PUBLIC HEALTH ASSESSMENT
IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LABORATORY (U.S. DEPARTMENT OF ENERGY)
[a/k/a IDAHO NATIONAL ENGINEERING LABORATORY (USDOE)]
IDAHO FALLS, BUTTE, CLARK, JEFFERSON AND BIN COUNTIES, IDAHO
Table A-1. Maximum Concentration of Non-Radiological Contaminants in On-Site Groundwater Monitoring Wells
Contaminant | On-Site Monitoring Wells | Comparison Value (ppb) | |||
Maximum Conc. (ppb) | Location | Date | Detection Frequency/ Total Sample | ||
VOCs | |||||
1,4-dichlorobenzene | 22 | Unspecified | 02/14/91 | 13/665 | 0.4 (RBC) |
1,1-dichloroethene | 19 | Unspecified | 11/21/96 | 52/1050 | 0.06 (CREG) |
1,2-dichloroethane | 6 | Unspecified | 10/11/94 | 6/702 | 0.4 (CREG) |
1,2-dichloroethene (total) | 9,900 | Unspecified | 11/21/95 | 83/382 | 55 (RBC) |
1,2-dichloroethylene (cis) | 7,700 | Unspecified | 04/26/94 | 205/651 | 70 (MCL) |
1,2-dichloroethylene (trans) | 3,900 | Unspecified | 04/26/94 | 146/420 | 200 (RMEG) |
2,4-dinitrophenol | 90 | Unspecified | 02/14/91 | 1/46 | 20 (RMEG) |
1,1,1-trichloroethane | 6,800 | RWMC | 08/12/97 | 13/22 | 200 (MCL) |
1,1,2-trichloroethane | 5 | Unspecified | 07/01/93 | 15/1060 | 0.6 (CREG) |
1,1,2,2-tetrachloroethane | 4 | Unspecified | 10/03/95 | 7/713 | 0.2 (CREG) |
1,2,3-trichloropropane | 46 | Unspecified | 08/10/93 | 4/541 | 0.002 (RBC) |
Acetonitrile | 440 | Unspecified | 07/20/98 | 11/263 | 120 (RBC) |
Benzene | 13 | Unspecified | 06/04/96 | 33/1,027 | 2 (CREG) |
Bromodichloromethane | 8 | Unspecified | 11/16/94 | 5/1033 | 0.6 (CREG) |
Carbon Tetrachloride | 8,900 | RWMC perched | NA | 167/1,058 | 0.3 (CREG) |
Chlorodibromomethane | 2 | Unspecified | 02/15/95 | 3/697 | 0.4 (CREG) |
Chloroform | 1,200 | D06-DL02 | 04/29/97 | 186/1,060 | 6 (CREG) |
Chloromethane | 490 | Unspecified | 11/14/94 | 19/697 | 2.1 (RBC) |
Methylene Chloride | 750 | Unspecified | 09/08/97 | 323/1,062 | 5 (CREG) |
Trichloroethylene | 32,000 | TAN | 06/16/93 | 585/1,068 | 5 (MCL) |
Tetrachloroethylene | 110 | TAN | 04/26/94 | 413/1063 | 5 (MCL) |
Toluene | 730 | TAN | 07/07/97 | 331/1,053 | 700 (IEMEG) |
Vinyl Chloride | 14 | Unspecified | 11/21/95 | 8/702 | 0.02 (CREG) |
SVOCs, PCBs, and Pesticides | |||||
Di(2-Ethylhexyl)phthalate | 370 | Unspecified | 05/16/95 | 59/179 | 3 (CREG) |
Aroclor 1254 | 3.6 | Unspecified | 10/11/94 | 1/38 | 0.7 (CEMEG) |
Metals | |||||
Antimony | 867 | TRA | 02/12/91 | 6 (MCL) | |
Arsenic | 1,080 | TRA | 02/12/91 | 504/1,319 | 0.02 |
Barium | 25,300 | Unspecified Perched | 12/01/98 | 1,116/1,131 | 700 (RMEG) |
Boron | 3,930 | Unspecified | 07/01/93 | 5/5 | 100 (IEMEG) |
Cadmium | 2,360 | RWMC Perched | 12/01/98 | 269/1,454 | 5 (MCL) |
Chromium (Total) | 56,000 | Unspecified | 04/28/96 | 908/1,466 | no value |
Chromium (Hexavalent) | 790 | USGS-53 | 07/10/95 | 101/166 | 100 (RMEG) |
Lead | 118,000 | Unspecified Perched | 12/01/98 | 15 (EPA Action Level) | |
Manganese | 237,000 | Unspecified Perched | 12/01/98 | 629/1,249 | 500 (RMEG) |
Mercury (Metallic) | 394 | TRA | 02/13/91 | no value | |
Nickel | 12,200 | Unspecified Perched | 12/01/98 | 303/1,028 | 700 (RMEG) |
Nitrate | 790,000 | Unspecified | 01/25/91 | 414/456 | 10,000 (MCL) |
Thallium | 197 | Unspecified | 07/03/90 | 48/997 | 2 (MCL) |
Sources: ATSDR 2000; USGS 1997.
