SEC Petition Evaluation Report 

Petition SEC-00113 

Report Rev #: 0 Report Submittal Date: September 29, 2009

Subject Expert(s): Lori Arent, Eugene Potter, Paul Ruhter 

Site Expert(s): N/A 

Petition Administrative Summary 

Petition Under Evaluation 

Petition # Petition 

Type 

Petition 

Qualification Date 

DOE/AWE Facility Name 

SEC-00113 83.13 June 27, 2008 Brookhaven National Laboratory 

Petitioner Class Definition 

All employees who worked in any area at the Brookhaven National Laboratory from January 1, 1947 through 

December 31, 2007. 

Class Evaluated by NIOSH 

All employees who worked in any area at the Brookhaven National Laboratory from January 1, 1947 through 

December 31, 2007. 

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

All employees of the Department of Energy, its predecessor agencies, and its contractors and subcontractors 

who worked at Brookhaven National Laboratory in Upton, New York, from January 1, 1947 to December 31, 

1979, for a number of work days aggregating at least 250 work days, occurring either solely under this 

employment, or in combination with work days within the parameters established for one or more other classes 

of employees in the Special Exposure Cohort. 

Related Petition Summary Information 

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

None 

Related Evaluation Report Information 

Report Title DOE/AWE Facility 

Name 

None 

ORAU Lead Technical Evaluator: Tim Adler ORAU Review Completed By: Daniel Stempfley 

Peer Review Completed By: [Signature on file] 9/29/2009 

Grady Calhoun Date 

SEC Petition Evaluation Reviewed By: [Signature on file] 9/30/2009 

J. W. Neton Date 

SEC Evaluation Approved By: [Signature on file] 10/1/2009 

Larry Elliott Date 

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Evaluation Report Summary: SEC-00113 

Brookhaven National Laboratory 

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-00113, qualified on June 27, 2008, requested that NIOSH consider the following 

class: All employees who worked in any area at the Brookhaven National Laboratory from 

January 1, 1947 through December 31, 2007. 

Class Evaluated by NIOSH

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

evaluated the following class: All employees who worked in any area at the Brookhaven 

National Laboratory from January 1, 1947 through December 31, 2007. 

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

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

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The 

NIOSH-proposed class includes all employees of the Department of Energy, its predecessor 

agencies, and its contractors and subcontractors who worked at Brookhaven National Laboratory 

in Upton, New York, from January 1, 1947 to December 31, 1979, for a number of work days 

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

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

employees in the Special Exposure Cohort. The class under evaluation was reduced (see Section 

3.0 below) because sufficient monitoring data are available to estimate exposures with sufficient 

accuracy for all workers employed beginning January 1, 1980. 

Feasibility of Dose Reconstruction

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

workers at the site from January 1, 1947 through December 31, 1979. Though NIOSH has found 

documentation indicating that the appropriate monitoring practices were conducted during the 

specified time period, historical data management and data retention practices prevent NIOSH 

from confirming the current retrievability of the data necessary to estimate doses for members of 

the class. With the exception of this class, per EEOICPA and 42 C.F.R. § 83.13(c)(1), NIOSH 

has established that it has access to 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 

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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 proposed class under 

plausible circumstances beginning January 1, 1980. 

Health Endangerment Determination

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

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

the members of the proposed class from January 1, 1947 through December 31, 1979. 

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

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

to have involved exceptionally high-level exposures. However, evidence indicates that some 

workers in the proposed class may have accumulated substantial chronic exposures through 

episodic intakes of radionuclides, combined with external exposures to gamma, beta, and neutron 

radiation. Consequently, NIOSH has determined that health was endangered for those workers 

covered by this evaluation who were employed for at least 250 aggregated work days either 

solely under their employment or in combination with work days within the parameters 

established for other SEC classes (excluding aggregate work day requirements). 

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Table of Contents 

Evaluation Report Summary: SEC-00113 Brookhaven National Laboratory ......................................... 3

1.0 Purpose and Scope ........................................................................................................................ 10

2.0 Introduction ................................................................................................................................... 10

3.0 SEC-00113 Brookhaven National Laboratory Class Definitions ................................................. 11

3.1 Petitioner-Requested Class Definition and Basis ................................................................ 11

3.2 Class Evaluated by NIOSH .................................................................................................. 12

3.3 NIOSH-Proposed Class(es) to be Added to the SEC .......................................................... 12

4.0 Data Sources Reviewed by NIOSH to Evaluate the Class ........................................................... 12

4.1 Site Profile Technical Basis Documents (TBDs) ................................................................. 13

4.2 ORAU Technical Information Bulletins (OTIBs) and Procedures ...................................... 13

4.3 Facility Employees and Experts........................................................................................... 14

4.4 Previous Dose Reconstructions............................................................................................ 15

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

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

5.0 Radiological Operations Relevant to the Class Evaluated by NIOSH ......................................... 16

5.1 BNL Plant and Process Descriptions ................................................................................... 16

5.2 Radiological Exposure Sources from BNL Operations ....................................................... 20

5.2.1 Internal Radiological Exposure Sources from BNL Operations .............................. 20

5.2.1.1 Uranium .................................................................................................... 21

5.2.1.2 Fission and Activation Products ............................................................... 23

5.2.1.3 Tritium ...................................................................................................... 23

5.2.1.4 Thorium..................................................................................................... 24

5.2.1.5 Plutonium .................................................................................................. 25

5.2.1.6 Americium ................................................................................................ 25

5.2.1.7 Polonium ................................................................................................... 26

5.2.2 External Radiological Exposure Sources from BNL Operations ............................ 27

5.2.2.1 Photon ....................................................................................................... 27

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

5.2.2.3 Neutron ..................................................................................................... 28

5.2.3 Incidents ................................................................................................................... 28

6.0 Summary of Available Monitoring Data for the Class Evaluated by NIOSH .............................. 30

6.1 Available BNL Internal Monitoring Data ............................................................................ 33

6.2 Available BNL External Monitoring Data ........................................................................... 43

7.0 Feasibility of Dose Reconstruction for the Class Evaluated by NIOSH ...................................... 47

7.1 Pedigree of BNL Data .......................................................................................................... 48

7.1.1 Internal Monitoring Data Pedigree Review ............................................................. 51

7.1.2 External Monitoring Data Pedigree Review ............................................................ 55

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7.2 Evaluation of Bounding Internal Radiation Doses at BNL ................................................. 56

7.2.1 Evaluation of Bounding Process-Related Internal Dose Data ................................. 56

7.2.1.1 Urinalysis Information and Available Data .............................................. 57

7.2.1.2 Whole Body Counting Information and Available Data .......................... 62

7.2.1.3 Other Types of Bioassay ........................................................................... 64

7.2.1.4 Evaluation of Bounding Process-Related Internal Dose Data 

Summary ................................................................................................... 64

7.2.2 Evaluation of Bounding Ambient Environmental Internal Doses ........................... 65

7.2.3 Methods for Bounding Internal Dose at BNL .......................................................... 65

7.2.3.1 Methods for Bounding Process-Related Internal Dose ............................. 65

7.2.4 Internal Dose Reconstruction Feasibility Conclusion .............................................. 68

7.3 Evaluation of Bounding External Radiation Doses at BNL ................................................ 68

7.3.1 Evaluation of Bounding Process-Related External Dose Data ................................ 69

7.3.1.1 Personnel Dosimetry Data ........................................................................ 69

7.3.1.2 Area Monitoring Data ............................................................................... 72

7.3.2 Evaluation of Bounding Ambient Environmental External Doses .......................... 72

7.3.3 BNL Occupational X-Ray Examinations ................................................................. 72

7.3.4 Methods for Bounding External Dose at BNL ........................................................ 73

7.3.4.1 Methods for Bounding Operational Period External Dose ....................... 73

7.3.5 External Dose Reconstruction Feasibility Conclusion ............................................ 74

7.4 Evaluation of Petition Basis for SEC-00113 ....................................................................... 74

7.4.1 No or Insufficient Internal Monitoring .................................................................... 74

7.5 Summary of Feasibility Findings for Petition SEC-00113 .................................................. 76

8.0 Evaluation of Health Endangerment for Petition SEC-00113 ...................................................... 77

9.0 Class Conclusion for Petition SEC-00113 .................................................................................... 77

10.0 References ..................................................................................................................................... 80

Attachment 1: BNL Internal Data Analysis Matrix ............................................................................. 102

Attachment 2: Number of Persons Monitored Each Year at BNL ...................................................... 106

Attachment 3: Two-Hundred-Person Data Capture ............................................................................. 112

Attachment 4: H-3 Results Not Matched, Total Results in the Index, and Total Results in PM and 

 Medical Files ................................................................................................................. 114

Attachment 5: Misc Bioassay Results Not Matched, Total Results in the Index, and Total Results 

 in PM and Medical Files ............................................................................................... 115

Attachment 6: WBC Results Not Matched, Total Results in the Index, and Total Results in PM 

 and Medical Files .......................................................................................................... 116

Attachment 7: Data Capture Synopsis ................................................................................................. 117

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Figure 

5-1: Aerial view of Brookhaven National Laboratory. ................................................................. 17

6-1: Maximum External Dose Range and Average Dose by Year ............................................... 46

Tables 

4-1: No. of BNL Claims Submitted Under the Dose Reconstruction Rule .................................. 15

5-1: Potential Contributors to BNL Internal Dose and Their Primary Modes of Decay .............. 21

5-2: Major BNL Incidents ............................................................................................................. 29

6-1: Sources for Monitoring Data ................................................................................................. 32

6-2: Internal Dosimetry Timelines and Data Source Descriptions ............................................... 33

6-3: Total No. of In Vitro Results/Yr and No. of Individual Radionuclide Results/Yr* .............. 36

6-4: Total No. of In Vivo Results/Yr and No. of Individual Radionuclide Results/Yr ................. 40

6-5: Minimum Detectable Levels for Photon, Beta, and Neutron Dose (mrem) .......................... 43

6-6: External Dosimetry Timelines and Data Source Descriptions .............................................. 44

7-1: BNL Data Capture Summary ................................................................................................ 50

7-2: Sixty-Nine-Person Requested Monitoring Data Retrieval Test ............................................ 54

7-3: Urine Results Obtained for Fission and Activation Products ................................................ 60

7-4: Summary of Feasibility Findings for SEC-00113 ................................................................. 76

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SEC Petition Evaluation Report for SEC-00113

1.0 Purpose and Scope 

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

area at the Brookhaven National Laboratory from January 1, 1947 through December 31, 2007. 

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 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 

 

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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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-00113 Brookhaven National Laboratory Class Definitions 

The following subsections address the evolution of the class definition for SEC-00113, 

Brookhaven National Laboratory (BNL). 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 the 

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-00113, qualified on June 27, 2008, requested that NIOSH consider the following 

class for addition to the SEC: All employees who worked in any area at the Brookhaven National 

Laboratory from January 1, 1947 through December 31, 2007. 

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

that accurate dose reconstruction over time is impossible for the BNL workers in question. 

NIOSH deemed the following information and affidavit statements sufficient to qualify SEC00113 for evaluation: 

 

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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“To the best of my knowledge there was no internal monitoring for some individuals at 

Brookhaven National Laboratory and insufficient internal monitoring for the class in the 

early 1980’s.” 

Based on its BNL research and data capture efforts, NIOSH determined that it has access to 

internal and external monitoring data for BNL workers during the time period under evaluation. 

However, NIOSH could not establish that internal records are available for all time periods. 

NIOSH concluded that there is sufficient documentation to support, for at least part of the 

proposed time period, the petition basis that internal personal monitoring or area monitoring 

radiation dose records may have been lost or were otherwise not retrievable from BNL, 

supporting an F2 petition basis. 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 accepted the petitioner-proposed class. Therefore, 

NIOSH defined the following class for further evaluation: All employees who worked in any 

area at the Brookhaven National Laboratory from January 1, 1947 through December 31, 2007. 

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

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

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The 

NIOSH-proposed class to be added to the SEC includes all employees of the Department of 

Energy, its predecessor agencies, and its contractors and subcontractors who worked at 

Brookhaven National Laboratory in Upton, New York, from January 1, 1947 to December 31, 

1979, for a number of work days aggregating at least 250 work days, occurring either solely 

under this employment, or in combination with work days within the parameters established for 

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

4.0 Data Sources Reviewed by NIOSH to Evaluate the Class 

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. 

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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 can consist 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 BNL Site Profile consists of a single document. As 

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

BNL operations or related topics/operations at other sites: 

• Summary Site Profile Document for the Brookhaven National Laboratory, ORAUT-TKBS0048; Rev. 00; August 30, 2006; SRDB Ref ID: 30090. 

4.2 ORAU Technical Information Bulletins (OTIBs) and Procedures 

An ORAU Technical Information Bulletin (OTIB) 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 OTIBs and procedures as part of its evaluation: 

• OTIB: Interpretation of Dosimetry Data for Assignment of Shallow Dose, ORAUT-OTIB0017, Rev. 01; October 11, 2005; SRDB Ref ID: 19434 

• OTIB: Analysis of Coworker Bioassay Data for Internal Dose Assignment, ORAUT-OTIB0019, Rev. 00; December 29, 2004; SRDB Ref ID: 19439 

• OTIB: Estimating Doses for Plutonium Strongly Retained in the Lung, ORAUT-OTIB-0049, 

Rev. 00; February 6, 2007; SRDB Ref ID: 29975 

• OTIB: Internal Dose Reconstruction, ORAUT-OTIB-0060, Rev. 00; February 6, 2007; 

SRDB Ref ID: 29984 

• PROC: Occupational Onsite Ambient Dose Reconstruction for DOE Sites, ORAUT-PROC0060, Rev. 01; June 28, 2006; SRDB Ref ID: 29986 

• PROC: Occupational X-Ray Dose Reconstruction for DOE Sites, ORAUT-PROC-0061, Rev. 

02; January 2, 2008; SRDB Ref ID: 39338 

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4.3 Facility Employees and Experts 

To obtain additional information, NIOSH interviewed nine current or former BNL employees. 

SC&A, Inc., a contractor for the EEOICPA Advisory Board on Radiation and Worker Health, 

also conducted interviews. 

• Personal Communication, 2008a, Personal Communication with Health Physics Manager, 

Telephone Interview by ORAU Team; November 21, 2008; SRDB Ref ID: 65829 

• Personal Communication, 2008b, Personal Communication with Health Physics Group 

Leader, Telephone Interview by ORAU Team; November 21, 2008; SRDB Ref ID: 65836 

• Personal Communication, 2008c, Personal Communication with Health Physics Manager, 

Telephone Interview by ORAU Team; December 11, 2008; SRDB Ref ID: 65827 

• Personal Communication, 2008d, Personal Communication with Health Physics Manager, 

Telephone Interview by ORAU Team; December 12, 2008; SRDB Ref ID: 65831 

• Personal Communication, 2008e, Personal Communication with Health Physics Manager, 

Telephone Interview by ORAU Team; December 12, 2008; SRDB Ref ID: 65832 

• Personal Communication, 2009a, Personal Communication with Custodian, Telephone 

Interview by ORAU Team; January 15, 2009; SRDB Ref ID: 65826 

• Personal Communication, 2009b, Personal Communication with Carpenter, Telephone 

Interview by ORAU Team; January 21, 2009; SRDB Ref ID: 65825 

• Personal Communication, 2009c, Personal Communication with Machinist, Pile Operator, 

Reactor Operator, Telephone Interview by ORAU Team; January 29, 2009; SRDB Ref ID: 

65844 

• Personal Communication, 2009d, Personal Communication with Plumber, Superintendent, 

Telephone Interview by ORAU Team; February 5, 2009; SRDB Ref ID: 65840 

• Personal Communication, 2009e, Personal Communication with Three Former BNL 

Employees; Interview by SC&A; May 19, 2009; SRDB Ref ID: 71451 

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4.4 Previous Dose Reconstructions 

NIOSH reviewed its NIOSH OCAS Claims Tracking System (NOCTS) to locate EEOICPArelated 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 September 10, 

2009) 

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

Description Totals 

Total number of claims submitted for dose reconstruction 92 

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

class under evaluation (January 1, 1947 through December 31, 2007). 92 

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). 28 

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

the evaluated class definition 21 

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

the evaluated class definition 43 

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

records could be obtained for the employee. NIOSH has been able to obtain monitoring data for 

some of the claims that meet the class definition. Of the total of 92 claims submitted for energy 

employees who meet the class definition under evaluation, BNL/DOE has responded to 64. Of 

these 64 claims, BNL/DOE has indicated that “there is no record of [internal] measurements 

having been made” for 61 claimants. The remaining three have tritium dose data from the 

Landauer records during the 1985-1995 time frame. As of this writing, an additional 18 

claimant’s files now contain some internal dosimetry data. Internal data found for these 18 

claimants resulted from NIOSH data capture efforts conducted during the course of this 

evaluation. Five of these 18 are for cases not yet responded to by BNL. 

Of the 64 claims receiving BNL/DOE responses, 43 (67%) contain external monitoring data. 

The other 21 responses specifically state that no records exist for the claimant. These 21 were in 

job categories that would not have been expected to have been monitored, such as secretary, 

ground water scientist, environmental survey sampler, design engineer, helicopter pilot, and iron 

worker. 

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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 September 10, 2009, there are over 2800 documents in 

this database pertaining to BNL. These documents were evaluated for their relevance to this 

petition. The documents include historical background on external and internal dosimetry 

programs and evaluations, monitoring summary reports, annual environmental reports, reviews 

and assessments of BNL, evaluations of specific buildings, site surveys, and facility and process 

descriptions. 

4.6 Documentation and/or Affidavits Provided by Petitioners 

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

by the petitioners: 

• SEC Petition Form B; [name redacted]; May 6, 2008; OSA Ref ID: 105908 

• Affidavit from Survivor; May 6, 2008; OSA Ref ID: 105908 

5.0 Radiological Operations Relevant to the Class Evaluated by 

NIOSH 

The following subsections summarize both radiological operations at BNL from January 1947 to 

December 2007 and the information available to NIOSH to characterize particular processes and 

radioactive source materials. From available sources NIOSH has gathered information regarding 

the identity and quantities of each radionuclide of concern, and information describing processes 

through which radiation exposures may have occurred and the physical environment in which 

they may have occurred. The information included within this evaluation report is intended only 

to be a summary of the available information. 

5.1 BNL Plant and Process Descriptions 

ATTRIBUTION: Section 5.1 and its related subsections were completed by Lori Arent, M. H. 

Chew & Associates, Inc. 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. 

BNL was founded in 1947 at Upton, Long Island, New York, under a contract between the U.S. 

Atomic Energy Commission (AEC) and Associated Universities, Inc. (AUI). BNL was 

established to provide facilities for scientific research and remains in operation (see Figure 5-1). 

The site was formerly Camp Upton and was used by the Army during World Wars I and II. 

BNL’s early research focused on advanced physics, but expanded into its current suite of 

research in the fields of medicine, biology, chemistry, physics, materials science, nuclear 

engineering, and environmental research. BNL was organized into departments that provided 

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research nuclear reactors, particle accelerators, and engineering facilities in support of the 

Biology, Chemistry, Physics, Medical, Applied Science, Accelerator, and Applied Mathematics 

Departments (ORAUT-TKBS-0048). BNL activities have been well-documented over the years 

and detailed descriptions are generally available in the public domain. As of September 10, 

2009, NIOSH has gathered and reviewed over 2800 documents pertaining to BNL from a variety 

of sources. Due to the large amount of information available for the sixty years of BNL work 

under evaluation, only brief summaries of the available information are provided within this 

report. 

Figure 5-1: Aerial view of Brookhaven National Laboratory. 

Research Reactors

BNL’s reactor operations began in 1950 with the Brookhaven Graphite Research Reactor 

(BGRR), a research reactor used for peaceful scientific exploration in the fields of medicine, 

biology, chemistry, physics, and nuclear engineering. The BGRR operated until 1968. In 1965, 

its capacity was surpassed by the High Flux Beam Reactor (HFBR). The higher thermal neutron 

fluence of the HFBR permitted shorter irradiation times and expanded support for researchers of 

all disciplines, from solid state physics to art history. The HFBR ceased operations in December 

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1996. BNL also designed and built critical assemblies (i.e., equipment and fissionable material 

engineered to achieve very low-power self-sustaining barely-critical nuclear chain reactions). 

Medical Research Center 

Medical research at BNL began in 1950 with the opening of one of the first hospitals devoted to 

nuclear medicine. It was followed by the Medical Research Center (MRC) in 1958 and the 

Brookhaven Medical Research Reactor (BMRR) in 1959. The first nuclear reactor built 

exclusively for medical and biological research, the BMRR came on line on March 15, 1959 and 

operated until October 2000. 

The Radiation Therapy Facility (RTF)

The Radiation Therapy Facility (RTF) is operated jointly by the BNL Medical Department and 

the State University of New York at Stony Brook. The RTF is a high-energy dual X-ray mode 

linear accelerator (LINAC) used for the radiation therapy of cancer patients. This accelerator 

was designed to deliver therapeutic beams of X-rays and electrons for conventional and 

advanced radiotherapy techniques. This facility began providing therapy in 1991 and is currently 

operational. 

Particle Accelerators

High-energy particle physics research began in 1952 with the Cosmotron, the first particle 

physics accelerator to achieve billion-electron-volt energies. The Cosmotron operated from 1953 

to 1966. In 1960, the Alternating Gradient Synchrotron (AGS), a large accelerator, was built to 

surpass the Cosmotron’s capabilities. The AGS is capable of accelerating protons to energies up 

to 30 GeV and heavy ion beams to 15 GeV/amu. The AGS achieved full energy in 1960 and is 

still in use. 

Between 1967 and 1970, the Tandem Van de Graaff, 60-inch Cyclotron, and Vertical 

Accelerator were used for medium-energy physics investigations and for special isotope 

production. The heavy ions from the Tandem Van de Graaff can also be injected into the AGS 

for physics experiments. The Tandem Van de Graaff began operating in 1970 and continues to 

the present. 

The Heavy Ion Transfer tunnel connects the coupled Tandem Van de Graaff and the AGS. The 

interconnection of these two facilities permits intermediate mass ions to be injected into the AGS 

where they can be accelerated to an energy of 15 GeV/amu. These ions then are extracted and 

sent to the AGS experimental area for physics research. The AGS Booster is a circular 

accelerator with a circumference of 200 meters that receives either a proton beam from LINAC 

or heavy ions from the Tandem Van de Graaff. The Booster accelerates proton particles and 

heavy ions before injecting them into the AGS ring. The Booster receives protons and heavy 

ions from the LINAC and Tandem Van de Graaff Facilities to increase their intensity for 

delivery to the AGS. 

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The Brookhaven LINAC Isotope Producer (BLIP) became operational in 1973. Protons from the 

LINAC are sent via an underground beam tunnel to the BLIP facility where they strike various 

target metals. These metals, which become activated by the proton beam, are then processed at 

the Target Processing Laboratory for use in radiopharmaceutical development and production. 

The targets are cooled by a continuously-recirculating water system. The BLIP facility 

underwent significant upgrades in 1996 in support of the Brookhaven Isotope Research Center 

(BIRC) program. The 200 MeV Proton Linear Accelerator serves as a proton injector for the 

AGS and also supplies a continuous beam of protons for radionuclide production by spallation 

reactions in the BLIP. 

In 1982, the National Synchrotron Light Source (NSLS) began operation. The NSLS guides 

charged particles in an orbit. As the electrons spin inside a hollow donut-shaped tube called an 

electron storage ring, they give off light called synchrotron light. This light, which can be 

detected by specialized instruments, is used to study the properties of matter. The NSLS utilizes 

a linear accelerator and booster synchrotron as an injection system for two electron storage rings 

that operate at energies of 750 MeV vacuum ultraviolet (VUV), and 2.5 GeV (X-ray). The 

synchrotron radiation produced by their stored electrons is used for VUV spectroscopy and for 

X-ray diffraction studies. 

Brookhaven’s newest accelerator facility is the Relativistic Heavy Ion Collider (RHIC), 

completed in 1999. The RHIC is designed to recreate a state of matter that scientists believe 

existed moments after the universe was formed. 

Department of Applied Science/Nuclear Energy 

The Target Processing Laboratory (also called the Hot Laboratory in 1993) officially opened on 

January 15, 1951, and is still in use today. The original purpose of the central facility was to 

provide appropriately shielded areas for research with large amounts of radioactive material. 

The “hot” area of the Hot Laboratory included five hot cells, three chemical-processing hot cells, 

and three high-level hot cells for handling and processing radioactivity in gaseous, liquid, or 

solid form. 

The High Intensity Radiation Development Laboratory (HIRDL), which contained (in the early 

1970s) a million-curie range of Co-60 and Cs-137 sources, was used for source development and 

experimental process irradiations. A Co-60 pool in the HIRDL facility operated at lower activity 

levels into the 1990s. Currently, very little mission-specific work is occurring within the 

HIRDL. 

Waste Management

Waste management has been intrinsic to BNL from the beginning of operations. In late 1949, 

the Health Physics & Safety Summary Monthly reports began to include a section titled “Waste 

Disposal” or “Waste Disposal and Reclamation,” and later, “Waste Management.” The group 

was composed of Safety and Environmental Protection (S&EP) personnel assisted by personnel 

from the Maintenance Department. The S&EP personnel remained quite constant over time as 

seen in organizational charts captured from the site (BNL, 1960-1966). This reference shows the 

same six individuals employed in this group from 1960-66, with a seventh individual added in 

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1963. Several of these individuals were still apparently working in waste management decades 

later. 

The group began with monitoring the liquid waste discharges. The Waste Disposal Group 

operated an incinerator in 1949 and then added a hot laundry operation. Building T-430 was 

replaced with a new building (Building 167) in 1955. Decontamination activities were added to 

the group’s activities, both liquid chemical decontamination and sand blasting, followed by shot 

blasting and vapor blasting capability. The group operated a mercury still that decontaminated 

and purified to a high level many tons of mercury. The group also decontaminated lead so it 

could be returned to service. The group conducted sizing operations (involving some explosive 

work) on items that were too large to fit into the normal container for disposal. They also 

conducted a temporary radioactive waste storage operation wherein highly-activated or highlycontaminated items were stored in trenches or buried containers until they could be disposed of 

properly. The group also containerized the radioactive material into drums for sea disposal until 

the early 1960s when they switched over to concrete container vaults that were shipped to Oak 

Ridge National Laboratory (ORNL) or West Valley for land burial. Another significant activity 

was disposing of evaporator bottom slurry or other liquid waste by mixing it with concrete and 

placing it in the above-mentioned containers, either alone or as a means of encasing other 

radioactive items already in the drums or vaults to provide some degree of shielding. The group 

reported monthly on the liquid and gaseous releases from BNL until 1971, at which time this 

reporting responsibility was moved to the environmental group. This group also periodically 

reported radioactive waste that was dispositioned by BNL (quarterly when required by AEC). 

A new Waste Management Facility (WMF) was opened in December 1997. The WMF replaced 

the original Hazardous Waste Management Facility in its entirety and consolidates several waste 

management operations into functional buildings. The WMF also provides for significant 

expansion within a dedicated site suitable for handling and storing hazardous and radioactive 

wastes generated at BNL. 

5.2 Radiological Exposure Sources from BNL Operations 

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

the BNL class under evaluation. 

5.2.1 Internal Radiological Exposure Sources from BNL Operations 

ATTRIBUTION: Section 5.2.1 and its related subsections were completed by Eugene Potter, M. 

H. Chew & Associates, Inc.; Paul Ruhter M. H. Chew & Associates, Inc.; Lori Arent, M. H. 

Chew & Associates, Inc. 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. 

Many of the radioactive source materials handled at BNL were alpha-particle emitters. Although 

alpha particles do not present an external exposure hazard, prevention of internal exposures to 

alpha-emitters was recognized from the onset of site operations as the most significant 

radiological internal hazard protection challenge (BNL, 1947, pdf p. 2). 

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There were also a variety of beta- and beta-gamma-emitting radionuclides that were potential 

internal dose hazards at BNL. Table 5-1 provides a summary of radionuclides that are 

recognized as potentially contributing to internal dose to BNL workers. This list is not 

all-inclusive, but it does include all of the most significant sources of internal radiation dose. 

Radionuclides that emit both alpha and beta(-gamma) are simply listed as alpha-emitters, since 

the alpha emission will be the predominant component of the internal dose. Likewise, 

beta-gamma emitters are simply listed as beta emitters. 

Table 5-1: Potential Contributors to BNL Internal Dose and Their Primary Modes of Decay 

Radionuclide Primary Mode of Decay 

H-3 Beta 

Mixed Fission Products (MFP) Beta

Mixed Activation Products (MAP) Beta

Th-232 Alpha

Uranium Alpha

Plutonium Alpha

Am-241 Alpha

Po-210 Alpha 

5.2.1.1 Uranium

Depleted and natural uranium compounds were commonly used in ton quantities at BNL. 

Uranium in various enrichments, including highly-enriched, was used in critical assemblies and 

reactors. 

Approximately 110 tons of natural uranium fuel slugs were fabricated into aluminum-clad fuel 

rods by the BNL metallurgy group. During the operation of the BGRR (1950-1958), there were 

28 reported ruptures of BGRR fuel and one rupture of a uranium oxide (U3O8) sample that was 

being irradiated for the radioiodine-production program (ORAUT-TKBS-0048, pdf p. 20). 

