ML20137M040

Northrop Triga Reactor Concrete Disposition Rept

ML20137M040
Person / Time
Site:	05000187
Issue date:	11/30/1985
From:	Crandall W NORTHROP CORP.
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ML20137M034	List: ML20137M029 ML20137M040
References
NUDOCS 8512030589
Download: ML20137M040 (38)

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{{#Wiki_filter:. I NORTHROP TRIGA REACTQB CONCRETE DISPOSITION REPORT NOVEMBER 1985 I Prepared by W.E. Crandall NORTHROP CORPORATION NORTHROP RESEARCH AND TECHNOLOGY CENTER One Research Park Palos Verded, CA 90274 ATTACHMENT A 05120305D? 051120 j'DR ADOCK 0D000107 VUN

I NORTHROP TDIGA REACTOR CONCRETE DISPOSITION REPORT The basis for seeking permission to ship and to bury the remaining concrete structure at a Los Angeles County dump site is summarized in this brief report. The neutron activation of the concrete, due to its proximity to the TRIGA Reactor (Figure 1), is perceived to be a hazard. The neutron fluence created in the core of the reactor during the twenty two years operation of the reactor was 2.2 x 1019 n/cm, 2 Figure 2 plots the neutron fluence versus distance from the core. The fraction of the time the reactor operated at different locations in the pool determined the magnitude of the exposure of various structural materials. The reactor operated at the exposure room position 45 percent of the operating period. The concrete at this location was exposed to the maximum neutron irradiation. Only the data related to the activation of concrete is presented in this report since all other activated materials, except for the concrete, were removed from the facility. Table 1 lists the weight fraction of the elements of radiological interest in the concrete in the reactor structure, determined by measurements on concrete samples. The list is divided into two categories, those contributing to the natural background radioactivity and those contributing to the neutron induced radioactivity. The neutron induced radioactivity in the concrete at the surface before the removal of the activated layer is shown in Table 1. Potassium-40, the t.ranium series, and the thorium series produce the background activity observed in normal, unirradiated concrete. Table 2 summarizes the radioactivity created by these naturally occurring radioisotopes. Table 3 summarizes the neutron induced activation of the~ concrete in the exposure room. Figure 3 plots the neutron induced activity versus the depth from the surface of the concrete, in the exposure room. The observed scatter in the data is due to the variation in the neutron fluence at the different surface positions. The essential conclusion from these data is that the neutron induced radioactivity is below the natural background activity at depth greater than 20 inches below the original surface of the concrete. The entire wall betwoon the exposure room and the pool was removed, and the remaining walls, ceiling, and floor were removed to a depth of 24 inches or greater, and shipped to the llanford Site for burial (Table 4).

The specific activity at the surface of the remaining concrete is 25 pCi/gm. The induced radioactivity falls off exponentially with depth, with a relaxation length of 4 inches. The induced activity is contained in a mass of 22 metric tons of concrete, with a total induced activity of 0.55 mil 11 curies, created by 0.000011 millimoles of radioisotopes due to neutron capture (Table 5). The natural background radioactivity gener-ated in the same mass of concrete is 0.64 millicuries, created by 8,820 millimoles of naturally occurring radioisotopes. The total mass of the concrete structure, approximately 1000 metric tons, generates 29 mil 11 curies of radioactivity, created by 400,000 millimoles of naturally occurring radioistopes. The ratio of the neutron induced radioisotopes to the background radioisotopes in the concrete is approximately one part in forty billion. The total activity in the 1000 metric tons of concrete rubble is summarized in Table 5, and the fraction of the allowed limit for burial of this material, as specified in the State of California Title 17, Section 30288 and Appendix B, is also listed. Table 5 shows the radioactivity created by the neutrons in the concrete rubble is only two percent of the allowed level. The natural primordial radioactivity in the concrete rubble is approximately the same as the measured radioactivity in ordinary dirt (Table 3), and is much less available since it is chemically bonded in the concrete. The gamma activity, measured in the exposure room af ter the removal of the activated concrete,is 21.3 uR/hr. The activity measured by the detector when complelely surrounded by 2 inches of lead was zero. The activity measured by the same detector placed above and below a 2 inch layer of lead bricks (Table 7) show that the gamma activity for a flat surface of the same concrete would be 10.7 uR/hr. The gamma activity measured on concrete surfaces in buildings in the Northrop Complex that are completely isolated f rom the Reactor Facility is 11.6 uR/hr. The same level is measured on public thorughfares outside the Northrop Complex (Table 8). The calculated level from the molar content of the naturally present radioisotopes is 14.3 uR/hr (Table 2D). The quantity of neutron induced radioactivity that will enter the soll af ter burial will be very low because the radio-isotopes are chemically bonded in the concrete, and their lifetimes are relatively short. In contrast, a significant fraction of the uranium and thorium series radioisotope will escape because the concrete will decompose during the very long lifetime of the parent isotopes, and also because of the gaseous phase of the radon link in the decay series will allow some of the radioisotopes to diffuse from the concrete rubble. The maximum level of the neutron capture radioactivity eroded into the soil from the concrete after burial is a same erosion conditions, pproximately 0.2 microcurie. For the the primordial radioactivity eroded into the soil will start at 10 micrcuries and increase linearly with time until the concrete is completely decomposed (Tables 9-10, and Figure 4).

h The eroded concrete rubble buried at the landfill site will ( be exposed to water infiltrated into the soil from natural rainfall. The radioisotopcc from the eroded concrete will be dissolved in the water and transported into the soil and rock structure. An analysis of the specific activity nf the ground-water, based on the geologic and hydrogeologic report and the climatological report is given in Table 11 and the dilution of the radioactivity versus time is tabulated in Table 12. The neutron induced radioactivity introduced into the groundwater at the site is negligible compared to the natural primordial radioactivity, and, in any event, will be completely contained within the site due to : the low permeability of the sandstone (75 ft/yr) and siltstone (0.05 ft/yr) formation ; the construc-tion of leachate barriers in the canyons ; and the large area of the landfill site (1365 acres) that precludes any of the induced radioactivity leaving the site during the relatively short lifetime of these neutron induced radioisotopes (Figure 5). In summary, the concrete can be safely transported to, and buried at a local dump site because the radioisotopes produced by the neutronsin the concrete structure are negligible ( one part in forty billion ) of the naturally occurring radioisotopes, and this small fraction of neutron produced radioisotopes will remain chemically bonded in the concrete rubble during their relatively short lifetimes.

