ORAU TEAM 

Dose Reconstruction 

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller & Associates I MJW Corporation 

Page 1 of 13

Document Title: 

External Coworker Dosimetry Data 

for the Rocky Flats Plant 

Document Number: ORAUT-OTIB-0058 

Revision: 00 

Effective Date: 05/12/2006 

Type of Document: OTIB 

Supersedes: None 

Subject Expert: Matthew H. Smith 

Document Owner 

Approval: Signature on File Approval Date: 05/04/2006 

John M. Byrne, Task 3 Manager 

Concurrence: Signature on File Concurrence Date: 05/11/2006 

Kate Kimpan, Project Director 

Approval: Signature on File Approval Date: 05/12/2006 

James W. Neton, Associate Director for Science 

 New Total Rewrite Revision Page Change 

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION. 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 2 of 13 

PUBLICATION RECORD 

EFFECTIVE 

DATE 

REVISION 

NUMBER DESCRIPTION 

05/12/2006 00 New technical information bulletin to provide information to allow 

ORAU Team dose reconstructors to assign doses at the Rocky Flats 

Plant to certain workers who have no or limited monitoring data, 

based on site coworker data. First approved issue. Training 

required: As determined by the Task Manager. Initiated by Matthew 

H. Smith. 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 3 of 13 

TABLE OF CONTENTS 

SECTION TITLE PAGE

1.0 Introduction .................................................................................................................................5

2.0 Purpose.......................................................................................................................................6

3.0 Background.................................................................................................................................6

4.0 General Approach.......................................................................................................................6

5.0 Applications and Limitations .......................................................................................................6

6.0 Coworker Data Development......................................................................................................7

7.0 Coworker Annual Dose Summaries............................................................................................9

LIST OF TABLES 

TABLE TITLE PAGE

6-1 Missed external doses ............................................................................................................... 8

7-1 Annual RFP external coworker doses (including NRDP data) modified to account 

 for missed dose ...................................................................................................................... 11

7-2 Annual RFP external coworker doses (excluding NRDP data) modified to account 

 for missed dose ....................................................................................................................... 12
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 4 of 13 

ACRONYMS AND ABBREVIATIONS 

DOE U.S. Department of Energy 

EEOICPA Energy Employees Occupational Illness Compensation Program Act 

LOD limit of detection 

NDRP Neutron Dose Reconstruction Project 

NIOSH National Institute for Occupational Safety and Health 

NOCTS NIOSH-OCAS Claims Tracking System 

OCAS Office of Compensation Analysis and Support 

ORAU Oak Ridge Associated Universities 

RFP Rocky Flats Plant 

TIB technical information bulletin 

TLD thermoluminescent dosimeter 

U.S.C. United States Code 

yr year 

§ section 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 5 of 13 

1.0 INTRODUCTION 

Technical information bulletins (TIBs) are not official determinations made by the National Institute for 

Occupational Safety and Health (NIOSH) but are rather working documents that provide historical 

background information and guidance to assist in the preparation of dose reconstructions at particular 

sites or categories of sites. They will be revised in the event additional relevant information is 

obtained. TIBs may be used to assist the NIOSH staff in the completion of individual dose 

reconstructions. 

In this document the word “facility” is used as a general term for an area, building, or group of 

buildings that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “Department of Energy [DOE] facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act [EEOICPA; 42 U.S.C. § 7384I(5) and (12)]. 

EEOICPA defines a DOE facility as “any building, structure, or premise, including the grounds upon 

which such building, structure, or premise is located ... in which operations are, or have been, 

conducted by, or on behalf of, the Department of Energy (except for buildings, structures, premises, 

grounds, or operations ... pertaining to the Naval Nuclear Propulsion Program)” [42 U.S.C. § 

7384I(12)]. Accordingly, except for the exclusion for the Naval Nuclear Propulsion Program noted 

above, any facility that performs or performed DOE operations of any nature whatsoever is a DOE 

facility encompassed by EEOICPA. 

