SEC Petition Evaluation Report
 

Petition SEC-00116 

Report Rev #: 1_ Report Submittal Date: January 28, 2010 

Subject Expert(s): Jake Alexander, Alex Boerner, Ray Clark , Monica Harrison-Maples 

Site Expert(s): N/A 

Petition Administrative Summary 

Petition Under Evaluation 

Petition # Petition 

Type 

Petition 

Qualification Date 

DOE/AWE Facility Name 

SEC-00116 83.13 November 4, 2008 United Nuclear Corporation 

Petitioner Class Definition 

All site employees that worked in any area of the United Nuclear Corporation – Hematite, MO, site from January 1, 1958 

through December 31, 1969 and January 1, 1970 through June 30, 2011 due to residual contamination. 

Class Evaluated by NIOSH 

All site employees that worked in any area of the United Nuclear Corporation – Hematite, MO, site from January 1, 1958 

through December 31, 1973 and the residual radiation period January 1, 1974 through July 31, 2006. 

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

None 

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 Evaluators: Ray Clark and Alex 

Boerner 

ORAU Review Completed By: Daniel Stempfley 

Peer Review Completed By: [Signature on file] 

LaVon Rutherford 

2/1/2010 

Date 

SEC Petition Evaluation Reviewed By: [Signature on file] 

J. W. Neton 

2/1/2010 

Date 

SEC Evaluation Approved By: [Signature on file] 

Stuart L. Hinnefeld 

2/1/2010 

Date 

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Evaluation Report Summary: SEC-00116, United Nuclear Corporation 

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-00116, qualified on November 4, 2008, requested that NIOSH consider the following class: All 

site employees that worked in any area of the United Nuclear Corporation – Hematite, MO, site from January 

1, 1958 through December 31, 1969 and January 1, 1970 through June 30, 2011 due to residual 

contamination. 

Class Evaluated by NIOSH 

Based on its preliminary research, NIOSH modified the petitioner-proposed class because, although the 

petitioner requested an end date of June 2011, the employment period end date is limited to the covered period 

defined by the DOE Office of Health, Safety and Security, which is July 2006. The covered operational period 

was also adjusted to account for the Department of Labor (DOL) change in the operational period which was 

extended through 1973. NIOSH evaluated the following class: All site employees that worked in any area of 

the United Nuclear Corporation – Hematite, MO, site from January 1, 1958 through December 31, 1973 and 

the residual radiation period January 1, 1974 through July 31, 2006. 

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

Based on its full research of the class under evaluation, including personnel interviews, NIOSH has obtained 

urinalysis, general area and fixed location air samples, personnel whole body dosimetry, and radiation survey 

records for the United Nuclear Corporation, Hematite, MO facility. Based on its analysis of these available 

resources, NIOSH found no part of the class under evaluation for which it cannot estimate radiation 

doses with sufficient accuracy. 

Feasibility of Dose Reconstruction 

Per EEOICPA and 42 C.F.R. § 83.13(c)(1), NIOSH has established that it has access to 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 by any member of the class; or (2) 

estimate radiation doses of members of the class more precisely than an estimate of maximum dose. 

Information available from the site profile and additional resources is sufficient to document or estimate the 

maximum internal and external potential exposure to members of the evaluated class under plausible 

circumstances during the specified period. 

Health Endangerment Determination 

Per EEOICPA and 42 C.F.R. § 83.13(c)(3), a health endangerment determination is not required because 

NIOSH has determined that it has sufficient information to estimate dose for the members of the evaluated 

class. 

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Table of Contents 

Evaluation Report Summary: SEC-00116, United Nuclear Corporation................................................ 3
 

1.0 Purpose and Scope.......................................................................................................................... 7
 

2.0 Introduction .................................................................................................................................... 7
 

3.0 SEC-00116 United Nuclear Corporation Class Definitions........................................................... 8
 

3.1 Petitioner-Requested Class Definition and Basis.................................................................. 8
 

3.2 Class Evaluated by NIOSH ................................................................................................... 9
 

3.3 NIOSH-Proposed Class(es) to be Added to the SEC ............................................................ 9
 

4.0 Data Sources Reviewed by NIOSH to Evaluate the Class........................................................... 10
 

4.1 Site Profile Technical Basis Documents (TBDs) ................................................................ 10
 

4.2 Technical Information Bulletins (TIBs) .............................................................................. 11
 

4.3 Facility Employees and Experts .......................................................................................... 11
 

4.4 Previous Dose Reconstructions ........................................................................................... 12
 

4.5 NIOSH Site Research Database .......................................................................................... 13
 

4.6 Other Technical Sources...................................................................................................... 13
 

4.7 Documentation and/or Affidavits Provided by Petitioners ................................................. 13
 

5.0 Radiological Operations Relevant to the Class Evaluated by NIOSH ......................................... 14
 

5.1 UNC-Hematite Plant and Process Descriptions .................................................................. 14
 

5.2 Radiological Exposure Sources from UNC-Hematite Operations ...................................... 16
 

5.2.1 Internal Radiological Exposure Sources from UNC-Hematite Operations............. 17
 

5.2.1.1 Uranium.................................................................................................... 17
 

5.2.1.2 Thorium .................................................................................................... 18
 

5.2.2 External Radiological Exposure Sources from UNC-Hematite Operations............ 18
 

5.2.2.1 Photon....................................................................................................... 18
 

5.2.2.2 Beta........................................................................................................... 19
 

5.2.2.3 Neutron..................................................................................................... 19
 

5.2.3 Incidents .................................................................................................................. 19
 

6.0 Summary of Available Monitoring Data for the Class Evaluated by NIOSH ............................. 20
 

6.1 Available UNC-Hematite Internal Monitoring Data........................................................... 20
 

6.2 Available UNC-Hematite External Monitoring Data.......................................................... 24
 

6.3 Summary of UNC-Hematite Available Monitoring Data ................................................... 28
 

7.0 Feasibility of Dose Reconstruction for the Class Evaluated by NIOSH ...................................... 31
 

7.1 Pedigree of UNC-Hematite Data......................................................................................... 32
 

7.1.1 Internal Monitoring Data Pedigree Review............................................................. 32
 

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

7.2 Evaluation of Bounding Internal Radiation Doses at UNC-Hematite................................. 35
 

7.2.1 Evaluation of Bounding Process-Related Internal Doses........................................ 36
 

7.2.1.1 Urinalysis Information and Available Data.............................................. 37
 

7.2.1.2 Lung Counting Information and Available Data...................................... 38
 

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7.2.1.3 Airborne Levels........................................................................................ 38
 

7.2.2 Evaluation of Bounding Residual Period Internal Doses ........................................ 41
 

7.2.3 Methods for Bounding Internal Dose at UNC-Hematite......................................... 41
 

7.2.3.1 Methods for Bounding Operational Period Internal Dose........................ 41
 

7.2.3.2 Methods for Bounding Residual Period Internal Dose............................. 42
 

7.2.4 Internal Dose Reconstruction Feasibility Conclusion ............................................. 43
 

7.3 Evaluation of Bounding External Radiation Doses at UNC-Hematite ............................... 43
 

7.3.1 Evaluation of Bounding Process-Related External Doses....................................... 44
 

7.3.1.1 Personnel Dosimetry Data........................................................................ 44
 

7.3.1.2 Area Monitoring Data............................................................................... 45
 

7.3.2 Evaluation of Bounding Residual Period External Doses....................................... 46
 

7.3.3 UNC-Hematite Occupational X-Ray Examinations................................................ 46
 

7.3.4 Methods for Bounding External Dose at UNC-Hematite........................................ 47
 

7.3.4.1 Methods for Bounding Operational Period External Dose....................... 47
 

7.3.4.2 Methods for Bounding Residual Period External Doses.......................... 48
 

7.3.5 External Dose Reconstruction Feasibility Conclusion............................................ 48
 

7.4 Evaluation of Petition Basis for SEC-00116 ....................................................................... 49
 

7.4.1 Personnel Records Lost, Falsified, or Destroyed .................................................... 49
 

7.4.2 Dose Reconstruction Infeasible............................................................................... 49
 

7.4.3 Lack of Site Profile.................................................................................................. 49
 

7.4.4 Lack of Internal Monitoring .................................................................................... 49
 

7.4.5 Monitoring Thoroughness ....................................................................................... 50
 

7.4.6 Lack of Personnel Radiation Dose Records ............................................................ 50
 

7.4.7 Residual Contamination .......................................................................................... 50
 

7.5 Other Potential SEC Issues Relevant to the Petition Identified During the Evaluation...... 51
 

7.6 Summary of Feasibility Findings for Petition SEC-00116.................................................. 52
 

8.0 Evaluation of Health Endangerment for Petition SEC-00116...................................................... 53
 

9.0 Class Conclusion for Petition SEC-00116 ................................................................................... 53
 

10.0 References .................................................................................................................................... 55
 

Attachment 1: Data Capture Synopsis................................................................................................... 69
 

Tables 

4-1: No. of UNC-Hematite Claims Submitted Under the Dose Reconstruction Rule .......................... 12
 

6-1: Summary of Urinalysis Samples Collected During the Operational Period.................................. 22
 

6-2: Summary of UNC-Hematite Available Internal and External Monitoring Data ........................... 28
 

7-1: Comparison of Air Sample Totals and Results for UNC and GUNFC Operations....................... 40
 

7-2: Summary of Feasibility Findings for SEC-00116.......................................................................... 52
 

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SEC Petition Evaluation Report for SEC-00116 

ATTRIBUTION AND ANNOTATION: All conclusions drawn from the data presented in this 

evaluation were made by the ORAU Team Lead Technical Evaluators: Ray Clark and Alex Boerner, 

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. 

1.0 Purpose and Scope 

This report evaluates the feasibility of reconstructing doses for all site employees that worked in any 

area of the United Nuclear Corporation site at Hematite, Missouri, from January 1, 1958 through 

December 31, 1973 and the residual radiation period January 1, 1974 through July 31, 2006. It 

provides information and analyses germane to considering a petition for adding a class of employees 

to the congressionally-created 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 Office of Compensation Analysis and Support’s (OCAS) Internal 

Procedures for the Evaluation of Special Exposure Cohort Petitions, OCAS-PR-004. 

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.1 

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 

1

 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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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 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.2 

3.0 SEC-00116 United Nuclear Corporation Class Definitions 

The following subsections address the evolution of the class definition for SEC-00116, United 

Nuclear Corporation at Hematite, Missouri (UNC-Hematite). 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-proposed class. If some portion of the petitioner-proposed 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-00116, qualified on November 4, 2008, requested that NIOSH consider the following 

class for addition to the SEC: All site employees that worked in any area of the United Nuclear 

Corporation, Hematite, MO, site from January 1, 1958 through December 31, 1969 and January 1, 

1970 through June 30, 2011 due to residual contamination. 

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

accurate dose reconstruction over time is impossible for the UNC-Hematite workers in question. 

NIOSH deemed the following information and affidavit statements sufficient to qualify SEC-00116 

for evaluation: 

No Hematite personnel radiation dose records have been provided to NIOSH and possibly do not 

exist; therefore, it is quite conceivable that a fair and accurate dose reconstruction cannot be 

obtained with sufficient accuracy because data are lacking for this site (Affidavits, 2008, pdf pp. 

28-29). 

I was never monitored for radium or thorium (Affidavits, 2008, pdf p. 36). 

At the time NIOSH qualified this petition, NIOSH’s UNC-Hematite research and data capture efforts 

(including interviews with former site employees) led to the conclusion that a significant number of 

site records exist for the petitioner-proposed class. However, NIOSH had been provided only limited 

internal and external dose information for UNC-Hematite workers during the time period under 

evaluation. While results were unavailable at that time, NIOSH believed that general area air 

sampling (continuous air monitoring) and fixed location (breathing zone) sampling were also 

conducted. In addition, NIOSH believed that external monitoring (i.e., personnel whole body [film 

badge] dosimetry and routine radiation surveys) were primary components of the external dosimetry 

program. Nevertheless, NIOSH determined that dosimetry monitoring data records were not currently 

available for all time periods or for all radionuclides. NIOSH concluded that there was sufficient 

documentation to support, for at least part of the proposed time period, the petition basis that internal 

and external radiation exposures and radiation doses were not adequately monitored at UNCHematite, 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. The details of the petition basis are addressed in Section 7.4. 

3.2 Class Evaluated by NIOSH 

Based on its preliminary research, NIOSH modified the petitioner-proposed class because, although 

the petitioner requested an end date of June 2011, the employment period end date is limited to the 

covered period defined by the DOE Office of Health, Safety and Security, which is July 2006. The 

covered operational period was also adjusted to account for the Department of Labor (DOL) change in 

the operational period which was extended through 1973 (DOL, 2009). Therefore, NIOSH defined 

the following class for further evaluation: All site employees that worked in any area of the United 

Nuclear Corporation, Hematite, MO, site from January 1, 1958 through December 31, 1973 and the 

residual radiation period January 1, 1974 through July 31, 2006. 

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

Based on its research and multiple on-site data capture efforts, NIOSH has obtained urinalysis, general 

area and fixed location air samples, personnel whole body dosimetry, and radiation survey records for 

UNC-Hematite. Based on its analysis of these available resources, NIOSH found no part of the class 

under evaluation for which it cannot bound the radiation doses (estimate radiation doses with 

sufficient accuracy). 

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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 UNC-Hematite. 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 DOE-National Nuclear 

Security Administration-Nevada Site Office-search. Attachment One contains a summary of UNCHematite documents. The summary specifically identifies 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 

UNC-Hematite operations or related topics/operations at other sites: 

•	 Battelle-TBD-6000, Site Profiles for Atomic Weapons Employers that Worked Uranium and 

Thorium Metals, PNWD-3738 Rev 0, Rev. F0; Battelle; December 13, 2006; SRDB Ref ID: 

30671 

•	 Battelle-TBD-6001, Site Profiles for Atomic Weapons Employers that Refined Uranium and 

Thorium, Rev. F0; Battelle; December 13, 2006; SRDB Ref ID: 30673 

•	 Battelle-TBD-6001, Appendix D, Site Profiles for Atomic Weapons Employers that Refined 

Uranium and Thorium—Appendix D United Nuclear Corp., Rev. 0; Battelle; March 14, 2008; 

SRDB Ref ID: 41835 

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4.2 Technical Information Bulletins (TIBs) 

A Technical Information Bulletin (TIB) is a general working document that provides guidance for 

preparing dose reconstructions at particular sites or categories of sites. An ORAU Procedure provides 

specific requirements and guidance regarding EEOICPA project-level activities, including preparation 

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

as part of its evaluation: 

•	 Battelle-TIB-5000, Default Assumptions and Methods for Atomic Weapons Employer Dose 

Reconstructions, PNWD-3741, Rev. 00; Battelle; April 2, 2007; SRDB Ref ID: 32016 

•	 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-0024, Estimation of Neutron Dose Rates from Alpha-Neutron Reactions in 

Uranium and Thorium Compounds, Rev. 00; Oak Ridge Associated Universities; April 7, 2005; 

SRDB Ref ID: 19445 

•	 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 

4.3 Facility Employees and Experts 

To obtain additional information, NIOSH interviewed four former UNC-Hematite employees. Three 

of the interviews were established through an initial telephone call followed by email correspondence 

that provided a preliminary list of anticipated interview questions, call-in information, and ORAUT 

contact information. The final interview was established and conducted on site during an ORAUT 

data capture trip in March 2009. NIOSH identified three production workers for possible interviews; 

however, attempts to make contact were unsuccessful. NIOSH was fortunate in locating three former 

managers and one former clerical employee. NIOSH was unable to locate any surviving Health 

Physics or Radiation Technicians. Following each interview, notes were prepared by team members 

and submitted to the DOE for classification review. 

•	 Personal Communication, 2009a, Personal Communication with Leader/Director (various titles); 

Telephone Interview by ORAU Team and NIOSH on February 4, 2009; SRDB Ref ID: 61673 

•	 Personal Communication, 2009b, Personal Communication with Office Worker; Telephone 

Interview by ORAU Team on February 5, 2009; SRDB Ref ID: 61669 

•	 Personal Communication, 2009c, Personal Communication with Engineer/Manager (various 

titles); Telephone Interview by ORAU Team and NIOSH on February 12, 2009; SRDB Ref ID: 

61676 

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•	 Personal Communication, 2009d, Personal Communication with Supervisor/Superintendant 

(various titles); On-site Interview by ORAU Team on March 12, 2009; SRDB Ref ID: 69965 

4.4 Previous Dose Reconstructions 

NIOSH reviewed its NIOSH OCAS 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 June 8, 2009) 

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

Description Totals 

Total number of claims submitted for dose reconstruction 51 

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

under evaluation (January 1, 1958 through December 31, 1973 and the residual radiation period 

January 1, 1974 through July 31, 2006). 511 

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). 33 

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

evaluated class definition 231 

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

evaluated class definition 231 

1 Of the 51 submitted claims: 

•	 Three were pulled by DOL and are no longer active; therefore, additional data linking has not occurred. 

•	 Eight were pulled by DOL because the claims are covered by an existing SEC class. These claims are no longer 

active; therefore, additional data linking has not occurred. 

•	 Four have employment only during the residual period; therefore, the data that may be available would not be 

representative of the site’s AEC operations. 

•	 Eight have missing data but have completed, compensable individual dose reconstructions. These claims are no 

longer active; therefore, additional data linking has not occurred. 

•	 Five have claimed UNC employment that is still being researched by the site (current status: no indication of 

UNC-Hematite employment for these individuals). 

As a result of the above actions and circumstances, NIOSH’s review of claims to evaluate available internal and 

external dosimetry data was performed only for the remaining 23 claims; all 23 have internal and external data for 

their UNC-Hematite employment during the covered operational period. 

NIOSH reviewed each claim as well as transcripts from the computer-assisted telephone interviews 

(CATI) to determine whether internal and/or external personal monitoring records could be obtained 

for the employee. Dose reconstructions performed to date were completed prior to the availability of 

personnel monitoring records. External doses estimates were based on a NIOSH assessment of the 

external dose information reported in a 1960 AEC inspection report for UNC-Hematite license 

renewal that was available when the TBD for UNC-Hematite was developed (Battelle-TBD-6001, 

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Appendix D). Internal doses estimates were based on a NIOSH assessment of the airborne 

radioactivity data (1959-1960 air samples) and personnel bioassay data (1962-1964 urinalysis data) 

that were available when the TBD for UNC-Hematite was developed (Battelle-TBD-6001, Appendix 

D). Dose reconstructions also employed the methodologies in ORAUT-OTIB-0004. During the data 

capture efforts conducted in support of the UNC-Hematite SEC petition evaluation, NIOSH identified 

internal and external monitoring records for individual UNC-Hematite workers that cover the entire 

Atomic Weapons Employer (AWE) operations period at the site. These data have been collected by 

NIOSH and are available for individual dose reconstructions, as applicable. 

4.5 NIOSH Site Research Database 

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

evaluation of the proposed class. As of June 15, 2009, 1136 documents in this database were 

identified as pertaining to UNC-Hematite. These documents were evaluated for their relevance to this 

petition. The documents include historical background on the evolution of the site, licensing 

documentation and correspondence, process descriptions and procedures, logbook entries, radiological 

monitoring summaries and data (urinalysis, general area and fixed location air samples, personnel 

whole body dosimetry, and radiation survey records), radiological and contamination control program 

information and reporting, criticality controls, and incident documentation 

4.6 Other Technical Sources 

ORAUT-TKBS-0014-2, Technical Basis Document for the Y-12 National Security Complex - Site 

Profile, Rev. 02; Oak Ridge Associated Universities; November 8, 2007; SRDB Ref ID: 36045 

4.7 Documentation and/or Affidavits Provided by Petitioners 

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

petitioners: 

•	 Affidavits, Authorization Forms, and Associated Attachments from Name1, Name2, Name 3, and 

Name4; June 13, 2008; OSA Ref ID: 106292, pdf pp. 1-39 (Affidavits, 2008) 

•	 NIOSH Dose Reconstruction Report for Name2, April 8, 2008; OSA Ref ID: 106292, pdf pp. 40-47 

(NIOSH, 2008) 

•	 NIOSH Dose Reconstruction Activity Report for Name2, correspondence; January 25, 2006; OSA 

Ref ID: 106292, pdf pp. 48-50 (NIOSH, 2006) 

•	 Engineering Evaluation and Cost Analysis Regarding Local Aquifer in the Vicinity of the 

Westinghouse Former Fuel Cycle Facility, select pages from a groundwater report; January 2003; 

OSA Ref ID: 106292, pdf pp. 51-53 (Cabrera Services, 2003) 

•	 Letter and Q&A Regarding the Combustion Engineering Plant at Hematite, Missouri Inspection 

Program, correspondence and select attachments; November 24, 1978; OSA Ref ID: 106292, pdf 

pp. 54-56 (Keppler, 1978) 

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•	 Investigation to Determine the Source of Technetium-99 in Groundwater Monitoring Wells 17 and 

17B, select pages of report; September 1996; OSA Ref ID: 106292, pdf pp. 57-61 (Gateway, 1996) 

•	 Cancel Permit Application, correspondence to EPA; December 27, 1973; OSA Ref ID: 106292, 

pdf p. 62 (Loysen, 1973) 

•	 Executed Application for Renewal of Operating Permit for Septic System, correspondence to 

Missouri Clean Water Commission; February 6, 1974; OSA Ref ID: 106292, pdf p. 63 (Darr, 

1974) 

•	 Hematite Revisited, news story; OSA Ref ID: 106292, pdf pp. 64-70 (MCW News, unknown date) 

•	 Remedial Investigation Report for the Westinghouse Hematite Site, select pages from 

report; January 2007; OSA Ref ID: 106292, pdf pp. 71-92 (SAIC, 2007) 

•	 Federal Register Notices, Volume 66, No. 11; January 17, 2001; OSA Ref ID: 106292, pdf pp. 93-

96 (Federal Register, 2001) 

•	 Consult Call Response Letter; October 3, 2008; OSA Ref ID: 107083, pdf p. 1 (Consult Call, 2008) 

•	 Clarification Responses to NIOSH on the Submitted Petition SEC 00116; document detailing SEC00116 changes; October 3, 2008; OSA Ref ID: 107083, pdf pp. 2-7 (Clarification , 2008) 

•	 Letter and Associated Attachments Discussing Incorrect and/or Assumed Statements; Name2; April 

15, 2008; OSA Ref ID: 107083, pdf pp. 8-14 (Letter, 2008) 

5.0 Radiological Operations Relevant to the Class Evaluated by 

NIOSH 

The following subsections summarize both radiological operations at UNC-Hematite from January 1, 

1958 through December 31, 1973 and the information available to NIOSH to characterize particular 

processes and radioactive materials for the covered period at the site. From available sources, NIOSH 

has gathered process and source descriptions, information regarding the identity and quantities of each 

radionuclide of concern, and information describing both the processes through which radiation 

exposures to workers 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 UNC-Hematite Plant and Process Descriptions 

The UNC-Hematite site was centrally located on approximately 228 acres of land roughly 40 miles 

south of St. Louis, Missouri near the town of Hematite, just west of Festus, Missouri. The northern 

boundary of the site is Missouri State Highway 21-A (also known as State Road P). Joachim Creek 

forms the southern boundary. Private property bounds the site on the east and west. The Mallinckrodt 

Corporation acquired 150 acres of farm property in 1955; construction of the original production 

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facilities began in March 1956. The plant first became operational in September 1956, producing 

uranium for use in the navy nuclear fuel program. Other non-navy production work involving 

radioactive materials subject to Atomic Energy Commission (AEC) licensing began in 1958. 

Additional purchases of surrounding land were negotiated in later years by the plant’s various owners, 

the last such purchase taking place in 1991 by Westinghouse Electric. 

There have been six owners of the UNC-Hematite facility: 

•	 U.S. Government contracting phase of operations: Mallinckrodt (1956-1961); United Nuclear 

Corporation (1961-1969); Gulf United Nuclear Fuels Corporation (1970-1973). 

•	 Commercial phase of operations: Combustion Engineering (1974-1989); Asea Brown Boveri 

Combustion Engineering (1989-2000); and Westinghouse Electric Company (2000-present). 

Site operations involved about seven acres near the geographic center of the property. The production 

facilities consisted of two main buildings, each with several thousand square feet of floor space. An 

incoming storage and blending building and an outgoing storage building were located between the 

two main buildings (AEC, 1960). 

