ORAU Team

NIOSH Dose Reconstruction Project

Technical Basis Document for Rocky Flats Plant – Occupational 

External Dosimetry

Document Number:

ORAUT-TKBS-0011-6 

Effective Date: 01/20/2004

Revision No.: 00

Controlled Copy No.: ________

Page 1 of 68

Subject Experts: Jim Langsted

Document Owner

Approval: _Signature on File____________ Date: 01/29/2004

Robert Meyer, TBD Team Leader

Approval: _Signature on File____________ Date: 01/29/2004 Judson L. Kenoyer, Task 3 Manager

Concurrence: _Signature on File__________Date: 01/29/2004

Richard E. Toohey, Project Director

Approval: _Signature on File_____________Date: 01/30/2004

James W. Neton, OCAS Health Science Administrator

Supersedes:

None

TABLE OF CONTENTS

Section

Record of Issue/Revisions ...................................................................................................................

Page

6

Acronyms and Abbreviations ...............................................................................................................7

6.1 Introduction................................................................................................................................. 9

6.1.1 Purpose ...............................................................................................................................9

6.1.2 Scope ..................................................................................................................................9

6.2 External Dosimetry Overview......................................................................................................9

6.3 Interpreting the External Dosimetry Record............................................................................... 11

6.3.1 Dosimetry Records Systems.............................................................................................. 11

6.3.2 Observed Data Discrepancies ........................................................................................... 14

6.3.2.1 Rounding ..................................................................................................................14

6.3.2.2 Deep Not Equal to Gamma Plus Neutron.................................................................. 14

6.3.2.2.1 Possible Algorithm Issue .................................................................................. 14

6.3.2.2.2 Possible Manual Correction.............................................................................. 14

6.3.3 Database Table-Specific Issues......................................................................................... 15

6.3.3.1 RHRST_ED_TLD_HISTORY .................................................................................... 15

6.3.3.1.1 1976 Records (individual employed after 1976)................................................ 15

6.3.3.1.2 1976 Records (individual employed before 1976)............................................. 15

6.3.3.1.3 Post-1976 Records........................................................................................... 15

6.3.3.2 RHRST_ED_TLD_DOS ............................................................................................ 16

6.3.4 Additional Data Available ................................................................................................... 18

6.3.4.1 Rocky Flats Work History File ................................................................................... 18

6.3.4.2 Neutron Dose Reconstruction Project File................................................................. 18

6.3.4.3 Job Exposure Matrix ................................................................................................. 18
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6.4 Historical Administrative Practices ............................................................................................ 18

6.4.1 Badged Population ............................................................................................................ 18

6.4.2 Badge Exchange Frequency.............................................................................................. 19

6.4.3 Field-Specific Calibration Factors ...................................................................................... 19

6.4.4 Minimum Reported Dose ................................................................................................... 20

6.5 Common Issues........................................................................................................................20

6.5.1 Number of Zero Readings.................................................................................................. 21

6.5.2 Discrepancies .................................................................................................................... 21

6.5.3 Missing Entry .....................................................................................................................22

6.5.4 Exposure Geometry........................................................................................................... 23

6.6 Photon Dose.............................................................................................................................24

6.6.1 Energy Groups ..................................................................................................................24

6.6.1.1 Exposure Spectra ..................................................................................................... 24

6.6.2 Calibration Factor .............................................................................................................. 25

6.6.2.1 Reported Dose-to-Organ-Dose Conversion Factor Units........................................... 25

6.6.3 Missed Dose......................................................................................................................25

6.6.3.1 Limit of Detection ...................................................................................................... 25

6.6.3.2 Number of Zero Readings......................................................................................... 26

6.6.3.3 Determination of Missed Dose .................................................................................. 26

6.6.3.4 Unmonitored Energy Range...................................................................................... 27

6.6.4 Geometry...........................................................................................................................27

6.6.4.1 Angular Dependence ................................................................................................ 27

6.6.4.2 Exposure Geometry .................................................................................................. 28

6.6.5 Uncertainty ........................................................................................................................28

6.6.5.1 Film...........................................................................................................................28

6.6.5.2 Thermoluminescent Dosimeter.................................................................................. 29

6.6.5.2.1 Loose Chip Thermoluminescent Dosimeters .................................................... 29

6.6.5.2.2 Panasonic Thermoluminescent Dosimeter ....................................................... 29

6.7 Neutron Dose............................................................................................................................30

6.7.1 Energy Groups ..................................................................................................................30

6.7.1.1 Exposure Spectra ..................................................................................................... 30

6.7.1.2 Reported Dose to Energy Groups ............................................................................. 31

6.7.2 Calibration Factor .............................................................................................................. 31

6.7.2.1 Dosimeter-Specific Quality Factor Conversion .......................................................... 31

6.7.2.2 Reported-Dose-to-Organ-Dose Conversion Factor Units .......................................... 32

6.7.3 Missed Dose......................................................................................................................32

6.7.3.1 Limit of Detection ...................................................................................................... 32

6.7.3.2 Number of Zero Readings......................................................................................... 34

6.7.3.3 Unmonitored Energy Range...................................................................................... 34

6.7.3.4 Neutron Dose Reconstruction Project ....................................................................... 35

6.7.4 Geometry...........................................................................................................................35

6.7.4.1 Angular Dependence ................................................................................................ 35

6.7.4.2 Exposure Geometry .................................................................................................. 36

6.7.5 Uncertainty ........................................................................................................................36

6.7.5.1 Film...........................................................................................................................36

6.7.5.2 Thermoluminescent Dosimeter.................................................................................. 36

6.8 Electron Dose ...........................................................................................................................36
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6.8.1 Energy Groups ..................................................................................................................38

6.8.1.1 Exposure Spectra ..................................................................................................... 38

6.8.1.2 Reported Dose to Energy Groups ............................................................................. 38

6.8.2 Calibration Factor .............................................................................................................. 38

6.8.2.1 Reported-Dose-to-Organ-Dose Conversion Factor Units .......................................... 38

6.8.3 Missed Dose......................................................................................................................39

6.8.3.1 Limit of Detection ...................................................................................................... 39

6.8.3.2 Number of Zero Readings......................................................................................... 40

6.8.3.3 Unmonitored Energy Range...................................................................................... 40

6.8.4 Geometry...........................................................................................................................40

6.8.4.1 Angular Dependence ................................................................................................ 40

6.8.4.2 Exposure Geometry .................................................................................................. 40

6.8.5 Uncertainty ........................................................................................................................40

6.8.5.1 Film...........................................................................................................................40

6.8.5.2 Thermoluminescent Dosimeter.................................................................................. 41

6.8.5.2.1 Loose Chip Thermoluminescent Dosimeters .................................................... 41

6.8.5.2.2 Panasonic TLD Dosimeter................................................................................ 41

6.8.6 Skin Contamination............................................................................................................ 42

6.9 Unmonitored Individuals............................................................................................................ 42

6.9.1 In Production Areas ........................................................................................................... 42

6.9.2 Outside Production Areas .................................................................................................. 43

6.10 Extremity Dosimetry..................................................................................................................43

References ........................................................................................................................................44

Glossary ............................................................................................................................................47

Attachment A Example External Dosimetry Record Documents.................................................. 51

(see List of Figures)

Attachment B Major Job Categories............................................................................................ 67
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LIST OF TABLES

Table

6-1 Rocky Flats external dosimeter history...................................................................................

Page

12

6-2 Conservatively determined dosimeter exchange frequencies................................................. 20

6-3 Dose limits based on exchange frequency ............................................................................. 22

6-4 Exposure geometry calculation .............................................................................................. 23

6-5 Exposure geometry defaults for major job categories............................................................. 23

6-6 Photon energy distribution for RFP materials ......................................................................... 24

6-7 Default photon energy distribution for RFP materials ............................................................. 25

6-8 Photon dose units for use with organ dose conversion factors ............................................... 25

6-9 Photon limit of detection for RFP dosimeters.......................................................................... 26

6-10 Uncertainty for photon film dose at RFP................................................................................. 28

6-11 Uncertainty for loose chip TLD photon dose at RFP............................................................... 29

6-12 Uncertainty for DOELAP-accredited TLD photon dose at RFP............................................... 30

6-13 Neutron dose measurements divided into energy groups....................................................... 31

6-14 Default neutron energy distribution......................................................................................... 31

6-15 Neutron dose units for use with organ dose conversion factors.............................................. 32

6-16 RFP neutron film track counting detail.................................................................................... 33

6-17 Neutron limit of detection for RFP dosimeters ........................................................................ 34

6-18 Potential missed neutron dose for early film dosimeters at RFP............................................. 34

6-19 RFP correction ratios for identified neutron film reading deficiencies...................................... 35

6-20 Uncertainty for TLD neutron dose measurements at RFP...................................................... 37

6-21 Beta limit of detection for RFP dosimeters ............................................................................. 39

6-22 Uncertainty for beta film readings at RFP............................................................................... 41

6-23 Uncertainty for loose chip TLD photon dose at RFP............................................................... 41

6-24 Uncertainty for DOELAP-accredited TLD beta dose at RFP................................................... 41

6-25 Depleted uranium at RFP....................................................................................................... 42

6-26 One-year-old depleted uranium.............................................................................................. 43
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LIST OF FIGURES

Figure

6-1 Oak Ridge-style film badge ....................................................................................................

Page

10

6-2 RFP multielement film badge ................................................................................................. 10

6-3 RFP interim TLD/film badge................................................................................................... 10

6-4 RFP Harshaw badge..............................................................................................................11

6-5 RFP Panasonic dosimeter...................................................................................................... 11

6-6 Estimated beta dose rate from uranium metal at various enrichment levels ........................... 37

6-7 Shallow dose rate from natural uranium slab.......................................................................... 38

A-1 Occupational Dose Report reviewed 6-4-02, page 1 .............................................................. 52

A-2 Occupational Dose Report reviewed 6-4-02, page 2 .............................................................. 53

A-3 Dosimetry History by Individual dated 3-10-03, page 1 .......................................................... 54

A-4 Dosimetry History by Individual dated 3-10-03, page 2 .......................................................... 55

A-5 Dosimetry History by Individual dated 3-10-03, page 3 .......................................................... 56

A-6 Health Physics Yearly External Exposure Activity Run, 1953 through 1958 ........................... 57

A-7 Health Physics Yearly External Exposure Run, 1962 ............................................................. 58

A-8 Health Physics Yearly External Exposure Activity Run, 1964................................................. 59

A-9 External Dosimetry Detail, 1981 through 1983 ....................................................................... 60

A-10 Health Physics External Radiation Exposure Report, 1967 .................................................... 61

A-11 Radiation Dosimetry Individual Lifetime Report dated 6-4-02................................................. 62

A-12 Radiation Health Records System – TLD Data....................................................................... 63

A-13 Radiation Dosimetry Termination Report dated 9-17-96, page 1............................................ 64

A-14 Radiation Dosimetry Termination Report dated 9-17-96, page 2............................................ 65

A-15 External Dosimetry Detail, 1985 and 1986 ............................................................................. 66
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RECORD OF ISSUE/REVISIONS

ISSUE 

AUTHORIZATION 

DATE

EFFECTIVE 

DATE

REV. 

NO. DESCRIPTION

Draft 10/23/2003 00-A New Technical Basis Document for the Rocky 

Flats Site – Occupational External Dose. Initiated 

by Robert Meyer.

Draft 11/26/2003 00-B Incorporates NIOSH and ORAU comments. 

Initiated by Robert Meyer.

Draft 12/19/2003 00-C Incorporates additional NIOSH comments.

Initiated by Robert Meyer.

Draft 12/24/2003 00-D Incorporates DU dose energy range split 

modification per T. Taulbee comment. Initiated by 

Robert Meyer.

01/20/2004 01/20/2004 00 First approved issue. Initiated by Robert Meyer.
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 7 of 68

ACRONYMS AND ABBREVIATIONS

AEC U.S. Atomic Energy Commission

AED aerodynamic equivalent diameter

AP anterior-posterior

BVO boiler vent operator

CDH Colorado Department of Public Health and Environment (previously Colorado 

Department of Health)

Cf californium

cm centimeter

cpm (or c/m) counts per minute

Cs cesium

CY calendar year

D&D decontamination and decommissioning

DAC derived air concentration

DDE deep dose equivalent

DOE U.S. Department of Energy

DOELAP DOE Laboratory Accreditation Program

DOL U.S. Department of Labor

dpm disintegrations per minute

DU depleted uranium

EEOICPA Energy Employees Occupational Illness Compensation Program Act

Emax maximum energy

EPA U.S. Environmental Protection Agency

EU enriched uranium

G-M Geiger-Müller

HEU highly enriched uranium

HIS-20 Health Physics Information System

H*(d) ambient dose equivalent

Hp(d) personal dose equivalent

Hp,slab(d) personal dose equivalent (slab phantom)

HPS Health Physics Services (company)

HSDB Health Sciences Database

ICRP International Commission on Radiological Protection

in. inch

IREP Interactive RadioEpidemiological Program

ISO isotropic

keV kilo electron volt

LANL Los Alamos National Laboratory

Lc critical level

LOD limit of detection
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 8 of 68

MeV mega electron volt

mm millimeter

mR milliroentgen

mrem millirem

NBS National Bureau of Standards

NCRP National Council on Radiation Protection and Measurements

NDRP Neutron Dose Reconstruction Project

NDT nondestructive testing

NIOSH National Institute for Occupational Safety and Health

NRC National Research Council

NTA Nuclear Track Type A (film)

OCAS Office of Compensation Analysis and Support (NIOSH)

OR Oak Ridge

ORAU Oak Ridge Associated Universities 

Pa protactinium

PDF portable document file (Adobe Acrobat)

pen penetrating (deep) dose

PoBe polonium-beryllium 

PNAD personal nuclear accident dosimeter

PNL Pacific Northwest Laboratory

PPE personal protective equipment

Pu plutonium

PuF4 plutonium tetrafluoride (or fluoride)

R roentgen

RATCHET Regional Atmospheric Transport Code for Hanford Environmental Tracking

RCT Radiation Control Technician

rem roentgen equivalent man

RFETS Rocky Flats Environmental Technology Site

RFP Rocky Flats Plant

RHRS Radiological Health Records System

ROT rotational

SOE stationary operating engineer

TBD Technical Basis Document

TLD thermoluminescent dosimeter

TRU transuranic

U uranium
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6.1 INTRODUCTION

The National Institute for Occupational Safety and Health (NIOSH) is responsible for developing the 

technical capabilities and guidance for use in implementing the Energy Employees Occupational 

Illness Compensation Program Act (EEOICPA). Oak Ridge Associated Universities (ORAU) is 

leading a team to support NIOSH in the performance of this major program. This technical basis 

document (TBD) represents a specific area of support to the ORAU Team concerning documentation 

of historic practices at the Rocky Flats Plant (RFP) regarding evaluation of external exposure data for 

monitored and unmonitored workers to be used as a supplement to or substitute for recorded 

individual worker dose. 

6.1.1

The purpose of this document is to describe RFP external dosimetry systems and practices. The 

ORAU Team will use this information to evaluate external occupational doses for EEOICPA claimants. 

Purpose

6.1.2

RFP operations played an important role in the U.S. nuclear weapons program. These operations 

included production of fissionable weapons components and waste management. This TBD contains 

supporting documentation to assist in the evaluation of occupational external doses from these 

processes using the methodology in the External Dose Reconstruction Implementation Guideline

(NIOSH 2002). 

