ML20085G725
| ML20085G725 | |
| Person / Time | |
|---|---|
| Site: | 05000047 |
| Issue date: | 08/31/1990 |
| From: | EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | |
| Shared Package | |
| ML20085G716 | List: |
| References | |
| NUDOCS 9110280007 | |
| Download: ML20085G725 (38) | |
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DEPAMTMENT OF THE ARMY '.. HEADQtAMTERS, U. S. ARMY MATTAIEL COMMAND t' W )
r'* 6001 (JEEN>tOWU; AVENUE, ALEXANDM1A, VA 333334401
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- 1. Refererco letter, Of fice of the Anr.ibtant Secretar/ of the Am/, 11 Jw2e 1991, SAD (encionure 1) ,
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- 2. Cerartment of the Actr/ licen.usen will bmlenent subject starttwd ef fective 1 Janws/ 1993.
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DW1 c%LL. J ' J001 E. PALED 1 Cdef Safety Office DISTRIBtJFIO!! SN pago 2 d h 9110200007 911003 PDR ADOCK OriOOOO47 P PDR
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}fgDA(!GB-AVtFS) WASH DC 20310-050; IOCA(CEEC-S0) k76H DC 20314-1000 HNA(SGPS-ISP-E), 3109 Leecburg Pike, Falin church, VA 22041-n59 CUYNDER Military Traffic thgarcnt Cc re,nd, 5611 Ccit rbia Pike, AT24: !n-SS,
- Falla Carch, VA 22041-5050 U.S. Arny Ccininni Trreestigaticn Camard, 5611 Ccitztbia Pike, ATn!: CIPA- ! MPS-5, Falls Chu.a. .h, VA 22041-5015 U.S. Antt/ Trainirg ard Dcctrine Ccrmvd AT34: IN, Fort ! brave, VA i 23651 O.S. Any Ir.telligarco ard Serrarity Comord, ATm IAlu-lis, Arlington lill Stacion, Ar12ngt a.1, VA 22212 U.S. Army Safety Center, ATni. CU':C4, Fort Rucker, AL 36362-5363 U.S. Any T,nfo.T3 tion Systtrno Caure.A. ATnt: AS-iU.-S, Fort Htachuca, A2, 85613 U.$. An:1y Forces Commd, ATnt FCJ1-Su, Fort FtPnetrson, CA 30330 U.S. Army Westorm Ccmwd, ATU1: APPF-SA, Fort Chafter HI 96350-5700 U.S. AnW He<h Serricos Catrard, AT21: HSAP/HtL-P, Fort Sam H Jstca, TX 78234 U.S. Antty Japan. ATnJ A7CA-SF-HRS, AIO San Frarcisco, CA 96343 Eighth U.S. Arg, J4, ATnt DJ-tE-!r (Colsen), ATO San Francisco 96301-00C9 U.S. Arm / South ' h', ATni SCCA-PCS, MO Miami 34004-0000 U.S. Anny Envizcatatal It giene t Agercy, ATnt: HSHB-!M/HSIG-!G-HPD/ HE-MR-1, Abenicen Prwing Gxturd, !o 21010 Special CVerations CoInard, ATni IGE, Fort Bra,rg, IC 20307-5000 l U.S. Antr / SYxic ard Hazanlous Materials Ageref, ATIN: CL%%-BC-A, Aberdeon l- Prtnirr; Grourd, to 21010-5401 l
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Scx 1500, Hunt.sville, AL 35807-3801 l Camardant U.S. Amy Chmical schcol. ATal: ATnFC4-A, Fort McClellan, AL 36305-5020 Cannmhmia-Chief, U.S. Ar.:t/ EurcSe & Soventh ArI:t/, A7Dh AElG\-D/AElGA-5, Mo Ift 09403 l Diructor, USAMC Field Safety Activity, ATnJ REOS, Charlestcwn, ni 47111-9569 , l IN, 1rairdtg Devices, ATnt: AMCDM'tD-SP, nwal Training Conter, Orlardo, FL 32S13 t 1
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& 3-(px .n CHARACTERIZATION REPORT FOR U.S. ARMY MATERIALS TECHNOLOGY LABORATORY RESEARCH REACTOR AuausT ?.990 e
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l l CHARACTER 12ATION REPORT FOR U.S. ARMY MATERIALS TECHNOLOGY LABORATORY RESEARCH REACTOR
. August 1990
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- Prepared by
! EG&G Idaho, Inc. L- Idaho National Engineering 1.aoecatory As Part of Work for Others Project No. 88845 t i Prepared for the Uaited States Army Toxic and Hazardous Materials.Ajency , u Base Closure Division-Aberdeen Proving Ground.. Maryland- 21010-and for the U.S. Department of Energy Idaho Operations Office : Under 00E Contract No. DE AC07-761001570
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SUMMARY
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This report describes the charactertzation for the decommissioning of the U.S. Army Materials Technology Laboratory (AMIL) Research Reactor, located at Watertown, Masachusetts. The characterization determined the radioactive and chemical contaminants present at the reactor facility to suppert the efforts to plan the decommissioning of this f acility. The AMTL research reactor was constructed in the late 1950s and 1960. The reactor started operations in June 1960 and continued through June 1970, when the reactor was deactivated. The reactor was used by AHTL as well as other Army arsenals, research centers, &nd local institutions to conduct various solid state physics research experiments and programs. Since the reactor deactivation in 1970, the reactor containtent facility has bean used to house various radiography experiments. Reactor op' e rations reports for the period June 15, 1960, through March 27, 1970, and the facility safety reports indicate that there was no fuel breached during reactor operations or fuel transfers. The low levels of radioactivity and contamination found in the reactor vessel and on the reactor components during the surveys further substantiate these indications. It is
~
not anticipated that any significant problems relating to the finding of unsuspected cont mination will be encountered during the decommissioning of N' the reactor facility. Analyses of sediment and soil samples collected around Building 100 and Cistern 242 dt. ring March 1990 did not detect any volatile or semivolatile organics, polychlorinated biphenyls/ organochlorine pesticides, organophosphorus pesticides / chlorinated herbicides, metals, lead or mercury at levels above Environmental Protection Agency regulatory limits pertaining to the identification and classification of hazardous wastes [as specified in 40 CFR 261, " Identification and Listing of Hazardous Waste," and including the
~
toxicity characteristic revisions effective September 25, 1990 (federal Register, March ?9, 1990)). Analysis of these samples fcr alpha and gamma emitters also indicate no findings significantly above background. 11
. _._ _ _ _.- _ _ . _ _ _ _ _ _ _ ~ _... _ _ _ _ . _ . _ ._.. _ _ __. _ _ _ _ _ _ . _ 4 CONTENTS
SUMMARY
....................................................... ii
- 1. INTRODUCTION AND OBJECTIVES .................................. 1
- 2. HISTORY AND BACKGROUhD ....................................... 3 2.1 History .............. ................................. 3 2.2 Background ............................................. 7
- 3. FACllllY DESCRIPT10L ....................................... 10 3.1 Building-100, Reactor Containment Building ............. 10 3.2 Building 97, Reactor Facility Laboratory ............... 15 r
3.3 Cistern 242, Waste Water Retention Tank ................. 18
- 4. CHARACTERIZATION ............................................. 20 -
4.1 Building 100, Reactor Containment Building ............. 20 4.2 Building 97, Reactor Facility Laboratory ............... 30 4.3 Cistern 242, Waste Water Retention Tank ................ 38 4.4 Area Surrounding Building 100 and Cistern 242 .......... 38
- 5. POTENTIAL PROBLEM ARLAS ...................................... 48
- 6. REFERENCES .................................................., 49 m,.
APPENDIX A - EPA APPENDIX IX ANALYTES APPENDIX B - EPA T0XICITY CHARACTERISTIC CONCENTRA110NS APPENDIX C - BACKGROUND S0ll SAMPLE DATA e FIGURES
-1. Location cf Army Materials Technology Laboratory, Watertown, Massachusetts ...... 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ' i
- 2. Army Materials Technology Laboratory general site map . . . . . . . . 4 iii
- _ .- m. ___ _ . _ - , . . _ . . . - . . _ , , , _ _ __ . . _ _, __.
4
- 3. View of Building 100, looking west. Buildin 97 is in the background .......................g..................
11
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4
- 4. Reactor containment shell crot s sectional view . . . . . . . . . . . . . . . 12
- 5. Reactor cont ainment shell floor pl ans . . . . . . . . . . . . . . . . . . . . . . . . 14
- 6. Army Haterials Technology Laboratory Research Reactor model ................................................ 16
- 7. Reactor core support ......................................... 17
- 8. View of Cistern 242, looking north. Buildin in background ..............................g 100
.................. 19 4
- 9. Smear survey locations for reactor basement . . . . . . . . . . . . . . . . . . 22
- 10. Smear survey locations for_ reactor operating floor . . . . . . . . . . . 23
- 11. Smear survey locations for reactor first platform . . . . . . . . . . . . 24
-12. Smear survey locations for reactor second plat form . . . . . . . . . . 25
- 13. Smear survey results and contact radiation readings for reactor annulus fuel element storage ..................... 26
- 14. Smear survey results and_ contact radiation readings for reactor annulus components ....,.....................,.... 27 1
- 15. Smear survey results and contact radiation readings fo r reactor annul u s fl oor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28
- 16. Contact radiation readings for internal components of reactor vessel (View No. 1) ............................... 31 17 Contact radiation readings for internal components of reactor vessel (View No. 2)................................ 32
- 18. Contact-radiation readings and smear survey results for internal components of reactor vessel . . . . . . . . . . . . . . . . . . . . 33
- 19. Smear survey results for internal components of reac tor ve s sel (Vi ew No. 1 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 l 20. Smear survey results for internal components of
- p, reactor vessel (View No. 2) .................................. 35
- 21. Building 100 and Cistern 242 area sediment and soil sample locations .............................................. 40 '
iv
k TABLES
- 1. Results of isotopic gamma scan for annulus smear sample ...... 29
- 2. Summary of the results or the AMTL Buildin smear sampling ...........................g.................... 100 36
- 3. Summary of the results of the AMTi. Building 100 radiation survey ............................................. 37
- 4. Summary of the results of the chemical analyses for suiface and subsurface sediment and soil samples collected around Building 100 and Cistern 242 ................................. 41
- 5. Analyst's results of rejected gamma-emitting nuclides for March 1990 sediment and soil samples-......................... 44
- 6. Analyst's results of man made true positive gamma emitting nuclides for March 1990 sediment and soil samples . . . . . . . . . . . 45 N@
4 l i . l V
- 1. INTRODUCTION AND OBJECTIVES
~
The United States Army Toxic and Hazardous Materials Agency (USATHAMA) requested assistance frem the Idaho National Engineering Laboratory (INEL) to perform the planning required to support the decommissioning of the U. S. Army Materials Technology Laboratory (AMTL) Research Reactor, located at Watertown, Massachusetts. The location of the reactor is shown in figure 1. The characterization was performed by EG&G Idaho, Inc., to determine the radioactive and chemical contaminants present at the reactor facility. The data included in this report will be used to support the options presented in the Decision Analysis Report, to be published. This report provides a facility description and history, and radiological characterization and findings for future accommissioning of Buildin3 100, the research reactor containment butiding; pipiny in Building 97, which housed the liquid waste handling system for the reactor; and Cistern 242. which is a retention tank that was used for storage of the liquid waste from the reactor. The radiological characterization identifies the locatien and intensity of radiation fields, the principal isotopes, and the areas of contamination in the reactor facility. Potential problems associatcd with the decommissioning of the facility are also explained in this report. 4 1
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S s.=* *t. Laboratory Ed cw" ** /, . Figure 1. Location of Army Materials Technology Laboratory in Watertown, Massachusette. 2
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,, 2. HISTORY AND BACKGROUND 2.1 History The first nuclear research reactor designed to meet the needs of the research programs on materials for the U.S. Army Ordnance Corps was constructed at Watertown, Massachusetts, during c,e late 1950s and 1960. The reactor was dedicated on May 17, 1960, io the memory of the late Dr. Horace Hardy tester, who won national recognition as a pioneer in the field of industrial radiography. Figure 2 is a general site map of the AMTL, including Building 100, the AMIL nuclear reactor containment facility.
Initial criticality of the nuclear reactor was achieved on June 15, 1960, at a power level of 1 MW. Post neutron tests consisting of shim rod calibrations, power calibration, temperature and void coefficients of reactivity measurements, and determinations of the worth of experimental facilities were conducted, culminating on September 16, 1960.' Various solid state physics rese:rch programs and experiments were conducted at the 1 MW power level through June 1966 by the Army Materials and Mechanics Research Center (AMMRC, now AMTL). Tne reactor was also used _ extensid.'y by the U.S. Army Picatinny Arsenal for study of explosive type materialt Other U.S. Army users included the Detroit and Frankford Arsenals and the Natick and Electronics Research and Development Laboratories Some of the programs conducted by the reactor users included: experiments in the structure of heavy-metal azides, lattice dynamics studies on explosive-type materials and determinations of vibrational spectra of organic secondary explosives, polycrystalline and single crystal coherent scattering materials and liquids, activation analysis of samples containing trace impurities, and inducing slight radiation effects in materials.1,2,3,4.s.6 3
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-l3 A number of local institutions (Boston College, Worcester Polytechnic
., Institute. University of New Hampshire, and Massachusetts Institute of
'} e M . Tcchelogy; also made use of the AMTL reattor for diffraction measuretrents and
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e, < ,, 4 M. ? Tr or's license v.as amended in June 1966 to allow the power level J.,,, [ N *
- be incre sed to 2 MW to provide higher neutron fluxes for experiments. The
,P,9 approach to 2 MW began cr. June 6,1966, nd was completed on June 15. The procedure that w u allowed was to increase power in steps of 200 KW and observe all measured pararaeters for several hours a* each step.3
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The reactor's license was uprated in 1969 from 2 MW to 5 MW.