TABLE 1 RADIOISOTOPE TABLE FOR CONCRETE IN THE NORTHEOP FACILITX RADIO PARENT CONTROLLING PARENT PARENT SPECIFIC ISOTOPE ISOTOPE LIFETIME ISOTOPIC CONCRETE SURFACE ABUNDANCE ABUNDANCE ACTIVITY (YEARS) (PERCENT) (PERCENT) (pCi/gm) (XA) (YB) (TA) (GB) (JECON) (AAERCON) ACTIVATION - NEUTRON CAPTURE FESS FE54 3.90 5.82 10.2000 7000 CO60 C059 7.60 100.00 0.0070 800 NI63 NI62 144.44 3.66 0.0015 1 ZN65 ZN64 0.97 48.89 0.0020 1 EU152 EU151 19.62 47.82 0.0005 2900 EU154 EU153 12.70 52.18 0.0005 240 ACTIVAYION - PRIMORDIAL K40 K40 1.81 E 9 0.01 2.4 E -8 17.00 RA226 U238 6.51 E 9 99.27 1.1 E -8 0.37 TH228 TH232 2.03 E 10 100.00 6.4 E -8 0.70 TH232 TH232 2.03 E 10 100.00 6.4 E -8 0.70 GGTE Summary of data from final report. AAERCON KA*1000G*AU*JECON*10000*LLER/100 = KA TABLE 3.1.3C AU 1.28 Ci/gm TABLE 3.1.3C = JECON TABLE 3.1.3B LLER 0.01 percent TABLE 3.1.3F =

s { TABLE 2A NATURAL BACKGROUND ACTIVITY IN CONCRETE POTASSIUM-40 I Nuclear Decay Reactiong K-40 = Ca-40 + beta + 1.3 MeV (89 percent) K-40 = Ar-40 + El.C.+ 1.5 MeV (11 percent) 9 x Tl/2 = 1.26 x 10 years Snecific Activity At = 17 pC1/gm - Total measured activity of K-40 Ab = 15 pC1/gm - Beta activity, 89 percent of A. t A = g 2 pC1/gm - Gamma activity, 11 percent of A

• t URANIUM SERIES Nuclear Decav Reactions U-238 --------> Pb-206 + 8 alphas + 6 betas + approx. 8 gammas /xrays 4.5 x 109 Tl/2

= years D-Mass 51.7 MeV Rest mass difference, see Bib-3.1.5. = D-alpha 42.9 MeV Kinetic energy, see Bib-6.4.1. = D-beta 5.7 MeV See Bib-6.4.1. = D-recoil 0.8 MeV Momentum conservation nuclear recoils = D part. 49.4 MeV Sum of particle kinetic energies = h D gamma 51.7 - 49.4 = 2.3 MeV Difference of above = E 42.9/8 = 5.4 MeV per alpha = a Eb 5.7/6 = 0.8 MeV per beta = Eg 2.3/8 = 0.3 MeV per gamma = Snecific Activity A1 0.37 pCi/gm Measured Ra-226 activity - 1 alpha decay = A = 8x0.37 = 3.0 pCi/ = 2.2 pCi/gm for the 8. alpha decays a Ab = 6x0.37 = 3.0 pCi/gm for the 6 beta decays A = 8x0.37 gm for the 8 gamma decays g A " h +^b+^g= 8.2 pCi/gm for all decay processes t a

s k TABLE 2B NATURAL BACKGROUND ACTIVITY IN CONCRETE THORIUM SERIES Nuclear Reactions Th-232 --------> Pb-208 + 6 alphas + 4 betas + approx. 6 gammas /xrays 1.41 x 1010 Tl/2 = years D-Mass 42.7 MeV Rest mass difference, see Bib-1.3.5. = D-alpha-35.8 MeV Kinetic energy, see Bib-6.4.1. = D-beta 3.2 MeV See Bib-6.4.1 = D-recoil 0.6 MeV Momentum conservation, nuclear recoils = D part. 39.6 MeV Sum of the particle energies = D gamma 42.7 - 39.6 = 3.1 MeV Difference of above = 35.8/6 = 6.0 MeV per alpha E = a E 3.2/4 = 0.8 MeV per beta b = Eg 3.1/6 = 0.5 MeV per gamma = Specific Activity A1 0.7 pCi/gm Measured Th-232 single alpha decay. = Aa 6x0.7 = 4.2 pCi/gm for the 6 alpha decays = Ab 4x0.7 = 2.8 pCi/gm for the 4 beta decays = Ag 6x0.7 = 4.2 pCi/gm for the 6 gamma decays = At " Aa+A +Ag = 11.2 pCi/gm for all decay products b r l l

1 TABLE 2C NATURAL BACKGROUND ACTIVITY IN CONCRETE

SUMMARY

OP BACKGROUND ACTIVITY DATA SOURCE SPECIFIC ACTIVITY OF THE VARIOUS PROCESSES ENERGY QE QE RADIATION ALPHA HEIA GAMMA SUBTOTALS GAMMAS (------------ pCi/gm--------------------) (MeV) K-40 15 2 17 1.5 Uranium series 3.0 2.2 3.0 8.2 0.3 Thorium series 4.2 2.8 4.2 11.2 0.5 Subtotals 7.2 20.0 9.2 36.4 0.7 b

TABLE 2D j NATURAL BACKGROUND ACPTVITY IN CONCRETE GAMMA BACKGROUND PADIATION LEVEL EXTERNAL TO CONCRETE Eneroy Density Conversion Factor in Uniformly Activated Material Kd 2.13 (uR/hr) / (pCi/gm) / MeV Specific Enernv Deposition from Unifornly Activated Material IIES UNITS PER PARTICLE TOTAL ALPHA HE.Tb GAMMA E MeV/ particle 5.7 1.2 0.7 x A pCi/gm 7.2 20.0 9.2 36.4 x Dix (pCi-MeV)/gm 41.0 24.0 6.4 71.4 D2x uR/hr (=K xDix) 87.3 51.1 13.6 152.1 d D uR/hr (=D2t) 152.1 sx BU (ul,E ) 2.1 g Dig uR/hr (=BUxD2g) 28.6 Dft uR/hr (=0,5xDst) 76.0 Dfg uR/hr (=0.5xDig) 14.3 NQIE l E, A, from previous table x x D ix = ((E xA) is specific energy source, expressed in pCi-MeV/gm. x x D2x " D dxDix) is specific energy density, expressed in uR/hr. E 3x = 2t is specific energy deposited in test material placed in a D small cavity in the uniformly activated material. is buildup factor for gamma radiation for 1 relaxation depth BU and for gamma energy, E ( see Bib-6.4.1). g D (BU x D20) is specific energy deposited in test material placed ig = lar in a surf ace. ge cavity, greater than range of charged particles from ( 0.5 xDyr) is energy deposited in test material Dft = placed near a surface of uniformly activated material (2pi geometry). tb8ran(ge.5xD 0

1) is energy deposited in test material placed beyond D

= 9 of the charged particles from a flat surface (2pi geom.).