Scope

The methods and concepts of measuring occupational external doses to workers have evolved since 

the beginning of RFP operations. An objective of this document is to provide supporting technical 

data to evaluate, with claimant-favorable assumptions, the external RFP occupational doses that can 

reasonably be associated with worker radiation exposures covered under EEOICPA legislation. 

These doses include occupational external exposures in RFP facilities and onsite exposures to RFP 

environmental releases. This document addresses the evaluation of unmonitored and monitored 

worker exposure and missed dose. Consistent with NIOSH Implementation Guidelines, this 

document identifies how to adjust the historic occupational external recorded dose to account for 

current scientific methods and protection factors. 

In addition, this document presents the technical basis of methods used to prepare RFP worker 

external dose records for input to the NIOSH Interactive RadioEpidemiological Program (IREP) used 

to evaluate worker dose. Information on measurement uncertainties is an integral component of the 

NIOSH approach. This document describes the evaluation of uncertainty for RFP exposure and dose 

records. 

This document comprises one part of the overall Rocky Flats Plant Site Profile. The Site Profile 

describes plant facilities and processes, historic information related to occupational internal and 

external doses and environmental data for use if individual worker recorded doses are unavailable. 

This document contains Section 6 - Occupational External Dosimetry, of the Rocky Flats Site Profile. 

It provides necessary background information and critical data for the dose reconstructor to perform 

individual claimant dose reconstructions. 

6.2 EXTERNAL DOSIMETRY OVERVIEW

Over the years RFP used a variety of dosimeters to measure occupational ionizing radiation dose. 

Between 1951 and 1959, the Plant used a stainless-steel film badge based on an Oak Ridge design 
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 10 of 68

Figure 6-1. Oak Ridge-style 

film badge (including brass 

filter).

Figure 6-2. RFP multielement 

film badge.

Figure 6-3. RFP interim 

TLD/film badge.

(Baker 2002). This was a two-element film badge with an open 

window and a 1-mm cadmium filter. In 1960, a brass filter with half 

the filtration of the cadmium filter was added to cover half the open 

window. This provided separation of the 60-keV photons from the 

lower energy component. Very little information has been located on 

the performance of this dosimeter (Figure 6-1). 

In 1963, a plastic film badge was introduced at Rocky Flats that 

included additional filters. In addition to the photon dosimetry system, 

this badge contained a personal nuclear accident dosimeter (PNAD; 

Figure 6-2). This portion of the badge was not used for routine 

personnel dosimetry. 

In 1969, a combination 

film/thermoluminescent 

dosimeter (TLD) badge was 

introduced at Rocky Flats, using 

TLD chips to measure photon 

dose. There were three TLDs in 

the lower part of the badge, 

covered with the same brass filter (two chips) and a thin cover 

(one chip) providing an open window. Film was used for neutron 

dose measurement. This badge contained a PNAD and was an 

interim badge until the introduction of the TLD neutron system 

(Figure 6-3). 

In 1971, a full TLD badge was introduced at Rocky Flats that 

used TLD chips manufactured by Harshaw Chemical Company 

(Figure 6-4). Referred to as the "Harshaw badge," it contained a 

four-chip albedo neutron dosimeter (Falk 1971). Although the dosimeter did have a location for 

including a neutron film, this feature was not used. Photon measurement used three filter-covered 

TLDs, similar to those in the previous badge. This badge contained a PNAD. 

In 1983, an automated Panasonic dosimetry system was introduced at 

Rocky Flats (Figure 6-5). This badge contains two Panasonic 

dosimeters, one for measuring photon and beta dose and one for 

measuring neutron dose. The beta/photon dosimeter contains two TLD 

phosphors and a lead filter over one of the elements. The neutron 

dosimeter contains three neutron-sensitive elements and one neutroninsensitive element, under cadmium or tin filters. This badge includes a 

PNAD. 

Table 6-1 summarizes the history of dosimeter use at RFP. The 

implementation dates listed in the table and used throughout this 

document are not exact. In many cases, dosimeters were phased in over 

a period of 1 to 3 years. Determining from an individual employee's 

dosimetry record which dosimeter was worn is not possible, which adds a 

degree of uncertainty to the dose reconstruction. Further research is 

necessary to identify exact dates for each dosimeter type.
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 11 of 68

Figure 6-4. RFP Harshaw badge.

Figure 6-5. RFP Panasonic dosimeter.

The following sections discuss each of these dosimeter types 

with respect to each necessary dose reconstruction parameter. 

6.3 INTERPRETING THE EXTERNAL DOSIMETRY 

RECORD

When the U.S. Department of Labor (DOL) requests an 

individual dosimetry record (file), the RFETS Radiological 

Health Department provides a significant amount of effort in 

reviewing and organizing the external dosimetry records. Both 

hardcopy and electronic files are reviewed. They provide 

comments if discrepancies are found. If there are hardcopy 

results that are not in the electronic file, the electronic file is 

updated. If the electronic file includes a reading that is not 

indicated in the paper file, it is noted as a comment, but left in 

place. The claimant-favorable assumption is to include 

discrepant data in the annual total, unless notes explain why 

the data should not be included.

External dosimetry results are reported as:

• Penetrating (pen) or deep - deep dose + 

neutron

• Skin - shallow dose + neutron

• Forearm (measured or estimated)

• Hand (estimated).

The penetrating or deep dose is reported as the sum 

of the deep gamma and the neutron dose. The skin 

dose is reported as the deep dose unless the lowenergy detector on the dosimetry badge indicates a 

response greater than the deep dose, in which case 

shallow gamma plus neutron were reported. RFP 

does not used finger rings on a routine basis, but estimates the hand dose using the forearm dose 

measured by a wrist badge and the application of a hand-to-wrist ratio.

6.3.1

In the 1950s, external dosimetry data were handwritten and reported manually. In the 1960s and 

early 1970s, information was maintained on early computer systems. The detailed data have not 

been carried forward. For the early years, the dose detail has been lost and only quarterly totals are 

available. RFP typically summed the deep gamma dose and the neutron dose into a "penetrating" 

value. In the early years, the neutron and deep gamma numbers were not retained and only the 

penetrating value remains.

Dosimetry Records Systems 

Electronic systems for which detailed data have been maintained include:

• HSDB (Health Sciences Database)–1976 to 1990

• RHRS (Radiological Health Records System)–1990 to 1999

• HIS-20 (Health Physics Information System, Canberra Industries)–1999 to present.
Effective Date 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 12 of 68

Table 6-1. Rocky Flats external dosimeter history. 

Year Holder

Beta/gamma

Neutron Extremity

Detector

Filtration

Deep Shallow Processor Detector Processor Holder Detector

19511 SS OR2 design Std. X-ray 1mm Cd None LANL Track Plate LANL SS OR design Std. X-ray

1952 │ │ │ │ │ │ │ │ │

1953 │ │ │ │ │ │ │ │ │

1954 │ │ │ │ │ │ │ │ │

1955 │ │ │ │ │ │ │ │ │

1956 │ │ │ │ HPS │ HPS │ │

1957 │ │ │ │ │ NTA Film │ │ │

1958 │ │ │ │ RFETS │ RFETS │ │

1959 │ │ │ │ │ │ │ │ │

1960 │ │ 1/2 brass3 │ │ │ │ 1/2 brass4 │

1961 │ │ │ │ │ │ │ │ │

1962 │ │ │ │ │ │ │ │ │

1963 Plastic │ Multiple Multiple │ │ │ │ │

1964 │ │ │ │ │ │ │ │ │

1965 │ │ │ │ │ │ │ │ │

1966 │ │ │ │ │ │ │ │ │

1967 │ │ │ │ │ │ │ │ │

1968 │ │ │ │ │ │ │ │ │

1969 Interim Plastic TLD 700 │ │ │ │ │ │ │

1970 │ │ │ │ │ │ │ │ │

1971 Harshaw │ │ │ │ TLD 600/700 │ Harshaw TLD 600/700

1972 │ │ │ │ │ │ │ │ │

1973 │ │ │ │ │ │ │ │ │

1974 │ │ │ │ │ │ │ │ │

1975 │ │ │ │ │ │ │ │ │

1976 │ │ │ │ │ │ │ │ │

1977 │ │ │ │ │ │ │ │ │

1978 │ │ │ │ │ │ │ │ │

1979 │ │ │ │ │ │ │ │ │

1980 │ │ │ │ │ │ │ │ │

1981 │ │ │ │ │ │ │ │ │

1982 │ │ │ │ │ │ │ │ │

1983 Panasonic UD-802 │ │ │ UD-809 │ │ │

1984 │ │ │ │ │ │ │ │ │

1985 │ │ │ │ │ │ │ │ │

1986 │ │ │ │ │ │ │ │ │

1987 │ │ │ │ │ │ │ │ │

1988 │ │ │ │ │ │ │ │ │

1989 │ │ │ │ │ │ │ │ │

1990 │ │ │ │ │ │ │ │ │

1991 (DOELAP) Panasonic UD-813AS11

1992 │ │ │ │ │ │ │ │ │

1993 │ │ │ │ │ │ │ │ │

1994 │ │ │ │ │ │ │ │ │

1995 │ │ │ │ │ │ │ │ │

1996 │ │ │ │ │ │ │ │ │
Effective Date 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 13 of 68

Table 6-1. (Continued)

Year Holder

Beta/gamma

Neutron Extremity

Detector

Filtration

Deep Shallow Processor Detector Processor Holder Detector

1997│││││││││

1998│││││││││

1999│││││││ (DOELAP) 

2000│││││││││

2001│││││││││

2002│││││││││

2003│││││││││

1. Dates are approximate, overlap occurred during changeover

2. Oak Ridge

3. Brass not used on beta open window

4. Brass not used on beta open window, no brass on wrist-side 
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 14 of 68

In general, data migrated from one system to another. Little is known, or at least documented, about 

the precise method and decisions made during the migration of the HSDB to RHRS. However, the 

result of examining the contents of the data tables and hardcopy reports can be described.

6.3.2

6.3.2.1 Rounding

Observed Data Discrepancies

An annoying but manageable problem is exhibited by the rounding of individual deep dose values as 

well as the yearly or quarterly totals. The electronic data in RHRS and many of the reports contain 

both gamma and neutron components as well as a deep dose equivalent.

It appears that rounding to the nearest millirem (mrem) value occurred on the external deep dose after 

the values were added to calculate the deep dose equivalent (DDE). In many cases, this results in a 

discrepancy on the report cards of 1 mrem per measurement. Depending on the exchange 

frequency, there could be a difference of several mrem.

6.3.2.2 Deep Not Equal to Gamma Plus Neutron

In this case, the problem is clearly not due to rounding but rather to a discrepancy between the deep 

dose components and the deep dose value that is stored separately. The magnitude of the 

discrepancy is greater than 1 mrem. Two specific situations have been identified, as described in the 

following sections.

6.3.2.2.1 Possible Algorithm Issue

A group of results for a period, roughly July to October 1984, appear to indicate a reporting problem 

with the dosimetry algorithm used to calculate dose equivalents. In general, these results contain a 

gamma component that was calculated to be zero and a neutron dose that was calculated to be 

between about 15 and 50 mrem. However, the deep dose on both the report cards and in the 

electronic record was zero.

A review of a paper copy of the dose algorithm from that time (Rocky Flats 1983) and discussion with 

the algorithm developer indicates that the algorithm was developed in such a way that it should not 

have been possible to have a zero gamma dose with a non- zero neutron dose. In such a case, the 

algorithm would set the neutron dose to zero.

In these cases, however, the deep dose is reported as zero, and the neutron component was not set 

to zero before it was reported.

6.3.2.2.2 Possible Manual Correction

In another group of records, the deep dose is much greater than the gamma and neutron 

components. In the electronic data, these records appear during a period identified as "1976.” A 

review of a number of these records from the archive at the Federal Center found in all cases a letter 

in the file instructing the staff to modify the individual’s data due to a dose reconstruction or 

reevaluation. It appears that dose components were not provided in the letter and, therefore, were 

not made to add up to the deep dose.

The date of 1976 appears to have no relationship to the actual date associated with the dose record. 

According to the reports, many of the actual doses were assigned from 1984 to 1986.
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6.3.3

Two database tables contain the external dosimetry data in RHRS, as discussed in the following 

sections. Each table has specific information on the external monitoring period, and the distinctions 

between the tables are notable.

Database Table-Specific Issues

6.3.3.1 RHRST_ED_TLD_HISTORY

This table contains external dosimetry data for years generally before 1991, the time of RHRS 

implementation. These data migrated from earlier computer records systems such as the Health 

Sciences Data Base. Most of the records contain only a date referred to as "Activity Date.” In 

general, the activity date is close to the dosimeter return date if the actual return date is available.

To migrate these data to the current electronic database, HIS-20, an issue date had to be fabricated. 

Because the activity date is closer to the return date and there was no information on the exchange 

frequency, the issue date was set to 1 day before the return date.

6.3.3.1.1 1976 Records (individual employed after 1976)

This table contains a record dated 31-DEC-1976 for every individual in the database who was hired 

before 1989, even if they did not start work until after that date. This appears to have been an artifact 

from the initial migration of data from HSDB to RHRS. Therefore, a data record might appear in 

Health Physics file reports called “External Dosimetry (TLD) Detail” (from RHRS) and ‘’Dosimetry 

History by Individual” (from HIS-20) for 1976 when the individual was not yet hired.

Zero Dose Records

As a general rule, these records are not attributed to the individual, and they report a deep dose of 

zero.

Nonzero Dose Records

A 1976 record appears occasionally with a deep dose greater than zero. Such records are regarded 

as valid, and the official dose is attributed to the individual even though it is outside the employment 

period (see Section 6.3.2.2.2).

6.3.3.1.2 1976 Records (individual employed before 1976)

For individuals employed before 1976, the 1976 record represents a lump sum total of the deep dose 

for all prior years. However, the details for each year should be available during a review of report 

cards for an individual.

In addition, a database from the Colorado Department of Health (Ruttenber et al. 2003) was used to 

replace the lump sum with an annual deep dose values. Again, there is no electronic source for the 

deep dose components (neutron and gamma) or for skin and extremity values.

6.3.3.1.3 Post-1976 Records

Because the only date available before 1991 was the "Activity Date,” records can appear in reports 

that are outside the employment period. The activity date was used to document a "wear period" if 

there was no knowledge of the frequency of the dosimetry exchange. Therefore, the records might 

appear before the hire date or after the termination date.
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6.3.3.2 RHRST_ED_TLD_DOS 

This table, which has an identical structure to RHRST_ED_TLD_HISTORY, contains post-1991 data. 

The records are from a download of the external dosimetry computer system called FALCON. This 

system collects and processes data directly from the Panasonic TLD readers. The records generally 

contain values for each column, including a variety of dates – issue date, return date, and activity 

date.

There could be discrepancies between the monitoring period and the employment period. Individuals 

who did not check out properly might not have an accurate employment termination date. In addition, 

the computer systems typically documented the dates that the person wore dosimetry, and not 

necessarily an employment period. This is particularly true for subcontractors.

Dose History Hardcopy File Contents

The RFP Radiological Health organization reviews the individual dose record and summarizes it in an 

Occupational Dose Report worksheet (Attachment 6A-1). This document shows the measured dose

on an annual basis, summarizing dose data available from the printed record in the rest of the file. 