Leaking or spent fuel elements were moved to a pool-type underwater storage area (“canal”) 

where they were chopped up for shipping for off-site disposal. Corrosion and oxidation of the 

natural fuel slugs occurred in the fuel transfer and storage canal. Over 2414 fuel elements 

generated during a 12-year period were shipped from the canal. The contaminated water, filter 

media, and back-flush from the ion exchange columns were pumped to the storage tanks at the 

Waste Concentration Facility, Building 811. In 1959, the natural uranium was replaced with a 

smaller enriched uranium core. The BGRR was partially decommissioned in 1972. The exhaust 

ducts from the reactor and to the stack have been sealed from the fans. The fans remain in their 

cells. The intake duct, exhaust duct, and fans are grossly contaminated from the fuel failures 

(ORAUT-TKBS-0048, pdf p. 21). The HFBR and MRR were operated with enriched uranium 

fuel. Both facilities have now been closed and the spent fuel sent off site. Un-irradiated fuel for 

the three reactor facilities was stored in secure vaults (DOE, 1996, pdf p. 39). 

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In about 1950, BNL started investigating the feasibility of processing spent fuel elements by 

dissolving them in fluorine-based interhalide compounds. After a laboratory study, a distillation 

plant was constructed in 1951; an engineering test facility was designed in 1953. On May 15, 

1957, a series of explosions of liquid bromine trifluoride, uranium hexafluoride, and uranium 

metal occurred in Building 801. One worker was seriously burned and several others were 

treated and released. Approximately 50 pounds of natural, un-irradiated uranium were released 

to the atmosphere (Volatility, 1957). 

Uranium was also used in critical assemblies for nuclear reactor research. Research and 

development on Liquid Metal Fuel Reactor (LMFR) technology took place in Building 820 from 

1957-75. A simulated reactor with a core of uranium dissolved in bismuth was studied 

(ORAUT-TKBS-0048, pdf p. 36). Radiation and Chemical Technology Buildings 526-527 

contained unknown quantities of uranium of various enrichments. This area originally housed a 

criticality facility for reactor physics (ERDA, 1977, pdf p. 48; Liverman 1977). U-233 was used 

in the Th-U-233 Fuel Rod Development Program in 1962. ORNL was to fabricate and send 

1000 rods to BNL for study in its critical experiments facility. A total of approximately 30 kg of 

U-233 was in the uranium-thorium mixture (Special Nuclear, 1963). The U-233 generally 

contains U-232 as an unavoidable contaminant. In 1974, U-233 targets were irradiated at the 

cyclotron using alpha particles, but only in milligram amounts (Progress Report, September 

1974). 

Uranium was fabricated into targets for irradiation in reactors and accelerators. The uranium 

was machined in the Hot Machine Shop (Building 530, replaced by Building 462). Uranium 

targets were reprocessed. For example, from March of 1952 to June of 1960 there was a 

program at the Hot Laboratory to produce I-131 by acid-dissolution of irradiated uranium 

samples. U-234 foils (100 μg) were irradiated with deuterons to produce Pu-234 in 1975 (Hull, 

1977a). 

Depleted uranium (DU) was used in target areas of the AGS (ORAUT-TKBS-0048, pdf p. 25). 

A muon shield consisting of over 15 tons of DU was set up for a 1966 AGS experiment (HP 

Summary, May 1966). DU was cleaned for an experiment at CERN (Conseil Européen pour la 

Recherche Nucléaire, or European Council for Nuclear Research) in 1985-86. 

Building 1008 was the Uranium Calorimeter Factory in 1988. One calorimeter module housed 

fifty 102-inch by 25-inch uranium plates. There were enough plates to construct 20 modules 

(Lazo, 1988b). NIOSH has obtained no further information about what went on in this factory. 

In 1995, an inventory showed that DU was present in eleven buildings in quantities from a few 

grams to nearly 27,000 kilograms. Natural uranium was located in four buildings in quantities 

from 10s of grams to nearly 85 kilograms (Miltenberger, 1995). 

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5.2.1.2 Fission and Activation Products

Fission and activation products were present at BNL from the earliest days to the present. Some 

fission and activation products were the intended products of the BNL reactors and accelerators. 

For example, targets were irradiated to produce materials for basic research, medical research, or 

source manufacture. Other fission and activation products were produced as unintended 

byproducts of these operations; for example, activation of facilities and equipment, cooling air 

activation, or activation of contaminants in targets. BNL also imported fission and activation 

products from other AEC/DOE facilities and commercial sources. 

By 1948, 25 different isotopes were already in use, well before the start of operations at the 

BGRR (Cowan, 1948). From March 1952 to June 1960, there was a program at the Hot 

Laboratory to produce I-131 by acid-dissolution of irradiated uranium samples. During the late 

1950s and early 1960s, a number of radioisotopes were in development and/or production at 

what was known then as LEAF (Low Energy Accelerator Facility) which included the cyclotrons 

and the Van de Graaff accelerator (Flood, 1982). The major purpose of these isotopes was 

medical research. In the 1970s, the BLIP was set up to utilize the excess capacity of the 200 

MeV Linac to produce radionuclides to be used in the development of new radiopharmaceuticals, 

mostly for diagnostic purposes. The Chemistry Linac Irradiation Facility (CLIF) operated in a 

similar way, but it was used for irradiations of a few hours or less (ERDA, 1977). The Hot 

Laboratory and other locations were used to process targets (ORAUT-TKBS-0048, p. 40). In 

1971-1972, the High Intensity Radiation Development Laboratory (HIRDL), which contained 

million-curie range Co-60 and Cs-137 sources, was used for source development and 

experimental process irradiations (ORAUT-TKBS-0048). 

The above are just some examples of the many uses of fission and activation products used or 

produced at BNL. They ranged from small quantities of short-lived isotopes to significant 

quantities of long-lived material. Many of these activities only involved a few researchers in 

close contact with the materials. In addition, the isotopes produced for diagnostic medical use 

had short half-lives to reduce the dose to the patients. After discontinuation of the research, only 

the longer-lived material remained as residual contamination. Much of the equipment used was 

decontaminated or disposed of as waste. The primary exception was at the BGRR. In 2000, 

there were an estimated 1,400 Ci of Fe-55, 0.7 Ci of Co-60, 13 Ci of Sr-90, and 15.5 Ci of 

Cs-137 remaining in the BGRR complex due to operations with failed fuel (Musolino, 2000). 

5.2.1.3 Tritium

Tritium was encountered in several forms: tritiated water (HTO), tritiated gas (HT), organicallybound tritium (OBT), and metal tritide (MT). H-3 appears to have been widely used in medical 

and biological research. Medical research involving OBTs started in the 1950s. Tritiated 

thymidine was injected into patients and animals in the mid-1960s (Flood, 1967). In 1967, bean 

plants were grown in 2 Ci/liter of HTO at Medical/Biology (HP Summary, April 1967). In 1969, 

after gross H-3 contamination of one of the organic chemistry labs, a reference states that urine 

samples and CAMs indicated that the form was H-3-labeled benzoic acid (HP Summary, April 

1969). There was a long-running experiment with mice in the 1970s and disposal of large 

quantities of contaminated mouse litter was reported monthly (Progress Reports, 1974). In 1972, 

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H-3-contaminated vacuum pump oils were a problem, especially at the 3.5 MeV 

Physics/Chemistry Van de Graaff (Flood, 1972). When tritium ions were accelerated, 

approximately 200 Ci/month of HT was used (ERDA, 1977). The Hot Laboratory fabricated 

H-3 into accelerator targets. The tritium targets were used at the 18-inch cyclotron, the 50 MeV 

AGS LINAC, the 3.5 MeV Van de Graaff, the Tandem Van de Graaff, and the 200 MeV 

LINAC. Accelerator targets were in the form of SMTs, such as zirconium tritide. At Building 

919 in 1973, the 80-inch bubble chamber facility had a 250 mCi gas chromatograph source, as 

well as other sources up to 100 mCi (Bubble Chamber, 1973). Cooling water at the AGS 

became tritiated, especially at the target stations. The levels ranged from 1,000 pCi/L to 400,000 

pCi/L. These were closed systems that were drained prior to 2009 (Lessard, 2009). 

The amount of H-3 on site increased dramatically with the start-up of the HFBR in 1965. The 

HFBR was a 30-60 MW thermal heavy-water-moderated nuclear research reactor. Heavy water 

flowing in the core was exposed to a dense neutron field which activated the deuterium atoms in 

the water to produce tritium. The typical concentration was about 2 mCi of H-3 per cm3

 of 

heavy water. The form was HTO, and this was the most important source of H-3 exposure at 

BNL from 1965 to 1999. The second most important was probably the 3.5 MeV Van de Graaff 

where H-3 tritium beams and targets were frequently used. High beam currents of proton or 

deuterons would cause the H-3 to diffuse out of the zirconium targets and into the beam pipe and 

the surrounding area. Substantial build-up of contamination was noted in 1970 (HP Summary, 

February 1970). During the change-out of a leaking H-3 source bottle in 1971, levels reached 

2000 MPC in the area of leak. However, the highest exposure to the workers involved was only 

24 mrem (HP Summary, October 1971). 

5.2.1.4 Thorium

Thorium was present at BNL starting in the 1950s, and was used primarily in nuclear 

engineering research. All references to thorium at BNL are to natural thorium (Th-232-series). 

Control and accountability procedures were set up indicating that thorium was to be handled as a 

source material like uranium (BNL, 1948; Fox, 1950). In 1959, a study was made of ThO2

hazards as a result of the increased use of this material in the Nuclear Engineering Laboratory 

(HP Summary, May 1959). The MPC was taken from a proposed revision of NBS Handbook 52 

as 4x10-12μCi/cm2, making it “very hazardous,” and appropriate arrangements were being made 

for containment and monitoring. Various chemical compounds and physical forms (including 

dispersible powders) were present (BNL, October 1957; BNL, December 1957; HP Summary, 

February 1959; Progress Report, March 1952; Progress Report, April 1952; Progress Report, 

May 1952; Progress Report, October 1952; Progress Report, November 1953; Progress Report, 

December 1953; Progress Report, June 1954; Progress Report, August 1954; Rice, 1966). There 

is evidence that thorium operations were monitored by health physics staff. For example, in 

1969, among the operations monitored was the change-out of filters in line with a Th-228 

molecular beam apparatus in Chemistry (HP Summary, October 1969). In 1971, thorium foils 

were used in studies for a fission track personnel dosimeter (HP Summary, September 1971). In 

the mid-1970s, a “thorium cow” was in use at Bldg. 510. This is a device that concentrates the 

daughter products from thoron (notably Pb-212) by precipitation on a charged electrode. This 

device was used to produce calibration sources and at the Tandem Van de Graaff (Progress 

Report, January 1974; Progress Report, November 1975; Progress Report, December 1975). In 

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1986, five workers in the Department of Applied Science working with “thorium series 

(magma)” were identified for whole body counts (Lukas, 1986), indicating that a small program 

still existed (magma apparently referred to geothermal-research-related samples containing trace 

amounts of thorium). An inventory of dispersible radioactive material in 1997 indicated that 

only microcurie amounts were still on site (Flores, 1998). 

5.2.1.5 Plutonium

Plutonium was among the first safety concerns at BNL, probably because its hazards were well 

known by the time BNL was established. Its early uses are not well described, but seemed to 

involve studying its various properties. Due to the activation of uranium, plutonium was present 

in the fuel of the operating reactors; however, BNL fuel was sent to other sites for reprocessing 

(Van Horn, 1962-1963). Nevertheless, plutonium was present in the residual contamination of 

some facilities, particularly the BGRR which had a history of operations with failed natural 

uranium fuel elements. There was also Pu in the fission product mixture processed by the waste 

handlers (HP Summary, March 1949). Plutonium was also contained in neutron sources at 

Medical, Chemistry, and the calibration facility (ORAUT-TKBS-0048, pdf p. 94). 

The following text briefly summarizes known occurrences involving Pu at BNL. In January 

1963, a leaking glass carboy containing gold in a solution contaminated with plutonium was 

received at BNL (AEC, 1963, pdf p. 68). In December 1963, plans were being prepared for the 

conversion of a gamma facility in the Hot Lab to a plutonium metallurgy laboratory to perform 

physical and chemical tests on cold and irradiated plutonium carbide fuels (Progress Report, 

December 1963). In 1966, a lathe contaminated with U-235 and Pu-239, which originally came 

from Mallinckrodt, appears to have been used in the shops at BNL, (HP Summary, January 

1966). In 1966, plutonium was also used in nuclear engineering research in the critical assembly 

area; plans were designed to prevent surface or airborne contamination or damage to the 

encapsulated source material (HP Summary, March 1966). In March 1967, four grams of Pu239 in the forms of oxide and carbide were introduced into one of the glove boxes at the Hot 

Lab. The experiment consisted of vaporization of oxide in a closed system. The operation was 

reviewed and covered by health physics (Progress Report, February 1967). In 1970, three Pu 

vaporization experiments were conducted in the alpha-gamma facility (HP Summary, February 

1970). In June 1971, 61 PuO2-UO2 pellets containing 439 grams of Pu were encapsulated by the 

Hot Lab health physics personnel in a new glove box facility set up for this purpose (HP 

Summary, June 1971). By September 1971, plutonium work at the Hot Lab appears to have 

ended since some of the equipment was being converted to use in the chemical processing of 

BLIP targets at the Hot Lab (HP Summary, September 1971). In 1996, there were still gram 

quantities of plutonium stored in an SNM vault (DOE, 1996, pdf p. 40). In 2000, a total of 1.22 

Ci plutonium isotopes were estimated to remain in the BGRR complex (Musolino, 2000). 

5.2.1.6 Americium

Americium is generally present at BNL as a by-product of plutonium production/irradiation. 

There is also evidence that operations involving purified Am-241 took place on site during the 

time period under evaluation. In 1959, an Am-241-contaminated dry box from the criticality 

facility was partially cleaned prior to storage (HP Summary, May 1959). Americium sources 

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were also used for calibrations (HP Summary, October 1964; HP Summary, April 1965; HP 

Summary, June 1965) and X-ray fluorescence studies (Progress Report, Oct-Nov 1983). In 

1966, americium “in sizable amounts” was to be used in the critical assembly area; plans were 

designed to prevent surface or airborne contamination or damage to the encapsulated source 

material (HP Summary, March 1966). There is no subsequent mention of this material, which is 

likely an indication that no problems were experienced. Site interviews indicate that since 1989 

Am-241 has only been present in μCi amounts for research projects (Personal Communication, 

2008c). An inventory of dispersible radioactive material in 1997 indicated that only microcurie 

amounts were still on site (Flores, 1998). However, it may still be present in residual 

contamination with plutonium isotopes. In 2000, a total of 0.072 Ci of Am-241 was estimated to 

remain in the BGRR complex (Musolino, 2000). 

5.2.1.7 Polonium

Polonium was among the first radionuclides received at BNL. Apparently polonium sources 

were initially used due to security issues associated with using plutonium sources (HP Summary, 

October 1949). The two most common uses appear to have been as an alpha source for basic 

research and as a Po-Be neutron source for calibrations and other purposes. The hazards of 

polonium were recognized early on, and in 1947 safety precautions were published by groups 

using polonium sources (Salant, 1947). 

A Po-Be source was requested as early as 1947 (Hayner, 1947). There was a 1949 request for a 

replacement polonium source to be used in a spectrometer (Lancaster, 1949). Initially, the 

sources were constructed using a thin nickel plating which could allow the polonium to diffuse 

through it, and some of these sources leaked (Cowan, 1947; Progress Report, April 1965). Two 

individuals acquired 20% of the maximum permissible body burden (MPBB) from an incident in 

August 1960 (Haworth, 1960; HP Summary, January 1961). In 1963, the Chemo Nuclear group 

worked with 10-Ci polonium sources. The operations manual for this work was reviewed by 

health physics and emergency instructions were brought up-to-date prior to use. Instrumentation 

for monitoring these experiments was checked and found to be in working order (Progress 

Report, September 1963). A Po-210 contamination incident also occurred on December 21, 

1964 (Progress Report, January 1965). A physics experiment which involved 297 mCi of 

Po-210 was planned in 1966 (HP Summary, March 1966). The material was to be dissolved in 

hydrofluoric acid, placed in a sealed container in the alpha dry box at the Hot Lab, and then 

transferred to the Physics lab in a sealed bag. Documentation has not been located that indicates 

whether the experiment took place. An inventory of dispersible radioactive material in 1997 

indicated that only microcurie amounts were still on site (Flores, 1998). 

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5.2.2 External Radiological Exposure Sources from BNL Operations 

Given the broad scope of BNL activities involving ionizing radiation, workers were potentially 

exposed to external photon, beta and/or neutron radiation from a variety of sources. Potential 

sources included radioactive materials, nuclear reactors, particle accelerators, and X-raygenerating equipment. 

5.2.2.1 Photon

Many BNL radiological operations involved gamma and X-ray photon radiation fields. Potential 

photon exposure sources to workers would have been associated with the following: 

• Gamma-emitting fission and/or activation products resulting from reactor and accelerator 

operations. 

• Production and use of high-intensity gamma sources, typically Co-60 and Cs-137. 

• Radioisotopes used in medical research and treatment. 

• X-ray-generating machines. 

• Calibration sources of americium, thorium, radium, cobalt, cesium, and other miscellaneous 

radionuclides. 

The very high-intensity sources were handled in a shielded configuration or shielded facility. 

Highly-contaminated or activated equipment was handled using standard health physics controls 

of time, distance, and shielding. 

5.2.2.2 Beta

BNL research and operations did not focus on activities with beta-particle-emitting source terms. 

However, beta radiation over a broad range of energies could have been encountered from: 

activation and fission products from reactor and accelerator operations; and other radionuclides 

such as those used as calibration sources and for medical treatment and research. 

Whether a beta source is considered an internal hazard or both an internal and external hazard 

depends on the maximum energy of the beta emission for a given radionuclide, the shielding 

employed, and the use of protective clothing. Higher-energy beta-emitters present both an 

external hazard (to the skin) and an internal hazard. In many cases, beta-emitting radionuclides 

also emit characteristic photons. 

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5.2.2.3 Neutron

There were many sources of potential neutron radiation exposure associated with BNL 

operations. The source of the neutron emissions from these activities and potential worker 

exposure would have been associated with the following: 

• Accelerators 

• Operating reactors, especially those designed to create neutron beams 

• Neutron-generating sources, either via the α,n reaction (PuBe, RaBe, PoBe) or via 

spontaneous fission sources (Cf-252) 

The broad scope of BNL neutron-generating activities resulted in a correspondingly extensive 

neutron energy spectrum. The spectrum ranged from the thermal energy region of 0.025 eV 

through the fission spectrum of 0.1 to 6.0 MeV (predominant energy of 0.7 to 1.0 MeV), and 

included high-energy, accelerator-produced neutrons greater than 14 MeV. Additional 

information is available in ORAUT-TKBS-0048. 

5.2.3 Incidents 

Incidents that occurred at BNL were documented and worker exposures were assessed when the 

event involved radioactive sources. Incident reports are maintained at BNL and copies of many 

of these reports have been obtained through NIOSH data capture efforts and are now in the 

SRDB. 

BNL reportedly maintains an unofficial spreadsheet with information on historical spills and 

other contamination incidents as part of the “Radiological Footprint Project.” The purpose of the 

spreadsheet is to assist with D&D activities. This spreadsheet was not made available to 

NIOSH, but was mentioned in one of the SC&A interviews (Personal Communication, 2009e). 

Table 5-2 summarizes nine major BNL incidents that occurred during the evaluation time frame 

and that might have significant potential for internal or external personnel exposure. 

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Table 5-2: Major BNL Incidents 

(This table spans two pages) 

Facility/Building Year Description 

BGRR, 

Building 701 1952-57 

During the early years of BGRR operation, fuel failures occurred that resulted in 

radioactive materials being released to the air stream that cooled the reactor. There 

were 28 reported ruptures of BGRR fuel during the period 1952-1957. All occurred 

with natural uranium. There was one rupture of a uranium oxide (U3O8) sample that 

was being irradiated for the radioiodine production program. Aside from Ar-41, 

I-131 was the most important radionuclide discharged to the atmosphere from the 

BGRR that would contribute to a potential dose. Br-82 and I-133 were released in 

somewhat larger concentrations. (BGRR History, 1997) 

Hot Laboratory, 

Building 801 

5/15/1957 

There was a serious incident involving the Volatility Project where uranium 

reprocessing was the objective. There was a series of explosions of UF6/BrF3 and a 

few people were injured, one hospitalized. There was a release of about 50 lbs of 

natural, un-irradiated uranium to the local environment. Apparently, the UF6 readily 

combines with moisture to form an oxide. The BrF3 is very corrosive and damaged 

equipment in the building, nearby trees, and automobiles. Eight workers with the 

highest inhalation received uranium urine bioassay; the highest concentration was 

0.54 mg/l uranium. (Volatility, 1957) 

Inner Alpha 

Laboratory 

Building T-137 

8/2/1960 

Alpha contamination occurred during experiments conducted with a 10-Ci Po-210 

source that was supposedly sealed. Two individuals acquired internal body burdens 

from this incident; the highest result was 14% of the 0.03 microcurie body burden 

permissible by NBS Handbook 69 (Haworth, 1960 ; Cowan, 1961). 

Physics Lab 

Building 510 10/30/1962 

Exposure from a Physics Department x-ray diffraction apparatus was investigated. 

The estimated exposure to the operator was 10 rad to the left hand and 260 rad to 

part of the right hand. Audible and electrical interlocks were specified to avoid 

future incident (Distenfeld, 1962). 

Laboratory W-9 

Building 703 12/19/1975 

Contamination from a sample transfer process was investigated. The original 

sample contained approximately 0.5 of Ci Ce-14l and 80 mCi of Ce-143. Three 

workers were evaluated and one was assigned 330 mrad following fecal and WBC 

analyses (Roesler, 1976; Tony, 1976). 

BLIP Facility 

and 

Hot Lab (Bldg 801) 

5/16/1978 

7/31/1978 

Two I-126 iodine exposure incidents occurred in 1978 affecting BLIP and Hot Lab 

workers. At BLIP, a target vaporized and at the Hot Lab, there was visible 

contamination on a needle used for nuclide extraction from BLIP-irradiated targets. 

Eight workers were potentially exposed and they received whole body and thyroid 

counts. The highest exposure was 1.35 rem to the thyroid (Miltenberger, 1978b; 

Miltenberger, 1978c). 

Calibration Facility 

Building T-348 4/10/1978 

An investigation was performed due to an external exposure incident involving a Cs137 source that became stuck in its irradiation tube. The source was rated at 3.8 

R/hr at 50 cm (4/13/78). Initially a gamma exposure of 4.3 rem was assigned, 

which was subsequently refined to 2 rem after further evaluation (White, 1978; 

Flood, 1978). 

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Table 5-2: Major BNL Incidents 

(This table spans two pages) 

Facility/Building Year Description 

HFBR 

Building 750 

March and 

April 1990 

At HFBR, there was a contamination incident that resulted in a formal investigation. 

Workers were installing a new valve in the reactor vessel in preparation for start-up. 

A new portal monitoring had been installed and workers began experiencing alarms 

upon exit and entry. After contamination was found in two personal vehicles, onand off-site surveys were conducted determine the extent of the contamination. 

Low-level spots of contamination were found off-site in four additional personal 

vehicles and in two homes; contamination was easily removed in each case. A total 

of 108 residences were surveyed. Whole body counts were performed for 60 HFBR 

workers and three were found to have very low internal depositions. The general 

public was not affected (DOE, 1990). 

6.0 Summary of Available Monitoring Data for the Class 

Evaluated by NIOSH 

ATTRIBUTION: Section 6.0 and its related subsections were completed by Tim Adler, Oak Ridge 

Associated Universities; Eugene Potter, M. H. Chew & Associates, Inc.; Paul Ruhter, M. H. 

Chew & Associates, Inc. These conclusions were peer-reviewed by the individuals listed on the 

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

text. 

The following subsections provide an overview of the state of the available internal and external 

monitoring data for the Brookhaven National Laboratory (BNL) class under evaluation. The 

personnel monitoring program at BNL has always been officially organized under a health and 

safety-oriented department. Various names and organizational structures have existed. The 

administrative chronology of BNL’s personal monitoring programs is summarized in Section 

7.1. 

Despite the existence of organized occupational monitoring departments at BNL, some aspects 

of the personnel monitoring programs have been decentralized for much of the site’s history. 

This decentralization is particularly applicable to internal exposure monitoring record 

maintenance. Monitoring requirements were determined primarily within specific departments 

or divisions (e.g., Reactor Division) on work area and activity-specific bases. This was 

accomplished through the assignment of health physicists to specific BNL work areas. The 

health physicists decided monitoring requirements for workers under their purview based on 

their judgment of exposure potential. After analysis, personal monitoring results were returned 

to the area health physicists for comparison to standards in existence at the time, to assess safety 

adequacy, and guide future monitoring. Internal monitoring results were frequently stored only 

in files located at the various site work areas. Records have also been stored in individual 

workers’ files, medical files, or vendor files that, in turn, may exist in several different locations 

on site or in off-site archives. These personnel data management practices (i.e., lack of 

centralized databases) preclude the summarization and presentation of total internal monitoring 

Page 30 of 120 
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data availability. In addition to complicating the data availability assessment, BNL’s data 

management practices have apparently adversely affected the ultimate retrievability of internal 

monitoring data collected prior to 1980. This latter determination is discussed in more detail in 

Section 7.1. 

It is noteworthy that external radiation monitoring and the associated records have historically 

been more centralized. This may be due in part to the relatively low internal exposure potential 

for most work performed at BNL. From the beginning an entity known as the “Personal 

Monitoring Group” collected and compiled all site external monitoring data for inclusion into 

external exposure summary reports as required by DOE (initially AEC). Detailed further in 

Section 6.2, this group maintained a more centralized reporting and monitoring data record 

system. As time passed increased centralization of both internal and external monitoring 

requirements and data management has occurred. 

Consolidation of BNL monitoring records is an ongoing effort at BNL. Data storage technology, 

in particular, has improved since the first data were collected in 1947. The launch of the Health 

Physics Record System (HPRS) can be considered the most significant technology change to the 

program thus far. The HPRS was launched in 1996 with a phased implementation between 

March 1995 and January 1996. Prior to that time, data were kept on hard copy or in vendor files. 

Table 6-1 briefly summarizes the sources for historical monitoring data relative to availability 

within the HPRS. 

Page 31 of 120 
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Table 6-1: Sources for Monitoring Data 

Type of Data Date Range Where Found

Internal Monitoring Data 1949 - 2001 Individual/detailed data are not in 

HPRS. Results are available in hard 

copy stored in individual personal 

monitoring files and/or medical files. 

Some results from 1995 - 2000 are 

stored electronically, but not in 

HPRS. 

Internal Monitoring Data After 2001 Data are in the HPRS. This 2001 

date reflects the current status but 

will keep moving back as BNL 

continues to migrate older 

monitoring data into HPRS. 

Film badges Prior to 1985 BNL data are in hard copy/reports, 

personnel cards. Summary data are 

in HPRS. 

Film badges/CR-39/Lexan 1985 – 1996 Landauer database and microfiche. 

Some electronic data are available 

on disk. Paper copy is available in 

bound books. 

TLD/CR-39/Lexan* After Jan 1996* HPRS 

* Lexan was not used after June 1997; therefore, Lexan dose results are not stored in HPRS after that time.

Because the majority of the available internal monitoring data applicable to the evaluation time 

frame still exists in hard copy form, in multiple locations, primarily sorted into individual 

employee files, a definitive assessment of total monitoring data availability would only be 

possible through the perusal and tallying of each file’s contents. Constraints on the retrievability 

of the data from the site, especially for internal monitoring data prior to 1980, precluded 

NIOSH’s accomplishment of this task. However, NIOSH has extracted and electronically 

entered monitoring data found within the approximately 2300 documents that were captured 

from the site and other sources as of May 2009. Furthermore, NIOSH conducted two additional 

data capture exercises focused specifically on retrieving monitoring data from individual worker 

files; and data available within those captured files has been summarized in this evaluation. 

The results of the NIOSH data capture efforts provide the basis for the observed data availability 

summaries presented in the following subsections. It is important to remember that the data 

presented do not represent the actual total available monitoring data, but rather, a subset that was 

available within the documents retrieved. Presentation of the captured results therefore 

expectably indicates the presence of temporal and data quantity gaps. Nevertheless, when 

coupled with numerous captured documents describing health and safety practices at BNL, the 

data obtained thus far provide additional support for the existence of a comprehensive and 

conscientious worker monitoring program appropriately based on exposure potential. However, 

personnel monitoring data retrievability issues, which are compounded by the site’s recordkeeping practices over the years, present the most significant issues affecting this report’s 

Page 32 of 120 
SEC-00113 09-29-09 FINAL Brookhaven

evaluation. It is apparent that there was a turning point in the BNL radiological program and 

record-keeping requirements at the beginning of 1980 (following a 1979 site assessment). Based 

on this information, the assessment of NIOSH’s ability to bound dose for the class under 

evaluation is primarily focused on the ability of the site (or other applicable entity) to identify, 

retrieve, and provide (to NIOSH) the applicable BNL personnel internal and external monitoring 

data. 

6.1 Available BNL Internal Monitoring Data 

For much of the site’s operational history, department/division health physics representatives 

designated personnel for participation in the internal dosimetry program (WBCs and/or 

urinalysis) using professional judgment. This judgment could also have included monitoring 

frequency (BNL, 1995; Holeman, 1999). Table 6-2 summarizes in vivo and in vitro monitoring 

practices and data storage media for the evaluation period. In general, in vivo and in vitro

dosimetry was performed for initial employment checks, annual physicals, for employees 

engaged in higher-exposure-potential work, and incidents. Details regarding the various 

analyses used and the associated minimum detectable activities are presented in the BNL TBD 

for Occupational Internal Dose (ORAUT-TKBS-0048). 

