03E-06	2.98E-01	2.08E-02
Totals:g
Low-level	1.4E-02	5.4E+02	2.7E+00
Mixed	2.1E-04	1.9E+01	4.7E-01
Transuranic	2.1E-03	2.4E+00	1.6E-01

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction..

g. For incident-free dose, the sum of waste streams 1 through 12 are used to calculate the corresponding dose of low-level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitutes the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-11. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste for alternative C - expected waste forecast.

---

	Dose from incident-free transportation
Waste stream	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	2.37E-11	2.10E-06	4.56E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	9.27E-05	7.28E+00	1.80E-01
4. Offsite job-control	2.03E-06	2.47E-01	3.94E-03
5. Low-activity equip.	5.74E-06	7.80E+01	1.11E-02
6. Inter.-level job-control	9.23E-03	7.52E+01	1.04E+00
7. Long-lived	1.83E-03	3.10E+01	7.43E-01
8. Tritiated job-control	3.08E-08	2.30E-03	5.95E-05
9. Low-level waste soils	1.26E-07	1.33E-02	2.43E-04
10. Suspect soils	1.90E-07	1.96E-02	3.68E-04
11. Tritiated soils	9.72E-08	1.03E-02	1.88E-04
12. MW inorganic debrisb	9.06E-06	6.82E-01	1.76E-02
13. Mixed waste soil	1.08E-05	1.14E+00	2.09E-02
14. MW comp. filters	1.51E-06	1.36E-01	2.92E-03
15a. 0.01 Ci/m3 TRU wastec,d	1.07E-10	3.92E-06	2.07E-07
15b. 1.5 Ci/m3 TRU waste	1.18E-08	4.14E-04	2.29E-05
15c. 208 Ci/m3 TRU waste	1.61E-06	5.91E-02	3.11E-03
15d. Bulk eq. TRU waste	9.23E-09	2.46E-04	1.79E-05
15e. Bulk eq. Rmt. TRUe	1.28E-04	8.58E-02	6.32E-03
16. MW aqueous liquids	8.37E-06	4.24E-03	1.37E-02
17. MW organic debris	1.28E-07	1.11E-02	3.33E-04
18. Organic sludge	1.19E-06	1.20E-01	3.07E-03
19. Heterogeneous debris	9.07E-06	1.37E+00	2.35E-02
19a. Lead	3.16E-08	5.11E-03	8.20E-05
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	2.29E-06	1.15E-03	3.75E-03
22. Ashcrete	1.6E-05	6.1E-01	3.1E-02
23. Bulk waste	2.80E-06	8.00E-02	7.28E-03
24. Inorganic sludge	2.24E-06	1.08E-01	5.82E-03
25. Metal debris	2.58E-06	2.73E-01	6.70E-03
26. Sand/rock/gravel	1.80E-06	1.94E-01	4.67E-03
27. Paint waste	2.87E-07	6.13E-02	7.44E-04
28. Glass debris	3.18E-06	1.18E-01	8.25E-03
Totals:g
Low-level	1.1E-02	1.9E+02	2.0E+00
Mixed	5.8E-05	4.4E+00	1.2E-01
Transuranic	1.3E-04	1.5E-01	9.5E-03

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction..

g. For incident-free dose, the sum of waste streams 1 through 12 are used to calculate the corresponding dose of low-level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitutes the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-12. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste for alternative C - minimum waste forecast.

---

	Dose from incident-free transportation
Waste stream	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	9.21E-12	8.19E-07	1.78E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	7.82E-05	6.14E+00	1.52E-01
4. Offsite job-control	2.03E-06	2.47E-01	3.94E-03
5. Low-activity equip.	3.24E-06	4.39E+01	6.28E-03
6. Inter.-level job-control	5.07E-03	4.14E+01	5.72E-01
7. Long-lived	5.56E-04	9.41E+00	2.26E-01
8. Tritiated job-control	1.25E-08	9.29E-04	2.40E-05
9. Low-level waste soils	5.11E-08	5.43E-03	9.91E-05
10. Suspect soils	7.75E-08	7.98E-03	1.50E-04
11. Tritiated soils	3.66E-08	3.89E-03	7.09E-05
12. MW inorganic debrisb	3.73E-06	2.81E-01	7.22E-03
13. Mixed waste soil	2.71E-06	2.87E-01	5.25E-03
14. MW comp. filters	6.64E-07	6.01E-02	1.29E-03
15a. 0.01 Ci/m3 TRU wastec,d	7.70E-11	2.81E-06	1.49E-07
15b. 1.5 Ci/m3 TRU waste	8.25E-09	2.88E-04	1.60E-05
15c. 208 Ci/m3 TRU waste	1.12E-06	4.12E-02	2.17E-03
15d. Bulk eq. TRU waste	6.43E-09	1.71E-04	1.24E-05
15e. Bulk eq. Rmt. TRUe	8.91E-05	5.97E-02	4.40E-03
16. MW aqueous liquids	2.25E-06	1.14E-03	3.69E-03
17. MW organic debris	1.28E-07	1.11E-02	3.33E-04
18. Organic sludge	4.32E-07	4.37E-02	1.12E-03
19. Heterogeneous debris	3.74E-06	5.65E-01	9.69E-03
19a. Lead	1.36E-08	2.20E-03	3.52E-05
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	1.82E-06	9.18E-04	2.98E-03
22. Ashcrete	1.1E-05	4.5E-01	2.2E-02
23. Bulk waste	1.14E-06	3.25E-02	2.95E-03
24. Inorganic sludge	8.01E-07	3.86E-02	2.08E-03
25. Metal debris	1.35E-06	1.44E-01	3.52E-03
26. Sand/rock/gravel	4.53E-07	4.87E-02	1.17E-03
27. Paint waste	1.98E-07	4.22E-02	5.12E-04
28. Glass debris	1.75E-06	6.51E-02	4.55E-03
Totals:g
Low-level	5.7E-03	1.0E+02	9.8E-01
Mixed	2.3E-05	1.7E+00	5.0E-02
Transuranic	9.0E-05	1.0E-01	6.6E-03

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction..

g. For incident-free dose, the sum of waste streams 1 through 12 are used to calculate the corresponding dose of low-level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitutes the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-13. Annual radiological doses from incident-free transportation during onsite transport of low-level, mixed, and transuranic waste for alternative C - maximum waste forecast.

---

	Dose from incident-free transportation
Waste stream	Uninvolved workera	Involved workers	Uninvolved workers
1. Tritiated equipment	3.24E-11	2.88E-06	6.25E-08
2. Spent deionizers	2.89E-06	9.59E-02	4.42E-04
3. Low-level job-control	1.05E-04	8.22E+00	2.03E-01
4. Offsite job-control	4.06E-06	4.95E-01	7.88E-03
5. Low-activity equip.	1.50E-05	2.04E+02	2.92E-02
6. Inter.-level job-control	1.14E-02	9.32E+01	1.29E+00
7. Long-lived	2.58E-03	4.36E+01	1.04E+00
8. Tritiated job-control	1.07E-06	7.99E-02	2.07E-03
9. Low-level waste soils	1.98E-06	2.10E-01	3.83E-03
10. Suspect soils	3.00E-06	3.09E-01	5.81E-03
11. Tritiated soils	1.59E-07	1.68E-02	3.07E-04
12. MW inorganic debrisb	1.40E-05	1.06E+00	2.72E-02
13. Mixed waste soil	5.37E-05	5.70E+00	1.04E-01
14. MW comp. filters	2.04E-06	1.85E-01	3.95E-03
15a. 0.01 Ci/m3 TRU wastec,d	6.15E-09	2.25E-04	1.19E-05
15b. 1.5 Ci/m3 TRU waste	1.95E-07	6.83E-03	3.78E-04
15c. 208 Ci/m3 TRU waste	2.66E-05	9.75E-01	5.13E-02
15d. Bulk eq. TRU waste	1.52E-07	4.06E-03	2.95E-04
15e. Bulk eq. Rmt. TRUe	2.11E-03	1.42E+00	1.04E-01
16. MW aqueous liquids	1.30E-05	6.60E-03	2.13E-02
17. MW organic debris	1.47E-05	1.27E+00	3.82E-02
18. Organic sludge	1.65E-06	1.68E-01	4.28E-03
19. Heterogeneous debris	4.48E-05	6.77E+00	1.16E-01
19a. Lead	8.16E-08	1.32E-02	2.11E-04
20. PUREX solventsf	2.60E-08	1.77E-05	4.27E-05
21. Organic liquids	3.64E-06	1.84E-03	5.96E-03
22. Ashcrete	3.6E-05	1.4E+00	6.9E-02
23. Bulk waste	8.73E-06	2.50E-01	2.27E-02
24. Inorganic sludge	3.11E-06	1.50E-01	8.07E-03
25. Metal debris	1.07E-05	1.14E+00	2.79E-02
26. Sand/rock/gravel	8.98E-06	9.65E-01	2.32E-02
27. Paint waste	3.50E-07	7.47E-02	9.06E-04
28. Glass debris	8.03E-06	2.98E-01	2.08E-02
Totals:g
Low-level	1.4E-02	3.5E+02	2.6E+00
Mixed	2.0E-04	1.9E+01	4.5E-01
Transuranic	2.1E-03	2.4E+00	1.6E-01

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction..

g. For incident-free dose, the sum of waste streams 1 through 12 are used to calculate the corresponding dose of low-level waste in Chapter 4 transportation sections; 12 through 14 and 16 through 28 constitute the mixed waste dose; and 15a through 15e constitutes the transuranic dose. For each waste type, assumes the same individual has maximum exposure to each waste stream in a single year.

---

Table E.3-14. Accident probabilities for onsite shipments of low-level, mixed, and transuranic waste by alternative and waste forecast.

