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SEC Petition Evaluation Report

Petition SEC-00164 

Report Rev #: 0 Report Submittal Date: July 19, 2010

Subject Expert(s): Edward D. Scalsky, Eugene W. Potter, Ray Clark

Site Expert(s): N/A

Petition Administrative Summary

Petition Under Evaluation 

Petition # Petition 

Type

Petition

Receipt Date

Qualification Date DOE/AWE Facility Name

SEC-00164 83.13 January 26, 2010 March 18, 2010 Revere Copper and Brass 

Petitioner Class Definition 

Extruders and Shapes Specialists who worked in the Rod and Shape Mill at Revere Copper and Brass, Detroit, 

Michigan from 1943 through 1984. 

Class Evaluated by NIOSH 

All workers who worked at Revere Copper and Brass, Detroit, Michigan from July 24, 1943 through December 

31, 1954 and for the residual period from January 1, 1955 through December 31, 1984. 

NIOSH-Proposed Class(es) to be Added to the SEC

All Atomic Weapons Employer employees who worked at Revere Copper and Brass, Detroit, Michigan, from 

July 24, 1943 through December 31, 1954, for a number of work days aggregating at least 250 work days, 

occurring either solely under this employment or in combination with work days within the parameters 

established for one or more other classes of employees included in the Special Exposure Cohort. 

Related Petition Summary Information 

SEC Petition Tracking #(s) Petition Type DOE/AWE Facility Name Petition Status

None 

Related Evaluation Report Information 

Report Title DOE/AWE Facility 

Name

None 

ORAU Lead Technical Evaluator: Edward D. Scalsky ORAU Peer Review Completed By: Daniel Stempfley

Peer Review Completed By: [Signature on file] 7/19/10 LaVon Rutherford for Frank C. Crawford Date

[Signature on file] 7/19/10 SEC Petition Evaluation Reviewed By: 

J. W. Neton Date

[Signature on file] 7/20/10 SEC Evaluation Approved By:

Stuart L. Hinnefeld Date
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Evaluation Report Summary: SEC-00164, Revere Copper and Brass

This evaluation report by the National Institute for Occupational Safety and Health (NIOSH)

addresses a class of employees proposed for addition to the Special Exposure Cohort (SEC) per the 

Energy Employees Occupational Illness Compensation Program Act of 2000, as amended, 42 U.S.C. 

§ 7384 et seq. (EEOICPA) and 42 C.F.R. pt. 83, Procedures for Designating Classes of Employees as 

Members of the Special Exposure Cohort under the Energy Employees Occupational Illness 

Compensation Program Act of 2000. 

Petitioner-Requested Class Definition

Petition SEC-00164 was received on January 26, 2010 and qualified on March 18, 2010. The 

petitioner requested that NIOSH consider the following class: Extruders and Shape Specialists who 

worked in the Rod and Shape Mill at Revere Copper and Brass, Detroit, Michigan from 1943 through 

1984. 

Class Evaluated by NIOSH

Based on its preliminary research, NIOSH divided the petitioner-requested class. NIOSH evaluated 

the following class: All workers who worked at Revere Copper and Brass, Detroit, Michigan from 

July 24, 1943 through December 31, 1954 and the residual period from January 1, 1955 through 

December 31, 1984. These operational dates represent the beginning of the first extrusions performed 

for the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC) through the 

end of the last year that extrusions took place. January 1, 1955 represents the beginning of the 

residual period, which continued through the end of 1984, the year the facility was demolished. 

NIOSH-Proposed Class(es) to be Added to the SEC

Based on its full research of the class under evaluation, NIOSH has defined a single class of 

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSHproposed class includes all Atomic Weapons Employer employees who worked at Revere Copper and 

Brass, Detroit, Michigan, from July 24, 1943 through December 31, 1954, for a number of work days 

aggregating at least 250 work days, occurring either solely under this employment or in combination 

with work days within the parameters established for one or more other classes of employees included 

in the Special Exposure Cohort. The class under evaluation was divided (see Section 3.0 below) 

because although NIOSH has not obtained sufficient internal or external monitoring data for bounding 

doses during the operational period, NIOSH has a methodology for bounding doses for the residual 

period. 

Feasibility of Dose Reconstruction

NIOSH finds it is not feasible to estimate internal and external exposures with sufficient accuracy for 

all workers at the site from July 24, 1943 through December 31, 1954. NIOSH determined there was 

no monitoring program at Revere and insufficient data are available to determine the external and 

internal doses received by workers during the period under evaluation. With the exception of this 

class, per EEOICPA and 42 C.F.R. § 83.13(c)(1), NIOSH has established that it has access to 
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sufficient information to: (1) estimate the maximum radiation dose, for every type of cancer for which 

radiation doses are reconstructed, that could have been incurred in plausible circumstances; or (2) 

estimate radiation doses more precisely than an estimate of maximum dose. Available information 

and resources are sufficient to document or estimate the maximum internal and external potential 

exposure to members of the proposed class under plausible circumstances during the specified period 

January 1, 1955 through December 31, 1984. 

The NIOSH dose reconstruction feasibility findings are based on the following: 

• NIOSH finds that it is likely feasible to reconstruct occupational medical dose for Revere workers 

with sufficient accuracy.

• Principal sources of internal radiation for members of the proposed class included exposures to 

natural uranium and thorium metals existing either separately or as alloys. The modes of exposure 

were inhalation and ingestion during the processing of these metals.

• Based on lack of sufficient data for Revere workers or operations, internal dose reconstruction for 

the Revere operational period is not feasible; however, NIOSH has identified sufficient 

information and data to support bounding internal dose for the residual period using available 

methodologies. 

• Principal sources of external radiation for members of the proposed class included exposures to 

gamma and beta radiation associated with handling and working in proximity to natural uranium 

and thorium metals existing either separately or as alloys. The modes of exposure were direct 

radiation, submersion in potentially-contaminated air, and exposure to contaminated surfaces. 

• Except for medical X-ray dose, NIOSH has determined that reconstruction of external doses for 

Revere workers is not feasible for the operational period from July 1, 1943 through December 31, 

1954. NIOSH has determined that reconstruction of external doses is feasible for the residual 

period (January 1, 1955 through December 31, 1984) using the assumptions and approaches 

presented in Battelle-TBD-6000. 

• Pursuant to 42 C.F.R. § 83.13(c)(1), NIOSH determined that there is insufficient information to 

either: (1) estimate the maximum radiation dose, for every type of cancer for which radiation 

doses are reconstructed, that could have been incurred under plausible circumstances by any 

member of the class; or (2) estimate the radiation doses of members of the class more precisely 

than a maximum dose estimate.

• Although NIOSH found that it is not possible to completely reconstruct radiation doses for the 

proposed class, NIOSH intends to use any internal and external monitoring data that may become 

available for an individual claim or any area monitoring data (that can be interpreted using 

existing NIOSH dose reconstruction processes or procedures) to support partial dose 

reconstructions for the operational period at the site. Therefore, dose reconstructions for 

individuals employed at Revere Copper and Brass during the period from July 24, 1943 through 

December 31, 1954, but who do not qualify for inclusion in the SEC, may be performed using 

these data as appropriate.
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Health Endangerment Determination

Per EEOICPA and 42 C.F.R. § 83.13(c)(3), a health endangerment determination is required because 

NIOSH has determined that it does not have sufficient information to estimate dose for the members 

of the proposed class from July 24, 1943 through December 31, 1954. 

NIOSH did not identify any evidence supplied by the petitioners or from other resources that would 

establish that the proposed class was exposed to radiation during a discrete incident likely to have 

involved exceptionally high-level exposures. However, evidence indicates that some workers in the 

proposed class may have accumulated substantial chronic exposures through episodic intakes of 

radionuclides, combined with external exposures to gamma and beta radiation. Consequently, NIOSH 

has determined that health was endangered for those workers covered by this evaluation who were 

employed for at least 250 aggregated work days either solely under their employment or in 

combination with work days within the parameters established for other SEC classes (excluding 

aggregate work day requirements). 

For the period January 1, 1955 through December 31, 1984, a health endangerment determination is 

not required because NIOSH has determined that it has an established methodology for estimating 

dose. 
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Table of Contents

1.0 Purpose and Scope ........................................................................................................................ 11

2.0 Introduction .................................................................................................................................. 11

3.0 SEC-00164 Revere Copper and Brass Class Definitions ............................................................. 12

3.1 Petitioner-Requested Class Definition and Basis ................................................................ 12

3.2 Class Evaluated by NIOSH ................................................................................................. 13

3.3 NIOSH-Proposed Class(es) to be Added to the SEC .......................................................... 13

4.0 Data Sources Reviewed by NIOSH to Evaluate the Class ........................................................... 13

4.1 Site Profile Technical Basis Documents (TBDs) ................................................................ 14

4.2 Technical Information Bulletins .......................................................................................... 14

4.3 Facility Employees and Experts .......................................................................................... 15

4.4 Previous Dose Reconstructions ........................................................................................... 16

4.5 NIOSH Site Research Database .......................................................................................... 16

4.6 Documentation and/or Affidavits Provided by Petitioners ................................................. 16

5.0 Radiological Operations Relevant to the Class Evaluated by NIOSH ......................................... 17

5.1 Revere Copper and Brass Plant and Process Descriptions .................................................. 17

5.2 Radiological Exposure Sources from Revere Operations ................................................... 23

5.2.1 Internal Radiological Exposure Sources from Revere Operations .......................... 23

5.2.1.1 Uranium .................................................................................................... 23

5.2.1.2 Thorium .................................................................................................... 24

5.2.1.3 Residual Period ......................................................................................... 24

5.2.2 External Radiological Exposure Sources from Revere Operations ......................... 25

5.2.2.1 Photon ....................................................................................................... 26

5.2.2.2 Beta ........................................................................................................... 27

5.2.2.3 Neutron ..................................................................................................... 27

5.2.2.4 Residual Period ......................................................................................... 27

6.0 Summary of Available Monitoring Data for the Class Evaluated by NIOSH ............................. 28

6.1 Available Revere Internal Monitoring Data ........................................................................ 28

6.2 Available Revere External Monitoring Data ....................................................................... 32

7.0 Feasibility of Dose Reconstruction for the Class Evaluated by NIOSH ...................................... 33

7.1 Pedigree of Revere Copper and Brass Data ........................................................................ 34

7.1.1 Internal Monitoring Data Pedigree Review ............................................................. 34

7.1.2 External Monitoring Data Pedigree Review ............................................................ 35

7.2 Evaluation of Bounding Internal Radiation Doses at Revere .............................................. 35

7.2.1 Evaluation of Bounding Process-Related Internal Doses ........................................ 35

7.2.1.1 Airborne Levels ........................................................................................ 36

7.2.2 Evaluation of Bounding Residual Period Internal Doses ........................................ 36

7.2.3 Methods for Bounding Internal Dose at Revere ...................................................... 37

7.2.3.1 Methods for Bounding Operational Period Internal Dose ........................ 37
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7.2.3.2 Methods for Bounding Residual Period Internal Dose ............................. 37

7.2.4 Internal Dose Reconstruction Feasibility Conclusion ............................................. 40

7.3 Evaluation of Bounding External Radiation Doses at Revere ............................................. 40

7.3.1 Evaluation of Bounding Process-Related External Doses ....................................... 41

7.3.2 Evaluation of Bounding Residual Period External Doses ....................................... 41

7.3.3 Revere Occupational X-Ray Examinations ............................................................. 41

7.3.4 Methods for Bounding External Dose at Revere ..................................................... 42

7.3.4.1 Methods for Bounding Operational Period External Dose ....................... 42

7.3.4.2 Methods for Bounding Residual Period External Doses .......................... 42

7.3.5 External Dose Reconstruction Feasibility Conclusion ............................................ 45

7.4 Evaluation of Petition Basis for SEC-00164 ....................................................................... 45

7.5 Summary of Feasibility Findings for Petition SEC-00164 .................................................. 46

8.0 Evaluation of Health Endangerment for Petition SEC-00164 ...................................................... 47

9.0 Class Conclusion for Petition SEC-00164 ................................................................................... 47

10.0 References .................................................................................................................................... 49

Attachment 1: Data Capture Synopsis ................................................................................................... 55
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 Figures 

5-1: Buildings and Equipment at Revere Copper and Brass ................................................................. 18

6-1: Survey Area in the Revere Extrusion Area .................................................................................... 31

Tables 

4-1: No. of Revere Claims Submitted Under the Dose Reconstruction Rule ....................................... 16

5-1: Uranium Extrusions Performed at Revere for the MED, 1943-1944 ............................................ 20

5-2: Principal Radiation Emissions from Natural Uranium and Its Short-lived Decay Products ......... 25

5-3: Principal Radiation Emissions from Th-232 and its Short-Lived Decay Products ........................ 26

6-1: Available Uranium Air Sample Results for the Revere Operational Period .................................. 29

6-2: Available Thorium Air Samples for the Revere Operational Period ............................................. 30

6-3: Available Smear Surveys for the Revere Operational Period ........................................................ 30

6-4: ANL Survey Results for Revere Copper and Brass – April 22, 1981 ........................................... 32

7-1: Source Term Depletion Adjustments for the Revere Residual Period (1% Per Day) .................... 38

7-2: Source Term Depletion Adjustments for the Revere Residual Period (Exponential) .................... 39

7-3: Revere Residual Period Daily Effective Dose (1% Per Day) ........................................................ 43

7-4: Residual Period Daily Dose Rates Due to Uranium and Thorium (Exponential).......................... 44

7-5: Summary of Feasibility Findings for SEC-00164 .......................................................................... 46
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SEC Petition Evaluation Report for SEC-00164

1.0 Purpose and Scope

This report evaluates the feasibility of reconstructing doses for all workers who worked at Revere 

Copper and Brass, Detroit, Michigan from July 24, 1943 through December 31, 1954 and the residual 

period from January 1, 1955 through December 31, 1984. It provides information and analyses 

germane to considering a petition for adding a class of employees to the congressionally-created 

Special Exposure Cohort (SEC). 

This report does not make any determinations concerning the feasibility of dose reconstruction that 

necessarily apply to any individual energy employee who might require a dose reconstruction from 

NIOSH. This report also does not contain the final determination as to whether the proposed class 

will be added to the SEC (see Section 2.0). 

This evaluation was conducted in accordance with the requirements of EEOICPA, 42 C.F.R. pt. 83, 

and the guidance contained in the Division of Compensation Analysis and Support’s (DCAS) Internal 

Procedures for the Evaluation of Special Exposure Cohort Petitions, OCAS-PR-004.1

2.0 Introduction 

Both EEOICPA and 42 C.F.R. pt. 83 require NIOSH to evaluate qualified petitions requesting that the 

Department of Health and Human Services (HHS) add a class of employees to the SEC. The 

evaluation is intended to provide a fair, science-based determination of whether it is feasible to 

estimate with sufficient accuracy the radiation doses of the class of employees through NIOSH dose 

reconstructions.2 

42 C.F.R. § 83.13(c)(1) states: Radiation doses can be estimated with sufficient accuracy if NIOSH 

has established that it has access to sufficient information to estimate the maximum radiation dose, 

for every type of cancer for which radiation doses are reconstructed, that could have been incurred in 

plausible circumstances by any member of the class, or if NIOSH has established that it has access to 

sufficient information to estimate the radiation doses of members of the class more precisely than an 

estimate of the maximum radiation dose.

 

Under 42 C.F.R. § 83.13(c)(3), if it is not feasible to estimate with sufficient accuracy radiation doses 

for members of the class, then NIOSH must determine that there is a reasonable likelihood that such 

radiation doses may have endangered the health of members of the class The regulation requires 

NIOSH to assume that any duration of unprotected exposure may have endangered the health of 

members of a class when it has been established that the class may have been exposed to radiation 

during a discrete incident likely to have involved levels of exposure similarly high to those occurring 

 

1 DCAS was formerly known as the Office of Compensation Analysis and Support (OCAS).

2 NIOSH dose reconstructions under EEOICPA are performed using the methods promulgated under 42 C.F.R. pt. 82 and 

the detailed implementation guidelines available at http://www.cdc.gov/niosh/ocas.
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during nuclear criticality incidents. If the occurrence of such an exceptionally high-level exposure has 

not been established, then NIOSH is required to specify that health was endangered for those workers 

who were employed for at least 250 aggregated work days within the parameters established for the 

class or in combination with work days within the parameters established for other SEC classes 

(excluding aggregate work day requirements). 