These data are compared with the computerized data, which are in the Dosimetry History by 

Individual report (Attachment 6A-2). Prior to 1976, the data were entered on an annual basis. A 

review of the rest of the external dosimetry file might indicate some detail of what went into the annual 

total. After 1975, this report provides a dosimeter-by-dosimeter reading. The "End Date" indicates 

the end of the wear period. Looking at the previous "End Date" can indicate the exchange frequency. 

If the "Begin Date" was not known, it was set to one day before the "End Date." In this case, it can be 

assumed that the badge was worn from approximately the day after the previous "End Date" to the 

indicated "End Date" for that period. 

Several other reports are included, some of which contain more dosimetry result detail:

• Early years are reported on the Health Physics External Exposure Run, which provides a 

quarterly breakdown. Even though dosimeters might have been exchanged more frequently, 

data are summarized by quarter and more detailed data are not included.

• The 1953-1958 report Health Physics External Exposure Activity Run Yearly (Attachment 6A3) contains a quarterly summary of the exposure data for an individual. The dose equivalent 

values reported are "skin,” "pen" (penetrating; the deep dose to the whole body), and "hand" 

(regarded as the dose to the extremity, if monitored).

• The 1959-1963 report Health Physics Yearly External Exposure Run (Attachment 6A-4) 

contains all details for each measurement for an individual. Each reading is on a separate 

line, revealing the frequency of the monitoring. The dose equivalents are reported as "skin,” 

"penet" (the deep dose to the whole body), and "wrist" (the dose to the extremity, if monitored).

• The 1964 report Health Physics External Exposure Activity Run Yearly (Attachment 6A-5) 

appears to be a transition report. It contains a quarterly summary of exposure data for an 

individual. The dose equivalent values reported are "skin,” "pen" (the deep dose to the whole 

body), and "hand" (the dose to the extremity, if monitored). 

• The External Dosimetry (TLD) Detail, Computerized Information Through xx-xx-xx or External 

Dosimetry (TLD) Detail, Computerized Information for CY 19xx (Attachment 6A-6) provides 

dosimeter reading detail for the years indicated. The "Activity Date" indicates the nominal (a 
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 17 of 68

few days to either side) end date of the dosimeter wear period. "Time Code" indicates the 

identified exchange period for the badge:

 Time Code 1 - biweekly (once every 2 weeks)

 Time Code 2 - monthly

 Time Code 4 - quarterly.

During the transition between the Harshaw and the Panasonic badges, RFP used a code to indicate 

the source of the dosimetry result:

 Type Code C, "Calculated" - Panasonic badge result (calculated in Panasonic 

computer system), no wrist dosimeter data.

 Type Code R, "Raw" - Harshaw badge chip readings (raw chip readings, result 

calculated in RHRS database system), no wrist dosimeter data.

 Type Code H, "Hybrid" - Panasonic badge result and Harshaw wrist dosimeter chip 

readings.

• The Health Physics External Radiation Exposure Report for Year XX ("report card") 

(Attachment 6A-7) provides quarterly totals for the year. Because dose limits were on a perquarter basis, the purpose of this report was to monitor compliance with these limits. The 

dosimeter detail was lost. 

• The 1965-1989 report Health Physics External Radiation Exposure Report contains a quarterly 

summary of exposure data for an individual. The dose equivalent values reported are "pen" 

(the deep dose to the whole body), "skin,” and "hand" (the dose to the extremity, if monitored). 

In addition, these reports contain a "lifetime" (career) deep dose for exposure at Rocky Flats. 

After 1976, a column was added to the report for a value described as "forearm.” This dose 

equivalent appears to be similar to that for the hand. In 1977, the dose to the hand was set to 

the greater of the skin of the whole body and the measurement calculated from the actual wrist 

dosimeter. 

• Occasionally, for individuals employed after 1976 and until about 1986, there might be a report 

called External Dosimetry (TLD) Detail. This report contains greater detail on each 

measurement made during this period and a breakdown of gamma and neutron components.

• The Radiation Dosimetry Detail Report (Attachment 6A-8) provides very little detail other than 

a verification of the Reported Lifetime Dose. This includes offsite doses (from previous 

employers), which should be detailed in the file. 

• Radiological Health Records System (RHRS) Data report (Attachment 6A-9) provides details 

of the dosimeter results. The advantage of this report is that it shows the breakdown of the 

deep dose into neutron and gamma components. 

• Radiation Dosimetry Detail Report, Termination Report (Attachment 6A-10) provides a 

verification of lifetime and post-1987 exposure.

• Occupational Radiation Exposure Information (Attachment 6A-11) provides annual "Whole 

Body" dose, "Hand,” "Forearm,” and Accumulated Rocky Flats "Whole Body" doses. It is 

assumed the whole-body dose is penetrating.
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These data enable compilation of an external dosimetry history, as follows:

• 1951 – 1976, quarterly dose history (RHRS data will provide a neutron/gamma breakdown)

• 1977 – present, dosimeter exchange history.

In some cases additional data are available. The dose reconstructor is responsible for using the 

information in this TBD to provide claimant-favorable assumptions to fill in unavailable detail for a 

claimant's external dosimetry record.

6.3.4

Additional sources of information, which are known to exist, contain detail that is not in the dose 

history file. These data would provide additional detail that could be useful in refining dose estimates 

for some claimants.

Additional Data Available

6.3.4.1 Rocky Flats Work History File

The Rocky Flats Human Resources department kept job assignment records for many years on 5 in. x 

7 in. cards. Images of these cards could provide a further indication of the type(s) of work performed 

by the claimant. This information is not in the dose history file.

6.3.4.2 Neutron Dose Reconstruction Project File

As part of the Neutron Dose Reconstruction Project (NDRP) to reevaluate neutron film dosimetry, the 

original dosimetry laboratory worksheets were retrieved and arranged chronologically. The 

worksheets were grouped by building. A database has been constructed to include data for only 

those workers who were monitored for neutrons using film during the period between 1951 and 1970. 

Because the focus of the NDRP is on neutron dose, the database primarily contains data on 

plutonium workers and not on uranium or nonradiation workers. The database would provide a 

breakdown of the penetrating dose (neutron and gamma) and dosimeter-by-dosimeter data for some 

of the period during which data were lost when quarterly totals were generated from 1951 to 1975. 

This information is not in the dose history file.

6.3.4.3 Job Exposure Matrix

A U.S. Department of Energy-funded study performed by the University of Colorado Health Sciences 

Center and the Colorado Department of Public Health and Environment (Ruttenber et al. 2003) 

developed a Job Exposure Matrix that identified the building assignment and a job title snapshot 

during September for each year from 1952 to 1989. This matrix was matched with external dosimetry 

results and would provide dose distributions for groups and job titles to assist in estimating dose for 

unmonitored workers. These data are unavailable to DOE and are not in the DOE dose history file.

6.4 HISTORICAL ADMINISTRATIVE PRACTICES

6.4.1

When plant operations began in 1951, there was no external dosimetry, and there was not much 

radioactive material at the Plant. In September 1952, dosimeters became available for use. Some

individuals in Building 991 received neutron dosimeters. The use of dosimetry expanded to other 

RFP production operations. In 1964, the security badge was incorporated in the dosimetry badge, 

which ensured that each individual wore a dosimetry badge (Putzier 1982). This design was 

Badged Population
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maintained until the early 1990s, when the security badge was separated from the dosimeter and 

individuals unlikely to receive occupational radiation exposure greater than 100 mrem were no longer 

issued dosimeters.

6.4.2

The determination of badge exchange frequencies was based on the potential for external dose and 

the necessity to control dose to administrative limits. Badges were exchanged at various frequencies. 

Early dosimetry was exchanged on a weekly basis, which later became semimonthly and monthly. In 

later years, dosimetry was exchanged on semimonthly, monthly, and quarterly frequencies. In the 

1990s, exchange frequencies went to monthly, quarterly, and semiannually. An option for annual 

exchanges was identified, but never used.

Badge Exchange Frequency

Badge exchange frequency records have not been maintained. The exchange frequency for an 

individual can be determined by reviewing the external dose record, if individual dosimeter readings 

were maintained. After 1976, the dose record will show a dosimeter reading for each exchange. For 

earlier years, the dose has been combined into quarterly records for which the exchange frequency 

has been lost, although it is reasonable to assume badges were exchanged at least quarterly.

To determine the exchange frequencies used before 1976, original dosimetry laboratory worksheets 

were reviewed, many of which have been assembled as part of the NDRP. Dosimetry laboratory 

worksheets from 1951 through 1970 have been assembled and organized. A sample was obtained 

by selecting the September folder for each year. A review of each worksheet determined the 

exchange frequency, building, and dosimeter type (photon, beta, or neutron). These data were 

organized and reviewed to determine the most frequent exchange for the major job categories (see 

Attachment 6B) by year. The worksheets do not indicate job assignment. It was necessary to 

evaluate the job category based on the building and exchange frequency. In cases where multiple 

exchange frequencies were indicated for a major job category, the more frequent exchange frequency 

was selected. This provides a claimant-favorable assumption when determining missed dose. 

Dosimetry worksheets are not readily available from 1970 to 1976, so exchange frequencies were 

extrapolated forward for those years. This is appropriate because the Plant was relatively stable 

during that period. Table 6-2 lists the results of this analysis. These are the default values to use if 

the exchange frequency cannot be determined. If no job category can be determined, the dose 

reconstructor should use the most frequent exchange for that year.

6.4.3

Film dosimeters required the use of workplace-specific calibration factors, so it was necessary to 

know the facility in which the individual worked. The Dosimetry department determined this by using 

facility assignment rosters, issuing and retrieving badges to each major facility. Individuals sometimes 

worked in other facilities on temporary or overtime assignments, which the Dosimetry department 

could not detect. Area-specific calibration factors were necessary to evaluate readings from Xray/gamma dosimeters used in the plutonium areas and the beta/gamma dosimeters used in the 

uranium areas. If a dosimeter was exposed in a different field, this could not be detected, which 

introduced a source of uncertainty.

Field-Specific Calibration Factors

TLD systems use more tissue-equivalent detection elements, which do not require a field-specific 

calibration factor. This source of uncertainty is minimal with these dosimeters. 
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Table 6-2. Conservatively determined default dosimeter exchange frequencies. 

Year

Chemical 

operators

Metallurgical 

operators

Maintenance 

workers

Support 

personnel

Analytical 

laboratory 

technicians

Site 

support 

personnel

Radiation 

control 

technicians

Pu U Pu U

1951 sm sm sm sm m m sm m sm

1952 sm sm sm sm m m sm m sm

1953 sm sm sm sm m m sm m sm

1954 sm sm sm w m sm sm m sm

1955 sm sm sm w m sm sm m sm

1956 sm sm sm w m sm sm m sm

1957 sm sm sm w m sm sm m sm

1958 w w w w m sm sm m w

1959 w sm w w m sm sm m w

1960 w w w w m m sm m w

1961 sm sm sm w m m w m sm

1962 sm sm sm w m m w m sm

1963 sm m sm sm m m q m sm

1964 sm m sm m q m q q sm

1965 m -- m m q q q q m

1966 m -- m m m q q q m

1967 sm -- sm m m q q q sm

1968 sm -- sm m m m m m sm

1969 sm -- m m m m m m m

1970 sm -- m m m m m m m

1971 sm -- m m m m m m m

1972 sm -- m m m m m m m

1973 sm -- m m m m m m m

1974 sm -- m m m m m m m

1975 sm -- m m m m m m m

1976 sm -- m m m m m m m

w - weekly

sm - semi-monthly (twice per month)

m - monthly

q - quarterly

6.4.4

RFP appears to have embraced a philosophy of reporting dose down to zero between 1951 and 1992. 

In 1993, the Plant adopted a minimum reported dose threshold to remove the bias associated with 

reporting low doses and truncating doses calculated to be small negative numbers to zero. In 1993, a 

minimum reported dose level of 10 mrem was adopted. Any dose below this level was reported as 

zero (RFETS 2001). This policy is consistent with the limits of detection reported elsewhere in this 

TBD.

Minimum Reported Dose

6.5 COMMON ISSUES

This section discusses issues common to external photon, neutron, and electron dose measurement 

at RFP. These issues are addressed further only if there is an issue specific to that type of dose 

measurement.
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6.5.1

At present, available dosimetry records do not provide individual dosimeter results for the early years. 

Therefore, it will be necessary to estimate the dosimeter exchange frequency for the period from 1951 

to 1976. Table 6-2 provides an estimate based on major job category. If an individual’s job 

assignment cannot be determined, the most frequent dosimeter exchange used during that year must 

be assumed. This is a claimant-favorable assumption. 

Number of Zero Readings

Once the estimated exchange frequency has been established, the number of zero readings must be 

estimated. If the number of zero measurements cannot be determined, the missed dose becomes 

more complicated. When only the quarterly dose is known, the number of zero doses should be 

estimated based on the dose level and the monthly, quarterly, or annual limits for that year and the 

number of possible zero monitoring intervals. This would be the situation, for example, if an individual 

received a cumulative dose of 2,140 mrem in a given year at a facility that had a monthly monitoring 

frequency, and the maximum permissible exposure limit was 1,000 mrem per month. The minimum 

number of months in which this dose could have been received is 3. Therefore, the maximum number 

of missed dose months would be 9, and the minimum would be zero because the dose could have 

been received evenly throughout the year. The central estimated number of months should be the 

median, or 5; however, the upper bound would be 9 (NIOSH 2002).

Quarterly or annual limits: 1951 – 1967, 3 rem per quarter (Attachment 6A-7)

1968 – 1992, 5 rem per year (observed in Rockwell International 1985)

1993 – present, 2 rem per year (DOE 1992)

Table 6-3 divides these dose limits into exchange frequencies. Using the methodology of NIOSH 

(2002), it is possible to develop a claimant-favorable estimate of the number of zeros and ultimately 

the missed dose.

6.5.2

If the employee’s record contains discrepancies, it is claimant-friendly to use the higher dose in the 

dose reconstruction. Care must be taken to interpret dose numbers properly if units were not 

specified. RFP routinely used mR or mrem as the unit of dose. If a number has no unit indicated, it is 

probably not in rem. It is highly unlikely that a record would show a dose greater than the quarterly or 

annual limit without an additional record indicating an overexposure. 

Discrepancies

If no activity date is associated with a dose record, it is claimant-favorable to use that dose in the dose 

reconstruction. The dose reconstructor should use best judgment to credit the dose to the most likely 

year.

Corrections were noted in the dose record when calculation or computer errors occurred. Such 

corrections were usually noted on the hard-copy report, and a notation was entered if the electronic 

record was updated. If the record was updated and noted, the correction should not be applied again. 

