DRAFT 

ADVISORY BOARD ON RADIATION AND WORKER HEALTH 

NATIONAL INSTITUTE FOR 

OCCUPATIONAL SAFETY AND HEALTH 

A REVIEW OF NIOSH’S PROGRAM EVALUATION REPORT 

DCAS-PER-047, “GRAND JUNCTION OPERATIONS OFFICE” 

Contract No. 211-2014-58081 

SCA-TR-PR2015-0093, Revision 1 

Prepared by 

U. Hans Behling, PhD, MPH 

S. Cohen & Associates 

1608 Spring Hill Road, Suite 400 

Vienna, VA 22182 

February 2015 

Disclaimer 

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

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

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

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

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

information only and that premature interpretations regarding its conclusions are unwarranted.
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S. COHEN & ASSOCIATES:

Technical Support for the Advisory Board on

Radiation & Worker Health Review of

NIOSH Dose Reconstruction Program

Document No. 

SCA-TR-PR2015-0093, Revision 1

Effective Date: 

Draft – February 10, 2015

A REVIEW OF NIOSH’S PROGRAM 

EVALUATION REPORT DCAS-PER-047, 

“GRAND JUNCTION OPERATIONS

OFFICE”

Page 2 of 62

Task Manager:

________________________ Date: ___________

U. Hans Behling, PhD, MPH 

Supersedes:

Rev. 0

Project Manager:

________________________ Date: ___________

John Stiver, MS, CHP

Reviewer:

 John Stiver

Record of Revisions

Revision 

Number

Effective 

Date Description of Revision

0 (Draft) 01/27/2015 Initial issue

1 (Draft) 02/10/2015 Added observation to Section 3.0. Requested additional data from NIOSH to 

adequately assess GJOO photon and neutron doses, and radon exposure, which 

resulted in the rewriting of Sections 4.1 and 4.2.3. Changed and eliminated some 

Exhibits in Attachment B and renamed the attachment accordingly. Moved two 

Exhibits from Attachment B to Attachment C. Some minor formatting and 

typographical issues addressed.
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TABLE OF CONTENTS 

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

1.0 Statement of Purpose ...........................................................................................................6

2.0 Relevant Background Information .......................................................................................8

2.1 Overview of Facility History ...................................................................................8

2.2 Limitations Pertaining to Monitoring Data for GJOO Workers and the 

Inclusion in the SEC ................................................................................................8

3.0 Subtask 1: Identify the Circumstances that Necessitated the Need for 

DCAS-PER-047 ...................................................................................................................9

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

4.1 An Overview of the GJOO “Revised Template” for External Exposures .............10

4.1.1 Additional External Dose Data ..................................................................10

4.1.2 Changes to the Assignment of External Dose for Unmonitored 

Workers for Years 1960 through 2009 ......................................................10

4.1.3 Occupational Medical Dose .......................................................................15

4.2 An Overview of the GJOO Facility’s “Revised Template” for Internal 

exposures................................................................................................................16

4.2.1 Bioassay Monitoring Data .........................................................................16

4.2.2 Air Monitoring Data ..................................................................................16

4.2.3 Modeled Doses for Internally Exposed Unmonitored Individuals ............17

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

Potentially Affected DRs ...................................................................................................21

6.0 Subtask 4: Conduct Audits of a Sample Set of DRs Affected by DCAS-PER-047 .........22

7.0 References ..........................................................................................................................23

Attachment A: Relevant Excerpts from the Revised GJOO Template .........................................24

Attachment B: Exposure Data for GJOO Workers .......................................................................34

Attachment C: Excerpts from the Nineteenth Annual Report, Radiation Exposures for 

DOE and DOE Contractor Employees – 1986 ..................................................................60
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ABBREVIATIONS AND ACRONYMS 

Advisory Board 

or Board Advisory Board on Radiation and Worker Health 

AEC Atomic Energy Commission 

AP anterior-posterior 

Bq/g becquerels per gram 

CEP Controls for Environmental Pollution 

CFR Code of Federal Regulations

DAC derived air concentration 

DCAS Division of Compensation Analysis and Support 

D&D decontamination and decommissioning 

d/yr day per year 

DCF dose conversion factor 

DOE (U.S.) Department of Energy 

DR dose reconstruction 

EEOICPA Energy Employees Occupational Illness Compensation Program Act 

GJOO Grand Junction Operations Office 

GJRAP Grand Junction Remedial Action Program 

GM geometric mean 

GSD geometric standard deviation

hr/d hours per day 

HT target organ 

ICRP International Commission on Radiological Protection 

IG Implementation Guide 

INL Idaho National Laboratory 

IREP Interactive RadioEpidemiological Program 

keV kilo electron volt 

Ln lognormal 

LOD limit of detection

μCi/m3 microcurie per cubic meter 

μCi/mg microcurie per milligram 

μCI/ml microcurie per milliliter 

μCI/yr microcurie per year 

m meter 
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m

3

/hr cubic meter per hour 

MeV million electron volts 

mg milligram

mg/m3 milligrams per cubic meter 

mg/yr millgram per year 

MPC maximum permissible concentration 

mrem millirem

NIOSH National Institute for Occupational Safety and Health 

NURE National Uranium Resource Evaluation 

OCAS Office of Compensation Analysis and Support 

ORAUT Oak Ridge Associated Universities Team 

pCi/l picocurie per liter 

pCi/mg picocurie per milligram 

PEP Program Evaluation Plan

PER Program Evaluation Report 

POC probability of causation 

Qtr quarter 

R Roentgen 

rem roentgen equivalent man 

REMS Radiation Exposure Monitoring System 

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

SEC Special Exposure Cohort 

SNL Sandia National Laboratory 

SRDB Site Research Database 

TBD technical basis document 

TIB technical information bulletin

TLD thermoluminescent dosimeter 

U uranium 

UMTRA Uranium Mill Tailing Remedial Action 

U3O8 uranium oxide 

WL working level 

WLM working level month 

yr year 
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1.0 STATEMENT OF PURPOSE 

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

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

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

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

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

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

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

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

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

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

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

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

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

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

potential impacts. Most important in this assessment is the potential impact(s) on the Probability 

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

During a teleconference by the Advisory Board’s Procedures Review Subcommittee meeting on 

August 28, 2014, SC&A was tasked by the Board to conduct reviews of two PERs. Included 

among the PERs is DCAS-PER-047, Grand Junction Operations Office (DCAS 2014). In 

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

which is discussed in this report: 

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

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

characterized in the PER. 

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

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

information bulletins (TIBs), procedures] that have not yet been subjected to a formal 

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

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

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

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

a brief summary/conclusion of this review process. 

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

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

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

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

NIOSH’s re-evaluation is confined to a subset of DRs that, based on their scientific 
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judgment, have the potential to be significantly affected by the PER. In behalf of 

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

Subtask 4: Conduct audits of DRs affected by the PER under review. The number of DRs 

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

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

Subtask 5: Prepare a written report that contains the results of DR audits under Subtask 4, along 

with our review conclusions. 
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2.0 RELEVANT BACKGROUND INFORMATION 

2.1 OVERVIEW OF FACILITY HISTORY 

Between 1943 and 1946, the Manhattan Engineering District acquired the Grand Junction site in 

order to concentrate U3O8 from “green sludge” considered a byproduct of vanadium production. 

Subsequently in 1947, the U.S. Atomic Energy Commission (AEC) established a domestic 

uranium procurement program that was responsible for the receipt, sampling, and analysis of 

uranium (and vanadium) concentrates purchased from domestic ore processing operations until 

1974.

From 1974 to 1984, the Grand Junction Operations Office (GJOO) supported the National 

Uranium Resource Evaluation (NURE) Program in the preparation of samples prior to analytical 

analysis. Sample preparation activities, which included crushing, sizing, and blending, posed the 

greatest potential for internal exposure. 

Other activities included cleanup activities under the Uranium Mill Tailing Remedial Action 

(UMTRA) program starting in 1978, and the Grand Junction Remedial Action Program (GJRAP) 

involving 600 vicinity offsite properties from 1972 to 1988. However, offsite soil samples were 

prepared and analyzed in onsite facilities. By 2001, remediation that included onsite buildings 

had been completed and the facility had been approved for unrestricted use, but remains under 

the (U.S.) Department of Energy’s (DOE’s) purview to this day. 

2.2 LIMITATIONS PERTAINING TO MONITORING DATA FOR GJOO 

WORKERS AND THE INCLUSION IN THE SEC 

On April 29, 2011, the Secretary of Health and Human Services designated a Special Exposure 

Cohort (SEC) for workers at the GJOO (NIOSH 2011). The SEC designation was based on the 

following deficiencies/limitations: 

 NIOSH determined that there are insufficient personnel monitoring, workplace 

monitoring, or source term data to estimate unmonitored external exposures for the 

period March 23, 1943, through December 31, 1959. 

 NIOSH determined that there are insufficient information/data to reconstruct internal 

doses from all potential sources (inclusive of radon) during the period from March 23, 

1943, through January 31, 1975.

Although NIOSH concluded that it is not possible to reconstruct all radiation doses for 

employees who worked at the GJOO during the period from March 23, 1943, through January 

31, 1975, NIOSH nevertheless intends to use any available/credible internal and external 

monitoring data for DRs of individuals who do not qualify for inclusion in the SEC.
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3.0 SUBTASK 1: IDENTIFY THE CIRCUMSTANCES THAT 

NECESSITATED THE NEED FOR DCAS-PER-047

No Technical Basis Document (TBD) has been developed for DRs of workers at the GJOO; 

however, a “template” had been developed for guidance to assess exposures in behalf of claims. 

During NIOSH’s evaluation of the GJOO SEC petition, a substantial body of new information 

was discovered with the potential for significant impacts on previously completed DRs. The 

availability of new data for DR required the original template to be revised on September 5, 

2012, and the subsequent issuance of DCAS-PER-047 on March 26, 2014, in order to evaluate 

the effect of these revisions on previous DRs.

Among additional data requiring revisions to the GJOO template were the following: 

 External dosimetry data for years between 1982 and 1998 containing 15,000 records with 

gamma and beta results and a limited number of neutron exposures. 

 Source term data for modeling neutron exposures. 

 Surrogate exposure data for assigning annual gamma and beta doses to unmonitored 

workers. 

 Air sampling data that included radon measurements. 