Table 6-2: Internal Dosimetry Timelines and Data Source Descriptions 

Type Dates Description 

In vivo 

1960 - 1991 

Outputs are available from the whole-body counting system that was in place 

at the time (several whole-body counting systems were in place during this 

time period). This hard copy output is kept in personnel dose history files, 

some log books, and some medical records. 

1992-present 

In vivo bioassay performed routinely for Reactor Division personnel, Waste 

Management personnel, BLIP, Facility Support personnel, and 

Environmental Restoration personnel. These data are all available as hard 

copy reports from the PM Whole Body Counter. 

1999-present 

In vivo bioassay data are also available electronically on the workstation of 

the Whole Body Counting System. The data have been exported and 

provided to NIOSH (“ABACOS2K” files). The data indicate that 2815 

counts were performed on 963 individuals. 

In vitro 

1947- 1984 Results were manually kept in hard copy in different formats. This hard 

copy is kept in personnel dose history files. 

1984- 2003 In vitro bioassay performed for RD personnel. 1984-1995 tritium dose data 

were sent to Landauer and recorded in the Landauer System. Data are 

available on microfiche and have been entered into a spreadsheet by NIOSH. 

Many tritium monthly summaries from 1992 - 1999 are available in hard 

copy reports. The tritium data primarily are in terms of dose. Urinalysis 

data consisting of over 11,000 tritium results and a few gamma scans from 

the on-site Analytical Services Laboratory (“ASL” Access database) have 

been captured for the period 1995-2003.

1999- present After 1999, hard copy records of all in vitro bioassay results are maintained 

in the whole body counter office. After 2000, electronic versions are also 

available and have been captured by NIOSH. 

Other 1998-present Doses from intakes are recorded in HPRS. Doses could be the result of 

either in vivo or in vitro bioassay or assigned from air samples. 

Page 33 of 120 
SEC-00113 09-29-09 FINAL Brookhaven

Attachment 1 presents a summary of whole body counts and urinalysis monitoring data pulled 

from documents NIOSH captured during the initial general-evaluation data capture events (as of 

May 1, 2009) plus results obtained from two data-pedigree-focused efforts that occurred later. 

Results in Attachment 1 have been presented in terms of the number of employees monitored per 

year. Extraction and entry of individual analytical results was performed only for data found in 

documents captured prior to May 1, 2009 (over 2,300 documents at that time). These individual 

analytical results are presented and discussed the following two subsections. More-recently 

collected data (captured after May 1, 2009), which includes data from the 1990s forward, are 

included in the summary contained in Table 6-2, but have not been included in the Table 6-3 

assessment. 

6.1.1 Urinalysis Monitoring Data 

As mentioned above, Attachment 1 contains a compilation of the available in vitro bioassay 

results from the SRDB documents collected and posted by NIOSH as of May 1, 2009. The raw 

data compilation contains just under 9100 individual urinalysis sample results from 1049 

individuals. Table 6-3 below summarizes the total number of in vitro results currently captured 

by year and by individual radionuclide. Though many documents were used as data sources, a 

large portion of the internal data captured have come from two sets of urinalysis records from 

1952-1975 (Urinalysis Records, 1952-1975a; Urinalysis Records, 1952-1975b). These 

documents contain handwritten bioassay records for individual employees that were terminated. 

The records appear to include all bioassay results for each employee listed within the documents, 

not just their termination results. Of the results collected, 87% were surveys, 7% were incidents, 

5% were unknown, and 1% were re-checks. 

In general, results include the employee’s name and at least one identifier such as “BNL Life 

Number,” division/department, and/or a location indicator. Major work groups identified 

included: 

• Accelerator 

• Biology, Chemistry, and Physics 

• Critical Assembly, Department of Applied Science, and Nuclear Engineering 

• Health Physics, Safety & Environmental Protection, and Waste Management 

• Hot Lab and Medical 

• Plant Maintenance and Shops 

• Pile and Reactor 

Page 34 of 120 
SEC-00113 09-29-09 FINAL Brookhaven

Page 35 of 120 

The “BNL Bioassay Record” (Form 1720) was used from 1951 to 1967 and includes MFP, 

Sr-90, H-3, and alpha column headers. The other form used from 1952 to 1976 is titled 

“Urinalysis Record” and includes gross (gamma), Sr-90, and Po-210 column headers. There is 

also a “Gross Activity” form (BN-945), a “BNL H-3 Exposure Evaluation” form, and memos 

that detail incident follow-ups. Other radionuclides that were monitored for specific incidents 

included: 

• Ag-110 

• Am-241 

• Au-198 

• Ce-141/143 (urine and fecal) 

• Co-60 

• Hf-181 

• Na-24 

• P-32 

• Ra-226 

• Ru-106 

• U-233 

• Zn-65 
SEC-00113 09-29-09 FINAL 

Page 36 of 120 

Table 6-3: Total No. of In Vitro Results/Yr and No. of Individual Radionuclide Results/Yr* 

Note: A single sample may include more than one result (multiple analyses per sample.) 

(This table spans three pages) 

Year

Count of  

Samples

Count of Gross

(d/m/d)

Count of MFP

(d/m/d)

Count of Sr‐90

(d/m/d)

Count of H‐3

(μc/l)

Count of U/Total

U (ug/l)

Count of "U"

(d/m/d)

Count of Nat U

(μg/l)

Count of Nat U

(d/m/d)

Count of U‐238

(μg/l)

Count of EU/U‐

235 (d/m/d)

Count of Gross

alpha (d/m/d)

Count of Po‐210

(d/m/d)

Count of Pu/Pu‐

239 (d/m/d)

Count of I‐131

(d/m/d)

Count of I‐131

(μc/d)

Count of Gamma

(d/m/d)

1949 17 5 12 1950 52 1 3 4 44 1951 81 1 3 76 1952 93 43 48 2 1953 77 51 26 1954 172 104 45 4 21 1955 278 192 48 75 1 2 29 1956 244 149 68 53 38 1957 295 157 65 19 1 44 9 1958 189 90 91 13 2 1 5 1 1959 221 60 103 19 2 7 3 33 6 4 7 2 1960 293 104 116 29 2 12 5 28 2 12 56 1961 250 111 119 87 3 1 1 7 5 18 8 2 1962 309 120 160 100 4 6 1 7 14 4 8 1 2 1963 355 91 195 130 3 15 14 17 35 15 13 1 6 1 1964 222 59 140 59 12 4 1 6 2 1 5 1 12 2 1 1965 263 40 99 9 101 6 4 5 1 11 2 1 6 4 5 1966 410 37 112 5 231 4 7 19 6 2 2 4 1 
SEC-00113 09-29-09 FINAL 

Page 37 of 120 

Table 6-3: Total No. of In Vitro Results/Yr and No. of Individual Radionuclide Results/Yr* 

Note: A single sample may include more than one result (multiple analyses per sample.) 

(This table spans three pages) 

Year

Count of  

Samples

Count of Gross

(d/m/d)

Count of MFP

(d/m/d)

Count of Sr‐90

(d/m/d)

Count of H‐3

(μc/l)

Count of U/Total

U (ug/l)

Count of "U"

(d/m/d)

Count of Nat U

(μg/l)

Count of Nat U

(d/m/d)

Count of U‐238

(μg/l)

Count of EU/U‐

235 (d/m/d)

Count of Gross

alpha (d/m/d)

Count of Po‐210

(d/m/d)

Count of Pu/Pu‐

239 (d/m/d)

Count of I‐131

(d/m/d)

Count of I‐131

(μc/d)

Count of Gamma

(d/m/d)

1967 959 5 105 11 804 5 26 2 1 5 1 1 10 1 5 1968 713 1 74 624 1 12 1 4 3 63 1969 695 57 623 6 25 1 5 1 1 3 47 1970 566 2 38 531 9 33 1971 271 1 16 270 1 19 1972 220 1 6 219 9 1973 262 1 13 262 14 1974 341 6 341 6 1975 254 1 10 246 3 12 1976 70 1 70 1 1977 103 103 1978 116 109 1979 98 98 1 1980 95 91 1981 131 92 45 1982 102 102 1983 76 76 1 1984 102 54 1 
SEC-00113 09-29-09 FINAL 

Page 38 of 120 

Table 6-3: Total No. of In Vitro Results/Yr and No. of Individual Radionuclide Results/Yr* 

Note: A single sample may include more than one result (multiple analyses per sample.) 

(This table spans three pages) 

Year

Count of  

Samples

Count of Gross

(d/m/d)

Count of MFP

(d/m/d)

Count of Sr‐90

(d/m/d)

Count of H‐3

(μc/l)

Count of U/Total

U (ug/l)

Count of "U"

(d/m/d)

Count of Nat U

(μg/l)

Count of Nat U

(d/m/d)

Count of U‐238

(μg/l)

Count of EU/U‐

235 (d/m/d)

Count of Gross

alpha (d/m/d)

Count of Po‐210

(d/m/d)

Count of Pu/Pu‐

239 (d/m/d)

Count of I‐131

(d/m/d)

Count of I‐131

(μc/d)

Count of Gamma

(d/m/d)

1985 50 50 1 1986 41 38 1987 8 4 3 4 1989 1 

Grand

Total 9095 1422 1767 622 5165 65 87 54 22 190 43 65 181 179 22 13 264 

* Includes only the data available to NIOSH from data captured prior to May 1, 2009. 
SEC-00113 09-29-09 FINAL Brookhaven

Page 39 of 120 

6.1.2 Whole Body Counting Data 

Table 6-4 below summarizes the in vivo analytical results by year and by individual radionuclide 

extracted from SRDB documents captured as of May 1, 2009. During this evaluation process, NIOSH 

captured and entered over 1900 individual WBC results from 686 individuals. The data ranges from 

1960 (the start of whole body counting at BNL) to 2000, after which the data are kept in the HPRS. 

The majority of the captured data are from the 1980s; currently, data gaps exist for the years 1963, 

1965-69, 1971, and 1991. 

The data came primarily from several sets of whole-body results (WBC Summaries, 1987; WholeBody Results, 1973-1981; Whole-Body Results, 1975-1981; Whole-Body Results, 1979-1986; 

Whole-Body Results, 1988-1994; Whole-Body/Thyroid Results, 1983-1984). Much of the data was 

compiled from memos written from WBC program managers to S&EP representatives when they 

forwarded the WBC results for employees working in their respective areas. 

Typical radionuclides measured included: Cs-137, Co-58/60, Zn-65, Fe-59, Mn-54, and Be-7. There 

are also results for Cs-134, Ce-141/144, Ba/La-140, and the radioiodines. Results for lung and thyroid 

dose were also captured. 

In general, results include the employee’s name and at least one identifier such as “BNL Life 

Number,” division/department, and/or a location indicator. There is some uncertainty regarding the 

WBC identifiers and work locations, but the data were cross-matched with the in vitro data or 

organizational charts when possible. Major work groups identified included: 

• Accelerator 

• Biology, Chemistry, and Physics 

• Critical Assembly, Department of Applied Science, and Nuclear Engineering 

• Health Physics, Safety & Environmental Protection, and Waste Management 

• Hot Lab and Medical 

• Plant Maintenance and Shops 

• Pile and Reactor 
SEC-00113 09-29-09 

Table 6-4: Total No. of In Vivo Results/Yr and No. of Individual Radionuclide Results/Yr 

(This tables spans two pages)

Year

Total

Analyses

Cs‐137

(nCi)

Cs‐134

(nCi)

Co‐60

(nCi)

Co‐58

(nCi)

Zn‐65

(nCi)

Fe‐59

(nCi)

Ce‐41/144

(nCi)

Ba/La‐

140 (nCi)

Mn‐54

(nCi)

Be‐7

(nCi)

I‐133

(nCi)

1960 29 29 271961 2 1 1 1962 2 21964 3 31970 1 11972 8 8 11973 48 48 2 10 31974 83 82 71 1 1 1975 47 47 31976 14 131977 36 331978 36 21 7 10

4 

1979 33 31 1 3 1 1980 107 99 95 79 31 46 45 1981 137 124 1 117 17 3 15 1982 19 12 12 121983 21 15 2 12 14 2 4 3 2 1 1984 223 177 60 154 172 161 57 7 7 109 46 9 1985 117 101 1 79 79 80 25 1 1 9 28 52 1986 171 137 123 117 128 136 137 1 95 28 1987 165 140 59 104 114 113 134 70 59 1988 167 156 1 144 105 149 105 109 92 13 1989 238 219 1 177 3 100

4 67 142 60 

1990 2 2 21992 11993 114 111 111 111 7 2 110 110 1994 85 84 83 84 80 84 80 84 1 

Page 40 of 120 
SEC-00113 09-29-09 

41 of 120 

Table 6-4: Total No. of In Vivo Results/Yr and No. of Individual Radionuclide Results/Yr 

(This tables spans two pages)

Year

Total

Analyses

Cs‐137

(nCi)

Cs‐134

(nCi)

Co‐60

(nCi)

Co‐58

(nCi)

Zn‐65

(nCi)

Fe‐59

(nCi)

Ce‐41/144

(nCi)

Ba/La‐

140 (nCi)

Mn‐54

(nCi)

Be‐7

(nCi)

I‐133

(nCi)

1995

4 1

1996 21997 11998 21999 22000 1

Total 1921 1694 332 1211 697 1152 585 14 8 727 577 135 
SEC-00113 09-29-09 Brookhaven

6.1.3 Air Monitoring Data 

As a part of BNL’s radiation protection program, it is evident that extensive monitoring of 

airborne radioactive dust has been regularly performed. In addition, air monitoring for tritium 

was performed and charcoal cartridges were used to sample for iodines. Information supporting 

these conclusions can be found in many captured documents. For example: 

• Health Physics Summary for 1954 describes air monitoring activities in the canal area of the 

reactor in 1954 (HP Summary, December 1954). 

• Airborne Contamination at the Hot Laundry is an extensive study of airborne contamination 

in the Hot Laundry in 1956 (Bergin, 1956). 

• Monthly Hot Lab Reports and Progress Reports January-December 1963 is an analysis of 

continuous air samples at the Waste Concentration Plant in 1963 (Progress Reports, 1963) 

• Appendix on Radiation Safety for Particle Accelerators includes air sampling as one of the 

exposure control methods (BNL, 1969). 

• Monthly Reports for 1973 describes air monitoring results for Building 650 (Monthly 

Reports, 1973). 

• Air Samples provides results for air samples taken during an operation that welded 

percussion pins onto uranium plates (Lazo, 1988a). 

• Respirator Use by RCG Personnel discusses air samples taken to verify that respiratory 

protection was not required (Reciniello, 1992). 

Several appraisals of the air monitoring program have also been captured. A November 1961 

assessment by HASL for the AEC found the air sampling records at the Pile Health Physics 

office were lacking in that very little air sampling information is contained in the logbooks. Few 

air samples were taken and only the significant results were recorded. BNL apparently agreed to 

address the situation, and by January 1962, it was remedied (Breslin, 1961; Breslin, 1962a). In 

May 1962, the air sampling program during a shutdown at the BGRR was again criticized, 

stating that health physics relied too much on past experience with similar operations, nose 

swipes, and urine samples (Breslin, 1962b). Burns & Roe was contracted by BNL to conduct an 

appraisal of airborne monitoring in 1991. The appraisal identified where airborne monitoring 

was satisfactory, where some improvements were desirable, and where airborne monitoring was 

not required because only small amounts of radioactivity were being used in the operations 

(BNL, 1990-1991a; BNL, 1990-1991b). 

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Although evidence of an extensive air monitoring program has been found, very few monitoring 

results from this program have been located. As indicated in the references above, results for a 

few isolated situations have been located, but data that reflect the daily air sampling results that 

would be needed to reconstruct potential worker exposure have not been located. This same 

observation was made in the HASL reviews discussed above. The evidence suggests that, in 

general, airborne issues at the reactors, labs, and accelerators were very infrequent, thus resulting 

in a casual approach to record-keeping. The inability to locate comprehensive results limits the 

viability of using air monitoring results in the dose reconstruction process. Therefore, further 

assessment of potential internal dose using air sample data will not be included in this evaluation 

report. 

6.2 Available BNL External Monitoring Data 

From the beginning of operations that may have involved radioactive material (in 1947), 

exposure to external radiation was monitored. Table 6-5 summarizes the period of use, type of 

dosimeter, MDL, and exchange period. 

Table 6-5: Minimum Detectable Levels for Photon, Beta, and Neutron Dose (mrem) 

Period of Use Dosimeter MDL (mrem)a Exchange Frequency 

Start-up through 1954 Multi-element film + NTA 40 Weekly 

Monthly 

1955 through 1995 Multi-element film +NTA 30 Monthly 

1996 to present Harshaw 8814 and 8806 TLD 

+ CR-39 

10 Monthly 

Start-up through 1995 NTA filmb ~50 Weekly 

Monthly 

1996 to present CR-39b ~20 Monthly 

a

 Estimated MDLs for each dosimeter in the workplace even though many doses were reported at less than the 

MDL. 

b

 Processing done by R. S. Landauer. 

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Table 6-6 provides a more specific listing of the types of monitoring performed at various times 

throughout BNL’s history, the methods/materials used, how the data were recorded, and in what 

manner the data are available for retrieval for creating a worker’s exposure history. The table 

shows that BNL periodically changed the monitoring methods to adopt better technologies for 

performing personnel monitoring. 

Table 6-6: External Dosimetry Timelines and Data Source Descriptions 

Type Dates Description 

Whole Body 

Badges 

1947- 1965 BNL Film badges: BNL read its own data and recorded data on personnel 

cards. 

1965- 1984 BNL Film Badges: BNL read its own data and recorded data in a computer. 

These data are now available only in hard copy. 

1985- 1995 

Landauer read Landauer Film Badges and stored data on their system. 

These data are now available on microfiche and paper monthly reports. 

Summary data for lifetime Dose of Record for personnel has been entered 

in HPRS. 

1996 –present BNL implements TLDs, reads its own badges, and stores data in HPRS. 

Ring Dosimetry 

1947- 1965 BNL Ring Badges: BNL read its own data and recorded it on personnel 

cards. 

1965- 1984 BNL Ring Badges: BNL read its own data and recorded it in a computer. 

These data are available only in hard copy. 

1985- 1995 Landauer read Landauer Rings and stored data on their own system. These 

data are now available on microfiche. 

1996 –present Landauer read Landauer Rings and transmitted the data to BNL. These 

data are stored in HPRS. 

Environmental 

Monitoring 

1947 – mid 

1998 

4 TLD-200 (calcium fluoride) 1cm x 1cm chips placed in a brass sphere 

which was then placed in a small plastic bottle with string attached. 

Mid 1998 – 

present 

Harshaw 8807 with TLD 2211 cards. 

Area Monitoring 

1947- 1965 BNL Film badges: BNL read its own data and recorded it on personnel 

cards. 

1965- 1984 

BNL Film Badges: BNL read its own data and recorded it in a computer. 

These data are now available only in hard copy. Landauer read Landauer 

Badges and stored data on their own system; these data are now available 

on microfiche. Summary data for personnel have been entered in HPRS. 

1996 –present BNL implements TLDs, reads its own badges, and stores the data in HPRS. 

Neutron 

Dosimetry 

Pre-1984 BNL whole-body film badges used NTA films for neutron measurement. 

1985 - 1995 Landauer whole-body badges used combinations of NTA films, CR39, and 

Lexan for neutron monitoring. 

1996 - present 

BNL Harshaw 8806 TLD badges used a TLD-600 element in all badges 

with the addition of Landauer-supplied CR39 and Lexan (discontinued 

after June 1997) when high-energy neutron monitoring at the Alternating 

Gradient Synchrotron (AGS) was desired. 

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45 of 120 

Though the generally un-centralized nature of BNL’s radiation monitoring program has resulted 

in difficulty obtaining complete historical internal monitoring data sets, external monitoring 

summary data are available for the entire evaluation time period with the exception of the 

summary report for 1971. External results for individual employees are available for 1971, but 

the annual summary report was not captured. 

Radiation exposure data were submitted annually to the AEC/ERDA/DOE in accordance with 

reporting requirements. Attachment 2 displays these data (except for 1971 as noted above) and 

demonstrates that a significant number of workers were monitored every year. These data (from 

1974 to 2007) were collected from the Annual Reports available on the DOE REMS website, and 

from similar annual reports found among BNL records (prior to 1974) (AEC, 1970; AEC, 1972; 

AEC, 1973; WBC Summary, 1960; WBC Summary, 1961; WBC Summary, 1964; Whole-Body 

Results, 1965-1969). 

Figure 6-1 shows the dose distribution in the monitored population, indicating the maximum 

exposure range measured each year as well as the average exposure received by individuals with 

measureable exposure. Average dose data were not available in the summary reports for the 

years 1958-65 and 1971-73. Figure 6-1 shows that the maximum exposure range went from 

around 7-9 rem in the late 1950s down to around 4-5 rem from 1963 through the 1970s, and then 

slowly ramped down through the 1980s (2-4 rem) and 1990s (0-2 rem). Since 1990, the 

maximum exposure range has been 0-1 rem. For those years for which average dose data are 

available, the values were around 1-2 rem until 1980, after which the averages were generally 

below 1 rem. 
SEC-00113 09-29-09 

0123456789

10

1958

1959

1960

1961

1962

1963

1964

1965

1966

1967

1968

1969

1970

1971

1972

1973

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

2004

Maximum Dose Range

(rem)

Year

Maximum External Dose Range and Average Dose by Year

Maximum DoseRange (rem)Average Dose(rem)

Figure 6-1: Maximum External Dose Range and Average Dose by Year 

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SEC-00113 09-29-09 Brookhaven

The Personnel Monitoring Policy was to provide a radiation dosimeter to all workers who had 

the potential to receive external exposure (HP Procedures, 1948; Personnel Monitoring, 1948; 

Personnel Monitoring, unknown date; Pocket Chambers, 1952; Safety Manual, 1948; Use of 

Dosimetry, 1995). This was implemented by designating those facilities that used radioactive 

materials or created radiation sources as “radiation areas” and requiring that all who entered must 

have a radiation dosimeter. The available records clearly indicate that this policy was being 

implemented throughout the operating history. However, this resulted in a segment of workers 

who were not externally monitored and for whom no radiation exposure records are available. 

This is consistent with industry practice, as there would have been workers whose duties did not 

require that they be near a source of radiation and would not have been expected to have 

received radiation exposure in the location of their normal work assignment. It should be noted 

that AEC/ERDA/DOE requirements specified that only those individuals expected to exceed 

10% of the annual dose limit (or later, exceed 100 mrem/y) were required to be monitored. 

Some examples of the types of workers who may not have been monitored include: those in 

administrative positions whose normal work location was not in one of the facilities with 

radiation areas; construction trade workers whose projects were located in non-radiation areas; 

and engineers or scientific personnel whose duties did not require that they enter a radiation area. 

Personnel dosimeter monitoring data will not be available for such types of workers. 

NIOSH has identified that personnel dosimeter monitoring data for reconstructing external doses 

are available for the entire time that BNL has been operational. The data include extensive 

external monitoring results, including neutron exposure data. 

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 7.5. This approach is discussed in OCAS’s SEC Petition Evaluation 

Internal Procedures which are available at http://www.cdc.gov/niosh/ocas. 

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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-00113 as submitted by the petitioner. (Section 7.4) 

7.1 Pedigree of BNL Data 

ATTRIBUTION: Section 7.1 and its related subsections were completed by Tim Adler, Oak Ridge 

Associated Universities. 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. 

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. 

Personnel monitoring oversight organization at BNL has changed several times during the period 

under evaluation. The following is a brief summary of oversight history; additional details are 

available within captured documents, including some organization charts. Initially, the Health 

Physics Division was responsible for providing general monitoring guidance and health physicist 

oversight personnel. Within the division, this was accomplished by the “Personal Monitoring 

Group” which, through its dedicated health physicists, had responsibility for determining 

monitoring requirements, and data evaluation, reporting, and maintenance. Monitoring sample 

analysis has been performed by both off site services and also on site by Analytical Services (a 

group within the Health Physics Division). Later, the Health Physics Division became the Safety 

and Environmental Protection Division (S&EP) and then finally into the Radiological Control 

Division (RadCon). Whole-body counting services were provided by the Medical Division until 

1980 when that function was consolidated with other personnel monitoring under the S&EP 

Division. The transition was in part a result of criticisms from S&EP personnel that whole-body 

counting was not occurring as requested, records were seemingly getting misplaced, and that the 

Medical Division “does not specifically provide for diagnostics or the follow-up of positives" 

(Hull, 1979; Cohn, 1980). 

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Hundreds of documents retrieved from the site indicate the presence of a skilled and dedicated 

health and safety work force at BNL for the period under evaluation. Based on interviews and 

review of captured documents, it is apparent that workers dealing with known sources of 

potential exposures were monitored commensurate with the identified significance of the 

exposure. Unfortunately, sufficient data may not be retrievable to demonstrate that this was the 

case for all employment periods. Captured documents provide examples of how new potential 

exposure sources were characterized prior to determining monitoring/shielding requirements, and 

show that incidents were addressed with appropriate follow-up measurements. Extensive 

documentation of incidents also appears to have been an integral part of BNL’s culture for the 

evaluation time frame. Additionally, monitoring-data-report consistency checks, where possible, 

have indicated no consistency problems. It is noteworthy that, for the majority of BNL’s 

operating history, available monitoring records exist primarily in hard copy form only. The 

potential for inconsistencies between original and succeeding record storage media is therefore 

minimized. 

Despite evidence supporting adequate BNL worker monitoring practices, NIOSH identified two 

aspects of BNL data pedigree that have potential to impact data sufficiency for bounding doses 

for the class under evaluation: (1) the determination of the total quantity and type of internal 

monitoring data actually collected over the years (data availability); and (2) the current 

retrievability of that data. Difficulty in assessing these two pedigree characteristics result from 

trends in BNL data collection and storage during the period evaluated in this report. 

Specifically, difficulties result from the decentralized nature of internal monitoring data storage, 

and the lack of centralized electronic databases until the incorporation of the Health Physics 

Record System beginning in 1996 (see Section 6.0). Data still reside in several different 

locations at BNL, including individual workers’ monitoring files and medical files, log books, 

microfiche, and in memos and other miscellaneous documents that have been collected from 

many on-site locations and then indexed to applicable workers by name and BNL “Life 

Number.” Most of the collection and indexing work has been completed, but some of this work 

is still ongoing. 

Per interviews conducted with current BNL Personnel Monitoring Group staff, radiation 

exposure record storage can be broken into three general time periods. From 1947-1970s, BNL 

maintained an individual file folder by name for each monitored employee for the purpose of 

storing hard copies of monitoring results. Interviewees noted that during this time frame, in 

some cases, records indicating bioassay sample collection may have been filed without including 

the actual bioassay results. From the 1970s-1980s, limited electronic record keeping was started 

for some BNL monitoring datasets. BNL’s decision to leave the electronically-reported data 

stored as such resulted in a somewhat reduced use (and completeness) of the individual file 

folders. That is, though the electronically reported data are available, hard copies of this 

information were not typically placed within the individual file folders during this period. From 

the 1990s to the present, record maintenance has become more systematic and more 

electronically-based. This is most evident from 1996 forward with the initiation of the HPRS 

record-keeping system. 

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It is apparent that the inconsistency and timeliness with which hard copy internal monitoring 

results were placed directly into respective personnel monitoring files created a potential 

compromise of the currency and ultimate completeness of at least some employees’ internal 

monitoring records. This evaluation, as well as information provided by BNL interviewees, 

indicates that BNL’s historical handling of hard copy internal records could potentially have 

some effect on older data retrievability as recently as the early 1980s. Focused data capture 

work performed by NIOSH (described below) indicates that the effects from 1980 forward are 

likely minimal; however, the effects on pre-1980 data retrievability may be significant. 

NIOSH addressed the inability to readily obtain comprehensive historical monitoring data 

availability summaries by conducting much more extensive data capture and data entry activities 

than is typically necessary for DOE-operated facility evaluations (see Table 7-1, BNL Data 

Capture Summary). To date, NIOSH has captured and reviewed over 2800 documents from 

BNL and other sources. From these captured documents, NIOSH has extracted and 

electronically recorded over 9,000 urinalysis results, almost 2,000 whole-body counting results, 

5,900 tritium doses, and whole-body counter channel-by-channel printouts for 3,000 

measurements located in log books. Whenever noted in the documents, employee work group 

information was also recorded to best assess the appropriateness of monitoring being performed. 

In addition, NIOSH performed two data capture events focused specifically on retrieving 

selected workers’ monitoring data to further define data availability and retrievability. These 

efforts and the resulting conclusions are described in more detail below. 

Table 7-1: BNL Data Capture Summary 

Dates of Visit* Brief Summary of Captured Information Types 

7/6/2009 – 7/9/2009 

Medical and personnel monitoring files for selected past and present employees. 

Files included whole body counts, exposure investigations, tritium bioassay data, 

personnel contamination reports, and external exposure with some neutron data. 

6/29/2009 - 7/2/2009 

(Kansas City Records Center) 

HP and exposure investigations, urinalysis, and external exposure information for 

various employees (from within employee medical files). 

5/18/2009 - 5/21/2009 

(Kansas City Records Center)

Whole-body counts, urinalysis, and external exposure information for various 

employees (from within employee medical files).

5/11/2009 - 5/15/2009 

Internal dosimetry information from members of the Evaluation Team’s sample 

group, tritium exposure reports, liquid scintillation counter printouts with chains 

of custody for tritium bioassay samples, tritium monthly dose input sheets from 

1979 to 1986.