Throughout its history, the UNC-Hematite plant's primary function was to manufacture uranium metal 

and uranium compounds from natural and enriched uranium feed stocks for use as fuel in nuclear 

reactors, including the U.S. Navy’s submarine reactors. From its inception in 1956 through the end of 

the government contracting phase, the facility was used primarily in support of U.S. Government 

contracts that required production of enriched uranium products. Starting in 1959, the facility 

processed un-irradiated uranium scrap for the recovery of enriched uranium for use in the AEC’s 

nuclear weapons complex (DOE, 1997; Facility List, 2001; FUSRAP, 1987; FUSRAP, 2000; Major 

Activities, 1962; Un-irradiated Scrap, 1958). Recovering uranium, especially enriched uranium, from 

scrap, process effluents, and other waste was a high priority in the nuclear weapons complex due to 

scarcity and cost of these materials (DOE, 1997). This activity continued until 1973 (AEC, 1962; 

DOE, 1997; FUSRAP, 2000; Site Assessment, 2005). 

Radioactive material licenses issued to both Mallinckrodt Chemical Works (MCW) and 

UNC-Hematite authorized the site to possess thorium. Information from the Bureau of Mines 

Yearbook indicates that MCW and UNC-Hematite had the capability to process thorium in the early 

1960s (Bureau of Mines, 1932-1993; Thorium License, 1958). Documentation from 1963 indicates 

that the UNC-Hematite site placed a bid on an AEC-related thorium contract (Thorium Bid, 1963). 

Other information supports that this thorium work was related to the production of Th-U fuel 

assemblies for use in breeder reactors like the Elk River reactor (Personal Communication 2009a; 

UNC Health Physics, 1964). This may have been a common or collaborative effort between UNCHematite, MCW, and Weldon Spring (Project Proposal, 1966; Thorium Conversion, 1965; Thorium 

Meeting, 1965; Thorium Operations, 1965). In 1964, the UNC-Hematite facility also produced 

approximately nine tons of thorium dioxide fuel pellets as a demonstration of its ability to produce 

Th-U fuels (Pellet Plant, 1964; Personal Communication 2009a; UNC Health Physics, 1963; UNC 

Health Physics, 1964). Over the period 1964-1968, UNC-Hematite (and several other sites) provided 

examples of their product for AEC approval; W.R. Grace/Nuclear Fuel Services was ultimately 

selected as the primary Th-U fuel element contractor (Nuclear Fuel Services, 1967; Procurement, 

1968; Thorium Fuel Cycle, 2005; Thorium Shipments, 1969, pdf pp. 150, 167; W. R. Grace, 1963;). 

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UNC-Hematite shipped the remainder of the unused fuel to Maxey Flats disposal facility (Thorium 

Shipments, 1969, pdf p. 71). The information available on UNC-Hematite’s thorium operation 

provides no corroboration that this effort was AEC-related weapons work. Based on this information, 

the issue of thorium exposure during the residual radioactivity period is not considered covered under 

EEOICPA rules, and therefore, is not evaluated in this report. 

The operations at UNC-Hematite also included converting uranium hexafluoride to uranium dioxide 

powder using steam and dissociated ammonia. The UO2 was then pressed into pellets and furnacefired into a ceramic form suitable for loading into fuel assemblies. Chemical conversions of UF6 to 

uranium carbide and uranium metal also took place. In addition, various research and development 

projects were conducted at the plant, as were uranium scrap recovery processes performed for the 

AEC nuclear weapons programs. 

According to an AEC License inspection conducted on August 18-19, 1958 (Inspection, 1958) most 

operations at the UNC-Hematite plant at that time were being conducted under one of two AEC 

licenses issued to the Mallinckrodt Chemical Works Corporation: Source Material License No. 

C-2734, originally issued on September 23, 1955 (License C-2734, 1958), and License No. SNM-33, 

issued for special nuclear material (SNM-33, 1958). SNM-33 was amended and modified many times 

over the covered operational years at Hematite to authorize changes in operations and quantities of 

materials. 

Per an AEC license re-inspection conducted January 12-14, 1960, authorizations derived from two 

additional licenses had been activated: C-4495 and SNM-230 (AEC, 1960). By 1960, all licenses 

previously issued to the Mallinckrodt Chemical Works had been reissued to a new, wholly-owned 

subsidiary, Mallinckrodt Nuclear Corporation, with the exception of C-2734, which had been allowed 

to expire on November 30, 1959. 

This Evaluation Report emphasizes operations involving the use of radioactive materials occurring 

during the DOE defined time period of January 1, 1958 through December 31, 1973. This includes 

operations emphasizing uranium production activities for use in commercial and navy reactors. 

Thorium processing operations, isolated to a single project in 1964, are also included. The residual 

period, which commences on January 1, 1974, is considered separately in this and other sections of 

the report. 

5.2 Radiological Exposure Sources from UNC-Hematite Operations 

Based on information and documentation available to NIOSH, the potential for internal and external 

radiation doses from (primarily) uranium and uranium decay products existed at the UNC-Hematite 

site. To a much more limited extent, thorium compounds were also received, processed, and 

monitored at the plant. The following subsections provide an overview of the internal and external 

exposure sources for the UNC-Hematite class under evaluation. 

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5.2.1 Internal Radiological Exposure Sources from UNC-Hematite Operations 

Data capture efforts and subsequent review of the information available to NIOSH identified the 

potential for internal radiation exposures to workers. The primary source of this exposure was 

deposition of alpha-emitting materials via inhalation and ingestion of airborne uranium and thorium 

(and progeny). Alpha particles do not present an external exposure hazard. 

5.2.1.1 Uranium 

Uranium was present at UNC-Hematite in both natural (also referred to as “normal”) and enriched 

forms - as a solid metal and in various compounds, including uranium hexafluoride, uranium 

tetrafluoride, and uranium dioxide powder. Exposure to uranium posed a potential internal exposure 

hazard. Natural uranium refers to uranium consisting of approximately 0.7% U-235, 99.3% U-238, 

and a very small residual amount of U-234, by weight. In terms of radioactivity, natural uranium 

contains approximately equal percentages of U-238 (48.6%) and U-234 (49.2%). These radionuclides 

emit alpha particles with primary emission energies of 4.20 MeV and 4.15 MeV (U-238), and 4.77 

MeV and 4.72 MeV (U-234) (Radiological Health Handbook, 1970). The radioactivity contribution 

from U-235 is much smaller (approximately 2.2%) relative to U-238 or U-234. U-235 emits alpha 

particles with energies of 4.40 MeV and 4.37 MeV. 

Enriched uranium refers to uranium with a higher percentage of U-235 by weight. Through the 

gaseous diffusion process, the specific activity of uranium increases with enrichment primarily 

because of the increase in the amount of U-234 present, rather than the increase in U-235. The 

determination of the enriched uranium specific activity (typically performed for uranium alpha 

emitters) can be calculated and accounted for using standard methods if enrichment levels are known 

for the associated work areas (DOE-STD-1136-2000; Rich, 1988). 

Compliance Inspection Reports for License No. SNM-33, dated January 1960 and March 1961, 

describe two process areas designed for “Manufacture of cermet type fuel elements and metal from 

uranium enriched in U-235 to 20% and higher” and “production of low enriched materials up to 6% 

U-235” (AEC, 1960; Enriched Materials, 1959). A review of allocation requests from 1959 through 

1966 (the only such documents located to date) indicates that approximately 7,576 kilograms of 

uranium were requested for government-related projects, and 1,887 kilograms of uranium were 

requested for commercial projects (United Nuclear HSA, 2003; Westinghouse, 2003). 

In general, an increase in enrichment was associated with operations occurring in the Green Room (~2 

to 5 % enrichment), Blue Room (~5 to 20% enrichment), and Red Room (greater than 20% 

enrichment) (Personal communications, 2009a). Operations in the Green Room and Blue Room were 

designed for “low” and “intermediate” enrichment activities, respectively; the Blender Room was 

used for both low and intermediate enrichment operations (General Survey, 1959). Operations 

occurring in the Item Plant, which was often designated for classified operations, likely involved 

highly-enriched uranium. 

UNC-Hematite also contracted directly with the Oak Ridge AEC office and other government 

contractors for the recovery of uranium from scrap materials. Scrap recovery projects at UNCHematite included the recovery of uranium from scrap generated by a variety of Navy projects and 

CUNO [company name] filter scrap generated by the Aircraft Nuclear Propulsion program (United 

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Nuclear HSA, 2003; Westinghouse, 2003). Interviews with former energy employees (EE) indicate 

that only un-irradiated scrap was processed (Personal Communications, 2009a and 2009c). A 

FUSRAP Stewardship Report for Site “MO.O-03 - United Nuclear Corporation” documents that 

UNC-Hematite processed un-irradiated scrap for the AEC in the 1960s (FUSRAP, 2000). 

5.2.1.2 Thorium 

Thorium-232 is the parent radionuclide in the thorium series. Thorium-232 decays by alpha emission 

into Ra-228, emitting two primary alpha particles of 3.95 MeV (24% abundance) and 4.01 MeV (76% 

abundance). The natural thorium decay series includes six progeny that emit alpha particles, with 

energies ranging from 5.34 MeV to 8.78 MeV. 

Approximately nine tons of natural thorium was on site during the covered period for a single, specific 

project conducted in 1964 in the Pellet Plant. Thorium dioxide powder was blended with uranium 

dioxide powder to produce Th-U fuel pellets to be used in fuel assemblies for breeder reactors like the 

Elk River Reactor in Minnesota (Pellet Plant, 1964; Personal Communication 2009a and 2009c; 

Thorium Bid, 1963; UNC Health Physics, 1963; UNC Health Physics, 1964). Each pellet consisted of 

a mixture of 97 % ThO2 - 3 % UO2, compressed and sintered (heated) in a furnace. The uranium 

(un-irradiated) was “fully-enriched” with a nominal U-235 enrichment of 93% (Elk River, 1961, pdf 

p. 15). The fuel pellets were produced to demonstrate UNC-Hematite’s fuel fabrication capabilities in 

an attempt to obtain breeder-reactor-fuel contracts. Based on the operational and monitoring data, 

thorium exposures from the 1964 fuel pellet operations posed a potential internal hazard to plant 

production workers. Information accompanying some of the air sample data associated with the 

thorium operation indicates that clean-up of residual thorium dioxide was conducted (Pellet Plant, 

1964). 

5.2.2 External Radiological Exposure Sources from UNC-Hematite Operations 

Operations at the UNC-Hematite facility potentially would have resulted in exposures primarily to 

uranium and uranium decay products. Uranium operations included high-enriched uranium (HEU), 

low-enriched uranium (LEU), and the recovery of uranium in scrap materials. In addition, 

documented thorium operations would have been a potential source of external personnel exposures. 

Dose rates and resultant doses would have varied depending on the source term. 

5.2.2.1 Photon 

Personnel photon exposures at UNC-Hematite were directly related to uranium enrichment processes, 

primarily from operations in the Red Room, Blue Room, Green Room, and Item Plant. These 

processes are known to have been a routine component of plant operations during the entire covered 

period from 1958-1973 based on NIOSH review of plant radiation safety manuals and procedures (HP 

Standards, 1968; ThO2-UO2, 1964), plant correspondence and operations logs (Activities Log, 1969), 

film badge results (External Exposure Reports, 1963; External Exposure Reports, 1964; External 

Exposure Reports, 1965; Film Badge Summary, 1961; Film Badge Summary, 1962; Tabulation Sheet, 

1966; Tabulation Sheet, 1967; Tabulation Sheet, 1969; Tabulation Sheet, 1970; Tabulation Sheet, 

1971; Tabulation Sheet, 1972; Tabulation Sheet, 1973), and site interviews (Personal 

communications, 2009a and 2009c). Uranium in various forms and compounds was used (see Section 

5.1). Accordingly, external exposures to photon radiation would have resulted from radionuclides in 

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the uranium decay chain. The uranium progeny that result in the most significant photon exposures 

include Th-234 and protactinium-234m (Radiological Health Handbook, 1970). 

Secondary sources included exposures from thorium operations in the Pellet Plant. Thorium 

processing was limited to 1964 when thorium dioxide powder was mixed with uranium dioxide 

powder to produce fuel pellets. Radionuclides of interest included Th-232 and decay progeny (e.g., 

Ac-228, Th-228, and Ra-224). 

5.2.2.2 Beta 

Exposure to beta sources at UNC-Hematite would have resulted principally from uranium decay 

products. In the uranium-series decay scheme, beginning with U-238, the short-lived isotope 

Pa-234m emits the most energetic beta particle (2.28 MeV). It is this beta particle that accounts for 

the shallow-dose hazard associated with handling uranium. This radionuclide was likely encountered 

during routine scrap recovery operations and other production activities at the site. 

Beta exposures from thorium processing activities were also likely, though limited in both time and 

quantity relative to uranium. Decay progeny, including the beta emitters Ra-228 and Ac-228, can be 

(and likely were) liberated through heating processes (ThO2-UO2, 1964). 

5.2.2.3 Neutron 

There was a potential for personnel neutron exposures from the uranium-enrichment operations at 

UNC-Hematite. As described in Section 5.2.1.1, the site received and processed uranium compounds 

containing fluorine and oxygen. These low-atomic-number elements emit neutrons when struck by 

alpha particles, referred to as alpha-neutron (“α-n”) reactions. These reactions result in a radiation 

field that varies for fluorine compounds from 0.2 mrem/h to 4 mrem/h depending on a variety of 

factors, including enrichment levels (DOE-STD-1136-2000, pdf p. 157; ORAUT-OTIB-0024, pdf. p. 

12). The site was authorized by the AEC to receive enriched uranium hexafluoride (235UF6) and 

typically requested quantities of 50 to 100 kilograms (kg) on a quarterly basis with enrichments 

ranging from approximately 20 to 93% (Compliance, 1960, pdf pp. 4-5). Dose rates would therefore 

conceivably range up to the maximum value. By comparison, neutron yields for oxide compounds are 

lower by approximately 100 times, resulting in correspondingly lower exposure rates (DOE-STD1136-2000, pdf p. 159; ORAUT-OTIB-0024, pdf. p. 10). 

5.2.3 Incidents 

NIOSH did not identify any documented accidents at UNC-Hematite that resulted in exceptionally 

high personnel exposure levels (such as a criticality event). Interviews conducted with former site 

employees did not reveal any specific radiological or contamination events (Personal 

Communications, 2009a and 2009c). However, documentation was reviewed that cited several 

radiological incidents resulting in external or internal exposures during the covered operational period. 

In each instance, investigations were conducted, area and personnel samples collected for analysis, 

individuals identified by name and/or health number, and results provided. The plant reported these 

events to the AEC as warranted based on their evaluation of the circumstances. These incidents 

included: external radiological overexposures per film badge results in 1963 in the Pellet Plant 

(Overexposures, 1963); UF6 releases in the Red Room in 1966 (UF-6 Release, 1966) and 1967 (UF-6 

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Release, 1967); an HEU release in the Red Room in 1967 (Personnel Exposure, 1967); a UO2 release 

in the “Recycle” Room in 1968 (UO2 Release, 1968a); a Pellet Plant Press Hopper Release in 1968 

(UO2 Release, 1968b); a UO2 release in the Red Room Milling Hood in 1969 (UO2 Exposure, 1969); 

an HF6 release in the Oxide Building in 1969 (HF Leak, 1969); and various spills and releases in 1970 

(Special Bioassay, 1970). 

6.0 Summary of Available Monitoring Data for the Class Evaluated 

by NIOSH 

NIOSH researched, collected and reviewed site data made available to the agency through several 

means, including two on-site data capture efforts initiated and completed during one-week periods in 

March and April, 2009. The current owner of the former UNC facility (Westinghouse Electric) 

authorized NIOSH subcontractor staff to review and scan documents housed in several on-site 

locations. The following subsections provide an overview of the available monitoring data. 

UNC-Hematite was originally owned and operated by the Mallinckrodt Chemical Works (MCW) 

Company. Mallinckrodt initiated a film badge program at its original MCW location in 1942 to 

measure exposure to beta and gamma radiation. They also took periodic breath samples from those 

personnel whose duties involved exposure to radon. Initially, Mallinckrodt forwarded the film badges 

and breath samples to the AEC Medical Laboratories at Rochester, New York, for examination and 

checking, but later conducted complete handling of the film badges in-house (Fleishman-Hillard, 

1967). The monitoring program at UNC-Hematite was a natural extension of the program instituted 

early on in Mallinckrodt’s government work with uranium. The new operations drew on the history 

and experience of the previous health and safety programs. 

An August 1958, MCW Plant Inspection states personnel monitoring was conducted by routine use of 

film badges, bioassay, and physical examination (AEC, 1958). Film badges were obtained from the 

St. John X-Ray Laboratory in New Jersey and distributed on a frequency determined by individual job 

assignment. Permanent operating personnel were monitored on a weekly basis and rotating personnel 

were monitored monthly. The sections that follow discuss more specifically the available internal and 

external monitoring data for UNC-Hematite. 

6.1 Available UNC-Hematite Internal Monitoring Data 

Internal monitoring data available for the operational period primarily consist of urinalysis, dust 

sampling, and air monitoring results. “Dust” sampling was a commonly-used term during the covered 

period and refers to sampling for airborne radioactive dust particulates. Dust and air samples were 

collected in the same manner (i.e., using a pump to draw a known volume of air through a Whatman 

paper filter to collect particulates). Resulting airborne radioactivity concentrations were reported by 

the plant in μc/ml (representing the measurement units in “microcuries per milliliter” or “μCi/ml” as 

used today). This Evaluation Report will cite the airborne concentration measurement units used by 

the plant. Results were compared to the applicable site administrative levels (maximum acceptable 

concentrations) and federal airborne radioactivity limits. With one exception discussed below, data 

were collected covering the entire operational period. Tables 6-1 and 6-2 summarize available 

internal monitoring data for the operational period. 

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All UNC-Hematite employees were assigned a “Health Number” that was used in part to track worker 

doses. The methodology for reconstructing internal dose in the UNC-Hematite TBD (Battelle-TBD6001, Appendix D) assessed the limited personnel and area monitoring data available at the time the 

TBD was developed to establish maximum internal exposure scenarios. The evaluation in this report 

will include (as appropriate) recently-collected personnel internal monitoring data not available to 

NIOSH when the TBD was developed. 

Urinalysis Data 

Beginning in 1957, MCW Hematite plant operating personnel submitted urinalysis samples on a 

three- to six-month basis dependent on specific work assignments. Results recorded from 1957 until 

1960 included a maximum uranium alpha reading of 329.9 d/m/l (representing the measurement units 

in “disintegrations per minute per liter”), with an average value of 3-5 d/m/l (Compliance, 1960). 

NIOSH identified original, reliable data citing urinalysis results by year and employee as reported by 

three analysis vendors, Nuclear Science and Engineering Corporation, Controls for Radiation Inc., and 

Isotopes, Inc. (UNC urinalysis, 1962-1964; Bioassay Results, 1964; Bioassay Results, 1965; Bioassay 

Results, 1966; Bioassay Results, 1967; Bioassay Results, 1968; Bioassay Results, 1969; Special 

Bioassay, 1970). UNC-Hematite adopted various action levels for uranium in urine. In 1960, for 

example, the plant established a “desirable maximum” of 45 d/m/l (Urinalysis Results, 1960). In 

1966, the threshold for a follow-up investigation was 50 d/m/l (Bioassay Results, 1966). Data results 

occasionally included a breakdown by job categories that included operators, technicians, engineers, 

foremen, and guards. Sample analysis incorporated gross activity counting methods to determine 

uranium activity levels (Urinalysis Results, 1965-68). Expansion of the routine bioassay program to 

include additional radionuclides did not occur within the AWE operational period ending December 

31, 1973. 

The urinalysis sampling program was discontinued as of January 1, 1961. Plant management cited 

two primary factors: The program, in their view, had been in place for a sufficient period of time to 

furnish “reliable data for an overall evaluation of concentrations that may be routinely found in 

urinalysis samples from personnel working in the licensee’s Hematite plant.” Secondly, the program’s 

cost was compared to its value “as a real and practical device for routinely measuring radiation 

exposure.” The plant determined that bioassay services would be provided “where desirable or 

necessary” as required by 10 C.F.R. 20 (Compliance, 1961, pdf p. 14). 

The program was re-instituted in December 1962 following operational events where several plant 

operators in the Red Room had higher intakes to airborne radioactive materials than expected and a 

higher probability of reportable overexposures during the first six months of the program. These 

intakes exceeded 10 C.F.R. 20 limits and were reported to AEC officials (Various authors, 1963, pdf 

p. 47). In August 1963, several individuals were selected for follow-up whole-body counting 

radiation measurements at the DOE Y-12 nuclear weapons plant (Estimated Exposures, 1963; In Vivo, 

1964; Oak Ridge Trip, 1963; Various authors, 1963). A more complete discussion is provided in the 

next section. 

Although the urinalysis program continued uninterrupted from 1962 through the remainder of the 

operational period (1973), the site contracted with a new sample analysis vendor in 1971. In the 

1980s, this vendor was determined to have protocol discrepancies in the urinalysis work it performed 

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for other government sites. For all EEOICPA-related work, NIOSH has adopted the conservative 

position that analytical results provided by this vendor are suspect and thus are deemed unreliable. 

For this SEC evaluation report, this administrative decision impacts UNC-Hematite urinalysis data 

only for the period 1971 through 1973. There is no impact from this vendor on other applicable 

monitoring for this site for the period under evaluation. 

Table 6-1 summarizes by year the number of Energy Employees and the minimum number of 

bioassay samples collected during the operational period. The bioassay program emphasized 

production workers (operators) in the processing areas (e.g., Item Plant, Red Room) as these locations 

represented the workers receiving the highest internal exposures. Bioassay information for “nonoperators” was limited and is reported for one year (1968). UNC-Hematite evaluated bioassays by 

different analytical protocols, including enriched and fluorometric uranium techniques. 

Table 6-1: Summary of Urinalysis Samples Collected During the Operational Period 

Year No. of Energy Employees Minimum No. of Urinalysis Samples SRDB Ref IDs 

1958 19 7 62301 

1959 41 138 17606 

1960 37 106 17606 

 1961* 0 0 N/A

 1962* 74 196 11713, 11714, 11724 

1963 110 1730 11713, 11714, 11724 

1964 45 1537 62390 

1965 57 1238 62386 

1966 87 1351 62383 

1967 64 1320 62381 

1968 116 (operators) 1626 62379 

1968 74 (non-operators) 228 62379 

1969 131 (operators) 1980 62377 

1970 45 158** 62373 

1971 *** *** *** 

1972 *** *** *** 

1973 *** *** *** 

* From January 1, 1961 through December 1962, the routine bioassay program was discontinued. During this period, 

site management agreed to collect bioassay samples on a limited basis as warranted by operational situations 

(Compliance, 1961, pdf p. 13). In 1962, elevated air sampling results were obtained in process areas and bioassay 

samples were collected from selected workers. The routine bioassay program was re-instituted in December 1962 

(UNC In Vivo, 1963-1965; Various authors, 1963, pdf pp. 57-63). 

**	 Includes sample data from review of petition claims record. 

*** For the years 1971-73, routine urine sampling continued and the urinalysis data are available; however, the analytical 

results from the vendor are considered unreliable. The number of employees sampled under the site bioassay program 

and the number samples forwarded to the vendor are consistent with workforce levels for preceding years (1971: 789 

samples for 106 employees; 1972: 326 for 42 employees; 1973: 423 samples for 88 employees). 

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Whole Body Counting Data 

Direct (in vivo) bioassay data, as a component of a routine whole-body counting (WBC) program, 

were identified for the years 1968-1973 (In Vivo and Bioassay, 1960s; In Vivo Counts, 1967-73; 

Whole Body, 1969; Whole Body Counts, 1968-73; Whole Body Issues, 1968-69). These years 

represented the period when this methodology was becoming more widespread within the nuclear 

industry. UNC-Hematite contracted Helgeson Nuclear Services, Inc., to conduct WBC for evidence 

of U-235 intakes. 

WBC was also conducted during the years 1963, 1964, and 1965 for several workers, using “total 

body” counters available at the Y-12 plant in Tennessee (Estimated Exposures, 1963; In Vivo, 1964; 

Oak Ridge Trip, 1963; Various authors, 1963). Emphasis was placed primarily on several workers 

who had received elevated internal exposures in the Red Room (exceeding 10 C.F.R. 20 limits). The 

analysis was performed to assay the amount (micrograms) of U-235 in the workers’ lungs. Probable 

causes of the exposures, according to plant correspondence, were the lack of appropriate containment 

associated with the milling of uranium oxides and surface (hand) contamination. The workers were 

tracked for three years to confirm that U-235 levels in the body had decreased. 