SC&A’s Comments 

Among programmatic revisions that may impact the outcome of previously completed DRs and 

mandate the need for a PER, none is more justifiable than the discovery of new/site-specific 

information with the potential of significantly raising estimates of radiation exposures/doses. 

Based on the acquisition of new data for the GJOO facility as provided in the revised GJOO 

template, SC&A concurs with the issuance of DCAS-PER-047, and there are no findings.

A central component for SC&A’s review of DCAS-PER-047 is a critical assessment of the 

revised GJOO template. Templates (inclusive of the GJOO template), however, are not

posted/available on the NIOSH website and can only be retrieved in conjunction with a 

completed Dose Reconstruction Report for a claimant who worked at the GJOO facility. 

Observation #1. For facilities with no TBD and for which a “template” has been developed, such 

a template should be made available to SC&A on the NIOSH website without having to obtain a 

GJOO claimant’s Dose Reconstruction Report (containing Privacy Act information/data that are 

not the focus of the review). 
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4.0 SUBTASK 2: ASSESS NIOSH’S SPECIFIC METHODS FOR 

CORRECTIVE ACTION 

In instances where the PER involves technical issues that are supported by a document that has 

been formalized, Subtask 2 will provide a brief summary of said document. 

As stated in Section 3.0, the discovery of new data prompted NIOSH to revise/edit the original 

template issued on September 5, 2012, as the principal guidance document for the DR of GJOO 

claims. As a convenience to the reader, excerpts of the revised template for GJOO are enclosed

herein as Attachment A in a modified form in which Tables are numerically identified. 

4.1 AN OVERVIEW OF THE GJOO “REVISED TEMPLATE” FOR EXTERNAL 

EXPOSURES 

SC&A critically reviewed both the old and the revised templates and assessed the changes 

introduced. Summarized below are key changes, which reflect newly discovered data that are 

site-specific, as well as other data that NIOSH employed as surrogate values, along with 

comments/findings by SC&A. 

4.1.1 Additional External Dose Data 

NIOSH discovered a data report provided by the Idaho National Laboratory (INL), which 

contained more than 15,000 records of external monitoring data of GJOO workers for the period 

1982 to 1998. These records identify gamma (penetrating) doses and the contribution of the 

beta dose to the skin. Records also include a limited number of workers who were assessed for 

neutron exposures in the early years, but whose numbers increased in later years. 

SC&A’s Comments. SC&A briefly reviewed the collated exposure data cited in the ORAUT’s

Grand Junction Operations Office Dosimetry Spreadsheet, 1986–2007 (ORAUT undated) and 

verified dates, the number of available records, reported exposures for gamma (penetrating 

dose), beta (non-penetrating dose), and the very limited number of neutron measurements. The 

overwhelming gamma and beta exposures were recorded as zero (0) values and suggest low 

exposures for the operational and decontamination and decommissioning (D&D) periods 

between 1982 and 1998.

4.1.2 Changes to the Assignment of External Dose for Unmonitored Workers for Years 

1960 through 2009 

Although NIOSH assumed that all radiation workers at GJOO had been monitored, NIOSH also 

concluded that there were questions about the availability and completeness of these records. 

Deep Dose 

To address these concerns, NIOSH derived annual deep doses for the years 1960 through 2009 

in behalf of three categories of workers by means of surrogate data that represent “. . . maximum 

values from the DOE Annual Report summaries or the 95th percentile value from the REM 
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database” (See Table 1 of Attachment A) [Emphasis added]. A review of Attachment A, 

however, provides no reference(s) or databases, which served as the source for values shown in 

Table 1 of Attachment A. 

SC&A’s Comments/Findings 

In an attempt to verify “unmonitored gamma doses” cited in Table 1 of the revised GJOO 

template (see Attachment A), SC&A compared these values to values cited by NIOSH, as given 

in Exhibit B-1 of Attachment B. For illustration, the following data for 1985 should be 

compared. 

GJOO Template Data. Table 1 of Attachment A identifies a deep dose of 0.090 rem to be 

assigned for 1985 to a GJOO worker classified as Operator/Laborer. In behalf of Table 1, the 

GJOO template provides the following explanation/guidance for the assignment of doses for 

unmonitored workers: 

Deep Dose 

The maximum values from the DOE annual report summary or the 95th percentile 

value from the REMS database has been applied as a single exchange with 

missed dose applied to all other exchanges. This value was used to determine 

dose for the unmonitored “Operator/Laborer Dose” category as summarized in 

the table below. [Emphasis added.] 

For the year 1985, dosimeters were exchanged quarterly (i.e., four times per year) and the LOD 

value was 20 mrem. Thus, the 95th percentile recommended annual dose of 90 mrem represents 

the following components. 

 90 mrem = (95th percentile of neared doses) + (3 × LOD/2) 

 = 60 mrem + 30 mrem

Data Shown in Exhibit B-1. Exhibit B-2 represents data cited in Section 6.2 of the NIOSH SEC 

Petition Evaluation, Report Petition SEC-00175 (NIOSH 2011) that was issued January 11, 

2011. The following reported photon exposures (i.e., deep dose) correspond to the year 1985: 

No. of Average Dose Maximum Dose GM th 95 Percentile Dose 

Individuals (mrem) (mrem) mrem)( GSD (mrem) 

118 126.91 8,500 55.07 1.7 132.18 

Thus, for the 118 individuals with measurable doses in 1985, the 95th percentile dose was 

132.12 mrem, which does not include the aforementioned three missed doses that would raise 

the dose to a total of 162.18 mrem for 1985. 

The dose of 162 mrem is 72 mrem higher than the 90 mrem dose cited in Table 1 of the GJOO 

template. Based on this discrepancy (which is shared with all other years), SC&A in its first 

draft report issued on January 27, 2015, cautiously classified this as a “conditional finding.” 
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SC&A was requested to contact NIOSH in order to resolve this discrepancy in behalf of 

Conditional Finding #1, as well as Conditional Findings #4 and #6. In response to SC&A’s 

request for information that would explain the observed discrepancy, NIOSH provided the Excel 

spreadsheet “JGOO Photon.xlsx,” which provided dosimetry data for all years (1960–2009). 

For illustration and comparison to data shown above, SC&A selected spreadsheet data for photon 

doses monitored at GJOO in 1985 (see Exhibit B-2 and Exhibit B-3). 

Exhibit B-2 cites annual dosimeter data for 118 workers who had a measurable dose in 1985, as 

identified in Column C. It must be noted, however, that dose values in Column C are not real 

doses, but represent midpoint dose values of a distribution published in DOE reports (see 

Exhibit C-1 of Attachment C). Thus, in 1985, there was 1 person with a dosimeter reading 

between 8–9 rem, 5 persons with dosimeter readings between 100–250 mrem, and 112 persons 

with “measureable [sic] doses” between 0–100 mrem. 

Exhibit B-3 cites annual dosimeter data for 528 GJOO workers with measurable and nonmeasurable doses in 1985. Thus, Exhibit B-3 includes all data cited in Exhibit B-2 plus a total of 

410 workers with non-measurable dosimeter data whose assigned 1985 exposures are limited 

to four missed doses, or 40 mrem. 

Table 1 summarizes derived doses representing Table 1 of the revised GJOO template (see 

Attachment A), and Exhibit B-1, Exhibit B-2, and Exhibit B-3 in Attachment B. 

Table 1. 95th Percentile Dose for Unmonitored GJOO Workers for 1985 

Reference (Source) No. of Individuals 95th Percentile Dose 

(rem)

Table 1a0.090

Exhibit B-1

b

118 0.162e

Exhibit B-2

c

118 0.163

Exhibit B-3

d

528 0.090

a

 From Table 1 of the GJOO revised template. 

b

 From Section 6.2, Table 6-4, of SEC Petition Evaluation Report, Petition SEC-00175. 

c

 From spreadsheet GJOO Photon.xlsx: worker data with measurable dosimeter 

response for 1985. 

d

 From spreadsheet GJOO Photon.xlsx: worker data with measurable and nonmeasurable dosimeter responses for 1985. 

e

 Includes missed dose of 30 mrem. 

A comparison of doses identifies the fact that the recommended 95th percentile dose of 0.090 rem 

in Table 1 of the GJOO revised template was defined by data representing Exhibit B-3, which 

includes 410 workers with non-measurable doses among the 528 total workers for 1985. 

Conversely, Exhibit B-1 (which represents data cited in the GJOO SEC Petition Evaluation 

Report) identifies the 95th percentile dose of 0.162 rem that corresponds to data that are restricted 

to the 118 GJOO workers with measurable doses. 
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Based on these data, SC&A recommends that this discrepancy be resolved in favor of higher 

doses that exclude data representing workers with non-measurable doses for the following 

reasons: 

 Operators/laborers are traditionally regarded by NIOSH as the most highly exposed 

group among monitored workers and the inclusion of a majority fraction of workers with 

non-measurable exposures is inconsistent with the concept. 

 Secondly, there is inconsistency between data previously cited in the GJOO SEC 

Evaluation Report issued in January 2011 and the revised GJOO template issued in 

September 2012. 

 Lastly, there is inconsistency within Table 1 of the revised GJOO template regarding the 

methodology for deriving “. . . maximum values from the DOE annual report summary 

[versus] the 95th percentile value from the REMS database.” [Emphasis added.] 

“Maximum values” from the DOE annual reports as used for years 1960–1984 are based 

on the highest dose equivalent range to which even a single GJOO worker belonged. As 

an extreme example, had this protocol been extended to include the year 1985, 

Exhibit B-1 shows a maximum individual with exposure of 8,500 mrem. Thus, this value 

would have been assigned as the 95th percentile dose to unmonitored workers, which is 

nearly 100 times higher than the 90 mrem value recommended in Table 1 of the GJOO 

template. 

A second factor that precludes a common methodology for all years is the fact that prior 

to 1974, there was no separation between measurable and non-measurable dosimeter 

doses between 0–1 rem (see Exhibit C-2 of Attachment C). For this reason, exposures 

cited in Table 1 of the GJOO revised template identify the identical dose of 1.500 rem for 

all years 1960–1974. This value includes 1 rem of dose based on limitations that define 

the methodology for aggregating doses during these years, and 0.500 rem for 25 missed 

doses.

The use of two very different approaches for deriving assigned doses to unmonitored 

workers is evident by the more than 10-fold change in dose between years pre- and post1985.