For employees of DOE or its contractors with cancer, the DOE facility definition only determines 

eligibility for a dose reconstruction, which is a prerequisite to a compensation decision (except for 

members of the Special Exposure Cohort). The compensation decision for cancer claimants is based 

on a section of the statute entitled “Exposure in the Performance of Duty.” That provision [42 U.S.C. § 

7384n(b)] says that an individual with cancer “shall be determined to have sustained that cancer in the 

performance of duty for purposes of the compensation program if, and only if, the cancer ... was at 

least as likely as not related to employment at the facility [where the employee worked], as 

determined in accordance with the [probability of causation] guidelines established under 

subsection (c) ....” [42 U.S.C. § 7384n(b)]. Neither the statute nor the probability of causation 

guidelines (nor the dose reconstruction regulation) define “performance of duty” for DOE employees 

with a covered cancer or restrict the “duty” to nuclear weapons work. 

As noted above, the statute includes a definition of a DOE facility that excludes “buildings, structures, 

premises, grounds, or operations covered by Executive Order No. 12344, dated February 1, 1982 

(42 U.S.C. 7158 note), pertaining to the Naval Nuclear Propulsion Program” [42 U.S.C. § 7384l(12)]. 

While this definition contains an exclusion with respect to the Naval Nuclear Propulsion Program, the 

section of EEOICPA that deals with the compensation decision for covered employees with cancer 

[i.e., 42 U.S.C. § 7384n(b), entitled “Exposure in the Performance of Duty”] does not contain such an 

exclusion. Therefore, the statute requires NIOSH to include all occupationally-derived radiation 

exposures at covered facilities in its dose reconstructions for employees at DOE facilities, including 

radiation exposures related to the Naval Nuclear Propulsion Program. As a result, all internal and 

external dosimetry results are considered valid for use in dose reconstruction. No efforts are made to 

determine the eligibility of any fraction of total measured exposure for inclusion in dose reconstruction. 

NIOSH, however, does not consider the following exposures to be occupationally-derived: 

• radiation from naturally occurring radon present in conventional structures; 

• radiation from diagnostic X-rays received in the treatment of work-related injuries. 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 6 of 13 

2.0 PURPOSE 

The purpose of this TIB is to provide information to allow Oak Ridge Associated Universities (ORAU) 

Team dose reconstructors to assign doses to Rocky Flats Plant (RFP) workers who have no or limited 

monitoring data, based on site coworker data. The data in this TIB are to be used in conjunction with 

Use of Coworker Dosimetry Data for External Dose Assignment (ORAUT 2005a). 

3.0 BACKGROUND 

The ORAU Team is conducting a series of coworker data studies to permit dose reconstructors to 

complete certain cases for which external or internal monitoring data are unavailable or incomplete. 

Cases not having complete monitoring data could fall into one of several categories: 

• The worker was unmonitored and, even by today’s standards, did not need to be monitored 

(e.g., a nonradiological worker). 

• The worker was unmonitored, but by today’s standards would have been monitored. 

• The worker might have been monitored, but the data are not available to the dose 

reconstructor. 

• Partial information is available, but it is insufficient to facilitate a dose reconstruction. 

As described in ORAUT (2005a), some cases without complete monitoring data can be processed 

based on assumptions and methodologies that do not involve coworker data. For example, many 

cases falling in the first category can be processed by assigning ambient external and internal doses 

based on information in the relevant site technical basis documents. 

As described in Technical Basis Document for the Rocky Flats Plant – Occupational External 

Dosimetry (ORAUT 2004), operations at the site began in 1951. RFP used a variety of film dosimetry 

designs between 1951 and 1969. A combination film and thermoluminescent dosimeter (TLD) was 

used starting in 1969 until a full TLD was implemented in 1971. Use of dosimetry at RFP expanded 

as production operations increased. In 1964, the dosimetry package was incorporated into the 

security badge, which better ensured that each worker wore a dosimeter (ORAUT 2004). Exchange 

frequencies varied from quarterly to weekly, depending on job duties. There does not appear to be 

any significant administrative practice that would have jeopardized the integrity of the dose of record. 

4.0 GENERAL APPROACH 

As described in ORAUT (2005a), the general approach to developing coworker data for cases without 

external monitoring data is to assign either 50th- or 95th-percentile doses with the intent that the 

doses assigned represent, but do not underestimate, the doses that would have been assigned had 

the worker been monitored. 

5.0 APPLICATIONS AND LIMITATIONS 

Some RFP workers could have worked at one or more other major sites within the DOE complex 

during their employment history. Therefore, the data in this TIB must be used with caution to ensure 

that, for likely noncompensable cases, unmonitored external doses from multiple site employments 

have been overestimated. This will typically require the availability of the respective site recorded 

doses or TIBs for external coworker dosimetry data for all relevant sites. 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 7 of 13 

The data in this TIB address penetrating radiation from gamma and neutron radiation and 

nonpenetrating radiation from electron and/or low-energy photon radiation. Neutron data are not 

presented separately; therefore, methods for determining neutron dose are discussed in Section 7.0. 

