Formerly Utilized Sites Remedial Action Program (FUSRAP)

Maywood Chemical Company Superfund Site

ADMINISTRATIVE RECORD

Document Number

MISS- 010.

DOE/OR/20722-254 ‘-

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RADIOLUGICAL CHARACTERIZATION REPORT

FOR THE COMMERCIAL PROPERTY AT

100 HANCOCK STREET

LODI, NEW JERSEY

SEPTEMBER 1989

Prepared for

UNITED STATES DEPARTMENT OF ENERGY

OAK RIDGE OPERATIONS OFFICE

Under Contract No. DE-AC05-810R20722

BY

N. C. Ring, D. J. Whiting, and W. F. Stanley

Bechtel National, Inc.

Oak Ridge, Tennessee

Bechtel Job No. 14501

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‘U .S . D e p a r tm e n t o f E n e r g y O a k R i d g e O p e ra tio n s Post O ffice B o x 2 0 0 1 p a k Ridge , T e n n e s s e e 3 7 8 3 1 - 8 7 2 3

A tte n tio n : R o b e r t G . A tkin Techn ica l S e rvices D iv is ion

S u b ject: B e c h .te l J o b N o . 1 4 5 0 1 , P U S R A P P ro jec t D O E C o n trac t N o . D E - A C O S - 8 1 0 R 2 0 7 2 2 P u b l icat ion o f R a d io log ica l C h a r a c ter iza tio n R e p o r t- fo r seven te e n res iden tia l p rope r ties , fou r m u n icipz. p rope r ties , a n d seven commerc ia l p rope r ties in L o d i a n d M a y w o o d , N e w Jersey C o d e : 7 3 1 5 /W B S : 1 3 8

D e a r M r. A tkin :

E n c l o s e d is o n e copy e a c h o f th e 2 8 sub jec t pub l i shed repor ts fo r th e p rope r ties liste d in A tta c h m e n t 1 . T h e s e repo r ts Inco rpo ra te al l c o m m e n ts rece ived in th is rev iew cycle (CCNs 0 6 3 1 6 5 , 0 6 3 3 2 7 , 0 6 2 2 8 5 , a n d 0 6 1 5 6 8 1 a n d a re b e i n g pub l i shed w it’. app rova l o f S te v e O l d h a m , as repo r te d in C C N 0 6 3 8 6 8 .

A lso enc losed (as A tta c h m e n t 2 ) is a p r o p o s e d d is trib u tio n list fo r th e s e repo r ts. P lease send us any changes to th e p r o p o s e d distr ibut ion list a t your ear l iest conven ience so w e m a y d is trib u te th e repo r ts.

B N I w o u ld l ike to express ou r thanks to Hr . O l d h a m fo r h is c o o p e r a tio n a n d e ffo r ts to rev iew th e s e d ra fts in a n acce le ra te r m a n n e r . H i8 e ffo r ts h a v e a l l owed us to pub l i sh th e s e repo r ts o - schedu le . If y o u h a v e a n y q u e a tio n s a b o u t th e s e d o c u m e n ts, p l .e g s e cal l m e a t 5 7 6 - 4 7 1 8 .

V e ry tru ly your6 ,

C . R o b e r tso n P io ject M a n a g e r .0 P U S R A P

R C R :w fs:1 7 5 6 x Enc losu re : A s sta te d

cc: J. D . B e rger , O R A U (w /e ) N . J. Besk ld , A N L (w /e )

TABLE OF CONTENTS

List of Figures List of Tables Abbreviations

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1.0 Introduction and Summary 1 1.1 Introduction 1 1.2 Purpose 3 1.3 Summary 3 1.4 Conclusions 6

2.0 Site History 8 2.1 Previous Radiological Surveys 9 2.2 Remedial Action Guidelines 10

3.0 Health and Safety Plan 13 3.i Subcontractor Training 13 3.2 Safety Requirements 13

4.0 Characterization Procedures 15 4.1 Field Radiological Characterization 15

4.1.1 Measurements Taken and Methods Used 15 4.1.2 Sample Collection and Analysis 18

4.2 Building Radiological Characterization 18

5.0 Characterization Results 23 5.1 Field Radiological Characterization 23 5.2 Building Radiological Characterization 28

References 44

Appendix.A - Geologic Drill Logs for 100 Hancock Street A-l

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Table

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LIST OF FIGURES

Location of Lodi Vicinity Properties Location of 100 Hancock Street Borehole Locations at 100 Hancock Street Surface and Subsurface Soil Sampling Locations at 100 Hancock Street Gamma Exposure Rate Measurement Locations at 100 Hancock Street Areas of Surface Contamination at 100 Hancock Street Areas of Subsurface Contamination at 100 Hancock Street

LIST OF TABLES

Title Summary of Residual Contamination Guidelines for the Lodi Vicinity Properties Surface and Subsurface Radionuclide

BASE 2 4

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Concentrations in Soil for 100 Hancock Street 30 Downhole Gamma Logging Results for 100 Hancock Street 36 Gamma Radiation Exposure Rates for 100 Hancock Street 43

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cm cm2 cpm dw ft h in. knl2 L L/min m m2 MeV MVh mi mi2 min mrad/h mrem mrem/yr PWg pCi/L WL yd

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centimeter square centimeter counts per minute disintegrations per minute foot hour inch square kilometer liter liters per minute meter square meter million electron volts microroentgens per hour mile square mile minute millirad per hour millirem millirem per year picocuries per gram picocuries per liter working level yard cubic yard

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1.0 INTRODUCTION AWD SUMMARY

This section provides a brief description of the history and background of the Waywood site and its vicinity properties. Data obtained from the radiological characterization of this vicinity property are also presented.

1.1 JNTRODUCTION

The 1984 Energy and Water Appropriations Act authorized the U.S. Department of Energy (DOE) to conduct a decontamination research and development project at four sites, including the site of the former Maywood Chemical Works (now owned by the Stepan Company) and its vicinity properties. The work is being administered under the Formerly Utilized Sites Remedial Action Program (FUSRAP) under the direction of the DOE Division of Facility and Site Decommissioning Projects. Several residential, commercial, and municipal properties in Lodi, New Jersey, are included in FUSRAP as vicinity properties. Figure l-l shows the location of the Lodi vicinity properties in relation to the former Maywood Chemical Works.

The U.S. Government initiated FUSRAP in 1974 to identify, clean up, or otherwise control sites where low-activity radioactive contamination-(exceeding current guidelines) remains from the early years of the nation's atomic energy program or from commercial operations that resulted .in conditions Congress has mandated that DOE remedy (Ref. 1).

FUSRAP is currently being managed by DOE Oak Ridge Operations. As the Project Management Contractor for FUSRAP, Bechtel National, Inc. (BNI) is responsible to DOE for planning, managing, and implementing FUSRAP.

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CHEMICAL -_ ------

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SEE FIGURE

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FIGURE 1-l LOCATION OF LODI VICINITY PROPERTIES

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1.2 puRPose

The purpose of the 1988 survey performed by BNI was to locate the horizontal and vertical boundaries of radionuclide concentrations exceeding remedial action guidelines.

This report details the procedures and results of the radiological characterization of the property at 100 Hancock Street (Figure l-2) in Lodi, New Jersey, which was conducted in September 1988.

_ Ultimately, the data generated during the radiological characterization will be used to define the complete scope of

.- remedial action necessary to release the site.

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The property located at 100 Hancock Street is a commercial property that consists of a concrete block building with a grassy area and an asphalt-paved parking lot to the front of the building. Along the eastern side of the building is another grassy area with an inactive railroad spur. The western side of the building is bordered by an asphalt-paved loading area that adjoins another commercial property. The primary use of the property is the distribution of electronic components. The property is situated in a densely populated residential neighborhood; however, other commercial properties are located in close proximity.

-. This characterization confirmed that thorium-232 is the primary radioactive contaminant at this property. Results of surface soil samples for 100 Hancock Street showed maximum concentrations of thorium-232 and radium-226 to be 8.0 and 1.9 pCi/g, respectively. The maximum concentration of uranium-238 in surface soil samples was 6.7 pCi/g.