Finding #1. Dose estimates defined in Table 1 of the revised GJOO template are not only 

inconsistent with data cited in the Petition Evaluation Report for SEC-00175, but are 

inappropriately derived. SC&A recommends the exclusion of non-measurable data for deriving 

the 95th percentile value for Operators/Laborers, and proportional adjustments for Supervisors 

and Administrative personnel for the years 1985 through 2009. 

Shallow Dose 

For the assignment of a shallow dose for unmonitored workers, NIOSH recommends a beta-togamma ratio of 1.5 for all years (i.e., 1960–2009). 
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SC&A’s Comments 

SC&A reviewed the 95th percentile beta-to-photon doses cited in REMS (see Exhibits B-1 and 

B-4 in Attachment B) and concluded that the beta-to-gamma ratio of 1.5 selected by NIOSH was 

appropriate and claimant favorable. 

Neutron Dose 

Due to the limited availability of neutron exposure data prior to 1985, REMS neutron data for the 

years 1986–2009 were analyzed to obtain the 95th and 50th percentiles. These values were 

assigned to “geologists” and “all others,” respectively, on the assumption that pre-1985 

exposures were similar to post-1985 exposures. 

SC&A’s Comments/Findings 

SC&A reviewed neutron exposures cited in REMS for years 1985 through 2009 (see Exhibit B-5 

in Attachment B) as a basis for assigning neutron doses, as given in Table 2 of the revised 

template (see Attachment A). Table 2 of the template identifies neutron doses of 0.123 rem and 

0.031 rem as the 95th and 50th percentile values, respectively, for pre-1981 years, as well as for 

years 1981–1985.

Based on neutron data cited in the Petition Evaluation Report for Petition SEC-00175 and 

reproduced herein as Exhibit B-5 in Attachment B, SC&A was uncertain how NIOSH used these 

data to derive neutron doses cited in Table 2 of the revised GJOO template. In response to a 

request for additional information, SC&A received neutron data from NIOSH that are enclosed 

herein as Exhibit B-6 in Attachment B. 

Exhibit B-6 identified individual neutron doses for select years that include 1986–1992, 1996–

1999, and 2003–2004. For example, for 1986, there were six dosimeter readings that represented 

the following: average neutron dose of 94.17 mrem; a maximum dose of 181 mrem; a GM dose 

of 79.21 mrem; and a 95th percentile dose of 207.01 mrem. These values match values for 1986 

data shown in Exhibit B-5 and, therefore, reflect data representing data presented by NIOSH in 

the GJOO SEC Petition Evaluation Report. 

As shown in Exhibit B-6, NIOSH converted all 66 dosimeter values to their lognormal (Ln) 

values, yielding a Ln(Total) value of 227.65. When divided by 66, the mean Ln value of 3.450 

yields a GM dose of 31.48 mrem with a GSD of 2.2944 and the following 95th percentile dose: 

 95th Percentile Dose = (31.48) (2.2944)1.645 mrem 

 = (31.48) (3.919) mrem 

 = 123 mrem 

The derived values of 0.031 and 0.123 rem from data shown in Exhibit B-6 match the values of 

0.031 and 0.123 rem cited in Table 2 of the revised GJOO template (see Attachment A). 
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While SC&A was able to match dosimeter data in Exhibit B-6 with neutron doses recommended 

in Table 2 of the GJOO template, SC&A questions the inclusion of data that involve dosimeter 

values that are well below LOD values. 

Footnotes c and d of Table 2 of the GJOO revised template identify that, for neutron dosimeters, 

the LOD of 40 mrem is assumed. Inspection of Exhibit B-6 shows that a total of 40 dosimeters 

registered doses less than 40 mrem and 15 registered doses below LOD/2. 

SC&A recalculated the GM dose and the 95th percentile dose for the 26 dosimeter values with 

≥ 40 mrem values. Using this restrictive dataset, SC&A derived the GM dose of 67.85 mrem 

and the 95th percentile dose of 158.62 mrem (see Exhibit B-7 in Attachment B). 

Not surprisingly, both of these values are significantly higher than the corresponding neutron 

values of 31 mrem and 123 mrem cited in Table 2 of the GJOO revised template. 

Finding #2. SC&A recommends the exclusion of neutron dosimeter values below the LOD 

value of 40 mrem for deriving GM and 95th percentile neutron doses for unmonitored GJOO 

personnel for all years prior to 1985. 

4.1.3 Occupational Medical Dose 

The assignment of medical exposures applies to two time periods; (1) 1943 through 1946, and 

(2) 1962 through 1969. For all other years, x-rays were taken offsite and are, therefore, not 

included for DR. For the assignment/derivation of organ dose(s), the revised template provides 

the following guidance: 

A pre-employment, annual, and post-employment anterior-posterior (AP) chest 

and AP pelvis X-ray should be assumed for each year during the operational 

period prior to 1947. Between 1962 and 1969, a pre-employment, annual, and 

post-employments chest X-ray is assumed. However, since the view type is not 

known and the X-rays were done by a portable X-ray machine, all views should 

be considered (anterior-posterior, posterior-anterior, and photofluorographic).

[Emphasis added.] 

SC&A’s Comments/Findings 

Guidance for assigning occupational medical dose as currently stated in the template appears 

misleading and is assumedly incorrect. For example, for the years 1943 through 1946, the 

following guidance is given: 

. . . A pre-employment, annual, and post-employment anterior-posterior (AP) 

chest and AP pelvis X-ray should be assumed for each year during the 

operational period prior to 1947. [Emphasis added.] 

Taken literally/verbatim, this would imply the assignment of six x-rays per year, and for an 

employment period of 1943–1946, a total of 24 medical x-rays could be assigned. Obviously, 

this guidance is incorrect and needs to be properly phrased (i.e., remove words ‘each year.’) 
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Observation #2. Current guidance for the assignment of medical x-rays is ambiguous and 

requires clarification/editing. 

4.2 AN OVERVIEW OF THE GJOO FACILITY’S “REVISED TEMPLATE” FOR 

INTERNAL EXPOSURES 

4.2.1 Bioassay Monitoring Data 

Although there is no comprehensive bioassay database for the GJOO site, there are, nevertheless, 

limited/incomplete data during the SEC period (i.e., 1943–1975). For post-1975 years, the 

template provides the following additional information. 

. . . No bioassay samples have been captured for the period from February 1975 

(the end of the SEC period) until 1984. . . . The samples [i.e., urine and fecal] 

collected for the post-1975 period were for both off-site and on-site work. 

Therefore, for a given worker, the samples might not be for work that is covered 

by EEOICPA [42 U.S.C. §§ 7384 et seq.]. [Emphasis added.] 

SC&A’s Comments 

As previously stated in the template, when bioassay data are available during the SEC period 

(i.e., prior to 1975), they may, in fact, be used for a partial DR under select conditions (e.g., 

employment of less than 250 days or a member of the SEC class with a second, but nonpresumptive, cancer). 

For post-1975 periods, bioassay data are either unavailable or are compromised by the inability 

to segregate offsite from onsite exposures. For said reasons, estimates of internal exposures were 

derived/modeled from air monitoring data, as discussed below. 

4.2.2 Air Monitoring Data 

Prior to 1989, air samples generally lacked information regarding location. However, in 1986, 

time-weighted exposures for the first quarter were calculated in terms of maximum permissible 

concentration (MPC)-hours for individuals performing grinding operations of uranium mill 

tailings in the sample preparation laboratory. The exposure in MPC-hours was documented for 

the highest-exposed individual. 

Additionally, the revised GJOO template references the following other data for dose modeling/ 

reconstruction: 

(1) Among air samples recovered in the sample preparation area was a 1980 sample that was 

identified as “the most concentrated sample containing 0.0046 mg/m3

of uranium.” 

(2) Five hundred and sixty-nine air sample measurements were recovered for on-site 

D&D work, including both general area and breathing zone samples. . . . These 

samples can be used to assign doses to D&D workers and others (supervisors, etc.) 

if individual bioassay results are not available. 
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SC&A’s Comments and Findings 

In behalf of air monitoring data, NIOSH provided the reference ORAUT 1981 for the most 

concentrated air sample containing 0.0046 mg of uranium, and the reference ORAUT 1986 for 

the exposure in MPC-hours for the highest exposed sample preparation worker in 1986. SC&A 

reviewed these documents and verified values stated therein. However, no reference is provided 

that identifies the source/document for the “. . . Five hundred and sixty-nine air sample 

measurements [that] were recovered for on-site D&D work . . .” that spans the period 1989–

2009.

These three independent air sampling datasets were used by NIOSH for the development of 

inhalation and ingestion intake rates discussed in Section 4.2.3 below. 

Finding #3. NIOSH provides neither the raw data nor a documented source for the 569 air 

sample measurements associated with D&D work for years 1989–2006.

4.2.3 Modeled Doses for Internally Exposed Unmonitored Individuals 

Sample Preparation. For the post-1975 SEC period, unmonitored internal exposures for workers 

engaged in sample preparation were modeled for two time periods—1975 to 1984, and 1985 to 

2003—and for four different worker categories engaged in sample preparations. For the first 

period (i.e., 1975–1984), all modeled doses were based on the highest-recorded air sample value 

of 0.0046 mg/m3

of uranium ore taken in the Sample Plant in July 1980. 

For the second period (i.e., 1985–2003), intake values were based on time-weighted MPC-hr 

exposure to the highest exposed individual. The assigned MPC-hr exposure was conservatively 

assumed to represent thorium-230 (which has the most restrictive MPC value). 

Decontamination and Decommissioning. Internal exposures due to inhalation and ingestion of 

airborne contaminants among D&D workers for the period 1989–2006 were based on the 95th

percentile value of 569 air samples representing both general area and breathing zone samples. 

Modeled estimates of inhalation and ingestion rates for unmonitored worker groups are cited in 

Table 4 of Attachment A. Provided below is SC&A’s attempt to match a sample set of values 

reported in Table 4 of the revised template. 

SC&A’s Comments and Findings 

A standard element of SC&A’s audit is to verify key sources of data/information, as well as the 

associated methods used by NIOSH to derive intake estimates, such as those cited in Table 4 of 

Attachment A. 

