DRAFT 

ADVISORY BOARD ON RADIATION AND WORKER HEALTH 

NATIONAL INSTITUTE FOR 

OCCUPATIONAL SAFETY AND HEALTH 

A PRELIMINARY REVIEW OF NIOSH’S PROGRAM 

EVALUATION REPORT 

DCAS-PER-037, “AMES LABORATORY TBD REVISION” 

Contract No. 200-2004-03805 

SCA-TR-PR2013-0037, Rev. 0 

Prepared by 

U. Hans Behling, PhD, MPH 

SC&A, Inc. 

S. Cohen & Associates 

1608 Spring Hill Road, Suite 400 

Vienna, VA 22182 

January 2013 

Disclaimer 

This document is made available in accordance with the unanimous desire of the Advisory Board on 

Radiation and Worker Health (ABRWH) to maintain all possible openness in its deliberations. However, 

the ABRWH and its contractor, SC&A, caution the reader that at the time of its release, this report is predecisional and has not been reviewed by the Board for factual accuracy or applicability within the 

requirements of 42 CFR 82. This implies that once reviewed by the ABRWH, the Board’s position may 

differ from the report’s conclusions. Thus, the reader should be cautioned that this report is for 

information only and that premature interpretations regarding its conclusions are unwarranted.

 
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Document No. 

SCA-TR-PR2013-0037 

S. COHEN & ASSOCIATES: 

Technical Support for the Advisory Board on

Radiation & Worker Health Review of 

NIOSH Dose Reconstruction Program 

Effective Date: 

Draft – January 2, 2013 

A PRELIMINARY REVIEW OF NIOSH’S 

PROGRAM EVALUATION REPORT 

DCAS-PER-037, “AMES LABORATORY 

TBD REVISION” 

Page 2 of 23 

Task Manager: 

________________________ Date: ___________ 

U. Hans Behling, PhD, MPH 

Supersedes: 

N/A 

Project Manager: 

________________________ Date: ___________ 

John Stiver, CHP 

Reviewer(s): 

 John Mauro 

 John Stiver 

Record of Revisions 

Revision 

Number 

Effective 

Date Description of Revision 

0 (Draft) 01/2/2013 Initial issue 
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TABLE OF CONTENTS 

 

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

1.0 Statement of Purpose ...........................................................................................................5 

2.0

...................................................................................................................7 

Subtask 1: Identify the Circumstances that Necessitated the Need for 

DCAS-PER-037

2.1 Changes Incorporated in Revision 01 of ORAUT-TKBS-0055..............................7 

2.2 Changes Incorporated in Revision 02 of ORAUT-TKBS-0055..............................7 

2.3 Changes Incorporated in Revision 03 of the ORAUT-TKBS-0055 ........................8 

2.4 SEC Classes Added..................................................................................................9 

3.0 Subtask 2: Assess NIOSH’s Specific Methods for Corrective Action .............................10 

3.1 Documents Salient to DCAS-PER-037 That Have Not Been Evaluated ..............10 

3.2

.............................................................................................................11 

Preliminary Findings and The Need for a Formal Review of Salient 

Documents

3.2.1 Use of Potentially Inappropriate Dose Models/Surrogate Data.................11 

3.2.2 Use of NUREG-1400 for Modeling Intakes of Fission Products..............12 

3.2.3 Unsupported “Attributions and Annotations”............................................12 

3.2.4

.........................................................................................................17 

Failure to Address U and Th Blowouts as Significant Environmental 

Events

4.0

..............................................................................19 

Subtask 3: Evaluate the PER’s Stated Approach for Identifying the Number of 

DRs Requiring Re-evaluation of Dose

4.1 Identification of Two Employment Periods...........................................................19 

4.2

............................20 

SC&A’s Comments Regarding Corrective Actions Taken by NIOSH for 

Identifying Claims/DRs That May Require Further Evaluation

5.0 References..........................................................................................................................21 
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ABBREVIATIONS AND ACRONYMS 

A&A Attributions and Annotations 

ABRWH or Advisory Board on Radiation and Worker Health 

Advisory Board 

AWE Atomic Weapons Employer 

DCAS Division of Compensation Analysis and Support 

DOE Department of Energy (U.S.) 

DR Dose Reconstruction 

EEOICPA Energy Employees Occupational Illness Compensation Program Act 

IREP Interactive RadioEpidemiological Program 

LAT lateral 

μg/d micrograms per day 

μg/L micrograms per liter 

NIOSH National Institute for Occupational Safety and Health 

OCAS Office of Compensation Analysis and Support 

ORAUT Oak Ridge Associated Universities Team 

PA posterior to anterior 

pCi/d picocuries per day 

PEP Program Evaluation Plan 

PER Program Evaluation Report 

POC Probability of Causation 

SC&A S. Cohen and Associates (SC&A, Inc.) 

SEC Special Exposure Cohort 

SRDB Site Research Database 

TBD Technical Basis Document 

TIB Technical Information Bulletin 
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1.0 STATEMENT OF PURPOSE 

 

To support dose reconstruction (DR), the National Institute for Occupational Safety and Health 

(NIOSH) and the Oak Ridge Associated Universities Team (ORAUT) have assembled a large 

body of guidance documents, workbooks, computer codes, and tools. In recognition of the fact 

that all of these supporting elements in DR may be subject to revisions, provisions exist for 

evaluating the effect of such programmatic revisions on the outcome of previously completed 

DRs. Such revisions may be prompted by document revisions due to new information, 

misinterpretation of guidance, changes in policy, and/or programmatic improvements. 

