dtic ada402542: lakehurst naval air engineering station

IE RA-S D-BR-S R-2002-0004

UNITED STATES AIR FORCE IERA

Lakehurst Naval Air Engineering Station (NAES) Radiological Baseline Survey in Support of USAF BOMARC

Missile Accident Site Remediation Waste Transportation Plan,

New Jersey

Steven E. Rademacher, Major, USAF, BSC Eugene V. Sheely, Captain, USAF, BSC

Dale D. Thomas III

May 2002

Approved for public release;

distribution is unlimited.

Air Force Institute for Environment, Safety and Occupational Health Risk Analysis Surveillance Directorate Radiation Surveillance Division 2513 Kennedy Circle Brooks Air Force Base TX 78235-5116

20020612 092

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Prepared by:

EUGENE V. SHEELY, CaptaimTTSAF, BSC

Chief, Environmental Health Physics

~~£L )ALE D/THOMAS III, GS-13, DAF

Chief, Radioanalytical Branch

Reviewed by:

CRAIG-ALAN C. BIAS, Major, USAF, BSC

Chief, Occupational Health Physics Branch

Approved By:

STEVEN E. RADEMACHER, Major, USAF, BSC

Chief, Radiation Surveillance Division

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1. AGENCY USE ONLY (Leave blank) I 2. REPORT DATE 3. REPORT TYPE AND DATES COVERED

8 May 2002 4. TITLE AND SUBTITLE

Lakehurst Naval Air Engineering Station (NAES) Radiological Baseline Survey in

Support of USAF BOMARC Missile Accident Site Remediation Waste Transportation

Plan, New Jersey _ 6. AUTHOR(S)

Steven E. Rademacher, Major, USAF, BSC

Eugene V. Sheely, Captain, USAF, BSC

Dale D. Thomas III _ 7. PERFORMING ORGANIZATION NAMEIS) AND ADDRESS!ES)

Air Force Institute for Environment, Safety and Occupational Health Risk Analysis

Surveillance Directorate

Radiation Surveillance Division

2315 Kennedy Circle

Brooks AFB TX 78235-5116_ 9. SPONSORING/MONITORING AGENCY NAME(S) AND ADDRESS!ES)

HQ AMC/CEV

507 Symington Drive

Scott AFB IL 62225-5022

FINAL (2002) 5. FUNDING NUMBERS

8. PERFORMING ORGANIZATION REPORT NUMBER

10. SPONSORING/MONITORING AGENCY REPORT NUMBER

IERA-SD-BR-SR-2002-0004

12a. DISTRIBUTION AVAILABIUTY STATEMENT

Approved for public release; distribution is unlimited.

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13. ABSTRACT (Maximum 200 words)

The BOMARC Missile Site contains weapons grade plutonium (WGP) as the result of a nuclear weapon accident that

occurred in 1960. This report documents a background radiological survey conducted in support of the truck transport and

rail transfer of radiological waste from the USAF Boeing Michigan Aeronautical Research Center (BOMARC), Fort Dix,

N.J. through Lakehurst Naval Air Engineering Station (NAES), N.J. to rail facilities connecting to the NAES. The survey

was conducted from 9-10 January and 8-9 April 2002, with respresentatives from AFIERA/SDR, Environmental Division

of Lakehurst NAES, and Navy Radiological Affairs Support Office (RASO), Naval Sea Systems Command Detachment,

Yorktown, VA. The survey consisted of in-situ gamma and alpha radiation measurements, and soil sampling. The soils

were analyzed by high-resolution gamma spectroscopy analysis and isotopic plutonium through alpha spectroscopy. The

results of the surveys were unremarkable and typical for background radionuclides. Plutonium concentrations ranged from

(-7) to 80 femtocuries per gram (fCi/g), with a mean of 11.8 fCi/g.

14. SUBJECT TERMS

weapons grade plutonium

nuclear weapon accident

15. NUMBER OF PAGES

americium plutonium background BOMARC _66_

gamma spectroscopy alpha spectroscopy 16. price code

17. SECURITY CLASSIFICATION I 18. SECURITY CLASSIFICATION 19. SECURITY CLASSIFICATION 20. LIMITATION OF ABSTRACT

OF REPORT OF THIS PAGE OF ABSTRACT

Unclassified Unclassified Unclassified o*.-OQfl /Box/ 9-fiQ) (Fm

(This Page Intentionally Left Blank) i

u

TABLE OF CONTENTS

Report Documentation.i

Table of Contents.iii

List of Tables.iv

List of Figures.v

1. Introduction.1

2. Background.2

3. Methodology.4

3.1 Transportation Route and Rail Transfer Area Survey

3.2 Soil Sampling

3.3 Global Positioning System Measurements

3.4 Survey Personnel

4. Results and Discussion. 8

4.1 In-Situ Measurement and Soil Sampling Locations

4.2 In-Situ Measurement Data Summary

4.3 In-Situ Measurement Instrument Calibrations and Hot-Spot Calculations

4.4 Laboratory y-Spectroscopy Analysis Results

4.5 Laboratory Isotopic Plutonium Analysis Results

5. Conclusions.14

6. Acknowledgements.14

7. References.15

8. List of Acronyms.16

Appendix A - Lakehurst Overall Site and Rail Transfer Map.17

Appendix B - Baseline Survey Results.21

Appendix C - Calibration Logs and Hot-Spot Calculations.43

LIST OF TABLES

1 Isotopic Composition (by mass) of WGP in BOMARC Weapon Based on Los Alamos National Laboratory Estimates and Soil Analyses.2