NIOSH is required to document its evaluation in a report, and to do so, relies upon both its own dose 

reconstruction expertise as well as technical support from its contractor, Oak Ridge Associated 

Universities (ORAU). Once completed, NIOSH provides the report to both the petitioner(s) and to the 

Advisory Board on Radiation and Worker Health (Board). The Board will consider the NIOSH 

evaluation report, together with the petition, petitioner(s) comments, and other information the Board 

considers appropriate, in order to make recommendations to the Secretary of HHS on whether or not 

to add one or more classes of employees to the SEC. Once NIOSH has received and considered the 

advice of the Board, the Director of NIOSH will propose a decision on behalf of HHS. The Secretary 

of HHS will make the final decision, taking into account the NIOSH evaluation, the advice of the 

Board, and the proposed decision issued by NIOSH. As part of this decision process, petitioners may 

seek a review of certain types of final decisions issued by the Secretary of HHS.

3

 

3.0 SEC-00164 Revere Copper and Brass Class Definitions 

The following subsections address the evolution of the class definition for SEC-00164, Revere Copper 

and Brass. When a petition is submitted, the requested class definition is reviewed as submitted. 

Based on its review of the available site information and data, NIOSH will make a determination 

whether to qualify for full evaluation all, some, or no part of the petitioner-requested class. If some 

portion of the petitioner-requested class is qualified, NIOSH will specify that class along with a 

justification for any modification of petitioner’s class. After a full evaluation of the qualified class, 

NIOSH will determine whether to propose a class for addition to the SEC and will specify that 

proposed class definition.

3.1 Petitioner-Requested Class Definition and Basis

Petition SEC-00164 was received on January 26, 2010 and qualified on March 18, 2010. The 

petitioner requested that NIOSH consider the following class: Extruder and Shape Specialists who 

worked in the Rod and Shape Mill at Revere Copper and Brass, Detroit, Michigan from 1943 through 

1984. 

The petitioner provided information and affidavit statements in support of the petitioner’s belief that 

accurate dose reconstruction over time is impossible for the Revere workers in question. NIOSH 

deemed the following information and affidavit statements sufficient to qualify SEC-00164 for 

evaluation: 

The petitioner stated that, to the best of his knowledge, Revere Copper and Brass never 

used any type of monitoring device to detect radiation at the facility.

 

3 See 42 C.F.R. pt. 83 for a full description of the procedures summarized here. Additional internal procedures are 

available at http://www.cdc.gov/niosh/ocas.
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Based on its Revere Copper and Brass research and data capture efforts, NIOSH determined that it has 

access to a limited number of air sample and smear survey results for Revere during the time period

under evaluation. However, NIOSH also determined that medical records, bioassay data, and external 

monitoring results are not available. NIOSH concluded that there is sufficient documentation to 

support, for at least part of the requested time period, the petition basis that internal and external

radiation exposures and radiation doses were not adequately monitored at the Revere site, either 

through personal monitoring or area monitoring. The information and statements provided by the 

petitioner qualified the petition for further consideration by NIOSH, the Board, and HHS. 

3.2 Class Evaluated by NIOSH

Based on its preliminary research, NIOSH divided the petitioner-requested class because it was able to 

determine the end of the operational period, and thus, the duration of the residual period. Therefore, 

NIOSH defined the following class for further evaluation: All workers who worked at Revere Copper 

and Brass, Detroit, Michigan from July 24, 1943 through December 31, 1954 and for the residual 

period from January 1, 1955 through December 31, 1984. 

The operations start date was changed from 1943 to July 24, 1943 when the first extrusion was 

performed for the MED. The last extrusion performed for the AEC was on October 19, 1954; for the 

purposes of this evaluation, the operational period end date was extended to the end of 1954. January 

1, 1955 represents the beginning of the residual period, which continued through the end of 1984, the 

year the facility was demolished.

3.3 NIOSH-Proposed Class(es) to be Added to the SEC

Based on its research of the class under evaluation, NIOSH has defined a single class of employees for 

which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSH-proposed class 

to be added to the SEC includes all Atomic Weapons Employer employees who worked at Revere 

Copper and Brass, Detroit, Michigan, from July 24, 1943 through December 31, 1954, for a number 

of work days aggregating at least 250 work days, occurring either solely under this employment or in 

combination with work days within the parameters established for one or more other classes of 

employees included in the Special Exposure Cohort. 

4.0 Data Sources Reviewed by NIOSH to Evaluate the Class

As a standard practice, NIOSH completed an extensive database and Internet search for information 

regarding Revere Copper and Brass. The database search included the DOE Legacy Management 

Considered Sites database, the DOE Office of Scientific and Technical Information (OSTI) database, 

the Energy Citations database, the Atomic Energy Technical Report database, and the Hanford 

Declassified Document Retrieval System. In addition to general Internet searches, the NIOSH 

Internet search included OSTI OpenNet Advanced searches, OSTI Information Bridge Fielded 

searches, Nuclear Regulatory Commission (NRC) Agency-wide Documents Access and Management 

(ADAMS) web searches, the DOE Office of Human Radiation Experiments website, and the DOENational Nuclear Security Administration-Nevada Site Office-search. Attachment One contains a 
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summary of Revere Copper and Brass documents with data capture details and general descriptions of 

the documents retrieved.

In addition to the database and Internet searches listed above, NIOSH identified and reviewed 

numerous data sources to determine information relevant to determining the feasibility of dose 

reconstruction for the class of employees under evaluation. This included determining the availability 

of information on personal monitoring, area monitoring, industrial processes, and radiation source 

materials. The following subsections summarize the data sources identified and reviewed by NIOSH. 

4.1 Site Profile Technical Basis Documents (TBDs) 

A Site Profile provides specific information concerning the documentation of historical practices at 

the specified site. Dose reconstructors can use the Site Profile to evaluate internal and external 

dosimetry data for monitored and unmonitored workers, and to supplement, or substitute for, 

individual monitoring data. A Site Profile consists of an Introduction and five Technical Basis 

Documents (TBDs) that provide process history information, information on personal and area 

monitoring, radiation source descriptions, and references to primary documents relevant to the 

radiological operations at the site. The Site Profile for a small site may consist of a single document. 

As part of NIOSH’s evaluation detailed herein, it examined the following TBDs for insights into 

Revere Copper and Brass operations or related topics/operations at other sites: 

• TBD: Site Profiles for Atomic Weapons Employers that Worked Uranium and Thorium Metals, 

Battelle-TBD-6000, Rev. F0; Battelle; December 13, 2006; SRDB Ref ID: 30671 

• TBD: Site Profiles for Atomic Weapons Employers that Worked Uranium and Thorium Metals, 

Appendix AS – Copperweld Steel Co., Battelle-TBD-6000, App. AS, Rev. 0; Battelle; July 16, 

2007; SRDB Ref ID: 74751 

• TBD: Hanford Site – Site Description, ORAUT-TKBS-0006-2, Rev. 2; Oak Ridge Associated 

Universities; February 22, 2010; SRDB Ref ID: 79424 

4.2 Technical Information Bulletins

A Technical Information Bulletin is a general working document that provides guidance for preparing

dose reconstructions at particular sites or categories of sites. NIOSH reviewed the following 

Technical Information Bulletins as part of its evaluation: 

• Estimation of Ingestion Intakes, OCAS-TIB-009, Rev. 00; Office of Compensation Analysis and 

Support; April 13, 2004; SRDB Ref ID: 22397

• Estimating the Maximum Plausible Dose to Workers at Atomic Weapons Employer Facilities, 

ORAUT-OTIB-0004, Rev. 03 PC-2; Oak Ridge Associated Universities; December 6, 2006; 

SRDB Ref ID: 29949
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• Dose Reconstruction from Occupationally Related Diagnostic X-Ray Procedures, ORAUT-OTIB0006, Rev. 03 PC-1; Oak Ridge Associated Universities; December 21, 2005; SRDB Ref ID: 

20220

• Dose Reconstruction During Residual Radioactivity Periods at Atomic Weapons Employer 

Facilities, ORAUT-OTIB-0070, Rev. 00; Oak Ridge Associated Universities; March 10, 2008; 

SRDB Ref ID: 41603

4.3 Facility Employees and Experts

To obtain additional information, NIOSH conducted seven interviews with four former Revere 

Copper and Brass employees.

• Personal Communication, 2010a, Personal Communications with Former Lab Worker; Telephone 

Interviews by ORAU Team; April 13, 2010; follow-up call June 8, 2010; SRDB Ref ID: 81007

• Personal Communication, 2010b, Personal Communications with Former Chemist; Telephone 

Interviews by ORAU Team; April 15, 2010; follow-up call June 8, 2010; SRDB Ref ID: 81008

• Personal Communication, 2010c, Personal Communication with Former Tester; Telephone 

Interview by ORAU Team; April 16, 2010; SRDB Ref ID: 81009 

• Personal Communication, 2010d, Personal Communications with Former Draftsman; Telephone 

Interviews by ORAU Team and NIOSH staff; April 14, 2010; follow-up call June 7, 2010; SRDB 

Ref ID: 81010
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4.4 Previous Dose Reconstructions

NIOSH reviewed its NIOSH DCAS Claims Tracking System (NOCTS) to locate EEOICPA-related 

dose reconstructions that might provide information relevant to the petition evaluation. Table 4-1 

summarizes the results of this review. (NOCTS data available as of May 25, 2010) 

Table 4-1: No. of Revere Claims Submitted Under the Dose Reconstruction Rule

Description Totals

Total number of claims submitted for dose reconstruction 8 

Total number of claims submitted for energy employees who meet the definition criteria for the class 

under evaluation (January 1, 1943 through December 31, 1984). 8 

Number of dose reconstructions completed for energy employees who meet the definition criteria for 

the class under evaluation (i.e., the number of such claims completed by NIOSH and submitted to the 

Department of Labor for final approval). 8 

Number of claims for which internal dosimetry records were obtained for the identified years in the 

evaluated class definition 0 

Number of claims for which external dosimetry records were obtained for the identified years in the 

evaluated class definition 0 

NIOSH reviewed each claim to determine whether internal and/or external personal monitoring 

records could be obtained for the employee. NIOSH has not identified any internal or external 

dosimetry data for these claimants. The Computer Assisted Telephone Interview (CATI) 

documentation indicated that interviewees stated: (1) there was no monitoring; or (2) they did not 

know if monitoring was provided or if bioassay or biological samples were taken. 

4.5 NIOSH Site Research Database

NIOSH also examined its Site Research Database (SRDB) to locate documents supporting the 

assessment of the evaluated class. One hundred thirty-nine documents in this database were identified 

as pertaining to Revere Copper and Brass. These documents were evaluated for their relevance to this 

petition. The documents include process descriptions, discussions of radiation hazards associated with 

uranium, medical program descriptions, air sample data, experimental procedures for determination of 

extrusion parameters, and plant descriptions. 

4.6 Documentation and/or Affidavits Provided by Petitioners

In qualifying and evaluating the petition, NIOSH reviewed the following document submitted by the 

petitioner:

• Affidavit from Survivor Representative; January 21, 2010; OSA Ref ID: 110730 
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5.0 Radiological Operations Relevant to the Class Evaluated by 

NIOSH

ATTRIBUTION: Section 5.0 and its related subsections were completed by Ed Scalsky, Oak Ridge 

Associated Universities (ORAU). These conclusions were peer-reviewed by the individuals listed on 

the cover page. The rationales for all conclusions in this document are explained in the associated 

text.

The following subsections summarize the radiological operations at the Revere Copper and Brass site 

from July 1943 through December 1954 and the information available to NIOSH to characterize 

particular processes and radioactive source materials. The residual period from January 1955 through 

December 1984 is also discussed. From available sources NIOSH has gathered process and source 

descriptions, information regarding the identity and quantities of some radionuclides of concern, and

information describing processes through which radiation exposures may have occurred and the 

physical environment in which they may have occurred. The information included within this 

evaluation report is intended only to be a summary of the available information.

5.1 Revere Copper and Brass Plant and Process Descriptions 

The primary radioactive materials at Revere were natural uranium and thorium metals existing either 

separately or as alloys. Revere’s main function was the extrusion of uranium billets into rods and 

various other shapes for use by Hanford, Savannah River Site, and Oak Ridge National Laboratory 

(ORNL). During 1943 and 1944, under the MED contract, Revere extruded approximately 2,695,205 

lbs. of billets. Even though there was strict accountability of the metal, the total quantity of material 

processed over the period under evaluation is not accurately known. Thorium was extruded on an 

intermittent basis and the amount of thorium extruded is also not known. Additional work on the 

extrusion, shaping, and machining of uranium and thorium was done intermittently through 1954 

(Fisher, 1954; Montenyohl, 1952; Various Authors, 1949-1952). 

Revere Copper and Brass was formed in 1928 from a merger of six small copper and brass companies. 

Soon after its inception it was one of the largest copper manufacturers in the United States, producing 

copper pipes, bars, tubes, and sheets as well as cookware. The Revere site was located at 5851 W. 

Jefferson Street in Detroit, Michigan. The plant consisted of four buildings, including the Foundry 

building, the physical/chemical labs/machine shop building, the Extrusion Area building, and a 

smaller building that may have been used for offices. The portions of the site that are of particular 

interest in terms of potential radiological contamination are two extrusion presses and a furnace, all 

housed in the Extrusion Area building, as well as the high bay area of the Extrusion Area building that 

would have been susceptible to the accumulation of radioactive dust due to airborne contamination 

(DOE, 1990). Figure 5-1 shows the buildings and equipment locations at the Revere site (ANL, 

1981).
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Figure 5-1: Buildings and Equipment at Revere Copper and Brass

When the United States entered World War II, Revere turned its production from house wares to war 

materials. In 1942, Revere began making cartridge cases, rocket cases, and smoke bombs. In 1943, 

E. I. du Pont de Nemours and Company contracted with the MED to extrude natural uranium. In turn, 

DuPont issued purchase orders to Revere from July 24, 1943 through 1944 to extrude approximately 

1200 tons of natural uranium and to conduct special experiments (DuPont, 1945).

In December 1944, a MED letter stated that all Revere uranium extrusion operations had been 

terminated and a survey had been made to ascertain that all possible remaining metal had been 

recovered (Johnson, 1944). However, a June 21, 1946 MED monthly report (Schumar, 1946) stated

that “extrusion of myrnalloy [uranium-thorium]4

 rods and beryllium shapes was conducted at Revere 

on June 6, 1946.” This was an attempt to extrude two myrnalloy 6 1⁄2-inch diameter billets into 1 3⁄4-

inch rods. Nevertheless, during the 1943-1944 time frame, the vast majority of the MED work 

consisted of uranium extrusion. 

Revere had a separate contract with the AEC from mid-1949 through mid-1954 for extruding uranium 

and thorium for research activities. The amount of material handled for the AEC contract is unknown. 

Revere also performed other experimental extrusions for the AEC between 1947 and 1949 (Kattner, 

1947a; Kattner, 1947b; Kattner, 1947c; Kattner, 1947d). Documentation available to NIOSH 

indicates that the extrusion of thorium was done on an intermittent basis and appears to have consisted 

 

4 The Hanford Site Profile defines myrnalloy as thorium (ORAUT-TKBS-0006-2). However, the Argonne National 

Laboratory survey group referred to myrnalloy as a mixture of uranium and thorium (ANL, 1981). This evaluation report 

employs the ANL definition.
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of smaller quantities (as compared to the production quantities of uranium). One example is the 

extrusion of three bare and/or unsheathed thorium billets on November 5 and 6, 1952 (Various 

Authors, 1949-1952). In addition to natural uranium and thorium, Revere extruded alloys of these 

two elements that included stable fission elements such as columbium (niobium), molybdenum, 

zirconium, lanthanum, and ruthenium (Foote, 1944a; Foote, 1944b; Order Request and Shipping 

Receipt, 1944). 

When Revere became involved in the extrusion of uranium in 1943, the methods for the extrusion of 

uranium were being developed. The beginning of this effort and the associated problems encountered 

are best described in the DuPont document, The Metal Fabrication Program for the Clinton Engineer 

Works and the Hanford Engineer Works (DuPont, 1945). This document describes the DuPont 

Engineering Department program to produce uranium slugs. These slugs, each one a small cylindrical 

mass of uranium enclosed within an aluminum jacket, were used as the charge in the atomic pile to 

manufacture, through nuclear processes, minute quantities of plutonium for the atomic bomb project. 