Key: CREG = ATSDR's cancer risk evaluation guide; CEMEG = ATSDR's chronic environmental media evaluation guide; CV = comparison value IEMEG = ATSDR's intermediate environmental media evaluation guide; GWM = groundwater monitoring well; MCL = EPA's maximum contaminant level; ppb = parts per billion; RBC = EPA Region 3's risk-based concentrations; RMEG = ATSDR's reference dose media evaluation guide.
Note: Maximum concentrations were detected in groundwater samples from the Snake River Plain Aquifer unless otherwise specified as collected from the perched aquifer.
Table A-2. Maximum Concentration of Radionuclides
in On-Site Groundwater Monitoring Wells
Radionuclide | Groundwater Monitor Well | Groundwater Monitor Well-Perched | Comparison Values (pCi/L) | |||||
Conc. pCi/L (Bq/L) | Sample Location | Sample Date | Conc. pCi/L (Bq/L) | Sample Location | Sample Date | Value | Type | |
Radioactivity | ||||||||
Gross alpha | 4,700 (173.9) | INTEC | 12/93 | 8.3 (0.2) | INTEC | 10/94 | 15 | EPA MCL |
Gross beta | 949,000 (35,113) | INTEC | 12/93 | 148 (5.7) | TRA | 5/99 | 50 | EPA MCL |
Specific Radionuclide | ||||||||
Cesium-137 | 2,240 (82.8) | TAN | 7/92 | nd | 200 | EPA MCL | ||
Cobalt-60 | 1,390 (51.4) | TAN | 11/94 | nd | 100 | EPA MCL | ||
Iodine-129 | 17 (0.6) | RWMC | 4/96 | 11.8 (0.4) | INTEC | 12/95 | 1 | EPA MCL |
Radium-226 | 190 (7) | TAN | 9/97 | 396 (14.6) | TRA | 7/97 | 5 | EPA MCL |
Strontium-90 | 516,000 (19,092) | INTEC | 12/93 | 179 (6.6) | TRA | 7/93 | 8,000 | ATSDR RMEG |
Tritium | 75,500 (2,793.5) | INTEC | 1/95 | 746,000 (27,602) | TRA | 10/93 | 20,000 | EPA MCL |
Uranium (Total) | 49 (1.8) | RWMC | 4/97 | 41.6 (1.6) | RWMC | 11/99 | 30 | EPA MCL |
Source: ATSDR 2000.
Key: Bq/L = becquerel per liter; MCL = EPA's maximum contaminant level; nd = not detected; pCi/L = picocuries
per liter; RMEG = ATSDR's reference dose media evaluation guide.
Note: Uncertainty values were not provided in FFIMS data set (ATSDR 2000).
Table A-3. Maximum Concentration of Non-Radiological
Contaminants in On-Site Surface Soil
Non-Radiological Contaminant | Concentration (ppm) | Comparison Value (ppm) | ||
Maximum | Date | Value | Type | |
Metals | ||||
Arsenic | 13.8 | 1/13/94 | 0.5 | CREG |
Cadmium | 11.2 | 4/27/93 | 10 | EMEG |
Mercury | 233 | 9/28/94 | 23 | SSL |
Semivolatile Organic Compounds | ||||
Benzo(a)pyrene | 1 | 6/22/99 | 0.78 | CREG |
di(2-Ethylhexyl)phthalate | 110 | 3/12/97 | 50 | CREG |
Explosives | ||||
2,4,6-Trinitrotoluene | 79,000 | 6/1/99 | 20 | CREG |
Polychlorinated Biphenyls | ||||
Aroclor 1254 | 4.3 | 7/2/98 | 1 | EMEG |
Aroclor 1260 | 290 | 3/12/97 | 2.9 | RBC |
Source: ATSDR 2000.
Key: CREG = ATSDR's cancer risk evaluation guide; EMEG =ATSDR's environmental media evaluation guide; ppm = parts per million; RBC = EPA Region 3's risk-based concentration; SSL = EPA's soil screening level.