2 Major Radiation Emissions of Primary WGP Constituents.3

3 Survey Personnel.7

4 Summary Statistics for In-Situ Measurement Data (Transportation Route).9

5 Summary Statistics for In-Situ Measurement Data (Rail Transfer Area).9

B-l BOMARC Field Assessment Positional Data.23

B-2 BOMARC In-Situ Measurement Data.28

B-3 BOMARC Soil Sample y-Spectroscopy Analysis.33

B-4 BOMARC Soil Sample a-Spectroscopy Analysis.38

C Hot-Spot Code Efficiency Calculations.56

LIST OF FIGURES

FIDLER Calibration Configuration.

Histogram of24'Am Minimum Detectable Concentrations.

Isotopic Plutonium a-Spectral Plot for Sample NAES046.

Isotopic Plutonium Chemical Recovery Histogram.

January 2002 Lakehurst Radiological Background Study.

January and April 2002 Lakehurst Radiological Background Study

(This Page Intentionally Left Blank)

vi

1. Introduction

This report documents a background radiological survey conducted in support of the truck transport and rail transfer of radiological waste from the Boeing Michigan Aeronautical Research Center (BOMARC), Fort Dix, N.J. through Lakehurst Naval and Engineering Station (NAES), N.J. to rail facilities connecting to the NAES. The purpose of the survey is to establish pre-existing radiological conditions for in-situ measurement instruments and analyses of soil samples, and establish laboratory and field performance expectations for the post-transportation sampling and analysis. In addition, the information contained in this report will be a vital aid to field survey and assessments in the unlikely event that an accidental release of BOMARC contaminated soils occurs during truck transport or rail transfer on NAES.

The survey described in this document was conducted from 9-10 January and 8-9 April 2002, with representatives of the Radiation Surveillance Division of the Air Force Institute for Environment, Safety and Occupational Health Risk Analysis (AFIERA), Brooks AFB TX; Environmental Division of Lakehurst Naval Air Engineering Station (NAES), N.J.; and the Navy Radiological Affairs Support Office (RASO), Naval Sea Systems Command Detachment, Yorktown, VA. Instrumentation from both AFIERA and RASO were used in the survey, while only the results from the AFIERA instruments are provided here. Soil samples were analyzed by AFIERA, with split samples sent to RASO and Framatome ANP, Inc. (formerly Duke Engineering & Services).

Between the transportation route and the rail transfer area (railhead), a total of 121 samples were analyzed by AFIERA. The y-spectroscopy analyses were unremarkable, with positively identified radionuclides being naturally-occurring or from atmospheric nuclear weapons testing fallout. The isotopic plutonium analysis using a-spectroscopy found detectable concentrations of 239+240Pu in the samples, but at activity concentrations below 100 femtocuries per gram (fCi g'1). The concentrations of 239+240py rep0rted were within the range typical for fallout. Portable instrument measurements were typical for uncontaminated areas, with some variability that should be accounted for in field survey work accomplished during support of transportation operations.

1

2. Background

The BOMARC Missile Site is an inactive Air Force installation located in Plumstead Township, New Jersey. The site was an active nuclear missile defense site from 1958 - 1971. On June 7, 1960, a fire occurred in one of the shelters in which the shelter, missile, and warhead were partially consumed by the fire. The high explosive materials in the weapon ignited but did not detonate. The most intense period of the fire lasted about one hour. Water was applied to the shelter and weapons during the fire by the installation fire department. The fire melted the weapons grade plutonium (WGP) that was contained in the device. Turbulent local atmospheric conditions and the water applied during the fire contributed to scattering of WGP to the environment.

WGP is comprised primarily of 239Pu, with lesser mass amounts of 238Pu, 240Pu,241 Pu, and 242Pu. For many nuclear weapons, individual WGP isotopic assay information exists (classified). However, for the warhead on the BOMARC missile and other nuclear weapons produced during the same time, specific assay information is not available (Taschner 1998). Table 1 provides an estimate of the isotopic composition of the BOMARC missile based on information from Los Alamos National Laboratory (Taschner 1998) and soil analyses performed in 1997 (Rademacher 1999).

Table 1. Isotopic Composition (by mass) of WGP in BOMARC Weapon Based on Los Alamos National Laboratory Estimates and Soil Analyses (Rademacher 1999).

Isotope Mass Percent* Radiological Half-life (y) **

Pu-238 0.0099 87.74

Pu-239 93.7 24,110

Pu-240 5.6 6,560

Pu-241 0.47 14.35

Pu-242 Negligible 376,000

* Fractions in 1958 ** Walker et al 1984

The relative isotopic composition of WGP constituents changes over time due to radioactive decay. Shortly after chemical separation during production, the most significant change is due to the radioactive decay of24'Pu:

241 Pu-> 241 Am +

The daughter product,241 Am, is an a-particle emitter with a radiological half-life of 432 y (Walker et al 1984). Table 2 lists the major radiation(s) emitted by the primary constituents of WGP. For 239Pu and 240Pu, only infrequent low-energy photons are emitted. Direct assessment of either of

2

these isotopes in samples can be accomplished through high-resolution y-spectroscopy if sample activities are reasonable high. For low activity concentration samples, the most common assessment technique is through chemical dissolution, chemical separation, and a-radiation or mass spectroscopy. Because the a-particle energies of the Pu and Pu are very close, a-spectroscopy analysis is incapable of resolving the two isotopes. For radiation protection purposes, however, this does not present a problem because each isotope has the same activity to dose conversion factor (Eckerman 1999). The best estimate of the 239+240pu to241 Am activity concentration ratio for the BOMARC WGP contaminated soils is 5.4 (Rademacher 1999).

