site characterization plan - semspub.epa.gov · safety light corporation site characterization plan...

SDMSDocID 2081136

CHARACTERIZATION PLAN

SAFETY LIGHT CORPORATION SITE

BLOOMSBURG, PENNSYLVANIA

Chem-Nuclear Systems, Inc.140 Stoneridge DriveColumbia, SC 29210

December, 1991

AR100084

SAFETY LIGHT CORPORATION SITECHARACTERIZATION PLAN

TABLE OF CONTENTSSection Pace

1.0 GENERAL 1

1.1 INTRODUCTION 11.2 PURPOSE AND SCOPE 2

2.0 BACKGROUND INFORMATION 3

2.1 DESCRIPTION OF STUDY AREA 32.2 DESCRIPTION OF PRESENT ACTIVITIES 42.3 DESCRIPTION OF STUDY AREA HISTORY " 52.4 HISTORY OF WASTE HANDLING PRACTICES 6

2.4.1 SOLID WASTE MANAGEMENT 62.4.2 LIQUID WASTE MANAGEMENT 7

2.5 DESCRIPTION OF CHARACTERIZATION SITES 82.5.1 NUCLEAR BUILDING 82.5.2 GARAGE . 82.5.3 CONTAMINATED SOIL AREA IN FRONT OF ABOVE

GROUND SILO 112.5.4 METAL SILO ABOVE GROUND 112.5.5 SOLID WASTE BUILDING 112.5.6 OLD HOUSE 112.5.7 LIQUID WASTE BUILDING 122.5.8 8' x 8' BUILDING 122.5.9 UTILITY BUILDING 122.5.10 RADIUM VAULT 132.5.11 MACHINE SHOP 132.5.12 CONTAMINATED SOIL AREA NORTH OF MACHINE

SHOP 132.5.13 CONTAMINATED SOIL AREAS BETWEEN

ABANDONED CANAL AND RIVER 132.5.14 UNDERGROUND SILOS 142.5.15 EAST LAGOON 142.5.16 CARPENTER SHOP 152.5.17 WELL HOUSE 152.5.18 CESIUM ION EXCHANGE HUT 152.5.19 CONTAMINATED SOIL AREA UNDER LOADING DOCK 152.5.20 CEMENT TROUGH/SEWER GRATES BEHIND MAIN

BUILDING 162.5.21 HAND APPLICATION AREA SECOND FLOOR OF

MAIN BUILDING 162.5.22 MAIN BUILDING FIRST FLOOR 16

- i - AR100085


TABLE OF CONTENTS(Continued)

Section Page

2.5.23 SIDEWALK AREAS 192.5.24 PERSONNEL OFFICE BUILDING 192.5.25 EAST PLANT DUMP 202.5.26 PIPE SHOP 202.5.27 WEST LAGOON 202.5.28 WEST PLANT DUMP 212.5.29 ETCHING BUILDING .' 212.5.30 DRAIN LINES 242.5.31 CONTAMINATED SOIL AREA ADJACENT TO OLD

BERWICK 242.5.32 CONTAMINATED SOIL A R E A FROM

VANCE/WALTON PROPERTY 242.5.33 CONTAMINATED SOIL AREA NORTH OF LACQUER

STORAGE BUILDING 252.5.34 ABANDONED CANAL 252.5.35 CONTAMINATED SOIL AREA SOUTH OF RADIUM

VAULT 262.5.36 CONTAMINATED SOIL AREA EAST OF THE 8' X 8'

BUILDING 272.6 SUMMARY OF PREVIOUS INVESTIGATIONS AND

CHARACTERIZATIONS 27

3.0 CHARACTERIZATION METHODOLOGIES 32

3.1 SURFACE GEOPHYSICAL SURVEYS 323.1.1 PURPOSE 323.1.2 DESCRIPTION OF EQUIPMENT 333.1.3 OPERATION OF EQUIPMENT 353.1.4 LIMITATIONS 353.1.5 DATA MANAGEMENT 35

3.2 RADIOLOGICAL SURVEYS 353.2.1 PURPOSE 353.2.2 DESCRIPTION OF EQUIPMENT 363.2.3 OPERATION OR EQUIPMENT 363.2.4 LIMITATIONS 393.2.5 DATA MANAGEMENT 40

3.3 SURFACE SOIL SAMPLING 403.3.1 PURPOSE 40

AR100086



Section Page

3.3.2 DESCRIPTION OF EQUIPMENT 403.3.3 OPERATION OF EQUIPMENT 403.3.4 LIMITATIONS 413.3.5 DATA MANAGEMENT 41

3.4 DRILLING AND SUBSURFACE SOIL SAMPLING 423.4.1 PURPOSE 423.4.2 DESCRIPTION OF EQUIPMENT . . . ." 423.4.3 OPERATION OF EQUIPMENT 433.4.4 LIMITATIONS 443.4.5 DATA MANAGEMENT 45

3.5 MONITORING WELL INSTALLATION 453.5.1 PURPOSE 453.5.2 DESCRIPTION OF EQUIPMENT 463.5.3 OPERATION OF EQUIPMENT 473.5.4 LIMITATIONS 483.5.5 DATA MANAGEMENT 48

3.6 TEST TRENCH EXCAVATIONS AND SAMPLING 493.6.1 PURPOSE 493.6.2 DESCRIPTION OF EQUIPMENT 493.6.3 OPERATION OF EQUIPMENT 493.6.4 LIMITATIONS 513.6.5 DATA MANAGEMENT 51

3.7 GROUNDWATER SAMPLING 513.7.1 PURPOSE 513.7.2 DESCRIPTION OF EQUIPMENT 523.7.3 OPERATION OF EQUIPMENT 523.7.4 LIMITATIONS 533.7.5 DATA MANAGEMENT 54

3.8 SURFACE WATER SAMPLING 543.8.1 PURPOSE 543.8.2 DESCRIPTION OF EQUIPMENT 543.8.3 OPERATION OF EQUIPMENT 553.8.4 LIMITATIONS 563.8.5 DATA MANAGEMENT 56

3.9 CONCRETE/ASPHALT CORING AND SOIL SAMPLING 563.9.1 PURPOSE 563.9.2 DESCRIPTION OF EQUIPMENT 573.9.3 OPERATION OF EQUIPMENT 57

- in - AR100087



Section Page

3.9.4 LIMITATIONS 573.9.5 DATA MANAGEMENT 57

4.0 PRELIMINARY ACTIVITIES 58- ...»

4.1 LICENSING 584.2 STAGING AREA/FIELD OFFICE " 584.3 STUDY AREA SURVEY 594.4 ACCESS LOGISTICS 59

5.0 LABORATORY ANALYTICAL PARAMETERS 59

5.1 RADIOLOGICAL ANALYSES 605.1.1 • RADIOLOGICAL ANALYSES PARAMETERS 605.1.2 GROUNDWATER AND SURFACE WATER

ANALYSES 615.1.3 SURFACE SOIL AND SUBSURFACE SOIL

ANALYSES 625.2 HAZARDOUS CONSTITUENT ANALYSES 66

5.2.1 HAZARDOUS CONSTITUENT ANALYSESPARAMETERS 66

5.2.2 GROUNDWATER AND SURFACE WATERANALYSES . /. 66

5.2.3 SURFACE SOIL AND SUBSURFACE SOILANALYSES 69

6.0 SITE SPECIFIC CHARACTERIZATION PLANS 77

6.1 SURFACE GEOPHYSICAL SURVEYS 776.2 RADIOLOGICAL SURVEYS 78

6.2.1 GROUND SURVEYS 786.2.2 BUILDING SURVEYS 796.2.3 BOREHOLE SURVEYS 806.2.4 TEST TRENCH SURVEYS 80

6.3 SOIL SAMPLING 816.3.1 GRID SURFACE SOIL SAMPLING 826.3.2 ABANDONED CANAL 836.3.3 EAST LAGOON 84

- iv -AR100088



Section Page

6.3.4 WEST LAGOON 846.3.5 EAST AND WEST PLANT DUMPS 856.3.6 LOCALIZED CONTAMINATED SOIL AREAS 866.3.7 UNDERGROUND SILOS 876.3.8 CONTAMINATED SOIL AREAS ADJACENT TO OLD

BERWICK 886.3.9 PERSONNEL OFFICE BUILDING 7 896.3.10 PIPE SHOP 906.3.11 CONTAMINATED SOIL AREA NORTH OF LACQUER

STORAGE BUILDING . 906.3.12 LIQUID WASTE BUILDING 916.3.13 OLD HOUSE 926.3.14 DRAIN LINES (DRAINAGE DITCH FROM EAST

PLANT DUMP TO SUSQUEHANNA RIVER) 926.3.15 CONTAMINATED SOIL AREAS BETWEEN

ABANDONED CANAL AND RIVER 936.3.16 SIDEWALK AREAS 93

6.4 TEST TRENCH EXCAVATIONS AND SAMPLING 946.4.1 ABANDONED CANAL 946.4.2 EAST AND WEST PLANT DUMPS 956.4.3 UNDERGROUND SILOS 95

6.5 GROUNDWATER SAMPLING 966.6 SURFACE WATER SAMPLING 97

6.6.1 EAST LAGOON 986.6.2 WEST LAGOON 98

7.0 QUALITY ASSURANCE/QUALITY CONTROL 113

7.1 BASELINE MEASUREMENTS 1137.2 EQUIPMENT CALIBRATION 1147.3 QUALITY CONTROL SAMPLES 114

7.3.1 TRIP BLANKS 1147.3.2 FIELD BLANKS 1147.3.3 FIELD DUPLICATES 115

7.4 SAMPLE COLLECTION 1157.5 CHAIN-OF-CUSTODY 1177.6 EQUIPMENT DECONTAMINATION 1177.7 MANAGEMENT OF CHARACTERIZATION RESIDUES 118

. v - AR100089



Section Page

8.0 HEALTH AND SAFETY PROCEDURES 120

9.0 CHARACTERIZATION DATA EVALUATION 122

10.0 CHARACTERIZATION PLAN IMPLEMENTATION AND COST 123

11.0 REFERENCES f 131

- vi -AR100090


LIST OF FIGURES

Figure 1 Study Area Location Map

Figure 2 Location Map For Surface Geophysics

Figure 3 Location Map For Radiological Ground Survey and SurficialSoil Sampling

Figure 4 Location Map For Surface Soil Sampling and Deep SoilSampling

Figure5 Locat ion Map For Groundwater Sampling,Boreholes/Subsurface Soil Sampling, and ConcreteCoring/Soil Sampling

Figure 6 Location Map For Test Trench Excavations and SurfaceWater Sampling

- vn - AR100091


LIST OF TABLES

Table 2.1 - Characterization Sites Suspected Contaminants 9

Table 2.2 - Suspected Construction Details of Underground Silos 17

Table 5.1 - US Radium Corporation and Safety Light CorporationLicensed Radioisotope Amounts 63

Table 5.2 - Radiological Laboratory Analytical Methods for Water 64

Table 5.3 - Radiological Laboratory Analytical Methods for Soil 65

Table 5.4 - Hazardous Constituent Laboratory Analytical Methods for Water . 68

Table 5.5 - Limits of Quantification for Semi-Volatile Organics 70

Table 5.6 - Limits of Quantification for Volatile Organics 73

Table 5.7 - Hazardous Constituent Laboratory Analytical Methods for Soil ... 75

Table 6.1 - Laboratory Parameter Matrix for Surface Soil Sampleswithin Grid Blocks 99

Table 6.2 - Laboratory Parameter Matrix for Surface Soil Samples 101

Table 6.3 - Laboratory Parameter Matrix for Composite Soil Samples fromTest Trenches 105

Table 6.4 - Laboratory Parameter Matrix for Deep Subsurface Soil Samples . . 106

Table 6.5 - Laboratory Parameter Matrix for Borehole Soil Samples 108

Table 6.6 - Laboratory Parameter Matrix for Soil Samples belowConcrete Cores 110

Table 6.7 - Summary of Soil Samples for Analyses 111

Table 6.8 - Monitoring Wells Scheduled for Groundwater Sampling 112

- VIM - AR100092


LIST OF ACRONYMS

ALARA As Low As Reasonably AchievableASTM American Society of Testing MaterialsCNSI Chem-Nuclear Systems, Inc.EM ElectromagneticsEPA Environmental Protection AgencyGM Geiger MuellerGPR Ground Penetrating RadarHASP Health and Safety Planm MeterNal Sodium IodideNPDES National Pollutant Discharge Elimination SystemNRC Nuclear Regulatory CommissionORAL) Oak Ridge Associated UniversitiesPVC Polyvinyl ChlorideRCS Radiation Control SupervisorRMC Radiation Management CorporationSLC Safety Light CorporationTCLP Toxicity Characteristic Leaching ProcedureUSR United States RadiumUSRC United States Radium Corporation

- ix - AR100093

1.0 GENERAL

1.1 INTRODUCTION

The study area is owned and operated by the Safety Light Corporation

(SLC) to manufacture radioactive (tritium) products (ie, self illuminating

light sources, etc.) under a Nuclear Regulatory Commission (NRC) License,

No. 37-00030-08, and is located east of the city of Bloomsburg,

Pennsylvania. Both United States Radium (USR) Metals, Inc. and

Multimetals Products Corporation lease portions of the study area to

manufacture nonradioactive products. The majority of the study area

including grounds and structures were, in the past, us"ed for manufacturing

radioactive products or have the potential to contain radioactive

contamination from past production/disposal activities. Therefore, the

study area includes all portions of the SLC property (see Figure 1).

SLC production areas lie within the radiological restricted area and are

enclosed by a security fence. SLC also owns the property southeast of the

study area adjacent to the Susquehanna River hereafter referred to as the

Vance /Walton property.

Operations which took place in the late 1940's, 1950's and 1960's under

previous owners involved the use of Carbon-14 (UC), lron-55 (55Fe),

Cobolt-60 ("'Co), Strontium-90 (^Sr), Americium-241 (241Am),

Cesium-137 (137Cs), Radium-226 (22eRa), and other radionuclides (Berger,

1982). Although some attempts at decontamination of selected parts of

this study area were made in the 1970's, residual contamination, due to

past practices, remain. Monitoring data shows that soils beneath the

study area are contaminated with 22eRa, Tritium (3H), Sr, and 137Cs and

shallow groundwaters are contaminated with 3H and "Sr (NRC, 1988 and

CNSI, 1990).

- 1 -AR100094

Soil and groundwater contamination appear to have been caused by

disposal of radioactive waste and effluents. Site operators have discarded

both radioactive and chemical wastes at the study area. The site operators

have made numerous changes to the waste disposal and operation

practices in response to directions from regulatory agencies.

Attempts at mitigating site contamination were made by US Radium

Corporation (USRC), a previous owner of the study area, however, this

program was not completed. Therefore, a considerable section of the

study area remains contaminated with both radiological and hazardous

constituents.

1.2 PURPOSE AND SCOPE

This Characterization Plan has been developed in response to SLC's and

USR's request in response to the NRC's regulatory directives. The "Order

Modifying Licenses (effective immediately) and Demand for Information"

also referred to as the March 1989 Order, instructs the licensee to:

"describe in detail how a complete radiological and

geohydrological survey of all facilities and the surrounding surface

and subsurface soil and groundwater will be conducted in order

to fully determine the radionuclide concentrations and their lateral

and depth profiles, as well as their movement in the groundwater

and soil. The surveys shall be sufficient to develop a complete

plan for decontamination/removal operations necessary to permit

unrestricted access to site. The plan shall include, but not be

limited to, provisions to address the issues contained in the NRC

Environmental Evaluation of the Safety Light Corporation Site,

Bloomsburg, Pennsylvania (NRC-88). Particular attention shall be

given to identifying areas of the site that should be given priority

in the site decontamination activities" (NRC, 1989).

- 2 - AR100095

This Characterization Plan addresses characterization of surface and

subsurface soils, ground water, surface water, and study area structures.

In addition, this plan incorporates relevant aspects of the "NRC Staff's

Response to Licensing Board's Questions Expressed During Conference of

April 19, 1991."

The objective of this Characterization Plan is to provide an orderly cost-

effective and technically sound characterization of the study area, so when

completed, remediation technologies and costs can be developed for

specific areas within the study area, or combined as a whole. Then

site-specific remediation activities can be initiated, with the approval of

SLC, USR Industries, and the NRC.

2.0 BACKGROUND INFORMATION

2.1 DESCRIPTION OF STUDY AREA

The study area, contains approximately 10 acres (see Figure 1). Of this

area, SLC occupies approximately 2 acres. Portions of the remaining area

are leased to USR Metals, Inc. and Multimetals Products Corporation. The

study area lies within the South Central Township in Columbia County,

approximately 6 miles east of Bloomsburg, Pennsylvania. The study area

is bound on the north by Old Berwick Road (previously Route 11) and on

the south by the Susquehanna River. The Vance/Walton property located

along the southeast corner of the study area is owned by SLC. Other

residential tracts of land are adjacent to the east and west boundaries of

the study area.

Of the three companies located on the study area, only SLC currently uses

radioactive materials (3H) in their production activities. USR Metals, Inc.

and Multimetals Products Corporation do not use radioactive materials in

their production activities, however the areas leased and occupied by both

- 3 -AR100096

companies, was at one time associated with the production of radioactive

products and the use of radioactive materials. Therefore, the entire 10

acres are included in the study area. In the event, during characterization

activities, preliminary data indicates the need to conduct expanded

characterization activities in areas outside the study area, then an

amendment to this plan will be developed including scope-of-work,

permission for access, and costs.

2.2 DESCRIPTION OF PRESENT ACTIVITIES

SLC manufactures and distributes a variety of products which use 3H. The

principal products include self-luminous safety devices for use in

commercial/military aircraft, commercial buildings, and the marking of

aircraft and helicopter landing areas; research and development operations

for military and industrial applications; titanium tritide-coated rods and pins

for use in military and industrial type electron tubes; and 3H targets for use

in neutron generating devices. All production, handling, and storage

activities are located within a fenced restricted area.

USR Metals, Inc. leases areas within the study area, and conducts non-

radioactive operations involving the manufacture of dials, nameplates, and

other specialty products used in a variety of military and industrial

applications.

Multimetals Products Corporation leases areas within the study area, and

is involved in non-radioactive operations including anodizing of aluminum

products, and application of specialty protective films to the surfaces of

various metal items.

- 4 - AR100097

2.3 DESCRIPTION OF STUDY AREA HISTORY

During World War II and prior to occupation by USRC, the study area was

used to manufacture wooden toys (NRC, 1988). Radioactive operations

began at the plant site in 1948-49, with the relocation of USRC's radium

operations from Brooklyn to the Bloomsburg site. The radioisotopes in use

at that time were primarily 226Ra, and minor amounts of Polonium-210

(210Po). During the early 1950's, the expansion of USRC's radioactive

products included civil defense check sources and radiation sources

utilizing 137Cs in large quantities. Project F in the same time period resulted

in the production of approximately 500,000 deck markers for the U.S.

Navy involving an extensive ^Sr production line. 226Ra was being used

during this same time period primarily for clock and watch dials and hands;

however, radium rope and high level neutron and radiation therapy sources

were also being manufactured.

When other radioisotopes became available, at a later time period, the

research and development group carried out development work with

approximately 20 different radioisotopes. Although most radioisotopes

were handled only in small quantities, several became major sources of

revenue for the company. Tritium, 14C, and Thallium-204 (204TI), were

used for light sources; Nickel-63 (MNi) and 3H were developed for low-level

ionization sources; Krypton-85 (8sKr) was utilized, for light sources,

radiation sources, and for beta sources. In the early 60's work began with

Americium-241 (241Am), a replacement for 228Ra, in certain applications.

In 1968, USRC decided to discontinue all operations with 22eRa. In 1969,

all radioisotope business, except the 3H business, was sold. At this time,

the Nuclear Building, was erected to house the 3H production operation.

From this time on (July, 1969) the only radioisotope handled in production

has been 3H and all radioactive operations have been carried out in the

Nuclear Building (USRC, date unknown).

- 5 -AR100098

Throughout the site operational history various solvents and other chemical

agents were used to support operations including ethylene glycol, acetone,

and toluene.

2.4 HISTORY OF WASTE HANDLING PRACTICES

Throughout the-history of the~study area, during the periodfrom 1948 to

date7waste pfoductsrincluding solid and liquid waste, have been disposed

6Tby~various~means~ Although there does not appear to be any detailed

documentation concerning waste management practices, a comprehensive

review of available records does reveal a general understanding related to

how thes~e"Waste forms were handled.~\

2.4.1 SOLID WASTE MANAGEMENT

There is a lack of documentation concerning solid waste

management during the period from 1948 to 1950. There is)

howeverTlpeculation'that trTe"West Plant Dump was used cfiirihg

thisl>eriqd. cA^portioTTartheicanaJ was used to dispose of 226Ra

cContaminatedTJuct work earlyjn the:study:aTea:rTist6ry\^The Pipe

Shop was constructed over this filled portion of the Abandoned

Canal (Brown, 1979). During the period from 1950 to 1960,

solid waste was disposed of in the two buried Underground Silos,

as supported by documented interviews (Brown, 1979).

Following the closure of the silos, radioactive solid waste was

shipped off-site for disposal at approved low-level radioactive

disposal facilities. This practice continues to date. During 1971

amO 972712;OOCTpounds:pf isoil contaminated with 226Ra was

removed from the West Plant Dump area a_nd_shippedoftsite for

disposal?

- 6 - AR100099

2.4.2 LIQUID WASTE MANAGEMENT

Again, the early period of the study area history lacks

documentation concerning the method of liquid waste

management. (Internal rnemprandumsjand[laboratory notes from J

,_ indicate that_a!L liquid!?

<waste _f torn radioactive production activities were routed tp_qpejy

portions of the^anal. The major radioisotopes noted were 137Cs,

"Sr, and 226Ra. It appears that USRC decided to change liquid

waste handling practices due to the observed levels of radioactive

contamination in the canal. In the 1960 notes from Allam, plans

were being made to route all liquid effluents from the production

building to a holding tank and then to an evaporator. In

conjunction with this change, plans were made to precipitate out

the radioactive constituents in the canal water and discharge the

treated water to the Susquehanna River.(

{"sediments in the^ canalI vyerejtien to be excavated and disposed

r(Allam, 1960). Other documentation indicated this was done,

rhoweveri-the degree-of decontamination is uTriknown (Browrv

fT97fj],. /

Around 1960, a holding tank and evaporator was constructed in

the location of the Liquid Waste Building. The holding tank and

evaporator were constructed below grade and during 1972 the

Susquehanna River flooded the study area. The 1972 flood

destroyed the holding tank/evaporatorsystem. Subsequently, the

below grade structure was filled in and the present Liquid Waste

Building was constructed over this location.

During the period of 1972 to date, liquid effluents from the 3H

processing area are collected in above ground holding tanks in the

Liquid Waste Building. Upon 3H analyses and proper dilution the

-7 -AR100100

liquid effluent is discharged to the Susquehanna River in

accordance with the conditions of Environmental Protection

Agency (EPA) National Pollutant Discharge Elimination System

(NPDES) Permit No. 0111848. Presently, liquid scintillation

solutions are concentrated by evaporation and the dry residues

are shipped off-site for disposal at an approved low-level

radioactive disposal facility (SLC, 1981).

rSanitarywastes were, aToneTime^ discharged to the open canal,

fhoweverrthis practice was discontinued and sanitary wastes are

rcurrently routed~to~a~septic tank.

2.5 DESCRIPTION OF CHARACTERIZATION SITES

Thirty-five individual sites have been identified for characterization within

the study area. The locations of the sites are shown on Figure 1. The

description of the sites is presented below and a summary of the

suspected contaminants at each site is shown on Table 2.1. The site

specific characterization plans are described in Section 6.0.