2/17/2009 - 2/20/2009

Bioassay data for selected employees, tritium report with bioassay data and 

calculated doses, reactor operations monthly reports, Landauer tritium dose 

summary, High Flux Beam Reactor (HFBR) operational history and brief history, 

HFBR tritium and heavy water losses, the HFBR hazard category reduction 

justification, Alternating Gradient Synchrotron (AGS) operational history and 

bioassay Technical Basis Document (TBD), and the site annual technical reports 

from 1949-1970.

1/12/2009 - 1/23/2009

Station monitoring worksheets (1949-1969), whole-body count logbooks, visitors' 

bioassay, tritium documents, whole-body counts results, and whole-body count 

histories.

11/12/2008 - 11/21/2008

Whole-body counting protocol, environmental and bioassay results, memos 

regarding thorium powder metallurgy, current and historical BNL Personnel 

Monitoring procedures and supporting memos.

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Table 7-1: BNL Data Capture Summary 

Dates of Visit* Brief Summary of Captured Information Types 

10/19/2008 - 10/31/2008

Whole-body counting, urinalysis, bioassay records, exposure records, medical 

injury reports, radiological investigations. Data capture included inventory of 

Brookhaven's Safety and Environmental Protection Group records.

9/15/2008 - 9/26/2008

Radiological control procedures, exposure reports, radiological incidents, wholebody counts, neutron/proton information, glove box surveys, environmental 

monitoring procedures, hot laundry review, X-ray exposure information, 

HP/Chemistry monthly progress reports, urinalysis data, neutron surveys and data 

sheets. Data capture included inventory of Brookhaven's Safety and 

Environmental Protection Group records.

8/10/2008 - 8/23/2008

Urine sample results (1952 through 1975), whole-body count results (1970s to 

1980s), monthly reports (HP, IH, environmental protection, building safety), 

radiation surveys, bonnersphere measurements/neutron calculations, 5480.11 

implementation, RadCon manual implementation plans and reports of 

noncompliance, air monitoring, dose summaries, effluent releases. Data capture 

included inventory of Brookhaven's Safety and Environmental Protection Group 

records.

3/27/2006 - 3/30/2006 Various employees were questioned by reviewers and documents were provided 

to be scanned.

2/27/2006 – 2/4/2006 Various employees were questioned by reviewers and documents were provided 

to be scanned. 

* Unless noted otherwise, data capture events took place at Brookhaven National Laboratory. 

7.1.1 Internal Monitoring Data Pedigree Review 

Only brief assessments of data availability and pedigree were possible for the electronicallystored internal monitoring data associated with the 1990s forward (see Sections 6.1 and 6.2). As 

of the date of this evaluation, recently-retrieved datasets from BNL continue to be reviewed by 

NIOSH. As with earlier years, BNL’s post-1980s monitoring was based on exposure potential 

and overseen by health physics professionals. In addition, BNL adopted DOE’s RadCon Manual 

monitoring requirements in 1992. Continued centralization of data management and retention 

was also still occurring. Interviews with BNL data management personnel noted little likelihood 

of data retention/retrievability problems with this later era. 

Based on its assessment, as documented in this report, NIOSH has identified sporadic issues with 

obtaining personnel monitoring data over all BNL years; however, NIOSH has identified a 

significant deficiency in BNL internal data availability/retrievability for the years prior to 1980. 

As discussed in this report, 1980 corresponds with a period when monitoring program 

records-management changes were implemented at the site. 

Assessing Data Availability from Captured BNL Documents

As noted, BNL’s varied methods of maintaining hard copy internal monitoring records prior to 

the 1990s have complicated pedigree determination for this era. To initially assess data 

availability, internal monitoring analytical data were extracted during the review of over 2,300 

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documents captured by May 2009. These data summaries have been presented in Tables 6-3 

and 6-4 in this report. To better determine data availability, two additional data capture efforts 

were performed (yielding over 400 more documents). The resultant captured data were 

summarized only in terms of numbers of people/monitoring type/year. These latter data 

summaries are presented individually in succeeding subsections. They were also combined with 

earlier data capture information and presented in Attachment 1. 

The summarized results can at best provide an indication of total BNL monitoring data 

availability. The only way to determine the actual total hard copy data availability would be to 

access and compile data from each and every employee’s files as well as from other hard copy 

repositories BNL has used over the years; that level of effort has not been performed as part of 

this evaluation. Evaluation time constraints precluded this level of effort. Despite the 

limitations, the data captured are sufficient to provide support of some basic BNL monitoring 

program characteristics noted above and to give some insight into potential data availability for 

the class under evaluation. Although NIOSH cannot confirm the ability to consistently retrieve 

BNL personnel internal monitoring data prior to 1980, the data summarized in Attachment 1 

indicate that: 

• BNL workers have been monitored for internal exposures since at least 1949 forward. 

• Monitoring results were documented and reported to oversight personnel. 

• Workers engaged in higher internal-exposure-potential jobs (Reactors, BLIP, Hot Lab, Waste 

Disposal) appear to have been monitored more frequently than those in lower-exposurepotential positions 

• Uranium and mixed fission product urinalysis drops off after the BGRR shuts down and the 

HFBR starts up (with resultant increased H-3 analysis for HFBR workers) 

• Over time there has been a trend towards an increased use of whole-body counting versus 

urinalysis to monitor BNL workers. 

Two-Hundred-Person Monitoring Data Capture Exercise

NIOSH performed additional data capture focused specifically on obtaining employee 

monitoring data from BNL personnel files. This was done to expand the data availability 

knowledge that resulted from the general document capture work described above. Additionally, 

efforts were made to assess BNL data storage practices over time and also to gauge BNL’s 

progress in its ongoing effort to collect and file hard copy personnel monitoring information that 

is not currently stored in employee-specific files. Preferably, a random sampling of names 

would have been chosen from the BNL’s Human Resources Database. NIOSH access to this 

database was denied by BNL due to Privacy Act concerns; therefore, NIOSH selected 200 BNL 

employees’ names from over 2300 names identified in previously-captured documents for this 

BNL data capture and retrievability exercise/assessment. The sample size reflected the 

maximum deemed possible for a single data-capture event and was developed to include people 

from various workgroups and apparent employment times represented in the evaluation period. 

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All data available for the selected employees were captured from BNL’s two primary hard copy 

data repositories: (1) employees’ personal monitoring (PM) files; and (2) employees’ medical 

files. Comparisons were made to data that already existed for some of the selected 200 workers 

in NIOSH’s existing Excel spreadsheet. Comparisons were also made to BNL’s “Historical 

Bioassay Index.” This index is used to link a growing collection of miscellaneous hard copy 

data being recovered from various on-site locations (i.e., other than employees’ PM and medical 

files). The captured monitoring data were assessed and reviewed to compile data availability 

summaries for the 200-person sample group. 

Attachment 3 presents the 200-person data availability summary in terms of number of people 

monitored/year/analysis. Data from employees in the same work groups were totaled. To reduce 

the table size, selected work groups were also compiled. As with the previous work, the results 

are still just an indicator of total data availability and are limited by not having access to precise 

individual employment time frames and/or changes in work groups over time. Results shown in 

Attachment 3 generally reflect the trends seen in the summary of data initially compiled from the 

documents captured prior to May 2009. It is evident that at least some additional internal 

monitoring data are available within workers’ monitoring and medical files and that higherexposure-potential activities were monitored. 

Attachments 4, 5, and 6 present data type captured versus the storage repository in which it can 

be found by year. The purpose of these plots was to get an indication of historical data storage 

techniques and the relative presence of data in “expected” locations such as PM or medical files 

versus the amount of data obtained from less-secure locations, such as those being searched for 

compilation into the Historical Bioassay Index. It is important to note that identical results can 

be and often are found in more than one repository. An additional purpose of these plots was to 

assess BNL progress towards collection of miscellaneous hard copy records into the more 

retrievable and secure Historical Bioassay Index. To this end, data extracted from NIOSH’s 

initial document capture work was compared to data found during the 200-person exercise. 

Results of the numbers of employees with data found by NIOSH and not yet located in that 

employees’ PM files, medical files, or Historical Bioassay Index were plotted. These latter 

results are denoted in the Attachments as “[data type] NIOSH Captured Documents not Matched 

to Index, Medical or PM files.” 

As seen in the Attachments, tritium data storage seems to be much more consistently stored in 

the PM and medical files after the late 1960s. Trends in the storage of other urinalysis and 

whole-body counting data are not as clear. It is apparent, however, that most data are found 

stored in the PM and medical files from 1970 forward regardless of data type. Plots of data 

captured by NIOSH that have not yet been assimilated into BNL’s primary storage repositories 

shows at least some collection and filing work remains to be performed by BNL. Peaks 

observed for this latter data type are most often attributed to individual documents containing 

multiple employees’ results. 

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Sixty-Nine-Person Requested Monitoring Data Retrieval Test

NIOSH performed a final focused data capture to assess BNL’s historical monitoring program 

performance based on specific documented monitoring requests. The goal was to perform a test 

that would provide an indication of the program’s ability to execute requested monitoring, 

document the results, and preserve the results in a readily-retrievable manner over time. To this 

end, NIOSH again used captured documents to identify specific names and requested monitoring 

that spanned the years 1948-1992 (the time frame most likely to exhibit record retention 

problems). After selection, NIOSH searched for monitoring results responsive to the specific 

monitoring requests in the workers’ personal monitoring files, medical files, and the “Historical 

Bioassay Index.” Though this exercise was straightforward by design, unknown variables can 

still exist. Examples include the possibility of worker assignment changes or undocumented 

request modifications or cancellations made by BNL staff. 

The results of this exercise are summarized in Table 7-2. Results indicate a trend towards more 

consistent data collection and maintenance apparent in the 1970s which continues into a high 

data retrieval rate by 1980. This trend may be related to the general trend towards better 

monitoring data storage practices seen in the 200-person exercise. It is also likely evidence that 

shifting the whole-body counting responsibilities from the Medical Division to the S&EP 

division contributed to the improved record maintenance practices sought by BNL at that time. 

Centralization and improved control over personnel monitoring sample collection, analyses, 

follow-up work, and records maintenance were all goals of this reorganization (Hull, 1979; 

Cohn, 1980). 

Table 7-2: Sixty-Nine-Person Requested Monitoring Data Retrieval Test 

Request Time Span Data 

Available in 

BNL files? 

Percent 

Success

Comments

Yes No 

1992 11 0 100 All requests were WBC. 

1980 - 1989 12 1 92 One WBC request counted as not found because data that were found 

were 18 months after the request date. Five requests included 

urinalysis along with WBC and the urinalysis results were not found 

(see discussion below). 

1973 - 1979 12 4 75 All requests were WBC. 

1968 0 12 0 All requests were WBC. 

1950 2 9 18 Pre-WBC; all requests were for urinalysis. 

1948, 1949 0 6 0 Pre-WBC; all requests were for urinalysis. 

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Results of this exercise indicate that data collection and retention in readily-accessible storage 

locations has been very good from 1980 forward. The only “missing” whole-body count was 

from 1980. It was counted as missing because the closest result was 18 months after the request. 

Also noteworthy are five urinalysis results from the 1980s that were not found. Follow-up 

discussions with BNL data management personnel indicated that four out of the five requests 

were likely in error as whole-body counting would have been the analysis of choice for the listed 

isotopes of interest during the 1980s. The fifth request was for Pu. It is possible that the 

likelihood of exposure may have been revisited due to a lack of research with Pu during this time 

frame. Exposure to Pu was possible during remedial work associated with sealing the BGRR 

vents and ductwork, but this work was completed many years prior. It is also possible that the 

missing sample result exists but is still awaiting incorporation into the worker’s file. Whether or 

not this sample was ever collected or analyzed is unknown. 

NIOSH concludes that the BNL internal monitoring data pedigree is sufficient to bound doses for 

the evaluated class from January 1, 1980 through December 31, 2007. This conclusion is based 

on the results of extensive data capture, document reviews, interviews, and extra data availability 

and retrieval investigations performed. Prior to 1980, less-centralized control of sample analyses 

and record maintenance have apparently comprised the retrievability of BNL internal monitoring 

records. 

7.1.2 External Monitoring Data Pedigree Review 

External radiation exposure was performed by a single organization (generally called Personnel 

Monitoring) throughout BNL’s operating history. This group was responsible for processing the 

dosimeters and maintaining the records of personnel radiation exposure. Consequently, there is 

continuity to these records and they are still retrievable. The records are maintained in hard copy 

for the period prior to 1986, on microfiche for the period 1986-1995 (when an off-site vendor 

processed the dosimeters), and on the BNL HPRS database from 1996 to the present. 

The adequacy of the dosimeter to monitor the radiations encountered in BNL operations was 

well documented, particularly for the NTA film during the early accelerator operations with very 

unusual radiation energies. Film was used as the dosimetry medium until 1996. An off-site 

vendor was used to process the film from 1986-1995. That off-site vendor continues to process 

the CR-39 used for higher-energy neutrons. BNL processed the TLDs that were used from 1996 

to the present. BNL achieved dosimetry DOELAP accreditation in 1995 and has subsequently 

maintained accreditation through the present day, which is a demonstration of the satisfactory 

external dosimetry program at the site. 

All workers with a significant potential for workplace radiation exposure were issued dosimeters. 

Workers who entered a radiation area were required to wear a radiation dosimeter. A radiation 

area was defined as any area where a worker could receive more than 10 mrem in a day. 

Workers who used radioactive materials in areas where the exposure was expected to be less 

than 10 mrem in a day were also recommended to wear a radiation dosimeter. With this set of 

procedures in place, there would have been a population of workers that did not enter radiation 

areas or work with radioactive materials who would not have been monitored. 

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There has been continuity in the external radiation exposure monitoring program throughout 

BNL’s operating history. The appropriate workers were monitored with an appropriate 

dosimeter and their records are retrievable for the entire evaluation time frame. External 

monitoring records requested for monitored BNL claimants have consistently been supplied. 

Based on NIOSH’s assessment of BNL external dosimetry, the results of its extensive data 

captures and document reviews, and interviews with BNL personnel, NIOSH concludes that the 

BNL external monitoring data pedigree is sufficient to bound doses for the class under evaluation 

over the entire covered period. 

7.2 Evaluation of Bounding Internal Radiation Doses at BNL 

ATTRIBUTION: Section 7.2 and its related subsections were completed by Eugene Potter, M.H. 

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

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

The principal sources of internal radiation doses for members of the class under evaluation were: 

• Operation and maintenance of nuclear reactors and accelerators 

• Production of radioactive isotopes in reactors and accelerators 

• Chemical separations of radioactive isotopes 

• Research activities with radioactive isotopes 

• Medical diagnosis and treatment with radioactive isotopes 

• Fabrication, maintenance, and repair of ancillary equipment 

• Waste management activities 

The potential internal sources were dependent on the operational area and activities. The major 

sources of intakes have been fission products, activation products, and tritium. The records list a 

wide spectrum of radionuclides that were monitored, including transuranics. Many of the 

radionuclides apply to a small set of workers on a research project or to workers (e.g., radiation 

monitoring technicians) whose tasks could have exposed them to many different sources 

(ORAUT-TKBS-0048, Section 2.0). 

The following subsections address the ability to bound internal doses, methods for bounding 

doses, and the feasibility of internal dose reconstruction. 

7.2.1 Evaluation of Bounding Process-Related Internal Dose Data 

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 sources of internal radiation doses for members of the class under evaluation were 

inhalation of fission products, activation products, and tritium. There is no electronic database of 

bioassay records for most of BNL’s history. Unlike the external monitoring records, bioassay 

records were not collected in a single location at the BNL site. The hard copy records recovered 

by NIOSH include urine bioassay data analyzed for fission products, strontium, tritium, uranium, 

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plutonium, polonium, iodine, and cesium. There are also some gross alpha and gross gamma 

results. 

Multiple data capture efforts have taken place to support this evaluation. These efforts have 

gathered data from BNL, DOE Germantown, Lee’s Summit, DOE Grand Junction, Kansas City 

Federal Records Center, and Atlanta NARA. Hundreds of boxes of health physics records have 

been found pertaining to the BNL covered time period. Records include: monthly 

progress/status reports, environmental monitoring reports, investigation and incident reports, 

dose rate and contamination surveys, exposure/dose reports, whole body/thyroid counting 

results, urinalysis reports, and employee termination bioassay reports. 

It is clear from these efforts that comprehensive health physics programs were in effect at BNL 

during the 1947-2007 time period. From BNL’s onset, a Radiation Safety Committee (RSC) was 

formed to establish rules for the safe handling of radioactive materials (BNL, 1947). A Safety 

Manual was published and changed as necessary to promulgate the rules presented in the health 

physics chapter. The RSC recognized that urine bioassay procedures that had previously been 

used at other AEC sites would be necessary as soon as the site began receiving radioactive 

materials (i.e., before the operation of the first reactor or accelerator). By the end of 1948, the 

site had already received approximately 2.5 curies distributed among 25 isotopes, and the BNL 

Health Physics and Instrumentation Division had supported the machining of uranium for the 

BGRR at Chapman Valve (Cowan, 1948). 

The intention of the BNL radiological protection program was to avoid radioactive material 

intakes through the use of ventilation, enclosure in glove boxes and hoods, and respirators and 

supplied air masks. However, BNL realized that potential intakes could occur through upset 

conditions, such as spills, breakage of containers, or ventilation failure. Initially, contamination 

surveys and air samples were used to trigger the need for bioassay follow-up. For example, on 

December 2, 1949, two workers were sent to Medical for treatment following an incident with 

Sr-90. The urine samples were sent to Oak Ridge National Laboratory (ORNL) (SR-90, 1949). 

During most of the site’s existence, it appears that department/division safety representatives or 

managers designated personnel for participation in the internal dosimetry program (WBCs and/or 

urinalysis) based on potential exposure. Historically, lists of workers to be sampled or wholebody counted were produced. Therefore, it may be difficult to determine if monitoring should 

have occurred by job title. After the DOE RADCON manual was published in 1992, BNL 

introduced more formality into the designation of workers for participation in the bioassay 

program (BNL, 1991; BNL, 1992a; BNL, 1992b; BNL, 1992c). 

7.2.1.1 Urinalysis Information and Available Data 

In May 1949, the BNL Medical Department arranged for three plutonium urine samples per 

week to be sent to ORNL for analysis (HP Summary, May 1949). However, it appears that the 

RSC did not establish a policy of routine (“survey”) bioassay until February 1950 (HP Summary, 

1950). In 1959, the Medical Department’s protocol was described as "People working with 

significant amounts of isotopes have 24 hour urinalysis for strontium mixed fission products or 

whatever material they are working with" (Love, 1959). Urinalyses were also done as a part of 

separation physical examinations (Cowan, 1949; Williams, 1963). 

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Initially, support was obtained from Oak Ridge National Laboratory to perform urinalysis for 

plutonium, polonium, mixed fission products, barium-lanthanum, yttrium, and strontium 

(Urinalysis Records, 1950; Urinalysis Records, January-September 1951; Urinalysis Records, 

February-December 1952; Urinalysis Records, 1953-1954). Bioassay services were also 

received from the chemistry laboratory organized under the New York Operations Office 

(NYOO) of the AEC (Sample Records, 1962-1963; Urinalysis Records, 1955-1964; Urinalysis 

Records, June 1955; Urinalysis Results, 1964; Urinalysis Records, September-November 1965). 

This laboratory had developed methods for dealing with the hazards arising from NYOO 

facilities (e.g., uranium, beryllium, fluorine, thorium, and radium) (NYOO Reports, 1949). 

In the early 1950s, BNL developed its own analytical capabilities that were refined and expanded 

over the years. However, some types of urinalyses continued to be obtained from outside 

laboratories (Urinalysis Records, September-November 1965; Urinalysis Records, May 1968; 

Urinalysis Records, July 1968; Urinalysis Records, October 1968; Urinalysis Records, March 

1969; Urinalysis Records, June 1969; Urinalysis Records, June 1987; Urinalysis Records, April 

1988). In the late 1990s, BNL established a contract with Eberline for all bioassay analyses 

except for H-3 which remained in-house until April 2004. Eberline was replaced by the SevernTrent (ST) Laboratory in December 2001. ST also started to do the H-3 analyses when they 

were discontinued on site. The ST lab has since been renamed Test America. The current BNL 

bioassay program is accredited by the DOE Laboratory Accreditation Program (ORAUT-TKBS0048, Section 5.5.2). 

Initially, urinalysis records were maintained with the medical records, since they were part of the 

“treatment” of workers as a follow-up to positive nasal swabs, contamination events, or were 

done as a part of physical examinations. Later, these results were collected in individual 

Personnel Monitoring (PM) files that also contained the external dosimetry results. Data from at 

least as far back as 1952 appear to have been transferred to the PM files around 1967. However, 

some early bioassay records may still only be located in the medical records. Some additional 

results may have been forwarded to the employee’s group (e.g., Reactor, Accelerator) and not 

filed in the PM file. BNL has just within the last few years developed an index of some of this 

historical bioassay data. BNL now checks all three sources for information when an EEOICPA 

request is received. Since 2000, urine results from the contract laboratories have been stored 

electronically at BNL and hard copy back-ups are maintained in the site’s Whole Body Counter 

office. 

For this evaluation report, over 9,000 results were captured from various hard copy reports 

(termination reports, incident reports, etc.). This collection provides information on the types of 

urinalyses that were done over the site’s history. Radionuclides routinely measured included: 

gross gamma, Sr-90, mixed fission products, tritium, uranium (total, natural, enriched), gross 

alpha, and gamma spectroscopy (primarily Cs-137 and I-131). There are also Pu-239 results, 

including some associated with incidents. Additional data are located in the PM files; NIOSH 

has captured and analyzed data for approximately 200 people from this source. The NIOSH 

assessment of the specific urinalysis data is discussed in the following sections. 

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Uranium

BNL realized that a bioassay technique for uranium would be needed as early as 1949 (Cowan, 

1949). The first uranium analyses captured during this evaluation are from 1955, and were 

performed by NYOO. Thus, it appears that at least by 1955 uranium bioassay was a part of the 

bioassay program. It is not clear when an in-house capability was developed, but it appears that 

a fluorometric method with a detection limit of 5 μg/L was in place by 1982 (Urinalysis Records, 

August 1982). A “workgroup monitoring” program for uranium was proposed by Lessard in 

1987 (Lessard, 1987a) where only representative workers for a work group would be sampled. 

NIOSH has only recovered about 464 results for a period of about 32 years (1955-1987). The 

majority of the samples (251) were marked routine or survey, 64 were incident samples, and 147 

were not designated. The samples were collected from over 20 different work groups or 

locations, with the Hot Lab and Nuclear Engineering having the most. Only 46 of the samples 

recovered were designated specifically as EU or U-235. The following is a summary of the dates 

of uranium samples recovered from SRDB Documents: 

• U/Total U (ug/L) 12/26/55 to 4/17/69 65 results 

• U (dpm/d) 6/5/62 to 11/20/69 87 results 

• Nat U (ug/L) 5/4/59 to 7/25/69 54 results 

• Nat U (dpm/d) 12/16/65 to 4/23/68 22 results 

• U-238 (ug/L) 4/23/55 to 2/1/87 190 results 

• EU/U-235 (dpm/d) 4/9/58 to 5/6/69 43 results 

• U-233 (dpm/L) 4/9/58 3 results 

It is clear that many additional results may be located in the individual PM records. As some of 

the site’s older facilities have undergone decontamination and decommissioning (D&D) starting 

in 2000, D&D workers were sampled for U-234, U-235, and U-238 (ORAUT-TKBS-0048, p. 

75). 

Fission and Activation Products

Fission product urinalyses were initially obtained from outside laboratories. By June 1951, 

preliminary work started on development of an in-house MFP urine procedure (HP Summary, 

June 1951). During the operation of the BGRR, many workers were routinely sampled for 

mixed fission products (Urinalysis Records, 1952-1975a; Urinalysis Records, 1952-1975b). 

Sampling frequency varied from as short as monthly to as long as annually. During the 

operation of the HFBR, the concentrations of radionuclides other than tritium were not 

considered to be significant. The rationale was that the concentration of tritium in the primary 

cooling water was several million times its “tolerance limit” whereas fission products from fuel 

uranium surface contamination and activated coolant impurities, such as Na-24, were present at 

less than 100 times tolerance (ORAUT-TKBS-0048, Section 5.5.2). 

• Approximately 3200 mixed fission and activation product samples were located for the 

period 1950-1976. The majority of the samples are for Reactor and Hot Lab personnel. 

However, samples were also obtained from other groups, including (but not limited to) 

Health Physics, Plant Maintenance, Nuclear Engineering, Physics, and Accelerator. 

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• Some samples were specifically analyzed for Sr-90 (nearly all in conjunction with a fission 

product analysis). NIOSH has recovered over 600 Sr-90 results for the period 1949-1967. 

The majority of the samples are for the Reactor, Hot Lab, and Heath Physics groups. 

• Urine results for Cs-137 were also recovered. These results were essentially all from the 

1960s. Of the 175 results recovered, 140 were for the Hot Lab, with no other group having 

more than 10 results. 

• Thirty-five urine results for I-131 were recovered for 1959-1969. Nearly all of these were for 

the Hot Lab and Health Physics groups. 

Urine results recovered for other miscellaneous fission and activation products, other than those 

listed in this section, are summarized in Table 7-3. 

Table 7-3: Urine Results Obtained for Fission and Activation Products 

Radionuclide No. of Samples First Date Last Date Reason for Sample(s) 

Ag-110 1 8/7/1957 8/7/1957 Incident 

Au-198 3 11/19/1970 11/24/1970 Incident 

Be-7 1 1/29/1980 1/29/1980 Incident 

Ce-141/143 2 12/22/1975 12/22/1975 Incident 

Ce-144 1 11/17/1964 11/17/1964 Survey (routine) 

Co-60 9 10/10/1956 12/19/1980 1 survey; 1 incident; 7 unknown 

Cs-132 2 5/22/1978 6/7/1978 Unknown 

Hf/Hf-181 2 8/5/1966 8/5/1966 Incident 

I-126 5 5/22/1978 7/28/1980 Unknown 

Na-22 1 6/7/1978 6/7/1978 Unknown 

Na-24 2 2/26/1963 2/17/1964 Incident 

P-32 16 4/23/1957 4/7/1972 9 survey; 7 incident 

Ra-226 1 5/18/1964 5/18/1964 Incident 

Ru-103 1 4/17/1951 4/17/1951 Incident 

Ru-106 1 4/21/1965 4/21/1965 Incident 

Sr-82 1 3/16/1987 3/16/1987 Incident 

Zn-65 1 3/29/1963 3/29/1963 Incident 

Most of the samples in the table are incident-related and were not likely part of a routine 

program. The information in this section and Table 7-3 illustrates that BNL had the ability to 

sample and analyze for a great variety of radionuclides when potential intakes occurred. 

It is clear that many additional fission or activation product results are located in the individual 

PM records. After 1960, fission and activation products can be accounted for by whole-body 

counting, either directly or by using ratios. As some of the site’s older facilities have undergone 

D&D starting in 2000, D&D workers were sampled for Sr-90, (ORAUT-TKBS-0048, p. 75). 

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Tritium

In 1958, a vibrating reed electrometer and chambers suitable for tritium urinalysis were set up in 

Building T-145 (Progress Report, April 1958). By October 1959, the equipment was ready for 

standardization (HP Summary, October 1959). Initially, the analysis was done by combustion 

and gas counting. Liquid scintillation counting for tritium urinalysis was adopted in the early 

part of 1964 (Gemmell, 1967). 

NIOSH has captured 5165 H-3 results for the period 1959-1987. Over 99 percent of the results 

were routine (survey) samples. Most of the samples were for the Health Physics (1058) and 

Reactor (3141) groups. Over 100 samples per year were recovered for 1965-1975, 1977, 1978, 

and 1982. Over 800 results were recovered for 1967. The data show that the samples were 

probably collected monthly from the mid-1960s to the early 1970s. From the late 1970s to the 

early 1980s, samples were collected weekly. NIOSH evaluated the number of samples recovered 

for HFBR workers against an estimate of the number that were probably analyzed. The 

references did not consistently report the number of people assigned. Indications are that there 

were probably up to 150-200 people who worked at or visited the reactor each month. Of these, 

there was probably a core group of 20-30 people regularly sampled for H-3. 

For the period 1992-2000, NIOSH has captured several monthly tritium dose records. A few 

also have bioassay results (BNL, 1992b; BNL, 1992c; BNL, July-December 1999; Dose Report, 

April 1992; Dose Report, July 1995; Exposure Summaries, August-December 1992; Exposure 

Summaries, October 1992; Exposure Summaries, January 1993; Exposure Summaries, February 

1993; Exposure Summaries, August 1993; Exposure Summaries, September 1993; Exposure 

Summaries, October 1993; Exposure Summaries, 1994; Exposure Summaries, November 1994; 

Exposure Summaries, 1995; Exposure Summaries, January-September 1995; Exposure 

Summaries, 1996; Exposure Summaries, 1997; Exposure Summaries, January-November 1998; 

Exposure Summaries, 1998-1999; Tritium Assessments, August 1993; Tritium Assessments, 

October-November 1993; Tritium Assessments, October-December 1993; Tritium Assessments, 

January-February 1994; Tritium Assessments, February-March 1994; Tritium Assessments, 

January-August 1994; Tritium Assessments, December 1994; Tritium Assessments, JanuaryFebruary 1995; Tritium Assessments, January-March 1995; Tritium Assessments, December 

1996). 