4 TABLE 2E NATURAL BACKGROUND SURFACE ACTIVITY FROM CONCRETE ALPHA SURFACE ACTIVITY 2 A = K xAa dpm/100cm Surface activity from alphas sa a 2 R 0.005 gm/cm Range of 5.7 MeV alphas = X 0.5 Depth of emission factor = O 0.5 steradian Effective solid angle factor = 2 K 222 (dpm/100cm )/(pCi/gm) Conversion factor = d 2 K RxXx0xKd = 0.28 (dpm/100cm )/(pCi/gm) = a A = 7.2 pCi/gm Specific activity of alphas a sa 2.0 dpm/100cm2 A Surface activity from alphas = BETA SUFFACE ACTIVITY 2 Asb K b dpc/100cm Surface activity from betas b XA 2 0.25 gm/cm Mean range of betas R = X 0.125 Depth of emission factor = O 0.5 steradian Effective solid angle factor = 2 Kb RxXx0xKd = 14 (dpm/100cm )/(pCi/gm) = Ab 20.0 pCi/gm Specific activity of betas = 280 dpm/100cm2 A Surface activity from betas sb = l GAMMA SURFACE ACTIVITY 12 gm/cm2 R Mean range of gammas = 0.083 gm/cm2 XO Effective attenuation, depth, solid = l angle factor K 2 g R x XO x Kd = 222 (dpm/100cm )/(pCi/gm) = l g 9.2 pCi/gm Specific activity of gammas A = 2000 dpm/100cm2 A Surface activity from gammas = sg BETA-GAMMA SURFACE ACTIVITY 2 Asbg " Asb+Agg = 2300 dpm/100cm 1 i

TABLE 2P NATURAL BACKGROUND RADON COMPONENT NUCLEAR PFACTIONS U238 ----> Rn222 + 4 ALPHAS + 2 BETAS + 4 GAMMAS Rn222 ---> Pb206 + 4 ALPHAS + 2 BETAS + 4 GAMMAS Th232 ---> Rn220 + 3 ALPHAS + 2 BETAS + 3 GAMMAS Rn220 ---> Pb208 + 3 ALPHAS + 2 BETAS + 3 GAMMAS K40 -----> Ca40 0.89 BETAS K40 -----> Ar40 0.11 GAMMAS The Radon isotope splits the Uranium series and the Thorium series into two approximately equal decay components. Since Radon is a noble gas,it will tend to diffuse out of the surface of the concretc, and therefor will reduce the surface activity of the concrete if the surface is exposed. Since Rn222 has a halflife of 3.82 days, and Rn220 a halflife of 55.6 seconds, the diffusion time is relatively short. The halflife of the remaining decay products are all very short except for Pb210, which is 22 years. SPECIPIC ACTIVITY The Radon component represent 50 percent of the alphas,12 percent of the betas, and 25 percent of the gammas. CATEGORY

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PARTICLE---------

ALPHA BETA GAMMA SUBTOTALS RADON INDEPENDENT 3.6 17.6 6.9 28.1 pC1/gm RADON DEPENDENT 3.6 2.4 2.3 8.3 pCi/gm TOTALS 7.2 20.0 9.2 36.4 pCi/gm SURPACM ACTIVITY l CATEGORY

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PARTICLE---------

ALPHA BETA GAMMA SUBTOTLAL l I At 1 cm (w/o Rn) 1 250 1500 1750 dpm/100cm2 At 1 cm (with Rn) 2 280 2000 2300 dpm/100cm2 At 1 m (w/o Rn) 10.2 10.2 UR/hr At 1 m (with Rn) 14.3 14.3 uR/hr In cavity (w/o Rn) 21.4 21.4 uR/hr In cavity (with Rn) 28.6 28.6 uR/hr l 1 ) 1

L I TABLE 3

SUMMARY

OF CONCRETE AND SOIL SADPLE MEASUREMENTS NEUTRON INDUCED ACTIVATION IN CONCPETE OF EXPOSURE ROOM DEPTH FE-55 CO-60 EU-152 EU-154 TOTAL (INCHES) l--------------- pC1/gm-----------------------l 0-3 7060 796 2870 234 10960 17 1300 2.92 5.0 0.6 1307 20 73.5 2.74 8.2 0 84.4 24 (13) (2.5) (8.8) (0.7) (25.0) 29 1.86 0.36 1.25 0 3.5 NATURAL BACT! GROUND ACTIVITY IN NORMAL CONCRETE LOCATION K-lD RA-226 TH228 TH232 U235 1-----------------pCi/gm---------------------I EXP.RM. 14.4 EXP.RM. 14.0 EXP.RM. 18.6 0.38 0.041 POOL 18.6 0.31 POOL 17.9 0.46 POOL 14.6 OUT. WALL 20.0 0.32 0.73 0.64 AVERAGE 16.9 0.37 0.73 0.64 0.041 NATURAL BACKGROUND ACTIVITY IN SOII; BELOW EXP.RM 16.1 0.42 0.038 BELOW EXP.RM 18.3 0.35 0.047 AVERAGE 17.2 0.38' O.042 NOTE Blanks in table indicate that particular isotope was not analyzed, and does not necessarily mean that the isotope was not present in the material. Data at 24 inches is interpolated from actual measurements.

TABLE 4 RADIOACTIVE WASTE SHIPMENTS SHIP. DAIS HEIGHT VOLUME NUMBER ACTIVITY MAJOR Hg. EIHS CONTRIBUTORS 3 (1bs) (ft ) (mci) 1 7/15 43810 672 7LSA 211 CONC. REB. WOOD 2 7/17 43400 672 7LSA 168 CONC. REB. WOOD 3 7/19 44080 768 8LSA 142 CONC. REB. WOOD 4 7/31 44930 576 6LSA 22 CONC. REB. WOOD H3 (sealed) (21.4Ci source) Ra226 foils (84uCi) 5 8/8 44470 576 6LSA 204 CONC.REBAR Ra226 foils (66uC1) 6 8/15 43210 480 SLSA 293 CONC.REBAR 7 8/22 39880 536 SLSA 228 CONC.REBAR SDRUMS HT.EXCH'R TOTALS 303780 4280 44LSA 1268 CONCRETE (138 MT) 5 DRUMS REBAR-HT.EXCH'R WOOD ESTIMATES OF MATERIAL COMPOSITION LOCATION MATERIAL VOLgME DENSI{Y MASS (m ) (MT/m ) (MT) EXPOSURE ROOM CONCRETE 40 2.7 110 EXPOSURE ROOM REBAR 2.5 7.9 20 EZPOSURE ROOM WOOD 8 0.5 4 BEAM PORTS B.P., CONC. 2 2.7 4 TOTAL 52.5 2.7 138

TABLE 5A CONCRETE RUBBLE BURIAL AT LANDPILL SITE NEUTRON GENERATED RADIOACTIVITY IN CONCRETE RADIO RADIO ALLOWED ALLOWED FRACTION .TSOTOPE ACTIVITY ACTIVITY ACTIVITY ALLOWED LIMIT BASE (1000 MT) (EACH BUR) (PER YEAR) (PER YEAR) l--------------uCi-------------l---percent--l FESS 286 100,000 1,200,000 0.02 CO60 50 1,000 12,000 0.42 EU152 194 1,000 12,000 1.62 EU154 15 1,000 12,000 0.12 TOTAL 546 2.18 HQTE

1) The radiactivities listed in the table are the measured values given in Table 3.