2.5.1 NUCLEAR BUILDING

The Nuclear Building has been in operation since 1969 for the

production of tritium light sources. The only suspected

contaminant is 3H.

2.5.2 GARAGE

The Garage was originally used for the storage of radioactive

materials prior to 1950. The structure has been removed and a

partial cement foundation remains, approximately 20' x 12'. The

soil under the Garage is suspected to be contaminated with "Sr,226Ra, 137Cs, and 210Po.

- 8 - AR100101

TABLE 2.1CHARACTERIZATION SITES SUSPECTED CONTAMINANTS

SUSPECTED OMTANIgAlfTS

Study ATM Site

Nuclear Building

Garage

Contaminated Soil Area inf — :t of Above Ground Silo(' :Metal Si lo Above Ground

Solid Waste Building

Old House

Liquid Waste Building

8' x 8' Building

Utility Building

Radium Vault

Machine Shop

Contaminated Soil Area Northof Machine Shop

Cant MB! na ted Soil Areasbetween Abandoned Canal andRiveri1 -ground Silos

East Lagoon

Carpenter Shop

Well Mouse

Cesium Ion-Exchange Hut

Contaminated Soil Area underLoading Dock

Cement Trough/Sewer Grate(Behind Main Building)

3H

•

•

•

•

•

•

•

•

14C "Co

•

•

•

«NI

• •

•

•

"Sr

* •

•

•

•

•

•

•

•

•

•

1HCs

•

• .

*

•

•

•

•

•

ao4n "?Ac "7Np M1Am

•

•

•

"*Ra

•

•

•

•

•

•

•

•

•

•

•

•

•

Metals

*

•

*

Cyanide Solvents

•

•

•

Petrol eonHydrocarbons Radon

•

- 9 -AR100102

TABL£ 2.1CHARACTERIZATION SITES SUSPECTED CONTAMINANTS

(Continued)

Main Building

Sidewalk Areas

F -noel Office Building

East Plant Dump

Pipe Shop

Uest Lagoon

Uest Plant Dump

Etching Building

Drain Lines

Contaminated Soil AreaAdjacent to Old Berwick Road

Contaminated Soil Area FromVance/Walton Property

Contaminated Soil Area Northof Lacquer Storage Building

/;'"• ximate location ofAt .-Joned Canal

Contaminated Soil Area Southof Radium Vault

Contaminated Soil Area Eastof 8' x 8' Building

3H

•

•

•

•

•

•

MC

•

•

"Co

•

•

•

"Mi

•

•

•

"sr

•

t•

•

•

•

•

'"Cs

•

•

-

•

•

•

»«Tl

•

•

•

M7Ac "7Mp J41An,

•

•

•

"aRa

•

•

•

•

•

•

•

•

•

•

•

Metals

•

•

•

Cyanide

•

•

Solvents

•

PetroleunHydrocarbons

*

Radon

•

•

- 10-AR100103

2.5.3 CONTAMINATED SOIL AREA IN FRONT OF ABOVE GROUNDSILO

A small area of contaminated soil exists southwest of the Garage

and in front of the Above Ground Silo. The contamination is

believed to have resulted from a spill of 137Cs.

2.5.4 METAL SILO ABOVE GROUND

The Metal Silo Above Ground was used for the storage of 22eRa

ionitrons. The Metal Silo is currently used for the storage of 3H

contaminated equipment (approximately 25% storage capacity).

The Metal Silo is approximately 5' in diameter and is sitting on a

degrading cement foundation. The circular fence enclosure has

been removed. The silo and underlying soil are suspected of

being contaminated with 3H and 226Ra.

2.5.5 SOLID WASTE BUILDING

The Solid Waste Building is currently used for the storage and

compaction of low-level radioactive waste. The building is

vented routinely to reduce 3H activity. Miscellaneous pieces of

equipment including an old evaporator and empty drums are

stored behind the building. The suspected contaminants inside

the building are 3H, ^Sr, 2MRa, "Co, 137Cs, 86Kr, a3Ni, 210Po, and241Am.

(2.5.6 OLD HOUSED

<The Old House is an 1800's residential 2istorywood~hl>uslfwith

a dug-out earthen basement. The interior of the Old HouseJs in

pdoTstructural"condition.L_The. first floor is currentlyjjsedjgrthe/

^storage of contaminated equipment_(apprpximalely~95 %'l;torag3

^capacity). The second floorjs usedjor storagejol^contaminated

^records~and supplies—The-suspected-contaminant-is-22eRaT—1

- 11 -AR100104

2.5.7 LIQUID WASTE BUILDING

Before 1960, the Liquid Waste Building site contained

below-ground vaults used to dilute low-level radioactive waste

water from the Main Building and Etching Building prior to

discharge to the river. After the 1972 flood, the vaults were

capped and the Liquid Waste Building was built over the vaults.

The Liquid Waste Building is currently used for the dilution of

low-level radioactive waste water from the Nuclear Building. The

waste water is transported by a below grade drain line to a below

grade concrete sump within the Liquid Waste Building. The

waste water is pumped from the sump to" one of four 2,400

gallon above ground dilution tanks. The diluted waste water is

discharged to the river through NPDES Discharge Outfall #1,

Permit No. 0111848. (The waste water discharge does not

contain any radioisotopes other than tritium.) The Liquid Waste

Building has been noted to contain elevated radon

concentrations. The suspected contaminants in the building and

surrounding area are 3H, 137Cs, 226Ra, "Sr, "Co, 86Kr, 63Ni, 210Po,241 Am, radon, ethylene glycol and acetone.

2.5.8 8' x 8' BUILDING

The 8' x 8' Building was used for the storage of °°Sr deck

markers. The building is currently used for the storage of 3H

contaminated equipment. A small localized area of contaminated

soil is present in front of the building. The suspected

contaminants are KSr and 3H.

2.5.9 UTILITY BUILDING

The Utility Building was used for the storage of "Sr solution and

was formerly referred to as the TOSr Vault. The building has been

partially decontaminated and is currently used for the storage of

- 12- AR100105

non-radioactive materials and supplies (approximately 60%

storage capacity). The suspected contaminant is ^Sr.

2.5.10- RADIUM-VAULT

ThejIRadium Vault-was used for the pouringlQLlead-and-the

storage-of.radium foils.^ AH radioactive matenalslifeIrTought to

have been removedJrom the building^ Thejoof structure of the

, building has collapsed, thereby inhibitingI entry into'Jjie buildijTg.

The-suspected contaminants are 228Ra and lead.

2.5.11 MACHINE SHOP

In the early 60's this building was referred to as the Tritium

Building and used for the manufacturing and/or handling of tritium

foils and tritium luminous compounds. In 1969, the tritium

production operations were moved to the Nuclear Building

allowing partial decontamination of the building. The building is

currently used as a Machine Shop involving non-radioactive

materials. Contamination is known or suspected to remain in the

overhead ventilation lines, exhaust fan, and under the pavement

adjacent to the building. The suspected contaminants are 3H and

toluene.

2.5.12 CONTAMINATED SOIL AREA NORTH OF MACHINE SHOP

The contaminated soil area is a small localized area of surface

contamination which may have resulted from traffic from the old

Radium Laboratory (see Section 2.5.22). The suspected

contaminant is 226Ra.

2.5.13 CONTAMINATED SOIL AREAS BETWEEN ABANDONED CANAL

AND RIVER

- 13-AR100106

A large area of contaminated soil exists along the southern

boundary of the SLC property between the Abandoned Canal and

river. The soil contamination is suspected to have resulted from

the transfer of contaminants from other sites (East and West

Lagoons, East and West Plant Dumps, etc.) during the 1972

flood. The area is completely covered with heavy undergrowth.

The suspected contaminants are 3H, 137Cs, 226Ra, and ^Sr.

2.5.14 UNDERGROUND SILOS

Two Underground Silos were used for the disposal of solid

radioactive waste between 1950 and 1960. Silo #1 was used

between 1950 and 1952 for the disposal of 226Ra and "Sr, and

possibly 137Cs. Silo #2 was used between 1952 and 1960 for

the disposal of ^Sr and 137Cs, and possibly 22aRa. The

construction details of the silos are contained in Table 2.2. The

silo area is currently covered with grass and is enclosed by a

fence.

2.5.15 EAST LAGOON

The East Lagoon is an unlined earthen surface impoundment with

two visible influent drain lines. Between 1948 and 1954 the East

Lagoon was used for the disposal of sewage and process waste

water from the old Radium Laboratory in the Main Building.

Precipitation was conducted in the lagoon in the early 1960's

(see Section 2.4.2). The lagoon was flooded in 1972 and is

believed to have contributed to contamination of the surrounding

soils. The East and West Lagoons are the remaining portions of

the Abandoned Canal. The East Lagoon is currently used for

disposal of overflow sewage and stormwater. The suspected

contaminants are 3H, wSr, 228Ra, "Co, 137Cs, 86Kr, 63Ni, 210Po, and241Am.

- 14-AR100107

2.5.16 CARPENTER SHOP

The Carpenter Shop also referred to as the Old Maintenance Shop

is now used for the storage of contaminated equipment and

supplies. There is localized contamination on the east wall of the

building which resulted from the explosion of a Sr source. The

suspected contaminant is MSr.

i2757T7~WELTTl6uSE

The north end of the Well House contains the old water supply

well (Monitoring Weir 17). The south end of the Well House was

referred to as the! Adhesive Lab and was used for the formulation

of adhesives. The south end was decontaminated in 1958 and

is currently used for the storage of shredded packing paper.(the

suspected contaminants are 226Ra and solvents.

2.5.18 CESIUM ION EXCHANGE HUT

The Cesium Ion Exchange Hut once housed cesium ion exchange

systems used for the treatment of waste water from the Cesium

Laboratory in the Main Building. The Cesium Ion Exchange Hut

has been gutted, however, contamination remains on the wall

surfaces and floor. The suspected contaminant is 137Cs.

2.5.19 CONTAMINATED SOIL AREA UNDER LOADING DOCK

The loading dock was used as a porch for the entrance and exit

to the former Radium Laboratory located in the Main Building.

Through the years of operations the soil underlying the loadingi

dock has become contaminated as a result of the traffic from the

former Radium Laboratory. The soil underneath the pavement

adjacent to the loading dock may also be contaminated. The

loading dock is currently used as a passage way to dispose of

paper and metal wastes by Multimetals and USR Metals

- 15 -AR100108

custodians. The suspected contaminants are 226Ra, heavy

metals, and solvents.

2.5.20 CEMENT TROUGH/SEWER GRATES BEHIND MAIN BUILDING

The Cement Trough/Sewer Grates were part of the drain

conveyance which transported radioactive process waste water

from the Main Building to the East Lagoon. The suspected

contaminants are 22eRa and

2.5.21 HAND APPLICATION AREA SECOND FLOOR OF MAIN BUILDING

The Hand Application Area was used for hand painting using22eRa and 3H until July 1969 (USRC, 1978). The area was

partially decontaminated in 1968, however, contamination

remains in the attic, ductwork and rafters. The area is currently

used for storage of contaminated and uncontaminated records

and supplies. The suspected contaminants are 220Ra and 3H.

2.5.22 MAIN BUILDING FIRST FLOOR

The Main Building has undergone several structural expansions in

its history. The original building which currently houses the SLC

administrative offices (first floor only), contained 8,000 ft2 on the

first floor, 5,000 ft2 on the second floor, and a 600 ft2 lunch

room on the third floor. In this original building, 226Ra and 3H was

handled on the east half of the second floor where 3H and 22eRa

painting operations took place. In 1969, Safety Light contracted

a vendor to perform decontamination operations in the Main

Building and on the roof, which was accomplished to the degree

necessary to allow unrestricted access to all three floors of the

Main Building.

- 1 6 -AR100109

TABLE 2.2

SUSPECTED CONSTRUCTION DETAILS OF UNDERGROUND SILOS1

1Diameter (in feet)

Depth (in feet)

Volume (cubic feet)

Construction Material (ininches)

Date Constructed

Date Closed

MSr

"8Ra

117Cs

water level (in feet bis)

SILO NO. 1

10-12

15

1178-1697

3/1 6 steel cylinder

1950

1952

small quantities

large quantities

possibly

11-16

SILO NO. 2

10-12

15

1178-1697

3/1 6 steel cylinder

1952

after 1960

large quantities

possibly

small quantitiesi-

11-16

1 Brown, 1979

bis (below land surface)

- 17 -AR100110

Some time in the late 1940's, a one story addition was added

south of the three story main structure and east of the

mechanical application room. This addition added about 14,000

ft2. Sometime between the late 1940's and 1959, a one story

2,000 ft2 expansion was added to the east side of the 14,000 ft2

expansion. Currently the Main Building encompasses about

30,000 ft2.

About 5,000 ft2 of the first floor of the original Main Building has

been extensively renovated and now houses offices for SLC and

USR Metals. For the most part, the remaining 3,000 ft2 of the

original Main Building, first floor, is utilized by SLC for

non-radioactive processes. The one story, 14,000 ft2 addition is

also currently used by SLC for certain non-radioactive processes.

The 2,000 ft2 addition on the east side of the Main Building is

utilized primarily for storage.

The second and third floors of the Main Building are inactive.

The east half of the second floor is used for document and

equipment storage while the west half is predominantly as it

existed during former 3H and 228Ra work. The third floor lunch

room is empty. :

As previously stated, the original 3H and 228Ra dial paintings were

performed in the Main Building. Although free access is possible

in these areas, the potential exists for contamination in normally

inaccessible areas, areas which have been recovered, or areas

which are currently being used for non-radioactive processes.

(For example, the linoleum floor on the second floor is not original

and no surveys exist to document that the underflooring is

uncontaminated.)

- 18-AR100111

As operations were relocated to the 14,000 and 2,000 ft2

additions, radioactive work took place in certain portions of these

additions. Other isotopes were being handled in these additional

areas including ^Sr, 137Cs, 14C, ^Tl, Promethium-147 (U7Pm),60Co, 85Kr, 210Po, and 63Ni. As radioactive processes were

discontinued in these additions and moved to the Nuclear

Building, decontamination efforts were performed to the point

where unrestricted access was permitted by the on-site health

physics group. Over time, other equipment and support systems

were installed in these released areas, which are still in use

today. The suspected contaminants are ^Sr, 137Cs, 14C, 20*TI,147Pm, ^Co, 86Kr, 210Po, 63Ni, 226Ra, 3H, and radon.

2.5.23 SIDEWALK AREAS

The exterior sidewalks provide access primarily to the Main

Building. The Main Building is now used as an administration

building; however, it was previously used for radioactive material

processing. Traffic into and out of the Main Building is suspected

to have spread contamination to the sidewalks and adjacent soils.

The suspected contaminant is 220Ra.

(2.5724" PERSONNEL OFFICE BUILDING

The Personnel Office Building is one-story with a belowHgfade>

cellar which can be accessed from an external trap door. A 2'-

diameter hexagonal shaped concrete slab is located on tHe floor

of the cellar directly beneath the trap door The_slab_is_2" Jhick

and appears to have been poured in place. ";

The Personnel Office Building was used as administrative p_ffice

space and storage for 226Ra, ^ST^screenjng, machines,Zand/

strontiurrr chloride (Brown, 1979)7lt~is~"suspected^fhat'

- 19-AR100112

radioactive waste, was disposed in -a "dry well"-Jocated in-the

.below grade cellar of the building; however, there is, no known

record of such waste disposal. Reference to the disposahof

radioactive waste into _a "dry weH" may have been made referring

to the Undergroud Silos instead of the location of the Personnel

Office Building. The concrete slab is suspected to be covering

the "dry wellX The building is currently in poor structural

condition and is used for storage of miscellaneous radioactive and

non-radioactive items (approximately 40% storage capacity). The

suspected contaminants are 22eRa

2.5.25 EAST PLANT DUMP

The East Plant Dump is located between the East and West

Lagoons. This dump was used prior to the 1970's for disposal

of radioactive waste. The proximity of the East Plant Dump to

the East and West Lagoons suggests that it may have been part

of the Abandoned Canal. The suspected contaminant is ^Sr.

2.5.26 PIPE^SHQP

The~site^now occupied-by-the Pipe Shop, ~was used ir[ 1 948 for

the disposal of~raclium~contaminated ductwork from the USRC

Brooklyn, jsiew York facility. The building, then referred to as the

Maintenance Shop, was built over the disposal area. The

Maintenance Shop was used for maintenance and lead melting.

The building is how referred to as the Pipe Shop and is used for

the storage of-H screening machirfesT paintinytablelTirnd lead

,meltihg_potsT The" Pipe Shop is ventilated routrnely~to~reduce

radon concenfratiohsT The suspected contaminants are 226Ra, fH,

Radpn^and, le_ad.

2.5.27 WEST LAGOON

- 2 0 -AR100113

The West Lagoon is an unlined earthen surface impoundment.

The West Lagoon was used in the 1950's and 1960's for the

disposal of non-radioactive silver plating waste and anodizing

solutions from the Etching Building. In the 1960's the contents

of the East Lagoon was pumped one time into the West Lagoon,

thereby introducing radioactive contaminants. The lagoon was

flooded in 1972 and is believed to have contributed to

contamination of the surrounding soils. The West and East

Lagoons are the remaining portions of the Abandoned Canal. The

West Lagoon is currently abandoned. The suspected

contaminants are "Sr, 226Ra, 3H, "'Co, 13?Cs, 85Kr, 83Ni, 210Po,241Am, metals, cyanide and acids.

2.5.28 WEST PLANT DUMP

The West Plant Dump area was previously used for the disposal

of solid radioactive waste such as 226Ra dials and °°Sr deck

markers. In the 1970's the area was partially excavated and

approximately 78 drums of solid waste were filled and sent off-

site for disposal. The proximity of the West Plant Dump to the

West Lagoon suggests that it may have been part of the

Abandoned Canal. The dimensions of the area are approximately

40' x 50'. Currently, miscellaneous trash and drums are

exposed. The suspected contaminants are 226Ra and ^Sr.

2.5.29—ET_C_HING_ BUILDING

i v. The original Etching Building was constructed in~T94^--~a~nds

' consisted of approximately 16,025 ft-,-with_an additional 350 ft2

separate Radium Measuring Building. The Radium Measuringt '

• Building does not currently exist;_asa separate^Wuc^tlireT It was

xi located where the Carpenter ;j3hpp Ts now located Jn the Etching

Building. Between 1949 and 1976 thOtc^ing~Building-was

- 21 -AR100114

expanded to its current 32,000 ft2. This does not include a

6,000 ft2 manufacturing addition built in 1974 on the

northernmost end of the Etching Building. No radioactive

materials have been utilized in this building; therefore, it should

not require investigation or assessment. However, the ground

below this addition, particularly that area on the south end of the

addition which adjoins the original Etching Building structure, may

contain surface or subsurface contamination.

Many different activities took place in this building. However,

the primary radioactive processes involved the assembly and

manufacture of radium and tritium instruments, dials, etc. Some

areas of the building were used for support services such as

silver plating, chemical storage, maintenance activities, machining

tool and die, and office space. Depending on the radiological

controls practices used at the time (including decontamination

criteria), these support areas could contain low to moderate

amounts of contamination. Areas where tritium and radium were

handled and little or no decontamination efforts have been

undertaken, represent the areas of highest potential for

contamination. The Tritium Screening Room area is recognized

as the area containing the highest potential for contamination in

the building.

At present, approximately 25% of the Etching Building is leased

to USR Metals. This leased space has been extensively

renovated and is located on the east side of the building. SLC

utilizes about 1,600 ft2 on the north end of the building for

assembly of non-radioactive components for exit signs. Portions

of the remaining floor space, primarily on the south end, are used

for storage of various chemicals, supplies, and materials.

- 2 2 -AR100115

nApproximately 50% of the floor space is inactive and generally

in a fair to poor state of order and cleanliness. Except for the

Tritium Screening Room area (which is controlled as an exclusion

area) the roof structure is adequate and keeps the Etching

Building water-tight. Some floor spaces in this inactive area have

been utilized up to 100% for storage of various pieces of

equipment and materials, making access to such rooms difficult

at best. The building in general still contains potentially

contaminated floor drains and ventilation systems.

The roof, due to building exhaust, is also potentially

contaminated. In addition, attic space in the Etching Building

which is currently used to store documents, records, and

contaminated file cabinets, contains a potential for

contamination.

Specific areas of concern within the Etching Building which have

been noted previously by NRC are the Watch Dial Screening

Room, the Maintenance Area, and the Tritium Exit Sign Assembly

Area.

The Watch Dial Screening Room was used for applying 3H to

watch dials in large sheets. The area has been partially

decontaminated. The exhaust ducts, absolute filter banks,

blowers and discharge stack for the room are still intact. The

suspected contaminant is 3H.

-"' The Maintenance Area is enclosed by a wire mesh. The area has

a 12" thick concrete floor poured over a 228Ra contaminated drain

line. The suspected contaminant is 22flRa.

- 23-AR100116

Thef TritiumExi Sign Assembly Areawasjused-for the assembly

and storage of exit signs coritaining^H. "Rverarea is currently

used -fpiTthe^storage-of~metal die assemblies.._ The^suspected

contaminant (s

2.5.30 DRAIN LINES

Numerous drain lines located below grade were used for the

transfer of process waste water from the Main and Etching

Buildings to the canal and East and West Lagoons. The exact

locations of the inactive drain lines is unknown. The suspected

contaminants are 3H, 226Ra, "Sr, TOCo, 137*Cs, 63Ni, 210Po, ^Tl,241 Am, and 14C.

2.5.31 CONTAMINATED SOIL AREA ADJACENT TO OLD BERWICK

ROAD

A pile of contaminated soil is located northwest of the Main

Building outside of the SLC restricted area. The soil appears to

have been created by leveling an adjacent area of SLC property

for new construction. The pile is surrounded by heavy

overgrowth with dimensions of 30' x 15' x 2' -5' high. The

suspected contaminant is 22eRa.

2.5.32 CONTAMINATED SOIL AREA FROM VANCE/WALTON

PROPERTY

Contaminated soil was removed from the Vance/Walton property

and stockpiled south of the Above Ground Silo. The

contamination on the Vance/Walton property is believed to have

resulted from the transfer of contaminants from the study area

during the 1972 flood. The contaminated soil pile is uncovered,

with approximate dimensions of 16' x 10' x 2 - 4' high. The

suspected contaminants are 137Cs and 226Ra.

- 2 4 - AR100117

2.5.33 CONTAMINATED SOIL AREA NORTH OF LACQUER STORAGE

BUILDING

An area of suspected contaminated soil is located north of the

Lacquer Storage Building, some of which is now overlaid with

pavement. Previous operations within the Main Building resulted

in the direct disposal of solvents on the soil. These disposal

methods have since been discontinued. In the early to mid-70's

a spill of diesel fuel occurred near Monitoring Well 11. Evidence

of a very viscous free product is visible at Monitoring Well 11.

Free product is also evident to a lesser degree at Monitoring

Wells 12 and 13. The suspected contaminants are solvents and

diesel fuel.

2.5.34 ABANDONED CANAL

The Abandoned Canal extended along the southern boundary of

the SLC property parallel to the river. Portions of the Abandoned

Canal were still visible as of 1962 or 1963. The visible portions

were constructed of a rock-lined bottom and walls and was

approximately 20' wide. The wall of the canal away from the

river was located relatively close to the present drop off at the

southern border of the SLC property (Brown, 1979).

At one time as many as seven lagoons were constructed in the

canal by utilizing earthen dams to compartmentalize the canal.

The lagoons started on an east-west line approximately where

the Underground Silos are located and continued in a series to

the west edge of the study area (property line).

