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SEC Petition Evaluation Report

Petition SEC-00109 

Report Rev #:1 Report Submittal Date: August 13, 2012 

Petition Administrative Summary

Petition Under Evaluation

Petition # Petition 

Type

Petition

Receipt Date

Qualification Date DOE/AWE Facility Name

SEC-00109 83.13 April 3, 2008 May 29, 2008 Los Alamos National Laboratory (LANL)

Petitioner-Requested Class Definition 

Service Support Workers (which includes, but is not limited to, security guards, firefighters, laborers, custodians, carpenters, 

plumbers, electricians, pipefitters, sheet metal workers, ironworkers, welders, maintenance workers, truck drivers, delivery 

persons, rad technicians, and area work coordinators) who worked in any operational Technical Areas with a history of 

radioactive material use at the Los Alamos National Laboratory from January 1, 1976 through December 31, 2005.

Class Evaluated by NIOSH

Service Support Workers (which includes, but is not limited to, security guards, firefighters, laborers, custodians, carpenters, 

plumbers, electricians, pipefitters, sheet metal workers, ironworkers, welders, maintenance workers, truck drivers, delivery 

persons, rad technicians, and area work coordinators) who worked in any operational Technical Areas with a history of 

radioactive material use at the Los Alamos National Laboratory from January 1, 1976 through December 31, 2005.

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

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

at the Los Alamos National Laboratory in Los Alamos, New Mexico from January 1, 1976 through December 31, 1995, 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

SEC-00051

SEC-00061 

SEC-00170

83.13

83.14 

83.14

Los Alamos National Laboratory

Los Alamos National Laboratory

Los Alamos National Laboratory

One class added to the SEC

One class added to the SEC

One class added to the SEC

Related Evaluation Report Information 

Report Title DOE/AWE Facility Name

SEC Petition Evaluation Report for Petition SEC-00051

SEC Petition Evaluation Report for Petition SEC-00061 

SEC Petition Evaluation Report for Petition SEC-00109, Rev. 0 

SEC Petition Evaluation Report for Petition SEC-00170

Los Alamos National Laboratory (LANL)

Los Alamos National Laboratory (LANL)

Los Alamos National Laboratory (LANL)

Los Alamos National Laboratory (LANL)

SEC Petition Evaluation Prepared By: [Signature on File] 8/15/2012

Gregory Macievic Date

SEC Petition Evaluation Reviewed By: [Signature on File] 8/14/2012

J. W. Neton Date

SEC Evaluation Approved By: [Signature on File] 8/15/2012

Stuart L. Hinnefeld Date
SEC-00109, Rev. 1 08-13-12 LANL

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Evaluation Report Summary: SEC-00109, 

Los Alamos National Laboratory (LANL)

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. 

NOTE: This document is Rev. 1 of the SEC Petition Evaluation Report for Petition SEC-00109. In its 

initial (Rev. 0) report, dated January 22, 2009, NIOSH concluded that it had access to sufficient 

information to estimate with sufficient accuracy the radiation doses for members of the class under 

evaluation. Since that initial evaluation, following multiple meetings of the Advisory Board Work 

Group on LANL and subsequent research, NIOSH now finds that it lacks sufficient information to 

estimate with sufficient accuracy the potential internal exposures to fission and activation products, 

and various other radionuclides of concern. This has resulted in a proposed class to be added to the 

SEC, as discussed in greater detail below and throughout this report. 

Petitioner-Requested Class Definition

Petition SEC-00109 was received on April 3, 2008, and qualified on May 29, 2008. The petitioner 

requested that NIOSH consider the following class: Service Support Workers (which includes, but is 

not limited to, security guards, firefighters, laborers, custodians, carpenters, plumbers, electricians, 

pipefitters, sheet metal workers, ironworkers, welders, maintenance workers, truck drivers, delivery 

persons, rad technicians, and area work coordinators) who worked in any operational Technical 

Areas with a history of radioactive material use at the Los Alamos National Laboratory from January 

1, 1976 through December 31, 2005. 

Class Evaluated by NIOSH

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

the following class: Service Support Workers (which includes, but is not limited to, security guards, 

firefighters, laborers, custodians, carpenters, plumbers, electricians, pipefitters, sheet metal workers, 

ironworkers, welders, maintenance workers, truck drivers, delivery persons, rad technicians, and area 

work coordinators) who worked in any operational Technical Areas with a history of radioactive 

material use at the Los Alamos National Laboratory from January 1, 1976 through December 31, 

2005. 

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

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

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSHproposed class includes all employees of the Department of Energy, its predecessor agencies, and their 

contractors and subcontractors who worked at the Los Alamos National Laboratory in Los Alamos, 

New Mexico from January 1, 1976 through December 31, 1995, for a number of work days 
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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 end date specified for the class under evaluation (December 31, 2005) 

was changed to December 31, 1995for the proposed class (see Section 3.0 in this report) based on 

NIOSH’s presumption that LANL would have been in full compliance with 10 CFR 835, 

Occupational Radiation Protection, by that date. Full legal compliance with §835.402 requires 

routine bioassay monitoring for all radiological workers who, under typical conditions, are likely to 

receive a committed effective dose equivalent of 0.1 rem (0.001 sievert) or more from all occupational 

radionuclide intakes in a year. 

Feasibility of Dose Reconstruction

In its initial (Rev. 0) SEC Petition Evaluation Report for Petition SEC-00109, dated January 22, 2009, 

NIOSH concluded that it had access to sufficient information to: (1) estimate the maximum radiation 

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

incurred in plausible circumstances by any member of the class; or (2) estimate radiation doses of 

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

Since that initial evaluation, following multiple meetings of the Advisory Board Work Group on 

LANL and subsequent research, NIOSH now finds that it lacks sufficient information, which includes 

biological monitoring data, sufficient air monitoring information, or sufficient process and 

radiological source term information, to allow it to estimate with sufficient accuracy the potential 

internal exposures to fission and activation products, and various other radionuclides of concern, to 

which the proposed class may have been subjected.

Consequently, per EEOICPA and 42 C.F.R. § 83.13(c)(1), NIOSH has established that it does not 

have access to sufficient information to: (1) estimate the maximum radiation dose, for every type of 

cancer for which radiation doses are reconstructed, that could have been incurred in plausible 

circumstances by any member of the class; or (2) estimate radiation doses of members of the class 

more precisely than an estimate of maximum dose. Information available from the site profile and 

additional resources is not sufficient to document or estimate the maximum internal and external 

potential exposure to members of the proposed class under plausible circumstances during the 

specified period. 

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

• Principal sources of internal and external radiation for members of the proposed class included 

exposures to plutonium, uranium, tritium, fission and activation products, transuranic 

radionuclides, nuclear reactors, linear accelerators, radiography equipment, and a wide variety of 

other radioactive materials.

• NIOSH has determined that the available information is adequate to allow bounding of external 

radiation doses with sufficient accuracy for the proposed class of LANL workers. NIOSH also 

finds that it is likely feasible to reconstruct with sufficient accuracy the occupational medical dose 

for LANL workers.
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• NIOSH previously determined in its evaluations of petitions SEC-00051 and SEC-00170 that 

LANL workers could have received intakes of radioactive materials that went unmonitored during 

the period from March 15, 1943 through December 31, 1975, and that limitations in the available 

data did not allow NIOSH to estimate such radiation doses with sufficient accuracy. As a result, 

in 2010, the Department of Health and Human Services (DHHS) designated the following class 

for inclusion in the SEC: 

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

subcontractors who worked at the Los Alamos National Laboratory in Los Alamos, New Mexico 

from March 15, 1943 through December 31, 1975, 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. (DHHS, 2010) 

• In SEC-00051, NIOSH stated that it would continue its evaluation to determine at what historical 

point the available information and data would become adequate to: (1) estimate the maximum 

radiation dose incurred by any site worker; or (2) estimate radiation doses more precisely than a 

maximum dose. Through the course of on-going research, NIOSH has been unable to demonstrate 

that the limitations identified in its SEC-00051 and SEC-00170 evaluations did not persist beyond 

December 31, 1975. Specifically, NIOSH could not locate sufficient documentation to 

demonstrate that some radionuclides (e.g., certain alpha-emitters and fission and activation 

products) were monitored in a manner equivalent to the monitoring programs established for other 

well-monitored nuclides (e.g., plutonium and uranium). 

• NIOSH selected the end date of December 31, 1995 for the proposed class based on its 

presumption that LANL would have been in full compliance with 10 CFR 835, Occupational 

Radiation Protection, by that date. Full legal compliance with §835.402 requires routine bioassay 

monitoring for all radiological workers who, under typical conditions, are likely to receive a 

committed effective dose equivalent of 0.1 rem (0.001 sievert) or more from all occupational 

radionuclide intakes in a year. Dose reconstruction limitations during this period included the 

inability to bound unmonitored intakes of exotic alpha emitters, fission products, and activation 

products. NIOSH will continue to evaluate these issues for the post-1995 period. 

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

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

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

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

than a maximum dose estimate.

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

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

available for an individual claim (and that can be interpreted using existing NIOSH dose 

reconstruction processes or procedures). Therefore, dose reconstructions for individuals employed 

at LANL during the period from January 1, 1976 through December 31, 1995, but who do not 

qualify for inclusion in the SEC, may be performed using these data as appropriate. 
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Health Endangerment Determination

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

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

of the proposed class. 

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 intakes of inadequately 

monitored radionuclides and from direct exposure to radioactive materials. 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 this employment or in 

combination with work days within the parameters established for one or more other SEC classes. 
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Table of Contents

1.0 Purpose and Scope .......................................................................................................................... 9

2.0 Introduction .................................................................................................................................... 9

3.0 SEC-00109 Los Alamos National Laboratory Class Definitions ................................................. 10

3.1 Petitioner-Requested Class Definition and Basis ................................................................ 10

3.2 Class Evaluated by NIOSH ................................................................................................. 11

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

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

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

4.2 ORAU Technical Information Bulletins (OTIBs) and Procedures ..................................... 15

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

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

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

4.6 Other Technical Sources ...................................................................................................... 17

4.7 Documentation and/or Affidavits Provided by Petitioners ................................................. 18

5.0 Radiological Operations Relevant to the Class Evaluated by NIOSH ......................................... 19

5.1 LANL Plant and Process Descriptions ................................................................................ 19

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

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

5.2.1.1 Plutonium ................................................................................................. 21

5.2.1.2 Hydrogen-3 (Tritium) ............................................................................... 21

5.2.2 External Radiological Exposure Sources from LANL Operations ......................... 24

5.2.2.1 Photon ....................................................................................................... 24

5.2.2.2 Beta ........................................................................................................... 25

5.2.2.3 Neutron ..................................................................................................... 25

5.2.3 Incidents .................................................................................................................. 26

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

6.1 Available LANL Internal Monitoring Data ......................................................................... 28

6.2 Available LANL External Monitoring Data ........................................................................ 32

7.0 Feasibility of Dose Reconstruction for the Class Evaluated by NIOSH ...................................... 39

7.1 Pedigree of LANL Data ....................................................................................................... 39

7.1.1 Internal Monitoring Data Pedigree Review ............................................................. 40

7.1.2 External Monitoring Data Pedigree Review ............................................................ 41

7.2 Evaluation of Bounding Internal Radiation Doses at LANL .............................................. 41

7.2.1 Evaluation of Bounding Process-Related Internal Doses ........................................ 41

7.2.1.1 Urinalysis Information and Available Data .............................................. 44

7.2.1.2 Lung Counting Information and Available Data ...................................... 46

7.2.1.3 Other Types of Bioassay .......................................................................... 46

7.2.2 Evaluation of Bounding Ambient Environmental Internal Doses ........................... 47
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7.2.3 Methods for Bounding Internal Dose at LANL ...................................................... 47

7.2.3.1 Methods for Bounding Operational Period Internal Dose ........................ 47

7.2.3.2 Methods for Bounding Ambient Environmental Internal Dose ............... 53

7.2.4 Internal Dose Reconstruction Feasibility Conclusion ............................................. 53

7.3 Evaluation of Bounding External Radiation Doses at LANL ............................................. 53

7.3.1 Evaluation of Bounding Process-Related External Doses ....................................... 54

7.3.2 Evaluation of Bounding Ambient Environmental External Doses .......................... 56

7.3.3 LANL Occupational X-Ray Examinations ............................................................. 56

7.3.4 External Dose Reconstruction Feasibility Conclusion ............................................ 56

7.4 Evaluation of Petition Basis for SEC-00109 ....................................................................... 57

7.4.1 Cerro Grande Fire .................................................................................................... 57

7.4.2 Sigma Americium Contamination Incident ............................................................. 57

7.4.3 Neptunium Special Hazards .................................................................................... 57

7.5 Other Potential SEC Issues Relevant to the Petition Identified During the Evaluation ...... 59

7.6 Summary of Feasibility Findings for Petition SEC-00109 .................................................. 61

8.0 Evaluation of Health Endangerment for Petition SEC-00109 ...................................................... 62

9.0 Class Conclusion for Petition SEC-00109 ................................................................................... 62

10.0 References .................................................................................................................................... 65

Attachment 2: Data Capture Synopsis ................................................................................................... 83

Tables 

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

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

6-1: Number of Records in the LANL in vivo Database ....................................................................... 29

6-2: Number of LANL Urinalysis Samples, 1976-2005 ....................................................................... 31

6-3: Dose Data Types Recorded Over Time ......................................................................................... 33

6-4: Annual External Radiation Doses (1976-2005) ............................................................................. 35

6-5: LANL Recorded Gamma Dose > 50 mrem ................................................................................... 36

6-6: LANL Recorded Shallow Dose > 50 mrem ................................................................................... 37

6-7: LANL Recorded Neutron Dose > 50 mrem ................................................................................... 38

7-1: Zia Employee Access to Plutonium Areas ..................................................................................... 45

7-2: Summary of Feasibility Findings for SEC-00109 .......................................................................... 61
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SEC Petition Evaluation Report for SEC-00109

1.0 Purpose and Scope

This report evaluates the feasibility of reconstructing doses for Service Support Workers (which 

includes, but is not limited to, security guards, firefighters, laborers, custodians, carpenters, plumbers, 

electricians, pipefitters, sheet metal workers, ironworkers, welders, maintenance workers, truck 

drivers, delivery persons, rad technicians, and area work coordinators) who worked in any operational 

Technical Areas with a history of radioactive material use at the Los Alamos National Laboratory 

from January 1, 1976 through December 31, 2005. 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 Division of Compensation Analysis and Support’s (DCAS) Internal 

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

2.0 Introduction 

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

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

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

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

reconstructions.2

 

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

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

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

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

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

estimate of the maximum radiation dose.

 

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

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

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

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

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

 

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

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

the detailed implementation guidelines available at http://www.cdc.gov/niosh/ocas.
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during a discrete incident likely to have involved levels of exposure similarly high to those occurring 

during nuclear criticality incidents. If the occurrence of such an exceptionally high-level exposure has 

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

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

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

classes. 

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 the 

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

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

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

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

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

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

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

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

3

 

3.0 SEC-00109 Los Alamos National Laboratory Class Definitions 

The following subsections address the evolution of the class definition for SEC-00109, Los Alamos 

National Laboratory (LANL). When a petition is submitted, the requested class definition is reviewed

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

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

class. If some portion of the petitioner-requested class is qualified, NIOSH will specify that class 

along with a justification for any modification of 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-00109 was received on April 3, 2008, and qualified on May 29, 2008. The petitioner 

requested that NIOSH consider the following class: Service Support Workers (which includes, but is 

not limited to, security guards, firefighters, laborers, custodians, carpenters, plumbers, electricians, 

pipefitters, sheet metal workers, ironworkers, welders, maintenance workers, truck drivers, delivery 

persons, rad technicians, and area work coordinators) who worked in any operational Technical 

Areas with a history of radioactive material use at the Los Alamos National Laboratory from January 

1, 1976 through December 31, 2005. 

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

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

 

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

available at http://www.cdc.gov/niosh/ocas.
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deemed the following information and affidavit statements sufficient to qualify SEC-00109 for 

evaluation: 

In the narrative attached to the petition, the petitioner points out that, when evaluating LANL 

petition SEC-00051 (covering 1943 through 1975), NIOSH determined “that the available 

monitoring records, process descriptions, and source-term data are not sufficient to complete dose 

reconstructions for the proposed class of employees, at a minimum, through December 31, 1975.” 

The petitioner asserts that the evaluation report (ER) indicates that data are insufficient for dose 

reconstruction after 1975. The petitioner provided a large amount of documentation to support this 

assertion (a listing is provided in Attachment 1). In the SEC-00051 ER, NIOSH did note that “the 

potential for monitored and unmonitored intakes has existed throughout the history of the site.” 

NIOSH also recognized that potential dose reconstruction issues may exist for the post-1975 

period (e.g., internal dose assessment for mixed fission products). On this basis, NIOSH 

determined that petition SEC-00109 qualified for further evaluation. The petitioner also reported 

on a meeting of the Advisory Board in which NIOSH staff stated that there are “still issues on the 

table after 1975” and that “evaluation of the mixed fission products and a few of the other issues 

past 1975” would continue in order to determine if additional years need to be added to the SEC 

class. (Petition, 2008) 

The petitioner also provided ten affidavits (listed in Section 4.7). A number of these affidavits 

asserted that Service Support Workers with inadequate or no PPE were routinely assigned to areas 

in which workers were using full PPE. They also asserted that these Service Support Workers had 

little or no participation in the LANL urine sampling or whole-body counting program. Because 

this petition qualified for further evaluation based on the issues discussed in the preceding 

paragraph, these affidavit statements will be considered during the evaluation. 

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

counts, whole-body counts, bioassay results, urinalysis results, external dosimetry data, and air 

monitoring data for LANL workers during the time period under evaluation. However, NIOSH also 

acknowledged that certain issues raised during the research for SEC-00051 remain unresolved, in 

particular the assessment of dose from mixed fission products. NIOSH concluded that there is 

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

that radiation exposures and radiation doses were not adequately monitored at LANL, either through 

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

qualified the petition for further consideration by NIOSH, the Board, and HHS. The details of the 

petition basis are addressed in Section 7.4. 

3.2 Class Evaluated by NIOSH

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

defined the following class for further evaluation: Service Support Workers (which includes, but is not 

limited to, security guards, firefighters, laborers, custodians, carpenters, plumbers, electricians, 

pipefitters, sheet metal workers, ironworkers, welders, maintenance workers, truck drivers, delivery 

persons, rad technicians, and area work coordinators) who worked in any operational Technical Areas 

with a history of radioactive material use at the Los Alamos National Laboratory from January 1, 

1976 through December 31, 2005. 
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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 their contractors and subcontractors who worked at the Los Alamos National Laboratory in Los 

Alamos, New Mexico from January 1, 1976 through December 31, 1995, 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. 

During the proposed class period, LANL employees were involved with research and development, 

testing of the nuclear weapons lifecycle, strategic defense research, development of arms control and 

treaty verification technology, energy research, atmospheric sciences, and nuclear waste research.

In its initial (Rev. 0) SEC Petition Evaluation Report for Petition SEC-00109, dated January 22, 2009, 

NIOSH concluded that it had access to sufficient information to: (1) estimate the maximum radiation 

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

incurred in plausible circumstances by any member of the class; or (2) estimate radiation doses of 

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

Since that initial evaluation, following multiple meetings of the Advisory Board Work Group on 

LANL and subsequent research, NIOSH now finds that it lacks sufficient information, which includes 

biological monitoring data, sufficient air monitoring information, or sufficient process and 

radiological source term information, to allow it to estimate with sufficient accuracy the potential 

internal exposures to fission and activation products, and various other radionuclides of concern, to 

which the proposed class may have been subjected. 

NIOSH previously determined in its evaluations of petitions SEC-00051 and SEC-00170 that LANL 

workers could have received intakes of radioactive materials that went unmonitored during the period 

from March 15, 1943 through December 31, 1975, and that limitations in the available data did not 

allow NIOSH to estimate such radiation doses with sufficient accuracy. In 2010, the Department of 

Health and Human Services (DHHS) designated the following class for inclusion in the SEC: 

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

subcontractors who worked at the Los Alamos National Laboratory in Los Alamos, New Mexico 

from March 15, 1943 through December 31, 1975, 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. (DHHS, 2010). 
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Through the course of ongoing research, NIOSH has been unable to satisfactorily demonstrate that the 

dose reconstruction limitations identified in its SEC-00051 and SEC-00170 evaluations did not persist 

beyond December 31, 1975. NIOSH selected the end date of December 31, 1995 for the proposed 

class based on its presumption that by January 1, 1996, LANL would have been in full compliance 

with 10 CFR 835, Occupational Radiation Protection, which states (10 CFR 835 pt. 402):

§835.402 Individual monitoring.

 (c) For the purpose of monitoring individual exposures to internal radiation, internal dosimetry 

programs (including routine bioassay programs) shall be conducted for:

(1) Radiological workers who, under typical conditions, are likely to receive a committed effective 

dose equivalent of 0.1 rem (0.001 sievert) or more from all occupational radionuclide intakes in a 

year.

DOE Occupational Radiation Exposure (DOE/EH-0575, 1997), Section 2.1, Radiation Protection 

Requirements, states:

10 CFR 835 became effective on January 13, 1994, and required full compliance by January 1, 

1996. In general, 10 CFR 835 codified existing radiation protection requirements in DOE Order 

5480.11. The rule provides nuclear safety requirements that, if violated, will provide a basis for 

the assessment of civil and criminal penalties under the Price-Anderson Amendments Act of 1988, 

Public Law 100-408, August 20, 1988 as implemented by 10 CFR 820 “Procedural Rules for DOE 

Nuclear Activities,” August 17, 1993. 

Dose reconstruction limitations during this period included the inability to bound unmonitored intakes 

of exotic alpha emitters, fission products, and activation products. NIOSH will continue to evaluate 

these issues for the post-1995 period. 

4.0 Data Sources Reviewed by NIOSH to Evaluate the Class

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

regarding LANL. The database search included the DOE Legacy Management Considered Sites 

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

Citations database, and the Hanford Declassified Document Retrieval System. In addition to general 

Internet searches, the NIOSH Internet search included OSTI OpenNet Advanced searches, OSTI 

Information Bridge Fielded searches, Nuclear Regulatory Commission (NRC) Agency-wide 

Documents Access and Management (ADAMS) web searches, the DOE Office of Human Radiation 

Experiments website, and the DOE-National Nuclear Security Administration-Nevada Site Officesearch. Attachment 2 contains a summary of LANL documents. The summary specifically identifies 

data capture details and general descriptions of the documents retrieved.
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In addition to the database and Internet searches listed above, NIOSH identified and reviewed 

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

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

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

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

4.1 Site Profile Technical Basis Documents (TBDs) 

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

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

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

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

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

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

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

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

LANL operations or related topics/operations at other sites: 

• TBD for the Los Alamos National Laboratory – Introduction, ORAUT-TKBS-0010-1; Rev. 01; 

October 1, 2007; SRDB Ref ID: 35193 

• TBD for the Los Alamos National Laboratory – Site Description, ORAUT-TKBS-0010-2; Rev. 

00; May 7, 2004; SRDB Ref ID: 19561 

• TBD for the Los Alamos National Laboratory – Occupational Medical Dose, ORAUT-TKBS0010-3; Rev. 01; September 14, 2010; SRDB Ref ID: 87132 

• TBD for the Los Alamos National Laboratory – Occupational Environmental Dose, ORAUTTKBS-0010-4; Rev. 01; March 26, 2010; SRDB Ref ID: 80164 

• TBD for the Los Alamos National Laboratory – Occupational Internal Dose, ORAUT-TKBS0010-5; Rev. 01; October 15, 2010; SRDB Ref ID: 74987 

• TBD for the Los Alamos National Laboratory – Occupational External Dose, ORAUT-TKBS0010-6; Rev. 02; November 23, 2009; SRDB Ref ID: 77688 
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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: Dose Reconstruction from Occupational Medical X-Ray Procedures, ORAUT-OTIB-0006, 

Rev. 04; June 20, 2011; SRDB Ref ID: 98147 

• OTIB: Analysis of Coworker Bioassay Data for Internal Dose Assignment, ORAUT-OTIB-0019, 

Rev. 01; October 7, 2005; SRDB Ref ID: 19438 

• OTIB: Fission and Activation Product Assignment for Internal Dose-Related Gross Beta and 

Gross Gamma Analyses, ORAUT-OTIB-0054, Rev. 00 PC-1, November 19, 2007; SRDB Ref ID: 

36235 

• OTIB: Internal Dosimetry Coworker Data for Los Alamos National Laboratory, ORAUT-OTIB0062, Rev. 00; October 15, 2009; SRDB Ref ID: 75028 

• OTIB: Los Alamos National Laboratory Bioassay Data Project Final Report; ORAUT-OTIB0063, Rev. 00; August 24, 2009; SRDB Ref ID: 73101 

• OTIB: Guidance on Assigning Occupational X-ray Dose Under EEOICPA for X-rays 

Administered Off Site, ORAUT-OTIB-0079, Rev. 00; January 3, 2011; SRDB Ref ID: 89563 

• PROC: Occupational Onsite Ambient Dose Reconstruction for DOE Sites, ORAUT-PROC-0060, 

Rev. 01; June 28, 2006; SRDB Ref ID: 29986 

• PROC: Occupational X-Ray Dose Reconstruction for DOE Sites, ORAUT-PROC-0061, Rev. 03; 

March 3, 2010; SRDB Ref ID: 79758 

4.3 Facility Employees and Experts

NIOSH talked with current LANL technical staff concerning additional data capture that was 

subsequently performed: 

• Conference Call A: ORAU Team and NIOSH with LANL Radiation Protection Division 

Personnel; August 7, 2008; SRDB Ref ID: 55742 

• Conference Call B: ORAU Team and NIOSH with LANL Radiation Protection Division 

Personnel; August 28, 2008; SRDB Ref ID: 55741

• Conference Call C: ORAU Team and NIOSH with LANL Radiation Protection Division 

Personnel; September 9, 2008; SRDB Ref ID: 55744
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4.4 Previous Dose Reconstructions

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

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

summarizes the results of this review. (NOCTS data available as of August 8, 2012) 

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

Description Totals

Total number of claims submitted for dose reconstruction 1361

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

under evaluation (January 1, 1976 through December 31, 2005). 863

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). 627

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

evaluated class definition 736

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

evaluated class definition 495

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

records could be obtained for the employee. As indicated in Table 4-1, NIOSH has been able to 

obtain monitoring data for many of the claims that meet the proposed class definition. Of the total 

number of claims submitted for energy employees who meet the class under evaluation, 736 (85%) 

contain internal monitoring data and 495 (57%) contain external monitoring data. 