Prior to the production-scale extrusion program at Revere, the use of uranium (referred to in 

correspondence variously as T-metal, Tuballoy, X-metal, DuPont Special Alloy, Chemicals NO1BN, 

and C-105) had been generally limited to small amounts (grams) in the laboratory. At that time, little 

was known about uranium’s commercially-adaptable physical properties. The accelerated fabrication 

of hundreds of tons of uranium required the inauguration of an arduous series of experimental and 

developmental programs to determine not only the extrudability, machinability, and other physical 

characteristics of the metal, but also the influence of microscopic quantities of impurities on these 

characteristics (DuPont, 1945). Revere played a significant role in these efforts.

The DuPont Engineering Department realized early on the health hazards attendant to the fabrication 

of this metal. On March 20, 1943, prior to starting work on the slug program, they asked the 

University of Chicago Metallurgical Laboratory (Met Lab) for information about the precautions to be 

taken to protect the health of all individuals exposed to uranium. The Met Lab advised the use of

masks, respirators, and gloves as well as a complete physical examination of each employee prior to 

exposure to the metal. Entrance, periodic, and exit physical examinations were made by the plant 

physician, by a retained physician, or by members of the DuPont staff, as best fitted each vendor. Due 

to security requirements, the cost of all protective measures incurred by Revere (and other vendors) as 

a result of Met Lab and DuPont recommendations were reimbursable from the DuPont Engineering 

Department. This included the installation of adequate ventilation where necessary. 

When the fabrication program expanded to embrace machining, outgassing and straightening, 

canning, and rolling of the metal, the Met Lab medical group visited the program vendors and made 

further recommendations and tests. Among the latter was the determination of the dust count in the 

air near each of the operating machines. On the basis of these findings, a suggested tolerance limit of 

150 micrograms of uranium per cubic meter (μg U/m3

) of air was adopted. This figure later was 

reduced to 120 (μg U/m3) after continued study confirmed the need to reduce the tolerance limit 

(DuPont, 1945). 

Many dust counts taken at Revere, particularly those taken in areas of high local concentration, greatly 

exceeded the limit. After the first few extrusion runs at Revere, the Met Lab determined that 

ventilating equipment was needed at this location to reduce the dust count to a level below the 

tolerance limit. The DuPont Engineering Department confirmed this recommendation and further 
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proposed that a dust collector be installed in the system to save metal and to prevent the free discharge 

of uranium dust to the Detroit atmosphere; both were installed.

When the uranium slug program drew to a close in August 1944, strict accountability records for all 

scrap uranium material were required. To this end, an accounting was taken of all uranium sample 

pieces and scrap. The ventilating and dust-collecting systems at Revere were also cleaned to collect 

all possible deposits of uranium metal. 

The Initial Revere Extrusion Effort

Revere performed production-level work with natural uranium ingots from 1943 to 1944 and with 

natural uranium metal and uranium oxides from 1946 to the mid-1950s (FUSRAP, 2000). Table 5-1 

lists the dates, the number of billets and rods, and the weight of the billets that were processed for the 

MED at Revere from July, 1943 to August 31, 1944 (DuPont, 1945). On three occasions (April 18, 

May 11, and May 18, 1944), Revere extruded uranium alloys that contained stable fission elements 

such as molybdenum, niobium (columbium), lanthanum, ruthenium, and zirconium on an 

experimental basis as requested by DuPont or the Metallurgical Laboratory (Foote, 1944a; Foote, 

1944b; Order Request and Shipping Receipt, 1944). These alloys were classified as either Type I or 

Type II metals. Revere also extruded alloys of uranium-beryllium, uranium-thorium, and other 

uranium during the period under evaluation (ANL, 1981; Foote, 1944a; Foote, 1944b; FUSRAP, 

2010; Order Request and Shipping Receipt, 1944; Schumar, 1946). 

NIOSH has not identified any radioactive material processed after October 19, 1954. However, 

residual contamination may have existed on the equipment that was previously used for radioactive 

work. 

The first extrusion runs at Revere were performed on Saturday and Sunday, July 24-25, 1943. 

According to the documentation (DuPont, 1945, pdf pp. 39, 54-55), all Revere runs were made on 

weekends because security limitations prevented their execution during the normal workweek. 

However, it is noted that several runs were also made on weekdays. Revere extrusion runs are shown 

in Table 5-1. This initial extrusion effort continued until August 20, 1944. 

Table 5-1: Uranium Extrusions Performed at Revere for the MED, 1943-1944

Dates No. of Billets No. of Rods Billet Weight (lbs.)

Year 1943:

7/24-25 400 399 37,434.75

7/31, 8/1 500 498 46,219.75

8/14-15 620 614 56,673.25

8/21-22 309 309 29,356.25

8/21-22 205 205 19,864.75

8/29 5 5 438.5

8/28-29 590 589 51,587.00

9/4-5 600 596 53,061.50

9/11-12 550 543 50,628.00

9/18-19 580 578 56,974.00
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Table 5-1: Uranium Extrusions Performed at Revere for the MED, 1943-1944

Dates No. of Billets No. of Rods Billet Weight (lbs.)

10/2-3 416 410 41,098.75

10/9-10 550 549 52,838.50

10/16-17 590 588 60,280.25

10/23-24 500 498 50,932.00

11/6-7 570 567 57,690.63

11/13-14 630 513 53,355.00

100 10,489.88

11/19-21 1032 41 4,216.00

160 16,738.00

821 84,599.63

12/4-5 462 453 46,909.86

12/10-11 710 701 74,510.19

12/18-19 630 605 65,167.68

Year 1944:

1/8-9 535 526 63,321.87

1/22-23 679 625 78,697.13

2/5-6 333 332 35,985.95

20 20 2,138.38

2/12-13 570 557 82,417.93

2/19-20 381 349 44,840.00

3/4-5 612 607 73,976.91

3/11-12 306 306 36,729.19

3/24-25 607 605 73,358.13

3/31, 4/1 616 613 78,867.89

4/14-15 554 553 66,202.46

4/29 330 329 39,055.57

5/6-7 596 596 70,479.00

5/13 324 324 39,298.69

5/19-21 962 962 118,942.14

6/2-4 939 938 112,989.99

6/9-10 648 648 76,729.56

6/17-18 600 591 71,698.03

6/23-25 940 938 113,626.80

6/30, 7/1 640 639 71,804.53

7/15-16 657 656 78,199.63

7/29-30 654 653 79,459.26

8/12-13 620 620 74,963.21

8/19-20 676 676 84,357.89

Total 24,248 24,005 2,695,204.90

Outgassing and Straightening

In 1943, the DuPont Engineering Department determined that it wanted extruded rods outgassed and 

straightened. Outgassing involves removing hydrogen from the rod material. This was done by 

packing the rods in 10-inch diameter steel tubes, capping the ends of the tubes, and leaving a small 
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opening at each end. In order to outgas hydrogen, argon gas was passed through the steel tubes while 

they were being heated in a furnace to 1200 degrees F. (DuPont, 1945; Battelle-TBD-6000, App. AS).

Revere was not initially involved with the outgassing and straightening program. However, DuPont 

felt that if these processes were performed at the extrusion facility, it would expedite delivery and

result in a pronounced savings to the government by eliminating shipment to a third party with the 

associated security costs. Accordingly, Revere started outgassing Hanford-size rods on September 

11-12, 1943. From the end of November 1943 to August 1944, the outgassing procedure was 

standardized with little or no difficulty (DuPont, 1945, pdf pp. 77-79). 

Alpha Phase Extrusion Experiments

Additional experimental work was performed at Revere for the AEC to determine the optimum 

conditions for alpha phase extrusion of uranium rods. Between room temperature and its melting 

point (2070 degrees F.) uranium metal exists in three crystalline forms known as the alpha, beta, and 

gamma phases. Experiments were performed by Revere to determine the optimum conditions for 

alpha phase extrusion of uranium rods (Hanford Works, 1948; Kattner, 1947a; Kattner, 1947b; 

Kattner, 1947c; Kattner, 1947d). These experimental procedures are similar to the normal extrusion 

procedures and could have resulted in personnel exposures. These experiments were conducted on 

September 17-18, October 10, and November 3, 1947. In addition, the Massachusetts Institute of 

Technology (MIT) conducted some extrusion experiments at Revere on October 23-24, 1947 that 

involved the extrusion of beryllium and of uranium in the alpha phase (Kattner, 1947c).

Thorium Extrusions

Thorium extrusions were conducted at Revere on an experimental and intermittent basis in contrast to 

the production levels of uranium. NIOSH has identified the following thorium extrusion operations at 

Revere:

• October 8, 1946: Thorium rods were requested by Clinton Laboratories. Five of the best rods 

were chosen, indicating that more than five rods were extruded (Mecherey, 1947). 

• August 13-15, 1952: Two billets were expected to be extruded on an experimental basis. 

Documentation of completion of these extrusions has not been found (Hayes, 1952). 

• November 5 and 6, 1952: Three thorium billets were extruded (Various Authors, 1949-1952). 

• November 14, 1952: Thorium billets were extruded; the total quantity is not stated but sufficient 

thorium was extruded for the production of 200 slugs (Montenyohl, 1952; Noto, 1952). 

• October 19, 1954: Thorium rod was extruded for machining into slugs; half were shipped to 

Savannah River and half were shipped to Sylvania Electric Products (Fisher, 1954). 

The 1954 thorium extrusion operation ended the extrusion program at Revere. The residual period 

started on January 1, 1955 and continued until December 31, 1984, the year the facility was 

demolished. 
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5.2 Radiological Exposure Sources from Revere Operations

The primary sources of external exposure to Revere workers were due to direct radiation from 

handling and processing uranium and thorium as well as submersion in the air contaminated with 

these metals. Inhalation and ingestion of contaminated air resulting from re-suspension of surface 

contamination, during both operations and the residual period, was the primary source of internal 

exposure. 

The following subsections provide an overview of the internal and external exposure sources for the 

Revere class under evaluation.

5.2.1 Internal Radiological Exposure Sources from Revere Operations

Inhalation of airborne contamination during the various extrusion processes and inhalation of airborne 

contamination re-suspended during both operations and the residual period were the primary sources 

of internal exposure to Revere workers. 

5.2.1.1 Uranium

During the operations under the MED contracts (July 24, 1943 to August 31, 1944), the primary 

radionuclide of concern was uranium, also known as tuballoy, X-metal, T-metal, DuPont special 

alloy, and chemicals NO1BN and C-105. Revere was under a separate contract with the AEC to 

perform experimental work on rod extrusion as well as the development of slugs for the Clinton 

Engineer Works and the Hanford Engineer Works. 

The principal sources of internal exposure to radionuclides at the Revere site was from the inhalation 

of dust or fumes generated during various processes, including billet extrusion and shaping, 

quenching, rod straightening, butt removal, machining and cutting, outgassing, and handling during 

storing and shipping. Most of these operations were conducted in either the building that housed the 

furnaces and extrusion equipment, or in the building containing the machine shop and physical and 

chemical labs. Both the furnace and the extrusion machine were equipped with hoods. However, the 

hood over the extrusion machine was of questionable adequacy and, over time, the hood became 

warped, resulting in a large gap between the side wall and the hood. During the extrusion operations, 

large clouds of smoke poured out of the opening. In addition, there was a lack of maintenance on this 

hood (Nickson, 1944). Handling and storage of incoming material took place in a building called the 

DuPont compound. It is not clear where on site this building was. However, the material was trucked 

from that compound to the fabrication area. 
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During the fabrication process, the billets would first pass through a gas furnace where they were

heated to the desired temperature. They were then removed and taken to the extrusion machine. After 

extrusion, they went to a rolling table where they were partially straightened and allowed to cool to a 

certain extent. Following partial cooling, they were quenched in a water-filled basin, after which they 

were placed in another tank containing a 10 % sulfuric acid solution to remove the oxide that was 

formed during extrusion. At times, the operator used a brush to clean the oxides from the rods. The 

rods were then hosed off with fresh water. The rods were then removed to a rack where they were 

numbered and then packaged in boxes for shipping (Nickson, 1944). 

During each of these processes there was the possibility of airborne dust or fumes that potentially 

contained uranium metal. In particular, during the extrusion process and the brushing of the rods to 

remove the oxides, uranium oxides were a significant source of airborne contamination and potential 

internal exposure to workers. 

5.2.1.2 Thorium

Thorium extrusions were performed on a developmental and experimental basis in contrast to the 

production levels of uranium. Therefore, the workers’ internal exposure to thorium was significantly 

less than their exposure to uranium. However, the possibility of direct exposure to radiation from 

thorium as well as inhalation and ingestion of thorium dust and fumes did exist.

5.2.1.3 Residual Period

The primary source for internal exposure during the residual period could have been from working 

with the contaminated equipment used during the operational period, eating in the work area, and 

re-suspension of contamination. Several air samples were taken during the operational period both for 

uranium and thorium, as indicated in Section 6.1, Tables 6.1 and 6.2. The highest air sample result for 

uranium was 3300 μg/m3. All thorium air samples were within the tolerance level of 70 dpm/m3. 

However, the source term for the residual period was assumed to consist of both uranium and thorium 

in equal amounts at the maximum air concentration determined from the air sample results. As 

discussed in Sections 6 and 7, the highest uranium air concentration value was used to evaluate the 

contamination levels that could have existed at the beginning of the residual period, and ultimately, 

the air concentrations during the residual period. 
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5.2.2 External Radiological Exposure Sources from Revere Operations

The principal source of external exposure during the operational period (other than medical X-rays) 

was the direct exposure to natural uranium and thorium metal during the extrusion process, 

submersion in air potentially-contaminated with uranium and thorium metal, and exposure to 

contaminated surfaces. Uranium and thorium alloys were also extruded. Tables 5-2 and 5-3 list the 

radionuclides of concern for external radiation from uranium and thorium during the operational 

period. 

Table 5-2: Principal Radiation Emissions from Natural Uranium and Its Short-lived Decay Products

Radionuclide Half-life Beta Energy (MeV Max Photon (x or •) Energy (MeV)

U-238 4.468 x 109 years None x: 0.013 (8.8%)

Th-234 24.1 days 0.096 (25%) x: 0.013 (9.6%)

0.189 (73%) •: 0.063 (3.8%)

•: 0.093 (5.4%)

Pa-234m 1.17 minutes 2.28 (98.6%) •: 0.765 (0.2%)

~1.4 (1.4%) •: 01.001 (0.6%)

U-235 7.038 x 109 years None x: 0.013 (31%)

x: 0.090-0.105 (9.3%)

•: 0.144 (10.5%)

•: 0.163 (4.7%)

•: 0.186 (54%)

•: 0.205 (4.7%)

Th-231 25.5 hours 0.206 (15%) x: 0.013 (71%)

0.288 (49%) •: 0.026 (14.7%)

0.305 (35%) •: 0.084 (6.4%)

U-234 244,500 years None x: 0.013 (10.5%)

•: 0.053 (0.2%)

Source: Battelle-TBD-6000, pdf p. 20. The table shows the principal radiation emissions from natural uranium and its 

short lived decay products that were of concern for external radiation (not including bremsstrahlung).
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Table 5-3: Principal Radiation Emissions from Th-232 and its Short-Lived Decay Products

Radionuclide Half-life Beta Energy (MeV Max) Photon (x or •) Energy (MeV)

Th-232 1.405 x 1010 years None 0.059 (0.19%)

0.126 (0.04%)

Ra-228 5.71 years 0.389 (100%) 0.0067 (6 x 10-5%)

Ac-228 6.25 hours 0.983 (7%) 0.338 (11.4%)

1.014 (6.6%) 0.911 (27.7%)

1.115 (3.4%) 0.969 (16.6%)

1.17 (32%) 1.588 (3.5%)

1.74 (12%) ---

2.08 (8%) ---

(+33 more •s) ---

Th-228 1.9116 years

None

0.084 (1.19%)

0.132 (0.11%)

0.166 0.08%)

0.216 (0.27%)

Bi-212 60.55 minutes 1.59 (8%) 0.040 (1%)

2.246 (48.4%) 0.727 (11.8$)

--- 1.620 (2.75%)

Tl-208 3.1 minutes 1.28 (25%) 0.277 (6%)

1.52 (21%) 0.5108 (21.6%)

1.80(50%) 0.583 (85.8%)

--- 0.860 (12%)

--- 2.614 (100%)

Source: Handbook of Health Physics and Radiological Health (Rad Handbook, 1998). Intensities refer to the percentage 

of disintegrations of the nuclide itself, not to original parent of series. Gamma percents are given in terms of observable 

emissions, not transitions.