Other employees were also assayed for uranium at Y-12 during these years but not on a consistent 

basis. There was one specific internal assessment for thorium evaluated at Y-12 in 1965 with a 

subsequent “0” result (UNC In Vivo, 1963-1965). A specific explanation for the additional worker 

selection and thorium evaluation has not been determined either through available documentation or 

interviews conducted with site employees (Personal communications, 2009a and 2009c). The 

monitoring results for these workers are available to NIOSH (UNC In Vivo, 1963-1965; Various 

authors, 1963). 

Air Monitoring Data 

Considerable air monitoring data were also located. These data include periodic uranium airborne 

studies (General Survey, 1959; Uranium Dust, 1962) and air samples collected at specific plant 

locations over a week’s period and assigned to individual workers (AEC Visit, 1963; Dust Exposure, 

1962). Air samples were also routinely collected during the covered period in operational areas such 

as (but not limited to) the Red Room, Blue Room, Green Room, Item Plant, Pellet Plant, Oxide Plant, 

and the Blending Room (a summary of the available air monitoring data is provided in Table 6-2). 

Results were provided in units of μc/ml per the reporting convention in place during this time, and as 

was the case for bioassays by urinalysis, again emphasized exposure to uranium. As noted previously, 

this Evaluation Report will cite results using the measurement units employed during the operational 

period. 

Former site employees interviewed for this report emphasized that during the covered period, 

alpha-emitting radionuclides were the primary source of exposure rather than beta contributors. 

Consequently, potential alpha internal exposures received significant attention by UNC-Hematite 

radiological personnel (Personal communications, 2009a and 2009c). 

Air samples, specifying “ThO2” as the compound of interest, were also identified and evaluated. 

These samples were collected in the Pellet Plant in 1964 (Pellet Plant, 1964; Smear Surveys, 1966) 

and were related to processing thorium dioxide pellets and mixing them with uranium dioxide pellets 

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in the test production of thorium-uranium breeder reactor fuel elements. Over two hundred thoriumdesignated samples were collected; airborne concentrations were routinely less than 2x10-11 

μc/ml, the 

MAC established by UNC-Hematite for thorium work. Approximately 10% of the concentrations 

were greater than 1x10-10 μc/ml (the uranium MAC for that time period) and were associated with 

unusual events. The maximum result for the data representing UNC-Hematite’s Th-U fuel effort, 1.6 

x 10-8 μc/ml, was associated with a spill. Based on NIOSH’s review, the range and limits of this set of 

air sample data is comparable to the uranium airborne concentrations associated with the uranium 

work performed at the Pellet Plant and other plant areas. Based on the information in the air sample 

data sheets, the samples represent a combination of general area/high volume, process, breathing 

zone/lapel, stack, and hood air sample data (Pellet Plant, 1964; Smear Surveys, 1966). Several 

breathing zone air samples were identified in these data sets. Although the thorium air samples have 

notations indicating that they are thorium-related air samples, NIOSH was unable to confirm that 

specific analyses for thorium isotopes (e.g., Th-232) were conducted. 

Uranium area air samples were also collected in “clear” (clean) areas—such as the warehouse, lunch 

room, guard station, offices and bathrooms (Non-process Air Samples, 1961-63; Non-process Air 

Samples, 1964) - and at fence-line and off-site locations (Air Sample Summaries, 1963). These data 

can be compared to data collected from occupational areas. 

Smear Data 

Smear data, used as a measure of removable or transferable contamination, and therefore, as a 

potential supplemental means to assess inhalation and ingestion doses, were identified for the years 

1961-64, 1966, and 1971-72. This information was limited to partial years, collected on equipment, 

floor, and other surfaces, and for both “clear” (clean) and potentially- contaminated areas (Floor 

Swipes, 1962-64; Non-process Air Samples, 1961-63; Plant-wide, 1963; Smear Report, 1964; Smear 

Survey, 1964; Smear Surveys, 1966; Smear Survey, 1971; Smear Survey, 1972). Additional smear 

data, other than the data previously described, were not identified by NIOSH. However, NIOSH 

believes that additional data exist based on the plant’s health physics procedures that required the 

conduct of contamination surveys at a specified frequency (HP Manual, 1963, pdf p. 45). 

6.2 Available UNC-Hematite External Monitoring Data 

External monitoring data available to NIOSH consist of film badge results covering the entire 

operational period under evaluation. All UNC-Hematite employees were assigned a “Health Number” 

that was used in part to track worker doses. These results were identified during two on-site data 

capture trips to the UNC-Hematite facility in March and April 2009. Table 6-2 summarizes available 

external monitoring data for the operational period. 

An August 1958 AEC compliance inspection of MCW’s Hematite facility states personnel monitoring 

was conducted by routine use of film badges, bioassay, and physical examination (AEC, 1958). Film 

badges were obtained from the St. John X-Ray Laboratory in New Jersey and distributed on a 

frequency determined by individual job assignment. Permanent operating personnel were monitored 

on a weekly basis and rotating personnel were monitored monthly. 

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In January 1960, an AEC license compliance inspection reiterated that operations personnel working 

at the Hematite plant at that time were routinely monitored as part of a film badge program. Film 

processing was performed at the Mallinckrodt Chemical Works plant in St. Louis using a procedure 

patterned after the protocols established at the AEC Weldon Springs Plant (also operated by 

Mallinckrodt at that time). The film badges included an indium foil that could have been used to 

segregate personnel exposed in the event of a criticality event (Compliance, 1960; Personal 

Communications, 2009a and 2009c). According to the 1962 UNC-Hematite Health Physics Manual, 

all personnel assigned to the plant were issued a film badge upon entry to the facility (HP Manual, 

1963, pdf p. 15). Interviews with former site employees corroborated the use of film badges and the 

criticality foil (Personal Communications, 2009a and 2009c). 

Beta-Gamma 

During the operational period, the following AEC regulatory radiation exposure limits were in effect: 

• Whole body (including lens of eye): 3 rem per quarter (beta plus gamma) 

• Skin of whole body: 6 rem per quarter (beta plus gamma) 

The unit “rem” was cited specifically in the AEC regulations—a convention that continues today 

under the NRC’s 10 C.F.R. 20 radiation protection regulations. However, compliance inspections 

described in this section and other references in this Evaluation Report, cite other radiation units. 

These include the “rad” and the “rep,” or the units “millirad” (mrad) and “millirep” (mrep), 

representing a dose one thousand times smaller. In this Evaluation Report, the units specifically cited 

in reference documentation will be used. As a simplification, however, for results pertaining to beta 

and gamma radiations, a rad (millirad) or rep (millirep) can be considered equivalent to a rem 

(millirem). 

As stated in the 1958 AEC compliance inspection, “The average exposure of Hematite plant personnel 

during the past year, as indicated by the records, was 80 mrad due to beta radiation and 36 mrad due to 

gamma radiation. The maximum single six months accumulative exposure recorded as due to beta 

was 2,525 mrad while the maximum due to gamma was 380 mrad.” The report, however, did not 

identify the number of plant workers specifically monitored (AEC, 1958). 

The January 1960 AEC inspection report for site license renewal (applicable to the 1959 reporting 

period) stated plant exposures somewhat differently than the 1958 inspection in terms of the reporting 

period (monthly) and reporting units. The occupational external dose monthly average badge results 

for beta radiation were 80-90 millirep (mrep); the maximum monthly result was 240 mrep 

(Compliance, 1960). The “rep”—an abbreviation for “roentgen equivalent physical”—was a radiation 

unit still in use at that time. One rep was generally defined as the amount of ionizing radiation of any 

type (e.g., alpha, beta, gamma radiation) resulting in the absorption of energy at the point in question 

in soft tissue equivalent to 93 ergs per gram. One rep was equivalent to 1000 mrep. As previously 

stated, for the purpose of this report, it is considered equivalent to a dose in millirad or millirem 

(mrem). 

The 1960 compliance inspection report also states “Gamma readings to 15 mrem for the monthly 

program are also recorded.” This was reported as applicable to workers in the production areas. The 

report also indicated that readings were lower for all other monitored workers (i.e., pilot plant, 

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laboratory, and maintenance personnel). When extrapolated to an annual dose, the resulting 180 

mrem value (15 mrem per month times twelve months) would be representative of certain 

UNC-Hematite workers during the entire operational period. At the same time, however, the 

maximum (“to 15 mrem”) monthly gamma radiation exposure results for 1959—also included in the 

UNC-Hematite TBD (Battelle-TBD-6001, Appendix D)—are significantly lower relative to many 

workers monitored during all other years of the operational period. The explanation resides in the 

methodology for reconstructing external dose in the UNC-Hematite TBD. The methodology for 

reconstructing external dose in the TBD assessed the limited personnel dose information available at 

the time the TBD was developed to establish a maximum external exposure scenario. The evaluation 

in this report will include (as appropriate) recently-collected personnel external monitoring data not 

available to NIOSH when the TBD was developed in conjunction with the TBD methodology. 

During March 20-23, 1961, another AEC compliance inspection was conducted. Regarding the 1960 

external monitoring period, the report stated that no exposures were identified exceeding 10 C.F.R. 

Part 20 limits in effect prior to January 1, 1961 with “some few readings up to 100 mrem/wk but the 

majority of the readings were near the threshold of the film or no greater than 50 mrem/wk.” 

(Compliance, 1961) 

For the remaining years 1961-1973, annual film badge reports typically cited external beta and gamma 

exposures to personnel emitted from uranium isotopes and associated decay products (External 

Exposure Reports, 1963; External Exposure Reports, 1964; External Exposure Reports, 1965; Film 

Badge Summary, 1961; Film Badge Summary, 1962; Tabulation Sheet, 1966; Tabulation Sheet, 1967; 

Tabulation Sheet, 1969; Tabulation Sheet, 1970; Tabulation Sheet, 1971; Tabulation Sheet, 1972; 

Tabulation Sheet, 1973). Results were provided in these reports either as separate columns for beta 

and gamma dose, as collective “beta-gamma” results, or simply as a total “Exposure.” 

In contrast to the 1960 AEC inspection report, a broader range of maximum beta and gamma doses (in 

rem) were recorded in summary monitoring reports for 1961-1973. For the years 1961-1964, results 

were provided by calendar month and then compared to the “Maximum Permissible Dosages for a 

Calendar Quarter” or “Cumulative Quarterly Total” (e.g., as noted in the 1962 film badge summary 

report [Film Badge Summary, 1962]). A review of several end-of-quarter summary reports (ending in 

March, June, September, and December) for 1961-1964 revealed that the majority of the workers (70 

to 98%) received less than 0.25 rem on a calendar quarter basis (combined beta plus gamma). A much 

smaller percentage (up to 4%) would occasionally receive a quarterly dose of between one and two 

rem. No documentation was identified indicating that any site worker exceeded the quarterly limits. 

For the years 1965 through 1973, a different reporting format was used by UNC-Hematite by which 

annual dose totals (rem) were provided. Maximum employee exposures during these years (in 

chronological sequence) were 2.11, 6.35, 1.61, 5.98, 3.12, 4.91, 0.67, 2.57, and 6.64 rem (Tabulation 

Sheet, 1965; Tabulation Sheet, 1966; Tabulation Sheet, 1967; Tabulation Sheet, 1968; Tabulation 

Sheet, 1969; Tabulation Sheet, 1970; Tabulation Sheet, 1971; Tabulation Sheet, 1972; Tabulation 

Sheet, 1973). The lowest and highest values occurred in 1971 and 1973, respectively. The overall 

higher maximum values for 1965-1973 should not be interpreted as a consequence of the change from 

the 1961-1964 reporting format. A worker under the prior quarterly reporting system could 

conceivably meet or exceed these values when projected over an entire year. However, NIOSH was 

not able to determine the specific reason for the elevated maximum annual doses for 1965-1973 

relative to prior years. 

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NIOSH’s review of badging records also identified employees who were issued film badges that did 

not have job assignments in uranium-processing areas. Examples included employees assigned to 

office areas (Terminated, various years). This serves to confirm the “universal” aspect of the badging 

program (HP Manual, 1963, pdf p. 15). 

In addition to documentation containing dose summary information and reports for the years 1958 

through 1973, NIOSH received external monitoring records for former workers in the claim pool for 

the years 1961 through 1993 (monthly exchange) and 1994 through 2003 (annual exchange). 

Documentation was also identified pertaining to the conduct of routine site radiation and 

contamination surveys in clear and contaminated areas of the plant (AEC, 1960; Compliance, 1961; 

Beta-Gamma Survey, 1965; Hand Monitor, 1963; Plant-wide, 1963; Smear Survey, 1964). Surveys 

were required per the plant’s health physics manual and licensing requirements (AEC, 1960; HP 

Manual, 1963). 

Neutrons 

NIOSH reviewed available UNC-Hematite documentation to identify records related to neutron 

exposures. Records reviews included Health Physics procedural manuals, AEC regulations and 

licensing inspections, dosimetry records, and site radiation survey records. While UNC-Hematite 

received and processed uranium in various forms (including uranium hexafluoride), neutron exposures 

were not identified as a radiological concern by plant personnel either as a component of routine plant 

operations or the external dose monitoring program (Health Program, 1962; HP Manual, 1963; HP 

Standards, 1968). The AEC’s 10 C.F.R. 20 1961 regulations, Sections 20.201 (Surveys) and 20.202 

(Personnel Monitoring), only generally referred to the need to conduct surveys and provide 

monitoring devices. No specific requirement existed to conduct neutron surveys and track neutron 

personnel exposures (10 C.F.R. 20, pdf p.13). AEC licensing inspection reports did not cite the lack 

of routine neutron monitoring as a concern or recommend any action in this regard. No radiological 

monitoring records specifying exposure to neutron radiation were identified and UNC-Hematite did 

not list portable neutron instrumentation in its inventory (AEC, 1958; AEC, 1960; Compliance, 1961). 

A technical basis exists to justify the lack of routine neutron monitoring. A NIOSH hazard evaluation 

report for the Portsmouth Gaseous Diffusion Plant, cited and discussed in the Portsmouth External 

Dose TBD, assessed neutron dose rates on contact and at one meter from high-enriched uranium 

(ORAUT-TKBS-0015-6; Cardarelli, 1996). The report explored several radiation exposure scenarios, 

including different enrichments and worker stay times and concluded that, as a percentage of the 

applicable regulatory dose limits, neutron monitoring was unnecessary. In the case of UNC-Hematite, 

the site operator may also have concluded, based on operational history and/or regulatory compliance 

thresholds, that neutron monitoring was not warranted. In an interview with an individual who 

worked during the operational period, the person could not recall any specific discussions or 

correspondence during his tenure concerning a technical basis justification for or against a routine 

neutron survey and personnel monitoring program (Personal communications, 2009c). 

Because NIOSH did not identify radiological survey records addressing neutron personnel exposures, 

the neutron dose at UNC-Hematite will be estimated using other methods. Further discussion is 

provided in Section 7. 

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Although neutron exposure was not a site concern under normal operations, the potential for a nonroutine (accident) criticality event in the plant received significant attention following the Y-12 

criticality accident in 1958. UNC-Hematite purchased a radiation detection and alarm system (AEC, 

1958). In addition, the plant conducted frequent plant inspections, including routine instrumentation 

and alarm-operability checks, implemented corrective actions to avoid the potential for a criticality, 

and incorporated an indium foil in film badges to detect the presence of neutrons in the unlikely event 

of an accident. 

6.3 Summary of UNC-Hematite Available Monitoring Data 

Table 6-2 summarizes internal and external monitoring data available to NIOSH for the covered 

period. Values in the table for each data type represent either the minimum number of samples or 

measurements taken (for urinalysis, air samples, and smears) or the number of energy employees 

monitored (for whole body counting and film badge data). Summary data include samples collected 

from process and non-process (clean) areas. In some instances, information was either unavailable or 

present in limited quantities due to the manner in which the information was reported by the site 

during that period, or because NIOSH was unable to locate that information during data capture 

efforts. 

Table 6-2: Summary of UNC-Hematite Available Internal and External Monitoring Data 

Year 

Internal External 

Bioassay 

(Urinalysis) 

Bioassay 

(WBCRoutine) 

Bioassay 

(WBC-NonRoutine)1 

(SRDB ID) 

Dust/Air 

Sampling 

(SRDB ID) 

Smears 

(SRDB ID) 

Film Badges 

(SRDB ID) 

1958 7 --- --- 21 (3944) --- X2

 (3822) 

1959 138 --- --- 305 (62357) 

65 (3944) 

1620 (17606) 

--- X2

 (3944) 

X2

 (7145) 

1960 106 --- --- 1429 (17606) --- X2

 (56196) 

19613 0 --- --- 29 (62285) 

3 (62282) 244

 (62171) 150 (62278) 

38 (62283) 

112 (62276) 

294

 (62171) 

1962 196 --- --- 58 (62172) 10 (62352) 153 (62277) 

5 (62285) 53 (62345) 

4 (62282) 164

 (62345) 

21 (62276) 

35 (62306) 

4 (62345) 

64 (62171) 

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Table 6-2: Summary of UNC-Hematite Available Internal and External Monitoring Data 

Year 

Internal External 

Bioassay 

(Urinalysis) 

Bioassay 

(WBCRoutine) 

Bioassay 

(WBC-NonRoutine)1 

(SRDB ID) 

Dust/Air 

Sampling 

(SRDB ID) 

Smears 

(SRDB ID) 

Film Badges 

(SRDB ID) 

1963 1730 --- 5 (62318) 17 (62285) 

30 (62428) 

199 (62432) 

122 (62340) 

4 (62282) 

38 (62279) 

9 (62283) 

13 (62356) 

14 (62341) 

7 (62343) 

5635

 (62276) 

16 (62170) 

17 (62178) 

84

 (62171) 

356

 (62355) 

274 (62352) 

44 (62426) 

61 (62276) 

102 (62274) 

1964 1537 --- 4 (62314) 2927 (62168) 

445 (62279) 

578 (62356) 

8607

 (62343) 

125 (62348) 

246 (62341) 

3024

 (62361) 

8506 (62355) 

797 (62320 

and 62352) 

28 (62356) 

25084

 (62320, 

62352, 62358) 

130 (62272) 

1965 1238 --- 5 (11724) X2

 --- 137 (62271) 

1966 1351 --- --- 12 (62298) 665 (62384) 

4674

 (62384) 

139 (62180) 

1967 1320 --- --- 2 (62428) --- 127 (62267) 

1968 1854 118 (62412) --- 5390 (62300) --- 169 (62187) 

1969 1980 1039

 (62334, 

62412) 

--- X2 --- 182 (62266) 

1970 15810 67 (62020, 

62175, 

62419) 

--- 1169 (62207) 

65404

 (62184) 

6084

 (62186) 

3355 (62200) 

--- 213 (62231) 

1971 ---

11 71 (62020, 

62175, 

62419) 

--- 36 (62142) 

54854

 (62186) 

2965 (62212) 

478 (62442) 

4794

 (62442) 

64 (62229) 

1972 ---

11 48 (62020, 

62175, 

62419) 

--- 97 (62144) 

17 (62146) 

304

 (62149) 

314

 (62152) 

4974

 (62154) 

7034

 (62139) 

314

 (62140) 

52944

 (62155) 

101 (62436) 

5484

 (62436) 

93 (62227) 

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Table 6-2: Summary of UNC-Hematite Available Internal and External Monitoring Data 

Year 

Internal External 

Bioassay 

(Urinalysis) 

Bioassay 

(WBCRoutine) 

Bioassay 

(WBC-NonRoutine)1 

(SRDB ID) 

Dust/Air 

Sampling 

(SRDB ID) 

Smears 

(SRDB ID) 

Film Badges 

(SRDB ID) 

1973 ---

11 90 (62020, 

62175, 

62419) 

--- 66 (62137) 

44 (62146) 

154

 (62145) 

274

 (62152)

 2565

 (62139) 

274

 (62140) 

10804

 (62154) 

48944

 (62155) 

--- 64 (62225) 

1	 Whole body counting for a maximum of five site employees was conducted annually from 1963-1965 at the DOE 

Y-12 plant, Oak Ridge, Tennessee. Note: A subset of workers receiving exposures at UNC-Hematite were evaluated 

for because of potential elevated uranium/thorium exposures. 

2	 “

X” indicates that data exist, but the specific number of samples collected or individuals monitored was not available. 

3	 From January 1, 1961 through December 1962, the routine bioassay program was discontinued. During this period, 

site management agreed to collect bioassay samples on a limited basis as warranted by operational situations 

(Compliance, 1961, pdf p. 13). However, air sampling (including BZ and GA samples) continued in the work areas 

over this time period (Air Sample Data, 1961; Assorted Results, 1963; Overexposure Report, 1976; Green Room, 

1961-63; Air Sample Data, 1961-63; Pellet Plant, 1961-62; Uranium Dust, 1962; Blue Room, 1960-63; Blue Room, 

1962-63). In 1962, elevated air sampling results were obtained in process areas; consequently, bioassay samples were 

collected from selected workers. As a result of these elevated exposures, the routine bioassay program was reinstituted in December 1962 (UNC In Vivo, 1963-1965; Various authors, 1963, pdf pp. 57-63). 

4	 Collected in non-process areas (e.g., warehouse, lunch room, offices) other than fenceline (see Footnote 6). 

5	 Includes CUNO filter stack and additional stack samples. 

6	 Non-process fenceline samples. 

7	 Includes over 200 thorium samples. 

8	 Data available for one month in 1968. 

9	 Data only available for March, June, and December 1969. 

10	 Includes both routine and suspected overexposure samples. 

11	 For the years 1971-73, urinalysis data are available, but the analytical results from the vendor are considered 

unreliable (see Table 6-1 footnote). 

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7.0 Feasibility of Dose Reconstruction for the Class Evaluated by 

NIOSH 

The feasibility determination for the class of employees under evaluation in this report is 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 7.1. 

This approach is discussed in OCAS’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-00116 as submitted by the petitioner. (Section 7.4) 

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7.1 Pedigree of UNC-Hematite 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 

Two one-week data capture visits were conducted at the former UNC-Hematite site in March and 

April 2009. NIOSH now has reliable routine urinalysis for most years of the operational period 

(1958-1973) with the following exceptions: (1) January 1961 through early December 1962, during 

which time the program was discontinued [Compliance, 1961, pdf p. 13]; and (2) 1971-73 for which 

the vendor’s analytical vendor’s results are considered unreliable. Although bioassay samples were 

collected on a limited basis during the 1961-62 period (as warranted by operational occurrences), a 

routine bioassay program was not re-instituted until December 1962 (UNC In Vivo, 1963-1965; 

Various authors, 1963, pdf pp. 57-63). NIOSH also has routine air sampling data for the entire 

operations period. Whole body counting as an assay methodology for U-235 was used by UNCHematite beginning in the latter 1960s. This corresponds with the time when the use of whole body 

counting became more widespread within the nuclear industry. Contamination smear results for a 

portion of the covered period are also available. 

All these data are contained in primary sources (i.e., handwritten or typed documents). The data are 

legible (with some exceptions involving hand-written documentation). Appropriate reporting units 

were used. NIOSH reviewed the urinalysis reports received by UNC-Hematite from the main analysis 

vendor, Nuclear Science and Engineering Corporation [NSEC] (UNC urinalysis, 1962-1964; Bioassay 

Results, 1964; Bioassay Results, 1965; Bioassay Results, 1966; Bioassay Results, 1967; Bioassay 

Results, 1968; Bioassay Results, 1969; Special Bioassay, 1970) and two additional vendors, Controls 

for Radiation Inc., and Isotopes, Inc., that provided urinalysis results beginning in mid-1967 (Bioassay 

Vendor Results, 1967). The evaluation methods employed by the UNC-Hematite analytical vendors 

during the covered period focused on exposure to U-235 and alpha radioactivity. As discussed, 

NIOSH has access to personnel bioassay data for the entire operational period with the exception of 

1961-62 and 1971-73. Nevertheless, during those periods, the site maintained a routine air sampling 

program, including breathing zone (BZ) and general area (GA) air samples (discussed below). These 

data, coupled with the other sources of information and data discussed below, are of sufficient 

quantity and quality to support the ability to bound internal dose for the UNC-Hematite class under 

evaluation. 