Around 1962 or 1963, it was discovered that the three eastern

most lagoons had considerable amounts of radioactivity

suspended in the water due to high pH conditions. The water

- 2 5 -AR100118

was treated to precipitate out radionuclides. However, the

location of the treatment activities is unclear. One source of

information states that a considerable amount of calcium was

added to the three lagoons to neutralize them, then carrier

solutions were added to precipitate out the radionuclides (Brown,

1979). However, the recollection of present SLC employees is

that the water was pumped to the vaults located at the Liquid

Waste Building site for treatment. The supernate water was

pumped to the river and approximately 100 drums of precipitate

were removed, containerized, and shipped off-site for disposal.

Following this process, the two eastern most lagoons were

backfilled. The third eastern most lagoon was backfilled between

1976 and 1978. (There are indications that this lagoon was not

contaminated at the time it was backfilled). The fourth lagoon

from the east is now referred to as the East Lagoon. The fifth

lagoon from the east was filled in and the Pipe Shop constructed

partially on top of the fill area. The sixth lagoon from the east is

now referred to as the West Lagoon. The seventh lagoon from

the east was located between the West Lagoon and the western

property boundary of the study area. The seventh lagoon was

filled in and may have been used as a service dump (Brown,

1979). From the description, it is suspected that the West Plant

Dump is located over the backfilled seventh lagoon. The

suspected contaminants are ""Ra, °°Sr, 3H, "'Co, 137Cs, 86Kr, 83Ni,210Po, 241Am, solvents, and metals.

2.5.35 CONTAMINATED SOIL AREA SOUTH OF RADIUM VAULT

An area of contaminated soil is located south of the Radium Vault

adjacent to the entrance to the Radium Vault. The contamination

may have resulted from the transfer of contaminants through

- 2 6 -AR100119

traffic into and out of the Radium Vault. The suspected

contaminant is 226Ra.

2.5.36 CONTAMINATED SOIL AREA EAST OF THE 8' X 8' BUILDING

An area of contaminated soil is located east of the 8' x 8'

Building. The contamination may have resulted from the transfer

of contaminants through traffic into and out of the 8' x 8'

Building. The suspected contaminants are Sr and 3H.

2.6 SUMMARY OF PREVIOUS INVESTIGATIONS AND CHARACTERIZATIONS

Groundwater monitoring was initiated in 1978 by the installation of three

monitoring wells by the Giles Drilling Corporation. Soil and groundwater

samples from these three wells provided initial contamination levels and

indicated the need for additional monitoring (RMC, 1979).

During 1979, Meiser & Earl conducted a hydrogeological investigation

including the installation of thirteen monitoring wells with soil cores and

excavation of backhoe test pits. The data was evaluated to characterize

the hydrogeology of the study area.

In their report subsurface geologic conditions and water table

configurations were described, pumping tests were conducted,

groundwater flow rates calculated, water quality samples collected, and

remediation techniques discussed. Remediation techniques discussed

included waste removal/dewatering of groundwater, slurry wall

construction, grout curtain construction, and insitu chemical treatment.

In conjunction with the Meiser & Earl investigation, the Radiation

Management Corporation (RMC) conducted a radiological investigation,

using soil and groundwater collected by Meiser & Earl. In addition, RMC

collected and analyzed surface and near surface soil samples.

- 2 7 -AR100120

RMC concluded it their report the following:

• Present conditions of the study area do not represent a significant

public health hazard with regard to radiation or the release of

radioactivity into the environment;

• Remediation activities are not appropriate or justified at this time; and

• Continued and additional environmental monitoring is suggested.

During 1981, Oak Ridge Associated Universities (ORAU) performed an

extensive radiological survey at the study. Radiological analyses were

performed both on-site and off-site, on air, surface and subsurface soil,

ground water, vegetation, surface water and aquatic organisms (Berger,

1982).

ORAU concluded in their report:

• Direct radiation levels were elevated at the study area but below

federal guidelines for unrestricted use;

• Monitoring of atmospheric effluent was inconclusive while monitoring

of liquid effluent confirmed SLC results;

• On-site soil sampling indicated elevated 220Ra, 137Cs, and °°Sr and

on-site ground water sampling showed levels of 3H and "°Sr exceeding

NRC or EPA guidelines;

• Off-site monitoring indicated radionuclides are not accumulating in the

adjacent properties; and

- 2 8 -AR100121

• There is evidence that radioactive wastes remaining from USRC

operations are migrating into soil and groundwater. While it does not

appear to be accumulating off-site, they may be a source of future

concern.

In 1988, the NRC performed an environmental evaluation of the study area

using available monitoring data to compile relevant information about the

radioactive contamination of the study area, assess hazards to nearby

residents, and establish actions regarding the contamination.

The NRC concluded in their summary of available data the following:

"Disposal of radioactive wastes at the Safety Light Corporation

site near Bloomsburg, Pennsylvania has caused extensive

contamination of groundwater on and off-site and soil on-site.

Current decontamination efforts should focus on cleanup and

control of the disposal silos, open dumps, and contaminated

soils to minimize further contamination of the soil and

groundwater. Additional information is necessary to characterize

the sources of contamination, transport characteristics of the

site, and hazards posed to nearby residents by both radiological

and non-radiological hazardous constituents." (NRC, 1988)

In 1990, CNSI performed soil coring, monitoring well installations,

groundwater sampling and rainwater sampling as part of a hydrogeologic

and radiological evaluation of the study area. The selection of sampling

locations were directed at the Vance/Walton property, areas downgradient

of the Abandoned Canal, and the southwest corner of the study area. The

purpose of the investigation was to assess radiological contamination

off-site and downgradient of suspected radiological source areas.

Conclusions of this investigation were as follows:

- 2 9 -AR100122

• The hydrogeological characteristics of the study area, including the

stratigraphic units and groundwater flow patterns, appear to be

typical for this region. No detrimental features were observed that

might influence groundwater flow patterns.

• Groundwater flow appears to move from the northern portion of the

study area southward toward the Susquehanna River. Groundwater

flow is primarily controlled by topographic expression of the land

surface and appears typical for this area.

• Previous investigations suggested the normal southerly flow of

groundwater may be diverted laterally (east/west) by the Abandoned

Canal. Radiological and hydrogeological data collected and evaluated

during this study indicated groundwater flow is in a southerly

direction toward the Susquehanna River. There is no strong evidence

to support lateral flow along the Abandoned Canal.

• In addition, it has been suggested that 3H might be associated with

the Abandoned Canal and buried sources; however, this investigation

indicated the source and distribution of 3H within the study area is

associated with present and past atmospheric releases due to site

operations.

• Elevated 3H was detected in soil, groundwater, and rainwater. The

highest concentration of 3H were detected in soil and groundwater in

the southeastern quadrant of the study area and appears to be

released to atmospheric sources (present site operations).

• "Sr was detected in both soil and groundwater. This study and

previous investigations indicate the major source of the groundwater

contamination is from the Underground Silos located within the

-30 -AR100123

south-central portion of the study area. Low concentrations of ^Sr

were detected at drill sites located along the southeastern and

southwestern portions of the study area and may be attributed to

residual "Sr contamination along the canal when it was open or the

placement of contaminated fill when the canal was abandoned. "'Sr

migration, via groundwater movement along the east/west

Abandoned Canal, is not suspected.

• 137Cs, 226Ra, and 228Ra were detected in soil at low concentrations.

Drill sites were biased away from known or observed elevated levels

of surficial radiological contamination. In addition, previous

investigations and current observations indicate elevated levels of

surficial radiological contamination primarily within the southern

portion of the study area.

• The Abandoned Canal, located in the southern portion of the study

area, does not appear to be a potential pathway for the eastward

migration of contaminated groundwater away from the study area.

The characteristics of the Abandoned Canal within the boundaries of

the study area were not addressed during this study, however,

previous investigations indicate the Abandoned Canal may be a

source of radioactive contamination.

• Radioactive contaminated soil and groundwater was detected in areas

outside the boundaries of the study area. Due to the limited nature

of this project, additional environmental monitoring and site

characterization will be necessary to fully address the issue raised

during this investigation. These additional studies could be performed

as part of remedial action efforts or independently.

-31 -AR100124

During 1991, NUS Corporation Superfund Division, prepared a summary

document entitled "Preliminary Assessment of Safety Light Corporation"

under an EPA contract. This summary report used all existing reports and

information to date. This document was prepared at the direction of EPA

and was independent of the present NRC regulatory activities. The NUS

report summarized the conditions of the study area as follows:

"Some of the wastes from these operations were buried on-site

and, to date, have not been removed. Several studies of the site

have been completed (including site characterization), and some

decontamination of the site, mainly of the on-site buildings, has

taken place. A large section of the site remains contaminated

with radium-226, cesium-137, strontium-90, and tritium. The

waste disposal practices have improved dramatically over the

years; however, the soil and groundwater have been

contaminated by the radioactive wastes that are buried on site.

Extensive enforcement action has taken place at the site with

regards to employee exposure to radiation, safety violations, and

radiation releases to the atmosphere." (NUS, 1991)

3.0 CHARACTERIZATION METHODOLOGIES

Due to the complex nature of the study area, numerous characterization

methodologies will be required to determine the nature and extent of

contamination present. The characterization methodologies which will be used

within the study area are described in general terms below. The application of

methodologies within the study area is described in Section 6.0.

3.1 SURFACE GEOPHYSICAL SURVEYS

3.1.1 PURPOSE

-32-AR100125

The purpose of performing geophysical surveys within the study

area is to rapidly characterize the subsurface conditions without

disturbing the site. The application of geophysical methods will

assist to locate and define the boundaries of buried trenches,

disposal pits, and drain lines; map contaminant conductive

plumes; and, assist in selecting soil sampling locations. Both

surface and downhole geophysical methods will be used.

3.1.2 DESCRIPTION Of= EQUIPMENT

The geophysical techniques which may be employed at the study

area are magnetometer survey, electromagnetic survey, and

ground penetrating radar survey. These survey methodologies

are described below.

Magnetometers: The magnetometer will be used to locate buried

steel containers, define boundaries of disposal area filled with

ferrous containers and locate ferrous underground utilities.

Magnetometry is used to locate buried ferrous metals by

detecting anomalies in the earth's magnetic field caused by

ferrous objects. The magnetometer measures the intensity of the

earth's magnetic field. The presence of ferrous metals creates

variation in the local strength of that field, permitting their

detection. A magnetometer's response is proportional to the

mass of the ferrous target.

Electromagnetics: The electromagnetics (EM) survey will be used

to locate and map buried trenches and pits containing waste,

plume boundaries, and underground utilities. EM allows

measurement of subsurface electrical conductivities. The EM

transmitter coil radiates an electromagnetic field which induces

eddy currents in the earth below the instrument. Each of these

- 3 3 -AR100126

eddy current loops, in turn, generate a secondary electromagnetic

field which is proportional to the magnitude of the current

flowing within that loop. A part of the secondary magnetic field

from each loop is intercepted by the receiver coil and produces

an output voltage which (within limits) is linearly related to

subsurface conductivity. This reading is a bulk measurement of

conductivity; the cumulative response to subsurface conditions

ranging all the way from the surface to the effective depth of the

instrument.

Ground Penetrating Radar: The Ground Penetrating Radar (GPR)

survey will be used to locate and delineate buried waste and

contaminant plumes and will provide a cross-sectional picture of

the subsurface conditions. GPR is a reflection technique using

high frequency radio waves, which are bounced off subsurface

features. GPR uses the high frequency radio waves to acquire

subsurface information from a small antenna which is moved

slowly across the surface of the ground. Energy is radiated

downward into the subsurface, then reflected back to the

receiving antenna, where variations in the return signal are

continuously recorded; this produces a continuous cross-sectional

picture or profile of the subsurface conditions. The responses are

caused by radar wave reflections from interfaces of materials

having different electrical properties. (EPA-60017-84-064)

The GPR system used will be an impulse radar system. The radar

system consists of a control unit, antenna, graphic recorder and

an optional magnetic tape recorder. System power will be

supplied by a small gasoline generator. GPR will be conducted by

marking traverse lines across the study area and towing the

antenna by hand. Traverse speeds will range from 0.5 to 2km/h.

- 3 4 -AR100127

Resolution will range from centimeters to several meters

depending upon the antenna (frequency) used.

3.1.3 OPERATION OF EQUIPMENT

The study area will first be marked in a grid pattern by a land

surveyor for accurate location of survey measurement points.

The survey grid will consist of parallel lines of north-south and

east-west orientation spaced at 20' intervals. The survey will

begin by initializing the geophysical tool at a baseline reference

point. The geophysical tools will then be hand carried across the

study area along the grid lines. Readings will be recorded

continuously or at regular interval grid nodes.

3.1.4 LIMITATIONS

All geophysical techniques are susceptible to signal interference

from above and below ground sources (powerlines, radio

transmitters, atmospheric conditions, etc.) therefore, care must

be taken in interpreting results.

3.1.5 DATA MANAGEMENT

The magnetometer data will be recorded on a strip chart or map.

The EM data will be recorded on a strip chart or magnetic tape

recorder. The GPR data will be recorded by a graphic recorder

and/or magnetic tape recorder. The geophysical data obtained

may be computer processed to provide for spatial corrections,

overlay multiple sets of data, and/or contour data.

3.2 RADIOLOGICAL SURVEYS

3.2.1 PURPOSE

Radiological surveys with portable radiation detectors will be

performed to determine the locations of areas with radiation

- 3 5 -AR100128

levels in excess of background levels, the extent of

contamination and activity concentrations, and affected area or

volume. Surveys will be conducted of the study area grounds,

buildings, stored equipment and materials, and in boreholes and

test trenches. Current knowledge of activities involving the

storage, treatment, and disposal of radioactive material will assist

in selecting specific surveying locations.

3.2.2 DESCRIPTION OF EQUIPMENT

Portable radiation detectors will be used to measure gross alpha,

beta, and gamma activities. For alpha measurements an Eberline

ESP-1 with an Eberline AC-3, Alpha Scintillation Probe, will be

used. For direct beta measurements a pan cake Geiger Mueller

(GM) probe will be used: Eberline HP-210, Hand Probe or

equivalent. For gamma measurements a 2" x 2" sodium iodide

(Nal) detector with a rate meter/sealer will be used: Eberline

ESP-1 with Eberline SPA-3, Scintillation Probe or equivalent.

3.2.3 OPERATION OR EQUIPMENT

Background Survey: Prior to conducting the radiological surveys,

a background survey will be performed. The background survey

will measure the direct radiation levels and concentrations of the

potential radionuclide contaminants in construction materials and

soils in the vicinity of the site. Measurements from six to eight

locations will be used to obtain a representative background

value.

Ground Surveys: Prior to conducting radiological ground surveys,

a grid system will be established consisting of integrating lines,

referenced to a bench mark. The grid system will be marked off

by a licensed surveyor. High contamination potential surface

- 3 6 -AR100129

areas will be gridded at 10' x 10' intervals. Moderate and low

potential contamination areas will be gridded at 20' x 20'

intervals.

A scale drawing will be developed of the survey ground areas

indicating facility features and superimposing the grid reference

system.

Soil surfaces will be scanned for gamma radiations only. Ground

surfaces will be gamma scanned prior to sampling to identify the

presence of elevated direct radiation. The'probe will be swung

in a pendulum fashion, keeping the detector near the surface

while advancing at a speed of about 0.5 m per second.

Locations of direct radiation exceeding 1.5 to 2 times the

background level will be marked on study area map and identified

for further measurements and/or sampling. Gamma exposure rate

measurements will be conducted 1 m above the ground at

systematic locations and at locations of elevated radiation,

identified by area gamma scans.

In addition to the gamma scans, paved areas will be scanned for

alpha and/or beta radiations. The same techniques will be used

as described below for scans of building surfaces.

Direct measurements of surface activity levels will be performed

on paved surfaces, following the procedures described below for

building surfaces.

Surface soil samples will be collected as described in Section 3.3.

If there is a potential for activity beneath paved surfaces, the

surface will be removed by coring and the underlying soil

- 3 7 -AR100130

sampled, as described in Section 3.9. Direct measurements will

be taken of the soil samples to determine the contamination level

and the sample shipping requirements.

Gamma logging of boreholes will be performed to identify the

presence of subsurface deposits of gamma-emitting

radionuclides. A sensitive gamma detector such as a Nal gamma

scintillation probe will be lowered into the hole and a count rate

determined at approximately 0.3 to 0.5 m intervals.

Building Surveys: Before conducting additional measurements,

surfaces will be gamma scanned to identify the presence of

elevated direct radiation which might indicate hot-spots. Building

interior surface scans will then be conducted for alpha, beta, and

gamma radiations. The scanning detector will be kept as close

as possible to the surface and moved across the surface at a

slow speed. Nominally, the distance between the detector and

the surface will be maintained at less than several centimeters,

with the exception of alpha scanning for which the distance will

be less than 1 cm. For paniculate radiations (alpha and beta) the

detector speed will be approximately 1 detector width per

second. For gamma radiation the scanning speed will be greater;

the detector will be kept as close as possible to the surface and

moved back and forth, while walking at a speed of about 0.5 m

per second. Locations of direct radiation exceeding 1.5 to 2

times the background level will be marked on site sketches and

identified for further measurements and/or sampling, if feasible.

Direct measurements of surface alpha and beta activity will be

conducted by using a one minute integrated counting technique.

Surface activity measurements will be performed at randomly

- 3 8 -AR100131

selected locations and at locations of elevated direct radiation,

identified by surface scans. Measurements will be noted on the

site sketch.

Gamma exposure rate measurements will be conducted 1 m

above the floor at random locations and locations of elevated

radiation, identified by area gamma scans. Measurements will be

recorded in accordance with CNSI Procedure, FS-RP-009.

To identify fixed contamination, samples of the construction

material will be taken from walls and floors in areas of similar

contamination. Analyses of these samples will assist in

identifying contamination which may be masked by renovations,

resurfacing, painting, etc.

The materials of construction in the area to be sampled will

dictate the type of sampling methodology. Types of sampling

equipment may include picks, chisels, hammers, and scraping

blades. The samples will be sent to an analytical laboratory for

radioisotopic analyses. Locations of construction material

samples will be recorded on a building or area survey sketch.

3.2.4 LIMITATIONS

The radiological survey instruments are limited in that the

instruments can not detect the presence of tritium and will be

unable to detect alpha and beta radiation which is covered or

masked (i.e. through painting or resurfacing). In addition, the

radiological survey instruments will be unable to detect

radioactive waste or materials which is buried at depths of more

than a few feet.

- 3 9 -AR100132


Radiological survey readings will be recorded in accordance with

CNSI Procedure, FS-RP-009, "Surface Contamination Surveys".

3.3 SURFACE SOIL SAMPLING

3.3.1 PURPOSE

The purpose of surface soil sampling is to determine the lateral

extent of contamination, specific constituents of the

contamination, and concentrations of contamination within the

study area. Prior to the surface soil sampling, geophysical and

radiological ground surveys will be conducted within the study

area on a grid system (see Sections 3.1 and 3.2). The

preliminary results of the geophysical and radiological surveys

and surface soil sampling will better define the locations to

perform drilling and subsurface sampling of soils to determine the

depth of contamination (see Section 3.4).


The equipment used to obtain surface soil samples will consist of

a variety of hand tools including scoops, shovels, or trowels.

Due to the shallow depth of sampling and the presence of

abundant cobbles and boulders in the uppermost sediments,

augering devices will not be used.


Surface soil samples will be collected within 100'x100' grid

blocks and at site-specific locations of known contamination

within the study area. Once the area has been selected for

sampling, a 1 ft2 area will be sampled to a depth not to exceed

6" and an aliquot taken of the soil for the sample. The sampling

tools will be decontaminated prior to use at each location. Soil

-40 -AR100133

samples will be placed in appropriate containers and handled per

laboratory requirements. Personnel protection will include, at a

minimum, surgical gloves. Upon collection of the surface soil

samples, a portion of the samples will be screened in the field

using portable counting equipment. If the sample is to be sent

for laboratory analyses the Radiation Control Supervisor (RCS)

will perform a radiological survey of the sample containers and

package the sample containers in accordance with CNSI

Procedure RA-OP-001, "Operating Procedure for Brokering of

Radioactive Materials at Commercial Facilities". A

Chain-Of-Custody Form will be completed and accompany the

samples to the laboratory.

3.3.4 LIMITATIONS

All surface samples will be limited to a depth not to exceed 6".


All aspects of surface soil sampling will be documented by noting

exact sampling locations and completing the following forms:

• "Radiological/Hazardous Constituent Sample Collection Form"

contains name, date, time of sample collection, and type of

analyses. This form will be submitted with all samples to

contract laboratories.

• "Chain-of-Custody Form" serves as a means of documenting

sample movement from point of collection to point of

analyses.

-41 -AR100134

3.4 DRILLING AND SUBSURFACE SOIL SAMPLING

3.4.1 PURPOSE

Drilling and subsurface soil sampling consist of penetrating down

to the desired depth, removing the material penetrated so that it

may be examined at the surface, recording the depths at which

changes in materials or subsurface conditions are found, and

obtaining samples of the material penetrated. The purpose of

drilling and subsurface soil sampling within the study area is to

obtain soil samples or other subsurface materials for the

identification of radioisotopes and/or hazardous constituents by

either direct measurements or laboratory analyses. Additional

lithologic and stratigraphic information obtained through

subsurface sampling will be used to supplement the conceptual

geologic model of the study area.

Upon receipt of the laboratory analyses the data will be used to

determine the vertical distribution of contaminants with depth.

Specific contaminants and concentrations will be identified. In

conjunction with surface soil sampling, the subsurface sampling

will provide analytical results illustrating the 3-dimensional

distribution of contaminants within the study area. If necessary

the borehole advanced by drilling and subsurface soil sampling

methods will be utilized for monitoring well installations.


There are numerous types of drilling methods used for this

purpose including augering methods, mud rotary methods, air

hammer methods, etc. The augering method is preferred when

soil samples are scheduled for laboratory analyses. The

subsurface conditions underlying the study area are difficult to

auger, particularly north of the Abandoned Canal, due to the

- 4 2 -AR100135

presence of large cobbles and boulders in the near-surface

deposits. In addition, the sands overlying the shale bedrock tend

to flow up the augers (sand heave) throughout the study area.

Despite these difficulties, augering is preferred as it provides

discrete soil samples, minimal cross contamination, and adequate

quantities of soils for laboratory analyses (CNSI, 1990).

One type of augering is hollow-stem augering. Hollow-stem

augering provides a rapid and efficient method for drilling in

materials which can be penetrated by an auger. The hollow-stem

auger eliminates the need for casing and permits sampling

without withdrawing the auger by inserting sampling devices

through the auger, thus increasing the rate of drilling and

sampling. It is possible to drive split-spoons and relatively

undisturbed tube samples with hollow-stem augers. A selection

of different diameter drive tubes are available based on the soil

volume requirements for soil testing or laboratory analyses or the

resistance of the materials. Three inch inside diameter by 24"

long split-spoon barrels have shown to be compatible with the

study area soil conditions. Both sampling within the unsaturated

zone or within the saturated zone are possible with the use of

steel finger catchers located in the lowermost portion of the

split-spoon.


This method utilizes modified American Society of Testing

Materials (ASTM) sampling equipment and procedures (ASTM D

1586-84). The modification is based solely on the diameter of

the split-spoon barrel. A 3" diameter split-spoon sampler will be

advanced ahead of 4-1 /4" or larger, lead hollow-stem auger using

a 140 Ib. hammer and cat head hoisting device. The split-spoon

- 43 -AR100136

sampler will be removed from the augers utilizing either AW or

NW size drill rods. The results of this sampling method provides

adequate soil volumes and minimal fluid or soil cross

contamination. Once the split-spoon is hoisted to the surface, a

radiological survey is performed to detect gross contamination.

Upon completion of this task, the split-spoon is opened, the thin

outer layer of the soil sample is removed, a lithologic description

performed and the soil is transferred to appropriate sample

containers. The split-spoons are then decontaminated and the

process repeated at 4' intervals or other selected sampling

intervals.

Soil sample containers will be labeled as described in Section 7.4.