ORAUT (2004) and the following two documents should be used as the basis for assigning neutron 

doses, when relevant: 

• Use of Rocky Flats Neutron Dose Reconstruction Project Data in Dose Reconstructions

(ORAUT 2005b)

• Technical Basis Document for the Neutron Dose Reconstruction Project (Falk et al. 2005) 

External onsite ambient dose should be applied as specified in the latest revision of ORAUT-PROC0060, External On-Site Ambient Dose Reconstruction for DOE Sites (ORAUT 2005c). 

6.0 COWORKER DATA DEVELOPMENT 

Dosimetry data for monitored RFP workers contained in the Health Information System (HIS20) were 

selected for this evaluation. The HIS20 system was the last one used at RFP for the retention of 

occupational radiation exposure data. The information in this system contains data that have been 

transferred from previous electronic systems and hard-copy health physics files. In addition, HIS20 

now contains the results of the Neutron Dose Reconstruction Project (Falk et al. 2005). 

The annual data for each worker reported between 1952 and 2005 were prorated to account for 

partial years of employment based on an analysis of the length of monitored employment associated 

with the data (see “Special Considerations” for further discussion). The data were prorated so 

coworker doses representing a full year of monitored employment could be derived; this permits the 

dose reconstructor to assign appropriate doses based on specific employment dates and job 

descriptions. 

The validity of the data used for coworker dose development was confirmed by selecting a sampling 

of beta-gamma film badge worksheets (handwritten records) and comparing them to data for 

penetrating radiation listed in the HIS20 database. 

Each beta-gamma worksheet contains film badge results for numerous workers for a given building 

and quarter. For each worker-year, four sheets are combined to comprise the annual beta-gamma 

dose record. Thirty such worker-years were examined and compared to data for the same workeryear. 

Of the 30 worker-years compiled (representing data for 30 individuals), 22 (73%) were complete, in 

that all quarterly data were found, and the total annual dose was in agreement. For 5 worker-years 

(17%), one quarter of data was missing, but the annual total calculated with that missing quarter 

agreed with the HIS20 database. For 3 worker-years (10%), some quarterly data were missing or 

blank and the annual totals did not agree with the HIS20 database. In all three of those instances, the 

HIS20 database annual values were higher than the data extracted from the beta-gamma worksheets. 

6.1 ADJUSTMENT FOR MISSED DOSE 

According to External Dose Reconstruction Implementation Guideline (NIOSH 2002), missed doses 

are assigned for zero or unrecorded readings for each monitoring cycle to account for the possibility 

that doses were received but either not recorded by the dosimeter or not reported by the site. Annual 

maximum potential missed doses are calculated by multiplying the number of zero or unrecorded 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 8 of 13 

badge readings by the reported dosimeter limit of detection (LOD) and summing the results. These 

values are used as the 95th percentile of a lognormal distribution to calculate the probability of 

causation, which is determined by the U.S. Department of Labor. Thus, in the Interactive 

RadioEpidemiological Program (IREP), the parameter 1 input is equal to the calculated maximum 

annual missed doses multiplied by 0.5, and the parameter 2 input is equal to 1.52. These values 

represent the geometric mean and geometric standard deviation, respectively, for each year of 

analysis. 

The assignment of maximum potential missed doses for monitored workers is particularly significant 

for RFP workers from 1954 to 1962 when they could have been monitored weekly. Table 6-1 lists the 

maximum annual missed dose by monitoring period based on information in ORAUT (2004). 

Table 6-1. Missed external doses based on ORAUT (2004). 