2) The neutron produced radioactivity in the concrete rubble is only 2.2 percent of the allowed burial limits.

TABLE SB \\ CONCRETE RUBBLE BURIAL AT LANDFILL SITE NATURAL PRIMORDIAL RADIOACTIVITY IN CONCRETE. SOIL, AND GROUNDWATER RADIO RADIO ALLOWED ALLOWED FRACTION ISOTOPE ACTIVITY ACTIVITY ACTIVITY AI.T.OWRD LIMIT HAS.E (1000 MT) (EACH BUR) (PER YEAR) (PER YEAR) l--------------uci-------------l---percent--I NATURAL PRIMORDIAL ACTIVITY IN CONCRETE K40 17,000 100 1,200 1417 THORIUM 690 50,000 600,000 0.12 URANIUM 410 50,000 600,000 0.07 TOTAL 19,000 1417.19 .==================================================== NATURAL PRIMORDIAL ACTIVT'PY IN SOIL K40 17,200 .100 1,200 1430 THORIUM

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not measured------------------

URANIUM 410 50,000 600,000 0.07 TOTAL 17,610 1430.07 NOTE

1) The radiactivities listed in the table are the measured values given in Table 3.

2) The natural primordial radioactivity in the concrete rubble is less than the natural primordial activity measured in ordinary dirt, and is much less available since it is chemically bonded in the concrete.

Therefor it is less hazardous than ordinary dirt.

TABLE 6 RADIOACTIVITY AND MOLES OF PADIOISOTOPTJ IN CONCRETE POR DISPOSAL RADIO CONTROLLING l SURFACE 22 MET. TONS] l REMAINING 1000 MET.TONSI ISOTOPE LIFETIME RADIO RADIOACTIVE RADIO RADIOACTIVE ACTIVITY MOLES ACTIVITY MOLES (YEARS) (uCi) (uMoles) (ucuries) (uMoles) (XA) (TAX) (AXNM) (NXNM) (AXNM) (NXNM) NEUTRON CAPTURE RADIOISOTOPES FESS 3.9 286 0.002 0 0 CO60 7.6 55 0.001 0 0 EUl52 19.6 194 0.007 0 0 EU152 12.7 15 0.001 0 0 SUBTOTAL 550 0.011 0 0 PRIMORDIAL RADIOISOTOPES (AXBM) (NXBM) (AXBM) (NXBM) K40 1.81 E 9 374 1310000 17000 60000000 URSER 6.51 E 9 114 1440000 5200 66000000 THSER 2.03 E 10 154 6060000 7000 66000000 SUBTOTAL 642 8820000 29200 4010000d0

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TOTAL 1192 8820000 29200 401000000 AXNM = KN*AXN*M Neutron capture activity in concrete. AXBM = KN*AXB*M Natural background alpha and beta activity. KN = 1.94 E -6 uMoles/uCi/ year - Conversion factor AXN Specific activity from neutron capture at the surface of the remaining concrete. AXB Specific activity from natural primordial radioactivity in the concrete. NXNM = AXNM* TAX Number neutron capture radioisotope nuclei. NXBM = AXBM* TAX Number primordial radioisotope nuclei. TAX Mean lifetime of radioisotope

1 TABLE 7 EXPERIMENTAL DATA FOR CAVITY DOSE RATE EXPERIMENT A Ludlum low level gamma scintilator, with a 1 inch diameter by 1 inch long sodium iodide detector was placed in the center of the exposure room. It measured 21.3 UR/hr activity. A2 inch thick by 8 inch wide by 16 inch long layer of lead was placed below the detector, with the center of the detector at approximately 1.4 inches above the center of the surface. The meter read 14 uR/hr. The detector was placed below the layer of lead at approximately 1.9 inches below the surface. The meter read 15.5 uR/hr. The meter read zero when completely surrounded with a 2 inch layer of lead. ANALYSIS UPPER HRMTSHERE AU = 14 uR/hr SU = 2 pi + 8 x ARCSIN ( l.4 / ( l.42+ (42+82 )).5 ) SU = 6.28 + 1.23 = 7.5 Steradians ASU= AU/SU = 1.87 uR/(hr-ster) LOWER HEMISPHERE AL = 15.5 uR/hr SL = 2 pi + 8 x ARCSIN ( l. 9 / ( l. 92+ (42+82 )).5 ) SL = 6.28 + 1.65 = 7.93 Steradians ASL= AL/SL = 1. 95 uR/ (hr-ster) AVERAGE ACTIVITY ASA= ( ASU + ASL ) / 2 = 1.89 uR/(hr-ster) AT = 4 pi x ASA = 23.7 uR/hr (calculated) AM = 21.3 uR/hr (measured) The minor discrepancy between the calculated and measured total activity indicates the actual solid angles for the upper and lower measurements were slightly larger than calculated. BACKGROUND PLAT SURPACE ACTIVITY AC = AM / 2 = 10.7 uR/hr ( Calculated for 2 pi geometry ) AC = 14.3 uP/hr (Calculate from specific activities, Table 2D) AM = 11.6 uR/hr ( Measured background - see Table 7 ) The agreement indicates the concrete in the exposure room is at background level.

l TABLE 8 BACKGROUND SURVEY MEASUREMENTS AT UNRESTRICTED AREAS w MEASUREMENT GAMMAS BETA-GAMMAS ALPHAS NQ, LOCATION AT 1 METER AT <1 CM AT < 1 CM (GR) (BG) (A) (uR/hr) (dpm/100cm2) (dpm/100cm2) 1 BKGD-GATE 15 AREA 12 1612 0 1 BKGD-GATE 15 AREA 12 1612 0 2 BKGD-BLDG-3-55' 12 1612 0 3 BKGD-BLDG-3-55 11 1612 0 4 BKGD-BLDG-3-55 9 1612 0 5 BKGD-BLDG-3-55 11 1612 0 6 BKGD-BLDG-3-55 12 3224 0 7 BKGD-BLDG-3-10 12 1612 0 8 BKGD-BLDG-3-10 12 1612 0 9 BKGD-BLDG-3-10 11 1612 0 10 BKGD-BLDG-3-61 12 1612 0 11 BKGD-BLDG-3-61 11 1612 0 12 BKGD-BLDG-3-61 12 1612 0 13 BKGD-BLDG-3-7 9 1612 0 14 BKGD-BLDG-3-7 11 1612 0 15 BKGD-BLDG-3-7 11 1612 0 16 BKGD-PARKLOT-747 12 1612 0 17 BKGD-PARELOT-747 12 1612 0 18 BKGD-PARKLOT-747 12 1612 0 19 BKGD-BLDG-1-153 12 1612 0 20 BKGD-BLDG-1-153 12 1612 0 21 BKGD-WINTUNLOT-1-76 12 1612 0 22 BKGD-WINTUNLOT-1-76 12 1612 0 23 BKGD-TRANSWHOUSE 12 1612 0 24 BKGD-TRANSWHOUSE 12 1612 0 24 BKGD-TRANSWHOUSE 12 1612 0 25 BKGD-PRAIRIB-NORTHROP 12 3224 0 26 BKGD-PRAIRIE-EL SEGUNDO 12 1612 0 27 BKGD-NORTHROP-CRENSHAW 12 1612 0 27 BKGD-NORTHROP-CRENSHAW 12 1612 0 AVERAGE (30 READINGS) 11.6 1720 0 STANDARD DEVIATION 0.8 410 0 MAX.LIKELYHOOD DOSE RATE 12.7 2140 0