NIOSH has also captured tritium dose records that were maintained for the site by the R. S. 

Landauer Company. The date range is 1984 to July 1995. Recently, over 11,000 electronic 

tritium bioassay results were captured from the Analytical Services Laboratory (ASL) database 

for the period 1995-2003. It is clear that many additional tritium results are located in the 

individual PM records. 

Thorium

No thorium-specific urine bioassay records were recovered. It is not clear whether additional 

data capture would produce any urine data. It appears that whole-body counting was the method 

of choice for thorium bioassay after 1959; therefore, assessment of whether sufficient 

information (represented by whole-body counts) exists to support bounding the thorium dose, is 

contained in Section 7.2.1.2. 

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Plutonium

Plutonium urinalyses were among the first samples requested at BNL. In May 1949, Medical 

arranged for three Pu urine samples/week to be sent to ORNL (HP Summary, May 1949). In 

1959, Pu urinalysis services were purchased from Nuclear Science and Engineering Corp., and 

gross alpha analyses were being done at BNL as a check, while consideration was being given to 

doing the Pu analyses in-house using the Hanford method (HP Summary, November 1959). 

NIOSH has recovered 179 results for the period 1949-1971. Most of the results are for routine 

(survey) samples. The work groups for more than a third of these samples are unknown. Most 

of the remaining samples are for the Reactor, Hot Lab, and Health Physics groups in the early 

1950s. As some of the site’s older facilities have undergone D&D starting in 2000, D&D 

workers were sampled for Pu-238, Pu-239, and Pu-240 (ORAUT-TKBS-0048, p. 75). 

Americium

Only a few Am-241 urine results have been recovered. One sample was collected in the Health 

Physics Group in 1958 and one from the reactor in 1959, indicating that BNL had the ability to 

analyze urine samples for this radionuclide. The lack of samples recovered to date may indicate 

that the routine operations involving Am-241 were considered to be well-controlled. However, 

two gross alpha results were tied to an americium incident on July 28, 1975; the incident 

involved “HPS students” as opposed to BNL employees. The results for both samples were 

given as “ND” (not detected). No other information on this incident was located. As some of 

the site’s older facilities have undergone D&D starting in 2000, D&D workers were sampled for 

Am-241, (ORAUT-TKBS-0048, p. 75). 

Polonium

Like plutonium, polonium was one of the earliest urinalyses requested from ORNL by BNL. 

NIOSH has recovered 181 results for the period 1954-1967. Most of the samples are for the Hot 

Lab and Nuclear Engineering and most are for the period 1954-1960. The lack of Po-210 

urinalyses in later years is probably a reflection of the fact that polonium use fell out of favor 

across the DOE complex. Furthermore, its short half-life means that there is no residual 

contamination from earlier operations. 

7.2.1.2 Whole Body Counting Information and Available Data

The Medical Division began using a whole-body counter at the end of 1958 (Unknown author, 

1958). It was first used as a research tool, but it became evident that it was also of use when 

someone was potentially involved in an incident. Pile operators were the first group to be 

routinely counted (Cowan, 1964b, pdf p. 29; Davis, 1970). Like the urine program, facility 

health physicists were asked to supply lists of individuals whose jobs put them at risk for intakes 

of radioactive material (Various authors, September-November 1973; Whole Body Counting, 

1973). After confirmed intakes, whole-body counting was repeated daily and the results were 

correlated with daily urine excretion results (Cowan, 1964b). Beginning in 1960, whole-body 

counts on BNL employees were recorded in periodic physical log books, indicating that the 

whole-body counter was considered operational. In the 1960s, whole-body counts were also 

included in the separation physical examinations for reactor operators (Davis, 1970). By 1968, 

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over 1000 individuals had been counted and only Cs-137 and K-40 (both present in background) 

had been detected, with the exception of Zn-65 in some Pile operators (Cowan, 1968). There 

were three references located for thorium WBCs for occupational exposures (HP Summary, May 

1959; Lukas, 1986; Miltenberger, 1979). An additional reference was found related to its use in 

medical research (Various authors, 1966). 

NIOSH has recovered the logbooks for the WBCs done on approximately 1000 people from 

1961-1968 (Cowan, 1968; Whole-Body Results, March-May 1963; Whole-Body Results, MayJuly 1963). However, data are in the form of counts per channel; they would need to be handentered and analyzed before they would be useful for dose reconstruction. 

Starting in late 1979, S&EP took over the routine and special whole-body counts (Hull, 1978; 

Hull, 1979). The same counter was used to support research in the Marshall Islands. When the 

counter was in the Marshall Islands, the Medical facility’s counter was available to support the 

occupational program (Cohn, 1980; Miltenberger, 1980a). For positive results in the S&EP 

counter, additional counts could be done with the Medical 54-detector whole-body counter to 

localize the contamination (Cohn, 1980). In 1987, the S&EP whole-body counter was described 

as “chair type system” using a 28 cm by 10 cm NaI detector that could be positioned in either a 

lung/thyroid or a whole-body counting geometry (Miltenberger, 1987a). 

Around 1990, the site lost the use of the counter that had supported both the site and the Marshall 

Island programs. The fixed facility at Medical was still available, but apparently routine counts 

were not performed. In 1992, a new “standup” counter using high-purity germanium detectors 

was put into operation and counting resumed for HFBR workers. After the resumption of wholebody counting, workers were designated for counts in accordance with the DOE RADCON 

Manual (BNL, 1992a; BNL, 1992b). The gap may have extended to 1995 for AGS workers 

(Murray, 1995) who were considered to be at lower risk. In 1999, the site received DOELAP 

accreditation in in vivo counting. In 2004, the high-purity germanium detectors were replaced 

with broad-energy germanium detectors. 

For this evaluation report, 1921 in vivo counts (WBC, lung, and thyroid counts) for about 680 

individuals were captured from SRDB documents. Most came from tables attached to memos to 

S&EP representatives giving the results for employees in their areas. The primary work groups 

monitored were the AGS, HFBR, and Medical (laboratory) staff working in the medical isotope 

program, primarily with iodine isotopes. About 20 counts were found from 1960 and 1962 (not 

including the counts in the log books). Most of the data cover the time period from 1970-1989 

and 1993, with none from 1990-92. Electronic data for the period 1999-2009 (ABACOS data) 

has recently been captured, consisting of over 2,800 counts of BNL personnel. 

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7.2.1.3 Other Types of Bioassay

No records of information exist to support the routine performance of chest (lung) counts at the 

BNL site. In 1973, the whole-body counting facility was not considered to be responsive enough 

to detect uranium and/or plutonium (Whole-Body Results, January-February 1973). However, 

some counts were performed for an off-site project with an estimated “lower limit of detection” 

of 1 nCi for U-235. Lung counts were also performed as a result of incidents involving certain 

gamma or positron emitters (Xe-127, Sr-82, Co-60) (Lessard, 1987b; Miltenberger, 1987c; 

Miltenberger, 1987d). 

Monitoring for radioactive iodines was by urine and whole-body counting in the 1960s (Progress 

Reports, 1961). Some early thyroid monitoring for iodine may only be in the medical records 

(Personal Communication, 2008b). Routine as well as incident thyroid counts were performed 

starting in the 1970s (Atkins, 1974; Carter, 1976; Iodine, 1970s; Iodine Results, 1980s; Lessard, 

1984a; Lessard, 1986; Lessard, 1987c; Miltenberger, 1980b; Miltenberger, 1987c; Thyroid 

Count Results, July-August 1981; Thyroid Count Results, January 1988a; Thyroid Count 

Results, January 1988b; Thyroid Count Results, January 1988c; Thyroid Count Results, February 

1988; Thyroid Count Results, March 1988a; Thyroid Count Results, March 1988b; Thyroid 

Count Results, October 1988; Whole-Body Results, July-August 1978; Whole-Body/Thyroid 

Results, 1984-1985; Whole-Body/Thyroid Results, January 1986). Only one person who did 

iodinations was on a thyroid counting program in 2006 (ORAUT-TKBS-0048, Section 5.6.2). 

7.2.1.4 Evaluation of Bounding Process-Related Internal Dose Data Summary

NIOSH’s data capture efforts have revealed that no conclusive evidence exists to support the 

ability to consistently retrieve BNL personnel bioassay prior to 1980 for uranium, MFP, MAP, 

plutonium, and americium; however, after January 1, 1980, urinalyses for these radionuclides 

have been identified in the BNL files and are available to NIOSH to support bounding potential 

doses for the post-1979 portion of the class under evaluation. NIOSH also has no conclusive 

evidence that polonium bioassay are sufficiently retrievable prior to 1980. By January 1, 1980, 

significant research with polonium had ended; therefore, further evaluation of the ability to 

bound polonium internal dose will not be performed for this report. After January 1, 1965, 

tritium urinalyses have been identified in the BNL files and are available to support bounding the 

tritium dose for the post-1964 portion of the class under evaluation. 

Retrievability of other types of bioassay data is similar to that determined for urinalyses. No 

conclusive evidence exists to support the ability to consistently retrieve in vivo, chest (lung) 

counts, or thyroid counts prior to 1980. After 1980, in vivo counts are available in BNL files to 

support bounding assessments for penetrating gamma-emitters (e.g., Cs-137, Co-60), uranium, 

thorium, and americium/plutonium dose assessment. Chest and thyroid counts are similarly 

available to support bounding dose for the post-1979 portion of the class under evaluation. 

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7.2.2 Evaluation of Bounding Ambient Environmental Internal Doses 

The BNL ambient air-monitoring program began in 1950. The annual environmental 

surveillance reports summarize yearly results. Stack release points and principal radionuclides in 

the airborne effluent are contained in the annual reports. These data are described in detail in 

ORAUT-TKBS-0048, Section 4.0. For its entire history, BNL monitored workers entering 

radiological areas with external dosimeters. Workers who were not monitored for external dose 

would not have received internal dose associated with hazards in the operational areas. NIOSH 

can assess potential internal doses for these non-radiological workers through the assignment of 

ambient environmental intakes. Although the ambient environmental internal dose would be 

accounted for in the available post-1979 operational data and information, sufficient information 

is available to support evaluating ambient environmental internal dose for the entire covered 

period for the BNL site. 

7.2.3 Methods for Bounding Internal Dose at BNL 

ATTRIBUTION: Section 7.2.3 and its related subsections were completed by Eugene W. Potter, 

M. H. Chew & Associates, Inc. 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. 

7.2.3.1 Methods for Bounding Process-Related Internal Dose

Intakes to monitored workers may be estimated using the available in vitro and/or in vivo data for 

the specific radionuclides that were analyzed, which is generally recognized in this report as 

available starting in 1980. Therefore, these post-1979 intake estimates may then be used to 

bound post-1979 doses from those radionuclides, using the methodologies described in the BNL 

TBD (ORAUT-TKBS-0048). Because pre-1980 personnel internal monitoring data cannot be 

reliably obtained from the site, the assessment of the ability to bound the pre-1980 processrelated internal dose is not included here. 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. 

Uranium

Based on NIOSH’s assessment of BNL, there are questions concerning the retrievability of the 

data due to the lack of a centralized records repository at the BNL site and the random nature that 

data and documentation has been discovered during data captures and site visits to support this 

SEC. However, from 1980 forward, in vivo and in vitro data can be used to support bounding 

uranium dose. 

If the isotopic information is not available, NIOSH can bound the doses to uranium by assuming 

a bounding mass-to-activity conversions for fluorometric urine results, and fully-enriched 

uranium for radiometric results. 

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Fission Products and Activation Products

Starting in 1980, it appears that S&EP filed the BNL personnel WBCs counts in the PM files, 

which includes WBC data for MFP and MAP. ORAUT-OTIB-0054 discusses mixed fission 

product/mixed activation products ratios and the calculation of intakes based on a single nuclide 

(e.g., Cs-137). The dose calculation for an organ of interest would take into account the 

differences in biokinetics between the two radionuclides. 

For I-125, the recovered thyroid counts start in 1981. After 1974, workers who were not 

monitored for radioactive iodine were unlikely to be exposed. 

Tritium

For 1965-1999, the most prevalent urine bioassay sampling was tritium for workers employed at 

the HFBR. During HFBR operation, the concentrations of radionuclides in the moderator other 

than tritium were not considered to be significant. 

For the period 1965-1983, NIOSH has captured from 70 to over 800 results per year from 

documents along with additional results from PM files. For the Period 1984-1995, NIOSH has 

obtained the dose reports for every worker monitored for H-3 (Tritium Assessments, 1984-1995). 

For the period 1992-1999, NIOSH has recovered other dose reports for the HFBR and MRR 

workers (see Section 7.2.1.1.). Using these data, NIOSH could recover sufficient H-3 data from 

the individual PM files and the ASL data to bound tritium dose for 1965-1999. For 2000 to 

present, urine results from the contract laboratory also have been captured. 

Exposures to tritiated water and/or vapor (HTO) and gaseous tritium (HT) were the most 

prevalent forms of tritium exposure at BNL. Organically-bound tritium (OBT) would have been 

encountered only in locations where biological research with labeled compounds was conducted, 

primarily Medical and Biology. Exposures to the stable metal tritide (SMT) form of tritium may 

have been encountered as the result of the storage of tritium adsorbed on rare metals, particularly 

as accelerator targets. On a case-by-case basis, intakes of OBT and SMT compounds may be 

bounded using the methodologies outlined in ORAUT-OTIB-0066. For workers at Biology, 

Medical, and Chemistry, the doses to H-3 can be bounded by assuming the form is either HTO or 

OBT, whichever results in the highest dose to the organ of interest. Similarly, for workers at the 

accelerators, H-3 doses can be bounded by assuming the form is either HTO or SMT, whichever 

results in the highest dose to the organ of interest. Historically zirconium tritide was the 

compound used in the targets (Progress Report, April 1958, pdf pp.3-4). Workers at the HFBR 

and the MMR reactors represent the largest population monitored for H-3. The doses to these 

workers can be bounded by assuming the form is HTO. Workers at the BGRR were unlikely to 

be exposed to significant concentrations of other H-3 compounds. Therefore, NIOSH concludes 

that the H-3 dose to all workers can be bound for the period 1965-present. 

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Thorium

It appears that the remaining post-1980 thorium work at BNL was the 1986 work involving 

relatively small amounts encountered in geothermal research (thorium in “magma”) (Lukas, 

1986). 

No post-1980 thorium-specific urine bioassay results were captured for this report. 

It is unclear whether additional data capture would provide much WBC data for thorium. From 

the information gathered for this report, NIOSH concludes that the few workers exposed to 

thorium were monitored by whole-body counting and that, after January 1980 when the S&EP 

took over the WBC program, the counts were filed in the workers’ PM files. Therefore, NIOSH 

concludes that WBCs can be used to bound the doses for thorium for 1980-1996. An inventory 

of dispersible radioactive material in 1997 indicated that only microcurie amounts of thorium 

were still on site (Flores, 1998). Therefore, NIOSH concludes that intakes were unlikely for the 

period 1997-2007. 

Plutonium

Whole-body counting is not an effective method of detecting intakes of plutonium at the levels 

of interest for internal dosimetry. Although some MDAs were located for the various systems, it 

was not until the addition of broad-energy germanium detectors to the stand-up whole-body 

counter in 2004 that in vivo counting could detect reasonably low levels of plutonium indirectly 

by counting Pu-241’s daughter, Am-241, in a chest-counting configuration. Therefore, NIOSH 

concludes that, for most of the site’s post-1979 history, doses from plutonium cannot be bounded 

by whole- body counts. 

 The lack of plutonium urinalysis results recovered for 1972-1999 is an indication that there was 

probably very little plutonium research in this time frame. Therefore, NIOSH concludes that 

plutonium intakes were unlikely for the period 1972-1999. As some of the site’s older facilities 

have undergone D&D starting in 2000, D&D workers were sampled for Pu-238, Pu-239, and 

Pu-240 (ORAUT-TKBS-0048). After 2000, urine results are available electronically and have 

been captured. Therefore, NIOSH concludes that, after January 1, 1980, sufficient monitoring 

data and dose reconstruction methods are available to bound plutonium dose at BNL. 

Americium

Whole-body counting with NaI detectors or high-purity germanium detectors is not an effective 

method of detecting intakes of americium at the levels of interest for internal dosimetry. It was 

not until the addition of broad-energy germanium detectors to the stand-up whole-body counter 

in 2004 that in vivo counting could detect reasonably low levels of Am-241 in a chest-counting 

configuration. Therefore, NIOSH concludes that, for most of the site’s post-1979 history, doses 

from americium cannot be bounded by whole- body counts. 

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As some of the site’s older facilities have undergone D&D starting in 2000, D&D workers were 

sampled for Am-241 (ORAUT-TKBS-0048). After 2000, urine results are available 

electronically and have been captured. Therefore, NIOSH concludes that, after January, 1980, 

sufficient monitoring data and dose reconstruction methods are available to bound americium 

dose at BNL. 

Polonium

Whole-body counting cannot be used to detect or bound the doses to polonium. 

NIOSH has determined that polonium intakes after 1980 were unlikely. An inventory of 

dispersible radioactive material in 1997 indicated that only microcurie amounts were still on site 

(Flores, 1998). 

Incidents

Incidents often resulted in requests for special bioassays (see Section 5.2.3 for a summary of the 

incident-related data). In such cases, these bioassay results may be used to support bounding 

intake estimates for the exposure situations/conditions associated with the incidents using the 

internal dose reconstruction methods defined in the BNL TBD (ORAUT-TKBS-0048). 

7.2.4 Internal Dose Reconstruction Feasibility Conclusion 

Prior to January 1, 1980, the whole-body counts necessary to bound the doses from gammaemitters were frequently not performed as requested. In addition, the site’s system for filing 

results of WBCs and urinalyses was inconsistent, leading to uncertainty regarding the complete 

retention and availability of the monitoring records. NIOSH concludes in this evaluation that 

sufficient in vitro and in vivo bioassay data are available to support bounding internal dose for 

members of the proposed class for the period January 1, 1980 to December 31, 2007. 

7.3 Evaluation of Bounding External Radiation Doses at BNL 

The principal sources of external radiation doses for members of the proposed class were BNL 

particle accelerators, nuclear reactors, and laboratory facilities (ORAUT-TKBS-0048). Potential 

radiation exposure to workers included beta particles, X-rays and higher-energy photons, and a 

wide energy range of neutrons. 

The following subsections address the ability to bound external doses, methods for bounding 

doses, and the feasibility of external dose reconstruction. 

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7.3.1 Evaluation of Bounding Process-Related External Dose Data 

ATTRIBUTION: Section 7.3.1 and its related subsections were completed by Paul Ruhter, M. H. 

Chew & Associates, Inc. These conclusions were peer-reviewed by the individuals listed on the 

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

text. 

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

reconstructing the process-related external doses of members of the class under evaluation. 

7.3.1.1 Personnel Dosimetry Data

From the beginning of BNL operations, the measurement of radiation dose was an integral part 

of an extensive radiation safety monitoring program intended to assure worker protection. 

Portable radiation instruments, pocket ionization chambers, and personnel dosimeters were used 

to evaluate radiation fields, establish appropriate controls to minimize personnel exposures, and 

monitor and document personnel exposures. 

Phillips provides an extensive description of the film badge in use at BNL and its capabilities 

(Phillips, 1974). The BNL badge was adopted from the Martin Marietta badge used at Oak 

Ridge National Laboratory. As described in ORAU-TBKS-0048, BNL processed the film 

badges on site until 1985, at which time they began using a vendor-processed film badge. The 

DOE Laboratory Accreditation Program accredited a BNL TLD badge in 1995. In 1996, the 

film badge was replaced by the TLD badge; the TLDs were processed on site (Loesch, 1995). 

The film and TLD badges were designed to monitor all the radiations types anticipated to exist at 

BNL (i.e., photon, beta, and neutron). 

Attachment 2 presents radiation exposure data was submitted annually to the AEC/ERDA/DOE, 

as required. These data were collected from the Annual Reports available on the DOE REMS 

website (from 1974 to 2007), and from similar annual reports found among BNL records (prior 

to 1974) (AEC, 1970; AEC, 1972; AEC, 1973; Annual Report, 1961; WBC Summary, 1960; 

WBC Summary, 1964; Whole-Body Results, 1965-1969). The data show the dose distribution in 

the worker population, indicating the maximum exposure measured each year as well as the 

average exposure received by the workers with measureable exposure. 

Photon

Personnel exposure monitoring data were kept on a separate card for each employee for each 

year (Cowan, 1964b). As indicated in ORAUT-TKBS-0048, the radiation exposure assigned to 

each monitored worker was recorded in this fashion until 1995. From 1996 to the present, 

radiation exposure records have been kept on the Health Physics Record System (HPRS), a 

computerized database. These records are available, and when adjusted for missed dose and the 

dosimeter uncertainty correction factor (as defined in ORAUT-TKBS-0048), represent an 

adequate basis for bounding BNL radiation exposures. Numerous “termination” reports or dose 

histories can be found in the documents obtained from BNL. In particular, two of these dose 

histories demonstrate the ability to assemble dose histories in 1981 and 1992 that stretched back 

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throughout the history of BNL (Dosimetry History, 1949-1981; Dosimetry History, 1962-1992). 

External radiation exposure was monitored and the data were collected in a retrievable manner. 

Although a large fraction of the worker population was monitored for external radiation 

exposure, there clearly was a portion unmonitored. This is to be expected because some portions 

of the BNL staff would have been assigned to work in areas not associated with radioactive 

materials or radiation areas, and therefore, they would not have been required to be monitored. 

The annual statistics for external exposures are presented in Attachment 2. 

As of August 11, 2009, 64 EEOICPA claims meeting the class definition under evaluation had 

been returned from DOE with supporting information. For 43 of those 64 claims, DOE has 

provided external dose data that essentially cover the period(s) of employment specified by the 

claimants. Consequently, when compared with the data being provided by DOE, the number of 

employees with and without external exposure information appears consistent with the historical 

number of employees who were monitored and unmonitored. 

As discussed in ORAUT-TKBS-0048, it also appears that all workers were issued dosimeters 

from start-up through 1954. However, after 1954, it was the policy that employees who were 

unlikely to exceed 10% of the annual limit (later, exceed 100 mrem/y), or who did not enter 

radiation areas, were not monitored. Based on this information, NIOSH concludes that the 

external photon dose for unmonitored individuals is bounded by the maximum exposure scenario 

represented by the monitored workers. ORAUT-TKBS-0048 contains the applicable monitored 

and unmonitored worker dose reconstruction methodology applicable to the completion of 

individual claims for the BNL site. 

Based on the information available on the BNL monitoring program and the available 

monitoring data, NIOSH concludes that sufficient data are available to bound photon doses for 

the class under evaluation. 

Beta

The preceding general discussion about personnel dosimetry and record-keeping applies equally 

well to the beta component of the dosimeter data. The beta dosimeters used throughout BNL 

history were sensitive to, and calibrated to, beta energies likely to be encountered at BNL. 

Extremity and wrist dosimeters were also used when it was deemed appropriate due to the 

radiation fields in the working environment. On occasion, special dosimeters were worn to 

monitor non-routine work that resulted in “significantly non-uniform doses to various areas of 

the whole body” (Sengupta, 2000). The special dosimeters were worn without the regular 

dosimeter. The highest dose measured by any of the special dosimeters was the dose of record. 

All of these dosimeters would have recorded any exposure to beta radiations. Extremity and 

wrist badge results are also available and can be used to supplement the reported dosimeter skin 

dose, as applicable. 

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The monitoring records were retained and should be available in the employee files. The missed 

dose and bias/uncertainty factors described in ORAUT-TKBD-0048 should be applied. With 

these adjustments, the data available should be sufficient to establish a bounding beta/shallow 

dose estimate for the class under evaluation. 

Neutron

The preceding general discussion about personnel dosimetry and record-keeping applies equally 

well to the neutron dosimeter. The neutron doses were measured with NTA film from start-up 

through 1995, when it was replaced with the TLD. High-energy particles would create spallation 

products that would produce stars on the NTA film; the total number of prongs on the stars was 

counted, and the resulting dose, generally using 10 mrem/prong, was added to determine the total 

neutron dose. 

In addition, starting in the mid-1980s, CR-39 and Lexan were also used in neutron dosimetry. 

The use of CR-39 continued after 1995. The CR-39 and Lexan were analyzed by an outside 

vendor (Lexan, 1988). 

Numerous references attest to the appropriateness of the personnel neutron dosimetry used at 

BNL. Cowan discussed the adequacy of the dosimeter to radiation fields encountered at the 

AGS and concluded it was “fail safe” for the radiations typically found at the accelerators 

(Cowan, 1964a). Throughout BNL history, the evaluation of the film always assumed a QF or 

RBE of 10. The NTA film was known by BNL to under-respond to the low-energy neutrons that 

would have been more prevalent at the reactors; this was the best available technology at the 

time. The Cd-shielded portion of the film badge was also used as an indication of low-energy 

neutron exposures. The correction factors provided in ORAUT-TKBS-0048, Table 6-7, 

appropriately account for this known under-response. The dosimetry in place in the mid-90s and 

later successfully passed the DOELAP Performance Tests, demonstrating its adequacy for 

personnel monitoring applications. 

Unmonitored workers were those who would not have been assigned to work in posted radiation 

areas. Neutrons do not constitute a significant exposure source in the natural environment; a 

source is required to generate neutrons, be it a radioactive source, an accelerator, or a reactor. 

Since these sources were normally well-controlled at BNL (i.e., inside posted radiological 

control areas), the unmonitored worker would not have been exposed to neutron sources or 

received neutron exposures. Consequently, neutron exposures are not applicable for 

unmonitored workers. 

NIOSH’s review of the available dosimetry data identified some gaps in the neutron exposure 

records for some monitored workers. An internal audit of radiation surveys at the Physics 

Department noted that the NTA film was always "processed," but only "read" (the laborintensive part of the process) if: (a) the beta-gamma dose was >100 mrem; (b) the Cd area 

indicated a thermal neutron exposure; or (c) the individual was on the special list (based on 

neutron exposure potential) prepared by an area HP (Gollon, 1982). The auditor noted that only 

half a dozen personnel out of 32 actually had neutron doses in the two previous years. Based on 

NIOSH’s reviews, the criteria used at BNL seem reasonable considering the common dosimetry 

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practices for the time period under evaluation. For the purpose assessing these data gaps in 

support of bounding neutron doses for applicable members of the class under evaluation, gaps in 

monitoring records can be assessed as “zero” dose results rather than unmonitored periods. 

The monitoring records were retained and are available in the employee files based on DOEprovided records for claims. The missed dose and bias/uncertainty factors described in ORAUTKBD-0048 should be applied. With these adjustments, the available data should be sufficient 

to establish a bounding neutron dose estimate for the class under evaluation. 

7.3.1.2 Area Monitoring Data

Area monitoring results have been discovered in the BNL data capture process. However, the 

available documents do not cover all facilities for all time frames. The ready availability of 

personnel monitoring data obviates the need for area monitoring data. 

7.3.2 Evaluation of Bounding Ambient Environmental External Doses 

ATTRIBUTION: Section 7.3.2 and its related subsections were completed by Paul Ruhter, M. H. 

Chew & Associates, Inc. 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. 

ORAUT-TKBS-0048 provides a discussion and method for evaluating the Ambient 

Environmental External Dose at BNL. This information is sufficient for evaluating potential 

external dose in the case of dose reconstruction for unmonitored workers. However, for the 

purpose of the bounding assessment in this evaluation, NIOSH concludes that the ambient 

environmental dose is included in the available dosimetry data, which represent the bounding 

external exposure scenario for the BNL class under evaluation. Therefore, further assessment of 

the ambient environmental dose is not included in this report. 

7.3.3 BNL Occupational X-Ray Examinations 

The frequency of required X-ray examinations differed over the years. This information should 

be in the individual worker file provided by DOE along with notations regarding both the date 

and the purpose of the exam. BNL records also will indicate the exam view (ORAUT-TKBS0048). 

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7.3.4 Methods for Bounding External Dose at BNL 

ATTRIBUTION: Section 7.3.4 and its related subsections were completed by Paul Ruhter, M. H. 

Chew & Associates, Inc. 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. 

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

Photon Dose

Photon doses for monitored workers have been measured with sensitive dosimeters throughout 

BNL’s history (see Section 7.3.1.1). BNL workers were required to wear film badges when 

entering a “radiation area” and to have a neutron film in that badge when a neutron exposure was 

possible (Personnel Monitoring, 1948). The resultant monitoring data have been retained over 

the entire course of the class period. With the methods described in ORAUT-TKBS-0048, 

including the missed dose and bias corrections, these data permit adequate estimation of 

bounding photon doses for the class under evaluation. 

Beta Dose

As with photon doses, beta (electron) doses for monitored workers have also been measured with 

sensitive dosimeters throughout BNL’s history (see Section 7.3.1.1). The monitoring data have 

been retained over the entire duration of the class under evaluation. With the methods described 

in ORAUT-TKBS-0048, including the missed dose and bias corrections, these data permit 

estimation of bounding photon doses for the NIOSH-evaluated class. 

Neutron Dose

The dosimetry used to monitor neutron exposures reflected the state-of-the-art technology 

available during BNL operations. The limitations were known and discussed in the documents 

collected at BNL. ORAUT-TKBS-0048 provides correction factors that make appropriate 

adjustments for these limitations. The monitoring data are available for the monitored workers. 

Neutron exposures should not be included for unmonitored workers. 