Several original, handwritten dust monitoring results (General Survey, 1959; Uranium Dust, 1962) as 

well as air sampling results (Air Sample Data, 1963; Air Sample Log, 1964; Assorted Results, 1963; 

Blending Room, 1961-63; Blue Room, 1962-63; Green Room, 1964; Item Plant, 1964; Uranium Dust, 

1962) and employee termination summaries (Terminated, various years) were identified. These data 

are legible with some exceptions (especially for years early in the operational period). Appropriate 

reporting units were used. Based on its review of the available data, NIOSH has access to air sample 

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data that can be used to supplement the bioassay data. These data include breathing zone (BZ) and 

general area (GA) air samples for the UNC Hematite work areas from 1961-1962 during the period 

when UNC-Hematite discontinued its personnel bioassay program. 

Air sampling emphasized uranium alpha monitoring and evaluation. An exception was the short-term 

workplace air monitoring for thorium conducted in the Pellet Plant for work performed in 1964 

associated with the thorium-uranium fuel pellet work. A former site employee stated that it was 

highly unlikely that “dedicated” workers were assigned to the Pellet Plant for this project alone 

(Personal Communications, 2009a). 

The thorium-uranium fuel pellet activities involved work with thorium dioxide powder and the 

concern was alpha radioactivity. Air samples, designated specifically as “ThO2” (thorium dioxide) 

were collected in the Pellet Plant during 1964 (Pellet Plant, 1964; Smear Surveys, 1966). NIOSH 

identified the collection of over two hundred “ThO2” samples. The highest airborne concentration 

reported, associated with a spill, was 1.6 x10-8 μc/ml (Pellet Plant, 1964, pdf p. 60) though the vast 

majority of results were less than 1x10-10 μc/ml. These air sampling results are handwritten 

documents and are legible. NIOSH’s analysis of these results, which represent a combination of 

general area/high volume, process, breathing zone/lapel, stack, and hood air sample data, indicate that 

the results are representative of all operations performed during the Th-U fuel pellet work (Pellet 

Plant, 1964; Smear Surveys, 1966). These results are similar to the range of available uranium air 

sample values. In addition, there is documentation discussing the application of Maximum Allowable 

Concentrations (MAC) values for the thorium work, including discussion of administrative limits and 

adjusted MAC values for mixtures of radionuclides (Pellet Plant, 1964; Smear Surveys, 1966; ThO2-

UO2, 1964). Based on this information, NIOSH concludes that the data are of sufficient pedigree to 

support the evaluation of the thorium dose for UNC-Hematite’s Th-U fuel pellet work performed 

during 1964. 

NIOSH identified routine whole-body counting results for 1968 through 1973 (In Vivo and Bioassay, 

1960s; In Vivo Counts, 1967-73; Whole Body, 1969; Whole Body Counts, 1968-73; Whole Body 

Issues, 1968-69). The site contracted with Helgeson Nuclear Services, Inc. for this service. The 

analysis emphasized the detection and quantification of gamma rays emitted from U-235. These data 

are in original form (either hand-written or typed documents) and are legible. Results for 1968 and 

1969 are limited relative to other years; data for only one month in 1968 and three months in 1969 

were identified. The contractor’s operations and processes for personnel counting are provided or 

available for the personnel counts. As the personnel urine bioassay are available for the time period 

that in vivo/whole body counts were performed, the in vivo data can be used to supplement the 

available urine bioassay data for bounding the dose for the UNC-Hematite class under evaluation. 

NIOSH also has several investigation reports, correspondence and analyses on elevated internal 

exposures pertaining to unanticipated operational events in 1962 for which a group of individuals 

were sent to Oak Ridge during three consecutive years (1963-1965) for in vivo monitoring for U-235 

at the Y-12 plant (Estimated Exposures, 1963; In Vivo, 1964; Oak Ridge Trip, 1963; Various authors, 

1963). A more complete discussion is provided in Section 6.1. These data are in original form (either 

hand-written or typed documents) and are legible. These data can be used, as applicable, to 

supplement the evaluation of internal dose for the specific time frame of the site’s review, for the 

UNC-Hematite class under evaluation. 

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Smears for evidence of removable contamination are available for 1961-1964, 1966, and 1971-1972 

(Plant-wide, 1963; Smear Report, 1964; Smear Survey, 1964; Smear Surveys, 1966; Smear Survey, 

1971; Smear Survey, 1972). Original smear data were reviewed from restricted and clean (nonprocess) areas of the plant. Smears were also collected on respirators for evidence of radioactive 

contamination. Because the data provided to NIOSH was handwritten, legibility in certain 

circumstances was a factor. Additional data presumably exist because the plant’s health physics 

procedures required the conduct of contamination surveys at a specified frequency (HP Manual, 1963, 

pdf p. 45). However, because internal dose estimates employ bioassay results (supplemented with air 

sample and in vivo data) as the primary means of dose assessment, and these bioassay (and air sample) 

data are available, the acquisition and pedigree analysis of additional smear data was not performed 

for this evaluation. 

Based on the information available to NIOSH, UNC-Hematite management and supervisory staff 

tracked and reported worker exposures as required by 10 C.F.R. 20 and implemented corrective 

actions when necessary. This included job rotations to reduce exposures (Assignments, 1969; 

Urinalysis Results, 1960; Whole Body Issues, 1968-69, pdf p. 14) and additional urinalyses and whole 

body counting (see the discussion above regarding Y-12’s assistance with evaluating elevated worker 

exposures). The total number of site workers during the covered period is not clear; however, a 

universal badging policy was applied (HP Manual, 1963, pdf p. 15). A review of urinalysis data 

indicates that an average of 76 workers was monitored annually for internal exposures (External 

Exposure Reports, 1963; External Exposure Reports, 1964; External Exposure Reports, 1965; Film 

Badge Summary, 1961; Film Badge Summary, 1962; Tabulation Sheet, 1966; Tabulation Sheet, 1967; 

Tabulation Sheet, 1969). An annual summary of exposures for 1961 indicated that 150 employees 

were monitored for external exposures and 132 via air monitoring. Results of that monitoring relative 

to the federal radiation regulatory limits were documented. This included those operational and 

supervisory workers involved in uranium enrichment activities in the Green, Blue, and Red Rooms, 

and the Item Plant. 

In summary, bioassay and air sampling data are available in sufficient quantity and quality to 

adequately represent internal dose for the UNC-Hematite class under evaluation over the entire 

operational period. These data, applied as defined in the UNC-Hematite TBD (Battelle-TBD-6001, 

Appendix D), can also be used to support the evaluation of the UNC-Hematite internal dose over the 

site’s residual radioactivity period. Multiple site documents were located containing bioassay and air 

sampling results for the covered period. Reliable routine urinalysis data are available for the entire 

operational period with the exception of 1961-62 and 1971-73. Daily and weekly air samples were 

collected in operational and clean areas of the facility per procedure (HP Manual, 1963, pdf p.11). 

The available air sample data, including BZ and GA data, are available and can be used to supplement 

the bioassay data, or as the primary source of internal monitoring data for the period from 1961-1962. 

In addition, NIOSH has access to other radiological monitoring data and investigation reports that 

support bounding internal dose for the UNC-Hematite class under evaluation. 

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7.1.2 External Monitoring Data Pedigree Review 

The external monitoring data, based on film badge dosimetry results, are available in sufficient 

quantity and quality to adequately represent the class under evaluation. Between 100 and 200 

employees were monitored on any given year during the operational period (External Exposure 

Reports, 1963; External Exposure Reports, 1964; External Exposure Reports, 1965; Film Badge 

Summary, 1961; Film Badge Summary, 1962; Tabulation Sheet, 1966; Tabulation Sheet, 1967; 

Tabulation Sheet, 1969; Tabulation Sheet, 1970; Tabulation Sheet, 1971; Tabulation Sheet, 1972; 

Tabulation Sheet, 1973). With limited exceptions (some reported badge contaminations), no problems 

were reported by the analysis vendor in evaluating the film badges (External Exposure Reports, 1964; 

External Exposure Reports, 1965). 

The available external dosimetry data are primary source documents that contain the personnel 

monitoring (film badge) results for individual workers across the site. The data are legible and 

appropriate reporting units were used. There are documented reports of the practice of universal 

external monitoring using film badges (Compliance, 1960; HP Manual, 1963, pdf p. 15) as well as 

accounts from former UNC-Hematite workers confirming that universal badging was employed 

(Personal Communications, 2009a and 2009c). The monitoring results were provided in summary 

reports to the AEC. NIOSH also identified supporting source-term information contained in licensing 

documentation, and several summary work history external dose reports. 

In summary, the available external dosimetry monitoring data are available in sufficient quantity and 

quality to adequately represent external dose for the UNC-Hematite class under evaluation over the 

entire operational period. The dosimetry data are the primary data source that will be used to bound 

external dose for the UNC-Hematite class under evaluation. These data, applied as defined in the 

UNC-Hematite TBD, can also be used to support the evaluation of the UNC-Hematite external dose 

over the site’s residual radioactivity period. 

NIOSH did not identify any neutron dosimetry data; therefore, a pedigree review of neutron external 

dosimetry data was not possible. Based on its review of the available information, the potential 

neutron dose was evaluated using guidance contained in ORAUT-OTIB-0024, Estimation of Neutron 

Dose Rates from Alpha-Neutron Reactions in Uranium and Thorium Compounds (see Section 7.3 of 

this report). 

7.2 Evaluation of Bounding Internal Radiation Doses at UNC-Hematite 

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

uranium metal and uranium oxides in the form of radioactive particulates (Mallinckrodt, 1960). 

Thorium dioxide processing did not represent routine plant operations as it was a special project 

limited to a single time period in 1964. However, air samples to evaluate the presence of thorium 

were collected during this operation (Pellet Plant, 1964; Smear Surveys, 1966). The following 

subsections address the ability to bound internal doses, methods for bounding doses, and the 

feasibility of internal dose reconstruction. 

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7.2.1 Evaluation of Bounding Process-Related Internal Doses 

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. 

The primary contributor to internal radiation dose during the time period under evaluation was 

inhalation of uranium isotopes. To a much more limited extent, thorium exposure (thorium dioxide) 

was also a contributor (Pellet Plant, 1964; Smear Surveys, 1966). With the exception of 1961-62, 

internal monitoring data were collected annually (at a minimum) during the covered period via 

indirect bioassay (urinalysis) in order to evaluate alpha activity from uranium isotopes. There is a 

substantial quantity of bioassay data for uranium; however, urinalysis vendor results for 1971-73 are 

considered unreliable. Beginning in the latter 1960s, direct bioassay methods in the form of wholebody counting became more available. Data from such measurements are restricted to 1968-1973 

with limited results for 1968 and 1969 available for UNC-Hematite workers. Non-routine WBC was 

conducted during 1963-1965 at the Y-12 plant in Oak Ridge, Tennessee to address several elevated 

worker intakes in UNC-Hematite process areas (Estimated Exposures, 1963; In Vivo, 1963; In Vivo, 

1964; Oak Ridge Trip, 1963). 

In support of this evaluation, NIOSH obtained documentation through various means, including a 

finding aid provided by the current owner for use with several hundred boxes of site records. This 

information was reviewed and used in support of two data capture efforts at the Hematite facility near 

Festus, Missouri (March and April 2009). It is clear from these efforts that a credible radiation safety 

program was in effect at UNC-Hematite during 1958-1973 in conjunction with significant regulatory 

oversight by the Atomic Energy Commission. Based upon an initial review of site records, 712 boxes 

and 12 file cabinets were identified as containing site information and health physics related records 

for the time period under evaluation. A more focused review determined that 113 boxes and 29 files 

from the file cabinets were potentially valuable to the evaluation. NIOSH performed a labor-intensive 

on-site review of over 85 percent of these boxes in addition to the records identified from the file 

cabinets. 

Identified records include: correspondence on plant management and operating issues, radiological 

and contamination surveys, licensing documentation, general and special operating procedures, site 

inspections, audits, equipment and facilities descriptions, exposure reports, urinalysis reports, air 

sampling and monitoring results, radiation incident reports, radiation work permits, radioactive 

material handling, stack air monitoring, nasal smears, whole body counting, and As Low As 

Reasonably Achievable (ALARA) reports. 

These site-specific and health physics records indicate that uranium (and thorium) isotopes in various 

forms were handled, processed, and monitored. For example, glove-boxes were employed as 

engineering controls, airborne concentrations were monitored, personal protective equipment (PPE) 

(e.g., respirators) was used, surface contamination surveys were conducted, and radiation protection 

oversight was provided. 

NIOSH investigated the test production of Th-U fuel pellets performed at UNC-Hematite. Procedures 

for the use of thorium, license modifications to allow thorium work, and several references to thorium 

in the Historical Site Assessment documents were obtained; however, no purchases and/or shipments 

of thorium powder to or from the UNC-Hematite facility have been identified (United Nuclear HSA, 

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2003; Westinghouse, 2003). Nevertheless, interviews with former site employees confirmed that in 

1964 thorium dioxide was used in concert with uranium to produce mixed-oxide fuel pellets for use in 

breeder reactors like the Elk River Reactor Project (Personal Communications, 2009a and 2009c). 

Reviewed correspondence provided insights into UNC-Hematite management’s commitment to 

evaluate each individual’s internal exposures. Emphasis was placed on identifying a priori those 

individuals with significant potential for elevated radiation exposures, or a posteriori employing 

corrective measures to prevent re-occurrence. This included reassignments and job rotations 

employed as “ALARA-equivalent” measures to reduce unnecessary exposures (Assignments, 1969; 

Overexposures, 1963; Whole Body Issues, 1968-69). 

Various incidents that occurred during the covered period as a result of operational activities were 

documented. Examples include: external radiological overexposures per film badge results in 1963 in 

the Pellet Plant (Overexposures, 1963); UF6 releases in the Red Room in 1966 (UF-6 Release, 1966) 

and 1967 (UF-6 Release, 1967); an HEU release in the Red Room in 1967 (Personnel Exposure, 

1967); a UO2 release in the “Recycle” Room in 1968 (UO2 Release, 1968a); a Pellet Plant Press 

Hopper Release in 1968 (UO2 Release, 1968b); a UO2 release in the Red Room Milling Hood in 1969 

(UO2 Exposure, 1969); an HF6 release in the Oxide Building in 1969 (HF Leak, 1969); and various 

spills and releases in 1970 (Special Bioassay, 1970). 

7.2.1.1 Urinalysis Information and Available Data 

Uranium 

The largest intakes at UNC-Hematite involved isotopes of uranium. Internal exposure data from 

uranium isotopes for the entire covered period are readily available. The majority of the results are for 

in vitro (bioassay) sampling. UNC-Hematite implemented a bioassay (urinalysis) program, initially 

conducted on a routine basis, from the latter 1950s through 1960. This bioassay program was 

discontinued in 1961 and re-instituted in late 1962. The program incorporated gross counting 

methods to determine exposure to uranium. 

The routine bioassay program was not designed to monitor all UNC-Hematite workers. Rather, it was 

based on job assignment and those with exposure potential. Workers were divided into specific 

groups, provided with a urine sample schedule (Air Sample Summaries, 1963, pdf 19-20), and 

informed of their responsibilities to provide urine samples. Responsibilities typically entailed 

receiving a collection device prior to the weekend and returning the sample the following Monday 

(Personal Communication, 2009c). One of these groups was comprised of the plant operators who 

worked in all process areas containing low- to high-enriched uranium. Due to the nature of their job 

assignments, these workers had the greatest probability of exposure to uranium compounds. NIOSH 

confirmed through record reviews that each group, including operators, was routinely evaluated for 

uranium intakes. UNC-Hematite employed off-site vendors to determine the urinalysis results 

(typically reported in units of d/m/l) on a specified frequency and by employee. The availability of 

bioassay data for most of the covered period, coupled with the air sampling data and whole body/in 

vivo count data (discussed below), provides sufficient data to bound internal uranium doses for all 

operational years at UNC-Hematite. Based on this information, NIOSH can identify the maximallyexposed work group/scenario at the site. This information supports NIOSH’s ability to bound the 

internal uranium dose for the UNC-Hematite class under evaluation. 

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Thorium 

No specific personnel thorium bioassay data, other than one whole-body count, were located by 

NIOSH for the thorium work. The site did perform thorium air sampling (see Section 7.2.1.3). 

7.2.1.2 Lung Counting Information and Available Data 

Whole-body and lung counting was not commonplace in the 1960s and was limited to a few locations 

in the United States. As noted in Section 7.2.1.1, urinalysis was the primary bioassay method in place 

at UNC-Hematite during this period. However, beginning in 1968 and continuing until 1973 (the end 

of the covered period), there was increased use of direct bioassay as a routine monitoring method. 

The only other whole body/lung count information available for UNC-Hematite is for individuals who 

were identified for follow-up in vivo bioassay based on their urine bioassay results (identified as 

personnel with potential exposures to elevated airborne radioactivity levels in their work area). The 

exposures were the result of enriched uranium deposited in the lungs of the involved individuals. One 

source was the exposure to airborne concentrations in excess of the limits specified in 10 C.F.R. 20. 

Hand contamination was found to be another contributor. Individuals found to have exceeded 

allowable internal exposure limits were sent to the DOE Oak Ridge Y-12 plant in 1963 for lung 

counts. Follow-up annual urinalysis and lung count measurements for U-235 were taken in 1964 and 

again in August 1965 (Estimated Exposures, 1963; In Vivo, 1963; In Vivo, 1964; Oak Ridge Trip, 

1963). While uranium was the primary element of interest, there was one evaluation for exposure to 

thorium. These data are available to NIOSH (Various Authors, 1963), but are not considered the 

primary data source for the purpose of evaluating the ability to bound UNC-Hematite personnel 

internal dose. The available data can be used to supplement the urine bioassay data but the lack of 

in vivo/whole body count data does not preclude NIOSH’s ability to bound dose for the proposed 

worker class evaluated in this report. 

7.2.1.3 Airborne Levels 

Uranium 

Substantial airborne dust and air monitoring data, involving thousands of samples, were identified for 

the entire covered period. From 1961-1973, air samples were collected routinely in a variety of 

process and clean (“clear”) areas. In addition to urinalysis results (Section 7.2.1.1), these samples can 

be used as a means for reconstructing and supporting bounding estimates of UNC-Hematite internal 

doses during the operational period under evaluation. 

Thorium 

As discussed in this report, NIOSH has analyzed the thorium air samples associated with the Th-U 

pellet work at UNC-Hematite. These air samples represent a combination of general area/high 

volume, process, breathing zone/lapel, stack, and hood air sample data and are representative of all 

operations performed during the performance of the Th-U fuel pellet work (Pellet Plant, 1964; Smear 

Surveys, 1966). Of the two hundred plus available air samples taken during UNC-Hematite’s thorium 

work, more than 75% of the results were less than 2 x 10-11 

μc/ml, which was the thorium 

administrative MAC established by UNC-Hematite for thorium work (Pellet Plant, 1964; Smear 

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Surveys, 1966; ThO2-UO2, 1964). Most of the results greater than 1x10-10 μc/ml (the uranium MAC 

for that time period) were associated with unusual events or include descriptions related to unusual 

events (e.g., material spills). The maximum result for the data representing UNC-Hematite’s Th-U 

fuel work was associated with a spill; the value was 1.6 x 10-8 μc/ml (Pellet Plant, 1964; Smear 

Surveys, 1966; ThO2-UO2, 1964). These results are similar to the range of available uranium air 

sample values. Because the uranium work continued at the site during the same time and the same 

building as the thorium work, there are potential contributions from uranium airborne contaminants on 

the air samples. Because there is no indication that air samples were specifically analyzed for thorium 

isotopes, a bounding estimate of the thorium dose contribution could be accomplished by assuming 

that 100 percent of the particulates collected on the filters designated as thorium samples were due to 

thorium deposition. Based on this information, NIOSH concludes that the data are sufficient for use 

in evaluating its ability to bound thorium dose for the Th-U fuel pellet work performed at UNCHematite during 1964. 

Evaluation of the Impact of Changing Site Operators 

During a review of SRDB documents, nothing was located that implied or otherwise stated that 

Hematite site operations were affected in any material way with the change from UNC to Gulf United 

Nuclear Fuels Corporation (GUNFC) in the spring of 1970. Observed experience at other 

government-funded operational sites undergoing similar corporate mergers and business alterations 

would indicate that there were only minimal effects to the on-going day-to-day operations (e.g., Y-12, 

sequence of operators: Eastman, 1943-47; Union Carbide, 1947-84; Martin Marietta, 1984-94; 

Lockheed-Martin Energy Systems, 1994-98; BWXT Y-12, 1998 – present [ORAUT-TKBS-0014-2]). 

Beginning in 1957, MCW Hematite plant operating personnel submitted urinalysis samples based on 

specific work assignments (Compliance, 1960). An August 1958 MCW Plant Inspection stated that 

personnel monitoring was conducted by routine use of film badges, bioassay, and physical 

examination (AEC, 1958). Permanent operating personnel were monitored on a weekly basis and 

rotating personnel were monitored monthly. The urinalysis sampling program was discontinued as of 

January 1, 1961 but was re-instituted in December 1962, and continued for the duration of the 

operational period (Compliance, 1961). 

Internal monitoring data available for the operational period primarily consist of urinalysis, dust 

sampling, and air monitoring results. Results were compared to the applicable site administrative 

levels (maximum acceptable concentrations) and federal (10 C.F.R. 20) airborne radioactivity limits. 

Airborne exposure limits were established in 1959 with 5.0 x 10-ll 

μc/ml/40 hr. week the permissible 

level for uranium (AEC, 1960; Mallinckrodt, 1960). Additionally, health physics procedures were 

established to control exposures to personnel; they remained in effect throughout the operational 

period (HP Manual, 1963). 

NIOSH found no documentation to suggest there were changes in the level of operations from UNC to 

GUNFC. Operations under GUNFC continued under licenses C-2734 and SNM-33, which were in 

effect at the time of changeover (License Review, 1979). As shown in Table 7-1, continuous air 

monitoring records for the period of 1963-1973 do not show increases other than occasional “spikes” 

recorded in single-day measurements. Notations in the “comments” section of the data sheets indicate 

that these spikes accompany maintenance actions (filter changes, etc.) Neither the number of records 

nor the levels recorded indicated any increasing trends. This information, coupled with the 

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comparison of operations controls and methods, provides sufficient support for using the values in 

Battelle-TBD-6001, Appendix D to bound the potential exposures for the period. The 1963-1973 

timeframe has equivalent, or lower, potential exposures based on the data comparison. 

Table 7-1: Comparison of Air Sample Totals and Results for UNC and GUNFC Operations 

Year No. Dust/Air Samples 

(SRDB ID) 

High Sample 

(10-10 uCi/ml) 

Low Sample 

(10-10 uCi/ml) 

Sample Total 

for Year 

1963 17 (62285) 

30 (62428) 

199 (62432) 

122 (62340) 

4 (62282) 

38 (62279) 

9 (62283) 

13 (62356) 

14 (62341) 

7 (62343) 

563 (62276) 

16 (62170) 

17 (62178) 

8 (62171) 

35 (62355) 

0.48 

18.50 

27.00 

270.00 

1.20 

52.60 

0.38 

1022.5 

6.40 

0.45 

473.30 

4.90 

170.0 

1.30 

0.05 

.0013 

.008 

0.00017 

0.0011 

0.019 

0.001 

0.013 

0.014 

0.06 

0.02 

0.00 

0.005 

0.14 

0.00 

0.000 

1016 

1964 2927 (62168) 

445 (62279) 

578 (62356) 

860 (62343) 

125 (62348) 

246 (62341) 

302 (62361) 

850 (62355) 

26.79 

52.60 

188.30 

204.384 

26.79 

5.30 

1.172 

0.086 

0.000 

0.000 

0.000 

0.000 

0.000 

0.000 

0.000 

0.000 

6333 

1965 X --- --- X 

1966 12 (62298) 687.085 0.438 12 

1967 2 (62428) 1.373 0.033 2 

1968 5390 (62300) 39.175 0.000 5390 

1969 X --- --- X 

1970 1169 (62207) 

6540*

(62184) 

608* (62186) 

335 (62200) 

101.955 

4.611 

2.027 

18.612 

0.000 

0.000 

0.000 

0.000 

8652 

1971 36 (62142) 

5485*

(62186) 

296* (62212) 

12.473 

2.808 

10.562 

0.000 

0.001 

0.000 

5817 

1972 97 (62144) 

17 (62146) 

30* (62149) 

31* (62152) 

497* (62154) 

703* (62139) 

31* (62140) 

5294*

(62155) 

29.425 

1.461 

2.774 

.233 

7.864 

.030 

.233 

3.66 

0.0 

.004 

.004 

0.0 

0.0 

0.0 

.002 

0.0 

6700 

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Table 7-1: Comparison of Air Sample Totals and Results for UNC and GUNFC Operations 

Year No. Dust/Air Samples 

(SRDB ID) 

High Sample 

(10-10 uCi/ml) 

Low Sample 

(10-10 uCi/ml) 

Sample Total 

for Year 

1973 66 (62137) 

44 (62146) 

15* (62145) 

27* (62152) 

256* (62139) 

27* (62140) 

1080*(62154) 

4894* (62155) 

9.009 

2.774 

.169 

.233 

.18 

.205 

.012 

1.147 

.006 

.002 

0.0 

0.0 

0.0 

0.0 

0.0 

0.0 

6409 

“

X” indicates that data exist, but the specific number of samples collected was not available. 