Alternative A

Alternative B

Alternative C

Waste

Expected

Minimum

Maximum

Expected

Minimum

Maximum

Expected

Minimum

Maximum

1. Tritiated equipment

5.62E-07

2.19E-07

7.70E-07

5.62E-07

2.19E-07

7.70E-07

5.62E-07

2.19E-07

7.70E-07

2. Spent deionizers

6.56E-08

6.56E-08

6.56E-08

6.56E-08

6.56E-08

6.56E-08

6.56E-08

6.56E-08

6.56E-08

3. Low-level job-control

2.87E-04

2.42E-04

3.24E-04

2.87E-04

2.42E-04

3.24E-04

2.87E-04

2.42E-04

3.24E-04

4. Offsite job-control

5.92E-06

5.92E-06

1.18E-05

5.92E-06

5.92E-06

1.18E-05

5.92E-06

5.92E-06

1.18E-05

5. Low-activity equip.

5.45E-05

2.66E-05

1.85E-04

3.98E-05

2.05E-05

1.26E-04

2.51E-05

1.41E-05

6.57E-05

6. Inter.-level job-control

5.28E-05

2.90E-05

6.54E-05

5.28E-05

2.90E-05

6.54E-05

5.28E-05

2.90E-05

6.54E-05

7. Long-lived

1.97E-04

6.00E-05

2.78E-04

1.97E-04

6.00E-05

2.78E-04

1.97E-04

6.00E-05

2.78E-04

8. Tritiated job-control

1.82E-06

7.34E-07

6.31E-05

1.82E-06

7.34E-07

6.31E-05

1.82E-06

7.34E-07

6.31E-05

9. Low-level waste soils

1.85E-06

7.55E-07

2.92E-05

1.85E-06

7.55E-07

2.92E-05

1.85E-06

7.55E-07

2.92E-05

10. Suspect soils

2.77E-05

1.13E-05

4.37E-04

2.77E-05

1.13E-05

4.37E-04

2.77E-05

1.13E-05

4.37E-04

11. Tritiated soils

1.44E-06

5.41E-07

2.34E-06

1.44E-06

5.41E-07

2.34E-06

1.44E-06

5.41E-07

2.34E-06

12. MW inorganic debrisa

1.19E-05

4.88E-06

1.84E-05

1.19E-05

4.88E-06

1.84E-05

1.19E-05

4.88E-06

1.84E-05

13. Mixed waste soil

7.08E-05

1.78E-05

3.53E-04

7.08E-05

1.78E-05

3.53E-04

7.08E-05

1.78E-05

3.53E-04

14. MW comp. filters

2.66E-05

1.17E-05

3.61E-05

2.66E-05

1.17E-05

3.61E-05

2.66E-05

1.17E-05

3.61E-05

15a. 0.01 Ci/m3 TRU wasteb,c

1.76E-05

1.26E-05

1.01E-03

1.76E-05

1.26E-05

1.01E-03

1.76E-05

1.26E-05

1.01E-03

15b. 1.5 Ci/m3 TRU waste

1.24E-05

8.63E-06

2.05E-04

1.24E-05

8.63E-06

2.05E-04

1.24E-05

8.63E-06

2.05E-04

15c. 208 Ci/m3 TRU waste

1.28E-05

8.88E-06

2.10E-04

1.28E-05

8.88E-06

2.10E-04

1.28E-05

8.88E-06

2.10E-04

15d. Bulk eq. TRU waste

2.57E-06

1.79E-06

4.24E-05

2.57E-06

1.79E-06

4.24E-05

2.57E-06

1.79E-06

4.24E-05

15e. Bulk eq. Rmt. TRUd

4.79E-08

3.33E-08

7.90E-07

4.79E-08

3.33E-08

7.90E-07

4.79E-08

3.33E-08

7.90E-07

16. MW aqueous liquids

3.46E-05

9.32E-06

5.38E-05

3.46E-05

9.32E-06

5.38E-05

3.46E-05

9.32E-06

5.38E-05

17. MW organic debris

1.51E-06

1.51E-06

1.74E-04

1.51E-06

1.51E-06

1.74E-04

1.51E-06

1.51E-06

1.74E-04

18. Organic sludge

2.93E-04

1.06E-04

4.07E-04

2.93E-04

1.06E-04

4.07E-04

2.93E-04

1.06E-04

4.07E-04

19. Heterogeneous debris

8.03E-05

3.31E-05

3.97E-04

8.03E-05

3.31E-05

3.97E-04

8.03E-05

3.31E-05

3.97E-04

19a. Lead

7.45E-05

3.20E-05

1.92E-04

7.45E-05

3.20E-05

1.92E-04

7.45E-05

3.20E-05

1.92E-04

20. PUREX solventse

3.71E-07

3.71E-07

3.71E-07

3.71E-07

3.71E-07

3.71E-07

3.71E-07

3.71E-07

3.71E-07

Table E.3-14. (continued).

Alternative A

Alternative B

Alternative C

Waste

Expected

Minimum

Maximum

Expected

Minimum

Maximum

Expected

Minimum

Maximum

21. Organic liquids

8.89E-06

7.07E-06

1.41E-05

8.89E-06

7.07E-06

1.41E-05

8.89E-06

7.07E-06

1.41E-05

22. Ashcretef

23. Bulk Waste

3.03E-06

1.23E-06

9.44E-06

3.03E-06

1.23E-06

9.44E-06

3.03E-06

1.23E-06

9.44E-06

24. Inorganic Sludge

9.66E-06

3.45E-06

1.34E-05

9.66E-06

3.45E-06

1.34E-05

9.66E-06

3.45E-06

1.34E-05

25. Metal Debris

2.01E-05

1.06E-05

8.39E-05

2.01E-05

1.06E-05

8.39E-05

2.01E-05

1.06E-05

8.39E-05

26. Sand/Rock/Gravel

2.63E-05

6.61E-06

1.31E-04

2.63E-05

6.61E-06

1.31E-04

2.63E-05

6.61E-06

1.31E-04

27. Paint Chips/Solids

4.25E-05

2.92E-05

5.17E-05

4.25E-05

2.92E-05

5.17E-05

4.25E-05

2.92E-05

5.17E-05

28. Glass Debris

3.98E-06

2.20E-06

1.00E-05

3.98E-06

2.20E-06

1.00E-05

3.98E-06

2.20E-06

1.00E-05

Source: Washburn (1995).

a. MW = Mixed waste.

b. Ci/m3 = Curie per cubic meter.

c. TRU = Transuranic.

d. Rmt = Remotely-handled.

e. PUREX = Plutonium-uranium extraction

f. See Table E.3-16.

---

Table E.3-15. Radiological doses from a single accident during onsite transport of low-level, mixed, and transuranic waste under any alternative.

Waste	Uninvolved workers	Involved workers	Uninvolved workersa	Probability
1. Tritiated equipment	7.15E+02	6.50E+01	9.24E-03	5.62E-07
2. Spent deionizers	5.76E-02	3.28E-03	4.69E-07	6.56E-08
3. Low-level job-control	3.83E-02	3.80E-03	5.42E-07	2.87E-04
4. Offsite job-control	6.40E-02	6.34E-03	9.04E-07	5.92E-06
5. Low-activity equip.	3.83E-02	3.80E-03	5.42E-07	1.04E-05
6. Inter.-level job-control	6.18E-01	1.08E-02	1.54E-06	5.28E-05
7. Long-lived low-level waste	6.96E-01	8.44E-03	1.21E-06	1.97E-04
8. Tritiated job-control	2.03E-03	2.59E-04	3.69E-08	1.82E-06
9. Low-level waste soils	6.39E+01	6.35E+00	9.06E-04	1.85E-06
10. Suspect soils	6.39E+00	6.35E-01	9.06E-05	2.77E-05
11. Tritiated soils	6.45E+01	6.80E+00	9.70E-04	1.44E-06
12. MW inorganic debris	1.37E-02	1.36E-03	1.94E-07	1.19E-05
13. Mixed waste soil	1.44E+02	1.43E+01	2.04E-03	7.07E-05
14. MW comp. filters	7.18E-03	7.14E-04	1.02E-07	2.66E-05
15a. 0.01 Ci/m3 TRU wastec,d	2.22E+00	1.95E-01	2.78E-05	1.76E-05
15b. 1.5 Ci/m3 TRU waste	3.33E+02	2.92E+01	4.17E-03	1.24E-05
15c. 208 Ci/m3 TRU waste	4.61E+04	4.05E+03	5.78E-01	1.28E-05
15d. Bulk eq. TRU waste	3.09E+05	2.72E+04	3.88E+00	2.6E-06
15e. Bulk eq. Rmt. TRUe	3.09E+05	2.72E+04	3.88E+00	4.79E-08
16. MW aqueous liquids	3.57E-03	3.54E-04	5.05E-08	3.46E-05
17. MW organic debris	2.96E+01	2.84E+00	4.05E-04	1.51E-06
18. Organic sludge	2.32E+00	2.22E-01	3.17E-05	2.93E-04
19. Heterogeneous debris	5.92E+01	5.68E+00	8.10E-04	8.03E-05
19a. Lead	3.71E-01	3.56E-02	5.08E-06	1.49E-04
20. PUREX solventsf	2.50E-01	2.19E-02	3.13E-06	3.71E-07
21. Organic liquids	3.57E-03	3.54E-04	5.05E-08	8.89E-06
22. Ashcreteg
23. Bulk waste	6.32E-01	6.05E-02	8.64E-06	3.03E-06
24. Inorganic sludge	6.95E+01	6.67E+00	9.51E-04	9.66E-06
25. Metal debris	5.90E+00	5.68E-01	8.10E-05	2.01E-05
26. Sand/rock/gravel	8.90E+01	8.56E+00	1.22E-03	2.63E-05
27. Paint chips/solids	9.25E+00	8.89E-01	1.27E-04	4.25E-05
28. Glass debris	1.39E+02	1.33E+01	1.90E-03	3.98E-06

Source: Washburn (1995).

a. Dose in rem; all other doses in person-rem.

b. MW = Mixed waste.

c. Ci/m³ = Curie per cubic meter.

d. TRU = Transuranic.

e. Rmt = Remotely-handled.

f. PUREX = Plutonium-uranium extraction.

g. The dose from an accident involving ashcrete varies among alternatives. See Table E.3­16.

---

Table E.3-16. Probability of and radiological dose from a single accident during onsite transport of low-level and mixed waste ashcrete from the Consolidated Incineration Facility under each alternative.

---

Waste forecast	Onsite population	Offsite population	Offsite MEIb	Probability
Alternative A
Expected
Low-level waste	4.3E-02	4.2E-03	6.0E-07	6.1E-05
Mixed waste	4.3E-02	4.2E-03	6.0E-07	1.4E-04
Minimum
Low-level waste	7.9E-02	7.5E-03	1.1E-06	1.7E-05
Mixed waste	7.9E-02	7.5E-03	1.1E-06	3.9E-05
Maximum
Low-level waste	2.2E-02	2.1E-03	3.0E-07	3.0E-04
Mixed waste	2.2E-02	2.1E-03	3.0E-07	6.9E-04
Alternative B
Expected
Low-level waste	3.5E-01	3.4E-02	4.9E-06	2.8E-05
Mixed waste	3.5E-01	3.4E-02	4.9E-06	7.5E-06
Minimum
Low-level waste	1.3E-01	1.3E-02	1.8E-06	3.8E-05
Mixed waste	1.3E-01	1.3E-02	1.8E-06	4.1E-05
Maximum
Low-level waste	2.9E-01	2.8E-02	4.0E-06	4.2E-05
Mixed waste	2.9E-01	2.8E-02	4.0E-06	1.6E-05
Alternative C
Expected
Low-level waste	6.0E-01	5.6E-02	8.0E-06	9.1E-06
Mixed waste	6.0E-01	5.6E-02	8.0E-06	1.9E-06
Minimum
Low-level waste	5.2E-01	4.9E-02	7.0E-06	6.9E-06
Mixed waste	5.2E-01	4.9E-02	7.0E-06	1.2E-06
Maximum
Low-level waste	6.4E-01	6.0E-02	8.6E-06	1.2E-05
Mixed waste	6.4E-01	6.0E-02	8.6E-06	8.1E-06

Source: HNUS (1995).

a. The Consolidated Incineration Facility would not operate under the no-action alternative, so no ashcrete would be generated.

b. MEI = Maximally exposed individual.

---

Table E.3-17. Radiological doses from incident-free transportation and accidentsduring offsite transport of low-level (low-activity equipment), mixed waste (lead), and low-level waste volume reduction.

		Annual dose from incident-free transportation							Dose from a single potential accident
		Remote		Involved		Remote		RemotePopulation
Description	MEIa		workers		Population			Population
	Alternative A - Expected Waste Forecast
Low-activity equipmentb	NAc		NA		NA			NA
Lead	3.2E-08		3.6E-01		7.5E-02			4.7E-03
	Alternative A - Minimum Waste Forecast
Low-activity equipmentb	NA		NA		NA			NA
Lead	1.4E-08		1.6E-01		3.2E-02			4.7E-03
	Alternative A - Maximum Waste Forecast
Low-activity equipmentb	NA		NA		NA			NA
Lead	8.2E-08		9.3E-01		1.9E-01			4.7E-03
	Alternative B - Expected Waste Forecast
Low-activity equipment	5.2E-05		1.7E+01		2.6E+01			4.8E-04
Lead	3.2E-08		3.6E-01		7.5E-02			4.7E-03
Low-level volume reduction	8.1E-05		1.6E+01		6.4E+00			3.7E+02
	Alternative B - Minimum Waste Forecast
Low-activity equipment	2.7E-05		8.8E+00		1.3E+01			4.8E-04
Lead	1.4E-08		1.6E-01		3.2E-02			4.7E-03
Low-level volume reduction	6.6E-05		2.0E+01		5.2E+00			3.7E+02
	Alternative B - Maximum Waste Forecast
Low-activity equipment	1.6E-04		5.4E+01		8.2E+01			4.8E-04
Lead	8.2E-08		9.3E-01		1.9E-01			4.7E-03
Low-level volume reduction	9.6E-05		8.0E+01		7.5E+00			3.7E+02
	Alternative C - Expected Waste Forecast
Low-activity equipment	3.3E-05		1.1E+01		1.6E+01			4.8E-04
Lead	3.2E-08		3.6E-01		7.5E-02			4.7E-03
	Alternative C - Minimum Waste Forecast
Low-activity equipment	1.8E-05		6.0E+00		9.2E+00			4.8E-04
Lead	1.4E-08		1.6E-01		3.2E-02			4.7E-03
	Alternative C - Maximum Waste Forecast
Low-activity equipment	8.6E-05		2.8E+01		4.3E+01			4.8E-04
Lead	8.2E-08		9.3E-01		1.9E-01			4.7E-03

Source: Washburn (1995).

a. Remote maximally exposed individual along transportation route. Dose is rem; all others in person-rem.

b. No low-activity equipment would be shipped offsite under alternative A.

c. NA = not applicable.

---

Table E.3-18. Waste volumes (in cubic meters) shipped in each alternative.