The process for evaluating potential impacts of programmatic changes on previously completed 

DRs has been proceduralized in OCAS-PR-008, Preparation of Program Evaluation Reports 

and Program Evaluation Plans (OCAS 2006), Revision 2, dated December 6, 2006. This 

procedure describes the format and methodology to be employed in preparing a Program 

Evaluation Report (PER) and a Program Evaluation Plan (PEP). 

A PER provides a critical evaluation of the effect(s) that a given issue/programmatic change may 

have on previously completed DRs. This includes a qualitative and quantitative assessment of 

potential impacts. Most important in this assessment is the potential impacts on the Probability 

of Causation (POC) of previously completed DRs with POCs of <50%. 

As needed, a PEP may be issued that serves as a formal notification of an impending PER. The 

PEP provides a preliminary description of the issue(s) that will be addressed in the PER, and 

summarizes the likely scope of the effort required to complete the PER. 

During an Advisory Board meeting on November 1, 2012, SC&A was tasked by the Board to 

conduct a review of DCAS-PER-037, Ames Laboratory TBD Revision (DCAS 2012). In 

conducting a PER review, SC&A is committed to perform the following five subtasks, each of 

which is discussed in this report: 

Subtask 1: Assess NIOSH’s evaluation/characterization of the “issue” and its potential impacts 

on DR. Our assessment intends to ensure that the “issue” was fully understood and 

characterized in the PER. 

Subtask 2: Assess NIOSH’s specific methods for corrective action. In instances where the PER 

involves a technical issue that is supported by document(s) (e.g., white papers, technical 

information bulletins, procedures) that have not yet been subjected to a formal SC&A 

review, Subtask 2 will include a review of the scientific basis and/or sources of 

information to ensure the credibility of the corrective action and its consistency with 

current/consensus science. Conversely, if such technical documentation has been 

formalized and previously subjected to a review by SC&A, Subtask 2 will simply provide 

a brief summary/conclusion of this review process. 

Subtask 3: Evaluate the PER’s stated approach for identifying the universe of potentially 

affected DRs, and assess the criteria by which a subset of potentially affected DRs was 

selected for re-evaluation. The second step may have important implications in instances 
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NOTICE:

where the universe of previously denied DRs is very large and, for reasons of practicality, 

NIOSH’s re-evaluation is confined to a subset of DRs that, based on their scientific 

judgment, have the potential to be significantly affected by the PER. In behalf of 

Subtask 3, SC&A will also evaluate the timeliness for the completion of the PER. 

Subtask 4: Conduct audits of DRs affected by the PER under review. Based on information 

contained in Table 1 (and discussed in Section 3.1 below), the number of DRs selected 

for audit for a given PER will vary. (It is assumed that the selection of the DRs and the 

total number of DR audits per PER will be made by the Advisory Board.) 

Subtask 5: Prepare a comprehensive written report that contains the results of the above-stated 

subtasks, along with our review conclusions. 
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2.0 SUBTASK 1: IDENTIFY THE CIRCUMSTANCES THAT 

NECESSITATED THE NEED FOR DCAS-PER-037 

DCAS-PER-037 was issued on July 17, 2012, in response to a series of technical revisions to the 

Ames Laboratory Technical Basis Document (TBD) (ORAUT-TKBS-0055) and the sequential 

designation of four classes of employees at Ames for addition to the Special Exposure Cohort 

(SEC) authorized under EEOICPA. 

While some changes incorporated in these revisions increased the assigned doses, others resulted 

in a decrease. As stated in DCAS-PER-037, all changes introduced in Revision 01, Revision 02, 

and Revision 03 of ORAUT-TKBS-0055 (ORAUT 2009, ORAUT 2011a, and ORAUT 2012, 

respectively) reflect formal internal reviews by ORAUT, as well as NIOSH review comments. 

2.1 CHANGES INCORPORATED IN REVISION 01 OF ORAUT-TKBS-0055 

On December 18, 2009, Revision 01 of the Ames TBD (ORAUT 2009) was issued, which 

contained the following changes that impacted dose estimates: 

 Incorporated SEC-00075. This class includes all employees and subcontractors at Ames 

Laboratory from January 1, 1942, through December 31, 1954. 

 Occupational Medical Doses. In Revision 00, it had only been assumed that preemployment medical chest x-rays used a posterior to anterior (PA) exposure geometry. 

In the absence of empirical documentation, dose estimates to skin and other organs were 

also derived for a lateral (LAT) exposure geometry. As a result, Tables 3-1 through 3-6 

were modified and Tables 3-7 and 3-8 were added for each of the four time periods. 

 Default Intake Values (for workers without bioassay data). Select default intake values 

that were cited in Table 5-7 of Revision 00 were corrected in Table 5-8 of Revision 01. 

 Revision to Unmonitored Doses before 1953. Sections 6.2.1 and 6.3.1 of Revision 01 of 

the Ames TBD were revised to address changes for deriving external doses. Prior to 

1953, reference to ORAUT-OTIB-0004 was replaced with methods described in BattelleTBD-6000 (Battelle 2006a) and Battelle-TBD-6001 (Battelle 2006b). Section 6.3.1.2 of 

Revision 01 was modified to include coworker doses between 1952 to the present. For 

Ames Laboratory, the label of an unmonitored worker includes workers who were not 

monitored, as well as monitored workers without dosimeter records or whose records 

were incomplete. 

2.2 CHANGES INCORPORATED IN REVISION 02 OF ORAUT-TKBS-0055 

On January 14, 2011, Revision 02 of the Ames TBD (ORAUT 2011a) was issued, which 

contained the following changes salient to dose reconstruction: 
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 Revision 02 included SEC-00075. This SEC class includes sheet metal workers, plant 

maintenance and associated support staff, and supervisory staff who worked at least 

250 days from January 1, 1955, through December 31, 1970. 

