• SH

EI

LD • ALARA • NEUTRON • A

E

D

E • ELECTRON • TEDE • INTERNAL • CEDE • GAMMA • BETA • SHIELD • ALARA • NEUTRON • AEDE • ELECTRON • TEDE • INTERNAL • CEDE • GAMM

2003 Report

DOE OCCUPATIONAL

RADIATION

EXPOSURE

DOE/EH-0688

DEPARTMENT OF ENERGY

UNITED STATES OF AMERICA

http://www.eh.doe.gov/rems/
This report has been reproduced directly from the best available copy.

Available to DOE and DOE Contractors from the Office of Scientific and

Technical Information, P.O. Box 62, Oak Ridge, TN 37831; prices available from

(865) 576-8401.

Available to the public from the U.S. Department of Commerce, Technology

Administration, National Technical Information Service, Springfield, VA 22161,

(703) 487-4650.

Printed with soy ink on recycled paper
2003 Report

DOE OCCUPATIONAL

RADIATION

EXPOSURE

DEPARTMENT OF ENERGY

UNITED STATES OF AMERIC

A

DOE/EH-0688

• BETA • SH

EI

LD • ALARA • NEUTRO

N • A

E

D

E • ELECTRON • TEDE • INTERNAL • CEDE • GAMMA • BETA • SHIELD • ALARA • NEUTRON • AEDE • ELECTRON • TEDE • INTERNAL • CEDE • GAMMA 

The U.S. Department of Energy

Assistant Secretary for Environment, Safety and Health

Office of Corporate Performance Assessment
2003 Report Foreword iii

John S. Shaw

Acting Assistant Secretary

Environment, Safety and Health

Foreword Foreword

The goal of the U.S. Department of Energy (DOE) is to conduct it’s operations, including radiological 

Foreword

operations, to ensure the safety and health of all DOE employees, contractors, and subcontractors. The 

DOE strives to maintain radiation exposures to its workers below administrative control levels and 

DOE limits and to further reduce these exposures to levels that are “As Low As Reasonably Achievable” 

(ALARA). 

The Rule 10 CFR 835 702 (a) and (b) requires annual individual radiation exposure records for all monitored DOE employees, contractors, subcontractors and members of the public to be reported to the 

Radiation Exposure Monitoring Systems (REMS) Repository according to procedures provided in DOE 

Order 231.1A and DOE M 231.1-1A (Chapter 3 and Appendix G). The 2003 DOE Occupational Radiation 

Exposure Report provides a summary and analysis of the occupational radiation exposure received by 

individuals associated with DOE activities and annually reported to REMS. 

A brief discussion of the analysis of the occupational exposure data at DOE for 2003 is provided in the 

Executive Summary

This report is intended to be a valuable tool for managing radiological safety programs and resources. The 

process of data collection, analysis, and report generation is streamlined to provide a current assessment 

of the performance of the Department with respect to radiological operations. The key to the timeliness 

of this report is the correct and prompt reporting of employee radiation exposure data by the sites. Your 

feedback and comments are important to us to make this report meet your needs.

Frank B. Russo

Deputy Assistant Secretary

Office of Corporate Performance Assessment
iv This page intentionally left blank. DOE Occupational Radiation Exposure
2003 Report Table of Contents v

Conents

FOREWORD ...............................................................................................................................................................................iii

EXECUTIVE SUMMARY.......................................................................................................................................................xi

SECTION 1 — INTRODUCTION

 1.1 Report Organization .............................................................................................................................. 1-1

 1.2 Report Availability ................................................................................................................................. 1-1

SECTION 2 — STANDARDS AND REQUIREMENTS

 2.1 Radiation Protection Requirements .................................................................................................... 2-1

 2.1.1 Monitoring Requirements .......................................................................................................... 2-2

 2.1.1.1 External Monitoring ........................................................................................................... 2-2

 2.1.1.2 Internal Monitoring ............................................................................................................ 2-2

 2.2 Radiation Dose Limits ........................................................................................................................... 2-3

 2.2.1 Administrative Control Levels.................................................................................................... 2-4

 2.2.2 ALARA Principle ......................................................................................................................... 2-4

 2.3 Reporting Requirements....................................................................................................................... 2-5

 2.4 Change in Internal Dose Methodology ............................................................................................... 2-5

SECTION 3 — OCCUPATIONAL RADIATION DOSE AT DOE

 3.1 Analysis of the Data ............................................................................................................................... 3-1

 3.2 Analysis of Aggregate Data.................................................................................................................... 3-1

 3.2.1 Number of Records for Monitored Individuals........................................................................ 3-1

 3.2.2 Number of Records for Individuals with Measurable Dose.................................................... 3-1

 3.2.3 Collective Dose............................................................................................................................ 3-2

 3.2.4 Average Measurable Dose .......................................................................................................... 3-5

 3.2.5 Dose Distribution ........................................................................................................................ 3-6

 3.3 Analysis of Individual Dose Data ...................................................................................................... 3-10

 3.3.1 Doses in Excess of DOE Limits ................................................................................................ 3-10

 3.3.2 Doses in Excess of Administrative Control Level ................................................................... 3-11

 3.3.3 Internal Depositions of Radioactive Material......................................................................... 3-11

 3.4 Analysis of Site Data ............................................................................................................................ 3-15

 3.4.1 Collective TEDE by Site and Operations/Field Offices.......................................................... 3-15

 3.4.2 Dose by Labor Category ........................................................................................................... 3-17

 3.4.3 Dose by Facility Type................................................................................................................. 3-18

 3.4.4 Radiation Protection Occurrence Reports............................................................................. 3-19

 3.4.4.1 Radiation Exposure Occurrences .............................................................................. 3-20

 3.4.4.2 Personnel Contamination Occurrences..................................................................... 3-21

 3.4.4.3 Occurrence Cause ....................................................................................................... 3-24

 3.5 Activities Significantly Contributing to Collective Dose in 2003..................................................... 3-25

 3.6 Transient Individuals ........................................................................................................................... 3-28

 3.7 Historical Data Collection................................................................................................................... 3-31

Table of Contents

Table of Contents
vi DOE Occupational Radiation Exposure 

SECTION 4 — ALARA ACTIVITIES AT DOE

 4.1 ALARA Activities at the Hanford Site..................................................................................................................................................4-1

 4.1.1 Fluor Hanford, Inc. Implements ALARA During Open Air Demolition of 233S Plutonium Concentration Facility ........4-1

 4.1.2 Bechtel Hanford, Inc. Uses Rust Doctor® Fixative to Reduce Airborne Radioactivity During Demolition

 of 1304N Emergency Dump Tank...........................................................................................................................................4-6

 4.1.3 CH2M HILL Hanford Group, Inc. Saved 6.5 Person-Rem Using Cast Antimonial Lead Shielding During

 Sluice and Retrieval of Saltcake from S-112 Tank.................................................................................................................4-8

 4.2 ALARA Activities at the West Valley Demonstration Project.............................................................................................................4-9

 4.2.1 Project Description of PPC-S...................................................................................................................................................4-9

 4.2.1.1 Radiological Concerns..................................................................................................................................................4-9

 4.2.1.2 Implementation of Innovative ALARA Techniques...................................................................................................4-10

 4.2.1.3 Estimated Dose Avoided..............................................................................................................................................4-11

 4.2.2 Project Description of HECs and Radiological Concerns .................................................................................................4-12

 4.2.2.1 Implementation of Innovative ALARA Techniques...................................................................................................4-12

 4.3 ALARA Activities at Brookhaven National Laboratory ...................................................................................................................4-14

 4.3.1 Removal of the Brookhaven Graphite Research Reactor Below Ground Duct Outlet Air Filters..................................4-14

 4.3.1.1 History and Description of the Brookhaven Graphite Research Reactor .............................................................4-14

 4.3.1.2 Radiological Condition of the BGD Outlet Air Filters .............................................................................................4-15

 4.3.1.3 Filter Removal Method ...............................................................................................................................................4-15

 4.3.1.4 Collective Dose............................................................................................................................................................4-17

 4.4 Hanford ALARA Center of Excellence .............................................................................................................................................4-18

 4.5 Submitting ALARA Success Stories for Future Annual Reports.....................................................................................................4-18

 4.6 Lessons Learned Process Improvement Team.................................................................................................................................4-19

SECTION 5 — CONCLUSIONS

 5.1 Conclusions...................................................................................................................................................................5-1

GLOSSARY ..................................................................................................................................................................................G-1

REFERENCES............................................................................................................................................................................... R-1

APPENDICES

 A DOE Reporting Sites and Reporting Codes...............................................................................................................A-1

 B Additional Data ............................................................................................................................................................ B-1

 C Facility Type Code Descriptions................................................................................................................................. C-1

 D Limitations of Data.......................................................................................................................................................D-1

 E Access to Radiation Exposure Information .............................................................................................................. E-1
2003 Report Table of Contents vii

LIST OF EXHIBITS

 Exhibit ES-1: Collective TEDE Dose (person-rem), 1999-2003 ........................................................................................... xi

 Exhibit ES-2: Average Measurable TEDE (rem), 1999-2003 ................................................................................................ xi

 Exhibit ES-3: Number of Individuals Exceeding 2 rem TEDE, 1999-2003 ........................................................................ xii

 Exhibit ES-4: Number of Individuals Exceeding 5 rem TEDE, 1999-2003 ........................................................................ xii

 Exhibit 2-1: DOE Dose Limits from 10 CFR 835 ...............................................................................................................2-3

 Exhibit 3-1: Monitoring of the DOE Workforce, 1999-2003 ..............................................................................................3-2

 Exhibit 3-2: Components of TEDE, 1999-2003...................................................................................................................3-3

 Exhibit 3-3: Average Measurable Neutron, DDE, and TEDE, 1999-2003..........................................................................3-5

 Exhibit 3-4: Distribution of Dose by Dose Range, 1999-2003 ..........................................................................................3-6

 Exhibit 3-5: Percentage of Collective Dose above Dose Values During 1999-2003.......................................................3-7

 Exhibit 3-6: Neutron Dose Distribution, 1999-2003 ..........................................................................................................3-8

 Exhibit 3-7: Extremity Dose Distribution, 1999-2003........................................................................................................3-9

 Exhibit 3-8: Number of Individuals Exceeding 5 Rem (TEDE), 1999-2003..................................................................3-10

 Exhibit 3-9: Doses in Excess of DOE Limits, 1999-2003 .................................................................................................3-10

 Exhibit 3-10: Number of Doses in Excess of the DOE 2 Rem ACL, 1999-2003...............................................................3-11

 Exhibit 3-11: Number of Internal Depositions, Collective CEDE, and Average Measurable CEDE (Graph),

 1999-2003.......................................................................................................................................................3-12

 Exhibit 3-12: Number of Internal Depositions, Collective CEDE, and Average Measurable CEDE 

 by Nuclides (Data), 2001-2003 ....................................................................................................................3-12

 Exhibit 3-13: Internal Dose Distribution from Intakes, 1999-2003 ..................................................................................3-13

 Exhibit 3-14: Distribution of Collective CEDE vs. Dose Value, 1999-2003.......................................................................3-14

 Exhibit 3-15: Collective TEDE by Site for 2001-2003 ........................................................................................................3-15

 Exhibit 3-16: Collective TEDE and Number of Individuals with Measurable TEDE by Site, 2001-2003 ......................3-16

 Exhibit 3-17: Number with Measurable Dose, Collective TEDE, and Average Measurable TEDE 

 by Labor Category, 2001-2003 ......................................................................................................................3-17

 Exhibit 3-18: Graph of Collective TEDE by Labor Category, 2001-2003..........................................................................3-17

 Exhibit 3-19: Graph of Collective TEDE by Facility Type, 2001-2003 ..............................................................................3-18

 Exhibit 3-20: Number with Measurable Dose, Collective TEDE, and Average Measurable TEDE

 by Facility Type, 2001-2003...........................................................................................................................3-18

 Exhibit 3-21: Criteria for Radiation Exposure and Personnel Contamination

 Occurrence Reporting .................................................................................................................................3-19

 Exhibit 3-22: Number of Radiation Exposure Occurrences, 1999-2003.........................................................................3-20

 Exhibit 3-23: Radiation Exposure Occurrences by Site, 1999-2003................................................................................3-21

 Exhibit 3-24: Number of Personnel Contamination Occurrences, 1999-2003...............................................................3-21

 Exhibit 3-25: Personnel Contaminations by Affected Area, 1999-2003 ..........................................................................3-22

 Exhibit 3-26: Number of Individuals Contaminated by Affected Area in 2003.............................................................3-22

 Exhibit 3-27: Personnel Contamination Occurrences by Site, 1999-2003......................................................................3-23

 Exhibit 3-28: Radiation Exposure Occurrences by Root Cause, 2001-2003 ..................................................................3-24

 Exhibit 3-29: Personnel Contamination Occurrences by Root Cause, 2001-2003 ........................................................3-24

 Exhibit 3-30: Activities Significantly Contributing to Collective TEDE in 2003 for Six Sites........................................3-25

 Exhibit 3-31: Dose Distribution of Transient Workers, 1999-2003....................................................................................3-29