The telephone interviews conducted with individual LANL claimants for dose reconstruction purposes 

provided additional detailed information regarding work locations, hours worked, incidents, and 

hazards encountered. The interviews also identified conditions for which there would have been 

potential for either internal or external exposures.

4.5 NIOSH Site Research Database

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

assessment of the evaluated class. Over 7,700 documents in this database were identified as 

pertaining to LANL. These documents were evaluated for their relevance to this petition. The 

documents include historical background on external and internal dosimetry programs and 

evaluations, monitoring reports, annual environmental reports, reviews and assessments of LANL, 

evaluations of specific buildings, site surveys, and facility and process descriptions. 
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4.6 Other Technical Sources

NIOSH reviewed the following technical sources in support of the evaluation of the proposed class: 

• Tritium Calculations with IMBA, OCAS-TIB-002, Office of Compensation Analysis and Support, 

Technical Information Bulletin, April 22, 2003; SRBD Ref ID: 22407 

• Overview of Los Alamos National Laboratory - 1997, LA-UR-97-4765; LANL Environment, 

Safety, and Health Division; 1998; SRDB Ref ID: 27224 

• Internal Dosimetry and Dose Assessment at Los Alamos National Laboratory, Inkret, W. C., 

LANL; 1993; SRDB Ref ID: 14522 

• Air Monitoring and Its Evolution at the LASL Plutonium Facility, LA-4076; LASL; 1969; SRDB 

Ref ID: 27223 

• History of LANL’s Bioassay Program from Inception to 1993, LA-UR-05-1942; Clark, M. J.; 

LANL; 2005; SRDB Ref ID: 17157 

• Brief History of Biological Monitoring and Dose Assessment for Tritium at Los Alamos, LANL, 

1987; SRDB Ref ID: 14512 

• Compendium of Reports on Various Nuclides, Work Groups and Operations, Circa 1945, LASL; 

1946; SRDB Ref ID: 14878 

• Evaluation of Polonium-210 Exposure for Termination Reports, LANL, 1979. SRDB Ref ID: 

14519 

• Interim Report of the Los Alamos Historical Document Retrieval and Assessment (LAHDRA) 

Project, ChemRisk et al.; Version 3B; July 27, 2004; SRDB RefID: 27260 

• Evaluation of Continuous Air Monitor Placement in a Plutonium Facility, J. J. Whicker, J. C. 

Rodgers, C. I. Fairchild, R. C. Scripsick, and R. C. Lopez; Health Physics, Volume 72, pp. 734–

743; 1997; SRDB Ref ID: 13095

• Relationship of Air Sample Measurements to Internal Dose: A Review, J. J. Whicker; Health 

Physics Society Midyear Topical Meeting; 2004; SRDB Ref ID: 13096

• In Vivo Assessment of Whole Body Radioisotope Burdens at the Los Alamos National Laboratory, 

D. G. Vasilik and I. C. Aikin; LA-9858-MS, Los Alamos National Laboratory; 1983: SRDB Ref 

ID: 925 

• Internal memorandum, Health Protection of Maintenance Personnel Working in Contaminated 

Areas, J. F. Tribby; Los Alamos Scientific Laboratory; May 14, 1946; SRDB Ref ID: 27980
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• Los Alamos National Laboratory (LANL) Bioassay Data Project Final Report, J. M. O’Brien; 

Shonka, Inc.; Atlanta, Georgia; June, 2006; SRDB Ref ID: 49287

• Identifying Uranium Intakes from Bioassay Data in the Presence of Environmental Background, 

T. T. Little, G. Miller, and R. Guilmette; Proceedings of the 49th Annual Radiobioassay & 

Radiochemical Measurements Conference; 2003; http://www.bioassay.org/2003; SRDB Ref ID: 

12939

• Health Physics Checklist, http://eshdb.lanl.gov/~esh12/new_eshdb/Matrices, accessed April 30, 

2004; SRDB Ref ID: 12969 

• Tiger Team Assessment of the Los Alamos National Laboratory, U.S. Department of Energy; 

November 1991; SRDB Ref ID: 23620 

• E-mail correspondence, LANL Lab Notebooks, J. Buddenbaum; ENSR|AECOM; Westford, 

Massachusetts; September 1, 2006; SRDB Ref ID: 27995 

• Conference Call Minutes, Final, J. Buddenbaum; ENSR|AECOM; Westford, Massachusetts; 

February 13, 2006; SRDB Ref ID: 27992

• Los Alamos National Laboratory Radiological Dose Assessment – Tritium Internal Dosimetry, W. 

C. Inkret, D. Lewis, G. Miller, and M. E. Schillaci; LA-UR-99-838; Los Alamos National 

Laboratory; 1999; SRDB Ref ID: 12899 

• Los Alamos National Laboratory Radiological Dose Assessment – Tritium Internal Dosimetry and 

Bioassay Programs, Inkret, W. C., D. Lewis, T. T. Little, G. Miller, and M. E. Schillaci, 

LA-UR-99-832; Los Alamos National Laboratory; 1998; SRDB Ref ID: 13485 

• Los Alamos National Laboratory Radiological Dose Assessment – Americium Internal Dosimetry 

and Bioassay Program, W. C. Inkret, D. Lewis, G. Miller, and M. E. Schillaci; LA-UR-99-836; 

Los Alamos National Laboratory; 1998; SRDB Ref ID: 13488 

4.7 Documentation and/or Affidavits Provided by Petitioners

In qualifying and evaluating the petition, NIOSH reviewed a large number of documents submitted by 

the petitioners prior to the Rev. 0 version of this evaluation report. These documents are in the file of 

supporting documents submitted with the SEC-00109 Petition (OSA Ref ID: 105765); the document 

titles and/or descriptions can be found in the first list provided in Attachment 1. This same file also 

contains the following ten affidavits from workers or survivors: 

• Affidavit from D&D Laborer, February 13, 2008; pdf pp. 213-214 

• Affidavit from Security Officer, March 24, 2008; pdf pp. 173-175 

• Affidavit from Assembly Technician, April 12, 2005; pdf pp. 204-208 
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• Affidavit from Laborer (unspecified), June 6, 2006; pdf pp. 211-212 

• Affidavit from Survivor of Uncle who worked as Chemical Plant Operator, Prototype Machinist, 

and Plant Engineering Technician; February 28, 2007; pdf pp. 215-216 

• Affidavit from Engineer-Operator, March 18, 2008; pdf pp. 186-199 

• Affidavit from Electrician, June 21, 2006; pdf p. 176 

• Affidavit from Custodial Worker, February 12, 2008; pdf pp. 209-210 

• Affidavit from current staff member of the Office of Nuclear Worker Advocacy (State of New 

Mexico) and former LANL administrative worker; also documenting work history of deceased 

father who worked as a Truck Driver; March 21, 2008; pdf pp. 177-181 

• Affidavit from Radiation Technician, April 12, 2005; pdf pp. 200-203 

After the issuance of Rev. 0 of the SEC-00109 Evaluation Report, and prior to the issuance of this 

Rev. 1 version, the petitioners submitted additional supporting material, including a slide presentation, 

two videos, and additional documents. Titles and/or descriptions can be found in the second list 

provided in Attachment 1. 

5.0 Radiological Operations Relevant to the Class Evaluated by 

NIOSH

The following subsections summarize both radiological operations at the LANL from January 1, 1976 

through December 31, 2005 and the information available to NIOSH to characterize particular 

processes and radioactive source materials. From available sources NIOSH has gathered process and 

source descriptions, information regarding radionuclides of concern, and information describing 

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

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

only to be a summary of the available information. 

5.1 LANL Plant and Process Descriptions 

NOTE: The LANL Evaluation Report for Petition SEC-00051 (covering 1943 through 1975) provides 

a detailed historical description of the LANL site. Additional information can also be found in the 

Site Description TBD of the Site Profile, ORAUT-TKBS-0010-2. The following discussion focuses 

on the time period currently under evaluation (1976 through 2005). 

Nuclear weapons-related activities have been the primary function of LANL since the laboratory was 

established in 1943. Since that time until 2006, including the entire period covered by this evaluation, 

the laboratory was managed by the University of California. Work with radioactive materials in the 

very early years involved primarily plutonium, enriched uranium, and fission products. Since those 
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early years through the present time, the site has been performing a variety of activities involving a 

wide array of radioactive materials, nuclear reactors, accelerators, and other machines that generate 

ionizing radiation. 

To accomplish its mission, LANL was divided into a number of physically separate Technical Areas 

(TAs) which spread in time over a relatively large area. These TAs and locations, along with their 

significant radiation sources, are briefly described in Table 5-1 of the Evaluation Report for Petition 

SEC-00051. 

The LANL site’s main functional areas include:

• Weapons Development and Testing 

• Critical Assemblies, Reactors, and Reactor Development

• Accelerators, X-ray Equipment, and Radiography Sources 

• Biomedical Research

• Project Sherwood and Fusion Research 

• Waste Treatment and Disposal

Overviews of each of these functional areas are presented in Section 5.2 of the SEC-00051 Evaluation 

Report. More detailed information on TAs and functional areas is also available in ORAUT-TKBS0010-2. 

5.2 Radiological Exposure Sources from LANL Operations

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

LANL class under evaluation. 

5.2.1 Internal Radiological Exposure Sources from LANL Operations

In the SEC-00051 Petition Evaluation Report, data deficiencies for mixed fission and mixed activation 

products, Am-241 (separated from plutonium), Th-232, Th-230, Ac-227, Pa-231, Np-237, and 

Cm-244 were identified for the 1970 through 1975 time period. NIOSH subsequently recognized that 

these internal dose reconstruction issues may also exist for the post-1975 period. On this basis, 

NIOSH determined that this current petition (SEC-00109) qualified for evaluation. Potential intakes of 

these “exotic” radionuclides are therefore a focus of this evaluation report. The primary exposure 

sources (tritium, uranium, and plutonium) are also included for completeness. 

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

alpha particles do not present an external exposure hazard, prevention of internal exposures to alphaemitters was recognized from the onset of site operations as the most significant radiological hazard 

protection challenge.

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

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

potentially contributing to internal dose to LANL workers. This list is not all-inclusive, but it includes 

all of the more significant sources of internal radiation dose. Radionuclides that emit both alpha and 
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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. 

Specific TAs where various radionuclides may have been present are provided in Table 5-1 of the 

SEC-00051 Evaluation Report. 

Table 5-1: Potential Contributors to LANL Internal Dose and Their 

Primary Modes of Decay 

Radionuclide Primary Mode of Decay

H-3 Beta

Sr-90/Y-90 Beta

Mixed Fission Products (MFP) Beta

Mixed Activation Products (MAP) Beta

Ac-227 Alpha (progeny)

Th-230 Alpha

Th-232 Alpha

Pa-231 Alpha

uranium Alpha

Np-237 Alpha

plutonium Alpha

Am-241 Alpha

Cm-244 Alpha

5.2.1.1 Plutonium 

Freshly-separated weapons-grade plutonium is comprised of nominally 93% by weight Pu-239, 6% 

Pu-240, and less than 1% (combined) of Pu-238, Pu-241, and Pu-242. With time, Am-241 begins to 

“grow in” to the mix as Pu-241 decays. Kilogram quantities of weapons-grade plutonium have been 

handled at LANL throughout its history. 

Beginning in 1968, heat sources (radioisotope thermoelectric generators) containing primarily Pu-238 

were developed at LANL for space electric-power applications and for powering artificial organs. 

Such programs involving the use of Pu-238 have been on-going for the duration of this evaluation 

period. 

5.2.1.2 Hydrogen-3 (Tritium)

Tritium is a primary component of thermonuclear weapons and was used extensively at LANL 

throughout the time period under evaluation. Megacurie quantities of H-3 have been handled at 

LANL. Tritium at LANL has taken several forms, including water (HTO), organically-bound tritium 

(OBT), metal tritide (MT), and gaseous hydrogen (T2 or HT). Gaseous tritium could have been 

contained as a pressurized gas or adsorbed onto various metals (e.g., uranium or palladium). 
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5.2.1.3 Uranium 

Depleted and natural uranium compounds were commonly used in kilogram quantities at LANL. 

Enriched uranium and U-233 were used in critical assemblies. The U-233 contained U-232 as an 

unavoidable contaminant. 

5.2.1.4 Mixed Fission and Activation Products 

Mixed fission and products (MFP) and mixed activation products (MAP) are generally beta and/or 

gamma-emitters. MFP is common in reactor areas. MFP includes Cs-137, Sr-90, radioactive noble 

gases, and others. MAP is common in accelerator and reactor areas. MAP includes C-11, N-13, O15, Ar-41, Be-7, Na-22, Na-24, Co-58, Co-57, Mn-54, Mn-52, V-48, and others. A recognized 

non-reactor location where exposure to MAP may have occurred during this time period was the Los 

Alamos Neutron Science Center/Los Alamos Meson Physics Facility (LANSCE/LAMPF). Although 

the predominant component of worker exposure in and around this facility would likely have been 

from external photons and neutrons (external dose was clearly the radiological concern that received 

the most attention from the LANL health physics staff), intakes of MAP also could have occurred. 

5.2.1.5 Strontium-90/Yttrium-90 

Sr-90/Y-90 is a common component of MFP. It is also listed separately here because it is a residual 

contaminant from the radioactive lanthanum (RaLa) program, in which case it could be present in 

some areas in the absence of other mixed fission products. The RaLa program ended in 1963 (Bayo, 

1963). Residual Sr-90 contamination from the RaLa program was still present in some areas after 

1975. H-1 Health Physics Quarterly Progress Reports for October-December 1979 and JanuaryMarch 1980 discuss decommissioning activities at Ten Site involving an estimated 0.021 Ci of Sr-90 

in 260 m3 of waste debris (Quarterly, 1979; Quarterly, 1980). A Radiological Work Permit from 1995 

addresses an asbestos removal operation involving Sr-90 contamination (RWP, 1995). 

5.2.1.6 Thorium-230 

In the 1950s, an effort was underway within the AEC complex to build a production capacity for 

Th-230 (also called “ionium”) as a potential heat source. It appears that LANL may have had some 

involvement with this effort since there were a number of bioassays conducted for Th-230 in the year 

1958. There is no evidence of its use since that time. 

5.2.1.7 Thorium-232 

According to the LANL Occupational Internal Dose TBD, casting, machining, and powder metallurgy 

were conducted with Th-232 at LANL (ORAUT-TKBS-0010-5). There is evidence of operations 

involving Th-232 beginning in the mid-1940s (Steele, 1998; SCA-TR-TASK1-0011). There are also 

indications that operations involving Th-232 continued into later years, as evidenced from an Office 

Memorandum from H-1 Division, dated October 29, 1976, titled Health Physics Aspects of Thorium. 

(Buckland, 1976). This memo compares Th-232 with depleted uranium with respect to specific 

activities. It also compares Th-232 to Pu-238 from an internal dose perspective, pointing out the 

tremendous difference between Th-232 and Pu-238 in terms of specific activity. Special Work 
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Permits (SWPs) for Radiation Work from 1992 discuss operations involving Th-232 contamination 

(SWP, 1992). 

5.2.1.8 Americium-241 

As mentioned in Section 5.2.1.1, Am-241 is a component that is always present in aged 

weapons-grade plutonium. There is also evidence that operations involving purified Am-241 took 

place at LANL during the time period under evaluation (post-1975). For example, a 1982 

memorandum that discusses the criteria for routine Am-241 urine sampling states: “However, in the 

plutonium recovery process Am-241 concentrates in the residues (which contain little plutonium) such 

that the weight percent of Am-241 is much larger than initial values. These high Am-241 content 

residues may be recycled for more efficient plutonium recovery, further processed to recover the 

Am-241 specifically, or prepared for recoverable storage. Personnel involved in these operations 

would be americium workers.” (Criteria, 1982). 

5.2.1.9 Neptunium-237 

Neptunium-237 was not a commonly-used radionuclide at LANL. There is, however, evidence of 

periodic operations involving Np-237 prior to 1975 and continuing to at least 2002. Approximately 

seven kg of Np-237 metal were used for a criticality experiment conducted in 2002 (Mosteller, 2003). 

A TA-55 “Radiological and Hazardous Work Permit,” dated August 30, 1994, addresses radiological 

issues for work involving Np-237 contamination (TA-55 RWP). The SEC-00109 petitioner also 

describes use of 100-gram quantities of neptunium powders (Neptunium, 2005). 

5.2.1.10 Actinium-227 

There is no indication that Ac-227 was frequently used post-1975. LANL research operations with 

Ac-227 were focused on its possible use as a “substitute” radionuclide to replace Po-210, which had a 

short half-life (DOE, 1993). The “substitute material” program was cancelled in 1955 (DOE, 1993). 

For the time period under evaluation (post-1975), only residual material would have formed a 

potential for a presumptive exposure. For example, decommissioning and decontamination of Filter 

Building 153 in 1978 (Harper, 1981) is likely to have resulted in potential exposures to Ac-227. 

5.2.1.11 Protactinium-231 

In a survey conducted by the Mound site in 1970, LANL projected its future needs for Pa-231 for the 

years 1979, 1980, and 1981, as 0.1 g, 30.1 g, and 11.0 g, respectively (Eppley, 1979). Another Mound 

site reference states that the semi-works operated at Mound from 1974 through 1979, and that during 

this time, 0.890 g of Pa-231 were produced (DOE, 1993). The end of Pa-231 processing in the 

semi-works precludes delivery of the material to LANL after 1979. Although NIOSH has been unable 

to find specific evidence of Pa-231 use at LANL, the topic is included in this section because it was 

identified in the SEC-00051 Evaluation Report as being a radionuclide for which internal dose 

reconstruction issues may exist after 1975. 
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5.2.1.12 Curium-244 

There is evidence that operations involving Cm-244 took place at LANL in the 1950s (and perhaps 

into the 1960s). In an external “Radiation Exposure Follow-up” report, dated 1985, there is mention 

of a weld encapsulation operation of highly-radioactive materials, including Cm-244 (Follow-up, 

1985). 

A special dose assessment for Cm-244 was performed in 2003 because an individual’s security badge 

triggered an alarm and was found to be contaminated with Cm-244 (Little, 2003). The source of the 

contamination was one of many uncharacterized items that site personnel had packed into a cooler and 

shipped to TA-59 for pre-disposal characterization. These were legacy items that had been placed 

inside two stainless steel boxes and stored inside a shielded pit in the hot cell area of TA-48. TA-48 

personnel were engaged in an effort to identify and dispose of unnecessary material so that the hazard 

category of the facility could be reduced. Quoting the Occurrence Report (ORPS, 2003), these items 

had been stored for “tens of years (at least one sample was dated 1970’s). The owner (as indicated by 

labeling on the boxes) has been retired from the laboratory for some time. When contacted by TA-48 

personnel, he did not remember what might be in the boxes.” Through a series of administrative 

oversights, the individual’s badge, smock, and radiological van became contaminated by Cm-244 

when she repackaged items in the van. The presence of this legacy material supports the notion that 

operations involving Cm-244 took place at some point during the site’s history. 

5.2.2 External Radiological Exposure Sources from LANL Operations

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

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

included numerous radioactive materials, nuclear reactors, particle accelerators, and miscellaneous Xray-generating equipment.

5.2.2.1 Photon 

Many LANL 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. 

• Uranium and associated decay progeny.

• Bremsstrahlung radiation from various beta-emitting radionuclides.

• X-ray-generating machines.

• Plutonium and associated decay progeny 

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

radionuclides. 
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5.2.2.2 Beta

LANL facilities during the period under evaluation involved diverse activities with an extensive beta 

particle-emitting source term. Beta radiation over a broad range of energies could have been 

encountered from: certain plutonium isotopes; uranium progeny; thorium progeny; tritium; activation 

and fission products from reactor and accelerator operations; and other radionuclides such as those 

used as calibration sources. 

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 continuum 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. 

 

5.2.2.3 Neutron 

There were several sources of potential neutron radiation exposure associated with LANL operations. 

Neutron exposures could have resulted from LANL weapons development operations, 

neutron-generating sources, criticality experiments, and operating reactors and accelerators. The 

source of the neutron emissions from these activities and potential worker exposure would have been 

associated with the following:

• Spontaneous fission 

• Alpha-neutron (α,n) reactions particularly with low-atomic-number elements

• Operating reactors

• Criticality experiments with plutonium or enriched uranium

• Accelerators

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

fission sources (Cf-252) 

The broad scope of LANL 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 up to 20 MeV. Estimated neutron energy spectra for 

various LANL operations are in SEC-00051, Table 5-4. More detailed information is available in 

ORAUT-TKBS-0010-6. 
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5.2.3 Incidents

After researching the historical monitoring programs and their records disposition, the LANL staff has 

provided the following accounting of incident-related records that are available:

Hardcopy Historical Incident Files (1944 – 1991), including: 

• Miscellaneous event-related and monitoring records 

• Type A/B/C investigation reports (also available through DOE/HSS) 

• Radiation Occurrence Reports (RORs) (1974 – 1991) 

- Record inventory summaries for each year 

- Datatrieve entry forms for each ROR

- Datatrieve printouts

- Details of events and personnel involved 

- Indications whether special bioassay was performed

• Radiological Incident Reports related to significant ROR events

Radiological Incident Reports (RIRs) / Radiation Protection Observations (RPOs): 

• Includes details of events and personnel involved 

• Name changed to RPO in 2005 

• Hardcopy for 1989-2000 in LANL archives

• Hardcopy RIRs archived in: 

- Late 1980s to early 1990s: FRC (Denver) 

- Late 1980s to early 1990s: NSSB (LANL, accessible) 

- Mid 1990s-2000: TA-35 (LANL, inaccessible – in transit to NSSB 

- 2001-present: database, TA-59 

ORPS Reports (1990-present): 

• DOE-maintained database includes details of events, but no personal information

Hardcopy Dose Assessment Reports (1998-present): 

• Includes methods, data, and results of special dose assessments 

Hardcopy Personnel Radiological Files (1944-present): 

• Includes any dose-related information incremental to routine dosimetry

Electronic Bioassay Data Repository (1944-present): 

• Includes all bioassay results (routine, special, in vitro, in vivo)

Internal Dosimetry Database (1944-present): 

• Includes bioassay and dose assessment results from Pu-238, Pu-239, Am-241, and H-3 intakes 

Personnel Dose Records (1944-present): 

• Internal doses for applicable individuals 

There was an attempt to comprehensively review LANL incidents in the past. In 1999, the Centers for 

Disease Control and Prevention (CDC) began the Los Alamos Historical Document Retrieval and 
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Assessment (LAHDRA) project. The purpose of the LAHDRA project was to identify information 

available concerning past releases of radionuclides and chemicals at the LANL site. Millions of 

documents were reviewed; however, issues regarding access to classified information prevented 

access to all files. As a result, a large but still partial chronology of incidents was compiled. The 

following incidents are examples of incident types that occurred during the time period under 

evaluation. These incidents are drawn from Appendix L of the 2007 Interim Report of CDC’s 

LAHDRA Project (LAHDRA, 2007). 

• January 1, 1976: Air release – Approximately 3271 Ci of tritium was released into the 

environment. 

• July 15, 1976: Air Release – Tritium release of 22,000 Ci from TA-3-34. 

• January 1, 1977: Air Release – Approximately 6417 Ci of tritium was released into the 

environment. 

• October 6, 1977: Air Release – Tritium release of 33, 800 Ci from TA-33-86. 

• November 11, 1977: Fire – At the TA-54 Burial Pit, seven bales of suspect low-level radioactive 

contaminated combustible waste auto-ignited.

• May 4, 1979: Air Release – Tritium release of approximately 3000 Ci from SM-34. 

• August 22, 1979 – Air Release – Approximately 200 grams of UF-6 was released at Building 23 

TA-18 Parajito Site.