 Revision 02 initiated the inclusion of SEC-00166. This class includes all employees and 

contractors with at least 250 days employment between January 1, 1955, and December 

31, 1960. 

 Section 5.1.1.3 (Resuspension During Periods with No Uranium Operations) was updated 

with internal intake data from SEC-00166. Changes involved daily inhalation and 

ingestion values in the Chemistry Building, which increased from 1.8 and 0.16 pCi/d to 

4.1 and 0.68 pCi/d as given in Table 5-4. 

 In 1951, a hot laboratory that had operated in the Chemistry Building since 1943 was 

replaced by a hot cell. Revision 01 had stated that “... Intakes from the hot cell would 

have been negligible.” This statement was deleted in Revision 02 with the acceptance of 

SEC-00166, which stated that “... intakes from the hot cell cannot be determined for 

radionuclides other than uranium. 

 Occupational Medical Exposure. In Revision 00 of the Ames TBD, Occupational 

Medical Exposure was defined for the PA exposures geometry of chest x-rays as a 

requirement for employment. 

In Revision 01, occupational medical exposures were amended to include the LAT 

exposure geometry for chest x-rays. 

In Revision 02, medical occupational exposures were no longer included, based on the 

following explanation: 

Occupational medical exposures are only included for medical 

examinations obtained at the Ames Laboratory facility (ORAUT 2011[c]). 

There were no X-ray examinations performed onsite, therefore no

occupational medical exposures were incurred. [Emphasis added.] 

2.3 CHANGES INCORPORATED IN REVISION 03 OF THE ORAUT-TKBS-0055 

On January 3, 2012, Revision 03 of the Ames TBD was issued, which incorporated the following 

changes salient to dose reconstruction: 

 Expanded the three previous SEC classes by defining a fourth; SEC-00185 class. SEC00185 encompasses all previous Ames SEC periods and includes all Ames employees 

and contractors with 250 or more workdays for the period August 13, 1942 (the official 

start of the Manhattan Project), through December 31, 1970. 
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NOTICE:

 Section 5.4.1 was amended for those Research Building workers who after 1951 did not

work with the hot cell or associated laboratories. Exposures for these workers are to be 

limited to environmental internal and external doses. 

 Changes to unmonitored external doses were made due to the fact that Battelle 2006a was 

updated to Battelle 2011, and Battelle 2006b was cancelled and replaced with other 

references. Changes in surrogate dose models altered select internal exposure estimates 

cited in Section 5.1, as well as external dose estimates, as given in Tables 6-4, 6-5, and 

6-6. 

Summary of Revisions and Their Impacts

While some of the aforementioned revisions resulted in an increase in assigned dose, others 

decreased the dose, and still others decreased in an earlier revision and increased in a subsequent 

revision, as summarized below: 

 Revision 01 increased uranium intakes for researchers in the Ames Chemistry Building 

from August 1942 through December 1953. This change remained unchanged in 

Revisions 02 and 03. Revision 01 also added LAT exposure dose estimates to 

occupational medical exposure. 

 External dose for unmonitored workers for some job categories before 1946 increased in 

Revision 01, remained the same in Revision 02, but increased again in Revision 03. 

 External dose for unmonitored workers between 1946 and 1953 decreased for all job 

categories and locations in Revision 01, remained the same in Revision 02, but increased 

in Revision 03. 

 Revision 02 increased uranium intakes for all employees in the Chemistry Building for 

the period January 1954 through May 1976. These higher intakes remained unchanged in 

Revision 03. All occupational medical exposures were eliminated in Revision 02 and 

Revision 03. 

2.4 SEC CLASSES ADDED 

NIOSH added classes to the SEC in 2006 and 2007 to include worker groups based on work 

locations and job descriptions. On November 5, 2010, the final SEC class was added. 

The 2010 class determined that the information available about worker job descriptions, work 

locations, and/or movement about the site was insufficient to determine if an employee worked 

in any of the affected areas identified in prior SEC classes. Thus, in 2011, NIOSH designated a 

fourth class (SEC-00185) that included all Ames employees/contractors for all previous Ames 

SEC periods with one exception: the covered period’s start date was switched from January 1, 

1942, to August 13, 1942, to coincide with the start of the Manhattan Project. Thus, the covered 

period for SEC-00185 extended from August 13, 1942, through December 31, 1970. 
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3.0 SUBTASK 2: ASSESS NIOSH’S SPECIFIC METHODS FOR 

CORRECTIVE ACTION 

As previously stated in Section 1.0 above: 

. . . In instances where the PER involves a technical issue that is supported by 

document(s) (e.g., white papers, technical information bulletins, procedures) 

that have not yet been subjected to a formal SC&A review, Subtask 2 will 

include a review of the scientific basis and/or sources of information to ensure 

the credibility of the corrective action and its consistency with 

current/consensus science. Conversely, if such technical documentation has 

been formalized and previously subjected to a review by SC&A, Subtask 2 will 

simply provide a brief summary/conclusion of this review process. [Emphasis 

added.] 

It must be noted that there have been several instances among completed reviews of PERs by 

SC&A in which technical issues were supported by documents that had not been previously 

evaluated by SC&A. Their inclusion in the PER review, however, was considered manageable 

and appropriate. For example, in behalf of OCAS-PER-014, Construction Trades Workers

(OCAS 2007b), SC&A critically evaluated the technical support provided by Technical 

Information Bulletin (TIB) ORAUT-OTIB-0052, Parameters to Consider When Processing 

Claims for Construction Trade Workers (ORAUT 2011b). However, as discussed below, the 

magnitude of the changes to the Ames site profile encompassed by this PER far exceed those that 

we have experienced in the past, and the scope of work required to evaluate these revisions is 

more akin to site profile as opposed to PER reviews. This issue is discussed in greater detail 

below, along with SC&A’s suggestions on how the Board might best deal with this unique 

circumstance. 