 Exhibit 3-32: Individuals Monitored at More Than One Site (Transients) During the Year, 1999-2003........................3-30

 Exhibit 3-33: Collective and Average Measurable Dose to Transient Individuals, 1999-2003.......................................3-30

 Exhibit 3-34: Collective TEDE to Transient Workers by Site, 1999-2003 ..........................................................................3-31
viii DOE Occupational Radiation Exposure 

LIST OF EXHIBITS (continued)

 Exhibit 4-1: 233S Prior to Demolition....................................................................................................................................................4-1

 Exhibit 4-2: The Mechanical Shears Quickly Cut Up Reinforced Concrete Walls, Metal Sheet Walls,

 and Ventilation Ducting .....................................................................................................................................................4-2 

 Exhibit 4-3: Debris From the Shearing Operation is Scooped Up and Transported to the Environmental

 Restoration Disposal Facility .............................................................................................................................................4-3 

 Exhibit 4-4: Wall Saw is Mounted on the Installed Track. The Concrete Roof was Cut Into Four Sections and

 Removed First .....................................................................................................................................................................4-3 

 Exhibit 4-5: Once the Roof was Removed, the Contractor Began Removing Sections of Wall.......................................................4-3 

 Exhibit 4-6: A Closeup of the Wall-Mounted Saw as it Cuts Through the Wall of the Process Hood Portion

 of 233S Plutonium Concentration Facility .......................................................................................................................4-3

 Exhibit 4-7: Fog Cannon Operating During Shearing of the Low- and Medium-Risk Areas. Two Cannons were

 Staged to Provide Continuous Fogging During Shearing................................................................................................4-4

 Exhibit 4-8: The Mechanical Shear Also had a Fogger Attached. Water with Fixative Controls the Release of

 Airborne Radioactivity During Shearing Operations......................................................................................................4-4

 Exhibit 4-9: Gutters were Installed on the Interior of the Building Where the Wall Saw Cuts were to be Made to

 Collect Water and Debris During the Cutting Operation and Control Release of Airborne Radioactivity................4-5

 Exhibit 4-10: Inside Surface of the Tank. Rust Doctor® Turned the Red Rust to Black. The Coverage Is Apparent......................4-6

 Exhibit 4-11: The Spray Rig was a Counterweighted Arm About 28 Feet in Length Extending from the Center

 Shaft Toward the Wall of the Tank. Approximately 100 Gallons of Rust Doctor® were used to Fix the

 Contamination in the Tank. The Top of the Spray Rig Can be Seen Leaning Up Against the Wall in

 the Left of the Photo...........................................................................................................................................................4-7

 Exhibit 4-12: Nuclear Lead Company Antimonial-lead Shielding was Placed Over a Temporary Above-ground

 Radioactive Waste Transfer Line. This Line is Adjacent to Another Temporary Transfer Line that was

 Buried in a Trench and Covered with Steel Plates. The New Method Saved 6.5 Person-rem and

 Significant Labor Costs ......................................................................................................................................................4-8

 Exhibit 4-13: Removal of Slab Tank in PPC-S..........................................................................................................................................4-9

 Exhibit 4-14: Schematic Drawing of PPC-S ...........................................................................................................................................4-11

 Exhibit 4-15: Remote Packaging of Waste from the HECs...................................................................................................................4-12

 Exhibit 4-16: Automobile Rescue Tool Being Used to Cut Through Pipes and Rods.......................................................................4-13

 Exhibit 4-17: Brookhaven Graphite Research Reactor at Brookhaven National Laboratory ..........................................................4-14

 Exhibit 4-18: Filter Bank .........................................................................................................................................................................4-14

 Exhibit 4-19: Separator Inside Duct Service Building .........................................................................................................................4-15

 Exhibit 4-20: Application of Fixative .....................................................................................................................................................4-16

 Exhibit 4-21: Brokk Machine Loading Filter Element Into Hammer Mill..........................................................................................4-16

 Exhibit 4-22: Remote Video Display Terminal ......................................................................................................................................4-16
2003 Report Table of Contents ix

TABLE OF ACRONYMS

10 CFR 820 Title 10 Code of Federal Regulation Part 820 “Procedural Rules for DOE Nuclear Activities,” 

August 17, 1993 

10 CFR 835 Title 10 Code of Federal Regulation Part 835 “Occupational Radiation Protection,” 

December 14, 1993

10 CFR 835, Amendment Issued on November 4, 1998

ACL Administrative Control Level

AEDE Annual Effective Dose Equivalent

AEC Atomic Energy Commission

ALAP As Low As Practicable

ALARA As Low As Reasonably Achievable

ANL-E Argonne National Laboratory - East

ANL-W Argonne National Laboratory - West

ANSI American National Standards Institute

ANSI N13.30-1996 ANSI Note on Performance Criteria for Radioassay

BGD Below Ground Ducts

BGRR Brookhaven Graphite Research Reactor

BHI Bechtel Hanford, Inc.

BNFL British Nuclear Fuels Limited

BNL Brookhaven National Laboratory

CAP Corrective Action Plan

CDE Committed Dose Equivalent

CEDE Committed Effective Dose Equivalent

CEDR Comprehensive Epidemiologic Data Resource 

CPC Chemical Process Cell

D&D Decontamination and Decommissioning

DDE Deep Dose Equivalent

DOE Department of Energy

DOE HQ DOE Headquarters

DOE M 231.1-1 Manual for Environment, Safety and Health Reporting, September 10, 1995

DOE Notice 441.1 Radiological Protection for DOE Activities, September 29, 1995

DOE Order 5480.11 Radiation Protection for Occupational Workers, December 1988

DOE Order 5484.1 Environmental Protection, Safety and Health Protection Information 

Reporting Requirements, February 24, 1981, Change 7, October 17, 1990 

DOELAP DOE Laboratory Accreditation Program

DSB Duct Service Building

EDE Effective Dose Equivalent

EDT Emergency Dump Tank

EH-32 DOE Office of Corporate Performance Assessment

EPA Environmental Protection Agency

ERDA Energy Research and Development Administration

ES&H Environment, Safety and Health

ETTP East Tennessee Technology Park (formerly K-25)

EUO Enriched Uranium Operations 

Fermilab Fermi National Accelerator Laboratory

FHI Fluor Hanford, Inc.

FRT Filter Removal Tool

GPC General Purpose Cell

HEC Head End Cells

HLW High-Level Waste

ICRP International Commission on Radiological Protection

INEEL Idaho National Engineering and Environmental Laboratory

INTEC Idaho Nuclear Technology and Engineering Center

ISMS Integrated Safety Management System

LANL Los Alamos National Laboratory

LASO Los Alamos Site Office

LBNL Lawrence Berkeley National Laboratory

LDE Lens (of the eye) Dose Equivalent 
x DOE Occupational Radiation Exposure

LEHR Laboratory for Energy-related Health Research

LLNL Lawrence Livermore National Laboratory

LLPIT Lessons Learned Process Improvement Team

NCRP National Council on Radiation Protection and Measurements

NNSA National Nuclear Security Administration

NRC Nuclear Regulatory Commission

NREL National Renewable Energy Laboratory

NTS Nevada Test Site 

ORNL Oak Ridge National Laboratory

ORPS Occurrence Reporting and Processing System

OSHA Occupational Safety & Health Administration

OSL Optically Stimulated Luminescent Dosimeters

PBS Polymeric Barrier SystemTM

PFP Plutonium Finishing Plant

PGDP Paducah Gaseous Diffusion Plant

PMC Process Mechanical Cell

PNNL Pacific Northwest National Laboratory

PORTS Portsmouth Gaseous Diffusion Plant 

PP Pantex Plant

PPC Product Purification Cell

PPE Personal Protective Equipment

PR Product Receiver

PSEs Planned Special Exposures

RadCon Radiological Control Manual, June 1992

RCO Radiological Control Operations

RCS Radiological Control Standard

RCT Radiological Control Technician

REMS Radiation Exposure Monitoring System

RFETS Rocky Flats Environmental Technology Site

RW Radiological Workers

RWP Radiological Work Permit

SARF Supercompactor and Repackaging Facility

SCBA Self Contained Breathing Apparatus

SDE Shallow Dose Equivalent

SDE-ME Shallow Dose Equivalent to the Maximally Exposed Extremity

SDE-WB Shallow Dose Equivalent to the Skin of the Whole Body

SLAC Stanford Linear Accelerator Center

SNF Spent Nuclear Fuel

SNL Sandia National Laboratory

SOC Standard Occupational Classification

SRR Scrap Removal Room 

SRS Savannah River Site

TEDE Total Effective Dose Equivalent

TLD Thermoluminescent Dosimeters

TLND Thermoluminescent Neutron Dosimeter

TODE Total Organ Dose Equivalent

TRA Test Reactor Area

TRU Transuranic

UHP Ultra High Pressure

UMTRA Uranium Mill Tailings Remedial Action

UNSCEAR United Nations Scientific Committee on the Effects of Atomic Radiation

WAC Waste Acceptance Criteria

WIPP Waste Isolation Pilot Plant

WRAP Waste Receiving and Processing

WVDP West Valley Demonstration Project

WVNS West Valley Nuclear Services, Inc.

WVNSCO West Valley Nuclear Services Company

Y-12 Plant Y-12 National Security Complex

TABLE OF ACRONYMS (continued)
2003 Report Executive Summary xi

Summary

Executive Summary

Executive Summary

1999 2000 2001 2002 2003

0

400

800

1200

1600

Collective Dose (person-rem)

Year

1,295 1,267 1,232

1,360

1,445

1999 2000 2001 2002 2003

0.00

0.01

0.02

0.03

0.04

0.05

0.06

0.07

0.08

0.09

0.10

Average Measurable TEDE (rem)

Year

0.078 0.079

0.074

0.080 0.083

Exhibit ES-1:

Collective TEDE Dose (person-rem), 1999-2003.

Exhibit ES-2:

Average Measurable TEDE (rem), 1999-2003.

The U.S. Department of Energy (DOE) Office of Corporate Performance Assessment (EH-3) publishes the 

annual DOE Occupational Radiation Exposure Report. This report is intended to be a valuable tool for 

DOE and DOE contractor managers and workers in managing radiological safety programs and to assist 

them in prioritizing resources. We appreciate the efforts and contributions from the various stakeholders 

within and outside DOE to make the report most useful.

This report includes occupational radiation exposure information for all monitored DOE employees,

contractors, subcontractors, and members of the public. DOE is defined to include the National Nuclear 

Security Administration sites. The exposure information is analyzed in terms of aggregate data, dose to 

individuals, and dose by site. For the purposes of examining trends, data for the past 5 years are included 

in the analysis.

As shown in Exhibit ES-1, between years 2002 and 2003, the DOE collective Total Effective Dose 

Equivalent (TEDE) increased by 6% from 1,360 person-rem (13,600 person-mSv) to 1,445 person-rem 

(14,450 person-mSv) primarily due to increased doses at four of the six DOE sites with the highest 

radiation dose. The average dose to workers with measurable dose increased by 4% from 0.080 rem

(0.80 mSv) in 2002 to 0.083 rem (0.83 mSv) in 2003, as shown in Exhibit ES-2, because of the 10% increase 

in the collective dose and a 3% increase in the number of workers with measurable dose. The number 

of individuals with measurable dose increased from 17,051 in 2002 to 17,484 in 2003. The percentage 

of monitored individuals receiving measurable dose remained the same for the past 3 years at 17%. 

There were two exposures in excess of the DOE 5 rem (50 mSv) annual TEDE limit and one exposure in 

excess of the DOE Administrative Control Level (ACL) of 2 rem (20 mSv) TEDE. The two individuals who 

received exposures in excess of the 5 rem (50 mSv) annual TEDE limit resulted from plutonium intakes 

at Los Alamos National Laboratory (LANL) (8.170 rem and 10.197 rem).

Eighty percent of the collective TEDE for the DOE complex was accrued at six DOE sites in 2003. These

six sites are (in descending order of collective dose for 2003) Hanford, Savannah River, Los Alamos, 

Rocky Flats, Oak Ridge, and Idaho. Sites reporting under the category of weapons fabrication and testing 

account for the highest collective dose. Even though these sites are now primarily involved in nuclear 

materials stabilization and waste management, they report under this facility type. For the past 3 years,

technicians and production staff have received the highest collective dose of any specified labor category.
xii DOE Occupational Radiation Exposure 

1999 2000 2001 2002 2003

0

1

2

3

4

5

Year

Number of Individuals

Exceeding 2 Rem (TEDE)

1

3 3

1

3

1999 2000 2001 2002 2003

0

1

2

3

4

5

Year

Number of Individuals

Exceeding 5 Rem (TEDE)

0

1

3

0

2

Exhibit ES-3:

Number of Individuals Exceeding 2 Rem TEDE, 1999-2003.

Exhibit ES-4:

Number of Individuals Exceeding 5 Rem TEDE, 1999-2003.