If there is no obvious notation to indicate the incorporation of a correction, the claimant-favorable 

action is to incorporate the correction in the dose used for reconstruction.
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Table 6-3. Dose limits (rem) based on exchange frequency. period 52 26 12 4 2

Year Limit (rem) (yr) weekly semimonthly monthly quarterly semiannually

1951 3 0.25 0.231 0.462 1.000 3.000

1952 3 0.25 0.231 0.462 1.000 3.000

1953 3 0.25 0.231 0.462 1.000 3.000

1954 3 0.25 0.231 0.462 1.000 3.000

1955 3 0.25 0.231 0.462 1.000 3.000

1956 3 0.25 0.231 0.462 1.000 3.000

1957 3 0.25 0.231 0.462 1.000 3.000

1958 3 0.25 0.231 0.462 1.000 3.000

1959 3 0.25 0.231 0.462 1.000 3.000

1960 3 0.25 0.231 0.462 1.000 3.000

1961 3 0.25 0.231 0.462 1.000 3.000

1962 3 0.25 0.231 0.462 1.000 3.000

1963 3 0.25 0.231 0.462 1.000 3.000

1964 3 0.25 0.231 0.462 1.000 3.000

1965 3 0.25 0.231 0.462 1.000 3.000

1966 3 0.25 0.231 0.462 1.000 3.000

1967 3 0.25 0.231 0.462 1.000 3.000

1968 5 1 0.096 0.192 0.417 1.250

1969 5 1 0.096 0.192 0.417 1.250

1970 5 1 0.096 0.192 0.417 1.250

1971 5 1 0.096 0.192 0.417 1.250

1972 5 1 0.096 0.192 0.417 1.250

1973 5 1 0.096 0.192 0.417 1.250

1974 5 1 0.096 0.192 0.417 1.250

1975 5 1 0.096 0.192 0.417 1.250

1976 5 1 0.096 0.192 0.417 1.250

1977 5 1 0.096 0.192 0.417 1.250

1978 5 1 0.096 0.192 0.417 1.250

1979 5 1 0.096 0.192 0.417 1.250

1980 5 1 0.096 0.192 0.417 1.250

1981 5 1 0.096 0.192 0.417 1.250

1982 5 1 0.096 0.192 0.417 1.250

1983 5 1 0.096 0.192 0.417 1.250

1984 5 1 0.096 0.192 0.417 1.250

1985 5 1 0.096 0.192 0.417 1.250

1986 5 1 0.096 0.192 0.417 1.250

1987 5 1 0.096 0.192 0.417 1.250

1988 5 1 0.096 0.192 0.417 1.250

1989 5 1 0.096 0.192 0.417 1.250 2.500

1990 5 1 0.096 0.192 0.417 1.250 2.500

1991 5 1 0.096 0.192 0.417 1.250 2.500

1992 5 1 0.096 0.192 0.417 1.250 2.500

1993 2 1 0.038 0.077 0.167 0.500 1.000

1994 2 1 0.038 0.077 0.167 0.500 1.000

1995 2 1 0.038 0.077 0.167 0.500 1.000

1996 2 1 0.038 0.077 0.167 0.500 1.000

1997 2 1 0.038 0.077 0.167 0.500 1.000

1998 2 1 0.038 0.077 0.167 0.500 1.000

1999 2 1 0.038 0.077 0.167 0.500 1.000

2000 2 1 0.038 0.077 0.167 0.500 1.000

2001 2 1 0.038 0.077 0.167 0.500 1.000

2002 2 1 0.038 0.077 0.167 0.500 1.000

2003 2 1 0.038 0.077 0.167 0.500 1.000

6.5.3

If the dosimetry history contains a missing entry, this probably indicates that the individual missed the 

dosimeter exchange and that the next dosimeter includes the dose from both exchange periods. A 

less likely indication is that the badge was lost and no dose was assigned for that period. The 

claimant-favorable assumption is that the dosimeter was lost; dose should be assigned for that period 

Missing Entry
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using dosimetry data preceding and following that period (consider the approach of Watson, Wood, 

Tankersley, and West 1994).

6.5.4

Because little information is available on the exposure geometry for an individual, estimates have 

been made for each major job category (Attachment 6B). To estimate the exposure geometry for 

major job categories, engineering judgment was used and a simple calculation was performed. The 

fraction of the dose received via each geometry is a product of the dose rate and exposure duration 

that each worker experienced. Workers experienced a higher dose rate when working hands-on with 

radioactive material, and a lower dose rate as they performed other tasks in the radiation control area. 

An estimate of the fraction of hands-on time was selected for each major job category. Selection of

source geometry was based on as assumed configuration of the radioactive material to which the 

workers were exposed. From this, a relative dose was estimated for hands-on work (1 foot away) and 

non-hands-on work (4 feet away), using simple rules of thumb. These were combined to estimate the 

fraction of the dose received via the anterior-posterior (AP) geometry (hands-on) or other geometries 

for the balance of the exposure (ICRP 1996). Table 6-4 presents these results. The non-AP 

exposure was estimated to come from either the rotational (ROT) or isotropic (ISO) geometry. The 

difference is that ISO considers exposure from all angles (including above and below) while ROT 

considers only exposure from all horizontal directions to the upright individual. Chemical operators 

receive doses from above and below due to pipes in the overhead and near the floor. All others were 

assumed to receive their non-AP doses from the ROT geometry. Table 6-5 lists these fractions, 

which are rounded.

Exposure Geometry

Table 6-4. Exposure geometry calculation. 

Major job category Hands-on work (time) Source geometry

Calculated dose received

AP ISO or ROT

Chemical operators 25% Line 57% 43%

Metallurgical operators 75% Point 98% 2%

Maintenance workers 75% Plane 98% 2%

Support personnel 5% Plane 46% 54%

Analytical laboratory tech. 75% Point 98% 2%

Site support personnel 0% Plane 0% 100%

Radiation control technicians 10% Plane 64% 36%

D&D workers 75% Plane 98% 2%

Table 6-5. Exposure geometry defaults for major job 

categories. 

Major job category

Default selected

AP ISO ROT

Chemical operators 50% 50%

Metallurgical operators 100%

Maintenance workers 100%

Support personnel 50% 50%

Analytical laboratory tech. 100%

Site support personnel 100%

Radiation control technicians 60% 40%

D&D workers 100%
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6.6 PHOTON DOSE

6.6.1

The NIOSH IREP probability of causation program (NIOSH 2002) contains three photon energy 

bands:

Energy Groups

• Below 30 keV

• 30 to 250 keV

• Above 250 keV. 

Separation of the dose from each energy band is required.

6.6.1.1 Exposure Spectra

Very little spectroscopy data indicating the gamma spectrum in RFP work areas have been located. 

To estimate the gamma spectrum to which workers were exposed, MicroShield 5.03 (Grove 

Engineering 1998) was used. With the use of the MicroShield decay feature, radionuclide source 

concentrations (DOE 1980) for weapons-grade plutonium, enriched uranium, and depleted uranium 

were used (freshly separated material) and then decayed for 10 and 30 years. These decay times 

give an understanding of the material to which workers were exposed. Depleted and enriched 

uranium were routinely handled in the open with no shielding. Plutonium was almost exclusively 

handled in glove boxes, providing shielding from the glovebox materials. This calculation assumed 

large pieces of material (infinitely thick with respect to the photon path length in that material) and 

1/16-in. stainless steel as the shielding provided by the glovebox. Table 6-6 presents these results.

Table 6-6. Photon energy distribution for RFP materials. Shield Energy Fresh Pu 10-yr Pu 30-yr Pu Fresh EU 10yr EU 30yr EU Fresh DU 10yr DU 30yr DU

None

<30 keV

Not applicable

0% 0% 0% 0% 0% 0%

30-250 keV 100% 99% 98% 100% 3% 3%

>250 keV 0% 1% 2% 0% 97% 97%

1/16 

inch 

steel

<30 keV 0% 0% 0%

30-250 keV 100% 85% 88% Not applicable

>250 keV 0% 15% 11% 

Plutonium processed at RFP varied in age from freshly separated to wastes that have been stored 

onsite for many years. Using the default assumption that the material is freshly separated, results in a 

claimant-favorable dose resulting from exposure to the 30 - 250 keV photon energy range.

234mPa is a decay product in the 238U (depleted uranium) decay chain and emits a 2.29 MeV beta 

particle. Thus, a significant quantity of photons resulting from bremsstrahlung radiation are produced 

and contribute photons of intermediate energy (30 - 250 keV). These photons are not included in 

Table 6-6. Bremsstrahlung radiation can contribute up to 40% of the photon dose from uranium metal 

(DOE 2001). This decay product grows-in fairly rapidly and is present in equilibrium quantities for 

most depleted uranium that was processed at RFP. It is appropriate to use the default assumption for 

depleted uranium that 50% of the dose is contributed by photons in the 30 - 50 keV photon energy 

range and 50% of the dose is a result of exposure from photons in the >250 keV photon energy 

range. 

Although enriched uranium has significantly less in-growth of 234mPa, 235U and it's decay products emit 

a 185.7 keV photon 57% of time and a 143.8 keV photon 11% of the time. These photons dominate 

the measured photon energy spectra. Thus, for enriched uranium, it is appropriate to use the default 
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assumption that all the photon dose is a result of exposure in the 30 - 250 keV photon energy range.

This is a claimant-favorable assumption. The default assumptions are shown in Table 6-7.

Table 6-7. Default photon energy distribution for RFP materials. 

Energy Plutonium Enriched uranium Depleted uranium

<30 keV 0% 0% 0%

30-250 keV 100% 100% 50%

>250 keV 0% 0% 50%

6.6.2

6.6.2.1 Reported Dose-to-Organ-Dose Conversion Factor Units

Calibration Factor

Standard X-ray film was initially used for photon dosimetry at Rocky Flats. This film was processed 

by Los Alamos National Laboratory (LANL). This was followed by a period in which a subcontractor 

performed the processing, after which RFP took over the processing. 

Little is known about the LANL-provided dosimetry, but it is reasonable to assume that the dosimeter 

was calibrated in roentgens (R).

When RFP provided the film dosimetry, it appears that roentgens continued as the unit of calibration 

(Dow Chemical 1967). It is reasonable to assume that this continued until calibration of the 

Panasonic TLD dosimetry system, which was performed using DOELAP sources at Pacific Northwest 

Laboratory (PNL). DOELAP sources have been used since that time. The Personal Dose Equivalent 

[Hp(10)] is the appropriate unit to use for this period.

Table 6-8 summarizes dose units to use for organ dose conversion factors.

Table 6-8. Photon dose units for use with organ dose conversion factors. 

Year Year Year Year Year Year

1951 R 1961 R 1971 R 1981 R 1991 Hp(10) 2001 Hp(10)

1952 R 1962 R 1972 R 1982 R 1992 Hp(10) 2002 Hp(10)

1953 R 1963 R 1973 R 1983 Hp(10) 1993 Hp(10) 2003 Hp(10)

1954 R 1964 R 1974 R 1984 Hp(10) 1994 Hp(10)

1955 R 1965 R 1975 R 1985 Hp(10) 1995 Hp(10)

1956 R 1966 R 1976 R 1986 Hp(10) 1996 Hp(10)

1957 R 1967 R 1977 R 1987 Hp(10) 1997 Hp(10)

1958 R 1968 R 1978 R 1988 Hp(10) 1998 Hp(10)

1959 R 1969 R 1979 R 1989 Hp(10) 1999 Hp(10)

1960 R 1970 R 1980 R 1990 Hp(10) 2000 Hp(10)

6.6.3

Section 2.1.2 of NIOSH (2002) recommends the use of the LOD/2 method for determining missed 

dose.

Missed Dose

6.6.3.1 Limit of Detection

The film badge initially used at RFP is similar to that developed at the University of Chicago and used 

at other U.S. Atomic Energy Commission (AEC, a DOE predecessor agency) sites. All of these 

badges used X-ray film surrounded with a metal badge holder. They had an open window and an 
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 26 of 68

area covered with 1 mm of silver, tin, or cadmium (Alvarez et al. 2003). A PNL study of this twoelement dosimeter (Wilson, Fix, Baumgartner, and Nichols 1990) identified a detection level of about 

40 mR at the upper 95% confidence level for radium gamma radiation. Improved film, implemented at 

Hanford in 1960 (Wilson, Fix, Baumgartner, and Nichols 1990), reduced this detection level to about 

15 mR. Information found at RFP indicated that a DuPont 558 film packet was used in 1964 (Owen 

1964). This packet contained a piece of DuPont 508 sensitive film and a piece of DuPont 1290 

insensitive film. The 1290 film was not processed unless the 580 film was too exposed to read. It is 

not clear if RFP used the earlier 502 film or when it changed to the 508 film. Hanford changed to 508 

film in 1960 (Wilson, Fix, Baumgartner, and Nichols 1990). It is claimant-favorable to assume that 

RFP used the less sensitive film until 1960, and then used the more sensitive 508 film. The film LOD 

selected is that determined by Wilson, Fix, Baumgartner, and Nichols (1990) for the Hanford badge.

In 1969, RFP started using Harshaw TLD chips to measure photon dose. Again, this dosimeter was 

similar to one used at Hanford. Wilson, Fix, Baumgartner, and Nichols (1990) identified an estimated 

detection level of 20 mR for radium gamma detection. The limit of detection information has not been 

identified specifically for TLD implementation at RFP, but is believed to be similar to that for the 

Hanford dosimeter.

The 1983 switch at RFP to the Panasonic dosimeter in 1983 achieved improved sensitivity. 

Information on the limit of detection during this period has not been identified, so the claimantfavorable value of 20 mrem, similar to that achieved in 1982, is recommended. 

In 1992, a study was performed to reduce the variability in low-dose measurements. An uncertainty 

criterion incorporated in the algorithm resulted in more stable dose measurements at low doses. This 

resulted in an estimated limit of detection of 10 mrem. A dose-reporting threshold of 10 mrem was 

implemented. Any dose below this was reported as 0.

Table 6-9 lists photon limits of detection for the RFP dosimeters.

Table 6-9. Photon limit of detection for RFP dosimeters. 

Year LOD Year LOD Year LOD Year LOD Year LOD Year LOD

1951 40 mR 1961 40 mR 1971 20 mR 1981 20 mR 1991 20 mrem 2001 10mrem

1952 40 mR 1962 40 mR 1972 20 mR 1982 20 mR 1992 20 mrem 2002 10mrem

1953 40 mR 1963 40 mR 1973 20 mR 1983 20 mrem 1993 10 mrem 2003 10mrem

1954 40 mR 1964 40 mR 1974 20 mR 1984 20 mrem 1994 10 mrem

1955 40 mR 1965 40 mR 1975 20 mR 1985 20 mrem 1995 10 mrem

1956 40 mR 1966 40 mR 1976 20 mR 1986 20 mrem 1996 10 mrem

1957 40 mR 1967 40 mR 1977 20 mR 1987 20 mrem 1997 10 mrem

1958 40 mR 1968 40 mR 1978 20 mR 1988 20 mrem 1998 10 mrem

1959 40 mR 1969 20 mR 1979 20 mR 1989 20 mrem 1999 10 mrem

1960 40 mR 1970 20 mR 1980 20 mR 1990 20 mrem 2000 10 mrem

6.6.3.2 Number of Zero Readings

Section 6.5.1 of this TBD discusses the determination of the number of zero readings.

6.6.3.3 Determination of Missed Dose

Determination of missed dose is performed using LOD/2 times the number of zero readings, as 

discussed in Section 2.1.2.2 of NIOSH (2002). For the period from 1977 to the present, the number of 

zero readings can be determined directly from the dosimetry data. The missed dose is assumed to be 

lognormally distributed with central tendency nLOD/2, and the upper 95% dose is nLOD, where n is 
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 27 of 68

the number of zero readings. If the number of zero readings cannot be determined, it must be 

estimated assuming prorated dose limits were not exceeded. Section 6.5.1 of this TBD and Section 

2.1.2.3 of the reconstruction guidance discuss this estimate. In this case, the estimate is assumed to 

be lognormally distributed with central tendency mLOD/2, where m is the median of minimum and 

maximum possible number of zero readings, and the upper 95% dose is pLOD, where p is the 

maximum possible number of zero readings.

6.6.3.4 Unmonitored Energy Range

All dosimeter types used at RFP were calibrated and their response was corrected for photon 

energies resulting in worker dose in the work areas (low-energy X-rays, americium photons, and highenergy photons). No corrections for unmonitored photon energy range are appropriate.