Prior to shipment of the soil samples, the RCS will perform a

radiological survey of the sample containers and package the

sample containers in accordance with CNSI Procedure

RA-OP-001.

Upon completion of characterization activities within the deep

subsurface holes and boreholes, the holes will be sealed by filling

with cement.

3.4.4 LIMITATIONS

Hollow-stem augering and split-spoon sampling is limited to the

unconsolidated sediments overlying the shale bedrock. Due to

the dense nature of the indurated shale bedrock, no sampling will

occur below this contact.

-44-AR100137

Due to subsurface borehole instability and flowing sands at

depth, drilling and soil sampling must be conducted with minimal

disruptions in the drilling process.


All subsurface drilling and sampling activities will be documented

by the drilling supervisor. This documentation will include, but

not limited to, the following:

• "Daily Drilling Report" contains names of all crew members,

hourly log of all important and relevant events during all

drilling activities.

• "Lithologic Description Forms" contains complete visual

lithologic field descriptions, strip chart, and comments.

• "Radiological/Hazardous Constituent Sample Collection

Form" contains name, date, time of sample collection, and

type of analyses. This form will be submitted with all

samples to contract laboratories.


sample movement from the point of collection to the point

of analyses.

Geologic cross sections and/or fence diagrams will be developed

to illustrate the geologic subsurface conditions underlying the

study area.

3.5 MONITORING WELL INSTALLATION

3.5.1 PURPOSE

-45 -AR100138

The purpose of groundwater monitoring well installation is to

provide a means to withdraw groundwater from a discrete

subsurface interval. The well casing, bentonite seal, and cement

grout isolates the screened interval from other water-bearing

zones and prohibits surface water infiltration. Upon well

development, the monitoring well provides representative

groundwater for laboratory analyses. In addition, the monitoring

well can be used to obtain water level measurements and

determine groundwater flow paths.


To install a groundwater monitoring well a borehole is advanced

through the unsaturated zone and beyond the water table to a

selected depth. Due to the instability of the soils underlying the

study area, hollow-stem augers will be left in place in the

borehole to provide an unobstructed annular space to construct

the monitoring well. The components of a groundwater

monitoring well are as follows:

• 2" polyvinyl chloride (PVC) schedule 80 flush joint slotted

screen: Provides the intake area for groundwater and

prohibits the entry of filter sand.

• 2" PVC schedule 80 flush joint casing: Isolates the screen

interval from other water-bearing zones and provides an

access point to the screened interval.

• Filter sand: Provides a filtering media around the screened

interval to remove solids prior to entry into the screen.

- 4 6 -AR100139

• Bentonite seal: Isolates the underlying filter sand from the

overlying cement grout in the annular space between the

casing and the borehole.

• Cement grout: Seals and isolates the annular space

between the casing and the borehole immediately above the

bentonite seal and extending to land surface.

• Well cap, protective casing, and well pad: A surface

component of a monitoring well designed to preserve the

integrity of the monitoring well a"nd prohibit surface

contaminants from entering the well.


The anticipated procedures for monitoring well installation within

the study area (based on previous drilling experience), are as

follows:

• Install the 2" PVC schedule 80 screen and casing through

the hollow-stem augers;

• Lower AW-size drill rods inside the casing and screen to

provide counter weight during auger extraction;

• Pull the hollow-stem auger while ensuring the well assembly

remains in place;

• Measure the amount of borehole collapse using a tag bar;

• In the event portions of the screened interval is exposed

above the collapsed section, tremie filter sand two feet

-47 -AR100140

above the top of the screen, using tag bar to verify

placement;

• Tremie 50 pounds (or approximately 2') of bentonite pellets

above the filter sand, using tag bar to verify placement.

Allow bentonite pellets to hydrate;

• Tremie cement grout (~ 13.0 -14.0 Ibs/gal) from the top of

the bentonite seal to land surface. Verify and record

density of cement grout with a mud balance. Check weight

prior to pumping and upon termination of grouting (from

borehole). Insert protective casing around the casing and

into the cement grout;

• Develop well using an airlift method until pH and

conductivity measurements stabilize. Containerize all well

development water in 55-gallon drums and label

appropriately; and

• Install 4'x4'x6n well pad and dedicated PVC bailer.

3.5.4 LIMITATIONS

The minimum depth for monitoring well placement will depend on

current static water level and seasonal fluctuations. The

maximum depth for monitoring well placement is the top of the

shale bedrock surface. The shale bedrock surface has been

eroded to a relatively flat surface and the depth to bedrock has

been determined by previous investigations (CNSI, 1990, and

Meiser and Earl, 1979).


- 48 -AR100141

All monitoring wells installed within the study area will be

documented by the following:

• "Department of Environmental Resources, Topographic and

Geologic Survey, Water Well Completion Report" - required

regulatory report form by the state of Pennsylvania.

• "Daily Drilling Report" - containing names of crew members,

hourly log of all important and relevant events during all

drilling activities.

• "Monitoring Well Construction Diagram" - containing all

relevant as-built construction details.

3.6 TEST TRENCH EXCAVATIONS AND SAMPLING•

3.6.1 PURPOSE

The purpose of test trench excavations and sampling is to

investigate the subsurface conditions within the study area. Test

trench excavations will be followed by visual observations, direct

measurements, and sampling of the exposed soils for laboratory

analyses.


A backhoe or trackhoe will excavate the test trench. This

equipment, or similar equipment, will be capable of excavating a

trench with the anticipated dimensions of 10' deep by 50' long.

The width dimensions will be dependent on soil stability

characteristics or safety considerations if entry into the test

trench is required.


-49 -AR100142

Prior to the removal of any soil from the test trenches, a baseline

radiological survey will be performed within the proposed

excavation area. Excavations will continue both laterally and

vertically until the target depth is reached. In the event the

excavation extends down to the water table, test trenching will

be discontinued due to instability of the saturated soils. Upon

reaching the desired depth, the slopes will be laid back to 1H: 1V

(horizontal to vertical) or benched if entry by personnel is

required. During excavation and upon completion of excavation,

the following characterization activities will be conducted.

• Description of native soils and fill material will be

documented by a geologist familiar with the site

stratigraphy. Documentation will include photographs,

sketches, and written notes. The ability to define the

contact between native soils and fill material will be

important as related to definition of disposal areas.

• Direct measurements of radioactivity and hazardous

constituents will be conducted (see Section 3.2). These

results will guide in the selection of soil sampling locations

for laboratory analyses (see Section 3.3).

• Soil or buried debris will be sampled for laboratory analyses.

Upon completion of characterization activities within the

excavation, all soil removed from the test trench will be

backfilled. All backfilling will be conducted in lifts followed by

compaction with the backhoe bucket. Following backfill

operations, the general area will be surveyed and compared to

the baseline radiological survey. Placement of uncontaminated

- 5 0 -AR100143

soil material may be necessary within the work area to ensure the

surface conditions of the backfilled test trenches are similar to

baseline conditions.

3.6.4 LIMITATIONS

The depth of excavation will be limited to specific target depths

or the water table. Excavations beyond the water table will not

be conducted due to the instability of saturated soils and the

potential spread of contaminated water. The width dimensions

will be limited by the soil stability characteristics.


Documentation concerning test trench excavations will be

recorded in a bound field notebook. Direct measurements and

soil sampling will be conducted and documented per the

following sections:

• Section 3.2 Radiological Survey

• Section 3.3 Surface Soil Sampling

3.7 GROUNDWATER SAMPLINGf

3.7.1 PURPOSE

The purpose of groundwater sampling within the study area is to

obtain representative groundwater samples to analyze for

radiological and hazardous constituents. Laboratory analytical

results will identify what contaminants are in transit within the

study area groundwater flow system. Current knowledge of past

activities concerning storage, handling, and disposal methods for

potential contaminants in conjunction with groundwater flow

maps will control the selection of monitoring wells and selection

of the parameters for analyses. The observation of specific

- 51 -AR100144

contaminants will assist in the identification of radiological and

hazardous contamination source areas and defining contaminant

plumes. In addition, the occurrence and concentration of

contaminants will assist in the determination of mobility and

toxicity of the contaminants in the ground water flow system.


Prior to obtaining ground water samples, the water standing in the

monitoring well casing and screened interval must be evacuated.

There are numerous groundwater evacuation/sampling devices

available; site specific conditions will dictate the selection of

specific equipment.

4" Diameter Monitoring Wells: For large diameter monitoring

wells, a 1/3 hp, 110 volt dedicated submersible pump will be

installed in each well. This device is well suited to evacuate large

volumes of groundwater at high flow rates. A small portable

electric generator will be used to operate the submersible pump.

2" and 1-1/2" Diameter Monitoring Wells: For small diameter

monitoring wells, a dedicated PVC bailer will be installed in each»

well. This device is well suited for evacuating small volumes of

water.


Upon arrival at the well location, the conditions of the well will

be inspected to note and record any unusual conditions (damage,

vandalism, etc.). A drop plastic cover will be placed on the

ground around the well head, particularly if the surface is

potentially contaminated.

- 5 2 -AR100145

Prior to well evacuation or sampling, the water level will be

measured to the nearest tenth foot and recorded on the Field

Groundwater Sampling Report Form.

The total volume of standing water in the well (gallons) is

calculated and recorded. A total of three well volumes will be

removed by dedicated PVC bailers or dedicated submersible

pumps. All groundwater evacuated will be placed in 55-gallon

drums, sealed and labeled. Samples will then be collected using

the dedicated pump or bailer.

Sample containers will be filled and identified as described in

Section 7.4.

All relevant sampling data will be recorded on the Field Sampling

Report Form.

Upon collection of the groundwater samples, the RCS will

perform a radiological survey of the sample containers and

package the sample containers in accordance with CNSI

Procedure RA-OP-001.

3.7.4 LIMITATIONS

Once the groundwater samples are collected in the appropriate

type of containers and any necessary preservative is added, the

samples will be stored and cooled to 4 degree C (primarily for

hazardous constituents). The samples will be transported to the

analytical laboratory and analyzed within the predescribed holding

time. In the event the groundwater samples are not collected per

these specifications the results will be considered "void".

- 53 -AR100146


All groundwater sampling within the study area will be


• "Field Groundwater Sampling Report Form" contains all

relevant information concerning ground water evacuation and

sampling.


sample movement from the point of collection to the point

of analyses.

3.8 SURFACE WATER SAMPLING

3.8.1 PURPOSE

The purpose of surface water sampling within the study area is

to obtain representative surface water samples for radiological

and hazardous constituents analyses. Laboratory analytical

results will identify what contaminants are suspended in the

surface water and whether surface water is transferring

contaminants. Current knowledge of past activities concerning

radioactive and hazardous materials storage, handling and

disposal will control the selection of surface water sampling

locations. The observation of specific contaminants will assist in

the identification of radiological and hazardous contamination

sources.


The samples to be collected will be discrete or composite

samples which represent conditions at the site sampled at the

time of sampling. The location and accessibility of the surface

water stream will dictate the equipment to be used for sampling.

The two most prevalent pieces of equipment to be used for

- 54- AR100147

surface water sampling are a pond sampler and a weighted bottle

sampler.

The pond sampler consists of an adjustable clamp attached to the

end of a long pole. The sample is collected in a jar or beaker

which is secured in the clamp and transferred to a pre-cleaned

container.

The weighted bottle sampler consists of a glass bottle, weight

sinker, bottle stopper, and a line used to open the bottle and to

lower and raise the sample. The sampler is lowered to the

desired sampling depth, the stopper is pulled out by a sharp pull

of the line, the bottle is allowed to fill and is raised to the

surface. The bottle will be used as the sampling container or the

contents will be transferred to a pre-cleaned container.


Upon arrival at the sampling site a plastic drop cloth will be

placed on the ground near the designated sampling point.

Samples will be collected avoiding any surface debris. When

collecting samples from open water bodies, boats, pully lines, or

pipe extensions will be used as needed to assist in sample

collection.

The containers will be identified with the appropriate information

described in Section 7.4.

Upon collection of the surface water samples, the RCS will

perform a radiological survey of the sample container and

package the containers in accordance with CNSI Procedure

RA-OP-001.

- 5 5 -AR100148

3.8.4 LIMITATIONS

Once the surface water samples are collected in the appropriate

type of containers and any necessay preservative is added, the

samples will be stored and cooled to 4 degrees C (primarily for

hazardous constituents). The samples will be transported to the

analytical laboratory and analyzed within the specified holding

time. In the event the surface water samples are not collected

per these specifications, the results will be considered "void".


All surface water sampling within the study area will be


• "Field Sampling Report Form" contains all relevant

information concerning surface water sampling.

• "Chain of Custody Form" serves as a means of documenting

sample movement from the point of collection to point of

analyses.

3.9 CONCRETE/ASPHALT CORING AND SOIL SAMPLING

3.9.1 PURPOSE

The purpose of concrete/asphalt coring is to provide an access

point in areas where suspected contamination has been

identified. Once the access point has been established by coring,

the underlying soil or materials can be sampled.

Areas where concrete or asphalt overlie suspected contamination

include:

• Concrete cap in the basement of the Personnel Building.

• Portions of the sidewalks within the study area.

• Portions of the asphalt roads within the plant site area.

- 5 6 -AR100149

• Concrete covers over the two underground silos.


A commercial grade concrete/asphalt core drilling machine will be

used to provide an access for sampling. Due to limited coring

activities, a light duty machine will be used. An electrical

powered core drilling machine will be required due to use in some

confined space areas.


The concrete/asphalt core drilling machine will be operated per

the manufacturing procedures. In the event, upon coring an

access point, a void is encountered underlying the

concrete/asphalt, a portable borehole camera will be used to

observe and document the void space and contents within the

void space. The air space within the void space will be

monitored to detect the presence of explosive atmospheres or

toxic gases.

Because the media to be sampled may be variable, the following

methods or techniques may be utilized:

• Section 3.3 Surface Soil Sampling

• Section 3.4 Drilling and Subsurface Soil Sampling

• Section 3.7 Groundwater Sampling

3.9.4 LIMITATIONS

Concrete/asphalt core samples will be limited by access

constraints.


- 5 7 -AR100150

characterization tools and equipment and to package solid and liquid waste

generated during site characterization.

4.3 STUDY AREA SURVEY

Prior to conducting field characterization activities a detailed location map

will be constructed. This map will include all portions of the study area,

such as buildings, roads, property lines, fence lines, monitoring wells and

other man-made features. In addition to the location map, a topographic

map with 2' contours will be constructed and shown on the location map.

The grid system, consisting of 10'x10' grids (southern section) and

20'x20' grids (northern section) will be established in the field and will be

used for geophysical and radiological survey methodologies.

4.4 ACCESS LOGISTICS

Due to the extensive geophysical and radiological characterization activities

within the study area, unobstructed access will be required for movement

of personnel and equipment. The area north of the Abandoned Canal has

good access. However, the southern portion of study area has poor

access due to the heavy undergrowth of vegetation. This undergrowth will

be cut and removed. The larger hardwood trees will not be cut unless

required under specific circumstances. The removal of the undergrowth

will be cut with hand tools and special attention will be given to avoid

contact with the wide-spread occurrence of poison ivy.

5.0 LABORATORY ANALYTICAL PARAMETERS

The characterization plan is designed to determine the type and extent of

radiological and hazardous constituents. The parameters for laboratory analyses

were selected based on knowledge of past radioactive and hazardous material

handling practices and the properties of the contaminants.

- 5 9 -AR100151

4.0 PRELIMINARY ACTIVITIES

Prior to conducting characterization activities several preliminary activities will

be performed to prepare the study area and provide for an orderly progression

of work. The major preliminary activities include ensuring the appropriate

regulatory licenses are in place, setting up the staging area and field office,

surveying the study area, and clearing the study area to allow easy access.

4.1 LICENSING

CNSI possesses Radioactive Material License No. 39-23004-01,

Amendment No. 3, which authorizes receipt, use, and/or possession of

radioactive material incident to:

• transport in packages or containers;

• decontamination of facilities, equipmentand containers;

• solidification and treatment of wastes;

• packaging for transport; and

• any activity related to site characterization studies.

In accordance with Condition No. 14 of the above referenced license, CNSI

will obtain written authorization from the NRC to conduct characterization

and remediation activities under the license.

4.2 STAGING AREA/FIELD OFFICE

Upon mobilization and with the permission of SLC, a field office will be set

up at the Vance/Walton property (provided the property is available for

use). The garage section will serve as the field office and storage area for

equipment. Storage areas adjacent to the garage will be used to place

large and bulky supplies required during site characterization. A

decontamination area will also be set up within the boundaries of the

Vance /Walton property. This area will be used to decontaminate

- 58- AR100152

5.1 RADIOLOGICAL ANALYSES

5.1.1 RADIOLOGICAL ANALYSES PARAMETERS

As described in previous sections, the owners and operators of

the study area have used many different radioisotopes in the

manufacturing of radioactive products. The specific radio-

isotopes, quantities used, and the time period in which these

products were manufactured as well as the waste handling

practices for solid waste and liquid effluents from radioactive

production activities lack detailed documentation.

In order to develop a list of radioisotopes which have been used

at the site, License 37-30-2/37-00030-2 and License

37-00030-8 were reviewed. The first column in Table 5.1 shows

radioisotopes which were licensed at the study area. The second

column shows the half life of each radioisotope; the third column

shows the approximate licensed amounts per year. Although the

licensed amounts may not reflect the actual amounts processed,

it does provide an estimate.

From Table 5.1, several radioisotopes can be deleted from the

analytical parameter list based on their half life and the number

of half lives that have occurred from the date of fast receipt to

the present. These radioisotopes include Cerium-144 (144Ce),

Polonium-210 (210Po), Promethium-147 (147Pm), and

Ruthenium-106 (109Ru). Because 85Kr is a noble gas it is also

deleted from the parameter list.

There are four radioisotopes including 3H, 137Cs, 226Ra, and ^Sr

that have been detected in previous investigations within the

study area. The analytical methods necessary to detect these

radioisotopes include liquid scintillation, gamma spectroscopy and

-60- AR100153

radiochemistry. The analytical methods, limit of quantification

(LOQ), required sample size, and instrumentation are shown on

Tables 5.2 and 5.3.

Since liquid scintillation counting necessary to detect 3H will also

identify 14C, 14C has been included in the parameter list.

Gamma spectroscopy will be necessary to identify 137Cs and226Ra and will also identify "'Co, a°4TI( Actinium-227 (227Ac),

Neptunium-237 (237Np), and 241Am. These radioisotopes have

been included in the parameter list.

identification will require radiochemistry. Due to the

observed distribution of "Sr in groundwater and soil at the study

area and documentation of large-scale production lines involving

"Sr, separate radiochemistry method will be required.

63Ni will also require radiochemistry for identification, however,

given the limited licensed amounts and lack of detection in

previous investigations, this radioisotope will be analyzed on a

limited basis.

5. 1 .2 GROUNDWATER AND SURFACE WATER ANALYSES

Selected groundwater and surface water samples will be sent to

a laboratory and analyzed by liquid scintillation and gamma

spectroscopy methods. In addition, gross alpha and gross beta

analyses will be performed on all water samples as a screening

tool to reduce analytical costs and increase sample

turn-around-time. Based on the results of gross alpha and gross

beta, additional analyses may be required. For example, if gross

beta shows positive results, then "'Sr radiochemical analyses will

- 61 -AR100154

be performed. Refer to Table 5.2 for the radiological laboratory

analytical methods for water samples.

5.1.3 SURFACE SOIL AND SUBSURFACE SOIL ANALYSES

Based on direct field measurements using a 2" x 2" Nal detector,

pancake GM Probe, and alpha detector soil samples will be sent

to a laboratory and analyzed by liquid scintillation (distillation) and

gamma spectroscopy methods. Again, gross alpha and gross

beta will be used as a screening tool. Positive results from gross

beta will indicate the need for additional analyses. Refer to Table

5.3 radiological analytical laboratory methods for soil samples.

- 6 2 -AR100155

TABLE 5.1.

US RADIUM CORPORATION AND SAFETY LIGHT CORPORATIONLICENSED RADIOISOTOPE AMOUNTS

RADIOISOTOPE

Hydrogen-3 ('H)1

Carbon-14 (14C)

Cobalt-60 (•"Co)

Nickel-63 (63Ni)

Krypton-85 (MKr)

Strontium-90 (""Sr)1

Cesium-137 ('"Cs)1

Cerium-144 (144Ce)

Promethium-147 (147Pm)

Ruthenium- 106 (109Ru)

Thallium-204 (""TO

Polonium-210 (210Po)

Actinium-227 (227Ac)

Neptunium-237 |"7Np)

Americium-241 (241Am)

Radium-226(Z2aRa)1-a

HALF UFE

12.28 years

5730 years

5.271 years

100.1 years

1 0.72 years

28.6 years

30.17 years

284.3 days

2.6234 years

368.2 days

3.779 years

138.378 days

21. 773 years

2 140000 years

432.2 years

1 600 years

LICENSED AMOUNT/YEAR

300 Ci to 350,000 Ci

500 mCi

50-Ci

200 mCi to 5 Ci

1,OOOCito 1,500 Ci

lOOCi

250 Ci

5Ci

100C1

200 mCi to 1 Ci

25 Ci

10Cito 15 Ci

1 Ci

6 mCi to .01 Ci

1 mCi to 32 Ci

designated quantity unspecified

1 DETECTED IN GROUNDWATER AND/OR SOIL2 REGULATED BY PENNSYLVANIA DEPARTMENT OF HEALTH

- 6 3 -AR100156

TABLE 5.2RADIOLOGICAL LABORATORY ANALYTICAL METHODS FOR WATER

METHOD

Liquid Scintillation

3H14C

Gamma Spectroscopy

137Cs2MRa•°Co204T|

227 Ac237Np241Am

Radiochemistry *°Sr

LOQ SAMPLE SIZE INSTRUMENTATION

1 00 mis Liquid ScintillationAnalyzer

5 pCi/mL

1 000 mLs Gamma Spectrometer

0.3 pCi/mL5 pCi/mL

0.3 pCi/mL

0.5 pCi/mL0.5 pCi/mL0.1 pCi/mL

5 pCi/mL 1

-

L Liquid ScintillationAnalyzer

Radiochemistry **Ni

Gross Alpha/Beta

Alpha EmittersBeta Emitters

300 mLs Gross Alpha/Beta Counter

74 pCi/L48 pCi/L

L LitermLs MilliliterpCi Picocurie

Level of Quantitation (LOQ) - A LOQ is established for each method that is higher than the Method DetectionLimit (MDL) by a factor of 3.3 to 10. Reports are done at the LOQ level instead of the MDL level because ofthe types of solid waste matrices that are often encountered and the matrix interferences that often occur withsolid waste samples. Matrix interferences can lead to false positives at the MDL level. Use of the LOQ givesa higher level of confidence that false positives are not reported.

Method Detection Limit (MDL) - The MDL is established according to a statistical analysis of data from thereplicate analysis of 7 to 10 spiked aliquots of laboratory deionized water (40 CFR Part 136, Appendix B).

-64 - AR100157

TABLE 5.3

RADIOLOGICAL LABORATORY ANALYTICAL METHODS FOR SOIL

METHOD LOQ


*H 50 pCi/ml14C

Gamma Spectroscopy

1I7Cs 3.0 pCi/a22sRa 20 pCi/g

wCo 3.0 pCi/o204J,

227 Ac 5.0 pCi/g

"7Np 5.0 pCi/g241 Am 5.0 pCi/g

Radio-chemistry *°Sr 5.0 pCi/g

SAMPLE INSTRUMEN-SIZE TATION

100 g LiquidScintillation

Analyzer

500 g GammaSpectrometer

100g LiquidScintillation

Analyzer

Radiochemistry "Ni

Gross Alpha/Beta

Alpha Emiters 46 pCi/g

Beta Emiters 1 0 pCi/g

10 g GrossAlpha/Beta

Counter

- 6 5 -AR100158

5.2 HAZARDOUS CONSTITUENT ANALYSES

5.2.1 HAZARDOUS CONSTITUENT ANALYSES PARAMETERS

Minimal documentation is available regarding the use and disposal

of hazardous constituents. From discussions and available

information, the hazardous constituents which are suspected to

have been used and/or disposed of within the study area are as

follow:

• Lead used in smelting operations in the Radium Vault and

Pipe Shop:

• Cyanide and silver used in plating operations in the Etching

Building; and

• Solvents used for cleaning in the Etching and Main Buildings.