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On August 22, 1969, the power escalation program began and the re ctor power was increased in 1 MW steps to the maxiruum licensed power level of 5 MW. This i program was completed with a 79 hour 5 MW run dur%g the week of September 8 k! with no ab, ormal results observed during the power-escalation program.6 Experiments similar to those described above were planned using the higher power level as v.ll as new experiments for advaaced materiel and iar research on, development of, and application of composita materials, improved , metal allovs, and ceramics.3d'3 6 4 In December 1269, the Department of the Army decid'.4 to abut down the v operation of the AMTL reactor and to place the facility in a stanoDy condition in 1970, On March 27s 1370, Ge reastor operations were shut down and the raactor was placeo in a standby mode.' A deactivation report was submitted to o the Division of Reactor Li<ansing and to O p *rmy 'icactor Systems Health and Safety Review r.ommittee in Decerrber 1970 ~ ,, The following radioactive materials were removed from the reactor building and disposed of as follows: ' s
- The fuel elements containing special nacloar material were .
. removed and returned to the U.S. Atomic Energy Commission.
5
Y The irradiated and untrradiated fuel elements and materials were disposed of under contract with National Lead Company. ' e Th' kn yllium oxide toeu) r#fle: tor elements, shim safet i
. us, armatures, and stainless-steel pieces from the guide -
tubes were disposed of as 'gh-activity radioactive waste. e The fission chambers containing U 235 were ' ansported to another reactor facility and reported under SNM 244.
- The ionizat on chambers were disposed of as low level radioactive waste.
The radioactive sources used for calibration and check of s 9y meters were transferred to the Army Radiation and Oct pational Safety Branch. The water f'om the primary and secondary coolant systems, secondary coolant sump, main reactor pool, fuel storage tank (in basement), and Cistern 242 was_ drained and disposed of.# Indications a e that thc water was monitored for_ radioactivity and-discharged according to standard proteoure,
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which was *, either discharge to the sanitary sewer, if found to be below regul ator) standards, or to dilute to achieve acceptable release criteria before discharging. The following li, quid-waste system equipment was removed and disposed of _, fromBuildin,g,9J:
- Three each 3,000-gal decontamination storage tanks
- Disposable ion exchange system
=* Pool fill, make-up,- and laboratory demineralizer system
- Pumps, valves, and piping associated with the above systems.
The' reactor stack, exhaust fan, absoluto filter, and the secondary cociant towers were removed and disposed of at a later date. -; 6
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,, The major equipment that remains to be dispo;ed of during the decommissioning of the facility is described in.che= following three paragraphs.
The piping (ccolant transfer line, sump nep drain line, demineralized water line, and test connection lire) connecting Buildings 97 and 100 is still in place. (The piping between Buildings 97 and 100 is approximately 3-1/2 ft below the surface.) If total dismantlement of the reactor facility is performed, the utility p)ing (condensate return line, air line, steam line, and city water lint) between Buildings 97 and 100 would also have to be removed. The stainless-steel pool liner, reactor pedestal, grid plate, and portions of the-beam tubes, corr 91 rods, and instrument rack remain in the reactor vessel. The top covers for t W reactor vessel are also in place. The primary coolant system (heat exct, w demineralizer systems, pumps and associated piping) remain in the re.m or facility basement. The secondary coolant sump, three pumps, and piping to the primary coolant system were also left in place outside the containment shell. Cis' t rn_2R and the associated piping going into Building 97 will also be removed during the decomn issioning. 2.2 Backaround 3 % f During the initial criticality, leaks of reacior :oolant water through the concrete biological shield were observed. The leaks grew progtsssively Arse anda first Mm6t to rectify the croble.a was to drain the annulus and
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apply glass tape and epoxy resin to all all and floor joints. All surfaces-of the annulus were also finished with epoxy r esins. In the annulus there are
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cavities created by the encasements of concrete over the slant tubes as they
. pass through the :nnulus, lhe concrete encasements had been provided with aluminum drain lines, which passed from the cavities to the main section of u,, tne annulus. The drain lines vere provideo so that no witer remained in the l
cavities when the annulus was emptied. These lines were determined to be leaking and were plugged, which considerably reduced the leakage in the region 7 A
o where the first balcony is tied to the shield. These efforts to stop the leakt had 1imited success, l. ate in 1961, a second attempt was made to stop " the leakage oy orilling selected holes (2 in. ' diameter) and pressure-grouting a lean cement mix into the holes. This was unsuccessful because very little grout was accepted by the holer. A chemical grout (AM-9) that could be pumpec as a liquid with a preset jelling time was tnen tried in place of the cement mix and proved to be quite successful. This method, along with the use of pressure-sensitive tape around each beam tube joint, eliminated approximately 75% of the leaks. Some small leaks continued intermittently but did not hamper reactor operations and did not require any special cleanup.' In 1966 a stainless-steel liner was installed in the reactor, pool and it eliminated the leaks ' In 1968 the volume between the stainless-steel lir.er and 'he concrete
-shield was connected by a drain to the basement sump in order to remove any water leakage) The water that leaked through the biological shield did not cause any major contamination spread outside the shield but is suspected of contaminating approximately 50% of the high-density concrete. The wate- that did reach the reactor basement drained to the ma .
la 1961, during an unloading of the reactor core, difficulty was experienced in removing some of the Be0 reflector elements. An examination revealed that an element had swollen. Further examination indicated that water was leaking into the elements. Since_there is no reaction between Be0
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and water ("1 der the operating conditions of the reactor, it was decided that v perforated Be0 reflector elements could be used.' No further difficulties were experienced after modifications were made to reflector elements. In July 1963 the heat exchanger of the reactor coolant system-developed a leak. The heads were' pulled and the corroded leaking tube was plugged. Leaks developed on four other occasions and in January 1964 the aluminum tube , bundle was removed and replaced. It was determined after examination of the corroded tube bundle and the well water being used that two actions would be initiated to remedy this problem: (1) replace the aluminum bundle with one made from stainless steel and (2) install a recirculating-water cooling tower l to provide secondary coolant.' These actions were completed in January 1965.2 - 8
An ,urplanned. release of 4900 gal _ of.radioacti.ve_ libid_ waste occurred from the underground liquid-waste retention _tanL(C.11tenL232Lduring_1he
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perdod.4stween Echtuar.y_2LanLfahrnty 27, 19691 The leak was detected af ter a review of records of the tank level recorder, which indicated that the level of the tank's contents droppea from 15 to 11 ft during this period. Total activity re' 1 sed was 10 pCi as reported by the health physicist. The tank's contents were sampled after the release and the gross activity was determined to be 5.7 x 10'7 pCi/mL. It was con:ludeo by the Reactor Facility Safety Committeethatthereleasewaslessthan10%ofthelimitsetby-10_CfRjf,~ R Appendix C, for burial of radioactive waste in the soil.a Between January 1, 1969, and March 27, 1970, there were 62 unscheduled shutdowns of the reactor. In many instances, no direct cause was read.ly apparent, as the shutdown would manifest itself as a single rod dropping without any evidence of malfunction or unsafe condition. Tne majority of these unexplained rod drops were believed to be caused by noise in the period safety channel, which momentarily reduced the magnet current below the drop current.' Based on the information contained in the operations reports of the U.S. Army. Materials Research Agency Nuclear Reactor Facility covering the period from June 15, 1960, through March 27, 1970,1,2,3.4.5.6 and a review of the
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f acility safety reports, there are ro indications that any fuel was breached
# during reactor operations or fuel transfers be* ween the reactor core and the annulus. Further evidence that no fuel was breached are the low levels of radioactivity end contamination found in the reactor vessel and on the reactor internal components.
9
- 3. FAtllllY DESCRIPTION
~
Buildino lppdra_q.tpr Containment Buildina 3.1 Building 100, the reactor containment structure (see Figure 3), is a cylindrical pressure vessel 80 ft in diameter, approximately 67 ft high from ground level, with an elliptical top. A cross-section of the containmant shell is showr. in Figure 4. The basement foundation is approximately 19 ft below ground-level and a 6-ft-di meter gamma-ray facility extends an additional 9 ft below the foundation level. The perimeter walls of the gas-tight containment shell are 2 ft-thick concrete and extend up to the crane rails 44 ft above ground level. 'i ne above-ground walls and the roof are covered with a 1/2-in, welded steel plate. There are two large penetrations in the perimeter wall for personnel airlocks permitting access to the interior of the shell. ~he electrical utilities are brought in through seals which consist of a conduit box filled'with a sealant and a metal tube welded to the shell which allows the electrical cables to pass through the contai .aent shell. The wate- inlet lines (city water and secondary cooling water) and outlet lines (liquid waste and secondary cooling water) pass through pipes welded to the shell. The air, steam, return condensate, and demineralized-water lines also enter the containment shell from Building 97 through pipes _ _ , weidtd to the steel shell. Air inlet and outlet is accomplished through steel ducts with flang6s welded tc the shell and provided with .. omatic cloeing d> 'ncr - Overprassurization protection for the shell is provided by a 2-in. line with-e water trap equivalent tc a 5-ft head of water installed between the shell and the atmosphere. Thr containment shell completely encloses the reactor and all of its aIsociated rautpment with the exception of Cistern 242 and the secondary coolant pump pad. The bottom of the basement floor is approximately 19 ft below grade. The-groundwater in the area of the reactor building is apparently 14 to 16 ft below grade. During deconmissioning (assuming total dismantlement) when the basement floor is excavated and removed, routine practicos will be used to minimize any contamination spread to the groundwater in the event that contamination exists beneath the basement ficor. 10
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The containment shell floor plans are shown in Figure 5. The main operating floor, which is at ground level, is about 76 ft in diameter and is e completely free for experimental use with the exception of the stairways and necessary equioment. The first platform provided access to the six slant beam tubes which exit at this level from the reactor vessel. The second platfnrm provided an area for the reactor control room and space for personnel and equipment for loading and unloading the reactor. A sttndard 10-ton crane, mounted on a circular track, was used to service the main floor, the platforms, and part of the basement through floor openings. The basen. ant area was used for experirental and operational purposes. A gamma ray exposure experimental facility was built below the basement floor level, the garr;na-ray facility co"1d also be used for fuel storage. There are 16 vertical storage tubes in one part of the basement floor that could be used for storage of radioactive materials, such as beam tube plugs, collimators, and irradiated samples. These 16 vertical tebes are 4 ft 3 in deep. Two tubes are 12 in, in diameter, two are 10 in. in diameter, eight tre 8 in. in diameter, and four are 4 in in diameter. All the primary coolant equipment for the operation of the reactor is located in the basement and is separated from occupied areas by 2-ft-thick, ordinary concrete walls. A main sump is also located in the-basemert to which
~
all liquid-waste within the containment snell drained. The liquid waste was
'# then autom2tically pumped to a liquid waste storaca, tank, which was part of the liquid waste handling system that was iocater in Bujlding 97 before ig' g , ,
removal. " #' # The reactor is a version of the " swimming pool" type with the pool having been replaced by an octagonal open tank, completely above ground. Tha l
- interal dimensions of the tank are 10-1/E ft in diameter by a cepth of 30 f t,
! which provided 4 f t of water shielding from the fuel horizontally and 22 ft of water shielding above the centerline of the fuel vertically. The concrete biological shield consists of approximately an inner 16 in, of' ordinary
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j i Maximum neutron team facilities were utilized by the addition of 10 horizontal 6 in. beta tubes. one horizontal 6-in, through tube, and six slant 6-in. team
, tubes. See Figure 6 for a three-dimensional model of the reactor.
A cover made up of hinged metal plates closed of f most .f the tap of the pool. This allowed access to the pool for transfer of fuel elemants between the reactor and the lead lined recessed storage positions available in the annulus. The annulus was built around the upper portion of the reactor pool and is accessible from the pool through a removable, watertight gate which permitted the movement of fuel elements under water. The fuel elements used in the open-top, tank-type, thermal, heterogeneous, H2 0 cooled and-moderated reactor were Materials Testing Reactar type assemblies fitted into a grid plate and expanded to a 7 x 9 in, array. The increase -in grid-plate size permitted changes of core configuration, as well as providing the greater fuel loading needed to overcome reactivity losses to the beam tubes and for opera +. ion at higher power levels. The reactor grid plate is supported on a pedestal on the bottom of the pool as shown in Figure 7. 3.2 Suildina 97. Reactor Facility Laboratory
~~
The reactor facility included portions of Building 97, which provides
~
-t access to Building 100 through an_ airlock and contained ' offices and-laboratories for support of the reactor operations (see figure 3). The.
liquid waste handling system for the reactor was also contained in the soutn-
=end of this building. This. system consisted of three above-ground 3000 gal waste water _ storage tanks and a disposable cation, anion and mixed ion exchange.systemforstoringand'iieatingcontaminatedwaterfromthe[eactor.