3.1 DOCUMENTS SALIENT TO DCAS-PER-037 THAT HAVE NOT BEEN 

EVALUATED 

Our evaluation of DCAS-PER-037 with regard to documents considered relevant to this review 

has identified the following documents, none of which SC&A has been requested to evaluate: 

 Site Profiles

 ORAUT-TKBS-0055, Rev. 00, (06/22/2007) Site Profile for Ames Laboratory 

(ORAUT 2007c) 

 ORAUT-TKBS-0055, Rev. 00 PC-1, (08/20/2008) Site Profile for Ames Laboratory 

(ORAUT 2008) 

 ORAUT-TKBS-0055, Rev. 01, (12/18/2009) Site Profile for Ames Laboratory 

(ORAUT 2009) 

 ORAUT-TKBS-0055, Rev. 02, (01/04/2011) Site Profile for Ames Laboratory 

(ORAUT 2011a) 
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 ORAUT-TKBS-0055, Rev. 03, (01/03/2012) Site Profile for Ames Laboratory 

(ORAUT 2012) 

 SEC Petitions

 Petition SEC-00075: January 1, 1955 through December 31, 1970 

 Petition SEC-00166: January 1, 1955 through December 31, 1960 

 Petition SEC-00185: August 13, 1942 through December 31, 1970 

SEC Petition Evaluation Reports

 SEC Petition Evaluation Report: Petition SEC-00075 (January 1, 1955, through 

December 31, 1970), Approved May 14, 2007 (OCAS 2007a). 

 SEC Petition Evaluation Report: Petition SEC-00166 (January 1, 1955, through 

December 31, 1960), Approved July 30, 2010 (DCAS 2010b). 

 SEC Petition Evaluation Report: Petition SEC-00185 (August 13, 1942, through 

December 31, 1970)—REVISED, Revised July 14, 2011; corrects the start date to match 

the Manhattan Engineering District start date (DCAS 2011). 

 Technical Guidance Documents

 ORAUT-OTIB-0079, 2011, Guidance on Assigning Occupational X-Ray Dose under 

EEOICPA for X-Rays Administered Offsite, Rev. 00 (ORAUT 2011c) 

 DCAS-IG-003, 2010, Radiation Exposures Covered for Dose Reconstructions Under 

Part B of the Energy Employee Occupational Illness Compensation Program Act, Rev. 01

(DCAS 2010a) 

3.2 PRELIMINARY FINDINGS AND THE NEED FOR A FORMAL REVIEW OF 

SALIENT DOCUMENTS 

The need to thoroughly evaluate the above-cited documents prior to our review of DCAS-PER037 is supported by SC&A’s very preliminary review of the Ames Laboratory’s TBDs 

(ORAUT-TKBS-0055, Rev. 00 through Rev. 03). Presented below is but a sample of potential 

issues that the Subcommittee on Procedures Review/Board may have to address. 

3.2.1 Use of Potentially Inappropriate Dose Models/Surrogate Data 

Uranium Inhalation. From the very beginning of the Manhattan Project in 1942 through 1953, 

monitoring of worker exposures to uranium at Ames Laboratory was either absent or insufficient 

for DR. Surrogate data in Revision 00 of ORAUT-TKBS-0055 (ORAUT 2007) was based on 

ORAUT-OTIB-0004 (ORAUT 2005), which was replaced by Battelle-TBD-6000, Revision F0 

(Battelle 2006a), and Battelle-TBD-6001, Revision F0 (Battelle 2006b), in Revision 01 (ORAUT 

2009) and Revision 02 (ORAUT 2011a) of the Ames TBD. 
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In Revision 03 (ORAUT 2012), internal doses from uranium metal were based on Battelle-TBD6000, Revision 01 (Battelle 2011) and Christofano and Harris 1960. The questionable use of 

these data/dose models is largely based on unsupported assumptions, as discussed in Section 

3.2.4 below. 

Exposure to Thorium Contamination after 1954. Air concentrations and daily intakes as given in 

Table 5-5 of the Ames TBD were derived by extrapolation from (1) the 1995 wipe survey data 

of the East Pipe Tunnel located in the sub-basement of Wilhelm Hall, and (2) the 95th percentile 

air concentration for “General Air Samples” as reported in Table III by Paul B. Klevin in a 1952 

survey (Klevin 1952). 

SC&A has reviewed these sources and questions their applicability for use in DR. 

3.2.2 Use of NUREG-1400 for Modeling Intakes of Fission Products 

Between 1943 and 1951, workers at the Ames hot laboratory separated plutonium from 

uranium and their associated fission products. In the absence of empirical survey/bioassay data, 

Table 5-7 of the Ames TBD provides modeled estimates based on a generic formula defined in 

NUREG-1400: Air Sampling in the Workplace (Hickey et al. 1993): 

 Ip = Q × 10-6 × R × C × D (Eq. 1) 

 where, 

 Q = total quantity of unencapsulated material 

 R = release fraction 

 C = confinement factor 

 D = dispersibility 

The intent of NUREG-1400 is to assist licensees in establishing air sampling programs that 

conform with recommendations in the 1992 Regulatory Guide 8.25, Revision 1, Air Sampling in 

the Workplace (NRC 1992), and the regulatory requirements stated in 10 CFR Part 20 (NRC 

1991). Thus, modifying factors for the intake Ip are based on licensed facilities that reflect 

current-day timeframes of operation. For example, the 10-6 factor cited in Equation 1 represents 

a rule of thumb that applies “. . . when normal precautions are taken [and] a worker is not likely 

to have an intake Ip exceeding 10-6 of the material being handled . . .” [Emphasis added.] 

