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Home My WebLink About881741.tiff was„ t': n w�>r ti:.sr,,7Kli,,s • tw v'+' r r , Health Impacts.Assessment 3 Table ,12.2.1-1 . AVERAGE,ANNUAL EFFECTIVE DOSE EQUIVALENT ;IN THE .U.S. POPULATION-.: • Avenge Annual Effective Dose . Source -,"Equivalent irr mrem - Natural: Radon/radon progeny 200 cosmic, terrestrial; and internal 100 Occupational - 0,9 Nuclear fuel cycle 0:05 Consumer products 5-13 Miscellaneous environmental sources ' 0:06 Medical: Diagnostic X,rays' 39 Nuclear;:medicine 14 Total Approximately 360 .. . Source: ,NCRP 1987. ,._.. SSCAP12A228883. DEIS Volume IV Appendix 12 • Health Impacts Assessment 4 of cancer induction by low dose-radiation because the degree of risk is so low that it cannot be observed directly and..there is great uncer- tainty as to the dose-response"function most appropriate for extrapolat- ing in the low-dose region." (SEIR U) Alsa, the adverse effects. iden- tified from radiation exposure have been observed in natural (background only) environments and can be linked to other causes. The committee also agreed that any somatic effect that may ensue-from.-the-natural-and- man-made background dose equivalent, 360 mrem/yr, would be masked by other factors; In addition, the committee agreed that no low level radiation-induced genetic affects have been observed in humans; and that it is unlikely that such genetic effects willbe distinguished from tile spontaneous genetic disorders in man. To assess the potential genetic risks, estimates can only be made through extrapolation from animal experiment-data. Hence,. the r lation- ships between health effect (risk) and low dose radiation exposure are derived from a chain of estimates of varying uncertainty and varying: applicability. The usual practice in making these 'estimates is to be conservative to protect the individual: C. The releases of radiation/radioactive materials from, SSG, activities are excepted to be quite low, and the expected radiation dose to any indi- vidual would be a small fraction (1/1,000th) of natural background.. , The effects considered are long-delayed (latent) somatic;,and->,geneiic effects. Knowledge:of these delayed effects of low doses of.;radiation is necessarily indirect, because their incidence is very low compared to the much higher background incidence of similar effects from other competing causes. - 12.2.1.2 fiarardgus/Toxic uteri air tf till The amounts of HTtis that may be associated with SSC.construction are, expected to be small and typical of any construction project of this scope that involves tunneling. There are no unusual conditions at any of the sites that would increase hazards in a major way, and there are no unique features of the SSC design that affect construction hazards. Similarly, the HTHs associated with operation of the SSC are typical of those at any light industry or research laboratory,. and standard proce- dures exist for dealing with them. It is important to note that the SSC isonly-at the conceptual design stage, ?nd details of some possible HTH source-generating terms do not exist. SSCAP12A228884' DEIS Volume IV Append'Vx• 12'' Health Impacts Assessment 5 12.2.1.3 Level of Resolution A. Temporal The impact analysis and evaluation has focused on impacts during con- struction and operations. 8. Zratjal The boundaries for assessment of health hazards vary depending on the potential source and the site-specific environmental parameters. The. extent of the potential impact on the environment varies only slightly from site to site. For radiological impacts, the assessment boundaries are: o Direct radiation - controlled area boundaries o Airborne radioactivity - out to 25 mi (40 km) o lerrestrial and aquatic radioactivity - restricted area boun- daries (50m) o ' Transportation - transportation route to final destination For HTMs, the assessment boundary is 1 mi beyond the SSC facilities. 