Table 2. Major Radiation Emissions of Primary WGP Constituents (Scheien 1992).

Radionuclide a-Particle Energies (MeV) & Frequency

P-Particle Energies (MeV) & Frequency

Photon Energies (MeV) & Frequency

Pu-239 5.155 (0.733) 5.143 (0.151) 5.105 (0.115)

None 0.113 (0.0005) 0.014 (0.044)

Pu-240 5.168 (0.735) 5.123 (0.264)

None 0.054 (0.0005) 0.014(0.11)

Pu-241 None 0.021 (1.00) None

Am-241 5.486 (0.852) 5.443 (0.128) 5.388 (0.014)

None 0.014 (0.427)

0.0595 (0.359) 0.026 (0.024)

3

3. Methodology

The survey consisted of in-situ measurements, soil sample collection, and laboratory analysis of soil

samples. In-situ y-measurements were made on soil along the NAES transportation route. Soil

samples were taken from these same locations and sent for radioanalysis. Additional in-situ y- and

a-measurements were made on the paved portions of the NAES transportation route. The Air Force

agreed to collect measurements and samples at an interval of every one-eight mile. Because an automobile was used for transportation between sampling locations and its odometer was used for sample location spacing, it was more practical to set increments at 0.1 miles. This increment exceeded the one-eight mile increment and provided for more sampling and measurements.

3.1 Transportation Route and Rail Transfer Area Survey

3.1.1 Number of Measurements

The Air Force agreed with the Navy to collect in-situ measurements at every soil sampling location.

AFIERA/SDR decided to collect additional background in-situ measurements on asphalt and

concrete road surfaces of the transportation route. This additional sampling was performed to assess background measurement conditions in the event contaminated soils were accidentally deposited on these surfaces. Mr. Martin, Navy RASO, and Capt Sheely, AFIERA. agreed that taking one measurement every other paved surfaces measurement location was sufficient to establish background conditions for the paved surfaces. A total of 94 measurement locations were set along the NAES transportation route. Among these, 31 locations had the additional in-situ measurement collected on an asphalt or concrete surface. At the railhead, it was decided to collect 27 soil samples and paired in-situ measurements. The approximate spacing for these measurements and sampling was 10 meters (m). Like the transportation route, additional in-situ measurements were collected on paved areas and the gravel base of the newly constructed rail spur. Figures A-l and A-2 (Appendix

A) contain sample and measurement locations.

3.1.2 In-Situ y-Measurements

In-situ y-measurements were performed using a Bicron 12.7 centimeter (cm) diameter x 1.6 millimeter (mm) thick thallium-drifted sodium iodide [Nal(Tl)] detector coupled with a Ludlum

model 2221 scalar. The detector in this set-up is commonly referred to as a field instrument for the detection of low energy radiations (FIDLER). The model of detector used was fitted with a thin beryllium entrance window to minimize the attenuation of low energy photons. Prior to field survey

work, at the AFIERA Instrument Calibration Facility (ICF), a relatively small energy window was

set on the meter pulse height discriminator around the 59.5 keV 241 Am y-ray along with instrument reliability checks. At the same time, measurements were collected with an 241 Am source at a distance of 30 cm from the detector entrance window at lateral distances from the perpendicular of 0, 20, 40, 50, 60, 80, and 100 cm as illustrated in Figure 1. These measurements were used to calculate surface detection efficiencies for use with the “Hot-Spot” computer code produced by Lawrence Livermore National Laboratory (LLNL). In the field, daily instrument reliability was assessed by collecting 15 sequential measurements with an24'Am calibration source and the chi-square statistical

test. Battery and discriminator checks were made daily. For these tests and field measurements, a

4

special detector stand was used to retain the detector at a constant detector to ground distance of 30 cm. Additional field measurements were collected with an24'Am calibration source at lateral distances from the perpendicular of 0 and 50 cm. These field measurements were collected at a

location near the railhead and described later in the report as the QA/QC location.

Figure 1. FIDLER Calibration Configuration.

3.1.3 a-Measurements

In-situ a-radiation measurements were made at the same locations as the in-situ y-radiation measurements on the asphalt, concrete, and gravel surfaces. A Ludlum model 43-89 scintillator connected to a Ludlum model 2360 scalar was used for the measurements. Detector calibrations were conducted at the AFIERAICF prior to the field survey work with a 239Pu calibration source for

the a-radiation channel, and 99Tc and 90Sr for the P-radiation channel. In the field, daily instrument

battery checks were accomplished and a-radiation response was assessed with a thoriated lantern

mantle.