The change in operational status of DOE facilities has had the largest impact on radiation exposure 

over the past 5 years due to the shift in mission from production to cleanup activities and the shutdown 

of certain facilities. For 2003, this resulted in an increase in the collective dose as sites handled more 

radioactive materials for processing, storage, or shipping. Reports submitted by four of the sites that 

experienced increases in the collective dose indicate that the increases were due to thermal stabilization 

and repackaging of plutonium-bearing materials, processing of spent fuels, and accelerated cleanup 

of tank farms at Hanford, resumption of processing of radioactive material, special programs, and 

accelerated facility closure and waste processing activities at Savannah River, and work activities 

associated with the building 9204-4 Cleanup Project and the TVA Off-Specification Fuel repackaging 

project at Oak Ridge, and the processing of more materials containing americium, an upgrade to the 

material storage vault, and the decontamination and decommissioning of the Omega West reactor at 

LANL. 

A statistical analysis was performed to determine the trend in collective dose over the past 5 years. The 

analysis indicates that while the collective TEDE, neutron, and extremity dose increased between 2002

to 2003, it does not represent a statistically significant change in the dose received by individual workers 

at DOE. Further tests revealed fewer individuals received neutron doses above 0.500 rem (5 mSv). This

may be the result of a positive change in accordance with ALARA (Note: keeping individual doses below 

a value alone is not necessarily ALARA).

Over the past 5 years, few occupational doses in excess of the 2 rem (20 mSv) ACL and 5 rem (50 mSv) 

TEDE regulatory limit have occurred at DOE facilities, as shown in Exhibits ES-3 and ES-4. All but two 

of the doses in excess of 2 rem (20 mSv) in the past 5 years were due entirely to internal dose. Three 

individuals received doses in excess of 2 rem (20 mSv) in 2003. Two of these individuals received a dose 

in excess of the 5 rem (50 mSv) TEDE limit in 2003 from plutonium intakes at LANL.

Note: Number of individuals exceeding 2 rem TEDE includes those 

individuals that also exceeded 5 rem TEDE shown in Exhibit ES-4.
2003 Report Executive Summary xiii

The collective internal dose (CEDE) increased by 38% between 2002 and 2003. Due to the increase 

in the collective CEDE and an increase in the number of internal depositions, the average measurable 

CEDE increased by 32% from 0.028 rem (0.28 mSv) in 2002 to a value of 0.037 rem (0.37 mSv) in 2003. 

The 38% increase in the collective CEDE in 2003 was due to a nearly four-fold increase in internal dose 

from plutonium. The main contributor to this increase was the two exposures in excess of 5 rem (50mSv) 

at LANL (see Section 3.3.1). Mound and Rocky Flats also reported increases in internal dose from 

plutonium from 2002 to 2003. 

A transient worker, or transient, is defined as an individual monitored at more than one DOE site in a 

year. The results of this analysis on the transient workforce at DOE show that the number of transient 

workers monitored has decreased by 6% from 2,848 in 2002 to 2,665 in 2003 and still remains a very low 

percentage (2.6%) of the monitored workforce at DOE. The collective dose for these transients increased 

by 54% from 36.5 person-rem (365 mSv) in 2002 to 56.1 person-rem (561 mSv) in 2003. As a result, the 

average measurable dose to transients increased by 41% from 0.066 rem (0.66 mSv) in 2002 to 0.093 rem 

(0.93 mSv) in 2003. The average measurable dose to transient workers is 0.093 rem (0.93 mSv) which 

is 12% higher than the 0.083 rem (0.83mSv) value for the overall DOE workforce in 2003. This is the 

first year since the transient data have been analyzed where the average measurable dose of transients 

exceeded the value for the overall DOE workforce.

To access this report and other information on occupational radiation exposure at DOE, visit the 

Radiation Exposure Monitoring System (REMS) web site at:

http://www.eh.doe.gov/rems/
xiv This page intentionally left blank. DOE Occupational Radiation Exposure
2003 Report Introduction 1-1

Introduction Section One 1

Introduction

Provides a description of the content and organization of this report.

Provides a discussion of the radiation protection and dose reporting requirements and their impacts on 

data interpretation. Additional information on dose calculation methodologies, personnel monitoring 

methods and reporting thresholds, regulatory dose limits, and ALARA is included.

Presents the occupational radiation dose data from monitored individuals at DOE facilities for 2003. The 

data are analyzed to show trends over the past 5 years.

Includes examples of successful ALARA projects within the DOE complex. 

Presents conclusions based on the analysis contained in this report.

Lists reporting codes and organizations, a detailed breakdown of the data analyzed in this report, 

limitations of the data, and ways to access the REMS data.

Section One

Section Two

Section Three

Section Four

Section Five

Appendices

http://www.eh.doe.gov/rems/

Ms. Nirmala Rao

DOE REMS Project Manager

EH-32, 270 Corporate Square Building

U.S. Department of Energy

1000 Independence Avenue, SW

Washington, D.C. 20585-0270

E-mail: nimi.rao@hq.doe.gov

The U.S. Department of Energy (DOE) Occupational 

Radiation Exposure Report, 2003 reports 

occupational radiation exposures incurred by 

individuals at DOE facilities during the calendar 

year 2003. This report includes occupational 

radiation exposure information for all DOE 

employees, contractors, subcontractors, and 

members of the public. The 99 DOE organizations 

submitting radiation exposure reports for 2003 

have been grouped into 27 geographic sites across 

the complex (see Appendix Exhibit B-1c). This 

information is analyzed and trended over time 

to provide a measure of DOE’s performance in 

protecting its workers from radiation.

1.1 Report Organization

This report is organized into the five sections and 

appendices listed below. Supporting technical 

information, tables of data, and additional items 

identified by users as useful are provided in the 

appendices.

1.2 Report Availability

Requests for additional copies of this report, 

access to the data files, or individual dose records 

used to compile this report should be directed to: 

A discussion of the various methods of accessing 

DOE occupational radiation exposure information 

is presented in Appendix E. Visit the DOE 

Radiation Exposure web site for information 

concerning occupational radiation exposure in 

the DOE complex at:
1-2 This page intentionally left blank. DOE Occupational Radiation Exposure
2003 Report Standards and Requirements 2-1

Section Two 2

One of DOE’s primary objectives is to provide 

Standards and Requirements

a safe and healthy workplace for all employees 

and contractors. To meet this objective, DOE’s 

Office of Health establishes comprehensive and 

integrated programs for the protection of workers 

from hazards in the workplace, including ionizing 

radiation. The basic DOE standards are radiation 

dose limits, which establish maximum permissible 

doses to workers and members of the public. In 

addition to the requirement that radiation doses 

not exceed the limits, contractors are required 

to maintain exposures as low as reasonably 

achievable (ALARA).

This section discusses radiation protection 

standards and requirements in effect for the year 

2003. Requirements leading up to this time period 

are also included to facilitate a better understanding 

of changes that have occurred in the recording 

and reporting of occupational dose.

2.1 Radiation Protection 

Requirements

DOE radiation protection standards are based 

on federal guidance for protection against 

occupational radiation exposure promulgated by 

the U.S. Environmental Protection Agency (EPA) in 

1987.[1] These standards are provided to ensure 

that DOE workers are adequately protected from 

exposure to ionizing radiation. This guidance, 

initially implemented by DOE in 1989, is based on 

the 1977 recommendations of the International 

Commission on Radiological Protection 

(ICRP) [2] and the 1987 recommendations of 

the National Council on Radiation Protection 

and Measurements (NCRP).[3] This guidance 

recommended that internal organ dose (resulting 

from the intake of radionuclides) be added to the 

external whole body dose to determine the Total 

Effective Dose Equivalent (TEDE). Prior to this, the 

whole body dose and internal organ dose were 

each limited separately. The present DOE dose 

limits based on the TEDE were established from 

this guidance.

DOE became the first federal agency to implement 

the EPA guidance when it promulgated DOE Order 

5480.11, “Radiation Protection for Occupational 

Workers,” in December 1988.[4] DOE Order 

5480.11 was in effect from 1989 to 1995.

In June 1992, the “DOE Radiological Control 

(RadCon) Manual” [5] was issued and became 

effective in 1993. The “RadCon Manual” was the 

result of a Secretarial initiative to improve and 

standardize radiological protection practices 

throughout DOE and to achieve the goal of making 

DOE the pacesetter for radiological health and 

safety. The “RadCon Manual” is a comprehensive 

guidance document written for workers, line 

managers, and senior management. The “RadCon 

Manual” states DOE’s views on the best practices 

currently available in the area of radiological 

control. The “RadCon Manual” was revised in 1994 

in response to comments from the field and to 

enhance consistency with the requirements in 10 

CFR 835 “Occupational Radiation Protection.” [6] 

In July 1999, the “RadCon Manual” was formally 

reissued as the Radiological Control Standard 

(RCS).[7] The RCS incorporates changes resulting 

from the amendment to 10 CFR 835 issued on 

November 4, 1998.

The 10 CFR 835 rule became effective on January 

13, 1994, and required full compliance by January 

1, 1996. In general, 10 CFR 835 codified existing 

radiation protection requirements in DOE 

Order 5480.11. The rule provides nuclear safety 

requirements that, if violated, provide a basis for 

the assessment of civil and criminal penalties 

under the Price-Anderson Amendments Act of 

1988, Public Law 100-408, August 20, 1988 [8] as 

implemented by 10 CFR 820 “Procedural Rules for 

DOE Nuclear Activities,” August 17, 1993.[9]

One and one-half years after the promulgation of 

10 CFR 835, DOE Order 5480.11 was canceled and 

the “RadCon Manual” was made non-mandatory 

guidance with issuance of DOE Notice 441.1, 

“Radiological Protection for DOE Activities,” 

[10] (applicable to defense nuclear facilities). 

This notice was issued to establish radiological 

Standards and Requirements
2-2 DOE Occupational Radiation Exposure 

protection program requirements that, combined 

with 10 CFR 835 and its associated non-mandatory 

implementation guidance, formed the basis for a 

comprehensive radiological protection program. 

DOE N 441.1 continued in effect until June 1, 2000, 

when compliance with the amendment to

10 CFR 835 (issued November 4, 1998) was 

achieved by DOE sites.

During 1994 and 1995, DOE undertook an initiative 

to reduce the burden of unnecessary, repetitive, or 

conflicting requirements on DOE contractors. As 

a result, DOE Order 5484.1 [11] requirements for 

reporting radiation exposure records were split 

into two directives; DOE Order 231.1, “Environment, 

Safety, and Health Reporting” [12], which required 

the reporting of occupational radiation exposure 

records, and DOE Manual 231.1-1, “Environment, 

Safety, and Health Reporting Manual” [13], which 

specified the format and content of the required 

reports. Both became effective September 30, 1995.

Most sites reported radiation monitoring results 

under DOE Order 231.1 and Manual 231.1-1 

for 1996. Each site implemented the change in 

requirements as operating contracts were issued 

or renegotiated. DOE Order 231.1 underwent 

two subsequent revisions (Change 1 in 1995 

and Change 2 in 1996) and was reissued as DOE 

Order 231.1A [14] in August of 2003. DOE Manual 

231.1-1 underwent similar revisions (Change 1 in 

1996 and Change 2 in 2000) and was reissued as 

DOE Manual 231.1-1A and approved on March 

19, 2004.[15]

2.1.1 Monitoring Requirements

10 CFR 835.402(a) requires that, for external 

monitoring, personnel dosimetry be provided to 

general employees likely to receive an effective 

dose equivalent to the whole body greater than

0.1 rem (1 mSv) in a year or an effective dose 

equivalent to the skin or extremities, lens of the 

eye, or any organ or tissue greater than 10% of 

the corresponding annual limits. Monitoring for 

internal radiation exposure is also required when 

the general employee is likely to receive 0.1 rem

(1 mSv) or more Committed Effective Dose 

Equivalent (CEDE) in a year. Monitoring for 

minors and members of the public is required 

if the TEDE is likely to exceed 50% of the annual 

limit of 0.1 rem (1 mSv) TEDE. Monitoring of 

declared pregnant workers is required if the TEDE 

to the embryo/fetus is likely to exceed 10% of the 

limit of 0.5 rem (5 mSv) TEDE during the gestation 

period. 

Monitoring for external exposures is also required 

for any individual entering a high or very high 

radiation area.

2.1.1.1 External Monitoring

External or personnel dosimeters are used to 

measure ionizing radiation from sources external 

to the individual. The choice of dosimeter 

is based on the type and energy of radiation 

that the individual is likely to encounter in the 

workplace. External monitoring devices include 

thermoluminescent dosimeters (TLDs), optically 

stimulated luminescent dosimeters (OSLs), pocket 

ionization chambers, electronic dosimeters, 

personnel nuclear accident dosimeters, bubble 

dosimeters, plastic dosimeters, and combinations 

of the above.

Beginning in 1986, the DOE Laboratory 

Accreditation Program (DOELAP) formalized 

accuracy and precision performance standards for 

external dosimeters used for dose of record and 

quality assurance/quality control requirements for 

external dosimetry programs at facilities within 

the DOE complex. All DOE facilities requiring 

accreditation were DOELAP-accredited by the fall 

of 1995. 