12.2.1.4 Definition of Impacts Regulatory exposure limits and standards are established to protect the health and well of.individuals. To comply with the intent of the regulatory 'limits, an operating facility may;choose_ to set operational exposure. guidelines that are a fraction of the regulatory limits. In this way, appropriate measures can be taken to limit exposures well before the 'regulatory exposure limits are exceeded. For the purpose of evaluating the proposed SSC sites, regulatory exposure limits are used as points of reference of significant impact. A radiological impact is considered if any annual dose equivalent is in excess of the standards or guidelines (based on health effects) found in: o 40 CFR 61 Subpart H o 40 CFR 141 Draft o DOE Order5480.18 o Applicable state or local standards. The limit set by DOE for the exposure to individuals of the public to.,, radiation as a consequence of routine DOE'activities'and actions is an annual effective dose equivalent equal to 100 mrem (DOE Order 5400.3 Draft). Out of the 100 mrem accumulated per year, no more than 25 mrem -SSCAP12A228885 DEIS Volume IV Appendix 12 . . Health Impacts Assessment 6 may come from airborne radioactivity (air pathwayWand no-more than -- 4 mrem may come from radioactivity in..public drinking water (aquatic pathways). For the general public, the total dose equivalent from.back ground and man-made radiation including medical procedures is estimated to be approximately' 360 mrem per'=year (see Volume T, Chapter 4', Section 4.6.1.3). For comparison, the maximum annual limit-for radiation to` —workers is 5,000 mrem (DOE order 5480.11- Draft). With the exception of federal drinking water standards and general fed eral, states and` local air quality-standards that regulate a very`few . ' toxic" substances 'health-based' standards'which limit exposure • of the • . '.- ' general"publis 'to 'specific` Fills' do'`not exist. •''The established-exposure limits, such as the OSHA Permissible Exposure Limits (Pttsy and the American .Conference of Governmental Industrial Hygienists „(ACGIH)_ Threshold Limit Values (TLVs);vt(ave"'6ei developed strictly 'forioccu- pational settings and are not directly applicable to the general public. Therefore, no yardstick is-avaffable to apply to source tends'for public exposure as there is for worker exposures. • An alternate method was used to' assess public exposures. , If the pro- jected'public exposure-' vaiue begafr"tto'=approactr the occupational limit (for the purposes of this assessment an arbitrary crfterion'of`t/30th of the PEL or TLV was used), then the health impact was, evaluated. No attempt"war 'made"to'^apply. a,antitative criterta to a projected` source term for public exposure. 12.2.2 Referenced Data Used in Assessments . Data used in this assessment include source terms generated in Appendix 10; ,oberational, data from high-energy'-particle accelerators including. , Fermilab; CERt1 and'SLAC; the'SSC'Conceptnal Design?•Report as'modified by the >tnvitation' for Stte"Proposals and subsequent' coninnttee reports; and site-specificmdata from Appendix-5. ' 12.2.3 `Assessment`iethodologies The purpose of this assessmentItis ,to examine the potentiaihealthhealth pacts of the SSC on the.general public and workers. Operational guide- lines wereused to'carry out this-'assessmeat ' ' A Safety Analysis Report (SAR) for construction of the SSC will be pre- ' pared once DOE has selected the final site for the SSC.., The SAR will address, in detail, the expected hazards associated`with'construction. In this manner, all health hazards to workers and 'the _publi c'wtich may result from SSC construction would be fully evalnated'prior'to-the start of construction. Hazards which may be associated with he,i'astatlatton an• d operations of the SSC`would'be addressed‘by,theroperatii+q'contractor'tn,z separate SAR` that would-b'e`'tssued'prfor-te the start'of'the fnstal7atlorr work.;. .. SSCAp12A228886 DEIS Volume IV Appendix lr Health Impacts Assessment 7 • The following assessment methodologies were used and are consistent with assumptions and recommendations'of_.:the EPA, the rational Council on Radiation Protection and Measurements (NCR?), the International