* Includes CUNO filter stack and additional stack samples. 

7.2.2 Evaluation of Bounding Residual Period Internal Doses 

Although non-AEC-related radioactive materials work continued at UNC-Hematite after 1973, 

NIOSH is required to evaluate the potential internal exposures from the residual radioactivity that 

remained as a result of weapons-related work during the operational years at the site (1958-1973); 

under EEOICPA rules, this would not include the site’s Th-U pellet work. The weapons-related work 

performed during the covered operational years involved uranium only. For the purpose of bounding 

the internal uranium dose associated with the weapons-related residual radioactivity that remained on 

site after the end AEC-related operations, NIOSH can use the method defined in the UNC-Hematite 

TBD (Battelle-TBD-6001, Appendix D, Section D.6). For reconstructing internal dose, the method 

involves determining a maximum air concentration which is assumed to settle and accumulate over a 

predetermined amount of time at the end of the operations period. NIOSH can back-calculate the 

airborne concentration for use in this method based on the bounding/maximum intakes rates for the 

UNC-Hematite operational period, as discussed in Battelle-TBD-6001. The available air monitoring 

data for the site can be used to supplement the calculations and corroborate that this method provides 

a bounding internal dose reconstruction approach for the residual radioactivity period. 

7.2.3 Methods for Bounding Internal Dose at UNC-Hematite 

7.2.3.1 Methods for Bounding Operational Period Internal Dose 

Intakes to monitored UNC-Hematite workers may be estimated using readily-available in vitro 

(urinalysis) and/or in vivo (whole body counting) data for uranium isotopes. Of the two evaluation 

methods, significantly more urine bioassay data exist for the covered period under consideration. The 

description of the radiological program as it relates to internal monitoring and dose assessment 

supports that: (1) the primary radionuclide of concern was uranium (other than the case of the thorium 

blended for thorium-uranium fuel pellets in 1964); (2) those with the potential for exposure to 

uranium were monitored for internal exposures; (3) there are breathing zone and general area air 

sampling data available for the work performed over the operational years at UNC-Hematite, and (4) 

NIOSH has access to the applicable monitoring data. NIOSH intends to use the personnel 

monitoring data and existing internal dose reconstruction processes and procedures set forth in 

Battelle 6001, Appendix D, to reconstruct uranium dose for the class under evaluation. NIOSH may 

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also use the available uranium air monitoring data, source term information, and process descriptions 

to supplement the reconstruction of the uranium dose and support bounding the associated dose. 

These resources support the ability to reconstruct uranium dose using methods that are more precise 

than a bounding dose estimate. 

NIOSH also has access to extensive air monitoring data for the natural thorium work associated with 

the thorium-uranium fuel pellet work performed at the site. NIOSH intends to use this air monitoring 

data, coupled with the available source term information, process descriptions, and existing internal 

dose reconstruction processes and procedures set forth in Battelle 6001, Appendix D, to support 

bounding the thorium dose for the class under evaluation. Based on the assessment in Section 7.2.1.3, 

and the evaluation of the thorium air sample data, NIOSH intends to apply the uranium MAC of 1x10-

10 μc/ml (applied as 100% Th-232) as the bounding airborne concentration for routine Th-U pellet 

operations performed at UNC-Hematite during 1964. For identified incidents (e.g. spills) that may 

have occurred during the period, NIOSH intends to evaluate the range of values greater than 1x10-10 

μc/ml to establish a bounding thorium airborne concentration applicable to the specific situation. 

These airborne concentrations can be converted to personnel intake rates by applying a standard 

breathing rate and exposure time. NIOSH can consider the application of the MAC for mixtures (U 

and Th: 8.7x10-11 

μc/ml); the thorium MAC for the time period (3x10-11 μc/ml); the UNC-Hematite 

Administrative MAC (2x10-11 μc/ml); or a percentage of the selected MAC in order to evaluate an 

internal dose estimate that is more precise than a bounding estimate for members of the class under 

evaluation. Such an approach would be applicable for evaluating internal exposures over a wide range 

of job titles/duties. 

7.2.3.2 Methods for Bounding Residual Period Internal Dose 

Although non-AEC-related radioactive materials work continued at UNC-Hematite after 1973, 

NIOSH is required to evaluate the potential internal exposures from the residual radioactivity that 

remained as a result of weapons-related work during the operational years at the site (January 1, 1958 

through December 31, 1973). The weapons-related work performed during the covered operational 

years at UNC-Hematite involved uranium only. Residual contamination from weapons-related work 

may have been present in various outdoor and indoor locations at UNC-Hematite (Battelle-TBD-6001, 

Appendix D). The UNC-Hematite Historical Site Assessment also mentioned this likelihood 

(Westinghouse, 2003). This results in the potential for internal exposure from inhalation and 

ingestion of residual radioactive materials/contamination as a result of re-suspension. Battelle-TBD6001, Section D.6, provides a method to bound internal doses associated with residual radioactivity 

exposures at UNC-Hematite. The method involves determining a maximum operational period air 

concentration (from bounding/maximum intake rates associated with the operations period) which is 

assumed to settle and accumulate over a predetermined amount of time at the end of the operations 

period. NIOSH may also choose to evaluate the residual contamination/radiation based on the 

maximum air sample results over the operational period versus the calculated value based on intake 

rates. Standard re-suspension factors can be applied to the calculated surface contamination values to 

support calculating a post-1973 airborne concentration as a result of the residual radioactivity. The 

airborne concentration can be used to determine a corresponding intake of those radioactive materials 

(applying standard breathing rate and work period). Since the development of the UNC-Hematite 

TBD, NIOSH has collected personnel and area monitoring data for the operational and post-AEC 

operations period. These data, coupled with the approaches defined in Battelle-TBD-6001, support 

NIOSH’s ability to bound internal dose for the residual radioactivity period. 

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As presented and discussed in ORAUT-OTIB-0070, Dose Reconstruction During Residual 

Radioactivity Periods at Atomic Weapons Employer Facilities, more precise intake estimates can be 

evaluated considering the depletion of the AEC related source term/material, and the decline of the resuspension factor, over the residual period at UNC-Hematite. 

7.2.4 Internal Dose Reconstruction Feasibility Conclusion 

This evaluation concludes that NIOSH can bound internal dose (reconstruct dose with sufficient 

accuracy) for members of the class under evaluation. NIOSH located sufficient personnel monitoring 

data to support bounding internal uranium and thorium exposures at UNC-Hematite for the 

operational period of January 1, 1958 through December 31, 1973, and to support bounding 

AEC-related residual radioactivity exposures during the residual radioactivity period from January 1, 

1974 through July 31, 2006. This feasibility conclusion is based on the collective availability of 

bioassay (urinalysis) and air sampling data in sufficient quantity and quality for the entire covered 

period to adequately represent the class under evaluation. Supporting information, while limited, 

exists related to workplace activities, area monitoring, and associated source terms. Whole-body 

counting, thorium air sampling, and smear data represent additional, partial data sources and can be 

used to supplement and corroborate the bounding exposure assessments for the class. 

7.3 Evaluation of Bounding External Radiation Doses at UNC-Hematite 

The principal source of external radiation exposure for members of the class under evaluation was 

photon and beta (electron) radiation associated with AEC operational activities, including handling of 

radioactive materials in production or research activities; or radioactive waste-handling operations. 

Uranium metal and uranium compounds from natural and enriched uranium constituted the principal 

external radiation dose-producing material sources for members of the class. Per a Westinghouse 

Decommissioning Plan, these materials included uranium hexafluoride (UF6), uranium dioxide (UO2), 

uranium carbide, uranium dioxide pellets, and uranium metal (Personal Communications, 2009a and 

2009c; Westinghouse, 2006; Westinghouse Plan, 2006). 

As of the date of this evaluation, NIOSH has located individual external monitoring records for 

UNC-Hematite employees associated with uranium material processing during the operational period 

under evaluation. As expected, the highest doses were received by operations workers in the plant’s 

processing areas. Documentation retrieved from the site verifies that a robust personnel external 

monitoring program existed for photon and beta radiation exposures, as reflected in the individual 

external monitoring records. Neutron personnel exposures were not tracked as a component of the 

routine external dosimetry program. Possible reasons for this decision are discussed in Section 6.2. A 

suggested approach to bound neutron dose in lieu of monitoring data is provided in Section 7.3.4.1. 

The available documentation and information for the operational period also supports NIOSH’s ability 

to bound the post-1973 residual period external dose from exposures to residual 

radioactivity/contamination remaining on site as a result of AEC weapons-related operations. 

Employment at UNC-Hematite involved routine medical X-ray examinations required as a condition 

of employment; therefore, occupational X-rays are also a source of external radiation dose. 

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The following subsections address the ability to bound the operational period and residual period 

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

7.3.1 Evaluation of Bounding Process-Related External Doses 

As discussed in the prior sections of the evaluation, UNC-Hematite historical documentation specifies 

potential workplace external radiation hazards, applicable radiation exposure guidelines, and methods 

to limit worker exposure. 

NIOSH has located external monitoring records for beta and gamma radiation for UNC-Hematite 

employees associated with uranium processing during the class period under evaluation. Individual 

dosimetry data for the operational period is the preferred data source for evaluating the external 

radiation doses for members of the UNC-Hematite class. However, no dosimetry data was identified 

related to potential personnel exposures to neutrons; therefore, an approach for bounding neutron 

doses is provided in Section 7.3.4.1. 

NIOSH has the methodology and external uranium dose reconstruction assumptions and approaches 

described in Battelle-TBD-6001 at its disposal. NIOSH will use individual dosimetry data in 

conjunction with this methodology and to validate or adjust any assumptions, as appropriate. The 

monitoring data and methodologies available to NIOSH support its ability to bound external dose 

associated with UNC-Hematite uranium operations. 

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

reconstructing the process-related external doses of members of the class under evaluation. 

7.3.1.1 Personnel Dosimetry Data 

NIOSH has located records documenting the implementation of an external monitoring program for 

beta and photon exposure at UNC-Hematite. A routine external monitoring program for neutron 

exposure did not exist at the site. In addition to the documentation described below, NIOSH 

conducted interviews with two former workers who stated that they routinely wore a film badge 

(Personal Communications, 2009a and 2009c). An interview with a third person confirmed that 

badging occurred at the site, but the type of badging (film, etc.) could not be recalled (Personal 

Communication, 2009b). A review of the CATI interview reports for information on the routine use 

of radiation dosimeters supports a routine badging program at UNC-Hematite. 

Photon 

The available personnel external monitoring data, in the form of film badges, provide external 

photon/gamma dose information for the personnel working during the operational period at UNCHematite. These data can be used to reconstruct dose for members of the worker class under 

evaluation. In addition, Battelle-TBD-6001, Appendix D, describes how to develop the estimate of 

photon exposure for the former UNC-Hematite workers when site information is not available. As 

discussed in this evaluation, the available personnel monitoring data include data that represent the 

maximally-exposed work group and work scenario over the UNC-Hematite operational period. 

Therefore, NIOSH has concluded that the available personnel monitoring data and information for 

UNC-Hematite support its ability to bound the photon dose for the class under evaluation. 

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Beta 

The available personnel external monitoring data, in the form of film badges assigned to workers over 

the operational time period, were used to evaluate not only whole-body photon doses, but also 

workplace beta doses. Information regarding external exposures to beta radiation is also described in 

Battelle-TBD-6001, Appendix D, Section D.4, which references a 1960 AEC inspection report 

(Clarification, 2008) describing monthly badge results for workers in operations areas. Information 

for beta dose, as described in Battelle-TBD-6001, Appendix D, shows how to develop the estimate of 

beta exposure for the former UNC-Hematite workers when site information is not available. As 

discussed in this evaluation, the available personnel monitoring data include data that represents the 

maximally-exposed work group and work scenario over the UNC-Hematite operational period. 

Therefore, NIOSH has concluded that the available personnel monitoring data and the UNC-Hematite 

TBD support NIOSH’s ability to bound the beta dose for the class under evaluation. 

Neutron 

A routine external monitoring program for neutron exposure did not exist at UNC-Hematite. Rather, 

the site emphasized administrative and engineering controls to prevent a criticality accident. An 

indium foil (for indication of a neutron exposure from such an accident) was included with worker 

film badges. 

Because a routine monitoring program for neutrons did not exist, NIOSH evaluated several possible 

methods to bound neutron doses. A suggested approach that employs ORAUT-OTIB-0024 is 

provided in Section 7.3.4.1. 

7.3.1.2 Area Monitoring Data 

A Compliance Inspection Report (AEC, 1960) states that routine radiation surveys were made of the 

Hematite plant area with portable radiation survey instruments, that results of the surveys were 

recorded on floor plans, and that these surveys were usually made weekly by the health physics 

technician but the frequency varied depending on the work load of the technician. Records of the 

surveys show almost all readings to be < 2.5 mr/hr gamma with an occasional beta plus gamma 

reading recorded as 20 * [* = illegible symbol]. (Note: “mr/hr” represented the unit used during this 

period representing an exposure rate in milliroentgens per hour; today, it would be cited as “mR/hr.”) 

“Mr. [name redacted]; Supervisor, Industrial Hygiene Department] stated that instruments with 20 

mr/hr maximum range have been used for the surveys and that the readings recorded as greater than 

20 mr/hr would not be expected to exceed 20 mr/hr to a significant extent. Mr. [name redacted] 

stated that no readings in excess of 2 mr/hr have been observed outside the Hematite restricted area.” 

(AEC, 1960, pdf p. 51) 

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NIOSH identified records addressing the conduct of routine site radiation and contamination surveys 

in clear and contaminated areas of the plant (AEC, 1960; Beta-Gamma Survey, 1965; Hand Monitor, 

1963; Plant-wide, 1963; Smear Survey, 1964). Surveys were required per the plant’s health physics 

manual and licensing requirements (AEC, 1960; HP Manual, 1963). NIOSH does not intend to use 

this as the primary source of information for the purpose of bounding external dose. However, this 

data can be used to supplement the personnel external dosimetry data and to corroborate the defined 

bounding approaches for the class under evaluation. 

7.3.2 Evaluation of Bounding Residual Period External Doses 

As previously discussed, non-AEC-related work continued at UNC-Hematite after 1973. NIOSH is 

required to evaluate the potential external exposures from the residual radioactivity that remained as a 

result of weapons-related work during the operational years at the site (1958-73). The weaponsrelated work performed during the covered operational years at UNC-Hematite involved uranium 

only. For the purpose of bounding the external dose associated with the weapons-related residual 

radioactivity that remained on site after the end AEC-related operations, NIOSH can use the method 

defined in the UNC-Hematite TBD (Battelle-TBD-6001, Appendix D, Section D.6). For 

reconstructing external dose, the method involves determining a maximum air concentration which is 

assumed to settle and accumulate over a predetermined amount of time at the end of the operations 

period. NIOSH can use the method of calculating external exposure rates based on the 

bounding/maximum accumulated radioactive material at UNC-Hematite, as discussed in BattelleTBD-6001. The available air monitoring data for the site can be used to supplement the calculations 

and corroborate that this method provides a bounding external dose reconstruction approach for the 

residual radioactivity period. 

7.3.3 UNC-Hematite Occupational X-Ray Examinations 

Per interviews with former UNC-Hematite plant management and records reviews, employees were 

required to complete medical examinations, including chest X-rays (posterior-anterior and lateral 

X-rays) prior to beginning work, annually, and upon termination (Health Program, 1962, pdf p. 12; 

HP Manual, 1963, pdf p. 15; Personal Communications, 2009a and 2009c; Medical Program, 1962). 

Although NIOSH has not located specific parameters associated with these occupational medical 

X-rays (i.e., specific information on the X-ray devices), default values of entrance kerma, developed 

for the three most commonly-used occupational medical diagnostic procedures are available in 

ORAUT-OTIB-0006, Dose Reconstruction from Occupationally Related X-Ray Procedures. These 

values can be used to support bounding the medical X-ray dose for the time period under evaluation. 

These default values are maxima or upper limit values developed from review of patient doses as 

reported in the literature, machine characteristics, and knowledge of X-ray procedures used during 

different time periods. These default values can be used in lieu of actual measurement data or 

entrance kerma derived from technique factors to bound the occupational X-ray exposures for UNCHematite. NIOSH believes this methodology supports its ability to bound occupational medical X-ray 

doses (reconstruct the medical X-ray dose with sufficient accuracy) for the class under evaluation. 

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7.3.4 Methods for Bounding External Dose at UNC-Hematite 

Dose reconstructions performed prior to the date of this evaluation were completed using estimates of 

external dose based on source term data and worker stay times derived from interview data and site 

operations (Battelle-TBD-6000). External monitoring records are now available for beta and photon 

radiation exposures; these primary data sources will be used in conjunction with Battelle-TBD-6000 

methodologies for the purpose of bounding the external dose. External dosimetry data associated with 

neutron exposures were not identified. 

There is an established protocol for assessing external exposure when performing dose reconstructions 

(these protocol steps are discussed in the following subsections): 

• Photon Dose 

• Beta Dose 

• Neutron Dose 

• Medical X-ray Dose 

7.3.4.1 Methods for Bounding Operational Period External Dose 

NIOSH has obtained sufficient personal dosimetry records for individual workers exposed to beta and 

photon radiation during the AWE operations period. A routine neutron dosimetry program did not 

exist at UNC-Hematite; therefore, an alternative bounding approach is provided below. 

Photon Dose 

Photon doses can be reconstructed using available film badge summary reports for all years associated 

with the covered period. Badging extended to all site employees whether in process or non-process 

areas. 

Beta Dose 

Exposures to beta radiation were routinely recorded during the covered period as a component of the 

external dosimetry (i.e., film badging) program. General area beta doses (rem), as measured by 

personnel dosimeters, were provided in annual dose summaries either as stand-alone “beta” results or 

as “beta-gamma.” NIOSH located no indication of beta dose monitoring of extremities by the 

radiation protection program; however, NIOSH confirmed that the site did attempt to determine hand 

exposures to alpha particles by survey (HP Standards, 1968). Using process-specific electron dose 

rates provided in Table 7.3 of Battelle-TBD-6001, NIOSH has determined that it is possible to 

evaluate a reasonable upper-bound estimate of shallow beta dose to extremities. Estimation of 

extremity dose would be necessary only if warranted by the specific parameters of an individual case. 

Sufficient dosimetry information exists to estimate external doses from this radiation type. 

Neutron Dose 

Because a routine monitoring program for neutrons did not exist, NIOSH evaluated several possible 

methods to bound these potential doses. These methods included consideration of spontaneous 

fission, uranium compound source terms and quantities used at the site, enrichment levels, neutron 

yields from alpha-neutron and spontaneous fission reactions, worker stay times under different 

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exposure scenarios, and neutron-to-photon ratios. Due to its low production rate, spontaneous fission 

can be eliminated as a viable dose contributor (Battelle-TBD-6000). Based on the remaining 

considerations, NIOSH has determined that it can bound neutron doses using information contained in 

ORAUT-OTIB-0024, Estimation of Neutron Dose Rates from Alpha-Neutron Reactions in Uranium 

and Thorium Compounds. 

Medical X-ray Dose 

UNC-Hematite employees were required to have chest X-rays prior to beginning work, annually, and 

upon termination. Although NIOSH has not located specific parameters associated with these 

occupational medical X-rays, default values of entrance kerma, developed for the three most 

commonly-used occupational medical diagnostic procedures are available in ORAUT-OTIB-0006, 

Dose Reconstruction from Occupationally Related X-Ray Procedures. These values can be used to 

support bounding the medical X-ray dose for the time period under evaluation. 

7.3.4.2 Methods for Bounding Residual Period External Doses 

Although non-AEC-related radioactive materials work continued at UNC-Hematite after 1973, 

NIOSH is required to evaluate the potential external exposures from the residual radioactivity that 

remained as a result of weapons-related work during the operational years (from January 1, 1958 

through December 31, 1973). Battelle-TBD-6001, Section D.6, provides a method to bound external 

doses associated with residual radioactivity exposures at UNC-Hematite. The method involves 

determining a maximum operational period air concentration (from bounding/maximum intake rates 

associated with the operations period) which is assumed to settle and accumulate over a predetermined 

amount of time at the end of the operations period. NIOSH may also choose to evaluate the residual 

contamination/radiation based on the maximum air sample results over the operational period versus 

the calculated value based on intake rates. NIOSH could evaluate the bounding personnel external 

exposure based on the calculated dose rates associated with the accumulated radioactive materials. 

Since the development of the UNC-Hematite TBD, NIOSH has collected personnel and area 

monitoring data for the operational and post-AEC operations period. These data, coupled with the 

approaches defined in Battelle-TBD-6001, support NIOSH’s ability to bound external dose for the 

residual radioactivity period. 

More precise external dose estimates can be evaluated by accounting for the depletion of the 

AEC-related source term/material over the UNC-Hematite residual period. This can be evaluated as 

presented and discussed in ORAUT-OTIB-0070, Dose Reconstruction During Residual Radioactivity 

Periods at Atomic Weapons Employer Facilities. 

7.3.5 External Dose Reconstruction Feasibility Conclusion 

This evaluation concludes that NIOSH can bound external dose (reconstruct dose with sufficient 

accuracy) for members of the class under evaluation. NIOSH located sufficient personnel beta and 

photon monitoring data to estimate external exposures at UNC-Hematite for the operational period of 

January 1, 1958 through December 31, 1973, and to support bounding AEC-related residual 

radioactivity exposures during the residual radioactivity period from January 1, 1974 through July 31, 

2006. This feasibility conclusion is based on the availability of film badge data in sufficient quantity 

and quality for the entire covered operational period to adequately represent the class under 

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evaluation. While more limited, there is supporting information related to workplace activities, area 

monitoring, and associated source terms. Due to the absence of neutron monitoring data, an 

alternative approach for bounding neutron doses employs the methods provided in ORAUT-OTIB0024, Estimation of Neutron Dose Rates from Alpha-Neutron Reactions in Uranium and Thorium 

Compounds. 

7.4 Evaluation of Petition Basis for SEC-00116 

The following subsections evaluate the assertions made on behalf of petition SEC-00116 for the 

United Nuclear Corporation. 

7.4.1 Personnel Records Lost, Falsified, or Destroyed 

SEC-00116: It is our position that personnel records are being lost, falsified, or destroyed. 

Based on its review and assessment of the available data in the SRDB and in NOCTS, NIOSH has not 

found evidence that would corroborate the petitioner’s claim of falsified or destroyed personnel 

monitoring records. NIOSH verified during data capture visits to the Hematite site in March and 

April 2009, that hundreds of records boxes and other data files were present in multiple on-site 

locations and maintained under appropriate document control procedures, including key access and 

Westinghouse administrator control. 

7.4.2 Dose Reconstruction Infeasible 

SEC-00116: It is our position that a Dose Reconstruction cannot be completed with sufficient 

accuracy given the lack of data, absence of a site profile, and extensive on-off site contamination. 

As confirmed during NIOSH’s review, substantial internal and external data exist. The process and 

source term information, coupled with the NIOSH approaches for reconstructing uranium dose, are 

sufficient to support bounding the uranium internal and external dose for members of the class under 

evaluation. 

7.4.3 Lack of Site Profile 

SEC-00116: No site profile of the Hematite facility has been performed. 