External dosimeters have a lower limit of detection 

of approximately 0.005 to 0.030 rem (0.05 to 0.30 

mSv) per monitoring period. The differences are 

attributable to the particular type of dosimeter 

used and the types of radiation monitored. 

Monitoring periods are usually quarterly for 

individuals receiving less than 0.300 rem/year

(3 mSv/year) and monthly for individuals who may 

receive higher doses or who enter higher radiation 

areas.

2.1.1.2 Internal Monitoring

Bioassay monitoring includes in-vitro (outside 

the body) and in-vivo (inside the body) sampling. 

In-vitro assays include urine and fecal samples, 

nose swipes, saliva samples, and hair samples. 

In-vivo assays include whole body counting, 

thyroid counting, lung counting, and wound 

counting.
2003 Report Standards and Requirements 2-3

Monitoring intervals for internal dosimetry depend 

on the radionuclides being monitored and their 

concentrations in the work environment. Routine 

monitoring intervals may be monthly, quarterly, 

or annually, whereas special monitoring intervals 

following an incident may be daily or weekly. 

Detection thresholds for internal dosimetry are 

highly dependent on the monitoring methods, the 

monitoring intervals, the radionuclides in question, 

and their chemical form. Follow-up measurements 

and analysis may take many months to confirm 

preliminary findings. DOELAP has developed 

a Radiobioassay Accreditation Program in 

conjunction with the publication of American 

National Standards Institute (ANSI) N13.30-1996, 

“Performance Criteria for Radiobioassay. ” 

Implementation of the program began in 

November 1998 with issuance of the amendments 

to 10 CFR 835.402.(d), with full compliance 

achieved in January 2004.

2.2 Radiation Dose Limits

Radiation dose limits are codified in 10 CFR 

835.202, 206, 207, 208 and are summarized in 

Exhibit 2-1. While some of these sections have 

been revised, the limits remain the same. 

Under 835.204, Planned Special Exposures (PSEs) 

may be authorized under certain conditions 

allowing an individual to receive exposures in 

excess of the dose limits shown in Exhibit 2-1. With 

the appropriate prior authorization, the annual 

dose limit for an individual may be increased by 

an additional 5 rems (50 mSv) TEDE above the 

routine dose limit as long as the individual does 

not exceed a cumulative lifetime TEDE of 25 rems 

(250 mSv) from other PSEs and doses above the 

limits. PSE doses are required to be recorded 

separately and are only intended to be used in 

exceptional situations where dose reduction 

alternatives are unavailable or impractical. No 

PSEs have occurred since the requirement became 

effective.

Exhibit 2-1:

DOE Dose Limits from 10 CFR 835

������� �������� ������������������������������� ���� ������

���������

�������������������������������� ������� �������

������������������������������� ������

��������������������������������

����������������������������

�������������������������������

��������������������������������� ��� �������

����������������������������������� ������ �������

��������������������������� ���

��������� ������

�������� �������� ������������������������������� ���� �����������

�������� ���������

������� ������

������ �������� ������������������������������� ���� �������

���������� �������� ������������������������������� ���� �������

���������������

���������������

���������

��������

����������

���������� ���������������� �������

������

�����

����������������������������������
2-4 DOE Occupational Radiation Exposure 

2.2.1 Administrative Control Levels 

Administrative Control Levels (ACLs) were 

initially established in the “RadCon Manual” and 

retained in the RCS. ACLs are established below 

the regulatory dose limits to administratively 

control and help reduce individual and collective 

radiation dose. ACLs are multi-tiered, with 

increasing levels of authority needed to approve a 

higher level of exposure.

The RCS recommends a DOE ACL of 2 rem

(20 mSv) per year, per person, for all DOE activities. 

Prior to allowing an individual to exceed this level, 

approval from the appropriate Secretarial Officer 

or designee should be received. In addition, 

contractors are encouraged to establish an annual 

facility ACL. This control level is established by 

the contractor senior site executive and is based 

upon an evaluation of historical and projected 

radiation exposures, workload, and mission. The 

RCS suggests an annual facility ACL of 0.5 rem (5 

mSv) or less; however, the RCS also states that a 

control level greater than 1.5 rem (15 mSv) is, in 

most cases, not sufficiently challenging. Approval 

by the contractor senior site executive must be 

received prior to an individual exceeding the 

facility ACL. In addition to the annual ACL, the 

RCS recommends the establishment of a lifetime 

ACL of “N” rem, where N is the age of the person

in years. Special control levels are also 

recommended to be established for personnel 

who have lifetime doses exceeding N rem.

2.2.2 ALARA Principle

Until the 1970s, the fundamental radiation 

protection principle was to limit occupational 

radiation dose to quantities less than the 

regulatory limits and to be concerned mainly with 

high dose and high-dose rate exposures. During 

the 1970s, there was a fundamental shift within the 

radiation protection community to be concerned 

with low dose and low-dose rate exposures 

because it could be inferred from the linear 

no-threshold dose response hypothesis that there 

was an increased level of risk associated with any 

radiation exposure. The As Low As Practicable 

(ALAP) concept was initiated and became part 

of numerous guidance documents and radiation 

protection good practices. ALAP was eventually 

replaced by ALARA. DOE Order 5480.11 and

10 CFR 835 require that each DOE facility have an 

ALARA Program as part of its overall Radiation 

Protection Program.

The ALARA methodology considers both 

individual and group doses and generally involves 

a cost/benefit analysis. The analysis considers 

social, technical, economic, practical, and 

public policy aspects of the overall goal of dose 

reduction. Because it is not feasible to reduce 

all doses at DOE facilities to zero, ALARA cost/

benefit analysis must be used to optimize levels of 

radiation dose reduction. According to the ALARA 

principle, resources spent to reduce dose need to 

be balanced against the risks avoided. Reducing 

doses below this point results in a misallocation of 

resources; the resources could be spent elsewhere 

and have a greater impact on health and safety.

To ensure that doses are maintained ALARA at 

DOE facilities, the DOE mandated, in DOE Order 

5480.11 and subsequently in 10 CFR 835, that 

ALARA plans and procedures be implemented 

and documented. To help facilities meet 

this requirement, DOE developed a manual 

of good practices for reducing exposures to 

ALARA levels.[16] This document includes 

guidelines for administration of ALARA programs, 

techniques for performing ALARA calculations 

based on cost/benefit principles, guidelines 

for setting and evaluating ALARA goals, and 

methods for incorporating ALARA criteria into 

both radiological design and operations. The 

establishment of ALARA as a required practice at 

DOE facilities demonstrates DOE’s commitment to 

minimize the risk to workers from the operation of 

its facilities.
2003 Report Standards and Requirements 2-5

2.3 Reporting Requirements

In 1987, DOE promulgated revised reporting 

requirements in DOE Order 5484.1, 

“Environmental Protection, Safety, and Health 

Protection Information Reporting Requirements.” 

Previously, contractors were required to report 

only the number of individuals who received an 

occupational whole body dose in one of 16 dose 

equivalent ranges. The revised Order required 

the reporting of the results of radiation exposure 

monitoring for each employee and member of 

the public. Required dose data reporting includes 

the TEDE, internal dose equivalent, Shallow Dose 

Equivalent (SDE) to the skin and extremities, and 

Deep Dose Equivalent (DDE). Other reported 

data include the individual’s age, sex, monitoring 

status, and occupation, as well as the reporting 

organization and facility type.

On August 19, 2003, DOE approved and issued 

the revised DOE Order 231.1A. The DOE Manual 

231.1-1A, which details the format and content of 

reporting radiation exposure records to the DOE, 

was approved on March 19, 2004. The revisions 

affect the content and reporting of radiation 

exposure records that will be reported to the DOE 

Radiation Exposure Monitoring System (REMS) 

repository in 2006. Readers should take note of 

these revisions for the potential future impact 

on the recording and reporting of occupational 

exposure to the REMS repository.

2.4 Change in Internal Dose 

Methodology

Prior to 1989, intakes of radionuclides into the 

body were not reported as dose, but as body 

burden in units of activity of systemic burden, 

such as the percent of the maximum permissible 

body burden. The implementation of DOE Order 

5480.11 in 1989 specified that the intakes of 

radionuclides be converted to internal dose and 

evaluated against the dose limits using the Annual 

Effective Dose Equivalent (AEDE) methodology. 

AEDE as well as CEDE were required for reports to 

employees.

With the implementation of the “RadCon Manual” 

in 1993, the required methodology used to 

determine compliance within the dose limits 

and report internal dose was changed from the 

AEDE to the 50-year CEDE. The change was 

made to provide consistency with scientific 

recommendations, facilitate the transfer of workers 

between DOE and Nuclear Regulatory Commission 

(NRC)-regulated facilities, and simplify record 

keeping by recording all dose in the year of intake. 

The CEDE methodology is now codified in

10 CFR 835.

This report primarily analyzes dose information 

for the past 5 years, from 1999 to 2003. During 

these years, the CEDE methodology was used to 

calculate internal dose; therefore, the change in 

methodology from AEDE to CEDE between 1992 

and 1993 does not affect the analysis contained 

in this report. When analyzing TEDE data prior to 

1993, readers should keep in mind the change in 

methodology.

When analyzing TEDE data prior to 1993, 

readers should note that the method of 

calculating internal dose changed from 

AEDE to CEDE between 1992 and 1993.
2-6 This page intentionally left blank. DOE Occupational Radiation Exposure
2003 Report Occupational Radiation Dose at DOE 3-1

Section Three 3Occupational Radiation Dose at DOE

Occupational Radiation Dose at DOE

For 2001-2003, the same percentage (75%) 

of the DOE workforce was monitored for 

radiation dose, and the same percentage 

of monitored individuals received a 

measurable dose (17%).

3.1 Analysis of the Data

Analysis and explanation of observed trends 

in occupational radiation dose data reveal 

opportunities to improve safety and demonstrate 

performance. Several indicators were identified 

from the data submitted to the central data 

repository, which can be used to evaluate the 

occupational radiation exposures received at 

DOE facilities. In addition, the key indicators are 

analyzed to identify and correlate parameters 

having an impact on radiation dose at DOE.

Key indicators for the analysis of aggregate data 

are: number of records for monitored individuals 

and individuals with measurable dose, collective 

dose, average measurable dose, and the dose 

distribution. Analysis of individual dose data 

includes an examination of doses exceeding DOE 

regulatory limits and doses exceeding the 2 rem 

(20 mSv) DOE ACL. Analysis of site data includes 

comparisons by site, labor category, facility type, 

and occurrence report information. Additional 

information is provided concerning activities 

at sites contributing to the collective dose. To 

determine the significance of trends, statistical 

analysis was performed on the data.

3.2 Analysis of Aggregate Data

3.2.1 Number of Records for Monitored 

Individuals

The number of records for monitored individuals 

represents the size of the DOE worker population 

provided with radiation dose monitoring. The 

number represents the sum of all records for 

monitored individuals, including all DOE

employees, contractors, subcontractors, and 

members of the public. The number of monitored 

individuals is determined from the number 

of monitoring records submitted by each site. 

Because individuals may have more than one 

monitoring record, they may be counted more 

than once. The number of records for monitored 

individuals is an indication of the size of a 

dosimetry program, but it is not necessarily an 

indicator of the size of the exposed workforce. 

This is because of the conservative practice at 

some DOE facilities of providing radiation dose 

monitoring to individuals for reasons other than 

the potential for exposure to radiation and/or 

radioactive materials exceeding the monitoring 

thresholds. Many individuals are monitored 

for reasons such as security, administrative 

convenience, and legal liability. Some sites offer 

monitoring for any individual who requests 

monitoring, independent of the potential for 

exposure. For this reason, the number of records 

for workers who receive a measurable dose best 

represents the exposed workforce.

3.2.2 Number of Records for Individuals 

with Measurable Dose

DOE uses the number of individuals receiving 

measurable dose to represent the exposed 

workforce size. The number of individuals with 

measurable dose includes any individuals with 

reported TEDE greater than zero.

Exhibit 3-1 shows the number of DOE workers 

and contractors, the total number of records 

for monitored individuals, and the number with 

measurable dose for the past 5 years. Compared 

to 2002, the same percentage (75%) of the DOE 

workforce was monitored for radiation in 2003, and 

the same percentage (17%) of monitored 

individuals received a measurable dose. The total 

number of records of individuals monitored for 

radiation has decreased over the past 5 years, but 

increased over the past 3 years by 5% from 97,818 

in 2001 to 102,509 in 2003. The percentage of the 

DOE workforce monitored for radiation exposure 

has decreased by 12% from 87% in 1999 to 75% 

in 2003. However, most (84%) of the monitored 

individuals over the past 5 years did not receive 
3-2 DOE Occupational Radiation Exposure 

Exhibit 3-1:

Monitoring of the DOE Workforce, 1999-2003.

1999 2000 2001 2002 2003

0

20,000

40,000

60,000

80,000

100,000

120,000

140,000

160,000

Number of Individuals

Year

16,668

113,064

130,453

Number of DOE Workers and Contractors

Total Number of Records for Monitored Individuals

Number with Measurable Dose

102,881

15,983

129,653

97,818

16,687

130,884

100,221

17,051

133,703

17,484

102,509

136,710

The number of workers with measurable 

dose increased from 17,051 in 2002 to 

17,484 in 2003.