In brief, very little is known about the operation of the Ames hot laboratory that operated 

between 1943 and 1951, and generic values and guidance provided in Section 1.2 of NUREG1400 focused on air sampling needs and was never intended for use in DR. 

3.2.3 Unsupported “Attributions and Annotations” 

Revision 01 of ORAUT-TBKS-0055 (ORAUT 2009) contains a total of 44 Attributions and 

Annotations (A&As), many of which are based on little or no recorded information or records. 

For example, the above-cited concerns regarding the “hot laboratory’s environmental releases as 
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well as worker intake estimates of fission products” must be viewed in context with A&As, 

which state: 

 A&A #10

 . . . The exact nature of the hot laboratory used in the 1940s was not discovered 

in the records. Presumably, it would have involved some methods for recognizing 

and controlling the spread of contamination with some filtration on the exhausts, 

but it was unlikely that the controls of the hot laboratory were as good as those 

for the hot cell. [Emphasis added.] 

 A&A #26

Strontium is type F with the exception of the titanate form, which is rare. There is 

no reason to suspect strontium titanate was in use at Ames Laboratory. 

[Emphasis added.] 

A word search for the words assume, assumed, assumption, and presume in Revision 3 of 

ORAUT-TKBS-0055 (ORAUT 2012) identified a total of 114 instances (85 in the text of TBD 

and 29 in A&As). In most instances, these words were prefaced with “. . . because no 

information/ . . . no data/ . . . no records were found an assumption was made . . .” For 

illustration, Section 5.1.1.1 of ORAUT-TKBS-0055 is reproduced here as Exhibit 1 with key 

words/phrases highlighted and underlined. 
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EXHIBIT 1: Section 5.1.1.1 of ORAUT-TKBS-0055 

5.1.1.1 Uranium Inhalation 

From 1942 through August 1945, individuals working in Physical Chemistry Annex 1 (also 

known as Little Ankeny) can be assigned doses from inhalation of uranium [12]. Similarly, 

individuals who worked in the Chemistry Building during this period or in Physical Chemistry 

Annex 2 from 1944 through December 1945 should be assigned doses from inhalation of 

uranium [13]. Job titles of researchers acknowledged for their work in uranium production 

(Fulmer 1947) include (1) chemist, (2) associate chemist, (3) junior chemist, (4) research 

assistant, (5) junior research assistant, (6) physicist, (7) analyst, (8) assistant physicist, (9) 

associate director, and (10) director. However, it is not entirely clear how much time these 

researchers spent in the area where production was performed. 

Because it is not clear if there were clerical, janitorial, or nontechnical personnel and other types 

of researchers working in these buildings, and it is not known what precautions might have been 

taken for contamination control, it can be assumed that all individuals who worked in the 

buildings had some potential for exposure to uranium. 

The data in Tables 5-1 and 5-2 were derived from data in Christofano and Harris (1960). In 

Christofano and Harris (1960), there is a description of the process for metal reduction that is 

similar to the process used at Ames Laboratory for production of uranium metal (Fulmer 1947). 

The primary difference appears to be that at Ames Laboratory the process used granulated 

calcium metal and at AWE sites the process used magnesium. Fulmer (1947) describes the 

process using magnesium, and it appears to be similar enough to be representative of the intakes 

at Ames Laboratory. 

Table 5-1. Chemistry Building uranium intakes (pCi/d) 

Period Inhalation Ingestion

Aug 1942–December 1953 8.5a,b 0.09b

 a. No data were available for determination of intakes in the Chemistry Building; therefore, it was assumed that 

research activities would have one-hundredth the intake of production activities since uranium metal 

production was moved to the Physical Chemistry Annex 1. 

 b. Values are for workers assumed to work in research or production full time. For supervisors, assume onequarter of the intake; for all other employees (clerical, janitorial, security, etc), assume one-tenth of the 

supervisor’s intake. 

Table 5-2. Physical Chemistry Annex 1 uranium intakes (pCi/d) 

Period Inhalation Ingestion

Aug 1942–December 1945 853a 8.7a

a. Values are for workers assumed to work in research or production full time. For supervisors, assume onequarter of the intake; for all other employees (clerical, janitorial, security, etc), assume one-tenth of the 

supervisor’s intake. 
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Exhibit 1 (Continued) 

Table 5-2. Physical Chemistry Annex 1 uranium intakes (pCi/d) 

Period Inhalation Ingestion

January 1942–December 1950 6,061a 124a

January 1951–December 1953 5,556a 114a

a. Values are for workers assumed to work in research or production full time. For supervisors, assume onequarter of the intake; for all other employees (clerical, janitorial, security, etc), assume one-tenth of the 

supervisor’s intake. 

Christofano and Harris (1960) provide data for multiple stages of the production operation for 

operators. Using the techniques outlined in Default Assumptions and Methods for Atomic 

Weapons Employer Dose Reconstructions (Battelle 2007), the values in the above tables were 

calculated from Table 8 of Christofano and Harris (1960). However, review of Ames Laboratory 

documentation did not reveal any information specific enough for determination of who would 

be responsible for what aspects of the process and for how long. Therefore, the value used for 

determining inhalation intakes, which was from Christofano and Harris (1960, Table 8), is for 

the Bomb Preparation operator, who is assumed to work a 2400-hour year. This value was the 

highest intake rate for the metal reduction process. This number is then scaled for the potential 

for intake (see Tables 5-1 and 5-2). 