Table A-4. Maximum Radionuclide Concentrations
in On-Site Surface Soil
Radionuclide | Concentration pCi/g (Bq/kg) | Estimated Dose mrem (mSv) | ||
Maximum | Location | Date | ||
Radioactivity | ||||
Gross alpha | 330 (12,210) | TSF | 6/93 | no value |
Gross beta | 25,600 (947,200) | TSF | 6/93 | no value |
Specific Radionuclides | ||||
Americium-241 | 3,200 (118,400) | TRA/NSA | 5/94 | 888 (8.88) |
Cesium-137 | 30,400 (1 x106) | TSF | 6/93 | 65,238 (652) |
Cobalt-60 | 570 (21,090) | TRA/NSA | 5/94 | 72 (7.17) |
Lead-210 | 2.22 (6.66) | SPERT | 8/92 | 30 (2.96) |
Plutonium-238 | 25.4 (939) | EBR | 5/95 | 7 (0.0733) |
Plutonium-239 | 36 (1,332) | EBR | 4/94 | 11 (0.108) |
Plutonium-239/240 | 5.1 (188.7) | INTEC | 8/93 | 2 (0.0162) |
Radium-226 | 11.9 (440.3) | ARA | 7/97 | 251 (2.51) |
Strontium-90 | 38,000 (1 x106) | TRA/NSA | 5/94 | 632,700 (6,330) |
Thorium-230 | 1.63 (60.31) | RWMC | 5/92 | 13 (0.13) |
Thorium-232 | 2.13 (78.81) | TRA/NSA | 5/94 | 70 (0.7) |
Thorium-234 | 48 (1,776) | CFA | 7/95 | 8 (0.0799) |
Uranium | 35 (1,295) | CFA | 7/95 | 6 (0.0583) |
Uranium-234 | 22.6 (836) | CFA | 7/95 | 4 (0.0401) |
Uranium-235 | 15 (555) | BORAX | 10/95 | 6 (0.055) |
Source: ATSDR 2000.
Key: Bq/kg = becquerel per kilogram; pCi/g = picocuries per gram; mrem = millirems; mSv = Millisieverts.
Note: Uncertainty values were not provided in FFIMS data set (ATSDR 2000).
Table A-5. Geometric Mean Concentration
of Select Radionuclides in On-Site Surface Soil
Radionuclide | Concentration pCi/g (Bq/kg) | Estimated Dose mrem (mSv) | ||
Geometric mean | Geometric Standard Deviation | Mean Dose | 95% Upper Limit | |
Americium-241 | 0.17 (6.29) | 13.9 | 0 (0.000472) | 8 (0.0776) |
Cesium-137 | 2.45 (90.65) | 10.1 | 5 (0.0526) | 49 (0.486) |
Radium | 1.94 (71.78) | 1.56 | 41 (0.409) | 107 (1.07) |
Strontium-90 | 2.6 (96.2) | 6.73 | 43 (0.433) | 267 (2.67) |
Source: ATSDR 2000.
Key: Bq/kg = becquerel per kilogram; pCi/g = picocuries per gram; mrem = millirems; mSv = Millisieverts.
Note: Uncertainty values were not provided in FFIMS data set (ATSDR 2000).
Table A-6. Maximum Concentration of Non-Radiological
Contaminants in On-Site Air
Non-Radiological Contaminant | Concentration (µg/m3) | Comparison Value (µg/m3) | ||
Maximum | Location | Value | Type | |
1,1,1-Trichloroethane | 136,000 | RWMC | 10,800 | AEMEG |
1,1,2,2-Tetrachloroethane | 151,000 | RWMC | 2,800 | IEMEG |
1,1,2-Trichloro-1,2,2-Trifluoroethane | 23,000 | RWMC | 0.11 | RBC |
1,1-Dichloroethane | 10,500 | CFA | 510 | RBC |
1,1-Dichloroethene | 18,600 | CFA | 81 | IEMEG |
1,2-Dichloroethane | 9,710 | RWMC | 2,500 | CEMEG |
1,2-Dichloroethene,Trans- | 31.7 | CFA | 800 | AEMEG |
1,2-Dichloropropane | 300 | CFA | 235 | AEMEG |
1,3-Dichloropropene, Cis- | 590,000 | RWMC | 14 | IEMEG |
Benzene | 147 | CFA | 163 | AEMEG |
Bromoform | 26,900 | RWMC | 0.9 | CREG |
Carbon Tetrachloride | 20,800,000 | RWMC | 1,280 | AEMEG |
Chlorobenzene | 506,000 | RWMC | 62 | RBC |
Chloroform | 3,080,000 | RWMC | 500 | AEMEG |
Dichlorodifluoromethane | 10,900 | CFA | 180 | RBC |
M,P-Xylene or Total Xylenes | 434,000 | RWMC | 4,400 | AEMEG |
Methylene Chloride | 7,290 | RWMC | 2,100 | AEMEG |
Tetrachloroethylene | 81,400 | RWMC | 1,380 | AEMEG |
Toluene | 4,520 | RWMC | 3,800 | AEMEG |
Trichloroethylene | 2,470,000 | RWMC | 10,900 | AEMEG |
Trichlorofluoromethane | 16,900 | CFA | 730 | RBC |
Source: ATSDR 2000.
Key: CREG = ATSDR's cancer risk evaluation guide; CEMEG = ATSDR's chronic environmental media evaluation guide; IEMEG = ATSDR's intermediate environmental media evaluation guide; AEMEG = ATSDR's acute environmental media evaluation guide; ppb = parts per billion; RBC = EPA Region 3's risk-based concentrations; RMEG = ATSDR's reference dose media evaluation guide.