3.2 Soil Sampling

3.2.1 Number of Samples

Soil samples were collected at the 94 measurement locations along the transportation route and at 27 locations around the railhead site. For the samples collected on the transportation route, sampling was conducted at the global positional system (GPS) measurement location. For samples at the rail transfer area, sample collection was split among gravel areas directly below the newly installed rail

or at adjacent areas that contained soil. It was determined by discussions with AFIERA and the Navy representative that this approach provided more information about background radiological conditions rather than just the sampling of one media. For measurements along the rail transfer area, GPS measurements were uniformly collected only at soil areas, regardless of whether the sample was collected at the soil location or the gravel beneath the rail. The separation distance between the

soil locations and gravel sampling/in-situ measurement locations was about 3 m.

5

3.2.2 Soil Samples

Soil samples were collected on the surface to a depth of approximately 0.5 cm. To ensure adequate

sample mass for y-spectroscopy analysis, a minimum required sample mass was set at 200 grams (g). Actual sample masses ranged from 275 to over 1212 g. Vegetation, large stones, etc. were rejected from collection in the field. Sampling location was annotated on the plastic sample bag containers in the field. Prior to preparation for packaging and shipment, the samples were enclosed in an

additional plastic bag. A chain of custody form was enclosed with the samples prior to shipment. Field sampling tools were cleaned between sampling locations with de-ionized water. At every tenth

sampling location, two duplicate samples were collected: one for Framatome ANP, Inc., a private

commercial laboratory (also providing quality assurance analysis of soils for Duratek, Inc. during the

remediation and final status survey phase of the BOMARC site remediation), and the other for Navy

RASO.

3.2.3 Laboratory Analysis

In the laboratory, samples were weighed, dried in an oven at 44 °C for 24 hours, sieved to remove stones, blended, and homogenized. One gram (nominal) and 100 g aliquots were pulled from the

preparations for a- and y-spectroscopy analyses, respectively.

The Air Force and Navy agreed to isotopic plutonium analysis for the soils. AFIERA, based on

routine procedure for unknown samples, also performed high-resolution y-spectroscopy prior to the

isotopic plutonium analysis procedure. Aliquots prepared for y-spectroscopy analysis were placed in 250 ml right-cylindrical polyethylene containers and counted for 10,000 seconds (~ 2.8 hours). A

peak search was accomplished with Canberra Inc. Genie 2000™ y-spectroscopy software to identify isotopic content. The analytical results were reviewed for identified radiological constituents. Reported analytical results for 228Ac, 241Am, 137Cs, 40K, and 234Th were compiled.

Aliquots prepared for a-spectroscopy analysis were mixed with a highly concentrated mixture of HF, HNO3, and HC1, and heated to high temperature and pressure in a CEM Corp. microwave digestion system (if necessary for complete dissolution). A 242Pu tracer was added to every alicjuot to assess chemical recovery. Plutonium chemical separations were accomplished with BioRad™ resin. Plutonium was coprecipitated with a cerium fluoride carrier onto Tuffryn™ membrane filters

[25 mm diameter, 0.2 pm pore size]. Passive implanted planer silicon detectors contained in

vacuum chambers were used to count sample a-radiation emission by energy. Samples were

counted for 20,000 seconds (~ 5.6 hours), with background counted for 86,400 seconds (24 hours). 242Pu tracer recovery and 239+240Pu activity concentrations were assessed using Canberra Inc. Genie

2000™ a-spectroscopy software.

6

3.3 Global Positional System Measurements

The Environmental Division of Lakehurst NAES provided GPS measurements. The measurements were collected with a Trimble™ GPS Pathfinder Pro XR satellite positioning system (Trimble 1998). The Environmental Division used post-processing differential correction to achieve accuracy within 1 m. GPS location in New Jersey State Grid Coordinates was downloaded for this

report.

3.4 Survey Personnel

Table 3 contains a listing of the survey personnel. Some personnel only participated in one part of the survey. For these individuals, the specific portion of survey participation in annotated.

Table 3. Survey Personnel.

Health Physicist Steven Rademacher AFIERA/SDR

Health Physicist Lary Martin NAVSEADET RASO

Health Physicist (January Only)

Eugene Sheely AFIERA/SDRH

Health Physics Technician (January Only)

Donald Carbajal AFIERA/SDRH

Health Physics Technician Kimberly Murchison AFIERA/SDRH

GIS Technician (January Survey Only)

John Crawford Environmental Division, Lakehurst NAES

GIS Technician (April

Survey Only)

Jessica Ditner Environmental Division,

Lakehurst NAES

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4. Results and Discussion

4.1 In-Situ Measurement and Soil Sampling Locations

Figure A-l, Appendix A, provides a map of Lakehurst NAES with detailed annotation of the soil sampling and in-situ measurement locations from the January 2002 portion of the background survey. For the locations along the transportation route, sample identification (i.e., NAES001,

NAES011, etc.) annotation was made for every tenth location. Locations are in sequential order, allowing interpolation for those locations without annotation. During the January 2002 survey, two rail transfer location samples (RH001 and RH002) were collected on grassy areas on the opposite

side of the road from the rail spur. As well, the QA/QC location, where background and calibration

measurements were made, was on the opposite side of the road, but farther down from the rail

transfer area.