l TABLR 9 l RADIOAC'PIVITY IN SOIL DUE TO PROSTON OF CONCRETE AFTER BURIAL EROSION OP NEUTRON ACTIVATED SURPACE The dimensions of the exposure room, after the removal of 24 inches of the activated concrete, was 4.2 x 4.2 x 4.8 meters. The remaining activity had a mean depth of 10 cm. The total mass of concrete remain-ing in the concrete structure was approximately 1000 metric tons. The rate at which activity is eroded into the soil can be estimated for a specific erosion rates of the concrete, K, and for a specific sizes of the concrete rubble, LR. The analysis is for an erosion rates of 1 mm/100 yrs, and for rubble with a uniform mass distribution from 1 cm cubes to 1 meter cubes. EROSION OP NEUTRON ACTIVATED SURPACE SN = 106 m2 Exposure room surface area - no window wall. 0.00001 m/yr Erosion rate. K = RC = 2.7 MT/m3 Density of concrete AX = Specific activity of radioisotope X at time of burial - Table 3. AX0 = K x SN x RC x AX Activity of radioisotope, X, at time of burial, for 1 years erosion. TAX Mean life of radioisotope, X - Table 1. = AXT = AX0 x T x EXP(T/ TAX) Activity of eroded radioisotope, X, in soil after T years burial - Table 10. ANT = SUM (AXT) Total radioactivity from neutron capture radioisotopes eroded into the soil after T years of burial - Table 10. EROSION OF PRIf10RDIAL ACTIVATED SURPACES RL = 0.01 m Smallest size cubic concrete rubble. RH = 1 m Largest size cubic concrete rubble. 1000 Total concrete mass. M = AX0= K x M x AX x LOG (RH/RL) / (RH-RL) Activity at burial - see above. AXT and ABT As described above. The eroded activity of the neutron-capture radioisotopes and primordial background isotopes are tabulated in Table 10, for various burial times. The total eroded radioactivities for the neutron-capture radioisotopes and the primordial radioisotopes, and their logarithmic value, are listed in Table 10. These data are plotted in figure 3.1.7.

TABLE 10 l RADIOACTIVITY IN SOIL PROM CONCRETE PRODFD AFTER BURIAL RADIO l---------- RADIOACTIVITY FROM ERODED CONCRETE----------l ISOTOPE FIRST FOURTH SIXTEENTH SIXTY-FOURTH 128TH YEAR YEAR YEAR YEAR YEAR l-------- --uCi-----

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l (XA)

(AX1) (AX4) (AX16) (AX64) (AX128) NEUTRON CAPTURE FESS 0.029 0.05 0.01 0.00 0.000 k CO60 0.006 0.02 0.01 0.00 0.000 EU152 0.024 0.08 0.18 0.06 0.005 EU154 0.002 0.01 0.01 0.00 0.000 Total 0.061 0.16 0.21 0.06 0.005

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( PRIMORDIAL K40 3.954 15.82 63.26 253.04 506.047 TH232 2.605 10.42 41.68 166.71 333.397 U238 1.935 7.74 30.96 123.83 247.648 Total 8.494 33.98 135.90 543.58 1087.092

SUMMARY

OF TOTALS TIME l-------RADIOACTIVITY------l--------- LOG RADIOACTIVITY-----l AFTERl NEUTRON ACTIV.lPRIMOR ACTIVll TIME llNEUT. ACTIVl l PRIM.ACTIVl BUR. lYRSl-----------uCi-------------l----------- LOG + 3 -----------l (T) l -- ( ANT) ----- l ----- ( ABT) ---- l -LT-- l-LOG ( ANT) ---- l --LOG ( ABT) -- l 1 0.061 8.5 0.000 1.733 3.969 4 0.160 34.0 0.628 2.170 4.597 16 0.210 135.9 1.256 2.293 5.225 64 0.060 543.6 1.884 1.726 5.853 128 0.005 1087.1 2.198 0.600 6.167

l TABLE 11 / RAINFALL IMPILTRATION DILUTION OF RADIOACTIVITY, ERODED CONCRETE AFTER BURIAL l The radioisotopes released from the eroded concrete are diluted by the rainfall infiltrating the landfill site. The dilution by the direct flow of permeating water throdgh the concrete rubble is estimated from the known average annual rainfall of 0.40 meters (13 inches) and an assumed infiltratJon factor of 50 percent. The . concrete rubble is assumed to cover 1000 square meters. The dilution for the rainfall over the total area of the site is based on a site area of 5,520,000 square meters (1365 acres). SL = 1000 m2 Area of rubble RF 0.4 m Annual rainfall (13 inches) = I 0.5 Infiltration factor = VL = SL*RF*I = 200 m3 Annual direct dilution volume of water VLT = VL*T Total direct dilution at year T ANT Total neutron induced eroded R/A at T ABT Total primordial R/A at year T ANLT = ANT /VLT Direct specific neutron induced activity ABLT = ABT/VLT Direct specific primordial activity VS = SS*RF*I = 1,105,000 m3 Annucl site dilution water VST = VS*T Total site dilution at year T ANST = ANT /VST Site specific neutron induced activity ABST = ABT/VST Site specific primordial activity 3 AGST = 12300 pC1/m Specific activity in ground water due to potassium-40, for 14 mg/l of elemental potassium (Bib 3.1.10). There may be other activitics in groundwater, but not measured. NOTE Data tabulated in Table 12.

i TABLE 12 ( RAINFALL INPILTRATION DILUTION OF EPODFD CONCRETF PADIOACTIVITY f IIHS TOTAL l TOTAL [ LOCAL [ ElIS l l ACTIVITY l WATER VOLUME lSPECIPIC ACTIV.lSPECIPIC ACT[ylIY l lNEUT. PRIM. l LOCAL 9 i NEUT.

EEIH, lNR T.

PRIM. GFD W. lyrl-----uci-----l--1000m---l-------------pci/n}(---------------[I (T) l ( ANT) (ABT) l(VLT) (VST) l (ANLT) (ABLT) [ ( ANST) ( ABST) ( AGST) l 1 0.061 8.5 0.2 1000 305 42000 0.06 8 12300 4 0.160 34 0.8 4000 200 42000 0.04 8 12300 16 0.210 136 3.2 16000 66 42000 0.01 8 12300 64 0.060 544 12.8 64000 5 42000 0.001 8 12300 256 0.005 1090 25.6 128000 0.2 42000 0.0000 8 12300 ANT Data from Table 10 ABT Data from Table 10 VLT Data from Table 11 VST Data from Table 11 ANLT = ANT /VLT ABLT = ABT/VLT ANST = ANT /VST ABST = ABT/VST AGST : Data from Table 11 HQIS The radioactivity, produced by neutrons, that is dissolved in the groundwater at the site is negligible compared to the other radioactivity in the water, and this neutron generated radio-activity will decay before the groundwater leaves the site.