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S u b s u r fa c e soi l s a m p l e c o n c e n tra tio n s r a n g e d fro m 0 .6 to 5 .4 P C i/g fo r th o r i u m - 2 3 2 a n d fro m 0 .3 to 2 .2 p C i/g fo r r6d iu .m 2 2 6 . T h e a v e r a g e b a c k g r o u n d leve l in th is a r e a fo r b o th r a d i u m - 2 2 6 a n d th o r i u m - 2 3 2 is 1 .0 pc i /g . T h e c o n c e n tra tio n s o f u r a n i u m - 2 3 8 in subsur fa c e soi l samp les r a n g e d fro m 0 .6 to 7 .2 p C i/g . B e c a u s e th e m a jor c o n ta m i n a n ts a t th e vicinity p rope r ties a re th o r i u m a n d r a d i u m , th e d e c o n ta m ina tio n gu ide l i nes p rov ide th e 'app rop r i a te g u i d a n c e fo r th e c l e a n u p ac tivities . D O E be l ieves th a t th e s e gu ide l i nes a re conserva tive fo r cons ider ing p o te n tia l adverse h e a l th e ffec ts th a t m igh t occur in th e fu tu re fro m a n y res idua l c o n ta m ina tio n . T h e d o s e c o n trib u tio n s fro m u r a n i u m a n d a n y o the r rad ionuc l ides n o t numer ica l ly spec i fie d in .th e s e gu ide l i nes a re n o t expec te d to b e s ign i fica n t fo l l ow ing d e c o n ta m ina tio n . In a d d i tio n , th e vicinity p rope r ties w ill b e d e c o n ta m ina te d in a m a n n e r so as to r e d u c e fu tu re doses to levels th a t a re as l ow as reasonab ly ach ievab le ( A U R A ) ( R e f. 2 ) .

S o il ana lys is d a ta fo r th is p rope r ty ind ica te d sur fa c e c o n ta m ina tio n . S u b s u r fa c e investig a tio n by g a m m a l ogg ing ind ica te d c o n ta m ina tio n to a d e p th o f 2 .7 4 m (9 .0 ft).

E xter ior g a m m a rad ia tio n exposu re ra tes r a n g e d fro m 5 to 4 1 p R /h , inc lud ing b a c k g r o u n d . T h e i ndoo r m e a s u r e m e n t s h o w e d a ra te o f 9 p R /h , inc lud ing b a c k g r o u n d .

T h e r a d o n - 2 2 2 m e a s u r e m e n t ins ide th e bu i l d ing ind ica te d a c o n c e n tra tio n o f 0 .7 p C i/L , w h ich is w ith in th e D O E gu ide l i ne o f 3 .0 p C i/L .

T h e m e a s u r e m e n t fo r r a d o n d a u g h ters w a s 0 .0 0 1 work ing leve l ( W L ) , a n d th e m e a s u r e m e n t fo r th o r o n d a u g h ters w a s 0 .0 0 1 W L .

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All data tables for this property appear at the end of this report.

1.4 mNCLUSI=

Evaluation of data collected, analyses performed, and historical documentation reviewed indicates the presence of radiological contamination on the property located at 100 Hancock Street. This contamination is both surface and subsurface contamination. The surface contamination is located in two areas along the eastern boundary of the property in a iow-lying, grassy area. One area is near an open culvert that intersects the buried conduit containing the present-day channel of Lodi Brook. The other area is in the southeast corner of the property along the property line. The subsurface contamination ranges from a depth of 1.07 m (3.5 ft) to 2.74 m (9.0 ft). In addition, the contamination appears to extend beneath the building, and there is a high probability that the contamination extends beneath the street in front of the building. The total affected area is estimated to be approximately 40 percent of the property. These conclusions are supported by documentation that establishes the presence of the former channel of Lodi Brook in this area. This channel is the suspected transport mechanism for the radiological contamination.

From review of aerial photographs of the area, it has been determined that the former channel of Lodi Brook was realigned and buried in concrete conduit parallel to Hancock Street on this property. Prior to this realignment, it is suspected that the former channel flowed across the property in a southwesterly direction in the area where the building now stands. Confirmation of this suspicion could not be obtained because of restricted physical access to the

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area in question. Indoor boreholes could not be drilled to confirm the presence of contamination because of the small office area and size of equipment needed to accomplish the task.

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2.0 SITE WISTORY

The Waywood Chemical Works was founded in 1895. The company began processing thorium from monazite sand in 1916 (during World War I) for use in manufacturing gas mantles for various lighting devices. Process wastes from manufacturing operations were pumped to two areas surrounded by earthen dikes on property west of the plant. Subsequently, some of the contaminated wastes migrated onto adjacent and vicinity properties.

In 1928 and again between 1944 and 1946, some of the residues from the processing operations were moved from the company's property and used as mulch and fill in nearby low-lying areas. The fill material consisted of tea and coca leaves mixed with other material resulting from operations at the plant. Some fill material apparently contained thorium process wastes (Ref. 3).

. . Uncertainty exists as to how the properties in Lodi were contaminated. According to an area resident, fill from an unknown source was brought to Lodi and spread over large portions of the previously low-lying and swampy area. For several reasons, however, a more plausible explanation is

-.. that the contamination migrated along a drainage ditch originating on the Maywood Chemical Works property. First, it can be seen from photographs and tax maps of the area that the course of a previously existing 6tream known as Lodi Brook, which originated at the former Maywood Chemical Works, generally Coincide6 with the path of contamination in Lodi. The brook was subsequently replaced by a storm drain system as the area was developed. Second, samples taken from Lodi properties indicate elevated concentrations of a series of element6 known a6 rare earths. Rare earth element6 are typically found in monazite Sands, which also contain

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thorium. This type of sand wa6 feeds toc k at the Maywood Chemical W orks, and elevated level6 are known to exis t in the by-product of the extraction process. Third, the ratio of thorium to O ther tadionuc lides found on these Lodi properties is comparable to the ratio found in contaminated material on other properties in Lodi (Ref. 4). And finally , long-time residents of Lodi recalled chemical odor6 in and around the brook in Lodi and s team ris ing off the water. These observations suggest that discharges of Contaminant6

occurred upstream.

L.. The Stepan Chemical Company (now called the Stepan.Company) purchased Maywood Chemical W orks in 1959. The Stepan Company ,itself ha6 never been involved in the manufacture or

processing of any radioactive materials (Ref. 5). ._-

2.1 PREVIO U S RADIO L O G ICAL SURVEYS

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Numerous surveys of the Maywood s ite and its v ic inity properties have been conducted. Among the past surveys, three that are pertinent to this v ic inity property are detailed in this sec tion.

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Januarv 1981--The Nuclear Regulatory Commis s ion direc ted that a survey be conducted of the Stepan Company property and its v ic inity properties in January 1981. Us ing the Stepan Company plant a6 the center, a 10.3~km2 (S-mi2) aerial survey was conducted by the EGLG Energy Measurements G roup; which identified anomalous concentrations of thorium-232 to the north and 6OUth O f the Stepan Company property. The Lodi v ic inity properties were inc luded in this survey (Ref. 6).

June 1984--In June i984, O ak R idge National Laboratory (ORAL) conducted a "drive-by n survey of Lodi using its

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mscanning van." Although not comprehensive, the survey indicated areas reguiring further investigation (Ref. 7).

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geotember 1986--At the regue6t of DOE, ORNL conducted radiological ourveys of the vicinity properties in Lodi in September 1986 to determine which properties contained radioactive contamination in exces6 of DOE guideline6 and would, therefore, require remedial action (Ref. 8).

2.2 REMEDIAL ACTION GUIDELINES

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Table 2-l 6ummhrizes the DOE guideline6 for residual contamination. The thorium-232 and radium-226 limit6 listed in Table 2-l will be used to determine the extent of remedial action required at the vicinity properties. DOE developed these guideline6 to be consistent with the guidelines established by the U.S. Environmental Protection Agency (EPA) for the Uranium Mill Tailings Remedial Action Program.

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TABLE 2-l SUMMARY OF RESIDUAL CONTAMINATION GUIDELINES

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&II Concsntrstlon (pCVg) Above Bsckgroune

6pCUOwhons~ragdovrrthr~‘vrt15ad~Ukbw ths surfwe; IS pCiIg when svsrsgsd svsr sny l-thick aoll kysr bekw the surf- fsyer.

Other Ftsdiiudides 8oll guldetinea wtt be cskulsted on a site-apecifk basis using the DOE manual devebped for this use.