Ccntaminated water stored in the retention tank, Cistern 242, cou'Id also be pumped to this system for processing. The three storage tanks, mixed ion
~
exchange system, and pool fill, make-up, and laboratory demineralizer system were removed after deactivation of the reactor to make room for 6 particle accelerator. 15
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4 Only the portion of the piping described in Section 3.1 that remains tctween Buildings 97 and 100 and to Cistern 242 will oe addressed in this report.
~
Building 97 presently contains chemistry laboratories, an ion-implantation
~
facility, and a particle accelerator for neutron production. 3.3 Cistern 242. Waste Water Retention Tank A buried retention tank, Cistern 242, located approximately 25 ft southwest of Building 100, served as the low level waste storage tank for the reactor (see Fig e 8).,-T6e'E3-i/2 ft square tank is constructed of 1 ft-
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thickconcreteandis(15ftdeeg,-Amanholecoverprovidesaccesstothe tank's interior. The tank was used to hold the reactor poni water during reactor maintenance to minimize the time and axpense of supplying
- demineralized water to refill the pool. If the reactor pool water had become seriously contaminated, it could also have been pumped to the retention tank.
The contaminated water could then be processed in the liquid-waste handling system located in Building 97. In October 1956 a liquid-level-indicating recorder was installed to facilitate waste management and to provide a method of monitoring the retentio:t tank for any appreciable leakage.' The water contained in the retentioi, tank was dr_ajned ,and th_e, tank. flushed to the sewer system after the reactor was deactivated.
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- 4. CHARACTERIZATION In September 1989, radiological surveys iere conducted in Building 100, the reactor containment, to characterize the reactor facility for future decommissioning.
The water in Cistern 249. was sampled during February 1990 and- _th_e results u ._. indicated that the radioactivity levels were well below the drinking-
- - - - - - ^
water standards. ANTL was requested to remove the water from the cistern in NFder~thatthecistern'sinteriorcouldbesampledinMarchwhenadditional
.soll sampling was to be performed.
During March 1990, sediment and soll samples were collected at the surface and subsurface frum locations around Building 100 and Cirtern 242 to
-determine _ the presence of any metals, lead, mercury, Appendix IX analytes, alpha-emitting nuclides and gamma-emitting nuclides. Smears were also collected from piping located in Building 97, which housed the liquid-waste handling system, to determine the levels of radioactive contamination. The interior of Cistern 242 was not sampled during this san.pling trip. Local regulatory authorities are still' reviewing information submitted by AMTL and requests to remove the water in order to allow access to the tank interior.
Details of the results of sampling efforts are contained in Sections 4.1 ve through 4.4 and the associated figures and tables. 4.1 Saildino 100. EgActor Containment Buildjng EG&G personnel conducted radiological surveys of the inside of the
' deactivated reactor containment building from September 11-15, 1989. Areas surveyed .insida the building were as follows: the basement, the operations floor, the first and second platforms, the reactor control room (located on the second platform), the top of the reactor, the reactor vessel, the reactor '
pedestal and the reactor annulus.' 20 s
. , . . .~ . . - - - . - . - - . _ . . . . _ _ . - -...- . - _ - .- ~.-. ..-
All radiation measurements were made with portable beta gamma radiation instruments with detection efficiencies of 10?. Detection efficiency relates i instrument output to radiation input. ror example, an instrument with an
- efficiency of 10%-that receives radiation of 1000 disintegrations per minute (dpm). would read 100 counts per minute. The rmears that were collected were counted at the INEL with a decade scaler. These instruments were utilized for all the areas surveyed.
All smears taken and analyzed for the reactor basement area except smear number 34 were less than the most restrictive part of NRC Regulatery Guide 1.86, which gives acceptable surface contamination levels. The acceptable - levels for -emovable' contamination are: less-than 200 dpm/100 cm 2beta gamma and less than 20 dpm/100 cm2 alpha. Smear number 34~was collectea inside the 2 storage tubes of. the storage facility. and read 293 dpm/100 cm beta gamma and 2 less than 20 dpo>'100 cm alpha. Figure 9 shows in detail the location and number of each saear taken and contact-radiation readings (circled) in areas where readings could be detected-in the basement. Figveest10, 11, and 12 show the location and number of each smear taken a.1c the contact-radiation readings (circled) in' areas where readings could be idetetigd for theLoperating floor and the- first and second platforms, respectively. Smears- obtained and analyzed for these areas were all less than. ED6dpm/100cm2 beta-gamma and less than 20 dpm/100 :mz alpha.
, w-- ,
'Eigures 13,14, and 15 provide the location >,- numbers, and resul ts of smkar$ taken.in-the reactor annulus. Contact-radiation readings are also Thown forLareas with the highest activities. -The resv of an isotopic gamma-
- Scan, performed on one of the~ more-contaminated smears from the reactor rnnulus~, showed europium-152-(Eu-152), Eu-154 and cobalt-60 (Co-60)-in the amounts shown in Table'l.
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- s\ 4/f 4ll47');%p%;, 7, o , Ky l' t i 7,1 'i- -l lable 1. Results'of Isotopic Gamma Scan for Annulus Smear Sample SAMPLE NAME: ANNULUS SMEAR SAMPLE ID: 112189023 5 AMPLE COLLECTION (DATE/ TIME); ?l89/1241 SAMPLE COUNIED (DAl[/ TIME): ,12189/1241 SAMPL E -(}UANT ITY: 1.0 0$ NOTE: The percent error st- m for ea_h radionuclide is the statistical / fitting component obtained fram weighted results of all phctopeaks found for the nuclide. Other error componer ts that should be considered in the total error are detector efficiency (5.07.), geometry /positioaing (5.0%), and any other errces that can be quantified (0.0%). 2 RA010NUCilDF SAMPL E ACTIVITY f uCi/100 cm ) % [RROR (1-Il Co-60 1.016E-03 2.52 EU-152 4.848E-03 3.76 EU-154 8.500E-05 22.56 l l l Figures 16, 17, and 18 prc, vide the location of contact-radiation readings taken internally in the reactor vessel. Figures 18, 19, and 20 'I _ provide the locations, numbers, and results of smears taken in the reactor ! vessel. W:ter samples, believed to be primary w :er, obtained from the reactor beam tubes contained no measurable acti ty. Table 2 provides a summary of the smear sampling, and Table 3 provides a , summary of the radiation survey conducted in the reactor building. Based on these surveys it appears ti,at only the reactor annulus and some of the reactor components are contaminated. Tran: uranic isotopes were not detected on any of the smears but, as shown in Table 1, Eu-152, Eu 154, and Co-60 isotopes were detected. The highest radiation rehdings were measured on components contained within the reactor annulus and vessel. 4.2 Buildi.y 97 Reactor Facility Laboratory Building 97 originally contained the liquid waste handling system for the reactor. This system was removed to make room for_a, particle accelerator, as discussed in Section 3.2. 311 that presently renains is the piping MTh~ ~ iron cioian't transfer line, 2-1/2-in, i; on sump pump drain line, 2 in. aluminum demineralized water line, and 1-in iren test connection _line) connecting Buildings 97 and 100. j'If total dismantlement of the reactor facility-is performed, the' utility piping (1-1/2-in. iron condensate return ., line, 2-in galvanized steel air line, 4-in. iron steam line, and 4-in. iron city water line) between Buildings 97 and 100- 5ould ~. also have to be removed. - The portion of this piping between buildings is approxiihat'ely'3;1,/2 ft below the surface. The condensate return and steam lines are encased in asbestos coverings. .(Some of the asbestos has been removed.) Smears taken from the piping-inside Building 97 indicate that the radioactivity levels are less than 2 2 2')0 dom /100 cm beta-gamma and less than 20 dpm/100 cm alpha. The piping (2-1/2-in. -iron outlet line, 4-in. iron inlet line, and 4-in, cast iron overflow line) to Cistern 242 is mostly inaccessible since it is underground and will be- surveyeiduring the decommissiocing of the facilityyThe inlet and outlet ,. . pipes are_ buried 5-1/2 ft deep and the overflow pipe is buried 3-1/2 f t deep. , -n .w ~ L__ 30
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- 200 mR/h - on back of flange i
15 mR/h - on ~ ' top of - experiment tube s ;.3. -f., , mse m, w '; ' , . i 25 mR!h - on ?%id$.g... ^ l , - Ng flange I +~ l M - yt % g 5 .r% l + v 1% ._ -;3- - - , < ; 04225 10 mR/h - on top of expenment tube 30 mR/h - on top of both expenment tubes figure 17. Contact-radiation readings for internal components of reactor vessel (View No. 2). g l ,II II I[t6 l!i -11l1l ~ ,ii1i sj!I ;!'l;1 ,!kll ;F ~ - nl oa l e e gg - w nn 2l e laa f l 1 s f o s f f oo J e v e - T g k n t c n aor bf 7 f la - f - nn 2 9 o r oo 6 e f o M A 0 c a ) hh / / 4 f s 2 RR )' . 2 n t - m mm . o l u c i s - s 0 00 h e 0 05 / r 1 5 R 1 m m y p 000 e 222 0 v d < < 7 ( r a u . h s) lp . 3 - r A a . e6 mf - s - w - r de - q o ni - lo aV - m f ( c n s - 0 o gl ne 0 1 is / 1 d s m ae o p ev d ( N r r - a 000 000 no m 22 2 ot < < e - i c - m t a - a .- ae G i , a - d i r af te ro _ -- B - . ,- t s ct % an t e nn oo - - C p -- o m j o t r ei .c , a 2 t 8 e 1 21 fu 1 l - a m n en S o rr ue gt 2 i n - j o fi f y - n o b i - : R - - mro , . 4 1 f lo . - w , ;!I ,; ll4ii i ! ,l , 4 :ii1il t = i i
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Nv 2 o N 3 w . 2 s s e 4 e i _ ) 0 b t u V ( __ 2 m la t l c n e _ e s _ 0 s 0 1 i m e r / e v _- 4 p 00000 x r _ i - 22222 e o _ < < s<( f t _ h a o c a e lp e . A r id r _ o s _ lo i n f f o . n n _ o ~ o s - t _ 0 n _ . ) 2 8 1 e _ _ n _ m o o o c N p N _ 0 m 0 1 / y i: , o c _ m p y l a d ( s' E n . a 00000 r 00000 e _ m 22222 t _ m < < < ( < n a i G - , r a o _ te f B l, _ s _ t _ < l *r*- u _ s e _ r y ... o _ N o . lo f e v r r 01 3 n u a e 891 1 1 o s m 9 r _ S a o e N m S ( 0 2 _ e n r _ od u - n g - 3 a i 1 s s F , .k e _ ocb Nr au t w* ! ll!!' ! . l l,l !ll! lll!l 'l'll! ll(i!Il l; > i 1! 4 j jIii , i Table 2. Summary of the results of the AMTL . Building 100:= car; sampling Location Beta-Gamma Alpha (dom /100 cm2 ) (dom /100 cmi ) ' Basement inside Tubes of the Storage facility 293 <20 All Other Basement Smears <200 <20 Main Floor All Main Floor Smears- <200 <20 First Platform All- First-Platform Smears <200 <20 Escond Platform All Second-Platform Smears <200- <20 r-Reactor vessel internals Floor by the-Access Ladder 204 (20 All Other Peactor-Vessel -Internal S. nears- <200 <20 Reactor Annulus - Stainless-Steel Racks 293-395- <20 . Annulus floor 200-725 <20 Stainless-Steel Piping below Reactor Gate 749-5707 <20 36 l l t _ _ , _ , - - . , - v s- -~--w' 7_ k. Table 3. Summary of the results of the AMTL Building 100 radiation survey Location Contact-Radiation Repdino (mR/h) = Basement. Demineralizer ............................................. 2.0 6.0 Heat Exchangers ........................................... 0.3 Fission Product Monitor ................................... 0.05 Main Floor Californium 252 Source .................................... 16.0 Mobile N Ray ............ .............. .................. 0.2 First Platform Reactor Keeper Slide ...................................... 0.2 Second Platform Reactor Top ............................ .................. 0.7 Magnets in Cabinet ....................... ................ 0.4 Reactor Vessel Internals ~s Blind Flanges ............ ..... ... .. ... ............... 50.0-550.0 Slant Tubes ...................................... ........ 8.0-30.0 Valves................................................... 10.0-60.0 Ped e s t al ( t o p ) . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... .. 550.0 Ped e s t al ( bo t t om) . . . . . . . . . . . . . . . . . . . . . . . . . ............. 15.0 Reactor Anaulm Stainless-Steel Racks and Stainless-Steel Pipe . . . . . . . . . . . . 55.0 Below Reactor Gate ........................................ 1,300.0 General Body Field by Stainless-Steel Pipe at 3 ft . . . . . . . . 18.0 4 37 l 1 4.3 Cistern 242. Waste Water Retention Tank ~ Cistern.242 was filled with water during the radiological surveys s conductej at AMIL'during September 1989 and was not surveyed at that time. -Smears and sediment samples were also postponed until the tank is pumped. The water in the cistern was sampled during February 1990 and found to be well below- the radioactivity levels of drinking water standards. There was no measurable gamma activity, other than the natural pot >:stum 40 and radon / thoron daughters from the natural uranium and thorium decay chains. The gross alpha and beta activity levels for the sample in pCi/mL were (2 1 5) x 10"0 and (1.3 ! 0.17) x 10'8, respectively." l
- l. Samples were not collected from the interior of Cistern 242 during the week of March 26, 1990, as the water had not been removed when the EG&G Idaho sample team was at AMIL. Based on the above results of the analysis of the water sample taken in February 1990 and on the low levels of contamination found in the reactor vessel, it is assumed that the cistern does not contain any substantial amount of radioactively contaminated materials in t,he form of sediment or sludge.' If the cistern interior'is Tot sam' pled uit W l
the Iimi'of'the decot.nissidning activities and is found to contain mixed . waste, it could have a significant impact on the decommissioning costs. 4.4 Area Surroundino Buildina 100 and Cistern 242 we During September 1989, five o:tside soil grab samples were collected around the reactor containment structure. One soil sample was also collected between Building 97 and Cistern 242 because hand-held gamma instrumentation detected higher-than background levels of radionuclides. These soil samples l were obtained_only to be used as gross indicators to ascertain whether or not contamination had migrated outside the reactor containment facility. As the i samples were not obtained using proper sampling protocol and are not legally s l defensible, the results are not reported in this report. l 1 38 x. In March 1990, sediment and soil samples were collected at the surface and subsurface from locations around Building 100 and Cistern 242 using proper l ,, sampling protocol" (see Figtire 21). These biased and random samples were collected to determine the variance of possible contaminants on the surface and at depths surrounding these areas. The cistern and reactor area samples were analyzed by the following Environmental Protection Agency (EPA) methods as specified in the Samolina and Analysis Plan for the MTL Cistern and Reactor Atta": metals by inductively coupled plasma (ICP) atomic emission spectroscopy (SW-846, method 6010),leadbygraphitefurnaceatomicab'sodption spectroscopy (GFAAS, method 7421), and mercury by atomic absorption (AA, method 7471/7470). in addition to the above analyses, a broad suite of analyses for organic compounds was also performed at two sample locations (MTLO90lMP and I MTLO902MP). These analyses were conducted to the following EPA methods: volatile organics by method 8240, semivolatile organics by method 8270, polychlorinated biphenyls (PCBs)/ pesticides by method 8080, organophosphorus pesticides by method 8140, and chlorinated herbicides by method 8150 (see Appendix A*). Table 4 provid,es the results of the chemical analyses for the above _ , . sediment and soil samples collected around Building 100-and Cistern 242. v
- a. The main purpose of including chemical analyses of soil samples collected around Building 100 and Cistern 242 during this characterization effort was to identify any potential hazard to workers during decommissioning. Release of the site by the NRC for unrestricted use depends only on radioisotopic concentrations in the soil.