5.2.2.1 Photon

The majority of the photons from natural uranium metals are in the 30-250 keV energy range. Solid 

uranium objects provide considerable shielding of the lower-energy photons and harden the spectrum, 

causing the majority of the photons emitted from a solid uranium object (such as a billet or rod) to 

have energies greater than 250 keV. While it is recognized that solid uranium sources will have a 

hardened photon spectrum, exposure to a thin layer of uranium on a surface will result in a larger 

fraction of exposure to lower-energy photons (Battelle-TBD-6000). 

Table 5-2 shows the primary isotopes and photon energies associated with the uranium metal. 

Exposure to these photons was possible during all phases of the extrusion process from direct 

radiation during metal-handling and to submersion in metal-contaminated air.
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Thorium has a significant number of higher-energy photons in the Th-232 decay chain. Based on the 

half lives of the progeny, only a partial equilibrium is possible; therefore, it is conservative to state 

that equilibrium would be reached in this decay chain. It has been assumed that Ra-228 and Th-228 

progeny were in equilibrium with Th-232. Therefore, air concentrations were assumed equal for all 

progeny. Under this assumption, the progeny are the major source of both penetrating and 

non-penetrating external exposure. Table 5-3 shows the primary isotopes and photon energies 

associated with thorium and its progeny. 

5.2.2.2 Beta

Tables 5-2 and 5-3 show the principal beta emitters and their energies for the uranium and thorium 

metal used during the extrusion process. As indicated in these tables, there are a significant number of 

high-energy beta radiations that represent a shallow dose exposure concern to site workers. Workers 

who handled the uranium and thorium metal would have received shallow dose exposures. The 

primary exposure areas would have been the hands and forearms, the neck and face, and other areas of 

the body that might not have been covered. 

5.2.2.3 Neutron

Neutrons were not measured at Revere and were not expected to be a source of exposure for the class 

under evaluation. However, neutrons could arise from the •-n reaction with light elements (e.g., 

beryllium), interactions with the oxides, and through spontaneous fission. According to BattelleTBD-6000, uranium oxides would be the most common generators of (•,n) reactions. However, the 

quenching and the brushing off of the rods would minimize this source of neutrons. Although 

beryllium was extruded by MIT at Revere (DuPont, 1943; Kelley, 1949), the available documentation 

indicates that only one uranium-beryllium rod was extruded on June 6, 1946 (Schumar, 1946). 

Spontaneous fission yields and (•,n) yields in oxides are provided in Table 3.5 of Battelle-TBD-6000. 

Based on its analysis, NIOSH concludes that none of these sources would be sufficient to result in a 

significant neutron exposure to Revere workers. 

5.2.2.4 Residual Period

During the residual period, January 1, 1955 to December 31, 1984, workers were potentially exposed 

to direct radiation from surface contamination as well as exposure resulting from submersion in air 

contaminated with re-suspended residual uranium and thorium. This would include re-suspension 

from incidental removal of residual contamination (e.g., via housekeeping and personnel and 

equipment movement). A survey was performed on April 22, 1981 at Revere in three areas where 

operations with uranium and thorium were conducted (ANL, 1981, pdf pp. 3-4). The survey included 

direct radiation measurements and smear surveys. The survey results are presented in Section 6.1. 
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6.0 Summary of Available Monitoring Data for the Class Evaluated 

by NIOSH

NIOSH reviewed its NIOSH OCAS Claims Tracking System (NOCTS) to determine whether internal

and/or external personal monitoring records have been obtained for EEOICPA claimants; no internal 

or external monitoring data have been found or discovered for any Revere claimants. The following 

subsections provide an overview of the state of the available internal and external monitoring data 

obtained from other sources for the Revere class under evaluation.

6.1 Available Revere Internal Monitoring Data

ATTRIBUTION: Section 6.1 was completed by Eugene Potter, Mel Chew & Associates; and Ed 

Scalsky, Oak Ridge Associated Universities (ORAU). These conclusions were peer-reviewed by the 

individuals listed on the cover page. The rationales for all conclusions in this document are explained 

in the associated text.

Medical Records

Under the early uranium program, the DuPont Company had the responsibility for directing the 

medical examinations and all medical records were to be turned over to them (DuPont, 1945, pdf p. 

16; Wirth, 1945, pdf p. 6). These records have not been located or recovered. 

Bioassay Data

No bioassay data are available for Revere. References in the site documentation to periodic urine 

samples were probably about non-radiological medical tests as part of medical monitoring (Nickson, 

1944). Most of Revere’s uranium work was performed in 1943-1944 (DuPont, 1945). Fluorometric 

measurement techniques for uranium were not in use until the late 1940s (Stannard, 1988, pdf p. 132). 

Blood counts were part of the required physical examinations before starting work; they were repeated 

at three-month intervals (Norwood, 1944). Moderate anemia (low count of healthy red blood cells) 

was noted in the pre-employment examinations for two of the employees (Quigley, 1943). Blood 

counts were used in the early years to monitor potential radiation damage to the hematopoietic system. 

Note: Blood count information is not normally used as bioassay data for the purpose of radiological 

dose reconstruction. 

Whole Body Counting Data

Whole body counting, a technique employed to monitor photon-emitting radionuclides in the body, 

was not developed until the early to mid-1960s; by that time, radioactive work had concluded at 

Revere.
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Air Sample Data

A limited number of uranium air sample results were discovered for the Revere operational period. 

They are listed in Table 6-1 along with their source documents. All results are from MED consultants 

who visited the site to review health and safety practices. Initially, medical doctors from the Met Lab

were assigned to conduct dust studies and to recommend ventilation improvements and the use of 

protective devices, such as respirators (DuPont, 1945, pdf p. 18). There is no indication that an 

in-house air sampling program existed. Radioactive material extrusions were performed in the same 

areas as normal plant operations but under MED supervision. These operations were conducted 

during off-hours and weekends when most of the workforce was not present. 

Table 6-1: Available Uranium Air Sample Results for the Revere Operational Period

Sample Date Sample Location Result

(μg/m3) SRDB Ref ID

July 24, 1943 East of the furnace 580 10782, 11207

North of the extrusion press operator 230 10782, 11207

Point of false butt removal 2320 10782, 11207

August 21, 1943 Northeast corner of the roll table 2200 10782, , 11207, 17357

Outlet of the extruder 1100 10782, 11207, 17357

Furnace outlet where the operator cleans billet 

with wire brush

3300 10782, 11207, 17357

East side of furnace 100 10782, 11207, 17357

September 17-19, 1943 Outlet gas from outgassing furnace 0 10782, 17357

South of point where dummy butts are 

pounded off

120 10782, 17357

Corner where south edge of dry roll table 

abuts rolls leading from extruder

240 10782, 17357

South of extruder valve operator, side of 

extruder

2500 10782, 11207, 17357

Inlet to rod straightening machine 2500 10782, 11207, 17357

Outlet to rod straightening machine 2600 10782, 11207, 17357

February 5, 1944 Extruder operator 1650 11207

Edge of hood at outlet of extruder 100 11207

May 5, 1944 Four locations – illegible Partially illegiblea 80176

May 7, 1944 Four locations – illegible Partially illegibleb 80176

November 16, 1944 Next to the extrusion apparatus

(numerical result not given)c

<150 80439

Next to the butt removal procedure

(numerical result not given)c

<150 80439

December 21, 1949 General air result: 0.9 alpha dpm/m3 0.59d 10773

a

 Three values are four digits; one value is three digits. b

 Three values are three digits; one value is four digits. c The author stated: “In neither instance was a tolerance figure obtained on the samples.” d Calculated assuming a conversion factor of 1.52 dpm/μg of natural uranium. This value is consistent with the statement 

in the source document that the result was less than 2% of tolerance (<3 μg/m3

).
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The available air sampling results for thorium operations are also limited. The only results NIOSH

has obtained are for samples taken during thorium extrusion performed on November 5-6, 1952 

(Various Authors, 1949-1952). This work was under the supervision of the AEC (which replaced the 

MED on January 1, 1947). Apparently, the monitored thorium operation was part of “development 

work” and was not production-related. Health and safety support was provided by MIT personnel 

who took the air samples. The report lists the results in units of counts per minute per cubic meter. 

No conversion factor from counts per minute to disintegrations per minute was provided. The author 

noted that the thorium tolerance limit was 70 disintegrations per minute and stated that the results 

were well below this level (Various Authors, 1949-1952). The thorium results appear in Table 6-2. It 

is assumed that the term “covered,” which is used in the reference, refers to the fact that the billets 

were clad with some other metal before extrusion.

Table 6-2: Available Thorium Air Samples for the Revere Operational Period

Sample Date Description: Units Given Result

(dpm/m3)

a

SRDB Ref ID

November 5, 1952 No extrusions (background): 2.4±2.4 

counts/min/m3

<70 10773

Covered thorium: 0±2.4 counts/min/m3 <70

Uncovered thorium: 4.8±4.8 counts/min/m3 <70

November 6, 1952 Uncovered thorium: 9.6±2.4 counts/min/m3 <70

Background 1⁄2 hour later: 8.4±2.4 

counts/min/m3

<70

a Calibration factors were not published. All results were termed “well within tolerance” (70 dpm/m3

). This implies that 

the calibration factor was in the range of 4-6 dpm/cpm.

Operational Survey Data

Smear surveys may have been done routinely during the operational period by the MED/AEC or their 

consultants. However, only a few records have been located. The results are listed in Table 6-3. 

Table 6-3: Available Smear Surveys for the Revere Operational Period

Sample Date Sample Location Result

(• dpm/100 cm2) 

SRDB Ref ID

December 21, 1949 Surface of extrusion press previously used for 

uranium work

24 10773

Under runout table 11

Beta thickness gauge 25

Die in storage (previously used for uranium work) 2700
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Residual Survey Data

There is one record of a “preliminary survey” during the residual period conducted by Argonne 

National Laboratory on April 22, 1981 (ANL, 1981). This survey “found no evidence to indicate that 

an immediate radiological hazard exists.” Figure 6-1 shows the general area where the Extrusion Area 

survey was performed. 

Figure 6-1: Survey Area in the Revere Extrusion Area

The results of ANL’s direct radiation measurements and smear samples are shown in Table 6-4. 

Alpha survey instruments did not show detectable contamination in the Extrusion Area or the Physical 

Laboratory where uranium billets were stored and where a power saw had been used to cut extruded 

rods. Smear surveys were taken of the steel floor and glazed tiles in the Extrusion Area and of the 

power saw in the Physical Laboratory. From the context of the source document (ANL, 1981), the 

box labeled “1” in Figure 6-1 is likely the “Radioactive Anomaly on the Steel Floor” referred to in 

Table 6-4. The smears indicated background levels. The furnace and one of the extrusion presses was 

in operation and could not be surveyed. However, the furnace was not the one that had been used for 

uranium and thorium work. The surveyors were not aware that some ventilation equipment had been 

used during these operations and speculated that contamination had likely migrated to the overhead 

members and vents in the roof, which was of steel bridge truss construction. A more thorough survey 

was recommended (ANL, 1981). The recommended re-survey was never conducted, and when DOE
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officials visited the site in 1989, they found that it had been demolished. A “cursory radiological 

survey” conducted during this visit did not find any levels above background (DOE, 1990).

Table 6-4: ANL Survey Results for Revere Copper and Brass – April 22, 1981

Area 1 – Physical Laboratory (former storage area for uranium billets)

Survey Meters Glazed Wall Tile General Floors & Tile Background in Area

PRM-7(A) 15 μR/h 8-9 μR/h 8-9 μR/h

PRM-5-3 1500-2000 cpm 1000 cpm 1000 cpm

PAC-4G-3 < 50 cpm •

400 cpm ••

< 50 cpm •

250 cpm ••

< 50 cpm •

250 cpm ••

Area 2 – Power Hacksaw Used to Cut Billets

Survey Meters Present and Former Location of Power Hacksaw

PRM-7, PRM-5-3, 

PAC-4G-3 

All readings indicated background level

Area 3 – Extrusion Area

Survey Meters Spot on Steel Floor Floor Bricks Background in Area

PRM-7(A) 7 μR/h

(contact)

3-4 μR/h 3-4 μR/h

PRM-5-3 (B) 3000 cpm 1500-2000 cpm 500- 1000 cpm

PAC-4G-3 (C) < 50 cpm •

7500 cpm ••

< 50 cpm •

200 cpm ••

< 50 cpm •

220 cpm ••

Smear Results “Radioactive Anomaly on 

the Steel Floor”

Glazed Tile Power Hacksaw

background level background level background level

6.2 Available Revere External Monitoring Data

ATTRIBUTION: Section 6.2 was completed by Ray Clark and Ed Scalsky, Oak Ridge Associated 

Universities (ORAU). These conclusions were peer-reviewed by the individuals listed on the cover 

page. The rationales for all conclusions in this document are explained in the associated text.

Operations Period

NIOSH has found no external personnel monitoring results (including medical X-ray records) for the 

Revere operations period from 1943 through 1954.

Residual Period

NIOSH has found little survey data for Revere during the residual period from 1955 through 1984. A 

preliminary (screening) survey was conducted on April 22, 1981 by the Argonne National Laboratory 

Radiological Survey Group (ANL, 1981). Although the preliminary survey revealed no evidence of 
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an immediate radiological hazard, the group recommended that a complete radiological assessment be 

conducted of the entire facility when the furnace and extrusion presses were shut down and in a cold 

condition. NIOSH has found no evidence that this follow-up survey was conducted. 

On September 13, 1989, a DOE official and “representatives” visited the site and observed that it had 

been demolished. A cursory radiological survey revealed no areas with direct radiation levels above 

background levels. Preliminary survey results of a facility in the Detroit area used for similar 

purposes, whose structures were intact, did not identify any areas of residual contamination. Based on 

this information, DOE concluded that there was little or no potential for radiological exposure beyond 

background radiation; therefore, additional investigations were deemed unnecessary (DOE, 1990).

 

7.0 Feasibility of Dose Reconstruction for the Class Evaluated by 

NIOSH

The feasibility determinations for the class of employees under evaluation in this report are governed 

by both EEOICPA and 42 C.F.R. § 83.13(c)(1). Under that Act and rule, NIOSH must establish 

whether or not it has access to sufficient information either to estimate the maximum radiation dose 

for every type of cancer for which radiation doses are reconstructed that could have been incurred 

under plausible circumstances by any member of the class, or to estimate the radiation doses to 

members of the class more precisely than a maximum dose estimate. If NIOSH has access to 

sufficient information for either case, NIOSH would then determine that it would be feasible to 

conduct dose reconstructions. 

In determining feasibility, NIOSH begins by evaluating whether current or completed NIOSH dose 

reconstructions demonstrate the feasibility of estimating with sufficient accuracy the potential 

radiation exposures of the class. If the conclusion is one of infeasibility, NIOSH systematically 

evaluates the sufficiency of different types of monitoring data, process and source or source term data, 

which together or individually might assure that NIOSH can estimate either the maximum doses that 

members of the class might have incurred, or more precise quantities that reflect the variability of 

exposures experienced by groups or individual members of the class as summarized in Section 7.5. 

This approach is discussed in DCAS’s SEC Petition Evaluation Internal Procedures which are

available at http://www.cdc.gov/niosh/ocas. The next four major subsections of this Evaluation 

Report examine:

• The sufficiency and reliability of the available data. (Section 7.1) 

• The feasibility of reconstructing internal radiation doses. (Section 7.2) 

• The feasibility of reconstructing external radiation doses. (Section 7.3) 

• The bases for petition SEC-00164 as submitted by the petitioner. (Section 7.4) 
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7.1 Pedigree of Revere Copper and Brass Data

This subsection answers questions that need to be asked before performing a feasibility evaluation. 

Data Pedigree addresses the background, history, and origin of the data. It requires looking at site 

methodologies that may have changed over time; primary versus secondary data sources and whether 

they match; and whether data are internally consistent. All these issues form the bedrock of the 

researcher’s confidence and later conclusions about the data’s quality, credibility, reliability, 

representativeness, and sufficiency for determining the feasibility of dose reconstruction. The 

feasibility evaluation presupposes that data pedigree issues have been settled. 