Battelle (2011) provides data for a process of scrap recovery that is similar to the scrap recovery 

process described in Fulmer (1947). Data from Battelle (2011, Table 7.8) are used in Table 5-3 

for Ames Laboratory workers who worked in the Physical Chemistry Annex 2 building. The 

value used in Battelle (2011, Table 7.8) represents the most conservative intake for the scrap 

recovery operations, similar to those performed in Physical Chemistry Annex 2. 

Research in the Chemistry Building began in January 1942. For workers involved only in 

research from January through July 1942 in the Chemistry Building, an exposure of one-tenth of 

that of the workers involved in the production operations is assumed, which corresponds to 

smaller quantities of uranium [14]. This period is prior to the beginning of the covered period 

for the EEOICPA statute, which is August 1942, the start of the Manhattan Engineer District, 

known later as the Manhattan Project. The process developed by this research was moved to the 

Physical Chemistry 1 building in July/August of 1942. There are very few details on the 

research activities in the Chemistry Building after July 1942; therefore, it was assumed that 

another one-tenth fraction should be applied (for a 1/100 reduction overall from operations). 

These intakes should be applied to researchers in the Chemistry Building through 1953, when 

production ended. 

Individuals supervising the production processes were assumed to be exposed for one-fourth of 

the time of the production staff [15]. 

For workers not directly associated with uranium metal research or production, an exposure of 

one-tenth of that of the supervisors was assumed (see Tables 5-1, 5-2, and 5-3) [16]. 
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Exhibit 1 (Continued) 

The intakes in Tables 5-1, 5-2, and 5-3 were compared to the few actual bioassay results found 

for workers in approximately the same period. Chapter 7 in Stone (1951), “Uranium Excretion 

Studies,” provided data from a series of uranium bioassays obtained from Ames Laboratory 

workers in 1944 and 1945. Of special interest was a series of samples from the supposedly 

highest exposed worker at Ames Laboratory and samples from the most highly exposed group of 

workers at the Laboratory (21 samples from 11 workers). An intake evaluation was performed 

on the results for the highest exposed worker assuming chronic intake from the start of that 

person’s employment and absorption type M uranium (the document indicated the person was 

exposed to UF4). The estimated intake was 1,200 μg/d or 820 pCi/d assuming natural uranium. 

This is consistent with the intake estimate in Table 5-2 for Physical Chemistry Annex 1 and quite 

a bit lower than that in Table 5-3 for Annex 2. The average bioassay result for the group of 

highest exposed workers was 75 μg/L. Assuming chronic intake for 1 year before the bioassay, 

the estimated intakes were: 

 Absorption type F: 390 μg/d, 260 pCi/d 

 Absorption type M: 1,670 μg/d, 1,100 pCi/d 

 Absorption type S: 45,400 μg/d, 31,000 pCi/d. 

If the geometric mean of the data is used, the estimated intakes are smaller; if the highest 

bioassay result of the set is used, the estimated intakes are 2.7 times greater. For type M, this 

range is still consistent with the intakes in Tables 5-1, 5-2, and 5-3. . . . 
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3.2.4 Failure to Address U and Th Blowouts as Significant Environmental Events 

ORAUT-TKBS-0055, Revision 3 (ORAUT 2012), Section 4.5, Significant Environmental Event, 

states the following: 

The only significant environmental event in the history of the Ames Laboratory 

was the release to the environment from operations that occurred from July 1951 

through August 1952. Metallic thorium was being produced from thorium nitrate 

tetrahydrate. During an early stage of the process, a filtrate with traces of 

thorium in the form of thorium nitrate and oxalate was released to the sewer that 

connected to the City of Ames sewer system. [Emphasis added.] 

These statements are in conflict with earlier statements contained in Section 2.3 of the TBD that 

include the following: 

There were frequent small explosions and fires associated with the uranium and 

thorium production operations (Payne 1992). Payne (1992) cited as many as six 

small fires in a single day; these fires contributed to work-area contamination 

and potential airborne radioactive material exposures. No records were found to 

indicate that air sampling or contamination control was associated with these 

fires. [Emphasis added.] 

Moreover, these statements not only understate the magnitude of these events, but totally ignore 

environmental releases, as well as potentially high internal doses to workers, as reported by 

SC&A in three previous draft reports. 

In the first and second draft reports [Review of the Ames Laboratory Special Exposure Cohort 

(SEC) Petition SEC-00038 (SC&A 2006) and An Assessment of Worker Eligibility Criteria

(SC&A 2007b)], SC&A identified to the Advisory Board the relatively common radiological 

incidents of chemical explosions or “blowouts” at the Ames facility in context with the 

250-workday requirement. In response to SC&A’s concern, the Advisory Board appointed an ad 

hoc working group chaired by Dr. James Melius to further evaluate this issue. The work group 

requested SC&A to (1) review all available records/sources that would establish the frequency 

of such events, and (2) provide scoping calculations that would assess reasonable estimates 

of potential internal exposures associated with a single event. 

This request was fulfilled in a third SC&A draft report, The Relevance of the 250-Workday 

Requirement to Potential Exposures Associated with a Single Blowout (SC&A 2007a), which 

was submitted on March 22, 2007. Included in the report were several personal recollections of 

blowouts by Dr. Frank H. Spedding, Director of the Ames Laboratory, who provided the 

following accounts: 

. . . Although I remember one night we had an explosion that blew the whole 

south end of the building out and being an old wooden building, when things 

quieted down we all went outside and shoved the wall back in again and went to 

work. 
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NOTICE:

 . . . Mr. [name deleted] was adding a booster to the reactor in a room a few doors 

down the hall from my office. Suddenly there was a terrific explosion which blew 

out several of the windows in the front of the Chemistry Building. When I came 

out of my office to see what happened, the corridor was filled with dust about six 

feet above the floor to the ceiling . . . [Emphasis added.] 