 Assessment of Intake Rates during Ore Sample Preparation (1975–1984). Intake 

estimates were based on the “highest air concentration” sample containing 0.0046 mg/m3

of uranium. 
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 For the highest exposed worker (i.e., operator), SC&A derived the following annual 

intakes: 

 Total U-234, -235, -238 inhaled per year (mg/yr): 

 (0.0046 mg/m3)(1.2 m3/hr)(8 hr/d)(250 d/yr) = 11.04 mg/yr 

 Total U inhaled per year (μCi/yr): 

 (11.04 mg/yr)(6.83E-04 μCi/mg) = 7.54E-03 μCi/yr 

 

 Total Th-230 and Ra-226 inhaled per year: 

Based on activity fractions defined in Table 1 of Attachment A, SC&A calculates 

the following yearly intakes: 

 For Th-230 or Ra-226 = (Activity for U)(Activity fraction) 

 = (7.54E-03 μCi/yr)(0.249/0.502) 

 = 3.74E-03 μCi/yr 

A comparison of values derived by SC&A to those cited in Table 4 of Attachment A 

shows that, for the Operator, the intake of uranium at 7.54E-03 μCi/yr matches the value 

of 7.57E-03 μCi/yr cited by NIOSH. 

For both Th-230 and Ra-226, SC&A’s derived yearly intake rate of 3.74E-03 is slightly 

less than one-half of NIOSH’s derived value of 7.57E-3 μCi/yr. 

Finding #4. In the derivation of intake rates for Ra-226 and Th-230, NIOSH failed to employ 

activity fractions cited in Table 3 of Attachment A. 

 Assessment of Intake Rates during Tailing Sample Preparation (1985–2003) 

Intake rates for this time period were based on MPC-hr data assigned to the highest 

exposed worker. 

For the highest exposed worker (i.e., operator), SC&A calculates the following intakes 

that are based on the assigned value of 61 MPC-hrs/Qtr for Th-230: 

- Annual Th-230 Exposure = (61 MPC-hr/Qtr)(4 Qtr/yr) 

 = 244 MPC-hrs/yr 

- Annual Inhalation Th-230 = (244 MPC-hrs/yr)(MPCTh-230) 

 (for a breathing rate of 1.2 m3/hr and the MPC value of 1 × 10-5 μCi/m3) 

 

Annual Inhalation Th-230 = (244 MPC-hr/yr)( 1.2 m3/hr)(1E-05 μCi/m3

 Annual Inhalation Th-230 = 2.928E-03 μCi/yr 

 - Annual Inhalation U-234, -235, -238 = (2.928E-03 μCi/yr)(Activity fraction) 

 = (2.928E-03 μCi/yr)(0.092/0.454) 

 = 0.593 μCi/yr 
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A comparison of values derived by SC&A to values cited in Table 2 of Attachment A 

show essential equivalency. (The slightly lower value derived by NIOSH assumes 

2,000 work-hrs/yr (or 500 work-hrs/Qtr) versus the 2,080 work-hrs/yr (or 40 work-hrs/ 

week) defined in 10 CFR 20, Appendix B.) 

There are no findings associated with the intake rates (inhalation and ingestion) assigned 

to workers engaged in sample preparation of tailings for years 1985–2003.

 Assessment of Intake Rates during D&D Activities for Years 1989–2006

The revised template states that “. . . The 95th percentile of the lognormal analysis was 

used to determine the intake rates to be assigned.” 

SC&A assumes that the “95th percentile of the lognormal analysis . . .” refers to the 

aforementioned 569 air sample measurements that NIOSH recovered for onsite D&D, 

which, however, were not referenced (see Finding #3 above). 

In the absence of data, SC&A is not able to assess/confirm assigned intakes during D&D 

activities cited in Table 2 of Attachment A. 

Radon Exposures. The revised template states that:

. . . Radon in buildings was studied extensively in the D&D era (1989–2001) . . . 

including 300 daughter measurements taken in 1985 . . . In 1990, the site 

implemented and participated in the DOE radon study that included all occupied 

buildings on site at that time. The available radon measurements can be used to 

establish the dose from radon and decay products for February 1, 1975, to 

December 31, 2001. . . . The table below provides the results of a lognormal 

analysis of the 1990 radon study. [Emphasis added.] 

Based on these statements the revised template identifies radon concentrations/exposures for the 

following two time periods: 

Years Radon Concentration WLM/yr

1975–1998 5.7 pCi/l 3.4E-01

1999–2001 1.6 pCi/l 9.6E-02

SC&A’s Comments and Findings 

In spite of several cited radon surveys/studies (including the “1990 radon study” as the source for 

deriving radon exposures cited above), the template does not identify these studies in its 

Reference List. 

Upon request, NIOSH submitted the following additional information in support of the abovecited radon data: 
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 By 1975, the last drum of concentrated radium-containing material had been shipped 

offsite and it is assumed that radium contamination remained constant until remediation 

in 1997–1998.

 The 1990 radon study showed that only three buildings showed radon levels above 

4 pCi/l, with the highest recorded level at 5.7 pCi/l. 

 Following remediation, radon levels were reduced to 1.6 pCi/l.

 After 2001, radon levels were reduced to background levels. 

In context with the additional information provided by NIOSH, SC&A concurs with radon 

exposure estimates cited in the revised GJOO template, and there are no findings.
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5.0 SUBTASK 3: EVALUATE THE PER’S STATED APPROACH FOR 

IDENTIFYING THE UNIVERSE OF POTENTIALLY AFFECTED 

DRs 

Given the extensive revision to the original template, NIOSH reviewed all claims (independent 

of the issue date of the revised template) to determine if the latest information (i.e., revised 

template) was used. Additionally, claims with no employment after 1959 were not considered 

for re-evaluation, provided they met criteria needed for inclusion to the added SEC class(es). 

These screening criteria identified a total of 24 claims requiring re-evaluation using guidance 

contained in the revised GJOO template. The re-evaluation of these 24 claims yielded the 

following POC values: 

 The POC values for 22 claims remained below 45%. 

 For one claim, the revised POC fell between 45% and 50% and required further 

evaluation, with 30 Interactive RadioEpidemiological Program (IREP) Input runs of 

10,000 iterations each. The final POC, however, remained below 50%. 

 For the single remaining claim, the revised POC exceeded 50%. 

SC&A’s Comments 

SC&A’s assessment of DCAS-PER-047 included a critical comparison between the original and 

revised GJOO templates. SC&A concurs with NIOSH that revisions were extensive and 

mandated a review of all previously completed claims that represented the original template and 

were exempt from inclusion in the SEC class. 

There are no findings pertaining to the selection criteria used to identify claims potentially 

affected by PER-047 and the need for re-evaluation. 
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6.0 SUBTASK 4: CONDUCT AUDITS OF A SAMPLE SET OF DRs 

AFFECTED BY DCAS-PER-047

NIOSH identified a total of 24 re-evaluated DRs/claims, of which 22 claims yielded POCs 

below 45%, one claim resulted in a POC between 45% and 50%, and one claim exceeded 50%. 

SC&A’s assessment suggests that the impact of DCAS-PER-047 and the implementation of dose 

reconstruction under the revised template are likely to vary significantly among the 24 claims 

subject for selection and review by SC&A. 

Most significantly impacted are claims with prolonged employment periods that (1) either postdate 1960 (when unmonitored external dose can be reconstructed) and/or post-date 1975 (when 

unmonitored internal and radon doses can be reconstructed); and (2) involve workers in the job 

category of operators/general laborers.

SC&A therefore recommends the selection of three (3) cases with significant employment 

periods as operators/laborers for the following three employment periods: 

(1) Post-1960 

(2) Post-1975 (sample preparation period) 

(3) Post-1989 (or the D&D period) 
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7.0 REFERENCES 

10 CFR 20, Appendix B. Annual Limits on Intake (ALIs) and Derived Air Concentrations 

(DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations 

for Release to Sewerage; Final Rule, 56 FR 23409, May 21, 1991. 

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

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

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

42 U.S.C. §§ 7384 et seq., Energy Employees Occupational Illness Compensation Program Act 

of 2000; as amended; OCAS web site. 

DCAS 2014. Grand Junction Operations Office, Rev. 0, DCAS-PER-047, NIOSH’s Division of 

Compensation Analysis and Support, Cincinnati, Ohio. March 26, 2014. 

ICRP (International Commission on Radiological Protection) 1991. 1990 Recommendations of 

the International Commission on Radiological Protection, Publication 60, Pergamon Press, 

Oxford, England. 

NIOSH 2011. SEC Petition Evaluation Report, Petition SEC-00175, Rev. 0, Grand Junction 

Operation Office, January 12, 2011. 

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

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

Ohio. December 6, 2006. 

ORAUT 1981. 1980 Environmental Monitoring Report – U.S. Department of Energy Facilities, 

Grand Junction, Colorado, and Monticello, Utah (Bendix Field Engineering Corporation, Grand 

Junction, Colorado, BFEC-1981-3, April 1981), Oak Ridge Associates Universities, Cincinnati, 

Ohio. SRDB Reference ID 90862. 

ORAUT 1986. Summary of MPC – Time Weighted Exposure for the First Quarter

(memorandum from B. Rothman to A.N. Tschaeche, Bendix Field Engineering Corporation, 

Grand Junction, Colorado, April 1, 1986), Oak Ridge Associates Universities, Cincinnati, Ohio. 

SRDB Reference ID 98100. 

ORAUT (Undated). Grand Junction Operations Office Dosimetry Spreadsheet, 1986-2007, Oak 

Ridge Associates Universities, Cincinnati, Ohio. SRDB Reference ID 107374. 

SEC 2011. Special Exposure Cohort Designation for a Class of Employees from Grand Junction 

Operations Office, Grand Junction, Colorado, Secretary of Health and Human Services. April 

29, 2011. 

U.S. DOE (Department of Energy) 1987. Nineteenth Annual Report, Radiation Exposures for 

DOE and Doe Contractor Employees – 1986, Office of Nuclear Safety, December 1987.
Effective Date:

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ATTACHMENT A: RELEVANT EXCERPTS FROM THE REVISED 

GJOO TEMPLATE 

Dose Reconstruction Methodology 

External Dose 

Monitored Individuals 

Exposure records are maintained at the Grand Junction office and in a database maintained by 

the Idaho National Laboratory (INL). A data report through the use of INL location codes was 

provided by INL that includes personnel believed to be associated with Grand Junction. This 

report has data between the years 1982 and 1998 and contains over 15,000 records, each with a 

gamma and beta result. There are also occasional neutron results in this spreadsheet. The 

persons listed in this report may include individuals involved in off-site remediation work. As a 

claimant-favorable assumption, all exposures listed in this report would be assumed to have 

occurred on site. 