Figure B-1. Demographic Variables in 1, 5, and 10 Mile Increments from Facility Buildings
Figure B-2. Demographic Variables in 1, 5, and 10 Mile Increments from Facility Buildings
APPENDIX C: INEEL WASTE AREA GROUPS
Information in this appendix comes from the year 2000 Oversight and Overview report, which is a synopsis of activities and issues related to the INEEL from the state agency charged with overseeing the site on behalf of the citizens of Idaho.
WAG 1—Test Area North (TAN) (10 OUs, 63 SWMUs)
The Test Area North (TAN) is located approximately 27 miles northeast of Central Facilities Area (CFA) at INEEL and roughly 13 miles west of the nearest community (Mud Lake, population 179). Between 1986 and 1990, the TAN supported research of the 1979 Three-Mile Island incident.
Several of the TAN facilities are used for handling, storing, examining, and conducting research and development on spent nuclear fuel. The major facilities at TAN include the following:
Contained Test Facility (CTF): The CTF is located on the west end of TAN. The mission of CTF was to perform reactor loss-of-coolant studies. After these studies were completed, the facility was decontaminated and used for decontamination and decommissioning of reactors used in the Aircraft Nuclear Propulsion Program. Currently, part of the CTF serves as an operational facility for the Specific Manufacturing Capability (SMC) project. The SMC manufactures armor assemblies for the Army's Tank Unit.
Technical Support Facility (TSF): The TSF is located in the central part of TAN and serves as the main administration, assembly, and maintenance section for TAN and houses the fire department. This area also serves as an operational facility for the SMC project.
Water Reactor Research Test Facility (WRRTF): The WRRTF is located 1.6 miles south of TSF and was originally constructed to conduct pool and table reactor experiments. Various reactor programs were conducted at WRRTF, including the Semiscale (TAN 646), Thermal Hydraulic Loss-of-Coolant Project (TAN-646), the Blowdown Facility (TAN-640), and Two-Phase Flow Loop (TAN-640) loss-of-coolant projects. The facility is currently used by the Applied Engineering and Development Laboratory to work on experimental projects.
From 1953 to 1972, low-level radioactive, chemical, and sanitary wastewater at TAN was injected into the Snake River Plain Aquifer (SRPA) through a 310-foot-deep well. After 1972, wastewater was disposed of at a 35-acre infiltration pond. During 1959-95, about 61 curies (Ci) of radioactivity was discharged in wastewater to the well and infiltration pond, or about 1.2 curie per year (Ci/yr). Of this amount, about 20 Ci was discharged to the disposal well in 1968 and 1969 in response to problems with an evaporator used to reduce the volume of liquid waste. No records are available as to the amount of radioactivity in wastewater discharged at TAN prior to 1959. No wastewater discharge was recorded for 1994-95. The primary groundwater contaminants resulting from the past wastewater disposal practices are volatile organic compounds (VOCs) and radionuclides, such as tritium, strontium-90, cesium-137, and uranium.
Groundwater beneath the TAN is contaminated primarily with VOCs that were injected in the aquifer until 1972. In-situ bioremediation is being used to convert groundwater contamination to non-hazardous compounds in the areas of highest contamination; natural attenuation is reducing VOC-contaminant concentrations at the distal portions of the plume.
WAG 2—Test Reactor Area (TRA) (13 OUs, 49 SWMUs)
The Test Reactor Area (TRA) is located in the southwestern area of the INEEL, approximately 5 miles northwest of the CFA and about 12 miles from Atomic City, the nearest community. The area was originally established in the early 1950s to conduct experiments associated with developing, testing, and analyzing materials used in nuclear and reactor applications. Since the 1950s, seven nuclear reactors have been built and operated at the TRA. The reactors and associated facilities supported research on the effects of radiation on materials, fuels, and equipment. Today, the Advanced Test Reactor (ATR) is the only active reactor at TRA, producing isotopes for medicine, research, and industry.
Starting in the 1950s, low-level radioactive, chemical, and sanitary wastewater was discharged to an injection well and various ponds. Since March 1982, this wastewater has been discharged to two cold-waste infiltration ponds. The average annual discharge during 1964-1991 to the well and the infiltration ponds was about 230 million gallons during 1964-1991 and about 195 million gallons during 1992-1995.
In 1976, DOE began a three-phase program at the TRA to reduce radioactivity in wastewater. The first phase ran from 1976 through 1980; the second phase, from 1981 to 1987. The contractor finished the final phase of the program in 1993. The volume of radioactive wastewater discharged at the TRA decreased as a result of this program. By August 1993, two lined evaporation ponds replaced the radioactive-waste infiltration ponds. The evaporation ponds keep radioactive wastewater out of the aquifer. In 1974-1979, 10% of the radioactivity in wastewater discharged was attributed to tritium; in 1980, 50% was attributed to tritium; and in 1981-1985, 90% was attributed to tritium. In 1992-1995, about 96% of the radioactivity in wastewater discharged at the TRA was attributed to tritium.