---

No-Action

Alternative A

Alternative B

Alternative C

Waste

Expected

Minimum

Maximum

Expected

Minimum

Maximum

Expected

Minimum

Maximum

1. Tritiated equipment

1.18E+03

1.18E+03

4.61E+02

1.62E+03

1.18E+03

4.61E+02

1.62E+03

1.18E+03

4.61E+02

1.62E+03

2. Spent deionizers

3.00E+01

3.00E+01

3.00E+01

3.00E+01

3.00E+01

3.00E+01

3.00E+01

3.00E+01

3.00E+01

3.00E+01

3. Low-level job-control

3.66E+05

3.66E+05

3.09E+05

4.14E+05

3.66E+05

3.09E+05

4.14E+05

3.66E+05

3.09E+05

4.14E+05

4. Offsite job job-control

1.26E+04

1.26E+04

1.26E+04

2.52E+04

1.26E+04

1.26E+04

2.52E+04

1.26E+04

1.26E+04

2.52E+04

5. Low-activity equip.

1.33E+04

6.95E+04

3.40E+04

2.35E+05

5.08E+04

2.61E+04

1.61E+05

3.20E+04

1.80E+04

8.37E+04

6. Inter.-level job-control

2.27E+04

2.27E+04

1.25E+04

2.81E+04

2.27E+04

1.25E+04

2.81E+04

2.27E+04

1.25E+04

2.81E+04

7. Long-lived

3.30E+03

3.30E+03

1.00E+03

4.64E+03

3.30E+03

1.00E+03

4.64E+03

3.30E+03

1.00E+03

4.64E+03

8. Tritiated job-control

3.86E+03

3.86E+03

1.56E+03

1.34E+05

3.86E+03

1.56E+03

1.34E+05

3.86E+03

1.56E+03

1.34E+05

9. Low-level waste soils

1.98E+04

1.98E+04

8.07E+03

3.12E+05

1.98E+04

8.07E+03

3.12E+05

1.98E+04

8.07E+03

3.12E+05

10. Suspect soils

2.97E+04

2.97E+04

1.21E+04

4.68E+05

2.97E+04

1.21E+04

4.68E+05

2.97E+04

1.21E+04

4.68E+05

11. Tritiated soils

1.53E+03

1.53E+03

5.75E+02

2.49E+03

1.53E+03

5.75E+02

2.49E+03

1.53E+03

5.75E+02

2.49E+03

12. MW inorganic debrisa

1.52E+04

1.52E+04

6.24E+03

2.35E+04

1.52E+04

6.24E+03

2.35E+04

1.52E+04

6.24E+03

2.35E+04

13. Mixed waste soil

7.56E+04

7.56E+04

1.90E+04

3.77E+05

7.56E+04

1.90E+04

3.77E+05

7.56E+04

1.90E+04

3.77E+05

14. MW comp. filters

2.85E+03

2.85E+03

1.26E+03

3.86E+03

2.85E+03

1.26E+03

3.86E+03

2.85E+03

1.26E+03

3.86E+03

15a. 0.01 ci/m3 TRU wasteb,c

4.40E+03

4.40E+03

3.16E+03

2.53E+05

4.40E+03

3.16E+03

2.53E+05

4.40E+03

3.16E+03

2.53E+05

15b. 1.5 ci/m3 TRU waste

3.11E+03

3.11E+03

2.16E+03

5.13E+04

3.11E+03

2.16E+03

5.13E+04

3.11E+03

2.16E+03

5.13E+04

15c. 208 ci/m3 TRU waste

3.20E+03

3.20E+03

2.23E+03

5.28E+04

3.20E+03

2.23E+03

5.28E+04

3.20E+03

2.23E+03

5.28E+04

15d. Bulk eq. TRU waste

1.17E+04

1.17E+04

8.14E+03

1.93E+05

1.17E+04

8.14E+03

1.93E+05

1.17E+04

8.14E+03

1.93E+05

15e. Bulk eq. rmt. TRUd

2.09E+02

2.09E+02

1.46E+02

3.45E+03

2.09E+02

1.46E+02

3.45E+03

2.09E+02

1.46E+02

3.45E+03

16. MW aqueous liquids

3.27E+04

3.27E+04

8.81E+03

5.09E+04

3.27E+04

8.81E+03

5.09E+04

3.27E+04

8.81E+03

5.09E+04

17. MW organic debris

2.42E+02

2.42E+02

2.42E+02

2.78E+04

2.42E+02

2.42E+02

2.78E+04

2.42E+02

2.42E+02

2.78E+04

18. Organic sludge

3.67E+03

3.67E+03

1.34E+03

5.11E+03

3.67E+03

1.34E+03

5.11E+03

3.67E+03

1.34E+03

5.11E+03

19. Heterogeneous debris

2.57E+04

2.57E+04

1.06E+04

1.27E+05

2.57E+04

1.06E+04

1.27E+05

2.57E+04

1.06E+04

1.27E+05

19a. Lead

5.96E+03

2.98E+03

1.28E+03

7.68E+03

2.98E+03

1.28E+03

7.68E+03

2.98E+03

1.28E+03

7.68E+03

20. PUREX solventse

3.45E+02

3.45E+02

3.45E+02

3.45E+02

3.45E+02

3.45E+02

3.45E+02

3.45E+02

3.45E+02

3.45E+02

21. Organic liquids

8.45E+03

8.45E+03

6.72E+03

1.34E+04

8.45E+03

6.72E+03

1.34E+04

8.45E+03

6.72E+03

1.34E+04

22. Ashcretef

0.00E+00

1.63E+05

4.49E+04

7.96E+05

2.81E+04

6.38E+04

4.62E+04

8.79E+03

6.55E+03

1.65E+04

TE

Table E.3-18. (continued).

---

No-Action

Alternative A

Alternative B

Alternative C

Waste

Expected

Minimum

Maximum

Expected

Minimum

Maximum

Expected

Minimum

Maximum

23. Bulk waste

1.04E+04

1.04E+04

4.20E+03

3.23E+04

1.04E+04

4.20E+03

3.23E+04

1.04E+04

4.20E+03

3.23E+04

24. Inorganic sludge

3.64E+03

3.64E+03

1.30E+-3

5.05E+03

3.64E+03

1.30E+-3

5.05E+03

3.64E+03

1.30E+-3

5.05E+03

25. Metal debris

1.29E+04

1.29E+04

6.77E+03

5.37E+04

1.29E+04

6.77E+03

5.37E+04

1.29E+04

6.77E+03

5.37E+04

26. Sand/rock/gravel

1.27E+04

1.27E+04

3.19E+03

6.32E+04

1.27E+04

3.19E+03

6.32E+04

1.27E+04

3.19E+03

6.32E+04

27. Paint waste

2.13E+03

2.13E+03

1.47E+03

2.60E+03

2.13E+03

1.47E+03

2.60E+03

2.13E+03

1.47E+03

2.60E+03

28. Glass debris

3.00E+03

3.00E+03

1.65E+03

7.56E+03

3.00E+03

1.65E+03

7.56E+03

3.00E+03

1.65E+03

7.56E+03

29. Low-activity equipmentg

0.00E+00

0.00E+00

0.00E+00

0.00E+00

1.68E+04

8.68E+03

5.31E+04

1.05E+04

5.94E+03

2.76E+04

30. Leadg

0.00E+00

2.98E+03

1.28E+03

7.68E+03

2.98E+03

1.28E+03

7.68E+03

2.98E+03

1.28E+03

7.68E+03

31. Low Level Job Controlh

0.00E+00

0.00E+00

0.00E+00

0.00E+00

1.87E+05

1.58E+05

2.10E+05

0.00E+00

0.00E+00

0.00E+00

32. Low Activity Equiph

0.00E+00

0.00E+00

0.00E+00

0.00E+00

1.44E+05

9.85E+04

1.61E+05

0.00E+00

0.00E+00

0.00E+00

33. LLW from Deconh

0.00E+00

0.00E+00

0.00E+00

0.00E+00

4.54E+05

2.29E+05

1.63E+06

0.00E+00

0.00E+00

0.00E+00

34. Supercompactedh,i

0.00E+00

0.00E+00

0.00E+00

0.00E+00

1.02E+05

7.57E+04

1.01E+05

0.00E+00

0.00E+00

0.00E+00

35. Incinerate/S'compactedh,i

0.00E+00

0.00E+00

0.00E+00

0.00E+00

2.19E+03

1.63E+03

2.19E+03

0.00E+00

0.00E+00

0.00E+00

36. Reduce/ Repkg (CIF) h,i

0.00E+00

0.00E+00

0.00E+00

0.00E+00

4.26E+04

3.17E+04

4.21E+04

0.00E+00

0.00E+00

0.00E+00

37. Reduce/Repkg (vaults)h,i

0.00E+00

0.00E+00

0.00E+00

0.00E+00

1.64E+04

1.39E+04

1.84E+04

0.00E+00

0.00E+00

0.00E+00

38. Metal / Supercompacth,i

0.00E+00

0.00E+00

0.00E+00

0.00E+00

1.03E+04

8.72E+03

1.16E+04

0.00E+00

0.00E+00

0.00E+00

39. Supercompacted Equip.h,i

0.00E+00

0.00E+00

0.00E+00

0.00E+00

1.44E+05

9.85E+04

1.61E+05

0.00E+00

0.00E+00

0.00E+00

40. Supercompacted Deconh,i

0.00E+00

0.00E+00

0.00E+00

0.00E+00

4.54E+05

2.29E+05

1.63E+06

0.00E+00

0.00E+00

0.00E+00

Onsite totals: Low-level waste

4.74E+05

5.30E+05

3.92E+05

1.63E+06

5.26E+05

4.03E+05

1.58E+06

5.02E+05

3.83E+05

1.48E+06

Mixed waste

2.15E+05

3.40E+05

1.22E+05

1.59E+06

2.17E+05

1.21E+05

8.14E+05

2.14E+05

7.50E+04

8.09E+05

Transuranic waste

2.24E+04

2.24E+04

1.57E+04

5.50E+05

2.24E+04

1.57E+04

5.50E+05

2.24E+04

1.57E+04

5.50E+05

Offsite totals: Low-level waste

0.00E+00

0.00E+00

0.00E+00

0.00E+00

1.57E+06

9.54E+05

4.02E+06

1.05E+04

5.94E+03

2.76E+04

Mixed waste

0.00E+00

2.98E+03

1.28E+03

7.68E+03

2.98E+03

1.28E+03

7.68E+03

2.98E+03

1.28E+03

7.68E+03

Source: Washburn (1995), Sinkowski (1995).

a. MW = mixed waste.

b. Ci/m3 = Curies per cubic meter.

c. TRU = transuranic.

d. Rmt. = Remote-handled.

e. PUREX = Plutonium-uranium solution.

f. Ashcrete values are the result of processing of low-level and mixed waste only.

g. Offsite shipments.

h. Low-level volume reduction offsite shipments.

i. Low-level volume reduction return shipments to SRS.

---

SECTION 4

OCCUPATIONAL AND PUBLIC HeaLTH

Table E.4-1. Average number of workers assigned to onsite facilities.

---

	No-Action	Alternative A				Alternative B				Alternative C
Facility		Min.	Exp.	Max.		Min.	Exp.	Max.		Min.	Exp.	Max.
E-Area Vaults	7	7	7	14		7	7	14		3	3	5
Containment building	0	10	10	25		10	10	19		10	10	13
RCRA-Permitted Disposal Vaults	1	5	6	11		5	5	11		5	5	11
Long-Lived Waste Storage Building	1	1	1	1		1	1	1		1	1	1
MW Storage Buildingsb	39	10	16	67		9	14	65		10	13	65
Non-alpha vitrification facility	0	0	0	0		0	13	25		51	63	79
Shallow land disposal	8	8	8	16		8	8	16		8	8	16
TRU waste characterization/certification facilityc	5	26	38	122		20	20	107		20	20	107
TRU waste retrieval operations	4	4	4	4		4	4	4		4	4	4
TRU Waste Storage Pads	14	10	10	96		10	10	97		11	11	99
Alpha vitrification facility	0	0	0	0		40	40	119		40	40	119
Soil sort facility	0	3	3	3		3	3	3		3	3	3
Aqueous and Organic Waste Storage Tanks	15	0	0	0		0	0	0		0	0	0
Consolidated Incineration Facility	0	26	26	26		26	26	26		10	10	10
F/H-Area Effluent Treatment Facility	40	40	40	40		40	40	40		40	40	40
H-Area Tank Farm	1,562	1,562	1,562	1,562		1,562	1,562	1,562		1,562	1,562	1,562
Replacement High-Level Waste Evaporator	15	15	15	15		15	15	15		15	15	15
Waste removal operations	10	10	10	10		10	10	10		10	10	10
M-Area Compaction Facility	4	4	4	4		4	4	4		4	4	4
M­Area Liquid Effluent Treatment Facility	31	31	31	31		31	31	31		31	31	31
M-Area Vendor Treatment Facility	10	10	10	10		10	10	10		10	10	10
SRTC MW Tanks/Ion Exchanged	4	4	4	4		4	4	4		4	4	4
D-Area Ion Exchange Process	1	1	1	1		1	1	1		1	1	1
F-Area Tank Farm	308	308	308	308		308	308	308		308	308	308
253-H Compaction Facility	3	3	3	3		3	3	3		3	3	3
Waste management workers (average yearly)	2,082	2,098	2,117	2,373		2,131	2,148	2,495		2,163	2,178	2,520

a. Source: Hess (1994e).

b. MW = mixed waste.

c. TRU = transuranic.

d. SRTC = Savannah River Technology Center.