The percentage of monitored workers 

receiving measurable dose remained the 

same, at 17%, in 2003.

any measurable radiation dose. An average of 

16% of monitored individuals (13% of the DOE 

workforce) received a measurable dose during the 

past 5 years. The percentage of monitored workers 

receiving measurable dose has remained fairly 

constant for the past 5 years: 15% in 1999 and 17% 

in 2003. The overall DOE workforce has increased 

by 2% from 133,703 in 2002 to 136,710 in 2003.

Fourteen of the 27 reporting sites (see Appendix 

Exhibit B-1c) experienced decreases in the 

number of workers with measurable dose from 

2002 to 2003. The largest decrease in total number 

of workers with measurable dose occurred at 

Rocky Flats. The largest increases in the number 

of workers receiving measurable dose occurred 

at Los Alamos National Laboratory (LANL) and 

Savannah River. A discussion of activities at the six 

highest-dose facilities is included in Section 3.5.

3.2.3 Collective Dose

The collective dose is the sum of the dose received 

by all individuals with measurable dose and is 

measured in units of person-rem (person-Sv). 

The collective dose is an indicator of the overall 

radiation exposure at DOE facilities and includes 

the dose to all DOE employees, contractors, 

subcontractors, and members of the public. DOE 

monitors the collective dose as one measure of 

the overall performance of radiation protection 

programs to keep individual exposures and 

collective exposures ALARA.

As shown in Exhibit 3-2, the collective TEDE 

increased at DOE by 6% from 1,360 person-rem 

(13.60 person-Sv) in 2002 to 1,445 person-rem 

(14.45 person-Sv) in 2003. Fifty-two percent of the 

DOE sites (14 out of 27 sites) reported increases in 

the collective TEDE from the 2002 values. Four out 

of six of the highest dose sites reported increases 

in the collective TEDE. The six highest dose sites 

are (in descending order of collective dose for 

2003) Hanford, Savannah River, Los Alamos, Rocky 

Flats, Oak Ridge, and Idaho. These sites attributed 

the increase in dose to thermal stabilization and 

repackaging of plutonium-bearing materials, 
2003 Report Occupational Radiation Dose at DOE 3-3

1,000

500

0

1,500

1999 2000 2001 2002 2003

Year

Collective TEDE (person-rem)

Internal Dose (CEDE)

from New Intakes During

the Monitoring Year

Photon (Deep)

Neutron

Legend

NOTE: The percentages in

parentheses represent the

percentage of each dose

component to the collective TEDE.

59

(4.8%)

153

(11.8%) 181

(14.3%)

886

(68.4%)

256

(19.8%)

842

(66.5%)

244

(19.2%)

945

(76.7%)

228

(18.5%)

1,295 1,267

1,232

69

(5.1%)

1,024

(75.3%)

267

(19.6%)

1,360 95

(6.6%)

1,053

(72.9%)

297

(20.5%)

1,445

Photon dose (deep) - the component of external dose from 

gamma or x-ray electromagnetic radiation. (Also includes 

energetic betas.)

Neutron dose - the component of external dose from neutrons 

ejected from the nucleus of an atom during nuclear reactions.

Internal dose - radiation dose resulting from radioactive 

material taken into the body.

Exhibit 3-2:

Components of TEDE, 1999-2003.

The collective TEDE 

increased by 6% at DOE 

from 2002 to 2003.

Fifty-two percent of 

the DOE sites reported 

increases in the collective 

TEDE from 2002 values.

The collective internal 

dose increased by 38% 

from 2002 to 2003.

Neutron dose increased 

by 11% from 2002 to 

2003.

Photon dose increased by 

3% from 2002 to 2003.
3-4 DOE Occupational Radiation Exposure 

processing of spent fuels, and accelerated cleanup 

of tank farms at Hanford, resumption of processing 

of radioactive material, special programs, and 

accelerated facility closure and waste processing 

activities at Savannah River, and work activities 

associated with the building 9204-4 Cleanup Project 

and the TVA Off-Specification Fuel repackaging 

project at Oak Ridge, and the processing of more 

materials containing americium, an upgrade to the 

material storage vault, and the decontamination 

and decommissioning of the Omega West reactor 

at LANL. A discussion of the activities leading to 

this increase is included in Section 3.5. 

A statistical analysis was performed to analyze the 

trend in collective dose over the past 5 years. The 

analysis examines the logarithmic mean of the 

TEDE, neutron, and extremity dose in comparison 

with prior years. The analysis revealed no 

significant changes to the logarithmic mean 

TEDE, neutron, or extremity dose between 2002 

and 2003. This indicates that while the collective 

TEDE, neutron, and extremity dose increased 

between 2002 to 2003, it does not represent a 

statistically significant change in the dose 

received by individual workers at DOE. Further 

tests revealed a statistically significant downward 

shift in the neutron dose distribution, indicating 

that fewer individuals received doses above 0.500 

rem (5 mSv). See Section 3.5 for more information 

on activities contributing to the collective dose 

and Section 4 for a discussion of notable ALARA 

activities.

It is important to note that the collective TEDE 

includes the components of external dose and 

internal dose. Exhibit 3-2 shows the types of 

radiation and their contribution to the collective 

TEDE. Internal dose, photon, and neutron 

components are shown.

It should be noted that the internal dose shown 

in Exhibit 3-2 for 1999 through 2003 is based on 

the 50-year CEDE methodology. The internal dose 

component increased by 38% from 69 person-rem 

(690 person-mSv) in 2002 to 95 person-rem (950 

person-mSv) in 2003, although it remains lower 

than the values for 1999 through 2000. There were 

three individuals who received a TEDE dose above 

2 rem (20 mSv) in 2003. All three occurred at 

LANL. Two of these individuals received internal 

dose from plutonium, and the third received 

an external dose. The collective internal dose 

can vary from year to year due to the relatively 

small number of intakes of radioactive material 

and the fact that they often involve long-lived 

radionuclides, such as plutonium, which can 

result in relatively large committed doses. Due to 

the infrequent nature of these intakes, care should 

be taken when attempting to identify trends from 

the internal dose records.

The external deep dose (comprised of photon, 

energetic beta, and neutron dose) is shown 

in Exhibit 3-2 in order to see the contribution 

of external dose to the collective TEDE. The 

collective photon dose increased by 3% from 1,024 

person-rem (10.24 person-Sv) in 2002 to 1,053 

person-rem (10.53 person-Sv) in 2003. Three of 

the sites that reported the largest increases in the 

photon dose attributed the increase to activities 

involving the processing of more materials 

containing americium, an upgrade to the material 

storage vault, and the decontamination and 

decommissioning of the Omega West reactor at 

LANL, the resumption of processing radioactive 

material, special programs, and accelerated 

facility closure and waste processing activities at 

Savannah River, and the building 9204-4 Cleanup 

Project and the TVA Off-Specification Fuel 

repackaging project at Oak Ridge. See Section 3.5 

for more information on activities at these sites.

The neutron component of the TEDE increased by 

11% from 267 person-rem (2.67 person-Sv) in 2002 

to 297 person-rem (2.97 person-Sv) in 2003. This 

is primarily due to an 18% increase in the neutron 

dose at LANL. LANL contributed 30% of the 

neutron dose during 2003. LANL and Rocky Flats 

process plutonium in gloveboxes, which can result 

in a neutron dose from the alpha/neutron reaction 

and from spontaneous fission of the plutonium. 

The collective neutron dose for 2003 by site is 

shown in Appendix Exhibit B-5. External deep dose 

(DDE) and TEDE for prior years (1974 through 

2003) can be found in Appendix Exhibit B-3.
2003 Report Occupational Radiation Dose at DOE 3-5

The average measurable neutron dose 

increased by 7% and the average 

measurable DDE increased by 2%, 

while the average measurable TEDE 

increased by 4% from 2002 to 2003.

3.2.4 Average Measurable Dose

The average measurable dose to DOE workers 

presented in this report for TEDE, DDE, neutron, 

extremity, and CEDE is determined by dividing the 

collective dose for each dose type by the number 

of individuals with measurable dose for each dose 

type. This is one of the key indicators of the overall 

level of radiation dose received by DOE workers.

The average measurable neutron, DDE, and TEDE 

is shown in Exhibit 3-3. The average measurable 

neutron dose increased by 7% from 0.069 rem 

(0.69 mSv) in 2002 to 0.074 rem (0.74 mSv) in 

2003, primarily due to increases in neutron dose 

at LANL. The average measurable neutron dose 

increased by 17% from 0.063 rem (0.63 mSv) in 

1999 to 0.074 rem (0.74 mSv) in 2003. The average 

measurable DDE increased by 2% from 0.084 rem 

(0.84 mSv) in 2002 to 0.086 rem (0.86 mSv) in 

2003 and increased by 13% from 0.076 rem (0.76 

mSv) in 1999 to 0.086 rem (0.86 mSv) in 2003. The 

collective TEDE increased, as well as the number 

with measurable dose, resulting in a 4% increase 

in the average measurable TEDE from 0.080 rem 

(0.80 mSv) in 2002 to 0.083 rem (0.83 mSv) in 

2003. The average measurable TEDE increased by 

6% from 0.078 rem (0.78 mSv) in 1999 to 0.083 

rem (0.83 mSv) in 2003. The average measurable 

neutron, DDE, and TEDE values are provided for 

trending purposes, not for comparison between 

them.

While the collective dose and average measurable 

dose serve as measures of the magnitude of 

the dose accrued by DOE workers, they do not 

indicate the distribution of doses among the 

worker population.

Exhibit 3-3:

Average Measurable Neutron, DDE, and TEDE, 1999-2003.

0.00

0.01

0.02

0.03

0.04

0.05

0.06

0.07

0.08

0.09

0.10

Average Measurable Dose (rem)

0.063

0.054

0.062

0.069

0.074 0.076 0.076

0.079

0.084 0.086

0.078 0.079

0.074

0.08

0.083

Average Measurable

Neutron Dose (rem)

Average Measurable

DDE (rem)

Average Measurable

TEDE (rem)

1999 2000 2001 2002 2003 1999 2000 2001 2002 2003 1999 2000 2001 2002 2003
3-6 DOE Occupational Radiation Exposure 

Exhibit 3-4:

Distribution of Dose by Dose Range, 1999-2003.

3.2.5 Dose Distribution

Exposure data are commonly analyzed in terms 

of dose intervals to depict the dose distribution 

among the worker population. Exhibit 3-4 shows 

the number of individuals in each of 18 different 

dose ranges. The dose ranges are presented for 

the TEDE and DDE. The DDE is shown separately 

to allow for analysis of the external dose, 

independent of changes in internal dose, and 

includes the photon and neutron dose. The 

number of individuals receiving doses above 0.1 

rem (1 mSv) is also included to show the number 

of individuals with doses above the monitoring 

threshold specified in 10 CFR 835.402(a) and (c).

Exhibit 3-4 shows that few individuals receive 

doses in the higher ranges, that the vast majority 

of doses are at low levels, and that the collective 

TEDE dose decreased from 1999 to 2000, but has 

increased over the past 3 years from 2001 to 2003. 

Another way to examine the dose distribution is to 

analyze the percentage of the dose received above 

a certain dose value as compared to the total 

collective dose.

The United Nations’Sources and Effects of Ionizing 

Radiation, United Nations Scientific Committee 

on the Effects of Atomic Radiation UNSCEAR 

2000 Report to the General Assembly, with 

Scientific Annexes, Volume I [17] recommends 

the calculation of a parameter “SR” (previously 

referred to as CR) to aid in the examination of 

the distribution of radiation exposure among 

workers. SR is defined to be the ratio of the annual 

collective dose incurred by workers whose annual 

doses exceed 1.5 rem (15 mSv) to the total annual 

collective dose. The UNSCEAR report notes that 

a dose level of 1.5 rem (15 mSv) may not be 

useful where doses are consistently lower than 

this level, and they recommend that research 

organizations report SR values lower than 1.5 rem 

�����������������������������������������

���� ����

�����������������������������������������������������������������������������������������������������������������������

�����������������

����

���� ���� ���� ���� ���� ���� ���� ����

��������������������

����������������

�����������

����������

����������

����������

�����

�����

�����

�����

�����

�����

�����

�����

������

�������

�������

����

���������������������������

���������������������

���������������������������

������������������������

����������������

��������������������

����������������������������

�����������������������������

������ ������

������ ������

����� �����

��� ���

��� ���

��� ��

�� ��

�

�

�

������� �������

������ ������

����� �����

��� ���

����� �����

����� �����

������ ������

������ ������

����� �����

��� ���

��� ���

�� ��

�� ��

�

�

�

������� �������

������ ������

����� �����

��� ���

����� �����

����� �����

������ ������

������ ������

����� �����

��� ���

��� ���

�� ��

�� ��

�

������ ������

������ ������

����� �����

��� ���

����� �����

����� �����

���� ���� ���� ����

������ ������

������ ������

����� �����

��� ���

��� ���

�� ��

�� ��

� �

������� �������

������ ������

����� �����

��� ���

����� �����

����� �����

����

������

������

�����

���

���

���

��

�

�

�

�������

������

�����

���

�����

�����

������

������

�����

���

���

���

��

�

�������

������

�����

���

�����

�����
2003 Report Occupational Radiation Dose at DOE 3-7

Exhibit 3-5:

Percentage of Collective Dose above Dose Values During 1999-2003. (15 mSv) where appropriate. For this reason, the 

DOE calculates and tracks the SR ratio at dose 

levels of 0.100 rem (1 mSv), 0.250 rem (2.5 mSv),

0.500 rem (5 mSv), 1.0 rem (10 mSv), and 2.0 rem

(20 mSv). The SR values in this report were 

calculated by summing the TEDE to each 

individual who received a TEDE greater than, or 

equal to, the specified dose level divided by the 

total collective TEDE. This ratio is presented as a 

percentage rather than a decimal fraction.