The two-element film dosimeter used at RFP is similar to those used at other sites. The response of 

this dosimeter is addressed in the Savannah River Site TBD (ORAU 2003). These documents 

address the significant over-response of film to low photon energies. The dosimeter (open window) 

was calibrated with low-energy photons. To correct for this over-response, a portion of the openwindow dose was added to the deep dose measured under the 1-mm cadmium filter. There is 

evidence (Falk 2003) that this correction was used at RFP. This indicates that the early film 

dosimeter was corrected for energy response. No missed photon dose correction factor is 

appropriate for this dosimetry system.

The multielement film dosimeter used at RFP provided better energy response to measure worker 

dose more accurately. Although little information is available on this dosimetry system, it appears that 

corrections were incorporated to prevent missed photon dose. Therefore, no missed photon dose 

correction factor is appropriate for this dosimetry system.

Harshaw TLD chips were used at RFP in an interim neutron film/photon TLD badge, and then in the 

RFP TLD badge. These dosimeter elements were shielded and of various thicknesses. Most 

important, the TLD elements were relatively tissue-equivalent with respect to photon response and 

unlikely to have missed photon dose in an energy range to which workers were exposed. No missed 

dose correction is appropriate for this dosimetry system.

The initial implementation of the Panasonic TLD system was based on a range of DOELAP exposure 

categories. The response of the dosimeter was evaluated with respect to these exposures, and the 

algorithm was derived from these exposures. Thus, the initial implementation of the Panasonic TLD 

system and the later DOELAP-accredited operation of that system are unlikely to have missed photon 

dose in an energy range to which workers could be exposed. No missed-dose correction is 

appropriate for this dosimetry system.

6.6.4

6.6.4.1 Angular Dependence

Geometry

The film dosimeters used at RFP experienced varying angular response. Dosimeters were not always 

exposed straight-on, resulting in varying responses with respect to actual worker exposure. There is 

insufficient data to identify an angular dependence correction to apply to any of the dosimeters. 

Because any correction would reduce the dose or, in the case of the Panasonic dosimeter, increase 

the dose only slightly, not including this correction factor is generally claimant-favorable.
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The film dosimeter experienced an apparent increase in dose when exposed from the edge because 

photons were able to expose the film under the filter, without passing through the filter. RFP has 

generated limited experimental exposure data that demonstrates this phenomenon qualitatively. 

Edge-on exposure with 60-keV photons indicated a factor of 4 over-response.

TLD dosimeters are likely to experience the same problem. No information on this issue in relation to 

the neutron film/photon TLD badge or the Harshaw TLD badge photon response has been found.

Quantitative information is available for the RFP Panasonic dosimeter (RFETS 2001). The dosimeter 

was tested in 1993 and 1996. For eight DOELAP exposure categories, element responses generally 

decreased as the angle increased. For angles of incidence from -30° to +30°, the ratio of reported 

dose to delivered dose ranged from 0.88 to 0.99 for photons. 

6.6.4.2 Exposure Geometry

Exposure geometry is common to all types of radiation exposure, as addressed in Section 6.5.4.

6.6.5

The External Dose Reconstruction Guideline (NIOSH 2002) describes methods for quantification of 

laboratory uncertainty associated with reading film and TLDs. These methods provide a statistical 

treatment of the variability associated with reading dosimeters in the laboratory.

Uncertainty

6.6.5.1 Film

Rocky Flats used film to measure photons between 1951 and 1968. The DuPont 558 film packet 

(containing the sensitive 508 film) was used in 1964 (Owen 1964). The 508 film was the successor to 

502 film and both films have a useful range from 10 - 20 mR up to approximately 10 R (NRC 1989). It 

is not clear if RFP used 502 film or when it changed to 508 film. Hanford changed to 508 film in 1960 

(Wilson, Fix, Baumgartner, and Nichols 1990). Both film types have approximately the same reading 

uncertainty.

The method in the External Dose Reconstruction Implementation Guideline (NIOSH 2002) was used 

to determine the laboratory uncertainty (upper 95% confidence dose) for film readings. This method 

is detailed in Film Badge Dosimetry in Atmospheric Nuclear Tests (NRC 1989). The discussion of this 

method cites sensitivity parameters for 502 film. A spreadsheet was developed using these 

parameters to match the example provided and then modified with RFP-specific parameters. RFP 

densitometer readings appear to be a factor of 1,000 greater than those illustrated in the example. It 

is believed that these are "milli" density units. Results are consistent with the example when this 

assumption is used. Review of dosimetry worksheets indicate that density readings were recorded to 

the nearest whole number; therefore, the densitometer reading uncertainty is assumed to be ± 0.5 

density unit. Reviewing RFP density-to-dose conversion charts from 1966 to 1968, it was possible to 

determine film sensitivity. Using this parameter, the upper 95% confidence doses for various 

dosimeter readings were calculated. 

Although the uncertainty is reduced at higher exposures, the NRC methodology recognizes that 

additional uncertainty contributed by variability in calibration, film processing, and reading the 

calibration curve, prevents the upper 95% confidence dose from falling below 120% of the reported 

exposure. This limitation has been applied here and effects the estimate of the upper 95% confidence 

dose above 27 mR. These are listed in Table 6-10. 
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6.6.5.2 Thermoluminescent Dosimeter

TLDs provided improved photon dosimetry. The uncertainty 

associated with this type of dosimeter is estimated for the early 

years of use, and then measured when DOELAP performance 

testing began.

6.6.5.2.1 Loose Chip Thermoluminescent Dosimeters

Harshaw TLD chips were used to measure photon dose at RFP 

from 1969 through 1982. These chips were carried in a dosimeter 

holder, but were removed to be read, thus the term "loose chips." 

A calculation was performed to estimate the uncertainty associated 

with reading the photon dose from these dosimeters.

Little information has been located describing the variability of chip response when these chips were 

in service. A chip sorting procedure was used to remove chips from service that responded outside 

set criteria (Link and Pennock 1983). The procedure was to expose the chips to a 1,000-mrem dose 

equivalent using a 137Cs source. The chips were then read and any that responded outside the mean 

± 0.165 * mean were removed from use. Assuming that the chip response was normally distributed 

such that 5% of the chips were removed during the sorting process (a claimant-favorable 

assumption), the upper and lower cutoffs would have to be 1.96 standard deviations of the existing 

chip population. Thus the initial chip population standard deviation is (0.165 * 1,000)/1.96 = 84.18 or 

8.4%. Performing a Monte Carlo simulation on this distribution, removal of the chips outside the 

criteria results in a truncated normal distribution with a standard deviation of 7.4%. The higher 8.4% 

was selected as a parameter describing the chip population routinely used to measure dose (a 

claimant-favorable assumption). Using the Simplified Dosimetry Uncertainty calculation 

recommended by NIOSH (2002), and assuming the critical level 

(Lc) is the LOD estimated in Section 6.3.1 of this TBD, Table 6-11

lists the upper 95% confidence dose.

6.6.5.2.2 Panasonic Thermoluminescent Dosimeter

Table 6-12 summarizes the uncertainty associated with DOELAPaccredited Panasonic dosimeter dose readings. These values 

were calculated using the TLD uncertainty methodology detailed 

in Section 2.1.1.3.2 of NIOSH (2002). This method recognizes 

that elements of the uncertainty are quantified in the dosimetry 

program documentation available for a DOELAP-accredited 

program. The standard deviation for null readings is from a study 

performed at RFP (RFETS 2001), and the relative standard 

deviation at high readings is the standard deviation of the 

DOELAP performance test results (RFETS 2001; Stanford 1990). 

The reasonable worst-case value was selected to provide a 

claimant-favorable result. No data are available for the initial algorithm implementation of the 

Panasonic dosimetry system (1983 to 1989). Similar performance to that after 1990 is assumed.

Table 6-11. Uncertainty for 

loose chip TLD photon dose at 

RFP.

Dose

Upper 95% confidence 

dose (mrem) 1969–1982

1 21

2 22

5 25

10 30

20 40

50 72

100 126

200 239

500 585

1,000 1,166

2,000 2,330

Table 6-10. Uncertainty for 

photon film dose at RFP.

Dose 

(mR)

Upper 95% confidence 

photon dose (mR)

1 6

2 7

5 10

10 15

20 25

50 60

100 120

200 240

500 600

1,000 1,200

2,000 2,400
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Table 6-12. Uncertainty for DOELAP-accredited TLD photon dose at RFP. 

Dose (mrem)

Upper 95% confidence dose (mrem)

Panasonic dosimeter DOELAP-accredited Panasonic dosimeter

1983–1989 1990–1998 1999–present

1 1 1 1

2 2 2 2

5 6a 6b 6c

10 12 12 12

20 25 25 24

50 61 61 59

100 123 123 118

200 245 245 235

500 614 614 588

1,000 1,227 1,227 1,176

2,000 2,455 2,455 2,353

a. 1.23 multiplier for any dose greater than 2 mrem.

b. 1.23 multiplier for any dose greater than 2 mrem.

c. 1.18 multiplier for any dose greater than 2 mrem.

6.7 NEUTRON DOSE

6.7.1

The measured neutron dose must be divided into energy groups consistent with the dose conversion 

factors provided in Appendix B of NIOSH (2002). These energy groups and the associated radiation 

weighting factors from International Commission on Radiological Protection (ICRP) Publication 60 

(ICRP 1990) are:

Energy Groups

• < 0.01 MeV (wt=5)

• 0.01–0.10 MeV (wt=10)

• 0.10–2.0 MeV (wt=20)

• 2.0–20 MeV (wt=10)

• > 20 MeV (wt=5).

The analysis in this TBD is based on neutron spectra measured at RFP (Brackenbush et al. 1989).

6.7.1.1 Exposure Spectra

In August and September 1988, PNL provided technical assistance to RFP related to neutron and 

photon dose measurements (Brackenbush et al. 1989). This activity performed multisphere neutron 

measurements in representative high-neutron dose situations. The measurements included 

production locations, mockup situations in which plutonium parts were in a glovebox where 

measurements could be performed, and waste storage locations. Neutron shielding was in place, 

similar to that experienced by workers in that area. Relatively long (several-day) measurements were 

required to acquire sufficient dose to achieve accurate results.

The neutron spectra were determined from the multisphere measurements and presented in the PNL 

report. Dose rate was derived from neutron flux density information, flux-to-dose conversion factors 

from National Council on Radiation Protection and Measurements (NCRP) Report 38 (NCRP 1971). 

No neutron flux was identified for energies greater than 20 MeV. For this TBD, the dose rate 

information was divided into energy groups as required for NIOSH dose reconstruction. Table 6-13 

lists this information.
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Table 6-13. Neutron dose measurements divided into energy groups. 

Location

Dose rate

rem/hr

Avg. energy

MeV

Portion of dose from neutron energy range

< 10 

keV

10–100 

keV

0.10–2 

MeV

2–20 

MeV

>20 

MeV

Building 771 fluorinator line 6.07E-04 0.33 0.090 0.028 0.678 0.204 0.000

Building 771 Tank 554 4.65E-03 0.91 0.025 0.014 0.600 0.361 0.000

Building 776 molten salt glovebox 1.71E-03 0.45 0.038 0.023 0.840 0.099 0.000

Building 776 molten salt storage vault 8.84E-03 0.39 0.085 0.015 0.711 0.189 0.000

Building 776 drum storage 2.46E-02 0.63 0.027 0.034 0.689 0.250 0.000

Building 707 high dose pit 7.35E-04 0.006 0.006 0.437 0.552 0.000

Building 707 low dose pit 2.88E-04 0.015 0.009 0.758 0.218 0.000

Building 707 oxide can 1.43E-03 0.85 0.018 0.019 0.676 0.286 0.000

Building 707 plutonium ingot 1.98E-03 1.00 0.014 0.002 0.791 0.193 0.000

Mean 0.035 0.017 0.687 0.261

std. dev. 0.031 0.010 0.117 0.130

6.7.1.2 Reported Dose to Energy Groups

This information does not show a clear pattern. Therefore, it is appropriate to apportion dose based 

on the mean breakdown listed in Table 6-13. Table 6-14 lists the default values selected for dose 

reconstruction.

Table 6-14. Default neutron energy distribution. 

Neutron energy 

intervals

Fraction of dose 

(NCRP 38)

Dose multiplier 

(ICRP 60) Dose multipliera

<10 keV 0.035 2.40 0.0851

10 - 100 keV 0.017 2.06 0.0342

0.1 - 2.0 MeV 0.687 1.98 1.36

2.0 - 20.0 MeV 0.261 2.50 0.654

>20 MeV 0.00 -- 0.00

a. Multiply the reported dose by these factors to determine the ICRP 60 neutron dose for 

each neutron energy interval

The doses and fractions discussed above are based on quality factors published in NCRP (1971). 

NIOSH (2002) indicates the use of radiation weighting factors from ICRP Publication 60 (ICRP 1990). 

To perform this correction, the neutron energy deposition values (rad) for each energy were multiplied 

by the ICRP radiation weighting factor to determine the corrected dose equivalent. These values 

were totaled for each neutron energy interval used in this dose reconstruction and compared with the 

value determined previously using quality factors from NCRP (1971). A multiplier, determined for 

each neutron energy interval, is listed in column 3 of Table 6-14. The fraction of the dose [using 

NCRP (1971) quality factors] and the dose multiplier [using ICRP (1990) radiation weighting factors] 

were combined to determine a dose multiplier. This value is listed in column 4 of Table 6-14. The 

neutron dose reported in the claimant's dose record is multiplied by these factors to determine the 

ICRP (1990) neutron dose for each neutron energy interval.

6.7.2

6.7.2.1 Dosimeter-Specific Quality Factor Conversion

Calibration Factor

The correction factor to convert from NCRP (1971) quality factors used in the neutron spectra 

measurements and the ICRP (1990) radiation weighting factors are discussed in Section 6.7.1.2 and 

listed in Table 6-14.
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6.7.2.2 Reported-Dose-to-Organ-Dose Conversion Factor Units

RFP initially used neutron track plates. These dosimetry elements were provided and processed by 

LANL. At this point, little is known about their calibration, but it is assumed that ambient dose 

equivalent is appropriate.

Neutron film was initially calibrated with an apparently unmoderated polonium-beryllium (PoBe) 

source. In 1962 or 1963, this was changed to plutonium fluoride (PuF4) (Mann and Boss 1963). The 

dose rate assigned to the source was the total dose for an energy of 1.4 MeV, found in NBS 

Handbook 63 (NBS). A set of polyethylene moderators was constructed. The spectra from these 

moderated sources compared well with work area spectra measured with a precision Long counter

and a series of paraffin moderators fitted over the counter (Mann and Boss 1963). Ambient dose 

equivalent is appropriate for this dosimeter.

Harshaw TLDs at Rocky Flats were initially calibrated using a 210-gram PuF4 source built at RFP and 

calibrated at the LANL standard pile, which was established as a neutron flux standard (Mann and 

Boss 1963). A set of polyethylene moderators was constructed to provide various degrees of 

moderation. The bare PuF4 source dose rate was calculated using neutron spectra from an unknown 

reference document and quality factors published in DOE Orders (Falk 1975). The dose rates for the 

moderated spectra were measured with currently available neutron dose rate instrumentation. The 

PuF4 source was placed in storage in about 1975 and replaced with a commercially manufactured and 

calibrated 252Cf source. The calculation of the dose rate used a published spectrum and dose rate 

(AEC 1968). A set of polyethylene moderators was manufactured for this source and ambient dose 

equivalent rates were determined in a manner similar to that used for the PuF4 source. Thus, the 

ambient dose equivalent [H*(10)] is the appropriate unit for this period.