39 - e- w-,- g,- g , -- , ..-m- ~ , 9 n o 3 - " N m o n o - n s o n o .5 o m - - - N N w n c1 n e n n y a y m v o ^ v e , . . n v M 3 A ~ O 5 ~n - m 5 o 5 s 55 co n 3 '2 e o n f /n ,J e n oc cn o n a
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co n 3m n a dd ~~ n v .O ~ - 22 y o ~ e d n ~ m _ sss none .2 o. i - e- a n o - ooo u 2 O esos coo~on e g s. c 4 J - a ri = I - o S . m S ~ $3"5 a0 A " m3 c m i ga n 8 - y - u cEu - 5 mese .- N e nuam o a o en m w , .: c u o -c m 1 D - I n = u s - a m c m - o 9 - b 1: e * *99 o - u & m n @a a: c3 . 2 a m 5 m n - n o n ymyy 3 e u ---- n - a e oceo - e -nnw n 2 m n ocoo - J 53 e ~~~~ w e- - - >= n cn m m - 2EEE oo N C n c. ' QQMQQ 3" 4 @ 4 unMn-ococo 25
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1 g 33 -t oo co'wS.wrm c A - '- 1 , ww m aa o .a u n l eo GN N""*'****"" $N 5 T *.cv e - oc 22222 -w on ,C - ww w m - EE w ==1= w ,r ~r ~r - ocoo -*rNn m nn N >=>=m .c -coco O N QQ a . a. . D w m ~ o "N ao 2222 " n -d > - - 3 bE m N m - = 52 53 nn , Q co " n wr N E oo D ot 0 c mo CC aa L 0 C3 co = c:: - o c: =$ .cn a u. i t 1 40 1 -w 4 4 I Table 4. Summary of the-results of the chemical analyses for surface and subsurface sediment and soil samples collected around Building 100 and Cistern 242 54rple so. j t0CAI104 lStPtM ltPL Sb g46 Se Cd to lCr Cu Mg et Se no in I I fft) (mg/bgi it egt.6g) (og/kg) togf6TI (*1/tfill*9/11) (*1fb18 (*1fkti (*1/69) (egftgl ut - , 2. 5 12 ~ 0.95 (og/6g).g 0.44 6.1 !23 92.4 0.4 26.se I.9 116 64: Mit olo: M (85ftem 2-3 f.18 ElI6foin Cl5IIIs 56 D4 Mit 030t M C151(#4 9 10 1 E67 29.3 Mit040ln iiillas Mt 7.61 24.6 Mit0102M Cl511as 21 15.1
- 60
. 28.) 31.1 . Mf4020/M Caillig ~$ 6 90.4 0.991 9.9I 26.1 23.1 391 Mit0302M (15ffan 9.5 10.5 80.6 e.65 29.1 2}.6 sifii5ls~ fi1 Tina 14-16 s.23 sit 0103M Ellitan 23 98.6 26.7 26.7 204 Mit0203M Cf5IEE4 56 }9.9 II. 7 Ill 4.Un 355 ! 'Mit0303M Cl5ifRN 9 10 78.3 24.9 25.7 EII0463M Il5II8N 84 15 97.2 '0.957 ~ 12.M 26.8 467 Mit0t04M f$51149 2-) 100 24.9 Mit0204M C15ITR4 l.lf }Ei 516 56 il 96 0.534 JT~e Mft0304M C851(84 9 10 13 ' e f45 ' _83.6 0.552 27.3 ft.) 202 Mit0404M [I5ilat 14-15 WO60lp 'RfAC10A AAfA $URfACf 0.47) 26.6 Mit070tn IIACIOC AAfA 96.4 10.4 37.1 )).4 .MtiO692M AIACICA AtfA Su# FACI O W1i6102M ItAC10e AntA 90.6 16.4 3s.4 E. 4 Mit 060)M SfACICR A#fA SuefAtt 96.2 SitiG61M~ Itf ACICA Aa( A M't0604M a(Acton Aa(A sua#A(t 21.6 Mit0104* AEACIO4 Aa(A ~0. 5.0 ) 16) 89.1 to.2 '34.2 Mftl}0tn REACIO4 A#iA tualA(( M t i I 302M IfACl04 ARIA 553I (( Mf(1303M 8(ACIO4 as(A ScafACE Mfil304M AIAttoa AAfA Suit 5i( 0.477 Mitt 30$M AIACf0E Aa(4 SuR8 ACE EIll306M IIICT6'A AREA METICi. Mill 30fM k(ACIOR ARIA 5URfACL 1.54 Mill 30en RfACIO4 A1(A Su8f AO' O.462 U2 29.1 Mill 309M stACIDA ARfA SU*fACf 7 Mill 310M RfACf04 AAfA 35ItiI[f 0.692 ~~ Mill 3tlM A(ACIOR AtfA SURFACf CI) 31.6 0.429 Itllt)lta A(ACICA A#f4 %IIIll 82.7 0.459 8.62 31.2 21.4 Iltill)M A(ACIOR AEfA $URf ACE 'Allilleg Iii[TOA AA(A Su4fACC Mit t 3 8 5M alACice AatA SuptACL Mit0404AM _IIITTim 14-16 APeca in 9 3. ) 1.00 te.2 17.7 Mit0104AM RiA[iwA AGl4 2s.o I 494 15 47 APPDI 18 112 15.3 44.5 Mit0%33MP IIIT(an 7 pig 31.1 516 a[Pt IC Alf a.22 Mit0902MP IIA [IOR AR{A li*lt 2[PtlCAlt 92.9 II.6 Mil 090)MP 38 23.2 i l[ ACID 4 AR(A AIPtiCAll 79.2 U2 Blank spaces indicate concentrations within the range of background concentrations. Background contentrations and sample locations are provided in Appendix C. . _ _ _ _ - - - _ . . .. _ ~ . O Comparison to background soils may not be representati w of soils at AMIL due to the number of different types of soils used for fill material at the 1 reactor site.' There were no volatile organic compounds, semivolatiles, 4 PCBs/ organochlorine pesticides, organophosphorus pesticides / chlorinated herbicides, lead, or mercury detected at elevations above EPA regulatory . limits pertaining to the identification and classification of hazardous wastes ~ (as specified in 40,CFR 261, " Identification and Listing of Hazardous Waste." and including .the toxicity characteristic revisions effective September 25 -1990 (Federal Register, March 29,1990)). Although metals were detected at concentrations greater than the upper tolerance limits with 95% confidence, all detections are less than EPA regulatory limits for hazardous wastes.12 The EFA regulatory limits are those that pertain to the identificatior, and classification of hazardous wastes, as specified in 40 CFR 261. BecaulfL metals were the only contaminants detected in soils, the relev nt section of . - these regulations is that which pertainsjoJhe_identifjcatjon of_" toxicity characteristic metels" identified in 40 CFR 261.24, through use of either the , ToTfcTtTCharacteristic Leaching Procedure ((TCLP), EPA Method 1311., 40 CFR 261 Appendix 11] or through a total analysis (see below). Effective September 25, 1990, the TCLP replaces the EP toxicity leaching procedure. ~
- b. Comparisons with background samples is an appropriate method to indicate if significant contamination has resulted from a given activity or process.
and the concept can be applied to any environmental setting, including industrial and residential setting. As indicated above, the use of different types of soil for fill materials at the reactor site may complicate these comparisons. However, the soil-sampling data at these areas show that gross chemical contamination (from spills, for example) has not occurred, and that hazardous waste / mixed waste would not be generated by any decommissioning activities involving _ soil removal or disturbance. 42 4 The TCLP method states that the TCLP test need not be run where a total analysis of the waste indicates that the regulatory thresholds could not possibly be exceeded. This situation is applicable to the soil samples taken ^ fromaroundBuilding100andCisttrn242,wheretotalanalysesformealh (using SW 846 methods) showed levels that could not possibly exceed the regulatory limits if subjected to the TLCP. In this and other cases Mre solid samples are involved, maximum TCLP levelt are calculated by assuming a ' dilution factor 'of 20 times the total metal concentration (based on 100'g of sample and a dilution with 2 L of extraction fluid), and a theoreticalworst-case leaching of 100%: 40 total contaminant cone. (mg/kg) x 0.1 kg maximum TCLP concentration (mg/L) - 2.0 L , Under this worst case assumption, metal concentrations in all samples are below the EPA toxicity characteristic limits in 40 CFR 261.24. (These limits are shown in Appendix B of this characterization report). _%- The March sediment and soil samples were also analyzed for gamma-emitting nuclides by gamma spectroscopy. InTable5aresummarizedthigamma-analysis results that were positive but that did not satisfy standard EG&G ~~ Radiation Measurements Laboratory (RML) selection criteria and those of the v analyst. Rejection criteria codes are described below Table 5." Table 6 summarizes the man-made radionuclide results from the computer-generated gamma-ray analysis summary that were found to be true positive according to the criteria contained in the EG&G RML procedure, "DM-1: Evaluation and Verification of Data for Radionuclide Identification and Sel ection. "" True positive results are defined as values that have a measured activity >2 measured standard deviations. Table 6 includes the activity with the associated statisti al L ' uncertainty, Activity (S), and the activity with total uncertainty, Activity (T). j 43 -Table 5. Analyst's results of rejected gamma emitting nuclides for March 1990 sediment and soil samples Samole ID No, Radionuclide (Gammal Analyst's Rejection (qdg - MTLO101AG Cs-137 1, 2 MTLO102AG Cs 137 1, 2 Eu 155 1, 2, 3, 4 MTL0iO2AG Cs 137 1, 2 MTLO203AG Cs 137 1, 2 Eu 154 1, 4 4 MTLO302AG Zn-65 1, 2, 4 MTLO303AG Co 60 1, 2 MTLO404AG Eu 155 1, 2, 3 MTLO601AG Agm 110 1, 2, 4 MTLO602AG Eu-155 1, 2, 3, 4 MTLO702AG Eu 152 -1, 2, 4 MTLO703AG Eu-155 1, 2, 3, 4 MTL080lG Cs-134 1, 2 HTLO805G - Agm 110 1, 2, 4 ~~ MTL1303G Eu-155 1, 2, 3. 4 MTL1307G Cs-134 1, 2 Cs-137 1, 2 Eu-155 1, 2, 3, 4 MTL1309G Cs-137 1, 2 MTL1313G Eu 155- 1, 2, 3, 4 MTL1315G Eu 152 1, 2, 4 Reiection Criteria Codes:
- 1. Uncertainty too high to be accepted by analyst.