Chemical wastewater from an ion-exchange system has been discharged to a chemical-waste infiltration pond at the TRA since 1962. The average annual discharge to this pond was about 18.5 million gallons from 1962 through 1995. The average for 1992-1995 was 6.8 million gallons, 37% of the long-term average. Sulfate and sodium were the predominant constituents in the chemical wastewater. During 1992-1995, average annual amounts of about 311,000 pounds of sulfate and 168,000 pounds of sodium were discharged to the chemical-waste infiltration pond; average annual concentrations of sulfate and sodium in the wastewater were about 5,400 and 3,000 milligrams per liter (mg/L), respectively.
Cleanup of the TRA radionuclide-, heavy metal-, and VOC-contaminated soil was completed in 1999. As part of the process, an underground barrier has been used to prevent insects and burrowing animals from reaching areas of subsurface contaminated soil. Groundwater is ongoing at the TRA.
WAG 3—Idaho Nuclear Technology Engineering (INTEC) (formerly known as Idaho Chemical Processing Plant [ICPP]) (13 OUs, 66 SWMUs)
The INTEC facility is located on approximately 200 acres in the south-central part of the INEEL, about 2 miles north of the CFA and 12 miles northwest of Atomic City, population 25. The facility was used to reprocess spent nuclear fuel. The facility recovered more than $1 billion worth of uranium-235. The reprocessing mission was discontinued in 1992. In May 1998, DOE changed the name from the ICPP to the Idaho Nuclear Technology and Engineering Center (INTEC) to reflect the change in the mission from reprocessing spent nuclear fuel to fuel storage and waste treatment. Today, DOE develops technologies for treatment and disposal of high-level waste at INTEC. DOE also uses INTEC for treating high-level waste and preparation for disposal at a permanent location.
From 1952 to February 1984, the facility discharged most of its low-level radioactive, chemical, and sanitary wastewater into the SRPA through a 600-foot-deep disposal well. The average annual discharge of wastewater to the well was about 363 million gallons. Two infiltration ponds currently are being used for wastewater disposal. The first pond was completed in February 1984; the second pond, in October 1985. In general, the volumes of wastewater discharged to the well and infiltration ponds have gradually increased over the years to an average annual discharge during 1992-95 of about 570 million gallons. Tritium has accounted for more than 90% of the radioactivity in wastewater discharged at INTEC since 1970. Despite the increasing volumes of discharged wastewater, tritium concentrations decreased over time. In 1990-91, only 2.7 Ci of tritium was discharged, and during 1992 and 1995 only about 0.3 Ci was discharged. No tritium was discharged during 1989, 1993, and 1994.
Cleanup at INTEC will address soil and groundwater contamination. Heavy metals, VOCs, and radionuclides will be disposed of in an on-site RCRA-compliant disposal facility, which is in early phases of construction. Some material may be disposed of off site. Impacts to groundwater will be reduced as the wastewater disposal ponds will be taken out of service. The INTEC area housed a tank farm, where radioactive material spilled from the transfer lines. To date, a remedial investigation work plan is currently under review and the DOE plans to seal the surface of the tank farm with polyurethane to prevent surface water from trickling down into the tank area.
WAG 4—Central Facilities Area (13 OUs, 38 SWMUs)
The Central Facilities Area (CFA) is located in the south-central part of the INEEL; it serves as the operational headquarters for services at INEEL. The facilities at CFA provide craft, office, services, and laboratory functions. The Van Buren Boulevard Monitoring station is located 2.2 miles west of the junction of Van Buren Boulevard and Highway 20/26.
The principal contaminant sources at CFA consist of solid waste landfills, fleet maintenance, and sanitary sewage. There are three inactive solid waste landfills north of CFA that were closed and capped in 1996 under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). There is also an active solid waste landfill north of CFA that receives office and cafeteria waste. Process wastewater from laboratories, medical facilities, and equipment repair shops are all routed to the sanitary sewer system. The CFA sewage treatment plant consists of three lined ponds where biological treatment of the wastewater takes place. The effluent is then sprinkler-irrigated on the land surface.
Most radioactive wastes discharged to sewage-plant tile drain field are from production well CFA-1, which draws water from within the INTEC contaminant plume in the SRPA. Most of the radioactivity in wastewater is attributed to tritium, which accounted for 1.5 Ci/yr, or about 99.7% of the total radioactivity in wastewater in 1992-93. No wastewater discharge was recorded for 1994-95.
High levels of contamination have been confirmed at the CFA, including mercury at a wastewater pond; cesium-137 in a draining field; and lead at a transformer yard. According to the July 2000 ROD, the wastewater pond will be excavated and the material will be deposited at the INTEC disposal area; the drainfield will be capped; and the lead-contaminated soil will be sent to a facility in Utah.