Commis- sion on Radiological Protection (ICRP), the Occupational Safety & Health Administr_ation__(OSHA),.._ant. the National Institute for Occupattonat - Safety'& Health,i iOSH)_ 12.2.3.1 Radiological Three radiation exposure pathways are addressed in the assessments: o Direct radiation o Air pathway o - Terrestrial and aquatic pathways. • Also, the transportation of radioactive materials- which include expo- sures from all three pathways is addressed. The flow chart for this assessment is presented in Figure 12.2.3-1. A. Direct Radiagjg0 The dose equivalent contribution from' externaT radtation. is based on dose equivalent curves generated by the COG Radiological Task Force (SSC-SR-1026) which are presented•in. Appendtx-1a.. ; B. Air Pathway An estimation of the health impacts of radioactive material released to ,the atmospheric: environment requires,,the-use.-of nnmerousmode}s and cal- culations which, for this assessment, consisted of the computer codes described below. The flow chart in Figure 12.2..3-2 illustrates and sum • - marizes the flow of data in tbfs assessaent:-. 1. Clean Air Act Codes (CAAC) CAAC implement the radiological- assessment methodology used for the preparation of the Environmental Protection Agency's 1984 Background Information Documents on Radionuclides. The codes include the following auxiliary routines,andidata library: o AIRDOS-EPA: Estimation ot,•radiation doses caused by airborne radionuclides around nuclear facilities. o DARTAB: Code system for combining airborne radionuclide environmental exposure data with dosimetric and health effects data. o PREPAR: A preprocessor to create. AIRDOS-EPA input data sets. o PREDA: A preprocessor to create DARTAB-input data sets. SSCAP12A228887 DEIS Volume IV Appendix 12 Health Impacts Assessment 8 Figure 12.2.3-1 FLOM CHART FOR RADIOLOGICAL IMPACTS SOURCE TERMS SITE PARAMETERS APP- 10 APP.5 i N DIRECT RADIATION HADRON MUON SKYSHINE ' AIRBORNE RADIOACTMTY AIR ACTIVATION PRODUCTS RADON-RADON PROGENCY SOIL/WATER RADIOACTMTY TRANSPORTATION OF RADIOACTIVE MATERIALS EXPOSURE PATHWAYS DIRECT - AIR TERRESTRIAL/AOUATIC HEALTIt IMPACTS PUBLIC' OCCUPATIONAL • SSCAPI2AZ26888 - 0EIS Volume IV Appera lc 12 r _ '.1`4J'{ Health Impacts Assessment 9 E.1gco 12.2.3-2 SUMMARY`OF ccnputg'CODES USED-MID DATA FLOW IN THE CAAC ASSESSMEaQ [ [ C 6 .7. +moo 1. t r r I a D700{IFwYD. . dWAE TAIE�IRpNs . - wwumrwcra, ooeEeEEs, Yenuac, MALI ncrono DATA OATA L C i oe 1 DATArA SSCAP12A226689 DEIS Volume IV Appendix 12 Health Impacts Assessment 10 o RADRISK.BCD: A file-of-dose and risk factor blocks for 502 radionuclides written with RADRISK for use with DARTAB. The data used for 1984 CAA assessment includes 50- and 70-year • • internal dose factors. o RADFMT: Converts RADRISK.BCD to binary. The CAAC is a code system for the implementation of an atmospheric dis- persion assessment required by the`.Clean Air Act. Thls code system implements the assessment methodology-used for the preparation of the EPA 1984 background information documents on radionuclides. The CAAC consists of six auxiliary routines and,data library. Atmospheric dis- persion and deposition are calculated by-AIRDOS-EPA. , Dose--and risk assessment tables are calculated':by DARTAB from the binary output file generated by the AIRDOS-EPA and: a file of dose..and risk factor: calcu- lated-by RADRISK. Preprocessors (PREPAR and' PREDA) and DARTA3 access databases of element and nuclide-dependent data to simplify the execu- tion of the principal prcyrams.. The AIRDOS-EPA computer code used by the U.S.