- 2. Radionuclide result below quoted RML detection limits.
- 3. Other radionuclide gamma-ray interferences.
~ 4. Graphical display of analyzed photopeaks (VTP) showed unacceptable photopeak fitting results. 44 T- - - + nm q s r + s . - 5
- l Table 6. Analyst's results of man-made true positive gamma-emitting nuclides for fiarch 1990 sediment and soil samples Radianucthje Act ivity (5)1 Uncertainties (%) Act twity (1)2 (pCi/g) 5 tat ist ica l Geo Eff (pct /g)
Saaple 10 No (G m ) Mit0103AG Co-60 (+6.32 +/- 30)E-01 4.8 5.0 5.0 (+6.32 +/- .54)[-01 Cs-137 ( +1.89 +/ 122)f- 01 11.5 50 5.0 (+1.89 +/ .26)f-01 Cs- n? (+3 18 +/ .34)f-01 10 6 50 50 (+3.18 */ .40)f-01 . Mil 0134A6 I I Mit0203AG Co-60 (+2 45 +/- .'9 ) f - 01 11.6 5. 0 50 (+2.45 +/- .$)f -01 Hit 0204AG C:.- 137 (+1 62 +/ .19)t-01 11 8 50 50 (+1.62 +/- 22)f-01 Mit0304AG Cs-137 (+1.72 +/ .28)t-01 16. 5.0 5.0 (+1.12 +/ .30){--01 Mit0601AG Cs-131 (+2.12 +/ 31)f-01 14 6 a.0 5.0 (+2 12 +/- 34){-01 , M1L 0t,02AG Cs-137 (* l . 83 +/- 31)t-01 16.8 5.3 5.C (+l 83 +/ .33)E-01
- Mit0603AG Cs-137 (+4.89 +/ .42)E-01 8.5 50 50 (+4 89 +/ .54)E-01 w
l 5.0 5C (+2.83 +/ .40)E-01 Mit 0604 AG Cs-137 (+2.83 +/- .34)t-01 12.0 Mit080lG Cs-137 (+2.50 +/ .34)[-01 13.5 5.0 5.G (+2.50 +/ .38)f-01 . I M!t0802G CP U (+3 19 +/- 46)E-01 12.0 5.0 50 (+3.79 +/ .53)t-01 MitC803G L '1 (+4_07 +/ 60)f-01 14.6 5.0 5.0 (+4.07 +/- E4)f-01 Mit0804G Cs-137 (+1.91 +/ .41)f-01 21.5 50 5.C (+i.91 +/- . 43)f-Cl , l. MiiO60$G Cs-137 (+3.24 +/- .42)1-01 13.0 50 5.0 (+3 24 +/- 4S M -01 NILO903GP Cs 137 (+1 81 +/- 28 )f - 01 15 4 50 5C (+1 SI +/- 31)f-01 H!t!30!G Cs-137 (+) ll +/ - 37)f-01 30 8 50 5C (*) 21 +/- 36)l-01 1 Mitl302G (s-131 (+1.26 +/- .30): 23 8 50 50 (+1 26 +/- 31)t 01 Mitl303b Cs-137 (+ 2 W +/ - 40)! 01 15 1 50 $C (+2.63 +/- 84)t-01 l I 8 '( ,! ; Table 6. Analyst's results of man-made true positive gama-emitting nuclides for March 1990 sediment and soil samples (cont.) Radionuc lide Activity (5)I uncertainties (%) Act 'vit y (I) Sample ID No. (Gama) (pC4/q) St a t ist ica l Geo Eff (pC:/vi Mill 304G Cs-131 (+ 4. 69 +/ .53)E-01 10.8 5.0 5.0 (+4.89 +/ Erli-01 Mill 30% Cs-131 (+2 07 +/ .30)E-01 14.6 iO 5.0 (+2 C7 +/ .34)i-01 M7' ' 'A Cs-131 (+2.19 +/ .29)[-01 13.2 50 5.0 (+2.19 +/ .33)':.-01 MILI308G Cs-131 (+2.41 +/ .33)t-01 13 5 5.0 5.0 (+2.41 +/ .37M-01 Mill 310G Cs-137 (+4.83 +/ .39)f-01 80 5.0 5.0 (+4.83 +/ 52)L-03 MTL1311G Cs-137 (+4.12 +/ .39)[-01 9.4 5.0 5.0 (+4.12 +/ .49)i-01 MIL 1312G Cs-137 (+3_64 +/ .38)f-01 10.5 5.0 50 (+3.54 +/- .46)?-01 MTL1313G Cs-137 (+2.10 +/ 32)E-01 15.3 5.0 5.0 (+2.10 +/ .35)!-01 , Mill 314G Cs-131 (+2.03 +/- 27)f-01 13.4 50 5.0 (+2.03 +/ .31)(-01 Mill 31% Cs-137 (+1 17 +/ .39)f-01 33.1 5.0 5.0 (+1.17 +/ 40)(-01 s 1 Note: (1) ACilvlIY (5) includes tre statistical encertainty, f e ars counting statistics aM photooeak f atting--ewpressed as I standard dev sat lon. (2) ACilWlif (I) Includes the total uncertainty result tng frce the statist ical, samle/ detector gaometry, and ef ficiency. These uncertainties tuve teen propogated in quadrature--espressed as I standard deviation. l I a
- The statistical unr',ainty includes the statistics associated with counting, backgrounds, and p..otopeak fitting. The total uncertainty includes the statistical uncertainty,'the estimates of the uncertainty in the sampl'e
^ geometry (5%), and the detector efficiency (5%). These uncertainties'ha've ~ been propagated in quadrature and are expressed as one estimated standard deviition, it is recommehded that the activity results with total "- ' uncertainties,- Activity '(T), be used for quantitative purposes on Table 6. i Gama emitting nuclides were detected in soil samples collected in March 1990, and the concentrations are summarized in Table 6. The values contained in Table 6 were reported after background values were subtracted. Theitwo samples cor.taining positive indications of Co 60 (MTLO103AG and MTLO203AG) were taken from the area between Building 97 and Cistern 242, where elevated radiation readings were detected during the preliminary radiological surveys performed in September 1389. The NRC has no published release criteria for radioisotopes in' soil. The NRC determines whether or not a site can be released based on an'NRC site-specific assessment. For comparison, the Department of Energy (DOE)_ has published release criteria for INEL soils" that have radioisotopic concentrations in releasable soil that are orders of magnitude higher thhn the AMTL samples. SincetheDOEcriteriaarebasedonveryextensivepathways analysis studies, it would appear that the AMTL soil levels have a very high probability-of meeting NRC requirements. During the analysis of soil samples for alpha-emitters, sample number MTL 0102 was the only sample that contained statistically positive Am-241. and/or Pu 238. The activity concentration of this sample is 0.21 pCi/g. As-stated previously, the NRC has no published release criteria for soil. For -comparison, however, the DOE INEL soil release criteria allow soil to be released with a Pu-238 concentration of 300 pCi/g and an Am-241 concentration-of 80 pct /g. It would appear that the AMTL soil has a very high probability of meeting NRC requirements-because the AMTL alpha-emitting radioisotopic concentration is orders of magnitude lower than the DOE criteria, which are base on very extensive pathways analysis studies." ~ 47
- 5. POTENTIAL PROBLEM AREAS i
, No major problems.are anticipated during the decommissioning of the AMTL reactor. This viewpoint is based on the results of the limited
- thira:teri:ct4;r. d: scribed 17, this riport end oti ihe operating history of the reactor. However, during decommissioning of the AMTL reactor (or any other nuclear facility), there is the possibility that previously undetected, sequestered contamination will be encountered. The potential for discovering unanticipated contamination exists in any of the reactor systems, components, and equipment, but the impact of any surprises can be minimized through standard decommissioning practices, which include continuous radiological monitorinc as work proceeds.
T!.e AMTL reactor system that presents the greatest potential for having sequestered, unexpected contamination is probably the radioactive. liquid-waste system, especially Cistern 242 since the cistern has not been characterized except for radiological analysis of the water, which showed no contamination. Discovery of radioactive or hazardous contamination in the cistern or soil beneath the cistern during decommissioning could increase the project cost and delay the schedule. In addition to'the liquid-waste system, another potential problem is the possible unexpected, sequestered contamination in concrete. This could ~ ~, e especially be-a_ problem if partial dismantlement is the selected decommissioning alternative and the sequestered contamination is discovered in the. concrete- floors and other concrete to be left intact in the reactor building. e 9 48 e,
- 6. REFERENCES
-- 1. Army Materials and Mechanics Researth Center (AMMRC), Doerations Reoort - of the U.S. Army-Materials Research Acency Nuclear Reactor Facility, . J6ns 15, 1900 LO OEce..fdsr 31, 1904.
- 2. AMMRC, Operations Report of the U.S. Army Materials Rese. arch Aaency Nuclear Reactor Facility, (License R-65, USAEC Docket 50 47), Raport No.
2, January 1, 1965 to December 31, 1965.
- 3. AMMRC, Operations Reoort of the U.S. Army Materials Research Aaency Nuclear Reactor Facility, (License R 65, USAEC Docket 50-47), Report No.
3, January 1, 1966 to December 31, 1966,
- 4. AMMRC, Operations Reoort of the U.S. Army Materials Research Aaency Nuclear Reactor Facility, (License R 65' USAEC
, Docket 50 47), Report No. 4, January 1,1967 to December 31, 1967.
- 5. AHMRC, Ocerations Reoort of the U.S. Army Materials Research Acency Nuclear Reactor Facility, (License R-65, USAEC Docket 50-47), Report No.
5, January 1, 1968 to December 31, 1968.
- 6. AMMRC, Operations Recort.of the U.S. Army Materials Research Aaency Nuclear Reector Facility, (License R-65, USAEC Docket 50-47), Report No.
-6, January 1, 1969 to March 27, 1970.
- 7. AMMRC, Deactivation Reoort of the Army Materials Research Reactor, December 8, 1970.
- 8. AMMRC, Report of insoection, C0 Report No. 47/69-1, U.S. Army Materials and Mechanics Research Center, License No. R-65, Category E, May 8 and
_ _ . 9, 1969, (U.S. Atomic Energy Commission, Region ! Division of Compliance). me
- 9. W. D. Schofield, Radioloaical Survey of the Army Materials Technoloav Laboratories, WDS-30-89, December 5, 1989.
- 10. T. C. Sorensen, Gamma Analysis of the Boston Army Material Reactor Liauid Samole #AMTL/A6A0U01, 105-05-90, February 28, 1990.
- 11. S. M. Burns et al., Samolina and Analysis Plan for the MTL Cistern and Reactor Area, EGG-WM-8889, March 1990.
- 12. ES&E,-Inc., MTL Samole Analysis Results, 6902012V 0402, May 1990.
- 13. K. J. Durfee et al., RML Gamma-Ray Analyses of MTL Cistern and Reactor brea Samoles for Environmental Restoration Proarams, ST-CS-023-90, June 1990.
- 14. Development of Criteria for Release of Idaho National Enaineerina Labor.atory Sites Followina Decontamination and Decommissionina, EGG-2400, August 1986, 49
_ ~- _ _ . l Y .o O APPENDIX'A EPA APPENDIX IX ANALYTES i, 4 e k \ N APPENDIX A. EPA APPENDIX IX ANALYTES (Ket. 40 CFR 264)*# APPENDIX IX - GROUND-WATER MONITORING LIST' Comrnon name ' S3 - CAS RN 8 Ctwd w;svects senace ev5em name
- ocs
- 3e Aconaonthene- . ,, 6.L;2-8 Awehinysene.12<Lhyon> 8100 200 Acenapnmytene - 8270 10 206-96-8 Acenaontnytene 8100 200 Acetona 8270 10 6744-1 2-Propanone -
Acetoonenone 8240 100 Acetonme: Memyt cyanca 98862 Ethanone,1.phenyt. . 75 05-8 Acetonwe . _ _ 8270 to 2 AcetytarnanoNorene; 2.AAF 8015 100 Acro:em 53-96-3 Acetatnde, N.9H.fluoten 2.yk 107-02-6 8270 10 2 Provenal .-. 8030 5 Acrytonrtnie 8240 5 107-13 1 2 Propenenstrue 8030 5 Aldnn 8240 5 00 000-2 1,4:5.8-Ownethanonacht .alene, 1.2.3.4.10,10.hexachloro- 8060 0.05 Anyt cr,crwh 1,4,44.5,8.8a-hexanycro Do.44,4ad.5<i.8a.843)- 8270 to 107-45 1 1 Progene. 3<,nioro-8010 5 ArunotHphenyt 8240 100 An4rw 92671 11.1'-B$henytJ-4 imine - 62 53.3 8270 to Anmracene - Eenzenarnene i 120 12 7 8270 10 Artmracene I 81CC 200 Anamom .- 8270- 10 (Teta!) Anorrmf . 6010 000 7040 2.000 ' ' w*' Atarrate 7041 30 140-57-4 Su.+Jrous ac::l,, 2<t.oroe thyt 2.[41.1 8270 to An.enx: cimemysemy0phencry).1 meryteinvi ester Arsene ~ (Totaf) 6010 500 7060 to Barium 7061 20 (Tota!) Banum 6010 20 Befuene 7060 1,000 71 43 2 Beruene 8020 2 8243 5 a. - Metals analyses were conducted at sample locations shown on Figure 21. Organic analyses were conducted for samples taken at two locations: MTLO90lMP and MTLO902MP. See text on page 39. [
- b. Specific analytical methods are identified in the Samolina and Analysis Plan for the MTL Cistern and Reactor Area."