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Medical X-ray Dose

The Medical records discussed in Section 7.3.3 are being made available through the claims 

process, and therefore, should be sufficient to provide a bounding estimate of any doses 

associated with medical X-ray procedures. ORAUT-OTIB-006, Dose Reconstruction from 

Occupational Related Diagnostic X-Ray Procedures, provides a bounding approach for those 

individuals for whom no Medical Records are available. 

7.3.5 External Dose Reconstruction Feasibility Conclusion 

The data sources for photon, beta, and neutron doses, as well as occupational X-ray examinations 

and ambient environmental external doses, have been examined and found to be adequate for 

bounding external doses for monitored BNL workers. The assessment of doses for unmonitored 

workers can be determined from the ambient environmental external dose methods defined in 

ORAUT-TKBS-0048. Based on NIOSH’s assessment of the available external data and the dose 

calculation methods available in ORAUT-TKBS-0048, NIOSH concludes that it is feasible to 

bound external dose for the class under evaluation. 

7.4 Evaluation of Petition Basis for SEC-00113 

ATTRIBUTION: Section 7.4 and its related subsections were completed by Tim Adler, Oak Ridge 

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

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

text. 

The following subsections evaluate the assertions made on behalf of petition SEC-00113 for the 

Brookhaven National Laboratory. 

7.4.1 No or Insufficient Internal Monitoring 

SEC-00113: To the best of my knowledge there was no internal monitoring for some individuals 

at Brookhaven National Laboratory and insufficient internal monitoring for the class in the early 

1980’s. 

NIOSH has identified information to corroborate the petitioner claim that for some members of 

the class under evaluation, neither personnel nor area monitoring was performed. It is expected 

that no internal monitoring would be necessary for work assignments with no internal exposure 

potential. Strong evidence exists that members of the evaluated class who performed work with 

internal exposure potential were monitored appropriately and a portion of the resultant data has 

been captured. Though it is evident that internal monitoring was performed as necessary for the 

class under evaluation, there is uncertainty regarding the complete retention and availability of 

radiation monitoring records necessary to bound doses prior to 1980. 

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7.4.2 Badge Overexposure Incident 

SEC-00113: ...was involved in an incident during that time. He came home one day to tell me 

that a person inspecting the badges wanted to know where he had been because his badge was 

overexposed. He mentioned that during one of the experiments on the equipment he maintained, 

the warning light system indicating a radioactive area had not been activated and he was in the 

area repairing some malfunction. He also mentioned that the equipment that he (was) repairing 

was still “hot.” 

NIOSH obtained and reviewed the claimant’s monitoring records, but was unable to locate any 

records that indicated an overexposure. The available records show that the claimant was 

consistently monitored for external radiation for the duration of his employment at BNL. There 

are no gaps evident in the available monitoring record. Additionally, all external monitoring 

results were very low, usually below detection limits. 

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7.5 Summary of Feasibility Findings for Petition SEC-00113 

This report evaluates the feasibility for completing dose reconstructions for employees at the 

Brookhaven National Laboratory from January 1947 through December 2007. NIOSH found 

that the available monitoring records, process descriptions and source term data available are 

sufficient to complete dose reconstructions for a portion of the evaluated class of employees. 

Table 7-4 summarizes the results of the feasibility findings at Brookhaven National Laboratory 

for each exposure source during the time period January 1947 through December 2007. 

Table 7-4: Summary of Feasibility Findings for SEC-00113 

January 1, 1947 through December 31, 2007 

Source of Exposure Reconstruction Feasible Reconstruction Not Feasible 

Internal1 X2

H-3 X (1/1/1965-12/31/2007) X (1/1/1947-12/31/1964) 

Mixed Fission Products (MFP) 

and Mixed Activation Products 

(MAP) 

X (1/1/1980-12/31/2007) X (1/1/1947-12/31/1979) 

Th-232 X (1/1/1980-12/31/2007) X (1/1/1947-12/31/1979) 

Uranium X (1/1/1980-12/31/2007) X (1/1/1947-12/31/1979) 

Plutonium X (1/1/1980-12/31/2007) X (1/1/1947-12/31/1979) 

Am-241 X (1/1/1980-12/31/2007) X (1/1/1947-12/31/1979) 

Po-210 X (1/1/1980-12/31/2007) X (1/1/1947-12/31/1979) 

Other X (1/1/1980-12/31/2007) X (1/1/1947-12/31/1979) 

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 whole-body count data (in vivo). 

PARTIAL DOSE RECONSTRUCTION INFORMATION: 

2

 INTERNAL: NIOSH will make use of any available internal monitoring data (that can be interpreted/evaluated 

using existing TBD methodologies) to support partial DRs from 1947 through 1979 for claims with 

non-presumptive cancers and those with less than 250-days of employment. 

As of August 11, 2009, a total of 92 claims have been submitted to NIOSH for individuals who 

worked at BNL and are covered by the class definition evaluated in this report. DOE has not yet 

responded with BNL data to 28 of these claims. Dose reconstructions have been completed for 

28 of the 64 individuals for which BNL response is available (44%). 

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8.0 Evaluation of Health Endangerment for Petition SEC-00113 

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. 

NIOSH has determined that there is uncertainty with regards to the retention and retrievability of 

BNL internal monitoring data prior to January 1, 1980. NIOSH’s evaluation determined, 

therefore, that it is not feasible to estimate radiation dose with sufficient accuracy for members of 

the NIOSH-evaluated class employed before January 1, 1980 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 required. 

9.0 Class Conclusion for Petition SEC-00113 

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

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The 

NIOSH-proposed class to be added to the SEC includes all employees of the Department of 

Energy, its predecessor agencies, and its contractors and subcontractors who worked at 

Brookhaven National Laboratory in Upton, New York, from January 1, 1947 to December 31, 

1979, for a number of work days aggregating at least 250 work days, occurring either solely 

under this employment, or in combination with work days within the parameters established for 

one or more other classes of employees in the Special Exposure Cohort. The class under 

evaluation was reduced because of data retention and retrievability uncertainties prior to 1980. 

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-00113. In addition, NIOSH reviewed its 

NOCTS dose reconstruction database to identify EEOICPA-related dose reconstructions that 

might provide information relevant to the petition evaluation. 

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These actions are based on existing, approved NIOSH processes used in dose reconstruction for 

claims under EEOICPA. NIOSH’s guiding principle in conducting these dose reconstructions is 

to ensure that the assumptions used are fair, consistent, and well-grounded in the best available 

science. Simultaneously, uncertainties in the science and data must be handled to the advantage, 

rather than to the detriment, of the petitioners. When adequate personal dose monitoring 

information is not available, or is very limited, NIOSH may use the highest reasonably possible 

radiation dose, based on reliable science, documented experience, and relevant data to determine 

the feasibility of reconstructing the dose of an SEC petition class. NIOSH contends that it has 

complied with these standards of performance in determining the feasibility or infeasibility of 

reconstructing dose for the class under evaluation. 

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10.0 References 

42 C.F.R. pt. 81, Guidelines for Determining the Probability of Causation Under the Energy 

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

Register/Vol. 67, No. 85/Thursday, p 22,296; May 2, 2002; SRDB Ref ID: 19391 

42 C.F.R. pt. 82, Methods for Radiation Dose Reconstruction Under the Energy Employees 

Occupational Illness Compensation Program Act of 2000; Final Rule; May 2, 2002; SRDB Ref 

ID: 19392 

42 C.F.R. pt. 83, Procedures for Designating Classes of Employees as Members of the Special 

Exposure Cohort Under the Energy Employees Occupational Illness Compensation Program Act 

of 2000; Final Rule; May 28, 2004; SRDB Ref ID: 22001 

42 U.S.C. §§ 7384-7385 [EEOICPA], Energy Employees Occupational Illness Compensation 

Program Act of 2000, as amended 

AEC, 1963, Division of Inspection Report; United States Atomic Energy Commission (AEC); 

April 11, 1963; SRDB Ref ID: 9714 

AEC, 1970, 1970 Whole-Body Radiation Exposure Summaries, various sites; Atomic Energy 

Commission (AEC); 1970; SRDB Ref ID: 13801 

AEC, 1972, 1972 Whole-Body Radiation Exposure Summaries, various sites; Atomic Energy 

Commission (AEC); 1972; SRDB Ref ID: 13802 

AEC, 1973, 1973 Whole-Body Radiation Exposure Summaries, various sites; Atomic Energy 

Commission (AEC); 1973; SRDB Ref ID: 13803 

AGS Exposure, 1980, Report of High Film Badge Exposure by Ad Hoc Radiation Investigating 

Committee Appointed by Accelerator Department, Brookhaven National Laboratory; August 28, 

1980; SRDB Ref ID: 50822 

Annual Report, 1961, Annual Report of External Radiation Exposures, from Brookhaven 

National Laboratory to the U.S. Atomic Energy Commission, New York Operations Office; data 

for 1961 reported January 30, 1962; SRDB Ref ID: 13789, pdf p. 32 

Atkins, 1974, Iodine-125 Body Burdens, correspondence to Dr. Cronkite; H. L. Atkins; October 

30, 1974; SRDB Ref ID: 53445 

Bellows, 1990, Investigation Report of the March 1990 High Flux Beam Reactor (HFBR) 

Contamination Incident at the Brookhaven National Laboratory (BNL), letter to N. P. Samios 

(BNL) from J. L. Bellows (DOE); U. S. Department of Energy; July 25, 1990; SRDB Ref ID: 

49952 

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Bergin, 1956, Airborne Contamination at the Hot Laundry, correspondence; Bergin; May 11, 

1956; SRDB Ref ID: 55640 

BGRR History, 1997, Historical Overview: Brookhaven Graphite Research Reactor (BGRR) 

Fuel Operations, Accountability, and Reporting, G. Shepherd; Brookhaven National Laboratory; 

October 28, 1997; SRDB Ref ID: 55624 

BNL, 1947, Proposed Precautionary Measures Against Laboratory Contamination; Brookhaven 

National Laboratory (BNL); 1947; SRDB Ref ID: 50599 

BNL, 1948; Procedures Covering the Handling of S/F Materials and S/F Accountability Records 

for Brookhaven National Laboratory; Brookhaven National Laboratory (BNL); November 3, 

1948; SRDB Ref ID: 55674 

BNL, October 1957, Nuclear Engineering Department LMFR Report for October 1957; 

Brookhaven National Laboratory (BNL) Nuclear Engineering Department; October 28, 1957; 

SRDB Ref ID: 55443 

BNL, December 1957, Nuclear Engineering Department Monthly Progress Letter for December 

1957; Brookhaven National Laboratory (BNL) Nuclear Engineering Department; December 26, 

1957; SRDB Ref ID: 55439 

BNL, 1958-1959, Medical and Injury Records for [Name Redacted], dates range from 

September 23, 1958 through July 11, 1959; SRDB Ref ID: 53316 

BNL, 1960-1966, Organization Charts for the Health Physics Division of Brookhaven National 

Laboratory; Brookhaven National Laboratory (BNL); June 1960-May 1966; SRDB Ref ID: 

55654 

BNL, 1969, Appendix E on Radiation Safety for Particle Accelerators; Brookhaven National 

Laboratory (BNL); October 1969; SRDB Ref ID: 53902 

BNL, 1990-1991a, Workplace Airborne Activity Correspondence and Results; Brookhaven 

National Laboratory (BNL); September 1990 through October 23, 1991; SRDB Ref ID: 50534 

BNL, 1990-1991b, Workplace Radioactive Air Monitoring Correspondence and Results; 

Brookhaven National Laboratory (BNL); September 1990 through October 4, 1991; SRDB Ref 

ID: 50536 

BNL, 1991, Reactor Division Whole-Body Counting Policy and Corrective Action Plans; 

Brookhaven National Laboratory (BNL); December 31, 1991; SRDB Ref ID: 55347 

BNL, 1992a, 1992 HFBR Whole-Body Count Request; Brookhaven National Laboratory (BNL); 

1992; SRDB Ref ID: 55353 

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BNL, 1992b, 1992 HFBR Whole-Body Count Request; Brookhaven National Laboratory (BNL); 

1992; SRDB Ref ID: 55396 

BNL, 1992c, 1992 HFBR Whole-Body Count Request; Brookhaven National Laboratory (BNL); 

1992; SRDB Ref ID: 55397 

BNL, 1995, Radiological Control Manual: Chapter 5, Radiological Health Support Operations, 

Brookhaven National Laboratory (BNL); November 20, 1995; SRDB Ref ID: 22455 

BNL, July-December 1999, Tritium Dose to HFBR Personnel; Brookhaven National Laboratory 

(BNL); July-December 1999; SRDB Ref ID: 22425 

Bond, 1973, Report of a Type C Occurrence Radiation Exposure, letter to J. P. Jewett (AEC) 

from V. P. Bond (BNL); Brookhaven National Laboratory; April 13, 1973; SRDB Ref ID: 55420 

Breslin, 1961, Monthly Occupational Health Survey-BNL; A. J. Breslin; December 8, 1961; 

SRDB Ref ID: 6517, pp. 66-67 

Breslin, 1962a, Monthly Occupational Health Survey-BNL; A. J. Breslin; January 31, 1962; 

SRDB Ref ID: 6517, pp. 68-69 

Breslin, 1962b, Monthly BNL Surveys-March 28, 29 and May 2, 3, 1962; A. J. Breslin; May 31, 

1962; SRDB Ref ID: 6517, pp. 71-74 

Bubble Chamber, 1973, Monthly Report – September 1973, memorandum to C. B. Meinhold 

from W. R. Casey; Brookhaven National Laboratory; October 10, 1973; SRDB Ref ID: 55414, 

pdf p. 12 

Carter, 1976, List of Personnel Needing Thyroid Scans; E. N. Carter; July 16, 1976; SRDB Ref 

ID: 55151 

Cohn, 1969, Radiation Exposure Accident, memorandum to C. Distenfeld from S. H. Cohn; 

Brookhaven National Laboratory; January 13, 1969; SRDB Ref ID: 6726 

Cohn, 1980, Response to Memo of August 27 Concerning Biomedical Whole-Body Counter, 

correspondence to R. Miltenberger; September 4, 1980; SRDB Ref ID: 55220 

Colsmann, 1949, Sr 90 “Spill” at T-527, memorandum to M. Fox from P. Colsmann; 

Brookhaven National Laboratory; December 12, 1949; SRDB Ref ID: 50608 

Cowan, 1947, Alpha Contamination of the Graphite Lab, correspondence to Lyle Berst; F. P. 

Cowan; August 22, 1947; SRDB Ref ID: 55361 

Cowan, 1948, Material for Six Month Progress Report of December 31, 1948, correspondence to 

J. B. H. Kuper; F. P. Cowan; December 27, 1948; SRDB Ref ID: 50610 

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Cowan, 1949, Draft of Love-Cowan Report to Radiation Safety Committee, correspondence to J. 

B. H. Kuper; F. P. Cowan; October 26, 1949; SRDB Ref ID: 50607 

Cowan, 1952, Health Physics and Medical Aspects of a Strontium-90 Inhalation Incident; 

Frederick P. Cowan, Lawrence B. Farabee, and Robert A. Love; May 1952; SRDB Ref ID: 

22543 

Cowan, 1953, Health Physics Program for the Brookhaven Cosmotron, F. P. Cowan and J. S. 

Handloser; BNL-264 CT-43; November 1953; SRDB Ref ID: 22516 

Cowan, 1961, Evaluation of Polonium Body Burden, correspondence; F. P. Cowan; January 11, 

1961; SRDB Ref ID: 53763 

Cowan, 1964a, Some Dosimetry Problems of the Alternating Gradient Synchrotron (AGS), F. P. 

Cowan, L. F. Phillips, and R. J. King; Health Physics Journal, Vol. 10, pp. 33-40; February 1964; 

SRDB Ref ID: 22492 

Cowan, 1964b, Minutes of Meeting Held at Brookhaven National Laboratory; transcribed by Dr. 

F. Cowan; June 27, 1964; SRDB Ref ID: 17344 

Cowan, 1968, Whole-Body Counting, correspondence to Area Health Physicists; F. P. Cowan; 

July 25, 1968; SRDB Ref ID: 53966 

Cowan, unknown date, Health Physics Program for the Brookhaven National Laboratory 

Synchrotrons, F. P. Cowan; unknown date; SRDB Ref ID: 22490 

Data Package, 2001, Brookhaven Data Package, Eberline Services, Albuquerque Laboratory; 

September 4, 2001; SRDB Ref ID: 22476 

Davis, 1970, Two Month Report, correspondence to C. Distenfeld; J. Davis; September 11, 1970; 

SRDB Ref ID: 53877 

Distenfeld, 1962, Exposure Incident of October 30, 1962, correspondence; C. Distenfeld, D. 

Clark, and F. P. Cowan; November 6 & 8, 1962; SRDB Ref ID: 53768 

DOE, 1990, March 1990 Contamination Incident Investigation Report of High Flux Beam 

Reactor (HFBR) Brookhaven National Laboratory (BNL); Department of Energy (DOE) 

Brookhaven Area Office; July 25, 1990; SRDB Ref ID: 49952 

DOE, 1996, Highly Enriched Uranium Working Group Report on Environmental, Safety, and 

Health (ES&H) Vulnerabilities Associated with the Department’s Storage of Highly Enriched 

Uranium, DOE/EH-0525; Department of Energy (DOE); September 1996; SRDB Ref ID: 22030 

Dose Report, April 1992, Radiation Dosimetry Report for Exposure Period from April 1, 1992 

through April 31, 1992; SRDB Ref ID: 55346 

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Dose Report, July 1995, Summary Dose Reports for Period of Interest: July 1-July 31, 1995; 

SRDB Ref ID: 55298 

Dosimetry History, 1949-1981, Dosimetry Exposure Record of [name redacted], BNL, [number 

redacted], Brookhaven National Laboratory, December 23, 1981; SRDB Ref ID: 53593 

Dosimetry History, 1962-1992, Exposure History Report for [name redacted], BNL Life [number 

redacted], Brookhaven National Laboratory, May 24, 1993; SRDB Ref ID: 50583 

ERDA, 1977, Final Environmental Impact Statement for Brookhaven National Laboratory in 

Upton, New York, ERDA-1540 UC-2, 11; Energy Research & Development Administration 

(ERDA); July 1977; SRDB Ref ID: 6384 

Exposure Summaries, August-December 1992, Exposure Summaries from August 1992 through 

December 1992; SRDB Ref ID: 55351 

Exposure Summaries, October 1992, Exposure Summary for October 1992; SRDB Ref ID: 

55345 

Exposure Summaries, January 1993, Exposure Summary for January 1993; SRDB Ref ID: 

55400 

Exposure Summaries, February 1993, Exposure Summary for February 1993; SRDB Ref ID: 

55401 

Exposure Summaries, August 1993, Exposure Summary for August 1993; SRDB Ref ID: 55447 

Exposure Summaries, September 1993, Exposure Summary for September 1993; SRDB Ref ID: 

55444 

Exposure Summaries, October 1993, Exposure Summary for October 1993; SRDB Ref ID: 

55449 

Exposure Summaries, 1994, Exposure Summaries from January 1994 through December 1994; 

SRDB Ref ID: 55285 

Exposure Summaries, November 1994, Exposure Summary for November 1994; SRDB Ref ID: 

55287 

Exposure Summaries, 1995, Exposure Summaries from January 1995 through December 1995; 

SRDB Ref ID: 55284 

Exposure Summaries, January-September 1995, Exposure Summaries from January 1995 

through September 1995; SRDB Ref ID: 55286 

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Exposure Summaries, 1996, Exposure Summaries from January 1996 through December 1996; 

SRDB Ref ID: 55283 

Exposure Summaries, 1997, Exposure Summaries from January 1997 through December 1997; 

SRDB Ref ID: 55282 

Exposure Summaries, January-November 1998, Exposure Summaries from January 1998 

through November 1998; SRDB Ref ID: 55281 

Exposure Summaries, 1998-1999, Exposure Summaries from January 1998 through August 

1999; SRDB Ref ID: 55280 

Film Badges, 1952, Required Use of Film Badges in T-197, memorandum from C. Williams to 

Personnel in T-197; Brookhaven National Laboratory; June 12, 1952; SRDB Ref ID: 50598, pdf 

p. 9 

Fire, 1994, Monthly Report – March 1994, memorandum to C. Flood and R. Miltenberger from 

R. Reciniello; Brookhaven National Laboratory; April 11, 1994; SRDB Ref ID: 50647, pdf p. 4 

Flood, 1967, Tritium Exposure at Medical, correspondence to L. Gemmell; C. Flood; April 4, 

1967; SRDB Ref ID: 50933 pdf p. 3 

Flood, 1972, Contaminated Oil at 3.5 MeV Van de Graaff, correspondence to J. Weneser; C. 

Flood; April 4, 1972; SRDB Ref ID: 53529 

Flood, 1978, Ad Hoc Investigation Committee Report; C. Flood, R. Fairchild, and J. Glenn; June 

21, 1978; SRDB Ref ID: 53502 

Flood, 1982, Radiation Safety Systems at Brookhaven National Laboratory’s Low-Energy 

Accelerators; Charles W. Flood, Jr., Safety & Environmental Protection Division of Brookhaven 

National Laboratory; 1982; SRDB Ref ID: 22488 

Flores, 1998, Dispersible Radioactive Material Inventory, correspondence to Department Chairs; 

E. A. Flores; December 22, 1998; SRDB Ref ID: 53365 

Fox, 1950, Revised Manual on Procedures and Facilities for Handling S/F Materials, 

correspondence to Department Heads; M. Fox; May 8, 1950; SRDB Ref ID: 55665 

Gemmell, 1952, Overexposure Investigation – J. Tritchler, memorandum from L. Gemmell and 

F. P. Cowan to the File; October 30, 1952; SRDB Ref ID: 50596 

Gemmell, 1967, Tritium Exposures to Medical Dept. Personnel, correspondence to V. P. Bond; 

April 5, 1967; SRDB Ref ID: 50933, pdf pp. 3 

Gollon, 1982, Audit of Radiation Surveys at Physics Department, P. J. Gollon; March, 1982; 

SRDB Ref ID: 55231 

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Haworth, 1960, August 2, 1960 Alpha Contamination Incident, correspondence to E. L. Van 

Horn; Leland J. Haworth; September 29, 1960; SRDB Ref ID: 6271 

Hayes, 1947, Brookhaven film badge results with cover memos from J. R. Hayes (University of 

Rochester, Atomic Energy Project) to Brookhaven; various dates in September 1947; SRDB Ref 

ID: 17343 

Hayner, 1947, Polonium-Beryllium Source, correspondence to T. S. Chapman from J. H. Hayner; 

April 28, 1947; SRDB Ref ID: 6283, pdf p. 19 

Holeman, 1999, Radiation Dosimetry Program, Brookhaven National Laboratory, Personnel 

Monitoring Group; March 24, 1999; SRDB Ref ID: 22477 

Hot Lab, 1962, Hot Lab Report for December 1961, memorandum to L. Gemmell from C. 

Foelix; Brookhaven National Laboratory; January 4, 1962; SRDB Ref ID: 53470, pdf p. 2 

HP Procedures, 1948, General Health Physics Procedures, memorandum from F.P. Cowan to 

Members Radiation Safety Committee; Brookhaven National Laboratory; February 18, 1948; 

SRDB Ref ID: 50635 

HP Summary, September 1948, Health Physics Summary for September 1948; Brookhaven 

National Laboratory (BNL); September 1948; SRDB Ref ID: 55454, pdf pp. 15-17 

HP Summary, March 1949, Health Physics and Safety Summary for March 1949; Brookhaven 

National Laboratory (BNL); March 1949; SRDB Ref ID: 55453, pdf p. 31 

HP Summary, May 1949, Health Physics Summary for May 1949; Brookhaven National 

Laboratory (BNL); May 1949; SRDB Ref ID: 55453, pdf pp. 23 

HP Summary, October 1949, Health Physics Summary for October 1949; Brookhaven National 

Laboratory (BNL); October 1949; SRDB Ref ID: 55453, pdf p. 7 

HP Summary, 1950, Health Physics and Safety Summaries for 1950; Brookhaven National 

Laboratory; January-December 1950; SRDB Ref ID: 55452 

HP Summary, June 1951, Health Physics Monthly Summary for June 1951; Brookhaven 

National Laboratory (BNL); June 1951; SRDB Ref ID: 54003 

HP Summary, November 1951, Health Physics Summary for November 1951; Brookhaven 

National Laboratory (BNL); November 1951; SRDB Ref ID: 22848, pp. 4-7 

HP Summary, December 1954, Health Physics Summary for December 1954; Brookhaven 

National Laboratory (BNL); December 1954; SRDB Ref ID: 55476, pdf p. 2 

HP Summary, February 1959, Health Physics and Safety Summary for February 1959; 

Brookhaven National Laboratory (BNL); February 1959; SRDB Ref ID: 55502, pdf p. 32 

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HP Summary, May 1959, Health Physics and Safety Summary for May 1959; Brookhaven 

National Laboratory (BNL); May 1959; SRDB Ref ID: 55502, pdf p. 22 

HP Summary, October 1959, Health Physics and Safety Summary for October 1959; Brookhaven 

National Laboratory (BNL); October 1959; SRDB Ref ID: 55502, pdf p. 11 

HP Summary, November 1959, Health Physics and Safety Summary for November 1959; 

Brookhaven National Laboratory (BNL); November 1959; SRDB Ref ID: 55502, pdf p. 7 

HP Summary, January 1961, Health Physics and Safety Summary for January 1961; Brookhaven 

National Laboratory (BNL); January 1961; SRDB Ref ID: 55494, pdf p. 33 

HP Summary, February 1962, Health Physics and Safety Summary for February 1962; 

Brookhaven National Laboratory (BNL); February 1962; SRDB Ref ID: 55493, pdf p. 35 

HP Summary, October 1964, Health Physics and Safety Summary for October 1964; Brookhaven 

National Laboratory (BNL); October 1964; SRDB Ref ID: 55601, pdf p. 10 

HP Summary, April 1965, Health Physics and Safety Summary for April 1965; Brookhaven 

National Laboratory (BNL); April 1965; SRDB Ref ID: 55600, pdf p. 30 

HP Summary, June 1965, Health Physics and Safety Summary for June 1965; Brookhaven 

National Laboratory (BNL); June 1965; SRDB Ref ID: 55600, pdf p. 24 

HP Summary, January 1966, Health Physics and Safety Summary for January 1966; Brookhaven 

National Laboratory (BNL); January 1966; SRDB Ref ID: 55599, pdf p. 52 

HP Summary, March 1966, Health Physics and Safety Summary for March 1966; Brookhaven 

National Laboratory (BNL); March 1966; SRDB Ref ID: 55599, pdf p. 49 

HP Summary, May 1966, Health Physics and Safety Summary for May 1966; Brookhaven 

National Laboratory (BNL); May 1966; SRDB Ref ID: 55599, pdf p. 37 

HP Summary, February 1967, Health Physics and Safety Summary for February 1967; 

Brookhaven National Laboratory (BNL); February 1967; SRDB Ref ID: 55606, pdf p. 42 

HP Summary, April 1967, Health Physics and Safety Summary for April 1967; Brookhaven 

National Laboratory (BNL); April 1967; SRDB Ref ID: 55606, pdf p. 34 

HP Summary, April 1969, Health Physics and Safety Summary for April 1969; Brookhaven 

National Laboratory (BNL); April 1969; SRDB Ref ID: 55604, pdf p. 39 

HP Summary, October 1969, Health Physics and Safety Summary for October 1969; Brookhaven 

National Laboratory (BNL); October 1969; SRDB Ref ID: 55604, pd p. 9 

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HP Summary, February 1970, Health Physics and Safety Summary for February 1970; 

Brookhaven National Laboratory (BNL); February 1970; SRDB Ref ID: 53907, pdf p. 39-42 

HP Summary, June 1971, Health Physics and Safety Summary for June 1971; Brookhaven 

National Laboratory (BNL); June 1971; SRDB Ref ID: 55602, pdf p. 35 

HP Summary, September 1971, Health Physics and Safety Summary for September 1971; 

Brookhaven National Laboratory (BNL); September 1971; SRDB Ref ID: 55602, pdf p. 17 

HP Summary, October 1971, Health Physics and Safety Summary for October 1971; Brookhaven 

National Laboratory (BNL); October 1971; SRDB Ref ID: 55602, pp. 11 

Hull, 1977a, Assignment of Robert Miltenberger to Oversee Whole Body Counting Program, 

correspondence to R. G. Love; A. P. Hull; December 1, 1977; SRDB Ref ID: 55246 

Hull, 1977b, Whole-Body Counting, correspondence to R. G. Love from A. P. Hull; December 1, 

1977; SRDB Ref ID: 55246 

Hull, 1978, Institution of Routine Whole-Body Counting by Safety and Environmental Protection 

Division, correspondence to C. Meinhold; A. Hull; August 28, 1978; SRDB Ref ID: 55254 

Hull, 1979, Whole-Body Counting Program Review and Recommendations, correspondence to C. 

B. Meinhold; A. P. Hull; October 31, 1979; SRDB Ref ID: 55177 

Iodine, 1970s, Various documents related to iodine exposures and dose calculations, Brookhaven 

National Laboratory; various authors and dates in the 1970s; SRDB Ref ID: 48269 

Iodine Results, 1980s, Various whole body counting results showing the presence of iodine 

exposures, Brookhaven National Laboratory; various dates in the 1980s; SRDB Ref ID: 50416, 

pdf pp. 70-71, 73-77, 88-89, 108-112, 117-122, 137-138, and 142 

Keane, 1989, Report of the Investigation Committee on Radiation Incident in Building 820 at 

BNL, December 18, 1989, J. T. Keane (Chairman, Investigation Board); Brookhaven National 

Laboratory; date uncertain (1989 or 1990); SRDB Ref ID: 49938 

Lancaster, 1949, Request for Polonium-210, correspondence to E. B. Meservey from J. H. 