---

Table E.4-2. Onsite facility workers annual dose during the 30-year period of interest (in person-millirem).

			Alternative A			Alternative B			Alternative C
Facility worker dose	Averageb annual dose	No-Action	Min.	Exp.	Max.	Min.	Exp.	Max.	Min.	Exp.	Max.
E-Area Vaults	16	112	112	112	224	112	112	224	41	41	82
Containment building	250	0	2,375	2,375	6,333	2,375	2,375	4,750	2,375	2,375	3,167
RCRA-Permitted Disposal Vaults	16	12	86	97	172	86	86	172	86	86	172
Long-Lived Waste Storage Building	16	16	16	16	16	16	16	16	16	16	16
MW Storage Buildingsc	16	624	160	256	1,072	144	224	1,040	160	208	1,040
Non-alpha vitrification facility	250	0	0	0	0	0	3167	6,333	12,667	15,833	19,792
Shallow Land Disposal	16	128	128	128	256	128	128	256	128	128	256
TRU waste characterization/certification facilityd	220	1,100	5,720	8,360	26,840	4,400	4,400	23,540	4,400	4,400	23,540
TRU waste retrieval operations	220	880	880	880	880	880	880	880	880	880	880
TRU Waste Storage Pads	220	3,080	2,200	2,200	21,120	2,200	2,200	21,340	2,420	2,420	21,780
Alpha vitrification facility	250	0	0	0	0	9,917	9,917	29,750	9,917	9,917	29,750
Soil sort facility	220	0	697	697	697	697	697	697	697	697	697
Aqueous and Organic Waste Storage Tanks	16	240	0	0	0	0	0	0	0	0	0
Consolidated Incineration Facility	350	0	9,135	9,135	9,135	9,135	9,135	9,135	3,465	3,465	3,465
F/H-Area Effluent Treatment Facility	1	40	40	40	40	40	40	40	40	40	40
H-Area Tank Farm	21	32,804	32,804	32,804	32,804	32,804	32,804	32,804	32,804	32,804	32,804
Replacement High-Level Waste Evaporator	149	2,235	2,235	2,235	2,235	2,235	2,235	2,235	2,235	2,235	2,235
Waste removal operations	21	210	210	210	210	210	210	210	210	210	210
M-Area Compaction Facility	1	4	4	4	4	4	4	4	4	4	4
M­Area Liquid Effluent Treatment Facility	1	31	31	31	31	31	31	31	31	31	31
M-Area Vendor Treatment Facility	250	2,500	2,500	2,500	2,500	2,500	2,500	2,500	2,500	2,500	2,500
SRTC MW Tanks/Ion Exchangee	8	32	32	32	32	32	32	32	32	32	32
D-Area Ion Exchange Process	2	2	2	2	2	2	2	2	2	2	2
F-Area Tank Farm	26	8,000	8,000	8,000	8,000	8,000	8,000	8,000	8,000	8,000	8,000
253-H Compaction Facility	1	3	3	3	3	3	3	3	3	3	3
Total annual dose, person-millirem		52,000	67,000	70,000	113,000	76,000	79,000	144,000	83,000	86,000	150,000
Average worker dosef, millirem per year		25	32	33	47	36	37	58	38	40	60

a. Source: Hess (1994e).

b. Average annual dose for a facility worker.

c. MW = mixed waste.

d. TRU = transuranic.

e. SRTC = Savannah River Technology Center.

f. Average annual worker dose from all facilities.

---

Table E.4-3. Summary of facility-specific doses to the offsite maximally exposed individual from atmospheric releases (in millirem).

---

	No-Action	Alternative A				Alternative B				Alternative C
Onsite facilities		Minimum	Expected	Maximum		Minimum	Expected	Maximum		Minimum	Expected	Maximum
Consolidated Incineration Facility	(b)	0.09	0.212	0.568		0.255	0.318	0.689		0.0667	0.0916	0.215
Compaction facilities	1.55E-06	1.55E-06	1.55E-06	1.55E-06		5.18-08	5.18E-08	5.18E-08		1.99E-07	2.40E-07	2.48E-07
Onsite vitrification facilities	(b)	(b)	(b)	(b)		0.315	0.561	8.08		2.56	5.20	118
M-Area Vendor Treatment Facilityc	0.00371	0.00371	0.00371	0.00371		0.00371	0.00371	0.00371		0.00371	0.00371	0.00371
Soil sort facilities	(b)	6.96E-07	2.58E-06	1.28E-05		8.17E-07	2.87E-06	1.75E-05		5.52E-07	2.03E-06	1.18E-05
Transuranic waste characterization/certification facility	(b)	0.0775	0.111	1.83		0.0775	0.111	1.83		0.0775	0.110	1.83
F/H-Area Effluent Treatment Facility	(d)	(d)	(d)	(d)		(d)	(d)	(d)		(d)	(d)	(d)
Containment building	(d)	1.22E-06	2. 41E-06	8.26E-06		7.99E-07	1.59E-06	5.55E-06		3.24E-07	6.82E-07	2.51E-06
30-year total	0.0037	0.171	0.327	2.41		0.651	0.994	10.6		2.71	5.40	120
Average annual dosee	1.24E-04	0.00571	0.0109	0.802		0.217	0.331	0.354		0.0902	0.18	4.02
Offsite facilities
Supercompaction, sorting	(b)	6.66E-06	1.52E-05	3.88E-05		3.83E-04	4.85E-04	6.86E-04		6.66E-06	1.52E-05	3.88E-05
Smelt, incinerate, metal melt	(b)	(b)	(b)	(b)		0.0377	0.0514	0.0927		0.00607	0.0108	0.0284
30-year total		6.66E-06	1.52E-05	3.88E-05		0.0381	0.0519	0.0934		0.00608	0.0108	0.0284
Average annual dosee		2.22E-07	5.08E-07	1.29E-06		0.00127	0.00173	0.00311		2.03E-04	3.61E-04	9.47E-04

Source: Chesney (1995).

a. Except where noted, the doses reported are for the 30-year period of interest.

b. Facility not operated in this alternative.

c. Doses are calculated from the center of SRS due to unavailability of other population data.

d. Routine operations are not expected to provide atmospheric releases.

e. Offsite-maximally-exposed individual average annual dose is determined by dividing the 30-year dose by 30. For onsite facilities the offsite maximally exposed individual is within 80 kilometers (50 miles) of SRS. For offsite facilities the offsite maximally exposed individual is considered to be within 80 kilometers (50 miles) of Oak Ridge, Tennessee.

---

Table E.4-4. Summary of facility-specific doses to offsite population from atmospheric releases (person-rem).

---

	No-Action	Alternative A			Alternative B			Alternative C
Onsite facilities		Minimum	Expected	Maximum	Minimum	Expected	Maximum	Minimum	Expected	Maximum
Consolidated Incineration Facility	(b)	5.31	12.6	33.9	15.1	18.8	36.2	3.95	5.42	12.6
Compaction facilities	6.15E-05	6.15E-05	6.15E-05	6.15E-05	2.05E-06	2.05E-06	2.05E-06	7.86E-06	9.49E-06	9.82E-06
Onsite vitrification facilities	(b)	(b)	(b)	(b)	12.5	24.4	330	141	293	6,790
M-Area Vendor Treatment Facilityc	0.00851	0.00851	0.00851	0.00851	0.00851	0.00851	0.00851	0.00851	0.00851	0.00851
Soil sort facilities	(b)	2.75E-05	1.02E-04	5.08E-04	3.23E-05	1.14E-04	6.93E-04	2.56E-05	9.38E-05	5.47E-04
Transuranic waste characterization/ certification facility	(b)	2.92	4.19	69.1	2.92	4.19	69.1	2.92	4.19	69.1
F/H-Area Effluent Treatment Facility	(d)	(d)	(d)	(d)	(d)	(d)	(d)	(d)	(d)	(d)
Containment building	(b)	4.83E-05	9.56E-05	3.27E-04	3.16E-05	6.31E-05	2.20E-04	1.28E-05	2.70E-05	9.93E-05
30-year total	0.0857	8.24	16.8	103	30.5	47.4	436	148	302	6,880
Average annual dosee	2.86E-04	0.275	0.560	3.43	1.02	1.58	14.5	4.92	10.1	220
Offsite facilities
Supercompaction, sorting	(b)	3.03E-06	6.93E-06	1.77E-05	1.74E-04	2.21E-04	3.13E-04	3.03E-06	6.93E-06	1.77E-05
Smelt, incinerate, metal melt	(b)	(b)	(b)	(b)	0.251	0.346	0.624	0.0409	0.0728	0.191
30-year total		3.03E-06	6.93E-06	1.77E-05	0.254	0.346	0.625	0.0409	0.0728	0.191
Average annual dosee		1.01E-07	2.31E-07	5.89E-07	0.00847	0.0115	0.0208	0.00136	0.00243	0.00637

Source: Chesney (1995).

a. Except where noted, the doses reported are for the 30-year period of interest.

b. Facility not operated in this alternative.

c. Doses are calculated from the center of SRS due to unavailability of other population data.

d. Routine operations are not expected to provide atmospheric releases.

e. Average annual dose is determined by dividing the 30-year dose by 30. For onsite facilities the offsite maximally exposed individual is within 80 kilometers (50 miles) of SRS. For offsite facilities the offsite maximally exposed individual is considered to be within 80 kilometers (50 miles) of Oak Ridge, Tennessee.

---

Table E.4-5.Summary of facility-specific doses to the 640-meter (2,100 feet) uninvolved worker from atmospheric releases (in millirem).

---

	No-Action	Alternative A			Alternative B			Alternative C
Onsite facilities		Minimum	Expected	Maximum	Minimum	Expected	Maximum	Minimum	Expected	Maximum
Consolidated Incineration Facility	(b)	1.77	4.25	11.5	5.07c	6.28	9.76	1.32	1.81	4.12
Compaction facilities	6.01E-05	6.01E-05	6.01E-05	6.01E-05	2.00E-06	2.00E-06	2.00E-06	7.67E-06	9.27E-06	9.59E-06
Onsite vitrification facilities	(b)	(b)	(b)	(b)	1.60	4.52	48.8	42.7	92	219
M-Area Vendor Treatment Facility	0.00856	0.00856	0.00856	0.00856	0.00856	0.00856	0.00856	0.00856	0.00856	0.00856
Soil sort facilities	(b)	2.69E-05	9.95E-05	4.96E-04	3.16E-05	1.11E-04	6.76E-04	6.76E-06	2.48E-05	1.45E-04
Transuranic waste characterization/ certification facility	(b)	3.26	4.68	77.1	3.26	4.68	77.1	3.26	4.68	77.1
F/H-Area Effluent Treatment Facility	(d)	(d)	(d)	(d)	(d)	(d)	(d)	(d)	(d)	(d)
Containment building	(b)	4.72E-05	9.33E-05	3.19E-04	3.09E-05	6.16E-05	2.14E-04	1.25E-05	2.64E-05	9.69E-05
Average annual dosee	2.85E-04	0.0109	0.156	2.57	0.169	0.209	2.57	1.42	3.07	73
Offsite facilities
Supercompaction, sorting	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)
Smelt, incinerate, metal melt	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)

Source: Chesney (1995).

a. Except where noted, the doses reported are for a 30-year period of interest.

b. Facility not operated in this alternative.

c. Italics indicate the facility that would produce the highest dose to any individual under each alternative/forecast. This maximum dose was used to calculate the average annual dose.

d. Routine operations are not expected to provide atmospheric releases.

e. Maximally exposed individual doses are not added; average annual dose is determined by dividing the 30-year dose from the highest impact facility (shown in italics) by 30.

f. The 640 meter worker is a receptor unique to DOE and is not evaluated by the Nuclear Regulatory Commission or agreement state licensees.