• February, 1981: Contamination Events – A total of eleven minor radiation accidents were reported 

internally.

• October 14, 1981: Contamination Event – Plutonium contamination incident at TA-3, SM-29. 

• November, 1981: Contamination Events – A total of ten minor radiation releases were reported 

internally.

• November 2, 1982: Liquid Release – Approximately 50-100 liters of waste liquid escaped from a 

tank vent at TA-21-257, contaminating the roof, walls, and surrounding area with plutonium, 

americium, and uranium. 

• June 1, 1983: Air Release - High airborne plutonium levels were detected in Room 429 at TA-55 

Building PF-4. 

• February 17, 1984: Fire – Filter bags were ignited in the TA-50 Building 1 ventilation exhaust 

plenum. 

• September 12, 1985: Fire – A fire in a glove box at TA55-4-429 resulted in high airborne activity 

and area contamination. 
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• October 30, 1986: Air Release – An estimated 633 Ci of tritium were released at TA-33, mostly in 

the form of tritiated water.

• February 27, 1990: Liquid Release – Cooling water overflowed into the exhaust system of 

TA-55-4. 

• March 1, 2000: Air Release - Eight workers at TA-55 were exposed to airborne plutonium. 

• May, 2000: Fire – A wild fire was ignited that ultimately burned nearly 50,000 acres in and around 

Los Alamos. This incident was cited by the petitioner (see Section 7.4.1) 

• July, 2005: Contamination Event - Am-241 contamination occurred at the Sigma Facility due to 

repeated handling of highly-contaminated components with no radiological controls in place. This 

incident was cited by the petitioner (see Section 7.4.1) 

6.0 Summary of Available Monitoring Data for the Class Evaluated 

by NIOSH

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

monitoring data for the LANL class under evaluation. 

6.1 Available LANL Internal Monitoring Data

In vivo counting equipment and techniques were developed in the late 1950s and have been in routine 

use for measuring X-ray and gamma-ray-emitting radionuclides since June 1969 (Internal Dosimetry, 

2007). There are indications that some of the counts recorded between 1955 (program onset) and the 

1960s were performed for program development rather than actual suspected intakes. NIOSH has 

been unable to locate any records of these early in vivo measurements. A detailed discussion of the 

early years of in vivo counting is provided in the ER for petition SEC-00051. 

In 1970, an in vivo counter capable of measuring four separate regions of the body began operation 

(Vasilik, 1983). Twin Phoswich (CsI and NaI) detectors were placed over the lungs. The two layers 

of the detector were capable of simultaneously, yet separately, monitoring chest burdens for 10- to 

250-keV photons (NaI), and 200- to 2,000-keV photons (CsI) for a qualitative assessment of a variety 

of fission and activation nuclides. A planar High Purity Germanium (HPGe) detector monitored the 

region between 10 and 250 keV with excellent energy resolution and could be positioned over the 

liver or thyroid as needed. Finally, an HPGe (previously a GeLi) detector was positioned under the 

prone subject. This detector was primarily for whole-body assessment. This system could both 

identify radionuclides and quantify the body burden. Pu-239 and Am-241 were a routine part of the in 

vivo analysis library for all individuals receiving lung counts. In recent years, U-235 and Th-234 (as 

U-238) were added to the routine library. Other nuclides would be identified at their corresponding 

MDA levels if they appeared in the gamma spectrum. MDAs for whole-body counting and lung 

counting by historical period are provided in Tables 5-17 and 5-19 in ORAUT-TKBS-0010-5. 
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Table 6-1 summarizes the records in the in vivo database for the post-1975 period, including 

non-positive results.

Table 6-1: Number of Records in the LANL in vivo Database

(This table spans two pages)

Analyte Number of Records

(1976 - 2004)

Am-241 36,129

As-72 15

Be-7 957

Bi-213 3

Bi-214 6

Br-76 81

Br-77 82

C-11/N-13 1,374

Cd-109 96

Ce-141 80

Cf-249 9

Cm-244 1

Co-56 8

Co-57 16

Co-57/Co-58 1

Co-58 13

Co-60 322

Cr-51 8

Cs-134 277

Cs-137 350

Cu-64 8

Cu-67 7

Eu-152 513

Fe-59 7

“Fission Prods” 1

Ge-67/Ga-67 4

Ge-68/Ga-68 6

Hf-173 3

Hg-195m 80

Hg-197 102

Hg-197m 81

Hg-203 97

I-123 2

I-125 159

I-131 6

I-132 1

Mn-54 960

Na-22 1,347

Na-24 24

Nd-147 80

Os-185 82

Pb-212 4

Pb-214 3

Pu-238 15
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Table 6-1: Number of Records in the LANL in vivo Database

(This table spans two pages)

Analyte Number of Records

(1976 - 2004)

Pu-238/Pu-239 2

Pu-239 36,069

Rb-83 84

Rb-84 82

Sb-124 84

Sc-46 16

Se-72/As-72 5

Se-75 91

Sm-145 81

Ta-179 95

Te-132 1

Th-234 1,318

Tl-201 80

Tl-202 82

“Tungsten” 1

U-235 1,318

U-237 4

U-238 7

“Unidentified” 1

V-48 9

Zn-65 10

Zr-95 4

Zr-95/Nb-95 4

Table 6-2 below shows that bioassay results are available for the development of co-worker studies 

for use in dose reconstructions. Data values for H-3, U-235, and U-238 for Jan-Jun 91 are absent 

from the static data subsets the ORAU Team derived from the LANL bioassay database. There 

appears to have been a change in record-keeping practices during that period with a modern database 

coming on line in mid-1991. In addition, there was a shift in analytical technique from Uranium 

Neutron Activation Analysis (UNAA) to Radiometric Alpha Spectroscopy (RAS). 

Details regarding the various analyses used and the associated minimum detectable activities are 

presented in the Technical Basis Document for the Los Alamos National Laboratory - Occupational 

Internal Dose (ORAUT-TKBS-0010-5).
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Table 6-2: Number of LANL Urinalysis Samples, 1976-2005

Year Am-241 H-3 Pu-238 Pu-239

Pu-239 + 

Pu-240 Pu-240 Th-228 Th-229 U* U-234 U-235 U-238

1976 963 2714 2757 1738

1977 815 3043 3070 1780

1978 756 2434 2441 2653

1979 1390 2703 2713 2724

1980 1589 2689 2711 2951

1981 1282 3297 3328 2972

1982 1063 2192 2211 1874

1983 930 1998 1990 1342

1984 1361 2172 2170 1189

1985 1566 2086 2087 925

1986 1492 1983 1983 822

1987 1666 1973 1970 768

1988 1611 1931 1927 954

1989 1870 2197 2201 272*** 604***

1990 2197 2218 2219 394*** 953***

1991 30 1250 1099 1099 538 538 538

1992 38 2302 2248 2248 1358 1358 1358

1993 28 1975 2584 2584 1432 1432 1432

1994 47 1694 2390 2390 1602 1602 1602

1995 58 1957 2002 2002 1651 1651 1651

1996 13 1649 1947 1965 12 1026 1026 1026

1997 85 1681 3728 4674 506 227** 825 825 825

1998 220 1691 4665 5304 325 230 829 829 829

1999 245 1673 4166 4902 370 122 740 740 740

2000 228 1624 4393 4921 276 133 905 905 905

2001 190 1471 4177 5530 679 368 1272 1272 1272

2002 284 1406 4412 6581 1086 426 748 748 748

2003 208 1427 4670 7879 1607 2378 772 772 772

2004 287 1260 4281 7506 1626 3237 1065 1065 1065

2005 153 1353 3274 5633 1861 1371 7 7 844 844 844

* Reported uranium samples for 1976-1988 are for non-isotopic-specific urinalysis.

** The introduction of TIMS analysis in 1997 made the separation of Pu-240 possible.

*** 1989 through June 1991 comprises a transition period to a new analytical technique for uranium. The uranium results for U-235 and U-238 for 1989 

 and 1990 correspond to EU and DU.
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6.2 Available LANL External Monitoring Data

NOTE: The following discussion focuses on the time period for the class under evaluation (1976 

through 2005). For a historical summary of the LANL external monitoring program as it developed 

from the onset of operations in 1943, see the LANL Occupational External Dose TBD (ORAUTTKBS-0010-6). That document discusses the evolution of dosimetric technology, analytical 

techniques, MDAs, calibration procedures, and methods for estimating missed dose. 

Historically, LANL had an extensive radiation safety monitoring program using portable radiation 

instruments, contamination surveys, zone controls, and personnel dosimeters for measuring exposure 

in the workplace. This program was conducted directly by, or under the guidance of, a speciallytrained group of radiation monitors or radiation protection technologists. The relevant types of 

personnel dosimetry technology in use during the time period under evaluation are listed below.

• The Cycolac film badge was adopted in 1962 and used until 1978. The multi-element Cycolac 

used several filters and two film packets: a DuPont 543 packet that contained DuPont 502 dental 

film and an Eastman Kodak Type B packet that contained an NTA fast neutron film. In addition, 

it contained indium, gold, and sulfur foils for accident dosimetry. The Cycolac badge was 

improved relative to earlier LANL dosimeters and was considered to have the advantages of 

relative gamma and X-ray energy independence (within 30%) from about 30 keV to 1,400 keV, 

the ability to evaluate thermal neutrons in the presence of X- and gamma radiations below 400 

keV, and improved directional independence. 

• Beginning in 1978, LANL began conversion to the Model 7776 thermoluminescent dosimeter 

(TLD). The TLD had cadmium (for use in neutron radiation fields) and non-cadmium versions. It 

incorporated copper, Cycolac plastic, and cadmium filters and used three TLD-700 chips (one 

covered with copper, one with thin Cycolac plastic, and the third with thicker plastic) and one 

TLD-600 chip (enriched in 6

Li). In the cadmium badge, the third TLD-700 chip and the TLD-600 

chip were shielded by cadmium pockets, as opposed to plastic covers in the non-cadmium badge. 

The changeover from film dosimeters to TLDs as the dosimeter of record was completed on 

January 1, 1980. The Model 7776 dosimeter was not designed to meet the DOELAP performance 

criteria for those categories involving low-energy beta particles or mixtures of beta and 

low-energy photons (Hoffman, 1999, pdf p. 4). 

Neutron dose determination with the Model 7776 dosimeter relied on the use of site- and 

operation-specific neutron correction factors (NCFs) to improve accuracy of the assigned neutron 

dose. TLD albedo dosimeters are sensitive to intermediate and lower-energy neutrons that other 

dosimetry methods could not detect, but their net neutron signal was highly energy-dependent and 

required the use of workplace-specific NCFs to convert the response to dose. NCFs could vary by 

more than an order of magnitude. As a consequence, NCFs that were assigned had conservative 

values; therefore, neutron doses were typically overestimated by factors of two to three 

(Blackstock, 1978). A detachable holder for NTA film was included in the Model 7776 TLD 

badge design to improve fast neutron measurement (Mallett, 1990). 
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• In 1995, LANL began using the Model 8823 TLD and a Track-Etch Dosimeter (TED or PN3), 

that is sensitive only to neutron radiation and employed for special field conditions. The Model 

8823 is an improved TLD design that contains two TLD cards containing a total of 8 TLD 

sensitive elements. The TED component contains three dosimetry-grade CR-39 track-etch plastic 

foils (Hoffman, 1999, pdf p. 30). The foils are placed in a hemispherically-shaped ABS plastic 

case on the sides of a triangular polystyrene pyramid to minimize angular dependence of the TED. 

(Hoffman, 1999, pdf p. 30). The Model 8823 became the dosimeter of record for LANL on April 

1, 1998. It satisfies DOELAP performance criteria in all categories and continues in use until the 

present.

Due to historical changes in dosimetric technology and analytical methodology, workers exposures 

have been recorded in different data types. Table 6-3 summarizes the dose data types that have been 

recorded in LANL worker exposure records over time. Interpretations of these data types for dose 

reconstruction are detailed in ORAUT-TKBS-0010-6, Attachment A. 

Table 6-3: Dose Data Types Recorded Over Time

Period Dose Data Types Recorded in Personnel Exposure Records

1960–1979 Gamma dose (rem)

Beta dose (rad)

Thermal neutron dose (rem)

Fast neutron dose (rem)

1980–1997 "Non-penetrating Rad" 

"Penetrating-rem" 

"Neutron-rem" 

"Total-rem" 

1998–present Beta shallow DE (mrem) 

Beta eye DE (mrem) 

Gamma shallow DE (mrem) 

Gamma deep DE (mrem) 

Gamma eye DE (mrem) 

Neutron deep DE (mrem) 

Total shallow DE (mrem) 

Total deep DE (mrem) 

Total eye DE (mrem) 

Total deep neutron DE (mrem)

Sources: LASL, 1977; LASL, 1979; LANL, 1986; LANL, 1989; LANL, 1996; LANL, 

2001; LANL, 2003
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LANL has always implemented a policy of monitoring individuals with the highest potential for 

exposure. When monitoring for external radiation exposures began in 1943, PICs were assigned to “a 

few persons thought to have the highest potential for receiving exposures at or above the ‘tolerance’ 

limit” (LANL, 1986, 10/6/81 Questionnaire). By 1945, when film badges were in use by a number of 

LANL groups, only workers with the “higher exposure potentials” were issued dosimeter badges 

(LANL, 1986, 10/6/81 Questionnaire). As of 1960, film badges were worn by about half of 

University of California employees, all of the Security Force, and 75% of Zia employees (LASL, 

1969). Between 1943 and late 1981, the number of persons monitored for external exposures 

increased from less than 100/yr to more than 5,000/yr, but personnel monitoring for external radiation 

still had not been extended to all LANL workers (LANL, 1996). In the 1970s, LANL initiated an 

Employee Health Physics Checklist (LANL, 2004a). This checklist allowed the evaluation of each 

individual for potential internal and external exposure. Individuals were placed on the appropriate 

monitoring schedule based on this checklist. During the first quarter of 1976, 50 such checklists were 

completed, as evidenced by the Group H-1 Health Physics Quarterly Progress Report, January – 

March, 1976 (Quarterly, 1976). The checklist is still used and was computerized in 1998 as the 

Dosimetry Enrollment System.

Table 6-4 lists the reported numbers of workers monitored by LANL from 1976 to 2003 along with 

total and average doses calculated from those data (LANL, 2004b). Estimates of the total number of 

workers employed at LANL each year are also presented. The estimated number of LANL workers 

for each year was obtained from a number of LANL sources; these values are quite uncertain for some 

years. Consequently, for some years the number of total workers supplied by LANL is smaller than 

the number of people who received dosimeters. Sources of workforce data for Table 6-4 included 

staff from LANL Human Resources - Workforce Data & Analysis, and Los Alamos publication 

LASL-77-25. The major source of uncertainty appears to stem from variability in the worker types 

included in the worker count each year. Worker categories include full-time regular, part-time, 

limited-term, students, subcontractors, and visitors. More recent data have worker type information 

recorded, but older data might not.
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In Table 6-4, “Average total dose” for each year is calculated as the total dose (person-rem) divided 

by the number of workers monitored (i.e., Column 2 divided by Column 3). The data have not been 

corrected for potential missed doses. 

Table 6-4: Annual External Radiation Doses (1976-2005)

Year Total Dose*

(person-rem)

No. of Workers Average Total

Monitored Total Dose (rem)

1976 393.26 5,254 6,224 0.07

1977 432.81 5,624 6,519 0.08

1978 364.53 7,045 7,162 0.05

1979 320.88 7,549 7,398 0.04

1980 375.54 7,638 5,317 0.05

1981 588.55 7,966 8,028 0.07

1982 672.83 7,997 7,639 0.08

1983 673.33 8,144 7,912 0.08

1984 798.77 8,622 8,467 0.09

1985 715.19 9,487 9,025 0.08

1986 531.67 9,612 9,265 0.06

1987 400.48 9,202 9,075 0.04

1988 391.98 9,469 9,128 0.04

1989 326.93 10,605 9,665 0.03

1990 228.85 10,796 10,806 0.02

1991 163.25 11,284 11,037 0.01

1992 132.49 11,560 11,377 0.01

1993 141.81 11,772 11,371 0.01

1994 178.44 11,783 11,386 0.02

1995 234.93 12,448 11,382 0.02

1996 188.70 10,958 11,603 0.02

1997 182.02 10,860 12,146 0.02

1998 158.21 11,167 12,829 0.01

1999 128.89 11,212 13,294 0.01

2000 87.45 10,456 12,987 0.01

2001 114.28 10,443 13,284 0.01

2002 160.06 10,871 14,332 0.01

2003 218.83 10,660 10,015 0.02

2004 113.29 10,192 13,652 0.01

2005 149.06 10,826 13,194 0.01

* Total Dose = deep dose + neutron dose

** Annual dose summaries are available for all years after 2005.
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Tables 6-5, 6-6, and 6-7 below summarize the mean and maximum doses values for LANL workers 

with reported gamma, shallow, and neutron doses > 50 mrem for the years 1976 through 2004 

(partial). These data can be used to estimate unmonitored doses and to bound dose for the class. They 

can also be used to estimate reasonable values of unrecorded doses for which no records exist. The 

data upon which these tables are based do not include the potential missed dose. 

Table 6-5: LANL Recorded Gamma Dose > 50 mrem

Year No. of Workers w/Reported 

Gamma Dose > 50 mrem

Dose (mrem)

Mean Maximum

1976 952 358 3,290

1977 921 422 4,460

1978 938 333 3,680

1979 779 270 1,870

1980 666 269 1,850

1981 832 271 2,400

1982 821 325 2,270

1983 1,017 296 2,160

1984 1,513 232 2,470

1985 733 354 1,880

1986 527 321 1,710

1987 420 314 2,740

1988 428 297 1,710

1989 436 256 1,470

1990 340 241 2,280

1991 298 187 1,860

1992 221 138 565

1993 224 140 946

1994 215 147 689

1995 193 126 285

1996 267 174 600

1997 327 200 1,210

1998 313 192 1,090

1999 253 158 641

2000 215 120 596

2001 281 169 2,130

2002 380 186 1,370

2003 453 250 2,350

2004 282 155 1,230

2005 339 157 1,266

* Parameters can be obtained for all years after 2005. 
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Table 6-6: LANL Recorded Shallow Dose > 50 mrem

Year No. of Workers w/Reported 

Shallow Dose > 50 mrem

Dose (mrem)

Mean Maximum

1976 1,231 411 3,920

1977 1,211 476 5,470

1978 1,183 387 3,990

1979 1,036 283 2,330

1980 1,087 228 2,350

1981 1,275 253 2,930

1982 1,191 302 2,810

1983 1,414 274 2,750

1984 2,269 205 2,840

1985 1,299 263 1,970

1986 651 303 1,820

1987 501 314 8,890

1988 497 290 1,820

1989 518 249 1,470

1990 431 237 2,550

1991 398 188 2,042

1992 323 144 630

1993 349 141 962

1994 343 143 734

1995 345 182 657

1996 335 174 618

1997 466 186 1,342

1998 390 190 1,126

1999 311 162 1,572

2000 250 130 611

2001 353 165 2,133

2002 470 179 1,381

2003 548 236 2,352

2004 332 156 1,230

2005 383 164 1,291

* Parameters can be obtained for all years after 2005. 
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Table 6-7: LANL Recorded Neutron Dose > 50 mrem

Year No. of Workers w/Reported 

Neutron Dose > 50 mrem

Dose (mrem)

Mean Maximum

1976 221 118 800

1977 162 160 990

1978 221 125 1,370

1979 418 198 1,380

1980 659 242 3,390

1981 723 415 3,970

1982 691 519 3,700

1983 586 555 3,790

1984 692 517 3,930

1985 779 538 3,390

1986 648 524 2,920

1987 616 409 2,270

1988 604 408 2,450

1989 602 326 1,510

1990 519 249 1,690

1991 369 248 1,523

1992 386 212 1,569

1993 408 217 1,651

1994 465 248 1,515

1995 592 265 1,705

1996 562 206 1,465

1997 412 206 1,374

1998 354 198 1,370

1999 333 207 1,451

2000 258 158 831

2001 272 177 1,474

2002 331 196 1,731

2003 411 190 1,564

2004 314 146 842

2005 382 165 1,584

* Parameters can be obtained for all years after 2005. 

Details regarding the various analyses used and the associated minimum detectable activities are 

presented in the Technical Basis Document for the Los Alamos National Laboratory - Occupational 

External Dose (ORAUT-TKBS-0010-6).
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7.0 Feasibility of Dose Reconstruction for the Class Evaluated by 

NIOSH

The feasibility determination for the class of employees under evaluation in this report is governed by 

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

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

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

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

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

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

reconstructions. 

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

reconstructions demonstrate the feasibility of estimating with sufficient accuracy the potential 

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

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

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

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

exposures experienced by groups or individual members of the class as summarized in Section 7.6. 

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

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

Report examine:

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

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

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

• The bases for petition SEC-00109 as submitted by the petitioner. (Section 7.4) 

7.1 Pedigree of LANL Data

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

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

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

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

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

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

feasibility evaluation presupposes that data pedigree issues have been settled.
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7.1.1 Internal Monitoring Data Pedigree Review

Beginning in 2004, LANL and NIOSH representatives began a collaborative effort to retrieve and 

evaluate LANL’s historical bioassay data and capture it in an active database for on-going use. The 

master database is hosted and maintained by LANL. The ORAU Team has three static subsets of this 

database on its network: in vivo data for the period 1960-2004, in vitro data prior to 1991, and in vitro

data for 1991-2008. These subsets are derived from periodic queries of the master database performed 

to provide data for use in individual dose reconstructions and co-worker studies. These datasets 

provide a readily-available source of bioassay results for the radionuclides considered the principal 

sources of internal radiation dose prior to, and during, the class period under evaluation. 

Based on a reconnaissance of the various databases and datasets that existed at LANL, it was decided 

to create the master bioassay database by modifying LANL’s existing Bioassay Enrollment, 

Scheduling, and Tracking (BEST) system, which already contained bioassay data from 1990 to the 

present. Modification and adaptation of the BEST system was an iterative process carried out in 

parallel with the retrieval and evaluation of historical bioassay data. Beyond the data already in the 

BEST system, the additional data incorporated into the database were derived from three principal 

sources:

• In vivo data from existing and historical databases

• In vitro data for americium and plutonium from a standalone database 

• In vitro data for tritium, uranium, and polonium (TUPo) extracted from an obsolete electronic 

archive format

Table 6-1 presents the in vivo analytes present in the database for the period 1976-2004; Table 6-2 

presents the same information for urinalyses. There are no records for bioassay for polonium in the 

database after 1965.

Because the in vivo data and later in vitro data had primarily been recorded electronically (and 

automatically), validation of the historical information incorporated into the database focused on the 

earlier in vitro records (i.e., TUPo data). The electronically-archived TUPo data had been entered 

from laboratory notebooks, which were the formal records for such information prior to about 1980. 

Thus, the fraction of the in vitro data obtained from lab notebooks was relatively small for the time 

period under evaluation in this report (1976-2005). Most of the in vitro data for the period were 

obtained (recorded) automatically. The LANL bioassay master database provides a readily-available 

set of bioassay results for the radionuclides considered the principal sources of internal radiation dose 

for the class period under evaluation. 
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7.1.2 External Monitoring Data Pedigree Review

NIOSH has found that LANL’s policies for the collection and maintenance of employee external 

radiation monitoring data are sufficient to provide estimates of employee gamma, beta, and neutron 

dose. Radiological instrument and dosimeter measurement methods used for external exposures made 

during the evaluated timeframe were consistent with prevailing industry standards. With the 

exception of neutron exposure data obtained from NTA film (see Section 7.3), the data obtained from 

the evaluated class timeframe are sufficient in quality and quantity to be used to evaluate external 

doses. 

Records of radiation doses to individual workers from personnel dosimeters worn by workers and 

co-workers are available for LANL operations beginning in 1943. Doses from these dosimeters were 

recorded at the time of measurement and routinely reviewed by operations and radiation safety 

personnel for compliance with radiation control limits. Administrative practices are described in the 

Photodosimetry Evaluation Book (LASL 1959a, 1969, and 1977a, 1979; LANL 1986, 1989, 1996, 

2001, and 2003) and LANL technical reports. Detailed information for each worker is in the NIOSH 

claim documentation. The claim documentation provides specific information to be evaluated on the 

recorded dose of record. There do not appear to have been significant administrative practices that 

jeopardized the integrity of the dose of record (ORAUT-TKBS-0010-6). Furthermore, data recording 

became more automated with time.

7.2 Evaluation of Bounding Internal Radiation Doses at LANL

The principal sources of internal radiation doses for members of the class under evaluation were the 

variety of site processes and incidents involving plutonium, americium, tritium, and uranium 

(ORAUT-TKBS-0010-5). The following subsections address the ability to bound internal doses, 

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

7.2.1 Evaluation of Bounding Process-Related Internal Doses

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 proposed class were inhalation of 

plutonium isotopes, tritium, uranium isotopes, and mixed fission and activation products (MFP/MAP). 