7.1.1 Internal Monitoring Data Pedigree Review

ATTRIBUTION: Section 7.1.1 was completed by Eugene Potter, Mel Chew & Associates; and Ed 

Scalsky, Oak Ridge Associated Universities (ORAU). These conclusions were peer-reviewed by the 

individuals listed on the cover page. The rationales for all conclusions in this document are explained 

in the associated text.

NIOSH did not locate any bioassay monitoring data for the period under evaluation. Therefore, an 

internal monitoring data sufficiency and pedigree evaluation is not possible for the internal monitoring 

data type.

The air sampling and survey data from the MED/AEC are contained in original reports, and are 

therefore primary data sources, as are the survey results reported by ANL in 1981. Therefore, no 

additional pedigree review was performed for those data. 

Air samples were taken on six occasions from July 24, 1943 to November 16, 1944 during the 

uranium production runs. However, during the research and development work (1944-1954), air 

sample results were only recovered for one small thorium run and those results were reported in 

“counts” with no conversion factor to activity. No results were found for the bulk of the operations 

during this period. Because of the nature of research and development work, no conclusion could be 

drawn about the representativeness of the single thorium sample for the operational period at the site. 

During the residual period, information is also lacking. All indications are that the residual 

contamination was at background levels for all but a single smear measurement from a die that had 

been used during uranium operations. However, the possibility exists that the survey data were not 

representative of all areas of the site. Because ventilation improvements were made throughout the 

production period, and the amount of material processed during the research and development period 

was smaller relative to the uranium operations, the worst-case air contamination conditions are 

known. 
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7.1.2 External Monitoring Data Pedigree Review

ATTRIBUTION: Section 7.1.2 was completed by Ray Clark and Ed Scalsky, Oak Ridge Associated 

Universities (ORAU). These conclusions were peer-reviewed by the individuals listed on the cover 

page. The rationales for all conclusions in this document are explained in the associated text.

NIOSH did not locate any external monitoring data for the operational period under evaluation (July 

24, 1943 through December 31, 1954). Therefore, a data sufficiency and pedigree evaluation is not 

possible for this data type for this period. 

NIOSH has identified limited data for the residual period (January 1, 1955 through December 31, 

1984). These data are the results of a survey performed by ANL in 1981 (ANL, 1981). This was the 

original report and no additional pedigree review was performed. 

There were several uranium air samples and one thorium air sample taken during the operational 

period. NIOSH has concluded that using the maximum air sample result, determining the surface 

contamination and resultant re-suspended air concentration would be sufficient for bounding the 

external dose during the residual period. 

7.2 Evaluation of Bounding Internal Radiation Doses at Revere

ATTRIBUTION: Section 7.2 and its related subsections were completed by Eugene Potter, Mel Chew 

& Associates. These conclusions were peer-reviewed by the individuals listed on the cover page. The 

rationales for all conclusions in this document are explained in the associated text. 

The principal source of internal radiation doses for members of the class under evaluation was the 

potential inhalation and ingestion of airborne natural uranium and thorium by employees directly 

involved in the extrusion, quenching, straightening, and cutting of the materials. Other employees 

were potentially exposed to the re-suspension of contamination on surfaces during the course of their 

work with non-radioactive materials. The following subsections address the ability to bound internal 

doses, methods for bounding doses, and the feasibility of internal dose reconstruction. 

7.2.1 Evaluation of Bounding Process-Related Internal Doses 

Because NIOSH did not locate urinalysis or other bioassay monitoring data for the period under 

evaluation, internal exposure must be determined based on radiological source term and area 

monitoring data. Workers not directly involved in the extrusion operations were potentially exposed 

to the re-suspension of contamination that may have been incompletely removed following radioactive 

material operations performed primarily during off-shift hours or weekends. 

The following subsections summarize the extent and limitations of information available for 

reconstructing the process-related internal doses of members of the class under evaluation. 
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7.2.1.1 Airborne Levels

Early in the operational period, air samples were taken on six occasions during uranium extrusions 

(see Section 6.1). The air samples were not consistently taken in the same areas; furthermore, 

information is lacking on the relationship of the sample locations to the areas occupied by workers. 

Initially, the air concentrations were quite high (up to 22 times the “tolerance” value of 150 μg U/m3). 

Gradually, ventilation improvements were made, but sample results still remained above the tolerance 

level. 

During non-MED work, the workers would have been potentially exposed to re-suspended uranium 

from incompletely-decontaminated surfaces. Workers directly involved in MED extrusions generally 

wore respirators (Cantril, 1944); however, respirators were probably not required during non-MED 

work when re-suspension could have produced exposures. 

As indicated in Section 5.1, the “development” period did not involve production-level quantities. In 

a 1989 letter to the Mayor of Detroit, DOE stated: “...the contract with AEC included extruding small 

amounts of uranium and thorium for research purposes...” (DuPont, 1945; Fiore, 1989). However, 

the exact workload data for this period has not been located. A number of references to the uranium 

or thorium work were located (Fisher, 1954; Hayes, 1952; Kattner, 1947a; Kattner 1947b; Kattner, 

1947c; Mecherey, 1947; Montenyohl, 1952; Schumar, 1946; Schumar, 1947; Various Authors, 1949-

1952). This information seems to indicate that the development work was occasional and probably 

did not exceed two days per month during this period. The only available operational air samples 

were from one of the thorium operations and were well below tolerance levels (see Table 6-2). These

results may or may not have been typical of the other MED/AEC operations given that the work was 

developmental and each operation could have presented unique exposure conditions. A single 

uranium air sample was taken in 1949 as a follow-up to suspected alpha contamination (Various 

Authors, 1949-1952); however, this sample was not taken during the performance of AEC extrusion 

operations. 

NIOSH has identified methods in Battelle-TBD-6000 to support bounding internal uranium dose for 

the type of metal work performed during the operational period at Revere Copper and Brass. 

However, NIOSH has not identified sufficient information or data to support bounding the thorium 

exposures for the operational period. 

In light of the above information, NIOSH has concluded that sufficient data are not available to 

estimate a bounding internal dose for the operations period from July 1943 through December 1954. 

7.2.2 Evaluation of Bounding Residual Period Internal Doses

During the residual period, January 1, 1955 to December 31, 1984, workers were potentially exposed 

to re-suspended uranium and thorium contamination. Worst-case residual period air concentrations 

can be based on the available data for the uranium production work early in the operational period. 

The data in Table 6-1 show that ventilation improved with time and that the air concentrations were 

reduced. The workload during research and development was much smaller. Techniques are 

available to determine bounding residual period intakes from airborne contamination. Therefore, 

there is sufficient information to support bounding internal dose during the residual period. 
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7.2.3 Methods for Bounding Internal Dose at Revere

7.2.3.1 Methods for Bounding Operational Period Internal Dose

Based on the evaluation in Section 7.2.1, a limited amount of airborne sample results are the only 

available data for bounding internal dose during the operational period. Battelle-TBD-6000 provides 

methods for bounding internal uranium dose for the type of metal work performed during the 

operational period at Revere Copper and Brass; however, NIOSH has found the available data 

insufficient to bound internal thorium dose. 

7.2.3.2 Methods for Bounding Residual Period Internal Dose 

Internal dose estimates for the residual period (January 1, 1955 through December 31, 1984) were 

based on inhalation and ingestion resulting from re-suspension of residual contamination from 

uranium and thorium extrusion operations. This would include re-suspension from incidental removal 

of residual contamination (e.g., via housekeeping and personnel and equipment movement). Intakes 

from the residual period can be bounded using the available data and the methods provided in 

Battelle-TBD-6000 and ORAUT-OTIB-0070. Battelle-TBD-6000 uses a default assumption for the 

initial air concentration at the start of the residual period. This Revere assessment used the 

site-specific maximum available air contamination value during the operational period of (3300 μg/m3

on August 21, 1943). The concentrations of uranium and Th-232 at the start of the residual period 

were each assumed to be equal to this value. This assumption is conservative because improvements 

were made to the ventilation system during uranium production operations. For example, the uranium 

concentration measured at the extrusion operator’s position on February 5, 1944 was 1650 μg/m3

, half 

of what is being employed in this current calculation. While the amount of uranium and thorium 

processed during research and development activities is not known, the amount is known to be 

considerably less than the multi-ton quantities of uranium initially processed during the operations 

period. The airborne activities of natural uranium and Th-232 at the start of the residual period were 

calculated by multiplying 3300 μg/m3 by their specific activities (0.683 pCi/μg for uranium; 0.109 

pCi/μg for Th-232) (Rad Handbook, 1970). 

In order to determine a surface contamination level, an indoor settling velocity of 7.5 x 10-4 m/s was 

applied over a one-year operating period. Settling was assumed to occur 20 hours per day for 250 

operating days. The result is an estimated surface contamination of 3.05 E7 pCi/m2 of uranium and 

4.86 E6 pCi/m2 of Th-232. A re-suspension factor of 1 x 10-6/m was applied to the surface 

contamination level to obtain an estimated airborne concentration of 30.5 pCi/m3 for uranium and 4.86 

pCi/m3 for Th-232. A respiration rate of 12 m3 per 10-hour day was applied to calculate the daily 

intake rates. These rates were normalized to 365 days (250 pCi/d for uranium; 40 pCi/d for Th-232) 

for the first year of the residual period. The Ra-228 and Th-228 daughters were assumed to be in 

equilibrium with Th-232; equal intake rates were assigned to them. 

A total alpha air concentration value (uranium, Th-232, and Th-228) was calculated for the start of the 

residual period. The calculated value, 89 dpm/m3, compares favorably with the alpha air 

concentration of 0.9 dpm/m3

 measured in 1949. This measurement was made during the operational 

period, but when AEC operations were not taking place. Thus, NIOSH is confident that the air 

concentrations at the start of the residual period were not higher than the model employed for this 

evaluation. Exposure will be evaluated on a case-by-case basis for individual claims, but the available 
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data and methods described here support NIOSH’s ability to bound internal dose for the evaluated 

class during the site’s residual period. 

The daily intake is based on source term data from large-scale operations and is likely to be 

significantly higher than intakes encountered at Revere at the start of the residual period. In order to 

account for the continued depletion of the operational source term during the residual period, two 

methods were considered, as discussed below. 

Method 1: A source term depletion of 1% of the surface activity per day is assumed to occur during 

the first year (1955); the resulting adjustment of 0.03 is applied for the second year (1956). Likewise,

a source term depletion of 1% of the surface activity per day is assumed to occur during the second 

year, and the resulting adjustment of 0.0007 is applied to the third year (1957). For the remainder of 

the residual period, the source term is assumed to remain constant (ORAUT-OTIB-0070, Table 3-1). 

Table 7-1 shows the adjustments used in this method to account for the depletion of the source term 

during the residual period and the resulting intake rates. 

Table 7-1: Source Term Depletion Adjustments for the Revere Residual Period (1% Per Day)

Year Depletion

Adjustment

U-Natural

Intake (pCi/d)

Th-232

Intake (pCi/d)

Ra-228

Intake (pCi/d)

Th-228

Intake (pCi/d)

1955 1 250 40 40 40

1956 0.03 7.5 1.2 1.2 1.2

1957 – 1984 0.0007 0.18 0.028 0.028 0.028

Method 2: A notional exponential depletion constant was calculated to account for the reduction in the 

source term. In the deposition scenario previously described, the alpha surface contamination at the 

start of the residual period was calculated to be approximately 893,000 dpm/100 cm2 (uranium, 

Th-232, and Th-228). This is clearly an overestimate. The alpha surface contamination measured in 

1981 was background. The background of the alpha instrument used was 50 cpm (see Table 6-4). 

The probe area would have been either 325 cm2 (floor probe) or 51 cm2 (wall probe). The conversion 

factor from cpm to dpm was approximately 5.9 according to a survey performed by the same Argonne 

National Laboratory team at another site in 1978 (Argonne, 1982). Using the favorable probe size (51 

cm2

), a potential alpha surface contamination of approximately 580 dpm/100 cm2 was calculated. 

From the two alpha surface contamination levels (893,000 and 580 dpm/100 cm2), a depletion 

constant of approximately 0.28 yr-1 and a depletion half-time of approximately 2.5 years were 

calculated based on the delay time of 9,608 days (January 1, 1955 to April 22, 1981). Table 7-2 

shows the adjustments used in this method to account for the depletion of the source term during the 

residual period and the resulting intake rates. This method is recommended for use since it is 

generally more favorable to claimants. Since the intake rate calculated by this method is less for 

1982-1984, it is favorable to use a depletion adjustment of 0.0007 for these years in accordance with 

the first method.
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Table 7-2: Source Term Depletion Adjustments for the Revere Residual Period (Exponential)

Year Depletion

Adjustment

U-Natural

Intake (pCi/d)

Th-232

Intake (pCi/d)

Ra-228

Intake (pCi/d)

Th-228

Intake (pCi/d)

1955 1.0 250 40 40 40

1956 0.76 189 30 30 30

1957 0.57 143 23 23 23

1958 0.43 108 17 17 17

1959 0.33 82 13 13 13

1960 0.25 62 10 10 10

1961 0.19 47 7.5 7.5 7.5

1962 0.14 36 5.7 5.7 5.7

1963 0.11 27 4.3 4.3 4.3

1964 0.081 20 3.3 3.3 3.3

1965 0.062 15 2.5 2.5 2.5

1966 0.047 12 1.9 1.9 1.9

1967 0.035 8.8 1.4 1.4 1.4

1968 0.027 6.7 1.1 1.1 1.1

1969 0.020 5.0 0.8 0.8 0.8

1970 0.015 3.8 0.6 0.6 0.6

1971 0.012 2.9 0.46 0.46 0.46

1972 0.0087 2.2 0.35 0.35 0.35

1973 0.0066 1.7 0.26 0.26 0.26

1974 0.0050 1.3 0.20 0.20 0.20

1975 0.0038 0.95 0.15 0.15 0.15

1976 0.0029 0.72 0.11 0.11 0.11

1977 0.0022 0.54 0.087 0.087 0.087

1978 0.0016 0.41 0.066 0.066 0.066

1979 0.0012 0.31 0.050 0.050 0.050

1980 0.00094 0.23 0.038 0.038 0.038

1981 0.00071 0.18 0.028 0.028 0.028

1982* 0.00054* 0.13* 0.022* 0.022* 0.022* 

1983* 0.00041* 0.10* 0.016* 0.016* 0.016* 

1984* 0.00031* 0.077* 0.012* 0.012* 0.012* 

* The intake rate calculated by the exponential method results in lower values for 1982-1984; therefore, it is favorable to 

use a depletion adjustment of 0.0007 for these years in accordance with the 1% per day depletion method.

 

Ingestion intakes can be calculated by applying the methodology present in Estimation of Ingestion 

Intakes, OCAS-TIB-009. The resulting daily intake values from both inhalation and ingestion are 

assumed to be the geometric means of lognormal distributions with a GSD of 5 (Battelle-TBD-6000). 
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7.2.4 Internal Dose Reconstruction Feasibility Conclusion 

Although there are methods available to NIOSH in Battelle-TBD-6000 to support bounding internal 

uranium dose for the operational period at Revere Copper and Brass, NIOSH has not identified 

sufficient information or data to support bounding the thorium exposures for the operational period. 

Based on lack of bioassay or other monitoring data for Revere workers, this evaluation concludes that 

internal dose reconstruction for the Revere operational period is not feasible; however, the internal 

dose for the residual period can be bounded using the available data and other parameters from 

Battelle-TBD-6000 and the methodologies discussed in ORAUT-OTIB-0070. 

Although NIOSH found that it is not possible to completely reconstruct internal radiation doses for the 

period from July 24, 1943 through December 31, 1954, NIOSH intends to use any internal monitoring 

data that may become available for an individual claim or any area monitoring data (that can be 

interpreted using existing NIOSH dose reconstruction processes or procedures) to support partial dose 

reconstructions for the operational period at the site. Dose reconstructions for individuals employed at 

Revere Copper and Brass during the period from July 24, 1943 through December 31, 1954, but who 

do not qualify for inclusion in the SEC, may be performed using these data as appropriate.

7.3 Evaluation of Bounding External Radiation Doses at Revere

ATTRIBUTION: Section 7.3 and its related subsections were completed by Ray Clark and Ed Scalsky, 

Oak Ridge Associated Universities (ORAU). These conclusions were peer-reviewed by the individuals 

listed on the cover page. The rationales for all conclusions in this document are explained in the 

associated text.