Dosimeter Dose 

Deep Dose Pre-1981 

Grand Junction used film badges prior to 1981. Limited film badge data are available for 1952 

through 1959. Through 1959, the exchange rate for film badges was biweekly. No information 

is available on exchange rates between 1960 and 1980; therefore, it is assumed that a biweekly 

exchange is continued during this period. Penetrating doses should be applied as 100% 30–

250 keV photons using acute exposure rate and exposure (R)-to-organ (HT) DCF values for the 

AP geometry in accordance with the External Dose Reconstruction Implementation Guideline. 

Reported and missed doses should be assigned in accordance with the guidance found in the 

Technical Information Bulletin: A Standard Complex-Wide Methodology for Overestimating 

External Doses Measured with Film Badge Dosimeters. The limits of detection are 0.04 rem for 

photons and 0.05 rem for electrons, respectively. 

Deep Dose Post-1980 

Grand Junction began using TLDs after 1980. The exchange frequency possibly varied from 

monthly to quarterly. Penetrating doses should be applied as 100% 30–250 keV photons using 

acute exposure rate and Deep Dose Equivalent [Hp(10)] DCF values for the AP geometry in 

accordance with the External Dose Reconstruction Implementation Guideline. Reported and 

missed doses should be assigned in accordance with the Technical Information Bulletin: A 

Standard Complex-Wide Methodology for Overestimating External Doses Measured with 

Thermoluminescent Dosimeters. The limit of detection is 0.020 rem for photons and electrons. 

Shallow Dose 

Shallow measured and missed doses based on the dosimetry records will be assessed per 

guidance found in the Technical Information Bulletin: Interpretation of Dosimetry Data for 

Assignment of Shallow Dose. Shallow dose will be assigned as an acute dose and 100% >15 keV 

electron energy range. 
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Attachment A: Relevant Excerpts from the Revised GJOO Template (continued) 

Neutron Dose 

Neutron doses should be applied as 100% 0.1–2.0 MeV neutrons with ICRP-60 weighting 

factors of 1.91 using chronic exposure rate and Deep Dose Equivalent [Hp,slab(10)] DCF values 

for the AP geometry in accordance with the External Dose Reconstruction Implementation 

Guideline. Exchange rates are assumed to be the same as photon doses. A neutron limit of 

detection of 0.040 rem for film badges and 0.020 for TLDs is assumed based on the known 

neutron detection limits for other major DOE sites, such as the Savannah River Site and Hanford. 

Unmonitored Individuals 

The Grand Junction Operations Office had a policy of monitoring all radiation workers. 

However, access to monitoring data is limited and it is unclear if what is reported is complete. 

Therefore, workers without dosimetry records should be given unmonitored dose (as described 

below). 

Deep Dose 

The maximum values from the DOE annual report summary or the 95th percentile value from the 

REMS database has been applied as a single exchange with missed dose applied to all other 

exchanges. This value was used to determine dose for the unmonitored “Operator/Laborer 

Dose” category as summarized in the table below. 

Table 1. Unmonitored Gamma Dose 

Year Operator/Laborer Dosea

(rem)

Supervisor Doseb

(rem)

Administrative Dosec

(rem)

1960 1.500 0.750 0.520

1961 1.500 0.750 0.520

1962 1.500 0.750 0.520

1963 1.500 0.750 0.520

1964 1.500 0.750 0.520

1965 1.500 0.750 0.520

1966 1.500 0.750 0.520

1967 1.500 0.750 0.520

1968 1.500 0.750 0.520

1969 1.500 0.750 0.520

1970 1.500 0.750 0.520

1971 1.500 0.750 0.520

1972 1.500 0.750 0.520

1973 1.500 0.750 0.520

1974 1.500 0.750 0.520

1975 1.250 0.625 0.520

1976 0.520 0.520 0.520

1977 1.000 0.520 0.520

1978 1.000 0.520 0.520
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Attachment A: Relevant Excerpts from the Revised GJOO Template (continued) 

Table 1. Unmonitored Gamma Dose (Continued) 

Year Operator/Laborer Dosea

(rem)

Supervisor Doseb

(rem)

Administrative Dosec

(rem)

1979 1.250 0.625 0.520

1980 1.500 0.750 0.520

1981d1.030 0.515 0.052

1982d1.030 0.515 0.052

1983d1.030 0.515 0.052

1984d1.030 0.515 0.052

1985 0.090 0.045 0.040

1986 0.064 0.040 0.040

1987 0.088 0.044 0.040

1988 0.056 0.040 0.040

1989 0.081 0.040 0.040

1990 0.079 0.040 0.040

1991 0.055 0.040 0.040

1992 0.087 0.043 0.040

1993 0.046 0.040 0.040

1994 0.058 0.040 0.040

1995 0.046 0.040 0.040

1996 0.058 0.040 0.040

1997 0.046 0.040 0.040

1998 0.104 0.052 0.040

1999 0.045 0.040 0.040

2000 0.046 0.040 0.040

2001 0.044 0.040 0.040

2002 0.052 0.040 0.040

2003 0.061 0.040 0.040

2004 0.046 0.040 0.040

2005 0.045 0.040 0.040

2006 0.042 0.040 0.040

2007 0.044 0.040 0.040

2008 0.045 0.040 0.040

2009 0.072 0.040 0.040

a.

 For pre-1981, doses are based on maximum value from the DOE annual summaries. For post-1984, doses are 

based on the 95th percentile of the REMS data for badges with end dates in that year. Value applied as a single 

exchange with missed dose applied to all other exchanges. 

b.

 Supervisor dose is assumed to be half of the Operator/Laborer dose or missed dose for all exchange frequencies. 

c.

 Administrative dose is assumed to be one-tenth of the Supervisor dose or missed dose for all exchange 

frequencies. 

d.

 Based on maximum recorded dose for adjacent years and missed dose based on current LODs and exchange 

frequency. 
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Attachment A: Relevant Excerpts from the Revised GJOO Template (continued) 

Shallow Dose

Since no beta data were provided during this period, a beta-to-gamma ratio from 1950s ‘era data 

was calculated to be 1.2. Using data reported by REMS for years after 1980, an average ratio 

was calculated to be 1.5 beta-to-gamma. As these later data include exposure from off-site 

remediation activities, the beta component may be expected to be high compared to on-site 

activities. However, the more claimant-favorable ratio of 1.5 should be used to bound shallow 

dose for all years between 1960 and 1980. 

Neutron Dose 

There are limited data for pre-1985 neutron exposures in individual claimant files. However, 

there are exposure data from REMS from 1985 through 2009, and there is no indication that the 

source term was any different prior to 1985. These data were analyzed to obtain the 95th and 50th

percentiles, which are considered a bounding estimate for unmonitored neutron exposures. 

Table 2. Neutron Doses 

Job Category Time Period Measured Dose 

(rem) Missed Dose (rem) Total Dose(rem)

GeologistaPre-1981 00.123 0.500c0.623

Geologista1981-1985 0.123 0.060d0.183

All OtherbPe-1981 0.031 0.500c0.531

All Otherb1981-1985 0.031 0.060d0.091

a. Based on 95th percentile 

b. Based on 50th percentile 

c. 0.500 rem = [(26-1)*(0.040/2)] 

d. 0.060 rem = [(4-1)*(0.040/2)] 

The number of workers that had potential to neutron exposures is limited due to the limited role 

of neutron sources at the Grand Junction Operations Office. Therefore, the 95th percentile should 

only apply to Geologist and the 50th percentile should apply to All Other job categories. After 

1985, neutron dosimetry records are assumed to be complete based on a review of GJOO 

records. Therefore, no unmonitored dose is assigned after 1985. 

As stated, all unmonitored doses are considered as bounding estimates and are applied as 

constant values in IREP. 

Medical Dose 

From 1943 through 1946, annual chest X-rays were taken of all employees, primarily anterior-toposterior views. For the years 1947 through 1992, X-rays were taken off site at the site doctor’s 

office or the Community Hospital in Grand Junction. However, for a short period between 1962 

through 1969, an office of the U.S. Public Health Service brought a portable X-ray unit to the 

Grand Junction Office three or four times a year and stayed for about a week to X-ray 

employees. 
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Attachment A: Relevant Excerpts from the Revised GJOO Template (continued) 

Even though some claimant files contain X-ray records, available records cannot be assumed to 

be complete. Information determined to be more claimant-favorable than the general guidance 

should be used. As an example, one claimant record indicates that several of the X-rays 

performed were “two views.” This would indicate that two posterior-anterior views should be 

assigned. The locations for X-ray records for various time periods are documented. 

A pre-employment, annual, and post-employment anterior-posterior (AP) chest and AP pelvis 

X-ray should be assumed for each year during the operational period prior to 1947. Between 

1962 and 1969, a pre-employment, annual, and post-employment chest X-ray is assumed. 

However, since the view type is not known and the X-rays were done by a portable X-ray 

machine, all views should be considered (anterior-posterior, posterior-anterior, and 

photofluorographic). For all other years, X-ray dose is not applicable since they were performed 

off site at a noncovered facility. X-ray doses will be assigned in accordance with the Technical 

Information Bulletin: Dose Reconstruction from Occupationally Related Diagnostic X-Ray 

Procedures. 

Internal Dose 

Dosimetry Data 

There are over a hundred bioassay-related documents in the Site Research Database that have 

been captured for the GJOO site. However, there was no comprehensive bioassay database for 

the site. The samples can be divided into two periods. From 1945–1973, the vast majority of the 

samples were analyzed for total uranium in urine in terms of mg/liter. No bioassay samples have 

been captured for the period from February 1975 (the end of the SEC period) until 1984. There 

are samples in 1984, 1986, and from 1990 to 1998. These were urine and fecal samples which 

were generally analyzed by alpha spectroscopy. The samples were typically analyzed for 

uranium-234, -235, and -238, but often included thorium-230 and radium-226. The samples 

collected for the post-1975 period were for both off-site and on-site work. Therefore, for a given 

worker, the samples might not be for work that is covered by EEOICPA. For part of this period, 

there was a pre-job sampling program, and many of the samples were collected for this purpose. 