The LANL internal dosimetry database contains bioassay data for U-234/235/238, Pu-238/239, 

tritium, Po-210, and Cs-137. Uranium, plutonium, and tritium were the primary contributors to the 

collective internal dose at LANL during the time period under evaluation. Po-210, widely used during 

the 1940s and 1950s, was not a significant nuclide for this time period. Am-241 was also a significant 

source of internal dose, primarily due to its association with weapons-grade plutonium, although it 

was not always associated with plutonium. There is an abundance of bioassay data for Am-241. Data 

for Cs-137 are available due to ease of detection using gamma spectroscopy systems. For the purpose 

of this discussion, the term “exotics” is used to include everything other than U-234/235/238, 

Pu-238/239, tritium, Am-241, and Cs-137 (i.e., radionuclides for which there are limited or no internal 

dosimetry data). This would include Sr-90, Th-232, Cm-244, Ac-227, Pa-231, Np-237, and others. 

Although not primary contributors to the collective dose at LANL, it is possible that for some 

individuals, one or more of these exotic radionuclides were the primary source of internal dose. 
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LANL clearly possessed capabilities to conduct bioassay measurements for these exotic radionuclides 

(LANL, 2008); however, specific data for such measurements are very sparse and generally 

unavailable.

Multiple data capture efforts have taken place to support this evaluation. These efforts have included 

trips to LANL as well as the National Archives in Denver. It is clear from these efforts that 

comprehensive health physics programs were in effect at LANL during the 1976-2005 time period. 

Hundreds of boxes of health physics records have been found pertaining to this time period. Records 

include: exposure reports, air monitoring reports, radiation incident reports, radiation work permits, 

special operating procedures, radioactive material handling, stack air monitoring, contamination 

surveys, nasal smears, whole body counting, urinalysis reports, CAM reports, ALARA reports, and 

employee checklists (Records, 2008) 

These health physics records appear to indicate that exotic radionuclides were handled, controlled, and 

monitored in a similar manner as the primary nuclides. For example, many alpha-emitting exotics 

were handled in a manner similar to handling plutonium: using glove-boxes, monitoring airborne 

concentrations, using personal protective equipment (PPE) such as respirators, performing surface 

contamination surveys, and covering jobs with radiation protection technicians. Although the vast 

majority of these documents were associated with the primary radionuclides, several documents 

pertaining to exotics were located. 

At the time of this Rev. 1 to the SEC-00109 Evaluation Report, NIOSH has been unable to 

satisfactorily demonstrate that exotic radionuclides were handled, controlled or monitored in a similar 

manner as primary nuclides. This issue is germane to the approach proposed by NIOSH in its initial 

(Rev. 0) SEC-00109 Evaluation Report to bound internal doses to workers who were not monitored 

for exotic radionuclides. This is discussed further in Section 7.2.3 (Methods for Bounding Internal 

Dose at LANL). 

Some examples of exotic radionuclide usage during the 1976-2005 time period are listed below: 

• A Special Work Permit (SWP) for Radiation Work, dated July 31, 1992, addressed an operation 

described as “disconnect thoria duct, stack, and fan.” Th-232 is identified as the radiological 

hazard associated with this operation. The PPE called for included double anti-contamination suits 

(anti-Cs) with taped openings and a full-face respirator. It also called for nose wipes and stated 

that urine samples were required, as requested (SWP, 1992). 

• An SWP, dated July 28, 1992, addressed an operation described as “remove service connections, 

wiring, and plumbing for Th contaminated hood.” Th-232 and U-238 are identified as the 

radiological hazards associated with this operation. The PPE called for included anti-Cs with taped 

openings and a full-face respirator, as requested. It also called for nose wipes (SWP, 1992). 
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• A Radiological and Hazardous Work Permit, dated August 30, 1994, addresses work involving 

Np-237 contamination. It calls for a continuous air monitor (CAM) to be used, with “settings 

changed to threshold 4.15, and window 1.5.” It also required Level 1 PPE with full-face respirator 

and continuous health physics tech (HPT) coverage (TA-55 RWP). 

• LANL report entitled, The Decommissioning of TA-21-153, Ac-227 Contaminated Old Filter 

Building, dated November 1981, includes a discussion about health physics controls used for this 

operation. The work was performed by experienced radiation workers who had received formal 

health physics training. Decommissioning work was not permitted without the presence of a 

health physics surveyor. All workers participated in a full-face respirator, fitting, testing, and 

training program. Air samplers and continuous air monitors (CAMs) were used with the 

maximum air concentration detected being 2.5 dis/s/m3

. All workers wore gamma and neutron 

film badges (TA-21-153, 1981). 

• Radiological Safety Procedures in P-Division, dated January 1977, contain a set of procedures 

prepared by the Radiation Safety Committee which describe various health physics practices 

designed to minimize exposure to radioactive materials (P-Division, 1977). 

• A memorandum, Standard Operating Procedures for the Handling of Actinide Elements, dated 

October 15, 1973 and reviewed and updated on April 20, 1976, states: “All manipulations of 

americium or curium are carried out in enclosed gloved-boxes or vacuum systems, maintained at a 

negative pressure with respect to laboratory air. Neoprene gloves, a minimum of 10-gauge 

thickness and tested for leaks before use are installed on these boxes. In addition, the operator 

uses surgeon’s gloves. Protective clothing and a full face mask respirator are supplied. 

Respirators are used whenever material from a ‘hot’ gloved-box is transferred out, or between 

boxes.” (SOPs, 1973). 

• An office memorandum entitled Radiation Protection Procedures, dated September 17, 1976, lists 

40 Standard Operating Procedures that pertain to radiation protection that were reviewed and 

found to be adequate and up-to-date (SOPs, 1976). 

The above is small sampling from hundreds of boxes of health physics-related records that are 

archived at LANL. 

NOTE: The LANL Evaluation Report for Petition SEC-00051 (covering 1943 through 1975) has a 

detailed description of the monitoring methods employed since the creation of the site. The following 

discussion focuses on the time period of the class currently under evaluation (1976 through 2005). 

In the 1970s, LANL initiated an Employee Health Physics Checklist. This checklist allowed the 

evaluation of each individual for potential internal and external exposure, the purpose being the 

identification of those individuals with significant potential for radiation exposure. Individuals were 

placed on a monitoring schedule based on this checklist. The checklist is still used and was 

computerized in 1998 as the Dosimetry Enrollment System (Checklist, 1985; Checklist, 1990; 

Checklist, 2000). 
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At the time of this Rev. 1 to the SEC-00109 Evaluation Report, NIOSH has been unable to 

satisfactorily demonstrate that the Employee Health Physics Checklists were effective for purposes of 

identifying individuals requiring bioassay monitoring. NIOSH will continue to evaluate this issue for 

the post-1995 period. 

7.2.1.1 Urinalysis Information and Available Data 

Excreta bioassay methods for determining internal exposures were developed in late 1944 for 

plutonium (fully implemented in April 1945); for uranium and americium in 1949; and tritium in 

1950. Methodologies for interpreting these resulting bioassay data over the years are presented in the 

LANL Internal Dose TBD. Although the number of monitored individuals increased over the years, 

not all individuals working at LANL were monitored. The Employee Health Physics Checklist was 

used to ensure that workers with the highest exposure potential were monitored. These checklists 

were completed for LANL employees, contractor employees, students, and visitors (Checklist, 1977). 

Workers involved in radiological incidents were also often monitored, as evidenced by the historical 

incident files maintained by LANL (see Section 5.2.3 for a summary of the incident-related records 

that are available). Nasal swipes and wound counts have also been used extensively at LANL to 

identify the need for bioassay. 

Plutonium 

The largest intakes at LANL have involved isotopes of plutonium. Current and historical bioassay 

results are stored with the plutonium results in the LANL bioassay database. There are over 70,000 

urine sample results for Pu-239 and over 60,000 results for Pu-238 in the LANL database, from 1976 

through 2005. The optimum source of data to estimate doses to unmonitored workers is co-worker 

data analyzed per ORAUT-OTIB-0019. This analysis has been performed and documented in 

ORAUT-OTIB-0062. In 1997, the TIMS analysis (which could separate Pu-239 and Pu-240) became 

available. There are over 3500 urine sample results for Pu-240, beginning in 1997. 

Many of the Service Support Workers, as defined in the petitioner-proposed class definition, were Zia 

Company employees. The Zia Company was the service workers’ contractor for many years. Zia 

employees participated in a plutonium bioassay program that required annual urine samples. In 1976, 

a program was used for Zia employees that restricted access to plutonium areas if participation in the 

plutonium bioassay program was not recorded within 425 calendar days. 
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Table 7-1 contains a list of criteria and exempt job categories (LASL, 1978a). In more recent years, 

other service contractors have participated in site activities and would be subject to these criteria. 

Table 7-1: Zia Employee Access to Plutonium Areas

Area

Urine Sample 

Within 425 

Days of Entry

Exempt

Job requiring respiratory protection X

Modifications or repairs on dry boxes or other highly contaminated equipment. X

Replacement of plutonium-contaminated filters at all sites. X

Janitorial (long-term) work in plutonium operation areas X

Long-term operations (weeks) in areas of low levels of plutonium contamination (>1,000 

dpm-60 cm2 and <10,000 dpm-60 cm2)

X

Decontamination of plutonium spills with >10,000 dpm-60 cm2 X

Work in burial pits at TA-54 when personnel contamination potential is moderate to high X

Short-term jobs (2-3 d) when sizable quantities of plutonium (grams of Pu-238 or kilograms 

of Pu-239) are present in dry boxes (even when work is being done outside dry box)

X

Supervisory personnel (base urine sample on record) X

Short-term jobs (2-3 d) in areas of CMR Building, Ten Site, TA-50, TA-55, TA-54, TA-18, 

TA-48, or TA-21, where there is little plutonium contamination (<1,000 dpm-60 cm2)

X

Jobs in other minimum exposure potential areas when respiratory protection is not required 

and possibility of plutonium contamination is minimal.

X

Americium

At LANL, Am-241 is usually encountered as a trace contaminant in plutonium; however, there is 

potential for exposure to pure Am-241, as seen in the 2005 Am-241 contamination incident discussed 

by the petitioner. The americium bioassay program began in 1954, although a procedure for 

determining Am-241 in urine was in development in 1948. Also, laboratory notebook pages dated 

1950 through 1957 list approximately 950 urinalyses for Am-241; many of these results were 

pre-1954 (Kirkham, 2006). Current and historical bioassay results are stored with the plutonium 

results in the Los Alamos Bioassay Data Repository database. There are over 1200 urine sample 

results for Am-241 in the LANL database, from 1991 through 2005. 

Tritium

Tritium was encountered in several forms: tritiated water (HTO), tritiated gas (HT), organically-bound 

tritium (OBT), and metal tritide (MT). Each form has unique characteristics. From 1950 until the 

present, an average of 100 individuals per year has been monitored for tritium intakes at LANL. The 

form generally encountered was HTO. There are no records of tritium monitoring prior to 1950. 

Urinalysis for tritium began on January 1, 1950; data are available in the Los Alamos Bioassay Data 

Repository database. There are over 40,000 urine sample results for tritium in the LANL database, 

from 1976 through 2005. The tritium bioassay data were sufficient to derive a co-worker model to 

estimate tritium doses after 1950 (ORAUT-OTIB-0062).
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Uranium 

Monitoring for uranium consisted of routine urinalysis, starting in 1949, for employees identified as 

being at risk for exposure (ORAUT-TKBS-0010-5, Table 5A-14, Routine Sampling Procedure). 

Nasal swipes with more than 50 cpm indicated the need for follow-up bioassay. Internal monitoring 

data are available in the Los Alamos Bioassay Data Repository database and doses due to intakes of 

uranium can be reconstructed for the period after 1949. There are over 40,000 urine sample results for 

uranium in the LANL database, from 1976 through 2005. The co-worker data were sufficient to 

derive intake estimates for unmonitored workers for uranium after January 1, 1950 (ORAUT-OTIB0062).

Strontium-90 

Records of routine or special Sr-90 urinalyses are very sparse for the post-1975 time period. 

Conversations in 2004 with current bioassay personnel indicate that possibly 200 Sr-90 analyses have 

been performed throughout the history of the site. In 1979, four urine samples were analyzed in 

association with a decommissioning operation at Ten Site, in an area that had been contaminated with 

Sr-90 due to the RaLa program prior to 1963 (Quarterly, 1980). Results are also available for three 

Sr-90 analyses performed in 1997 (Targeted Sr-90).

7.2.1.2 Lung Counting Information and Available Data 

In vivo counting equipment and techniques were developed in the late 1950s and have been in routine 

use for measuring X-ray and gamma-ray-emitting radionuclides at LANL since 1970. Descriptions of 

the counting equipment in use over the years at LANL are included in the LANL Internal Dose TBD 

(ORAUT-TKBS-0010-5).

Prior to the recent consolidation efforts by LANL and NIOSH (see Section 7.1.1 and ORAUT-OTIB0063), in vivo counting data from 1960-2003 were maintained in a legacy system called “OMNIS7”. 

Table 6-1 summarizes the numbers of in vivo records, by analyte, that are available in the LANL 

database during the post-1975 time period. Methodologies for interpreting these resulting bioassay 

data over the years are presented in the LANL Internal Dose TBD (ORAUT-TKBS-0010-5). 

Validation of these data sources is described in Section 7.1.1. 

7.2.1.3 Other Types of Bioassay 

Wound Counts 

In August 1959, the H-6 Group acquired a probe to be used to monitor wounds contaminated with 

plutonium. This probe was capable of detecting soft plutonium X-rays. The sensitivity of this probe 

was 1 × 10-9 Ci of plutonium unshielded. This was equivalent to detection of one-tenth of a 

permissible body burden of plutonium embedded in tissue to a depth of 1 cm (LASL 1959a). In 1977, 

a new NaI detector (12 mm x 2 mm) was being evaluated. This produced an MDA of 0.07 nCi based 

on weapons-grade plutonium (LASL 1977c). No other information on instrumentation or sensitivities 

is available (ORAUT-TKBS-0010-5).
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Wound counting was used primarily as a tool for surgeons to locate plutonium in the wound, and 

results were not used to calculate internal dose. Wound monitoring continues to be performed. In 

most cases, intake and dose will not be assessed directly from the wound count but rather from the 

resultant in vitro (urine and fecal samples) bioassay data. Follow-up studies of wounds found that, in 

the majority of incidents, plutonium does not readily migrate away from the wound site. Wound 

count results are added to a worker’s case file, and although they are not used specifically to 

reconstruct dose, may indicate that a potential uptake occurred that should be accounted for during 

dose reconstruction. 

7.2.2 Evaluation of Bounding Ambient Environmental Internal Doses

An ambient air-monitoring program at LANL began as early as 1954. Historical results of the 

AIRNET monitoring network through 2000 are available on the LANL website (LANL, 2003); annual 

environmental surveillance reports summarize yearly results. Emissions data are also available. 

These data are described in detail in ORAUT-TKBS-0010-4 and are used to evaluate airborne 

environmental intakes for application to individual dose reconstructions. Table 4-31 in ORAUTTKBS-0010-4 provides site-wide maximum ambient intakes for the entire class period under 

evaluation. Although available post-1975 data enable dose reconstruction, in this evaluation, workers 

are assumed to be maximally exposed to conditions that potentially existed in operational areas. 

Ambient environmental dose is bounded by the assignment of this operations-related dose.

7.2.3 Methods for Bounding Internal Dose at LANL

7.2.3.1 Methods for Bounding Operational Period Internal Dose

Application of Available Bioassay Data for Monitored Workers 

Intakes to monitored workers may be estimated using the available in vitro and/or in vivo data for the 

specific radionuclides that were analyzed. These intake estimates may then be used to bound organ 

doses from those radionuclides, for those monitored individuals, using the methodologies described in 

the LANL Internal Dose TBD (ORAUT-TKBS-0010-5).

Application of Co-Worker Data for Internal Dose Reconstruction 

Technical information bulletin ORAUT-OTIB-0062 has been developed for dose reconstruction, for 

unmonitored individuals, using co-worker data for Pu-239, Pu-238, uranium, tritium, and Cs-137. 

The intake rates provided in the OTIB cover the class period under evaluation.

 

The discussion below was put forth by NIOSH in its initial (Rev. 0) SEC-00109 Evaluation Report. 

In this discussion and elsewhere in that report, NIOSH attempts to demonstrate through various health 

physics records that exotic radionuclides were handled, controlled, and monitored in a similar manner 

as the primary nuclides. This proposed methodology has been a primary topic of discussion in 

subsequent Advisory Board Work Group meetings and one of the key issues that led to NIOSH’s 

decision to issue a revised evaluation report. 
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EXCERPT: SEC-00109, Rev. 0, Section 7.2.3.1, Methods for Bounding Operational Period 

Internal Dose: 

Application of Co-Worker Data for Internal Dose Reconstruction:

... In Section 7.2.1, it was demonstrated through various health physics records that exotic 

radionuclides were handled, controlled, and monitored in a similar manner as the primary 

nuclides. The applicable guidelines for controlling airborne concentrations and surface 

contamination levels for all radioactive materials are defined in units of activity (e.g., μCi/m3

 and 

dpm/100cm2

). The guidelines for many of the exotic alpha-emitters were the same as, or more 

restrictive than, the guidelines established for Pu-238 and Pu-239. For this reason, in the 

absence of specific internal dosimetry data, it is possible to bound intakes of many of the exotic 

alpha-emitting radionuclides using co-worker data for Pu-238 and/or Pu-239. Co-worker data 

for LANL are given in draft ORAUT-OTIB-0062. Daily intake rates for Pu-239 taken from 

ORAUT-OTIB-0062, in units of pCi/d, may be assigned separately for each alpha-emitting exotic 

radionuclide that would have required similar controls: Ac-227, Pa-231, Np-237, and Th-230. To 

process an individual claim, on a case-by-case basis, the nuclide that results in the highest dose to 

the organ of interest for the energy employee could be used as the bounding intake. Since the 

properties of Cm-244 are more similar to Pu-238, daily intake rates for Pu-238 could be used for 

Cm-244. Since the radiological properties and health physics controls for natural thorium are 

comparable to uranium, co-worker data for uranium could similarly be used to bound intakes of 

natural thorium. 

At the time of this writing, NIOSH has been unable to satisfactorily demonstrate that this proposed 

methodology would adequately bound intakes of exotic radionuclides to unmonitored workers at 

LANL. Generally, the surrogate nuclide approach might not be appropriate for bounding exotics for 

the following possible reasons: 

• Exposure for many exotics might be on an intermittent, experimental basis leading to episodic 

exposures that are not adaptable to chronic-exposure models. 

• The controls in place for smaller bench-top-type operations might not have been as 

well-engineered as the controls in place for larger routine operations. 

• The operations involving these exotics might have been of a sufficiently different nature as to 

preclude a direct comparison to those of U and Pu. 

In Rev. 0 of the ER, NIOSH anticipated that sufficient documentation would be available to address 

these issues. After a thorough review of the available information, none could be found. As a result, 

the conclusions regarding bounding intakes of specific exotic radionuclides listed in the following 

sections have been revised in several cases to identify infeasibilities.
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Incidents

Incidents often resulted in requests for special bioassays (see Section 5.2.3 for a summary of the 

incident-related records that will be available for data capture by NIOSH in early 2009). In such 

cases, these bioassay results may be used to support bounding intake estimates for the exposure 

situations/conditions associated with the incidents. 

7.2.3.2 Bounding Methods by Radionuclide 

Plutonium 

The LANL bioassay programs for plutonium were extensive. Monitored worker intakes were 

determined by chest counting and through urine bioassay. These data are readily available to bound 

dose from plutonium isotopes for monitored workers. 

Unmonitored worker intakes may be bound using monitored co-worker data. Internal dosimetry coworker data for LANL are presented in ORAUT-OTIB-0062. 

Hydrogen-3 (Tritium) 

The tritium bioassay program at LANL was extensive. Monitored worker doses were determined 

through urine bioassay. These data are readily available to bound tritium dose to monitored workers. 

Unmonitored worker intakes may be bound using monitored co-worker data. Unmonitored worker 

intakes may be bound using monitored co-worker data. Internal dosimetry co-worker data for LANL 

are presented in ORAUT-OTIB-0062. 

Exposures to tritiated water and/or vapor (HTO) and gaseous tritium (HT) were the most prevalent 

forms of tritium exposure at LANL. Organically bound tritium (OBT) would have been encountered 

only in locations where biological research with labeled compounds was conducted. 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. Exposure to these compounds is a specialized circumstance (Inkret, 

1999b). On a case-by-case basis, intakes of OBT and SMT compounds may be bounded using the 

methodologies outlined in ORAUT-OTIB-0066. 

At the time of this revision to the SEC-00109 Evaluation Report, NIOSH has been unable to 

satisfactorily demonstrate that the available tritium bioassay data are sufficient to bound intakes from 

all sources and chemical forms of tritium that may have been encountered at LANL. NIOSH will 

continue to evaluate this issue for the post-1995 period, and for purposes of performing partial dose 

reconstructions for earlier years.

Uranium 

The LANL bioassay programs for uranium were extensive. Monitored worker intakes were 

determined by chest counting and through urine bioassay. These data are readily available to bound 

dose to uranium isotopes for monitored workers. 

Internal dosimetry co-worker data for LANL are presented in ORAUT-OTIB-0062. 
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Mixed Fission and Activation Products 

By 1976, in vivo counting methods were well-established and available for assessing intakes of MFP 

and MAP. For monitored workers, these data may be used to bound intakes of the monitored 

radionuclides. 

ORAUT-OTIB-0054 discusses MFAP ratios and the calculation of intakes based on a single nuclide 

(e.g., Cs-137 co-worker data). Cesium-137 co-worker data are available and presented in the LANL 

co-worker study, ORAUT-OTIB-0062. For bounding intakes to unmonitored workers at reactor 

facilities, these Cs-137 co-worker data (ORAUT-OTIB-0062) may be used in conjunction with 

ORAUT-OTIB-0054. 

For non-reactor facilities such as LANSCE, NIOSH recognizes that the reactor-derived radionuclide 

ratios presented in ORAUT-OTIB-0054 may not be representative or appropriate for bounding intakes 

of MAP by unmonitored workers. Since the issuance of the initial (Rev. 0) SEC-00109 Evaluation 

Report, NIOSH has proposed an alternative approach to bound MAP intakes for unmonitored workers 

at the LANSCE facility that is based upon co-worker bioassay data for Be-7 and the use of ratios to 

Be-7 to estimate intakes of other more difficult to detect radionuclides. At the time of this writing, 

however, NIOSH has not satisfactorily demonstrated that this alternate approach is bounding or 

sufficiently accurate. NIOSH will continue to evaluate this issue for the post-1995 period, and for 

purposes of performing partial dose reconstructions for earlier years. 

Strontium-90/Yttrium-90 

Sr-90/Y-90 is often associated with other mixed fission products. In such cases, bounding intakes 

may be estimated by assessing intakes of Cs-137, another fission product with a similar fission yield 

and similar physical half-life as Sr-90. Intakes of Cs-137 can be readily determined by in vivo

counting. Intakes of Sr-90/Y-90 for workers exposed to MFP who were monitored for Cs-137 can 

therefore be estimated from Cs-137 intake assessments (assuming that the Sr-90/Y-90 is a component 

of MFP). The details of this method are described in ORAUT-OTIB-0054. 

Urine bioassay methods for Sr-90/Y-90 were well-established by 1976. Due to a lack of necessity, 

routine Sr-90/Y-90 bioassay was uncommon. As described previously, the only activity at LANL 

known to have involved Sr-90 contamination (other than as a component of MFP) was the RaLa 

program. Although this program ended in 1963, residual Sr-90 contamination remained in specific 

associated areas long after the program ended. The available health physics records provide 

information supporting that operations in affected areas were sufficiently controlled from a 

radiological exposure control perspective. After the RaLa program ended, NIOSH found no 

indication of work that could result in significant exposures (or disturbance of the residual Sr-90 

contamination) until the commencement of decommissioning activities at the associated locations. 

The decommissioning operation at Ten Site during the late 1979 and early 1980 time period involved 

hundreds of air tests, continuous air monitoring (CAM) during all operations, hundreds of routine and 

special air tests, hundreds of nose swipes and four urine bioassay samples (Quarterly, 1979). RWPs 

from the 1990s are available for the decommissioning work conducted in TA-35 where Sr-90 

contamination was known to have been present (RWP, 1995). These operations were conducted by 

trained radiation workers and involved the use of CAMs, other air monitoring, radiological technician 

coverage, level 1 PPE, nasal swipes, etc. Workers with significant potential for Sr-90 intakes during 
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these decommissioning activities would likely have been monitored via urine bioassay. At the time of 

this writing, however, these data are not included in the LANL bioassay database, thus making them 

unavailable for bounding intakes. 

Following a NIOSH request, LANL staff has provided evidence of targeted urine bioassay for Sr-90 

involving three workers performed in 1997 (Targeted Sr-90, 1997). At the time of this writing, 

however, these data are not included in the LANL bioassay database.

Thorium-230 

NIOSH has not found any evidence of work with separated Th-230 at LANL since the late 1950s. 

