ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller I MJW Technical Services

Page 1 of 12

DOE Review Release 08/23/2011

Document Title:

Analysis of Potential Exposures Resulting 

from the Burning of Degraded Solvents at the 

Savannah River Site

Document Number: ORAUT-RPRT-0051

Revision: 00

Effective Date: 08/16/2011

Type of Document: Report

Supersedes: None

Subject Expert(s): James M. Mahathy and Joseph S. Guido

Approval: Signature on File Approval Date: 08/08/2011

James M. Mahathy, Document Owner

Concurrence: Signature on File Concurrence Date: 08/09/2011

James P. Griffin, Deputy Project Director

Concurrence: Signature on File Concurrence Date: 08/11/2011

Kate Kimpan, Project Director

Approval: Signature on File Approval Date: 08/16/2011

James W. Neton, Associate Director for Science

New Total Rewrite Revision Page Change

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-RPRT-0051 Revision No. 00 Effective Date: 08/16/2011 Page 2 of 12

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION

NUMBER DESCRIPTION

08/16/2011 00 This report describes activities performed by the Savannah River Site

(SRS) related to the burning of radioactive solvent waste with the 

objective of determining the feasibility of reconstructing internal 

doses potentially received from exposures to fission product and 

alpha radionuclides. Incorporates formal NIOSH review comments. 

Training required: As determined by the Objective Manager. 

Initiated by James M. Mahathy and Joseph S. Guido.
Document No. ORAUT-RPRT-0051 Revision No. 00 Effective Date: 08/16/2011 Page 3 of 12

TABLE OF CONTENTS

SECTION TITLE PAGE

Acronyms and Abbreviations ...............................................................................................................4

1.0 Introduction.................................................................................................................................5

2.0 Radiological Monitoring...............................................................................................................6

3.0 Potential Intake Analysis .............................................................................................................7

3.1 Fission Products Radionuclides...........................................................................................8

3.2 Alpha-Emitting Radionuclides ..............................................................................................8

4.0 Potential Intake Analysis .............................................................................................................9

References ........................................................................................................................................10

LIST OF TABLES

TABLE TITLE PAGE

1-1 Estimate of solvent burned..........................................................................................................6

2-1 Burning pit fission product air monitoring data.............................................................................7

2-2 Burning pit alpha activity product air monitoring data .................................................................. 7

3-1 Fission product radionuclide annual intake quantities from 95th percentile 

gross beta air concentration - 1965-1972....................................................................................8

3-2 Plutonium annual intake quantities (pCi) based on gross alpha air 

concentration ..............................................................................................................................9
Document No. ORAUT-RPRT-0051 Revision No. 00 Effective Date: 08/16/2011 Page 4 of 12

ACRONYMS AND ABBREVIATIONS

cm centimeter

cpm counts per minute

ft foot

g gram

gal gallon

L liter

m meter

mL milliliter

MPC maximum permissible concentration

NIOSH National Institute for Occupational Safety and Health

pCi picocurie

SRS Savannah River Site

μCi microcurie
Document No. ORAUT-RPRT-0051 Revision No. 00 Effective Date: 08/16/2011 Page 5 of 12

1.0 INTRODUCTION

A series of burning/rubble pits was used at the Savannah River Site (SRS) from site construction 

through 1974 to dispose of various types of wastes. The burning pits were set up at the Central 

Shops Area and in F-Area to burn construction wastes. As reactors were built and brought on line, 

rubble pits were installed near each reactor to burn construction waste and other nonradioactive 

waste items including scrap materials and volatile organic materials. Mostly nonradioactive materials 

were burned in pits in D-, F-, K-, L-, P-, and R-Areas. There were also burning pits for nonradioactive 

materials at the TNX facility and the metals burning pit. A pit for burning radioactive waste was 

constructed in the Radioactive Waste Burial Ground, 643-G. Burning pits were created by bulldozing 

open trenches between 8 to 12 ft deep and from 250 to 400 ft long. The waste was burned about 

once a month (RAC 2001). At 643-G, solvent was burned in an 8 × 8 × 4-ft steel pan with a rain shed 

over the top; the pan was replaced in 1964 due to corrosion by a longitudinally halved 400-gal tank 

(DuPont 1973).

Materials Burned

Most of the radioactive materials burned at the SRS Radioactive Waste Burial Ground were spent and 

degraded solvents, such as tributyl phosphate and kerosene collected from the separations areas. 

Before being burned, the solvents were washed as part of SRS solvent recovery (DuPont 1958a). 