After 1990 or so, the practice was to collect pre-job samples but discard them after a period 

(about one year) if the worker had not been exposed to greater than 10% of a DAC or 

40 DAC-hours. Data were sometimes re-sent by the contract laboratories due to re-analyzed 

samples, etc. Some sample collection dates are missing in the references. The actual period of 

D&D (decontamination and decommissioning) work began in 1988–1989 with the “extensive” 

decontamination of Buildings 33 and 35 and the start of the remediation of the outdoor tailings. 

Thirty-six GJOO Rust employees and subcontractor employees were involved in non-intrusive 

radiological field assessment activities from approximately October 1993 through May 1994 at 

Sandia National Laboratories (SNL). These employees submitted a total of 186 samples for 

bioassay analysis to the SNL Internal Radiological Dosimetry Program while working at SNL. 

Ninety-eight of the 186 samples were analyzed by Controls for Environmental Pollution (CEP). 

The only other samples sent to CEP were some waste characterization samples, but the results 

failed quality assurance and were determined to be unusable contamination.
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Attachment A: Relevant Excerpts from the Revised GJOO Template (continued) 

Air Monitoring Data 

After January 1975 and before the start of the D&D work in 1989, air samples are generally 

lacking in the references. As noted above, the most hazardous on-site work was probably at the 

sample preparation area. Five sets of samples were recovered for this area from July 1980 to 

June 2002. The 1980 environmental report noted that the principal environmental problem was 

the dust generated from grinding and crushing samples. Air sampling was performed in the 

Sample Plant during July 1980 while ore samples were being prepared. The most concentrated 

sample contained 0.0046 mg/m3of uranium. This is the maximum credible concentration of 

natural uranium since non-ore materials were processed most of the time. All but one of the July 

1980 to June 2002 samples are spot measurements. However, time-weighted exposures for the 

first quarter of 1986 were calculated for individuals working in the sample preparation lab 

performing grinding of uranium mill tailings. These samples were taken for comparison to the 

allowable maximum permissible concentration exposure (MPC-hours). These are the most 

reliable data for sample preparation activities on tailings samples since they were collected over 

an entire quarter. The exposure in MPC-hours was documented for the highest-exposed worker. 

Five hundred and sixty-nine air sample measurements were recovered for on-site D&D work, 

including both general area and breathing zone samples. These samples indicate that air 

concentrations were well-controlled during these activities (generally less than 10% of the DAC 

or action level in use). These samples can be used to assign doses to D&D workers and others 

(supervisors, etc.) if individual bioassay results are not available. 

Source Terms 

All of the significant exposures were to uranium and its decay products. Yellowcake was 

sampled and stored on site during the uranium procurement program. Buildings that had been 

used as the sampling plants and buildings that were used as indoor storage were likely 

contaminated with yellowcake. Uranium ore was brought on site for processing in the pilot 

plants, and some was buried with tailings on site. During the NURE program, most of the 

material prepared for sampling was not ore, but occasionally ore samples were processed. 

Tailings were present in outdoor areas, but also potentially in former pilot plant buildings. After 

1984, the main work of the sampling plant and analytical chemistry was processing of soil 

samples contaminated with tailings. Unless a worker’s job is very well described, it will not be 

possible to determine whether the primary exposure was to yellowcake, ore, or tailings. 

Therefore, the most claimant-favorable activity fractions should be used in the dose 

reconstruction. 

As mentioned above, some small quantities of unsealed radioactive materials were handled that 

were not part of the uranium series (for example, plutonium, americium, and tritium). 
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Attachment A: Relevant Excerpts from the Revised GJOO Template (continued) 

These were part of waste treatability studies, bioassay measurements for others, etc. GJOO also 

possessed a few tritium-containing Zetatron tubes (small neutron generators). Documentation 

indicates that surveys and, in some cases, precautionary bioassays were performed. In addition, 

the Analytical Chemistry Laboratory used liquid or solid reference materials in concentrations of 

a few tens of microcuries per milliliter (μCi/ml) or becquerels per gram (Bq/g). Intakes of any of 

these materials appear to have been unlikely to unmonitored personnel.

Activity Fractions 

The contamination remaining from yellowcake procurement and storage was essentially 

uranium. Only a small fraction of the thorium-230 and radium-226 present in ore was carried 

through to the yellowcake. The fractions varied with time and the processes used in the mills. 

After the end of the SEC period, exposures to yellowcake contamination without ore and tailings 

cannot be ruled out. Therefore, it is recommended that dose reconstructors choose the more 

favorable option between ore and tailings. 

During the NURE program, most of the material sampled was not ore. If an ore sample was 

being processed, the dust would have only contained between 0.15 percent and 0.3 percent 

uranium oxide. During the period with the highest workload and particulate concentrations, 

ventilation was necessary to protect workers against the non-radioactive constituents of the 

samples, such as silica dust. The small amounts of uranium in the dust were present in their 

natural isotopic abundances. 

The mixture of the radioisotopes present in the tailings varied, depending on the composition of 

the ore, when the ore was milled, and what process was used. An assumption is made that 90 

percent of the uranium was recovered and that all of the thorium-230 and radium-226 remained 

in the tailings. The table below was constructed assuming that uranium-238, uranium-234, 

thorium-230, and radium-226 are in equilibrium in ore and that the uranium-235 activity is 2% of 

the uranium-234/-238 activity. The total activity fractions in the table can be used to assign 

intakes when only a total activity is reported for a sample. After 1975, air samples were 

generally counted using a proportional counter which could discriminate between alpha and beta 

counts. The gross alpha counts obtained were then compared to a conservative MPC or DAC 

value.

Table 3. Relative Activity and Total Activity Fractions in Ore and Tailings 

Nuclide Relative 

Activity in Ore

Removed by 

Milling

Relative 

Activity in 

Tailings

Total Activity Fractions

Ore Tailings

U-234/235/238 2.02 90% 2.02 0.502 0.092

Th-230 1 0% 1 0.249 0.454

Ra-226 1 0% 1 0.249 0.454

Unless work was short term, it may not be possible to determine if a worker was exposed to 

natural uranium ore or tailings. 
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Attachment A: Relevant Excerpts from the Revised GJOO Template (continued) 

Most of the bioassay samples available for the post-SEC period will probably have been 

analyzed isotopically. In cases where the bioassay is reported in total uranium mass, the uranium 

data can be evaluated as natural uranium, using the specific activity of 683 pCi/mg to calculate 

the uranium activity. Corresponding intakes of radium-226 and thorium-230 should be 

calculated using the ratios from the table above based on ore or tailings (whichever is more 

claimant-favorable). 

Fitted internal doses are applied in IREP as a lognormal distribution with a geometric standard 

deviation of 3.000. Missed internal doses are applied as a triangular distribution. 

Incidents 

In the post-January 1975 period, the number of documented incidents that could have resulted in 

internal doses was relatively small. There are two reports of interest. In 1992, there was a spill 

of yellowcake during disposal of what was thought to be UMTRA soil samples. Nine 

individuals were involved, and initial 24-hour urine samples and follow-up samples were 

collected. A formal investigation was conducted. This report indicates that one of the 

employees involved, but who was not contaminated, intentionally contaminated his bioassay 

sample with material not involved in the spill. The identities of the individuals involved are not 

given in the report, but can be determined from a 1992 report of internal doses to DOE. In a 

second incident in 1994, a water leak in the attic in Building 7 occurred during work involving 

conversion of old yellowcake processing areas into office space, causing contamination of the 

spaces below. Fecal samples were collected from 4 workers. There was “no significant activity 

in the samples.” The names of the individuals involved are given. 

Unmonitored Individuals 

Sample Preparation and Analytical Chemistry Operations 

As noted above, sample preparation was the highest on-site exposure scenario in the post-SEC

period and prior to D&D operations. It is logical to divide the sample preparation activities at 

GJOO into two time periods: 

1975–1984 

When samples potentially containing ore and samples potentially containing tailings were 

prepared for the NURE and GJRAP programs, intake rates were calculated using the July 1980 

sample. The July 1980 sample was a high sample for the time and was cited as an upper bound 

in environmental reports of subsequent years. The mass loading of uranium in air could be 

converted to an air concentration of tailings, but the assumption of ore is more favorable. The

intakes are provided in the table below and are assigned as constant values. 

Post-1984 

The values selected were for the highest worker, and it was assumed that the values measured 

were thorium-230. This is favorable since it is likely that total activity was measured and 

compared to thorium-230 (most restrictive MPC). These values are higher than would be 

calculated from the one-day air samples collected through June 2002. 
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Attachment A: Relevant Excerpts from the Revised GJOO Template (continued) 

The data are assigned to all operations personnel. Intakes for other workers were determined 

using the ratios between job classes found in Section 8.5.1 of the Technical Basis Document: 

Site Profiles for Atomic Weapons Employers That Worked Uranium Metals. Laborers received 

one-half the intake of operators, supervisors receive one-quarter, and administrative personnel 

receive one-tenth of the supervisor intake. The intakes are provided in the table below and are 

assigned as constant values. 

Decontamination and Decommissioning 

The 95th percentile of the lognormal analysis was used to determine the intake rates to be 

assigned. The 95th percentile from the collective analysis resulted in intakes about 40% higher 

than the year-by-year analyses (assuming exposure during the D&D entire period). The use the 

air samples to determine a chronic intake over a year’s period will be favorable to claimants 

involved in D&D work. The results are shown for both ore and tailings in the table below. The 

ore values overestimate the doses from yellowcake by assuming that radium-226 and 

thorium-232 are in equilibrium with uranium-238.