Panasonic TLDs at RFP were calibrated with DOELAP exposure standards. In the early 1980s, PNL 

was developing the neutron standards that were used for the original DOELAP performance testing. 

The development of all Panasonic dosimeter algorithms used at RFP was based primarily on these 

exposures. Therefore, the deep dose equivalent [Hp,slab(10)] is appropriate.

Table 6-15 summarizes the dose units to use for organ dose conversion factors.

Table 6-15. Neutron dose units for use with organ dose conversion factors. 

Year Year Year Year Year Year

1951 H*(10) 1961 H*(10) 1971 H*(10) 1981 H*(10) 1991 Hp,slab(10) 2001 Hp,slab(10)

1952 H*(10) 1962 H*(10) 1972 H*(10) 1982 H*(10) 1992 Hp,slab(10) 2002 Hp,slab(10)

1953 H*(10) 1963 H*(10) 1973 H*(10) 1983 Hp,slab(10) 1993 Hp,slab(10) 2003 Hp,slab(10)

1954 H*(10) 1964 H*(10) 1974 H*(10) 1984 Hp,slab(10) 1994 Hp,slab(10)

1955 H*(10) 1965 H*(10) 1975 H*(10) 1985 Hp,slab(10) 1995 Hp,slab(10)

1956 H*(10) 1966 H*(10) 1976 H*(10) 1986 Hp,slab(10) 1996 Hp,slab(10)

1957 H*(10) 1967 H*(10) 1977 H*(10) 1987 Hp,slab(10) 1997 Hp,slab(10)

1958 H*(10) 1968 H*(10) 1978 H*(10) 1988 Hp,slab(10) 1998 Hp,slab(10)

1959 H*(10) 1969 H*(10) 1979 H*(10) 1989 Hp,slab(10) 1999 Hp,slab(10)

1960 H*(10) 1970 H*(10) 1980 H*(10) 1990 Hp,slab(10) 2000 Hp,slab(10)

6.7.3

6.7.3.1 Limit of Detection

Missed Dose

LANL processed neutron track plates for RFP from 1951 through 1956. Little is known about the 

performance of this system. A claimant-favorable assumption is that the minimum detectable dose is 
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 33 of 68

similar to that experienced by RFP with NTA film (see below). The LOD is conservatively (claimantfavorably) assumed to be 400 mrem.

In 1957, RFP switched to Nuclear Track Type A (NTA) film that was processed and read by a 

subcontractor. Little is known about this processing period, so again an LOD of 400 mrem is 

assumed.

Beginning in July 1958, RFP processed NTA film at the site. The NDRP has assembled a processing 

history (NDRP 2003), summarized in Table 6-16. Based on a background (blank) reading of 16 tracks 

per 10 mm2

, reported by Mann and Boss (1963) for 1962, LODs were calculated based on the most 

conservative calibration factor.

Table 6-16. RFP neutron film track counting detail. 

Date Determined positive

Calibration

(mrem/track/mm2) LOD

1959 >2x blank 40 128 mrem

1960 >2x blank 40 128 mrem

1961 >1.5x blank 40 96 mrem

1962 >blank+1.65*sqrt(blank) 40 or 100 369 mrem

1963 >blank+1.65*sqrt(blank) 100 369 mrem

1964 >2x blank 100 or 70 320 mrem

1965 >2 x blank or all 70 or 40 224 mrem

1966 All 110 --

Mann and Boss (1963) determined that a typical background film for 2 weeks had 16 tracks/10 mm2. 

Using three times the standard deviation of the background and a 10-mrem/track calibration factor, 

the minimum detectable dose is 120 mrem. 

Based on the LOD, the most claimant-favorable value was selected for each year. Mann and Boss 

(1963) estimates were used for years when LODs were not used or not known.

In 1971, RFP started using an albedo neutron TLD. Documentation of the research performed to 

develop this dosimeter (Falk 1971) indicates a practical lower neutron dose limit of 10 to 20 mrem in 

the presence of a photon dose as high as 100 mrem. The upper limit of this estimate was selected as 

the LOD for this dosimeter.

In 1983, the Panasonic UD-809 dosimeter was introduced at RFP to measure neutrons. Data are not 

available on the LOD for this dosimeter system. Because the hardware is the same as that used in 

1990, it was assumed to be similar to performance of the system at that time. The assumed LOD is 

32 mrem.

In 1990, an algorithm update was incorporated in the Panasonic dosimetry system (Stanford 1990). 

The documentation cites a minimum detectable neutron dose of 15 to 32 mrem for a moderated 252Cf 

source.

In 1993, an algorithm update was incorporated in the Panasonic dosimetry system (RFETS 2001) to 

include element reading uncertainty controls to reduce large dose fluctuations at low dose. This 

update, which has passed DOELAP performance testing, results in a stated minimum response for 

routine RFP neutron fields of approximately 15 mrem. Table 6-17 includes this value.
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Table 6-17. Neutron limit of detection for RFP dosimeters. 

Year LOD Year LOD Year LOD Year LOD Year LOD Year LOD

1951 400mrem 1961 120mrem 1971 20mrem 1981 20mrem 1991 32mrem 2001 15mrem

1952 400mrem 1962 369mrem 1972 20mrem 1982 20mrem 1992 32mrem 2002 15mrem

1953 400mrem 1963 369mrem 1973 20mrem 1983 32mrem 1993 15mrem 2003 15mrem

1954 400mrem 1964 320mrem 1974 20mrem 1984 32mrem 1994 15mrem

1955 400mrem 1965 224mrem 1975 20mrem 1985 32mrem 1995 15mrem

1956 400mrem 1966 120mrem 1976 20mrem 1986 32mrem 1996 15mrem

1957 400mrem 1967 120mrem 1977 20mrem 1987 32mrem 1997 15mrem

1958 400mrem 1968 120mrem 1978 20mrem 1988 32mrem 1998 15mrem

1959 128mrem 1969 120mrem 1979 20mrem 1989 32mrem 1999 15mrem

1960 128mrem 1970 120mrem 1980 20mrem 1990 32mrem 2000 15mrem

6.7.3.2 Number of Zero Readings

Section 6.5.1 of this TBD discusses the number of zero readings.

6.7.3.3 Unmonitored Energy Range

NTA film is a poor detector of neutron energies below 500 to 800 keV (Griffith, Hankins, Gammage, 

and Tommasino 1979; Wilson, Fix, Baumgartner, and Nichols 1990). Before 1963, RFP appears to 

have calibrated neutron film with a variety of unmoderated neutron sources. RFP recognized that 

dosimetry results were not consistent with instrument measurements and initiated a project in 1962 to 

improve neutron film dosimeter calibration (Mann and Boss 1963).

Before 1963, neutron dose resulting from neutrons below approximately 800 keV probably was not 

detected. To determine how much dose was potentially missed, the neutron measurements 

performed in RFP work areas (Brackenbush et al. 1989) were corrected for ICRP (1990) radiation 

weighting factors, and the fraction of the dose resulting from neutrons less than 800 keV was 

determined. Table 6-18 lists these values.

Table 6-18. Potential missed neutron dose for early film 

dosimeters at RFP. 

ICRP 60 below

Location rem/hr 800 keV

Building 771 Fluorinator Line 1.13E-03 52%

Building 776 Molten Salt Glovebox 3.25E-03 60%

Building 776 Molten Salt Storage Vault 1.67E-02 29%

Building 776 Drum Storage 4.46E-02 57%

Building 707 High Dose Pit 1.18E-03 22%

Building 707 Low Dose Pit 5.26E-04 29%

Building 707 Oxide Can 2.53E-03 47%

Building 707 Plutonium Ingot 3.70E-03 16%

There appears to be no distinct pattern in these data. It is appropriate to take a claimant-favorable 

approach and select the largest value of 56%. Thus, the total neutron dose from RFP measurements 

prior to 1964 (1951 through 1963) should be multiplied by 1.79 before applying the multiplicative 

factors from Table 6-14.

In 1962, RFP began a project to refine neutron dosimeter calibration to match the neutron spectra 

experienced in the production areas more accurately. Mann and Boss (1963) documented an effort to 

develop a calibrated PuF4 source with various moderators. The spectra from the moderator 
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 35 of 68

configurations of this source were compared with neutron spectra measurements taken in the 

plutonium production areas with a precision long counter and a series of paraffin moderators. This 

resulted in dosimeter calibrations that more accurately matched the exposure spectra. No missed 

dose correction is required for RFP neutron film dosimeters after 1963.

The RFP TLD neutron dosimeter systems (Harshaw and Panasonic) were calibrated using variously 

moderated spectra. There is no need for missed neutron dose corrections. After 1990, the 

Panasonic TLD system was DOELAP-accredited, supporting the decision to forego a missed neutron 

dose correction.

6.7.3.4 Neutron Dose Reconstruction Project

In the early 1990s, RFP addressed the issue of neutron film processing. It had been long recognized 

that, in the dosimetry laboratory, human factors associated with reading large numbers of neutron 

films under a microscope can significantly affect neutron dosimetry results. A pilot study in 1994 

reevaluated neutron doses for selected plutonium workers. This study indicated that the original 

evaluations of films might have contained significant errors, and that the resulting neutron doses might 

be significantly higher or lower than the doses actually received. The Neutron Dose Reconstruction 

Project was initiated to provide current and former radiation workers and assessment of the neutron 

exposure received in the plutonium production facilities. The scope of this project will be for the years 

from 1952 through 1970.

The NDRP will reread neutron films (where available) with appropriate quality controls, and will 

reevaluate neutron doses. In addition, it will determine notional neutron doses for plutonium workers 

with missing or unreadable films and for non-neutron-monitored plutonium workers.

To provide a claimant-favorable correction until NDRP data are available, it is appropriate to use the 

neutron correction ratio reported in Report of Epidemiologic Analyses Performed for Rocky Flats 

Production Workers Employed Between 1952-1989 (Ruttenber et al. 2003). These analyses used a 

combination of workplace instrument measurements and Harshaw and Panasonic TLD results to 

estimate "correction ratios" for total penetrating doses. This ratio provides an estimate for the "total 

penetrating dose" (gamma + neutron), which provides an initial correction for the identified bias in the 

neutron film reading. This correction should be applied to personnel who worked in the noted neutron 

buildings from 1951 - 1967. When the NDRP is complete, a more accurate neutron dose will be 

available for each worker who was monitored for neutrons. An updated ratio can be generated from 

these data for use with unmonitored workers in this work area. Table 6-19 lists the current correction 

ratios.

Table 6-19. RFP correction ratios for identified neutron 

film reading deficiencies. 

Building Mean Standard deviation

771 1.99 0.92

Other neutron buildingsa 1.13 0.82

a. 123, 774, 776, 777, 779, 886, 991, and others if record 

suggests neutron monitoring

6.7.4

6.7.4.1 Angular Dependence

Geometry

Film neutron dosimeters generally experience a slight increase with exposure from angles other than 

front-on. It is claimant-favorable to ignore this slight difference.
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The Panasonic dosimeter was evaluated for angular dependence. For neutron fields, the element 

responses generally decreased as the angle between the incident radiation and the plane 

perpendicular to the TLD increased. For angles of incidence from -30° to +30°, the ratio of reported 

dose to delivered dose ranged from 0.87 to 1.00 for neutrons. The slight variability does not warrant a 

specific correction.

6.7.4.2 Exposure Geometry

The worker exposure geometry for neutron dose is similar to that for photons, and is discussed in 

Section 6.5.4.

6.7.5

6.7.5.1 Film

Uncertainty

The NDRP is evaluating film uncertainty. Until that project is complete, these data will not be 

available. Until then, a neutron "correction ratio" has been applied (Section 6.7.3.4). The standard 

deviation reported for this correction ratio (Table 6-19) reflects the variability in the data used to derive 

this correction ratio. This value should be used until better data is available.

6.7.5.2 Thermoluminescent Dosimeter

Falk (1971) describes the Harshaw TLD system development. That document describes field tests in 

RFP plutonium production facilities. The results indicate "... that the survey dose range is consistently 

within 20 percent of the TLD neutron dose indication." Thus, for the Harshaw neutron dosimeter, a 

95% confidence interval of 20% has been selected. Thus, the standard deviation is 20% ÷ 1.96 = 

10.2%. The methodology for TLD uncertainty in NIOSH (2002) is used.

The initial Panasonic TLD algorithm was evaluated during development (Rocky Flats 1983). The

results of the evaluation state: "A large number of (relative) biases in the range -0.100 to +0.100 and 

the paucity of the (relative) biases outside the ±0.200 range indicate a robust, effective algorithm." 

Based on this evaluation, the maximum relative bias of 0.206 was selected as the 95% confidence 

interval and a standard deviation of 0.206 ÷ 1.96 = 10.5% is determined.

The Stanford (1990) algorithm upgrade was tested during DOELAP performance testing. The 

unmoderated neutron dose category resulted in a standard deviation of 0.072. This value was 

selected to determine the upper 95% confidence dose during this period.

The 1993 algorithm upgrade (RFETS 2001) was tested during 1999 DOELAP performance testing. 

The unmoderated neutron dose category resulted in a standard deviation of 0.065. A mixture of 

neutrons with both low- and high-energy photons was tested. The worst-case standard deviation was 

0.090. This value was selected to determine the upper 95% confidence dose for all dates after the 

implementation of this algorithm.

Table 6-20 lists the uncertainties for these dosimetry systems.

6.8 ELECTRON DOSE

Beta radiation fields are usually the dominant external radiation hazard in facilities requiring contact 

work with unshielded forms of uranium. This was the case at RFP for enriched and depleted uranium 
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 37 of 68

Table 6-20. Uncertainty for TLD neutron dose measurements at RFP. 

Dose 

(mrem)

Upper 95% Confidence Dose (mrem)

Harshaw TLD dosimeter Panasonic dosimeter DOELAP accredited Panasonic dosimeter

1971–1982 1983–1990 1991–1992 1993–present

1 1.25 1.25 1.21 1.23

2 2.43 2.44 2.32 2.38

5 6.01a 6.04b 5.72c 5.89d

10 12 12 11 12

20 24 24 23 24

50 60 60 57 59

100 120 121 114 118

200 240 241 228 235

500 600 603 571 588

1,000 1,200 1,206 1,141 1,176

2,000 2,400 2,412 2,282 2,353

a. 1.20 multiplier for 5 mrem or greater.

b. 1.21 multiplier for 5 mrem or greater.

c. 1.14 multiplier for 5 mrem or greater.

d. 1.18 multiplier for 5 mrem or greater.

work. Figure 6-6 shows estimated beta dose rates from a semi-infinite slab of uranium metal at 

various enrichment levels. For uranium enrichments up to 30%, the beta radiation field is dominated 

by contributions from 238U decay products. Thus, for depleted uranium, one is dealing essentially with 

2.29-MeV (Emax) beta particles from 234mPa, the most energetic contributor to the beta exposure.

Figure 6-6. Estimated beta dose rate from uranium metal at various 

enrichment levels (DOE 2001).

Processes that separate and sometimes concentrate beta-emitting uranium daughters are not 

uncommon in DOE uranium facilities. The uranium foundry operations at RFP produced "skull" that 

resulted in high beta dose rates. Surface beta dose rates on the order of 1 to 20 rad per hour have 

been observed at some DOE facilities. Exposure control is complicated by the fact that considerable 

contact work takes place in facilities that process uranium metal. At RFP, large foundry ingots were 

generally handled by lifting devices, but machined uranium parts were handled with gloved hands. 