SRS implemented an improved solvent washing procedure in May 1955 that used a higher 

concentration of NaOH in the caustic wash followed by an additional water wash to remove residual 

caustic material and the associated activity more efficiently (DuPont 1955). A continuous solvent 

wash system was implemented in the 200-Area in 1956 (Christl 1956). As an example of solvent 

washing results, the SRS Works Technical Department reported that as of May 28, 1956, hot solvent 

gamma activities in F-Area for the previous 4 weeks had averaged 2.2 × 104 cpm/mL unwashed; and 

4.5 × 103 cpm/mL washed (DuPont 1956b). Residues from the washing process that were too high to 

burn were stored in tanks to enable decay of short-lived fission product activity. Residues were 

monitored by gross gamma, gross beta, and gross alpha analysis, as needed, before being burned 

(DuPont,1956c,d, 1957a,b, 1958b, 1963a, 1965a). The gamma activity level in 1957 was 4,000

cpm/mL (DuPont 1957b). By 1960, the SRS Health Physics Section had implemented a gamma 

activity limit of 1,000 cpm/mL; solvents exceeding that amount could not be burned (DuPont 1960). In 

addition, gamma dose rates were measured at the burning pit (DuPont 1957b, 1963a,b, 1965a).

Information and data about the burning of solvents have been reported in some Works Technical 

Department monthly progress reports. A total of 170,000 gallons of solvent were burned prior to 

February 1964 and it is believed that the best estimate of the total amount burned to be 400,000 

gallons between 1956 and 1972 (RAC 2001). Table 1-1 below provides a tabular summary of 

monthly quantities burned, based on available data.

Monthly reports suggest that burning was not continuous and varied tremendously from month to 

month ranging from zero to 19600 gal (in one week in May 1962). Burning rates were sparsely 

reported as well. The initial burn rate reported in February 1956 was 2 gal/min (Dupont 1956a) and 

was reported as 0.2 gal/min in the May 1956 (Dupont 1956b). In a December 1956 report, the burn 

rate was noted as ‘accelerated’ to 100 gal/hr (Dupont 1957c). The notion that a 1 gal/min burn rate 

was standard is further supported by a May 1963 document indicating trial burning at an accelerate 

rate of 3 gal/min which produced a smoke plume while no airborne activity was detected at a burning 

rate of 1 gallon per minute (Dupont 1963d).

The number of burning days for each month may be conservatively bounded using the 95th percentile 

of the data in Table 1-1 (7400 gal) and apply a burring rate of 1 gal/min. This corresponds to a total of 

5 burning days per month and may be used in conjunction with the intake estimates presented later in 
Document No. ORAUT-RPRT-0051 Revision No. 00 Effective Date: 08/16/2011 Page 6 of 12

section 3 of this document to provide a claimant favorable estimate of internal exposure from solvent 

burning activities.

Table 1-1. Estimate of solvent burned.

Period Gallons burned Period Gallons burned

02/56 200 9/58–10/58 2,894a

3/56–4/56 1,380a 11/58–3/60 3,400a

05/56 830 04/60 1,000

06/56 690 5/60–7/60 6,650a

07/56 5,300 8/60–4/62 30,389a

08/56 4,000 05/62 19,600

9/56–10/56 4,980a 6/62–12/63 27,495a

11/56 870 1/64–3/64 21,600a

12/56 10,700 04/64 4,000

01/57 3,300 5/64–12/64 57,600a

02/57 0 01/65 3,000

03/57 1,930 02/65 5,000

04/57 270 03/65 8,533a

05/57 3,565 04/65 1,800

06/57 1,126 5/65–7/65 25,600a

07/57 1,790 08/65 1,800

08/57 1,447a 9/65–10/65 17,067a

09/57 0 11/65 9,000

10/57 0 12/65 7,250

11/57–12/57 2,894a 01/66 800a

01/58 1,115 02/66 0

2/58–6/58 7,555a 3/66–8/66 4,800a

07/58 8,180 09/66 7,800

08/58 2,050 10/66–12/73 68,800a

a. Indicates calculated average based on summary data and quantities accounted for 

in intervening months

2.0 RADIOLOGICAL MONITORING

The SRS performed downwind air monitoring during the infrequent (as many as 3 days per month)

(DuPont 1956b) burning events. Ground-water monitoring was also performed but is not the subject 

of this report. Stationary sampling using adhesive paper and monitoring of vegetation around the 

perimeter of the burial ground indicated negligible fallout from the solvent burning (DuPont 1973). 

RAC 2001 stated that the release of radionuclides from solvent burning had been negligible through 

1970.

NIOSH has identified summary results of the fission product air monitoring data mentioned above. 

The data were recorded in monthly reports and other documents (Butler 1956; DuPont 1956e,f, 

1957c,d,e,f,g, 1958a,b, 1960, 1963c,d, 1965a). Maximum permissible concentrations (MPCs) for 

fission products in air was 200 pCi/m3

. Results of air monitoring are not provided for all months 

because the formats of the monthly reports varied during the period of solvent burning (RAC 2001). 