The third SC&A report (2007a) was the central topic of discussion for the Work Group Meeting 

of the Advisory Board on November 29, 2007. Much of the discussion focused on the feasibility 

of bounding doses associated with blowouts, identifying those individuals (with less than 

250 workdays and/or a cancer not included under SEC rules) who may have been exposed to one 

or more blowouts, and the promise by NIOSH to reconsider the inclusion of blowouts in dose 

reconstruction [see pp. 133 through 158 of the November 29, 2007, meeting transcript 

(ABRWH 2007)].
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4.0 SUBTASK 3: EVALUATE THE PER’S STATED APPROACH FOR 

IDENTIFYING THE NUMBER OF DRS REQUIRING 

RE-EVALUATION OF DOSE 

Based on time periods of facility operations at the Ames Laboratory and changes introduced in 

Revisions 01, 02, and 03 to the Ames Laboratory TBD (ORAUT-TKBS-0055), NIOSH 

identified two discrete groups of claimants in DCAS-PER-037 whose previous dose 

reconstruction may have been affected by changes in the final revision of (i.e., Rev. 03) of 

ORAUT-TKBS-0055. 

4.1 IDENTIFICATION OF TWO EMPLOYMENT PERIODS 

The first group of potentially affected claimants involves workers with employment before 1954 

and whose DRs were processed before January 3, 2012, with POC values of less than 50%. 

NIOSH identified 19 claims with the following breakdown: 

 Two claims met the criteria for inclusion in the SEC-00185 class 

 Seven claims had previously assigned organ doses that were ≥ what would currently be 

assigned under Revision 03 of ORAUT-TKBS-0055 

 The remaining 10 claims were subject to a new DR using the criteria defined in 

Revision 03 of ORAUT-TKBS-0055 

The second group of claims was based on the same criteria as the first group, except the 

required employment changed to January 1954 through June 1976. NIOSH identified a total of 

61 claims that met these criteria with the following results: 

 Sixteen claims qualified for the inclusion in the SEC-00185 class. 

 The remaining 45 claims were reviewed to determine whether Chemistry Building 

intakes had been assigned using a previous revision of the ORAUT-TKBS-0055. The 

review identified that six claims had been assigned Chemistry Building intakes based on 

previous version of the TBD. 

 These 6 claims (along with the 10 claims from the first group) were subject to a DR 

under the criteria defined in Revision 03 of ORAUT-TKBS-0055. 

Of the total 16 claims (10 from the first group and 6 from the second group) that were reevaluated using Revision 03 of the Ames TBD, 13 claims yielded POC values below 45%. The 

remaining three claims with POCs >45% were evaluated by expanded IREP iterations. This 

yielded only one claim with a POC that exceeded 50%. 
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NOTICE:

4.2 SC&A’s COMMENTS REGARDING CORRECTIVE ACTIONS TAKEN BY

NIOSH FOR IDENTIFYING CLAIMS/DRs THAT MAY REQUIRE FURTHER 

EVALUATION 

NIOSH’s criteria for the selection of claims potentially affected by DCAS-PER-037, as well as 

the protocol for their new DR, are based on several revisions to the Ames TBD, several additions 

to the SEC class, and recently issued guidance documents that impact DR. 

Due to the fact that SC&A has not been requested to review these documents, our comments 

pertaining to corrective actions [that include the selection of affected claims and revised 

method(s) for dose reconstruction] must be viewed as premature and of limited value. 

SC&A concludes that a credible evaluation of DCAS-PER-037 will have to await a decision by 

the Subcommittee on Procedures Review on the need to include a full review of all documents 

relevant to the genesis of PER-037. 
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5.0 REFERENCES 

42 CFR 82, 2002. Methods for Radiation Dose Reconstruction under the Energy Employees 

Occupational Illness Compensation Program Act of 2000; Final Rule, Federal 

Register/Vol.67, No. 85/Thursday, May 2, 2002, p. 22314. 

ABRWH 2007. Transcript of the meeting of the Advisory Board on Radiation and Worker 

Health, Special Exposure Cohort (SEC) Issues (including the 250 day issue) Work Group, held 

on November 29, 2007. 

Battelle 2006a. Site Profiles for Atomic Weapons Employers that Worked Uranium and Thorium 

Metals, Battelle-TBD-6000, Revision F0, Battelle, Pacific Northwest Division, Richland, 

Washington, December 2006. 

Battelle 2006b. Site Profiles for Atomic Weapons Employers that Refined Uranium and 

Thorium, Battelle-TBD-6001, Revision F0, Battelle, Pacific Northwest Division, Richland, 

Washington, December 2006. 

Battelle 2007. Default Assumptions and Methods for Atomic Weapons Employer Dose 

Reconstructions, Battelle-TIB-5000, Rev. 00, Battelle, Pacific Northwest Division, Richland, 

Washington. April 2, 2007. 

Battelle 2011. Site Profiles for Atomic Weapons Employers that Worked Uranium Metals, 

Battelle-TBD-6000, Rev. 1, Battelle, Pacific Northwest Division, Richland, Washington. June 

17, 2011. 

Christofano, E., and W.B. Harris, 1960. “The Industrial Hygiene of Uranium Refining,” 

Archives of Environmental Health, volume 1, pp. 438–460 (reprinted). 