Battelle-TBD-6001, Appendix D, provides a site profile for UNC-Hematite. A site profile is not a 

prerequisite for the performance of dose reconstruction. 

7.4.4 Lack of Internal Monitoring 

SEC-00116: The employees did not receive routine internal monitoring such as bioassays, blood 

samples, and breath (sic) tests. 

During the AWE operational period for UNC-Hematite (1958 through 1973), workers were monitored 

by bioassay and required to submit urinalysis samples on a specified frequency (ranging from monthly 

to every three-to-six months, depending on job assignment and year). While the bioassay program 

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was discontinued in 1961, air sampling continued in both process and non-process areas and the data 

were evaluated by the site for potential internal doses. A routine bioassay program was re-instituted 

in December 1962 (UNC In Vivo, 1963-1965). Examples of existing internal data are in the following 

reference documents: Bioassay Results, 1964; Bioassay Results, 1965; Bioassay Results, 1966; 

Bioassay Results, 1967; Bioassay Results, 1968; Bioassay Results, 1969; HP Standards, 1968; In Vivo 

and Bioassay, 1960s; In Vivo Counts, 1967-73; UNC urinalysis, 1962-1964; UNC urinalysis, 1963-

1964; Various Authors, 1963; Whole Body, 1969; Whole Body Counts, 1968-73; Whole Body Issues, 

1968-69; Special Bioassay, 1970. 

7.4.5 Monitoring Thoroughness 

SEC-00116: The former Atomic Energy Commission, the Department of Energy, the Nuclear 

regulatory [sic] Commission nor NIOSH has [sic] thorough personnel or environmental monitoring. 

See the NIOSH response in Section 7.4.4 above. 

7.4.6 Lack of Personnel Radiation Dose Records 

SEC-00116: As far as we know, no Hematite personnel radiation dose records have been provided to 

NIOSH and possibly do not exist. 

NIOSH has obtained bioassay, air sampling, and external dosimetry data in sufficient quantity and 

quality to adequately represent internal and external dose for the UNC-Hematite class under 

evaluation over the entire operational period (see Sections 6.1, 6.2, and 6.3). These data can also be 

used to support the evaluation of the UNC-Hematite external dose over the site’s residual radioactivity 

period. 

7.4.7 Residual Contamination 

SEC-00116: The Hematite site remained active as a commercial manufacturer until 2000 without a 

proper decommissioning. Residual contamination is evidently present and just as radioactive today. 

NIOSH recently collected personnel and area monitoring that support bounding the internal dose for 

the UNC-Hematite operational period. In addition, NIOSH has access to personnel and area 

monitoring data collected at UNC-Hematite during non-AEC operations that continued into the 

residual radioactivity period (after AEC operations ended in 1973), as well as site remediation 

surveys. In addition to individual external monitoring records, status surveys and confirmatory 

surveys performed during the residual period would be used along with available personnel records to 

establish the upper bound of potential exposure from residual radiation. Knowledge of the AEC 

process operations performed during the operational period, and the available data for the associated 

timeframes, support NIOSH’s ability to reconstruct dose during the residual radioactivity period at the 

site. For the UNC-Hematite residual period, only the personnel exposures to AEC-related residual 

radioactivity are assessed. This topic is discussed further in Sections 7.2.2 and 7.3.2. 

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7.5 Other Potential SEC Issues Relevant to the Petition Identified During the 

Evaluation 

During the feasibility evaluation for SEC-00116, issues were identified by NIOSH that needed further 

analysis and resolution. The issue and its current status are: 

•	 ISSUE: Was thorium present at the site? 

RESPONSE: Interviews with former UNC-Hematite energy employees confirm the presence of 

thorium powder in site operations. The thorium operations occurred in 1964 and included the 

production of UO2-ThO2 pellets for reactor fuel rods. NIOSH maintains that by bounding the 

doses for uranium oxides, the lesser radionuclides, including thorium, are also bounded. 

Through a review of air sampling logs, NIOSH identified the collection of air samples in the Pellet 

Plant during 1964 specifically for the presence of thorium dioxide. Air sampling results fell 

within the range of uranium air sampling results. Therefore, NIOSH maintains that uranium 

results can be used to bound thorium results. 

•	 ISSUE: Why was neutron personnel monitoring non-existent as a component of a routine external 

dosimetry program? 

RESPONSE: NIOSH interviewed a former UNC-Hematite plant manager who could not recall 

any technical discussions concerning the need for a routine neutron survey and personnel 

monitoring program. NIOSH reviewed available UNC-Hematite documentation to identify 

records related to neutron exposures. Records reviews included Health Physics procedural 

manuals, AEC regulations and licensing inspections, dosimetry records, and site radiation survey 

records. While UNC-Hematite received and processed uranium in various forms (including 

uranium hexafluoride), neutron exposures were not identified as a radiological concern by plant 

personnel either as a component of routine plant operations or the external dose monitoring 

program. AEC regulations in 10 C.F.R. 20 (1961) only generally referred to the need to conduct 

surveys and provide monitoring devices. No specific requirement existed in the regulations to 

conduct neutron surveys and track neutron personnel exposures. AEC licensing inspection reports 

did not cite the lack of routine neutron monitoring as a concern or recommend any action in this 

regard. No radiological monitoring records specifying exposure to neutron radiation were 

identified and UNC-Hematite did not list portable neutron instrumentation in its inventory. 

Because neutron records were not identified, NIOSH provided an alternative approach to bound 

the neutron dose at UNC-Hematite using a combination of operational site information and 

ORAUT-OTIB-0024, Estimation of Neutron Dose Rates from Alpha-Neutron Reactions in 

Uranium and Thorium Compounds. 

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7.6 Summary of Feasibility Findings for Petition SEC-00116 

This report evaluates the feasibility for completing dose reconstructions for employees at 

UNC-Hematite from January 1, 1958 through December 31, 1973, and for the residual period from 

January 1, 1974 through July 31, 2006. NIOSH found that the available monitoring records, process 

descriptions and source term data available are sufficient to complete dose reconstructions for the 

evaluated class of employees. 

Table 7-2 summarizes the results of the feasibility findings at UNC-Hematite for each exposure source 

during the time periods from January 1, 1958 through December 31, 1973, and for the residual period 

from January 1, 1974 through July 31, 2006. 

Table 7-2: Summary of Feasibility Findings for SEC-00116 

January 1, 1958 through December 31, 1973; residual period from January 1, 1974 through July 31, 2006 

Source of Exposure Reconstruction Feasible Reconstruction Not Feasible 

Internal1

 X 

 - U X 

 - Th X 

External X

 - Gamma X 

 - Beta X 

 - Neutron X 

 - Occupational Medical X-ray X 

1

 Internal includes an evaluation of urinalysis (in vitro), airborne dust, and limited lung (in vivo) data 

As of June 8, 2009, a total of 51 claims have been submitted to NIOSH for individuals who worked at 

UNC-Hematite and are covered by the class definition evaluated in this report. Dose reconstructions 

have been completed for 33 individuals (~65%). 

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8.0 Evaluation of Health Endangerment for Petition SEC-00116 

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. 

Based on available data, knowledge of source terms and activities, and surveys conducted during both 

the operational and residual periods, NIOSH’s evaluation determined that it is feasible to estimate 

radiation dose for members of the NIOSH-evaluated class with sufficient accuracy based on the sum 

of information available from available resources. Modification of the class definition regarding 

health endangerment and minimum required employment periods, therefore, is not required. 

9.0 Class Conclusion for Petition SEC-00116 

Based on its full research of the class under evaluation, NIOSH found no part of said class for which it 

cannot estimate radiation doses with sufficient accuracy. This class includes all site employees that 

worked in any area of the United Nuclear Corporation, Hematite, MO, site from January 1, 1958 

through December 31, 1973 and the residual radiation period January 1, 1974 through July 31, 2006. 

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-00116. 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 

10 C.F.R. 20, Standards for Protection Against Radiation, U. S. Atomic Energy Commission; Federal 

Register; November 17, 1960; SRDB Ref ID: 62588 

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 

Activities Log, 1969, Log of Activities for 1969, handwritten, various names and dates; United 

Nuclear Corporation; 1969; SRDB Ref ID: 62378 

AEC, 1958, Compliance Inspection Report, initial; U.S. Atomic Energy Commission (AEC); August 

18-19, 1958; SRDB Ref ID: 3822 

AEC, 1960, Compliance Inspection Report, re-inspection (1); U.S. Atomic Energy Commission 

(AEC); January 12-14, 1960; SRDB Ref ID: 7145, pdf p. 44 and 3944, pdf pp. 45-59 

AEC, 1961, External Penetrating Radiation Exposure Evaluation, information sheet; U.S. Atomic 

Energy Commission (AEC); Information Sheet 0523-051; SRDB Ref ID: 13789, pdf p. 70 

AEC, 1962, Major Activities in the Atomic Energy Programs January-December 1961, select pages 

(pages 343, 51, 342) of book; U.S. Atomic Energy Commission (AEC); January 1962; SRDB Ref ID: 

3944, pdf pp. 17-18, 26, 29 

AEC Visit, 1963, AEC Visit if July 25 and 26, 1963, interoffice memo plus integrated dust exposures 

and film badge reports; United Nuclear Corporation; various dates in 1963; SRDB Ref ID: 62295 

Affidavits, 2008, Affidavits, Authorization Forms, and Associated Attachments from Name1, Name2, 

Name3, and Name4; June 13, 2008; OSA Ref ID: 106292, pdf pp. 1-39 

Air Sample Data, 1961, Air Sample Data Sheet –United Nuclear Corporation; AEC Health and Safety 

Laboratory; August 1961; SRDB Ref ID: 7105 

Air Sample Data, 1961-63, Air Sample Data Sheet –United Nuclear Corporation; Mallinckrodt 

Chemical Works; various dates in 1961-63; SRDB Ref ID: 62285 

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Air Sample Data, 1963, Air Sample Data Sheet – Cuno Filter Area, United Nuclear Corporation; June 

and July 1963; SRDB Ref ID: 62170 

Air Sample Log, 1964, Pellet Plant Air Sample Log, United Nuclear Corporation; November and 

December 1964; SRDB Ref ID: 62158 

Air Sample Summaries, 1963, Various Air Sample Summaries for Hematite, United Nuclear 

Corporation; various dates in 1963; SRDB Ref ID: 62432 

Assignments, 1969, Acceptable Restricted Exposure Assignments, United Nuclear Corporation; June 

23, 1969; SRDB Ref ID: 62421 

Assorted Results, 1963, Assorted Air and Contamination Study Results, United Nuclear Corporation; 

various dates in 1963; SRDB Ref ID: 62276 

Battelle-TBD-6000, Site Profiles for Atomic Weapons Employers that Worked Uranium and Thorium 

Metals, PNWD-3738 Rev 0, Rev. F0; Battelle; December 13, 2006; SRDB Ref ID: 30671 

Battelle-TBD-6001, Site Profiles for Atomic Weapons Employers that Refined Uranium and Thorium, 

Rev. F0; Battelle; December 13, 2006; SRDB Ref ID: 30673 

Battelle-TBD-6001, Appendix D, Site Profiles for Atomic Weapons Employers that Refined Uranium 

and Thorium—Appendix D United Nuclear Corp., Rev. 0; Battelle; March 14, 2008; SRDB Ref ID: 

41835 

Battelle-TIB-5000, Default Assumptions and Methods for Atomic Weapons Employer Dose 

Reconstructions, PNWD-3741, Rev. 00; Battelle; April 2, 2007; SRDB Ref ID: 32016 

Beta-Gamma Survey, 1965, Beta Gamma Survey Nov. 13, 1965, J. D. Baker; room diagrams with 

readings; United Nuclear Corporation; November 13, 1965; SRDB Ref ID: 62427 

Bioassay Results, 1964, Various handwritten bioassay results for Hematite workers; United Nuclear 

Corporation; 1964; SRDB Ref ID: 62390 

Bioassay Results, 1965, Various handwritten bioassay results for Hematite workers; United Nuclear 

Corporation; 1965; SRDB Ref ID: 62386 

Bioassay Results, 1966, Various handwritten bioassay results for Hematite workers; United Nuclear 

Corporation; 1966; SRDB Ref ID: 62383 

Bioassay Results, 1967, Various handwritten bioassay results for Hematite workers; United Nuclear 

Corporation; 1967; SRDB Ref ID: 62381 

Bioassay Results, 1968, Various handwritten bioassay results for Hematite workers; United Nuclear 

Corporation; 1968; SRDB Ref ID: 62379 

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Bioassay Results, 1969, Various handwritten bioassay results for Hematite workers; United Nuclear 

Corporation; 1969; SRDB Ref ID: 62377 

Bioassay Vendor Results, 1967, Urinalysis Results from Various Analytical Vendors for United 

Nuclear Corporation Urine Samples; various vendors; various dates in 1967; SRDB Ref ID: 62376 

Blending Room, 1961-63, Blending Room Air Sample Data, United Nuclear Corporation; various 

dates in 1961-1963; SRDB Ref ID: 62282 

Blue Room, 1960-63, Various Air Sample Data Sheets, Mallinckrodt Chemical Works; various dates 

1960-1963; SRDB Ref ID: 62328 

Blue Room, 1962-63, Various Air Sample Data Sheets, Mallinckrodt Chemical Works; various dates 

1962-1963; SRDB Ref ID: 62340 

Bureau of Mines, 1932-1993, Bureau of Mines Minerals Yearbook (1932-1993), U. S. Department of 

the Interior, U.S. Geological Survey; database at the University of Wisconsin Ecology and Natural 

Resources Collection; http://minerals.usgs.gov/minerals/pubs/usbmmyb.html 

Burial Site, 1983, Radiological Survey of the Combustion Engineering Burial Site, Hematite, 

Missouri, Radiation Management Corporation for U.S. Nuclear Regulatory Commission; 

NUREG/CR-3387; July 1983; SRDB Ref ID: 57100 

Cabrera Services, 2003, Engineering Evaluation and Cost Analysis Regarding Local Aquifer in the 

Vicinity of the Westinghouse Former Fuel Cycle Facility, select pages from a groundwater report; 

Cabrera Services, Inc.; January 2003; OSA Ref ID: 106292, pdf pp. 51-53 

Cardarelli, 1996, NIOSH Health Hazard Evaluation Report: HETA 96-0198-2651, Portsmouth 

Gaseous Diffusion Plant; Portsmouth, Ohio, J. Cardarelli; Centers for Disease Control and 

Prevention, National Institute for Occupational Safety and Health; 1996; SRDB Ref ID: 8122 

Clarification, 2008, Clarification Responses to NIOSH on the Submitted Petition SEC 00116; 

document detailing SEC-00116 changes, Name1; October 3, 2008; OSA Ref ID: 107083, pdf pp. 2-7 

Compliance, 1960, Compliance Inspection Report; Licensee: Mallinckrodt Nuclear Corporation, St. 

Louis, Missouri; Inspected Site Location: Mallinckrodt Site at Hematite, Missouri; Inspection 

performed by U. S. Atomic Energy Commission; January 12-14, 1960; SRDB Ref ID 3944, pdf p. 51 

Compliance, 1961, Compliance Inspection Report; Licensee: Mallinckrodt Nuclear Corporation, St. 

Louis, Missouri; Inspected Site Location: Mallinckrodt Site at Hematite, Missouri; Inspection 

performed by U. S. Atomic Energy Commission; March 20-23, 1961; SRDB Ref ID 56196, pdf p. 12 

Consult Call, 2008, Consult Call Response Letter; Name1; October 3, 2008; OSA Ref ID: 107083, pdf 

p. 1 

Criticality Issues, 1962-64, Various memos, plans, reviews, and surveys related to criticality issues, 

United Nuclear Corporation; various authors and dates in 1962, 1963, and 1964; SRDB Ref ID: 62261 

57 of 83 
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Darr, 1974, Executed Application for Renewal of Operating Permit for Septic System, correspondence 

to Missouri Clean Water Commission; David Darr, Nuclear Fuels Company; February 6, 1974; OSA 

Ref ID: 106292, pdf p. 63 

Decommissioning, 1979, License SNM-33 Decommissioning Plan, Combustion Engineering, Inc., 

Nuclear Fuel Manufacturing, Hematite Plant; January 15, 1979; SRDB Ref ID: 62051 

DOE, 1997, Linking Legacies, select pages from Appendix B; Department of Energy (DOE); January 

1997; SRDB Ref ID: 3944, pdf pp. 20-21 

DOE-STD-1136-2000, Guide of Good Practices for Occupational Radiological Protection in 

Uranium Facilities, U.S. Department of Energy; December 2001 (Change Notice No. 3); SRDB Ref 

ID: 4617 

DOL, 2009, United Nuclear Corporation, Hematite, Missouri, letter from R. P. Leiton (Department of 

Labor) to L. Elliott (National Institute for Occupational Safety and Health); May 1, 2009; OSA Ref 

ID: 108883 

Dust Exposure, 1962, United Nuclear Corporation Integrated Dust Exposure, United Nuclear 

Corporation; various dates in 1962; SRDB Ref ID: 62197, pdf pp. 7-54 

Elk River, 1961, Examination of an Irradiated Prototype Fuel Element for the Elk River Reactor, L. 

A. Neimark; Argonne National Laboratory; ANL-6160; January 1961; SRDB Ref ID: 60150 

Enriched Materials, 1959, Special Nuclear Material License No. SNM-33, letter from D. E. Jablonski 

(Mallinckrodt Nuclear Corporation) to L. Johnson (AEC); June 5, 1959; SRDB Ref ID: 3944, pdf p. 5 

Estimated Exposures, 1963, Estimated Lung Exposures for Entire Year, 1963, letter from J. A. 

Lindberg (V.P., UNC) to C. Keller (AEC); United Nuclear Corporation; October 28, 1963; SRDB Ref 

ID: 62316 

Exposures, 1960, Personnel exposures exceeding 10 CFR 20 limits, Compliance Inspection Report on 

Mallinckrodt Nuclear Corporation site at Hematite, Missouri; U. S. Atomic Energy Commission; 

January 12-14, 1960; SRDB Ref ID 3987, pdf pp. 51-52 

External Exposure Reports, 1963, External Radiation Exposure Reports for various months in 1963; 

United Nuclear Corporation; 1963; SRDB Ref ID: 62274 

External Exposure Reports, 1964, External Radiation Exposure Reports for various months in 1964; 

United Nuclear Corporation; 1964; SRDB Ref ID: 62272 

External Exposure Reports, 1965, External Radiation Exposure Reports for various months in 1965; 

United Nuclear Corporation; 1965; SRDB Ref ID: 62271 

58 of 83 
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Facility List, 2001, Worker Advocacy Facility List: United Nuclear Corp., U. S. Department of 

Energy; accessed June 6, 2001; http://tis.eh.doe.gov/advocacy/faclist/showfacility.cfm; SRDB Ref ID: 

3944, pdf p. 7 

Federal Register, 2001, Federal Register Notices, Volume 66, No. 11; January 17, 2001; OSA Ref ID: 

106292, pdf pp. 93-96 

Film Badge Summary, 1962, Film Badge Summary - United Nuclear Corporation, United Nuclear 

Corporation; various dates in 1962; SRDB Ref ID: 62277 

Film Badge Summary, 1961, United Nuclear Corporation Film Badge Radiation Exposure Summary 

for 1961, United Nuclear Corporation; January 11, 1962; SRDB Ref ID: 62278 

Fleishman-Hillard, 1967, Fuel for the Atomic Age—Completion Report on St. Louis-Area Uranium 

Processing Operations, 1942-1967; Fleishman-Hillard, Inc.; September 30, 1967; SRDB Ref ID: 

6538 

Floor Swipes, 1962-64, Surface Contamination Survey, United Nuclear Corporation; 1962-1964; 

SRDB Ref ID: 62352 

Follow-up Survey, 1990, Followup Radiological Survey of Construction Area, Combustion 

Engineering, Inc., Hematite, Missouri, Energy/Environment Systems Division of Oak Ridge 

Associated Universities; June 25, 1990; SRDB Ref ID: 62268 

FUSRAP, 1987, Sites Investigated under FUSRAP in the St. Louis Area, list from A. Wallo to S. 

McCracken; from FUSRAP Aerospace database; SRDB Ref ID: 3944, pdf pp. 39-42 

FUSRAP, 2000, Database Report for United Nuclear Corp.; FUSRAP Considered Sites database; 

January 16, 2000; SRDB Ref ID: 3944, pdf pp. 36-37 

Gateway, 1996, Investigation to Determine the Source of Technetium-99 in Groundwater Monitoring 

Wells 17 and 17B, select pages of report; Gateway Environmental Associates, Inc.; September 1996; 

OSA Ref ID: 106292, pdf pp. 57-61 

General Survey, 1959, General Survey of Radioactive Airborne Dust in the Hematite, Missouri, 

Uranium Processing Plant, Mallinckrodt Chemical Works, St. Louis; January 28, 1959; SRDB Ref 

ID: 62357 

Green Room, 1961-63, Green Room Air Sample Data, Mallinckrodt Chemical Works; various dates in 

1961-63; SRDB Ref ID: 62283 

Green Room, 1964, Green Room Alpha Activity, United Nuclear Corporation; various dates in 1964; 

SRDB Ref ID: 62279 

Hand Monitor, 1963, Hand Monitor Use, various memos, United Nuclear Corporation; various dates 

in 1963; SRDB Ref ID: 62425 

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Health Program, 1962, Health Program for Protection Against Radiation at United Nuclear 

Corporation, United Nuclear Corporation; May 1, 1962; SRDB Ref ID: 62414 

HF Leak, 1969, HF Leak in Oxide Building, interoffice memo to D. G. Carr from L. F. Brotherton; 

United Nuclear Corporation; July 7, 1969; SRDB Ref ID: 62163 

HP Manual, 1963, United Nuclear Corporation, Chemicals Operation, Health Physics Manual, 

United Nuclear Corporation; August 15, 1963; Revised November 25, 1964; SRDB Ref ID: 62362 

HP Standards, 1968, H. P. Standards (Manual), interoffice memo with Health Physics Standards from 

L. J. Swallow to D. G. Darr; United Nuclear Corporation; August 12, 1968; SRDB Ref ID: 62363 

Inspection, 1958, Inspection Report Dated August 18-19, 1958, Mallinckrodt Chemical Works, St. 

Louis 7, Missouri – License No’s C-2734 and SNM-33, U.S. AEC Division of Licensing and 

Regulation; August 18-19, 1958; SRDB Ref ID: 3822, pdf p. 3 

In Vivo, 1963, In Vivo Monitoring Results of UNC Employees, letter from C. A. Keller (AEC – Oak 

Ridge) to C. Kuhlman (UNC); U.S. Atomic Energy Commission; September 5, 1963; SRDB Ref ID: 

62318 

In Vivo, 1964, In Vivo Monitoring of UNC Personnel – March 16, 1964, memo from C. A. Keller 

(AEC – Oak Ridge) to C. Kuhlman (UNC); U.S. Atomic Energy Commission; April 10, 1964; SRDB 

Ref ID: 62314 

In Vivo and Bioassay, 1960s, Various Personnel Selected for Whole-Body Counting Based on 

Urinalysis Results; United Nuclear Corporation; various dates in the 1960s; SRDB Ref ID: 62338 

In Vivo Counts, 1967-73, In-Vivo Count Results (ugm U-235), United Nuclear Corporation; 1973; 

SRDB Ref ID: 62419 

Item Plant, 1964, Item Plant Air Samples, United Nuclear Corporation; various dates in 1964; SRDB 

Ref ID: 62356 

Keppler, 1978, Letter and Q&A Regarding the Combustion Engineering Plant at Hematite, Missouri 

Inspection Program, correspondence and select attachments; November 24, 1978; OSA Ref ID: 

106292, pdf pp. 54-56 

Letter, 2008, Letter and Associated Attachments Discussing Incorrect and/or Assumed Statements; 

Name2; April 15, 2008; OSA Ref ID: 107083, pdf pp. 8-14 

License C-2734, 1958, Source Material License C-2734, Letters to/from AEC to/from Mallinckrodt 

Chemical Works; SRDB Ref ID: 56068, pdf pp. 31-36 

License Review, 1979, Review of License Amendment Application Dated January 12, 1979, and 

Supplement Transmitted by Letter Dated March 8, 1979 Concerning Decommissioning Plan, PC No. 