Hazardous constituent analyses will be used to determine the

presence and extent of hazardous constituent contamination and

determine whether waste removed during remediation would be

classified as a hazardous or mixed (hazardous and radioactive)

waste. Any waste determined to be a hazardous or mixed waste

will be managed in accordance with the requirements of the

Resource Conservation and Recovery Act (RCRA).

The hazardous constituent parameters which may be analyzed

and associated analytical methods are shown on Tables 5.4 and

5.7.

5.2.2 GROUNDWATER AND SURFACE WATER ANALYSES

Although numerous studies have been performed to determine

the concentration of radioisotopes in the study area groundwater

analyses for hazardous constituents have not been performed.

Selected groundwater samples will be sent to a contract

- 6 6 -AR100159

laboratory and analyzed for metals, cyanide, volatile organics,

and semi-volatile organics. The analytical methods, limit of

quantification, required sample size, and instrumentation are

shown on Table 5.4. The constituents which are classified as

semi-volatile organics and volatile organics are shown on Tables

5.5 and 5.6.

- 6 7 -AR100160

TABLE 5.4HAZARDOUS CONSTITUENT LABORATORY ANALYTICAL METHODS FOR WATER

PARAMETER/ANALYSIS

Metals

Antimony

Arsenic

Beryllium

Cadmium

Chromium

Copper

Lead

Mercury

Nickel

Selenium

Silver

Thallium

Zinc

Total Cyanide

Semi-Volatile Organics w/LibrarySearch

Volatile Organics w/Library Search

LOQ

170//g/L

15//g/L

50 j/g/L

15//g/L

45//Q/L

45//g/L

75 j/g A.

0.3 UQIL

120fjg/L

9 j/g/L

50//g/L

630 j/g/L

100j/g/L

0.02 mg/L

•SeeTable 5.5

* See Table5.6

SAMPLE SIZE (U

0.500

"•

1.0

1000 mis x 2

40 mis x 4

METHOD

6010

7060

6010

6010

6010

6010

6010

7470

6010

7740

6010

6010

6010

9010

8270

8260

INSTRUMENTS

1C?

GFAA

ICP

ICP

ICP

ICP

ICP

AACVA

ICP

GFAA

ICP

ICP

ICP

UV-VIS-SPEC

GC/MS

GC/MS

mLs • MillilitersL - LitersV - Micrograms

ICP - Inductively Coupled Plasma SpectrometerGFAA - Graphite Furnace - Atomic Absorption SpectrometerAACVA - Atomic Absorption • Cold Vapor AnalyzerUV-Vis-Spec - Ultra-Violet-Visible SpectrophotometerGC/MS - Gas Chromatograph/Mass Spectrometer

- 6 8 -AR100161

5.2.3 SURFACE SOIL AND SUBSURFACE SOIL ANALYSES

Based on suspected or known waste management activities

select soil samples will be sent to a laboratory for hazardous

constituent analyses. Analyses of total metals, semi-volatile, and

volatile organics will be performed as screening tools when the

presence of hazardous constituents is unknown. Analyses of

teachable levels of metals and organics using the Toxicity

Characteristic Leaching Procedure (TCLP) will be performed to

determine the presence of hazardous and mixed (hazardous and

radioactive) waste when the presence of hazardous constituents

is suspected.

Analyses of cyanide and sulfide will be performed on samples

from select locations to assist in identifying contamination from

. the disposal of plating waste.

Analyses of total petroleum hydrocarbons will be performed on

samples from select locations to assist in identifying

contamination associated with the diesel fuel spill.

The analytical methods, LOQ, required sample size for soil, and

instrumentation are shown on Table 5.7.

The constituents which are classified as semi-volatile and volatile

organics and associated LOQ's are shown on Tables 5.5 and 5.6.

- 6 9 -AR100162

TABLE 5.5LIMITS OF QUANTIFICATION FOR SEMI-VOLATILE ORGANICS

COMPOUND

Pyridine

N-Nitrosodimethylamine

Aniline

Bis(2-Chloroethyl)ether

2-Chlorophenol

1 ,3-Dichlorobenzene

Phenol



Benzyl Alcohol

Bis(2-Chloroisopropyl)ether

Hexachloroethane

2-Methylphenol (o-Cresol)

N-Nitrosodi-n-propylamine

Nitrobenzene

4-Methylphenol (p-Cresol)

Isophorone

2-Nitrophenol

2,4-Dimethylphenol

Bis ( 2-Chloroethoxy) methane

1 ,2,4-Trichlorobenzene

2,4-Dichlorophenol

Naphthalene

4-Chloroaniline

Hexachlorobutadiene

2-Methylaniline

LOQ (ppm)

0.02

0.02

0.01

0.02

0.01

- 0.01

0.01

0.01

0.01

0.01

0.02

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

- 7 0 -AR100163


(Continued)

COMPOUND

4-Chloro-3-methyl phenol

Hexachlorocyclopentadiene

2,4,6-Trichlorophenol

2,4, 5-Trichlorophenol

2-Chloronaphthalene

2-Nitronaniline

Acenaphthylene

Dimethyl phthalate

2,6-Dinitrotoluene

3-Nitroaniline

Acenaphthene

2,4-Dinitrophenol

Dibenzofuran

4-Nitrophenol

2,4-Dinitrotoluene

Fluorene

4-Chlorophenylphenyl ether

Diethyl phthalate

4-Nitroaniline

4,6-Dinitro-2-methylphenol

N-Nitrosodiphenylamine

Azobenzene

4-Bromophenylphenyl ether

Hexachlorobenzene

LOO (ppm)

0.01

0.02

0.01

0.01

- 0.010.02

0.01

0.01

0.01

0.02

0.01

0.02

0.01

0.02

0.01

0.01

0.01

0.01

0.03

0.01

0.01

0.01

0.01

0.01

-71 -AR100164


(Continued)

COMPOUND

Pentachlorophenol

Phenanthrene

Anthracene

Carbazole

Di-n-Butyl phthalate

Fluoranthene

Pyrene

Butylbenzyl phthalate

Benzo(a)anthracene

3,3-Dichlorobenzidine

Chrysene

Bis(2-ethylhexyl)phthalate

Di-n-octyl phthalate

Benzo(b)fluoranthene

Benzo(k)fluoranthene

Benzo(a)pyrene

Indenod ,2,3-cd)pyrene

Dibenzo(a,h)anthracene

Benzo(g,h,i)perylene

LOQ (ppm)

0.01

0.01

0.01

0.01

' 0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.01

0.02

0.02

0.02

0.02

LOQ Limit of Quantificationppm Parts per Million

- 7 2 -AR100165

TABLE 5.6LIMITS OF QUANTIFICATION FOR VOLATILE ORGANICS

COMPOUND

Chloromethane

Vinyl Chloride

Bromomethane

Chloroethane

Trichlorofluoromethane

Acrolein

1 , 1 -Dichloroethy lene

1 ,1 ,2-Trichloro- 1 ,2,2-Trifluoroethane

Acetone

Carbon Disulfide

Allyl Chloride

Methylene Chloride

Trans-1 ,2-Dichloroethylene

Acrylonitrile

Vinyl Acetate

1,1-Dichloroethane

2-Butanone (MEK)

Chloroform

1,1,1-Trichloroethane

Cyclohexane

Carbon Tetrachloride

Benzene

1 ,2-Dichloroethane

Trichloroethylene

1 ,2-Dichloropropane

Dibromomethane

LOQ (ppm)

0.010

0.009

0.015

0.026

0.010

0.034

0.007

0.010

0.025

0.007

0.008

0.006

0.007

0.011

0.012

0.006

0.015

0.007

0.012

0.007

0.009

0.005

0.006

0.013

0.011

0.011

- 7 3 -AR100166

TABLE 5.6LIMITS OF QUANTIFICATION FOR VOLATILE ORGANICS

(Continued)

COMPOUND

Bromodichloromethane

2-Chloroethyl Vinyl Ether

Trans- 1 ,3-Dichloropropene

4-Methyl-2-Pentanone; MIBK

Toluene

Cis-1 ,3-Dichloropropene

1 , 1 ,2-Trichloroethane

Tetrachloroethylene

2-Hexanone

Dibromochloromethane

1 ,2-Dibromomethane

Chlorobenzene

1 ,1 ,1 ,2-Tetrachloroethane

Ethylbenzene

m,p-Xylene

o-Xylene

Styrene

Bromoform

1 , 1 ,2,2-Tetrachloroethane

1,2,3-Trichloropropane

1 ,3-Diochlorobenzene



LOO (ppm)

0.005

0.009

0.005

0.011

0.010

0.006

0.0096

0.028

0.011

0.006

0.006

0.011

0.005

0.005

0.006

0.006

0.006

0.007

0.013

0.007

0.018

0.019

0.014

LOQ Limit of Quantificationppm Parts per Million

- 74-AR100167

TABLE 5.7HAZARDOUS CONSTITUENT LABORATORY ANALYTICAL METHODS FOR SOIL

PARAMETER

Total Metals

Arsenic

Barium

Cadmium

Chromium

Lead

Mercury

Nickel

Selenium

Silver

Total Cyanide

Total Sulftde

TCLP Metals

Arsenic

Barium

Cadmium

Chromium

Lead

Mercury

Selenium

Silver

TCLP Organics

Benzene

Carbon tetrachloride

Chlorobenzene

o-Cresol

m-Cresol

p-Cresol

LOQ(ppm)

0.75

10.0

0.75

2.25

3.75

0.15

6.0

0.45

2.50

1.0

1.0

0.02

0.02

0.02

0.05

0.08

0.003

0.01

0.05

0.084

0.153

0.187

0.04

0.04

0.04

SAMPLE SIZE(a)

100

100

100

200

•ff

200

METHOD

7060

6010

6010

6010

6010

7470 *

6010

7740

6010

9010

9030

1311

7060

6010

6010

6010

6010

7470

7770

6010

1311/8260/8270

INSTRUMENT

GFAA

ICP

ICP

ICP

ICP

AA-CVA

ICP

GFAA

ICP

UV-Vis Spec

UV-Vis Spec

TCLPExtractor

GFAA

ICP

ICP

ICP

ICP

AA-CVA

GFAA

ICP

GC/MS•

- 7 5 -AR100168

TABLE 5.7HAZARDOUS CONSTITUENT LABORATORY ANALYTICAL METHODS FOR SOIL

(Continued)

PARAMETER

Cresol

1 ,4-Oichlorobenzene

1 ,2-Dichloroethane

1 , 1 -Dichloroethylene

2,4-Dinitrotoluene

Hexachlorobenzene

Hexachloroethane

Methyl ethyl ketone

Nitrobenzene

Pentrachlorophenol

Pyridine

Tetrachloroethylene

Trichloroethylene



Vinyl chloride

Semi-Volatile Organicsw/Library Search

Volatile Organicsw/Library Search

Total PetroleumHydrocarbon

LOQ(ppm)

0.12

0.323

0.238

0.119

0.04

0.04

0.04

0.255

0.04

0.04

0.08

0.476

0.221

0.04

0.04

0.153

SeeTable 5.5

SeeTable 5.6

100mg/kg

SAMPLE SIZE(g)

4 0 g x 2

2 0 g x 2

60gms

METHOD

-

-

8270

8260

9070/413

INSTRUMENT

GC/MS

GC/MS

Gravimetric

- 7 6 - AR100169

6.0 SITE SPECIFIC CHARACTERIZATION PLANS

6.1 SURFACE GEOPHYSICAL SURVEYS

Surface geophysical surveys will be conducted within the study area to

locate and define the boundaries of buried waste, map conductive

contaminant plumes and locate underground utilities. The specific

objectives of conducting surface geophysical surveys within the study area

are as follows:

• Delineate the boundaries of the Abandoned Canal, East and West

Plant Dumps, Underground Silos, and the disposal area under Pipe

Shop;

• Identify physical forms and quantities of buried waste;

• Locate drain lines and select adjacent soil sampling locations;

• Locate underground utilities so that they may be avoided during soil

sampling; and,

• Identify contaminant plumes for correlation with groundwater

sampling locations.

Surface geophysical surveys will be the first characterization technique

performed within the study area. Prior to conducting the surface

geophysical surveys the area will be cleared of undergrowth and a 20' x

20' grid pattern established. An EM survey as described in Section 3.1

will be conducted first by taking readings with an EM-31 or equivalent

instrument over the grid lines shown on Figure 2. The magnetometer

survey will be conducted following the EM survey to identify buried ferrous

objects. The raw data from these two surveys will be reviewed in the field

and areas where anomalies are indicated will be selected for surveying

- 7 7 -AR100170

using GPR. As described in Section 3.1.2, GPR will provide a

cross-sectional picture which will be used to estimate the configuration

and depths of buried disposal areas and buried waste. Based on available

information concerning previous disposal activities, is anticipated that GPR

will be conducted over the suspected area of the Abandoned Canal, East

and West Plant Dumps, Underground Silos, and Pipe Shop (see Figure 2).

If required the geophysical data will be computer processed to provide for

spatial corrections, overlay the electromagnetic and GPR data, and/or

contour the data.

6.2 RADIOLOGICAL SURVEYS

Radiological surveys with portable radiation detectors will be performed to

determine the location of areas with radiation levels in excess of

background levels, the extent of contamination in activity levels, and

affected area or volume. The procedures and equipment described in

Section 3.2 will be used for the radiological surveys.

6.2.1 GROUND SURVEYS

A continuous gamma scan will be performed over the study area

grounds along a 10' x 10' (see Figure 3) grid in areas with a

moderate to high potential of contamination and a 20'x20' grid

in areas with a low potential of contamination using 2" x 2" Nal

detector. The locations of direct radiation exceeding 2 times the

background level will be marked on site sketches or maps and

identified for consideration for surficial soil sampling.

Numerous areas located south of the SLC Main Building are

documented disposal areas for radioactive waste or have been

contaminated through the storage and use of radioactive

materials within the study area. Radiological contamination has

- 7 8 - AR100171

also been documented in the northern part of the SLC study area

although to a much lesser degree.

(The majorityjprthe buildings within the sjtudyîreajiaye been

icjDntarnjr@ted_or are susj)ected of being contaminated through

jthe~storage~~and yse^ ofj-adipactive. materials. Most qf_the/

buildings^râbandonecl[oraûsed solely for storage. However,

the Nuclear Building, Machine Shop, and portions of the Main and

Etching Buildings are currently used for production operations.

Radiological surveys will be performed on the interior of these

buildings in accordance with the procedures in Section 3.2.

jPrior to entering the buildings to perform radiological suryeys_an

inspection wiljjae performed ojjthe structurafintegrityJ/Tnt is~)" ~~ • —— __. ^- .—I

(determinelttrlat~the~bu iId inrglsTunsaf eTtbênt¥r measureiTwiII be

radiologicaT surVey^~withbufêlTteTirTg~the

of ~mountihg~radiation detection "devices~oni

(extension rods or suspending the detectors with cords or ropes;

(The^tructuraLintegrity- of the Old House .and .Personnel _0f f ice

r"Buildingjppears to bejjnsgundj^

As many of the buildings are utilized for the storage of

contaminated and uncontaminated items a general inventory of

the contents will be made of the items in place. The inventory

will note the types of items stored, configuration, access

constraints, and locations of "hot spots" on the items. In no

event will the stored items be moved without the prior approval

of the RCS and SLC Radiation Control Officer (RCO).

- 79 -AR100172

Composite samples of the construction materials will be taken as

determined in the field within rooms or areas which have similar

contamination. These samples will be analyzed for gross alpha,

gross beta, liquid scintillation, and gamma spectroscopy. If the

analytical results indicate elevated gross beta the samples will be

analyzed by radiochemistry for ^Sr. Samples taken from portions

of the Main Building may also be analyzed by radiochemistry for63Ni.

6.2.3 BOREHOLE SURVEYS

Twenty-three boreholes will be drilled within the study area (see

Figure 5) to allow for the identification of radiological and/or

hazardous contaminants through the laboratory analyses of

subsurface soil samples or direct field measurement. All

boreholes will be gamma logged using the procedures in Section

3.2 and the gamma measurements recorded with depth.

Samples will be collected from all 23 boreholes. Samples from

9 of the boreholes will be submitted for laboratory analyses.

Samples from the remaining 14 boreholes will be retained and

analyzed if additional information is required.

The gamma measurements will be compared to laboratory

analyses to determine whether a correlation exists between the

two sets of data.

6.2.4 TEST TRENCH SURVEYS

Nine test trenches will be excavated within the study area (see

Figure 6) to allow for the identification of radiological and

hazardous contaminants through the laboratory analyses of

subsurface soil samples or direct field measurements. All test

trenches will be scanned for gamma radiation using the

- 8 0 -AR100173

procedures in Section 3.2. Elevated measurements will be noted

on site sketches or maps. The results of the gamma survey will

be used to select soil sampling locations within the test trenches.

6.3 SOIL SAMPLING

Both surface and subsurface soil samples will be collected within the study

area.

Surface soil samples (SS) will be collected at the following locations:

• Predetermined locations within 100'x100' grid blocks along the

southern portion of the study area;

• Site specific locations at areas of known contamination;

• Locations of observed contamination based on radiological and

geophysical surveys (the locations will be selected in the field during

the characterization activities); and

• Within test trench excavations.

The methodology for collecting the surface soil samples is described in

Section 3.3. The locations of the surface soil samples are shown on

Figures 3, 4, and 6. The radiological and hazardous constituents for

laboratory analyses are shown on Tables 6.1, 6.2, and 6.3.

The laboratory analytical results from the surface soil samples will identify

specific contaminants, concentrations, and the lateral extent of

contamination.

Three types of subsurface soil samples will be collected: deep subsurface

samples (DS), borehole soil samples (BH), and concrete core samples. All

subsurface soil samples will be collected at site specific location of known

contamination.

-81 -AR100174

Deep subsurface soil samples will be collected from 0.5' to 4.5' and

composited into one sample for laboratory analyses. The 0-0.5' increment

from the deep subsurface soil sampling location will be collected as a

discrete surface soil sample or composited with other similar surface soil

samples. Borehole subsurface soil samples will be collected in 4'

increments from the land surface to a specific target depth (i.e., bottom of

Abandoned Canal). Of the 23 boreholes to be drilled samples will be

collected and analyzed by a laboratory from 9 boreholes. Samples will be

collected and retained from the remaining 14 boreholes. If no correlation

can be made between analytical results and gamma logging of the

boreholes the retained samples may also be analyzed.

The methodology for collecting the subsurface soil samples is described in

Section 3.4. The locations of the subsurface soil samples are shown on

Figures 4 and 5. The radiological and hazardous constituents for

laboratory analyses are shown on Tables 6.4, 6.5, and 6.6.

The laboratory analytical results from the subsurface soil samples will

identify specific contaminants, concentrations, and the vertical extent of

contamination.

A summary of the soil samples and analytical parameters is shown on

Table 6.7. Site specific soil sampling strategies are described below.

6.3.1 GRID SURFACE SOIL SAMPLING (100' X 100' GRID)

Surface soil sampling (0-6") will be conducted at 21 locations

within the southern portion of the study area (see Figure 3)

within 100' x 100' grid blocks. Within each grid block a soil

sample will be collected at the center and at four points midway

between the center and the block corners and then composited

- 8 2 -AR100175

into one sample for laboratory analyses. The results from this

sampling will provide an unbiased indication of surficial

contamination showing specific contaminants and corresponding

concentrations of contaminants. All samples will be analyzed for

radiological parameters.


At one time in the past, the Abandoned Canal (No. 37, Figure 1)

was open throughout the entire length of the study area.

Available documentation indicates the canal portion has a high

potential for gross contamination. The Abandoned Canal extends

from the east property boundary to the west property boundary.

Although the East Lagoon, East Plant Dump, West Lagoon, and

West Plant Dump appear to be part of the canal system, these

sites will be characterized separately.

Upon definition of the boundaries of the Abandoned Canal by

geophysical and/or radiological surveys, a total of 10 boreholes

will be advanced through the canal to an anticipated depth of 12'

below land surface (see Figure 5). Samples will be collected at

4' intervals from each borehole. Samples collected from 3

boreholes (37-BH-1, 37-BH-4, and 37-BH-7) will be sent to a

contract laboratory for analyses. Samples collected from the

remaining seven boreholes will be retained and analyzed if

additional data is required.

Five test trenches will be excavated across the width of the

Abandoned Canal (see Figure 6). One composite soil sample will

be collected for laboratory analyses from each test trench.

- 8 3 -AR100176

The Abandoned Canal has a high potential for multiple

contaminants; therefore, a wide variety of radiological and

hazardous constituent parameters have been selected for

analyses.

6.3.3 EAST LAGOON

Up to the period of 1960, liquid waste was routed to the East

Lagoon (No. 18, Figure 1). A total of 4 surface soil samples will

be collected along the banks of the East Lagoon just above the

water line and composited into one sample for laboratory

analyses (see Figure 4). Analytical results from this sample will

provide an estimate of surficial contamination within the East

Lagoon.

A borehole will be advanced along the southern edge of the

lagoon and samples collected and analyzed at 4' intervals to

provide information concerning the depth of contamination and

identify migration of contaminants from the lagoon (see Figure 5).

Information concerning the types of liquid waste disposed of in

this lagoon from the Main Building provided guidance in the

selection of the analytical parameters.

6.3.4 WEST LAGOON

Up to the period of 1960, liquid waste was routed to the West

Lagoon (No. 30, Figure 1). A total of 7 surface soil samples will

be collected along the banks of the West Lagoon just above the

water line and composited into two samples for laboratory

analyses (see Figure 4). Analytical results from these samples

will provide an estimate of surficial contamination within the

West Lagoon.

- 84 -AR100177

Two boreholes will be advanced along the southern edge of the

lagoon and samples collected at 4' intervals to provide

information concerning the depth of contamination and the

migration of contaminants from the lagoon (see Figure 5).

Samples collected from borehole 30-BH-1 will be sent to a

contract laboratory for analyses. Samples collected from

borehole 30-BH-2 will be retained and analyzed if additional

information is required.

Information concerning the types of liquid waste disposed of in

the lagoon from the Etching Building provided guidance in the

selection of analytical parameters.

6.3.5 EAST AND WEST PLANT DUMPS

Prior to 1970, the Plant Dumps were used to dispose of

radioactive waste. These sites appear to be part of the

Abandoned Canal. Geophysical and radiological surface surveys

will be necessary to assist in delineating the boundaries of the

Plant Dumps prior to soil sampling. To characterize the lateral

extent of contamination at both Plant Dumps, 3 surface soil

samples and a 0-6" sample from a deep subsurface soil sample

location will be collected and composited into one sample for

laboratory analyses.

To determine the vertical extent of contamination, a 0.5'-4.5'

deep subsurface soil sample will be collected at both Plant

Dumps (see Figure 4).

As described in Section 6.4 one composite soil sample will be

collected from each test trench excavated through the Plant

Dumps (see Figure 6).

- 8 5 -AR100178

Similar to other portions of the Abandoned Canal, the potential

contaminants are numerous; therefore, a wide variety of

' radiological and hazardous constituents have been selected for

/ analyses.

6.3.6 LOCALIZED CONTAMINATED SOIL AREAS

The localized Contaminated Soil Areas include the following sites:

• Contaminated Soil Area in front of Above Ground Metal Silo

(No. 3, Figure 1).