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e FIGURE 3 r I* l O i0 30 30 40 so 30 e i ,ga e SPECMC RADIOACTIVITY VERSUS DEPTH IN CONCRETE CONCRETE REMOVED * - CONCRETE REMAINING ~ 10 -10 p 4 '. k "??N Q I;[$ <2 i -i .. 4 ( v. v., .#dd b$ .t. y; T, y a a ga e 'Aigs 't, T5 5;GC!~ t .i y y 7 .i j a. 'I' k m h Ad'Es NATURAL BACKGROUND ACTIVITY n * :?.l. ^! ',I!!l,s' Il/, jl /, '/ /l 2t /l -.'// / / / / /, / g 7 ; ;;m. ;.. ' /// / /.' /., ' / /,/./ /' g ?': J,: ';, / '/. ,/ / ,l, ,/ .' l,,I /,/ ,Il ~ .ni. _,o, /,/ ' .il/i / s '/./. l-/ // l g 'f, }&*.{.;g_., i g,.

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FIGURE 4 1 1 ERODED BURIED CONCRETE The radioactivity created by neutron capture is always small compared to the natural primordial radioactivity eroded from the concrete, and also is small compared to the natural radioactivity already present in the soil, e e I I y I I h recooo. [,F#DE9mbeym,orrr-debvrrz I 3 I I y 7,,,Qqa !,%Em m .3 l I i i l 10000 s-s' s / I .f _f i i rty' - 1 i i looC _,g g' vif 1 1 y ,M' I W loo i se I f -- 4J", ' A_._=_, i i w I I _F 10 1 q.,. T N I kl 1 l5&N#E&$ 5} - ?'Y1' [5 d'~ j ff[ f i d .? yy 1 S - A .I W l n I 3 g i X .08 t 1 i I s l s \\ i 1 s I 1, a il .oes 1 \\ H __' ~d 2:2 i ~, i ~ b M N g 1 a I !r l . cc-I i 1 1 I \\

PIGURE 5 GROUNDWATER RADIOACTIVITY The radioactivity created by the neutron capture, that is ( dissolved in the groundwater by the infiltrating rainwater, is extremely small compared to the natural primordial activity already existing in the groundwater. This neutron produced radioactivity will completely disappear before the groundwater diffuses from the L burial location to any off-site location .. too, w p, c ..,.c.: .o

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l. ATTACHMENT B Excerpt from a geologic and hydrogeologic report on the Puente Hills Landfill by LeRoy Crandall ^ and Associates, k _1 w.

'3.' Loc'al' Environment A. General Description The Puente Hills Landfill site is surrounded by various land uses. To the north, between the existing landfill operation and the Pomona Freeway, is a par-tially complete industrial park and a small residential development. Beyond the industrial park, at a distance of 1000 feet from the site boundary and north of the Pomona Freeway, is a condominium development known as Whittier Woods. North and east of the Whittier Woods development and north of the San Jose Creek [ diversion channel, is the community of Avocado Heights which is located within L 1500 feet to 1 1/2 miles frm this site. Ric Hondo College and the Rose Hills Memorial Park.To the southwest of the site is the Immediately west of the site is industrial land use within the City of Industry. Residential develop-ment abuts the property on the east in the Hacienda Heights community. North of .the Pomona Freeway, east of the existing landfill operation and north of the 151 acre parcel, is the Wildwood Mobile Home Park. Exhibit IV-1 shows the landfill site and existing nearby land use. B. Topography Environmental Setting. The Puente Hills Landfill site is located within a nortnwes t trending arm of the western Puente Hills. The Puente Hills, in the project area, rise to modest elevations and overlook the San Gabriel Valley. Together with the San Jose Hills, the Puente Hills fom a western extension of the Santa Ana Mountains. The western Puente Hi.11s, in the project area, are bounded on the north and east by the San Jose Creek floodplain, on the west by the Whittier Narrows flood control basin, dam, and recreation area, on the southwest by the San Gabriel River floodplain, and on the southeast by Turnbull Canyon. Elevations on the property range from 226 feet above mean sea level at a stream channel near the Workman Mill Road entrance to nearly 1,245 feet at its southernmost point. The eastern side of the property contains six east-west trending, v-shaped canyons with intermittent stream channels. Vertical relief in these canyons is from 200 to 300 feet from canyon bottom to ridge top. South facing slopes have gradients from 30 to 45 degrees. Slopes facing north are noticeably less steep and have gradients from 20 to 30 degrees. In general, the four southernmost canyons are more rugged than the northernmost canyons, cany 3 and 4. This is 9eologically significant in that the difference is due to the composition of the soil strata and their orientation. the project area is characterized by three canyons, two of which terminate onT the 151 acre parcel. plateau which has been created by the current landfill activities. fill has been constructed on top of several small previous canyons and their The existing ridges. Two prominent triangle shaped excavations with north facing 2 to 1 (horizontal length to vertical height) slopes are present where earthcutting has been necessary for the current landfill operations. West of the present The northermost canyon exits the property at a point no canyons. Rio Hondo College Police Training Facility and attains a maximum width of approximately 200 feet. The southernmost canyon (cmmonly referred to as unusual feature of steepened cliffs, some of which overhang.te College under pemit from the Districts.of this canyon are richly veptatM and O The lower oortions South of the site are the man-made slopes

• ct km W h Hemert.:1 Park and the wide. stream coarinel of the Sycame Canyon.