79047A, U.S. Nuclear Regulatory Commission; June 5, 1979; SRDB Ref ID: 62052 

60 of 83 
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Loysen, 1973, Cancel Permit Application, correspondence to EPA; Peter Loysen, Gulf United 

Nuclear Fuels Corporation; December 27, 1973; OSA Ref ID: 106292, pdf p. 62 

Major Activities, 1962; Major Activities in the Atomic Energy Programs, U.S. Atomic Energy 

Commission; January-December 1962; SRDB Ref ID: 3944, pdf pp. 23-24 

Mallinckrodt, 1958, Letter requesting modification to Source Material License C-2734, from W. M. 

Leaders (Mallinckrodt Chemical Works) to L. Johnson (AEC); April 7, 1958; SRDB Ref ID: 56164 

Mallinckrodt, 1960, Letter and exposure data from F. Zeitlin (Mallinckrodt Chemical Works, Nuclear 

Division) to H. L. Price (AEC Division of Licensing & Regulation); December 16, 1960; SRDB Ref 

ID: 17606 

MCW News, unknown date, Hematite Revisited, news story; MCW News; unknown date; OSA Ref 

ID: 106292, pdf pp. 64-70 

Medical Program, 1962, Discussion of Medical Program for United Nuclear Corporation, C. D. 

Harrington (UNC); various dates in 1962; SRDB Ref ID: 62309 

NIOSH, 2006, NIOSH Dose Reconstruction Activity Report for Name2, correspondence; National 

Institute for Occupational Safety and Health (NIOSH); January 25, 2006; OSA Ref ID: 106292, pdf 

pp. 48-50 

NIOSH, 2008, NIOSH Dose Reconstruction Report for Name2; National Institute for Occupational 

Safety and Health (NIOSH); April 8, 2008; OSA Ref ID: 106292, pdf pp. 40-47 

Non-process Air Samples, 1961-63, Lunchroom, Armco Warehouse, and Other Locations Air 

Samples, United Nuclear Corporation; various dates in 1961-1963; SRDB Ref ID: 62171 

Non-process Air Samples, 1964, Front Office and Lunchroom Air Samples, United Nuclear 

Corporation; various dates in 1964; SRDB Ref ID: 62361 

Nuclear Fuel Services, 1967, Review of Accountability Controls Over Special Nuclear Materials, 

Nuclear Fuel Services, Inc., Report to Joint Committee on Atomic Energy, Congress of the United 

States by the Comptroller General of the United States; September 1967; SRDB Ref ID: 7214 

Oak Ridge Trip, 1963, Twenty-Four Hour Urine Sample, interoffice memo from L. J. Swallow; 

United Nuclear Corporation; August 15, 1963; SRDB Ref ID: 62416 

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 

ORAUT-OTIB-0004, Estimating the Maximum Plausible Dose to Workers at Atomic Weapons 

Employer Facilities, Rev. 03 PC-2; Oak Ridge Associated Universities (ORAU); December 6, 2006; 

SRDB Ref ID: 36191 

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ORAUT-OTIB-0006, Dose Reconstruction from Occupationally Related X-Ray Procedures, Rev. 03 

PC-1; Oak Ridge Associated Universities (ORAU); December 21, 2005; SRDB Ref ID: 20220 

ORAUT-OTIB-0024, Estimation of Neutron Dose Rates from Alpha-Neutron Reactions in Uranium 

and Thorium Compounds, Rev. 00; Oak Ridge Associated Universities; April 7, 2005; SRDB Ref ID: 

19445 

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-0014-2, Technical Basis Document for the Y-12 National Security Complex - Site 

Profile, Rev. 02; Oak Ridge Associated Universities; November 8, 2007; SRDB Ref ID: 36045 

ORAUT-TKBS-0015-6, Portsmouth Gaseous Diffusion Plant—Occupational External Dose, Rev. 01 

PC-1; Oak Ridge Associated Universities; August 20, 2007; SRDB Ref ID: 34469, pdf p. 19 

Overexposure Report, 1976, Report of Possible Exposure to Airborne Concentrations of Uranium in 

Excess of 10 CFR Part 20 Limits, from H. E. Eskridge (Combustion Engineering, Inc.) to Director of 

Inspection and Enforcement (U.S. Nuclear Regulatory Commission); April 9, 1976; SRDB Ref ID: 

62281 

Overexposures, 1963, Radiation Exposure, memo from D. B. Baugus to R. W. Shearer; United 

Nuclear Corporation – Hematite; January 28, 1963; SRDB Ref ID: 62284 

Pellet Plant, 1961-62, Pellet Plant Air Sample Data, Hematite, Mo., Mallinckrodt Chemical Works; 

various dates in 1961-62; SRDB Ref ID: 62287 

Pellet Plant, 1964, Pellet Plant Station Alpha Activity Data Sheets, United Nuclear Company, various 

dates in 1964; SRDB Ref ID: 62343 

Personal Communication, 2009a, Personal Communication with Group Leader/Assistant Technical 

Director/Technical Director (various titles); Telephone Interview by ORAU Team and NIOSH; 

February 4, 2009; SRDB Ref ID: 61673 

Personal Communication, 2009b, Personal Communication with Health Physics Secretary; Telephone 

Interview by ORAU Team; February 5, 2009; SRDB Ref ID: 61669 

Personal Communication, 2009c, Personal Communication with Research and Development 

Engineer/Nuclear Safety Officer/Operations Chemical Officer/Construction Manager (various titles); 

Telephone Interview by ORAU and NIOSH Team ; February 12, 2009; SRDB Ref ID: 61676 

Personal Communication, 2009d, Personal Communication with Production Supervisor/Production 

Superintendant (various titles); On-site Interview by ORAU Team on March 12, 2009; SRDB Ref ID: 

69965 

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Personnel Exposure, 1967, Personnel Exposure to Excessive Airborne Concentrations, letter from D. 

G. Carr to D. F. Cronin; United Nuclear Corporation – Hematite; March 27, 1967; SRDB Ref ID: 

Phase 2 Survey, 1989, Radiological Survey of Phase 2 Construction Site, Combustion Engineering, 

Inc., Hematite, Missouri, Energy/Environment Systems Division of Oak Ridge Associated 

Universities; September 21, 1989; SRDB Ref ID: 62104 

Plant-wide, 1963, Plant-wide Contamination Survey (Loose and Direct) Including Hood Numbers of 

Floor Plan, United Nuclear Corporation; April 19, 1963; SRDB Ref ID: 62426 

Procurement, 1968, Procurement of Fuel Pellets, LWBR Demonstration Core, Bettis Atomic Power 

Laboratory; Westinghouse Electric Corporation; December 4, 1968; SRDB Ref ID: 8342 

Project Proposal, 1966, Thorium Precipitation Pilot Facility – Pilot Plant, National Lead Company of 

Ohio; August 16, 1966; SRDB Ref ID: 28949 

Proposal, 1992, Proposal for Site Material Disposal and Remediation of Affected Ground Area 

Adjacent to the Tile Barn of ABB Combustion Engineering, Quadrex Recycle Center; September 3, 

1992; SRDB Ref ID: 62048 

Radiological Health Handbook, 1970, Radiological Health Handbook; Compiled and edited by the 

Bureau of Radiological Health and the Training Institute—Environmental Control Administration; 

January 1970; SRDB Ref ID: publicly available, U.S. Government Printing Office 

Rich, 1988, Health Physics Manual of Good Practices for Uranium Facilities, Idaho National 

Engineering Laboratory; June 1988; SRDB Ref ID: 1781 

Rowden, 2001, Nuclear Fuel Plant in Hematite Closes, But Waste Remains, emailed news article; 

Tim Rowden; July 2, 2001; SRDB Ref ID: 3944, pdf pp. 9-12 

SAIC, 2007, Remedial Investigation Report for the Westinghouse Hematite Site, Rev. 01, Vol. 01, 

select pages from report; Science Applications International Corporation (SAIC) and GEO 

Consultants; January 2007; OSA Ref ID: 106292, pdf pp. 71-92 

Site Assessment, 2005, Historical Site Assessment, Hematite Former Fuel Cycle Facility 

Decommissioning, Westinghouse Electric Company LLC; 2005; SRDB Ref ID: 56469 

Smear Report, 1964, UNC – Health Physics Group Smear Survey Report, United Nuclear 

Corporation; 1964; SRDB Ref ID: 62320 

Smear Survey, 1964, Clear Area Floor Smear Survey Report, United Nuclear Corporation; 1964; 

SRDB Ref ID: 62358 

Smear Survey, 1971, Smear Survey Report, Health Physics Group, United Nuclear Corporation; 

various dates in January 1971; SRDB Ref ID: 62442 

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Smear Survey, 1972, Smear Survey Report, Health Physics Group, United Nuclear Corporation; 

various dates in November 1972; SRDB Ref ID: 62436 

Smear Surveys, 1966, Health Physics Smear Survey Report, United Nuclear Corporation; 1966; 

SRDB Ref ID: 62384 

SNM-33, 1958, Inspection Report Dated August 18-19, 1958, Mallinckrodt Chemical Works, St. Louis 

7, Missouri – License No’s C-2734 and SNM-33, U.S. AEC Division of Licensing and Regulation; 

August 18-19, 1958; SRDB Ref ID: 3822, pdf p. 18 

Soil Sampling, 1989, Soil Sampling Results, Limestone Piles A and C, Combustion Engineering, Inc., 

Hematite, Missouri, Energy/Environment Systems Division of Oak Ridge Associated Universities; 

September 25, 1989; SRDB Ref ID: 62260 

Special Bioassay, 1970, Bio-Assay Special Issue Log, United Nuclear Corporation, 1970; SRDB Ref 

ID: 62373 

State of Missouri, 1996, Letter Concerning Evidence of Enriched Uranium at the Hematite Plant, from 

R. Kucera (State of Missouri Department of Natural Resources) to R. B. Bangart (Nuclear Regulatory 

Commission); May 16, 1996; SRDB Ref ID: 62250 

Tabulation Sheet, 1965, Tabulation Sheet – Dosimetry Records, Year 1965, United Nuclear 

Corporation; 1965; SRDB Ref ID: 62181 

Tabulation Sheet, 1966, Tabulation Sheet – Dosimetry Records, Year 1966, United Nuclear 

Corporation; 1966; SRDB Ref ID: 62180 

Tabulation Sheet, 1967, Tabulation Sheet – Dosimetry Records, Year 1967, handwritten, United 

Nuclear Corporation; 1967; SRDB Ref ID: 62267 

Tabulation Sheet, 1968, Tabulation Sheet – Dosimetry Records, Year 1968, United Nuclear 

Corporation; 1968; SRDB Ref ID: 62187 

Tabulation Sheet, 1969, Tabulation Sheet – Dosimetry Records, Year 1969, handwritten, United 

Nuclear Corporation; 1969; SRDB Ref ID: 62266 

Tabulation Sheet, 1970, Tabulation Sheet – Dosimetry Records, Year 1970, United Nuclear 

Corporation; 1970; SRDB Ref ID: 62231 

Tabulation Sheet, 1971, Tabulation Sheet – Dosimetry Records, Year 1971, United Nuclear 

Corporation; 1971; SRDB Ref ID: 62229 

Tabulation Sheet, 1972, Tabulation Sheet – Dosimetry Records, Year 1972, United Nuclear 

Corporation; 1972; SRDB Ref ID: 62227 

Tabulation Sheet, 1973, Tabulation Sheet – Dosimetry Records, Year 1973, United Nuclear 

Corporation; 1973; SRDB Ref ID: 62225 

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Terminated, various years, Exposure Data – Terminated Employees, United Nuclear Corporation; 

start/end years of employment for each individual; various dates; SRDB Ref ID: 62185 

ThO2-UO2, 1964, Health Physics Considerations for Handling and Processing of ThO2-UO2, 

interoffice memo from D. G. Darr to E. F. Sanders; United Nuclear Corporation; May 7, 1964; SRDB 

Ref ID: 62430 

Thorium Bid, 1963, Health Physics Problems Associated with Thoria, letter from L. J. Swallow 

(United Nuclear Corporation) to A. Edelmann (Nuclear Science & Engineering); October 31, 1963; 

SRDB Ref ID: 62315 

Thorium Conversion, 1965, Test Conversion of Thorium Nitrate to Thorium Oxide, 224-U Building, 

General Electric, Hanford Atomic Products Operation – Richland, Washington; October 22, 1965; 

SRDB Ref ID: 52857 

Thorium Fuel Cycle, 2005, Thorium Fuel Cycle – Potential Benefits and Challenges, International 

Atomic Energy Agency; May 2005; SRDB Ref ID: 51181, pdf pp. 59-61 

Thorium License, 1958, Source Material License No. C-2734, Amendment 2, letter from J. C. Delaney 

(AEC Licensing Branch) to W. M. Leaders (Mallinckrodt Chemical Works); 1958; SRDB Ref ID: 

56165 

Thorium Meeting, 1965, Minutes of September 8, 1965 Thorium Operations and Planning Meeting, 

meeting between AEC and NLO at Fernald (discussion of Weldon Spring thorium work); September 

21, 1965; SRDB Ref ID: 43017 

Thorium Operations, 1965, Thorium Operations at MCW, memo from H. M. Roth (MCW Research 

and Development Division) to J. W. Ruch (MCW Feed Materials Division); November 2, 1965; 

SRDB Ref ID: 11799 

Thorium Shipments, 1969, Product Shipments, United Nuclear Corporation, various dates; SRDB Ref 

ID: 62478 

UF-6 Release, 1966, Report of UF-6 Release in Red Room on March 20, 1966, United Nuclear 

Corporation – Hematite; April 11, 1966; SRDB Ref ID: 62167 

UF-6 Release, 1967, UF-6 Release of 11-16-67, inter-office memo from R. E. Bilbrey to D. G. Darr; 

United Nuclear Corporation at Hematite; December 4, 1967; SRDB Ref ID: 62198 

UNC Health Physics, 1963, Health Physics Problems Associated with Thoria, letter from L.J Swallow 

(UNC) to Dr. Abraham Edelmann (Nuclear Science and Engineering); October 31, 1963; SRDB Ref 

ID: 62325 

UNC Health Physics, 1964, SNM-33 Amendment to Permit Blending Fully Enriched UO2 with 

Natural ThO2 in the Pellet Plant, letter from L.J Swallow (UNC Operations Control Manager) to Mr. 

Donald Nussbaumer (U.S. Atomic Energy Commission); March 31, 1964; SRDB Ref ID: 56730 

65 of 83 
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UNC In Vivo, 1963-1965, In Vivo Monitoring Data Results and Correspondence for 8-19-63 to 8-25-

65; SRDB Ref ID: 17041 

UNC Manual, 1963, Assorted pages of a United Nuclear Corporation , Hematite MO site, manual, 

United Nuclear Corporation, Chemicals Division; July 15, 1963; SRDB Ref ID: 62292 

UNC Memo, 1964, Disposition of Cleanliness and Criticality Problems Related to Item Process, 

inter-office memo from M. Collier to J. A. Lindberg; United Nuclear Corporation; July 30, 1964; 

SRDB Ref ID: 62290 

UNC Urinalysis, 1962-1963, UNC Uranium in Urine Sample Results for 12-3-62 to 3-25-63; SRDB 

Ref ID: 17045, pdf pp. 11-14 

UNC Urinalysis, 1962-1964, UNC Uranium in Urine Sample Results for 12-3-62 to 1-24-64; SRDB 

Ref ID: 11713 

UNC Urinalysis, 1963-1964, UNC Uranium in Urine Sample Results for 6-14-63 to 1-4-64; SRDB 

Ref ID: 11714 

UNC Urinalysis, 1972, UNC Urinalysis Data Sheet, United Nuclear Corporation, 1972; SRDB Ref 

ID: 62395 

Union Carbide, 1959, Health Physics and Hygiene Reports for the Operations Division for December 

1958 through October 1959; Union Carbide Nuclear Company; January 13, 1959 - November 13, 

1959; SRDB Ref ID: 17696 

Un-irradiated Scrap, 1958, Unirradiated Enriched Uranium Scrap Recovery, Atomic Industrial 

Progress and Second World Conference, U.S. Government; Jly-December 1958; SRDB Ref ID: 3944, 

pdf pp. 14-15 

United Nuclear HSA, 2003, Hematite Former Fuel Cycle Facility Decommissioning: Historical Site 

Assessment; DO-02-001, Rev. 0.2; Westinghouse Electric Company LLC; SRDB Ref ID: 56469 

UO2 Release, 1968a, Report on a UO2 Release in the Recycle Process Facility, from F. G. Stengel 

(General Manager, United Nuclear Corporation - Hematite) to L. D. Lowe (AEC); May 17, 1968; 

SRDB Ref ID: 62165 

UO2 Release, 1968b, Brown Monday Incident, from J. A. Rode to F. G. Stengel, United Nuclear 

Corporation - Hematite; April 11, 1968; SRDB Ref ID: 62196 

UO2 Exposure, 1969, Report of Red Room UO2 Exposure of May 14, 1969, from D. G. Darr to L. J. 

Swallow; United Nuclear Corporation - Hematite; 1969; SRDB Ref ID: 62141 

Uranium Allocations, 1959, Letter Requesting Allocations of Uranium Hexafluoride, from S. D. 

North (Manager, Hematite Plant) to L. Johnson (U.S. Atomic Energy Commission); Mallinckrodt 

Nuclear Corporation; October 27, 1959; SRDB Ref ID: 62275 

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Uranium Dust, 1962, Uranium Dust Study of Pellet Plant Operations – Bldg. 255-2, United Nuclear 

Corporation; October 1962; SRDB Ref ID: 62306 

Urinalysis Results, 1960, Urinalysis Results for Hematite Plant workers taken April 4 to May 15, 

1960; Mallinckrodt Chemical Works, St. Louis; July 7, 1960; SRDB Ref ID: 62311 

Urinalysis Results, 1965-68, Various handwritten bioassay results for Hematite Operators for 1965-

1968; United Nuclear Corporation; 1965-1968; SRDB Ref ID: 62335 

Various authors, 1963, UNC Bioassay Program Information and Some Results for 4-19-63 to 11-4-63; 

various authors; SRDB Ref ID: 11724 

W. R. Grace, 1963, Feasibility Report #47, report from F. Forscher (Nuclear Metals and Equipment 

Corporation) to C. A. Keller (AEC Production Division); October 22, 1963; SRDB Ref ID: 11965 

Westinghouse, 2003, Historical Site Assessment for Hematite Former Fuel Cycle Facility; 

Westinghouse; May 20, 2003; SRDB Ref ID: 30008 

Westinghouse, 2004, Westinghouse FFCF Radiological Survey Forms for Plant-wide Survey of 

Hematite Site, Westinghouse; various dates and site locations in 2004; SRDB Ref ID: 62026 

Westinghouse, 2006, Hematite Radiological Characterization Report, DO-04-010, Rev. 01; 

Westinghouse; April 2006; SRDB Ref ID: 56466 

Westinghouse Plan, 2006, Hematite Decommissioning Plan, Westinghouse; April 2006; SRDB Ref 

ID: 52882 

Whole Body, 1969, Whole Body Counting Results; interoffice memo from D. G. Darr to L. J. 

Swallow; United Nuclear Corporation; March 13, 1969; SRDB Ref ID: 62334 

Whole Body Counts, 1968-73, Results of Hematite Whole Body Counts, memos and results, United 

Nuclear Corporation; various dates; SRDB Ref ID: 62412 

Whole Body Issues, 1968-69, Various documents related to whole body counting parameters, results, 

job re-assignments, personnel restrictions, United Nuclear Corporation; 1968-1969; SRDB Ref ID: 

62429 

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Attachment 1: Data Capture Synopsis 

Table A1-1: Data Capture Synopsis for United Nuclear Corp., Hematite, Mo. 

Data Capture Information Data Captured Description Date 

Primary Site/Company Name: United Nuclear Corp AWE 1958-1969; Residual Radiation 1970-July 2006 Other company names: 1956-1961 Mallinckrodt Chemical Works 1961-1970 United Nuclear Corporation 1970-1973 Gulf United Nuclear Fuels Corporation, a joint venture of Gulf Nuclear Corporation and United Nuclear Corporation 1973 United Nuclear closed the plant and began decommissioning 1974-1989 Combustion Engineering, plant restarted to produce commercial nuclear fuel rods 1989-2000 Asea Brown Boveri/Combustion Engineering 2000-Present Westinghouse Electric Company (Ron Dutton: 314-810-3343) 

AEC/NRC inspections, air sample data, bioassay results, Brush Beryllium raffinates, burial pit area survey, daily air sample records (DASRs), lapel samples and contamination surveys, effluent monitoring reports, Elk River Thorium hand written note, four employees taken to Oak Ridge Office for in-vivo count with very high body burdens, environmental data, external exposure information, individual whole body counts, license SNM-33 items, list of materials for on-site burial, Mallinckrodt uranium urinary program document, memo with some details on thorium work, Maximum Permissible Concentration (MPC)cumulative hours for some employees, Pond and Joachim Creek sample results, radiological surveys, shipping log, Thorium Oxide MPC, Thorium Ceramics Technical Data Manual - Oxides, various incident reports, and weekly progress reports. 

04/14/2

State Contacted: Missouri Department of Natural Resources (Keith Henke: (573)751-6111; Rhonda Loveall 573-751-3043) 

Process knowledge interview, interim groundwater monitoring plan, site description, human health risk assessment, ecological risk assessment, and site chronology. 

09/30/2

Cincinnati Public Library Development and testing of high-loaded Uranium Oxide--Cb 

cermet fuel, fuel elements for the Argonne Advance Research Reactor, radiation protection during handling of plutonium recycle fuel rods and assemblies, United Nuclear Corporation Plutonium Facility, and uranium recovery as a by-product of phosphoric acid production. 

01/16/2

Comprehensive Epidemiologic Data Resource (CEDR) No relevant data identified. 12/03/2

DOE Hanford Declassified Document Retrieval System (DDRS) 

Inventory of Plutonium scrap. 09/18/2

DOE Legacy Management Grand Junction Office DVD Files 

Airborne radioactivity reports, environmental monitoring, material accountability reports, AEC licenses including correspondence and amendments, material transfers and purchases, compliance inspection reports, procedures, waste disposal, nuclear safety calculations, stakeholder complaints, shipping procedures, shipping container design, and AEC contracts. 

12/28/2

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Table A1-1: Data Capture Synopsis for United Nuclear Corp., Hematite, Mo. 

Data Capture Information Data Captured Description Date 

DOE Legacy Management - MoundView (Fernald Holdings, includes Fernald Legal Database) 

Comments on the proposed Clean Air Act effluent limitations for radionuclide emissions from NRC licensed activities. 

07/30/2

DOE OpenNet Eight major processes of the Nuclear Weapons Complex. 11/30/2Office of Scientific & Technical Information (OSTI) Carbide fuel development report. 11/06/2DOE OSTI Energy Citations Aerial radiological survey of the area surrounding UNC, carbide 

fuel development progress report, disposal of United Nuclear materials at the Y-12 Plant, examination of an irradiated prototype fuel element for the Elk River Reactor, out-of-pile properties of mixed uranium-plutonium carbides progress report, proposed plan for the United Nuclear Corporation disposal site at the Oak Ridge Y-12, and a study of uranium-plutonium monoxides report. 

04/28/2

DOE OSTI Information Bridge Carbide fuel development, groundwater monitoring, uranium alloy 

metallurgy, and FY-1973 radioisotope shipments. 

01/01/2

General Atomics System for Nuclear Auxiliary Power (SNAP) 8ER reports and 

GAMAS trailer exposures. 

01/10/2

Google U.S. nuclear weapons research, development, testing, and 

production, Naval Nuclear Propulsion Facilities, baseline human health risk assessment for the Westinghouse Hematite Site, Hematite Nuclear Fuel Facility chronology, various patents, Duane Hall talks about Elk River's Nuclear Reactor. 

05/10/2

National Archives and Records Administration (NARA) - Atlanta 

Bioassay program and results, processing, and in-vivo monitoring data. 

03/30/2

National Academies Press (NAP) No relevant data identified. 12/03/2NIOSH/OCAS Historical generation and flow of recycled uranium at the 

Savannah River Site. 

08/23/2

National Nuclear Security Administration (NNSA) - Nevada Site Office 

No relevant data identified. 12/03/2

Nuclear Regulatory Commission (NRC) Agencywide Document Access and Management (ADAMS) 

AEC licenses including correspondence and amendments, site radiological characterization, decommissioning status reports, FOIA responses, aerial survey, environmental impact information, compliance inspections, corrective action plans, decommissioning plans, and a burial site survey. 