Table 4. Inhalation and Ingestion Intake Rates (1975–2006) 

Job Categorya

Uranium Radium-226 Thorium-230

Inhalation

(μCi/yr)

Ingestion

(μCi/yr)

Inhalation

(μCi/yr)

Ingestion

(μCi/yr)

Inhalation

(μCi/yr)

Ingestion

(μCi/yr)

Sample Preparation 1975–1984 (Ore)

Operators 7.57E-03 1.59E-04 7.57E-03 1.59E-04 7.57E-03 1.59E-04

General Labor 3.79E-03 7.95E-05 3.79E-03 7.95E-05 3.79E-03 7.95E-05

Supervisors 1.89E-03 3.98E-05 1.89E-03 3.98E-05 1.89E-03 3.98E-05

Administrative 1.89E-04 3.98E-06 1.89E-04 3.98E-06 1.89E-04 3.98E-06

Sample Preparation 1985–2003 (Tailings)

Operators 5.74E-04 1.21E-05 2.83E-03 5.95E-05 2.83E-03 5.95E-05

General Labor 2.87E-04 6.03E-06 1.42E-03 2.98E-05 1.42E-03 2.98E-05

Supervisors 1.44E-04 3.01E-06 7.08E-04 1.49E-05 7.08E-04 1.49E-05

Administrative 1.44E-05 3.01E-07 7.08E-05 1.49E-06 7.08E-05 1.49E-06

Decontamination and Decommissioning 1989–2006 Natural Uranium (Ore, Yellowcake)

Operators 3.21E-03 6.74E-05 1.59E-03 3.33E-05 1.59E-03 3.33E-05

General Labor 3.21E-03 6.74E-05 1.59E-03 3.33E-05 1.59E-03 3.33E-05

Supervisors 8.02E-04 1.68E-05 3.97E-04 8.34E-06 3.97E-04 8.34E-06

Administrative 8.02E-05 1.68E-06 3.97E-05 8.34E-07 3.97E-05 8.34E-07

Decontamination and Decommissioning 1989–2006 (Tailings)

Operators 5.87E-04 1.23E-05 2.90E-03 6.09E-05 2.90E-03 6.09E-05

General Labor 5.87E-04 1.23E-05 2.90E-03 6.09E-05 2.90E-03 6.09E-05

Supervisors 1.47E-04 3.08E-06 7.25E-04 1.52E-05 7.25E-04 1.52E-05

Administrative 1.47E-05 3.08E-07 7.25E-05 1.52E-06 7.25E-05 1.52E-06

a. If worker duties cannot be determined, then the most claimant-favorable intake rate should be assumed. 
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Attachment A: Relevant Excerpts from the Revised GJOO Template (continued) 

Radon 

By February 1975, the last of the drums containing uranium concentrate had been shipped off 

site and the radium-226 in surface contamination, in soils, and under/around the buildings 

remained relatively constant until the remediation of the outdoor areas. Radon in buildings was 

studied extensively in the D&D era (1989–2001). There are indoor radon-decay-product 

measurements for most of the buildings, including 300 daughter measurements taken in 1985 in 

some of the former pilot plant buildings. Only Building 34, the former boiler building for the 

Large Pilot Plant, exceeded 0.02 WL (averaged over 100 hours). In 1990, the site implemented 

and participated in the DOE radon study that included all occupied buildings on site at that time. 

The available radon measurements can be used to establish the dose from radon and radon decay 

products for February 1, 1975, to December 31, 2001. After 2001, the site radon values were 

reduced to background levels, and there were no occupational exposures to radon at the GJOO 

site. The table below provides the results of a lognormal analysis of the 1990 radon study. 

Table 5. Radon Concentrations (1975–2001) 

Year Concentration (pCi/L) WL WLM/yr Distribution

1975–1998 5.7 2.85E-02 3.4E-01 Constant

1999–2001 1.6 8.00E-03 9.6E-02 Constant
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ATTACHMENT B: EXPOSURE DATA FOR GJOO WORKERS 

EXHIBIT B-1. (Source: NIOSH 2011) 
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Statistical Data on Annual Photon Exposure Reported by REMS and Annual DOE Report*

Year No. of 

Individuals 

Average 

(millirem)

Maximum 

(millirem)

Geometric 

Mean 

(millirem)

Geometric 

Standard 

Deviation

95th

Percentile 

(millirem)

Source

1975 54 0 468.88 26904

1976 33 0 0.00 26903

1977 90 0 94.11 26902

1978 120 0 101.00 26901

1979 150 0 268.79 26887

1980 180 0 250.00 26888

1981 55.07 250.00 REMS/26888

1982 55.07 250.00 REMS/26888

1983 55.07 250.00 REMS/26888

1984 55.07 250.00 REMS/26888

1985 118 126.91 8500 55.07 1.7 132.18 REMS

1986 54 48.44 145 41.67 1.75 104.91 REMS

1987 115 23.39 120 20.28 1.66 46.80 REMS

1988 62 23.45 146 18.03 1.9 51.99 REMS

1989 81 23.83 134 18.25 1.91 53.08 REMS

1990 147 21.45 442 16.45 1.73 40.64 REMS

1991 36 31.86 411 20.81 1.91 60.53 REMS

1992 46 38.41 193 30.39 1.85 83.86 REMS

1993 3 53 125 31.07 2.85 174.92 REMS

1994 12 61.08 317 25.92 3.09 166.75 REMS

1995 10 21.5 40 19.66 1.54 40.09 REMS

1996 24 15.58 30 14.92 1.34 24.18 REMS

1997 4 17.5 30 15.65 1.6 33.99 REMS

1998 120 40.41 189 31.94 1.99 99.41 REMS

1999 14 23.14 48 19.35 1.82 51.98 REMS

2000 34 5.5 35 3.29 2.7 16.94 REMS

2001 33 3.3 13 2.47 2.11 8.47 REMS

2002 31 6 17 4.38 2.33 17.69 REMS

2003 37 6.68 25 5.21 1.98 16.08 REMS

2004 41 5.51 29 3.87 2.24 14.64 REMS

2005 6 11.83 17 9.84 2.08 32.95 REMS

2006 4 12.5 24 11.13 1.57 23.43 REMS

2007 10 2.8 15 1.68 2.28 6.54 REMS

2008 39 3.23 25 2.28 2.12 7.88 REMS

2009 10 52.5 499 4.25 5.3 66.60 REMS

* Doses do not include three missed doses or 30 mrem. 
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EXHIBIT B-2. Photon Doses for 118 GJOO Workers in 1985 with 

Measurable Dosimeter Doses Plus Missed Dose

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

1 01-Jan-85 31-Dec-85 8500 364 1985 1.00 8.500 0.030 8.530 2.143589

2 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

3 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

4 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

5 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

6 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

7 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

8 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

9 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

10 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

11 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

12 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

13 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

14 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

15 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

16 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

17 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

18 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

19 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

20 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

21 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

22 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

23 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

24 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

25 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

26 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

27 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

28 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

29 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

30 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

31 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

32 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

33 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

34 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

35 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

36 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

37 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

38 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

37 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-2. Photon Doses for 118 GJOO Workers in 1985 with 

Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

39 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

40 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

41 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

42 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

43 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

44 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

45 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

46 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

47 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

48 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

49 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

50 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

51 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

52 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

53 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

54 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

55 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

56 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

57 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

58 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

59 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

60 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

61 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

62 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

63 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

64 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

65 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

66 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

67 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

68 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

69 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

70 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

71 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

72 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

73 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

74 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

75 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

76 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

77 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

38 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-2. Photon Doses for 118 GJOO Workers in 1985 with 

Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

78 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

79 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

80 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

81 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

82 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

83 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

84 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

85 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

86 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

87 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

88 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

89 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

90 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

91 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

92 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

93 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

94 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

95 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

96 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

97 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

98 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

99 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

100 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

101 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

102 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

103 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

104 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

105 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

106 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

107 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

108 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

109 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

110 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

111 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

112 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

113 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

114 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

115 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

39 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-2. Photon Doses for 118 GJOO Workers in 1985 with 

Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

116 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

117 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

118 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

Average Dose: 18.515/118 = 0.156 rem 

GM Dose = e(-288.662/118) = 0.087 rem 

95th percentile = (GSD1.645)(50th percentile) + missed dose 

95th Percentile = (1.71.645)(0.0557) + (0.030) = 0.163 rem 
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