A-1 p.m i _ _ - . , _ _ . - . -. - ..- - ~. .. . - . , . - . ~ . _ _ - . _ - - . . - . ~ . - - . - . ~ ~ . - . - . - ~ . - _ - - - - 4 4 4 Common name
- Sug.
CAS RN 5 I Chemcal atsva:ts semes meen name a Syy , oes * !- Demalt) anthracene; Benzaneracene .i 56-55-3 Ben 2[alanthracene . et00 209 l Berec(blfsoranmene ,. 8270 10 I . . 205-W2 Eem(elacepher.anthyene - 8100 t200 Sento(k}Puoranthene ~ 207-C6-9 8270 10 Senzo[k)fluoranther e - . ~ - 8100 200 Beme(;*p)perytene . 8270 '10 ' . 191 24-2 B emo(gNj perytene -..- ' 8100 200 . Bemo(alpyrene , 8270 10 l $b32-6 Eemetalprene 6100 200 l Benryt atcenet- 8270 to .100-51-6 Beryaum - Otmanememanoi . 8270 '20 * (Tota!) Be'yttium 6010 3 - 7090 50 2;hs4MC- , 7001 ? 31be4-6.. Cyclohexane,1.2.3.4.5.MancNoro ,(1a,2a.3A.4a.!A.8B). _ 8080 0.05 to ta.B HC .- 6250 10 31b45-7 Cyclohexane, 12.3.4.5.6-be rscNoro. (1 a.24.3a.4#.fc.63> 8080 0.05 ce!ta-EHC 31F.46-8 8250 ' - 40 Cydohexane, 1,2,3,4,5.5-hexacNoro ,(tala 3a.4A,5a.6BF 6080 0.1 gamma.6HC; fJncar's- 8250 "0 58-4b9 , Cyclohexane,1,2,3,4,5.MaucNoro..(t a.2a.34,4a.5a.6By 8080 0.05 B s(2 cNoroethory}mettano 8250 10 111.S1 1 Emane.1,1'.(memykneers (cry)) tis (2.cNoro._ Bis 12.cNoroemyi) ether 8270 to 111 44-4 Ethane,1,1'.orrest2.cNoro. B4(2.cNoro 1 metnyiethyl) einer, 22'.0L 106-40-1 Ptecane,2.lNryto[1.cmoro. 8270 10 ' cNorocusooropyt other ' 8010 100 - Bis (2 ethymeryt) pntha4te , 8270 10 117-81 7 1,2.Semeneccartoryte aed, bas.(2<rttrytheryt) ester " 8060 20 Bromocchloromethane 8270 ,.- 75-27 4 Methane, bromods:Nero. 10 801v i Bromotorm; Tnbromometnene 8240 5 75-25-2 Metnane, inbromo.
- 8010 2
#.Bromoonenyt phenyt stner- 8240 5 101- W 3 Bemene.1 bromo.4.pnercry. Bu1yt benzyl pnthantet Bemy) butyt pret.ab 85-68-7 8270 10 ste 1.2.Bemeneocarecryuc sed, turyt pnenyimetnyt ester 8060 5 Cacmum * ~ 8270 10 . (Tota 0 Castrwm ' . 6010 40 7130 50 Carton c.sufte - 4 15-0 Carbon crsube - '7131 1 ', Carton tetracNonoe - 8240 5. ~ - W 23-6 Me51ene, tetract*ro. 8010 1 Chercane 8240 ,5 57-74-3 4.7-Mecano.1H4ncene, 1.2.4.5 A7.8.8-oc:enoro. 8060 0.1 2.32s.4,7,7a.hexanyoro. PCNorcandine 106-47-8 Ben 2enamme, 4.cNoro. 8250 to Chbrcoercane 106- W 7 8270 20 Beruena, ct16oro. . t l 8010 2 8020 2 CNorocem: tate -- 510-15-6 8240 '5 Demenesceoc sed. 4:nlero a.(4<:titorooneny0egorcry. 8270 10 p-CNorowscresoi et*rr4 ester - 54-50-7 Phenot. W 8040 5 CNorce:nane: Emys cNonce , 8270 20 75 00-3 E:hane, cr. toro. 8010 5 l- CNortdonn 8240 10 . 87- M .0 Memane, Incnwo. _ __ 8010 0.5 - ECaorenacre.aaene - 8240 5 l 91-68-7 Noorft.asene,2 chloro. , 8120 10 2Ca::roote 8270 10 &$-57-8 Pw, 2<:tworo. l 5340 5 \ l 8270 10 l l A-2 y-~w--.-v=-- v -. ..y--- --ym ,,r.m-.v.,ww. wv ina- _ - - - - ,- - . * -. l
- l Sug.
CcWn aa+e 8 CAS RN a j Chemical abstracts service ences eame * [ ([,3 , oct* 44hkyoonov p%4 emer . 700b72-3 Benzene,1.cNor 0-4.onenory.._. . . _ . I 8270' 4 Chew one . ... .. . _ _ 126-94-4 1.3.&Amoene. 2<.Woro --- - .I 8010 I 50 8240i 5 Charnive9 .-.. ... (Tota!) Chromum - l 6010! 70 .l 7?M i 500 [ 7191! 10 Ohysene --_ -. .- ... . 21bC1 9 Wsene =. ... - . . . . 8100! D0 1 6270 10 Cotxt..._, . -_ .d ~ (TotaJ) Cobam-. . . - . . . . _ = - . . . 6010 70 7200 500 7201s 10 Cenew (Tr.:'; Cec;r _.. , . . . . _ _ . - - . . . . . . _ . 000 l 2.0 l j 7210j 200 m4resas .._.....i 136-34-4 Phenol. 3-memyt. .. _ . -.; B270! 10 o4rosod _ ..J 95-48 7 P*.enot 2.memy6 p.Crewt .-......-...._.........l 8270 '0 .. .. 1M-44 5 . Pws. 4aea y' . ...: f 270 ' 'O Cythioe -.. .. 57-12 5 ... ..- .d 9090 40 2.4 0 2 4.Dcruoroonenenace0c acus .. ...; 94.7b7lCyanice,. t Acetic aed. (2.44chooonenoryh -.. .. j 8150' 10 44 000. _ _-. ,.....' 72-54-4 i Benzene 1.1'42.2octuurostreconepbis(4.crworo. ....~ _.. 0060 : 01 1 8270 l 10 4 4'.OCE- 72-5b9 Benzone 1.1'-idetorceWioemtn{4.cnkaro - .- 80806 0 05 8270 ' 10 4,4 .CO T... _ -. 50-29-3 Denzene 1.1'42.2.2.trotoroomywenettes(4-choro. - -..l 8080 ! 01 8270 1 10 Dasate .. 2303-16-4 Carbamothoc avd. b s(1 metnyiemy4 , S. (2.34cioro-2 8270l 10 procenyt) ester Dbenzt a.hlantryw*na 53-70-3 Diberu[s.hlantrvacene . . . . . , . 8100 ' 200 l 87701 10 Dbenroturan , j 132- W 9 Dberuovyran. 8270 ' 10 D brottocncomoeane- CNoroo&omo- 124-46-1 Mamano C&omocnicro.- 8010 l 1 mamane 8240I $ 1.2Obromo 3-ctvorcpropane. CDCP . .. 96-12 4 Prooane.1.24tromo4.cmoro. . 8010 ' 100 8240> 5 ; 8270l 'O 1.2.Dbromoemane. Emyione obrtmoe 106-93-4 E thane.1.24 bromo. ., 5010 - 10 Di*outyt phthadate - l S240 i 5 64-74-2 1.2.Bentoneocarboryiic acx2 Sbuty1 ester.. ... .. _j 8060 ; 5 '#~. 8270 to o.Dcesorotenzene ,.-.....-....i 95-50-1 Benzene.1,2cchoo. -J 8010i 2 1 ' 8020 4 5 1 4 8120 i 10 8 Y 8270 10 b o W ooenzene d 541-73-1 Benzene.1.34cNoro . 8010 ' . ~ . . - - 5 8020 $ I ; 81204 10 8270 ?O o-Comrocenzene .. . t 06-46-7 ' Benzene.1,4-ommoro .. ...~. a010 2 6020 ; t 5 l 8120 : 15 l j 6270: to ?J-Cichocoermone . 4 91-94 1 l [1.1* Bohenyt].4.4'oarnme 3.3'oemoro .. . - 8270l 20 tranS 1.4.Dchoo 2-butene i 110-57-4 l 2. Butene.1.4ccNoro., (E)... 8240 ' 5 ' . . . - . . . . ~ . . . . . - . . . . . Dichcocmucrorretnano . 7b71-4 ' Metnano, dicmarodifluoro .. 8010 i to 8240i $ 1.10coroemene 7b34 3 Ethane.1.t ocNoro. - 8010! t 8240l 5 1.2-DcNoroethane; Ethytene dcNarce 107-06-2 Ethane.1.24cNoro- O5 3 8010! l 8240l 5 A-3 1 1 I- Sue-
- Conmw namea CAS RN 8 Cherrucal abstracts tennce shoes hesmee gee W PCL rnetn- (, gW poe e
- t,1.Dic woreetryem; vaytreem c-+teh l . 75-35-4, Ethene.1,14cnicro - . -. 4010 1 T - trans 1.2 0cmoroethytene e2= lf 156-60-5 Ethene.1.24cNuro .(Eb . . . - -- .i ' 0010 t 8240 5 2.4 0cNoropherd .; 120-83-2 Pharci, 2.44cNoro- .. -- 8040 5 4270 10 2.6-DcNoroohenot._ 8745-0 Phenoi. 2.64cNoro _ ~ 8270 10 1.2-OcNoropropane 76-87 5 Propane, IJocNoro. --- . _ . . ~ . 4010 0$ 8830 5 tas.t.3 DeNoropropone 10C41-01-5 1.Propone.1,34cNoro , (Zb 40 . . . 20 8240 5 1rans-1/J.ucNoropropone 10041 02-6 1. Propene.1,34cNoro.. (Eb , 8010 5 8240 5 Deidnn _. =. 60-57-1 2.7.3 6 Dmethanonannth(2.3 t:)orsene. 14.5 6.9 9*en. 8080 0 ".5 scNoro ta.2.2a.3.6.6a 7,74.octanyoro.. (1aa.2Alsa.3A 8270 to .63.8aa.7A.7aak j bothyl pntraare _ 84462 1,2 8enzeneccartery'ic scus. $ ethyl ester 8060- 5 8270 9 0.0 Dethyt 0 2frasnyt chosonorott-sta. l neuen 297 97-2 PhosonorotNow acid,0.04etnyt CLpyrsteyl ester . 8270 l . 9 Dmetheats 80-51-5 Phosonoroothoc acxt. 0.04rnethyt S-[2.(methytammoF2 ! 10 p-(Dmethyismnotazoberoene. caoethy0 ester 8270{ 60-11-7 Bemenartwne, N.N4 methyl-4.(pnenytazob 8270' 10 7.12.Dmethytbomialantnracone 57-97-6 Bem[alancracene,7.124metnyt. .. H 8270 10 3.3'.Dmetr4emone 116 93-7 [1.1'.Broneny0 4.4'4amme. 3.3'4methyt. .! 8270 to sicha, acna Dmethytphenethytamma 122 09-4 Bemeneetnanames, a.a4methyt _ _ ! 8270 to 2.4 Ometny5 ence 10 b67-9 Phenot. 2.44methyt._ . .I 8040 5 . 