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I l C. Geology and Sotis Environmental Setting. The following discussion on the geology and soils of the Puente Hills Landfill site is based upon a geologic and hydrogeologic investigation by LeRoy Crandall and Associates (1981). In the Puente Hills Landfill site, three bedrock famations made up of layers of different kinds of rocks are found. Four locations of the bedrock formations and surficialdifferent types of surface soils The IV-3. soils are shown in Exhibit Bedrock Fomations. The three bedrock formations include the Puen and Pico Fomations. gravelly sandstone rocks and is found in the southern third of the property The Repetto Tomation is made up of mostly siltstone with some minor lay sandstones and is found in the middle third of the property. is composed of sandstones and siltstones and is found in the northern third The Pico Fomation the property. and bend downward deep beneath the ground surface to t Gabriel Valley. Surface Deposits. stream alluvium, mass movement debris (i.e. landslides, s e tc. ) and artificial fil l. Alluvial materials are erosional soils that have been deposited from running water, rivers, or streams. The older alluvial deposits are made up of pebbles and gravel mixed with a filling of silty sand The deposits are found on the eastern edge of the property at the mouths of the canyons. The stream alluvium is fomed of pebbles and cobbles in a sand, silt, and clay filling. The stream alluvium is found in the bottom of canyons where stom waters have deposited erosional debris. of canyons are connected to alluvial deposits in the San Gabriel Valley. Al San Gabriel Vallee is dn important aquifer s The construction of Nchate barriers is necessary. ystem. For this reason, the The leachate barriers consist of impervious material constructed through the alluvial deposits and keyed into bedrock. constructed for the existing landfill operation.A leachate barrier system has a the eastern canyons are explained in Section 3-F of this Chapter. Proposed leachate deposits are made up of different soil materials, bedrock fragments, and solid Artificial waste placed by man. Faults. Several faults were found in the vicinity of the project discussed in greater and are detail in the report by Crandall and reports by the California Division of Mines and Geology and others.2 Faults that are outside of the property boundaries are the Workman Hill Fault Rowland Fault, and Whittier Fault. the Handorf Fault and the Whittier Heights Fault. Faults that are found within Fault and Workman Hill Fault are inactive.3 The Handorf Fault Rowland Fault is an active fault and is located 1.2 miles to the sout had The Whittier is one which has shown movement within the past 11,000 years. An act'ive fault

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An investigation o low potentially active.{ the Whittier Hofghts Fault detennined this fault to be A low potentially active fault is one which has shown movement from 1-3 million years ago. As indicated in Exhibit IV-3, the Whittier Heights Fault exits the property in the area of the existing leachate barrier' where traces of the fault die out. As a result of a request by the Citizens Advisory Committee, the Handorf Fault was reinvestigated by the consulting geologi st. Additional research substantiated that the Handorf Fault is inactive.5 Tnrough recent communications with the Department of Water Resources and the los Angeles County Flood Control District, it was found that the Handorf Fault did not affect groundwater levels in San Gabriel Valley alluvium as had been originally reported. The consultant's research concluded that the Handorf Fault is a subsurface feature identified by wildcat and exploratory wells and is buried by the alluvium of the San Gabriel Valley. The classification of faults by the consultjng geologist is substantiated by the Fault Map of California by Jennings (1975). Seismici ty. Seismici ty can be defi being subject to natural earthquakes."ged as ".......the likelihood of an area The consultant has reported a system of establi shing the seismicity for the site based upon the estimated maximum probable earthquake magnitude from a 120 mile radius search of faults and a 62 mile radius search of earthquake epicenters. The maximum probable magnitude earthquake is the maxitt.um that is "likely" to occur during a 100 year interval. It can only be regarded as a probable occurrence and not an assured event that will occur at a specific time. Crandall reports that for the Puente Hills Landfill site, the maximum probable magnitude earthquake over a 100 year recurrence-would be 7.0 on the Richter Scale. Crandall found that the Puente Hills Landfill site could be subjected to earthquake vibrations as intense as any other location within the Los Angeles-Metropolitan area. It was found that the landfill site was not within a currently established Alquist-Priolo fault hazard zone. The Alquist-Priolo Special Studies Act of 1972 requires the State Geologist to delineate conservatively large special studies zones to emcompass all potentially and recently active ' traces of the San Andreas and other such faults that constitute a potential hazard to structures from surface faulting or fault creep. A subject that was raised in the Citizens Advisory Committee meetings was the effect of large magnitude earthquakes on faults near the site. In response, the consultant has indicated that it is very unlikely that any of the faults on or near the site would be affected by movement along an active fault. In the case of the Whittier Fault, the nearest active fault, Crandall's research has shown that the majority of evidence for its activity is in the central and south-central portions of the fault, over 10 miles from the Puente Hills Landfill site. Also, the microseismic activity associated with the Whittier Fault is reported to be greater further to the south along the fault and appears to die out to the north near the Puente Hills area. The Citizens Advi sory Committee questioned whether or not refuse fill placement on or near the faults in the area would induce movement along those f aul ts. In response, Crandall has indicated that the association of extremely heavy loads with microseismic activity is known to have occurred on very deep and large capacity water reservoirs which lie over active faults. It is clear

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~ t from that data that tremendously heavy loads, such as tha% from cater reservoirs hundreds of feet deep, acting ever many thousands of acres can produce microseismic activity deep below the surface on active faults underneath the N rese rvoi r. The consultant indicated that there is no evidence to indicate that any microseismic activity of the faults on or near the site will result from the placement of fill materi al s. During the extensive field investigations conducted in the area of the leachate barrier, no unusual surface or subsurface features were encountered in the immediate vicinity of the Whittier Heights Fault where it crosses the barrier alignment as a result of the existing placement of solid waste. Another question raised during the Citizens Advisory Committee meetings was whether potential leachate from the proposed landfill could " lubricate" the low potentially active Whittier Heights Fault and cause it to move. Crandall has inspected the fault during field investigations and during construction inspection of the existing leachate barrier. Those inspections indicate that clay material is present in and along the fault. That clay material is sufficiently impemeable so as to preclude the movement of potential leachates along or across the fault. Crandall has indicated that there is no evidence that potential leachate could incu:e movement in the Whittier Heights Fault. The Citizens Advisory Committee ' questioned whether landfill gas drilling could induce movement al ong the faults in the immediate area. Crandall indicates that there would be no significant effects of gas drilling on these f aul ts, and that there is no evidence that inactive faults tend to move when forces such as drilling are applied to them. In this case, drilling would not Gven occur directly within the fault. Most gas well drilling would only occur within refuse fill and not in the underlying soil or bedrock fomations. Geologic Field investigations. The field investigations included extensive field mapping, geophysical explorations, and a rock and soil bore hole sampling Geologic mapping' investigated by the consultant covered a region over program. 100 square miles in size. The 1355 acre landfill site was subjected to five years of detailed study producing three maps and cluminating in three substantial volumes of data and findings. The geophysical exploration program involved 9570 linear feet of seismographic refraction investigations.. The investigations searched over 200 feet beneath the surface over the site. Landslides and soil movements were investigated. They were found to be located intemittently throughout the site (See Exhibit IV-3). Several seeps and intermittent springs were also found which result.fr.am rainfall' infiltration into soil and alluvium on site. Cover soil excavations and placement of solid waste fill over these intermittent seeps and sprtngs will largely remove them, since the rainfall will be diverted by the surface Tunoff drainage systems. The minor amount that is not intercepted could have the potential for contacting the waste material and produce leachate. A s6bdrain system will be made part of the leachate control systems which is discussed in Section F of this Chapter. A total of 14 bedrock and soil sampling ;bor.ings probed: over 150 feet under the surface of the site. Laboratory tests taken on samples from rock and soil borings investigated many physical and chemical properties. Those physical and chemical properties tested incluoed particle gradation, consolidation testing, rock shearing strength, moisture tests, expansion testing, compression testing,