STRUCTURE GUfDElJNES

Alrborne Redon Oeuy Products

Generic guidelines for wnoentratbnr of sirborne radon decay prodtir shall spply to sxiating asupied or hsbiiabk structures on private property thst has no radiological restrictiinr on its uaa; structures that will be demotiihed or buried sre l xduded. lha spplkabls generic guideline (40 CFR 192) is: In sny oscupkd or hsbiiable building, the objedivs of remadial sdbn shall be, and resaonabla effort shall k msde to rhieve, sn snnual average (or quivalent) rsdon decay product eoncentrstkn (including background) not to l xcesd 0.02 WL’. In sny csae, the radon decay product comentratkn (including bachground) shall not exceed 0.02 WL Remediil sctbns sre not required in order to comply with thii guideline when there is reasonable ururance that residual rsdiosctive matwiak M lpi the cause.

External Gamma Radktlon

The average level of gamma rsdiation inside a building or habitable structure on a site that has no nsdiokgkal restrktiona on ita use shall not exceed the background bvel by more than 20 pR/h.

Indoor/Outdoor Structure 8urfsse Contamtnstlon

Rsdbnuelide’

Albwsbb 8urfaoa Resldusl Contamlnstlsn” NP~W a+)

Average@’ 66sxlrnumw Renwsbbh~

frsnsursmka, Rs-226. Rs-226, Th-230, Th-226 Pa-231. k-227, l-125, l-129

100 300 20

Th-Nstura!, Th-282,8r-90, b-223, h-224 U-232, l-126, l-131, l-133

lJ-Nstural, U-236, U-236, snd -sd dewy producta

he-gamma smtttem (mdbnuclide~ with decay modes other than sfphs l mfaaiin or spomsnssus fbsbn) l xcrpt 8r-M and othen noted above

S,OOO a 15,000 a l.WO a

5.000 6-y lS,wo Q-y l.ooo 6-y

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TABLE 2-l (CONTINUED)

~guidslinrrtPlu~~nthOrowthdnBum226fromlhorlun-230~dndium221)frommalum~, and assume makr oqdUbrIum. if either thorium230 and ndium-226 or mm232 8nd rdium-22s 8ro both ~mN&h~~Wl-$. w’dd’?)l WY b e hiohsr eononbrtkn. wottmrmixbJmct

~dindMdualradiond~ohatlknduodrottlet1)thedoBe*k ~reswillnotex~thr~ic~Umiror2)(hrrumdrrdiarol~hrroil~pr~ *mbOIbWWlMtlorlh8t-iWiUnotur#dl~.

%heseQuIdellnetrepresetielIowsble~cancentration,above~~~~1sun-~ . byerloMydepthMdcveranyabrdguw1~wrho~

dA,rkinglevel(WL)irMyeomMnationdthort-lived~~~in1~ddr~wlBnsuftinme ulhate emissbn of 1.2 x 105 MDV of potmal alpha onorgy.

‘As used in thii tabb, dpm (diikttegmtions per minute) means the rate of emission by radiicthm material as determined by corredng the oounts per minute observed by an appropMe detector for &ck~round, efficiency, and geometric faotom associated V&I the instrumentation.

here ourfaoe contamination by bofh alpha- and betagamma-emltting radionwliis etists, ti timits estabtii for alphe- and betaqamma-emitting radionudiis should apply indepewtentty.

N4easurements of average contamination should not be averaged over mom than 1 d. For objeck of tess surka ama,theaverageshallbederivedforeaohsuohobject

9he average and maximum radiation levels essoa’ated with rurface contamination recutting from beta-gamma emitters should not exceed 0.2 mmdk and 1.0 mrad.41, respectMy, at 1 an.

iThe maximum contamination bvel applies to an area of not more &an 100 a~?.

khe amount of removable radioactive material per 100 an* of wrfaw ama should be determined by wiping that area with dry filter or sotI absorbent paper, applying moderate pressure, and measuring the amount of radioactive rnatetial on the wipe with an appmpriate instrument of known efft6ency. When removable oontarnination on objects ofsurfaatareaIs~sl100an?isdetermined,~~vitrperunitarea~uldbebasedonmeactualarsaand the entire surface should be wiped. The numbers in this column am maximum amounts.

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3.0 HEALTH AND SAFETY PLAN

BNI is responsible for protecting the health of personnel assigned to work at the site. As such, all subcontractors and their personnel were reguired to comply with the provisions of BNI health and safety requirements and as directed by the on-site BNI Health and Safety Officer.

3.1 BUBCONTRACTOR -NING

Before the start of work, all SUbCOntraCtOr petSO~e1 attended an orientation session presented by the BNI Health and Safety Officer to explain the nature of the material to be encountered in the work and the personnel monitoring and safety measures that are required.

3.2 SAFETY REOUIREMENTS

Subcontractor personnel complied with the following BNI requirements:

Bioassay--Subcontractor personnel submitted bioassay samples before or at the beginning of on-site activity, upon completion of the activity, and periodically during site activities as requested by BNI.

Protective Clothing/Equipment--Subcontractor personnel were required to wear the protective clothing/equipment specified in the subcontract or as directed by the BNI Health and Safety Officer.

Dosimetry--Subcontractor personnel were required to wear and return daily the dosimeters and monitors issued by BNI.

Controlled Area Access/Egress--Subcontractor personnel and equipment entering areas where access and egress were controlled for radiation and/or chemical safety purposes were surveyed by the BNI Health and Safety Officer (or personnel representing BNI) for contamination before leaving those areas.

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o Medical Surveillance--Upon written direction from BNI, subcontractor personnel who work in areas where hazardous chemicals might exist were given a baseline and periodic health assessment defined in BNI's Medical Surveillance Program.

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-- Radiation and/or chemical rafety surveillance of all activities related to the scope of work was under the direct supervision of personnel representing BNI.

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Health and safety-related requirements for all activities involving exposure to radiation, radioactive material, chemicals, and/or chemically contaminated materials and other associated industrial safety hazards are generated in compliance with applicable regulatory requirements and industry-wide standards. Copies of these requirements are located at the BNI project office for use by project personnel.

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4.0 CHARACTERIZATION PROCEDURES

A master grid was established by the surveyor. BNI's radiological support subcontractor, Therm0 Analytical/Eberline (T&W/E), established a grid on individual properties. The size of the grid blocks was adjusted to characteriee each

-- property adequately. The grid origin allows the grid to be reestablished during remedial action and is correlated with the New Jersey state grid system. All data correspond to coordinates on the characterization grid. The grid with the east and north coordinates is shown on all figures included in Sections 4.6 and 5.0 of this report.

L. 4.1 FIELD RADIOLOGICAL CHARACTERIZATIGN

. This section provides a description of the instrumentation and methodologies used to obtain exterior surface and subsurface measurements during radiological characterization of this property.

4.1.1 Measurements Taken and Methods Used

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An initial walkover survey was performed using an unshielded gamma scintillation detector [5.0- by 5.0-cm (2- by 2-in.) thallium-activated sodium iodide probe) to identify areas of elevated radionuclide activity. Near-surface gamma measurements taken using a cone-shielded gamma scintillation detector were also used to determine areas of surface contamination. The shielded detector ensured that the majority of the radiation detected by the instrument originated from the ground directly beneath the unit. Shielding against lateral gamma flux, or shine, from nearby areas of contamination minimized potential sources of error in the measurements. The measurements were taken 30.4 cm (12 in.) above the ground at the intersections of

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3.0-m (lO-ft) grid lines. The shielded detector was calibrated at the Technical Measurements Center (TMC) in Grand Junction, Colorado, to provide a correlation of counts per minute (cpm) to pioocuries per gram (pCi/g). This calibration demonstrated that approximately 11,000 opm corresponds to the DOE guideline of 5 pCi/g plus local average background of 1 pCi/g for thorium-232 in surface soils (Ref. 9).

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A subsurface investigation was conducted to determine the depth to which the previously identified surface contamination extended and to locate subsurface contamination where there was no surface manifestation. The subsurface characterization consisted of drilling 11 boreholes (Figure 4-l), using either a 7.6-cm- (3-in.-) or 15.2-cm- (6-in.-) diameter auger bit, and gamma logging them. The boreholes were drilled to depths determined in the field by the radiological and geological support representatives.