Lancaster; October 6, 1949; SRDB Ref ID: 45053, pdf p. 2 

Lazo, 1988a, Air Samples and Airborne Activity for Percussion Welding Pins into Uranium 

Plates, correspondence to John Taylor; Ted Lazo; June 23, 1988; SRDB Ref ID: 50626 

Lazo, 1988b, Urine Sample Bioassay Requirements at Building 1008, correspondence to N. 

Rohrig; T. Lazo; March 8, 1988; SRDB Ref ID: 50688 

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Lessard, 1980, Suspected Uptake of Fe-55, memorandum to T. Malinowski from E. T. Lessard, 

R. Miltenberger, and J. Steimers; Brookhaven National Laboratory; April 29, 1980; SRDB Ref 

ID: 59105 

Lessard, 1984a, 1983 Internal Exposure Summary, correspondence with results summary; E. 

Lessard; March 6, 1984; SRDB Ref ID: 53807 

Lessard, 1984b, Bioassay Results, memorandum to J. Roesler from E. Lessard and R. 

Miltenberger concerning an accident at the TRISTAN Facility; Brookhaven National Laboratory; 

November 16, 1984; SRDB Ref ID: 50894 

Lessard, 1986, Iodine-131 Spill at the Medical Research Center, correspondence to C. Meinhold; 

E. Lessard and E. Carter; May 9, 1986; SRDB Ref ID: 53653 

Lessard, 1987a, Urinary Sampling for Uranium, correspondence to C. Flood and J. Steimers; E. 

Lessard; May 14, 1987; SRDB Ref ID: 59099 

Lessard, 1987b, Sr-82 Exposure of [Name Redacted] at Building 801; E. T. Lessard and R. P. 

Miltenberger; April 14, 1987; SRDB Ref ID: 54013 

Lessard, 1987c, Annual Internal Radiation Exposure Summary for 1986, correspondence to C. J. 

Schopfer; E. T. Lessard; April 14, 1987; SRDB Ref ID: 54009 

Lessard, 1988, Department of Energy Appraisal of Health Physics: Develop Criteria for 

Selection of Personnel for Internal Monitoring, correspondence with attachments to N. Rohrig; 

E. T. Lessard; January 27, 1988; SRDB Ref ID: 54000 

Lessard, 2009, Brookhaven National Laboratory Accelerator Facilities Building 912, draft; E. T. 

Lessard; February 18, 2009; SRDB Ref ID: 60143 

Lexan, 1988, Lexan Control Neutron Badge Report, from Brookhaven National Laboratory to 

Landauer, Inc.; August 11, 1988; SRDB Ref ID: 55379 

Loesch, 1995, Laboratory Accreditation of Brookhaven National Laboratory (BNL) Personnel 

Dosimetry, letter from R. M. Loesch to C. L. Nealy (DOE/BAO); December 12, 1995; SRDB 

Ref ID: 22457 

Love, 1959, Work Regulations and Physical Exam Requirements for Reactor Work, 

correspondence to Theodore Fliedner; R. A. Love; September 25, 1959; SRDB Ref ID: 53618 

Love, 1962, Strontium-90 Uptake, correspondence; R. A. Love; October 3, 1962; SRDB Ref ID: 

53916 

Lukas, 1986, Annual Bioassay Program, correspondence to R. Miltenberger; A. E. Lukas; March 

3, 1986; SRDB Ref ID: 50619 

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Meinhold, 2001, Radiological Emissions and Environmental Monitoring for Brookhaven 

National Laboratory, 1947 – 1961, C. B. Meinhold and A. F. Meinhold; Brookhaven National 

Laboratory; May 2001; SRDB Ref ID: 6495 

Miltenberger, 1978a, U-235 Reference Material, correspondence to C. Flood; R. Miltenberger; 

October 12, 1978; SRDB Ref ID: 53973 

Miltenberger, 1978b, I-126 Release of May 16, 1978 from BLIF Facility, memorandum to File 

from R. Miltenberger; August 18, 1978; SRDB Ref ID: 48269, pdf p. 6 

Miltenberger, 1978c, Exposure of [Name Redacted] to Iodine-126 at Hot Lab, correspondence; 

R. Miltenberger; October 30, 1978; SRDB Ref ID: 55305 

Miltenberger, 1979, Whole-Body Counts for Two BNL Employees, correspondence to A. Lukas; 

R. Miltenberger; March 20, 1979; SRDB Ref ID: 55207 

Miltenberger, 1980a, Use of Medical Whole-Body Counter in Operational Bioassay Program for 

Brookhaven National Laboratory Employees, correspondence to S. Cohn; R. Miltenberger; 

August 27, 1980; SRDB Ref ID: 55221 

Miltenberger, 1980b, Iodine-125 Inhalation Exposure of [Name Redacted], correspondence to N. 

Carter; R. Miltenberger; January 16, 1980; SRDB Ref ID: 53446 

Miltenberger, 1987a, Whole-Body Counting Data Summary for BNL RAP Response to the 

Chernobyl Accident, correspondence with results; Robert Miltenberger; July 1, 1987; pp. 102-

123 

Miltenberger, 1987b, Whole-Body Counting Intercomparison Study Results, correspondence with 

results; Robert Miltenberger; October 16, 1987; SRDB Ref ID: 50416, pp. 35-46 

Miltenberger, 1987c, Suspected Uptake of Xenon and Iodine, correspondence with results; 

Robert Miltenberger and E. T. Lessard; January 14, 1987; SRDB Ref ID: 50416, pp. 150-154 

Miltenberger, 1987d, Co-60 Exposure of [Name Redacted] at Building 650; Robert P. 

Miltenberger and Edward T. Lessard; March 23, 1987; SRDB Ref ID: 54011, p. 2 

Miltenberger, 1995, Technical Justification for Not Using Working Levels in Radiation Dose 

Assessments, correspondence to H. Kahnhauser; R. Miltenberger; February 15, 1995; SRDB Ref 

ID: 48514 

Monthly Reports, 1973, Monthly reports for 1973 to N. A. Greenhouse from A. E. Lukas; 

Brookhaven National Laboratory; various dates in 1973; SRDB Ref ID: 55061, pdf pp. 5, 6, 10, 

13, 17, 18, 22, 24, and 26 

Murray, 1995, Determination of AGS Whole-Body Counting Participants, correspondence to 

Edwin Njoku; Bruce Murray; January 6, 1995; SRDB Ref ID: 22468 

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Musolino, 1987, High Radiation Events in the External Beam, memorandum to W. R. Casey 

from S. Musolino; Brookhaven National Laboratory; June 29, 1987; SRDB Ref ID: 50509 

Musolino, 2000, Technical Basis for Bioassay Requirements for BGRR Decommissioning 

Project; Stephen V. Musolino; September 27, 2000; SRDB Ref ID: 22428, pdf pp. 2-9 

Nappi, 1970, Estimate of Dose Delivered to [name redacted] – 4/8/70, memorandum to the File 

from A. Nappi; Brookhaven National Laboratory; April 14, 1970; 50792 

NYOO Reports, 1949, Progress Report for 1949; New York Operations Office (NYOO); 

January-December 1949; SRDB Ref ID: 6291 

Occurrence Report, 1988, Unusual Occurrence Report, BNL-RD-88-20/HFBR-88-5, V. Lettieri 

(Originator); Brookhaven National Laboratory; July 28, 1989; SRDB Ref ID: 53506 

Occurrence Report, 1990, Unusual Occurrence Report, UOR NO. 90-11, E. Lessard (Department 

Investigator); Brookhaven National Laboratory; May 2, 1990; SRDB Ref ID: 49966 

OCAS-IG-001, External Dose Reconstruction Implementation Guidelines, Rev.1, National 

Institute for Occupational Safety and Health; Office of Compensation Analysis and Support; 

2002; SRDB Ref ID: 38864 

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-0017, Interpretation of Dosimetry Data for Assignment of Shallow Dose, Rev. 

01; Oak Ridge Associated Universities; October 11, 2005; SRDB Ref ID: 19434 

ORAUT-OTIB-0019, Analysis of Coworker Bioassay Data for Internal Dose Assignment, Rev. 

00; Oak Ridge Associated Universities; December 29, 2004; SRDB Ref ID: 19439 

ORAUT-OTIB-0049, Estimating Doses for Plutonium Strongly Retained in the Lung, Rev. 00; 

Oak Ridge Associated Universities; February 6, 2007; SRDB Ref ID: 29975 

ORAUT-OTIB-0060, Internal Dose Reconstruction, Rev. 00; Oak Ridge Associated 

Universities; February 6, 2007; SRDB Ref ID: 29984 

ORAUT-PROC-0060, Occupational Onsite Ambient Dose Reconstruction for DOE Sites, Rev. 

01; Oak Ridge Associated Universities; June 28, 2006; SRDB Ref ID: 29986 

ORAUT-PROC-0061, Occupational X-Ray Dose Reconstruction for DOE Sites, Rev. 02; Oak 

Ridge Associated Universities; January 2, 2008; SRDB Ref ID: 39338 

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ORAUT-TKBS-0048, Summary Site Profile Document for the Brookhaven National Laboratory,

Rev. 00; Oak Ridge Associated Universities; August 30, 2006; SRDB Ref ID: 30090 

Pearsall, 1963a, Plutonium Contamination Incident, memorandum to L. Gemmell from S. G. 

Pearsall; January 16, 1963; SRDB Ref ID: 55634 

Pearsall, 1963b, Plutonium Contamination Incident and Precious Metal Packages, various 

correspondence; S. G. Pearsall, L. Gemmell, and J. Steimers; January-March 15, 1963 and 

August 4, 1970; SRDB Ref ID: 55132 

Personal Communication, 2008a, Personal Communication with Health Physics Manager, 

Telephone Interview by ORAU Team; November 21, 2008; SRDB Ref ID: 65829 

Personal Communication, 2008b, Personal Communication with Health Physics Group Leader, 

Telephone Interview by ORAU Team; November 21, 2008; SRDB Ref ID: 65836 

Personal Communication, 2008c, Personal Communication with Health Physics Manager, 

Telephone Interview by ORAU Team; December 11, 2008; SRDB Ref ID: 65827 

Personal Communication, 2008d, Personal Communication with Health Physics Manager, 

Telephone Interview by ORAU Team; December 12, 2008; SRDB Ref ID: 65831 

Personal Communication, 2008e, Personal Communication with Health Physics Manager, 

Telephone Interview by ORAU Team; December 12, 2008; SRDB Ref ID: 65832 

Personal Communication, 2009a, Personal Communication with Custodian, Telephone Interview 

by ORAU Team; January 15, 2009; SRDB Ref ID: 65826 

Personal Communication, 2009b, Personal Communication with Carpenter, Telephone 

Interview by ORAU Team; January 21, 2009; SRDB Ref ID: 65825 

Personal Communication, 2009c, Personal Communication with Machinist, Pile Operator, 

Reactor Operator, Telephone Interview by ORAU Team; January 29, 2009; SRDB Ref ID: 

65844 

Personal Communication, 2009d, Personal Communication with Plumber, Superintendent, 

Telephone Interview by ORAU Team; February 5, 2009; SRDB Ref ID: 65840 

Personal Communication, 2009e, Personal Communication with Three Former BNL Employees; 

Interview by SC&A; May 19, 2009; SRDB Ref ID: 71451 

Personnel Monitoring, 1948, Proposed SPI on Personnel Monitoring, memorandum from F. P. 

Cowan to Policy and Program Committee; Brookhaven National Laboratory; January 21, 1948; 

SRDB Ref ID: 50636 

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Personnel Monitoring, unknown date, General Procedures for Personnel Monitoring; 

Brookhaven National Laboratory; unknown date; SRDB Ref ID: 50569 

Phillips, 1974, Personnel Dosimetry, L. F. Phillips; Brookhaven National Laboratory; 1974; 

SRDB Ref ID: 22429 

Pittman, 1978, Results of Exposure Investigations, memorandum to R. Casey from A. Pittman; 

Brookhaven National Laboratory; February 9, 1978; SRDB Ref ID: 55212 

Pocket Chambers, 1952, Use of Pocket Ionization Chambers, memorandum from F. P. Cowan to 

Members of Radiation Safety Committee; Brookhaven National Laboratory; May 12, 1952; 

SRDB Ref ID: 50598, pdf p. 7 

Progress Report, August 1949, Progress Report for August 1949; C. F. Murphy; September 1, 

1949; SRDB Ref ID: 22847, pp. 2-4 

Progress Report, March 1952, Progress Report for March 1952; W. D. Small; March 31, 1952; 

SRDB Ref ID: 55243, pdf p. 18 

Progress Report, April 1952, Progress Report for April 1952; W. D. Small; April 30, 1952; 

SRDB Ref ID: 55243, pdf p. 16 

Progress Report, May 1952, Progress Report for May 1952; W. D. Small; June 2, 1952; SRDB 

Ref ID: 55243, pdf p. 14 

Progress Report, October 1952, Progress Report for October 1952; W. D. Small; November 3, 

1952; SRDB Ref ID: 55243, pdf p. 5 

Progress Report, November 1953, Progress Report, November 1953; L. Phillips; November 30, 

1953; SRDB Ref ID: 55242, pdf p. 3 

Progress Report, December 1953, Progress Report, December 1953; L. Phillips; January 4, 

1954; SRDB Ref ID: 55242, pdf p. 2 

Progress Report, June 1954, Progress Report, June 1954; L. Phillips; July 1, 1954; SRDB Ref 

ID: 55241, pdf p. 10 

Progress Report, August 1954, Progress Report, August 1954; L. Phillips; September 2, 1954; 

SRDB Ref ID: 55241, pdf p. 5 

Progress Report, April 1958, Progress Report, April 1958; W. H. Bishop; April 1958; SRDB Ref 

ID: 22919, pdf p. 7 

Progress Report, September 1963, Progress/Hot Lab Report for September 1963; C. Foelix and 

R. Stong; October 8 & 9, 1963; SRDB Ref ID: 53889, pdf p. 8 

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Progress Report, December 1963, Progress Reports for December 1963; R. Stong and C. Foelix; 

January 3 & 9, 1964; SRDB Ref ID: 53889, pdf p. 3 

Progress Report, January 1965, Progress Reports/Hot Lab Reports for January 1965; C. Foelix, 

M. Hilgemeier, and R. W. Stong; February 2 & 8, 1965; SRDB Ref ID: 53871, pp. 24-26 

Progress Report, April 1965, Progress Reports/Hot Lab Reports for April 1965; R. W. Stong, C. 

Foelix, and M. W. Hilgemeier; May 5, 7, and 17, 1965; SRDB Ref ID: 53871, pdf pp. 14-16 

Progress Report, February 1967, Progress Report, February 1967, C. Foelix, R Stong, and A. 

Lukas; March 15, 1967; SRDB Ref ID: 53851, pdf p. 16 

Progress Report, January 1974, Progress Report-Physics/Chemistry January, 1974; R. L. 

Gardner; February 15, 1974; SRDB Ref ID: 55322, pdf p. 22 

Progress Report, September 1974, Progress Report-Physics/Chemistry June-July, 1974; R. L. 

Gardner; September 5, 1974; SRDB Ref ID: 55322, pdf p. 14 

Progress Report, November 1975, Progress Report – November 1975, Physics/Chemistry, E. J. 

O’Connell, III; February 5, 1976; SRDB Ref ID: 55426 

Progress Report, December 1975, Progress Report-Chemistry/Physics December, 1975; E. J. 

O’Connell III; March 2, 1976; SRDB Ref ID: 53926 

Progress Report, Oct-Nov 1983, Progress Report for October/November 1983; E. N. Carter; 

December 15, 1983; SRDB Ref ID: 55042, pp. 2-5 

Progress Reports, 1961, Progress Reports and Hot Lab Reports for 1961; E. N. Carter; JanuaryDecember 1961; SRDB Ref ID: 53470 

Progress Reports, 1963, Progress/Hot Lab Reports for 1963; E. N. Carter and C. Foelix; 

January-December 1963; SRDB Ref ID: 53889 

Progress Reports, 1974, Progress Report for 1974; E. N. Carter; January-December 1974; SRDB 

Ref ID: 55336 

Reciniello, 1992, Respirator Use by RCG Personnel, correspondence to N. Holden; R. 

Reciniello; December 3, 1992; SRDB Ref ID: 48490 

Rice, 1966, Summaries of Fuels and Materials Development Programs, draft copy; edited by 

William L. R. Rice; March 1966; SRDB Ref ID: 21847 

Roesler, 1976, Cerium-141 and 143 Incident in Building 703, correspondence with attachments; 

James Roesler; January 13, 1976; SRDB Ref ID: 53964 

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SEC-00113 09-29-09 FINAL BNL

Rorer, 1984, Investigation of the Contamination Accident at the TRISTAN Facility at the High 

Flux Beam Reactor on October 24, 1984; David C. Rorer, Charles W. Flood, Jr., Ronald L. Gill, 

and David D. Warner; November 15, 1984; SRDB Ref ID: 53800 

Safety Manual, 1948, Summary of Responsibilities in Regard to Radiation Safety, memorandum 

from F. P. Cowan to the Radiation Safety Committee Members; Brookhaven National 

Laboratory; March 1, 1948; SRDB Ref ID: 50634 

Salant, 1947, Precautions in Handling Radioactive Sources, correspondence to the Nuclear 

Interaction Group (P-32); E. Salant; November 18, 1947; SRDB Ref ID: 50602 

Sample Records, 1962-1963, Air, Stack, Water, and Urine Sample Results from February 22, 

1962 through June 10, 1963; SRDB Ref ID: 9883 

Sengupta, 2000, Brookhaven National Laboratory External Dosimetry Technical Basis 

Document, S. Sengupta; PM-PD-003, Rev. 1; BNL Radiological Control Division; March 31, 

2000; SRDB Ref ID: 33173 

Special Nuclear, 1963, Special Nuclear Material Draft, Brookhaven National Laboratory; April 

4, 1963; SRDB 45051, pdf p. 3 

SR-90, 1949, Health Physics Summary for December 1949, Building Survey – Operations, 

Brookhaven National Laboratory; 1949; SRDB Ref ID: 55453, pdf p. 3 

Thyroid Count Results, July-August 1981, Results of Thyroid Count Performed on July 30, 

August 4, and August 17, 1981; SRDB Ref ID: 53790 

Thyroid Count Results, January 1988a, Results of Thyroid Count Performed on January 28, 

1988; SRDB Ref ID: 50640 

Thyroid Count Results, January 1988b, Results of Thyroid Count Performed on January 15, 

1988; SRDB Ref ID: 50703 

Thyroid Count Results, January 1988c, Results of Thyroid Count Performed on January 14, 1988 

for Building 490 Personnel; SRDB Ref ID: 53311 

Thyroid Count Results, February 1988, Results of Thyroid Count Performed on February 22, 

1988; SRDB Ref ID: 53310 

Thyroid Count Results, March 1988a, Results of Thyroid Count Performed on March 11, 1988; 

SRDB Ref ID: 53307 

Thyroid Count Results, March 1988b, Results of Thyroid Count Performed on March 2, 1988; 

SRDB Ref ID: 53309 

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SEC-00113 09-29-09 FINAL BNL

Thyroid Count Results, October 1988, Results of Thyroid Count Performed on October 17, 1988; 

SRDB Ref ID: 50670 

Tichler, 1983, Investigation of the Cold Neutron Facility Accident at the High Flux Beam 

Reactor on March 18, 1983, P. Tichler (Investigating Committee Chairman); Brookhaven 

National Laboratory; May 20, 1983; SRDB Ref ID: 53395 

Tony, 1976, Bioassay Results for [Name Redacted], correspondence; January 14, 1976; Tony G.; 

SRDB Ref ID: 67550 

Tritium Assessments, 1984-1995, Brookhaven Tritium Exposure Printout Results from January 

1, 1984 to July 1, 1995; SRDB Ref ID: 60147 

Tritium Assessments, August 1993, Summary Report for Tritium Exposures for August 1993; 

SRDB Ref ID: 55592 

Tritium Assessments, October-November 1993, Summary Report for Tritium Exposures for 

October/November 1993; SRDB Ref ID: 55596 

Tritium Assessments, October-December 1993, Summary Report for Tritium Exposures from 

October 1, 1993 through December 31, 1993; SRDB Ref ID: 55477 

Tritium Assessments, January-February 1994, Summary Report for Tritium Exposures from 

January 1, 1994 through February 28, 1994; SRDB Ref ID: 55377 

Tritium Assessments, January-August 1994, Summary Report for Tritium Exposures from 

January 3, 1994 through August 9, 1994; SRDB Ref ID: 55366 

Tritium Assessments, February-March 1994, Summary Report for Tritium Exposures from 

February 28, 1994 through March 31, 1994; SRDB Ref ID: 55387 

Tritium Assessments, December 1994, Summary Report for Tritium Exposures for December 

1994; SRDB Ref ID: 55352 

Tritium Assessments, January-February 1995, Summary Reports for Tritium Exposures from 

January 1995 through February 1995; SRDB Ref ID: 55289 

Tritium Assessments, January-March 1995, Summary Reports for Tritium Exposures from 

January 1, 1995 through March 31, 1995; SRDB Ref ID: 55290 

Tritium Assessments, December 1996, Summary Report for Tritium Exposures for December 

1996; SRDB Ref ID: 55363 

Unknown author, 1958, Whole-Body Counting Historical Review, handwritten notes; Unknown 

author; 1958; SRDB Ref ID: 48246 

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SEC-00113 09-29-09 FINAL BNL

Urinalysis Records, 1950, BNL Urinalysis Records for 1950; SRDB Ref ID: 53718 

Urinalysis Records, January-September 1951, BNL Urinalysis Records/Reports from January 

1951 through September 1951; SRDB Ref ID: 53766 

Urinalysis Records, February-December 1952, BNL Urinalysis Records/Reports from February 

12, 1952 through December 31, 1952; SRDB Ref ID: 53340 

Urinalysis Records, 1952-1975a, BNL Urinalysis/Bioassay Records from September 5, 1952 

through February 12, 1975; SRDB Ref ID: 48221 

Urinalysis Records, 1952-1975b, BNL Urinalysis/Bioassay Records from May 28, 1952 through 

September 22, 1975; SRDB Ref ID: 48224 

Urinalysis Records, 1953-1954, BNL Urinalysis Records/Reports from January 26, 1953 through 

May 19, 1954; SRDB Ref ID: 53338 

Urinalysis Records, June 1955, Urinalysis Record for Sample Taken on June 23, 1955; SRDB 

Ref ID: 6274 

Urinalysis Records, 1955-1964, Urinalysis Records from December 28, 1955 through July 27, 

1964; SRDB Ref ID: 6302 

Urinalysis Records, September-November 1965, Urinalysis Records from September 22, 1965 

through November 2, 1965; SRDB Ref ID: 6276 

Urinalysis Records, May 1968, Report of Analysis: Radiometric Uranium in Urine; Eberline 

Instrument Corporation; May 2, 1968; SRDB Ref ID: 59008 

Urinalysis Records, July 1968, Report of Analysis: Radiometric Uranium in Urine; Eberline 

Instrument Corporation; July 2, 1968; SRDB Ref ID: 59010 

Urinalysis Records, October 1968, Report of Analysis: Radiometric Uranium in Urine; Eberline 

Instrument Corporation; October 9, 1968; SRDB Ref ID: 58969 

Urinalysis Records, March 1969, Report of Analysis: Radiochemical Determination of Specific 

Uranium in Urine; Department of Nuclear Sciences; March 5, 1969; SRDB Ref ID: 59090 

Urinalysis Records, June 1969, Report of Analysis: Radiochemical Determination of Specific 

Uranium in Urine; Department of Nuclear Sciences; June 23, 1969; SRDB Ref ID: 58997 

Urinalysis Records, August 1982, Urinalysis Records/Report for Samples Collected from August 

19, 1982 through August 26, 1982; SRDB Ref ID: 55257 

Urinalysis Records, June 1987; Urinalysis Records/Report for Samples Collected from June 19, 

1987 through June 24, 1987; SRDB Ref ID: 59098 

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Urinalysis Records, April 1988, Urinalysis Records/Report for Samples Collected from April 7, 

1988 through April 12, 1988; SRDB Ref ID: 59128 

Urinalysis Results, 1964, Results for fluorimetric urinalyses for uranium, U.S. Atomic Energy 

Commission, Health and Safety Laboratory; January and February 1964; SRDB Ref ID: 9942, 

pdf pp. 115 and 121 

Urinalysis Results, November 2005, Sample Results [Urine], STL Richland (vendor); November 

29, 2005; SRDB Ref ID: 22542 

Use of Dosimetry, 1995, Use of Dosimetry, N. Contos; Brookhaven National Laboratory; FSSOP-4020; September 1, 1995; SRDB Ref ID: 50587 

Van Horn, 1962-1963, Various Correspondence Regarding BNL Permits; B. L. Van Horn; June 

11, 1962 through May 9, 1963; SRDB Ref ID: 6517, pdf pp. 103-119 

Various authors, 1966, Papers Presented at Conference on Distribution, Retention, and Late 

Effects of Thorium Dioxide; Various authors; April 20-April 22, 1966; SRDB Ref ID: 32706 

Various authors, September-November 1973, Whole-Body Counting Schedules; N. A. 

Greenhouse, C. W. Flood, W. R. Casey, and A. Humm; September 1, 1973 through November 7, 

1973; SRDB Ref ID: 55402, pp. 16-22 

Volatility, 1957, Explosion at Brookhaven National Laboratory, office memorandum to K. E. 

Fields from M. Eisenbud; U.S. Atomic Energy Commission, New York Operations Office; June 

7, 1957; SRDB Ref ID: 6319, pdf pp. 8-33 

WBC Summary, 1960, Summary of Whole Body Radiation Exposures to External Penetrating 

Radiation Accumulated During the Year 1960, U.S. Atomic Energy Commission, New York 

Operations Office; 1960; SRDB Ref ID: 13786, pdf p. 44 

WBC Summary, 1961, Summary of Whole Body Radiation Exposures to External Penetrating 

Radiation Accumulated During the Year 1961, U.S. Atomic Energy Commission, New York 

Operations Office; 1961; SRDB Ref ID: 13789, pdf p. 47 

WBC Summary, 1964, Summary of Whole Body Radiation Exposures to External Penetrating 

Radiation Accumulated During the Year 1964, U.S. Atomic Energy Commission, New York 

Operations Office; 1964; SRDB Ref ID: 14442, pdf p. 12 

WBC Summaries, 1987, Various summaries of whole body count results for 1987, Brookhaven 

National Laboratory; various dates in 1987; SRDB Ref ID: 50416 

White, 1978, Exposure Incident Investigation, various correspondence; O. White, A. Humm, A. 

Lukas; L. F. Phillips, G. Levine, and J. W. Baum; June 6-October 18, 1978; SRDB Ref ID: 

50920 

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SEC-00113 09-29-09 FINAL BNL

Whole Body Counting, 1973, Whole Body Counting, internal memorandum to S. Cohn from A. 