8270 10 Daethyt pnth, ste - 131-11-3 1.2.Bemeneecaroomy6c scus, cimethe ester m _ 8060, 5 8270 to m.Drutrocenzane 99-65-0 Benzene.1.34rvtro.. - . , 8270 'O 4.6-Cevtro.o croso - 534-52-1 Phero, 2.memyt464 nitro. . -4040 150 8270 10 2.4.Drwtrophenot $1 28-5 Phenol. 2.44nttro .; 8040 150 . 8270 50 2,4.Cemtrototuene 121-14-2 Benzene,1.methyi 2,44rstro- _ , . 8090 02 4 . 8270 to 2.6.Dwtrotoevene , 606-20-2 Bemene. 2 methy61.34rwtro. 4090 01 8270 10 Dnoseo: CNBp. 2 sec.8uty6-4 64rttro. 888k7 Phenol, 2.( t.methy+procytb4.64rutro. 8150 1 onence - 8270 10 N D-n.octyt entrsate 117-64-0 1.2 Benzeneocarcorytc acid. eccts ester l 8060 30 1 8270 to 1.4.Douane - - - 123-91-1 1.4.Oionane S015 1$0 Donervamine ! 122 36-4 Benzenarrene. N.pnenyt. ,' 8270 to Dsu foton.. 4 No-04-4 Phosonorodianoc acic. O,04etnyt 5-{2.(ethytttwok S-(2 8140 2 othy1} ester 8270 10 Encosurani 959-96-8 8.9.Metnano 2.4.3-0*nzoconstNeoin. 6.7.8.t.10.10.hes. 8080 : . 01 acNoro 1.5.5a.8.9.9e-nosanyoro., 3.omde (3e 5ad.6a.9a 8250 to .9eAb Endosudan 41 8080 0 05 ) 3321345.9 ls 6.0 6.7.8.9.10.1(Men. etoro.t n r2.4.3.benredouseNece1. 1.5.5a.C.9.9e+esahydro- 3.omde. (3a.5ea.GA.9A.9eak Encondtan sutete _ 1031-07-4 6,94Aethero2.4.3.bensooonathispet. 6.7.8.9.10.10. hem. 8080 0.5 acNoro- 1.5.54.8.9.9a.nemanyoro . 3.34omcat 8270 to Erenn 72 . 4 4 2.7:18-Omoinsionsonsh!2.3-0]onvene. 3.4.5A9,Seet. 8080 0t ecNoro ta.2.2a.3.8.6a.7.7a.octanyoro , (Isa. 8250 10 2A.2aA.3e.6a. Sad,7A.7aa> Enonn aioenyoe 7421-03-4 1.2.4.usehenocvesapente(caJr,.c. ; -AT.0-ander yce. 8080 02 1 2.2a.3.3.4.70- _ sw-:-s m ' sos (1a.2A.2aA,4A 8270 to .4ad.5A. sea.sbA.7R*)- A-4
- a;
_* Sue t ce=nm name
- f CAS m f
CW etmo ne~ee rees na- a '$'d! ocs* M, e u.e,, ._ _ . __._.- 2 [ -<i.4 se.ame.e y _. _ < _ _ _ . _ _ _ =0 2 l 8240 5 Emyt metnauytete~ ; 97-63 2 2Accenoic a id. 2 metnyt etne ester -- 8015' 10 8243 5 Etnyt methanewtonate -- 4270 10 . 62 50-0 Weeanesanorte acid emyt ester . - . _ . 8270! to Famonur._ - 52-85-7 Phoepenroinec . sesa. 044- 10 ' R270 l ((asmethytaminoisuttonplohengl.O.O.emetnp ester Fluornnmene ._. = I 2'3-44-0 Fluorentnene __. . -. 8100j 200 8270 i 19 fluorone . _ __ _ _ . . _ e6-73-7 9Mkr'ene - . . - - __ 8100 l 200 8270 ? 10 hootacrwor _. . . 76 44-8 4.7 Meowo1H.endens. 1.418.7,8 Ahaptacreoco. 8080 1 0 05 i 3t.4.7.7elets'vro- . GGG- 14 Hootactuor ecosice 1024-57-3 2.5.Metharo2H4noeno( 1,241o urene. 2.3 4.5.8.7.7Jwo- 8080 > 1 l tactwaro ta.10.5.Se 6.6t houarwt>. (l aa.t cJ.2.a.5a 8270 1' 13 i .5aa.es.saw H$tacNorocenzene q 116-74-1 Beruerw. Seaaerworo . -. 8120t 05 8270 ' 10 Hemac.uorocutMiene 87-68-3 1.34Ntadiene, 1,1.2.3,4,4.herscrooro-8?70i 5 _.l- 8270; 10 - 5esacruorocyctooentasone ~ 77-47 4 1.3.Cyoopentamene. 1,*..1 415.hwuncrooro._.. [ d 81201 BJ70l 10 5 Heta&.toroethane -- .I 57-72-1 Ethane, benacNt= o- - 81201 05 l 8270 10 Hexacmoroonene w 70 30-4 Pnenot. 22.metm4enobs(14 orIncteoro- 8 770 10 Hanacruorcorcoene . j 1884-71 7 1.Propone. 1.1.2.3.3,3.henactuoro- _ 8270 10 2-Mesanor'e 591 76-4 244enanone incenot1.2.3<4pper's -., . -- 8240j 50 _ 193-36-5 anoeno(1.2.3.cd] pyrene 8100t 200 8270I to Isoeute acohot 7&-83-1' 145rocanoi. 2.meey1. i ' 1Soonn . _1 _ __ _ 80151. 50 .. 465 73-6 1.4. 5.8.Ovnemanannontwem.1.2.3.4.10.10.he nacrworo- 4270i to j 1.4.44.5.6.Ba hexanvaro41a.4a.sa.S.54.8A84.J)- 1monorone_ 2.Cyc6cnemen-1.one. 3.5.5.tnmetne -_._ - 5 785bi . 8090 l1 60 j 8270l 10 isosatroie. 120-58-1 1,3 Bensoootose. 5.(1.orocenpF to Kocor'e . 8270 e J ,' . i 144 50-0 1.3.4.Metneno.2H<ycaocuto- (colpen'.aien.2.one, 8270i 10 t 1,1 a.3.3a.4.5.5.5a.54.64ecacNorooctanyoro-Lead _- _,,J (7otan Laac _ . . - ._ 6010 + 40 j 7420; 1.000- } 7421, 10 Dereury ..y - (Yotal) Mercury. 7470! __ 2 Ma<nacrytorstrue - i 110-06-7 2.Proponerwtrue,2.metnyt. -- y 8015 5 Memacymene - ~ ,. . . 82401 5 91-80-5 1.2.Emanessnwne. N.N4memyte2.pynsnyt#-(24rwen. 8270* 10 pmotny0 Metnonyensor - 72-43-5 Senrene 1.1'.(2.2.2.mc.,wJcc.aebs(4.metnosy. , 8080f 2 , I 8270 ; 10 Meme tremoe Bromomems.e _ ,. 74 83-0 Memano. bromo.. 20 8010 i-Memyt crwonde: CNorornemane g- l 8240i 10 74-87-3 Meemew.chwo._ - . . , . -8010! 1 3.Mempercantnrene 8240i 10 _-- ., : web 5 Beinz(lloosantnrpene.1.2eyero4aetnyt. 4l 82701 to o, - Mempene Dromw* Dbromomemene 74-95 3 Momene, ceremo. 8010t '15 MwtNene cheondet Derworometnene - .1 /5-Ob2 Meeane, diemoro- _'l 8240t 5 ' .) q 8010? 5 i , 4 8240 1- 5 L A5 _ a __ u. _ _. _ _m . . _ _ _ _ _ _ _ -
- i Sug. i s Oc w W e8 ! CAS AN s Chemcx anstras.s service inoen na.mo e Qhed j ,
, i i ocs' Metr'yt etN hetene. MEL .. ... l 78-93 4 2&tanone * ...._.1._~ , 8015! to j > 8240l 100 Methyt ecc--e. tocorsemar4 . .J 74-88 4 i Methana, a;x10. 80101 40 l 82401 ! Memyt rnethacry'ste . . .. . . . . . .....l 8462-6 { 2.Propenc*c ac4. 2 cretnyh rre?yt der......._.. . . _ , 8015 i 2 ]' ! 8240i ! Metr +yt rnetwesuffonata 86-27-3 Metharesutionic aed methyt ester . . . . - . 8270 ! 10 2 Methycarnmeene - _ .. ] 91 57-6 Nachthavne. 2.thethi _.. ._ .__ .- 8270l 10 l Mattivi parstbiort Farathon rnetnyt 298-00-0 Phoepnorothioc sec 044rnethe 044.<vticorenyo war _ 8140 - 05 l 8270 90 1
- 4. Methyl 2 pentanore. Methyt isoevtyt 108 10 1 2fentanone. 4.methy4 _ '
0015 $ ketone i 8240 50 Navnehawne - 91 20-3 Nachthrene -_ .. .- . _ ..., 8100 000 ; i 8270 ; 10 1.4.Nachthocinone _J 13415-4 i 1.4Aapturnaienecione . ; 8270i to l 1 Naphth 'rNT4 _ 134 32 7 i 1.Naornhaasname _i 8270 6 10 i 2-NapntNamee ._.. ....__.J 91 t6-8 ! 2 Napntnaenamne - . . - . . . . . BUO: 10 1 Nicmes ~ (7 cts) , Ncsos.. (010t .m- ! 50 l ?!?O . 400 , 04etrea%ne .._ ,. _ . ._ J 68-74-4 Semenai+==. 2*tro- BUO8 10 l m Mirearette .! 99-0&2 Beruenamne. 3.Mro.... _ . . . 8270 1 50 p-Nrtroenitane . . ~ . , 100-01-6 Berner strwne, 4.rstro . _ 8U0i W l Nitrocernene . ; 96-95 3 Beruene, ntro - . . . i 8090( 60 i 8270: ' o N trectierd j 88-75-5 Phened. 2.mtro .- . . - - . . . 8040' 10 5 8270- To p Nivccrmnot,___ 100 42 7 Phenot. 4-rvtro - 10 8040 I , 8270i 10 4-Neoqumoana 1.cssie ! $6-67-5 Quechne. 4-nrtro . Icade. _ _ _ aU01 10 N 4rroscx>ocutymtrwne $ 924-16-3 1 Butanarmne N4utyWrutrono . .__ 8270l 10 ANorosomethytarrine _) 55-18-5 Ethananne. N-ethy6N-!vtroso- 8270 l 10 NWeosocirnethytarane ! 62-7S-9 Methanarmne. N methy$.N-ruttoso- BUG; t0 Nettresodtphermarmne.
- 86-346 Bertronemne, N-ecceo N-onery- .
8270l 10 N.Netrc.soepropyurnene*, Dbr>propytnftrosa. 821-64
- 1.Prcoatiemme. N <vtror.owaye- i 8270i to frene , l N-Noroscreet'.ystrYamine - 10595-95-6 Ethanarnine. Nest *y.N.rvtroso- -.-....! 8U0! 10 NMrosomorpncane 59-8 % 2 Morprene,4-neoso .. t0 8270l N41resooscencrie ! 10475 4 Poenene,1.rutreso- . - - 8UDI 'O
-~ N.Necsowtonorw -
- 930.$$.2 Pynos,cne.1.rvtroso. _ 8270! to 5-Nftro o touomre _ 99658- Bentenarmne. 2.metrus.naro . . 8U0 to Paratroon- . .