RFP did have problems with elevated beta dose rates from contamination on leather gloves worn 

during foundry operations.
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6.8.1

6.8.1.1 Exposure Spectra

Energy Groups

The beta spectrum from uranium is highly dependent on the quantity of daughter products in the 

uranium, which is, in turn, dependent on the enrichment level of the uranium. Depleted uranium 

daughter products grow into secular equilibrium relatively quickly (~30 days) and can be 

conservatively assumed to be present at these levels. Figure 6-7 shows the relative dose rate with 

respect to energy. Depleted uranium would be similar to the natural uranium used for this experiment.

Figure 6-7. Shallow dose rate from natural uranium slab (DOE 2001). 

6.8.1.2 Reported Dose to Energy Groups

NIOSH (2002) indicates that because extensive research in the areas of dosimeter wear location, 

electron energy spectra, and film response is required to convert dose readings to shallow dose 

properly, "... the exposure is assumed to be equal to the shallow dose (Hp(0.07)), recognizing that 

this is an overestimation of the true shallow dose. Until further research is conducted, this assumption 

is considered reasonable." This assumption is claimant-favorable for RFP.

6.8.2

6.8.2.1 Reported-Dose-to-Organ-Dose Conversion Factor Units

Calibration Factor

Film dosimeters at RFP appear to have been calibrated in contact with uranium slabs. Although RFP 

documents in the 1960s report the dose rate from a uranium slab as 240 mR, mrad, and mrem per 

hour at the surface, it is assumed these were inaccurate references to a dose rate in mrad/hr. The 
Effective Date: 01/20/2004 Revision No. 00 Document No. ORAUT-TKBS-0011-6 Page 39 of 68

radiation weighting factor for electrons at all energies is 1 (ICRP 1990), thus, reported beta doses are 

equivalent to rem. This value is used directly for the Hp(0.07) dose.

6.8.3

6.8.3.1 Limit of Detection

Missed Dose

Beta dosimetry at RFP used open-window film calibrated to a uranium slab. It is believed that the 

beta minimum detectable dose would have been similar to that for photons. Thus 40 mrem was 

selected as the minimum detectable beta dose appropriate for the film dosimetry period.

Harshaw TLDs were used for beta detection starting in 1969. It is believed that the minimum 

detectable dose would have been similar to that for photons. Wilson, Fix, Baumgartner, and Nichols 

(1990) determined that the Hanford TLD system had a 20-mR minimum detectable dose. RFP TLD 

measurements were similar. A minimum detectable dose of 20 mrem beta (shallow) is appropriate for 

RFP during this period.

The algorithm initially developed for Panasonic TLD system implementation in 1983 contains a 

constraint to ensure the shallow dose equivalent does not fall below 0.90 times the deep dose from 

photons. Thus, the shallow minimum detectable dose is 0.90 times that determined for deep dose 

photons (20 mrem) for this system. The minimum detectable shallow dose for this period was 

determined to be 20 x 0.90 = 18 mrem (shallow), as indicated in Table 6-21.

Table 6-21. Beta limit of detection for RFP dosimeters. 

Year LOD Year LOD Year LOD Year LOD Year LOD Year LOD

1951 40mrem 1961 40mrem 1971 20mrem 1981 20mrem 1991 80mrem 2001 15mrem

1952 40mrem 1962 40mrem 1972 20mrem 1982 20mrem 1992 80mrem 2002 15mrem

1953 40mrem 1963 40mrem 1973 20mrem 1983 18 mrem 1993 15mrem 2003 15mrem

1954 40mrem 1964 40mrem 1974 20mrem 1984 18 mrem 1994 15mrem

1955 40mrem 1965 40mrem 1975 20mrem 1985 18 mrem 1995 15mrem

1956 40mrem 1966 40mrem 1976 20mrem 1986 18 mrem 1996 15mrem

1957 40mrem 1967 40mrem 1977 20mrem 1987 18 mrem 1997 15mrem

1958 40mrem 1968 40mrem 1978 20mrem 1988 18 mrem 1998 15mrem

1959 40mrem 1969 20mrem 1979 20mrem 1989 18 mrem 1999 15mrem

1960 40mrem 1970 20mrem 1980 20mrem 1990 80mrem 2000 15mrem

In 1990, the algorithm for the Panasonic Dosimetry system was improved. The documentation for this 

algorithm cites "... a minimum reportable beta dose of 25% of the total shallow dose (photon plus 

beta) or approximately 80 mrem for DU ..." (Stanford 1990). It also states that, "... beta doses 

delivered to radiation workers in the plant environments will likely be overestimated." A claimantfavorable decision to use the maximum 80-mrem (shallow) minimum detectable dose was made. This 

is a significant increase in the minimum detectable beta dose. Review of the algorithm documentation 

(Stanford 1990) indicates that a constraint was incorporated into the algorithm, to report beta dose 

only if the net open-window (element 1) value was over 25 mR (137Cs exposure response). This net 

element reading is determined by subtracting the expected photon response and the expected 

neutron response for that element, as determined by the relationship with other dosimeter elements in 

the badge. These calculations would result in significant variability in the net element 1 response and 

it is assumed that the constraint was included to reduce the variability in the resulting beta dose 

estimate to an acceptable level. The result is a significantly higher minimum detectable dose, 

however. This constraint appears to have been removed in the next algorithm update.
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In 1993, an algorithm update was incorporated in the Panasonic dosimetry system (RFETS 2001) to 

include element-reading uncertainty controls to reduce large dose fluctuations at low dose. This 

update has passed DOELAP performance testing and results in a stated minimum response for 

routine RFP beta fields of approximately 15 mrem (shallow) (RFETS 1993). This value has been 

incorporated in Table 6-21.

6.8.3.2 Number of Zero Readings

The number of zero readings is determined as discussed in Section 6.5.5 of this document.

6.8.3.3 Unmonitored Energy Range

Film and TLD are believed to respond to beta energies of dosimetric importance. Thus, there is no 

unmonitored energy range for which a correction factor is appropriate.

6.8.4

6.8.4.1 Angular Dependence

Geometry

The sensitive dosimeter elements are mounted in a dosimetry badge. The assembled badge displays 

severe angular dependence to beta exposure. Fortunately, in most cases a worker’s normal 

movements will tend to average out some of this dependence (DOE 2001).

For beta fields, the element responses of the Panasonic dosimeter generally decreased as the angle 

between the incident radiation and the plane perpendicular to the TLD increased from 0 degrees. For 

angles of incidence from -30° to +30°, the ratio of reported dose to delivered dose ranged from 0.36 to 

0.59 for beta particles. Based on DOE (2001), no angular correction factor is proposed.

6.8.4.2 Exposure Geometry

Exposure geometry is not a significant issue with skin exposure. Nonpenetrating radiations do not 

significantly expose tissue in other than a straight-on exposure. 

6.8.5

The method in NIOSH (2002) was used to determine the uncertainty (upper 95% confidence dose) for 

film readings. This method is based on a statistical discussion in Film Badge Dosimetry in 

Atmospheric Nuclear Tests (NRC 1989).

Uncertainty

6.8.5.1 Film

RFP used film to measure beta dose between 1951 and 1968. This is the same film described in 

Sections 6.3.1 and 6.5.1 of this TBD. A similar uncertainty estimation methodology was used; 

developing a spreadsheet matched the illustration given in NRC (1989). Review of RFP density-tobeta dose conversion charts from 1966 to 1968 determined film sensitivity. A saturation density for 

502 film was assumed. Using this approach, the upper 95% confidence doses for various beta doses 

were calculated. A limit of 120% was applied as discussed in Section 6.6.5.1. This limit effects the 

upper 95% confidence dose at 77 mrad and above. Table 6-22 presents these upper 95% confidence 

doses.
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6.8.5.2 Thermoluminescent Dosimeter

TLDs provided improved beta dosimetry. Harshaw TLD chips 

were used to measure beta dose at RFP from 1969 through 1982. 

The uncertainty associated with this type of dosimeter was 

estimated for the early years of use, and then measured when 

DOELAP performance testing was initiated.

6.8.5.2.1 Loose Chip Thermoluminescent Dosimeters

Harshaw TLD chips were used to measure beta dose in parallel 

with photon dose. As with the photon TLD uncertainty, the chip 

sorting procedure was used to estimate the standard error 

associated with the beta TLD measurements. Using the 

Simplified Dosimetry Uncertainty calculation recommended by NIOSH (2002), and assuming the 

critical level (Lc) is the beta LOD estimated in Section 6.8.3.1 of this TBD, Table 6-23 lists the upper 

95% confidence dose.

6.8.5.2.2 Panasonic TLD Dosimeter

Table 6-24 lists the uncertainty associated with DOELAPaccredited Panasonic dosimeter dose readings. These values 

were calculated using the TLD uncertainty methodology 

described in Section 2.1.1.3.2 of NIOSH (2002). This method 

recognizes that the elements of the uncertainty are quantified in 

the dosimetry program documentation available for a DOELAPaccredited program. The standard deviation for null readings is 

from a study performed at RFP (RFETS 2001), and the relative 

standard deviation at high readings is the standard deviation of

DOELAP performance test results (RFETS 2001; Stanford 

1990). The reasonable worst-case value was selected to 

provide a claimant-favorable result.

Table 6-24. Uncertainty for DOELAP-accredited TLD beta dose at RFP.

Dose (mrem)

Upper 95% confidence dose (mrem)

Panasonic dosimeter DOELAP-accredited Panasonic dosimeter

1983–1989 1990–1998 1999–present

1 1.19 1.19 1.19

2 2.29 2.29 2.28

5 6a 6b 6c

10 11 11 11

20 22 22 22

50 56 56 56

100 112 112 112

200 224 224 223

500 561 561 558

1,000 1,122 1,122 1,116

2,000 2,243 2,243 2,231

a. 1.12 multiplier for any dose greater than 2 mrem.

b. 1.12 multiplier for any dose greater than 2 mrem.

c. 1.12 multiplier for any dose greater than 2 mrem.

Table 6-22. Uncertainty for 

beta film readings at RFP.

Dose 

(mrad)

Upper 95% confidence 

dose (mrad)

1 17

2 18

5 21

10 26

20 36

50 66

100 120

200 240

500 600

1,000 1,200

2,000 2,400

Table 6-23. Uncertainty for loose 

chip TLD beta dose at RFP.

Dose 

(mrad)

Upper 95% confidence 

dose (mrad) 1969–1982

1 21

2 22

5 25

10 30

20 40

50 72

100 126

200 239

500 585

1,000 1,166

2,000 2,330
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6.8.6

Skin contamination incidents are routinely reported at RFP on a Contamination Report. Information 

generally indicates the location of the skin contamination and the initial count. The area of the 

contamination might not be available and should be estimated in the manner described in the Section 

2.3.3 of NIOSH (2002).

Skin Contamination

Depleted uranium is the RFP production material that would result in the greatest skin dose from 

surface contamination. The daughter products potentially contained in the material would result in a 

beta exposure to the skin.

The contamination report will not indicate the length of time that the contamination was present on the 

skin. A claimant-favorable assumption is that the contamination was present for 4 hours. This is a 

reasonable worst-case assumption that, for example, the individual received contamination at the 

beginning of the shift, did not take a midmorning break, and discovered the contamination upon 

monitoring when leaving the production area at lunch. Once the contamination is discovered, initial 

decontamination would be performed in the production building, resulting in removal of most of the 

contamination. Prior to 1970, self-monitoring equipment was not readily available, and a claimantfavorable assumption of 8 hours is appropriate.

Contamination values in the contamination report are typically in counts per minute (cpm or c/m). 

RFP typically used a G-M "pancake" probe to perform uranium surveys. This instrument typically has 

a 33.3% ± 1% (cpm/dpm) efficiency for depleted uranium.

Depleted uranium consists of 99.8% by weight 238U. Table 6-25 lists the other isotopes.

It is client-favorable to assume that the depleted 

uranium is 1 year old. This allows for ingrowth of 

daughter products to achieve secular equilibrium. A 

decay calculation using MicroShield 5.03 (Grove 

Engineering 1998) was performed. Table 6-26 lists 

the full suite of decay isotopes. 

Dose calculation might utilize software such as 

VARSKIN (recommended in NIOSH 2002) or other 

appropriate means.

6.9 UNMONITORED INDIVIDUALS

6.9.1

In the early 1950s only groups expected to receive doses greater than 10% of the Radiation 

Protection Guideline (called the "threshold dose" at RFP) would receive dosimeters. During this 

period the Radiation Protection Guideline was 3 rem per quarter. Thus, the missed dose estimate for 

unbadged individuals working in radiologically controlled areas would be one-half of 10% of 3 rem per 

quarter, or 600 mrem per year. A lognormal distribution should be assumed, with the upper 95% dose 

estimate for these individuals 10% of the Radiation Protection Guideline or 1.2 rem per year (NIOSH 

2002). 

In Production Areas

Table 6-25. Depleted uranium at RFP (DOE 

1980).

Mixture

Isotope Ci/g(mix)

Alpha Beta nCi/g(mix)

Th 231 4.90E-09 4.9

Th 234 3.40E-07 340

U 234 3.70E-08 37

U 235 4.90E-09 4.9

U 238 3.40E-07 340

Total 3.82E-07 3.45E-07 726.8
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6.9.2

After about 1990, many individuals at RFP who did not work in 

radiological areas were not badged. The site Radiological Protection 

organization determined that these individuals were unlikely to 

exceed 100-mrem occupational exposure in a calendar year. 

Outside Production Areas

For individuals working outside the radiologically controlled areas, 

environmental exposure would be a better estimate of their exposure 

(see Section 4.0, Environmental Dose, of this Site Profile).

6.10 EXTREMITY DOSIMETRY

Extremity dosimeters were used at RFP. Between 1951 and 1970, 

the site used an Oak Ridge-designed film dosimeter similar to that 

used for the body badge. The extremity dosimeter was worn on the 

wrist. It was modified with a brass filter similar to the body badge. 

Little performance information is available on this badge, but it 

probably performed similarly to the body badge of that period.

In 1971, RFP switched to an in-house-designed wrist dosimeter 

containing four Harshaw chips. This badge contained two TLD-600 

and two TLD-700 chips, enabling neutron and photon dose 

determination. Uranium workers received an open-window (thin 

Mylar) version.

In 1991, RFP switched to a Panasonic model UD-813AS11 (custom 

design) dosimeter in a plastic wrist holder. This dosimeter contains 

two 6

Li-borate elements and two 7Li elements, enabling neutron dose 

measurement. Two of the elements are under a thin open window for 

beta and low-energy photon dose measurements. The dosimeter, which has undergone DOELAP 

performance testing, is documented in RFETS (2000). 

RFP never used finger rings on a routine basis, but estimated the hand dose using the forearm dose 

measured by the wrist badge and the application of a hand-to-wrist ratio.

Many RFP workers did not receive extremity (wrist) dosimeters. In such cases, the wrist (forearm) 

dose was assigned as the measured skin (shallow) dose, and the hand dose was assigned the same 

value. If an extremity dosimeter was worn and the value was less than the skin dose measured by 

the body badge, the assumption was made that the extremity dosimeter was not worn and the skin 

dose was assigned as the wrist dose. If the extremity dosimeter did measure a dose greater than the 

body badge, the extremity measurement was assigned to the wrist and a hand-to-wrist ratio was used 

to estimate the dose to the hand. Several studies over the years determined the hand-to-wrist ratio; 

different values were used for different buildings (major job categories). Details on the ratios used are 

not available.