Using this method of plotting the data, an ideal 

distribution would show only a small percentage 

of the collective dose delivered to individuals in 

the higher dose ranges. In addition, this method 

can be used to show the trend in the percentage 

of the collective dose above a certain dose range 

over time. For example, a significantly decreasing 

trend from year to year may indicate the 

effectiveness of ALARA programs to reduce doses 

to individuals or may indicate an overall reduction 

in activities involving radiation exposure over 

time. An increasing trend over time may indicate 

deficiencies in the implementation of ALARA 

practices or an increase in production or cleanup 

activities resulting in radiation exposure.

Exhibit 3-5 shows the dose distribution given by 

percentage of collective TEDE and DDE above 

each of five dose values, from 0.1 rem (1 mSv) 

to 2 rem (20 mSv). This graph facilitates the 

examination of two properties described above 

which may be used as indications of effective 

ALARA programs at DOE: (1) a relatively small 

percentage of the collective dose accrued in the 

high dose ranges, and (2) a decreasing trend 

over time of the percentage of the collective dose 

accrued in the higher dose ranges. Exhibit 3-5

also shows that each successively higher dose 

range is responsible for a lower percentage of the 

collective dose. The values for the external dose 

(DDE) have fluctuated within a 5% margin for 

each dose range over the past 5 years. The values 

for TEDE in each dose range increased from 1999 

to 2000, decreased significantly in 2001, and have 

increased from 2002 to 2003. The increases from 

1999 to 2000 were due to the increase in internal 

doses that exceeded the DOE limits. In 2000, three 

individuals received a TEDE above 5.0 rem

(50 mSv), which contributed to 8.6% of the 

2003 2002 2001 2000 1999

80%

70%

60%

50%

40%

30%

20%

10%

0%

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

TEDE

2.0 rem

1.0 rem

0.5 rem

0.25 rem

0.1 rem

Dose Value

Year

Percentage of Collective TEDE Above Dose Values

75%

0.2%

5%

24%

47%

71%

48%

51%

29%

10%

8.6%

14%

30%

50%

71% 73%

28%

9%

1.0%

0.2%

6%

24%

47%

73%

1.4%

2003 2002 2001 2000 1999

80%

70%

60%

50%

40%

30%

20%

10%

0%

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

DDE

69%

45%

24%

7%

6%

25%

47%

71%

0%

0.2%

6%

25%

49%

74% 75%

52%

29%

9%

0.2%

0%

0%

5%

24%

48%

72%

2.0 rem

1.0 rem

0.5 rem

0.25 rem

0.1 rem

Dose Value

Year

Percentage of Collective DDE Above Dose Values
3-8 DOE Occupational Radiation Exposure 

�

�����������������������������������������������������������������

� ��������������������������������������������������������������������������������������������������������������������������������������������

�����������������������������������������������������

�����

������

�����

����

�����

���

����

��� ����

����������

�����������

������������

�������

�����

�������

���� ���������

��������

����

�����

����

�����

���������

���������

�����������

����������

������������

��� �

����

����

����

����

����

����

�������

������

������

������

������

�����

�����

�����

�����

�����

���

���

���

���

���

�������

�������

������

�������

�������

���

���

���

���

���

��

��

��

��

��

�

�

�

��

��

�

�

�

��

�����

�����

�����

�����

�����

�������

�������

�������

�������

�������

�����

�����

�����

�����

�����

Exhibit 3-6:

Neutron Dose Distribution, 1999-2003.

collective TEDE for the year, the highest 

percentage above 2 rem (20 mSv) since 1990. 

For 2003, two individuals received doses in 

excess of 5.0 rem (50 mSv). This resulted in an 

increase for the percentages in each dose range. 

In contrast, no individuals exceeded the DOE 

limits in 2001 and 2002. See Section 3.3 for more 

information on exposures in excess of the DOE 

limit. 

The neutron and extremity dose distributions are 

shown in Exhibits 3-6 and 3-7. The neutron dose 

is a component of the total DDE. Exposure to 

neutron radiation is much less common at DOE 

than photon dose. In 2003, 3,987 individuals 

received measurable neutron dose, which is 23% 

of the individuals with measurable TEDE, and 

4% of the total monitored individuals. The 

collective neutron dose in 2003 represents 21% 

of the collective TEDE. All neutron doses were 

below 2 rem (20 mSv) for the past 5 years. The 

collective neutron dose increased by 11% from 

267 person-rem (2.67 person-Sv) in 2002 to 297 

person-rem (2.97 person-Sv) in 2003. The average 

measurable neutron dose increased by 7% from 

0.069 rem (0.69 mSv) in 2002 to 0.074 rem (0.74 

mSv) in 2003. Statistical analysis reveals that the 

logarithmic mean neutron dose did not change 

significantly from 2002 to 2003. This indicates 

that while the collective neutron dose increased 

between 2002 to 2003, it does not represent 

a statistically significant change in the dose 

received by individual workers at DOE. Further 

tests revealed a statistically significant downward 

shift in the neutron dose distribution, indicating 

that fewer individuals received doses above 0.500 

rem (5 mSv). This reflects a positive change in 

accordance with ALARA to reduce neutron 

dose to individuals at higher annual dose levels. 

The neutron dose distribution for 2003 by site is 

shown in Appendix Exhibit B-5.

Exhibit 3-7 shows the distribution of extremity dose 

over the past 5 years. “Extremities” are defined as 

the hands and arms below the elbow, and the feet 

and legs below the knee. 10 CFR 835.402(a)(1)(ii) 

requires monitoring for an SDE to the extremities 

of 5 rem (50 mSv) or more in a year. As shown 

in Exhibit 3-7, less than 1% of individuals with 

measurable extremity dose have received doses 

above the 5 rem (50 mSv) monitoring threshold 

over the past 5 years.
2003 Report Occupational Radiation Dose at DOE 3-9

Exhibit 3-7:

Extremity Dose Distribution, 1999-2003.

�����

����

����

���

���

��

���

��

����������

���������

����

������������

�������

����������

���������

���� ����������

��������

����

��

��� ��

�����

���������

������

�����

����������

���������

� �������

���

�� ��� ��

�����������������������������������������������������������������

�

��

���������������������������������������������������������������������������������������������������������������������������������������������

�����������������������������������������������������

�������������������������������������������������������������������������������������������������������������������������������������������������

���������������������������

������

����

����������

����

����

����

����

����

����

������

������

������

������

������

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�������

�������

������

�������

�������

���

���

���

���

���

��

��

���

���

���

��

��

��

��

��

�

�

�

��

���

���

���

���

���

�������

�������

�������

�������

�������

�����

�����

�����

�����

�����

�

������

������

������

������

������

�

Forty-six percent, the highest percentage of the 

extremity exposures above 5 rem (50 mSv) in 

2003 occurred at Hanford, where operations 

involving the manipulation of radioactive 

materials are more common. Ninety-three 

percent of individuals with measurable extremity 

dose were monitored at four sites: Savannah 

River, Hanford, Rocky Flats, and Los Alamos. The 

number of individuals receiving a measurable 

extremity dose decreased by 2% from 12,300 

in 2002 to 12,109 in 2003, and the average 

extremity dose increased by 8% from 0.363 rem 

(3.63 mSv) in 2002 to 0.391 rem (3.91 mSv) in 

2003. The DOE annual limit for extremity dose 

is 50 rem (500 mSv). The higher dose limit is 

due to the lack of blood-forming organs in the 

extremities; therefore, extremity dose involves less 

health risk to the individual. The highest extremity 

dose in 2003 was 24.3 rem (243 mSv) received 

by an individual at Hanford. Statistical analysis 

reveals that the logarithmic mean extremity dose 

did not change significantly from 2002 to 2003. 

This indicates that while the collective extremity 

dose increased between 2002 to 2003, it does 

not represent a statistically significant change in 

the dose received by individual workers at DOE. 

The extremity dose distribution by site for 2003 is 

shown in Appendix Exhibit B-22.
3-10 DOE Occupational Radiation Exposure 

Exhibit 3-8:

Number of Individuals Exceeding 5 Rem (TEDE), 1999-2003.

In 2003 there were two individuals 

reported who received doses in excess 

of the 5 rem (50 mSv) TEDE limit.

Exhibit 3-9:

Doses in Excess of DOE Limits, 1999-2003.

3.3 Analysis of Individual Dose Data

The above analysis is based on aggregate data for 

DOE. From an individual worker perspective, as 

well as a regulatory perspective, it is important to 

closely examine the doses received by individuals 

in the elevated dose ranges to thoroughly 

understand the circumstances leading to these 

doses in the workplace and to better manage and 

avoid these doses in the future. The following 

analysis focuses on doses received by individuals 

that were in excess of the DOE limit (5 rem TEDE) 

or (50 mSv) and the DOE recommended ACL

(2 rem TEDE) or (20 mSv).

3.3.1 Doses in Excess of DOE Limits

Exhibit 3-8 shows the number of doses in excess 

of the TEDE regulatory limit (5 rem) or (50 mSv) 

from 1999 through 2003. Further information 

concerning the individual doses, radionuclides 

involved, and sites where the doses in excess of 

the 5 rem (50 mSv) TEDE limit have occurred 

during the past 5 years is shown in Exhibit 3-9.

In 2003, two individuals received internal doses 

that resulted in a TEDE in excess of the 5 rem (50 

mSv) TEDE limit. Both individuals had intakes of 

Plutonium 238 that occurred at LANL. The two 

employees were performing inventories of items 

on shelves in a high radiation area. The employees 

had completed two shelves, self monitoring after 

each, and no contamination was detected. While 

inventorying the third shelf, a continuous air 

monitor in the room alarmed. The two employees 

immediately exited the room, monitored 

themselves and upon finding contamination, 

summoned the responsible radiological 

control technician (RCT) for assistance. The 

two employees received clothing and skin 

contamination, and contamination was also found 

on the anti-c clothing of the RCT performing the 

���� ����� ����� ����� ������������������������ ������������������� ��������������

������ �����������

����� ����� ����� ����� ���������������������� ����������������� ����

������ ����� ������ ���������������������� ����������������� ����

������ ����� ������ ���������������������� ����������������������� ����

����

���� ����� ����� � ��� ����������������� ����

���� ����� ����� ����� ����� ������ ����� ����

������ ����� ����� ����� ������ ���������������� ����

���� ���������

���

����� ��������������� �������������� ����

�These three doses were all a result of the same occurrence.

����

�����

�������������

���

���������

�����

Year

1999 2000 2001 2002 2003

0

1

2

3

4

5

3

0

1

Number of Individuals

Exceeding 5 Rem (TEDE)

0

2
2003 Report Occupational Radiation Dose at DOE 3-11

whole-body survey. All three of the employees 

were placed on diagnostic bioassay. Initial nasal 

swipes indicated that the exposure could be in 

excess of 10 rem CEDE. The TEDE reported to 

DOE for two of the individuals was 8.170 rem and 

10.197 rem as a result of the intake of plutonium. 

There was a Type B investigation of this incident 

that determined the direct cause of the accident 

was the release of airborne contamination from a 

degraded package containing cellulose material 

and Pu-238 residues. A Corrective Action Plan 

(CAP) to address the Type B Board’s Judgement 

of Needs will be developed and implemented. 

The CAP will be submitted for approval and 

corrective actions will be tracked to completion 

and documented.

For more information, see the occurrence report 

ALO-LA-LANL-TA55-2003-0017. The investigation 

report is available at https://reports.eh.doe.gov/

csa/accidents/typeb/typeb.html (authorization 

required).

3.3.2 Doses in Excess of Administrative 

Control Level

The RCS [7] recommends a 2 rem (20 mSv) ACL 

for TEDE, which should not be exceeded without 

prior DOE approval. The RCS recommends that 

each DOE site establish its own, more restrictive 

ACL that would require contractor management 

approval to be exceeded. The number of 

individuals receiving doses in excess of the 2 rem 

(20 mSv) ACL is a measure of the effectiveness of 

DOE’s radiation protection program.

As shown in Exhibit 3-10, three individuals 

received a TEDE above 2 rem (20 mSv) during 

2003. Two of the three were also in excess of 5 

rem (50 mSv) as described in the previous section. 