01/01/2

NRC Records Annual exposure summaries, license SNM-33 correspondence, 

and airborne uranium dust exposures. 

07/13/2

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Table A1-1: Data Capture Synopsis for United Nuclear Corp., Hematite, Mo. 

Data Capture Information Data Captured Description Date 

ORAU Team Process knowledge interviews, employee lists, evaluations of 

medical and work history records, site profiles for AWE's that processed Uranium and Thorium, and Appendix D United Nuclear Corporation. 

02/05/2

ORAU Vault Mallinckrodt correspondence. 04/02/2

Science Applications International Corporation (SAIC) Annual summary of exposures. 09/02/2

Southern Illinois University Radiological contingency plans, requests for information, request 

for environmental monitoring, and news articles. 

10/27/2

University of Rochester Correspondence on fissionable materials. 08/20/2

U.S. Army Corps of Engineers Uranium residues historical synopsis. 03/18/2Washington State University (U.S. Transuranium and Uranium Registries) 

No relevant data identified. 12/03/2

Unknown Responses to exposure information requests, site descriptions and 

inspections, correspondence regarding and inspections of license SNM-33, material transfer requests, and recycled uranium program. 

07/06/2

TOTAL 

Table A1-2: Database Searches for United Nuclear Corp. 

Database/Source Keywords H

DOE OpenNet http://www.osti.gov/opennet/advancedsearch.jsp COMPLETED 11/30/2008 

"United Nuclear" + Hematite + 01/01/1957 - 11/25/2008 

DOE OSTI Energy Citations http://www.osti.gov/energycitations/ COMPLETED 04/28/2009 

"United Nuclear" + 01/01/1957 - 11/26/2008 "United Nuclear" + Hematite + 01/01/1957 - 11/26/2008 

DOE OSTI Information Bridge http://www.osti.gov/bridge/advancedsearch.jsp COMPLETED 01/01/2009 

"United Nuclear " + 01/01/1957 - 11/25/2008 "United Nuclear" + Hematite + 01/01/1957 - 11/26/2008 

NRC ADAMS Reading Room http://www.nrc.gov/reading-rm/adams/web-based.html COMPLETED 01/01/2009 

"United Nuclear" AND Hematite 

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Table A1-2: Database Searches for United Nuclear Corp. 

Database/Source Keywords H

DOE CEDR http://cedr.lbl.gov/ COMPLETED 12/03/2008 

"United Nuclear" 

DOE Hanford DDRS http://www2.hanford.gov/declass/ COMPLETED 09/18/2008 

"United Nuclear" + 01/01/1957 - 11/25/2008 

National Academies Press http://www.nap.edu/ COMPLETED 12/03/2008 

"United Nuclear" + Hematite 

NNSA - Nevada Site Office www.nv.doe.gov/main/search.htm COMPLETED 12/03/2008 

"United Nuclear" 

U.S. Transuranium & Uranium Registries http://www.ustur.wsu.edu/ COMPLETED 12/03/2008 

"United Nuclear" 

Google http://www.google.com COMPLETED 05/10/2009 

americium OR Am241 OR Am-241 OR "AM 241" OR 241Am OR 241-Am OR "241 Am"+"United Nuclear" + Hematite ionium OR Th230 OR Th-230 OR "Th 230" OR 230Th OR 230-Th OR "230 Th"+"United Nuclear" + Hematite neptunium OR Np237 OR Np-237 OR "Np 237" OR 237Np OR 237-Np OR "237 Np"+"United Nuclear" + Hematite polonium OR Po210 OR Po-210 OR "Po 210" OR 210Po OR 210-Po OR "210 Po" +"United Nuclear" + Hematite thorium OR Th232 OR Th-232 OR "Th 232" OR 232Th OR 232-Th+"United Nuclear" + Hematite "232 Th" OR "Z metal" OR myrnalloy OR "chemical 10-66" OR "chemical 10-12"+"United Nuclear" + Hematite ionium OR UX1 OR UX2 OR Th-230 OR Th230 OR "Th 230" OR 230-Th OR "230 Th"+"United Nuclear" + Hematite 

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Table A1-2: Database Searches for United Nuclear Corp. 

Database/Source Keywords H

230Th OR Th-234 OR Th234 OR "Th 234" OR 234-Th OR 234Th OR "234 Th"+"United Nuclear" + Hematite tritium OR H3 OR H-3 OR mint OR HTO+"United Nuclear" + Hematite  uranium OR U233 OR U-233 OR "U 233" OR 233U OR 233-U OR "233 U" +"United Nuclear" + Hematite U234 OR "U 234" OR U-234 OR 234U OR 234-U OR "234 U"+"United Nuclear" + Hematite U235 OR "U 235" OR U-235 OR 235-U OR 235U OR "235 U" OR U238 +"United Nuclear" + Hematite "U 238" OR U-238 OR 238-U OR 238U OR "238 U"+"United Nuclear" + Hematite U308 OR "U 308" OR U-308 OR 308-U OR 308U OR "308 U" OR "uranium extraction" OR "black oxide" OR "brown oxide"+"United Nuclear" + Hematite "green salt" OR "orange oxide" OR "yellow cake" OR UO2 OR UO3+"United Nuclear" + Hematite UF4 OR UF6 OR C-216 OR C-616 OR C-65 OR C-211 OR U3O8+"United Nuclear" + Hematite plutonium OR Pu-238 OR Pu238 OR "Pu 238" OR 238Pu OR 238-Pu OR "238 Pu" +"United Nuclear" + Hematite Pu-239 OR Pu239 OR "Pu 239" OR 239Pu OR 239-Pu OR "239 Pu"+"United Nuclear" + Hematite Pu-240 OR Pu240 OR "Pu 240" OR 240Pu OR 240-Pu OR "240 Pu"+"United Nuclear" + Hematite 

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Table A1-2: Database Searches for United Nuclear Corp. 

Database/Source Keywords H

Pu-241 OR Pu241 OR "Pu 241" OR 241Pu OR 241-Pu OR "241 Pu"+"United Nuclear" + Hematite radium OR Ra-226 OR Ra226 OR "Ra 226" OR 226-Ra OR 226Ra OR 226-Ra +"United Nuclear" + Hematite Ra-228 OR Ra228 OR "Ra 228" OR 228Ra OR 228-Ra OR "228 Ra"+"United Nuclear" + Hematite radon OR Rn-222 OR Rn222 OR "Rn 222" OR 222Rn OR 222-Rn OR "222 Rn"+"United Nuclear" + Hematite thoron OR Rn-220 OR Rn220 OR "Rn 220" OR 220Rn OR 220-Rn OR "220 Rn"+"United Nuclear" + Hematite protactinium OR Pa-234m OR Pa234m OR "Pa 234m" OR 234mPa OR 234m-Pa OR "234m Pa"+"United Nuclear" + Hematite strontium OR Sr-90 OR Sr90 OR "Sr 90" OR 90-Sr OR 90Sr OR "90 Sr"+"United Nuclear" + Hematite oralloy OR postum OR tuballoy OR "uranyl nitrate hexahydrate" OR UNH OR K-65 OR "sump cake"+"United Nuclear" + Hematite "uranium dioxide" OR "uranium tetrafluoride" OR "uranium trioxide"+"United Nuclear" + Hematite "uranium hexafluoride" OR "air count"+"United Nuclear" + Hematite accident+"United Nuclear" + Hematite "air dust" OR "air filter" OR "airborne test"+"United Nuclear" + Hematite "alpha particle" OR "belgian congo ore" OR bioassay OR bioassay+"United Nuclear" + Hematite 

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Table A1-2: Database Searches for United Nuclear Corp. 

Database/Source Keywords H

breath OR "breathing zone" OR BZ OR calibration OR "chest count" OR collimation OR columnation+"United Nuclear" + Hematite contamination OR curie OR denitration OR "denitration pot"+"United Nuclear" + Hematite derby OR regulus OR dose OR dosimeter+"United Nuclear" + Hematite dosimetric OR dosimetry OR electron OR environment+"United Nuclear" + Hematite "Ether-Water Project" OR exposure OR "exposure investigation" OR "radiation exposure"+"United Nuclear" + Hematite external OR "F machine" OR fecal OR "feed material" OR femptocurie OR film OR fission OR fluoroscopy+"United Nuclear" + Hematite "Formerly Utilized Sites Remedial Action Program" OR FUSRAP OR gamma-ray OR "gas proportional" OR "gaseous diffusion"+"United Nuclear" + Hematite health OR "health instrument" OR "health physics" OR "H.I." OR HI OR HP OR "highly enriched uranium" OR HEU+"United Nuclear" + Hematite hydrofluorination OR "in vitro" OR "in vivo" OR incident OR ingestion OR inhalation OR internal+"United Nuclear" + Hematite investigation OR isotope OR isotopic OR "isotopic enrichment" OR "JS Project" OR Landauer OR "liquid scintillation"+"United Nuclear" + Hematite log OR "log sheet" OR "log book" OR "low enriched uranium" OR LEU+"United Nuclear" + Hematite 

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Table A1-2: Database Searches for United Nuclear Corp. 

Database/Source Keywords H

"maximum permissible concentration" OR MPC OR metallurgy OR microcurie OR millicurie+"United Nuclear" + Hematite "mixed fission product" OR MFP OR monitor OR "air monitoring" OR nanocurie OR "nasal wipe" OR neutron OR "nose wipe"+"United Nuclear" + Hematite nuclear OR Chicago-Nuclear OR "nuclear fuels" OR "nuclear track emulsion" OR "type A" +"United Nuclear" + Hematite NTA OR "occupational radiation exposure" OR occurrence OR "ore concentrate" OR "PC Project"+"United Nuclear" + Hematite permit OR "radiation work permit" OR "safe work permit" OR "special work permit" OR RWP OR SWP+"United Nuclear" + Hematite "phosphate research" OR photofluorography OR photon OR picocurie OR pitchblende OR "pocket ion chamber" OR PIC OR problem OR procedure+"United Nuclear" + Hematite radeco OR radiation OR radioactive OR radioactivity OR radiograph OR radiological+"United Nuclear" + Hematite "Radiological Survey Data Sheet" OR RSDS OR radionuclide OR raffinate OR reactor+"United Nuclear" + Hematite respiratory OR "retention schedules" OR roentgen+"United Nuclear" + Hematite sample OR "air sample" OR "dust sample" OR "general area air sample"+"United Nuclear" + Hematite "solvent extraction" OR source OR "sealed source" OR spectra OR spectrograph OR spectroscopy +"United Nuclear" + Hematite 

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Table A1-2: Database Searches for United Nuclear Corp. 

Database/Source Keywords H

spectrum OR standard OR "operating standard" OR "processing standard"+"United Nuclear" + Hematite survey OR "building survey" OR "routine survey" OR "special 

survey" OR "technical basis"+"United Nuclear" + Hematite "thermal diffusion" OR "thermoluminescent dosimeter" OR TLD OR "Tiger Team"+"United Nuclear" + Hematite "tolerance dose" OR urinalysis OR urine OR "whole body count" OR WBC +"United Nuclear" + Hematite "working level" OR WL OR X-ray OR "X ray" OR Xray OR "xray screening"+"United Nuclear" + Hematite "Mallinckrodt Chemical Works"+Hematite "Gulf United Nuclear Fuels Corporation" GUNFCO "Combustion Engineering"+Hematite "Asea Brown Boveri/Combustion Engineering" "Asea Brown Boveri"+Hematite 

Table A1-3: OSTI Documents Ordered for United Nuclear Corp. 

Document Number Document Title R

NUREG-0532 OSTI ID: 6426034 SRDB: 

Final Environmental Statement Related To The United Nuclear Corporation, Morton Ranch, Wyoming Uranium Mill (Converse County, Wyoming) 

01/13/

PB-90-111311/XAB OSTI ID: 5274400 SRDB: N/A 

Health Assessment For United Nuclear Corporation Churchrock 

NPL (National Priorities List) Site, McKinley County, New Mexico, Region 6. CERCLIS No. NMD030443303. Final Report 

01/13/

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Table A1-3: OSTI Documents Ordered for United Nuclear Corp. 

Document Number Document Title R

NDA-2165-5 OSTI ID: 4803712 SRDB: N/A 

Carbide Fuel Development. Phase III Report, September 15, 1960-September 15, 1961 

01/13/

PB-89-206171/XAB; EPA/ROD/RO-6-88/044 OSTI ID: 5624608 SRDB: N/A 

Superfund Record Of Decision (EPA Region 6): United Nuclear Corporation, McKinley County, New Mexico, Ground-Water Operable Unit (First Remedial Action) September 1988 

01/13/

N/A OSTI ID: 6946920 SRDB: N/A 

Uranium Cartel's Fallout: Billion-Dollar Lawsuits Are Popping Up 

Everywhere Dated 11/21/1977 From Time? Pp 96-98 

01/13/

UNC-5118 OSTI ID: 4591969 SRDB: 65411 

Shield Small Source Experiments. Report No. 2 Dated 5/6/1965 01/13/

UNC-5046 OSTI ID: 4731602 SRDB: 65417 

Sponge Fuel Evaluation. Phase II Report, August 23, 1961 To January 31, 1963 

01/13/

UNC-5094 OSTI ID: 4618068 SRDB: 65412 

Carbide Fuel Development. Progress Report, October 1, 1963 To June 30, 1964 

01/13/

UNC-5081 OSTI ID: 4618481 SRDB: 65414 

Carbide Fuel Development. Phase V Report, October 1, 1962-September 30, 1963 

01/13/

UNC-5198 OSTI ID: 4511540 SRDB: 65410 

Post-Irradiation Examination Of High-Density (Upu)C PelletFueled Ebr-Ii Rods Irradiated To 30,000 Mwd/T Dated 1/1/1968 01/13/

UNC-5144 OSTI ID: 4537877 SRDB: 65007 

Study Of Uranium-Plutonium Monoxides. Final Summary Report Dated 1/31/1966 

01/13/

UNC-5138 OSTI ID: 4607769 SRDB: 65010 

Study Of Uranium-Plutonium Monoxides. Quarterly Progress Report, July 1- September 30, 1965 

01/13/

UNC-5055 OSTI ID: 4685476 SRDB: 65097 

Carbide Fuel Development. Phase IV Report, September 15, 1961-September 30, 1962 

01/13/

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Table A1-3: OSTI Documents Ordered for United Nuclear Corp. 

Document Number Document Title R

UNC-5074 OSTI ID: 4111496 SRDB: 65005 

Out-Of-Pile Properties Of Mixed Uranium-Plutonium Carbides. Final Report Dated 12/6/1963 

01/13/

UNC-5056 OSTI ID: 4685447 SRDB: 65092 

Carbide Fuel Development. Progress Report, October 1, 1962-March 31, 1963 

01/13/

UNC-RD-3061 CONF-650616-32 OSTI ID: 4450054 SRDB: 64285 

Some Problems And Advances In The State-Of-The-Art In The Analysis Of The Wood River Junction, Rhode Island Accidental Criticality Excursion Dated 1/1/1965 

01/13/

UNC-1001 OSTI ID: 4828518 SRDB: 64295 

Characterization Of Uo2 Powders. Quarterly Report No. 5, October 10, 1961 To January 10, 1962 

01/13/

UNC-1000 OSTI ID: 4832177 SRDB: 64300 

Characterization Of Uo2 Powders. Fourth Quarterly Report, July 10, 1961- October 10, 1961 

01/13/

ORO-468 OSTI ID: 4837429 SRDB: 64304 

Characterization Of Uo2 Powders. Progress Report No. 8, May And June 1961 

01/13/

CONF-39-51 OSTI ID: 4504180 SRDB: 64287 

Fuel Elements For The Argonne Advanced Research Reactor Dated 1/1/1962 From American Nuclear Society Meeting June 1963 Pg 18? 

01/13/

UNC-5072 OSTI ID: 4081098 SRDB: 64282 

Shield Small Source Experiments. Summary Report Dated 11/8/1963 

01/13/

UNC-5065 OSTI ID: 4159280 SRDB: 64284 

Out-Of-Pile Properties Of Mixed Uranium-Plutonium Carbides. Progress Report, February 6, 1962-October 31, 1962 

01/13/

UNC-5015 OSTI ID: 4772538 SRDB: 64290 

Fuel Cycle Development Program. Quarterly Progress Report, 

January 1 To March 31, 1962 

01/13/

CONF-127-1 OSTI ID: 4679109 SRDB: 61986 

Recent Advances In The Powder Metallurgy Of Uranium Carbide Dated 10/31/1962 

01/13/

UNC-3001 OSTI ID: 4787377 SRDB: 61993 

Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report, October 1-December 31, 1961 

01/13/

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Table A1-3: OSTI Documents Ordered for United Nuclear Corp. 

Document Number Document Title R

UNC-5263 OSTI ID: 4097063 SRDB: 61982 

Fast Reactor Mixed-Carbide Fuel Element Development Program. 

Twelfth Quarterly Progress Report, April--June 1970 

01/13/

UNC-5003 OSTI ID: 4816515 SRDB: 61996 

Carbide Fuel Development. Progress Report, September 15, 1961 To December 31, 1961 

01/13/

NDA-2162-3 OSTI ID: 4045372 SRDB: 61981 

Carbide Fuel Development. Progress Report Period, February 1, 1961 To April 30, 1961 

01/13/

UNC-5030 OSTI ID: 4785553 SRDB: 61990 

Carbide Fuel Development. Progress Report, April 1, 1962 To June 30, 1962 

01/13/

UNC-5013 OSTI ID: 4800249 SRDB: 61995 

Carbide Fuel Development. Progress Report, January 1, 1962 To March 31, 1962 

01/13/

UNC-5217 OSTI ID: 4476426 SRDB: 61985 

Fast Reactor Mixed-Carbide Fuel Element Development Program. Third Quarterly Progress Report, January--March 1968 

01/13/

UNC-5238 OSTI ID: 4176921 SRDB: 61984 

Fast Reactor Mixed-Carbide Fuel Element Development Program. Quarterly Progress Report No. 6, October--December 1968 

01/13/

UNC-5048 OSTI ID: 4721743 SRDB: 61989 

The Development Of Uranium Carbide As A Nuclear Fuel. Third Annual Report, September 1, 1961 To October 31, 1962 

01/13/

Y/ER/Sub-90 VK168/4-D2 ER-16-D2 OSTI ID: 5534924 SRDB: 61997 

Proposed Plan For The United Nuclear Corporation Disposal Site At The Oak Ridge Y-12 Plant, Oak Ridge, Tennessee Dated 3/1/1991 

01/13/

Y/TS-827 OSTI ID: 6677900 SRDB: 62000 

Disposal Of United Nuclear Company Materials At The Y-12 Plant Dated 12/19/1983 

01/13/

EGG-1183-1756-Rev. 1 OSTI ID: 6316102 SRDB: 61998 

Aerial Radiological Survey Of The Area Surrounding The UNC Recovery Systems Facility, Wood River Junction, Rhode Island Dated 5/1/1981 

01/13/

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Table A1-3: OSTI Documents Ordered for United Nuclear Corp. 

Document Number Document Title R

CONF-710617-1 OSTI ID: 4715735 SRDB: 61988 

Nuclear Materials Control System In A Multi-Enrichment 

Processing Plant. Dated 6/29/1971 From The 12th Annual Meeting Of The Nuclear Materials Management 

01/13/

UNC-5264 or BHO-66-1 OSTI ID: 4083688 SRDB: 60742 

Plutonium Passive Assay Facility Plant Instrumentation Program. First Quarterly Progress Report, April--June 1970 

01/13/

UNC-5266 or BHO-65-1 OSTI ID: 4084733 SRDB: 60745 

Enriched Uranium Active Assay Program. First Quarterly Progress Report, April--June 1970 

01/13/

US 3632095 OSTI ID: 4688644 SRDB: 57574 

Carrier For Uranium Oxide Pellets Dated 12/31/1972 (Patent) 01/12/

US 3413099 OSTI ID: 4794811 SRDB: 57573 

Production Of Uranium Tetrafluoride Dated 1/1/1968 (Patent) 01/12/

US 3019139 OSTI ID: 4822590 SRDB: 57572 

Chemical Process And Product Formed Dated 1/30/1962 (Patent) 01/12/

GB 1073198 OSTI ID: 4342486 SRDB: 57569 

Device For Measuring The Carbon Content Of Molten Metal Dated 7/1/1967 (Patent) 

01/12/

GB 1260562 OSTI ID: 4690162 SRDB: 57571 

Production Of Uranyl Fluoride Dated 1/1/1972 (Patent) 01/12/

N/A OSTI ID: 4531422 SRDB: 53617 

Carbide Fuel Development. Final Report, May 15, 1959-October 15, 1965 

01/12/

UNC-5134;(Vol.1) OSTI ID: 4550383 SRDB: 53617 

Carbide Fuel Development. Final Report, May 15, 1959-October 15, 1965 

10/20/

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Table A1-4: Cincinnati Public Library Documents Ordered for United Nuclear Corp. 

Document Number Document Title R

N/A OSTI ID: 4671348 

Effects Of Fabrication And Composition On The Irradiation Stability Of Uranium Carbide Dated 1/1/1964 From Met Soc, Am Inst Mining, Met Petrol Engrs, Inst Metals Div, Spec Rept, Vol. 13 Pp 765-784 

N/A 

N/A OSTI ID: 4767976 SRDB: 60045 

United Nuclear Corporation Plutonium Facility Dated 1/1/1962 From The Proceedings Of The Hot Lab Equipment Conference, 10th Pp 313-320 

01/13/

N/A OSTI ID: 4740539 SRDB: 59985 

Arc Skull Melting And Casting Of Uranium Carbide Dated 3/1/1963 From American Society Metals, Trans. Quart Vol 56 Pp 176-193 

01/13/

N/A OSTI ID: 4346387 SRDB: 59975 

Monoxide-Type Compounds Of Uranium And Plutonium: I. Oxycarbides Dated 6/21/1967 From The Journal Of American Ceram Soc Vol. 50 Pp 321-325 

01/16/

N/A OSTI ID: 4258537 SRDB: 60005 

Recovery And Restoration Phases Of A Criticality Accident Dated 1/1/1974 From The Transactions Of The American Nuclear Society Vol. 19 Pp 193-194 

01/15/

N/A OSTI ID: 4204735 SRDB: 60043 

Uranium Recovery As A By-Product Of Phosphoric Acid Production Dated 6/1/1975 From The Transactions Of The American Nuclear Society Vol. 21 Pg 245 

01/15/

N/A OSTI ID: 4100019 SRDB: 60041 

Requirements For Radiation Protection During Handling Of Plutonium Recycle Fuel Rods And Assemblies Dated 11/1970 From The Transactions Of The American Nuclear Society Vol. 13 Pp 883-884 

01/15/

N/A OSTI ID: 4828168 SRDB: 59976 

Selection Of A Uranium Diluent Enrichment For Recycled Plutonium Dated 11/1968 From The Transactions Of The American Nuclear Society Vol. 11 Pp 440-441 

01/14/

N/A OSTI ID: 4733964 SRDB: 59983 

Fabrication Of Uranium--Plutonium Carbides Dated 1/1/1969 From The Transactions Of The American Nuclear Society Vol. 12 Pp 

578-579 

01/14/

N/A OSTI ID: 4813768 SRDB: 59978 

Fundamental Study Of The Compatibility Of Stainless Steel And Mixed Carbide Fuel Dated 1/1/1968 From The Transactions Of The American Nuclear Society Vol. 11 Pg 511 

01/14/

82 of 83 
77SEC-00116 01-28-10 Rev.1 FINAL 

Table A1-4: Cincinnati Public Library Documents Ordered for United Nuclear Corp. 

Document Number Document Title R

N/A OSTI ID: 4762207 SRDB: 59999 

United Nuclear Corporation Plutonium Facility Dated 11/1/1962 From The Transactions Of The American Nuclear Society Vol. 5 Pp 328-329 

01/13/

N/A OSTI ID: 4705788 SRDB: 60001 

Fuel Elements For The Argonne Advanced Research Reactor Dated 6/1/1963 From Transactions Of The American Nuclear Society Vol. 6 Pg 161 

01/13/

N/A OSTI ID: 4511791 SRDB: 60003 

Development And Testing Of High-Loaded Uo2--Cb Cermet Fuel Dated 1/1/1967 From Transactions Of The American Nuclear Society Vol. 10 Pp 483-484 

01/13/

83 of 83