P. Hull; Brookhaven National Laboratory; October 25, 1973; SRDB Ref ID: 55141, pdf pp. 6-10 

Whole-Body Results, March-May 1963, Punch Tape Whole-Body 30 Minute Notebook from 

March 26, 1963 to May 17, 1963; SRDB Ref ID: 58866 

Whole-Body Results, May-July 1963, Punch Tape Whole-Body 30 Minute Notebook from May 

20, 1963 to July 24, 1963; SRDB Ref ID: 58852 

Whole-Body Results, 1965-1969, 1965-1969 Exposure of AEC and AEC Contractor Personnel 

to Whole-Body Penetrating Radiation, various sites; Atomic Energy Commission (AEC); 

October 1965 through December 31, 1969; SRDB Ref ID: 13800 

Whole-Body Results, January-February 1973, BNL Whole-Body Counting Results and 

Correspondence from January 26, 1973 through February 10, 1973; SRDB Ref ID: 55148 

Whole-Body Results, 1973-1981, BNL Whole-Body Counting Results from January 4, 1973 to 

December 12, 1981; SRDB Ref ID: 48265 

Whole-Body Results, 1974, BNL Whole-Body Counting Results throughout 1974; SRDB Ref ID: 

55215 

Whole-Body Results, February-December 1975, BNL Whole-Body Counting Results from 

February 25, 1975 through December 22, 1975; SRDB Ref ID: 55199 

Whole-Body Results, 1975-1981, BNL Whole-Body Counting Results from May 29, 1975 

through November 20, 1981; SRDB Ref ID: 48247 

Whole-Body Results, 1978-1979, BNL Whole-Body Counting Results from January 23, 1978 

through February 6, 1979; SRDB Ref ID: 55208 

Whole-Body Results, July-August 1978, BNL Whole-Body Counting Results from July 31, 1978 

through August 24, 1978; SRDB Ref ID: 59025 

Whole-Body Results, 1979-1986, BNL Whole-Body Counting Results from January 11, 1979 

through October 23, 1986; SRDB Ref ID: 48248 

Whole-Body Results, 1988-1994, BNL Whole-Body Counting Results from December 8, 1988 to 

July 22, 1994; SRDB Ref ID: 50704 

Whole-Body/Thyroid Results, 1983-1984, BNL Whole-Body and Thyroid Counting Results from 

November 22, 1983 to October 26, 1984; SRDB Ref ID: 48253 

Whole-Body/Thyroid Results, 1984-1985, Whole-Body and Thyroid Counting Results for 

December 11, 1984 and January 21, 1985; SRDB Ref ID: 53860 

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SEC-00113 09-29-09 FINAL BNL

Whole-Body/Thyroid Results, January 1986, Whole-Body and Thyroid Counting Results for 

January 28, 1986; SRDB Ref ID: 50622 

Williams, 1963, Medical Examinations of Reactor Operators, correspondence to V. P. Bond; 

Clarke Williams; January 29, 1963; SRDB Ref ID: 53887 

100 of 120 
SEC-00113 09-29-09 FINAL BNL

101 of 120 

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SEC-00113 09-29-09 

Attachment 1: BNL Internal Data Analysi

(This table spans four pages) 

Internal Data Analysis

Number of Employees Monitored per Year by Work Group 

WBC and Urinalysis Results (SRDB, PM and Medic

49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 

Reactor - BGRR & Pile1 1950 to 1968; exhaust fan/filter until 1972

Reactor - HFBR1 1965 to 1996

WBC 24 1 1 2 18 19 18 8 20 14 20 UA Gross & MFP 2 1 35 27 41 45 34 71 59 34 55 62 51 38 41 24 34 14 14 11 7 

Sr-90 2 27 7 3 1 2 10 31 24 16 13 6 2 

H-3 1 1 2 3 2 2 17 19 31 35 28 24 22 15 17 16 15 13 12 8 9 9 

U Less EU 1 1 1 9 11 2 8 10 1 2 5 4 6 

EU/U-235 1 1113 1 

Gross alpha 1 4 2 

Po-210 2 3 1 

Pu/Pu-239 4 14 17 1 1 2 

I-131 1 

Gamma 2 7 

Cs-137 1111 

Misc Bioassay6 2 23573588696354 1 

Other RA4 1 2 1 

49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 

Hot Lab, Medical & BLIP 1951 to present (Hot Lab & Medical) 1972 to present (BLIP)

WBC 1 4 8 14 14 1 3 4 4 UA Gross & MFP 1 1 5 5 26 20 17 16 33 21 29 35 38 27 33 30 25 19 9 7 8 2 8 1 

Sr-90 4 2 2 2 2 4 4 16 7 1 1 4 

H-35 2 2 1 2 1 4 7 9 7 4 4 8 6 14 1 5 3 4 4 3 

U Less EU 7 9 4 2 12 4 8 2 5 2 3 

EU/U-235 1 1 

Gross alpha 11566 2 

Po-210 3 13 9 4 2 3 2 1 1 1 

Pu/Pu-239 2 6 132 1 1 

I-131 2175 1 

Gamma 2 19 9 7 8 3 8 1 

Cs-137 6 30 25 18 1 

Misc Bioassay6 13144443423113 215321 

Other RA 1 2 1 

49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 

Page 102 of 120 
SEC-00113 09-29-09 FINAL 

Attachment 1: BNL Internal Data Analysis Matrix 

(This table spans four pages) 

HP, S&EP & Waste Assumed activities from 1949 to present

WBC 2 1 4 21 7 1 3 UA Gross & MFP 1 1 5 11 24 14 10 14 12 12 15 12 14 15 12 10 16 10 4 7 3 1 1 

Sr-90 1 1 2 10 5 7 5 2 3 4 4 9 5 1 3 1 

H-3 1 1 1 1 1 1 1 2 9 9 16 15 13 14 8 9 4 5 3 5 4 4 4 

U Less EU 121 16 1 5 

EU/U-235 1 

Gross alpha 2 

Po-210 6 2 1 

Pu/Pu-239 1 6 1 4 2 3 

I-131 1 1 3 1 2 

Gamma 1364 1 21 

Cs-137 4 

Misc Bioassay6 1 32111 112 1 11 1 

Other RA 1 1 1 1 

49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 

Accelerators (AGS, TVDG) 1960 to present (AGS) 1970 to present (TVDG)

WBC 2 1 5 2 7 3 9 1 UA Gross & MFP 1 1 1 1 1 1 1 2 2 1 2 4 2 1 2 

Sr-90 1 1 

H-3 1111 2 

U Less EU 2 1 1 

EU/U-235 2 

Gross alpha 

Po-210 

Pu/Pu-239 1 1 

I-131 1 1 

Gamma 2 1 

Cs-137 1 3 1 

Misc Bioassay6 1 

Other RA 

49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 

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SEC-00113 09-29-09 FINAL 

Attachment 1: BNL Internal Data Analysis Matrix 

(This table spans four pages) 

DAS & Nuclear Engineering2 Assumed activities from 1949 to present

WBC 5 3 3 2 1 2 UA Gross & MFP 3 3 13 12 63 8 17 21 27 14 22 20 7 1 14 21 7 5 6 8 3 6 3 5 

Sr-90 7412532372 1 

H-3 1 7 7 2 1 11 5 8 3 10 5 6 3 4 

U Less EU 1 2 11 16 3 8 25 6 1 16 16 7 11 

EU/U-235 1 81211 1 

Gross alpha 3 6 8 5 3 1 

Po-210 12 2 13 12 3 1 1 1 

Pu/Pu-239 6 6 2 1 1 

I-131 1 

Gamma 1 1 2 15 15 5 7 4 6 3 4 

Cs-137 1 1211 

Misc Bioassay6 1 1 2222332421 14 1 22 

Other RA 1 1 1 

49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 

Chem., Biology & Physics Assumed activities from 1949 to present

WBC 1122 4 UA Gross & MFP 1 1 1 2 3 5 1 10 6 4 5 2 5 1 3 4 

Sr-90 1 1 1413 

H-3 1 1 2 13 11 10 5 3 1 1 

U Less EU 2 3 3 

EU/U-235 1 1 1 

Gross alpha 3 2 

Po-210 1 3 1 1 1 

Pu/Pu-239 6 

I-131 

Gamma 1 

Cs-137 

Misc Bioassay6 11 1 1 1 

Other RA 3 1 1 

49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 

104 of 120 
SEC-00113 09-29-09 FINAL 

Attachment 1: BNL Internal Data Analysis Matrix 

(This table spans four pages) 

Plant Eng./Maint. & Shops Assumed activities from 1949 to present

WBC 1 1 

UA Gross & MFP 1 5 11 8 31 12 7 12 29 33 40 32 20 13 11 17 12 9 

Sr-90 3 5 4 1 2 9 8 11 3 

H-3 1 5 4 12 10 12 19 1 2 3 1 1 1 1 2 3 

U Less EU 21 31 321 

EU/U-235 1 2 

Gross alpha 

Po-210 1 2 1 1 

Pu/Pu-239 

I-131 

Gamma 14 10 8 

Cs-137 1 

Misc Bioassay6 122222211 

Other RA 

49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 

Other Work Groups3 Assumed activities from 1949 to present

WBC 1 3 5 16 2 3 8 1 1 

UA Gross & MFP 13 4 11 14 2 2 1 1 1 1 1 1 1 1 

Sr-90 1 1 3 1 

H-3 1 2 1212 1 1 

U Less EU 1 6 5 9 2 2 10 1 5 3 3 5 

EU/U-235 1 2 3 2 

Gross alpha 

Po-210 2 3 1 

Pu/Pu-239 3 15 34 1 1 

I-131 

Gamma 1 1

Cs-137 1 

Misc Bioassay6 

Other RA 1 1 

Notes: Represents operational time frame per BNL TBD Table 2-2.1) Reactor includes all reactor work groups (BGRR, Pile, and HFBR); overlapping years of operation (1965-1969) may be BGRR/Pile or HFBR.2) DAS-CA-NE includes the work groups Dept. of Applied Science, Critical Assembly, Nuclear Engineering, Cosmotron, Instrumentation, Metallurgy, Fuel Fission, LMF3) Other Work Groups includes AEC, Administrative, Management, PEP, Security, Technical Photo, Underwater Rig, Marshall Island, Visitor, Bldg 100, and Unknown 4) Includes three fecal samples for one employee in 1975.5) Includes one seminal fluid sample for a Medical worker in 1963.6) Misc bioassay includes data found in PM and Medical files; only one result/person per year was counted (may have more than one analyses per sample).

105 of 120 
SEC-00113 09-29-09 FINAL 

Attachment 2: Number of Persons Monitored Ea

(This table spans six pages) 

Year

 Monitoring 

Status

Total Not 

Monitored

 Total Number Monitored

 Number with Meas. Dose

Total 

Collective Dose (TEDE in personmrem)

 Average Meas. Dose (TEDE in mrem)

 No Meas. Exposure <1000

1000 - 1999

200299

2007 Employee 2058 184 6004 33 1874 184 0 2007 Public 137 6 266 44 131 6 0 2007 Govt Agency 25 1 7 7 24 1 0 2006 Employee 2031 144 5968 41 1887 144 0 2006 Public 127 3 139 46 124 3 0 2006 Govt Agency 11 0 0 0 11 0 0 2005 Employee 2346 214 10190 48 2132 214 0 2005 Public 162 2 26 13 160 2 0 2005 Govt Agency 10 0 0 0 10 0 0 2004 Employee 2461 297 23650 80 2164 297 0 2004 Public 164 4 28 7 160 4 0 2004 Govt Agency 14 0 0 14 0 0 2003 Employee 1731 247 11270 46 1484 247 0 2003 Terminated 2203 53 819 15 2150 53 0 2003 Govt Agency 51 3 69 23 48 3 0 2003 Public 150 3 25 8 147 3 0 2002 Employee 1896 335 23364 70 1561 335 0 2002 Terminated 2495 88 2599 30 2407 88 0 2002 Public 211 13 248 19 198 13 0 2002 Govt Agency 70 3 33 11 67 3 0 2001 Employee 1952 270 11507 43 1682 270 0 2001 Terminated 2718 108 2863 27 2610 108 0 2001 Public 299 6 151 25 293 6 0 

106 of 120 
SEC-00113 09-29-09 FINAL 

Attachment 2: Number of Persons Monitored Each Ye

(This table spans six pages) 

Year

 Monitoring 

Status

Total Not 

Monitored

 Total Number Monitored

 Number with Meas. Dose

Total 

Collective Dose (TEDE in personmrem)

 Average Meas. Dose (TEDE in mrem)

No Meas. 

Exposure <1000

1000 - 1999

200299

2001 Govt Agency 79 3 106 35 76 3 0 2000 Active 1776 311 18081 58 1465 311 0 

2000 Govt Agency 2583 58 2175 38 2525 58 0 2000 Terminated 1007 56 1927 34 951 56 0 2000 Visitors 90 3 153 51 87 3 0 2000 Govt Agency 28 2 48 24 26 2 0 1999 Active 1821 320 16664 52 1501 320 0 

1999 Terminated 631 79 3767 48 552 79 0 

1999 Non-Emp Rad 2672 110 2800 25 2562 110 0 

1999 Visitors 472 10 113 11 462 10 0 1999 Govt Agency 57 2 27 14 55 2 0 1998 Active 2236 533 52777 99 1703 533 0 

1998 Non-Emp Rad 2758 466 8866 19 2292 466 0 

1998 Terminated 155 25 941 38 130 25 0 1998 Visitors 381 25 232 9 356 25 0 1998 Govt Agency 66 6 149 25 60 6 0 1997 Active 2483 629 54142 86 1854 629 0 

1997 Non-Emp Rad 2735 772 13588 18 1963 772 0 

1997 Terminated 91 27 798 30 64 27 0 1997 Visitors 675 35 420 12 640 35 0 1996 Active 2449 719 92652 129 1730 714 5 

1996 Non-Emp Rad 3384 717 23569 33 2667 716 1 

1996 Terminated 94 12 550 46 82 12 0 1995 Active 1851 505 88215 175 1346 498 7 

1995 Non-Emp Rad 537 191 35347 185 346 191 1 

107 of 120 
SEC-00113 09-29-09 FINAL 

Attachment 2: Number of Persons Monitored Each Ye

(This table spans six pages) 

Total 

Collective Average 

 Number Dose Meas. 

 Total with (TEDE in Dose 

 Monitoring Total Not Number Meas. person- (TEDE in No Meas. 1000 - 200

Year Status Monitored Monitored Dose mrem) mrem) Exposure <1000 1999 299

1995 Visitors 275 246 17438 71 29 24601995 Terminated 188 31 4840 156 157 3101994 Active 1945 443 66230 150 1502 43851994 Visitors 217 215 13660 64 2 21511994 Non-Emp Rad 631 189 11340 60 442 18901994 Terminated 203 18 1050 58 185 1801993 Active 1971 462 50070 108 1509 45921993 Non-Emp Rad 587 116 6030 52 471 11601993 Visitors 124 120 3150 26 4 12001993 Terminated 123 15 650 43 108 1501992 Active 2129 440 43090 98 1689 44001992 Non-Emp Rad 1185 512 14740 29 673 51201992 Terminated 121 19 810 43 102 1901992 Visitors 2 2 50 25 0 201991 Active 1977 602 69430 115 1375 59751991 Non-Emp Rad 787 276 15790 57 511 27511991 Visitors 133 122 3310 27 11 12201991 Terminated 97 19 960 51 78 1901990 Active 1888 613 60450 99 1275 61121990 Non-Emp Rad 723 319 22960 72 404 31901990 Visitors 355 349 8580 25 6 34901990 Terminated 114 36 1910 53 78 3601989 Active 1809 860 98578 115 949 848 101989 Non-Emp Rad 684 368 20700 56 316 36801989 Terminated 163 76 4700 62 87 760

108 of 120 
SEC-00113 09-29-09 FINAL 

Attachment 2: Number of Persons Monitored Each Ye

(This table spans six pages) 

Total 

Collective Average 

 Number Dose Meas. 

 Total with (TEDE in Dose 

 Monitoring Total Not Number Meas. person- (TEDE in No Meas. 1000 - 200

Year Status Monitored Monitored Dose mrem) mrem) Exposure <1000 1999 299

1989 Visitors 538 527 14510 28 11 52611988 Active 1900 801 116000 145 1099 786 13

1988 Visitors 927 642 33000 51 285 64111987 Active 1849 964 133000 138 885 938 25

1987 Visitors 941 657 37000 56 284 65251986 Employee 1817 771 173000 224 1046 738 251986 Visitors 705 444 38000 86 263 44211985 Employee 1808 1019 219000 215 789 968 421985 Visitors 835 421 45000 107 183 41471984 Employee 1772 983 249000 253 845 927 481984 Visitors 481 303 41000 135 178 30031983 Employee 1733 854 239000 280 879 793 47 1983 Visitors 404 245 30000 122 159 24401982 Employee 1775 758 174000 230 1017 730 251982 391 206 28000 136 185 20411981 Employee 1885 1414 262000 185 471 1366 381981 Visitors 441 295 38000 129 146 29311980 Employee 1974 1791 192000 107 183 1741 391980 Visitors 473 385 9000 23 88 38121979 Employee 2011 1820 421000 231 191 1717 75 1979 Visitors 420 328 49000 149 92 3197

109 of 120 
SEC-00113 09-29-09 FINAL 

Attachment 2: Number of Persons Monitored Each Ye

(This table spans six pages) 

Total 

Collective Average 

 Number Dose Meas. 

 Total with (TEDE in Dose 

 Monitoring Total Not Number Meas. person- (TEDE in No Meas. 1000 - 20

Year Status Monitored Monitored Dose mrem) mrem) Exposure <1000 1999 29

1978 Employees 1971 1656 448000 271 315 1537 80 1978 Visitors 416 311 46000 148 105 307 3 1977 Employees 1871 1666 644000 387 205 1461 122 1977 Visitors 405 327 80000 245 78 311 9 1976 Employee 1843 1709 621000 363 134 1519 125 1976 Visitors 469 382 71000 186 87 #REF! 5 1975 All 2183 2052 839000 409 131 1823 127 1974 All 2108 2040 874000 428 68 1785 142 1973 Employee 1276 1774 1514 152 

1973 Visitors 8000 2016 2010 5 1972 Employee 1239 1796 1609 100 1972 Visitors 9200 2444 2441 3 1970 Employees 1484 2132 430000 201 2021 65 1970 Visitors 10000 3334 3333 1 1969 Employees 1761 2244 431000 192 2149 60 1969 Visitors 14300 3732 3725 6 1968 Employees 1683 2358 658000 279 2174 106 1968 Visitors 9800 4906 4900 6 

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SEC-00113 09-29-09 FINAL 

Attachment 2: Number of Persons Monitored Each Ye

(This table spans six pages) 

Total 

Collective Average 

 Number Dose Meas. 

 Total with (TEDE in Dose 

 Monitoring Total Not Number Meas. person- (TEDE in No Meas. 1000 - 20

Year Status Monitored Monitored Dose mrem) mrem) Exposure <1000 1999 29

1967 Employees 1679 2479 687000 277 2274 144 

1967 Visitors 9100 5527 5524 3 1966 All 3184 901000 283 2920 139 1965 All 3088 2960 103 1965 Visitors 69001964 All 1493 3005 2885 93 

1964 Visitors 7500 01963 All 1,043 3225 3122 79 1963 Visitors 12,600 7,200 01962 All 757 3215 3134 41 

1962 Visitors 11100 0

1961 All 948 2399 2296 47 1960 All 679 2417 2315 48 1959 All 2048 1925 45 

1958 All 1592 1495 45 

111 of 120 
SEC-00113 09-29-09 FINAL 

Attachment 3: Two-Hundred-Person Data 

(This table spans two pages) 

Org or Workgroup Analysis Record Type 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 

PM File 1 1 2 2 2 2 9 7 10 12 11 14 12 11 11 11 11 10 11 8 9 9 Medical File 1PM File 7 4 7 7 3 6 7 7 10 10 11 10 9 7 9 8 3 6 5 1 

Medical File 2 1PM File 1 9 9 12 6 9 5 8 Medical File 6534757PM File 11111111223434443333333Medical FilePM File 113313543443335112111 1 

Medical File 1 1 1 1 

PM File 1 1244112 

Medical File 1 1 1 

PM File 1 3 2 55634Medical FilePM File 112212322332541 14 1 22 

Medical File 1 1PM File 1232 Medical File 1PM File 1 3143443

Medical FilePM File 223516444543434113 425331 

Medical FilePM File 1 1334 132Medical File 21 PM FileMedical FilePM File 1 11 1 

Medical File 1PM File 1 1112 1 

Medical File 2 1

Tritium Bioassay

Misc. Bioassay

Whole Body Count

HP, S&EP & Waste

(32 people total)

Reactors

(51 people total)

Tritium Bioassay

Misc. Bioassay

Whole Body Count

Tritium Bioassay

Misc. Bioassay

Whole Body Count

Misc. Bioassay

Tritium Bioassay

DAS & Nuclear 

Engineering

(35 people total)

Accelerators (AGS, TVDG)

(13 people total)

Whole Body Count

Tritium Bioassay

Misc. Bioassay

Whole Body Count

Hot Lab, Medical & BLIP

(32 people total)

112 of 120 
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Attachment 3: Two-Hundred-Person Data Capt

(This table spans two pages) 

PM FileMedical FilePM File 2 1 1 1 1 1 

Medical FilePM File 332 1 Medical FilePM File 1111212 22111123Medical FilePM File 122222211 

Medical FilePM File Medical File PM File Medical FilePM FileMedical File 1PM File 1 

Medical File

Whole Body Count

Misc. Bioassay

Tritium Bioassay

Chem., Biology & Physics

(21 people total)

Whole Body Count

Misc. Bioassay

Tritium Bioassay

Other Work Groups

(5 people total)

Plant Eng./Maint. & Shops

(11 people total)

Tritium Bioassay

Misc. Bioassay

Whole Body Count

113 of 120 
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Attachment 4: H-3 Results Not Matched, Total Results in the Index, and 

05

1015202530

1949

1950

1951

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1953

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1962

1963

1964

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1973

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

Year

H-3 in NIOSH Captured Documents Not Matched to Index, MediTotal H-3 in IndexTotal H-3 in PM and Medical Files

Number of People with Results 

114 of 120 
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Attachment 5: Misc Bioassay Results Not Matched, Total Results in the Index

05

1015202530354045

1949

1950

1951

1952

1953

1954

1955

1956

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1958

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1960

1961

1962

1963

1964

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1974

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1978

1979

1980

1981

1982

1983

1984

1985

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1988

1989

Year

Misc. Bioassay in NIOSH Captured Documents Not Matched to Index, Total Misc Bioassay in Index

Total Misc Bioassay in PM and Medical Files

Number of People with Results 

115 of 120 
SEC-00113 09-29-09 FINAL 

116 of 120 

Attachment 6: WBC Results Not Matched, Total Results in the Index, an

05

101520253035

1949

1950

1951

1952

1953

1954

1955

1956

1957

1958

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1960

1961

1962

1963

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1982

1983

1984

1985

1986

1987

1988

Year

WBC in NIOSH Captured Documents Not Matched to Index, MedTotal WBC in IndexTotal WBC in PM and Medical Files

Number of People with Results 
SEC-00113 09-29-09 FINAL 

Attachment 7: Data Capture Synopsis 

Table A7-1: Data Capture Synopsis for Brookhaven National Laboratory 

Data Capture Information Data Captured Description Da

Primary Site/Company Name: Brookhaven National 

Laboratory (DOE 1947-present) Other Company Names:

Associated Universities, Incorporated Brookhaven Science Associates 

Brookhaven histories and highlights, bioassay and whole body count reports, bioassay TBD for the Brookhaven Graphite Research Reactor (BGRR) decommissioning, High Flux Beam Reactor (HFBR) dose assessment reports, neutron dose distributions, Alternating Gradient Synchrotron (AGS) neutron dosimetry and surveys, internal dosimetry TBD's, medical x-ray QC report, incident reports, HFBR stack samples, the Radiation Control Manual, Health Physics summaries, HFBR whole body counts and bioassay results, dosimetry procedures, thyroid counting results, Tristan reports and dosimetry reports, individual employees' dosimetry results from their personnel monitoring and medical files, radiological and environmental surveys, facility progress and status reports, Marshall Islands reports, S. Cohn whole body counter logbooks, HFBR visitor registers, annual reports through 1970, accelerator radiation monitoring systems, and decommissioning surveys and plans. 

08/

State Contacted: NA Note: Contacting the state was not considered necessary since 

Brookhaven is an active DOE site and cooperated with relevant data 

collection. 

09/

Curtiss-Wright Report from a radiological waste meeting hosted by Brookhaven. 03/Department of Labor/Paragon Material transfer reports and reports on uranium oxide reduction. 12/DOE Argonne National Laboratory - East A listing of Chicago Operations Office facilities, and AEC and ERDA 

neutron dosimetry conferences. 

09/

DOE General Atomics Material transfer reports and a report which cites Brookhaven's work on 

neutron beam teletherapy. 

01/

DOE Germantown Reports on beryllium hazards and proposed standards. UnkDOE Hanford Declassified Document Retrieval System (DDRS) 

Monthly reports on Hanford/Brookhaven metallurgical projects and discussions of neutron monitoring and dosimetry. 

11/

DOE Legacy Management - Grand Junction Office Material transfer requests and reports, characterization of the 

Brookhaven Graphite Research Reactor (BGRR) canal, and environmental reports. 

06/

DOE Legacy Management - MoundView (Fernald Holdings, includes Fernald Legal Database) 

Waste management reports, air emissions reports, AEC reports to 

Congress, and a report on the uptake and effects of thorium dioxide. 

11/

DOE Los Alamos National Laboratory (LANL) Reports on mixed waste streams, AEC facilities, and photodosimetry. 12/

Page 117 of 120 
SEC-00113 09-29-09 FINAL 

Table A7-1: Data Capture Synopsis for Brookhaven National Laboratory 

Data Capture Information Data Captured Description Da

DOE Oak Ridge Operations Vault 1947 film badge results, a 1955 site inspection, and transcripts of 1964 

interviews. 

10/

DOE Oak Ridge National Laboratory (ORNL) Report on the machining of uranium for the Brookhaven Graphite 

Research Reactor. 

04/

DOE OpenNet New York Operations Office (NYOO) status reports and AEC reports to 

Congress. 

12/

DOE OSTI Energy Citations Brookhaven Highlights 1978-1994 and appendices to the Tiger Team 

Assessment. 

02/

DOE OSTI Information Bridge Stannard's Radioactivity and Health, report on human radiation 

experiments, and U-232 content of sapphire material. 

01/

DOE Savannah River Site Savannah River Site dosimetry visitor cards from the 1950's. 08/Google Histories of the Brookhaven Graphite Research Reactor and Medical 

Reactor, environmental reports, and reports to Congress. 

03/

Health Physics Journal Articles on using a whole body counter to measure body burdens of a 

fallout-exposed population, an improved TLD system, radiation detection and alarm system for an accelerator complex, and the design and dosimetry of a strontium-yttrium beta irradiator. 

08/

Interlibrary Loan Brookhaven papers describing radiopharmaceuticals and defining low 

radiation doses. 

08/

Kansas City (Lee's Summit) Federal Records Center (FRC) Film badge reports and individual employees' dosimetry information 

from their medical files. 

07/

NARA - Atlanta DOE indoor radon study results, contamination of a Brookhaven 

zetraton neutron generator, polonium requests and requirements, and U233 reports. 

05/

Office of Compensation Analysis and Support (OCAS) Highly enriched uranium working group reports. 02/Office of Scientific and Technical Information (OSTI) The 2002 site environmental report, reactor progress report, Tiger 

Team action plan, pile operating manual, survey of irradiation facilities, and observations on chronic lymphocytic leukemia. 

08/

ORAU Team Summary site profile and process knowledge expert interviews. 01/Pacific Northwest National Laboratories (PNNL) Results of the 1965 film badge reliability study. 12/San Bruno Federal Records Center (FRC) 1963 Associated Universities organizations and objectives and 

summaries of fuels and materials development programs. 

02/

Sandy Cohen & Associates (SC&A) Process knowledge expert interviews. 08/Science Applications International Corp (SAIC) Radiation exposure summaries. 09/Southern Illinois University, Edwardsville, IL Disposal of Brookhaven wastes in the St. Louis area, AEC construction 

cost differentials, and the AEC cryptographic telephone network. 

10/

118 of 120 
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Table A7-1: Data Capture Synopsis for Brookhaven National Laboratory 

Data Capture Information Data Captured Description Da

University of Colorado Norlin Library Sixth ERDA workshop on personnel neutron dosimetry. 09/University of Rochester Miner Library Using threshold detectors for neutron measurement at the Cosmotron. 08/Unknown Site and NYOO status reports, environmental reports, and beryllium 

reports. 

04/

Viacom Records Newsletter noting that Westinghouse equipment powered the 

Brookhaven Cosmotron. 

12/

TOTAL 

Table A7-2: Database Searches for Brookhaven National Laboratory 

Database/Source Keywords / Phrases 

Note: The normally-prescribed publicly-accessible Internet database searches were not performed for Brookhaven. These searches were not 

being an active DOE site and the cooperation of the site in making available to the Data Capture Teams the collections of relevant data of wh

Internet searches were conducted to attempt to locate data not available via the site's resources. 

Table A7-3: OSTI Documents Ordered for Brookhaven National Laboratory 

Document Number Document Title 

NA OSTI ID: 4410609 SRDB: 71851 

Design and Dosimetry of a Strontium-90--yttrium-90 Beta Irradiation Facility from Health Phys., v. 26, no. 1, pp. 99-101 

07/

CONF-8705273- OSTI ID: 5168103 SRDB: 71828 

What is a Low Dose of Radiation from Int J Radiat Biol Relat Stud Phys, Chem, Med Vol. 53(1):1-12, 01/02/1988 

07/

NA OSTI ID: 4096108 SRDB: 71827 

Radiopharmaceuticals from Phys. Rep., v. 21, no. 6, pp. 315-367 07/

BNL-22664 OSTI ID: 6621747 SRDB: 71825 

Chronic Lymphocytic Leukemia: Concepts and Observations from Blood Cells Vol 3:637-649 

07/

119 of 120 
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120 of 120 

Table A7-3: OSTI Documents Ordered for Brookhaven National Laboratory 

Document Number Document Title 

BNL-10490 OSTI ID: 4421770 SRDB: 71849 

Improved Thermoluminescence Dosimetry System from Health Phys., 13: 567-73(June 1967). 

07/

BNL-17025 OSTI ID: 4569426 SRDB: 71850 

Radiation and Alarm System (Amos II) for Habitable Areas of an Accelerator Complex from Health Phys. 24: No. 4, 442-443(Apr 1973) 

07/

NA OSTI ID: NA SRDB: 56600 

A Whole Body Counter with an Invariant Response to Radionuclide Distribution and Body Size by S. H. Cohn, et al., Phys. Med. Biol. 14:4, pp. 645-658 (1969) 

12/

HKF-116(Rev) OSTI ID: NA SRDB: 54015 

Quarterly Report for October 1 to December 31, 1951 10/

HKF-1492D-41(Del) OSTI ID: NA SRDB: 54017 

Plutonium Production Reactor Progress Memorandum dated 9/25/1951 10/

M-4414 OSTI ID: NA SRDB: 54018 

Brookhaven National Laboratory Pile Operating Manual Book No. 2 dated 4/1/1949 

10/

HKF-1492D-39 OSTI ID: NA SRDB: 53179 

Criticality Hazards in Processing 1% Enriched Uranium dated 9/24/1951 

10/

BNL-52256 OSTI ID: 6628605 SRDB: 48682 

Action Plan for the Tiger Team Assessment Report dated 8/30/1990 08/

DOE/EH-0140 Vol. 2 OSTI ID: 6774838 SRDB: 48283 

Tiger Team Assessment of the Brookhaven National Laboratory Volume 2 dated 06/01/1990 

08/