• Contaminated Soil Area north of Machine Shop (No. 12,

Figure 1).

• Contaminated Soil Area under Loading Dock (No. 22, Figure

1).

• Contaminated Soil Area south of Radium Vault (No. 38,

Figure 1).

• Contaminated Soil Area east of 8'x8' Building (No. 41,

Figure 1).

These contaminated soil areas appear to be the result of

personnel traffic to and from adjacent buildings due to observed

contamination near the exit doorways.

The lateral extent of contamination appears to be limited and will

be verified by the radiological surface survey. At each site, three

surface soil samples will be collected and composited into one

sample for laboratory analyses.

At each site one location has been selected for a 0.5' to 4.5'

deep subsurface soil sampling to determine the vertical extent of

contamination (see Figure 4). The first increment (0-0.5') of the

- 8 6 -AR100179

deep subsurface sample will make up the third surface soil

sample for the composite.

Past use of materials within these buildings were used to select

parameters for analyses.


The Underground Silos (No. 17, Figure 1) were used during the

period of 1950-1960 for the disposal of solid radioactive waste

(see Section 2.5.14 for details). The approximate dimensions

and locations have been determined from existing information,

however, to obtain additional data and to verify historical data,

surface geophysical surveys will be conducted over and around

the Underground Silos.

CNSI has determined that direct sampling of the contents of the

Underground Silos poses unacceptable risks of contaminant

exposure to workers at the present time. As an alternative to

direct sampling, investigations will be conducted to verify and

determine the dimensions and type of construction of the

Underground Silos by sampling media (ie, soil and groundwater)

immediately outside or downgradient of the silos to infer the

specific constituents and activity within the confines of the silos.

Three surface soil samples will be collected within the fenced

area of the silos and composited into one sample for laboratory•

analyses (see Figure 4). The analytical results from this sampling

will characterize surficial contamination.

To characterize contamination with depth, 2 boreholes will be

advanced adjacent to each silo (see Figure 5). Soil sampling will

- 8 7 -AR100180

be conducted at 4' intervals from each borehole. The anticipated

target depth is 15' and/or at least 2' below the water table.

Samples collected from borehole 17-BH-1 will be sent to a

contract laboratory for analyses. Samples collected from

borehole 17-BH-2 will be retained and analyzed if additional


Information regarding the suspected contents of the silos was

used to select parameters for analyses.

6.3.8 CONTAMINATED SOIL AREAS ADJACENT TO OLD BERWICKROAD AND VANCE/WALTON PROPERTY

These two sites are represented by contaminated soil piles. The

Contaminated Soil Area adjacent to Old Berwick Road (No. 34,

Figure 1) is located north of the Annex Building (northwest corner

of study area). The origin of this 226Ra contaminated soil pile is

unknown; however, the soil may have resulted from grading

activities when the Annex Building was constructed. The

Contaminated Soil Area from the Vance/Walton Property is

located southeast of the Above Ground Metal Silo and is the

result of the removal of 137Cs contaminated soil from the

Vance/Walton property.

Upon completion of a surface radiological survey, the lateral

extent of contamination will be determined by 2 surface soil

samples taken at the visible edges of the piles and composited

into one sample for laboratory analyses (see Figure 4).

The vertical extent of contamination and concentration of

contaminants within the piles will be determined by 3 deep

subsurface soil coring locations (in this case subsurface refers to

below the surface of the pile). These three deep subsurface

- 8 8 - AR100181

samples will be composited into one sample for laboratory

analyses. The maximum depth of subsurface sampling should

not exceed 5'.

Knowledge of the contaminants within the two soil piles was

used to select parameters for analyses.

6.3.9 PERSONNEL OFFICE BUILDING

The Personnel Office Building (No. 27, Figure 1) is of particular

interest due to a suspected "dry well" in the basement which

may have been used for the disposal of radioactive waste (226Ra

and Sr).

Direct sampling of this well would be extremely hazardous due to

the instability of the building structure and inherent dangers

involved in confined space entry. If disposal activities did take

place in the well in the Personnel Office Building, given the

permeable nature of the underlying sediments and high mobility

of ^Sr, investigation of the downgradient groundwater should

provide information regarding the presence of contamination

within the well.

To assess whether contamination is migrating via groundwater,

a borehole will be advanced south of the Personnel Office

Building and samples collected and retained at 4' intervals (see

Figure 5). The anticipated depth for the borehole is 25' below

land surface. The samples will be analyzed if additional


- 8 9 -AR100182

6.3.10 PIPE SHOP

During 1948, 226Ra contaminated ductwork was disposed in a

portion of the open canal system. This area was backfilled and

the Pipe Shop (No. 29, Figure 1) was constructed over the

disposal location. Elevated radon levels within the Pipe Shop

support evidence of past disposal activities.

Detailed surface geophysical surveys will be carried out within

this portion of the study area to define the boundaries of solid

waste disposal. To characterize the contamination with depth,

one borehole (29-BH-1) will be advanced to the base of the

Abandoned Canal disposal area (see Figure 5). Soil samples will

be collected and retained at 4' intervals from the borehole. The

samples will be analyzed if additional information is required.

In the event the Pipe Shop completely overlies the disposal area

a concrete coring machine will be used to provide access for soil

sampling below the concrete (see Figure 5 and Section 3.9).

6.3.11 CONTAMINATED SOIL AREA NORTH OF LACQUER STORAGE

BUILDING

At some period in the past, direct disposal of solvents have been

reported to occur between the Main Building and the Lacquer

Storage Building.

During the early to mid-70's, an accidental release of heating fuel

(diesel) occurred near monitoring well No. 11 and also has been

detected, to a lesser degree, in adjacent monitoring wells.

To assess the potential extent of soil contamination due to the

disposal of solvent waste, 2 surface soil samples will be collected

- 9 0 - AR100183

from the 0-0.5' increment at the deep subsurface soil sampling

locations and composited into one sample for laboratory analyses

(see Figure 4).

The vertical extent of contamination will be determined by

comparing composite samples collected from 2 deep subsurface

soil sampling locations.

The vertical extent of diesel fuel contamination will be determined

by drilling a borehole adjacent to the suspected spill area (see

Figure 5). Soil samples will be collected and analyzed at 4'

intervals from the borehole. The soil samples collected at the

borehole location will be analyzed for hazardous constituents and

total petroleum hydrocarbons.

6.3.12 LIQUID WASTE BUILDING

As discussed in Section 2.5.17, the Liquid Waste Building (No. 7,

Figure 1) overlies the location of a below-grade vault. Prior to

1972, the below-grade vault was used to house a hold-up tank

and evaporator system and later used for liquid waste dilution.

During 1972, a flood damaged this facility and the below-grade

vault was filled in and the present Liquid Waste Building

constructed over this location. Damage from the flood resulted

in a release of contaminated liquid. Elevated radon levels within

the present structure support the presence of subsurface

contamination.

Two borehole locations have been selected adjacent to the Liquid

Waste Building (see Figure 5). Soil samples will be collected from

the boreholes at 4' intervals. Samples collected from borehole

7-BH-1 will be sent to a contract laboratory for analyses.

-91 -AR100184

Samples collected from borehole 7-BH-2 will be retained and

analyzed if additional data is required.

One concrete core will be conducted within the building to allow

for the collection of a subsurface soil sample (see Figure 5).

Radiological and hazardous constituent analyses conducted on

these soil samples will identify specific contaminants with depth

and the migration of contaminants from beneath the building.

6.3.13 OLD HOUSE

The Old House (No. 6, Figure 1) has been in the past and is

currently used to store radioactively contaminated equipment and

materials. To determine if any contamination has accumulated in

the dug-out earthen basement, 2 surface soil samples will be

collected and composited into one sample for analyses (see

Figure 4).

6.3.14 DRAIN LINES (DRAINAGE DITCH FROM EAST PLANT DUMP TO

SUSQUEHANNA RIVER)

The drainage ditch, beginning in the vicinity of the East Plant

Dump and terminating at the Susquehanna River (No. 33,

Figure 1) has been determined to be a source of radioactive

contamination (CNSI, 1990). Although the ditch accepts water

from the Multimetals NPDES discharge line (nonradioactive

effluent), the surface water and/or sediment along the drainage

ditch have been contaminated with radioactive constituents,

presumably due to surface contamination at the East Plant Dump.

One borehole will be advanced next to Monitoring Well No. 5,

and samples collected at 4' intervals and retained (see Figure 5).

- 9 2 - AR100185

Samples collected from the borehole will be analyzed if additional

data is required.

6.3.15 CONTAMINATED SOIL AREAS BETWEEN ABANDONED CANAL

AND RIVER

The Contaminated Soil Areas between the Abandoned Canal and

River (Nos. 13-16, Figure 1) may have resulted from the 1972

flood, which spread contamination from several known areas of

contamination (ie. Plant Dumps and Lagoons). The results of the

characterization activities conducted by CNSI during 1990 show

that the contamination appears to be isolated to surficial deposits

when road improvements were conducted along this area.

Grading of soils in this area removed the majority of observed

contamination. Upon completion of the radiological ground

survey along grid lines, specific areas of elevated contamination

will be identified.

Surficial soil samples and deep subsurface soil samples will be

collected at areas with elevated direct measurements. For the

purposes of this plan it is assumed that 12 surface soil samples

will be composited into 4 samples for analyses. Four deep

subsurface soil samples will be also collected for analyses.

However, the actual number and sampling locations will be

determined in the field. All samples will be analyzed for

radiological parameters.

6.3.16 SIDEWALK AREAS

The Main Building has been used in the past for the

manufacturing of radioactive products. Access from the Main

Building, during this time, resulted in the spread of contamination

to the sidewalk areas. Elevated areas have been identified near

- 9 3 -AR100186

the doorways. Four locations have been selected to core the

concrete and sample the underlying soils (see Figure 5). Samples

will be analyzed for radiological parameters.

6.4 TEST TRENCH EXCAVATIONS AND SAMPLING

Nine test trenches will be excavated and sampled within the study area to

investigate the subsurface conditions. Test trenches will be excavated in

accordance with the procedures in Section 3.6. Following excavation,

radiological surveying and soil sampling will be performed in accordance

with the procedures in Sections 3.2 and 3.3. Test trenches will be

excavated through the suspected location of the Abandoned Canal, around

portions of the perimeter of the Underground Silos, and through the East

and West Plant Dumps. The locations of the test trenches are shown on

Figure 6 and the parameters for analyses of the soil samples are shown on

Table 6.3.


The Abandoned Canal extended along the southern boundary of

the SLC property parallel to the river. The exact location is

unknown, however, the location has been assumed based on

topographic features. As described in Section 2.5.34, at least

portions of the Abandoned Canal were used for the disposal of

radioactive waste.

Five test trenches will be excavated in sequence from east to

west across the suspected boundaries of the Abandoned Canal.

These test trenches will be used to determine the exact location

and depth of the canal and visually observe any buried waste or

contaminated soil. Upon completion of each test trench, the

trench will be radiologically surveyed using direct measurements.

Based on visual observations and radiological survey readings,

- 9 4 - AR100187

five locations will be sampled from the bottom and/or walls of

each test trench and composited into one sample for laboratory

analyses.

As the Abandoned Canal has a high potential for multiple

contaminants a wide variety of radiological and hazardous

constituent parameters have been selected for analyses.

6.4.2 EAST AND WEST PLANT DUMPS

The East Plant Dump is located between the East and West

Lagoons. The West Plant Dump is located west of the West

Lagoon. As described in Sections 2.5.25 and 2.2.28, both

dumps were used for the disposal of radioactive waste.

A test trench will be excavated through each dump to define the

horizontal and vertical extent of the dumps and type of waste or

contamination present. Upon completion of each test trench, the

trench will be radiologically surveyed using direct measurements.

Based on visual observations and radiological survey readings five

locations will be sampled from the bottom and/or walls of each

test trench and composited into one sample for laboratory

analyses.

The parameters for analyses were selected based on information

concerning past waste disposal practices.


The Underground Silos are two 3/16" circular steel cylinders used

for the disposal of solid radioactive waste. Due to the unknown

radiological activity of the waste within the silos, a semi-circular

test trench will be excavated around the perimeter of each silo.

-95 -AR100188

The test trenches will allow determination of the exact

construction of the silos, the current condition of the silos and a

radiological survey of the exterior of the silos, without exposing

the waste or breaching the silos. If physically possible, the test

trenches will be excavated to the depth of the silos

(approximately 15').

Based on visual observations and direct radiological survey

readings, soil samples from two locations will be collected from

each trench and composited into one sample for analyses.

Parameters for analyses were selected based on infomation

concerning waste disposed of in the silos.

6.5 GROUNDWATER SAMPLING

Groundwater sampling will be conducted within the study area to obtain

representative groundwater samples for radiological and hazardous

constituent analyses. The detection of specific contaminants will assist in

the identification of radiological and hazardous contamination source areas.

In addition, the occurrence and concentration of contaminants will assist

in the determination of mobility and toxicity of the contaminants in the

groundwater flow system.

Twenty-two groundwater samples will be collected at existing monitoring

wells within the study area (see Figure 5). The methodology for

groundwater sampling is described in Section 3.7. Table 6.1 lists the

monitoring wells for groundwater sampling and shows the associated site

under investigation.

All twenty-two groundwater samples will be analyzed for radiological

parameters (see Table 5.2). In addition, 13 of the 22 groundwater

- 9 6 -AR100189

samples will be analyzed for hazardous constituent parameters (see Table

5.4). These wells are highlighted on Table 6.8. The rationale for the

selection of these wells for hazardous constituent analyses is described

below.

Monitoring well GW-15 will provide a sample upgradient of the study area.

Monitoring wells GW-A and GW-G will act as control points for the study

area boundaries. Monitoring wells GW-19 and GW-22 were selected for

sampling as they had elevated radiological results during the CNSI 1990

sampling effort. Monitoring wells GW-11, GW-12, and'GW-13 were

selected to determine the lateral extent of contamination from the diesel

fuel spill which occurred adjacent to GW-11. Monitoring wells GW-1 and

GW-5 will be used to identify the migration of any hazardous constituents

from the Underground Silos and Drainage Ditch Area, respectively.

Monitoring wells GW-A, GW-D, GW-4, and GW-7 were selected to identify

the migration of any hazardous constituents from the Abandoned Canal.

6.6 SURFACE WATER SAMPLING

Surface water sampling will be conducted within the study area to obtain

representative surface water samples for radiological and hazardous

constituent analyses in accordance with the methodologies presented in

Section 3.8. The analyses will determine whether the surface water in a

source of contamination and the method of management upon removal.

Surface water samples will be collected from the East and West Lagoons.

The locations for surface water sampling are shown on Figure 6. The

surface water samples will be analyzed for radiological and hazardous

constituents (see Tables 5.2 and 5.4).

- 9 7 -AR100190

6.6.1 EAST LAGOON

The East Lagoon is an unlined earthen surface impoundment used

previously for the disposal of radioactive and non-radioactive

waste water. Two surface water samples will be collected from

the East Lagoon and composited into one sample for radiological

and hazardous constituent analyses.

6.6.2 WEST LAGOON

The West Lagoon is an unlined earthen surface impoundment

used previously for the disposal of radioactive and

non-radioactive waste water. Three surface water samples will

be collected from the West Lagoon and composited into one

sample for radiological and hazardous constituent analyses.

- 9 8 -AR100191

TABLE 6.1LABORATORY PARAMETER MATRIX FOR SURFACE SOIL SAMPLES WITHIN GRID BLOCKS

(I SOIL SAMPLE DESIGNATION

II SS

II 01

RADIOLOGICAL ANALYSES:

Gross Alpha

Gross Beta


Gamma Spactroscopy

Radiochemistry (Ni-63)

Radiochamistry (Sr-90)

HAZARDOUS CONSTITUENTANALYSES:

Total Metals

Total Cyanida

Total Sulfide

TCLP Metals

TCLP Organlcs

Volatile Organics

Sami-Volatila Organics

Total Petroleum Hydrocarbons

1

1

1

•

SS-02

1

1

1

1

•

ss-03

1

1

1

1

•

ss-04

1

1

1

1

•

ss-05

1

1

1

1

•

88-06

1

1

1

1

•

ss-07

1

1

1

1

•

ss-08

1

1

1

1

•

ss-09

1

1

1

1

•

ss-10

1

1

1

1

•

ss-11

1

1

1

1

•

ss-12

1

1

1

1

•

ss-13

1

1

1

1

•

ss-14

SS-15

1

1

1

1

•

1

1

1

1

t

- 99 -AR100192

TABLE 6.1LABORATORY PARAMETER MATRIX FOR SURFACE SOIL SAMPLES WITHIN GRID BLOCKS

(Continued)


Gross Alpha

Gross Bota


Gamma Spectroscopy


Radiochemistry (Sr-90)


Total Matals

Total Cyanide

Total Sulfida

TCLP Metals

TCLP Organlcs

Volatile Organics

Semi-Volatile Organics


SOIL SAMPLE DESIGNATION

SS-16

1

1

1

1

•

ss-17

1

1

1

1

•

ss-18

1

1

1

1

•

ss-19

1

1

1

1

•

ss-20

1

1

1

1

•

ss-21

1

1

1

1

•

i

NOTES: Grid block locations shown on Figure 3.Numbers in table indicate number of samples per analytical parameter.' Sr-90 will be analyzed if gross alpha/beta is elevated.

- 100-AR100193

TABLE 6.2LABORATORY PARAMETER MATRIX FOR SURFACE SOIL SAMPLES

DESIGNATION OF COMPOSITE SAMPLE


Grose Alpha

Gross Beta


Gamma Spactroscopy

Radiochamistry (NI-63)

Radiochamiatry (Sr-90)


Total Matala

Total Cyanida

Total Sulfida

TCLP Matals

TCLP Organics

Volatile Organica

Sami-Volatila Organica


DESIGNATION OF SOIL SAMPLE LOCATIONS

03-SS-01

03-SS-02

O3-DS-01

03-SS-1/2

08-SS-01

06-SS-02

06-SS-1/2

12-SS-01

12-SS-02

12-DS-01

12-SS-1/2

13-SS-01

13-SS-02

13-SS-03

13-SS-1/3

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

i

14-ss-01

14-SS-02

14-SS-03

14-SS-1/3

1

1

1

1

•

- 101 -

AR100194


(Continued)



Gross Alpha

Gross Beta


Gamma Spectroscopy


Radiochemiatry (Sr-90)


Total Metals

Total Cyanide

Total Sulfide

TCLP Metals

TCLP Organlos

Volatile Organics



DESIGNATION OF SOIL SAMPLE LOCATIONS

15-SS-01

15-SS-02

15-SS-03

15-SS-1/3

16-SS-01

16-SS-02

16-SS-03

18-SS-1/3

17-SS-01

17-SS02

17-SS-03

17-SS-1/3

18-SS01

18-SS-02

18-SS-03

18-SS-1/4

18-SS-04

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

t

1

1

1

1

1

•

1

1

1

1

- 102-AR100195


(Continued)

DESIGNATION OF COMPOSITESAMPLES

COMPOSITE INTERNAL RADIOLOGICALANALYSES:

Grose Alpha

Gross Beta


Gamma Spactroscopy


Radiochamistry (Sr-901


Total Metals

Total Cyanide

Total Sulfide

TCLP Metals

TCLP Organics

Volatile Organics

Semi-Voletila Organics


DESIGNATION OF SOIL SAMPLE LOCATION

22-SS-01

22-SS-

22-SS-02

22-OS-01

1/2

28-SS-01

28SS-02

28-SS-03

28-DS-01

28-SS-1/3

30-SS-01

30-SS-02

30-SS-03

30-SS-1/3

30-SS-04

30-SS-05

30-SS06

30-SS-07

30-SS-4/7

1

1

1

1

•

1

1

1

1

1

•

1

1

1

1

1

1

1

1

•

1

1

1

1

t

1

1

1

1

1

•

1

1

1

1

- 103 -AR100196


(Continued)



Gross Alpha

I Gross Beta


Gamma Spaotroscopy

Radiochamlatry (Ni-63|



Total Matals

Total Cyanide

Total Sulflde

TCLP Matala

TCLP Organic*

Volatile Organlca




31-SS-01

31-SS-02

31-SS-03

31-DS-01

31-SS-1/3

34-SS01

34-SS-02

34-SS-1/2

35-SS-01

35-SS02

35-SS-1/2

38-SS01

38-SS-02

38-DS-01

38-SS-1/2

41-SS01

41-SS-02

41-DS-01

41 SS-1/2

1

1

1

1

•

1

1

1

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

i

1

1

1

1

•

NOTES: Surface soil sample locations shown on Figure 4.Numbers in table indicate number of samples per analytical parameter.Surface soil sample locations for sites No. 13. 14. 15, and 16 will be selected in the field based on the results of the geophysical and radiological ground surveys.* Sr-90 will be analyzed if gross alpha/beta is elevated.

- 104-AR100197

TABLE 6.3LABORATORY PARAMETER MATRIX FOR COMPOSITE SOIL SAMPLES FROM TEST TRENCHES


Gross Alpha

Gross Beta


Gamma Spectroscopy

Radiochamitttry (Ni-63)

Radiochamistry (Sr-90)


Total Matals

Total Cyanida

Total Sulflda

TCLP Matals

TCLP Organic*

Volatilo Organics

Semi-Volatila Organics

Total Patrolaum Hydrocarbons


17- 1 17-TT- TT-01 |02

28-TT-01

31-TT-01

37-TT-O1

37-TT-02

37-TT-03

37-TT-04

37-TT-05

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

fl)

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

1

-•

1

1

1

1

1

1

1

1

1

1

1

1

1

1

1

NOTES: Ta»t tranch locations shown on Figure 6.Numbers in tabla indicate number of samples par analytical parametar.* Sr-90 will ba analyzed if gross alpha/beta is elevated.

- 105 -AR100198

TABLE 6.4LABORATORY PARAMETER MATRIX FOR DEEP SUBSURFACE SOIL SAMPLES



Gross Alpha

Gross Bota


Gamma Spaetroacopy


Radiochamistrv (Sr-90)


Total Metals

Total Cyanide

Total Sulfida

TCLP Matals

TCLP Organics

Volatile Organics




03-DS-O1

12-DS-01

13-DS-01

14-DS-01

15-DS-01

16-DS-01

22-DS-01

28-DS-01

31-DS-01

34-DS-01

34-DS-02

34-DS-O3

34-DS-1/3

35-DS-01

35-DS-02

35-DS-03

35-DS-1/3

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

1

1

1

1

1

1

1

i

- 106-AR100199

TABU «.4LABORATORY PARAMETER MATRIX FOR DEEP SUBSURFACE SOIL SAMPLES

(Continued)



Gross Alpha

Gross Beta


Gamma Spectroscopy




Total Metals

Total Cyanide

Total Sulfida

TCLP Metals

TCLP Organics

Volatile Organics



DESIGNATION

36-DS-01

36-DS-02

38-DS-01

41-DS-01

OF SOIL SAMPLE LOCATION

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1 -'•-

•

NOTES: Deep subsurface soil sample locations shown on Figure 4.Numbers in table indicate number of samples per analytical parameter.13-DS-O1 through 16-DS-01 will be located In field based on the results of the geophysical and radiological ground surveys.34-DS-01 through 34-DS-03 will be consolidated Into one composite sample for laboratory analyses.3S-DS-O1 through 35-DS-03 will be consolidated Into one composite sample for laboratory analyses.* Sr-90 will be analyzed if gross alpha/beta is elevated.