Figure A-2 provides a map with detail of the rail transfer area measurement and sampling locations

from the April 2002 portion of the survey. This plot contains locations: RH001, RH002, and QA/QC that are also contained on Figure A-l. Sampling locations RH003 - RH027 are in sequential

order, with annotations at every fifth location. Locations RH003 - RH025 encompassed the rail spur and had approximate spacing of 10 m between them. Locations RH026 and RH027 did not contain rail, but did have some gravel material along the roadside and greater spacing between locations.

Table B-l, Appendix B, contains the field assessment positional data. The listing has measurement location identifier, GPS collection information and the corresponding New Jersey State Grid

Coordinates.

4.2 In-Situ Measurement Data Summary

Table B-2 contains the in-situ measurement data. For measurements along the transportation route, there is a FIDLER measurement for every sampling location and one at every other adjacent

pavement location where asphalt or concrete existed. For every pavement FIDLER measurement, an

a-radiation measurement was collected at the same location. Many locations along the route were not paved and subsequently the Table contains a “NA” notation where adjacent measurements were not collected. At the rail transfer area, for every location, the Table contains a listing of the soil,

gravel, and road measurements. For the measurements, the FIDLER and a-radiation measurements

were collected at the same location.

Table 4 contains the summary statistics for the field in-situ measurements of the transportation route, while Table 5 contains the summary statistics for the rail transfer area. For the transportation route FIDLER measurements, the mean of the pavement measurements was lower than that of the soil measurements. Both sets of FIDLER measurements had good agreement between the mean and median values, an indication of symmetrical data distributions. Both data sets had similar standard

deviations: 358 and 290 counts. For the measurements on soil, the maximum measurement was 3908 counts, more than double the mean, and six standard deviations higher than the mean of the data set. This observation may have been the result of a non-flat counting geometry, but generally

illustrative of the variability that can be encountered in field measurements with FIDLER

instruments. For the a-radiation measurements, the data ranged from 2 to 27 counts. The variability

8

observed is likely attributed to variability in road materials and the influence of naturally occurring radon progeny. An interesting observation from the data is that there is not a direct correlation

between the a-radiation and FIDLER measurement data; often the areas of highest a-radiation had

relatively low FIDLER response and visa versa.

Table 4. Summary Statistics for In-Situ Measurement Data (Transportation Route)

Summary Statistics

Integrated Counts (1-minute)

FIDLER Measurements Pavement a-Radiation Measurement Soil Pavement

Mean 1765 1495 10.4

Median 1516 9

Standard Deviation 358 290 5.7

Maximum 3908 1962 27

Minimum 1266 o

o

2

Observations 94 31 31

Table 5. Summary Statistics for In-Situ Measurement Data (Rail Transfer Area)

Summary Statistics

Integrated Counts (1-minute)

FIDLER Measurements a-Radiation Measurements j

Soil Gravel Road Soil Gravel Road

Mean 1008 859 1.4 1.1 2.0

Median 985 1 1 2

Standard Deviation 87 148 109 1.4 1.1 1.2

Maximum 1204 1244 1378 5 4 4

Minimum 892 682 798 0 0 0

Observations 25 25 25 25 25 25

For the rail transfer area, the FIDLER measurements, the highest mean was observed in the road measurements, with the gravel areas being the lowest, and the mean for the soil measurements between. This observation is opposite of that for the transportation route. Among rail transfer area measurement data sets, the standard deviation of the soil data was lowest and the gravel highest. Overall, for the three FIDLER data sets, variability was lower than those on the transportation route. This observation is logical since the transportation route has greater variability in terrain and surface

conditions than the rail transfer area. For the a-radiation measurements, overall among the three measurement areas the results were comparable and did not have as many high measurements as

observed on the transportation route.

9

4.3 In-Situ Measurement Instrument Calibrations and Hot-Spot Calculations

Appendix C contains copies of the in-situ calibration documents for the calibrations completed at the AFIERA ICF. The logs for daily reliability tests conducted in the field at the QA/QC location are contained in Appendix C. The chi-square tests conducted indicated that the instruments passed. Table C contains the Hot-Spot calculations for the FIDLER used in the field. The “K” parameter was calculated using the AFIERA ICF calibration data. The parameters of mean background and

instrument response to the241 Am source at lateral distance of 0 cm was based on field measurements. These measurements and calculations should be periodically checked with FIDLER

instrumentation to assess consistency in response.

The FIDLER instrument is susceptible to temperature fluctuations as are all field portable [Nal(Tl)]

detection systems. The in-situ measurements for this background survey were conducted over field

conditions that had a significant fluctuation in temperature. The first survey day, 9 Jan 02 was the

coldest, with the FIDLER instrument having a mean background of 1804 counts at the QA/QC

location. 10 Jan 02 was warmer and had a mean FIDLER background response of 1738 counts, a

fairly minor difference. 9 Apr 02 had two sets of measurements: one in the morning when it was

relatively cool and one at the end of the survey when it had warmed. The mean FIDLER background response for these sets of measurements was 1450 and 1224 counts, respectively, for the early and later data sets. For routine FIDLER survey work at the rail transfer area during transportation operations should have background and calibration measurements conducted at the same location to ensure consistency and allow for background corrections if necessary. The post transportation FIDLER measurements should use the same QA/QC measurement location as used in

this survey.