J $6-3b 2 P9v esw.c.c sod, C.O 4ethp4H4-nstreoner'vq ester 8770 to
- s '
Pcy:rnonnsted tunnonytn- PC8s _ _ ' See Note 7 1,r.6pher% c.recro ourwsuve*~ . . ._ 8060 , 50 8250} 100 #ctrcNormeted ceenzo-o Posycrnerirmeo ocemoturens. PCOFs oca:rt PCCOs .'} See Note 8 Deen 20(t:.e)(1.4)Oours crJoro cerwatives , See Note 9 i Deereofuran chscro cerwegves 8280 1 8280 l 0 01 0 01 Pernmensorocernene
- 606-GG.6 , Barnene, pentacracro- 8270 10 Pentacneorcemene 78-4 1-7 ' Emene, pentacrearo . 8240 5
, 82701 10 PentacrJororvtrocernene . 82 68-.8 ' Beruene, pentaenctoritro- - 8270l 10 Pentacrwcreonenot - J 87-86 6 Phenot, comacrooro ._ 8040 ; 5 ! 8270 l 60 P .necenn.... 82 44 2 . Acewn.oe. N# cnemw.yo ! eUOi 'o Pnenentrvene . 85-01-8 ' ' Phenantrvene -._. _ - - . , 81001 200 , 8270l 10 Phenc4 . 106-95-2 Phenoi . , 8040 ! 1 i ' l 8270i 'O p Pherty4eneo.amne 106-50.3 1.4-Berueneoanne . . . 82701 10 Phorare - 296- 02 2 Pnc gwirvoic acA O.0 oesnyt S Getnyttrwolme:.ty) i 81401 2 seger 1 8270 6 10
- A6
i --- m. .... . - .... . . . . - .. . &' l Comrmn name 8 CAC % 8 CAe,a,v m at swis we mes %.* 9 " 5 d ' M i 1 .~ I mew q w u* ' l - oQt .8 ..,... .. . , , . 1 ^' 2.Pechne . ... _ 10M4-4 Pymbne,2.metryk. . . S 40 'l 8770 ifi *ronomios. . _ . - 13964 64 6 Berwruos. 3.64chetvo.H1.1cmef92 grosyy>.- _ , ~ 8270 to % /. Epart e.pende . - _: 107 12 0 Nm .a ... _ . ~ .. ; 0016 ' tC AW., 4 4 Prone. - . . - . . 129 00-0 Prone . - - - -... b00 X4 M0 to Pyaddie . - 410 46 1 Pridne . ~ . - - . 4240, p se % ._.. _ _. _.._ e44s.7 1.34.nroorme. s<r.roow .._ _. _ . ._ _ -. m0 10 Seemum - -. htaa $eierwum . _ . . .. _ 6610 l 7M 7740! 20 7741 ?) $we' . _ Ucman Shor <... .,m_. .. 6010 70 7760 100 Shoc 2A 5.TP . .. . 9M21 Procenmc sc.1242.4.5 Increarophenor+ . _ . 8150 2 Styrone _~ .m.l , 100.A2 6 Saruwne, ethene . , . . . . .. W20 1 -Q40 $ S#ade .... _ 16496-26 4 Suthoe -. . . ~ . ..... .- .q 9030 1 10 000 e 4 6.T. 2 4.5.Tncheoruorenomcesc eod 9N65 Accec acad. (2.4 6.tncrisorophenory6 a 8150 2 21,7 6.TC00. 2.3.7.8-Tetractwormtsret>p. 1%8014 Ceonrolg.e)(1.4)dsomet L3,7.54evectuoro. .: z-.' 4290 0 001 $onin 1.2,4 5.Tstrech 7-.s . 95 44 3 Serwone.1.2.4.6.tevechgro. _ _ ._ 8 770 10 h 1.1.1.2.Tettecmoroe _ . 630 2C.4 Ethane. 1.1.1.2 109acrooro. _ ~ _. . 6010 $ l 8240 $ 1.1.2 2.TotrecNoroete _ 75 34 6 Etene.1.1,2.2.tevectdoro.. - . .- 8010 D6 8240 1 $ Tetrac9oroet.$ene; Portreoroetyene; 127 16 4 Ethene, totrecNoro... . _ -. .. 60t0 : 0$ ' Terechooroetnene 8240 6 2.3.4.6.Tevecrearochenot $4 9).2 Ph*NW. 2.3.4.6.ietreet*vo. . .. . . . . . . 8270 10 Tevnetnyt etNoorophoephete. $#otepp 3684-24 6 TNooohotohonc mod (((HChePt$)l 01, tetreepy asier $270 10 ! The* A . _ .. . - .. (Totan Thenum - . . . ... _ .. - - - ._ 6010 400 7640 1.000 7641 10 Tin. _ - _ _ . ._ (TcAa0 T1n _ . . . _ . . . . 7870 6-(Kio To4ene .. ~.. _m.. 104 66 0 99tuene, methyt. - _ . . . _ . 6020 2 6240 5 ~~ o.To6mne .- . 9543 a 8ersonarrene 2 metnyt . . .. . ~ . - . . ~ ~ 6270 10 1 Teachone - -.~. .. 9001 50 2 Tomachene . . m . _ .~. 8080 2 l 4250 10 ..' u 4.Tnen m ennen. ._ sehrer.. u4.incNo, _ _ __ __. _... ..i a270 i0 1.1.1.Tnctuo oesiew Wetvennrtworm._q71 u055-4 42.i 1.1.2.TncNoroethane - _ _..- 79 00.b Ethene.1.1.1.tncteoro. Etrone,1.L2.tncNoro. _ _._-__q 8240 0010 S 02 M4 $ i TncNorcemytenet TncNoroethane. _, TS.01 4 E Pierie. etcNoro. , toto 1 B240 $ TncNorohuorornsehene 75664 h tncreoro%ro.. - , 8010 10 8240 5 v 24 5.TncNarochanot . ._ 96 96 4 Phoned, 2,4.5.Victdoro. _ m.m .__q 6270 10 2.4 6.TncNoropnenot _ _ 04.Os.2 PhariW. 2A.6.Increaro. - todo .5 8270 10 1.2.3.TncNorotropane . 96 16-4 Propane.1.2.3 9icNoro. ._ . 8010 10 8240 $ i O.0.0.Tnethyt 0hreonorotheosto 126 e41 Phonohoroeuoc ead. O.C.Jyistnyt ester _ 6270 to sym.Trvuorocoruene. . 96354 Beneene.1.3.5 tnrvro.- . . . 6270 10 veneeun- . (Toten venedwi . 6010 60 fato 2.000 e 7911 40 4-A.7 ,r.,w ~ ~ .en-, _,,.c.9.-4 y_ .y ,w%w_-mer.~,. ..,%. . w w-r . L e i 4, !
- u. -
y,, c - esmo. cAs nN . ci m iem yi,w.. . .e.ns.o. s,og WY er.etate wycrom . .~. ...-....) 106 05-4 Acipec was, orienyt esist . . . 8240. _ . . 75-0i 4 t ewa amoro. _ . 6010 ; IL240 10 A l9ene (10te4 .. -- 1330-20 7 Benrene.chmete. . 807J $ 6740 5 3% . - (Total tinc . 6010 70 , 1 FMo , so
- The re$astory remeremente perten ervy to N bet of outsetances. M figPd hand co4Jmre (Metodo ed POL) We yven tur mformoscmel parpoise erw see seeo sootnoese 6 and 4.
e Comr%t rames are anose anosey used h govemmerit repAabors apen640 P***mana, eng corsynerce; emme east 6er meriy chemrse. , a Chemcal Aletects Ser.t.* repoty rueer %%ere "totel" is entered, ed near=a h tio yound erster mi conten tue seement are trusomi
- CAS nien namee are toes used a the $m CumiAaeve indes. ,
a $ggesies Memorse refer to wweiast procedure tienters used h EPA Repcyt SW-444 " feet hae vede for Eveksong 50ed Vteste*, twd l editen. Noverft or 1994 ArWyeoel geqeen can lpe IqNnd m $W.444 end M Oooumonteleon on Die el N egency. CAUTION: Ths metodo heted we ! resr=nentam SW 444 erocoowse end eney not enesys to N nuet sunsees merostel tr moroservig en ename uruer Fie reeAMne ;
- f**cscesr s Ttason LJmste (POLel tre the etpe'est concustsysears at wiefyies m grourse imeters Fet can tse rahatspy deterwened gemeen
$Med hr'*f* c4'on and eCcuracy D/ Fue Odoeted fhethoos under etWtrie natuurel(ry opersteng conGeort 'he MXJ ested are generney stAtte to cre p.rt.it hges, CAUTION The POL wws a many eswa are t>end oesy on a general essmate kr e e metros erst ce en a ootern.neton for e.ovosai compounce. POLE a+ rei a pe 1 of the reguseuort ' Forventonneted hepr4**re (CAS RN 1336+. h3); the ces contare congener rtemca's. mefuchng constituents of aroctor.1016 (CAS PN t?fr4*11+ll. ArocW,'221 {&AS AN 11104 29 71. Atoc80r.tr3 ( $ AN 11141-$6-51. Aroto 1242 (CAS RN Wep-219t Atoco.tgas (Ca5 RN 1?673494). Aroctor.1264 (CAS RN 11097 69-1), and Aroctor.1260 (CA5 RN 11096 42 6). The POL %.two es en everage we'ue for PC8 *YS category cor'tama not chemcas. mcegbng tetroch6orootentopdcars (see ereo 21.7 6.TCD01. pen'act.iorootenro edews > c4 henecespoo$ ento poca he POL anowe. e en everage ve6ue for PCDD congenert e TNs category coritaine congener chener.ae. encewjvig tetracr*roat>enrotwane, pontechaotoo.tenroturens. and besecnioroetenrofure's The POL shown is an everage vene for PCOF congenert *WD . n b 4 l A8 I I l - - . , . . , , , -. - - - , - . , . . . . - , , , , . , . , .----,--.-.-~,,,-.--rnn.c,-...v.-- -.-.w_.,,.~,,.-v. . I i i i f t i ? APPENDIX B : EPA TOXICITY CHARACTERISTIC CONCENTRATIONS a r ? 6 + Me * *44 e t ? t f I i 't k i ( , , . , _ . . . . . , ....44,..,y-.m,%,_,, , ,y,,,,.,~,---.._,,. _ , . . . . . , ._ , , _ _ , . . . , . . . . . . . _ _ _ , _ _ , . . _ . . . , . . . . . _ . . . , . . _ . . . . , . . . . . , _ _ , _ , _ . _ . _ - _ - _ _ _ . APPENDIX B EPA TOXICITY tdARACTERISTIC CONCENTRATIONS (Ref. 40 CFR 161.24) EPA Regulatory HW . Level No. __ Contaminant (mo/L) D004 Arsenic ..................... 5.0 0005 Barium ...................... 100.0 0018 Benzene ..................... 0.5 0006 Cadmium ..................... 1.0 0019 Carbon tetrachloride ........ 0.5 0020 Chlordane ................... 0.03 0021 Chlorobenzene ............... 100.0 0022 Chloroform .................. 6.0 0007 Chromium ..... .............. S.O D023 o Cresol .................... 200.0 0024 m Cresol .................... 200.0 0025 p Cresci .................... 200.0 0026 Cresol ...................... 200.0 0016 2,4 D ....................... 10.0 0027 1,4 Dichlorobenzene ......... 7.5 D028 1,2 Dichloroethare .......... 0.5 0029 1.1.Dichloroethylene ........ 0.7 0030 2.4.Dinitrotoluene ......-... 0.13 0012 Endrin ...................... 0.02 0031 Heptachlor (and hydroxide) .. 0.008 0032
- Hexachlorobenzene ........... 0.13
> - . 0033 Hexachlorobutadiene ......... 0.5 0034 Hexachloroethane ............. 3.0 .< 0006 Lead ........................ 5.0 0013 Lindane ..................... 0.4 0009 Mercury ..................... 0.2 0014 Methoxychlor ................ 10.0 0035 Methyl ethyl ketone ......... 200.0 0036 Nitrobenzene .............. 2.0 0037 Pentachlorophenol .......... 100.0 0038 Pyridine .................... 5.0 0010 Selenium .................... 1. D011 Stiver ...................... 5.0 D039 Tetrachloroethylene ......... 0.7 0015 Texaphene ................... 0.5 , 0040 Trichloroethylene ........... 0.5 0041 2,4,5 Trichlorophenol ....... 400.0 0042 2,4,6-Trichlorophenol ....... 2.0 . 0017 2,4,5 TP (silvex) ........... 1.0 0043 Vinyl chloride .............. 0.2 B1 wm_- - --+n _ - -a - 2 4-- A e"'O. ", "'* " p .a.ma , 1- -.- ---- 2 ,_ ,_a-l l , i APPENDIX C BACKGROUND SOIL SAMPLE DATA =.,,s d o - o i ! . APPENDIX C BACKGROUND SOIL SAMPLE DATA * (eg/kg) ' " ~" ' l M t P- 1 645 Mi t 64 s (l. __ l '~J _.I jac arc FA.eLQD 4mc N TLOC01AM 14100 sa coc I f .709 As urc 13 1 _fm arc 43 N arc 0 8i .!co_ art Os _cnarc_ 19 7 j 5 03 ~j jof_u2C 56 1 sy_urc _ 294 09 MTLDSO2Akt t476b 2 00! ~ 19 9 29 0 Tf~jf 04 1S e 1 4 47 s 39 1 22% 00 MTtosom 15090 1.!pj 21 1 _ 35 _ , 0][_. 04 19.9 5 *E 35 9 278 00 MTLOSO4AL4 13900 1 701 15 3 41 0 e: Oa 18 1 5 to 35 7 262 00 IULO605Ai.I 1U06 1 no 17 4._ 43 0 si O4 19 4- 4 99 6 34 7 215 00 i i ! _ -- ._I _ _. N,q;. 5 Sj 5 $ 5[_j 5 _ , 5 _. 5 5 _ 5 _ Sksn,j j - 3?_ , _ l 40 24 9g TAand. Dey. - 14480 450 435 0 130i 2f 17 3 _301 5 91F _ Cy5! f{l 0011 0 19 C.133 0 304 5 8 986 27 0191
- 7 M MPLEj e e.tt Otro .
Isi_ arc ) ra Rr0 ~ 'X_OJf C , M1 Gr0 j . IlGrc . _ _ Y_CU C IJ4 OCFC (J4 cOC _. ._ Mit0901AM 198 0 05G $4 0 06734 72! 1 00 tJ _ 77.4 l 217 0 26') - MILO502AM 157 0059 50 7 0270 6OLI 1 OC'9., 67 1 _l 891 0 2Ed MTLOSO3AM 182 0059 54 4 0 190 5 Bi t O vs t1 61 2 ' 207 0 2611 [ Mil 08024U 1}} l0 54 9 [ 0_392 9 6 Of _.. i Oyd[ se a 2 07j 0 31O t ] M TLC 805AM 239 iM 56 4 0 35jB 7 ti _ { 10 % Ti 5 213 1 0 2911_ _ ;B 57 5 021j9_ 5 di 4 0 9M& 76 3 207 02fh3 __ M. . $$. ." O$ $:5{ __. 0 9qt) 74 4 214 02d M 52 ? _. 0731 53' 1000 71 ? 20A 0 29,h1
- D 55 6 0 18'O 5 2r j Qt11 , 69 3.__, 205 B St 9 0. U 45! ! 1.00J 69 m 196 t 0 27f O 3411
~ 5' 3 . 114] to t 10 ] to 1 08 td , { %. . . ., L,, 193 so 00s. 5433 _ 0 37 5 so! 09s 70 ra ! 205 se 0 2c. aand o . 31.453 17. 30cf 23o3! O 17e o e3e , o Os41 4 753 1 744 0 026
- a. Background samples were surface-soil composites collected on the AMIL site. The composites were collected above the bunker, 25 ft south of the fence line surrounding the residence of the base comander.
The soil is a dark loamy sand with a considerable amount of organic material. Samples were collected at 10-ft intervals along a 50-ft transect. .}}