Urine bioassay methods for Th-230 were established in the 1950s, as there were a number of 

bioassays conducted for Th-230 in 1958 (ORAUT-TKBS-0010-5). In the initial (Rev. 0) SEC-00109 

Evaluation Report, NIOSH proposed that, in the absence of bioassay data, intakes of Th-230 from 

residual contamination could be bound using co-worker data for Pu-239, as described earlier in this 

section. At the time of this writing, NIOSH has been unable to satisfactorily demonstrate that this 

proposed methodology would adequately bound intakes of Th-230 for unmonitored workers. NIOSH 

will continue to evaluate this issue for the post-1995 period, and for purposes of performing partial 

dose reconstructions for earlier years. 

Thorium-232 

There is evidence of small-scale operations involving Th-232 extending into the 1990s (DOE, 1991). 

Due to a lack of necessity, routine Th-232 bioassays were uncommon; however, LANL maintained 

the ability to perform targeted bioassay for the duration of the evaluation period (post-1975). 

Targeted dosimetry was indicated for an international traveler in 1999 (Targeted Th-232, 2000). At 

the time of this writing, however, these data are not included in the LANL bioassay database. LANL 

maintains a DOELAP-accredited in vitro bioassay program for Th-230 and Th-232. In the initial 

(Rev. 0) SEC-00109 Evaluation Report, NIOSH proposed that, in the absence of bioassay data, 

Th-232 intakes could be bound using co-worker data for uranium, as described earlier in this section. 

At the time of this writing, NIOSH has been unable to satisfactorily demonstrate that this proposed 

methodology would adequately bound intakes of Th-232 for unmonitored workers. NIOSH will 

continue to evaluate this issue for the post-1995 period, and for purposes of performing partial dose 

reconstructions for earlier years.

Americium-241 

For intakes of Am-241 as a component of weapons-grade plutonium, plutonium bioassay data may be 

used to bound intakes of Am-241. Since 1970, LANL has maintained in vivo capability for Am-241. 

These data are readily available to bound intakes of Am-241 for monitored workers. Although 

bioassay data for Am-241 are abundant, in the initial (Rev. 0) SEC-00109 Evaluation Report, NIOSH 

proposed that unmonitored intakes could be bound using co-worker data for Pu-239, as described 

earlier in this section. At the time of this writing, NIOSH has been unable to satisfactorily 

demonstrate that this proposed methodology would adequately bound intakes of Am-241 for 

unmonitored workers. NIOSH will continue to evaluate this issue for the post-1995 period, and for 

purposes of performing partial dose reconstructions for earlier years.
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Neptunium-237 

Neptunium-237 was not a commonly-used radionuclide at LANL. There is, however, evidence of 

periodic operations involving its use prior to 1975 and continuing to at least 2002. Although LANL 

maintains the ready ability for targeted in vitro measurements (LANL, 2008), bioassay data are 

generally unavailable. In the initial (Rev. 0) SEC-00109 Evaluation Report, NIOSH proposed that, in 

the absence of bioassay data, intakes of Np-237 could be bound using co-worker data for Pu-239, as 

described earlier in this section. At the time of this writing, NIOSH has been unable to satisfactorily 

demonstrate that this proposed methodology would adequately bound intakes of Np-237 for 

unmonitored workers. NIOSH will continue to evaluate this issue for the post-1995 period, and for 

purposes of performing partial dose reconstructions for earlier years. 

Actinium-227 

Actinium is unlikely to have been a significant radiological hazard in the post-1975 period at LANL. 

The available literature suggests that work with this radionuclide was substantially complete by 1955 

(DOE, 1993). Residues of this material may exist in waste streams, including filter buildings and 

environmental disposal sites. 

Potential doses to affected workers from the 1978 decontamination and decommissioning of the Old 

Filter Building, TA-21-153 may be bounded using job-coverage data from the decommissioning 

report (Harper, 1981) when a realistic exposure scenario can be inferred from case-specific 

information. During this decommissioning project, workers wore respiratory protection, air 

monitoring was conducted throughout the project (air monitoring data are available), and the 

maximally exposed individuals received bioassay via whole-body counting. No measureable intakes 

were found (Harper, 1981). This is an example of “targeted dosimetry” as described by current LANL 

Radiation Protection Division staff (LANL, 2008). In the initial (Rev. 0) SEC-00109 Evaluation 

Report, NIOSH proposed that, in the absence of bioassay data, intakes of Ac-227 could be bound 

using co-worker data for Pu-239, as described earlier in this section. At the time of this writing, 

NIOSH has been unable to satisfactorily demonstrate that this proposed methodology would 

adequately bound intakes of Ac-227 for unmonitored workers. NIOSH will continue to evaluate this 

issue for the post-1995 period, and for purposes of performing partial dose reconstructions for earlier 

years.

Protactinium-231 

No LANL workers are on a routine Pa-231 bioassay program, although LANL has the ability to detect 

this nuclide through targeted in vivo measurements (LANL, 2008). In the initial (Rev. 0) SEC-00109 

Evaluation Report, NIOSH proposed that, in the absence of bioassay data, intakes of Pa-231 could be 

bound using co-worker data for Pu-239, as described earlier in this section. At the time of this 

writing, NIOSH has been unable to satisfactorily demonstrate that this proposed methodology would 

adequately bound intakes of Pa-231 for unmonitored workers. NIOSH will continue to evaluate this 

issue for the post-1995 period, and for purposes of performing partial dose reconstructions for earlier 

years.
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Curium-244 

LANL has the ability to detect Cm-244 through targeted in vitro measurements, if warranted, with 

sample analysis conducted at Oak Ridge (LANL, 2008). An example case of targeted bioassay was 

provided by LANL for a presumptive intake occurring in 2003 (Little, 2003b). In the initial (Rev. 0) 

SEC-00109 Evaluation Report, NIOSH proposed that, in the absence of bioassay data, intakes of 

Cm-244 could be bound using co-worker data for Pu-238, as described earlier in this section. At the 

time of this writing, NIOSH has been unable to satisfactorily demonstrate that this proposed 

methodology would adequately bound intakes of Cm-244 for unmonitored workers. NIOSH will 

continue to evaluate this issue for the post-1995 period, and for purposes of performing partial dose 

reconstructions for earlier years.

7.2.3.2 Methods for Bounding Ambient Environmental Internal Dose 

The LANL Environmental Occupational Dose TBD lists relevant monitoring or other data pertinent to 

estimating environmental internal dose (ORAUT-TKBS-0010-4). Although available post-1975 data 

enable dose reconstruction, in this evaluation, workers are assumed to be maximally exposed to 

conditions that potentially existed in operational areas. Ambient environmental dose is bounded by 

the assignment of this operations-related dose.

7.2.4 Internal Dose Reconstruction Feasibility Conclusion 

In its initial evaluation of SEC-00109, NIOSH concluded that internal dose reconstruction for 

members of the proposed class was feasible, based on: (1) using in vitro and in vivo bioassay data for 

monitored workers; and (2) using co-worker data to bound intakes to unmonitored workers, based on 

the co-worker study described in ORAUT-OTIB-62 and as described within this section of this 

evaluation report. Since that initial evaluation, following multiple meetings of the Advisory Board 

Work Group on LANL and subsequent research, NIOSH has now concluded that it lacks sufficient 

information, which includes biological monitoring data, sufficient air monitoring information, or 

sufficient process and radiological source term information, to allow it to estimate with sufficient 

accuracy the potential internal exposures to fission and activation products, and various other 

radionuclides of concern, to which the proposed class may have been subjected. 

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

period from January 1, 1976 through December 31, 1995, NIOSH intends to use any internal 

monitoring data that may become available for an individual claim (and that can be interpreted using 

existing NIOSH dose reconstruction processes or procedures). Dose reconstructions for individuals 

employed at LANL during the period from January 1, 1976 through December 31, 1995, but who do 

not qualify for inclusion in the SEC, may be performed using these data as appropriate. 

7.3 Evaluation of Bounding External Radiation Doses at LANL

The principal sources of external radiation exposure for members of the class under evaluation were

beta, photon (X-ray and gamma), and neutron radiation associated with: nuclear weapon development; 

reactor and accelerator operations; criticality experimentation; handling of radioactive materials in 

production or research activities; radiation-producing devices; or radioactive waste facilities or 

handling operations. For some workers, neutron radiation accounted for a large fraction of the 
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occupational external radiation dose. The principal sources of neutron dose over the time period 

under evaluation were accelerator and plutonium-handling operations. 

The following subsections address the ability to bound external doses, methods for bounding doses, 

and the feasibility of external dose reconstruction. 

7.3.1 Evaluation of Bounding Process-Related External Doses

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.

LANL historical documentation shows knowledge of potential workplace external radiation hazards, 

applicable radiation exposure guidelines, methods of limiting worker exposure, and an on-going 

pursuit of improved radiation instrumentation and dosimetry capabilities. Table 6-2 of the LANL 

External Dose TBD shows monitoring for a substantial fraction of the total workers for all years after 

1945 and certainly over the time period under evaluation (1976 through 2005) (ORAUT-TKBS-0010-

6). The values for 1976 through 2005 are shown in Table 6-4 of this evaluation. The dosimeters 

employed were state-of-the-art and included design features to provide sensitivity in the workplace 

radiation environments encountered by LANL workers. LANL made efforts to characterize the 

response of its personnel dosimeters to workplace radiation fields. For the period 1976 through 1979, 

the dosimeter of record for beta, gamma, and thermal-to-intermediate-energy neutron dose was the 

multi-element “Cycolac” film badge. In 1978, some workers began receiving thermoluminescent 

dosimeters (TLDs) which incorporated a new and improved technology. TLDs have been the 

dosimeter of record since 1980. For fast-neutron monitoring, NTA film was used in conjunction with 

the Cycolac film or TLD personnel dosimeters until 1995, when it was replaced with track-etch 

dosimeters (TEDs).

LANL has recorded gamma (penetrating), beta (non-penetrating), and neutron dose (or dose 

equivalent) for monitored workers over the time period under evaluation. Prior to 1980, fast and 

thermal neutron dose were recorded separately; total neutron dose (i.e., that from all neutron energies) 

has been recorded thereafter (ORAUT-TKBS-0010-6).

Data from LANL dosimetry systems and workplace instrument measurements such as multi-sphere 

and rem-meter workplace measurements of neutron dose and spectra, and recent LANL Rotating 

Neutron Spectrometer workplace measurements provide a basis for determining an upper-bound 

neutron dose for the corresponding periods of dosimeter use (ORAUT-TKBS-0010-6).

Photon 

The personnel dosimeters assigned to LANL workers over the time period under evaluation were 

capable of measuring photon doses in the workplace with sufficient accuracy to permit the calculation 

of bounding photon doses. The majority of workers were routinely monitored with state-of-the-art 

dosimeters and the measured photon doses are considered to be reasonably accurate based on 

laboratory-measured response characteristics of these dosimeters, and complete based on the worker 

dose records (ORAUT-TKBS-0010-6). These data have been used in several health effect studies of 

LANL workers. Potential missed dose is assigned using OCAS-IG-001 guidance. The Occupational 

External Dose TBD includes documentation of measures taken by LANL staff to characterize the 
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response of their personnel dosimeters to the low-energy photon fields associated with plutoniumhandling operations (ORAUT-TKBS-0010-6, Section 6.2.3.4). 

Table A-2 in the External Dose TBD gives gamma dose rate statistics for LANL dosimeter results 

(gamma dose ≥ 50 mrem) for all years of operation through 2003 and into 2004. These data include 

the mean, maximum, median, and 95th percentile values, and the corresponding geometric standard 

deviation. If these data are adjusted for missed dose and uncertainty, as applicable, they represent a 

reasonable means of bounding photon dose for all members of the class under evaluation. The 

External Dose TBD contains sufficient information with which to adjust the Table A-2 data for missed 

dose and uncertainty (ORAUT-TKBS-0010-6). 

Beta

Beta in association with photon radiation monitoring instrumentation was commonly used to evaluate 

workplace beta radiation fields. The personnel dosimeters assigned to LANL workers during the time 

period under evaluation had the capability to measure doses from significant beta radiation sources. 

Non-penetrating, beta, or shallow (depending upon terminology used at different times) doses were 

routinely recorded along with the photon dose. These data provide information to permit the 

calculation of bounding doses for members of the class. LANL shallow doses were based on uranium 

calibration (ORAUT-TKBS-0010-6). Mixed photon and beta radiation fields typically result in 

substantial overestimation of the shallow dose. Lower-energy beta radiation was not generally a 

significant source of dose at LANL (ORAUT-TKBS-0010-6). There is sufficient LANL 

documentation to allow bounding of beta dose for members of the class under evaluation. 

Neutron 

Neutron radiation monitoring instrumentation was commonly used to evaluate workplace neutron 

radiation fields. Prior to 1980, the NTA personnel neutron dosimeter was used to measure and record 

personnel neutron dose. Since NTA film-based dosimeters do not respond to neutrons with energies 

less than approximately 500 keV, the use of neutron-to-photon dose ratios is necessary to bound 

neutron dose prior to 1980 (ORAUT-TKBS-0010-6). After 1980, recorded neutron doses are 

considered to be sufficiently accurate based on a combination of albedo TLD (for low- and 

intermediate-energy neutrons) and NTA film (for high-energy neutrons).

Characterization of workplace neutron spectra at LANL showed that the neutron energies associated 

with plutonium-handling operations were consistent with those from well-moderated sources. 

Measurements performed in plutonium processing areas in 1978 indicated an average neutron energy 

of 200 keV. Neutron spectrometry data collected in these areas in 1993 showed that approximately 

90% of the neutron flux was from neutrons having energy of 1.2 MeV or less. Characterization of 

neutron spectra at TA-53 showed neutron energy spectra could vary widely, and included areas where 

the dominant contribution to neutron dose equivalent came from neutrons having energy greater than 

10 MeV. These measurements included evaluation of NTA and TLD measured neutron doses. 

(ORAUT-TKBS-0010-6).
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The External Dose TBD contains sufficient information to allow bounding of neutron dose using, as 

necessary, neutron-to-photon dose ratios in LANL areas where personnel neutron exposures occurred. 

It also contains sufficient information to allow assessment of missed dose and uncertainties associated 

with reported neutron dose after 1979, as well as reported neutron dose for the entire time period 

under evaluation. The combination of bounding neutron-to-photon dose ratios and the photon (i.e., 

gamma) dose information given in Table A-2 of ORAUT-TKBS-0010-6 therefore provides a means 

for bounding neutron dose for all members of the class for the period prior to 1980 when NTA film 

was still the principal means of neutron monitoring. The same approach could be extended to the 

post-1979 period; alternatively, an approach akin to that described above for bounding photon 

exposures could be used. Either way, sufficient information is available to allow bounding of neutron 

dose for all members of the class for the entire time period under evaluation. 

7.3.2 Evaluation of Bounding Ambient Environmental External Doses

LANL had a comprehensive program for monitoring ambient radiation exposure within its boundaries 

and in the surrounding area. This program and the data it generated are described in detail in 

ORAUT-TKBS-0010-4, which provides a thorough evaluation of ambient environmental dose as 

applicable to performing individual dose reconstructions. Table 4-25 in ORAUT-TKBS-0010-4 

provides site-wide maximum ambient dose data for the entire class period under evaluation. This 

information should be sufficient to allow bounding of ambient environmental external dose for all 

members of the class.

7.3.3 LANL Occupational X-Ray Examinations 

The information given in the Occupational Medical Dose TBD is sufficient to allow bounding of 

radiation dose associated with occupationally-related X-ray examinations received by members of the 

class under evaluation. The examination protocols and equipment used during the relevant time 

period are documented sufficiently to allow assessments of organ dose that may be considered 

bounding (ORAUT-TKBS-0010-3). Therefore, NIOSH concludes that it is likely feasible to 

reconstruct occupational medical dose for LANL workers with sufficient accuracy.

7.3.4 External Dose Reconstruction Feasibility Conclusion 

During the period of this evaluation, the majority of LANL workers were monitored as illustrated in 

Table 6-4. Information describing workplace radiation fields at LANL, performance of personnel 

dosimetry systems in those fields, and the monitoring data produced by LANL’s personnel dosimetry 

program have been reviewed as they pertain to bounding of radiation dose from external sources of 

photon, beta, and neutron radiation for members of the class under evaluation. Information describing 

dose from ambient sources of radiation and from occupationally-related X-ray examinations have also 

been reviewed. The available information has been found adequate to allow bounding of external 

radiation doses with sufficient accuracy for members of the class under evaluation. 
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7.4 Evaluation of Petition Basis for SEC-00109

The following subsections evaluate the assertions made on behalf of petition SEC-00109 for the 

LANL site. 

7.4.1 Cerro Grande Fire

SEC-00109: The petitioner identified the “Cerro Grande Fire” in 2000 as an unmonitored, unrecorded, 

or inadequately monitored exposure incident.

A study performed soon after the Cerro Grande fire included two dose calculations: (1) the 

hypothetical maximally-exposed firemen or volunteer who was working actively in the Los Alamos 

area throughout the worst of the burn duration; and (2) the maximally-exposed member of the public 

outside Los Alamos. Those calculations are updated in Updated Calculations of the Inhalation Dose 

from the Cerro Grande Fire Based on Final Air Data (Cerro Grande, 2001). In addition, a third 

calculation is added: a fireman or other worker in the vicinity of AIRNET (LANL’s ambient air 

monitoring network) Station #23 in Mortandad Canyon where elevated levels of LANL-derived 

airborne uranium occurred during the peak of the fire. In the initial (Rev. 0) SEC-00109 Evaluation 

Report, NIOSH concluded that these data could be used to bound the dose for any Service Support 

Worker who might have been exposed during the fire. NIOSH will continue to evaluate this issue in 

its ongoing evaluation of the post-1995 period. 

7.4.2 Sigma Americium Contamination Incident 

SEC-00109: The petitioner identified the “Sigma Americium Contamination Incident” in 2005 as an 

unmonitored, unrecorded, or inadequately monitored exposure incident.

The Type B Accident Investigation report on the July 14, 2005 americium contamination accident at 

the LANL Sigma Facility states that the maximum dose to Worker 1 (the maximally-exposed 

individual) was 500 mrem CEDE. Based on this assessment, a maximum intake may be estimated, 

which could then be used to bound the dose for service workers (Investigation, 2006). 

7.4.3 Neptunium Special Hazards 

SEC-00109: The process hazards analysis, HCPs, and work instructions for actinide fuels work do 

not adequately define or analyze the special hazards posed by the use of 100-gram quantities of 

neptunium powders by NMT-11 workers. 

NIOSH recognizes that there was a potential for unmonitored intakes of Np-237 at LANL. In the 

initial (Rev. 0) SEC-00109 Evaluation Report, NIOSH proposed a methodology for bounding intakes 

of Np-237 to unmonitored workers, as described in Section 7.2.3 of this report. At the time of this 

writing, NIOSH has been unable to satisfactorily demonstrate that this proposed methodology would 

adequately bound intakes of Np-237 for unmonitored workers. NIOSH will continue to evaluate this 

issue for the post-1995 period, and for purposes of performing partial dose reconstructions for earlier 

years. 
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7.4.4 LANL 7776 TLDS and Neutron Correction Factors 

SEC-00109: “NCFs can vary by more than an order of magnitude at LANL facilities.” Considering 

that Support Service workers could work at several facilities during a day, dose reconstruction using 

the data from the LANL 7776 type TLD cannot be done. 

Area-specific neutron correction factors (NCFs) are used at LANL to improve the accuracy of the 

neutron dose based on workplace instrument measurements (ORAUT-TKBS-0010-6). If workers 

frequented multiple facilities, or if the facilities frequented are unknown, NIOSH can bound neutron 

doses by applying the highest NCF for any of the buildings the worker may have entered. 

7.4.5 LANL Contamination Surveys, Postings, and Control 

SEC-00109: The Tiger Team Assessment Report (submitted by the petitioner) made a number of 

observations about the LANL site that are pertinent to the potential for unmonitored intakes (DOE, 

1991). In summary, the report observed that: (1) radiation surveys sometimes did not conform to 

LANL policies and documented schedules; (2) contamination control programs did not ensure 

complete control of the spread of contamination; (3) there were instances in which barriers had been 

removed or signage was inappropriate or missing; (4) posting was inconsistent throughout the site; (5) 

the frequency of surveys mandated by procedures was not consistently followed; (6) signs and labels 

throughout the plutonium and uranium facilities did not indicate radiological conditions, were not 

accurate, or had other problems that could lead to unsafe practices; (7) documentation of smear 

surveys was not consistently performed; (8) the use of open-front hoods led to an increased frequency 

of radioactive material contamination incidents; (9) cracked glovebox gloves were observed; (10) 

removable and fixed surface contamination limits for tritium and pure gamma-emitting nuclides were 

not in compliance with DOE Order 5480.11; (11) calibration and response-checking of fixed 

instruments and tritium monitors did not reflect the same level of attention and commitment given to 

portable instrumentation; (12) out-of-calibration instruments, such as glovebox hand and foot 

monitors and tritium monitors, were not placed out of service; (13) placement of air monitoring 

instruments at the DU sites was not based on studies of flow patterns; (14) facility air monitor alarm 

points, used per DOE Order 5480.11 to warn workers that airborne radioactive material contamination 

levels had exceeded an action level, were not always set at a uniform level, with the set points varying 

from monitor to monitor even in the same building; and (15) training programs had not been 

established to ensure that routine dose rate and contamination surveys were conducted in a consistent 

manner.

None of the numerous Tiger Team findings and observations pertains to the adequacy of the internal 

or external personnel monitoring programs; therefore, they do not compromise NIOSH’s ability to 

conduct dose reconstruction with sufficient accuracy. Dose reconstructions for LANL employees are 

based upon internal and external monitoring data. These data are also employed in co-worker studies 

to estimate unmonitored worker intakes. 
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7.5 Other Potential SEC Issues Relevant to the Petition Identified During the 

Evaluation

During the feasibility evaluation for SEC-00109, a number of issues were identified in the LANL ER 

for Petition SEC-00051 that needed further analysis and resolution. The issues and their current status 

are:

• ISSUE: SEC-00051, Sect. 7.2.1.1: There are no data available that permit internal dose 

contributions from Sr-90 to be reconstructed with sufficient accuracy.

RESPONSE: In the initial (Rev. 0) SEC-00109 Evaluation Report, NIOSH concluded that, 

although opportunities for exposure to Sr-90 at LANL after 1975 were rare, workers with 

significant potential for intakes would have been monitored via urine bioassay and the resulting 

data would been included in their personnel records. At the time of this writing, however, NIOSH 

finds that these data are not included in the LANL bioassay database and are therefore unavailable 

for bounding intakes. NIOSH will continue to evaluate this issue for the post-1995 period, and for 

purposes of performing partial dose reconstructions for earlier years.

• ISSUE: SEC-00051, Section 7.2.1.1: After 1970, with the onset of chest counting and improved 

analytical capabilities, LANL possessed the ability to monitor for all ROCs with the exception of 

Ac-227, Cm-244, and Pa-231. Ac-227 and Pa-231 possibly could be quantified by the chest count 

procedure. However, no information has been found that would indicate an attempt at this 

process or that any such data are available. Inventory records to establish the significance of the 

source term of these “exotic” radionuclides is limited. Most available information is limited to 

waste activity reports.

Few bioassay data are available for Ac-227, Cm-244, or Pa-231. Although opportunities for 

exposure to these radionuclides at LANL after 1975 were rare, in the initial (Rev. 0) SEC-00109 

Evaluation Report, NIOSH proposed a methodology to bound intakes of these nuclides by 

unmonitored workers using plutonium co-worker data, as described in Section 7.2.3 of this report. 

At the time of this writing, NIOSH has been unable to satisfactorily demonstrate that this proposed 

methodology would adequately bound intakes of Ac-227, Cm-244, or Pa-231 for unmonitored 

workers. NIOSH will continue to evaluate this issue for the post-1995 period, and for purposes of 

performing partial dose reconstructions for earlier years. 
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• ISSUE: SEC-00051, Section 7.2.1.2: Data for Pu-238, Pu-239, Am-241, and Cs-137 are 

available. Few data for other radionuclides are available prior to the 1980s when the use of 

germanium detectors became more common.

A significant amount of additional data has been captured from LANL since the SEC-00051 

Evaluation Report was written. In the initial (Rev. 0) SEC-00109 Evaluation Report, NIOSH 

proposed methodologies for bounding intakes to unmonitored LANL workers of the lessfrequently-encountered radionuclides, as described in Section 7.2.3 of this report. At the time of 

this writing, NIOSH has been unable to satisfactorily demonstrate that this proposed methodology 

would adequately bound intakes of the exotic radionuclides for unmonitored workers. NIOSH 

will continue to evaluate this issue for the post-1995 period, and for purposes of performing partial 

dose reconstructions for earlier years.
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7.6 Summary of Feasibility Findings for Petition SEC-00109

This report evaluates the feasibility for completing dose reconstructions for employees at LANL from 

January 1, 1976 through December 31, 2005. NIOSH found that the available monitoring records, 

process descriptions and source term data available are sufficient to complete dose reconstructions for 

the evaluated class of employees.

Table 7-2 summarizes the results of the feasibility findings at LANL for each exposure source during 

the time period January 1, 1976 through December 31, 2005. 