The fission product monitoring results, assumed to be gross beta analyses, are provided in Table 2-1.

The 3,500 pCi/m3 recorded in April 1965 resulted from the handling and burial of a highly 

contaminated heat exchanger. Some solvent was burned, but DuPont (1965a) implies that the highfission product resulted from the burial of the heat exchanger head and evaporator.

NIOSH has obtained maximum air monitoring results from four events in which solvents containing 

plutonium alpha wastes were burned. These results are shown in Table 2-2.
Document No. ORAUT-RPRT-0051 Revision No. 00 Effective Date: 08/16/2011 Page 7 of 12

Only two results showed detectable activity: 2 pCi/m3 (April 1963c) and 88 pCi/m3 (August 1965) 

(Dupont 1963c, DuPont 1965b). The maximum result, obtained on July 30, 1965 during field 

sampling, exceeded the 1965 site radioactivity concentration guide (RCG) for Pu by a factor of 44.

That particular operation was conducted over an 11-day period; about 1800 gal of spent process 

solvent was burned. The measured alpha air concentration had increased with each of four batches 

burned in that event; presumably due to a buildup of activity in the residue. Dupont 1965b states that 

solvent was more highly contaminated with alpha radiation than any previously burned solvent. That 

burning event was shut down immediately after the high result was obtained (DuPont 1965b).

Table 2-1. Burning pit fission product air monitoring data (pCi/m3

).

a

Month

Maximum 

measured air 

concentration

Radioactivity 

concentration 

guide

Reference

February 1956 20 200 Butler 1956

July 1956 20 200 DuPont 1956d

August 1956 24 200 DuPont 1956e

October 1956 160.00 200 DuPont 1956f

December 1956 1.0 200 DuPont 1957c

January 1957 1.0 200 DuPont 1957d

May 1957 < 1.0 200 DuPont 1957e

June 1957 1.0 200 DuPont 1957b

July 1957 < 1.0 200 DuPont 1957f

August 1957 < 1.0 200 DuPont 1957g

July 1958 31.8 200 DuPont 1958b

April 1959 90.0 200 DuPont 1960

January 1958 < 1.0 200 DuPont 1958a

April 1963 300 200 DuPont 1963c

May 1963 380 200 DuPont 1963d

April 1965 3,500 200 DuPont 1965a

a. Data represent maximum result measured during event monitoring when 

multiple samples were collected. Individual air sample results can be obtained 

from SRS air sample log sheets.

Table 2-2. Burning pit alpha activity product air monitoring 

data (pCi/m3

).

a

Month Maximum measured 

alpha air concentration Reference

July 1958 No detectable activity DuPont 1958b

April 1963 2b DuPont 1963

May 1964 No detectable activity DuPont 1964

July 20–30, 1965 88 DuPont 1965b

a. Data represent maximum result measured during event monitoring 

when multiple samples were collected. 

b. Individual air sample results can be obtained from SRS air sample 

log sheets.

Monitoring for alpha emitters was based on assay of the degraded solvent to be burned. Burned 

solvent was also monitored by gross alpha analysis in 1958, although no alpha activity was detected 

(DuPont 1958b).

3.0 POTENTIAL INTAKE ANALYSIS

While RAC 2001 reported that the release of radionuclides from solvent burning was considered to 

have been negligible, NIOSH analyzed the available air monitoring data to estimate air concentrations 

of fission products and from plutonium.
Document No. ORAUT-RPRT-0051 Revision No. 00 Effective Date: 08/16/2011 Page 8 of 12

3.1 FISSION PRODUCTS RADIONUCLIDES

The air concentration data listed in Table 2-1 were analyzed using the methodology in ORAUTPROC-0095 (ORAUT-2005) for the purpose of determining the 95th percentile of the airborne 

concentration distribution.

Given the small set of air monitoring data, the 95th-percentile air concentration of fission product 

radionuclides (1,800 pCi/m3

) was used as the basis for calculation of a daily intake quantity of fission 

product radionuclides. This air concentration was applied to a 180-day-old nuclide mixture yielding 

intake quantities shown below in Table 3-1 (ORAUT 2007). Inhalation intakes were calculated 

assuming an exposure duration of 40 hrs a month (i.e., 5 8 hr days), 12 months a year, for a total 

annual air inhalation of 576 m3

. Ingestion intakes in units of pCi/d were calculated by multiplying the 

air concentration in units of pCi/m3 by a factor of 0.2 (NIOSH 2004) and were further adjusted to 

calendar day intakes by multiplying by a factor of 60 (i.e., 5 burning days per month * 12 months = 60 

buring days / yr)).