The principal source of external radiation doses, other than medical X-rays, for members of the 

proposed class was exposure to gamma and beta radiation associated with handling and working in 

proximity to uranium and uranium compounds. Additionally, thorium rods were extruded 

intermittently between 1946 (Mecherey, 1947) and 1954, which would result in exposure to thorium 

during that period (Fisher, 1954; Various Authors, 1949-1952).

Documentation available to NIOSH indicates that the extrusion of thorium was done on an 

experimental basis and appears to have consisted of smaller quantities (as compared to the production 

quantities of uranium). One example is the extrusion of three bare and/or unsheathed thorium billets 

on November 5-6, 1952 (Various Authors, 1949-1952). Radionuclides of interest include Th-232 and 

its decay progeny (e.g., Ra-224, Ac-228, Th-228, Bi-212, and Tl-208). As indicated, thorium was 

extruded on an intermittent basis until 1954 and the amount extruded is not known (see Section 

5.2.1.2). Through a review of available documentation, NIOSH identified air sample collections in 

November 1952 specifically conducted to detect the presence of thorium. 

The following subsections address the ability to bound external doses, methods for bounding doses, 

and the feasibility of external dose reconstruction. 
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7.3.1 Evaluation of Bounding Process-Related External Doses

NIOSH has not identified any external monitoring records or personal dosimetry data associated with 

the uranium and thorium processing conducted during the period under evaluation. This was a unique 

project for which there were no operational logs, minimal descriptions of activities, and little 

corresponding radiological data. The sources of exposure at Revere were the beta, gamma, and X-ray 

radiation from the uranium, thorium, and their oxides. NIOSH has not identified any radiological 

surveys during the period under evaluation. However, NIOSH has identified several gross alpha air 

monitoring results from 1943, 1949, 1950, and 1952, along with several smear survey results (see 

Table 6.1) (AEC, 1949-1961; AEC, 1950; AEC, 1952; Cantril, 1944; Quigley, 1943; Various Authors, 

1949-1952). No other area monitoring data have been identified. 

NIOSH has identified methods in Battelle-TBD-6000 to support bounding external uranium dose for 

the type of metal work performed during the operational period at Revere Copper and Brass. 

However, NIOSH has not identified sufficient information or data to support bounding the external 

exposures associated with the thorium work during the operational period. 

In light of the above information, NIOSH has concluded that sufficient data are not available to 

estimate a bounding external dose for the operational period from July 1943 through December 1954. 

7.3.2 Evaluation of Bounding Residual Period External Doses 

With the exception of the radiological survey performed by ANL in 1981, and a cursory survey in 

1989 when the buildings were demolished, there were no other surveys conducted during the residual 

period. NIOSH has not identified any external dosimeter results during this period. Nevertheless, 

personnel were subjected to direct external exposure from surface radioactive contamination and to 

submersion in contaminated air as a result of re-suspension of surface contamination. Using the air 

contamination data obtained during the operational period and the methods in Battelle-TBD-6000, 

there are sufficient data and methods to support bounding the external dose during the residual period. 

7.3.3 Revere Occupational X-Ray Examinations 

Documents indicate that all new employees received physical exams prior to the start of work. In 

addition, “. . . urinalysis, blood tests, and X-rays of the chest” were included (Cantril, 1944; Perry, 

1943, pdf pp. 6-7). To date, NIOSH has found no records of the X-rays, the X-ray machine 

parameters used, or any indication that follow-up X-ray examinations were performed.

Occupational X-ray examinations were performed every six months during the operational period 

(Cantril, 1944). Medical dose for Revere workers can likely be bounded by using the assumptions in 

the complex-wide Technical Information Bulletin, Dose Reconstruction from Occupationally Related

Diagnostic X-Ray Procedures (ORAUT-OTIB-0006). 
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7.3.4 Methods for Bounding External Dose at Revere

Except for medical X-ray dose, NIOSH has determined that external doses for the Revere operational 

period from July 1, 1943 through December 31, 1954 cannot be bounded. NIOSH has determined that 

external dose can be bounded during the residual period (January 1, 1955 through December 31, 

1984). The following subsections address the ability to bound the external dose for the Revere site. 

7.3.4.1 Methods for Bounding Operational Period External Dose

NIOSH has not identified any external monitoring records or personal dosimetry data associated with 

the uranium and thorium processing conducted during the period under evaluation. This was a unique 

project for which there were no operational logs, minimal descriptions of activities, and little 

corresponding radiological data. Other than several gross alpha air monitoring and smear results, no 

other area monitoring data have been identified. Therefore, NIOSH has concluded that external doses 

for the operational period of July 1, 1943 through December 31, 1954 for Revere cannot be bounded. 

Pre-employment chest X-rays were required for Revere workers (Perry, 1943). ORAUT-OTIB-0006 

provides information and guidance for reconstructing doses for the early years for which specific data 

are unavailable. NIOSH believes this methodology supports its ability to bound occupational medical 

X-ray doses for the class under evaluation. 

7.3.4.2 Methods for Bounding Residual Period External Doses

External dose estimates for the residual period are based on exposure to direct radiation from residual 

surface contamination and submersion in contaminated air resulting from re-suspension of surface 

contamination from previous operations. The external dose caused by residual contamination can be 

bounded by determining the surface contamination using the maximum air sample results recorded 

during operations at the beginning of the residual period. 

NIOSH employed two methods for determining external dose from contamination during the residual 

period, as described below. 

Method 1: Employing the methodology in Battelle-TBD-6000, the Revere analysis uses the maximum 

air concentration from the available operational air sample results in Table 6-1 (i.e., 3300 μg/m3

). It is 

assumed that this air concentration exists at the beginning of the residual period and consists of 

uranium and Th-232 in equal amounts. Battelle-TBD-6000 provides a method for determining the 

surface contamination for uranium and thorium and their progeny and for the re-suspension of that 

surface contamination. NIOSH is aware that, in some cases, equilibrium cannot be attained; this only 

ensures that the final estimate is indeed bounding. 

The assumptions used in the Revere assessment consist of a settling velocity of 7.5 x 10-4 m-s

-1 for 20 

hours per day for one year, and a re-suspension factor of 1 x 10-6/m. Specific activity is given as 1.52 

dpm/μg for natural uranium and 0.242 dpm/μg for Th-232. Applying these factors results in surface 

contamination levels of 6.77 x 107 dpm/m2 (3.05 x 107 pCi/m2) for uranium and 1.08 x 107 dpm/m2

(4.86 x 106 pci/m2

) for Th-232. To determine the submersion dose, the values for the air concentration 

after applying the re-suspension factor of 1 x 10-6/m are 30.5 pCi/m3 for uranium and 4.86 pCi/m3 for

thorium. Assuming the Th-232 and progeny are in equilibrium (see Table 5-3), and using the dose 
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conversion factors in External Exposure to Radionuclides in Air, Water, and Soil (Federal Guidance

No. 12, 1993), the external dose due to surface contamination and the submersion dose resulting from 

re-suspension can be determined. 

ORAUT-OTIB-0070 discusses depletion of the source term during a residual period and suggests a 

depletion factor of 1% of the surface activity per day. This 1% depletion per day results in a depletion 

adjustment of 1 for the first year, 0.03 for the second year, and 0.0007 for the third year, after which 

the values remain constant. These adjustments can be applied in order to maintain calculation

consistency within this evaluation report; however, such application is unnecessary since the resulting 

external dose estimate would still be bounding. 

Table 7-3 shows the daily doses for a 10-hour workday that Revere personnel would receive from 

direct radiation from residual contamination for each year over the residual period for the class under 

evaluation. 

Submersion doses are not presented because they are over a factor of 1000 lower than for direct 

radiation

Table 7-3: Revere Residual Period Daily Effective Dose (1% Per Day)

(based on a 10-hour workday)

Residual Year(s) Depletion

Factor

Uranium Total 

Including Progeny 

(mrem/d)

Thorium Total 

Including Progeny

(mrem/d)

1955 1 1.02 2.65

1956 0.03 0.0263 0.0681

1957-1984 0.0007 0.0190 0.0491

Method 2: A second method was developed using the maximum contamination levels at the beginning 

of the residual period, the contamination levels provided by ANL in 1981, and correction factors 

provided by ANL in a report on a survey conducted at another site in 1978 (Argonne, 1982) 

As discussed in Section 7.2.3.2, Methods for Bounding Residual Period Internal Dose, a theoretical 

exponential depletion constant was calculated to account for the depletion of the source term during 

the period from 1955 through 1981. For the 1982, 1983, and 1984, the values from Method 1 in that 

section were used since they provide higher dose rates.

As noted previously, ANL performed a survey at another site in 1978 (Argonne, 1982) using the same 

instrumentation employed for their 1981 Revere survey. In its 1982 survey report, ANL provided 

various correction factors for the probes (with a window area of either 325 cm2 or 51 cm2) used in 

their 1978 survey. For consistency and simplicity, the depletion factor used for determining the 

internal intake calculations were also used for the external dose rate calculations.

The results of the dose rate calculations are presented in Table 7-4. These values incorporate the dose 

conversion factors for the uranium and thorium progeny provided in External Exposure to 

Radionuclides in Air, Water, and Soil (Federal Guidance No. 12, 1993). 
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Table 7-4: Residual Period Daily Dose Rates Due to Uranium and Thorium (Exponential)

Year Depletion

Factor

Uranium Total 

(mrem/day)

Thorium Total

mrem/day

Total dose

mrem/day

1955 1.000 1.02 2.65 3.67

1956 0.76 0.772 2.05 2.82

1957 0.57 0.584 1.55 2.13

1958 0.43 0.442 1.17 1.61

1959 0.33 0.335 0.886 1.22

1960 0.25 0.253 0.671 0.924

1961 0.19 0.192 0.508 0.699

1962 0.14 0.145 0.384 0.529

1963 0.11 0.110 0.291 0.400

1964 0.081 0.0830 0.220 0.303

1965 0.062 0.0628 0.166 0.229

1966 0.047 0.0475 0.126 0.173

1967 0.035 0.0360 0.0953 0.131

1968 0.027 0.0272 0.0721 0.0993

1969 0.020 0.0206 0.0545 0.0751

1970 0.015 0.0156 0.0413 0.0569

1971 0.012 0.0118 0.0312 0.0430

1972 0.0087 0.00892 0.0236 0.0326

1973 0.0066 0.00675 0.0179 0.0246

1974 0.0050 0.00511 0.0135 0.0186

1975 0.0038 0.00387 0.0102 0.0141

1976 0.0029 0.00293 0.00775 0.0107

1977 0.0022 0.00221 0.00586 0.00808

1978 0.0016 0.00167 0.00444 0.00611

1979 0.0012 0.00127 0.00336 0.00462

1980 0.00094 0.000959 0.00254 0.00350

1981 0.00071 0.000726 0.00192 0.00265

1982* 0.00054* 0.000549* 0.00145* 0.00200* 

1983* 0.00041* 0.000415* 0.00110* 0.00152* 

1984* 0.00031* 0.000314* 0.000833* 0.00115* 

* The dose rate calculated by the exponential method results in lower values for 1982-1984; therefore, it is favorable to 

use a depletion adjustment of 0.0007 for these years in accordance with the 1% per day depletion method.
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7.3.5 External Dose Reconstruction Feasibility Conclusion 

Although there are methods available to NIOSH in Battelle-TBD-6000 to support bounding external 

uranium dose for the operational period at Revere Copper and Brass, NIOSH has not identified 

sufficient information or data to support bounding the thorium exposures for the operational period. 

During this period, NIOSH was unable to determine a worker’s actual work locations or whether a 

worker was restricted to one location. Workers may have been able to move about freely; therefore, 

all workers’ exposures will be treated similarly. Therefore, except for medical X-ray dose, NIOSH 

has determined that reconstruction of external doses for Revere workers is not feasible for the 

operational period from July 1, 1943 through December 31, 1954. 

NIOSH has determined that reconstruction of external doses is feasible for the residual period from 

January 1, 1955 through December 31, 1984 using the assumptions and approaches presented within 

the preceding section of this report. 

Although NIOSH found that it is not possible to completely reconstruct external radiation doses for 

the period from July 24, 1943 through December 31, 1954, NIOSH intends to use any external 

monitoring data that may become available for an individual claim or any area monitoring data (that 

can be interpreted using existing NIOSH dose reconstruction processes or procedures) to support 

partial dose reconstructions for the operational period at the site. Dose reconstructions for individuals 

employed at Revere Copper and Brass during the period from July 24, 1943 through December 31, 

1954, but who do not qualify for inclusion in the SEC, may be performed using these data as 

appropriate. 

7.4 Evaluation of Petition Basis for SEC-00164

ATTRIBUTION: Section 7.4 was completed by Ed Scalsky, Oak Ridge Associated Universities 

(ORAU). These conclusions were peer-reviewed by the individuals listed on the cover page. The 

rationales for all conclusions in this document are explained in the associated text. 

The following assertion was made on behalf of petition SEC-00164 for the Revere site: 

SEC-00164: The petitioner stated that, to the best of his knowledge, Revere Copper and Brass 

never used any type of monitoring device to detect radiation at the facility. 

NIOSH determined that it has access to only a limited number of air sample and smear survey results 

for Revere during the time period under evaluation. Medical records, bioassay data, and external 

monitoring results are not available. NIOSH has concluded that the available information is 

insufficient bound the internal and external dose for the Revere operational period; however, the 

internal dose for the residual period can be bounded using the available data and other parameters as 

discussed within this evaluation report. 
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7.5 Summary of Feasibility Findings for Petition SEC-00164

This report evaluates the feasibility for completing dose reconstructions for employees at Revere 

Copper and Brass from July 24, 1943 through December 31, 1954 (operations) and from January 1, 

1955 through December 31, 1984 (residual period). NIOSH found that the available monitoring 

records, process descriptions and source term data available are not sufficient to complete dose 

reconstructions for the operations period. Doses for the residual period can be bounded. 

Table 7-5 summarizes the results of the feasibility findings at Revere Copper and Brass for each 

exposure source during the time period July 24, 1943 through December 31, 1954 (operations) and 

from January 1, 1955 through December 31, 1984 (residual period). 

Table 7-5: Summary of Feasibility Findings for SEC-00164

July 24, 1943 through December 31, 1954 (operations); 

January 1, 1955 through December 31, 1984 (residual period)

Source of Exposure

July 24, 1943 through December 

31, 1954 (operations)

January 1, 1955 through December 

31, 1984 (residual period)

Reconstruction 

Feasible

Reconstruction 

Not Feasible1

Reconstruction 

Feasible2

Reconstruction 

Not Feasible

Internal X X 

 - Uranium X X 

 - Thorium X X 

External X X 

 - Gamma X X 

 - Beta X X 

 - Neutron X N/A

 - Occupational Medical X-ray X X 

1 NIOSH has identified methods to support bounding internal uranium dose for the type of metal work performed 

during the operational period at Revere Copper and Brass. However, NIOSH has not identified sufficient 

information or data to support bounding the thorium exposures for the operational period.

2 Exposures will be evaluated on a case-by-case basis for individual claims, but the method described here supports

NIOSH’s ability to bound the dose for the evaluated class during the site’s residual period.

As of May 25, 2010, a total of eight claims have been submitted to NIOSH for individuals who 

worked at Revere Copper and Brass and are covered by the class definition evaluated in this report. 

Dose reconstructions have been completed for eight individuals (100%). 
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Although NIOSH found that it is not possible to completely reconstruct radiation doses for the 

proposed class, NIOSH intends to use any internal and external monitoring data that may become 

available for an individual claim (and that can be interpreted using existing NIOSH dose 

reconstruction processes or procedures) for the purpose of partial dose reconstructions. Therefore, 

dose reconstructions for individuals employed at Revere Copper and Brass during the period from 

July 24, 1943 through December 31, 1954 (operations) and from January 1, 1955 through December 

31, 1984 (residual period), but who do not qualify for inclusion in the SEC, may be performed using 

these data as appropriate.