- 107 -

AR100200

TABLE 6.5LABORATORY PARAMETER MATRIX FOR BOREHOLE SOIL SAMPLES

1 DESIGNATION OF SOIL SAMPLE LOCATION

07-BH-01

NUMBER OF SAMPLES

RADIOLOGICAL ANALYSES:Gross Alpha

Grots Beta


Gamma Spactroacopy

Radiochamiatry (Ni-63)

Radiochamiatry (Sr-90)


Total Matals

Total Cyanida

Total Sulfida

TCLP Metals

TCLP Organics

Volatile Orgonics

Semi-Volatila Organics

Total Petrolaum Hydrocarbons

4

4

4

4

4

•

3

1

1

3

3

':07*-.::>.-BH-::.'.:.;:?M.V;."

'• 4-':;;:::".:.;.

• : • ; > • • • viS

Wjj: is:;-

".IP 1

iitlirlf •'£•

V1/:-:'1;:'!.: !|;X

?V:;-'.vi :^

17-BH-01

5

•17-:::.BH-

'02:':.:-.

.:'8^:':'';

18-BH-01

4

5

5

5

5

•

4

1

1

4

4

5

-•;.;::•: . :;V :r"-:-:

vy.'^ri;••::;:; :;: :?;•;:

• ::-:;:H: i 'i1

:':. •.'.':;.'.:'.•:?•• y-

•: ••> •;• : ;'::'

4

4

4

4

4

•

"'&-*. ::'::';BH--:';:'lbr-:--:.::>;7

:;;.::H::

'• ' : ' :-! v • • - • ; • .

x :';'::. .' W ^:.;:'

flPi' ff~

:-¥^ •')

3

4

4

1

1

3

3

'•:;:;;-::;.; •: '•:

*'• 29- '••'•'•'.'

BHr :•'OIV^::

• '•••.: '•

30-BH-01

4

;^;.;'-; •:•?:•

•:;;::;:;.v.-::S;::::;;iv::;-

/! •••:1:1!:!"!1:.':

:•'•'-.•; •::::'"''

- . )-. . ._

4

4

4

4

4

•

:!36-V:: -'BH-02

4,-': • ' • ' ' •

: 31--'

BH-01

'4:

31-BH-02

4

33-BH-01

3

36BH-O1

4

37-BH-01

3

: • ;''• ;• ; •; . •

' .;.'.;,-.:..

3

4

4

1

1

3

3

" ' ' t

4

4

4

4

•

3

4

4

1

1

3

3

4

4

4

4

•

3

3

3

3

•

1

3

3

4

2

1

1

2

2

- 108 -AR100201

TABLE 6.6LABORATORY PARAMETER MATRIX FOR BOREHOLE SOIL SAMPLES

(Continued)

NUMBER OF SAMPLES

RADIOLOGICAL ANALYSES:Grata Alpha

Gross Bota


Gamma Spoctroscopy




Total Matala

Total Cyanida

Total Sulfida

TCLP Matala

TCLP Organics

Volatile Organics


Total Patrolaum Hydrocarbons


3* :; -.Vfr-f.

:0Z.::-":-:

J:::'

37-BH*

0*

3 ".!•

37-BH-04

3

" 37. ::.•;•8H-:.:i:

•oie^-:

.3.:'i:;.:'

37-B:HVt>;-;.

• be :;:h-o••i.'::;'::':

37-BH-07

3

:-'3?V:;-.• BHV;i;:-:

oi;-;:-.

^y."^"':"

37-BH-09 :

• 3 . - . .

•37-.-'-•:BH>^-::.i6:-?-

3 : ' ' ::..

": -4 •'.: .. i:': : :V:-.':.-;:: • • : . • : .^ • l^-.'f:(.^': i- ' • ' ; • ' .

.. ..-.-.

••'

"' • "•

•'•'''?•'. ••

"'. :f:..-:

"":"!' '

" ,-'••'

:' :' •,. • i.

• • •

v.

3

3

3

3

•

2

1

1

2

2

:.::--;:::':;-:-:':

•:Vr>^,_,,,,,,

' • ' • . ' . - • '/:,:

;• ' • ; ' - • • - • ' • / ; :

•' ':':.'.::v:

- • ' ; • • . - .

• •; • : •

3

3

3

3

•

2

1

1

2

2

'•: ':--' ' •• :::'

'?; if "•'*'.''•

'$&?i ';

:'::::i:: :':••':• ••

:>:;:::;,;;:•.

£.;\ - . • ' • •

:" ;•• ''.'-

• '!y. ":\

NOTES: Borehole subsurface soil sample locations shown on Figure S.Numbers in table indicate number of samples per analytical parameter.Shadowed boxes indicate subsurface soil samples will be collected and retained.* Sr-90 will be anelyzed if gross alpha/beta Is elevated.

109-AR100202

TABLE 6.6LABORATORY PARAMETER MATRIX FOR SOIL SAMPLES BELOW CONCRETE CORES


Gross Alpha

Gross Beta


Gamma Spectroscopy


Radiochamistry (Sr-901


Total Metals

Total Cyanida

Total Sulfida

TCLP Metals

TCLP Organics

Volatile Organics

Seml-Volatila Organics



02-CC-01

07-CC-01

26-CC-01

26-CC-02

26-CC-03

26-CC-04

29-CC-01

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

•

1

1

1

1

»

1

1

1

1

•

1

1

1

i

NOTES: Concrete core sample locations shown on Figure 5.Numbers in table indicate number of samples par analytical parameter* Sr-90 will be analyzed if gross alpha/beta is elevated

- 110-AR100203

TABLE 6.7SUMMARY OF SOIL SAMPLES FOR ANALYSES

PARAMETERS

Gross Alpha

Gross Beta


GammaSpectroscopy



Total Metals

Total Cyanide

Total Sulfide

TCLP Metals

TCLP Organics

Volatile Organics

Semi-VolatileOrganics

Total PetroleumHydrocarbon

TOTAL SAMPLES

SURFACESAMPLES

18

18

18

18

3

•

2

4

4

4

3

1

1

18

DEEPSUBSURFACE

SAMPLES

15

15

15

15

•

3

1

1

2

3

3

2

15

BOREHOLESAMPLES

34

34

34

34

8

•

22

12

12

8

9

25

25

9

34

GRID SAMPLES

21

21

21

21

*

*

21

TEST TRENCHSAMPLES

9

9

9

9

•

4

1

1

1

1

5

5

2

9

CONCRETECORE

SAMPLES

7

7

7

7

•

1

1

1

7

• 90Sr will be analyzed if gross alpha/beta is elevated.

- 111 -

AR100204

TABLE 6.8

MONITORING WELLSSCHEDULED FOR GROUNDWATER SAMPLING

GROUNDWATER SAMPLING DESIGNATION SITE AREA

1 7-GW-21 7-GW-3

31-GW-23

1 8-GW-6

20-GW-17

1-GW-l

37-GW-H37-GW-24

37-GW-E

Underground SiloUnderground Silo

,, .p,., yy^ RantOitthp

West Plant Dump

Drainage Area Between LagoonsEast LagoonContamtoatarf SoH Area Aisodsted

witl:t Solvent andLOtesal S|«li

with Soivanf and Dfawl SpiB

Well House (Shale Bedrock Well)

Upgradient Well

Abandoned Canal (Upgradient)Abandoned Canal (Upgradient)

Abandoned Canal (Downgradient)

Highlight indicates radiological and hazardous constituent analyses.

- 112-AR100205

7.0 QUALITY ASSURANCE/QUALITY CONTROL

The quality assurance and control program is established to ensure that the

samples collected in the field are representative and the data produced in the

field and laboratory is accurate and precise. Activities which will be conducted

to address quality assurance (QA) and quality control (QC) are described below.

7.1 BASELINE MEASUREMENTS

Regional background samples will be collected, distant from the study

area and away from cultural or industrial areas which might adversely

affect baseline measurements.

One water sample and one duplicate water sample will be collected from

the Bloomsburg municipal water supply. All radiological and hazardous

constituents will be analyzed. Favorable results from this sampling will

demonstrate that the same source of water could be used for field blanks

and decontamination water. Results from this sampling round will be

obtained prior to collecting samples within the study area.

A baseline groundwater sample and duplicate sample will be collected

from a domestic water well situated along the Susquehanna River

screened opposite glacial/fluvial deposits, similar to water-bearing

sediments within the study area. All radiological and hazardous

constituents will be analyzed.

A baseline surface soil sample and subsurface soil sample including

duplicates will be collected along the Susquehanna River in a geologic

setting similar to the study area. All radiological and hazardous

constituents will be analyzed. A limited radiological ground survey will be

conducted within the area of soil sampling to obtain baseline

measurements.

- 113-AR100206

7.2 EQUIPMENT CALIBRATION

The equipment used in collecting and analyzing the field data during the

characterization activities will include a variety of instruments. Proper

maintenance, calibration, and operation of each field instrument will be

the responsibility of the field technician and Project Manager. Proper

maintenance, calibration, and operation of the analytical laboratory

equipment will be the responsibility of the laboratory QA Manager and will

be reviewed by the CNSI QA Director.

7.3 QUALITY CONTROL SAMPLES

Precautions taken in the field and laboratory to assure the reporting of

accurate results include the collection and analysis of control samples.

Quality control samples are collected and analyzed along with routine

samples to indicate when results may be in error due to improper

operations or calibration of equipment, inadequate training of personnel,

deficiencies in laboratory procedures, or cross-contamination from

sampling equipment or other samples. Quality control samples may

consist of trip blanks, field blanks, and/or field duplicates. These types

of samples will be collected and analyzed during the characterization

activities.

7.3.1 TRIP BLANKS

Trip blanks would accompany sample containers to and from the

field. These samples can be used to detect any contamination or

cross-contamination during handling and transportation.

7.3.2 FIELD BLANKS

Field blanks would be collected at specified frequencies, which

will vary according to the probability of contamination or

cross-contamination. Field blanks will be metal- and/or

organic-free water aliquots that contact sampling equipment under

- 114- AR100207

field conditions and are analyzed to detect any contamination from

sampling equipment, cross-contamination from previously

collected samples, or contamination from conditions during

sampling (e.g., airborne contaminants that are not from the waste

being sampled).

7.3.3 FIELD DUPLICATES

Field duplicates would be collected at specified frequencies and

employed to document precision. The precision resulting from

field duplicates is a function of the variance of waste composition,

the variance of the sampling technique, and the variance of the

analytical technique (EPA, 1986).

7.4 SAMPLE COLLECTION

Samples collected during the execution of site characterization include

groundwater (GW), surface water (SW), surface soil samples (SS), deep

subsurface soil samples (DS), borehole subsurface soil samples (BH), test

trench soil samples (TO, concrete core soil samples (CO, and samples of

building construction materials. Each type of sample will require unique

sample collection requirements to ensure the samples are representative

of the media being sampled, to prevent cross contamination, and to

ensure the samples do not degrade from the time of collection to the time

of the analysis.

To ensure samples collected are representative of the media being

samples, specific pre-sampling activities may be required including

groundwater evacuation in monitoring wells, or removal of foreign

material in drilling/soil coring samples caused by the drilling process.

- 115 -AR100208

To prevent potential cross-contamination, samples will be collected with

dedicated sampling devices or by sampling devices that have been

completely decontaminated.

Once the sample is collected, it will be placed in appropriate containers

with appropriate preservatives as specified by the analytical laboratory.

The type of analyses to be conducted will dictate the amount of sample

to be collected and preservative necessary. In the event the minimum

required amount is not available, consolidation of samples into composite

samples may be necessary.

All sample containers will be labeled with the following minimum

information.

• Project name

• Sample Designation

• Sample Media

• Analyses to be Performed

• Date and Time

• Depth of Sample (if required)

• Initials of Individual Performing Sample Collection

Upon placement of samples into appropriate containers, the sample

containers will be placed into coolers (if required) or into strong-tight

shipping boxes. Prior to shipment, all samples will be packaged per CNSI

Procedure RA-OP-001, and Department of Transportation Regulations.

A Chain-Of-Custody Form and other appropriate field collection forms will

accompany the samples to the analytical laboratory.

- 116- AR100209

The timing of sample collection and the associated required time to

package and transport the samples to the laboratory, including the

necessary time for the laboratory to process and analyze the samples will

be evaluated to ensure recommended holding times are not exceeded.

7.5 CHAIN-OF-CUSTODY

The purpose of the Chain-Of-Custody Form is to document the movement

of all environmental samples from the point of collection to receipt at the

analytical laboratory- All intermediate transfer of environmental samples

necessary for shipment will be recorded.

During the transfer process, all samples must be accompanied by a

Chain-Of-Custody Form. When transferring the possession of samples,

individuals both relinquishing and receiving the samples will sign, date,

and record the time on the form. This record documents the transfer of

custody of the samples from the point of collection to the analytical

laboratory. Samples received by the laboratory will be cross-checked to

verify that the information on the sample labels match the

Chain-Of-Custody Form included with the shipment.

7.6 EQUIPMENT DECONTAMINATION

Decontamination of sampling equipment will be performed at a designated

central area within or adjacent to the study area. Decontamination in the

field will only be performed if circumstances prevent decontamination at

the staging area. The types of equipment which will require

decontamination include trowels, scoops, drill rigs, front-end loaders,

backhoes, and split spoon samplers, augers or equivalent core samplers.

Upon completion of sampling, all visible residue will be removed from the

equipment and the equipment will be radiologically surveyed. If the

survey indicates activity levels exceeding background levels, the

- 117-AR100210

equipment will be rinsed with potable water and resurveyed. If it is

determined that the contamination can not be removed through rinsing,

the sampling equipment will be cleaned with detergent followed by a final

rinse with potable water. Equipment which can not be decontaminated

will be classified based on the contamination present and packaged for

storage and disposal.

7.7 MANAGEMENT OF CHARACTERIZATION RESIDUES

Site characterization activities will result in the generation of

uncontaminated and contaminated waste and debris which will be

properly managed to protect the public and environment and meet

regulatory requirements. The types of materials which are anticipated to

be generated are as follow:

• • • • • Soil Residue from Sampling

-• Well Evacuation Water

* • Weil Development Fluids

-*• Well Drilling Mud and Cuttings

• Personnel Protective Equipment

• Decontamination Rinsate Solution

-• Disposable Equipment

• Samples Returned from Laboratory

^ • Laboratory Analytical Residue

- • Miscellaneous Trash (Discarded paper, Product Packaging)

• Cleared Undergrowth

All waste generated from the characterization activities will be

appropriately labeled and stored until it can be classified according to

waste type.* The wastes will be classified as sanitary (non-radioactive and

non-hazardous), radioactive, hazardous, or mixed (both radioactive and

hazardous) wastes. The waste will be classified in accordance with the

-118-AR100211

radioactive material release criteria in NRC Regulatory Guide 1.86 and the

hazardous waste criteria in 40 Code of Federal Regulations (CFR) 261.

CNSI will classify and containerize/package the waste for storage at the

SLC facility. Treatment and/or disposal of the characterization residues

will be undertaken as a separate project. To the extent feasible the liquid

characterization residues will be treated utilizing current SLC treatment

facilities (Liquid Waste Building).

The soil residue from sampling, well evacuation water, well development

fluids, well drilling sludge and cuttings will be segregated and labeled by

sampling location. Analytical results from the'groundwater or soil

samples will be utilized to classify the waste.

All personnel protective equipment generated will be assumed

radiologically contaminated, containerized, and labeled Radioactive Waste.

Initial rinsate solutions generated from personnel and equipment

decontamination will be sampled and analyzed by a commercial laboratory

to determine classification.

Disposable equipment and cleared undergrowth will be radiologicaily

surveyed and classified as sanitary waste or radioactive waste based on

the survey results.

Unused samples and sample residues returned from the commercial

laboratory will be classified based on the analytical results of the original

sample.

Residues generated by the laboratory analyses will be returned to SLC and

classified based on the characteristics of the materials provided by the

laboratory.

- 119- AR100212

Miscellaneous trash will be segregated from all potential sources of

radiological contamination and classified as sanitary waste.

8.0 HEALTH AND SAFETY PROCEDURES

A Health and Safety Plan (HASP) will be developed by CNSI prior to the initiation

of field work. The CNSI RCS will have the primary responsibility for

implementing the HASP. However, all project personnel shall be responsible to

conduct work in a manner which promotes personnel safety and adhere to the

As Low As Reasonably Achievable (ALARA) principles. 'The CNSI RCS will

coordinate all activities with the SLC Radiation Control Officer. The HASP will

address the following topics:

1.0 Scope

2.0 References

3.0 Organizational Structure

4.0 Task-By-Task Safety and Health Analysis/Controls

5.0 Personnel Training Requirements

6.0 Personnel Protective Equipment

7.0 Medical Surveillance Requirements

8.0 Exposure Monitoring

9.0 Site Safety Procedures and Control Measures

10.0 Decontamination Plan

11.0 Emergency Response Plan

12.0 Special Work Procedures

13.0 Spill Containment Program

14.0 Records

The HASP will be produced using available study area data and regulatory

guidance documents which are applicable to the characterization activities and

- 120-AR100213

anticipated conditions as references. These documents may include, but are not

limited to:

• CNSI Procedure, CN-SF-020, "Chem-Nuclear Health Physics Policy Manual."

• CNSI Procedure, FS-RP-001, "Radiological Controls Procedure for Field

Projects."

• CNSI Procedure, FS-RP-002, "Portable Instrumentation/Survey Record

Procedure for Field Projects."

• CNSI Procedure, FS-RP-012,'"Radiation Work Permits Application and Use."

• CNSI Procedure, FS-RP-008, "Dosimetry Program."

• CNSI Procedure, FS-RP-009, "Surface Contamination'Surveys."

• CNSI Procedure, FS-RP-011, "Airborne Paniculate Monitoring."

• CNSI Procedure, FS-RP-013, "Monitoring for Personnel Contamination and

Performing Personnel Decontamination."

• CNSI Procedure, FS-RP-015, "Release of Vehicles and Equipment/Materials

for Unrestricted Use."

• CNSI Procedure, FS-RP-016, "Respiratory Protection Program."

• CNSI Procedure, RA-AD-001, "Required Notifications and Reports Following

and Emergency."

• CNSI Procedure, RA-OP-001, "Operating Procedure for Brokering of

Radioactive Materials at Commercial Facilities."

• Code of Federal Regulation. Title 10, Part 20, Standards for Protection

Against Radiation.

• American Conference of Governmental Industrial Hygienists, Threshold Limit

Values and Biological Exposure Indices, latest edition.

• American National Standards Institute, 1980. Standard Practice for

Respiratory Protection. ANSI Z88 - 1980.

• Code of Federal Regulations. Title 29, Part 1926, U.S. Department of Labor,

OSHA Standards for the Construction Industry.

• Code of Federal Regulations. Title 49, Transportation, Subchapter C -

Hazardous Materials Regulations (Parts 171-178).

-121 -AR100214

-• Code of Federal Regulations. Title 40, Part 300, National Oil and Hazardous

Substance Pollution Contingency Plan.

• Code of Federal Regulations. Title 29, Part 1910, U.S. Department of Labor,

Occupational Safety and Health Standards.

In accordance with 29CFR1910.120, the minimum level of protection utilized

during characterization activities will be EPA level D with contingencies for EPA

Level C. EPA level C will be required if loose surface contamination levels on

equipment or soil exceed 50,000 dpm/100cm2 beta, gamma or 5,000

dpm/1000 m2 alpha. Contamination levels in excess of 500,000 dpm/100cm2

beta, gamma or 50,000 dpm/1000 m2 alpha will require a re-evaluation of the

characterization task being performed.

Based on available information concerning past waste disposal activities and

contamination levels, it is anticipated that the highest levels of personnel

protective equipment will be utilized for excavating test trenches in the

Abandoned Canal and adjacent to the Underground Silos, and drilling boreholes

along the Abandoned Canal, Plant Dumps and adjacent to the Personnel

Building.

9.0 CHARACTERIZATION DATA EVALUATION

The data generated from the characterization effort will provide the type,

concentration and extent of hazardous and radiological contamination in the

environmental medias and structures within the study area. This data will be

evaluated to identify specific sources of contamination, contaminant migration

pathways, assess the risks to the on and off-site population, and recommend

remedial action techniques. The final report will contain at a minimum the

following information:

- 122- AR100215

• A summary of the methods used to characterize the study area noting

deviations made from the approved characterization plan.

• Base location map of study area drawn to scale

• Sampling locations depicted on maps drawn to scale.

• Topographic map showing ground water flow.

• Hydrogeologic cross sections and profile maps.

- • Locations of hazardous and radioactive contamination.

• Results of geophysical surveys shown on a map drawn to scale depicting

suspected locations of buried waste or contamination.

• Radioisotope and hazardous constituent contour map.

• Monitoring well construction diagrams for ground water wells installed during

characterization.

• Summary of radiological working conditions.

• Results of quality control samples.

• Comparison with previous characterization data.

• Hazardous constituent and radiological constituent analytical results

presented in a tabular form.

• Copies of analytical laboratory reports.

• Sample collection forms shown as Appendix.

• Daily drilling reports shown as Appendix.

• Lithologic descriptions of subsurface soil samples shown as Appendix.

10.0 CHARACTERIZATION PLAN IMPLEMENTATION AND COST

In determining whether to implement the complete characterization of the study

area or some combination of characterization and remediation at this point, it

is important to evaluate the following issues:

• the public health and safety threat posed by current conditions at the

study area;

- 123-AR100216

•»•• the current environmental impact from the study area;

*• the levels of currently available funding for characterization and/or

remediation;

-- • the disruption to ongoing operations at the study area; and,

the lack of definitive applicable NRC and EPA guidance with respect to

characterization and standards for required levels of decontamination and

remediation.

To address the public health and safety, there is no apparent imminent public

health and safety threat posed by the study area, based on the information

gathered to date. Previous studies have shown that the groundwater flow

pattern is north-south toward the Susquehanna River and there is no evidence

of lateral or east-west migration through the Abandoned Canal, and, based on

information gathered to date, the high priority sites are located within the study

area boundaries.

Regarding the current environmental impact, while there are environmental risks

posed by the contamination present within the study area, these risks can be

adequately addressed through characterization coupled with remediation in a

phased approach.

Third, to address the issue of funding, there is currently somewhat less than

$500,000 available for use at the study area for characterization and/or

remediation, with the possibility of additional funding through litigation with

insurance companies for coverage. In our professional judgment, it would be

most prudent to use this funding in a manner which would make substantial

progress towards both characterizing the study area and reducing the potential

risks to the environment.

-124- AR100217

Fourth, a complete study area characterization at this time would disrupt

ongoing production activities of both SLC and the other tenants within the

study area. The sites which are currently used for production operations are

portions of the Main and Etching Buildings, Nuclear Building, Liquid Waste

Building, Solid Waste Building, and the Machine Shop. Disruption of ongoing

activities may pose an unnecessary financial impact on those activities. If CNSI

proceeds with characterizing the above mentioned production sites, all possible

measures will be taken to conduct the characterization in a fashion which will

minimize the impact on the production operations.

Finally, there is a significant uncertainty as to both the NRC's required level of

characterization and the EPA's standards and criteria for the required level of

decontamination/remediation. Thus, it is difficult to recommend an appropriate

level of characterization and a definitive remediation program at this time for

submittal to the NRC. Nevertheless, this characterization plan was developed

to provide a technically defensible characterization of the study area that would

lead to ultimate remediation. As noted by the Preliminary Assessment

performed on the study area by the NUS Corporation under contract with EPA,

SLC is being investigated as a potential CERCLA site. This characterization plan

was not developed using specific EPA characterization protocols, procedures,

and strategies. However, this plan was developed to provide an equally valid

characterization of the study area in a more economic fashion than using

specific EPA characterization protocols. If the characterization is performed

without EPA input, there is the possibility that the EPA would request additional

or different characterization information. In the worst case, EPA could consider

portions of the characterization invalid as they were not performed using EPA

recommended protocols or under the oversight of an EPA project manager. Due

to the uncertain EPA policies, attempts at speculating more on EPA's reaction

to the proposed characterization activities can not be made.