---

Table E.4-6. Summary of facility-specific dosesa to the 100-meter (328 foot) uninvolved worker (in millirem) from atmospheric releases.

---

	No-Action	Alternative A			Alternative B			Alternative C
Onsite facilities		Minimum	Expected	Maximum	Minimum	Expected	Maximum	Minimum	Expected	Maximum
Consolidated Incineration Facility	(b)	5.14	12.2	32.8	14.6	18.1	32.4	3.80	5.23	12
Compaction facilities	0.00169	0.00169	0.00169	0.00169	5.64E-05	5.64E-05	5.64E-05	2.16E-04	2.61E-04	2.70E-04
Onsite vitrification facilities	(b)	(b)	(b)	(b)	12.2	23.8	323	136c	283	6,580
M-Area Vendor Treatment Facility	0.304	0.304	0.304	0.304	0.304	0.304	0.304	0.304	0.304	0.304
Soil sort facilities	(b)	7.57E-04	0.0028	0.014	8.88E-04	0.00312	0.019	2.56E-05	9.40E-05	5.47E-04
Transuranic waste characterization/ certification facility	(b)	112	161	2,650	112	161	2,650	111	161	2,650
F/H-Area Effluent Treatment Facility	(d)	(d)	(d)	(d)	(d)	(d)	(d)	(d)	(d)	(d)
Containment building	(b)	0.00133	0.00263	0.00899	8.69E-04	0.00173	0.00604	3.53E-04	7.42E-04	0.00273
Average annual dosee	0.0102	3.73	5.37	88.3	3.73	5.37	88.3	4.53	9.43	219
Offsite facilities
Supercompaction, sorting	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)
Smelt, incinerate, metal melt	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)	(f)

Source: Chesney (1995).

a. Except where noted, the doses reported are for a 30-year period of interest.

b. Facility not operated in this alternative.

c. Italics indicate the facility that would produce the highest dose to any individual under each alternative/forecast. This maximum dose was used to calculate the average annual dose.

d. Routine operations are not expected to provide atmospheric releases.

e. Maximally exposed individual doses are not added; average annual dose is determined by dividing the 30-year dose from the highest impact facility (shown in italics) by 30.

f. The 100 meter worker is a receptor unique to DOE and is not evaluated by the Nuclear Regulatory Commission or agreement state licensees.

---

Table E.4-7. Summary of facility-specific doses to the offsite maximally exposed individual from aqueous releases

	No-Action	Alternative A			Alternative B			Alternative C
Onsite facilities		Minimum	Expected	Maximum	Minimum	Expected	Maximum	Minimum	Expected	Maximum
Consolidated Incineration Facility	(b)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Compaction facilities	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Onsite vitrification facilities	(b)	(b)	(b)	(b)	(c)	(c)	(c)	(c)	(c)	(c)
M-Area Vendor Treatment Facility	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Soil sort facilities	(b)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Transuranic waste characterization/certification facility	(b)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
F/H-Area Effluent Treatment Facility	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208
Containment building	(b)	(c)	(c)	2.07E-05	(c)	(c)	1.41E-05	(c)	(c)	(c)
30-year total	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208	0.0208
Average annual dose	6.93E-04	6.93E-04	6.93E-04	6.94E-04	6.93E-04	6.93E-04	6.94E-04	6.93E-04	6.93E-04	6.94E-04
Offsite facilities
Supercompaction, sorting	(b)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Smelt, incinerate, metal melt	(b)	(b)	(b)	(b)	(c)	(c)	(c)	(c)	(c)	(c)

Source: Chesney (1995).

a. Except where noted, the doses reported are for a 30-year period of interest.

b. Facility not operated in this alternative.

c. Routine operations are not expected to provide liquid releases.

---

Table E.4-8.Summary of facility-specific dosesa to the offsite population (in person-rem) from aqueous releases.

---

	No-Action	Alternative A				Alternative B			Alternative C
Onsite facilities		Minimum	Expected	Maximum	Minimum	Expected	Maximum	Minimum	Expected	Maximum
Consolidated Incineration Facility	(b)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Compaction facilities	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Onsite vitrification facilities	(b)	(b)	(b)	(b)	(c)	(c)	(c)	(c)	(c)	(c)
M-Area Vendor Treatment Facility	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Soil sort facilities	(b)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Transuranic waste characterization/ certification facility	(b)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
F/H-Area Effluent Treatment Facility	0.0203	0.0203	0.0203	0.0203	0.0203	0.0203	0.0203	0.0203	0.0203	0.0203
Containment building	(b)	(c)	(c)	1.82E-04	(c)	(c)	1.24E-04	(c)	(c)	(c)
30-year total	0.203	0.203	0.203	0.204	0.203	0.203	0.204	0.203	0.203	0.203
Average annual dose	0.00678	0.00678	0.00678	0.00679	0.00678	0.00678	0.00679	0.00678	0.00678	0.00678
Offsite facilities
Supercompaction, sorting	(b)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)
Smelter, incinerator, metal metal	(b)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)	(c)

Source: Chesney (1995).

a. Except where noted, the doses reported are for the 30-year period of interest.

b. Facility not operated in this alternative.

c. Routine operations are not expected to provide liquid releases.

---

Table E.4-9. Compactor facility dose distribution by isotope for the no-action alternative.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved workerd (2,100 feet)	100-meter uninvolved workerd (328 feet)
Cobalt-60	7.08	6.13	11.21	8.56
Cesium-134	6.13	3.94	5.15	3.90
Cesium-137	19.81	28.86	25.85	19.39
Europium-154	<1.0e	<1.0e	1.51	<1.0e
Tritium	18.44	18.31	11.37	12.11
Plutonium-238	31.18	29.68	33.96	41.53
Plutonium-239	<1.0e	<1.0e	<1.0e	1.35
Ruthenium-106	1.13	<1.0e	<1.0e	<1.0e
Strontium-90	8.36	4.44	1.75	2.16
Uranium-234	3.99	4.37	5.57	6.87
Otherf	3.88	4.28	3.62	4.13
	Millirem	Person-rem	Millirem	Millirem
Total doseg,h	1.55E-06	6.15E-05	6.01E-05	1.69E-03

Source: Blankenhorn (1994); Hess (1994f, g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. Dose to 640-meter and 100-meter uninvolved workers are based on an 80-hour work week.

e. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" category.

f. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

g. Dose refers to committed effective dose equivalent (see glossary).

h. Total doses are for the 30-year period of interest.

---

Table E.4-10. Consolidated Incineration Facilitydose distribution by isotope for alternative A.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	2.29	<1.0d	3.33	3.38
Cesium-134	20.25	11.00	16.03	15.89
Cesium-137	66.44	81.97	78.79	77.00
Strontium-90	7.62	2.83	<1.0d	<1.0d
Othere	3.40	4.20	1.75	3.74
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	0.21	12.60	4.25	12.20
Maximum	0.57	34.00	11.50	32.80
Minimum	0.090	5.31	1.77	5.14

Source: Blankenhorn (1994); Hertel et al. (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose is to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-11. Compactor facilities dose distribution by isotope for alternative A.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	7.08	6.13	11.21	8.56
Cesium-134	6.13	3.94	5.15	3.90
Cesium-137	19.81	28.86	25.85	19.39
Europium-154	<1.0d	<1.0d	1.51	<1.0d
Tritium	18.44	18.31	11.37	12.11
Plutonium-238	31.18	29.68	33.96	41.53
Plutonium-239	<1.0d	<1.0d	<1.0d	1.35
Ruthenium-106	1.13	<1.0d	<1.0d	<1.0d
Strontium-90	8.36	4.44	1.75	2.16
Uranium-234	3.99	4.37	5.57	6.87
Othere	3.88	4.28	3.62	4.13
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	1.55E-06	6.15E-05	6.01E-05	1.69E-03
Maximum	1.55E-06	6.15E-05	6.01E-05	1.69E-03
Minimum	1.55E-06	6.15E-05	6.01E-05	1.69E-03

Source: Blankenhorn (1994); Hess (1994f, g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-12. Soil sort facility dose distribution by isotope for alternative A.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	7.08	6.13	11.21	8.56
Cesium-134	6.13	3.94	5.15	3.90
Cesium-137	19.81	28.86	25.85	19.39
Europium-154	<1.0d	<1.0d	1.51	<1.0d
Tritium	18.44	18.31	11.37	12.11
Plutonium-238	31.18	29.68	33.96	41.53
Plutonium-239	<1.0d	<1.0d	<1.0d	1.35
Ruthenium-106	1.13	<1.0d	<1.0d	<1.0d
Strontium-90	8.36	4.44	1.75	2.16
Uranium-234	3.99	4.37	5.57	6.87
Othere	3.88	4.28	3.62	4.13
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	2.58E-06	1.02E-04	9.95E-05	2.80E-03
Maximum	1.28E-05	5.08E-04	4.96E-04	1.40E-02
Minimum	6.96E-07	2.75E-05	2.69E-05	7.57E-04

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-13. Transuranic waste characterization/certification facilitydose distribution by isotope for alternative A.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Plutonium-238	83.65	83.66	83.85	83.89
Plutonium-239	15.38	15.37	15.17	15.13
Otherd	0.97	0.97	0.98	0.98
Total dosee,f	Millirem	Person-rem	Millirem	Millirem
Expected	0.111	4.19	4.68	161
Maximum	1.83	69.1	77	2.650
Minimum	0.0775	2.92	3.26	112

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

e. Dose refers to committed effective dose equivalent (see glossary).

f. Total doses are for the 30-year period of interest.

---

Table E.4-14. Containment building dose distribution by isotope for alternative A.

---

	Atmospheric releases (percent of total dose)					Aqueous releases (percent of total dose)
Radionuclides	MEIa	Populationb	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)		MEIa	Populationb
Cobalt-60	7.08	6.13	11.21	8.56		<1.0c	5.97
Cesium-134	6.13	3.94	5.15	3.90		81.85	21.81
Cesium-137	19.81	28.86	25.85	19.39		<1.0c	<1.0c
Europium-154	<1.0c	<1.0c	1.51	<1.0c		<1.0c	<1.0c
Tritium	18.44	18.31	11.37	12.11		10.51	32.22
Plutonium-238	31.18	29.68	33.96	41.53		4.62	28.48
Plutonium-239	<1.0c	<1.0c	<1.0c	1.35		<1.0c	<1.0c
Ruthenium-106	1.13	<1.0c	<1.0c	<1.0c		<1.0c	2.37
Strontium-90	8.36	4.44	1.75	2.16		<1.0c	<1.0c
Uranium-234	3.99	4.37	5.57	6.87		<1.0c	<1.0c
Otherd	3.88	4.28	3.62	4.13		3.02	9.17
Total dosee,f	Millirem	Person-rem	Millirem	Millirem		Millirem	Person-rem
Expected	2.41E-06	9.56E-05	9.33E-05	0.00263		(g)	(g)
Maximum	8.26E-06	3.27E-04	3.19E-04	0.00899		2.07E-05	1.82E-04
Minimum	1.22E-06	4.83E-05	4.72E-05	0.00133		(g)	(g)

Source: Blankenhorn (1994); Hess (1994g, h); Simpkins (1994a); and Chesney (1995).

a. MEI = maximally exposed individual.

b. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS. For aqueous releases, the dose is to the people using the Savannah River from SRS to the Atlantic Ocean.

c. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

d. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

e. Dose refers to committed effective dose equivalent (see glossary).

f. Total doses are for the 30-year period of interest.

g. Routine operations are not expected to produce aqueous releases.