p'" permeability testing and excavation ' stability tests. The test data indicate that the bedrock siltstones are weathered and fim at the near surface but become hard at increasing depths. The bedrock sandstones contain some gravel r and cobbles and are hard to very hard. Bedrock materials contain minor amounts of moisture and the siltstones can be expansive. Pemeability tests were perfomed on bedrock cores extracted in a natural state from the boring program. Pemeabili ty is the measure of how quickly water can move through bedrock and soil materials under the pressure exerted by standing water. The consultant selected core samples that best matched the bedrock and soil conditions at the landfill site. The results indicated that the siltstones could only allow fluid movement of about 2/100 to 7/100ths of a foot per year (1.9 x 10-8 to 6.8 x 10-8 cm/sec) or about 100,000 to 1,000,000 times slower than the alluvium in the canyon bottoms. The sandstones could only allow movement of about 75 feet per year or about 1000 times slower than the alluvium in the canyon bottoms. As part of the crilling program a total 'of six monitoring wells were installed. Three of the wells were constructed in the canyon nouths through the alluvial deposits on the eastern boundaries of the site (See Exhibit IV-5). Three additional wells were established on the northern limit of the project One well was subsequently destroyed by the Crossroads Industrial Park area. development. The purpose of the monitoring wells was to provide sampling points at the subsurface drainage locations. These nonitoring wells would detect the fomation of any potential leachate. Groundwater samples are taken from these wells routinely, and water quality is analyzed. Groundwater results and the construction of leachate barriers are more fully discussed in Section 3-F of this Chapter. The extensive findings of the geologic field investigations indicate that it is feasible to develop the 1365 acre site as a Class II landfill with limited non-hazardous liquid disposal. This finding is substantiated by the geologic field mapping and testing of the bedrock and soils that make up the site. Because of the way the bedrock and soil materials are shaped and fitted together above the San Gabriel Valley, the threat of groundwater pollution is limited to the alluvial materials in the canyon bottoms. The alluvial materials will be severed by leachate barriers as explained in Section 3-F of this Chapter. In support of this conclusion, Crandall found that the relatively impemeable siltstone of the Repetto Fomation would separate potential leachate from usable groundwater in the San Gabriel Valley to the north. As an additional portion of his work pertaining to the practicality of on-site excavations, Crandall found that bedrock and soil materials could be excavated utilizing ordinary heavy equipment as is currently available in the existing operation. Abandoned Oil Wells. In the southeastern portion of the landfill property is a small inactive oil field identified as the North Whittier Heights Oil Field. Eleven wildcat or exploratory wells were drilled between 1915 and 1951. None of the wells produced oil or gas in commercial quantities. All wells in the project area were abandoned according to regulations that existed during the time of abandoment. Revisions in 1975 of the California Administrative Code will require re-abandoment of two of the eleven wells in accordance with new l I requi rments. The Sanitation Districts will follow cplicable requirements for abandoment of oil wells on the prcperty. ___,._..7-

I L F. Groundwater and Leachate Control r Environmental Setting. The landfill property is underlain by sedimentary rock t of marine origin. inis fomation has relatively low pemeability and does not contain groundwater. No waur was detected during geologic investigations r i conducted from 1975 to 1978 in eight wells drilled up to 150 feet deep into the bedrock. Water was found in abadoned oil wells drilled several hundred feet into underlying bedrock fomations. This water comes from great depths and does not constitute a part of any usab-e groundwater system. Weathering processes have eroded the near surface and exposed rock on the property and deposited coarse aliuvium onto the canyon bottoms. Precipi tation seasonally recharges the alluvium with limited amounts of water. This water has fomed a few small springs in the eastern canyons where the alluvium is very I s hallow. The water ul timately flows through the alluvium toward the San Gabriel Valley groundwater basin. This basin is a major aquifer and is situated l to the east, north, and west of. the landfill property. The water from the oil wells contains relatively high amounts of sodium and bicarbonate. It has a poor quality characterized by a high level of dissolved solids. Water quality infomation from an oil well ("Pellissier No. 3") is listed in Table IV-3. This infomation is representative of the other oil wells abandoned on the Puente Hills site. The water contained in the alluvium overlying the canyon bottoms has been monitored since 1975 using five wells installed during the geologic investiga-tion. The locations of the monitoring wells are shown on Exhibit IV-5. The eastern wells are monitored quarterly and monitoring well 4 on the west is moni tored monthly. Monitoring well 5 was destroyed in 1981 due to nearby construction activities. Four localized springs in the eastern canyons have also been monitored. wells is presented in Table IV-3. Water quality infomation for the springs and nonitoring The water in the alluvium is unifomly poor I in quality. This is due to the natural occurrence of mineral salts (e.g., sodium chloride, calcium sulfate and calcium carbonate) and organics in the l marine fomation. The salts contribute to the water's dissolved solids. The organics are residues frm marine vegetation and are measured principally by the parameter " COD" (Chemical oxygen demand). These organics may also contribute to a small degree to the parameter " BOD" (Biochemical oxygen demand). The BOD l measures the portion of the organics which is bio-degradable. The water quality in the San Gabriel Valley Groundwater basin is diverse. The diversity -results from the differing character of sediments within the basin, the range in sources for water recharge, and types of local land uses (e.g. industrial, agricultural, and residential). The water quality in a well situated in the basin upgradient and northeast of the property is illustrated in Table IV-3 (Well No. 15/10W 31PS). This well is representative of othen upgradient of the site. However, major parameters of water quality such a: dissolved solids may vary by a factor of two at nearby wells. The water in the San Gabriel Valley Basin is characteristically "hard" but much superior to that found in the Puente Hills canyon alluvium. This is because sediments within the basin are by comparison extensively weathered and do not readily release salts-l l

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SUMMARY

FIGURE IV-3 EASIERH1 WESIERN OI M LL CANYON AREA. PIEZ0 METERS 3 5AH GABRIEL WELLS WELLS (PELLISSIER No. 3) SPRINGS 4 YALLEY WELL (IS/10W-31PS) Pil 7.2 7.2 6.5 8.2 7.7 8.0 Calcium,mg/1 197 331 393 5.7 210 56 Magnesium,ag/l 137 148 161 7 143 14 Sodium, ag/l 237 210 230 724 116 58 Potassium, ag/l 8.5 13 20 4.4 6.9 2.4 Bicarbonate,ag/l 392 526 485 1,197 412 237 Sulfate,ag/l 857 933 719 73 868 86 Chloride,mg/l 103 257 348 403 82 25 Disssolved Solids, ag/l 1,906 2,541 2,530 2,306 1,619 376 Soluble COD, 15 91 103 N.R.5 N.R. N.R. Total BOD, ag/l <1.4 <3.9 13 N.R. N.R. N.R. 1 Average of Monitoring Wells 1, 2, & 3 2 Average of Monitoring Wells 4 & 5 3 Average of Four Piezometers 4 Average of Four Springs (SP-1 tiirough SP-4) 5 y,g,. Not Reported All groundwater monitoring locations are sliown on Ext:fbit IV 5.

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