Table 7-2: Summary of Feasibility Findings for SEC-00109

January 1, 1976 through December 31, 2005

Source of Exposure Reconstruction Feasible Reconstruction Not Feasible

Internal1 X 

 - Pu X

 - H-3 X2

 - U X

 - MFP and MAP X2

 - Sr-90/Y-90 X2

 - Th-230 and Th-232 X2

 - Am-241 X2

 - Np-237 X2

 - Ac-227 X2

 - Pa-231 X2

 - Cm-244 X2

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 lung/whole body count (in vivo) data 2 Likely feasible after full implementation of 10 CFR 835 on January 1, 1996. 

As of August 8, 2012, a total of 863 claims have been submitted to NIOSH for individuals who 

worked at LANL and are covered by the class definition evaluated in this report. Dose 

reconstructions have been completed for 627 individuals (~73%).
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8.0 Evaluation of Health Endangerment for Petition SEC-00109

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. 

In its initial (Rev. 0) report, dated January 22, 2009, NIOSH concluded that it had access to sufficient 

information to estimate with sufficient accuracy the radiation doses for members of the class under 

evaluation. Since that initial evaluation, following multiple meetings of the Advisory Board Work 

Group on LANL and subsequent research, NIOSH now finds that it lacks sufficient information to 

estimate with sufficient accuracy the potential internal exposures to fission and activation products, 

and various other radionuclides of concern. Therefore, in this revision of the report, NIOSH’s 

evaluation determined that it is not feasible to estimate radiation dose for members of the NIOSHevaluated class with sufficient accuracy based on the sum of information available from available 

resources. Therefore, the resulting NIOSH-proposed SEC class must include a minimum required 

employment period as a basis for specifying that health was endangered. 

9.0 Class Conclusion for Petition SEC-00109

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

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSHproposed class to be added to the SEC includes all employees of the Department of Energy, its 

predecessor agencies, and their contractors and subcontractors who worked at the Los Alamos 

National Laboratory in Los Alamos, New Mexico from January 1, 1976 through December 31, 1995, 

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. 

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-00109. 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 

10 CFR 835 pt. 402, Occupational Radiation Protection, Part 402, Individual Monitoring; accessed 

via Internet on July 23, 2012; http://ecfr.gpoaccess.gov/cgi/t/text/textidx?c=ecfr&rgn=div5&view=text&node=10:4.0.2.5.27&idno=10#10:4.0.2.5.27.5.82.2 

10 C.F.R. pt. 835, App. C, Occupational Radiation Protection, Appendix C: Derived Air 

Concentrations (DAC) for Controlling Radiation Exposure to Workers at DOE Facilities, accessed 

via the Internet on August 27, 2008; http://www.hss.energy.gov/HealthSafety/WSHP/Radiation/ 

10cfr835/finalfedregjune82007.pdf 

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; available on OCAS website: www.cdc.gov/niosh/ocas/ 

Asprey, 1964, Protactinium Fluorides, the New Class, MPaF6, L. B. Asprey and R. A. Penneman; 

Science 145, no. 3635, p. 934, August 28, 1964 

Bayo, 1963, Letter from N. E. Bradbury to C. C. Campbell; LANL; July 18, 1963; SRDB Ref ID: 885 

Bayo, date unknown, Estimates of Materials at the Bayo Canyon Firing Sites; author unknown; date 

unknown; Los Alamos Scientific Laboratory; SRDB Ref ID: 7895

Blackstock, 1978, Neutron Response of a New Albedo-Neutron Dosimeter, University of California, 

Los Alamos Scientific Laboratory, A. W. Blackstock, J. R. Cortez, G. J. Littlejohn, E. Storm, January 

17-19, 1978; SRDB Ref ID: 27246 

Buckland, 1976, Health Physics Aspects of Thorium, office memorandum from C. Buckland (Leader, 

H-1 General & Materials Monitoring) to Tom Larson (Alt. Group Leader, WX-2, MS-920); Los 

Alamos Scientific Laboratory; October 29, 1976; SRDB Ref ID: 54382 

Buddenbaum, 2006a, E-mail correspondence: LANL Lab Notebooks, J. Buddenbaum; 

ENSR|AECOM; Westford, Massachusetts; September 1, 2006; SRDB Ref ID: 27995 
SEC-00109, Rev. 1 08-13-12 LANL

66 of 98 

Buddenbaum, 2006b, Conference Call Minutes, Final, J. Buddenbaum; ENSR|AECOM; Westford, 

Massachusetts; February 13, 2006; SRDB Ref ID: 27992

Cerro Grande, 2001, Updated Calculations of the Inhalation Dose from the Cerro Grande Fire Based 

on Final Air Data; LA-UR-01-1132; February, 2001; SRDB Ref ID: 46247 

Checklist, 1977, Employee Health Physics Check List; Los Alamos National Laboratory; various dates 

in 1977; SRDB Ref ID: 54392 

Checklist, 1985, Employee Health Physics Checklist, Los Alamos National Laboratory, HS Form 

Number 3-1A (6/84); April 9, 1985; SRDB Ref ID: 54543 

Checklist, 1990, Employee Health Physics Checklist, Los Alamos National Laboratory, HS Form 

Number 3-1A (9/86); April 12, 1990; SRDB Ref ID: 51438 

Checklist, 2000, Health Physics Checklist, Version 2000 10 18 v1 release, Los Alamos National 

Laboratory; SRDB Ref ID: 12969 

Conference Call A, 2008: ORAU Team and NIOSH with LANL Radiation Protection Division 

Personnel; August 7, 2008; SRDB Ref ID: 55742 

Conference Call B, 2008: ORAU Team and NIOSH with LANL Radiation Protection Division 

Personnel; August 28, 2008; SRDB Ref ID: 55741

Conference Call C, 2008: ORAU Team and NIOSH with LANL Radiation Protection Division 

Personnel; September 9, 2008; SRDB Ref ID: 55744

Criteria, 1982, 1982 Criteria for Routine Am-241 Urine Sampling, J. N. P. Lawrence; June 24, 1982; 

SRDB Ref ID: 51533, pdf. pp 20-21 

DCAS-PR-004, Internal Procedures for the Evaluation of Special Exposure Cohort Petitions, Rev. 1, 

National Institute for Occupational Safety and Health (NIOSH); Cincinnati, Ohio; April 15, 2011; 

SRDB Ref ID: 94768 

DHHS, 2010, DHHS Designation of Additional Members of the Special Exposure Cohort under the 

Energy Employees Occupational Illness Compensation Program Act for Los Alamos National 

Laboratory, Los Alamos, New Mexico; Department of Health and Human Services (DHHS); August

23, 2010; DSA Ref ID: 112505 

DOE, 1990, Results of DOE Indoor Radon Study, August 1990, Vol. 1, DOE, August 1990; SRDB 

Ref ID: 13191 

DOE, 1991, Tiger Team Assessment of the Los Alamos National Laboratory, U.S. Department of 

Energy; November 1991; SRDB Ref ID: 23620 

DOE, 1993, Operable Unit 9 Site Scoping Report, Volume 7, Waste Management, U.S. Department of 

Energy; Environmental Restoration Program; February 1993; SRDB Ref ID: 11877 
SEC-00109, Rev. 1 08-13-12 LANL

67 of 98 

DOE Order 5480.11, Radiation Protection for Occupational Workers, U.S. Department of Energy, 

December 21, 1988; SRDB Ref ID: 8073 

DOE/EH-0575, 1997, DOE Occupational Radiation Exposure – 1997 Report, U.S. Department of 

Energy, Office of Worker Safety and Health; DOE/EH-0575; 1997; SRDB Ref ID: 64900, pdf p. 15 

Dummer, date unknown, Quarterly Progress Report April - June, 1978, J. E. Dummer, Los Alamos 

Scientific Laboratory, date unknown; SRDB Ref ID: 40679 

Ennis, M., 2003, Historical Minimum Detectable Activities for LANL’s In Vivo Measurements 

Laboratory, LA-UR-03-7702, Los Alamos National Laboratory; SRDB Ref ID: 27304 

Eppley, 1979, Reported Needs for the Radioactive Isotopes Uranium-234, Protactinium-231, 

Thorium-230, and Thorium-229, R. E. Eppley and R. E. Vallee; MLM-ML-77-46-0003; Monsanto 

Research Corporation, Mound Laboratory; June 1, 1979; SRDB Ref ID: 25195 

Farr, 1953, Crystal Structure of Actinium Metal and Actinium Hydride, J. D. Farr, A. I. Giorgi, and M. 

G. Bowman; LA-1545, Los Alamos National Laboratory, April 1953; SRDB Ref ID: 970 

Follow-up, 1985, Radiation Exposure Follow-up, Los Alamos National Laboratory, November 1985; 

SRDB Ref ID: 54280, pdf p. 3 

Harper, 1981, The Decommissioning of TA-21-153, 227Ac Contaminated Old Filter Building, J. R.

Harper and R. Garde; LA-9047-MS; Los Alamos National Laboratory; November 1981; SRDB Ref 

ID: 929 

Hoffman, 1999, The LANL Model 8823 Whole-Body TLD and Associated Dose Algorithm, J. M. 

Hoffman and M. W. Mallett; Los Alamos National Laboratory; Radiation Protection Journal; Vol. 77, 

No. 5 suppl, November 1999; OSA Ref ID: 105765 

Inkret, 1998a, Los Alamos National Laboratory Radiological Dose Assessment – Tritium Internal 

Dosimetry and Bioassay Programs, Inkret, W. C., D. Lewis, T. T. Little, G. Miller, and M. E. 

Schillaci, LA-UR-99-832, Los Alamos National Laboratory 1998; SRDB Ref ID: 13485 

Inkret, 1998b, Los Alamos National Laboratory Radiological Dose Assessment – Americium Internal 

Dosimetry and Bioassay Program, W. C. Inkret, D. Lewis, G. Miller, and M. E. Schillaci; 

LA-UR-99-836; Los Alamos National Laboratory; 1998; SRDB Ref ID: 13488 

Inkret, 1999a, Los Alamos National Laboratory Radiological Dose Assessment – Tritium Internal 

Dosimetry, W. C. Inkret, D. Lewis, G. Miller, and M. E. Schillaci; LA-UR-99-838; Los Alamos 

National Laboratory; 1999; SRDB Ref ID: 12899 

Inkret, 1999b, Internal Dosimetry for Inhalation of Hafnium Tritide Aerosols, W. C. Inkret, M. E. 

Schillaci, Y. S. Cheng, D. W. Efurd, T. T. Little, G. Miller, J. A. Musgrave, J. R. Werner; Los Alamos 

National Laboratory; LA-UR-98-4818; August 10, 1999; SRDB Ref ID: 12906 
SEC-00109, Rev. 1 08-13-12 LANL

68 of 98 

Inspection of Environment, 2005, Inspection of Environment, Safety, and Health Programs at the Los 

Alamos National Laboratory, Office of Independent Oversight, Office of Security and Safety 

Performance Assurance, Office of the Secretary of Energy, November 2005; OSA ID: 106015 pdf pp. 

993 

Internal Dosimetry, 2007, Internal Dosimetry Question, P. Hoover, Los Alamos National Laboratory; 

January 3, 2007; SRDB Ref ID: 28600 

Investigation, 2006, Type B Investigation of the Am-241 Contamination Accident at the Sigma 

Facility, LANL, July 14, 2005, Doug Minnema; National Nuclear Security Administration; May, 3, 

2006; SRDB Ref ID: 46117 

Jette, 1949a, CMR Division Progress Report July 20, 1949 – August 20, 1949, E. R. Jette; LAMS-945, 

Los Alamos National Laboratory; 1949; SRDB Ref ID: 41103 

Jette, 1949b, CMR Division Progress Report August 20, 1949 – September 20, 1949, E. R. Jette; 

LAMS-957, Los Alamos National Laboratory; 1949; SRDB Ref ID: 41104 

Kirby, 1959, The Radiochemistry of Protactinium, H. W. Kirby; U.S. Energy Commission Report 

NAS-NS 3016; Subcommittee on Radiochemistry, National Academy of Sciences, National Research 

Council; Washington, D.C.; December 1959; SRDB Ref ID: 41602 

Kirkham, 2006, Urine Bioassay Data Indicating Americium Bioassay Analysis (1954-1957), raw data 

logs captured by T. Kirkham; Los Alamos National Laboratory; various dates; SRDB Ref ID: 27951 

Langham, 1952, Toxicology of Actinium Equilibrium Mixture, W. Langham and J. Storer; LA-1372; 

Los Alamos National Laboratory; February 20, 1952; SRDB Ref ID: 974 

LANL, 1986, Photodosimetry Evaluation Book, Volume IV, Los Alamos National Laboratory; 1986; 

SRDB Ref ID: 8206 and 8209 

LANL, 1989, Photodosimetry Evaluation Book, Volume VI, Los Alamos National Laboratory; 1989; 

SRDB Ref ID: 27288 

LANL, 1996, Photodosimetry Evaluation Book, Volume VII, Los Alamos National Laboratory; 1996; 

SRDB Ref ID: 27273 

LANL, 2001, Photodosimetry Evaluation Book, Volume VIII, Los Alamos National Laboratory; 2001; 

SRDB Ref ID: 27292 

LANL, 2003, Photodosimetry Evaluation Book, Volume IX, Los Alamos National Laboratory, 2003; 

SRDB Ref ID: 27301 

LANL, 2004a, Health Physics Checklist, http://eshdb.lanl.gov/~esh12/new_eshdb/Matrices, accessed 

April 30, 2004; SRDB Ref ID: 12969 
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69 of 98 

LANL, 2004b, Notes Regarding the LANL Dosimetry Data Obtained During 2004, Los Alamos 

National Laboratory; 2004; SRDB Ref ID: 27261 

LANL, 2008, LANL Response to NIOSH Request Regarding SEC Petition [SEC-00109], Paul Hoover, 

Radiation Protection Division, Los Alamos National Laboratory; September 2, 2008; SRDB Ref ID: 

55136 

LASL, 1959a Photodosimetry Evaluation Book “Bible,” Volume I, Procedures 1944-1959; Los 

Alamos Scientific Laboratory; 1959; SRDB Ref ID: 8181 and 8266 

LASL, 1959b, H-Division Progress Report, August 20 - September 20, 1959, T. L. Shipman; Los 

Alamos Scientific Laboratory; HSPT-REL-94-912; SRDB Ref ID: 12914 

LASL, 1969, Photodosimetry Evaluation Book “Bible,” Volume II, Procedures 1960-1969; Los 

Alamos Scientific Laboratory; 1969; SRDB Ref ID: 8173 

LASL, 1977a, Photodosimetry Evaluation Book, "Bible" Volume III, Procedures, 1970-1977, Los 

Alamos Scientific Laboratory; SRDB Ref ID: 8176 and 8192 

LASL, 1977b, Quarterly Progress Report, July – September 1977, J. E. Dummer; Los Alamos 

Scientific Laboratory; Group H-1 Health Physics; SRDB Ref ID: 27314 

LASL, 1977c, Quarterly Progress Report, October – December 1977, J. E. Dummer; Los Alamos 

Scientific Laboratory; Group H-1 Health Physics; SRDB Ref ID: 27317 

LASL, 1978, Quarterly Progress Report, April – June 1978, Group H-1, Health Physics; Los Alamos 

Scientific Laboratory; 1978; SRDB Ref ID: 40697 

LASL, 1979, Photodosimetry Evaluation Book, Volume V, Los Alamos Scientific Laboratory; 1979; 

SRDB Ref ID: 2727 

LASL-77-25, Welcome to Los Alamos, capsule summary of LASL site; Los Alamos Scientific 

Laboratory; 1977; SRDB Ref ID: 54586 

List, 2008, Internet site: Complete List of All U.S. Nuclear Weapons, 

http://nuclearweaponarchive.org/Usa/Weapons/Allbombs.html, compiled from various cited reference 

sources

Little, 2003a, Identifying Uranium Intakes from Bioassay Data in the Presence of Environmental 

Background, T. T. Little, G. Miller, and R. Guilmette; Proceedings of the 49th Annual Radiobioassay 

& Radiochemical Measurements Conference; 2003; http://www.bioassay.org/2003; SRDB Ref ID: 

12939 

Little, 2003b, Special Dose Assessment, T. Little, G. Miller, and R. Guilmette, July 2, 2003; SRDB 

Ref ID: 55135 
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Mallett, 1990, High-Energy Neutron Dosimetry at the Clinton P. Anderson Meson Physics Facility, 

LA-11740-MS, University of California, Los Alamos National Laboratory; M. W. Mallett, D.G. 

Vasilik, G. J. Littlejohn, J. R. Cortez; January 1990; SRDB Ref ID: 912 

Mosteller, 2003, Creation of a Simplified Benchmark Model for the Neptunium Sphere Experiment, R. 

D. Mosteller and D. J. Loaiza; Los Alamos National Laboratory; ANS/ENS 2003 Winter Meeting; 

New Orleans, LA; November 16-23, 2003; SRDB Ref ID: 49288 

Mound, 1995, Technical Manual, Mound Site Radionuclides by Location, Issue 1, MD-22153, July 

26, 1995; SRDB Ref ID: 3240

Neptunium, 2005, Inspection of Environment, Safety, and Health Programs at the Los Alamos 

National Laboratory; Office of Independent Oversight, Office of Security and Safety Performance 

Assurance, Office of the Secretary of Energy; November 2005: OSA Ref ID: 106015, pdf. p. 993 

NUREG-1400, Air Sampling in the Workplace, Final Report, Division of Regulatory Applications, 

Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission; September 

1993; SRDB Ref ID: 20129 

O’Brien, 2006, Los Alamos National Laboratory (LANL) Bioassay Data Project Final Report, J. M. 

O’Brien; Shonka, Inc.; Atlanta, Georgia; June, 2006; SRDB Ref ID: 49287 

OCAS-TIB-002, Tritium Calculations with IMBA, Rev. 00, Office of Compensation Analysis and 

Support, Technical Information Bulletin, April 22, 2003; SRBD Ref ID: 22407 

ORAUT-OTIB-0006, Dose Reconstruction from Occupational Medical X-Ray Procedures, Rev. 04; 

June 20, 2011; SRDB Ref ID: 98147 

ORAUT-OTIB-0019, Analysis of Coworker Bioassay Data for Internal Dose Assignment, Rev. 01; 

October 7, 2005; SRDB Ref ID: 19438 

ORAUT-OTIB-0054, Fission and Activation Product Assignment for Internal Dose-Related Gross 

Beta and Gross Gamma Analyses, Rev. 00, November 19, 2007; SRDB Ref ID: 36235 

ORAUT-OTIB-0062, Internal Dosimetry Coworker Data for Los Alamos National Laboratory; Rev. 

00; October 15, 2009; SRDB Ref ID: 75028 

ORAUT-OTIB-0063, Los Alamos National Laboratory Bioassay Data Project Final Report; Rev. 00; 

August 24, 2009; SRDB Ref ID: 73101 

ORAUT-OTIB-0066, Calculation of Dose from Intakes of Special Tritium Compounds, Rev. 00, April 

26, 2007; SRDB Ref ID: 31421 

ORAUT-OTIB-0079, Guidance on Assigning Occupational X-ray Dose Under EEOICPA for X-rays 

Administered Off Site, Rev. 00; January 3, 2011; SRDB Ref ID: 89563 
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ORAUT-PROC-0060, Occupational Onsite Ambient Dose Reconstruction for DOE Sites, Rev. 01; 

June 28, 2006; SRDB Ref ID: 29986 

ORAUT-PROC-0061, Occupational X-Ray Dose Reconstruction for DOE Sites, Rev. 03; March 3, 

2010; SRDB Ref ID: 79758 

ORAUT-TKBS-0010-1, Technical Basis Document for the Los Alamos National Laboratory – 

Introduction, Rev. 01; October 1, 2007; SRDB Ref ID: 35193 

ORAUT-TKBS-0010-2, Technical Basis Document for the Los Alamos National Laboratory – Site 

Description, Rev. 00; May 7, 2004; SRDB Ref ID: 19561 

ORAUT-TKBS-0010-3, Technical Basis Document for the Los Alamos National Laboratory – 

Occupational Medical Dose, Rev. 01; September 14, 2010; SRDB Ref ID: 87132 

ORAUT-TKBS-0010-4, Technical Basis Document for the Los Alamos National Laboratory – 

Occupational Environmental Dose, Rev. 01; March 26, 2010; SRDB Ref ID: 80164 

ORAUT-TKBS-0010-5, Technical Basis Document for the Los Alamos National Laboratory – 

Occupational Internal Dose, Rev. 01; October 15, 2010; SRDB Ref ID: 74987 

ORAUT-TKBS-0010-6, Technical Basis Document for the Los Alamos National Laboratory – 

Occupational External Dose, Rev. 02; November 23, 2009; SRDB Ref ID: 77688 

ORPS, 2003, Curium 244 Detected on Employee’s DOE Badge, Badge Transported Off-site, 

Improper Shipment of Radioactive Material, ORPS Number DP-ALO-LA-LANL-ESHSUPT-2003-

0001, Los Alamos National Laboratory; March 6, 2003; SRDB Ref ID: 57071 

P-Division, 1977, Radiological Safety Procedures in P-Division, W. E. Stein, Radiation Safety 

Committee, Los Alamos National Laboratory; January 1977; SRDB Ref ID: 54253

Penneman, 1960, The Radiochemistry of Americium and Curium, R. A. Penneman and T. K. Keenan; 

NAS-NS-3006, National Academy of Sciences, National Research Council, University of California; 

January 31, 1960; SRDB Ref ID: 41106 

Petition, 2008, SEC Petition and narrative attachment submitted for SEC-00109; OSA Ref ID: 

105760, pdf pp. 11-12 

Processes, Author Unknown, Processes and Characteristics of Major Isotopes Handled at Mound, No 

author, no publication date. SRDB Ref ID: 12328 

Quarterly, 1976, Quarterly Progress Report January – March 1976, J. E. Dummer, Group H-1 Health 

Physics; no issue date; SRDB Ref ID: 44681 

Quarterly, 1979, Quarterly Progress Report October – December 1979, J. E. Dummer, Group H-1 

Health Physics, January 16, 1980; SRDB Ref ID: 40709 
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Quarterly, 1980, Quarterly Progress Report January – March 1980, J. E. Dummer, Group H-1 Health 

Physics, April 14, 1980; SRDB Ref ID: 40710 

Records, 2008, LANL Radiological Incident-related Records, Radiation Protection Division, Los 

Alamos National Laboratory; December 1, 2008; SRDB Ref ID: 55649 

RWP, 1995, Radiological Work Permit, author unknown, 1995; SRDB Ref ID: 51749 

SCA-TR-TASK1-0011, 2006, Los Alamos National Laboratory Site Profile Review, S. Cohen & 

Associates, Saliant Inc., August 2006; SRDB Ref ID: 46217 

SEC-00051, 2007, SEC Petition Evaluation Report, Petition SEC-00051, T. Vitkus, T. Adler, R. 

Clark, D. Mantooth, C. Barton, V. Shockley, R. Kathren; August 7, 2006; SRDB Ref ID: 41108, pdf. 

pp. 76 

Smith, 1979, Superconducting Properties of Protactinium, J. L. Smith, J. C. Spirlet, and W. Muller; 

Science, 205, 188-190, July 13, 1979 

SOPs, 1973, office memorandum, Standard Operating Procedures for the Handling of Actinide 

Elements, R. A. Penneman and L. B. Asprey, Los Alamos Scientific Laboratory, October 15, 1973; 

SRDB Ref ID: 54127 

SOPs, 1976, office memorandum, Radiation Protection Procedures, from J. E. Dummer to J. Aragon; 

Los Alamos Scientific Laboratory; September 17, 1976; SRDB Ref ID: 54264 

Steele, 1998, CMR Basis for Interim Operations, Steele, C. and J. E. O’Neil, Los Alamos National 

Laboratory; August 27, 1998; LAP (Los Alamos Project), 1944a. Progress Report Number Twelve of 

the Experimental Physics Division of the Los Alamos Project, LAM-48. January 1, 1944; 

http://www.doeal.gov/laso/SWEIS/LANLDocuments/279%20LANL%202004%20Cont%20Waste%2

0Gen.pdf 

SWP, 1992, Special Work Permit Radiation Work: Disconnect Thoria Duct, Stack, and Fan, Noel 

Calkins, Los Alamos National Laboratory; July 31, 1992; SRDB Ref ID: 52172, pdf pp. 33-45 

TA-21-153, 1981, The Decommissioning of TA-21-153, Ac-227 Contaminated Old Filter Building, J. 

R. Harper, R. Garde; Los Alamos National Laboratory; November 1981; SRDB Ref ID: 929 

TA-55 RWP, 1994, TA-55 Radiological and Hazardous Work Permit, Sammi Owens, Los Alamos 

National Laboratory; August 30, 1994; SRDB Ref ID: 52396 

Targeted Sr-90, 1997, LANL Bioassay Results for Targeted Sr-90 Dosimetry, Los Alamos National 

Laboratory; 1997; SRDB Ref ID: 55137 

Targeted Th-232, 2000, Whole Body/Chest Count Dosimetry Report, Los Alamos National 

Laboratory; February 23, 2000; SRDB Ref ID: 55138 
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Tribby, 1946, Internal memorandum, Health Protection of Maintenance Personnel Working in 

Contaminated Areas, J. F. Tribby; Los Alamos Scientific Laboratory; May 14, 1946; SRDB Ref ID: 

27980

Tyree, 1974, Single Scintillation Crystal Versus Phoswich Detectors for In Vivo Low-Energy Photon 

Detection, W. H. Tyree, Dow Chemical, January 7, 1974; SRDB Ref ID: 24382 

Tyree, 1975, Operating Parameters and Limitations of a Germanium-Lithium Drifted Detector System 

for the In Vivo Measurement of Americium-241, W. H. Tyree, R. B. Falk, R. W. Liskey, Dow 

Chemical, February 3, 1975; SRDB Ref ID: 24380 

Vasilik, 1983, In Vivo Assessment of Whole Body Radioisotope Burdens at the Los Alamos National 

Laboratory, D. G. Vasilik and I. C. Aikin; LA-9858-MS, Los Alamos National Laboratory; 1983: 

SRDB Ref ID: 925

Whicker, 1997, Evaluation of Continuous Air Monitor Placement in a Plutonium Facility, J. J. 