---

Table E.4-15. Mixed wasteoffsite vendor dose distribution by isotope for alternative A.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc
Cesium-134	<1.0d	1.62
Cesium-137	1.68	1.92
Tritium	75.92	32.52
Plutonium-238	13.54	44.04
Plutonium-239	<1.0d	1.39
Strontium-90	1.49	<1.0d
Uranium-234	3.68	12.12
Uranium-236	<1.0d	2.13
Othere	3.69	4.26
Total dosef,g	Millirem	Person-rem
Expected	1.52E-05	6.93E-06
Maximum	3.88E-05	1.77E-05
Minimum	6.66E-06	3.03E-06

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-16. Consolidated Incineration Facilitydose distribution by isotope for alternative B.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	2.26	1.72	3.32	3.33
Cesium-134	19.92	10.88	15.99	15.78
Cesium-137	65.28	80.97	78.62	76.38
Strontium-90	7.50	2.80	<1.0d	<1.0d
Tritium	2.30	<1.0d	<1.0d	<1.0d
Othere	2.74	3.63	2.06	4.48
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	0.318	18.8	6.28	18.1
Maximum	0.689	32.6	9.76	32.4
Minimum	0.255	15.1	5.07	14.6

Source: Blankenhorn (1994); Hertel et al. (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose is to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-17. Onsite compactor facility dose distribution by isotope for alternative B.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	7.08	6.13	11.21	8.56
Cesium-134	6.13	3.94	5.15	3.90
Cesium-137	19.81	28.86	25.85	19.39
Europium-154	<1.0d	<1.0d	1.51	<1.0d
Tritium	18.44	18.31	11.37	12.11
Plutonium-238	31.18	29.68	33.96	41.53
Plutonium-239	<1.0d	<1.0d	<1.0d	1.35
Ruthenium-106	1.13	<1.0d	<1.0d	<1.0d
Strontium-90	8.36	4.44	1.75	2.16
Uranium-234	3.99	4.37	5.57	6.87
Othere	3.88	4.28	3.62	4.13
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	5.18E-08	2.05E-06	2.00E-06	5.64E-05
Maximum	5.18E-08	2.06E-06	2.00E-06	5.64E-05
Minimum	5.18E-08	2.05E-06	2.00E-06	5.64E-05

Source: Blankenhorn (1994); Hess (1994f, g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" category.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-18. Onsite vitrificationfacilities dose distribution by isotope for alternative B.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cesium-134	4.04	3.00	7.97	4.30
Cesium-137	13.21	22.25	39.07	20.75
Plutonium-238	67.42	61.29	42.37	61.47
Plutonium-239	12.26	11.16	7.80	11.16
Otherd	3.07	2.30	2.79	2.31
Total dosee,f	Millirem	Person-rem	Millirem	Millirem
Expected	0.561	24.4	4.52	23.8
Maximum	8.08	330	48.8	323
Minimum	0.315	12.5	1.60	12.2

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

e. Dose refers to committed effective dose equivalent (see glossary).

f. Total doses are for the 30-year period of interest.

---

Table E.4-19. Soil sort facility dose distribution by isotope for alternative B.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	7.08	6.13	11.21	8.56
Cesium-134	6.13	3.94	5.15	3.90
Cesium-137	19.81	28.86	25.85	19.39
Europium-154	<1.0d	<1.0d	1.51	<1.0d
Tritium	18.44	18.31	11.37	12.11
Plutonium-238	31.18	29.68	33.96	41.53
Plutonium-239	<1.0d	<1.0d	<1.0d	1.35
Ruthenium-106	1.13	<1.0d	<1.0d	<1.0d
Strontium-90	8.36	4.44	1.75	2.16
Uranium-234	3.99	4.37	5.57	6.87
Othere	3.88	4.28	3.62	4.13
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	2.87E-06	1.14E-04	1.11E-04	0.00312
Maximum	1.75E-05	6.93E-04	6.76E-04	0.0190
Minimum	8.17E-07	3.23E-05	3.16E-05	8.88E-04

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-20. Transuranic waste characterization/certification facilitydose distribution by isotope for alternative B.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Plutonium-238	83.65	83.66	83.85	83.89
Plutonium-239	15.38	15.37	15.17	15.13
Otherd	0.97	0.97	0.98	0.98
Total dosee,f	Millirem	Person-rem	Millirem	Millirem
Expected	0.111	4.19	4.68	161
Maximum	1.83	69.1	77.1	2,650
Minimum	0.0775	2.92	3.26	112

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

e. Dose refers to committed effective dose equivalent (see glossary).

f. Total doses are for the 30-year period of interest.

---

Table E.4-21. Containment building dose distribution by isotope for alternative B.

---

	Atmospheric releases (percent of total dose)					Aqueous releases (percent of total dose)
Radionuclides	MEIa	Populationb	640-meter uninvolved worker (2,100 feet)	100 meter uninvolved worker (328 feet)		MEIa	Populationb
Cobalt-60	7.08	6.13	11.21	8.56		<1.0c	5.97
Cesium-134	6.13	3.94	5.15	3.90		81.85	21.81
Cesium-137	19.81	28.86	25.85	19.39		<1.0c	<1.0c
Europium-154	<1.0c	<1.0c	1.51	<1.0c		<1.0c	<1.0c
Tritium	18.44	18.31	11.37	12.11		10.51	32.22
Plutonium-238	31.18	29.68	33.96	41.53		4.62	28.48
Plutonium-239	<1.0c	<1.0c	<1.0c	1.35		<1.0c	<1.0c
Ruthenium-106	1.13	<1.0c	<1.0c	<1.0c		<1.0c	2.37
Strontium-90	8.36	4.44	1.75	2.16		<1.0c	<1.0c
Uranium-234	3.99	4.37	5.57	6.87		<1.0c	<1.0c
Otherd	3.88	4.28	3.62	4.13		3.02	9.17
Total dosee,f	Millirem	Person-rem	Millirem	Millirem		Millirem	Person-rem
Expected	1.59E-06	6.31E-05	6.16E-05	1.78E-03		(g)	(g)
Maximum	5.55E-06	2.20E-04	2.14E-04	6.04E-03		1.41E-05	1.24E-04
Minimum	7.99E-07	3.16E-05	3.09E-05	8.69E-04		(g)	(g)

Source: Blankenhorn (1994); Hess (1994g, h); Simpkins (1994a); and Chesney (1995).

a. MEI = maximally exposed individual.

b. For atmospheric releases, the dose to the population populationwithin 80 kilometers (50 miles) of SRS. For aqueous releases, the dose is to the people using the Savannah River Savannah Riverfrom SRS to the Atlantic.

c. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

d. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

e. Dose refers to committed effective dose equivalent (see glossary).

f. Total doses are for the 30-year period of interest.

g. Routine operations are not expected to produce aqueous releases.

---

Table E.4-22. Offsite supercompaction, sorting, repackaging dose distribution by isotope for alternativeB.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc
Cesium-134	<1.0d	1.62
Cesium-137	1.68	1.92
Tritium	75.92	32.52
Plutonium-238	13.54	44.04
Plutonium-239	<1.0d	1.39
Strontium-90	1.49	<1.0d
Uranium-234	3.68	12.12
Uranium-236	<1.0d	2.13
Othere	3.69	4.26
Total dosef,g	Millirem	Person-rem
Expected	4.85E-04	2.21E-04
Maximum	6.86E-04	3.13E-04
Minimum	3.83E-04	1.74E-04

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-23. Offsite smelting, incineration, and metal melt dose distribution by isotope for alternativeB.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc
Cesium-134	31.68	31.37
Cesium-137	44.16	36.07
Strontium-90	11.09	3.18
Uranium-234	9.24	21.21
Uranium-236	<1.0d	3.71
Othere	3.83	4.46
Total dosef,g	Millirem	Person-rem
Expected	0.0514	0.346
Maximum	0.0927	0.624
Minimum	0.0377	0.254

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-24. Consolidated Incineration Facilitydose distribution by isotope for alternative C.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	2.26	1.72	3.32	3.35
Cesium-134	19.93	10.88	15.97	15.77
Cesium-137	65.45	81.11	78.67	76.46
Strontium-90	7.50	2.80	<1.0d	<1.0d
Othere	4.86	3.49	2.04	4.42
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	0.091	5.42	1.81	5.23
Maximum	0.215	12.60	4.12	12.00
Minimum	0.0667	3.95	1.32	3.81

Source: Blankenhorn (1994); Hertel et al. (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose is to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

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Table E.4-25. Compactor facilities dose distribution by isotope for alternative C.

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	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	7.08	6.13	11.21	8.56
Cesium-134	6.13	3.94	5.15	3.90
Cesium-137	19.81	28.86	25.85	19.39
Europium-154	<1.0d	<1.0d	1.51	<1.0d
Tritium	18.44	18.31	11.37	12.11
Plutonium-238	31.18	29.68	33.96	41.53
Plutonium-239	<1.0d	<1.0d	<1.0d	1.35
Ruthenium-106	1.13	<1.0d	<1.0d	<1.0d
Strontium-90	8.36	4.44	1.75	2.16
Uranium-234	3.99	4.37	5.57	6.87
Othere	3.88	4.28	3.62	4.13
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	2.40E-07	9.49E-06	9.27E-06	2.61E-04
Maximum	2.48E-07	9.82E-06	9.59E-06	2.70E-04
Minimum	1.99E-07	7.86E-06	7.67E-06	2.16E-04

Source: Blankenhorn (1994); Hess (1994f, g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

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Table E.4-26. Onsite vitrificationfacilities dose distribution by isotope for alternative C.

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	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	<1.0d	<1.0d	3.11	2.94
Strontium-90	6.41	2.51	<1.0d	<1.0d
Cesium-134	17.13	9.82	15.37	14.21
Cesium-137	56.08	22.99	75.48	68.69
Plutonium-238	13.96	9.81	3.99	9.93
Plutonium-239	2.54	<1.0d	<1.0d	<1.0d
Othere	3.88	4.86	2.05	4.24
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	5.20	293	92	283
Maximum	118	6,790	2,190	6,580
Minimum	2.56	141	42.70	136

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

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Table E.4-27. Soil sort facility dose distribution by isotope for alternative C.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	8.37	8.14	19.89	15.29
Cesium-134	7.38	5.15	9.57	7.19
Cesium-137	24.12	38.23	46.91	34.70
Europium-154	<1.0d	<1.0d	2.78	2.15
Tritium	11.81	10.41	3.89	7.38
Plutonium-238	29.92	25.60	12.37	24.98
Plutonium-239	<1.0d	<1.0d	<1.0d	<1.0d
Ruthenium-106	1.32	<1.0d	<1.0d	<1.0d
Strontium-90	9.92	4.74	<1.0d	<1.0d
Uranium-234	3.34	3.49	<1.0d	4.15
Othere	3.82	4.24	4.58	4.16
Total dosef,g	Millirem	Person-rem	Millirem	Millirem
Expected	2.03E-06	9.38E-05	2.48E-05	9.40E-05
Maximum	1.18E-05	5.47E-04	1.45E-04	5.47E-04
Minimum	5.52E-07	2.56E-05	6.76E-06	2.56E-05

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

---

Table E.4-28. Transuranic waste characterization/certification facilitydose distribution by isotope for alternative C.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Plutonium-238	83.65	83.66	83.85	83.89
Plutonium-239	15.38	15.37	15.17	15.13
Otherd	0.97	0.97	0.98	0.98
Total dosee,f	Millirem	Person-rem	Millirem	Millirem
Expected	0.111	4.19	4.68	161
Maximum	1.83	69.1	77	2,650
Minimum	0.0775	2.92	3.26	112

Source: Blankenhorn (1995); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

e. Dose refers to committed effective dose equivalent (see glossary).

f. Total doses are for the 30-year period of interest.

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Table E.4-29. Containment building dose distribution by isotope for alternative C.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Cobalt-60	<1.0d	<1.0d	<1.0d	<1.0d
Cesium-134	<1.0d	<1.0d	<1.0d	<1.0d
Cesium-137	<1.0d	<1.0d	<1.0d	<1.0d
Europium-154	<1.0d	<1.0d	<1.0d	<1.0d
Tritiume	99	99	99	99
Plutonium-238	<1.0d	<1.0d	<1.0d	<1.0d
Plutonium-239	<1.0d	<1.0d	<1.0d	<1.0d
Ruthenium-106	<1.0d	<1.0d	<1.0d	<1.0d
Strontium-90	<1.0d	<1.0d	<1.0d	<1.0d
Uranium-234	<1.0d	<1.0d	<1.0d	<1.0d
Otherf	<1.0d	<1.0d	<1.0d	<1.0d
Total doseg,h	Millirem	Person-rem	Millirem	Millirem
Expected	2.17E-02	8.52E-01	5.16E-01	1.55E+01
Maximum	2.17E-02	8.52E-01	5.16E-01	1.55E+01
Minimum	2.17E-02	8.52E-01	5.16E-01	1.55E+01

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Tritium releases due to processing of tritium contaminated mercury pumps.

f. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

g. Dose refers to committed effective dose equivalent (see glossary).

h. Total doses are for the 30-year period of interest.