-EPA as part of the method- ' ology to evaluate health risks to humans from atmospheric radionuclide releases is a modified version of AIRDOS-II developed by Robert E. Moore at Oak Ridge National Laboratory. A modified Gaussian plume equation is used to estimate both horizontal_and:._verticle dispersion of radio- nuclides released from stacks or area sources. Both point sources and uniform area sources of atmospheric releases of radionuclides can be evaluated. .The---AIRDOS-EPA estimates. the concentrations of various radionuclides in air, rates of deposition on ground surfaces, ground surface concentrations • intake rate by human via food ingestion_and air inhalation, and radiation-doses received by humans Doses to humans are estimated for total body •and 'various organs, through five exposure pathways. These exposure pathways-include: o Immersion in air containing radionuclides o Direct exposure from radionuclides deposited on ground surface o Immersion in water containingradionuclides o Inhalation of radionuclides .. : o Ingestion of food produced in,the area. The radiation dose to individuals and the general public from all these pathways can be calculated with reasonable confidence. Estimates can be made of the amounts of radioactive gaseous effluent that may be released from SSC operations; however, the fractions reaching humans via various environmental pathways are based on a series of conservative assumptions. The DARTAB code predicts the health-impact-from radioactive airborne effluents by combining environmental exposure data, which is derived from AIRDOS-EPA, with a dosimetric and health effects database thatwas developed by using the RADRISK computer code. SSCAP12A2288810 , DEIS Volume IV Appendix 12 Health .impacts Assessment 11 2. Assumption; Because of-the spatial dependence `of atmospheric dispersion, the expo- sures to both airborne radionuclides 'and ground-plane depositions of radionuclides (as well as the intake rate of these radionuclides via ingestion of food and inhalation) are estimated for specified areas of interest. In this assessment, the areas of interest include the exit shafts of the tunnel at the service facilities and the exit shaft at the interaction region: An area of 5 -acres is assumed for each site. A detailed- description of_these facilities-maybe found in the CDR. Radiological exposure for"anF•indtvidual, within the- SSC boundary 24 hours per day and 365 days per year.—was-estimated, as'weil ' as for an individual 1 mi (1,6 kmj, 5 mi (8 km), 10 mi (lfi;km), .and 25 ml (40 km) from the center•of'the site: Popv`Yation :radiol,ogical exposure was also estimated for the same.tonditions. -.The-population density in`Illinois was assumed to be 719-people/km2 (as suburban,area): For..the other pro- posed sites,:Arizona, Colorado, Michigan, North Carolina, Tennessee, and Texas, the population density was`,assumed.to be 6.tpeople/kmz (as rural area). The population around a€Suburban; and rural site is shown in Figure 12.2.3-3 and Figure 12.2.3-4,. respectively. The radionuclides of significant quantity released.'from exhaust fans;of the tunnel and interaction region include H-3, Be-7, C-il, N-13, 0-15, C1-39, Ar-41,•-and-Rn-222-and -its:decay products_....Pb-214.and_81-214_.are the only .two Rn-222 decay ,products released:in significant quantity and are addressed. Most•of these-radionuclides/are in'gaseous.,form, except • Be-7, Pb-214, and B1-214-which :are particulates suspended in air. The release rate of-each 'radionuclide clay be.found- in. Appendix 10. In instances where-radionuclides'•are members`.of decay chains, -the..transport codes. have to include.the..ingrowth`oe the•"daughters. and identify them in the input. stream. Release oftritium is treated as a special,'case . - since tritium'.'(H=3) is-:an isotope-of'hydrogen and it may exchange with hydrogen atoms`,in water molecules:—.— Health risks to people from radiation exposure are determined not only by the release rate'of radionuclides but.-also-by.the environmental con- centrations and intake' rate by ingestion and inhalation: Meteorological . data, including annual average frequencies of wj.n( direction, wind speed, atmospheric. stability category,..