Whicker, J. C. Rodgers, C. I. Fairchild, R. C. Scripsick, and R. C. Lopez; Health Physics, Volume 72, 

pp. 734–743; 1997; SRDB Ref ID: 13095

Whicker, 2004, Relationship of Air Sample Measurements to Internal Dose: A Review, J. J. Whicker; 

Health Physics Society Midyear Topical Meeting; 2004; SRDB Ref ID: 13096

Wing 9, 1999, Wing 9 Hot Cells Support Work Involving Highly Radioactive Materials, Actinide 

Research Quarterly, 1st quarter 1999; Nuclear Material and Technology; Los Alamos National 

Laboratory; 1999; http://www.fas.org/sgp/othergov/doe/lanl/orgs/nmt/99spring.pdf. 

Wingfield, 1974, memorandum: Inventory of Quantities and Locations of Radioactivity in the 

Environment On and Near AEC Sites, from E. E. Wingfield (AEC) to R. Taschek (LASL), Los 

Alamos National Laboratory; February 19, 1974; SRDB Ref ID: 12978 

 
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Attachment 1: Documentation Provided by Petitioner

This attachment provides: (1) a list of the supporting documentation received from the petitioner for 

Rev. 0 of the SEC-00109 Evaluation Report; and (2) a list of supporting documentation received after 

the issuance of Rev. 0 and available for consideration for Rev. 1 of this report. 

Documentation Provided for SEC-00109, Rev. 0 

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

petitioner (SEC-00109 Petition: DSA Ref ID 105760): 

• Type B Investigation of the Am-241 Contamination Accident at the Sigma Facility, LANL; July 

14, 2005; Doug Minnema, PhD, CHP 

• Office Memorandum: Tritium Leak at TA-35-1; August 4, 1980; John Ahlquist 

• Informal Investigation Report: Kiva I UF6 Release Bldg 23, TA-18 on August 22, 1979; R. E. 

Malenfant, A. M. Valentine 

• LANL SEC Petition, 1943-1975 

• DOE/IG-0591 Allegations Concerning the Reporting of a Radiological Incident at the Los Alamos 

National Laboratory

• Stack Parameters Annual Review, 1984 

• The Los Alamos National Laboratory's Air Emissions Monitoring Program: A Quick Look 

Technical Review (9/9/91); Ray Waller, Charles Keller, and Sumner Barr 

• Resource Conservation and Recovery Act (RCRA) Permit Containing All Changes Since 1995; 

September 27, 2004; Jack Ellvinger 

• Aspects of Dispersion following an Explosive Release (2004); D. M. Deaves, C. R. Hebden 

• Improving the Accuracy of Dispersion Models; Richard H. Schulze 

• The Physics and Mechanisms of Primary Blast Injury; James H. Stubmiller, Yancy Y. Phillips III, 

and Donald R. Richmond 

• Blast Loading and Blast Effects on Structures - An Overview (2007); T. Ngo, P. Mendis, A. 

Gupta, and J. Ramsay 

• Guidelines for the Inclusion of Low Wind Speed Conditions into Risk Assessments (2000); I.G. 

Lines, J. H. Daycock, and D. M. Deaves 
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• Workbook on the Dispersion of Dense Gases (1988); R. E. Britter, J. McQuaid

• Considering the Feasibility of Developing a Simple Methodology to Assess Dispersion in 

Low/Zero Windspeeds (1998); I. G. Lines, D. M. Deaves 

• Tiger Team Report 1 

• Tiger Team Report 2

• Security and Other Issues Related to Out-Processing of Employees at Los Alamos National 

Laboratory; DOE/IG-0677 (2005) 

• Fire maps

• Comments on the 2002 Risk Assessment Corporation analysis of risks from the 2000 Cerro 

Grande fire at Los Alamos National Laboratory (2005); Abel Russ 

• Effects of the Cerro Grande Fire (Smoke and Fallout Ash) on Soil Chemical Properties; LA13769-MS

• Radiological and Nonradiological Effects after the Cerro Grande Fire; LA-1391 

• Updated Calculation of the Inhalation Dose from the Cerro Grande Fire; LA-UR-01-1132 

• The Cerro Grande Fire, Los Alamos, New Mexico; LA-UR-01-1630 

• Lessons Learned From the Cerro Grande (Los Alamos) Fire; GAO/T-RCED-00-273 

• Summary Report: Analysis of Exposure and Risks to the Public from Radionuclides and 

Chemicals Released by the Cerro Grande Fire at Los Alamos (2002); S. Shawn Mohler, et al. 

• Memo: Some Quality Assurance Issues Regarding Input Data For Unmonitored Sources Dose 

Estimation Date; September 1, 2002; Arjun Makhijani 

• Memo: Some issues for the ITAT review regarding unmonitored sources during the third CAA 

audit; July 11, 2002; Arjun Makhijani 

• DOE/EIS-0380D, June 2006 Draft, Site Wide Environmental Impact Statement for Continued 

Operation of Los Alamos National Laboratory; Los Alamos, New Mexico 

• LA-14341-ENV, Environmental Surveillance 2006 

• Long-Term Risk from Actinides in the Environment: Modes of Mobility (2000); David D. 

Breshears, et al.
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• LANL Hazardous Waste Permit Fact Sheet Attachment listing new SWMUs and AOCs

• Increased Wind Erosion from Forest Wildfire: Implications for Contaminant-Related Risks 

(2006); Jeffrey J. Whicker, John E. Pinder III, and David D. Breshears 

• LA-13839-MS, U.S. Department of Energy Report 2000; LANL Radionuclide Air Emissions 

(Parts 1, 2, and 4); Keith Jacobson 

• LA-UR-00-3471, Special Edition of the SWEIS Yearbook: Wildfire 2000 

• LA-UR-04-0195, Unplanned Airborne Releases at Los Alamos National Laboratory: A 

Comparison between Observations and Model Predictions (2004); Scot Johnson 

• New Mexico's Right to Know: The Impacts of Los Alamos National Laboratory Operations on 

Public Health and the Environment (2003); Bernd Franke, Catherine M. Richards, Steve Wing, 

and David Richardson 

• Final Report, Independent Technical Audit of Los Alamos National Laboratory for Compliance 

with the Clean Air Act, 40 CFR 61, Subpart H in 2001; DOJ File Number: 90-5-1749A; Case 

Name: CCNS v DOE October 2002 (Independent Technical Audit for 2001) 

• LANL Environmental Surveillance 2000 

• In-Place Testing Summary (1991); John P. Ortiz, Douglas Barney 

• Dispersion Near Buildings; Application of Simple Modeling (1997); I. G. Lines, D. M. Deaves 

• Citizens Monitoring and Technical Assessment - June 2007 Analysis of Radiochemical 

Contaminants in Los Alamos Region Biota and Environmental Materials at the Perimeter of the 

Los Alamos National Laboratory; Marco Kaltofen (PE), Tom Carpenter 

• Better Oversight Needed for Safety and Health, Activities at DOE's Nuclear Facilities; EMD-81-

108 (1981) 

• Nuclear Health and Safety Efforts to Strengthen DOE's Health and Epidemiology Program; 

GAO/RCED-91-67 (1991)

• GAO/RCED-98-197, Uncertain Progress in Implementing Reforms (1998) 

• Need for Improved Responsiveness to Problems at DOE Sites; GAO/RCED-90-101 

• DOE's Safety and Health Oversight Program at Nuclear Facilities Could Be Strengthened; 

GAO/RCED-84-50 (1993)

• Better Planning Needed to Correct Records Management Problems, GAO/RCED-92-88 (1992) 
SEC-00109, Rev. 1 08-13-12 LANL

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• Corrective Actions on Tiger Teams' Findings Progressing Slower Than Planned; GAO/RCED-93-

66 (1993) 

• Protecting Workers and the Public Continues to Challenge; DOE GAO/T-RCED-94-283 (1994) 

• Handbook on Atmospheric Diffusion (1982); Steven R. Hanna, Gary A. Briggs, and Rayford P. 

Hosker, Jr. 

• General and Specific Characteristics for Model: HOTSPOT

• Feasibility study of Modeling Particle Deposition onto a Person using Computational Fluid 

Dynamics (2006); N. Gobreau, D. Mark, and A. Garrard

• Audit Report on "The Department's Reporting of Occupational Injuries and Illnesses”; DOE/IG0648 (2004) 

• Characterization Wells at Los Alamos National Laboratory; DOE/IG-0703 (2005) 

• A Guide to Radiological Accident Considerations for Siting and Design of DOE Nonreactor 

Nuclear Facilities; J. C. Elder, et al.

• LA-13235-T, Compliance Program for 40 C.F.R. 61, Subpart H at Los Alamos National 

Laboratory (1997); Eric A. McNamara 

• Brief Climatology for Los Alamos, N. M.; UNL, 1999 

• Los Alamos Cancer Rate Study: Phase I Cancer Incidence in Los Alamos County, 1970- 1990 

Final Report (1993); William F. Athas, PhD; Charles R. Key, MD, PhD 

• LAMS-202, Explosives (1945); G.M. Kistiakowski 

• Death Rate Report for New Mexico by County, death years through 2002 

• LA-UR-97-4765, Overview of Los Alamos National Laboratory - 1997 

• LASL-77-36, Laboratory Activities Description of Work Done At MSL By Division, Department, 

and Group (1977) 

• LA-UR-00-1168, Siting of Environmental Direct-Penetrating-Radiation Dosimeters; Michael W. 

McNaughton, David H. Kraig, and Joseph C. Lochamy 

• LA-UR-00-3091, Performance Evaluation of LANL Environmental Radiological Air Monitoring 

Inlets at High Wind Velocities Associated with Re-suspension; John Rodgers, Piotr Wasiolek, Jeff 

Whicker, Craig Eberhart, Keith Saxton, and David Chandler 
SEC-00109, Rev. 1 08-13-12 LANL

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• Long Term Tracer Study at Los Alamos, New Mexico; Part I: Wind, Turbulence, and Tracer 

Patterns (1994); Brent M. Bowen 

• Long Term Tracer Study at Los Alamos, New Mexico; Part II: Evaluation and Comparison of 

Several Methods to Determine Dispersion Coefficients; Brent M. Bowen 

• New Mexico Air Quality Bureau Dispersion Modeling Guidelines (2003) 

• Mixing Heights, Wind Speeds, and Potential for Urban Air Pollution Throughout the Contiguous 

United States (1972); George C. Holzworth 

• Los Alamos National Laboratory Radiological Facility List; PS-OAB-403, Rev. 1 (2002); George 

F. Nolan 

• DOE/DP-0137, Plutonium - The First 50 Years (1996); United States Plutonium Production, 

Acquisition, and Utilization from 1944 through 1994 (1996) 

• The Effect of Stack Height, Stack Location and Rooftop Structures on Air Intake Contamination: 

A Laboratory and Full-Scale Study (2004); Ted Stathopoulos, Louis Lazure, Patrick Saathoff, and 

Amit Gupta

• Source Term Modeling of Releases within Building Complexes (2003); A. Scaperdas and C. R. 

Hebden

• LA-UR-98-4539, Emergency Responders' "Rules-of-Thumb" for Air Toxics Releases in Urban 

Environments (1998); Michael J. Brown 

• SCA-TR-TASK1-0011, Los Alamos National Laboratory Site Profile Review (2006); Joseph 

Fitzgerald

• Investigation of Excess Thyroid Cancer Incidence in Los Alamos County Final Report (1996); 

William F. Athas

• Dangerous Discrepancies: Missing Weapons Plutonium in Los Alamos National Laboratory 

Waste Accounts (2006); Arjun Makhijani and Brice Smith, 

• LANL-04M, Satellite Image of Los Alamos 

• Draft Report, Independent Technical Audit of Los Alamos National Laboratory for Compliance 

with the Clean Air Act, 40 CFR 61, Subpart H in 2001; DOJ File Number: 90-5-1749A; Case 

Name: CCNS v DOE October 2002 (CCNS Comments)

• Final Report, Independent Technical Audit of Los Alamos National Laboratory for Compliance 

with the Clean Air Act, 40 CFR 61, Subpart H in 2001; DOJ File Number: 90-5-1749A; Case 

Name: CCNS v DOE October 2002 (IEER Comments) 
SEC-00109, Rev. 1 08-13-12 LANL

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• Monitoring Report of the Institute for Energy and Environmental Research on the First 

Independent Technical Audit of the Los Alamos National Laboratory's Compliance Status with 

Respect to the Clean Air Act II; April 2000; Arjun Makhijani and Bernd Franke 

• Final Report of the Institute for Energy and Environmental Research on the Second Clean Air Act 

Audit of Los Alamos National Laboratory by the Independent Technical Audit Team; December 

13, 2000; Arjun Makhijani and Bernd Franke 

• Report of the Monitoring Team of the Institute for Energy and Environmental Research on the 

[Third] Independent Audit of Los Alamos National Laboratory for Compliance With the Clean Air 

Act, 40 CFR 61, Subpart H in 2001 to Concerned Citizens for Nuclear Safety; December 18, 

2002; Arjun Makhijani, Ph.D.; Bernd Franke 

• LANL Comments on the RAC Audit Draft Report 

• LANL ES&H Self Assessment LANL SWElS, 1999 

• Aerodynamic Properties of Urban Areas Derived from Analysis of Surface Form (1999); C. S. B. 

Grimmond and T. R. Oke 

• Application of Atmospheric Transport Models for Complex Terrain (1984); David S. King and 

Susan S. Bunker 

• Atmospheric Transport Models for Complex Terrain (1984); C. G. Davis, S. S. Bunker, and J. P. 

Mutschlecner 

• Diffusion in a Canyon within Rough Mountainous Terrain (April 1975); G. E. Start, C. R. 

Dickerson, and L. L. Wendall 

• Dispersion in Complex Terrain: A Summary of the AMS Workshop; Bruce A. Egan and Francis 

Schierrneier

• Dispersion Parameters over Forested Terrain (1988); R. T. Pinker and J. Z. Holland 

• Earth's Atmosphere, Wikipedia 

• Meteorology, Wikipedia 

• Influence of External Meteorology on Nocturnal Valley Drainage Winds (1988); Sumner Barr and 

Montie M. Orgill

• Harmonization in the Preprocessing of Meteorological Data for Atmospheric Dispersion Models 

(COST 710); Bernard Fisher and David Thomson 

• Nocturnal Wind Direction Shear and Its Potential Impact on Pollutant Transport (2000); Brent M. 

Bowen, Jeffrey A. Baars, and Gregory L. Stone 
SEC-00109, Rev. 1 08-13-12 LANL

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• Potential Temperature Analysis for Mountainous Terrain (1972); Owen P. Cramer 

• On Pressure-Driven Wind in Deep Forests (1989); Joshua Z. Holland 

• Surface Delays for Gases Dispersing in the Atmosphere (2001); John D. Wilson, Thomas K. 

Flesch, and Real D'Arnours 

• Tributary, Valley and Sidewall Air Flow Interactions in a Deep Valley (1989); William F. Porch, 

Richard B. Fritz, Richard L. Coulter, and Paul H. Gudikson 

• Two-Zone Convective Scaling of Diffusion in Complex Terrain (1994); C.E. Skupniewicz 

• U.S. Standard Atmosphere, 1976 

• Price-Anderson letters that detail violations by LANL of the Price-Anderson Act, as amended. 

• Special Environmental Analysis: Cerro Grande Fire

• Rad-NESHAPs Project Records: Quality Assurance Review of Dose Factors Calculated from 

Nuclear Decay Data for S-38 

• Rad-NESHAPs Project Records: Quality Assurance Review of Dose Factors Calculated from 

Nuclear Decay Data for S-37 

• Rad-NESHAPs Project Records: Quality Assurance Review of Dose Factors Calculated from 

Nuclear Decay Data for S-35 

• Rad-NESHAPs Project Records: Quality Assurance Review of Dose Factors Calculated from 

Nuclear Decay Data for Au-192 

Documentation Provided for SEC-00109, Rev. 1 

• PowerPoint Presentation by the Petitioner entitled Support Services Workers Special Exposure 

Cohort Petition (DSA Ref ID: 108272 

• Video of the play Dr. Atomic(DSA Ref ID: 108273 

• Video of an explosion with the heading LiveLeak from HumorOn.com(DSA Ref ID: 108274 

• Document of LANL issues assembled by the petitioner entitled LANL Health Physics Procedures 

and Source Terms(DSA Ref ID: 116585 

• Letter to NIOSH from the petitioner with an attachment listing issues of concern to LANL Support 

Service Workers(DSA Ref ID: 116812 
SEC-00109, Rev. 1 08-13-12 LANL

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Attachment 2: Data Capture Synopsis 

Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Primary Site / Company Name: Los Alamos National 

Laboratory; DOE 1942-Present

Alternate Site Names: Los Alamos Scientific Laboratory

Physical Size of the Site: Forty three square miles, >1,800 

buildings.

Site Population: Approximately 15,600 in 1993, 12,500 in 

1995, 7,580 at beginning of CY-2012, current estimate 

7,000 

Accelerator Health Protection progress report, air emissions monitoring 

program, air sampling analysis results, Albedo-TLD vs. film badge 

study for plutonium-239 recovery workers, aluminum ion plating of 

U(93) fast-burst reactor components, americium oxide production at 

Los Alamos National Laboratory, analyzing an environmental sample 

for PU-244 at LAMPF, neutron and collective dose values supplied by 

LANL, application of curium measurements for safeguarding at 

reprocessing plants, backgrounds for NTA film, bioassay data, division 

progress reports, curium-248 separation, detection limits for chest 

counting, disposal of solid contaminated waste materials, stack 

discharge reports, history of plutonium body burden from urine assays, 

enriched uranium processing operations, environmental monitoring 

program and reports, external dosimetry technical basis document, 

gamma analyses of LAMPF water samples, GMX-11 shots involving 

thorium at PHERMEX, history of LANL'S bioassay program, inventory 

of quantities and locations of radioactivity, determination of tritium in 

urine and water, LASL stack effluent results, locations of burial areas in 

Pajarito Canyon, lung and whole body counting results, multisphere 

neutron spectroscopy measurements, nasal swipe data, NTA film badge 

response to PUF neutrons, overview of the neptunium-237 experiments, 

personnel exposure data, power reactor experiment, radioactivity 

produced in LAMPF water, radiological incidents, radiological surveys, 

report of the Los Alamos Historical Document Retrieval And 

Assessment (LAHDRA) project, special work permits, standard 

operating procedures, TLD badge neutron correction factor at LAMPF, 

trip reports, tritiated water output, urinalysis results, and whole body 

count results.

01/05/2009 676

State Contacted: NA Contacting the state was not considered necessary since LANL is an 

active DOE site and cooperated with relevant data collection.

NA 0

Argonne National Laboratory - East Bioassay program reports, monthly summary of radiation safety 

activities, division reports of activities, radiation contamination 

investigation, special nuclear materials correspondence, and plutonium 

scrap processing.

03/26/2008 8
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Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Brookhaven National Laboratory Ambient air monitoring parameters at DOE facilities, body burdens and 

dose assessment for Bikini Island residents, Cs-137 concentration in 

deer meat at BNL, annual radiation exposure report, DOELAP 

accreditation for BNL, and urinalysis reports.

11/25/2008 10

Cincinnati Public Library Radiation safety in the Manhattan Project and historical information. 08/06/2008 2

Claimant Provided Publication "The Atom", nuclear propulsion for Rockets, and a memo 

concerning technical overexposures.

06/11/2009 8

Colorado State University Library Reclassification of the Tritium Research Laboratory. 04/10/2006 1

Curtiss-Wright, Cheswick, PA Shipping documentation, radiation exposure records, and an operations 

report.

05/01/2009 5

Department of Labor / Paragon Boron-10 production plant shutdown/standby condition, low-level 

mixed waste inventory characteristics, Pinellas plant overview, and 

tritium activities in the United States.

01/23/2012 6

DOE Albuquerque Operations Office Techniques of nuclear cloud sampling, supplement to Manhattan 

District history book, radioactive waste plan, radiological incident, 

hazard level classification, employee technical notebook, and National 

Environmental Policy Act (NEPA) categorical exclusion 

determinations.

01/17/2012 9

DOE Carlsbad Radiation properties of plutonium materials. 08/11/2010 1

DOE Germantown Site history and characterization, Manhattan District history, Ra-Be 

sources, and the effects of the bombing in Japan.

03/07/2011 16

DOE Legacy Management - Grand Junction Office Problems of waste disposal water supply and environmental hazards, 

decontamination of real property, description memo for ultra-hightemperature reactor experiment (UHTREX) decommissioning, 

engineering evaluation, environmental analysis of the Bayo Canyon, 

environmental assessment, low-level waste disposal capacity report, 

normal uranium scrap processing, progress reports, radiological 

surveys, summary of contractual procurement for site Y, and trip 

reports.

08/25/2011 49

DOE Legacy Management - Morgantown Bibliography of epidemiological papers, employee dosimetry files, 

external dose reports, monthly progress reports, radiological incidents, 

radiological work permits, recycled uranium material balance, scope of 

work for subcontract for formerly utilized sites remedial action program 

(FUSRAP), shipment and receipt documentation, and source and special 

nuclear material accountability station symbols.

09/19/2011 30
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Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

DOE Legacy Management - MoundView (Fernald 

Holdings, includes Fernald Legal Database)

Criticality dosimetry, Dayton polonium history file, DOE's annual 

radionuclide air emission report, effluent discharge information, history 

of Fernald, history of polonium dose evaluation research project, history 

of the operation of the Feed Materials Production Center by NLO, Inc., 

Mound technical basis document for stable tritiated particulate and 

organically bound tritium, nationwide survey of normal uranium scrap 

materials, polonium-210 urinalysis data, precious metals program, 

production reports, radioactive waste management status report, 

radiological incidents, shipping radioactive and fissile material 

information, trip reports, and weekly progress reports.

03/18/2009 58

DOE Legacy Management - Westminster Office Acceptance and processing status of PUO2 scrap, tritium incident, 

history of incineration and landfill operations, MED/AEC/DOE external 

dosimetry technology, technical basis document, plutonium metal 

recovery, and pond 207 complex data sheets.

03/14/2012 11

DOE Oak Ridge Operations Definitions of weapons usable uranium-233, external dose by age and 

year, Mallinckrodt Chemical Works – four-plant study classifications of 

radium, radon and thorium exposures, and radiation incidents.

11/18/2011 7

DOE ORO - RHTG Disposition of U-233 from thorex recycle streams. 04/05/2011 3

DOE Office of Scientific and Technical Information 

(OSTI)

Alternate breeder fuel development program report, annual progress 

reports, decontamination of laboratory surfaces for tritium, 

determination of the alpha counting efficiency of filter papers, 

development of techniques for rolling uranium metal, external 

monitoring data, process development quarterly reports, report on 

results of chest x-ray survey, survey of fission product release from 

NERVA fuel material, and thorium receipts.

03/26/2012 26

DOE RF Reading Room - Front Range Community College Beryllium surveillance semi-annual report. 09/15/2005 1

DOE / SC&A Tritium contamination/weapons components. 02/22/2012 1

Eastern Kentucky University Pantex plant history. 04/17/2009 1

Federal Record Center (FRC) - Boston Personnel exposure summaries. 04/27/2012 1

Federal Record Center (FRC) - Chicago Working group on radioactive waste management. 09/27/2012 1

Federal Record Center (FRC) - Dayton Radiation dose determinations from Indium foils. 03/03/2006 1
SEC-00109, Rev. 1 08-13-12 LANL

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Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Federal Record Center (FRC) - Denver ALARA reviews, radiation protection program assessment, autopsy 

related radiological analysis, basis for interim operations, bioassay 

program notebooks and operations documents, bioassay results, 

criticality safety review, cutting and encapsulation of Np-237 sample, 

decommissioning management plans, depleted uranium information, 

emissions from LANSCE, environmental assessment and findings, ESH 

operations procedures, gamma analyses of LAMPF water samples, 

monthly progress reports, quality assurance program plan, hot lab and 

spectrometer information, instrument calibration, LAMPF experiments, 

LANL operations at Nevada Test Site, laser induced fluorescence, 

incoming radioactive material shipments, occupational radiation 

exposure report, radiation safety procedures, radioactive effluent data, 

radiological incidents, radiological surveys including airborne, radiation 

and contamination data, radiological work permits, RCT log books, 

report for weekly LANL stack samples, shipment papers, target design 

for the accelerator production of tritium plant, tiger team self 

assessment, waste characterization and minimization progress reports, 

and whole-body exposure.