Monitoring 

period 

Penetrating 

LOD (rem) 

Nonpenetrating 

LOD (rem)a

Exchange 

frequency 

Maximum potential 

annual missed 

penetrating dose 

(rem) 

Maximum potential 

annual missed 

nonpenetrating dose 

(rem) 

1952–1953 0.04 0.05 Semimonthlyb 0.960 1.200 

1954–1962 0.04 0.05 Weeklyb 2.080 2.600 

1963–1964 0.04 0.05 Semimonthlyb 0.960 1.200 

1965–1966 0.04 0.05 Monthlyb 0.480 0.600 

1967–1968 0.04 0.05 Semimonthlyb 0.960 1.200 

1969–1976 0.02 0.03 Semimonthlyb 0.480 0.720 

1977–1992 0.02 0.03 Monthlyc 0.240 0.360 

1993–2005 0.01 0.02 Monthlyc 0.120 0.240 

a. Based on analysis of nonpenetrating LODs for other DOE sites in OTIB-0017 (ORAUT 2005d). Specific RFP data for 

nonpenetrating LOD is not available at this time. 

b. Based on maximum potential exchange frequency as shown in ORAUT (2004). 

c. The exchange frequency was not defined in ORAUT (2004). It is based on a review of claim data evaluated under the 

EEOICPA Subtitle B program. 

6.2 SPECIAL CONSIDERATIONS 

Certain aspects of the external dosimetry practices at the RFP documented in ORAUT (2004) were 

considered in the analysis of the site data. These include: 

• Conservatively determined default dosimeter exchange frequencies were used. Not all RFP 

employees would have had dosimetry exchanged at these upper-bound frequencies. 

• During the process of prorating HIS20 dose to account for partial years of employment, it was 

discovered that artificially short or long wear periods had been entered into the HIS20 

database. These artificial periods were entered because only one date (usually the end date) 

was available in the electronic data from previous database systems. To avoid skewing the 

overall dataset with artificially high or low prorated dose, data with a wear period less than or 

equal to 0.1 yr or greater than 1.25 yr were excluded from the analysis described in Section 

7.0. 

• Inclusion of Neutron Dose Reconstruction Project (NDRP) data in the HIS20 dataset led to the 

development of tables of data for penetrating and nonpenetrating dose that include and 

exclude the NDRP values. This was done to provide a method to separate a neutron dose 

component from 1952 to 1969. To determine neutron dose for 1970 to 2005, a neutron-tophoton ratio method defined in OTIB-0050 can be used (ORAUT 2005b). 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 9 of 13 

• OTIB-0027 should be used to choose the proper method for processing penetrating and 

nonpenetrating data to determine low-energy (less-than-30-keV) photon dose or electron 

(greater-than-15-keV) dose components as needed (ORAUT 2005e). 

As described in Section 7.0, a claimant-favorable approach was adopted in the development of 

coworker dose summaries, and this approach is intended to account for any underestimate of doses 

to radiological workers at the RFP based on these considerations. 

7.0 COWORKER ANNUAL DOSE SUMMARIES 

Based on the information and approaches described, RFP coworker annual external dosimetry 

summaries were developed for use in the evaluation of external gamma dose for certain workers 

potentially exposed to workplace radiation, but with no or limited monitoring data from DOE. These 

summaries were developed using the following steps: 

Step 1. As described in Section 6.0, for data between 1952 and 2005, the reported penetrating dose, 

which represented annual summary data, was modified for each worker to account for partial 

years of employment. This adjustment was made by analyzing the dosimetry wear dates 

supplied in the HIS20 database. For example, if in a particular calendar year the average 

employment period for all RFP employees in the NIOSH-OCAS Claims Tracking System 

(NOCTS) was 11 months, the reported annual doses were multiplied by 12/11 (1.09). This 

permits the dose reconstructor to assign an appropriate prorated dose to account for partial 

years of employment or potential exposure. 

Step 2. One-half of the maximum potential annual missed doses listed in Table 6-1 were added to the 

reported annual doses from Step 1 (except reported positive doses, in which case the 

maximum missed dose was reduced by the dose corresponding to one badge exchange 

because it is not possible that all individual badge results were zero if a positive annual dose 

was reported). 

Step 3. The 50th- and 95th-percentile annual coworker gamma doses were derived from the doses 

calculated in Step 2 by ranking the data into cumulative probability curves and extracting the 

50th- and 95th-percentile doses for each year. 

Step 4. Tables 7-1 and 7-2 list the results of the coworker analysis including and excluding NDRP 

data respectively. These percentile doses should be used for selected RFP workers with no 

or limited monitoring data using the methodologies outlined in Section 7.0 of ORAUT (2005a). 