WAG 5—Power Burst Facility (PBF) /Auxiliary Reactor Area (ARA) (9 OUs, 43 SWMUs)
The Power Burst Facility (PBF) is located in the south-central portion of the INEEL, about 6 miles from the CFA and 8 miles from Atomic City, population 25. The area was initially used for testing reactor transient behavior and for safety studies on light-water moderated enriched fuel systems. Five reactors were installed in four facilities at PBF. Four of the five reactors have been removed, and the fifth, the PBF reactor, has been in standby mode since 1975. In 1984 and 1985, three of the facilities were radiologically decommissioned and decontaminated and modified for new missions. The facilities are now used by Waste Management Operations for waste treatment and storage.
The Waste Experimental Reduction Facility (WERF) is used to reduce the volume of waste through sizing of metallic waste, compaction, and incineration. The Waste Reduction Operation Complex is used for storage and recovery of low-level and mixed radioactive waste. The Mixed Waste Storage Facility (MWSF) stores mixed radioactive and hazardous waste for which treatment technologies do not yet exist. There are no liquid process wastes generated by the facility. Sanitary waste is discharged to drain fields. Gaseous effluents from the incineration of low-level radioactive waste are discharged through the WERF stacks.
The ARA, formerly referred to as the Army Reactor Area, is also located on less than 40 acres in the south-central portion of the INEEL. The ARA reactor was active from 1957 to 1965 for use as a power source at remote military bases. Use of the ARA facilities has been minimal since the Army Reactor Program was phased out in 1965, and essentially no activities have been undertaken there since 1988. The ARA facilities are currently being decontaminated and dismantled. The Stationary Low-Power Reactor No. 1 (SL-1) burial ground is also located at ARA. The burial ground contains debris produced by a nuclear accident and steam explosion at the SL-1 reactor during maintenance operations on January 3, 1961. The SL-1 burial ground was capped and fenced in 1996.
Radionuclide, heavy metal, and VOC contamination has been confirmed at tank sites, in the soil, and/or at wastewater ponds at PBF/ARA. A ROD signed in January 2000 outlines measures to remove the contaminated soil and contaminated waste in the tank farms and ponds by June 2004.
WAG 6—Experimental Breeder Reactor-1/Boiling Water Reactor Experiment (5 OUs, 20 SWMUs)
The Experimental Breeder Reactor No. 1 (EBR-I) consists of the reactor building and annex (EBR-601), situated on approximately 10 acres of land located about 6 miles southwest of the CFA and 15 miles northwest of Atomic City. EBR-I was constructed in 1949 and the early 1950s; it was the first reactor in the world to generate usable amounts of electricity. Today, EBR-I is designated a Registered National Historical Landmark to mark the location where several reactor cores were tested.
WAG 7—Radioactive Waste Management Complex (RWMC) (14 OUs)
The Radioactive Waste Management Complex (RWMC) occupies 187 acres 7 miles southwest of CFA and 14 miles northwest Atomic City. The RWMC was established in 1952 as a controlled area for disposal of solid radioactive wastes. Since 1954, the facility has also received defense wastes for storage. Several research and development projects dedicated to shallow land burial technology and alternate ways of removing, reprocessing, and repackaging transuranic wastes are also conducted at the facility.
The RWMC is subdivided into three primary zones as follows:
Administrative Area: Office buildings and equipment maintenance facilities are in the Administrative and Operations Area, which occupies approximately 33 acres.
Subsurface Disposal Area (SDA): The SDA is a fenced 97-acre facility dedicated to the permanent disposal of low-level beta, gamma, and non-retrievable transuranic waste (buried prior to 1970) that is contaminated with mixed fission products and hazardous constituents. Major features at the SDA include pits, trenches, and soil vaults in which waste was buried, and Pad A, which received low-level waste, primarily nitrate salts, from off-site generators. An area in the northeast corner of the SDA, Pit 9, is to be remediated under CERCLA.
Transuranic Storage Area (TSA): The TSA is a 57-acre fenced facility dedicated to storing contact- and remote-handled solid transuranic wastes. The wastes stored at TSA included transuranic (e.g., plutonium) and intermediate-level waste. Major facilities at the TSA include the Type I and Type II storage buildings, TSA-1/TSA-Retrieval, TSA-2, and TSA-3. Within the TSA-2 and TSA-3 are air-support structures and the Stored Waste Examination Pilot Plant.
Solid and liquid radioactive and chemical wastes have been buried in trenches and pits at the SDA at the RWMC since 1952. About 550 Ci of plutonium-238; 21,000 Ci of plutonium-239; 4,900 Ci of plutonium-240; 165,000 Ci of plutonium 241; and 51,000 Ci of americium-241 were buried in the trenches between 1954 and 1970. An estimated 88,400 gallons of other waste were buried before 1970, including about 24,400 gallons of carbon tetrachloride; 39,000 gallons of lubricating oil; and about 25,000 gallons of other organic compounds, including 1,1,1-trichoroethane, trichloroethylene, perchloroethylene, toluene, and benzene. Before 1970, little or no sediment was retained between the evacuation bottoms and the underlying basalt. Since 1970, a layer of sediment has been added to inhibit downward migration of waste constituents. Sanitary sewage at the facility is discharged to a lined evaporation pond.