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Table E.4-30. Mixed wasteoffsite vendor dose distribution by isotope for alternative C.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc
Cesium-134	<1.0d	1.62
Cesium-137	1.68	1.92
Tritium	75.92	32.52
Plutonium-238	13.54	44.04
Plutonium-239	<1.0d	1.39
Strontium-90	1.49	<1.0d
Uranium-234	3.68	12.12
Uranium-236	<1.0d	2.13
Othere	3.69	4.26
Total dosef,g	Millirem	Person-rem
Expected	1.52E-05	6.93E-06
Maximum	3.88E-05	1.77E-05
Minimum	6.66E-06	3.03E-06

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

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Table E.4-31. Offsite smelter dose distribution by isotope for alternative C.

---

	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc
Cesium-134	31.68	31.37
Cesium-137	44.16	36.07
Strontium-90	11.09	3.18
Uranium-234	9.24	21.21
Uranium-236	<1.0d	3.71
Othere	3.83	4.46
Total dosef,g	Millirem	Person-rem
Expected	0.0108	0.0728
Maximum	0.0284	0.191
Minimum	0.00607	0.0409

Source: Blankenhorn (1994); Hess (1994g); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. The contribution from this radionuclide to the given receptor is less than or equal to 1.0 percent and is accounted for in the "Other" total.

e. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

f. Dose refers to committed effective dose equivalent (see glossary).

g. Total doses are for the 30-year period of interest.

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Table E.4-32. F/H-Area Effluent Treatment Facility dose distribution by isotope for all alternatives.

---

	Aqueous releases (percent of total dose)
Radionuclides	MEIb	Populationc
Cesium-137	70.52	18.79
Tritium	28.95	79.91
Otherd	.053	1.30
	Millirem	Person-rem
Total dosee,f,g	0.0208	0.203

Source: Blankenhorn (1994); Hess (1994g, i); Poirier and Wiggins (1994), Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce atmospheric releases.

b. MEI = maximally exposed individual.

c. For aqueous releases, the dose is to the people using the Savannah River from SRS to Atlantic Ocean.

d. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

e. Dose refers to committed effective dose equivalent (see glossary).

f. Total doses are for the 30-year period of interest.

g. Includes releases from processing of Defense Waste Processing Facility recycle. Remains essentially constant for all alternatives.

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Table E.4-33. M-Area Vendor Treatment Facility dose distribution by isotope for all alternatives.

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	Atmospheric releases (percent of total dose)
Radionuclides	MEIb	Populationc	640-meter uninvolved worker (2,100 feet)	100-meter uninvolved worker (328 feet)
Uranium-234	32.67	31.49	32.10	32.31
Uranium-238	64.93	65.98	65.48	65.31
Otherd	2.40	2.53	2.43	2.38
Total dosee,f	Millirem	Person-rem	Millirem	Millirem
All alternatives	0.00371	0.00851	0.00856	0.304

Source: Blankenhorn (1994); Hamby (1994); Hess (1994g, j); Simpkins (1994a); and Chesney (1995).

a. Routine operations are not expected to produce aqueous releases.

b. MEI = maximally exposed individual.

c. For atmospheric releases, the dose to the populationwithin 80 kilometers (50 miles) of SRS.

d. Refer to Table E.4-34 for a listing of the radionuclides included in "Other."

e. Dose refers to committed effective dose equivalent (see glossary).

f. Total doses are for the 30-year period of interest.

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Table E.4-34. Radionuclides listed under "Other" in Tables E.4-9 through E.4-33.

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Silver-110	Curium-246	Promethium-147	Strontium-89
Silver-110m	Curium-248	Promethium-148	Strontium-90
Aluminum-26	Chromium-51	Promethium-148m	Tantalum-182
Americium-241	Europium-154	Praseodymium-143	Terbium-160
Americium-243	Europium-155	Praseodymium-144	Technetium-99
Barium-137m	Europium-156	Plutonium-238	Tellurium-125m
Barium-140	Iron-55	Plutonium-239	Tellurium-127
Carbon-14	Iron-59	Plutonium-240	Tellurium-127m
Cadmium-113	Tritium	Plutonium-241	Tellurium-129
Cerium-141	Hafnium-181	Plutonium-242	Tellurium-129m
Cerium-144	Iodine-129	Rhodium-106	Uranium-233
Cobalt-58	Indium-113m	Ruthenium-103	Uranium-234
Cobalt-60	Indium-114	Ruthenium-103m	Uranium-235
Cesium-134	Krypton-85	Ruthenium-106	Uranium-236
Cesium-135	Lanthanum-140	Antimony-125	Uranium-238
Cesium-137	Manganese-54	Scandium-46	Yttrium-90
Californium-249	Nickel-59	Selenium-79	Yttrium 91
Californium-251	Nickel-63	Samarium-151	Zinc-65
Californium-252	Niobium-94	Tin-113	Zirconium-93
Californium-242	Niobium-95	Tin-119m	Zirconium-95
Californium-243	Niobium-95m	Tin-121m	Other Alpha
Californium-244	Neptunium-237	Tin-123	Other B/Gb
Californium-245	Palladium-107	Tin-126

Source: Blankenhorn (1994), Hunt (1994), and Chesney (1995).

a. Each of the listed radionuclides contribute less than or equal to 1.0 percent of the total dose unless identified as a major contributor to total dose.

b. B/G = Unidentifiable beta/gamma emitting radionuclides.

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SECTION 5

ENVIRONMENTAL JUSTICE

LOCAL ARea DOSES

Figure 4-6 is a map of the area around SRS out to a distance of 80 kilometers (50 miles). This map identifies annular sectors around SRS by a letter-number combination. Table E.5-1 uses these annular sector identifiers to show:

- The fraction of total population dose in each annular sector.

- The fraction of total population dose that the average person in each annular sector will receive (the per capita dose in each sector).

The total population dose for any of the alternatives and forecasts can be multiplied by the appropriate fraction associated with any annular sector to obtain the total population dose to the annular sector, or the per capita dose in that sector for any of the forecasts.

Tables E.5-2 through E.5-11 show the estimated per capita 30-year dose for identified types of communities within the 80 kilometer region for each of the alternatives and forecasts.

Table E.5-1. Annular sector factors for local dose evaluations.

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	Fraction of total population dose in annular sector						Fraction of total population dose that is dose to average person in annular sector
Annular number and distance from center of SRS	1 (5-10 mi)b	2 (10-20 mi)	3 (20-30 mi)	4 (30-40 mi)	5 (40-50 mi)		1 (5-10 mi)	2 (10-20 mi)	3 (20-30 mi)	4 (30-40 mi)	5 (40-50 mi)
Sectorc
A (N)	3.09E-04	2.79E-02	2.70E-02	8.63E-03	1.49E-02		1.19E-05	5.25E-06	2.69E-06	1.70E-06	1.22E-06
B (NNE)	5.86E-05	5.75E-03	4.71E-03	6.5-E-03	1.51E-02		9.77E-06	4.35E-06	2.28E-06	1.46E-06	1.05E-06
C (NE)	1.02E-05	1.35E-02	7.03E-03	8.33E-03	1.17E-02		1.02E-05	4.57E-06	2.40E-06	1.58E-06	1.15E-06
D (ENE)	2.76E-04	1.29E-02	9.56E-03	7.43E-03	4.15E-02		1.02E-05	4.12E-06	2.13E-06	1.39E-06	1.02E-06
E (E)	1.28E-03	2.21E-02	8.91E-03	9.67E-03	3.48E-03		8.27E-06	3.27E-06	1.68E-06	1.10E-06	8.02E-07
F (ESE)	2.55E-04	4.37E-03	2.79E-03	2.56E-03	2.24E-03		7.07E-06	2.81E-06	1.45E-06	9.44E-07	6.90E-07
G (SE)	1.29E-04	1.11E-03	6.78E-03	4.54E-03	4.25E-03		4.96E-06	2.02E-06	1.04E-06	6.79E-07	4.95E-07
H (SSE)	1.61E-04	6.63E-04	6.92E-04	8.10E-04	1.12E-03		4.04E-06	1.70E-06	9.00E-07	5.97E-07	4.40E-07
I (S)	2.25E-06	5.48E-04	7.24E-04	2.69E-03	9.34E-04		2.25E-06	9.83E-07	5.44E-07	3.71E-07	2.80E-07
J (SSW)	1.29E-05	2.42E-03	2.90E-03	4.11E-03	2.12E-03		6.46E-06	2.70E-06	1.45E-06	9.82E-07	7.22E-07
K (SW)	1.87E-04	4.17E-03	5.22E-03	4.06E-03	3.02E-03		1.10E-06	4.41E-06	2.33E-06	1.56E-06	1.14E-06
L (WSW)	5.18E-04	3.87E-03	1.32E-02	2.84E-03	5.31E-03		8.64E-06	3.50E-06	1.86E-06	1.24E-06	9.13E-07
M (W)	3.43E-04	8.52E-03	1.11E-02	7.51E-03	4.62E-03		6.24E-06	2.57E-06	1.40E-06	9.40E-07	6.82E-07
N (WNW)	2.89E-03	9.16E-03	1.57E-01	4.99E-02	8.33E-03		6.43E-06	2.74E-06	1.47E-06	9.92E-07	7.22E-07
O (NW)	2.23E-03	2.08E-02	1.57E-01	3.04E-02	2.48E-03		8.22E-06	3.52E-06	1.79E-06	1.14E-06	8.21E-07
P (NNW)	3.97E-03	8.47E-02	6.28E-02	9.74E-03	6.34E-03		1.09E-05	4.70E-06	2.31E-06	1.46E-06	1.04E-06

a. Source: Simpkins (1994b).

b. No population resides within 8 kilometers (5 miles) of the center of SRS.

c. Sector letter is letter shown on Figure 4-6. Letters in parentheses after the sector letter indicate the compass direction of the sector.

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Table E.5-2. Estimated per capita 30-year dose for identified communities in 80-kilometer (50-mile) region for the no¡action alternative.

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Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	9.37E-08	8.49E-08	9.97E-08	8.67E-08	9.02E-08	9.55E-08
0-32 km (0-20 miles)	4.50E-08	3.54E-08	6.20E-08	4.10E-08	4.27E-08	4.57E-08
0-48 km (0-30 miles)	2.42E-08	1.89E-08	2.95E-08	2.49E-08	2.57E-08	2.37E-08
0-64 km (0-40 miles)	1.97E-08	1.73E-08	2.28E-08	1.94E-08	2.11E-08	1.93E-08
0-80 km (0-50 miles)	1.84E-08	1.59E-08	2.03E-08	1.88E-08	1.93E-08	1.82E-08
Total population populationdose = 0.0086 person-rem.

Table E.5-3. Estimated per capita 30-year dose for identified communities in 80-kilometer (50-mile) region for alternative A - expected waste forecast.

---

Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	1.85E-04	1.68E-04	1.97E-04	1.71E-04	1.78E-04	1.89E-04
0-32 km (0-20 miles)	8.89E-05	7.00E-05	1.22E-04	8.11E-05	8.45E-05	9.04E-05
0-48 km (0-30 miles)	4.78E-05	3.74E-05	5.84E-05	4.92E-05	5.09E-05	4.69E-05
0-64 km (0-40 miles)	3.89E-05	3.43E-05	4.51E-05	3.83E-05	4.17E-05	3.82E-05
0-80 km (0-50 miles)	3.64E-05	3.15E-05	4.01E-05	3.71E-05	3.81E-05	3.60E-05
Total population populationdose = 17 person-rem.

Table E.5-4. Estimated per capita 30-year dose for identified communities in 80-kilometer (50-mile) region for alternative A - minimum waste forecast.

---

Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	8.93E-05	8.10E-05	9.51E-05	8.26E-05	8.60E-05	9.10E-05
0-32 km (0-20 miles)	4.29E-05	3.37E-05	5.91E-05	3.91E-05	4.07E-05	4.36E-05
0-48 km (0-30 miles)	2.30E-05	1.81E-05	2.82E-05	2.37E-05	2.45E-05	2.26E-05
0-64 km (0-40 miles)	1.88E-05	1.65E-05	2.17E-05	1.85E-05	2.01E-05	1.84E-05
0-80 km (0-50 miles)	1.76E-05	1.52E-05	1.94E-05	1.79E-05	1.84E-05	1.73E-05
Total population populationdose = 8.2 person-rem.

Table E.5-5. Estimated per capita 30-year dose for identified communities in 80-kilometer (50-mile) region for alternative A - maximum waste forecast.