. - The downhole gamma logging technique was used because the procedure can be accomplished in less time than collecting soil samples, and the need for analyzing these samples in a laboratory is eliminated.. A 5.0- by 5.0-cm (2- by 2-in.) sodium iodide gamma scintillation detector was used to

_- perform the downhole logging. The instrument was calibrated at TMC where it was determined that a count rate of approximately 40,000 cpm corresponds to the 15-pCi/g subsurface contamination guideline for thorium-232. This relationship has also been corroborated by results from previous characterizations where thorium-232 was found (Ref. 9).

Gamma radiation measurements were taken at 15.2~cm (6-in.) -. vertical intervals to determine the depth and concentration

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.-

.-

/b 0 CONTAMINATED BOREHOLE 0 UNCONTAMINATED BOREHOLE

6%' 1 (p26-R 1 1 1 1 p2271 j 1 1 HANCOCK STREET

N Win . . .--- I I, 1 I I

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I l ZOISR 0

I 2017R l GRASS 12016R

I . r

I 1 I II

N 1900 I x x 1 x

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I i I I I I I I I I I#“““~ Iii N 1750

r x

1 ,

s: .M

8 8 z E x

t.2 XJ

w w w w zr-r

FIGURE 4-l BOREHOLE LOCATIONS AT 100 HANCOCK STREET

17 MBW857.DGN -*

\ \

of the contamination. The gamma-logging data were reviewed to identify trends, whether or not concentrations exceeded the guidelines.

4.1.2 &mole Collection and Analvsfs

-

L

.

To identify surface areas where the level of contamination exceeded the DOE guideline of 5 pCi/g for thorium-232, areas with measurements of more #an 11,000 cpm were plotted. Using these data as well as data from previous surveys (Refs. 5, 6, 7, and F), the locations of biased surface soil samples were selected to better define the limits of contamination. Surface soil samples were taken at 11 locations (Figure 4-2) and analyzed for thorium-232, uranium-238, and radium-226. Each sample was dried, pulverized, and counted for 10 min using an intrinsic germanium detector housed in a lead counting cave lined with cadmium and copper. The pulse height distribution was sorted using a computer-based, multichannel analyzer. Radionuclide concentrations were determined by comparing the gamma spectrum of each sample with the spectrum of a certified counting standard for the radionuclide of interest.

Subsurface soil samples were collected from 11 locations (Figure 4-2) Using a 7.6-cm (3.0-in.) outside diameter (O.D.) split-spoon sampler mounted on a tripod or attached to a truck-mounted auger stem. The subsurface soil samples were analyzed for radium-226, uranium-238, and thorium-232 in the same manner as the surface soil samples. ,

4.2 BUILDING RADIOLOGICAL CHARACTERIZATION

After evaluating previous radiological survey data as well as data from this characterization, it was suspected that contamination might be present under the foundation of the

: 18

\’

- ^_. _-... _

_ .-

.-

-

.-

L.

.

_ .

-

A I I A HANCOCK STREET

I I

r x

1 I,

k2 s W Ir( I

FIGURE 4-2 SURFACE AND SUBSURFACE SOIL SAMPLING LOCATIONS AT 100 HANCOCK STREET

M3B’i¶E57.DCN

19

building. A radon measurement was obtained to verify the presence of contaminated material under the building and to estimate potential occupational exposures during future remedial actions.

An indoor radon measurement was made using the Tedlar bag method. Samples were collected by pumping air into a Tedlar bag at a rate of approximately 2 L/min. The air sample was transferred directly into a scintillation cell with an interior coating of zinc sulfide and an end window for viewing the scintillations. Analysis of the sample was simplified by a.lloving the radon decay products to build up over time. This method allowed all the radon decay products to come into secular equilibrium with the radon. The scintillation cell was placed in contact with a photomultiplier tube, and the scintillations were counted using standard nuclear counting instrumentation.

Indoor air samples were also collected to determine a WL for radon and thoron daughters. To measure radon daughters, an air sample was collected for exactly 5 min through a 0.45-micron membrane filter at a rate of 11 L/min for a total sample volume of 55 L. Alpha particle activity on the filter paper was counted 40 to 90 min after sampling. An alpha scintillation detector coupled to a count-rate meter or a digital scaler was used. Measurements for thoron daughters were made using the same method as for radon daughters with the exception of the time between collection of the air sample and counting of the alpha particle activity. In the case of thoron daughters, the sample was allowed to age for at least 5 h after sampling before alpha activity was counted. This elapsed time allowed radon daughters, which may have been present with the thoron daughters, to decay sufficiently so as not to interfere in calculating the WL for thoron daughters.

20

\\

L4

-

._

-

--

. . .

.-

. _

. . .

.

Exterior gamma exposure rate measurements were made at nine locations throughout the property grid s y s tem and at one location ins ide the office area of the building. To obtain these measurements, either a 5.0- by 5.0-cm (2- by 2-h.) thallium-ac tivated sodium iodide gamma s c intillation detector

designed to detect gamma radiation only or a pressurized ionization chamber (PIC) was used. Measurement locations are shown in F igure 4-3. The PIC ins trument has a response to gamma radiation that is proportional to exposure in roentgens. A conversion fac tor for gamma s c intillation to the PIC was established through a correlation of these two measurements at four locations in the v ic inity of the property. The unshielded gamma s c intillation detec tor readings were then used to estimate gamma exposure rates for

each location. These measurements were taken 1 m (3 ft) above the ground. The locations were determined to be representative of the entire property. Interior measurements are generally obtained w ith the gamma s c intillation ins trument rather than the PIC because of its smaller s ize and the desire to minimize the technic ian's time ins ide the building.

21

-

c

. _

.-

-~

-.

I 1 HANCOCK STREET

I I

N 1950

.I ,Ohh

N 1850

Ifl I III I I I

BLOCK BUILDING

s: 0 5: 0 0

M a z K z w w w w w

FIGURE 4-3 GAMMA EXPOSURE RATE MEASUREMENT LOCATIONS AT 100 HANCOCK STREET

nW3857.DCN 22

\ \

5.0 CHARACl'ERIZATION RESULTS

Radiological characterization results are presented in this section. The data included represent exterior surface and subsurface radiation measurements and interior radiation measurements.

5.1 FIELD RADIOLOGICAL CHARACTERIZATION

__

Near-surface gamma radiation measurements on the property ranged from 5,000 cpm to approximately 45,000 cpm. The average background level for this area is 5,000 cpm. A measurement of 11,000 cpm is approximately equal to the DOE guideline for thorium-232 of 5 pCi/g above background for surface soil contamination. Using this correlation, the near-surface gamma measurements were used to determine the extent of surface contamination and the basis for selecting the locations of soil samples. Areas of surface contamination are shown in Figure 5-l.

'-

Surface soil samples [depths from 0.0 to 15.2 cm (6.0 in.)] were taken at nine locations on the property and two locations in the street in front of the property (Figure 4-2). These samples were analyzed for thorium-232, Uranium-238, and radium-226. The concentrations in these samples ranged from 1.1 to 6.7 pCi/g for uranium-238, from 1.2 to 8.0 pCi/g for thorium-232, and from 0.6 to 1.9 pCi/g for radium-226. Analytical results for surface soils are provided in Table 5-l; these data showed,that concentrations of thorium-232 exceeded DOE guidelines (5 pCi/g plus background of 1 pCi/g for surface soils) with a maximum concentration of 8.0 pCi/g. Use of the "less than" (<) notation in reporting results indicates that the radionuclide was not present in concentrations #at are quantitative with the instruments and techniques used. The

23

-_

.-

.-

_

_-

.