4.4 Laboratory y-Spectroscopy Analysis Results

Table B-3 contains the AFIERA/SDRD analytical results for the y-spectroscopy analysis. One hundred twenty-one samples were analyzed. The results were reviewed for identified radiological constituents. The review did not identify any isotopes besides those that are typical constituents of natural background and sources of worldwide fallout. To document representative concentrations of some typical constituents of background and fallout, data was compiled for Ac, Cs, K, and 234Th. 241 Am is a constituent of fallout, but normally isn’t in concentrations that are traditionally

detected by y-spectroscopy analysis. However, since it is a co-contaminant in the BOMARC WGP, the minimum detectable concentrations (MDCs) are provided here for illustration of typical

detection limits for this method.

For 228Ac, 13 of the 121 samples had a reported concentration above the MDC, with the maximum at 0.62 + 0.12 picocuries per gram (pCi g'1). For the I37Cs, 76 samples had a reported concentration above the MDC, with the maximum at 1.79 ± 0.17 pCi g1. For 40K, 68 samples had a reported concentration above the MDC, with the maximum at 4.0 + 1.0 pCi g'1. For 34Th, only 12 samples had a reported concentration above the MDC, with the maximum at 1.4 + 0.7 pCi g'1. None of the samples had a reported241 Am concentration above the MDC. Figure 2 is a histogram of the MDCs for the 121 samples. From the plot, there are a significant number of samples with an MDC at or below 0.1 pCi g*1, but due to some samples with high MDC, the mean was 0.13 pCi g'. The highest

10

MDC was 0.2 pCi g'1. For the BOMARC WGP and an estimated 239+240pu to 24‘Am ratio, the surrogate 239+240pu MDC would be 1.1 pCi g'1, in close proximity to the agreed remediation criterion of 1 pCi g'1 for Lakehurst NAES, in the event that there is an accidental release during transportation operations.

Figure 2. Histogram of 241Am Minimum Detectable Concentrations.

50 t-

in m m in IT) m m m in r- oo ON o i—i <N cn Tt* in NO r- OO ON o o o r—< <—■ r-H i—( T—< r—4 i—i r-H 1—H

d d d d d d d d d d d d d

Minimum Detectable Concentration (pCi/g)

4.5 Laboratory Isotopic Plutonium Analysis Results

Table B-4 contains the laboratory isotopic plutonium results. For these samples, the reported result is listed, with the MDC for the sample, and plutonium chemical recovery. In contrast to the y-spectroscopy results, these results are reported in femtocuries per gram quantities because the concentrations were extremely low (1000 femtocuries is equal to one picocurie). Of the 121 analyses, only 17 had reported results greater than the MDC. The reported results ranged from (-7 + 8) to (80 + 50) fCi g'1, with a mean and median of 11.8 and 9 fCi g"1, respectively.

The a-spectral plot from the sample at location NAES046 is provided in Figure 3. The dominant peak in the plot is from 242Pu, the chemical tracer added to assess chemical recovery. The 239+240pu channel is higher in energy than the 242Pupeak, as annotated on the plot, but has significantly lower activity. The summed net counts in the 239f240pu channel was 12.7 counts, thus explaining the relatively high level of uncertainty for extremely low activity concentration samples.

11

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Among the 121 samples, the MDC’s ranged from 8 to 90 fCi g'1, with a mean and median of 34.4 and 35, respectively. Compared to the mean and maximum surrogate MDCs through use of 241Am by y-spectroscopy, this method is respectively, 20 and 15 times more sensitive. This method is more than adequate for measurements to meet the 1 pCi g'1 remediation criterion on Lakehurst NAES in the event of an accidental release.

Figure 4 contains a histogram of chemical recovery for the isotopic plutonium analyses. Overall, good chemical recoveries were observed. The recovery values ranged from 0.56 to 1.02, with a mean and standard deviation of 0.848 and 0.088, respectively.

Figure 4. Isotopic Plutonium Chemical Recovery Histogram.

Minimum Detectable Concentration (pCi/g)

For the 10 % AFIERA/SDRR duplicate samples, good agreement was observed in the paired analyses results. As well, for the 10 % duplicate samples sent to Framatome, good agreement was observed.

13

5. Conclusions

This report documents a radiological baseline survey conducted in support of the truck transport and rail transfer of WGP from the BOMARC site through Lakehurst NAES to rail facilities connecting to the NAES. The survey established pre-existing radiological conditions for both in-situ a-radiation and y-radiation, and for 239+240Pu.

Portable instrument measurements were typical for uncontaminated areas, with some variability that should be accounted for in field survey work accomplished while supporting transportation operations and for the post-remediation survey to be accomplished after transportation has ceased. Detectable concentrations of 239+240Pu were identified in the samples, with a mean and maximum concentrations of 11.8 and 80 fCi g'1, respectively.

6. Acknowledgements

Special thanks to Lary Martin, Navy RASO, and the staff of the Environmental Division of Lakehurst, NAES for valuable support in this project.

Special thanks to the AFIERA/SDRR staff for rush analysis of the samples to support the transportation plan tight timelines.

14

7. References

Eckerman, K.F.; Leggett, R.W; Nelson, C.B.; Puskin, J.S.; Richardson, A.C.B.; Cancer Risk

Coefficients for Environmental Exposure to Radionuclides, Federal Guidance Report No. 13, Environmental Protection Agency Report No. 402-R-99-001, September 1999.

Rademacher, S.E., Review of the Pu-239/240 to Am-241 Activity Ratio Analysis for Work Related

to Remediation of the BOMARC Missile Accident Site, Air Force Safety Center Technical Report AFSC-TR-1999-0002, November 1999.