Table 3-1. Fission product radionuclide annual intake 

quantities (pCi) from 95th percentile gross beta air 

concentration – 1965 - 1972.

Radionuclide Inhalation intake Ingestion intake

Ce-141 2.E+04 5.E+02

Ce-144 2.E+05 5.E+03

Cs-134 6.E+03 1.E+02

Cs-137 2.E+04 5.E+02

Eu-155 2.E+03 3.E+01

Fe-55 2.E+04 4.E+02

Nb-95 3.E+05 6.E+03

Pm-147 6.E+04 1.E+03

Ru-103 4.E+04 7.E+02

Ru-106 9.E+04 2.E+03

Sr-89 6.E+04 1.E+03

Sr-90 2.E+04 4.E+02

Y-91 1.E+05 2.E+03

Zr-95 1.E+05 3.E+03

3.2 ALPHA-EMITTING RADIONUCLIDES

The burning of degraded solvents containing alpha emitters (plutonium) was reported in only four of

the monthly described events – one each in 1958 (DuPont 1958b), 1963 (DuPont 1963c), 1964 

(DuPont 1964) and 1965 (DuPont 1965b); maximum gross alpha air concentrations were also 

reported with two of these four burning events (Table 3-2). SRS reported "no detectable activity" from 

field analysis performed for the 1958 and 1964 events. Due to the limited monthly number of burning 

events containing alpha activity in degraded solvents, NIOSH assumes that concentrations of uranium 

and plutonium were negligible in most burns. However, to bound potential intakes of alpha activity, 

NIOSH used the two positive air monitoring results to derive a bounding air concentration of plutonium 

released from solvent burning. The two measured air concentrations differed by a factor of 44. While 

the higher sample exceeded the RCG by a factor of 44, the smaller result was equal to the 1965 RCG 

(2 pCi/m3

). An air concentration of 2 pCi/m3 should be used to bound intakes of total plutonium from 

1956 through 1964 and from 1966 through 1972. An air concentration of total plutonium of 88 pCi/m3

should be used to bound intakes of plutonium for 1965 only. 
Document No. ORAUT-RPRT-0051 Revision No. 00 Effective Date: 08/16/2011 Page 9 of 12

Table 3-2 presents inhalation and ingestion intakes based on the air concentrations assumptions 

discussed above. Inhalation intakes were calculated assuming an exposure duration of 40 hrs a 

month (i.e., 5 8 hr days), 12 months a year, for a total annual air inhalation of 576 m3

. Ingestion 

intakes in units of pCi/d were calculated by multiplying the air concentration in units of pCi/m3 by a 

factor of 0.2 (NIOSH 2004) and were further adjusted to calendar day intakes by multiplying by a 

factor of 60 (i.e., 5 burning days per month * 12 months = 60 buring days / yr)).

Table 3-2. Plutonium annual intake quantities (pCi) based on 

gross alpha air concentration.

Period Inhalation intake Ingestion intake

1956–1964, 1966–1972 1152 24

1965 50688 1056

4.0 POTENTIAL INTAKE ANALYSIS

NIOSH has found adequate data to describe the burning process, to characterize the source term, 

and to quantify air concentrations that resulted through the release of radioactive emissions from the 

burning process. Further, while SRS stated that releases of radioactivity resulting from solvent 

burning were negligible, NIOSH can estimate potential and plausible intakes of fission products 

radionuclides and plutonium for SRS workers involved in waste operations.
Document No. ORAUT-RPRT-0051 Revision No. 00 Effective Date: 08/16/2011 Page 10 of 12

REFERENCES

Butler, H. L., 1956, “Health Physics Considerations of Solvent Burning at 643-G,” memorandum to 

W. W. Tryon, E. I. du Pont de Nemours and Company, Savannah River Plant, Aiken, South 

Carolina, February 16. [SRDB Ref ID: 49047, pp. 2-4]

Christl, R. J., 1956, “Project 8920 - 200 Area Continuous Solvent Washing - FDM 262-H,”

memorandum to E. E. Wilson, E. I. du Pont de Nemours and Company, Explosives 

Department, Wilmington, Delaware, January 6. [SRDB Ref ID: 89469, p. 2]

DuPont (E. I. du Pont de Nemours and Company), 1955, Monthly Progress Report, May 1955, Works 

Technical Department, DPSP·55-1-5, Atomic Energy Division, Savannah River Plant, 

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DuPont (E. I. du Pont de Nemours and Company), 1956f, Monthly Progress Report, September 1956,

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DuPont (E. I. du Pont de Nemours and Company), 1957e, Monthly Progress Report, April 1957,

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