02/17/2012 1,097

Federal Record Center (FRC) - Ft. Worth X-ray machine inspection, quality assurance of TLD badge processing, 

and radiation exposure reports.

07/27/2006 3

Federal Record Center (FRC) - Kansas City Acid canyon report on health physics support, analysis of samples for 

uranium, remedial action at Pueblo Canyon, environmental evaluation 

of the Bayo Canyon alternatives, multimedia contaminant 

environmental exposure assessment methodology, need for remedial 

action in Bayo Canyon, Los Alamos, New Mexico, photos of Acid 

Pueblo and Bayo Canyon, radiological plan for Acid Pueblo, 

radiological survey, and remedial action criteria.

08/15/2008 16

Federal Record Center (FRC) - San Bruno Corrective action plan, finger film dosimeter data, description of air 

sampling equipment, and radiation and toxic chemical records review.

09/15/2009 4

General Atomics Shipment information and radiation injury claims. 11/02/2005 2

Hagley Museum and Library Radiation incidents, plutonium button fabrication flow sheet, plutonium 

waste recovery process, trip report, solid radioactive waste incineration 

report, beta-gamma activity of plutonium, The Hanford Story, and Pu238 production.

10/10/2010 31
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Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Hanford Incident reports, shipment documentation of plutonium metals and other 

nuclear materials, Hanford Laboratories operation monthly activities 

reports, Health Division annual reports, Hanford Plutonium Finishing 

Plant (PFP) history, film badge exchange for plutonium exposure 

comparisons, Los Alamos specifications for incoming oxide, 

photodosimetry procedures, plutonium isotopic values contract, 

operations production reports, material accountability report, status 

report on analytical support services action plan for US Testing, storage 

of 16 percent Pu-240 ceramic grade plutonium oxide, determination of 

americium in urine, determination of fluoride in plutonium metal by 

thorium titration, and a weekly activities report.

02/15/2012 48

HASL - EML Airborne survey, urinalysis data, thorium sampling and storage, and 

criticality alarms and dosimetry.

01/21/2011 5

HP Journal Characterization of plutonium aerosol, excretion of plutonium, and 

godive IV radiation measurements.

12/03/2009 3

Idaho National Laboratory Tritium experience and radioactive source information. 04/04/2012 2

Interlibrary Loan Survey of mixed-waste HEPA filters in the DOE complex, 

environmental levels of radioactivity at Atomic Energy Commission 

installations, journal of Glenn Seaborg, and nuclear criticality safety.

05/29/2012 15

Internet - Defense Technical Information Center (DTIC) Chemical and radiochemical composition of thermally stabilized 

plutonium oxide from the plutonium, chloride-catalyzed corrosion of 

plutonium in glovebox atmospheres, effect of compositional variation in 

plutonium on process shielding design, actinide research quarterly 

report, laundry decontamination, final environmental statement, 

purification of 238PUO2 scrap for heat source fuel, reactions of 

plutonium dioxide with water, and a toxicological profile for plutonium.

01/09/2012 30

Internet - DOE Guide to good practices for occupational radiological protection in 

plutonium facilities and a handbook on airborne release fractions/rates.

12/04/2008 3

Internet - DOE Comprehensive Epidemiologic Data 

Resource (CEDR)

Impact of downsizing and reorganization. 01/23/2010 1

Internet - DOE Environmental Management Linking Legacies - Wastes. 10/28/2007 1

Internet - DOE Hanford Declassified Document Retrieval 

System (DDRS)

Monthly engineering and operations reports, hazards of exposure to 

tritium and tritium oxide, monthly report irradiation processing 

department, radiation protection criteria in the 234-5 building, and trip 

reports.

09/01/2010 21

Internet - DOE Legacy Management Considered Sites Monthly progress report. 10/25/2007 2
SEC-00109, Rev. 1 08-13-12 LANL

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Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Internet - DOE OpenNet Advisory committee on human radiation experiments final report, AEC 

response to Los Alamos National Laboratories concerning biological 

testing, WINDSTORM, BUSTER, and JANGLE, declassification of 

today's highly enriched uranium inventories at DOE laboratories, 

history of AFSWP 1947-1954 volume 5, manufacturing statement for 

weapons production schedule of transfers, mortality study of Los 

Alamos workers with higher exposures to plutonium, Mound Plant 

potential release site package, Newell Stannard interview, plutonium 

and environmental metals in man, quarterly progress report, radiation 

protection and the human radiation experiments, plutonium workers 

roundtable, and history of the Inhalation Toxicology Research Institute.

05/05/2012 43

Internet - DOE OSTI Decommissioning a tritium contaminated laboratory and handling 

tritium gas techniques.

02/18/2009 2

Internet - DOE OSTI / SC&A Pinellas Plant facts, accidents and incidents involving radiation in 

Atomic Energy commission activities.

02/21/2007 2

Internet - DOE OSTI Energy Citations Account of Oak Ridge National Laboratory's thirteen nuclear reactors, 

annual report of waste generation prevention progress, estimation of 

Cm-244 intake by bioassay measurements following a contamination 

incident, fabrication options for depleted uranium components in 

shielded containers, fast burst reactors in the U.S.A., and transuranic 

(TRU) waste phase I retrieval plan.

03/10/2012 12
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Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Internet - DOE OSTI Information Bridge 184-inch synchrocyclotron decommissioning, annual site environmental 

report, annual report of waste generation and pollution prevention 

progress, annual reports of the biomedical and environmental research 

program, risk of transporting plutonium oxide and liquid plutonium 

nitrate by truck, characterization of transuranium-contaminated solid 

wastes residues, effects of neutron radiation on niobium, fuel irradiation 

project, integrated data base report for U.S. spent nuclear fuel and 

radioactive waste inventories, inventory and sources of transuranic solid 

waste, quarterly status reports, nuclear facility decommissioning, 

performance and improvements of the tritium handling facility, 

plutonium and americium processing chemistry and technology, 

laboratory notebook, review of major plutonium pyrochemical 

technology, state background radiation levels: results of measurements, 

stockpile management program quarterly report, transportation and 

disposal configuration for low-level and mixed waste, transuranic 

contaminated waste form, tritiated wastewater treatment, and waste 

vitrification projects.

07/10/2012 139

Internet - DOE OSTI Information Bridge / SC&A Preparation and characterization of uranium oxides in support of the K 

basin sludge treatment project.

03/15/2012 1

Internet - Google Project experiments list, ALARA analysis, annual report on waste 

generation, transuranic waste inventory report, constructing predictive 

estimates for worker exposure to radioactivity during decommissioning, 

controlling particulates, temperature, and tritium in an inert glovebox, 

critical experiment logbooks, disposal of mixed radioactive waste, 

occupational radiation exposure, Durango Colorado uranium mill 

tailings inventory, environmental impact statement, environmental 

surveillance, historical timeline, incidents, report of the Los Alamos 

Historical Document Retrieval And Assessment (LAHDRA) project, 

labs accomplishments, mixed analyte performance evaluation program,

neutron tube target loading, NPX-A3 final report, overview of Los 

Alamos National Laboratory, radionuclide air emissions, annual site 

environmental report radiological doses and releases, summary of 

contaminated sites, superconducting properties of protactinium, 

synchrotron-radiation-based investigations, transportation of 

pyrochemical salts, trip reports, and validation of decontamination and 

volume reduction system potential cost savings. 

06/29/2012 273
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Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Internet - Health Physics Journal Estimation of actinide skeletal content in humans based on bone 

samples collected at autopsy and thermal and fast neutron effects on 

dosimeter films.

09/28/2010 2

Internet - LANL Air monitoring and its evolution, curium concentration in spent nuclear 

fuel, environmental surveillance, passive nondestructive assay of 

nuclear materials, Los Alamos site overview, and an actinide research 

quarterly report.

06/27/2011 13

Internet - NIOSH Residual radioactive contamination at atomic weapons employer. 03/24/2012 4

Internet - NRC Agencywide Document Access and 

Management (ADAMS) 

Defense waste and transportation management program implementation 

plan, final environmental impact statement, evaluation of the potential 

for recycling of scrap metals from nuclear facilities, exposure

investigations of workers whose TLD badges recorded exposures over 

the quarterly limits, investigations in gallium removal, methods for 

estimating fugitive air emissions of radionuclides, process modeling of 

plutonium conversion, spent nuclear fuel management programs at 

other generator/ storage locations, storage and disposition of weapons, 

and a waste management plan.

03/27/2012 85

Internet - ORNL Development of process for americium recovery, disposal of radioactive 

wastes, Electronuclear Research Division progress report, 

Homogeneous Reactor progress report, Metallurgy Division progress 

report, Neutron Physics Division progress report, NNSA type B 

accident investigation of the americium contamination accident at the 

SIGMA facility, Operations Division monthly report, Physics Division 

quarterly progress report, quarterly progress report Stable Isotope 

Research And Production Division, report on the disposal of radioactive 

wastes, and the Aircraft Nuclear Propulsion Project at the Oak Ridge 

National Laboratory quarterly progress report.

06/29/2012 55

Lawrence Berkeley National Laboratory Individual exposure records and bioassay logbook and samples. 05/25/2007 3

Lawrence Livermore National Laboratory Factors affecting the design of Albedo-neutron dosimeters, neutron and 

gamma-ray dose measurements at SHEBA, neutron and gamma-ray 

measurements on the little boy comet assembly, Nevada Test Site 

personnel gamma radiation exposures summary, and a radiation 

protection quarterly report.

04/01/2010 16
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Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

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To SRDB

Los Alamos Historical Document Retrieval and 

Assessment (LAHDRA)

235-uranium containing filters, alpha radiation measurements in acid 

canyon, aerosol studies section air emissions annual report, room airflow readings, ambient indoor air and stack air alpha concentration data, 

tritium effluent report, analysis of precipitation occurrences, appraisal 

of available information on uptake by plants of transplutonium elements 

and neptunium, evaluation of health aspects due to environmental 

radioactivity associated with the Trinity Site test, improved Kanne 

tritium monitoring system, in situ radiological survey of three canyons 

at the Los Alamos National Laboratory, analysis reports for samples 

submitted to the Health Physics Analytical Laboratory from stacks, 

analytical results from soil samples, average daily curie output at the 

omega stack, Bayo Canyon activities, beam information, bioassay data, 

chronology of key events, CMR-12 progress reports, discharge of 

radioactive material from stacks, emergency preparedness documents, 

environmental surveillance quarterly reports, approval for tritium items 

for burial, fissile material burial, fluorometric determination of uranium, 

gamma analyses of LAMPF water samples, Godiva radiation related 

documents, log notebooks and tritium swipe results, quarterly progress 

reports, historical stack release information, identification of fissile 

material, impact of strontium-90 and tritium on surface water and 

groundwater, iodine releases and issues, Kanne Chamber calibration 

data, LAMPF emissions, list of waste sources, misfired 500 curies 

experiment, neutron yields of initiator assemblies, neutron-excess 

nuclide procured by fast neutron reactions in LAMPF, estimating 

procedures for surface runoff, sediment yield, and contaminant 

transport, personnel exposure data, plutonium processing, Pu and 

americium radioactivity of solid waste generated, radioactive effluent 

and discharge monitoring report, radiological incidents, reports on stack 

particulate and vapor, strontium-90, cesium-137, and radioactive rare 

earths in environmental rain and air, summary of contaminated wastes 

to disposal pits, analysis reports from hot cell and stack, tritium 

analyses and data, ventilation and exhaust stack information.

12/28/2009 3,982

Los Alamos National Laboratory / SC&A Final Site-Wide Environmental Impact Statement for the Continued 

Operation of the Los Alamos National Laboratory, Los Alamos, New 

Mexico, Volume I - Main Report.

08/06/2004 1

Lovelace Respiratory Research Institute General information on LANL bioassay program. 09/11/2008 2
SEC-00109, Rev. 1 08-13-12 LANL

92 of 98 

Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Metals and Controls Corporation Analysis of Possible Nuclear Material Losses and Possible Liabilities 

Associated with Present Fuel Manufacturing.

08/24/2004 1

Missouri Department of Natural Resources Report on environmental, safety and health vulnerabilities associated 

with plutonium storage, and an environmental impact statement.

10/3/2008 4

Mound Museum Actinium process and equipment development, deuterium-tritium 

mixture sample results, liquid waste quarterly report, fabrication of 

weapon components, plutonium isotopic control, preparation of 

powdered thorium, tables used for decay of actinium-227, and trip 

reports.

02/01/2012 47

National Archives and Records Administration (NARA) -

Atlanta

Shipment documentation, incidents, special reactor report, personnel 

medical information, monthly accountability reports, documentation 

regarding U-233 thorium project, Pu heat source standards, indoor 

radon study, and a summary of work done at Berkeley.

06/17/2008 21

National Archives and Records Administration (NARA) -

Atlanta / SC&A

Dose rate from RTG heat sources, 239 PuBe neutron source 

information, and passive nondestructive assay of nuclear materials.

06/08/2006 3

National Archives and Records Administration (NARA) -

College Park

Availability of medical grade plutonium-238, incident reports, NIOSH 

visit/review notes, production of fissionable materials, personnel 

radiation exposure, report of AEC reactor safeguard committee on 

plutonium fast reactor, and toxicology of actinium.

08/18/2010 14

National Institute for Occupational Safety and Health 

(NIOSH)

Bioassay program overview, cancer rate study, characterization wells at 

Los Alamos National Laboratory, dangerous discrepancies: missing 

weapons plutonium in Los Alamos National Laboratory, environmental 

impact statement, environmental surveillance, hazardous waste permit 

fact sheet, health hazards associated with rolling normal and enriched 

uranium - evaluation and control, improving the accuracy of dispersion 

models, investigation of excess thyroid cancer incidence, long-term risk 

from actinides in the environment: modes of mobility, material control 

and accountability, national laboratory tritium technology deployments 

large scale demonstration and deployment project, radiological incident, 

RALA/Bayo Canyon implosion program, research laboratory Betatron 

files, security issues related to out-processing of employees, surface 

contamination control with uranium rolling operations, trip reports, 

unplanned airborne releases, and uranium aerosols from machining and 

metallurgy operations.

07/09/2012 195
SEC-00109, Rev. 1 08-13-12 LANL

93 of 98 

Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

National Institute for Occupations Safety and Health / 

SC&A

Engineered and administrative safety systems for the control of prompt 

radiation hazards at accelerator facilities and highly enriched uranium 

working group reports.

08/26/2008 6

Nevada Test Site (NTS) Final environmental impact statement for the Nevada Test Site, 

radioactive material shipping records and radiation survey of shipment 

from NTS to LANL.

07/16/2009 8

Nevada Test Site (NTS) / SC&A Aerial measurement of the Kiwi transient nuclear test, aerial 

radiological monitoring Nevada Test Site, Kiwi transient nuclear test 

dose rate survey, and the behavior of coated particles in a large nuclear 

transient.

04/20/2004 7

Nuclear Regulatory Commission Public Document Room Apparatus for the determination of tritium in body fluids and aqueous 

solutions, review of research conducted by Los Alamos National 

Laboratory for the NRC with emphasis on Maxey Flats, Kentucky 

shallow land burial site, audit reports, certificate of disposition for 

disposal of neutron sources, response to Exxon Nuclear Company to 

accept donation of plutonium previously shipped to Los Alamos 

National Laboratory, export license for tritium to Switzerland, projected 

transfer of all Pu-Be neutron sources, and license documentation.

08/08/2011 20

Oak Ridge Library for Dose Reconstruction History of the radioactive barium-lanthanum process and production, 

health physics research reactor hazards summary, Isotopes Division 

annual report, Operations Division monthly report, RALA source 

shipment, developments in uranium enrichment, remedial 

investigation/feasibility study for the Clinch River/Poplar Creek 

operable unit, and waste effluents committee reports.

05/20/2011 13
SEC-00109, Rev. 1 08-13-12 LANL

94 of 98 

Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

ORAU Team Annual dose n/p ratio analysis, annual report radiation exposures for 

DOE and contractor employees, basis for development of an exposure 

matrix for the Mallinckrodt Chemical Company, class of employees 

from LANL, documented communications, environmental nuclide dose 

comparisons, exposure report for Pantex employees at LANL, health 

and mortality among contractor employees at Department of Energy 

facilities, Health Physics Department procedures, history of Granite 

City Steel, instrumentation technical basis document on Eberline 

personnel contamination monitor, internal dosimetry coworker data, 

notes on plutonium contamination on early pits, NTA film fading, 

Pantex film badge data and results, report on alpha continuous air 

monitors, response comparison of film and TLD's, and a technical basis 

document for Los Alamos National Laboratory.

02/29/2012 63

Oak Ridge Institute for Science and Education (ORISE) Chelation DTPA data for DOE employees. 08/06/2009 22

Oak Ridge National Laboratory (ORNL) ORNL homogeneous reactor research and development program, 

technical review of liquid fuel reactors, decontamination of U-236, and 

minutes from the homogeneous reactor project group leaders meeting.

05/24/2012 19

Pantex Plant LANL pits survey and exposure information. 03/06/2008 3

Pantex Plant / SC&A Radiation safety procedures and a Clarksville contamination survey. 06/30/2011 2

Pacific Northwest National Laboratory (PNNL) Polycube oxidation and factors affecting concentrations of gaseous 

products.

04/26/2011 1

Portsmouth Gaseous Diffusion Plant Soluble uranium dosimetry methodology for urine bioassay. 06/30/2011 1

R. S. Landauer No relevant documents identified. 08/06/2012 0

Sandia National Laboratories, CA Exposure information, memo assigning tritium processes lead 

laboratory, shipping records, and tritium plasma experiment 

information.

05/09/2012 8
SEC-00109, Rev. 1 08-13-12 LANL

95 of 98 

Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Sandia National Laboratories, NM Beta dosimetry study and evaluation of Sandia National Laboratories 

Albuquerque, contracts of LANL providing whole body counting 

services for Sandia, health physics log, incident reports, Industrial 

Hygiene Division film dosimetry manual, instrument 

evaluation\calibration, interviews with workers, lung count data, 

operational procedures for portable ion chambers, personnel exposure 

information, plutonium neutron source, shipping data records, 

proceedings of the symposium on instrumentation, experience, 

radioactive waste management data inventories and shipping 

spreadsheet, radiological surveys, Ross Aviation area surveys, sample 

dosimetry reports for Sandia personnel on trips to LANL and Pantex 

sites, shielding analysis and design for the Sandia Engineering Reactor 

Facility (SERF), the new Los Alamos Scientific Laboratory film badge 

and personnel neutron dosimetry packet, trip reports, and urinalysis and 

bioassay records.

02/17/2012 51

Sandia National Laboratories, NM / SC&A Radiological surveys of various areas. 09/15/2010 6

Santa Susana Field Laboratory (SSFL) Characteristics of Pu-Be neutron source and ventilation system 

correspondence.

10/28/2009 3

Savannah River Site Californium packaging facility general information, dosimetry visitors 

cards, health protection monthly summary, historical Pu irradiations, 

material accountability worksheet, radiation survey logsheets, ratio of 

U-232 to U-233 in irradiated thorium, request for whole body 

comparison from Los Alamos National Laboratory , Savannah River 

Laboratory monthly report, trip report, and a Works Technical 

Department progress report.

03/19/2012 30

S. Cohen & Associates (SC&A) Health and safety report Chemicals and Metallurgical Division, 

Operations Grommet and Toggle onsite radiological safety report, 

xenon separation and purification program, intersite analyses of 

deuterium-tritium mixture, indium foil data, review of Sandia 

symposium on instrumentation experience and problems in health 

physics tritium control, Works Technical Department progress report, 

tritium aging effects in LANL, and an AEC workshop on personnel 

neutron dosimetry.

08/05/2011 22
SEC-00109, Rev. 1 08-13-12 LANL

96 of 98 

Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

SC&A / Argonne National Laboratory - East Chicago Operations Office investigation of radioactive contamination 

of a scientist, hot laboratory problems in isolating gram quantities of 

transplutonium elements, report of the Argonne National Laboratory 

committee established to investigate the apparent overexposure of an 

individual to radioactive contamination, and plutonium injection cases.

06/24/2010 4

SC&A / Idaho National Laboratory Airborne radionuclide waste management, CPP production monthly 

report, CPP radiation alarm system, inventory and manufacturing 

statement, environmental survey preliminary summary report of the 

defense production facilities, health physics activity during RALA run, 

inventory and manufacturing statement, radioecological effects on 

animal and human populations near the Idaho National Engineering 

Laboratory, reactor nuclear incidents, summary of RALA cases, and 

transuranic elements in the environment.

06/24/2010 74

SC&A / Internet - DOE Hanford DDRS Hanford monthly report. 10/05/2007 1

SC&A / Los Alamos National Laboratory Accelerator facility, x-ray facility definitions, aerial radiological survey, 

annual x-ray protection survey, application of Bayesian techniques in 

the interpretation of bioassay data, assessment of contamination control, 

Biological and Medical Research group (H-4) annual report, continuous 

air monitor correlation to fixed air sample data at LANL, Monte Carlo 

validation of internal dosimetry algorithms, occupational medicine 

operating procedures for the diagnostic x-ray unit, operational health 

physics and occupational radiation exposure experience at a medium 

energy, high-intensity linear proton accelerator, passive and active 

neutron measurement control and calibration, radiation exposure 

investigation, programmatic assessment of the internal dosimetry, 

ALARA and portable instruments programs, radiation surveys, dose 

assessment non-uniform skin dose, SC&A site expert interview 

questions and responses, and summary of medical and biological 

research activities.

03/29/2012 60

SC&A / NIOSH Plutonium working group report and an environment, safety and health 

progress assessment at Pantex Plant.

06/01/2011 2

SC&A / Nevada Test Site Santa Fe Operations manager report. 06/24/2010 1

SC&A / Stanford Linear Accelerator Center Radioactive material experiments. 06/13/2011 1

SC&A / Sandia National Laboratories, CA Albuquerque Operations Office end of year report. 02/16/2009 1

SC&A / Santa Susana Field Laboratory Trip report and counting tritium smears. 06/24/2010 2

Science Applications International Corp (SAIC) Radiation exposure summary. 09/02/2004 9
SEC-00109, Rev. 1 08-13-12 LANL

97 of 98 

Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Southern Illinois University Review of operations and thorium exposures at the Dow Chemical 

Company Madison Plant, evaluation of environmental control 

technologies for commercial uranium nuclear fuel fabrication facilities, 

disposal of radioactive wastes in the metropolitan St. Louis area, and 

environmental and health legacy of the Mallinckrodt Chemical Works.

10/29/2008 8

Stanford Linear Accelerator Center (SLAC) / SC&A Documents related to actinide experiments. 04/13/2006 1

University of Colorado Norlin Library Workshop on personnel neutron dosimetry and the study of cost and 

benefits of a formal safety program.

04/10/2006 2

University of Rochester, Rad Safety Unit Shipping documentation. 08/20/2008 3

University of TN Library Actinide distribution in the human skeleton, biomedical aspects of 

plutonium, comparative particle sizing study, estimation of initial 

distribution of Am-241 in adult male human skeleton, report of 

plutonium task force 7, and a United States Transuranium and Uranium 

Registries annual report.

03/18/2012 13

Unknown Bayo Canyon operations and procedures, description of technical areas 

and facilities, dosimetry for the Godiva 2, environmental surveillance, 

exposure level of employees, film-badge method of differential 

measurements, gamma-ray signal produced by a neutron flux, high 

energy neutrons in a collimated beam from the fast plutonium reactor, 

history of the Neutron Science Center, history of the plutonium 

bioassay program, in vivo data, film badge procedures, introduction to 

neutron scattering, nuclear radiation measurements facilities at the 

radiochemistry laboratory, occupational radiation exposure report, 

periodic survey of canyon areas for radioactive contamination, 

photodosimetry evaluation book, radiation for Bayo Canyon shots, 

radioactive shipments, radioactivity contaminated precious metal, 

radiochemistry of the fission products, radiological incidents, response 

of film to x-radiation of energy up to 10 mev, study of selected 

plutonium workers, trip reports, urinalysis results, and whole body dose 

from tritium in body water.

08/11/2008 163

Unknown / SC&A Operation Crossroads, Operation Phalanx onsite radiological safety 

report.

08/19/2003 3

US Transuranium and Uranium Registries Proposal to manage and operate the United States Transuranium and 

Uranium Registries.

08/22/2005 1

Weldon Spring Internal contamination during decontamination/decommissioning. 11/29/2004 1

Westinghouse Site (Hematite) In vivo counting with uranium 235. 03/13/2009 1
SEC-00109, Rev. 1 08-13-12 LANL

98 of 98 

Table A2-1: Data Capture Synopsis for LANL

Data Capture Information General Description of Documents Captured Date 

Completed

Uploaded

To SRDB

Y-12 Radioactive material shipment inspection reports. 05/16/2012 1

TOTAL 7773

Table A2-2: Databases searched for LANL

Database/Source Keywords / Phrases Hits Selected

NOTE: Keyword Internet searches were not conducted on LANL because it is an active DOE site 

that has been cooperative regarding access to relevant archived documentation.

Table A2-3: OSTI Documents Requested for LANL

Document Number Document Title Requested

Date

Received

Date

No documents requested.