Various agencies are involved in cleaning up contaminated groundwater and soil at the RWMC. Since 1996, DOE has been using vacuum pumps to remove VOCs from the vadose zone, the area between the ground surface and the SRPA. More than 50,000 pounds of VOCs has been extracted. DOE and the Idaho Department of Environmental Quality are exploring options to manage the waste in the soil so that is does not migrate down to the groundwater.
Most soil cleanup involves contamination from the large landfill DOE used for waste disposal for more than 30 years. Highly contaminated waste has been detected at Pit 9, an acre of the landfill containing transuranic waste from weapons production at the Rocky Flat Plant in Colorado. Stage I activities at Pit 9 indicate that most of the contamination is concentrated in hot spots rather than dispersed throughout the site. Stage II activities will target the hot spots, and stage III activities will remediate the entire site.
WAG 8—Naval Reactors Facility (8 OUs, 54 SWMUs)
The Naval Reactors Facility (NRF) is in the central part of the INEEL, about 8 miles north of the CFA and 16 miles northwest of Atomic City. It is operated by Bechtel Bettis, Inc., for DOE's Pittsburgh Naval Reactors Office. The facility has been used to examine spent reactor fuel from Navy reactors at the Expended Core Facility. There are also a number of prototype reactors at the facility that were used as training platforms for US Navy personnel. The prototypes have been permanently shut down.
Wastewater at the NRF is discharged to a 3-mile long industrial-waste ditch and to sewage ponds. During 1992-95, about 148 million gal/yr of wastewater was discharged to the industrial-waste ditch. Some 15 million gal/year of sewage effluent was discharged to the sewage ponds. The 1992-95 disposal rates are an increase since 1989-91, when 115 million gal/yr was discharged. Chloride, sulfate, and sodium were the predominant chemical constituents in wastewater discharged to the industrial-waste ditch.
WAG 9—Argonne National Laboratory-West (ANL-W) (4 OUs, 14 SWMUs)
The ANL-W is operated by the University of Chicago and reports to the DOE Chicago Field Office. ANL-W administratively controls an area of about 890 acres in the southeastern corner of the INEEL, while the facilities themselves cover less than 60 acres. The area is about 16 miles northeast of the CFA and the Atomic City. Over the years, the ANL-W has supported research and development efforts of liquid metal fast feeder reactor technology, spent nuclear fuel, and waste treatment technologies.
Radioactive liquid wastes are evaporated and solidified in the Radioactive Liquid Waste Treatment Facility. Process wastewater, which mainly consists of secondary loop reactor cooling water, is discharged to an infiltration pond. The Fuel Conditioning Facility and the Hot Fuel Examination Facility are the two primary air emissions sources at ANL-W.
Most of the contamination found at ANL-W is in the soil (cesium) and in wastewater ponds. DOE is exploring ways to eliminate the need for digging and off-site disposal of the contaminated soils. One option is phytoremediation, in which plants are used to take up cesium from contaminated soil.
WAG 10—Miscellaneous Units and SRPA (4 OUs, 13 SWMUs)
The experimental Field Station (EFS) was previously known as the Experimental Dairy Farm. It was a small-scale dairy farm used to study the movement of radionuclides through the entire air-vegetation-cow-milk sequence of the human food chain. The site is 6 miles north of CFA along the channel of the Big Lost River. Research on methods to provide barriers to water, small mammal, ant, and vegetation root intrusion through protective caps at waste disposal areas is currently being conducted there.
The Security Training Facility consists of two adjacent areas located approximately 2.5 miles east of CFA. This facility was formerly known as the Experimental Organic Cooled Reactor and Organic Moderated Reactor Experiment (OMRE) areas. The Experimental Organic Cooled Reactor was constructed directly northwest of the OMRE in 1962. The project was canceled prior to completion, and the area has since been used for materials storage, security force practice, and explosives testing. The facility was decontaminated and dismantled in 1979. The OMRE was designed to develop power from an organic coolant reactor. It consisted of a reactor control building, a reactor, heat exchangers, a septic system, a leach pond, and a water tank. The buildings and underground reactor were disassembled; radioactive matter was disposed at the RWMC; and uncontaminated parts were sold as scrap. The leach pond was backfilled with soil, and the entire area was revegetated with a mixture of native grasses in 1981.
Areas of INEEL have also been used by the Navy as practice artillery firing ranges. DOE has cleaned up known range locations and continues to look for shells while investigating other on-site locations.
Table D-1. 2000 Demographics in the 10-mile Buffer from Site Boundary by County.