-annual•ytainfall rate, height of atmospheric mixing layer, and annual average temperature,.were employed as input data to estimate the annual- average concentration of each radionuclide at ground level as a function of direction, and distance from the release point.. All of the meteorological data were obtained from the weather station in themajor, metropolitan area nearest. the pro- - posed SSC sites. The wind data may, be found' in 5.1.3. The remaining meteorological data used in this- assessment are listed in Table 12.2.3-1. The physical stack height for the exhaust fan was assumed to be 15 ft above the ground level and the diameter of the vent was assumed to be 2 ft. The plume is assumed to not rise above the stack as a result of the momentum of the gas. SSCAP12A2288811 DEIS Volume IV Appendix 12 Health Impacts Assessment Figure 12.2.3-3 Su6uRBAZCPOPULAI.101i':DISIRISUIIDN Fes;,,ffilDIOLOGICAL ASSESSId£IFIS, 19616 :I ,:.;19616• 0 271146 �I , 27iD6 ppi�pp_ .W4V.� 662.� 8628 27106 - ,- 360 .19616 79816 21106 360 27406 • . 8628 19616 Y1106 8628 21106iii;0 a.360, 19846 r 86x6 360I3G0 8626' 27106 27106 27106 27106. • 27106 ; 27106 49816 19816' - 198ss Rotes: 1. Populati dtstrnl on utton vat'stieeted for 4, 5:'10. and 25 as True the release-point. Mo'Yestdencd`Tr aliened in the Tee-sliaple area. .2..'. Vlat'Ts nar pea led, . .. SSCAPI2A2268812 DEIS Volume IV Appendix 12 • Health Impacts Assessment 13 Figure 12.2.3-4 RURAL POPULATION DISTRIBUTI0N • FOR RADIOLOGICAL ASSESSMENTS 1584 1584 • 1584 1584 226 226 226 226 158.4 , 72 72 1584 226 72 72 226 . 72 3 3 3 3 72 1584 7i6 3 3 1584 72._ 3 3 72 226 72 3 3 72 226 1584 226 3 3 1584 72 3 3 3 3 72 226 72 72 226 1584 72 72 1584 226 226 226 226 1584 . 1584 1584 1584 Notes. 2.. Population distribution um estimated for 5. 10, and 25 ci fron the release point.- No nsldrm is allow d in the ta•riuph`area. 2. Plat is not scaled. SSCAPI2A2268813 DEIS Volume IV. Appendix. 12 Health Impacts Assessment 14 Particulates and reactive or soTubl-v'gases deposit on ground or water surfaces through dry deposition.;.aad scavenging. -Exposure may result from immersion in water that:-contains"trace arouats'of radionuclides. A fraction of the radionuclides'mar'emter-the food chain through vegeta- tion, milk, and beef, and be ingested by people. The agricultural use of land around the proposed sites was estimated based on the observa- tions during the site visit (RTK 1988): The default values used in the assessment are listed in Table 12.2.3-2. - • These estimates of exposure and intake are..multiplied by information on organ dose committment values..per"unit exposure"or_._intake to estimate the health impact. The animal organ dose rates are'used to estimate the annual excess risk as a result of radiation_exposure using risk factors provided by the U.S../EPA. Th6' 'sk" factors are-trasecLon an`average of _ absolute and relative risks/tam tat BEIR 11 report\,..(NAS 1,972). An actuarial life table -composed of age.-..specific mortalityNr,ates for all causes of death: in a gsien population was emptoyed`tn developing \these factors. Health. effect factori worettvaluated as`the numbeer"of excess deaths within' a 'cohort of IO0,000 Personsa11 simultaneously live-born and all experiencing a•nnit exposure:* aniI atakeVrate throughout each person's lifetime::-. The EXTRACTcode extracts the-dose 'factors for'ingesti•on and inhalation dose from the DARTAB"-'RADRTSKsdafabase. This pe gr,.am extracts dose fac- tors for ail nuclides inihe.•TNPLT file, which.,tonsisis._of-elameat-.aad radionuclide-data:" PREPAR is a preprocessor to-create ATRDOS-EP input data 9et5 ' r. PREDA is a preprocessor to creaie..,DARTAB lapt edata. sett: RADRISK.BCD is a file contataing"dose risk cotversion•,factors for 502 radionuclides for.lhe\use,.of DARTAB. %The data\used' indades dose risk factors for both. 50-year;and-:7O-Year_lntern,aL- $apositionc"\, The RADRISK code is used to generate a. data base of dosimetric and-health effects for those radionuclides of interest "71',ince'C -39is'not. in tliis list, data from Br-84 wereitsed'`to estimate,dosimeir*c'and healtr effects of C1-39. Their chemical,"Nradiological, and physical 'properties are very similar. - 3. Radon and Its Program, Recent attention to radon in homes has been prompted by the correlation of radiological exposure to adverse health effects, which indicates that a significant fraction of lung cancer deaths, an estimated 5,000 to 20,000 per year in the U.S., may be caused by chronic exposure to ele- vated concentrations of radon and-radoe .progeny-.., .this-bea.3tb act is synergistic 'Nltt smoking and exposure to ,other..ai.rborne respiratory irritants. On the basis of current data, the EPA has doieioped-recom- mended action levels for reducing the concentration of radon measured in homes. The Mine Safety and Health Administration of the Department of SSCAP12A2288814 ` DEIS Volume IV Appendix 12 Health Impacts Assessment 15 . ... , : N .