- 125-AR100218

In order to address each of these significant considerations, we have developed

six alternatives to implement characterization and partial remediation of the

study area. Each of the six alternatives would include a surface radiological and

geophysical grid survey of the study area.

Information regarding the exact locations of the waste disposal within the study

area is extremely vague. Therefore, the radiological and geophysical surveys

are critical to the effective implementation of the remainder of the

characterization plan. The radiological grid survey will allow the identification

of areas of surface contamination which require further investigation or removal;

the geophysical grid survey will identify the locations and boundaries of buried

waste or contamination within the study area. The radiological and geophysical

surveys will be used to refine the characterization plan so that it may be

completed when additional money is available, and provide an indication of the

magnitude of the potential environmental problems. As the above mentioned

surveys will be used to a large degree as the basis for adjusting the remainder

of the characterization activities, we recommend that these surveys be done in

connection with each or any of the six alternatives.

The alternatives in order of preference are described below. Again, as stated

above each of the alternatives includes performing the geophysical and

radiological surface grid surveys.

• Alternative No. 1 is the Preferred Alternative. Alternative No. 1 would

include performing the geophysical and radiological surface grid surveys,

evaluating the data obtained from the surveys, and using the data to

refine the characterization plan. These activities will provide valuable

information regarding the contamination within the study area, provide for

a more effective characterization of the study area, and possibly serve to

reduce the cost of the remainder of the characterization effort. The cost

estimate for performing these tasks is $320,000.

- 126- AR100219

If additional funds remain after the completion of these tasks the funds

could be spent towards removing and packaging for storage (within the

study area) the Contaminated Soil Areas Adjacent to Old Berwick Road

and from the Vance/Walton Property. Although these soil piles are

considered to be a relatively low environmental risk they are located

outside the radiological restricted area and could contribute to off-site

transport of contaminants. The additional costs to remove, package, and

relocate the soil piles is $103,000. The cost estimate for disposal of this

material as low-level radioactive waste at $140/cubic foot is $380,000.

Alternative No. 2 would include excavation and on-site storage of

contaminated materials from the Underground Silos and soil piles. From

the information gathered to date, the Underground Silos and soil piles do

not pose a safety risk but they could pose environmental risks. Using the

results of the geophysical and radiological surveys over and around the

silos as guidance, the silos would be excavated by carefully removing the

surrounding soil. Areas of contaminated soil would be sampled and

analyzed for radiological and hazardous constituents. Contaminated

materials would be packaged in storage vessels and stored in a designated

location within the study area boundaries.

The primary advantage of this alternative is that the funds would be used

to minimize the potential of contaminants being carried away through

surface water run-off by removing the soil piles but, more importantly, the

funds would be used to eliminate one of the major suspected sources of

groundwater contamination by removing the silos and/or waste within the

silos and packaging their contents.

The cost estimate for performing Alternative 2 is $956,900.

- 127- AR100220

• Alternative No. 3 involves removing contaminated materials from the

Underground Silos and soil piles and disposal of the contaminated

materials off-site. Assuming the silos contain non-hazardous, low-level

radioactive waste, the silos and/or waste within the silos will be removed,

appropriately packaged, and disposed of at a commercial low-level

radioactive waste disposal facility. Samples will also be collected and

analyzed from the contaminated soil area adjacent to Old Berwick Road

and the contaminated soil area from Vance/Walton Property. These

contaminated soil areas (piles) will be removed, appropriately packaged,

and also disposed of at a commercial low-level radioactive waste disposal

facility.

The cost estimate for performing Alternative No. 3 is $2,203,300.

• Alternative No. 4 would focus on the sites which are suspected of posing

the greatest potential risks to the environment within the study area.

Based on the information gathered to date, these sites do not pose an

imminent public health and safety threat. The sites within the study area

which are considered high priority are the Underground Silos, East and

West Lagoons, East and West Plant Dumps, and the Abandoned Canal.

Characterization of these sites would include the radiological and

geophysical surveys, collecting surface and subsurface soil samples,

collecting surface water samples within the lagoons, and excavating test

trenches at these sites. If any funds remain, they will be spent on

initiating remediation at one or more of the high priority sites.

The cost estimate for performing Alternative No. 4 is $835,700.

• Alternative No. 5 is a thorough characterization of the study area,

exclusive of the buildings, equipment, supplies, and materials contained

within the buildings. Characterization of the grounds will be performed

- 128-AR100221

by conducting radiological and geophysical surveys, sampling of surface

and subsurface soils, ground water and surface water, and excavating test

trenches.

Alternative No. 5 would provide a complete picture of the magnitude of

the ground contamination problem and environmental risks associated

with the study area grounds, but it would provide no remediation of the

known environmental concerns.


• Alternative No. 6 is a thorough characterization of the entire study area

including characterization of the buildings and the equipment, supplies,

and materials contained within the building. The buildings and contents

would be characterized by inventorying the contents of the buildings,

performing radiological surveys of the buildings and contents, and

collecting samples of the building construction materials. The study area

would be characterized by performing the radiological and geophysical

surface grid surveys, collecting samples of surface and subsurface soil,

groundwater and surface water, and excavating test trenches.

While Alternative 6 would provide a complete picture of the magnitude of

the contamination problem and environmental risks associated with the

study area, it would provide no remediation of the known environmental

funds.


In summary, to most efficiently utilize the currently available funding we

recommend implementing a phased characterization of the study area coupled

with remediation by undertaking the Preferred Alternative, Alternative No. 1.

- 129-AR100222

Information gained in performing Alternative No. 1 would be used to optimize

the remaining characterization and remediation activities. As additional funds

are available other segments of the characterization plan can be implemented

which would lead to an orderly progression towards remediation of the entire

study area.

The costs provided for the six alternatives are estimates developed based on

vague details concerning the magnitude of the contamination problem at the

study area. A cost effective approach towards characterization and remediation

would be to utilize a time and materials cost schedule coupled with fixed task

milestones. In this manner, funds would be spent only towards actual work

performed.

- 130- AR100223

11.0 REFERENCES

Allam, Irvin, File Notes, 1960.

American Society for Testing and Materials, Penetration Test and Split-Barrell

Sampling of Soils, ASTM-D-1586-84, 1979.•.

J.D. Berger, Environmental Survey of the Safety Light Corporation,

Bloomsburg, Pennsylvania, 1982.

Brown, Terry, Phone Conversation with Edward Burtsavage on June 19,

1979, 1979.

Brown, Terry, Interrogation of Edward Burtsavage, Sr. at Harrisburg, Pa. on

July 18, 1979, 1979.

Brown, Terry, Interview with Clayton Carroll of February 16, 1979, 1979.

Chem-Nuclear Systems, Inc., Soil Coring/Monitoring Well Installation Program

and Hydrogeological/Radiological Evaluation of the Safety Light Facility,

Bloomsburg, Pennsylvania, 1990.

McGraw, David, An Abbreviated History of Radioactive Operations at U.S.

Radium Corporation's Bloomsburg Facility, 1979.

Meiser and Earl, Hydrogeologic Investigation of Alluvial Ground-Water System,

U.S. Radium Corporation, Bloomsburg, Pa., 1979.

NUS Corporation, Preliminary Assessment of Safety Light Corporation, 1991.

- 131 -AR100224

Radiation Management Corporation, Radiological Investigation of the Grounds

and Ground Water, U.S. Radium Corporation, Bloomsburg, Pennsylvania,

1979.

U.S. Environmental Protection Agency, Geophysical Techniques for Sensing

Buried Wastes and Waste Migration, EPA-600/7-84-064, prepared by

TECHNOS, Inc., 1984.

U.S. Environmental Protection Agency, Test Methods for Evaluating Solid

Waste, SW-846, Third Edition, 1986.

U.S. Nuclear Regulatory Commission, Environmental Evaluation of the Safety

Light Corporation Site, Bloomsburg, Pennsylvania, 1988.

U.S. Nuclear Regulatory Commission, Order Modifying Licenses (Effective

Immediately) and Demand for Information, 1989.

U.S. Radium Corporation, Summary of Radioanalytical Results for Various

Environmental Media, Date Unknown.

- 132- AR100225

VANCE/WALTON PRW€flTY 1 |3

FIGURE 1,. STUDY AREALOCATION MAP

1. NUCLEAR BULDMO

. I OARAOC

1. OONTAUMATED SOL AREA( M FRONT OF ABOVE GROUND SLO1

. 4. UCTAL $LO (ABOVE OflOUMO)

i. SOU) WASTE BULDMd

«. OLD HOUSE

r. LOUC WASH BULDNOIL ••••' BUI.DMOI. imUTT BUV.OMO

Itt HAOUH VAU.T

I1. IUCHWC SHOT

f». CON7A1IMATCO SOL AHEA(NOmH OF UACWfi CHOP)

U-li CONTAUMATEO KM. AfVAB(BETWEEN A6AKOOWOCANAL AND favEm

1T tWKROflOLKI 8COI

1«. EAST LAOOOH

It. CARPENTCA SHOP

20 WELL HOUSE

f I. CEGUW ON eiCHAMae HUT

11 CONTAUHATEO BOL AREAOM1CR LOAOMQ DOCK)

f). CEMENT TROUOH/SEWER ORATE(BEHMD UAM BUUIMOJ

(4. HAND APPlXATON AREAS. (SECOND FLOOR OF UAH BULOMO)

f I. UAN BULDMO (FRST FLOOR)

>« SOCWALK AREAS

If HRVONHEL VFCI BULDMO

>• EA9T PLANT DUW

zrpnsHOP • . • -M. WEST LAOOON '

Jl. WEST PLANT DUMP

' J» CTCHNO OULOMO

9) ORAMLMES

34. CONTAUHATED VOL AREA•(ADJACENT TO OLD BERWICK ROAD)

•9 CONTAUMATED tOL AREA(FROW VANC&WAL70N PftOPERTr)

» CONTAUMATEO SOI. AREA(NORTH OF LACQUERSTORAGE BULOMO)

37 AFfnOXMATE IOCATCHOf ABANDONED CANAL

W. CONTAUHATED SO*. AREA(SOUTH OF RAOUI VAUL1)

31. LACOUER STORAOE BULDNQ

40 UU.TICTAK WASTETREATUENT PLANT

11. coNrAWMAreo soc AREA(EAST OF »•»•' BUtDMQ)

41. TRTTUU STACK

4). ANNEX BULOtM

MKI20NTAL SCAIE M till

OLD BEmnU ROAD

AR100226

VANCE/WAI TON PROPER

—' * 9100

• X PL A NATION

1 NUCLEAR D

3 GARAGE

4 ME1AL HO l*BOV[ GROUND)

4 SOLO WASTE: BULDNG6 OLD HOUSE7. LOUD WASTE DU1DMG• B>« eucowct. UTLlTY BIM-DNG

10 RADUM VAULT

11 UACHNE SHOP

12 CONTAMINATED SOL AHf A(NORTH OF UACHME SHOP]

13-10 CONTAMMATED SOL AREA(BETWEEN ABANDONEDCANAL AND RIVER)

\T UNDERGROUND SlOS

1* EAST LAGOON

it CARPENTER SHOP

10 WELL HOUSE

71 CESUU ON EXCHANGE HUl

13 CEMENT TROUGH/SEWER CRATE

(BEHHO MAM BULDNO)

14 HAND APPLCATQN AREAS(SECOND FLOOR OF MAM BULDWGI

» MAM BULOMQ IF«ST FLOORI

?« SOEWALK AREAS

31 PERSONNEL OfFCE OULDMC

II EAST PLANT DUMP

It PPE SHOP

30 WEST LAGOON

31. WEST PLANT DUMP

32. ETCHMGBULOMG

39 DRAM LHES

3J CONTAMWATFD SOI ARCA[FROM VANCE/WALTON PROPER

36 CONIAUMATEO SOL AREA[NORIM or l*COUERSTORAGE BU«.DWG)

39 LACOUER S'ORAGE BULDM

40 MULTUETALS W A S T ETREATMENT PI ANT

41 CONtAMMATEO SOL AREA[ E A S T OF B 1

42 TRlTLM STACK

43 ANNEX BUI.DUG

FIGURE 2. LOCATION MAPFOR SURFACE GEOPHYSICS

J0'»201 QRIO INDICATES LOCATION OF ELECTROMAGNET!'8UHVCV AND UAOE10HETCR SURVEY.

SHADED PORTIONt OF STUDY AREA INDICATES LOCATICOF QROUND PENETRATING RADAR SURVEY.

HORIZONTAL SCAlE

OLD BERWCK ROAD

AR100227

VANCE/WALTON

i

tT-:"I"

.::trI--ii_.

Iff

¥ij.11iii

i

r

-

~

-

iiii

'--—

* T

- -

.

. _

- (

—

\

\

\

\

0

- •

= ~

^rV

-•-

— r*

—

.„.

—

-

J iJ

. .. - -

"- - -

*" — -j

. . _ . _ !

. - .. .

\ -/• --'

' ~

|

- - * ' "-

~ = *. _

• : .-

r

1

-

- -' - -'- •• •

.... ..•

—

i gp ' w

1. -

* I

if •

- i---_ . . _ - ! . —

~T~ ~- ~ •+

1 - -: -

"'Trn-ii i .

•i:FOFT L '-i-i

.:^':E--p

• •"1 1 t~. ~

\ 1

11

L -, "I

~ :i- '"-

-

S- - . g•"•««!-.. S

BJ •:

" " '• '

_ ..

i1 ' ' 'l . 1

—- - — .

. \ 11 r. 7_ 1

;h •*&

1 ;. . . ._

.. i _•1

_ J

= i':f

- • •=E

'--'-

•-s

-'! - f -

- • -

— ! —-

- ""< A .,„•— ¥ -^ " ' .V • l

. . „ . . . _ . _ » _ . _ _

1 •

. _;. .:-.«.- ~ _ - .... 41

-:^I;:::::::E;;:

..::::::: "^ : ^S4J

- - - - f - „. . .. a l ,. Lj v 7<

. ; - T- - >i — • • i ~r- ' ~ -

c n; -

74

" 1 11

- . ... . |^ .:::::,; |

t----?j. -i^Tj.\

\ .• \ 1^ •\ s

^ &V \3--A--^

' 1 : s

/

J:::(:::::::::::_ _ . i _

zs . ^IT

J — ==^ i :: zi

•

'• N

'• ' --1- - t '. •:.

-J L . I 3»_j £ ,

3 1 ' ^

C- - -

•. J ' ' "

„ £ . _ _ -

, j~

._ . — : : x x X

.. .. .„_.. 5 n_. .. ._

r) " •::'"~ *~>.

= :c

i a

t

1

t j!

HI

Irr

'•f =

--

—

...._±

t -4 -— .

3

.*P...~.T,ON FIGURE

SURVE

"•• ;rr8^0 SAMPL1 ( M FRONT OF ABOVE GROUND S4.0I

~| 4 METAL SLO (ABOVE WOUND)

— | 9 SOLD WASTE BULDMQ

— s OLD HOUSE

I • il BULDMO ^

— 10 RAOLM VAULT

— n. UACHWE SHOP •

12. CONTAMMATED SOL AREA— (NORTH Of UACHME SHOP)

U 18 CONTAMINATED SOL AREAS— . (BETWEEN ABANDONED •

- ' ' IT UNOEROAOUND SLOS

20. WELL HOUSE

(UNDER LOAONO DOCK)

"( 24. HAW ATPLCAtCN AREAS ALONQ 10(SECOND FLOOR OF UAH BULDHQ)

•94BO 25 HAM BULDMO (FR9T FLOOR)

• t 26 SOEWALK AREASA JT. PERSONNEL OFFCE BULDNO

5 it EAST PLANT DUMP

• H PM SHOP; ^ M. WEST LAGOON

f n. WEST PLANT DUUP

g 32. ETCHMO BULOMQ

SSIOO 31 DRAM LMES

— ( 34 CONTAUMATEO SOL AREA(ADJACENT TQ OLD BEHWCK RO»D)

95 CONIAMMATED SOL AREA(FROM VANCE/WALTON PROPERf]

3t CONTAUMATED SOL AREA(NORIH OF LACQUERSTORAGE BULOMO)

37. APPROXMATE LOCAICNOF ABANDONED CANAL

- SlfO 3» CONTAMMATCD SOL AREA(SOUTH OF RADUU VAULT)

31 LACOUER STORAGE BUI D WO

40 MULTMETALS WASIETREATMENT PLAN!

42 TRI1LM STACK

•- S100.

3. LOCATION MAP\DIOLOGICAL GROUNDV AND SURFICIAL SOILNG

• 1 OF 1 SURFICIAL SOIL

NOTE: ALL 1 LOCATIONB• -A TO BE CONSOLIDATED INTO• i COMPOSITE SAMPLE

' INDICATES OHIO BLOCK« LOCATION

— INDICATES MEDIATO BE SAMPLED

AL OHOUNO SURVEY TO BE CONDUCTED• 10' AND lO'.IO1 GRID BLOCKS AB SHOWN

0 40 BO l?0 160

HORIZONTAL SCALE M F E E T

; . - . - . .

OLD BERWICK ROAD

AR100228

(' \ r-, fTzn\ \\

•«it.||. 10 Ac

•jt

•0«-l•OS-1<•«« I01-1

• XPLANATION

t. NUCLEAR BULIWO

J. OAAAOE

3 CONTAfcHATED SOt AREA( H FRONT or ABOVE GROUND SLO)

4. METAL SLO iAOOVE OHOUNO)

9. SOLO WASTE BUUWO

• OLD HOUSE

r. LOUO WASTE BULDWO

• ••*•' BULDWO

t. UtLJlY 6ULDWO

10. RADLM VAULT

11. MACHWE SHOP

II. CONTAUNATEO SOL AREA(NORTH OF UAO«C SHOP)

IJ-l«.CONrAMWATEDSOI. AREAS(BETWEEN ABANOOtCOCANAL AND RIVER)

IF. UNOEROflOUHO SLQS

II EAST LAOOON

it. CARPENTER SHOP

10. WCLi. HOUSE

11. CEStM ON EXCHAMOE HUT

13 CEMENT TROUOH'SEWER OflATC(BEHH) UAM BUUJMO)

24 HAND APPICATKM AREAStWCOTO rtOOR OF MAN BULDMQI

I» UAM BUI.DNO (FUST fLOOR)

7«. SO€ WALK AREAS

ir PERSOHNEI. of Fee BULOMQ

if EAST PLANT DUMP

21. PM SHOP

10 WEST LAQOON

n. WEST PLANT DUMP

32 CTCHMO BUlONQ

93 DRAM LMES34. CONTAUMATEO SOL AREA

(ADJACENT TO OLD BERWCK ROAD)

31 CONTAUNATED SOL AREA(FROM VANCE/WALTON PROPERTY)

36 CONTAMMATED SOL AREA(NORTH OF LACQUERSTORAGE BUCOHOI

19 IACOUER STORAGE BUID«O

1 CONTAMMATTD SOL AREA[EAST Of S'lB' 6UI.DWGI

! TFOTLN STACK

3 ANNEX DUIDNO

FIGURE 4. LOCATION MAPFOR SURFACE SOIL SAMPLINGAND DEEP SOIL SAMPLING

O .INDICATES t

i INDICATES I(LOCATION

IDICATE8 BITE AREA

OLD BERWICK ROAO

AR100229

VANCE/WALTON »nOPC>*

• XPLANATION •-

1. NUCLEAR BUlCWQ

I. OAflAOt

3. COMTAUNA1ED SOL A«AI M FRONT Of ABOVE OROLWO SLO)

4. METAL SLO (ABO*E GROUND)

i SOLD WASTE BULOWQ

«. OLD HOUSE

I UOUO WASTE BU1.DWO

• • it BULDMO

I. UTLITY BULOMO

10. RAOUU VAULT

I1. UACHME SHOP\J. COHTAUHATEO SOL AREA

(NORTH OF MACMWE SHOP)

13-<« COWTAVWA TED SOL AREAS(BETWEEN ABANDONEDCANAL AND ftlVEH)

tT UNOERQROUND SLO3

II EAST LAOOON

If CARPENTER SHOP

tO. WELL HOUSE11. CESWU ON EXCHANGE Wt

J3 CEMENT TROUOH^SEWER ORAIE(BEHHD UAH BM.OHQ)

14. HAND APPlXATCN AREAS(SECOND FLOOR OF MAN BULOM

IB HAH BULDNO (FRST FLOOR)

K. SOCWA^K AREASIT. PERSONNEL OFFCE BUt-OWO

IB EAST PLANT out*

it PPC SHOP

VI WEST LAOOON

li. WEST PLANT DUMP

31. ETCHNQ BULDt4O

33. OR AN LHES34. CON? AM WAT ED BOt AREA

(AOJACCNF ro OLD afnwtcn BOA

35. CONTAMMATED SOL AREA(FROM VANCE/WALTON PROPERTY

39 CONTAMHATED SOI AREA(NORTH OF LACQUERSTORAGE BLH.ONO)

39 LACOUE* STORAQE PULOMQ40. MULTMETALS WASTE

TREATMENT PLANT

4 I. CONTAUMATED SOL AREA(EAST OF • )• e

41. TRHLM STACK

43 ANNEI BULDNd

FIGURE 5.-LOCATION MAP_FORGROUNDWATER SAMPLING.BOREHOLES / SUBSURFACE SOILSAMPLING, AND CONCRETECORING / SOIL SAMPLING.

O INDICATES QROUNDWATER SAMPLING LOCATION.

INDICATES BOREHOLE / SUBSURFACE SOILSAMPLINd LOCATION.

.INDICATES CONCRETE COHINO / SOIL

INDICATES SITE AREA

LOCATION OF SAMPLING POINT

HORIZONTAL SCALE « FEET

OLD BERWCK ROAD

AR100230

n O M .

"C

.

— -

I2t

' : =j

3.-lo._.'

&b \\

AC,

• XDLANATION

1 NUCLEAR BULOWG

3 OARAGE

3 CONTAhMATCO SOL'ARCA( M FRONT OF ABOVE GROUND SLO)

«. UETAL SLO (ABOVE OWXMQ)

9. SOLO WASTE BULDHQ

6 OLD HOUSE

7. LOUD WASTE BULONO

• • >e BULOINO

v. unrTY em. DUG •

10 RADUU VAULT

1 1. UACHME SHOP

13-16 CONTAUHATEO SOL AREA(BETWEEN ABANDONEDCANAL ANO RlViK)

17 UNDERGROUND SLOS

10 EAST LAQOON

1» CARPENTER SHOP

20 WELL HOUSE

3 1. CESUU ON EXCHANGE HUT

13 CEUENT TKOUOH/SCWER OXATE(BCHMD HAM BULOMO)

. 14. HAND APPLCATON AREAS(SECOND FLOOR OF MAN eutowo)

II UAM BM.OMO (FRST FLOOR)

I« 5DEWA1.K AREAS ,

I' PERSONNEL OFfCB BIM.OMO

>• EAST PLANT DUMP

it prc SHOP

JO WEST LAOOON

3' WEST PLANT out*

31 E TCHNQ BULDMO

33 DRAM LUES

34 CONTAUMATED SOL AREA(ADJACENT TO OLD BERWICK ROAD)

36 CONTAMMATED SOL AREA(NORTH Or LACOUEflSTORAGE BULDNQ)

Jt IACOLCH STORAOC B

41. TRlTUU STACK

43. ANNEX BULOMO

FIGURE 8. LOCATION MAPFOR TEST TRENCH EXCAVATIONSAND SURFACE WATER SAMPLING1

INDICATE! flTC AREA

INDICATE! UIOIA TO BI SAMPLED

OE5IQNATION Of SAMPLING POINT .

LOCATION OP •AUPIINQ POINT

INDICATES UE01A TO BC ftAMPLCO

HORIZONTAL SCALE M FEET

OLD BERWICK ROAD

AR100231

site characterization plan - semspub.epa.gov · safety light corporation site characterization plan...

Documents