. . .--- I I, I I I I. !-. L.. I

I I I II I II I 1 GRASS I II I II

I& STORY BRICK & CINDER --- BLOCK BUILDING

N 1800

, I

s 2 8 5: 3 z 8 5s x x w w Y w 1+-T

FIGURE 5-l AREAS OF SURFACE CONTAMINATION AT 100 HANCOCK STREET

24

"less than" value represents the lover bound of the quantitative capacity of the instrument and technique used. The "less than" value is based on various factors, including the volume, cize, and weight of the sample; the type.of detector used; the counting time: and the background count rate. The actual concentration of the radionuclide is less than the value indicated. In addition, since radioactive decay is a random process, a correlation between the rate of disintegration and a given radionuclide concentration cannot be precisely established. For this reason, the exact concentration of the radionuclide cannot be determined. As such, each value that can be quantitatively determined has an associated uncertainty term (+), which represents the amount by which the actual concentration can be expected to differ from the value given in the table. The uncertainty term has an associated confidence level of 95 percent.,

-- Thorium-232, the primary contaminant at the site, is the radionuclide most likely to exceed a specific DOE guideline in soil. Parameters for soil sample analysis were selected to ensure that the thorium-232 would be detected and measured at concentrations well below the lower guideline value of

-

_-

5 pCi/g in excess of background level. Radionuclides of the uranium series, specifically uranium-238 and radium-226, are also potential contaminants but at lower concentrations than thorium-232. Therefore, these radionuclides (considered secondary contaminants) would not be present in concentrations in excess of guidelines unless thorium-232 was also present in concentrations in excess of its guideline level. Parameters selected for the thorium-232 analyses also provide detection sensitivities for UraniUm-238 and radium-226 that demonstrate that concentrations of these radionuclides are below guidelines. However, because of the relatively low gamma photon abundance of uranium-238, many of the uranium-238 concentrations were below the detection

25

sensitivity of the analytical procedure; these concentrations are reported in the data tables as "less than" values. To obtain more sensitive readings for the uranium-238 radionuclide with these analytical methods, much longer instrument counting times would be required than were necessary for analysis of thorium-232, the primary contaminant.

Analytical results for subsurface soil samples are given in Table 5-1, and gamma logging data are given in Table 5-2. The results in Table 5-2 shoved a range from 7,000 cpm to 61,000 cpm. A'.measurement of 40,000 cpm is approximately equal to the DOE guideline for subsurface contamination of '15 pCi/g. Analyses of subsurface soil samples indicated uranium-238 concentrations ranging from 0.6 to 7.2 pCi/g, thorium-232 concentrations ranging from 0.6 to 5.4 pCi/g, and radium-226 concentrations ranging from 0.3 to 2.2 pCi/g.

-

On the basis of near-surface gamma radiation measurements, surface and subsurface soil sample analyses, and downhole gamma logging, contamination on this property is believed to consist primarily of subsurface contamination at depths ranging from 1.07 m (3.5 ft) to 2.74 m (9.0 ft). The areas of subsurface contamination are shown in Figure 5-2. The subsurface contamination appears to extend beneath the building as well as into the street in front of the property.

It is apparent from review of historical documentation ted., aerial photographs of the area, interviews with local residents, and previous radiological ourveys) that the subsurface contamination on this property lies along the former channel of Lodi Brook and its associated floodplain.

26

\\

_

.-

--

-

. .

--

--

FIGURE 5-2 AREAS OF SUBSURFACE CONTAMINATION AT 100 HANCOCK STREET

IOBU3857.DGN

27

-

The contamination on the property is similar to contamination found on a residential property and a commercial property in close proximity to it. It has been established that the Lodi Brook channel through these neighboring properties once occupied locations connecting to those where stream sediments were found at 100 Hancock Street. Thus, the elevated gamma readings shown on gamma logs from boreholes drilled on this property serve as further indication of the suspected mechanism of transport for radiological contamination (i.e., stream deposition from Lodi Brook).

The vertical and horizontal limits of contamination as determined by this characterization effort are being evaluated to determine the volume of contaminated material that will require remedial action. To develop this estimate, BNI will consider the location of the contamination, construction techniques, and safety procedures.

5.2 BUILDING RADIOLGGICAL CHARACTERIZATICN

Results of an indoor radon measurement using the Tedlar bag method indicated a concentration of 0.7 pCi/L. This measurement was substantially less than the applicable DOE guideline of 3.0 pCi/L above background (Ref. 10).

The result of a measurement for radon daughters was 0.001 WL. These results were substantially less than the applicable generic guideline detailed in the Code of Federal Regulations, 40 CFR 192 (Ref. lo), which states that an annual average (or equivalent) radon decay product concentration not exceed 0.02 WL.

28

-- The,result of a measurement for thoton daughters was 0.001 NL. The generic guideline is more restrictive for radon-222 (radon) than for radon-220 (thoron) according to the National Council on Radiological Protection [see NCRP Report No. 50 (Ref. ll), which was used as the guideline for thoron daughter measurements].

Exterior gamma radiation exposure rate measurements ranged

- from 5 to 41 PR/h, including background. These results can be found in Table 5-3. Assuming an employee spends 5 hours per week for 50 weeks per year (250 hours or 1 hour per day

- for 5 days per'week) outside the building, the average exterior exposure rate of 16 &R/h would lead to a yearly dose

- of 2 mrem above background (after subtracting average background of 9 &R/h; Ref. 12).

The indoor exposure rate measurement was 9 pR/h, including background (Table 5-3). The indoor exposure rate does not - exceed average background. For comparison, the DOE guideline for indoor exposure rate is 20 C.rR/h.

-

- Based on the above information, the exposure rates and doses at this property are within DOE guidelines. Further, it should be emphasized that natural background exposure rates

- vary widely across the United States and are often significantly higher than average background for this area.

29

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35

TABLE 5-2

Pa- 2 of 7

(continued)

Coordinatesa East

Depthb North t-1

Count Rate= (CPN

L..

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Borehole 2020R (continuedl.

2289 1704 2289 1704 2289 1704 2289 1704 2289

: ;;;;.

2289 2289 1704

Borehole 2019Rd

- 9.0 7000 9.5 7000

10.0 7000 10.5 6000 .ll.O 7000 11.5 8000 12.0 10000

2295 1794 0.5 2295 1794 1.0 2295 1794 1.5 2295 1794 2.0 2295 1794 2.5 2295 1794 3.0 2295 1794 3.5 2295 1794 4.0 2295 1794 4.5 2295 1794 5.0 2295 1794 5.5 2295 1794 6.0 2295 1794 6.5 2295 1794 7.0 2295 1794 7.5 2295 1794 8.0 2295 1794 8.5 2295 1794 9.0 2295 1794 9.5

Botehole 2QwP 2302 1855 0.5 7000 2302 1855 1.0 11000 2302 1855 1.5 13000 2302 1855 2.0 14000 2302 1855 2.5 15000

8000 12000 15000 15000 13000 13000 12000 12000 12000 11000 11000 11000 11000 11000 10000 10000 10000 10000 11000

- 37

\\

. TABLE 5-2

DOwNHoLe GAMMA LOGGING RESULTS

FOR 100 HANCOCK STREET

Paue 1 of 7

Coordtitesa East

Depthb North (it)

Count RateC (cpm)

2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993 2275 1993

Borehole 2020R

2289 1704 0.5 8000 2289 1704 1.0 12000 2289 1704 1.5 15000 2289 1704 2.0 15000 2289 1704 2.5 13000 2289 1704 3.0 13000 2289 1704 3.5 11000 2289 1704 4.0 10000 2289 . 1704 4.5 8000 2289 1704 5.0 10000 2289 1704 5.5 11000 2289 1704 6.0 11000 2289 1704 6.5 11000 2289 1704 7.0 10000 2289 1704 7.5 9000 2289 1704 8.0 8000 2289 1704 8.5 8000

1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0

5000 8000

10000 11000 11000 10000 10000 10000 10000 10000 10000 10000 11000 10000

9000 10000

36

-.-. (continued)

TABLE 5-2

P-e 3 of 7

C rdinatena East' North

Depthb (=I

Count Rate" (CPW

Borehole 2018R (continuedld

2302 1855 2302 1855 2302 1855 2302 1855 2302 1855 2302 1855 2302 1855

Borehole 2017Rd

3:: 18000 30000

4.0 27000 4.5 19000 5.0 14000 5.5 12000 6.0 10000

-,

-,

2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306 2306

1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921 1921

0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 8.5 9.0 9.5

10.0 10.5 11.0 11.5 12.0

14000 15000 15000 14000 15000 14000 14000 16000 18000 20000 20000 19000 32000 42000 37000 36000 61000 56000 21000 14000 11000 10000

9000 9000

38 -

.

L..

L..