- .3. Y 1" E .... w Ai b a YY 8 N 4 + $ 3 .,. V) 2 0 a c. F- 5 0 z S 6 3 J O W gn c. ry ti N a yy r L L. C4. Y 9 Z R_ vT y 7. ^ OyyL OLy[ i 9 t. P . 1 pp ` pp < $ C V C - Y M 2 P K `4 ₹ SG YC . N SSCAP22A2288815- DEIS Volume IV Agpead#xk12, 418429 0 - 88 - tO (BOOK 71 Health Impacts Assessment 16 ' Table 12.2.3-2 ' CAAC DEFAULT VALUES DEFAULT YALUES of PREPARED VARIABLES USED:IN ENVIRONMENTAL RADIOLOGICAL ASSESSMENT DEFAULT _ . VARIABLE REFERENCE 14400'0. ' ACON n.r. ... 0.5 AMAD Moore et al. (1979) 8035.28 . BRTIRT USEPA (1978) 0.01 CUTOFF -. Nelson (1982) 0.5 :' D01. Moore at al, (1979) 0.2 FlING -. Moore et al. (1979) 0.2 - F1INN. Moore et al. (1979) 1. F38EFM 1. F3MLKM comp. 1. F3VEGM Coup. ,FSUBG Noore et al.. (I979) 1. .FSUOL. Moore et a1. (1079) 0.4 FSUBP Moore et e1. (1979) 0.43 FSUBS MGora et al. 11979) 14400'0. GCON n.r. 1.0 GSFAC Nelson (1982) 0 IFLAG n.r. 1 IWEIN n.r. 0 KFLAIi n.n. 0.0029' - :' LAW . Miller and Hoffman (1982) 20'0 - LIST n.r. .200: MSU88. Moore et al.- (1979) - 'TYPO'- NAMNUC n.r. 'TOT.BODY' NAMORG Moore et a). (1979) •'R MAR' 'LUNGS' 'ENDOST' 'S WALL' 'LLI WALL' 'THYROID' 'LIVER' 'KIDNEYS' 'TESTES' - - 'OVARIES' -: - 0 NNIB n.r. NOL n.r. 1 NW NRL - . n.r NRTB n.r. NSTB NUB n.r. 1 NUOORG n.r. . . ,NLMST NUTB n.r. . NVTB n.r. AN n.r. 9* OPTION - - n.r. fele ORGLST n.r. 215. p - - Moore et al. (1979) 1. 0. CH .n.r. 15.6 - - :(SUBF' MOOre et-al.,(1979) 0.57' .RI Moore etal.-(1979) 0.2 - :R2 ''Madre et al. (1979) 1. - . RBEF Corp. SSCAP12A2288817 , • • DEIS Volume IV Appendix 12 Health Impacts Assessment 17 Table rz:2.3-2:(tont) CUt DEFAULT VAWES DEFAULT VARIABLE 0, '0 . . �• , • ROI; WI Moon at al.,-(1979) o, II P02,'RY2 Moore et al (1979) canp .. SC' Moore et al. (1979) O Y SE014 Moore ePeY' (2979) 765.24 7 - .. : Moore st al.'(1979) 0.00381._ - TAUBEF. - : Moor'eat al. (1979): 8.18. O. •TOCF I Moore et al. (1979) 0.0570..0. - TOCY Moore et al. (1979) 0.0728. TG Moore et al,„(1979) • 0.1090, 0.1455 - I.:: ::;730BB Moore•et al_ (1979) >20...; .., :.,TSUBEI , :MoorraYsl."(1909) 1440:` TSIBf2 ,-. Moore et al. (1979) , 2. .TSUBF. Moore et:at (1979) 2160. TYJBH2 Ibore at al': 419791 336. I5U8K3 - - Moore,,et al (1979) 736. TSUBM4 Mon et al (1979) 7A. . .; • :TSUp5. -. MOOreat at,-(1973') ,85. tIf . . . � Ruopt.C1980) 28. at BMW (1980), 176. ... ,W, tire et al: (1979) -eanp - VD Moore et .1, (1979) 400"0 VOCOEF n.r. camp VG Moore et al. (1979) 11. :YSUBN' : -. Moore et a3. (t979) 4:28 TS116V1 Moore et al. (1979) -0,726 YSUBV2.. : . - Moore'et al. (1979) carp Value 4. computed n.r. No reference • SSCAP12A2288818 DEIS Volume IV Appendix'.12, Health Impacts Assessment 18 Labor has also promulgated regulations ,regarding the testing of mines and the protection of underground miners against excessive occupational • exposure in both uranium and,:;nonuranium:mines These concerns and guidelines will be considered in the health hazards assessments for the following SSC activities. a. Construction Radon concentration and health hazard considerations in the construction of the SSC; facilities- and tunnel are' related-to the requirements applied to- the protection: of underground mining-.personnel. These are outlined in Title-20 CFR Parts 57.5-37 through 57.5-47 and relate to the measured radon flux: and working levels encountered in the occupational environ- ment of the mine (or tunnel). Health, hazard considerations will dictate ventilation rates-and thus venting to the atmosphere. b. 0oerati,Qns Estimates -of radon and radon progeny concentration in the underground structures. are derived in Appendix 10'• "Working levels are