Additional information on these dosimeters will be required for dose reconstruction for shallow dose to 

the extremity, if necessary. 

Table 6-26. One-year-old 

depleted uranium.

Nuclide curies becquerels

Ac-227 1.63E-15 6.04E-05

* Bi-210 6.69E-19 2.47E-08

Bi-211 1.28E-15 4.75E-05

* Bi-214 7.00E-17 2.59E-06

Fr-223 2.25E-17 8.34E-07

Pa-231 1.04E-13 3.84E-03

* Pa-234 5.44E-10 2.01E+01

Pa-234m 3.40E-07 1.26E+04

* Pb-210 7.10E-19 2.63E-08

Pb-211 1.28E-15 4.75E-05

* Pb-214 7.00E-17 2.59E-06

Po-210 2.16E-19 7.99E-09

Po-211 3.50E-18 1.30E-07

Po-214 6.99E-17 2.59E-06

Po-215 1.28E-15 4.75E-05

Po-218 7.00E-17 2.59E-06

Ra-223 1.28E-15 4.75E-05

Ra-226 7.21E-17 2.67E-06

Rn-219 1.28E-15 4.75E-05

Rn-222 7.00E-17 2.59E-06

Th-227 1.39E-15 5.15E-05

Th-230 3.33E-13 1.23E-02

* Th-231 4.90E-09 1.81E+02

* Th-234 3.40E-07 1.26E+04

Tl-207 1.28E-15 4.74E-05

U-234 3.70E-08 1.37E+03

U-235 4.90E-09 1.81E+02

U-238 3.40E-07 1.26E+04

per gram of DU

*Indicates isotope is included in 

VARSKIN Mod 2.
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NIOSH (National Institute for Occupational Safety and Health), 2002, External Dose Reconstruction 

Implementation Guide, OCAS-IG-001, Rev. 1, Cincinnati, Ohio.

NRC (National Research Council), 1989, Film Badge Dosimetry in Atmospheric Nuclear Tests, 

National Academy Press, Washington D.C.

ORAU (Oak Ridge Associated Universities), 2003, Technical Basis Document for the Savannah River 

Site, To Be Used for Dose Reconstructions, ORAUT-TKBS-0003, Revision No. 1.

Owen, J. B., 1964, Handling and Processing Dosimeter Film at Rocky Flats Division. 

Putzier, E. A., 1982, The Past 30 Years at Rocky Flats Plant, Rockwell International Energy Systems 

Group, Rocky Flats Plant, Golden, Colorado.

RFETS (Rocky Flats Environmental Technology Site), 1993, Basis and Effects of the Inclusion of 

Minimum Detectable Dose Calculations in the Latest Revision of the Personnel Dose 

Algorithm on Personnel Doses at Rocky Flats Plant. 

RFETS (Rocky Flats Environmental Technology Site), 2000, External Dosimetry Technical Basis 

Document - Extremity Dosimetry, ED-TBM-05.

RFETS (Rocky Flats Environmental Technology Site), 2001, External Dosimetry Technical Basis 

Document - Whole Body Dosimetry, ED-TBM-04, Rev. 2.

Rockwell International, 1985, Radiation Exposure to Rockwell Employees at the Rocky Flats Plant, 

Annual Report -- Year 1984, Radiation Dosimetry Section of Environmental & Occupational 

Health Branch.

Rocky Flats, 1983, Algorithm for Panasonic 802 and 809 Dosimeters for the Rocky Flats Dosimetry 

Badge, Rock Flats Plant.

Ruttenber, A. J., M. Schonbeck, S. Brown, T. Wells, D. McClure, J. McCrea, D. Popken, J. Martyny, 

2003, Report of Epidemiologic Analyses Performed for Rocky Flats Production Workers 

Employed Between 1952-1989, Department of Preventive Medicine and Biometrics, University 

of Colorado Health Sciences Center and Colorado Department of Public Health and 

Environment.

Stanford, N., 1990, Whole Body TLD Dose Algorithm for Panasonic 802/809 TLD Pair, Rocky Flats 

Plant External Dosimetry Program.
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Watson, J. E., J. L. Wood, W. G. Tankersley, and C. M. West, 1994, "Estimation of Radiation Doses 

for Workers without Monitoring Data for Retrospective Epidemiologic Studies," Health Physics, 

Vol. 67, No. 4, pp. 402-405.

Wilson, R. H., J. J. Fix, W. V. Baumgartner, and L. L. Nichols. 1990. Description and Evaluation of 

the Hanford Personnel Dosimeter Program From 1944 Through 1989. PNL-7447. Pacific 

Northwest Laboratory, Richland, WA.
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GLOSSARY

Atomic Energy Commission (AEC)

Original agency established for nuclear weapons and power production; a predecessor to the 

U.S. Department of Energy.

beta dose 

A designation (i.e., beta) on some external dose records referring to the dose from lessenergetic beta, X-ray, and/or gamma radiation (see open window, or shallow dose). 

beta radiation

Radiation consisting of charged particles of very small mass (i.e., the electron) emitted 

spontaneously from the nuclei of certain radioactive elements. Most (if not all) of the direct 

fission products emit beta radiation. Physically, the beta particle is identical to an electron 

moving at high velocity.

deep absorbed dose

The absorbed dose at the depth of 1.0 cm in a material of specified geometry and 

composition.

deep dose equivalent (Hd) 

The dose equivalent at the respective depth of 1.0 cm in tissue.

dose equivalent (H)

The product of the absorbed dose (D), the quality factor (Q), and any other modifying factors. 

The special unit is the rem. When D is expressed in Gy, H is in Sieverts (Sv). 

(1 Sv = 100 rem.)

dosimeter

A device used to measure the quantity of radiation received. A holder with radiation-absorbing 

elements (filters) and an insert with radiation-sensitive elements packaged to provide a record 

of absorbed dose or dose equivalent received by an individual. (See albedo dosimeter, film 

dosimeter, neutron film dosimeter, thermoluminescent dosimeter.)

dosimetry

The science of assessing absorbed dose, dose equivalent, effective dose equivalent, etc., 

from external or internal sources of radiation. 

dosimetry system

A system used to assess dose equivalent from external radiation to the whole body, skin, or 

extremities. This includes the fabrication, assignment, and processing of dosimeters as well 

as interpretation and documentation of the results.

exchange period (frequency) 

Period (weekly, biweekly, monthly, quarterly, etc.) for routine exchange of dosimeters.

exposure

As used in the technical sense, exposure refers to a measure expressed in roentgens (R) of 

the ionization produced by photons (i.e., gamma and X-rays) in air. 
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extremity

That portion of the arm extending from and including the elbow through the fingertips, and that 

portion of the leg extending from and including the knee and patella through the tips of the 

toes.

field calibration

Dosimeter calibration based on radiation types, intensities, and energies in the work 

environment.

film

In general, a "film packet" that contains one or more pieces of film in a light-tight wrapping. 

When developed, the film has an image caused by radiation that can be measured using an 

optical densitometer.

film density

See optical density.

film dosimeter

A small packet of film within a holder that attaches to a wearer.

fission

The splitting of a heavy atomic nucleus, accompanied by the release of energy.

fissionable

Material capable of undergoing fission.

gamma rays

Electromagnetic radiation (photons) originating in atomic nuclei and accompanying many 

nuclear reactions (e.g., fission, radioactive decay, and neutron capture). Physically, gamma 

rays are identical to X-rays of high energy, the only essential difference being that X-rays do 

not originate in the nucleus. 

ionizing radiation

Electromagnetic or particulate radiation capable of producing charged particles through 

interactions with matter.

isotope

Elements having the same atomic number but different atomic weights; identical chemically 

but having different physical and nuclear properties.

neutron

A basic particle that is electrically neutral weighing nearly the same as the hydrogen atom.

neutron film dosimeter

A film dosimeter that contains a Neutron Track Emulsion, type A, film packet.

Nuclear Track Emulsion, Type A (NTA)

A film that is sensitive to fast neutrons. The developed image has tracks caused by neutrons 

that can be seen by using an appropriate imaging capability such as oil immersion and a 

1000X-power microscope or a projection capability.
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open window (OW)

Designation on film dosimeter reports that implies the use of little (i.e., only security credential) 

shielding. Commonly used to label the film response corresponding to the open-window area. 

operating area

Designation of major onsite operational work areas.

optical density

The quantitative measurement of photographic blackening; density defined as D = Log10 (Io/I).

personal dose equivalent Hp(d)

Represents the dose equivalent in soft tissue below a specified point on the body at an 

appropriate depth (d). The depths selected for personnel dosimetry are 0.07 mm and 10 mm 

for the skin and body, respectively. These are noted as Hp(0.07) and Hp(10), respectively. 

photon

A unit or "particle" of electromagnetic radiation consisting of X- or gamma rays. 

photon - X-ray

Electromagnetic radiation of energies between 10 keV and 100 keV whose source can be an 

X-ray machine or radioisotope.

pit

Nuclear weapon core, made of fissionable material.

quality factor, Q

A modifying factor used to derive dose equivalent from absorbed dose.

radiation

Alpha, beta, neutron, and photon radiation. 

radioactivity

The spontaneous emission of radiation, generally alpha or beta particles, gamma rays, and 

neutrons from unstable nuclei.

radionuclide

A radioactive isotope of an element, distinguished by atomic number, atomic weight, and 

energy state.

rem

A unit of dose equivalent equal to the product of the number of rad absorbed and the quality 

factor.

Roentgen (R or r)

A unit of exposure to gamma (or X-ray) radiation. It is defined precisely as the quantity of 

gamma (or X-) rays that will produce a total charge of 2.58 x 10-4 coulomb in 1 kg of dry air. 

An exposure of 1 R is approximately equivalent to an absorbed dose of 1 rad in soft tissue for 

higher (~>100 keV) energy photons.
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shallow absorbed dose (Ds) 

The absorbed dose at a depth of 0.007 cm in a material of specified geometry and 

composition.

shallow dose equivalent (Hs) 

Dose equivalent at a depth of 0.007 cm in tissue.

shielding

Any material or obstruction that absorbs (or attenuates) radiation and thus tends to protect 

personnel or materials from radiation.

silver shield(s)

The 1-mm thick shields covering the film packet in early personnel film dosimeters. 

skin dose

Absorbed dose at a tissue depth of 7 mg/cm2

. 

thermoluminescence

Property of a material that causes it to emit light as a result of being excited by heat.

thermoluminescent dosimeter (TLD)

A holder containing solid chips of material that when heated will release stored energy as light. 

The measurement of this light provides a measurement of absorbed dose. 

whole-body dose

Commonly defined as the absorbed dose at a tissue depth of 1.0 cm (1000 mg/cm2

); however, 

also used to refer to the recorded dose.

X-ray

Ionizing electromagnetic radiation of external nuclear origin.
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ATTACHMENT A

EXAMPLE EXTERNAL DOSIMETRY RECORD DOCUMENTS
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Figure A-1. Occupational Dose Report reviewed 6-4-02, page 1. 
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Figure A-2. Occupational Dose Report reviewed 6-4-02, page 2. 
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Figure A-3. Dosimetry History by Individual dated 3-10-03, page 1. 
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Figure A-4. Dosimetry History by Individual dated 3-10-03, page 2. 
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Figure A-5. Dosimetry History by Individual dated 3-10-03, page 3. 
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Figure A-6. Health Physics Yearly External Exposure Activity Run, 1953 through 1958. 
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Figure A-7. Health Physics Yearly External Exposure Run, 1962. 
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Figure A-8. Health Physics Yearly External Exposure Activity Run, 1964. 
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Figure A-9. External Dosimetry Detail, 1981 through 1983. 
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Figure A-10. Health Physics External Radiation Exposure Report, 1967. 
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Figure A-11. Radiation Dosimetry Individual Lifetime Report dated 6-4-02. 
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Figure A-12. Radiation Health Records System – TLD Data. 
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Figure A-13. Radiation Dosimetry Termination Report dated 9-17-96, page 1. 
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Figure A-14. Radiation Dosimetry Termination Report dated 9-17-96, page 2. 
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Figure A-15. External Dosimetry Detail, 1985 and 1986. 
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ATTACHMENT B

MAJOR JOB CATEGORIES

Chemical Operators 

Primary job duties included highly enriched uranium (HEU; B881 and plutonium (B771/371) metal 

reprocessing using dissolution, fluorination, calcine, and other wet chemistry methods to purify metal 

in preparation for foundry casting operations. Molten salt processing (B776) was an exceptionally 

high neutron process. Other typical job duties included waste treatment (B774/374) for waste 

solutions generated across RFP.

Metallurgical Operators

Primary job duties included casting (B881), rolling and pressing HEU (B883), Pu (B776/ 707), and DU 

(B444/447 and 883). Exposures tended to be less than those to Chemical Operators. Machinists, 

Assemblers, Material Analysts and Welders had similar exposures. 

Non-Destructive Testing (NDT) Technicians had similar, but probably lower exposures because work 

was often done on completed pits that inherently shielded fissile materials. Experimental Operators 

had similar, but probably higher, exposures because they often worked with prototype systems or 

processes that lacked shielding and other radiological controls as the regular production processes.

Maintenance Workers

Typical trades (i.e., machinists, pipefitters, welders, carpenters, painters, electricians) had varied 

exposures because they often did more intrusive work on contaminated systems than production 

personnel. Examples of intrusive work include repairing leaks on process lines (pipefitters), refractory 

replacement in casting and heat treat furnaces (carpenters), repair of mechanical systems 

(machinists) and repair of instruments and controllers inside gloveboxes and other systems 

(electricians), painting over contamination (painters).

Support Personnel

This category includes Clerk Packers, Metrology Technicians, Janitors, and Handymen, who worked 

in process areas but did little or no hands-on work with radioactive materials. Exposures would be 

incidental to working in rooms with process equipment (metallurgical and chemical operations).

Analytical Laboratory Technicians

These individuals worked primarily in B559 (Pu samples) or B881 (HEU/DU samples) and probably 

had lower exposures than operators performing hands-on work with significantly higher material 

quantities.

Site Support Personnel

Stationary Operating Engineers (SOEs, also known as Boiler Vent Operators, BVOs), Security 

Guards, Shift Managers and Configuration Control Authority personnel performed little if any hands-on 

work, but had routine access to process areas. SOEs monitored exhaust systems, waste tanks, and 

process waste lines. Exposures would be incidental to working in rooms with process equipment 

(metallurgical and chemical operations).

Radiation Control Technicians

Radiation Control Technicians (RCTs) probably had exposures from supporting production chemical 

and metallurgical processes. Some exposures probably occurred during decontamination activities, 

surveys of contaminated areas, upset conditions. They generally performed no hands-on work, but 

generally worked side-by-side with production operators.
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Decontamination and Decommissioning Workers

Decontamination and decommissioning (D&D) work includes draining actinide systems, 

decontamination, size reduction and removal of contaminated equipment, gloveboxes, piping, 

ductwork, exhaust systems, waste packaging of removed equipment, low-level and TRU wastes. 

Work is often in high (>2,000 dpm removable) airborne contamination areas with Derived Air 

Concentration (DAC) levels from >0.1 to 106. Personal Protection Equipment (PPE) includes Air 

Purifying Respirator, Powered Air Purifying Respirator, or PremAir supplied air. There were some 

high exposures due to direct work with highly radioactive equipment and contamination events.