. .

r/

r . . TABLE 5-2

L,

Pa- 4 of 7

(continued)

m East North

Depthb Count Rate= (ftl (cpm)

2377 1927 2377 1927 2377 1927 2377 1927 2377 2377 ._ y=;. 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927 2377 1927

Borehole 1227Rd

2402 1993 2402 1993 2402 1993 2402 1993 2402 1993 2402 1993 2402 1993 2402 1993 2402 1993 2402 1993 2402 1993

0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 8.5 9.0 9.5

10.0 10.5 11.0 11.5 12.0

12000 17000 14000 15000 14000 14000 14000 14000 14000 13000 18000 15000 32000 28000 35000 39000 33000 33000 29000 27000 17000 18000 15000 16000

0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0

2: 5.5

8000 10000 10000

9000 9000 9000 9000

11000 11000 11000 11000

39

.- TAELE 5-2

.-

Pa- 5 of 7

(continued)

Coordinatepa East

Depthb North t-1

Count Rate= (cpm)

Borehole 1227R lcontinuedld

2402 1993 6.0 9000 2402 - 1993 6.5 9000 2402 1993

3:: 9000

2402 1993 9000

Borehole-20158

--

/ .._

2453 2453 2453 2453 2453 2453 2453 2453 2453 2453 2453 2453 2453 2453 2453 2453

1931 1931 1931 1931 1931 1931 1931 1931 1931 1931 1931 1931 1931 1931 1931 1931

Borehole 2013R

2454 1780 2454 1780 2454 1780 2454 1780 2454 1780 2454 1780 2454 1780 2454 1780 2454 1780 2454 1780 2454 1780

0.5 1.0 1.5 2.0 2.5

3:: 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0

0.5

i:: 2.0 2.5 3.0 3.5 4.0 4.5

18000 22000 21000 20000 15000 14000 15000 20000 25000 29000 41000 35000 17000 12000 10000 10000

8000 .10000

9000 11000 11000

9000 9000

10000 7000 8000 8000

40

\\

-.._-._ ---_. __

c_

. .

--

i _

-_

TABLE 5-2

(continued)

Paa- 6 of 7

Coordinatesa East

Depthb North (ft)

Count Rate= (CPW

Borehole 2013R fcontinuea

2454 1780 2454 1780 2454 1780 2454 1780 2454 1780 2454 . 1780 2454 1780 2454 1780 2454 1780

Borehole 2012R

24 56 24 56 24 56 24 56 2456 2456 2456 2456 2456 2456 2456 2456 2456 2456 2456 2456 2456 2456 2456 2456

1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710 1710

6.0 6.5

$2 8.0 8.5 9.0 9.5

10.0

0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0

t-z 9:5

10.0

9000 8000 9000

10000 10000 10000

9000 8000 8000

10000 11000 11000 11000 10000 10000

9000 9000 8000 7000 8000 8000 8000 8000 8000 8000 9000

10000 10000 11000

41

TABLE 5-2

Paue 7 of 7

(continued)

C rdinatesa EasF" North

Depthb Count Rate= (ft) (cpm)

L_

-

-

. .-

Borehole 2014R

2456 1855 2456 1855 2456 1855 2456 1855 2456 ' 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855 2456 1855

0.5

i:: 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 8.0 8.5 9.0 9.5

10.0

11000 15000 16000 14000 12000 11000 10000 10000 10000 10000 10000

9000 9000 8000 7000 8000 9000

10000 10000 10000

aBorehple locations are shown in Figure 4-l.

bThe variations in depths of boreholes and corresponding results given in this table are based on the boreholes penetrating the contamination or the drill reaching refusal.

CInstrument used was 5.0- by 5.0-cm (2- by 2-in.) thallium-activated sodium iodide gamma scintillation detector.

dBottom of borehole collapsed.

42

.-

.-

TABLE 5-3

GAMMA RADIATION EXPOSURE RATES

FOR 100 HANCOCK STREET

Coordinates" Rateb East North WWh)

2280 1900 2300 1700 2300 1750 2320 1920 2350 1920 2430 1920 2455 1820 2470 1910 2480 1700

5 9 5

is 13

8 41 27

Interior of Building 9

aMeasurement locations are shown in Figure 4-3.

bMeasurements include background.

43

1.

2.

3.

4.

5.

6.

7.

8.

REFERENCES

U.S. Department of Energy. pescriotion of the Formerlv Ptilised Sites Remedial Action Proarm, ORO-777, Oak Ridge, Tenn., September 1980 (as modified by DOE in October 1983).

Argonne National Laboratory. Action DescriDtion Nemorandum. Interim Remedial Actions at MavwoodL New Jersey, Argonne, Ill., March 1987.

Argonne Nbtional Laboratory. Action DescriDtioq Memorandum. ProDosed 1984 Remedial Actions at Mavwood, New Jersey, Argonne, Ill., June 8, 1984.

Bechtel National, Inc. Post-Remedial Action ReDort for the Lodi Residential ProDerties, DOE/OR/20722-89, Oak Ridge, Tenn., August 1986.

NUS Corporation. Radiolouical Studv of Mavwood Chemical. Mavwood. New Jersey, November 1983.

EGCG Energy Measurements Group. An Aerial Radioloaic Survev of the Stevan Chemical Comvanv and Surroundinq Area. Mavwood. New Jersev, NRC-8109, Oak Ridge, Tenn., September 1981.

Oak Ridge National Laboratory. R-of& GaInma Scannina Activities in Lodi. New Jersey, ORNL/RASA-84/3, Oak Ridge, Tenn., October 1984.

Oak Ridge National Laboratory. Results of the Radioloaical Survev at 100 Hancock Street IIJo581, Lodi, New Jersey, ORHL/RASA-88/15, Oak Ridge, Term., March 1988.

44

'-

9. Therm0 Analytical/Eberline. -Technical Review of PUSRAP Instrument Calibrations by Comparison to TMC Calibration Pads”, Hay 1989.

10. U.S. Code of Federal Reoulw . 40 CPR 192, "Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings," Washington, D.C., July 1986.

11. National Council on Radiation Protection and Measurements. environmental Radiation Measuremente, NCRP Report No. SO, Washington, D.C., December 27, 1986.

i- 12. Levin, S. G., R. R. Stoms, E. Kuerze, and W. Huskisson.

aSummary of Natural Environmental Gamma Radiation Using a Calibrated Portable Scintillation Counter."

- Radioloaical H ealth Data ReDOI% 9:679-695 (1968).

45

APPENDIX A GEOLOGIC DRILL LOGS FOR 100 HANCOCK STREET

-

L

.~

_-

-

--

.-

.

.-

.~.

\

-

-.

L_

. . . .

c-

I-.

._

GEOLOGIC DRILL LOG OJECT 06 NO. HEEf ND. HOLE NO. ---- - .- _ -_--

5‘ TE f USRAP

fNAlES 14501-13q 1 OF 1 1 1226R

Haeiock St. (LODI) GLE fR(ll NW REARING

N 1,99- - - --- 3 L 2,275 -- . 9 ------

RILL M K E AND MCOEL RWRDEN rnr

ROEX (FT.) TOTAL DEPTI ..mm- v. a -- -a - -a #s _ _. -- - -.

i iE RECDVERY (FT./X) . ..I.*. I mu85kE m -37

E ROXESSAUPLESEL. TOP CRSING 0.5” 1 1u.u I

UJNO EL. 1 1u.u

6.6/69 5 Pr/EL. DRWND WIER EPWEL. TOP OF ROCK

SAMPLE KWER YIGHl/FALL (USING LEFT IN NDLE: DJA./ENGTN 1~066~~ BY: I /

s = SPLIT 1 = DENNISC+

SHELBY TUBE; 1 P = PITCHER; 0 = OTllERl Hancock St. (LODI)

1.

P -

1 izt J I

E

G - : -

T J?

LLEU

e

H

6

10

#SCRI.ptION RND CUSSIPfCAtION

0.D-D.9 ?t. Orovd, broken butit ~mwl.

~&%&ui!!i%%%!z!!~yb~~t and ochul grwrl; thin hym of o&onic rut. 4.044 Ft. Silt, mai&, my, soft,

\ d-p. I , I “‘(i&~i!! ~~$oo~~~~~gy:~

iron-oxid;mottling.

4.4-4.7 Ft. Piecea of mddi~h brown and dark preen silt mixed in.

4.4-6.0 Ft. Dy. rtii, crumbly.

L.O-lO.OFt. Damp. I

Bottom of borahoh at 10.0 Ft. Borehoh backfilled with ~poti, 12/S/87.

IOTES ON: @TER LEVELS, @,TER RETURN, IHRRfiCTER OP ‘RILLINQ, ETC. 3onholr advanced I-10 Ft. using 6.6 in 1.d. bOUOr-rkm

1.0-0.5 Ft. Not ampled. Rod bus.