8.0 Evaluation of Health Endangerment for Petition SEC-00164

The health endangerment determination for the class of employees covered by this evaluation report is 

governed by both EEOICPA and 42 C.F.R. § 83.13(c)(3). Under these requirements, if it is not 

feasible to estimate with sufficient accuracy radiation doses for members of the class, NIOSH must 

also determine that there is a reasonable likelihood that such radiation doses may have endangered the 

health of members of the class. Section 83.13 requires NIOSH to assume that any duration of 

unprotected exposure may have endangered the health of members of a class when it has been 

established that the class may have been exposed to radiation during a discrete incident likely to have 

involved levels of exposure similarly high to those occurring during nuclear criticality incidents. If 

the occurrence of such an exceptionally high-level exposure has not been established, then NIOSH is 

required to specify that health was endangered for those workers who were employed for a number of 

work days aggregating at least 250 work days within the parameters established for the class or in 

combination with work days within the parameters established for one or more other classes of 

employees in the SEC. 

Due to a lack of internal and external monitoring data, NIOSH’s evaluation determined that it is not 

feasible to estimate radiation dose for members of the NIOSH-evaluated class with sufficient accuracy

for the operations period (July 24, 1943 through December 31, 1954). Modification of the class 

definition regarding health endangerment and minimum required employment periods, therefore, is

required. For the residual period (January 1, 1955 through December 31, 1984), a health 

endangerment determination is not required because NIOSH has determined that it has an established 

methodology for estimating dose. 

9.0 Class Conclusion for Petition SEC-00164

Based on its full research of the class under evaluation, NIOSH has defined a single class of 

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSHproposed class to be added to the SEC includes all Atomic Weapons Employer employees who 

worked at Revere Copper and Brass, Detroit, Michigan from July 24, 1943 through December 31, 

1954, for a number of work days aggregating at least 250 work days, occurring either solely under this 

employment or in combination with work days within the parameters established for one or more 

other classes of employees included in the SEC. The class under evaluation was divided because 

although NIOSH has not obtained sufficient internal or external monitoring data for bounding doses 

during the operational period, NIOSH has a methodology for bounding doses for the residual period. 
SEC-00164 07-19-10 Revere Copper and Brass

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NIOSH has carefully reviewed all material sent in by the petitioner, including the specific assertions 

stated in the petition, and has responded herein (see Section 7.4). NIOSH has also reviewed available 

technical resources and many other references, including the Site Research Database (SRDB), for 

information relevant to SEC-00164. In addition, NIOSH reviewed its NOCTS dose reconstruction 

database to identify EEOICPA-related dose reconstructions that might provide information relevant to 

the petition evaluation. 

These actions are based on existing, approved NIOSH processes used in dose reconstruction for 

claims under EEOICPA. NIOSH’s guiding principle in conducting these dose reconstructions is to 

ensure that the assumptions used are fair, consistent, and well-grounded in the best available science. 

Simultaneously, uncertainties in the science and data must be handled to the advantage, rather than to 

the detriment, of the petitioners. When adequate personal dose monitoring information is not 

available, or is very limited, NIOSH may use the highest reasonably possible radiation dose, based on 

reliable science, documented experience, and relevant data to determine the feasibility of 

reconstructing the dose of an SEC petition class. NIOSH contends that it has complied with these 

standards of performance in determining the feasibility or infeasibility of reconstructing dose for the 

class under evaluation. 
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10.0 References 

42 C.F.R. pt. 81, Guidelines for Determining the Probability of Causation Under the Energy 

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

Register/Vol. 67, No. 85/Thursday, p 22,296; May 2, 2002; SRDB Ref ID: 19391 

42 C.F.R. pt. 82, Methods for Radiation Dose Reconstruction Under the Energy Employees 

Occupational Illness Compensation Program Act of 2000; Final Rule; May 2, 2002; SRDB Ref ID: 

19392 

42 C.F.R. pt. 83, Procedures for Designating Classes of Employees as Members of the Special 

Exposure Cohort Under the Energy Employees Occupational Illness Compensation Program Act of 

2000; Final Rule; May 28, 2004; SRDB Ref ID: 22001 

42 U.S.C. §§ 7384-7385 [EEOICPA], Energy Employees Occupational Illness Compensation 

Program Act of 2000, as amended

AEC, 1949-1961, Data Analysis Results, United States Atomic Energy Commission (AEC); Various 

Dates Between 1949-1961; SRDB Ref ID: 11451 

AEC, 1950, Air Dust and Smears, Revere Copper and Brass; United States Atomic Energy 

Commission (AEC); January 4, 1950; SRDB Ref ID: 10779 

AEC, 1952, Air Dust Samples, Revere Copper and Brass; United States Atomic Energy Commission 

(AEC); February 19, 1952; SRDB Ref ID: 10780 

ANL, 1981, Notes and Comments Regarding the Survey Conducted at Revere Copper and Brass, 

Detroit, Michigan; Argonne National Laboratory (ANL) Radiological Survey Group; April 1981; 

SRDB Ref ID: 80027 

Argonne, 1982, Formerly Utilized MED/AEC Sites Remedial Action Program, Radiological Survey of 

Universal Cyclops, Inc., Titusville Plant (Formerly Vulcan Crucible Steel Company), Aliquippa, 

Pennsylvania, May 2-8, 1978; Argonne National Laboratory, Radiological Survey Group; May 1982; 

SRDB 6325 

Battelle-TBD-6000, Site Profiles for Atomic Weapons Employers that Worked Uranium and Thorium 

Metals, Rev. F0; Battelle; December 13, 2006; SRDB Ref ID: 30671 

Battelle-TBD-6000, App. AS, Site Profiles for Atomic Weapons Employers that Worked Uranium and 

Thorium Metals, Appendix AS – Copperweld Steel Co., Rev. 0; Battelle; July 16, 2007; SRDB Ref ID: 

74751 

Bickerstaff, 1974, PFDL Special Procedure, Evaluation of Plutonium Release from Pressurized Fuel 

Pins, Revision 0; September 12, 1974; C.W. Bickerstaff; September 16, 1974; SRDB Ref ID: 62964 
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Cantril, 1944, Clinton Laboratory Subcontractors and Our Health Responsibility to Them; 

correspondence; S.T. Cantril, R.S. Stone; April 1, 1944; SRDB Ref ID: 11207, pdf pp. 3-6 

DOE, 1990, Formerly Utilized Sites Remedial Action Program, Elimination Report, Former Revere 

Copper and Brass Corporation; U.S. Department of Energy (DOE), Office of Environmental and 

Waste Management, Office of Environmental Restoration, Decontamination and Decommissioning 

Division; March 30, 1990; SRDB Ref ID: 80028 

DuPont, 1943, Furnace and Extrusion Log and Summary; E.I. DuPont de Nemours and Company 

(DuPont); September 1943; SRDB Ref ID: 80168 

DuPont, 1945, The Metal Fabrication Program for the Clinton Engineer Works and the Hanford 

Engineer Works Including the Dummy Slug Program and the Unbonded Slug Program – Project 

1553; E.I. DuPont de Nemours and Company, Incorporated, Engineering Department–Construction 

Division (DuPont); August 1945; SRDB Ref ID: 33190 

Federal Guidance No. 12., 1993, Federal Guidance Report No. 12: External Exposure to 

Radionuclides in Air, Water, and Soil, EPA-402-R-93-081; prepared for the Office of Radiation and 

Indoor Air, U.S. Environmental Protection Agency by K. F. Eckerman and J. C. Ryman of Oak Ridge 

National Laboratory; September 1993; SRDB Ref ID 11997

Fiore, 1989, Notification of Upcoming DOE Radiological Survey of Former Revere Copper and Brass 

Property, correspondence to Coleman A. Young; Fiore, A. Wallo; July 17, 1989; SRDB Ref ID: 

75275 

Fisher, 1954, Thorium Slugs from Extruded Rod; correspondence to P.J. Hagelston; R.E. Fisher; 

November 3, 1954; SRDB Ref ID: 42306 

Foote, 1944a, Confirmation of Extrusion Billet Shipment to Revere Copper and Brass, correspondence 

to J. Collins; Frank Foote; April 18, 1944; SRDB Ref ID: 81063 

Foote, 1944b, Confirmation of the Shipment of Two 100-Pound Billets, correspondence to J. Collins; 

Frank Foote; May 18, 1944; SRDB Ref ID: 81066 

Fuqua, 1944, Present Status of Special Health Hazards at Baker Bros., Toledo and at Revere Copper 

& Brass, Detroit; P.A. Fuqua, M.D.; May 13, 1944; SRDB Ref ID: 80176 

FUSRAP, 2000, FUSRAP Database Report, Site: MI.04, Revere Copper and Brass Co.; Formerly 

Utilized Sites Remedial Action Program (FUSRAP); website link: 

http://www.projectperformance.com/fusrap/report_action.asp; January 16, 2000; SRDB Ref ID: 

10762, pdf pp. 2, 5 

FUSRAP, 2010, FUSRAP Database Report, Site: MI.04, Revere Copper and Brass Co.; U.S. 

Department of Energy, Office of Legacy Management; FUSRAP Considered Sites; website link: 

http://www.lm.doe.gov/Considered_Sites/Revere_Copper_and_Brass_Co_-_MI_04/; March 29, 2010; 

SRDB Ref ID: 80169 
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Hadlock, 1944, Metal Requirements for X-10 Project; correspondence and billet requirement and 

production schedules; Canfield Hadlock; March 8, 1944; SRDB Ref ID: 71013 

Hanford Works, 1948, Hanford Works Monthly Report, March 1948; Hanford Works; April 26, 1948; 

SRDB Ref ID: 37587 

Hayes, 1952, Thorium; correspondence to J.C. Woodhouse; E.E. Hayes; August 8, 1952; SRDB Ref 

ID: 49612 

Hickson, 1944, In re: Visit to Revere Copper & Brass Co., Detroit, Michigan on 11-10-44; 

correspondence to G.H. Gehrman; J.J. Hickson; November 28, 1944; SRDB Ref ID: 80439 

Johnson, 1944, Revere Copper and Brass Company, Detroit, Michigan; correspondence written to Lt. 

Col. W.B. Parsons (District Engineer, Manhattan District); Lyall E. Johnson; December 29, 1944; 

SRDB Ref ID: 80183, pdf p. 2 

Kattner, 1947a, Alpha Extrusion at Revere Copper and Brass Company, Detroit, Michigan–September 

17 to 18, 1947; W. T. Kattner; September 29, 1947; SRDB Ref ID: 80137 

Kattner, 1947b, Alpha Extrusion at Revere Copper and Brass Company, Detroit, Michigan–October 

10, 1947; W. T. Kattner; October 22, 1947; SRDB Ref ID: 80138 

Kattner, 1947c, Alpha Extrusion at Revere Copper and Brass Company, Detroit, Michigan–November 

3, 1947; W. T. Kattner; November 14, 1947; SRDB Ref ID: 80139 

Kattner, 1947d, Characteristics of Uranium Rods Extruded in the Alpha Phase at Revere Copper and 

Brass, Detroit, Michigan – October 10, 1947, correspondence to T.W. Hauff; W.T. Kattner, E.A. 

Smith; December 2, 1947; SRDB Ref ID: 80158 

Kelley, 1949, Monthly Status and Progress Reports, monthly reports from 1949; W.E. Kelley; 1949; 

SRDB Ref ID: 6291 

Mecherey, 1947, Centerless Grinding of Thorium Rods; Robert Mecherey; January 21, 1947; SRDB 

Ref ID: 81068 

Montenyohl, 1952, Progress Report, Thorium Irradiation Program; V.I. Montenyohl; November 25, 

1952; SRDB Ref ID: 49629 

Nickson, 1944, Summary of Revere Visit and Plant Recommendations, correspondence to Dr. 

Gehrman; J.J. Nickson; November 2, 1944; SRDB Ref ID: 80440 

Norwood, 1943, Results of Revere Copper and Brass Workers’ Examinations and Air Samples, 

correspondence to H.M Todt; September 1943; SRDB Ref ID: 17357, pdf pp. 4-5, 9 

Norwood, 1944, Health Conditions in Various Industries Supplying Metal to Du Pont Co. Under 

Contract; correspondence to Stafford Warren; W.D. Norwood; March 20, 1944; SRDB Ref ID: 

11207, pdf p. 13 
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Noto, 1952, Thorium Fabrication; correspondence to G.W. Wensch and F.M. Belmore; A. Noto; 

November 10, 1952; SRDB Ref ID: 81071 

OCAS-PR-004, Internal Procedures for the Evaluation of Special Exposure Cohort Petitions, Rev. 0, 

National Institute for Occupational Safety and Health (NIOSH); Cincinnati, Ohio; September 23, 

2004; SRDB Ref ID: 32022 

OCAS-TIB-009, Estimation of Ingestion Intakes; Office of Compensation Analysis and Support; Rev. 

00; April 13, 2004; SRDB Ref ID: 22397 

ORAUT-OTIB-0004, Estimating the Maximum Plausible Dose to Workers at Atomic Weapons 

Employer Facilities, Rev. 03 PC-2; Oak Ridge Associated Universities; December 6, 2006; SRDB 

Ref ID: 29949

ORAUT-OTIB-0006, Dose Reconstruction from Occupationally Related Diagnostic X-Ray 

Procedures, Rev. 03 PC-1; Oak Ridge Associated Universities; December 21, 2005; SRDB Ref ID: 

20220 

ORAUT-OTIB-0070, Dose Reconstruction During Residual Radioactivity Periods at Atomic 

Weapons Employer Facilities, Rev. 00; Oak Ridge Associated Universities; March 10, 2008; SRDB 

Ref ID: 41603

ORAUT-TKBS-0006-2, Hanford Site – Site Description, Rev. 2; Oak Ridge Associated Universities; 

February 22, 2010; SRDB Ref ID: 79424 

Order Request and Shipping Receipt, 1944, Billet Order Request and Shipping Receipts for Shipments 

to Revere Copper and Brass Company; various dates in May 1944; SRDB Ref ID: 81064 

Perry, 1943, correspondence to U.S. War Department, District Engineer, Manhattan District; John L. 

Perry; August 17, 1943; SRDB Ref ID: 10782, pdf pp. 6-7 

Personal Communication, 2010a, Personal Communications with Former Lab Worker; Telephone 

Interviews by ORAU Team; April 13, 2010; SRDB Ref ID: 81007; follow-up call June 8, 2010: 

SRDB Ref ID: Not yet in SRDB

Personal Communication, 2010b, Personal Communications with Former Chemist; Telephone 

Interviews by ORAU Team; April 15, 2010; SRDB Ref ID: 81008; follow-up call June 8, 2010: 

SRDB Ref ID: Not yet in SRDB

Personal Communication, 2010c, Personal Communication with Former Tester; Telephone Interview 

by ORAU Team; April 16, 2010; SRDB Ref ID: 81009 

Personal Communication, 2010d, Personal Communications with Former Draftsman; Telephone 

Interviews by ORAU Team and NIOSH staff; April 14, 2010; SRDB Ref ID: 81010; follow-up call 

June 7, 2010: SRDB Ref ID: Not yet in SRDB
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Quigley, 1943, Revere Copper and Brass Worker Re-examinations, correspondence to H.M. Todt; 

J.A. Quigley; November 17, 1943; SRDB Ref ID: 17357, pdf p. 2 

Rad Handbook, 1970, Radiological Health Handbook, U.S. Department of Health, Education, and 

Welfare, Public Health Service; PHS-PUBL-2016; January 1970; SRDB Ref ID: 75017 

Rad Handbook, 1998, Handbook of Health Physics and Radiological Health, 3rd Edition, B. Shleien, 

L. A. Slaback, Jr., B. K. Birky, editors; 1998; SRDB Ref ID: 22737 (commonly available from public 

resources)

Schier, 1948, Trip Report-Revere Copper & Brass Co.-Detroit, Michigan, March 24 and 25, 1948; 

written correspondence to T.W. Hauff; R. J. Schier; April 7, 1948; SRDB Ref ID: 80195 

Schumar, 1946, Monthly Report; J. Schumar, C. Swanson; June 21, 1946; SRDB Ref ID: 80029 

Schumar, 1947, Extrusion Order Instructions, correspondence to A. R. Kaufman from J. F. Schumar; 

July 3, 1947; SRDB Ref ID: 81069 

Stannard, 1988, Radioactivity and Health: A History; J. Newell Stannard; October 1988; SRDB Ref 

ID: 22738, pdf p. 132 

Various Authors, 1949-1952, Health Hazards in Thorium Extrusion; correspondence on thorium 

extrusion at Revere Copper and Brass; various authors; various dates in 1949-1952; SRDB Ref ID: 

10773 

Wirth, 1945, Subcontractors for Clinton Laboratories, correspondence to John L. Ferry; J.E. Wirth; 

March 28, 1945; SRDB Ref ID: 12754 
SEC-00164 07-19-10 Revere Copper and Brass

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SEC-00164 07-19-10 Revere Copper and Brass

Page 55 of 64 

Attachment 1: Data Capture Synopsis

Table A1-1: Data Capture Synopsis for Revere Copper and Brass

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded to 

SRDB

Primary Site/Company Name: Revere Copper and Brass

BE 1946-1950; AWE 1943-1950s; Residual Radiation 

1960-1984 

Other Site Names: Revere Copper Products (Successor 

Company)

Revere Copper Products does not hold old Revere Copper and Brass 

records. Per the successor contact they most likely were destroyed.