calculated for comparison to"occupational exposure standards (see Section - 12.3.1.2). However, working levels are only operative if the tunnel is occupied for maintenance. According:to the proposed SSC operating procedure;;' the tunnel will not be occupied for any reason except maintenance. Between maintenance periods, only very low ventilatiom rates may be established to control the -tunnel environment' temperature and humidity.,, The"quasi-stagnant air flow condition could allow the concentration: of radon and radon progeny to rise, but no adverse impacts would-occur,to' either the technical systems, operating personnel, or the environment. • The venting of a sector of the tunnel prior to maintenance will be. a point source release-over a short period of time of the radon content accumulated in the tunnel sector to be vented, and is assessed in Sec- tion 12.3.1.1.. C. Terrestrial and Aquatic Pathways According to the SSC Task Force Report on Environmental Radiation Shielding, an accidental loss of beam at any point along the collider ring can activate the soil adjacent to the tunnel, thereby generating radionuclides, including tritium and Na-22. These radionuclides could migrate to nearby water wells and other water supply facilities; The dimensions of the activated soil block and the'activities of Na-22 and tritium were presented in the Task Force Report (Jackson 1987)`. For each beam loss, the activities of tritium and Na-22 potentially avail- able to- migrate to a nearby water supply are presented in Table 12.2.3-3. The dimension of activated soil block is approximately 3 m x 4 m x 20m (SSC-SR-1026). SSCAP12A2288819 OEIS Volume IV Appendix2l2 - • Health ImpactsAssessment 19 • Table 12 2.3-3 - RADIONUCLIDESOURGE TERIISFOR r TERRESTRIAL AND AQUATIC PATHWAYS • H-3 Na-22 RKere^al• - Radioactive Half-Life 12.3 years _ 2.58 years Decay Constant - 1.78-x 10 9 S-I 8.45 x 10-9 S-1 Ca v $ (atoo/star) 0.075 'x0;020;• Jackson, 1987 Critical Organ Body tissue 7otal,body ICRP2' - E 0.010 MeV 1 B,MeY . ICRPZ Effective Half-Life 12 days 4l.aeys • ICRP2 Source term 0.0091 Ci 0.002a C.i ' SSC-SR-1026 *leachable fraction (20%) It is assumed that beam loss could,occur anywhere around :the collider : ' ring. To be conservative,,...the. acttvated--sofa—black-.can_beJocated at any position onahe:aranverse--p-}ane: 7That-ts;-regardless of the"4lrec-- - Oen and-pattern of local groundwater flow, it is assumed that concen trations. .oftthe two radionuclides in groundwater is within_a,__normal distaste of--"-r' on_ each side of the tunae] The region cf deposition of radionuclides is assumed 20 meters in length and one meter in radius outside the tunnel. With a tunnel diameter of 3 meter, the deposition volume was modeled as being rectangular, 4 meter high and 3 meter wide in cross section and of length 20 meter as shown in Figure 12.2.3-5. At the source, a "plug-flow" scenario was assumed. That is, radionuclides will be "picked up" by groundwater on one passing. Texas and Arizona were not included in this analysis because-inigration , - - of radionuclides into the groundwater. are considered not probable. Arizona has a dry surface and its local aquifer is below the tunnel depth (Hollett 1987). Texas his- some small perched alluvium aquifers in • streambeds intersecting the: tunnel at several spots, but its major aquifer is below tunnel depth (Flanigan-1987). CDG has determined the characteristics of the source (Jackson 1987). The computer model EXACT (van Genucten and Alves 1982), and analytical equations of well hydraulics for confined aquifer and an unconfined aquifer (Bouwer 1978) were used to compute the concentrations of Na-22 and H-3 in the-well water as functions of time through several decades. Input parameters for these models-.were the site data or estimates in cases when site data were unavailable. Figure 12.2.3-5 presents an illustration of the scenario of the activation of- soil/rock and trans- port of H-3 and Na-22. • SSCAP12A2288820 DEIS Volume IV Appendix 12 ., r+ t, ? c , ,k , as •v . ,;�q°,u �.�s,. 'tip+r rn^*"L ,�' .`� _ ."