:NMET nadr >SOO ‘pm with probe at 6 3. in l 10.0 Ft. goring.

dcntification and Iusification of oils by visual xcmimtion.

OLE NO.

1226R

‘.-

. . .

--.

.-~

,.

.-.

_-

.-

.__.

--

_-

-.-

i

jS 2.

DE iNNI9ON; P = PITCHER; 0 = OTHER1

2 + ie c $ i- B

b

b

ii

b

b

G ,i ; ” !! ;g 01 ‘d “1 cgz

r&Tgz

+T

15 17:20

-1 a -

z

E - ! ifti - 2

i

% 6

.’ ‘. .:, ‘. .:, ‘. ..‘, ‘. ,:, a

J. Lord . I

=smIPtfw - -SfFI~tIw wmR RETURN, CHARACTER dF

4.0 F’t. Bccomin& mom aandy with depth. 7.0 Ft. Unit bu ytiorish my (6 y/2) oilt. Much better 6”

cd to * unifmn

sorted; clcw~rr. Moret to rhxmtcd for the 1-t 6”. Grad- from rtiff to runny. Slightly cohcliw in the moist upper intwvaI.

“o~~~~~‘b*~~~~~dium- to coarse-grained sand. Subangular, poorly lorted with 20% silt. Adheaivr due to the moisture. No ahcsr dnngth. Mixed feldspar aad quartr miner&.

I~RIuINO, rrc.

Bomholr advanced O-12 Ft. using 12 in. o.d. hollow stem

ii%%0 ‘ally runplc sndgsmm P rearmed by TMA-Eberlin., Inc.

Bottom of bonholc at 12.0 Ft. Borehole ba&filled with clean spoils, o/2/88.

7.5 Ft. Groundwatrz r obrtrvcd.

1.0 Ft. Top of undisturbed roil.

Dacri tion and classi 2 cation of soils by visual rxamiaation.

100 Hancock St. (LODI) A-2

NOLE NO.

2020R J

-

L

.-

L.-

--

-._.

.-

I-

-._

. . _.

._

j_

-

‘-

\_

GEOLOGIC DRILL LOG RDJECT

SITE @OUlDlNAlES WCLE I

im m

m l7

37 LA1

p-6-l

n - -

-

-

- 1

;$i J d

-

! ii2 * 2

I SPCON; ST = SNELBY 1 ) - DENNISW; P I PITCHER; 0 * 07HERJ

6.

10

I

i

I

::. ;‘. ,:. ::. ::.

h

1 DESCRIPTION WD CLRSSIfI~T1~ WATER LEVELS,

Bonholr mivmcrd O-12 Ft. using 12 in. ~.;,-flow atem

--... ~.fwrm-iii-&timd Iii

.._. iatdiuin-pirnid mud @?i*%j. Probable FILL.

iunplcbmd I ~~k~~~~,“r,c. _ . . --__--

d Groundwater -L _--.- 2 -b 9.8 -d 4.9 Fk.vfqiqtgrc ia~naaiag. Some olive 111 iyi;;ru-- -

6.2 Ft. Top of undisturbed roil.

20.0-1l.a Ft. Increasing pluticity ud rntwmtion. Softer. Cow-Sr&rd aand.

ii.1 - 12.0 Ft. &gD (SW).

Modrmtr bmrn (SYIU/I) ‘ub”&~ucoB’- to very COVH-grained mnd. Adhestvr due to the moisture. No rhcar rtnngth. Mixed feldspar and quartz mincral&

Bottom of bonhola at 12.0 Ft. Borehole bnettihd with rpol, and top F+

uphdt, O /O/as.

Ducri tion and cluri ication of P soih by visual auninbtion.

l . 1.111, r--., --.:., -;~ J, b ut 110 thread. turcr curly wth ruk finger prarun.

ssnd ia rubrounded, medium- to come-grained, mixed minr~~Io~y. Id

1 ..-. - ..^ “WC MU. 2019R

\\

-

100 Hancock St. (LODI) A-3

-

\

‘,-

._’

\-

-

.-

L

.-

i-

--

.-

--

-

._

100 Hancock St. (LODI) I N 1,655 E 2,302 I Vertical 1 -s--w- SILL RkKE AND KX)EL RRURDEN RDU: (FT.) TOTAL DEPTH

EMPIRE SOILS CME 45B 14.0 14.0 CVNO EL. EPTNIEL. GRCUND MATER EPTWEL. TOP OF ROCK

7.5/ mm6 /

AMPLE IUIWER WCtIl/FALL SING LEFT IN IWE: DIA./LENGTH kOSDED II:

GEOLOGIC DRILL LOG OJECT HOLE NO.

FUSRAP 2018R ITE WINATES I~NGLE FRu4 H~UU~~E*~ING

- -- =DP ml; s 1 m = DENNISDN; P = PITCHER; 0 8 OTWER~

F

7$iT

m 17:17

-8-10 10

m - I

! iE! * 1

;:. ::. ::, :., ::, ::. I.‘, i

NOTES ON: DESCRIPTION W4O CLAsSIf~-TxOt’4 WRTER LEVELS,

WATER RETURN. HRRRCTER OF- RILLING, ETC.

ch I bf%ns~to cobble Borehole advanced

O-14 Ft. using 12 in.

0.8 - 4.9 Ft. giltr (FILL). o.d. hollow l rm

1.0-4.0(Y) Ft. Modemte brown (6YFt4/4) matrix rrth mixed colon snd organic tkkr. Compressad, cohaivr, dry. Crumblw wily. No thrud. To of undiiturbed 4.0-4.9 Ft. Becoming mixed Moduatr brow 10 ip not =w+d.

, and dark 6vbenish my (SGW).

icnues with depth.

7.6 Ft. Groundrate: observed.

6.0-6.0 Ft. Lifiht.brown (SYR6/4). ModcmtrI co my. Sat.urated at 6 Ft. for

;$&kv~t~;:&;!~bIe I I

a.0 - 14.0 Ft -~~:~~Lti~:~~rn- to . brown f10

coarse-‘grained’, tied mincralblgy of feldnpu and quartz. Moist, adhesive, no

j ahau stnn deposition gt&uetures rem. Moisture

h. No orgurics, no

deuruinn snd stiffness iaurrinn with I \ depth. -

Bottom of bonhole at 14.0 Ft. Bo~bs~v:o~llF+$to 10.0 Ft. depth upon Borehole backfilled’rith 3-Y ut from 10 to s

ft., with rpoilr to 6 in es, 8nd with new uphslt in the top 6 incha, O /l/S&

.E 100 Hancock St. (LODI) 2018R

A-4 4 \

Da& tion and clawi x*tion of P wib by virual uuninrtion.

;-

L-

i-

\-

-.

--..

.~.

_~

_-

--

.~-

---

.-

‘-

,o-)o FXF 11

Fgzgr

,8 . .

r-(-1

;)-9-

D . .

-

I h sz ST ribi & Ii L. LIL

! isi 1

311; ST = SHELBY TU8ET ENNIBON; P = PITCNER; 0 = OTHER

IE

:LEU a

5.

10.

: 2

1

.’ ‘.., 7 : ..‘, ::. ‘. .:, ‘. ..’

I NOTES ON: DESCRlPTtON &ND #ASSIFIC~,fION WATER LEVELS.

2 inchm of of limestone cobble

1.0 - 0.1 5%. w (FILL).

‘UATER iET%i; ~~~RIxTER of= DRILLINE, ETC.

Bonhoh danced O-14 Ft.urin612in. o.d. hollow stem wpn.

1.0.Lo(?) Ft. Duhy browI (SYR2[2) twtrix rith inixed colon and organrc flecks. Compressed, cohaive, dry. Crumblcl l ily. No thread.

intrrd. 0.0-9.1 Ft. Sane but SATURATED.

I ’ I Bottom of borehole at 14.0 Ft. Bonholr backfilled with

r ut from 14 to 8

ft., with npoili to 6 iu es, and with new uphdt in thr top 6 inelm, Q/1/88.

-

100 Hancock St. (LODI) A-5

:z$:$nu1,: oil) by viwal ram instion.