---

Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	1.12E-03	1.02E-03	1.19E-03	1.04E-03	1.08E-03	1.14E-03
0-32 km (0-20 miles)	5.39E-04	4.24E-04	7.42E-04	4.91E-04	5.12E-04	5.48E-04
0-48 km (0-30 miles)	2.89E-04	2.27E-04	3.54E-04	2.98E-04	3.08E-04	2.84E-04
0-64 km (0-40 miles)	2.36E-04	2.08E-04	2.73E-04	2.32E-04	2.53E-04	2.32E-04
0-80 km (0-50 miles)	2.21E-04	1.91E-04	2.43E-04	2.25E-04	2.31E-04	2.18E-04
Total population populationdose = 103 person-rem.

Table E.5-6. Estimated per capita 30-year dose for identified communities in 80-kilometer (50-mile) region for alternative C - expected waste forecast.

---

Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	3.29E-03	2.98E-03	3.50E-03	3.04E-03	3.17E-03	3.35E-03
0-32 km (0-20 miles)	1.58E-03	1.24E-03	2.18E-03	1.44E-03	1.50E-03	1.61E-03
0-48 km (0-30 miles)	8.49E-04	6.65E-04	1.04E-03	8.73E-04	9.04E-04	8.33E-04
0-64 km (0-40 miles)	6.92E-04	6.09E-04	8.01E-04	6.81E-04	7.41E-04	6.79E-04
0-80 km (0-50 miles)	6.47E-04	5.59E-04	7.13E-04	6.59E-04	6.76E-04	6.39E-04
Total population populationdose = 302 person-rem.

Table E.5-7. Estimated per capita 30-year dose for identified communities in 80-kilometer (50-mile) region for alternative C - minimum waste forecast.

---

Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	1.61E-03	1.46E-03	1.72E-03	1.49E-03	1.55E-03	1.64E-03
0-32 km (0-20 miles)	7.74E-04	6.09E-04	1.07E-03	7.06E-04	7.35E-04	7.87E-04
0-48 km (0-30 miles)	4.16E-04	3.26E-04	5.08E-04	4.28E-04	4.43E-04	4.08E-04
0-64 km (0-40 miles)	3.39E-04	2.99E-04	3.92E-04	3.34E-04	3.63E-04	3.33E-04
0-80 km (0-50 miles)	3.17E-04	2.74E-04	3.50E-04	3.23E-04	3.31E-04	3.13E-04
Total population populationdose = 148 person-rem.

Table E.5-8. Estimated per capita 30-year dose for identified communities in 80-kilometer (50-mile) region for alternative C - maximum waste forecast.

---

Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	7.49E-02	6.79E-02	7.98E-02	6.93E-02	7.22E-02	7.64E-02
0-32 km (0-20 miles)	3.60E-02	2.83E-02	4.96E-02	3.28E-02	3.42E-02	3.66E-02
0-48 km (0-30 miles)	1.93E-02	1.52E-02	2.36E-02	1.99E-02	2.06E-02	1.90E-02
0-64 km (0-40 miles)	1.58E-02	1.39E-02	1.82E-02	1.55E-02	1.69E-02	1.55E-02
0-80 km (0-50 miles)	1.47E-02	1.27E-02	1.62E-02	1.50E-02	1.54E-02	1.46E-02
Total population populationdose = 6,880 person-rem.

Table E.5-9. Estimated per capita 30-year dose for identified communities in 80-kilometer (50-mile) region for alternative B - expected waste forecast.

---

Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	5.01E-04	4.54E-04	5.33E-04	4.64E-04	4.83E-04	5.11E-04
0-32 km (0-20 miles)	2.41E-04	1.89E-04	3.31E-04	2.19E-04	2.29E-04	2.45E-04
0-48 km (0-30 miles)	1.29E-04	1.01E-04	1.58E-04	1.33E-04	1.38E-04	1.27E-04
0-64 km (0-40 miles)	1.05E-04	9.28E-05	1.22E-04	1.04E-04	1.13E-04	1.03E-04
0-80 km (0-50 miles)	9.85E-05	8.52E-05	1.09E-04	1.00E-04	1.03E-04	9.73E-05
Total population populationdose = 46 person-rem.

Table E.5-10. Estimated per capita 30-year dose for identified communities in 80-kilometer (50¡mile) region for alternative B - minimum waste forecast.

---

Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	3.27E-04	2.96E-04	3.48E-04	3.02E-04	3.15E-04	3.33E-04
0-32 km (0-20 miles)	1.57E-04	1.23E-04	2.16E-04	1.43E-04	1.49E-04	1.60E-04
0-48 km (0-30 miles)	8.43E-05	6.61E-05	1.03E-04	8.68E-05	8.98E-05	8.28E-05
0-64 km (0-40 miles)	6.87E-05	6.05E-05	7.95E-05	6.77E-05	7.36E-05	6.74E-05
0-80 km (0-50 miles)	6.43E-05	5.56E-05	7.09E-05	6.55E-05	6.72E-05	6.35E-05
Total population populationdose = 30 person-rem.

Table E.5-11. Estimated per capita 30-year dose for identified communities in 80-kilometer (50¡mile) region for alternative B - maximum waste forecast.

---

Distance	All	Persons of color more than 50% of Population	Persons of color 35% to 50% of Population	Persons of color less than 35% of Population	Low incomes more than 25% of population population	Low incomes less than 25% of Population
0-16 km (0-10 miles)	4.43E-03	4.02E-03	4.72E-03	4.10E-03	4.27E-03	4.52E-03
0-32 km (0-20 miles)	2.13E-03	1.67E-03	2.93E-03	1.94E-03	2.02E-03	2.16E-03
0-48 km (0-30 miles)	1.14E-03	8.97E-04	1.40E-03	1.18E-03	1.22E-03	1.12E-03
0-64 km (0-40 miles)	9.32E-04	8.21E-04	1.08E-03	9.18E-04	9.99E-04	9.15E-04
0-80 km (0-50 miles)	8.72E-04	7.54E-04	9.61E-04	8.89E-04	9.12E-04	8.61E-04
Total population populationdose = 407 person-rem.

6.0 REFERENCES

ACGIH (American Conference of Governmental Industrial Hygienists), 1993, "Threshold Limit Values for Chemical Substances and Physical Agents and Biological Exposure Indices," Technical Affairs Office, Cincinnati, Ohio.

Arnett, M. W., 1994, Savannah River Site Environmental Data for 1993, WSRC-TR-94-077, Westinghouse Savannah River Company, Aiken, South Carolina.

Blankenhorn, J. A., 1994, Westinghouse Savannah RiverCompany, Aiken, South Carolina, Interoffice Memorandum to L. C. Thomas, Westinghouse Savannah River Company, Aiken, South Carolina, "Waste Management Environmental Impact Statement Waste Streams (U)," SWE-SWO-94-0200, August 10.

Chesney, S. D., 1995, Halliburton NUS Corporation, Aiken, South Carolina, Interoffice Memorandum to B. H. Bradford, Halliburton NUS Corporation, Aiken, South Carolina, "Dose Analysis for Waste Management Environmental Impact Statement," RHSES-002, Revision 1, June 30.

EPA (U.S. Environmental Protection Agency), 1994, Environmental Justice Initiatives 1993, EPA 200-R-93-001, Washington, D.C., February.

Cummins, C. L., D. K. Martin, and J. L. Todd, 1991, Savannah River Site Environmental Report for 1990, WSRC-IM-91-28, Westinghouse Savannah River Company, Aiken, South Carolina.

Hamby, D. M., 1994, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum to J. B. Pickett, Westinghouse Savannah River Company, Aiken, South Carolina, "Modeling Results for an Atmospheric Release of U-235 from M-Area," SRT-940013, February 1.

Hertel, N. E., H. M. Coward, J. A. Mulholland, and M. G. Robinson, 1994, "Dose Comparison for Air Emissions from the Incineration and Compaction of SRS Low Level Radioactive Job Control Wastes," GT/ERDA-94041-001, Revision 3, Georgia Institute of Technology, Atlanta, Georgia, October 10.

Hess, M. L., 1994a, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Revised Spreadsheets Min. Mixed Case C," ESH­NEP­94-0213, October 21.

Hess, M. L., 1994b, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Revised Spreadsheets LLW Case A," ESH­NEP­94­0215, October 24.

Hess, M. L., 1994c, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Revised Spreadsheets All TRU Except No-Action," ESH-NEP-94-0216, October 24.

Hess, M. L., 1994d, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Revised Spreadsheets Min Case B LLW and Case B TRU," ESH-NEP-94-0223, October 27.

Hess, M. L., 1994e, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Revised Annual Worker Dose by Facility," ESH­NEP­94-0212, October 21.

Hess, M. L., 1994f, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Emission Factors," ESH-NEP-94-0161, September 10.

Hess, M. L., 1994g, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Complete Set of Flowsheets," ESH­NEP­94­0241, November 15.

Hess, M. L., 1994h, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Containment Building Emissions," ESH­NEP­94­0206, October 18.

Hess, M. L., 1994i, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Decontamination Factors for Effluent Treatment Facility," ESH-NEP-94-0136, September 23.

Hess, M. L., 1994j, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum Data Transmittal to H. L. Pope, U.S. Department of Energy, Savannah River Operations Office, Aiken, South Carolina, "Air Emissions Estimate for the M-Area Vendor Treatment Process," ESH-NEP-94-0131, September 20.

HNUS (Halliburton NUS Corporation), 1995, Transportation Radiological Analysis for the Waste Management Environmental Impact Statement, Savannah River Center, Aiken, South Carolina.

Hunt, P. D., 1994, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum to R. C. Shank, Westinghouse Savannah River Company, Aiken, South Carolina, "1027 Hazard Categorization Re-Evaluation," SWE-SWE-94-0176, April 7.

NIOSH (National Institute of Safety and Health), 1990, Pocket Guide to Chemical Hazards, National Institute for Occupational Safety and Health, Cincinnati, Ohio.

Poirier, M. R. and Wiggins, A. W., 1994, Westinghouse Savannah River Company, Aiken, South Carolina, Interoffice Memorandum to J. P. Wood, Westinghouse Savannah River Company, Aiken, South Carolina, "Treating Environmental Restoration Purge Water at the ETF (U)," WSRC­RP-94-00632, June 28.

Rollins, E. M., 1995, Halliburton NUS Corporation, Aiken, South Carolina, Interoffice Memorandum to B. H. Bradford, Halliburton NUS Corporation, Aiken, South Carolina, "Traffic Analysis for Waste Management Environmental Impact Statement," RHSES-001, Revision 1, June 30.

SCDHEC (South Carolina Department of Health and Environmental Control), 1976, "State Safe Drinking Water Act of 1976, "South Carolina Code of Laws, Section 61-58.

Simpkins, A. A., 1994a, Westinghouse Savannah RiverCompany, Aiken, South Carolina, Interoffice Memorandum to J. J. Mayer, Westinghouse Savannah River Company, Aiken, South Carolina, "Waste Management eis- Environmental Dosimetry Calculations," SRT-ETS-940121-draft, July 26.

Simpkins, A. A., 1994b, Westinghouse Savannah RiverCompany, Aiken, South Carolina, Interoffice Memorandum to C. B. Shedrow, Westinghouse Savannah River Company, Aiken, South Carolina, "Interim Management of Nuclear Materials eis- Environmental Dosimetry Calculations," SRT­ETS­940079.

Sinkowski, D., 1995, Halliburton NUS Corporation, Aiken, South Carolina, Interoffice Memorandum to B. H. Bradford, Halliburton NUS Corporation, Aiken, South Carolina, "WMCIS Transportation Analysis for LLW Volume Reduction," May 17.

Washburn, T. A., 1995, Halliburton NUS Corporation, Aiken, South Carolina, Interoffice Memorandum to B. H. Bradford, Halliburton NUS Corporation, Aiken, South Carolina, "Transportation Radiological Analysis for the Waste Management Environmental Impact Statement," RHSES-003, Revision 1, June 30.

Wike, L. D., R. W. Shipley, J. A. Bowers, A. L. Bryan, C. L. Cummins, B. R. Del Carmen, G. P. Friday, J. E. Irwin, H. E. Mackey, J. J. Mayer, E. A. Nelson, M. H. Paller, V. A. Rogers, W. L. Specht, and E. W. Wilde, 1994, SRS Ecology Environmental Information Document, WSRC-TR-93, Westinghouse Savannah RiverCompany, Aiken, South Carolina.

WSRC (Westinghouse Savannah River Company), 1993, SCDHEC Regulation No. 62.5 Standard No. 2 and Standard No. 8, Compliance Modeling Input/Output Data, ESH-ESS-93-0531, Savannah River Site, Aiken, South Carolina.

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