Shleien, B. Editor, The Health Physics and Radiological Health Handbook, Table 8.13, Scinta Inc.,

1992.

Taschner, J.C., Technical Staff Member, Los Alamos National Laboratory, Personal

Communication, November 1998.

Trimble, Pro XR/XRS Receiver Manual, Trimble Navigation Limited, Sunnyvale CA, 1998.

Walker, F. W.; Miller, D. G.; and Feiner, F.; Chart of Nuclides, 13th Edition, General Electric

Company, 1984.

15

8. LIST OF ACRONYMS

Ac actinium

AFB Air Force Base

AFIERA Air Force Institute for Environmental Safety, and Occupational Health Risk Analysis

Am americium

BOMARC Boeing Michigan Aeronautical Research Center

cm2 centimeters squared

cpm counts per minute

Cs cesium

fCi femtocurie

FIDLER field instrument for the detection of low energy radiation

ICF Instrument Calibration Facility

K potassium

LANL Los Alamos National Laboratory

LLNL Lawrence Livermore National Laboratory

MARSSIM Multi-Agency Radiation Survey and Site Investigation Manual

MDC minimum detectable concentration

NA not applicable

NAES Naval Air and Engineering Station

Nal(Tl) thallium-drifted sodium iodide

pCi picocurie

Pu plutonium

RASO Radiological Affairs Support Office

SDR Radiation Surveillance Division

SDRH Health Physics Branch

Th thorium

16

Appendix A

Lakehurst Overall Site and Rail Transfer Area

17


18

2002

Lak

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Appendix B

Baseline Survey Results

21


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Appendix C

Calibration Logs and Hot-Spot Calculations

43


44

Institute for Environment, Safety and Occupational Health Risk Analysis

Calibration Data Sheet Date 4-Jan-02

Due 4-Jul-02

MFG.

Instrumentation Data

Mode! Serial No. MFG.

Detector Data

Model Serial No.

Ludlum 2221 169214 Bicron G-5 FIDLER B603M

Isotope

Calibrated Check Sources

Serial # Cal date MFG.

Pulser

Model Serial No.

Am-241 2Q156 1-Apr-02 Ludlum 500 102951

Emission

Sensitivity/Window

Sensitivity Window Temperature

Calibration Conditions

Humidity Location

Gamma 12 mV 22 mV 64.2 28.50% ICF/Bldg 1193

Electronics Package

Rate meter Check Range

Multiplier Reference

Point As found Response Corrected Response

% error

X1000 400000 400000 400000 0.00%

X1000 100000 100000 100000 0.00%

XI00 40000 40000 40000 0.00%

X100 10000 10000 10000 0.00%

XI0 4000 4000 4000 0.00%

XI0 1000 1000 1000 0.00%

XI 400 400 400 0.00%

XI 100 100 100 0.00%

Range Multiplier

Reference Point

Scaler Check

As found Response Corrected Response

% error

XI000 400000 396343 396343 -0.91%

XI000 100000 98980 98980 -1.02%

X100 40000 39644 39644 -0.89%

X100 10000 9874 9874 -1.26%

XI0 4000 3961 3961 -0.98%

XI0 1000 988 988 -1.20%

XI 400 397 397 -0.75%

XI 100 98 98 -2.00%

Calibrated by:

Bryan D. Blasy, SSgt Health Physics Technician 1 of[Pages]

CRYSTAL RESOLUTION

FIDLER

60 KeV (Am-241) Peak Channel LHM (Channel) RHM (Channel)

~411 354 470

% FWHM= 28.22%

High Voltage Plateau

FIDLER

60 KeV (Am-241)_HV_CPM

900 104208 Max Reading=

Final HV=

Statistical Reliability Check

FIDLER

60 Kev (Am-241)

1

2

3

4

5

6

7

8

9

10

Average=

Std. Dev.=

Chi2=

Source Counts

103580

103803

103552

104512

104207

104270

103639

104308

104103

104390

104036.4

360.3162808

11.23116909

FIDLER Program

Distance (cm) CPM (60 KeV)

10 Minute Background 5382.00

0 104092

20 57094.00

40 20404

50 12541

60 8090

80 3827

100 2265

Calibrated by:

Bryan D. Blasy, SSgt Health Physics Technician

104208

900

2of[Pages]

Institute for

Environment, Safety and Occupational Health

ilfek Analysis

Calibration Data Sheet Date 2-Jan-02

Due l-Jul-02

Instrumentation Data Detector Data

MFG. Model Serial No. MFG. Model Serial No.

Ludlum 2360 145487 Ludlum 43-89 PR154738

Calibrated Check Sources Pulsar

Isotope Serial # Cal date MFG. Model Serial No.