In general, the 50th-percentile dose can be used as a best estimate of a worker’s dose when 

professional judgment indicates the worker was likely exposed to intermittent low levels of 

external radiation. The 50th-percentile dose should not be used for workers who were 

routinely exposed. For routinely exposed workers (i.e., workers who were expected to have 

been monitored), the 95th-percentile dose should be applied. For workers who are unlikely to 

have been exposed, external onsite ambient dose should be used rather than coworker 

doses. 

Step 5. Workers exposed to neutrons from work in plutonium facilities from 1952 to 1969 were, in 

general, included in the NDRP study. Therefore, the neutron dose component for 1952 to 

1969 should be calculated by subtracting (at the chosen 95th or 50th percentile) the 

penetrating non-NDRP dose (Table 7.2) from the penetrating dose including NDRP data 

(Table 7-1). The results for penetrating dose in Table 7-2 represent the gamma component of 

penetrating dose for 1952 to 1969. To separate the neutron and gamma components of the 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 10 of 13 

penetrating dose for 1970 to 2005, the neutron-to-photon ratio method defined in OTIB-0050 

should be used (ORAUT 2005b). It should be noted that the NDRP data includes an estimate 

of missed neutron dose (addressed as notional dose by the NDRP project), therefore, no 

adjustments are needed for missed neutron dose for the period 1952 to 1969. Likewise, for 

the period 1970 to 2005, missed neutron dose is accounted for when the applicable neutron 

to photon ratio is applied to the data in Table 7-1. 

Step 6. In instances where non-penetrating dose is considered for the period 1952-1969, Table 7-1 

values should be used for workers at plutonium facilities (i.e. non-penetrating dose is due to 

low-energy photons). For workers at non-plutonium facilities (i.e. non-penetrating dose is due 

to electrons), the non-penetrating values in Table 7-2 should be used. 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 11 of 13 

Table 7-1. Annual RFP external coworker doses (including NDRP 

data) modified to account for missed dose (rem). 