All three individuals received doses in excess 

of 2 rem (20 mSv) at LANL. The third individual 

was reported to have received 2.4 rem (24 mSv) 

TEDE, which included 1.731 rem (17.31 mSv) from 

neutrons. Neutron dose is more common at LANL 

due to the nature of the work involving plutonium 

at this facility. The dose was anticipated and 

formally approved by the LANL ALARA Steering 

Committee prior to incurring the dose; therefore, 

no occurrence report was required for this event.

3.3.3 Internal Depositions of Radioactive 

Material

As shown in Exhibit 3-9, some of the highest doses 

to individuals have been the result of intakes 

of radioactive material. For this reason, DOE 

emphasizes the need to avoid intakes and tracks 

the number of intakes as a performance measure.

The number of internal depositions of radioactive 

material (otherwise known as worker intakes), 

collective CEDE, and average measurable CEDE for 

1999-2003 are shown in Exhibit 3-11. The number 

of internal depositions increased by 6% from 2,418 

in 2002 to 2,572 in 2003, while the collective CEDE 

increased by 38%. Due to the increase in the 

collective CEDE and the increase in the number of 

internal depositions, the average measurable CEDE 

increased by 32% from 0.028 rem (0.28 mSv) in 

2002 to 0.037 rem (0.37 mSv) in 2003.

Exhibit 3-10:

Number of Doses in Excess of the DOE 2 Rem ACL, 1999-2003.

1999 2000 2001 2002 2003

0

1

2

3

4

5

Year

3 3

Number of Individuals

Exceeding 2 Rem (TEDE)

1 1

Combination of Internal and External

Dose (CEDE+DDE) accrued during

the monitoring year.

LEGEND

Internal Dose (CEDE) Accrued during

Monitoring Year

External Dose (photon & neutron)

accrued during monitoring year

3
3-12 DOE Occupational Radiation Exposure 

Exhibit 3-11:

Number of Internal Depositions, Collective CEDE, and Average Measurable CEDE (Graph), 1999-2003.

The number of internal depositions of radioactive 

material for 2001 through 2003 is also shown 

in Exhibit 3-12. The internal depositions were 

categorized into eight radionuclide groups. 

Intakes involving multiple nuclides are listed as 

“mixed”. Nuclides where fewer than 10 individuals 

had intakes each year over the 3-year period 

are grouped together as “other. ” Only those 

records with internal dose greater than zero are 

included in this analysis. It should be noted that 

the different nuclides have different radiological 

properties, resulting in varying minimum levels of 

detection and reporting.

The 38% increase in the collective CEDE from 

69 person-rem (690 person-mSv) in 2002 to 95 

person-rem (950 person-mSv) in 2003 was due to 

a nearly four-fold increase in internal dose from 

plutonium. The main contributor to this increase 

was the two exposures in excess of 5 rem (50 mSv) 

at LANL (see Section 3.3.1). Mound and Rocky 

Flats also reported increases in internal dose 

from plutonium from 2002 to 2003. Internal dose 

from other radionuclides decreased or essentially 

remained the same from 2002 to 2003.

Exhibit 3-12:

Number of Internal Depositions, Collective CEDE, and Average Measurable CEDE by Nuclides (Data), 2001-2003.

������������������

������������

���������������

������������

�����������������������

��������������������

� �������������������������������������������������������������������������������������������������������������������������������������

�������������������������������������������������������������������������

1999 2000 2001 2002 2003

0

500

1000

1500

2000

2500

3000

Year

2,463

2,277 2,362 2,418

2,572

1999 2000 2001 2002 2003

0

50

100

150

200

Year

153

181

59 69

95

1999 2000 2001 2002 2003

0.000

0.020

0.040

0.060

0.080

0.100

Year

0.062

0.079

0.025 0.028

0.037

�����������������������������������������������������������������

� ���������������������������������������������������������������������������������������������������������������

����

�������

������������������

������������

���������������

������������

������������������

�������������������������

��������������������

���������

�������

�������

���������

�������������

�����

�����

������

���

��

��

�����

���

��

��

��

�����

�����

�����

�����

������

������

�����

�����

�����

������

�����

�����

�����

�����

�����

�����

�����

�����

�����

���� ���� ���� ���� ���� ����

���

�

��

�����

���

��

��

�

�����

�����

�����

�����

������

�����

�����

�����

�����

������

�����

�����

�����

�����

�����

�����

�����

�����

�����

����

���

��

��

�����

���

��

��

��

�����

����

�����

�����

�����

������

�����

�����

�����

�����

������

����

�����

�����

�����

�����

�����

�����

�����

�����

�����
2003 Report Occupational Radiation Dose at DOE 3-13

Exhibit 3-13:

Internal Dose Distribution from Intakes, 1999-2003.

During the past 5 years, there have been several 

intakes from plutonium or uranium in excess of 2 

rem (20 mSv) each year, with some of the doses in 

excess of 5 rem (50 mSv) (see Exhibit 3-9). While 

the number of internal depositions above 2 rem 

(20 mSv) has been few, they have contributed 

significantly to the collective internal dose for 

the years 1999 and 2000. No such intakes were 

reported for 2001 and 2002, and the reduction in 

the collective CEDE reflects this fact. For 2003, two 

intakes resulted in doses in excess of 5 rem (50 

mSv) which resulted in a significant increase in 

collective CEDE.

The highest collective CEDE and number of 

depositions in 2003 are due to uranium intakes. 

Almost all of the collective dose from uranium 

(99%) occurred at the Oak Ridge Y-12 facility 

during the continued operation and management 

of Enriched Uranium Operations (EUO) facilities 

at the site. The highest average measurable CEDE 

in 2003 is from plutonium, primarily due to the two 

high doses at LANL, but increases in the collective 

CEDE from plutonium at Mound and Rocky Flats 

also contributed. 

Because relatively few workers receive measurable 

internal dose, fluctuations in the number of 

workers and collective CEDE can occur from year 

to year.

Exhibit 3-13 shows the distribution of the internal 

dose from 1999 to 2003. The total number of 

individuals with intakes in each dose range is the 

sum of all records of intake in the subject dose 

range. The internal dose does not include doses 

from prior intakes (legacy AEDE dose). Individuals 

with multiple intakes during the year may be 

counted more than once. Doses below 0.020 rem 

(0.20 mSv) are shown as a separate dose range to 

show the large number of doses in this low-dose 

range. There were two internal doses above 2 

rem (20 mSv) in 2003 and these two individuals 

received doses in excess of 5 rem (50 mSv).

������

�����

������

�����

������

�����

������

�����

������

�����

����

���

����

���

����

���

����

��� ����

�����

������

������

���������������� �������������

����

������������

�������������������������������������������������������������������

����

�����

������ �

����������������������������������������������������������������������������������������������������������������������������

��������������������������������������������������������������������������������������������������

���� ����� ��� ��� �� �� �� �� � � ����� �������

���� ����� ��� ��� �� � � � ����� �������

���� ����� ��� �� �� � � ����� ������

���� ����� ��� ��� �� � ����� ������

���� ����� ��� ��� �� � � � ����� ������
3-14 DOE Occupational Radiation Exposure 

The internal dose records indicate that 

the majority of the intakes reported 

are at very low doses.

Over the 5-year period, internal 

doses accounted for only 11% of the 

collective TEDE.

The internal dose records indicate that the 

majority of the intakes reported are at very low 

doses. In 2003, 63% of the internal dose records 

were for doses below 0.020 rem (0.20 mSv). Over 

the 5-year period, internal doses from intakes 

accounted for 11% of the collective TEDE, and 8% 

of the individuals who received internal dose were 

above the monitoring threshold specified (100 

mrem or 1 mSv) in 10 CFR 835.402(c).

The internal dose distribution can also be shown 

in terms of the percentage of the collective dose 

delivered above certain dose levels. Exhibit 3-14

shows this information for the CEDE for each 

year from 1999 to 2003. While the fluctuations in 

internal dose prohibit definitive trend analysis, it is 

evident from the graph that from 1999 to 2000, there 

was an increase in the percentages above 2 rem 

(20 mSv), which was due to the individuals who 

exceeded the DOE annual limits. In 2000, the

percentages above 2 rem (20 mSv) were 

dominated by the three doses in excess of the DOE 

annual limit that occurred at LANL. For 2001 and 

2002, the percentage of internal dose above each 

dose range decreased dramatically because of the 

lack of any internal doses above 2 rem (20 mSv).

In 2003, there were two internal doses above 5 rem 

(50 mSv), which increased the percentages for 

each dose range by about 18%. The distribution 

of internal dose by site and nuclide for 2003 is 

presented in Appendix Exhibit B-21.

Exhibit 3-14:

Distribution of Collective CEDE vs. Dose Value, 1999-2003.

2003 2002 2001 2000 1999

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage of CEDE Above Dose Values

Year

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

2.0 rem

1.0 rem

0.5 rem

3.0 rem

0.1 rem

4.0 rem

5.0 rem

Dose Value

54%

21%

19%

18%

18%

18%

18%

82%

49%

22%

6%

6%

4%

4%

80%

62%

60%

60%

60%

60%

60%

39%

3%

0%

0%

0%

0%

42%

9%

5%

0%

0%

0%

0%

0%
2003 Report Occupational Radiation Dose at DOE 3-15

Note: More complete details for each site, 

Operations/Field Office, and reporting 

organization can be found in Appendix B.

Exhibit 3-15:

Collective TEDE by Site for 2001-2003.

When examining trends involving internal 

dose, several factors should be considered. 

Some of the largest changes in the number 

of reported intakes over the years resulted 

from changes in internal dosimetry practices. 

Periodically, sites may implement new technology 

or change monitoring practices or procedures, 

which may involve increasing the sensitivity of 

the detection equipment, thereby increasing 

the number of individuals with measurable 

internal doses. Conversely, sites may determine 

that internal monitoring is no longer required 

due to historically low levels of internal dose 

or a decreased potential for intake. There are 

relatively few intakes each year, and the CEDE 

method of calculating internal dose can result 

in large internal doses from the intake of longlived nuclides. This can result in variability of the 

internal dose data from year to year.

3.4 Analysis of Site Data

3.4.1 Collective TEDE by Site and 

Operations/Field Offices

The collective TEDE for 2001 through 2003 for 

the major DOE sites and Operations/Field Offices 

is shown in Exhibit 3-15. A list of the collective 

TEDE and number of individuals with measurable 

TEDE for the DOE Sites and Operations/Field 

Offices is shown in Exhibit 3-16. Operations/Field 

Office dose is shown separately from the site dose 

wherever it is reported separately (see Appendix 

Exhibit A-2). Other small sites and facilities that 

do not contribute significantly to the collective 

dose are included within the numbers shown for 

“Ops. and Other Facilities.” The collective TEDE 

increased by 6% from 1,360 person-rem (13.60 

person-Sv) in 2002 to 1,445 person-rem (14.45 

person-Sv) in 2003, with six of the highest dose 

sites (Hanford, Savannah River, Los Alamos, Rocky 

Flats, Oak Ridge, and Idaho) contributing 80% of 

the total DOE collective TEDE.

Oak Ridge

Operations

Savannah

River Site

Oak Ridge

Site

Chicago

Operations Portsmouth

Gas. Diff. Plant

Mound

Plant

Paducah

Gas. Diff.

Plant

Stanford Linear

Accel. Center

(SLAC)

 Fermi

 National

 Accelerator

 Laboratory

Fernald Envir.

Mgmt. Project

Idaho

National

Engineering

Laboratory Hanford

 Site

Rocky

Flats

Plant

Los Alamos

National

Laboratory

Nevada

Test Site

Oakland

Operations

Lawrence Livermore

National Laboratory

Argonne

West

Sandia

National

Laboratory

Albuquerque

 Operations

Pantex

Plant

Argonne

East

Brookhaven

National

Laboratory

West

Valley

Grand

Junction

Ohio

Operations

Lawrence Berkeley

National Laboratory

Battelle

Memorial

Institute

DOE

Headquarters

Collective

TEDE

(person-rem)

LEGEND

2001 2002 2003

0

100

200
3-16 DOE Occupational Radiation Exposure 

Exhibit 3-16:

Collective TEDE and Number of Individuals with Measurable TEDE by Site, 2001-2003.