Pu-239 k-827 2-Mar-99 Ludlum 500 48124

Tc-99 514-38-2 2-Jan-96

Sr-90 221-1-6 6-Jan-88

Sensitivity/Window Calibration Conditions

Isotope Sensitivity Window Temperature Humidity Location

Alpha 120 mV n/a 70.9 22.00% ICF/Bldg 1193

Beta 3.5 mV 30 mV

Gamma n/a n/a Final Voltage 775

ELECTRONICS PACKAGE

Range Reference Corrected % error %error One minute count @

Multiplier Point As found Response Response (A) (B) 40000 CPM

XI000 400Kcpm 400K 400K 0 0 39881

XI000 10OKcpm 100K 100K 0 0

X100 40Kcpm 40K 40K 0 0

X100 lOKcpm 10K 10K 0 0

X10 4Kcpm 4K 4K 0 0

X10 IKcpm IK Ik 0 0

XI 400cpm 400 400 0 0

lOOcpm 100 100 0 0

Efficiency

2pi

Pu-239 Tc-99 Sr-90

Heal 22.26 17.54 46.21

Center 21.21 15.83 45.84

Toe 19.35 17.47 48.37 Averaqe 20.94 16.95 46.81

Calibrated by:

SSgt Bryan D. Blasy

Health Physics Technician

4/3/2002 47

1 of 2

High Voltage

HV Back Ground

775 0/212

800 0/247

825 2/311

Efficiency

Pu-239 DPM Alpha

3.23E+03 Heal 719

Center 685

Toe 625

Tc-99 DPM Beta

2.22E+05 Heal 38935

Center 35139

Toe 38781

Sr-90 DPM Beta

2.26E+04 Heal 10443

Center 10360

Toe 10932

Calibrated by:

SSgt Bryan D. Blasy


4/3/2002 2 of 2 48

institute for

Analysis

Calibration Data Sheet Date

Due

2-Jan-02

1-Jul-02

/

Instrumentation Data Detector Data

MFG. Model Serial No. MFG. Model Serial No.

Ludlum 2360 145470 Ludlum 43-89 PR153659

Calibrated Check Sources Pulsar

Isotope Serial # Cal date MFG. Model Serial No.

Pu-239 k-827 2-Mar-89 Ludlum 500 48124

Tc-99 514-38-1 2-Jan-96

Sr-90 221-1-6 6-Jan-88

Sensitivity/Window Calibration Conditions

Isotope Sensitivity Window Temperature Humidity Location

Alpha 120 mV n/a 67 28.30% ICF/Bldg 1193

Beta 3.5 mV 30 mV

Gamma n/a n/a Final Voltage 800

ELECTRONICS PACKAGE

Range Reference Corrected % error %error One minute count @

Multiplier Point As found Response Response (A) (B) 40000 CPM

XI000 400Kcpm 400K 400K 0 0 39903

XI000 lOOKcpm 100K 100K 0 0

X100 40Kcpm 40K 40K 0 0

X100 lOKcpm 10K 10K 0 0

X10 4Kcpm 4K 4K 0 0

X10 IKcpm IK Ik 0 0

XI 400cpm 400 400 0 0

xl lOOcmp 100 100 0 0

Pu-239

35%

Efficiency

2pi

Tc-99

20%

Sr-90

35%

Heal 22.01 16.81 50.00

Center 20.62 15.04 46.92

Toe 21.61 14.35 45.14

Averaqe 21.41 15.40 47.35

Calibrated by:

SSgt Bryan D. Blasy

Health Physics Technician 49

4/3/2002 1 of 2

High Voltage

HV BKG

775 0/202

800 0/243

825 0/341

Pu-239 DPM

Efficiency

Alpha

3.23E+03 Heal 711

Center 666

Toe 698

Tc-99 DPM Beta

2.22E+05 Heal 37312

Center 33396

Toe 31852

Sr-90 DPM Beta

2.26E+04 Heal 11301

Center 10604

Toe 10201

Calibrated by:

SSgt Bryan D. Blasy


4/3/2002

Chi-Square Background Check

Date 9-Jan-02 Time 0938 Temperature_26 degrees F

Location LAKEHURST N433068.394 E544002.318

1 1804 Estimated 2 1866 Standard deviation

3 1825 | 42.47 |

4 1774 5 1817 6 1711 7 1794

8 1757 Real

9 1776 Standard deviation

10 1775 43.51

11 1837 12 1828 Chi-Square

13 1814 14.69

14 1795 15 1886 Confidence level

0.05

Critical Value 25.00

Data passes Chi-Square test

Instrument FIDLER B603M / 2221 Meter 169214

High Voltage: 902 Threshold: 133 Window in: 174

51


Date 10-Jan-02 Time 0905 Temperature_36 degrees F

Location LAKEHURSTN433068.394 E544002.318

1 1776 Estimated 2 1769 Standard deviation

3 1729 |“ 41.69 ]

4 1703 5 1737

6 1777

7 1812

8 1676 Real


10 1732 43.88

11 1738 12 1778 Chi-Square

13 1654 15.50


0.05





52


Date 9-Apr-02 Time_0740 Temperature_60 degrees F

Location LAKEHURSTN433068.394 E544002.318

1 1428 Estimated


3 1452 38^08 |

4 1433 5 1431 6 1441 7 1405 8 1433 Real


10 1490 27.99

11 1514 12 1485 Chi-Square

13 1433 7.56


0.05





53


Date 9-Apr-02 Time 1130 Temperature 75 degrees F

Location LAKEHURST N433068.394 E544002.318

1 1266 2 1193 3 1198

4 1232 5 1168

1252 1243 1223

> 1214 > 1263

1187 1237 1219 1237 1253

Estimated Standard deviation

35.01 |

Real

Standard deviation 29.15

Chi-Square 9.71

Confidence level 0.05





54

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