05/05/2010 0 

Michigan State contacted A description of how Revere collected and handled machining scrap, 

trip reports, and the DOE's 1981 investigation into ownership of the 

site.

04/16/2010 6 

Chicago Federal Records Center No relevant data identified. 04/23/2010 0 

Dayton Federal Records Center No relevant data identified. 05/18/2010 0 

Department of Labor/Paragon 1954 AEC memos, including an order to ship thorium slugs from 

Revere to the FMPC.

12/30/2008 1 

DOE Argonne National Laboratory - East No relevant data identified. 05/07/2010 0 

DOE Environmental Measurements Laboratory records 

collection, now located at DOE Legacy Management - 

Grand Junction Office

New potential data source recently identified by DOE Headquarters. A 

data capture has been scheduled for the week of 06/07/2010.

OPEN 0 

DOE Germantown A summary AEC report identifying Revere as having processed thorium 

metal and the DOE's initial investigation into former thorium processing 

sites.

Unknown 2 

DOE Hanford New potential data source recently identified by NIOSH. A request for 

a search of Hanford's records databases was made on 05/19/2010.

OPEN 0 

DOE Legacy Management - Grand Junction Office Materials transfer and shipment reports, FUSRAP documents and 

correspondence, and FUSRAP elimination reports. 

05/01/2010 33

DOE Legacy Management - Morgantown Awaiting DOE Legacy Management response. OPEN 0 

DOE Office of Scientific and Technical Information A 1949 report regarding a beryllium extrusion test. 03/29/2010 1 

Hagley Museum (DuPont records repository) No relevant data identified. 05/10/2010 0 

Internet - DOE Comprehensive Epidemiologic Data 

Resource (CEDR)

No relevant data identified. 03/23/2010 0 
SEC-00164 07-19-10 Revere Copper and Brass

56 of 64 

Table A1-1: Data Capture Synopsis for Revere Copper and Brass

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded to 

SRDB

Internet - DOE Hanford Declassified Document Retrieval 

System (DDRS)

Hanford progress reports referring to extrusion runs at Revere, materials 

transfer and shipment reports, correspondence regarding Revere's status 

as a DuPont subcontractor. NOTE: 7 of the 16 Hanford DDRS 

documents were added to Revere by site association reviews and 9 

documents were chosen from the specific search of DDRS for 

documents pertaining to Revere.

03/23/2010 16

Internet - DOE OpenNet New York Operations Office progress reports, the medical program 

from the Manhattan District History, references to work at Revere in 

Linking Legacies, and Hanford's history of operations.

03/23/2010 7 

Internet - DOE OSTI Energy Citations No relevant data identified. 03/29/2010 0 

Internet - DOE OSTI Information Bridge Reports on aluminum flat plate bonded fuel jacket and beryllium 

extrusions at Revere.

03/23/2010 2 

Internet - Google Newspaper articles on contaminated atomic weapons employer sites, 

monthly reports, contract documentation, the FUSRAP Authority 

Review, a flat plate bonded fuel element progress report, and site 

description.

03/22/2010 17

Internet - National Academies Press (NAP) No relevant data identified. 03/23/2010 0 

Internet - National Nuclear Security Administration 

(NNSA) - Nevada Site Office

No relevant data identified. 03/23/2010 0 

Internet - NRC Agencywide Document Access and 

Management (ADAMS)

No relevant data identified. 03/23/2010 0 

Internet - Washington State University (U.S. Transuranium 

and Uranium Registries)

No relevant data identified. 03/23/2010 0 

Michigan State University No relevant data identified. 05/07/2010 0 

NARA Atlanta Materials transfer and shipment reports, accountability reports, a report 

outlining health measures at Revere, a health and safety inspection, and 

radiological surveys.

05/12/2010 29

NARA Chicago No relevant data identified. 04/23/2010 0 

New York State Department of Environmental 

Conservation

An order for the machining of thorium slugs at the FMPC from rods 

that had been extruded at Revere.

02/25/2008 1 

ORAU Team Project spreadsheet and documented communications with former 

Revere workers.

04/16/2010 5 

ORO Vault Medical examinations of Revere workers and surveys of airborne metal 

dust concentrations.

05/13/2004 1 

Savannah River Site Reports listing revere as the source for thorium slugs used in the 

Thorium Irradiation Program.

07/22/2008 2 
SEC-00164 07-19-10 Revere Copper and Brass

57 of 64 

Table A1-1: Data Capture Synopsis for Revere Copper and Brass

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded to 

SRDB

University of Detroit - Mercy No relevant data identified. 05/07/2010 0 

University of Michigan No relevant data identified. 05/07/2010 0 

Unknown New York Operations Office progress reports, beryllium studies, a 

discussion of the health hazards of thorium extrusion, a contamination 

investigation, a claim against Revere, airborne radioactivity surveys, 

and monthly thorium accountability reports.

07/09/2004 16

US Army Corps of Engineers, Buffalo District New potential data source recently identified by NIOSH. A data 

capture has been scheduled for the week of 06/21/2010.

OPEN 0 

Wayne State University No relevant data identified. 05/07/2010 0 

TOTAL 139

Table A1-2: Database Searches for Revere Copper and Brass

Database/Source Keywords / Phrases Hits Uploaded

DOE CEDR

http://cedr.lbl.gov/

COMPLETED 03/23/2010

"Revere Copper" 0 0 

DOE Hanford DDRS

http://www2.hanford.gov/declass/

COMPLETED 03/23/2010

"Revere Copper" 9 9 

DOE OpenNet

http://www.osti.gov/opennet/advancedsearch.jsp

COMPLETED 03/23/2010

"Revere Copper" 16 7 

DOE OSTI Energy Citations

http://www.osti.gov/energycitations/

COMPLETED 03/29/2010

"Revere Copper" 28 0 

DOE OSTI Information Bridge

http://www.osti.gov/bridge/advancedsearch.jsp

COMPLETED 03/23/2010

"Revere Copper" 21 2 
SEC-00164 07-19-10 Revere Copper and Brass

58 of 64 

Table A1-2: Database Searches for Revere Copper and Brass

Database/Source Keywords / Phrases Hits Uploaded

Google

http://www.google.com

COMPLETED 03/22/2010

"Revere Copper" "air count"

"Revere Copper" "air dust"

"Revere Copper" "air filter"

"Revere Copper" "airborne test"

"Revere Copper" "belgian congo ore"

"Revere Copper" "black oxide" "brown oxide" "green salt" "orange 

oxide" "yellow cake" UO2 UO3 UF4 UF6 C-216 C-616 C-65 C-211 

U3O8 "uranium extraction" "uranium dioxide" "uranium hexafluoride" 

"uranium tetrafluoride" "uranium trioxide"

"Revere Copper" "body burden"

"Revere Copper" "chest count"

"Revere Copper" "derived air concentration" DAC

"Revere Copper" "dose"

"Revere Copper" "Ether-Water Project"

"Revere Copper" "F machine"

"Revere Copper" "feed material"

"Revere Copper" "Formerly Utilized Sites Remedial Action Program" 

FUSRAP

"Revere Copper" "gas proportional"

"Revere Copper" "gaseous diffusion"

"Revere Copper" "highly enriched uranium" HEU

"Revere Copper" "in vitro"

"Revere Copper" "in vivo"

"Revere Copper" "isotopic enrichment"

"Revere Copper" "JS Project"

"Revere Copper" "K-65"

"Revere Copper" "liquid scintillation"

"Revere Copper" "low enriched uranium" LEU

"Revere Copper" "lung count"

"Revere Copper" "maximum permissible concentration" MPC

"Revere Copper" "mixed fission product" MFP

249,021 17
SEC-00164 07-19-10 Revere Copper and Brass

59 of 64 

Table A1-2: Database Searches for Revere Copper and Brass

Database/Source Keywords / Phrases Hits Uploaded

"Revere Copper" "nasal wipe"

"Revere Copper" "nose wipe"

"Revere Copper" "nuclear track emulsion type A" NTA

"Revere Copper" "occupational radiation exposure"

"Revere Copper" "operating standard" "processing standard"

"Revere Copper" "ore concentrate"

"Revere Copper" "PC Project"

"Revere Copper" "phosphate research"

"Revere Copper" "pocket ion chamber" PIC

"Revere Copper" "Radiological Survey Data Sheet" RSDS

"Revere Copper" "retention schedules"

"Revere Copper" "solvent extraction"

"Revere Copper" "sump cake"

"Revere Copper" "thermal diffusion"

"Revere Copper" "thermoluminescent dosimeter" TLD

"Revere Copper" "Tiger Team"

"Revere Copper" "tolerance dose"

"Revere Copper" "uranyl nitrate hexahydrate" UNH

"Revere Copper" "whole body count" WBC

"Revere Copper" "working level" WL

"Revere Copper" accident

"Revere Copper" alpha

"Revere Copper" americium Am241 Am-241 "Am 241" 241Am 241-

Am "241 Am"

"Revere Copper" beta

"Revere Copper" bioassay bio-assay

"Revere Copper" breath "breathing zone" BZ

"Revere Copper" calibration

"Revere Copper" columnation

"Revere Copper" contamination

"Revere Copper" curie

"Revere Copper" denitration "denitration pot"

"Revere Copper" derby regulus
SEC-00164 07-19-10 Revere Copper and Brass

60 of 64 

Table A1-2: Database Searches for Revere Copper and Brass

Database/Source Keywords / Phrases Hits Uploaded

"Revere Copper" dosimeter

"Revere Copper" dosimetric

"Revere Copper" dosimetry

"Revere Copper" electron

"Revere Copper" environment

"Revere Copper" exposure "exposure investigation" "radiation 

exposure"

"Revere Copper" external

"Revere Copper" fecal

"Revere Copper" femptocurie

"Revere Copper" film

"Revere Copper" fission

"Revere Copper" fluoroscopy

"Revere Copper" gamma-ray "gamma ray"

"Revere Copper" health "health instrument" "health physics" H.I. HI HP

"Revere Copper" hydrofluorination

"Revere Copper" incident

"Revere Copper" ingestion

"Revere Copper" inhalation

"Revere Copper" internal

"Revere Copper" investigation

"Revere Copper" ionium Th230 Th-230 "Th 230" 230Th 230-Th "230 

Th"

"Revere Copper" isotope

"Revere Copper" isotopic

"Revere Copper" Landauer

"Revere Copper" log "log sheet" "log book"

"Revere Copper" metallurgy
SEC-00164 07-19-10 Revere Copper and Brass

61 of 64 

Table A1-2: Database Searches for Revere Copper and Brass

Database/Source Keywords / Phrases Hits Uploaded

"Revere Copper" microcurie

"Revere Copper" millicurie

"Revere Copper" monitor "air monitoring"

"Revere Copper" nanocurie

"Revere Copper" neptunium Np237 Np-237 "Np 237" 237Np 237-Np 

"237 Np" palm palmolive

"Revere Copper" neutron

"Revere Copper" nuclear "Chicago-Nuclear" "nuclear fuels"

"Revere Copper" occurrence

"Revere Copper" oralloy

"Revere Copper" permit "radiation work permit" "safe work permit" 

"special work permit" RWP SWP 

"Revere Copper" photon

"Revere Copper" picocurie

"Revere Copper" pitchblende

"Revere Copper" plutonium Pu-238 Pu238 "Pu 238" 238Pu 238-Pu 

"238 Pu" Pu-239 Pu239 "Pu 239" 239Pu 239-Pu "239 Pu" Pu-240 

Pu240 "Pu 240" 240Pu 240-Pu "240 Pu" Pu-241 Pu241 "Pu 241" 241Pu 

241-Pu "241 Pu"

"Revere Copper" polonium Po210 Po-210 "Po 210" 210Po 210-Po "210 

Po"

"Revere Copper" postum

"Revere Copper" problem

"Revere Copper" procedure

"Revere Copper" protactinium Pa-234m Pa234m "Pa 234m" 234mPa 

234m-Pa "234m Pa"

"Revere Copper" radeco
SEC-00164 07-19-10 Revere Copper and Brass

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Table A1-2: Database Searches for Revere Copper and Brass

Database/Source Keywords / Phrases Hits Uploaded

"Revere Copper" radiation

"Revere Copper" radioactive

"Revere Copper" radioactivity

"Revere Copper" radiograph

"Revere Copper" radiological

"Revere Copper" radionuclide

"Revere Copper" radium Ra-226 Ra226 "Ra 226" 226-Ra 226Ra "226 

Ra" Ra-228 Ra228 "Ra 228" 228Ra 228-Ra "228 Ra"

"Revere Copper" radon Rn-222 Rn222 "Rn 222" 222Rn 222-Rn "222 

Rn"

"Revere Copper" raffinate

"Revere Copper" reactor

"Revere Copper" respiratory

"Revere Copper" roentgen

"Revere Copper" sample "air sample" "dust sample" "general area air 

sample"

"Revere Copper" sampling "air sampling" "dust sampling" "general area 

air sampling"

"Revere Copper" source "sealed source"

"Revere Copper" spectra

"Revere Copper" spectrograph

"Revere Copper" spectroscopy

"Revere Copper" spectrum

"Revere Copper" strontium Sr-90 Sr90 "Sr 90" 90-Sr 90Sr "90 Sr"

"Revere Copper" survey "building survey" "routine survey" "special 

survey"

"Revere Copper" ''technical basis"
SEC-00164 07-19-10 Revere Copper and Brass

63 of 64 

Table A1-2: Database Searches for Revere Copper and Brass

Database/Source Keywords / Phrases Hits Uploaded

"Revere Copper" thorium thoria Th232 Th-232 "Th 232" 232Th 232-Th 

"232 Th" "Z metal" Z-metal myrnalloy "chemical 10-66" "chemical 

1066" "chemical 10 66" "chemical 18-12" "chemical 1812" "chemical 

18 12" "chemical 10-12" "chemical 1012" "chemical 10 12" UX1 UX2 

Th-234 Th234 "Th 234" 234-Th 234Th "234 Th"

"Revere Copper" thoron Rn-220 Rn220 "Rn 220" 220Rn 220-Rn "220 

Rn"

"Revere Copper" tritium H3 H-3 mint HTO

"Revere Copper" tuballoy

"Revere Copper" uranium U233 U-233 U 233 233U 233-U 233 U U234 

"U 234" U-234 234U 234-U "234 U" U235 "U 235" U-235 235-U 235U 

"235 U" U238 "U 238" U-238 238-U 238U "238 U" U308 "U 308" U308 308-U 308U "308 U"

"Revere Copper" urinalysis

"Revere Copper" urine

"Revere Copper" X-ray "X ray" Xray

Revere Copper & Brass

National Academies Press

http://www.nap.edu/

COMPLETED 03/23/2010

"Revere Copper" 0 0 

NNSA - Nevada Site Office

www.nv.doe.gov/main/search.htm

COMPLETED 03/23/2010

"Revere Copper" 0 0 

NRC ADAMS Reading Room

http://www.nrc.gov/reading-rm/adams/web-based.html

COMPLETED 03/23/2010

"Revere Copper" 15 0 

U.S. Transuranium & Uranium Registries 

http://www.ustur.wsu.edu/

COMPLETED 03/23/2010

"Revere Copper" 0 0 
SEC-00164 07-19-10 Revere Copper and Brass

64 of 64 

Table A1-3: OSTI Documents Requested for Revere Copper and Brass

Document Number Document Title Requested

Date

Received

Date

AECD-3852; MIT-SVA-18

Ref ID: 80196

Extrusion at Revere Copper and Brass, Inc., March 1, 1949 dated 10-

31-1956

03/12/2010 03/29/2010