Year 

Penetrating 

95th percentile 

Penetrating 

50th percentile 

Nonpenetrating 

95th percentile 

Nonpenetrating 

50th percentile 

Number of 

Monitored 

Workers 

1952 5.018 2.505 5.133 2.620 42 

1953 4.190 0.751 4.553 0.892 319 

1954 3.233 1.095 3.600 1.361 353 

1955 4.411 1.165 5.266 1.431 529 

1956 4.461 1.135 5.617 1.415 781 

1957 5.136 1.177 6.004 1.454 918 

1958 6.015 1.253 7.553 1.584 1062 

1959 7.186 1.581 8.002 1.908 1063 

1960 7.121 1.293 7.728 1.645 1284 

1961 7.850 1.527 8.201 1.923 1638 

1962 6.523 1.542 7.062 1.828 2003 

1963 5.955 0.940 6.232 1.104 2176 

1964 4.875 0.648 5.012 0.799 2834 

1965 3.533 0.511 3.663 0.598 2826 

1966 4.767 0.592 4.976 0.679 2888 

1967 4.379 0.627 4.735 0.761 2902 

1968 3.276 0.578 3.591 0.714 3101 

1969 2.702 0.327 2.919 0.450 3471 

1970 2.301 0.307 2.460 0.423 3308 

1971 1.938 0.384 2.096 0.500 3398 

1972 1.853 0.377 1.995 0.494 3282 

1973 1.697 0.380 1.848 0.497 3020 

1974 1.881 0.497 2.047 0.612 2687 

1975 1.329 0.401 1.525 0.516 2489 

1976 0.826 0.248 1.030 0.364 2424 

1977 0.589 0.122 0.699 0.177 3740 

1978 0.698 0.120 0.830 0.180 4176 

1979 0.906 0.122 1.074 0.180 3893 

1980 0.743 0.120 0.889 0.168 3752 

1981 0.853 0.110 1.008 0.180 4060 

1982 0.990 0.121 1.174 0.166 4851 

1983 1.212 0.134 1.440 0.193 5360 

1984 1.204 0.141 1.551 0.200 5673 

1985 1.302 0.142 1.584 0.203 6140 

1986 1.365 0.183 1.860 0.301 4942 

1987 1.510 0.259 2.265 0.457 2583 

1988 1.236 0.199 1.614 0.373 2778 

1989 0.550 0.115 0.733 0.180 5296 

1990 0.288 0.130 0.435 0.201 3369 

1991 0.337 0.154 0.471 0.228 5641 

1992 0.267 0.150 0.421 0.235 5831 

1993 0.207 0.080 0.296 0.150 5313 

1994 0.179 0.084 0.242 0.142 4839 

1995 0.200 0.080 0.275 0.137 4130 

1996 0.274 0.105 0.357 0.168 3454 

1997 0.352 0.085 0.420 0.145 3718 

1998 0.275 0.073 0.337 0.130 3470 

1999 0.192 0.072 0.256 0.127 3655 

2000 0.164 0.060 0.224 0.120 3576 

2001 0.160 0.060 0.223 0.120 3443 

2002 0.157 0.060 0.215 0.120 3502 

2003 0.127 0.060 0.194 0.120 3373 

2004 0.097 0.060 0.164 0.120 2758 

2005 0.175 0.071 0.234 0.129 955 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 12 of 13 

Table 7-2. Annual RFP external coworker doses (excluding NDRP data) modified to 

account for missed dose (rem). 

Year 

Penetrating 

95th percentile 

Penetrating 

50th percentile 

Nonpenetrating 

95th percentile 

Nonpenetrating 

50th percentile 

Number of 

Monitored 

Workers 

1952 1.004 0.853 1.119 0.968 2 

1953 1.829 0.690 2.151 0.818 295 

1954 1.858 1.075 2.747 1.340 343 

1955 2.572 1.145 3.203 1.411 507 

1956 2.551 1.095 3.334 1.370 696 

1957 2.956 1.135 3.879 1.405 872 

1958 3.907 1.155 5.314 1.445 1011 

1959 4.757 1.256 5.684 1.573 1029 

1960 3.877 1.108 4.586 1.415 1242 

1961 4.204 1.250 4.760 1.581 1593 

1962 4.264 1.248 4.864 1.538 1942 

1963 3.558 0.646 3.941 0.798 2097 

1964 2.337 0.545 2.520 0.675 2775 

1965 2.548 0.416 2.717 0.498 2781 

1966 4.362 0.541 4.565 0.620 2846 

1967 4.231 0.571 4.565 0.702 2871 

1968 2.674 0.536 3.026 0.660 3063 

1969 1.787 0.278 2.113 0.395 3390 
Document No. ORAUT-OTIB-0058 Revision No. 00 Effective Date: 05/12/2006 Page 13 of 13 

REFERENCES 

Falk, R. B., J. M. Aldritch, J. Follmer, N. M. Daugherty, D. E. Hilmas, and P. L. Chapman, 2005, 

Technical Basis Document for the Neutron Dose Reconstruction Project, Neutron Dose 

Reconstruction Protocol, ORISE 05-0199, Oak Ridge Institute of Science and Education, Oak 

Ridge, Tennessee, February 7. 

NIOSH (National Institute for Occupational Safety and Health), 2002, External Dose Reconstruction 

Implementation Guideline, OCAS-IG-001, Rev. 1, Office of Compensation Analysis and 

Support, Cincinnati, Ohio, August. 

ORAUT (Oak Ridge Associated Universities Team), 2004, Technical Basis Document for Rocky Flats 

Plant – Occupational External Dosimetry, ORAUT-TKBS-0011-6, Rev. 00, Oak Ridge, 

Tennessee, January 20. 

ORAUT (Oak Ridge Associated Universities Team), 2005a, Use of Coworker Dosimetry Data for 

External Dose Assignment, ORAUT-OTIB-0020, Rev. 01, Oak Ridge Tennessee, October 7. 

ORAUT (Oak Ridge Associated Universities Team), 2005b, Use of Rocky Flats Neutron Dose 

Reconstruction Project Data in Dose Reconstructions, ORAUT-OTIB-0050, Rev. 00, Oak 

Ridge, Tennessee, December 13. 

ORAUT (Oak Ridge Associated Universities Team), 2005c, External On-Site Ambient Dose 

Reconstruction for DOE Sites, ORAUT-PROC-0060, Rev. 00, Oak Ridge, Tennessee, 

March 7. 

ORAUT (Oak Ridge Associated Universities Team), 2005d, Interpretation of Dosimetry Data for 

Assignment of Shallow Dose, ORAUT-OTIB-0017, Rev. 01, Oak Ridge, Tennessee, 

October 11. 

ORAUT (Oak Ridge Associated Universities Team), 2005e, Supplementary External Dose Information 

for Rocky Flats Plant, ORAUT-OTIB-0027, Rev. 00, Oak Ridge, Tennessee, May 19.