County | |||||
Bingham | Bonneville | Butte | Clark | Jefferson | |
Total Population | 280 | 110 | 1,936 | 54 | 1,751 |
Racial Characteristics | |||||
White | 217 | 73 | 1,817 | 48 | 1,437 |
Black | 0 | 0 | 9 | 1 | 2 |
American Indian and Alaska Native alone | 8 | 7 | 20 | 0 | 8 |
Asian alone | 3 | 0 | 9 | 0 | 7 |
Native Hawaiian and Other Pacific Islander alone | 0 | 0 | 0 | 0 | 0 |
Some other race alone | 50 | 30 | 51 | 2 | 282 |
Hispanic or Latino | 72 | 39 | 90 | 5 | 340 |
Two or More races | 3 | 0 | 29 | 3 | 17 |
Sensitive Populations | |||||
Children Age 6 or younger | 32 | 17 | 212 | 6 | 244 |
Females 15- 44 | 51 | 21 | 339 | 8 | 343 |
Adults Age 65 and over | 24 | 9 | 288 | 5 | 148 |
Other Variables | |||||
Total Housing | 118 | 49 | 890 | 22 | 583 |
Total Age 18 and Older | 198 | 72 | 1,376 | 34 | 1,024 |
Total younger than 18 | 83 | 38 | 556 | 20 | 677 |
ATSDR scientists use comparison values (CVs) to screen environmental data that are relevant to the exposure pathways. CVs are concentrations of contaminants that are considered to be safe levels of exposure. ATSDR use CVs only to screen contaminants for further evaluation; the agency DOES NOT use CVs or the health guidance values from which they are derived to assess toxicological implications.
The derivation of a CV uses exposure assumptions resulting in values that are much lower than exposure concentrations observed to cause adverse health effects, thus ensuring that the CVs protect public health in all exposure situations. That is, if the concentrations in the exposure medium are less than the CV, the exposures cannot make people ill, and no further analysis of the pathway is required.
CVs are based on Health Guidance or regulatory doses, such as MRLs and RfDs. These doses are derived by serially applying "uncertainty factors" that can make them as much as 10,000 times lower than the lowest dose observed to cause harm, or the highest dose below that minimal toxic dose that is observed NOT to cause harm. Sometimes, in addition to up to 4 factors of 10 for uncertainty, additional "modifying factors" are applied, which can lower the advisory or regulatory values even further. ATSDR therefore has many reasons to be strongly confident that CVs derived by applying intake assumptions to advisory and regulatory doses will not understate potential for harm.
That is why, while concentrations below the CV are not expected to lead to any observable health effect, one cannot infer that a concentration greater than a CV will necessarily lead to adverse effects. In addition to default intake assumptions and uncertainty and modifying factors, site-specific environmental exposure factors (for example, duration of exposure) and activities of people that result in exposure (time spent in area of contamination) influence whether exposure to levels above the CV could lead to a health effect. Therefore, CVs are not used to predict adverse health effects.
The CVs used in this evaluation are defined as follows:
Cancer Risk Evaluation Guides (CREGs)
Estimated contaminant concentrations that would be expected to cause no more than one excess cancer in a million (10-6) persons over a 70-year life span based on a 95% maximum likelihood estimate over a 70-year life span. ATSDR's CREGs are calculated from EPA's cancer slope factors (CSFs). The CSF assumes that the dose and risk are proportional down to the last molecule or quantum of exposure, that there is no safe level (threshold), and that the slope relating dose and risk does not diminish with decreasing concentration. Although these assumptions have never been conclusively proved (and it may be beyond science ever to prove them in general, although they have been disproved for some special cases), this method allows data from observations of doses tens of thousands of times greater than those encountered from environmental contamination to be used to generate extremely protective CVs. ATSDR can be very strongly confident that people exposed to levels at or below the CREG are not expected to get cancer therefrom.
Environmental Media Evaluation Guides (EMEGs)
EMEGs are concentrations of a contaminant in water, soil, or air that are not expected to cause adverse noncancer effects over a specified duration of exposure. EMEGs are derived from ATSDR minimal risk levels by factoring in default body weights and ingestion or inhalation rates. Separate EMEGS are computed for acute (< 14 days), intermediate (15-364 days), and chronic (> 365 days) exposures for oral and inhalation routes.
Reference Dose Media Evaluation Guides (RMEGs)
RMEGs are the concentrations of contaminants in air, water or soil that correspond to EPA's reference doses of reference concentrations for that contaminant when ATSDR's default values for body weight and intake rates are taken into account.
Maximum Contaminant Levels (MCLs)
MCLs are EPA drinking water standards. MCLs are considered protective of human health over a lifetime (70 years) for individuals consuming 2 liters of water per day. MCLs are used for CVs when EMEGs and RMEGs are not available. As with other CVs, MCLs are not thresholds of toxicity.
EPA Region III Risk-Based Concentrations (RBCs)
These are used only when neither the values ATSDR derived from MRLs or RfDs and RfCs nor EPA's MCLs, nor (for this public health assessment) state of Idaho CVs are available. EPA combines reference doses and cancer slope factors (CSFs) with that agency's "standard" exposure scenarios to estimate risk-based concentrations, which are chemical concentrations based on fixed risk levels (i.e., an EPA hazard quotient of 1, or extrapolated CSF-based lifetime cancer risk of 10-6, whichever occurs at a lower concentration) in water, air, fish tissue, and soil.
References
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