DCAS 2010a. Radiation Exposures Covered for Dose Reconstructions Under Part B of the 

Energy Employees Occupational Illness Compensation Program Act, DCAS-IG-003, Rev. 1, 

Division of Compensation Analysis and Support, Cincinnati, Ohio, October 5, 2010. 

DCAS 2010b. SEC Petition Evaluation Report, Petition SEC-00166, Rev. 0, Division of 

Compensation Analysis and Support, Cincinnati, Ohio, July 30, 2010. 

DCAS 2011. SEC Petition Evaluation Report, Petition SEC-00185, Rev. 0, Division of 

Compensation Analysis and Support, Cincinnati, Ohio, July 14, 2011. 

DCAS 2012. Ames Laboratory TBD Revision, Rev. 0, DCAS-PER-037, NIOSH’s Division of 

Compensation Analysis and Support, Cincinnati, Ohio. July 17, 2012. 

Fulmer, E.I., 1947. History of the Ames Project Under the Manhattan District to December 31, 

1946, ISC-10, Iowa State College, Ames, Iowa. 
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However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82.

Hickey, E.E., G.A. Stoetzel, D.J Strom. G.R. Cicotte, C.M. Wiblin, and S.A. McGuire, 1993. 

Air Sampling in the Workplace, NUREG-1400, U.S. Nuclear Regulatory Commission, Office of 

Nuclear Regulatory Research, Washington, DC. September 1993. 

Klevin, P.B., 1952. Ames Research Laboratory Occupational Exposure to Thorium and 

Beryllium, Ames-1, U.S. Atomic Energy Commission, New York Operations Office, New York, 

New York, July 14, 1952. 

NRC 1991. Standards for Protection Against Radiation, 10 CFR Part 20, U.S. Nuclear 

Regulatory Commission, Washington, DC. 

NRC 1992. Air-Sampling in the Workplace, Regulatory Guide 8.25, Rev. 1, U.S. Nuclear 

Regulatory Commission, Washington, DC. 

OCAS 2006. Preparation of Program Evaluation Reports and Program Evaluation Plans, 

OCAS-PR-008, Rev. 2, NIOSH’s Office of Compensation Analysis and Support, Cincinnati, 

Ohio. December 6, 2006 

OCAS 2007a. SEC Petition Evaluation Report, Petition SEC-00075, Rev. 0, NIOSH, Office of 

Compensation Analysis and Support, Cincinnati, Ohio, May 14, 2007. 

OCAS 2007b. Program Evaluation Report, Construction Trade Workers, Rev. 00, Oak Ridge 

Associated Universities, Cincinnati, Ohio, November 27, 2007. 

ORAUT 2005. Estimating the Maximum Plausible Dose to Workers at Atomic Weapons 

Employer Facilities, ORAUT-OTIB-0004, Rev. 03, PC-01, Oak Ridge Associated Universities, 

Cincinnati, Ohio. November 18, 2005. 

ORAUT 2007. Site Profile for Ames Laboratory, ORAUT-TKBS-0055, Rev. 00, Oak Ridge 

Associated Universities, Cincinnati, Ohio, June 22, 2007. 

ORAUT 2008. Site Profile for Ames Laboratory, ORAUT-TKBS-0055, Rev. 00 PC-1, Oak 

Ridge Associated Universities, Cincinnati, Ohio, August 20, 2008. 

ORAUT 2009. Site Profile for Ames Laboratory, ORAUT-TKBS-0055, Rev. 01, Oak Ridge 

Associated Universities, Cincinnati, Ohio, January 18, 2009. 

ORAUT 2011a. Site Profile for Ames Laboratory, ORAUT-TKBS-0055, Rev. 02, Oak Ridge 

Associated Universities, Cincinnati, Ohio, January 14, 2011. 

ORAUT 2011b. Parameters to Consider When Processing Claims for Construction Trade 

Workers, ORAUT-OTIB-0052, Rev. 01, Oak Ridge Associated Universities, Cincinnati, Ohio, 

February 17, 2011. 

ORAUT 2011c. Guidance on Assigning Occupational X-Ray Dose Under EEOICPA for X-Rays 

Administered Off Site, ORAUT-OTIB-0079, Rev. 00, Oak Ridge Associated Universities, 

Cincinnati, Ohio, January 3, 2011. 
Effective Date: 

January 2, 2013

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However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82.

NOTICE:

ORAUT 2012. Site Profile for Ames Laboratory, ORAUT-TKBS-0055, Rev. 03, Oak Ridge 

Associated Universities, Cincinnati, Ohio, January 3, 2012. 

Payne, C.S., 1992. The Ames Project: Administering Classified Research as a Part of the 

Manhattan Project at Iowa State College, 1942-45, PhD dissertation, Iowa State University, 

Ames, Iowa. [SRDB Ref ID: 18851] 

SC&A 2006. Review of the Ames Laboratory Special Exposure Cohort (SEC) Petition, 

SEC-00038. SCA-SEC-TASK5-0031, SC&A, Inc., Vienna, Virginia. June 5, 2006. 

SC&A 2007a. The Relevance of the 250-Workday Requirement to Potential Exposures 

Associated with A Single Blowout, (Draft White Paper), SC&A, Inc., Vienna, Virginia. March 

22, 2007. 

SC&A 2007b. An Assessment of Worker Eligibility Criteria For Less Than 250-Days 

Employment: Ames Case Study, (Draft White Paper), SC&A, Inc., Vienna, Virginia. January 11, 

2007. 

Stone, R. S. (editor), 1951. Industrial Medicine on the Plutonium Project, National Nuclear 

Energy Series, Manhattan Project Technical Section, Division IV, Plutonium Project Record, 

Vol. 20.