I_

.__-

‘-

.-

_

_

&2!! Ql

P 9 0% pe 6-(r-1

FGi m

1-2 -.

m

15 n--52

9-25 0-29

ST - SHELBY YIJBE; iNNlsoY; P = PITCNER; 0. OTHER

-

100 Hancock St. (LODI) A-6

JTES ON: 9TER LEVELS, 9TER RETURN, 4RRRCTER OF PIUINP, ETC.

onh& advanced .14 Ft. using 12 in. d. hollow atom

L.5 Ft. Top of rdisturbed roil.

.O Ft. Groundware! brtned.

Ilcvated gamma-log t 8-11 ft. interval.

kcription and luaitication of oib by visual xamination.

OLE NO.

2016R

\ -

,_ . .

i-

--

L _

. .-

. -_

-

L -

. ~ -

.-

\

-

I -21-:

Ty

F

fi

iE i 26.26

= S P L IT m m ; = D E N N I E O W ; P * P IT

L c1

- n x g l i J C

-

E -

e ’ i% ! - I

- = S H ‘C A E R ; 0 t O T H E R

N C

E L E U .

-

D . H a m i s h

D E S C R I P T I O N R N D C L A S S IFICATIDN

0.0-0.8 ?t. S IJty ~rsvd, b roken basal t #wvcl .

D.8.2.0 Ft. G m veUy silt, dark ndd i i h b r o w n ( 5 Y R .3 sands tom a n d

S ) , g rave l u Brunswick basalt , m e d i u m stiff.

\ ;& i & S Ft. G rawl ly a S lt, m y (lO Y R 6 /1 ) ,

I

Bot tom o f b o r e h o l r at 1 0 .0 ft. B o r e h o l e backf i l led wi th spoi la , 1 2 /B /8 7 .

H a n cock S t. ( LO D I) A - 7 \’

3 T E S O N : R T E R L E V E L S , A T E R RETURN. H A R R C T E R O F - RILLINQ, ETC. o n h o l r d a n c e d - 1 0 Ft. r u i ng 6 .5 in .d . hd lox -s tem r i innpt 0.0-0.5 FI

m p ld a n d u n m r - l o g l d by ‘M A - E b & Inc .O-4 .0 Ft. S & p lc’ r t rn auge r t ight&.

INMET rwds 8 0 p t m o u th o f 4.0 w a 0.0 Ft. d e e p h o l e .

3 c a tifiu tio a a n d IvriI iut ion o f B U S by v isual x a m i n a tio n .

IO L E N O .

1 2 2 7 R

GEOLOGIC DRliL LOG POJECT HOLE NO.

FUSRAP 2015R fr1re lcoGftDrmAras NGLE FROl IICWIGEARIUG

‘i-

._

_

‘.-

-

.-

‘-_

_d

‘-

-

.

..-

-

x-

S-L

-

100 Hmcock St. (LODI) I N 1,931 E 2,453 I Vertical 1 -s--e- RILL WKE UID )IQ)EL RRURDEY K (FT.) TOTAL DEPTI

EMPIRE SOILS CME 45B 3.5 8.0 CWE RECDVERY (flJX) OlJND EL.

P:n’EL. - m ’ER EPWEL. TOP OF ROCK

/ RMPLE KANtER UEIGWT/FALL SING LEFT IN IIDLE: DIA./LRYGTH iLDCGED BY:

Ii ” L/

1 I/ k

D

62

rf

A2 J’r \ I’

!I iUl ui 3 ’ ‘d *I

‘-to’:

!E MOTES ON: URl-lZR LEVELS, YRTER RETURN, MFaRRCTER OF DRILLINO, ETC.

Borehole sdvmcad O-6 Ft. using 2.0 in. c.d. I

P lit-spoon

ramp cr. Radrolo ‘ully

6 %&&he Inc. No pmm-log: After 2nd spoon with no recovery, high pp lrvclt Qtl OVA (>lOOO) md l S in. chunk o! concrete in thr qmon’r mouth, it appeared that. ston drain had ken brewzhcd at 3.6 It: However, o%CwatlOn to 4.6 ft. proved no conduit WY present.

-

NO SAMPLES from S.6 Ft. to bottom of

-liis%---- Bonholr and acwdion backSlIed ritb spoti

011 O/Y~.

roils by visual examination.

E HOLE UO.

2015R 100 Hancock St. (LODE) * DEWSON; P = PITCHER; 0 = OTHER1

A-8 \ \

_

1-

L

L.

‘-.~

.-

‘-

I~_

‘.-

--

.~

L-.

-~

.-~

m: $1 = SHELBY TU8E: 1’ iWNISOU; P = PITCHER; 0 s OTHER1

2 ‘I

I. I

ii 3 3 Iv

1 c Yl

I ;

I 2.t

n

n

I.

P -

a ljnc J c -

I L :‘: 31 - 0% md IF m

- E

DESCRIPTXON rug) CLASSIFIWTION ;::: ,“:t,, e --.. __ RTER RETURN,

Bonholt advanced O-10 Ft. uring 12 in. ad. bollor stem um*n.

1 (40%). h&liiiFIU.

6.0 Ft. Toe of

6.0 - 10.0 Ft. Not runpled but wagered to. I

depth of 10.0 ft. Auger ilight ramplu suggut aand to 10 Ft.

Bottom of borehole at 10 Ft Borchole backfilled with BP&, D/28/88.

EzEzi%n~!d maila by vimal orunin*tion.

100 Hancock St. (LODI) A-9

I 2013R \’

\--’

‘-

--

L

i

-

L

.-

L

L

-

.--

_-

-

B I Ii 8

‘ii c b

!a

ca

e i ’ ia a/ ;g 8i PSB El ( in5 n-20

z=2 -

7

- YT

I

- s = SPLIT sPooN; I t SHELB = OEYWBON; P = PITCHER; 0

:. .,

7 IER

I igfi J d

- ! iE ’ r - 1

c : i

5.

10

3

E 5 3E ,’ . ::.. :: . . .:, ‘_ ,:, ::

$ ‘. C’, : ,.‘, . . .:, ‘. ..‘, i

J. Lord I

OBSCRIPTION W4C ELllSSIPICATION

6.0 - 10.0 Ft. Not sampled put myred to a \ ;i$$&&tt-&%$i?it t?ft. and /

Bottom of bonhoh at 10 ft. Bonholr backfIled with spoils, 9/28/W.

100 Hancock St. (LODI) A-10

NOTES ON: IWATER LEVELS, ~WRTER RETURN, CHRRCICTER OF pRILLING, ETC.

Eonhole advanced O-10 Ft. using 12 in. o.d. hollow .tcm Wm.

beti tion and lurifipcation of $&b,gp

DLE NO.

2012R

i-

-

h._

.-

-

I.-.

\-

i.

‘.

GEOLOGIC DRILL LOG ROJECT HOLE NO.

FUSRAP 2014R i lTE plJRDIRATES kvGLE fRU4 KIRI7$EARlNG

100 Hancock St. (LODI) I N 1,855 E 2,456 I Vertical I -w---- RJLL M U Z RI0 )(ODEL IZE RBLIROEN ROCK (FT.) TOTAL DEFT)

EMPIRE SOILS CME 45B 12” 10.0 10.0 U.JND EL. Ps”~;L.&aJ~D WTER EPWEL. TOP OF ROCK

. / /

MPLE IUMER UIGHT/fML @SING LEFT IN H&E: DJA./,&,,GT,, jlocca, ‘y:

Ls 9-io

- SHELBY TUBE; * OENNIEOW; P = PITCHER; 0 8 OTHER

2%

LIEU.

.E 100 Hancock St. (LODI)

A-11 ’ \

I J. Lord

oEscR1PT1cN RN0 cLasx~xcaTIoN

2..gt Irrc~dng stiftnar sad day 1

1 6.0-‘I.0 Ft. Increasing moimtun; deemvim finea. Stiffer. dmser.

Bottom of bonhole ot 10 ft. Bomholr bacLZilled with rpoila, g/28/88.

‘Xl3 ON: ,TER LWELS, TER ReTURN, ARACTBR OF ‘IUINQ, NC.

mholr advanced 10 Ft. using 12 in. I. bollox rtrm gen.

rdioio ‘cJlr mplr % to 8 and 7g~~p;~gO c.

;~F&d~mundwwl

IFt. Topof #disturbed soil.

ma-lo w&k rding of I 6,308 cpr 15’ deep.

ucri tion and um xrtion of 2 ,ilr by visual c8min~tion.

ILE NO.

2014R