� Health Impacts Assessmert 20 Figure f2.Z.3t5 Generation sad Ithatlatton tram-Some 7.osc 1) LOSS OF BE'A'i01 • tl— (magnified view) loss of beam • A . 2) HADRONICCASGADE.ORMATi0DJ ,,� "It"WroN,... ,irx ea •la"7.„7w'�-c�,�, , ,..—�: . 1• z �Q7e�/•proton •�� #`"+✓ .w.,.xP,rxpY� 'u�" k.YM, Sk .T,ii6OT ' e4,4,-..• , :; s � , t,7".t."; v, 1# dronctaescade r'• - r•reN�rr•• r s w w.e...yan.n SSCAP12A2268821 DEIS Volume IV Appendix 12 Health Impacts Assessment 21 Figure 12.2.3-5 (Cont) Generation and Migration, frca Seas Loss. . 3)ACTIVATION ZONE Proton interacts with a nucleus <... '� N�► forming a hadronic cascade 3 m which•is absorbed in a mblock of soil/rock 3m x 4m x 20m. 4m 4)SOIL/ROCK ACTIVATION ,,,... t 27 22 1 p + AI - Na+ 3 P + 3 n " ,w t N ,., w,,,, 13 � °"tr✓p'Fn . »"'.�'"".^ff V n ,proton interacts with stable aluminum atom in soil/rock producing sodium-22. 5) LEACHING Tritium is also produced by activation.. w w' u rw. P: ,�t M�= N• 4 �wrr f N. ,tiv SOdwm 22atom produced at surface leaches (Ito water surrounding rock/soil. Sodium-22 is assumed to be 20%leachable. Tritium is 100%leachable. SSCAP12A2268822 DEIS Volume IV Appendix 12 Health Impacts Assessment 22 Figure 12.2.3-5 (Cont) Generation and Migration from Beam Loss 6)MIGRATION FROMSOL7ROGR BLOCK ,.,-,- 1 Hr., inV��.vwYwWY N ~ ... � .... . 1 h k Acyotvn' < 171"l,.-.a P G %, I tbaC ✓z -' 'O tit,,, � ..7„,...<.®: ' ` ',�yY .. '''/._n;,-4? LI.n ,.•W I 'Sodium-22;and'tritium are transported m one direction only which•is toward a hypothetical well. • Assumption is that ail of the radioactivity leached from the soil/rock block is transported to the well and none is lost to the side. 7) MIGRATION OF RADIOACTIVITY TO WELL;¢IIEMEW) —1,211.0 wand oe • S Groundwater level ocandwatarlemely watermSu.otowwd MZ r 1 `.'� ! %f mewmoWletOWNdwen . s > f e--56 m-- <ir> `�. � 4- • U/ sr > a 1 ms's < H .. _ ,. 3 4 M < 3 - H In (magnflled view) SSCAP12A22681323 DEIS Volume IV Appendix 12 Health Impacts Assessment 23 `Flgure;12;2.3t Cont)( Generation and Migration from Beam Loss. • - 8) MIGRATION OF RADIOACTIVITY TO WELL (TOP VIEW) 111 1 u , 'Il 1 lit 111 I II��'II,II 1 I!lot' III II I IIIti`n 1 II ulll['1 11�1� II I'tI ' ll�lrl �Ililli Ili 1 Illll t l � • '1.1 lIII• I '�l 1 111, ,.1 � I .r, 1 1 11111 I� 1111'li ' I 111 I I'� (Ii�III II 11 I I,I'll ,ii.; ;11 i•I• � I,tl l�ln ,f 1 111,11 1 I I'll • 111'111 I' • I �I 1111 11 • 111111 tp 111 I1 11 1;1 , III �1 III 11111 1II II 11 _. Ili 1 11 • LtI ;III I l ! 1 ' • L 11161 I yl Ill I II �. I 1111 1 11 i1 1 1111 'IIII III III II III ill! I I!1 'I III 11 II u; .1 11'111 1 I 1 wy�rroa Ill III(VIII l' Illul IIIiG' l"111 IIII Illl'I; 1 i wUMyM+MsaMY 11 II I III I I�I�Ii1111 ( I'111�;11 III II I dIIII111 Il•••' 1 • 11� �I II IIIIIIIIIi�llll II'I'll 1 1111 Illl�nll 1• 111, L 1111 1" �1('� It. 1111111 i1 II 41n I ' 'I ,'1111'11, �I Ill.., 1I, I1�• I , :'� I�I Ill�I II•1• 11 11 .nl"! 1 ql• I I 4j1 1h1 C 11I'1 F11III�'l4 y 11 VIII I V ' • I: '1411 Il 11 II 1 •(IIII l''1 1 II q�l,lllflll ; 11 • • 1 1 1 II 111 I 111111 i'• I II 111 { it 111 Iln ll' I' •III! l 11 111111 11 11' I I I IIII lllu'1 IIII 11111 1111 II flll ' 11111 fj11 r. I II�II�� 1111) � 1 1 {11111 I� I�i 11 IIII 111 III 1 11 "I'I h II ILI 1 1 1 1 11 (11 11 '111h1 I IIII II 1111111 j 1 1 II 111 h111i I I 1 l 11 1 tl III l i t VIII I•1 {I 1 I ( 111 ;�•�Il 111111•Ij fl II'�II PI ! I111 11U9 j kr • II�III� i 11111 I tip .:.. - ram containing icy,rwbaotlwpl (msov+af0d vievi) • SSCAP12A2268824 DEIS Volume IV Appendix 12 S., Health Impacts Assessment 24 Figure 12.2.3-5 (Cont) Generation and,Migration from Beam toss 9)Unconfined Aquifer pumped well 7"17.i., t 1 « h,pry.r • f � 4vry ,. •r r W M ui y5yry t.v. �` rJ. /� , ° " pir w Iw '4. f� r I Wit, 4'"d�� 5 t r 4, .,,,4� �h , k' )•r y,�,. vab �s �p i. 4 .4"1'. ('W R I. a• ≥ > q r ti� ! W z� IFS` �1s+va4 ki f{r �l j bad ..' gig , Jj ..3 « '4yYi7N` t� efi � .5._._....'.; u s r max. =1 UgenCi /i iii e�11�� n,tlro"� Ar air quifer(�A 9f COfId1 1Q� Aqudard`not water conducting) Grouis ter Level SSCAP12A2268825 DEIS Volume IV Appendix 12 Hello