40 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

1 01-Jan-85 31-Dec-85 8500 364 1985 1.00 8.500 0.030 8.530 2.143589

2 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

3 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

4 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

5 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

6 01-Jan-85 31-Dec-85 175 364 1985 1.00 0.175 0.030 0.205 -1.58475

7 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

8 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

9 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

10 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

11 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

12 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

13 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

14 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

15 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

16 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

17 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

18 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

19 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

20 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

21 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

22 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

23 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

24 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

25 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

26 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

27 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

28 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

29 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

30 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

31 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

32 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

33 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

34 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

35 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

36 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

37 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

41 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

38 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

39 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

40 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

41 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

42 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

43 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

44 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

45 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

46 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

47 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

48 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

49 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

50 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

51 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

52 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

53 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

54 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

55 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

56 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

57 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

58 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

59 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

60 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

61 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

62 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

63 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

64 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

65 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

66 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

67 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

68 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

69 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

70 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

71 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

72 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

73 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

74 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

42 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

75 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

76 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

77 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

78 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

79 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

80 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

81 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

82 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

83 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

84 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

85 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

86 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

87 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

88 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

89 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

90 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

91 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

92 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

93 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

94 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

95 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

96 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

97 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

98 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

99 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

100 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

101 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

102 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

103 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

104 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

105 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

106 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

107 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

108 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

109 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

110 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

111 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

43 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

112 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

113 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

114 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

115 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

116 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

117 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

118 01-Jan-85 31-Dec-85 50 364 1985 1.00 0.050 0.030 0.080 -2.52573

119 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

120 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

121 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

122 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

123 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

124 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

125 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

126 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

127 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

128 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

129 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

130 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

131 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

132 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

133 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

134 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

135 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

136 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

137 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

138 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

139 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

140 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

141 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

142 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

143 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

144 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

145 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

146 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

147 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

148 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

44 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

149 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

150 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

151 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

152 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

153 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

154 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

155 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

156 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

157 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

158 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

159 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

160 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

161 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

162 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

163 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

164 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

165 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

166 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

167 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

168 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

169 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

170 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

171 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

172 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

173 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

174 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

175 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

176 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

177 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

178 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

179 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

180 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

181 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

182 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

183 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

184 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

185 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

45 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

186 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

187 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

188 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

189 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

190 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

191 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

192 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

193 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

194 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

195 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

196 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

197 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

198 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

199 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

200 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

201 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

202 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

203 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

204 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

205 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

206 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

207 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

208 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

209 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

210 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

211 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

212 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

213 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

214 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

215 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

216 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

217 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

218 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

219 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

220 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

221 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

222 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

46 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

223 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

224 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

225 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

226 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

227 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

228 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

229 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

230 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

231 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

232 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

233 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

234 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

235 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

236 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

237 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

238 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

239 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

240 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

241 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

242 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

243 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

244 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

245 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

246 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

247 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

248 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

249 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

250 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

251 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

252 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

253 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

254 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

255 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

256 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

257 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

258 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

259 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

47 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

260 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

261 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

262 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

263 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

264 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

265 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

266 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

267 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

268 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

269 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

270 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

271 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

272 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

273 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

274 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

275 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

276 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

277 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

278 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

279 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

280 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

281 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

282 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

283 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

284 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

285 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

286 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

287 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

288 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

289 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

290 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

291 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

292 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

293 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

294 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

295 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

296 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

48 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

297 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

298 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

299 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

300 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

301 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

302 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

303 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

304 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

305 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

306 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

307 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

308 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

309 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

310 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

311 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

312 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

313 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

314 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

315 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

316 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

317 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

318 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

319 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

320 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

321 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

322 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

323 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

324 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

325 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

326 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

327 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

328 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

329 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

330 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

331 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

332 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

333 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

49 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

334 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

335 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

336 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

337 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

338 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

339 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

340 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

341 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

342 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

343 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

344 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

345 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

346 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

347 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

348 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

349 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

350 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

351 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

352 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

353 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

354 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

355 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

356 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

357 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

358 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

359 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

360 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

361 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

362 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

363 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

364 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

365 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

366 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

367 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

368 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

369 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

370 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

50 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

371 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

372 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

373 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

374 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

375 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

376 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

377 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

378 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

379 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

380 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

381 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

382 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

383 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

384 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

385 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

386 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

387 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

388 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

389 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

390 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

391 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

392 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

393 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

394 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

395 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

396 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

397 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

398 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

399 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

400 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

401 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

402 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

403 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

404 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

405 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

406 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

407 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

51 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

408 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

409 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

410 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

411 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

412 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

413 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

414 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

415 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

416 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

417 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

418 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

419 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

420 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

421 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

422 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

423 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

424 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

425 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

426 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

427 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

428 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

429 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

430 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

431 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

432 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

433 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

434 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

435 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

436 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

437 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

438 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

439 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

440 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

441 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

442 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

443 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

444 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

52 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

445 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

446 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

447 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

448 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

449 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

450 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

451 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

452 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

453 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

454 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

455 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

456 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

457 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

458 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

459 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

460 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

461 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

462 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

463 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

464 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

465 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

466 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

467 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

468 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

469 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

470 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

471 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

472 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

473 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

474 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

475 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

476 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

477 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

478 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

479 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

480 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

481 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

53 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

482 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

483 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

484 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

485 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

486 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

487 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

488 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

489 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

490 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

491 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

492 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

493 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

494 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

495 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

496 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

497 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

498 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

499 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

500 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

501 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

502 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

503 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

504 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

505 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

506 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

507 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

508 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

509 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

510 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

511 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

512 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

513 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

514 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

515 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

516 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

517 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

54 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-3. Photon Doses for 528 GJOO Workers in 1985 with Measurable and 

Non-Measurable Dosimeter Doses Plus Missed Dose (continued)

MON_START_DATE MON_END_DATE DDE_PHOTON days year fraction annual rem Missed Total ln(Total)

518 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

519 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

520 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

521 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

522 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

523 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

524 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

525 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

526 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

527 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

528 01-Jan-85 31-Dec-85 0 364 1985 1.00 0.000 0.040 0.040 -3.21888

Mean Dose = 34.915 rem/528 = 0.066 rem 

GM Dose = e-1608.4/528 = 0.0475 rem 

95th Percentile Dose = (GSD)1.645 (50th Percentile Dose) 

95th Percentile Dose = (1.4771.645)(0.0475) rem = 0.090 rem 
Effective Date:

February 10, 2015

Revision No.

1

Document No.

SCA-TR-PR2015-0093

Page No.

55 of 62

NOTICE: This report has been reviewed for Privacy Act information and has been cleared for distribution. 

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

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

EXHIBIT B-4. (Source: NIOSH 2011) 

Statistical Data on Annual Beta Exposure Reported by REMS and Annual DOE Report

Year No. of 

Individuals 

Average 

(millirem)

Maximum 

(millirem)

Geometric 

Mean 

(millirem)

Geometric 

Standard 

Deviation

95th 

Percentile 

(millirem)

1975 0 562.65

1976 0 0.00

1977 0 112.93

1978 0 121.20

1979 0 322.54

1980 0 300.00

1981 66.084 300.00

1982 66.084 300.00

1983 66.084 300.00

1984 66.084 300.00

1985 0 0 0 0.00

1986 48 57.85 323 39.23 2.29 153.94

1987 126 29.99 426 22.82 1.86 63.53

1988 76 31.84 146 22.62 2.22 84.33

1989 91 80.12 2441 27.02 3.1 174.76

1990 156 26.15 462 18 1.94 53.72

1991 50 38.6 411 26.59 2.05 86.92

1992 60 45.58 193 35.8 1.93 105.94

1993 7 62.43 170 36.96 2.73 193.82

1994 13 80.92 349 34.65 3.51 275.08

1995 12 21.33 40 19.3 1.58 41.05

1996 26 24.77 240 17.25 1.81 45.92

1997 7 32.86 60 26.43 2.02 84.32

1998 125 45.38 255 35.19 2.04 114.11

1999 18 31.44 70 25.67 1.94 76.61

2000 50 7.56 58 3.84 2.94 22.76

2001 40 4.8 14 3.72 2.1 12.65

2002 36 6.72 19 5.25 2.07 17.44

2003 41 7.61 28 6.08 1.98 18.77

2004 54 7.67 61 4.29 2.79 23.32

2005 52 5.65 28 4.06 2.25 15.47

2006 48 7.29 29 5.04 2.41 21.52

2007 39 6.03 27 4.19 2.27 16.21

2008 49 7.82 131 3.93 2.66 19.74

2009 17 48.76 471 6.68 4.98 94.45
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However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

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EXHIBIT B-5. (Source: NIOSH 2011) 

Statistical Data on Annual Neutron Exposure Reported by REMS and Annual DOE Report

Year No. of 

Individuals 

Average 

(millirem)

Maximum 

(millirem)

Geometric 

Mean 

(millirem)

Geometric 

Standard 

Deviation

95th 

Percentile 

(millirem)

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985 0 0 0 0.00

1986 6 94.17 181 79.21 1.79 207.01

1987 18 26.61 68 19.17 2.47 85.23

1988 13 51.38 180 40.59 1.92 119.09

1989 2 50.5 76 43.59 1.74 108.72

1990 9 36.44 128 28.91 1.8 76.25

1991 5 67.4 223 40.98 2.47 182.19

1992 3 22 31 21.12 1.32 33.39

1993 0 0 0 0.00

1994 0 0 0 0.00

1995 0 0 0 0.00

1996 1 20 20 20 1 20.00

1997 1 20 20 20 1 20.00

1998 3 62 70 61.75 1.09 71.19

1999 3 37.33 49 36.5 1.23 51.36

2000 0 0 0 0.00

2001 0 0 0 0.00

2002 0 0 0 0.00

2003 1 15 15 15 1 15.00

2004 0 0 0 0.00

2005 1 15 15 15 1 15.00

2006 0 0 0 0.00

2007 0 0 0 0.00

2008 0 0 0 0.00

2009 0 0 0 0.00
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EXHIBIT B-6. Neutron Measurements Used to Derive Dose in Table 2 of the GJOO Template

MON_YEAR DDE_NEUTRON Ln(Total)

1986 55 4.007333

1986 181 5.198497 31.47686 GM

1986 161 5.081404 2.294372 GSD

1986 47 3.850148 123.391 95th

1986 41 3.713572

1986 80 4.382027

1987 19 2.944439

1987 35 3.555348

1987 68 4.219508

1987 33 3.496508

1987 21 3.044522

1987 6 1.791759

1987 30 3.401197

1987 40 3.688879

1987 30 3.401197

1987 8 2.079442

1987 60 4.094345

1987 40 3.688879

1987 33 3.496508

1987 33 3.496508

1987 6 1.791759

1987 8 2.079442

1987 3 1.098612

1987 6 1.791759

1988 40 3.688879

1988 50 3.912023

1988 50 3.912023

1988 70 4.248495

1988 180 5.192957

1988 29 3.367296

1988 70 4.248495

1988 25 3.218876

1988 28 3.332205

1988 20 2.995732

1988 18 2.890372

1988 70 4.248495

1988 18 2.890372
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EXHIBIT B-6. Neutron Measurements Used to Derive Dose in Table 2 of the GJOO Template 

(continued)

MON_YEAR DDE_NEUTRON Ln(Total)

1989 25 3.218876

1989 76 4.330733

1990 25 3.218876

1990 40 3.688879

1990 32 3.465736

1990 15 2.70805

1990 21 3.044522

1990 20 2.995732

1990 128 4.85203

1990 21 3.044522

1990 26 3.258097

1991 42 3.73767

1991 22 3.091042

1991 223 5.407172

1991 33 3.496508

1991 17 2.833213

1992 31 3.433987

1992 19 2.944439

1992 16 2.772589

1996 20 2.995732

1997 20 2.995732

1998 59 4.077537

1998 70 4.248495

1998 57 4.043051

1999 32 3.465736

1999 49 3.89182

1999 31 3.433987

2003 15 2.70805

2005 15 2.70805

227.6507
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EXHIBIT B-7. Derived Dose Estimates Based on Neutron Dosimeter Readings 

Above LOD (40 mrem) 

MON_YEAR DDE_NEUTRON

1991 223 5.407172

1986 181 5.198497 67.8593 GM

1988 180 5.192957 1.675601 GSD

1986 161 5.081404 158.6244 95th

1990 128 4.85203

1986 80 4.382027

1989 76 4.330733

1988 70 4.248495

1988 70 4.248495

1988 70 4.248495

1998 70 4.248495

1987 68 4.219508

1987 60 4.094345

1998 59 4.077537

1998 57 4.043051

1986 55 4.007333

1988 50 3.912023

1988 50 3.912023

1999 49 3.89182

1986 47 3.850148

1991 42 3.73767

1986 41 3.713572

1987 40 3.688879

1987 40 3.688879

1988 40 3.688879

1990 40 3.688879

2047 109.6533
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ATTACHMENT C: EXCERPTS FROM THE NINETEENTH ANNUAL 

REPORT, RADIATION EXPOSURES FOR DOE AND DOE 

CONTRACTOR EMPLOYEES – 1986 
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EXHIBIT C-1 (Source: U.S. DOE 1987) 
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EXHIBIT C-2 (Source: U.S. DOE 1987)