�����������

������������

���� ����

���������������

������������

�����������

����������

�����������

����������

�����������

����������

���������������

������������

���������������

���������

���� ���

����

��� ���

����� �����

���� ���

���� ���

��� ���

���� ���

���� ���

���� ���

���� ���

���� �����

��� ��

��� ��

��� ��

���� ���

��� ���

��� ��

����� �����

��� ��

��� ��

��� ��

���� ���

���� ���

��� ���

���� ���

����� �����

����� �����

����� �����

������� ������

�����������

�������

������

�����

������

�������

���������

����

�����������

��������

��������������

������

�������������������������

�������������������������������

�����������������

��������������������������

���������������

�������������������������

����������������������������������

����������������������������������

���������������������������

������������������������������������

����������������

������������������������

��������������������������

����������

����������������������

�������������������������

������������������������������������

�������������������������������������

����������������������������������

������

�������������������������

��������������

����������������������������������

������������������������������

�������

�������������������������

��������������������������������������

��������������������������������

�������

�����������

�����������

�����������������������������������

������������

�������������������������

�����������������������������������������������������������

�������������������������������������������������������������������

��� ���

����� �����

���� ���

��� ���

��� ���

���� ���

���� ���

���� ���

���� ���

��� �

���� �����

��� ��

��� ��

��� ��

���� ���

��� ��

��� ���

����� �����

��� ���

��� ��

��� ��

���� ���

���� ���

��� ���

���� ���

����� �����

����� �����

����� �����

������� ������

��� ��

����� �����

���� ���

��� ��

��� �

��� ���

���� ���

���� ���

���� ���

���� ���

��� �

��� �

����� �����

��� ��

��� ���

��� ��

���� ���

��� ��

��� ���

����� �����

��� ���

��� ��

��� ��

���� ��

���� ���

��� ��

���� ���

����� �����

����� �����

����� �����

������� ������
2003 Report Occupational Radiation Dose at DOE 3-17

Exhibit 3-17:

Number with Measurable Dose, Collective TEDE, and Average Measurable TEDE by Labor Category, 2001-2003.

Exhibit 3-18:

Graph of Collective TEDE by Labor Category, 2001-2003.

3.4.2 Dose by Labor Category

DOE occupational exposures are tracked by labor 

category at each site to facilitate identification 

of exposure trends, which assists management in 

prioritizing ALARA activities. Worker occupation 

codes are reported in accordance with DOE 

M 231.1-1 and are grouped into major labor 

categories in this report. The collective TEDE 

for each labor category for 2001 through 2003 is 

shown in Exhibits 3-17 and 3-18. Technicians and 

production staff have the highest collective TEDE 

and average measurable TEDE for the past 3 years 

because they generally handle more radioactive 

sources than individuals in the other labor 

categories. In 2003, 51% of the technician dose 

was attributed to radiation protection technicians, 

and 76% of the dose to production personnel is 

attributed to plant operators.

In 2003, the “unknown” category had the highest 

number of individuals with measurable TEDE. 

Ninety percent of the dose in the “unknown” 

category for 2003 is attributed to LANL. 

Currently, the LANL computer system does not 

maintain the data necessary to report occupation 

codes in accordance with DOE M 231.1-1. Other 

sites also report individuals with an occupation 

code of “unknown.” Typically, these workers are 

subcontractors or temporary workers. Information 

concerning these workers tends to be limited.

An examination of internal dose from intake by 

labor category from 2001 to 2003 is presented in 

Appendix Exhibit B-19. In addition, Appendix 

Exhibit B-20 shows the TEDE distribution by labor 

category and occupation for 2003.

�����������

������������

��������

����������

�����

����������

����������

�������

�����������

���������

�������

������

�����������������������������������������������������������������

��������������

���������������������� ���������������������������� ������������������������

���� ���� ���� ���� ���� ����

�

�����

���

�����

�����

�����

�����

���

�����

���

�����

������

���

����

����

�����

�����

�����

�����

����

�����

���

�����

�������

���

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

���� ���� ����

�

�����

���

�����

�����

�����

�����

���

�����

���

�����

������

���

����

����

����

�����

�����

�����

����

�����

���

�����

�������

���

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�

�����

���

�����

�����

�����

�����

���

�����

���

�����

������

���

�����

����

����

�����

�����

�����

����

�����

����

�����

�������

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

Technicians

Transport

Unknown

Scientists

Service

Production

Misc.

Management

Laborers

Construction

Agriculture

350

300

250

200

150

100

50

0

0

50

100

150

200

250

300

350

2001

2002

2003

Collective TEDE (person-rem)

Labor Category
3-18 DOE Occupational Radiation Exposure 

Exhibit 3-20:

Number with Measurable Dose, Collective TEDE, and Average Measurable TEDE by Facility Type, 2001-2003.

Exhibit 3-19:

Graph of Collective TEDE by Facility Type, 2001-2003.

3.4.3 Dose by Facility Type

DOE occupational exposures are tracked by 

facility type at each site to better understand 

the nature of exposure trends and to assist 

management in prioritizing ALARA activities. The 

contributions of certain facility types to the DOE 

collective TEDE is shown in Exhibits 3-19 and 3-20. 

The collective dose for each facility type at each 

major site of each DOE Operations/Field Office 

from 2001 to 2003 is shown in Appendix Exhibit 

B-7. An examination of internal dose from intake 

by facility type and nuclide for 2001 to 2003 is 

presented in Appendix Exhibit B-17.

The collective TEDE for 2001 through 2003 

was highest at weapons fabrication and testing 

facilities. Fifty-two percent of this dose was 

accrued at Rocky Flats in 2003, with 22% at 

Savannah River and 16% at the Oak Ridge Y-12 

facility. It should be noted that, although weapons 

fabrication and testing facilities account for the 

highest collective dose, Rocky Flats and Savannah 

River account for the majority of this dose, and 

these sites are now primarily involved in nuclear 

materials stabilization and waste management. 

See Section 3.5 for information concerning the 

current activities at these sites.

Weapons Fab. & Test.

Waste Proc./Mgmt.

Research, General

Research, Fusion

Reactor

Other

Maint. and Support

Fuel Processing

Fuel Fabrication

Fuel/Uran. Enrichment

Accelerator

450

400

350

300

250

200

150

100

50

0

0

50

100

150

200

250

300

350

400

450

2001

2002

2003

Collective TEDE (person-rem)

Facility Type

�������������

���������������������� ���������������

������������

���� ����

������������������������

�����������������������������������������������������������������

�����������

�����������������������

����������������

���������������

�����������������������

�����

�������

����������������

�����������������

����������������������

������������������������

������

���� ���� ���� ���� ����

���

���

���

�����

�����

�����

���

���

�����

�����

�����

������

����

����

����

����

����

�����

����

����

���

�����

�����

�����

�������

����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

���

���

�����

�����

�����

���

���

�����

�����

�����

������

����

����

����

����

�����

�����

����

���

�����

�����

�����

�������

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

���

���

�����

�����

�����

���

�����

���

�����

�����

������

����

����

����

����

�����

�����

����

�����

���

�����

�����

�������

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����
2003 Report Occupational Radiation Dose at DOE 3-19

Exhibit 3-21:

Criteria for Radiation Exposure and Personnel Contamination Occurrence Reporting.

3.4.4 Radiation Protection Occurrence 

Reports

Sites are required to report certain unusual or 

off-normal occurrences involving radiation under 

DOE Order 231.1A. These reports are submitted 

to Occurrence Reporting and Processing System 

(ORPS) in accordance with the reporting criteria of 

DOE M 231.1-2. Two of the occurrence categories 

are directly related to occupational exposure 

and are required to be reported under Group 6 

as “Subgroup C” and “Subgroup D” occurrences. 

Subgroup C reports radiation exposure occurrences,

and Subgroup D reports personnel contamination

occurrences. DOE Manual 231.1-2 became 

effective in August 2003 and replaced DOE 

Manual 232.1-1A. The new manual contains 

several changes in the reporting requirements for 

occurrence reports. The occurrence reporting 

requirements for DOE M 231.1-2 are summarized in 

Exhibit 3-21.

The number of reports submitted to ORPS is

usually indicative of breaches or lapses in

radiation protection practices resulting in

unanticipated radiation exposure or 

contamination of personnel or clothing. 

Significant increases or decreases in the number 

of occurrences reported may reflect trends in 

radiation exposures, the effectiveness of DOE 

radiation protection programs, or changes to 

the reporting procedure or thresholds. However, 

changes in the number of radiation exposure and 

confirmation occurrences reported from year to 

year may reflect statistical variability rather than 

any performance trend.

It is important to note that reports are submitted to 

ORPS for an occurrence or event. In some cases, one 

event could result in the contamination or exposure 

of multiple individuals. In ORPS, this is counted as 

one occurrence, even though multiple individuals 

were exposed. In addition, one report may involve 

the roll up of similar or multiple occurrences. For the 

analysis included in this report, only the number of 

occurrences is considered. Also, it should be noted 

that some occurrences are reported based on an 

initial estimate of exposure, but may be recategorized 

later pending the receipt of the final determined 

exposure.

��������

��������

��������������

������

�������� �����������������������

������������

��������

��������� ������� � �����������������������������������������������������������������������������

�������� ��������������������������������������������������������������������������

���������� ��������������������������������������������������������������������������

�������������������������������������

���������� � ������������������������������������������������������������������������

�����������������������������������������������������������������������������

� ����������������������������������������������������������������������

������������������������������������������������������������������������������

������������������������������������������������������������������������������

������������������

� ���������������������������������������������������������������������

��������������������������������������������������������������������������

������������������������������

��������� ������� � �������������������������������������������������������������������������������

������������� ����������������������������������������������������������������������������������

���������� �����������������������������������������������������������������

���������� � �������������������������������������������������������������������������

���������������������������������������������������������������������������

�����������������������������������������������������������������������������

�������������������������������������

����� � ���������������������������������������������������������������������������

������������������������������������������������������������������������������

����������������������������������������������������������������������������

����������������������������������������������������������������������������

����������������������������������������
3-20 DOE Occupational Radiation Exposure 

Exhibit 3-22:

Number of Radiation Exposure Occurrences, 1999-2003.

The number of radiation exposure 

occurrences decreased by 44% from 

2002 to 2003.

The number of occurrences reported under 

Personnel Radiological Protection is broken 

into two subcategories: Radiation Exposure, and 

Personnel Contamination. Results for those two 

subcategories are presented in Exhibits 3-22 and 

3-24. 

3.4.4.1 Radiation Exposure Occurrences

Two criteria for reporting Radiation Exposure 

occurrences are when individuals are exposed

to radiation above anticipated levels, or when

the resulting exposure exceeds 100 mrem

(0.1 rem) (1 mSv) external (whole-body, skin, or 

extremity) or internal. The number of radiation 

exposure occurrences decreased by 44% from 18 

in 2002 to 10 in 2003 as shown in Exhibit 3-22. The 

number of people involved in radiation exposure

occurrences reported in 2003 (14 people) was 

44% less than those in 2002 (25 people). 

One of the internal exposures reported in 2003 

occurred in 2000 and another one occurred in 

2002. In one case (see Occurrence Report

ALO-LA-LANL-CMR-2003-002), an internal dose 

was discovered during a routine bioassay program 

for an individual working in an administrative 

area. The employee had not been involved in a 

radiological incident and a thorough investigation 

was performed including: (1) extensive 

radiological surveys of the employee’s office 

resulting in no detectable activity; and (2) review 

of bioassay results for co-workers during the 

same time period that revealed no uptake. Thus, 

there was no evidence that an intake actually 

occurred. During the same time period, at the 

analysis lab, a number of high-priority samples 

containing plutonium were being processed and 

an unexplained increase in the number of blanks 

measuring above minimum detectable activity 

occurred. Although it could not be verified, it 

was determined that cross-contamination in the 

analysis was the likely cause. An intake of 0.5 rem 

CEDE for Pu-238 was assigned to the employee 

for CY 2000. In the other case (see RFO-KHLLSOLIDWST-2003-0012), routine bioassay results 

were positive for plutonium for one individual 

following a continuous air monitor alarm incident. 

Six of seven follow-up bioassay samples over a 

4-month period confirmed contamination. An 

internal dose of 660 mrem was assigned to the 

individual for CY 2002.

There were zero Unusual Events recorded for 

radiation exposure occurrences in 2003 compared 

to one in 2002. 

In one radiation exposure occurrence for 2003 

(see Occurrence Report RL-PHMC-PFP-2003-0015), 

a failed glovebox glove resulted in two workers 

receiving an intake of americium and plutonium 

resulting in a dose in excess of 100 mrem CEDE. 

Nasals smears indicated contamination and after 

nose blows, results were less than detectable. A 

chest count for one worker detected americium-241 

and medical treatment (DTPA) was administered.

In another case, a small spill occurred in a room 

with 15 employees (see Occurrence Report 

ALO-LA-LANL-TA55-2003-002). All 15 employees 

submitted nasal smears resulting in no detectable 

contamination. Bioassay samples were also 

submitted and one employee received an intake of 

plutonium resulting in a dose of 219 mrem CEDE. 

1999 2000 2001 2002 2003

0

5

10

15

20

25

Number of Occurrences

Year

12

1

14

1

16 17

1

10

LEGEND

Unusual Occurrence

Off-Normal

0

0
2003 Report Occupational Radiation Dose at DOE 3-21

The number of Personnel Contamination 

occurrences reported decreased by 6% 

between 2002 and 2003.

In another case (see Occurrence Report

RFO-KHLL-371OPS-2003-0009), an employee was 

repositioning an intake hose when it slipped 

out of his hand resulting in a release of airborne 

contamination (plutonium). After submitting 

bioassay samples, three of the six employees 

present at the time were determined to have 

received contamination that resulted in CEDE 

doses of 330 mrem, 0 mrem, and 52 mrem. 

None of the 72 radiation exposure occurrence 

reports submitted to the ORPS between 1999 and 

2003 involved exposure to minors, members of the 

public, or pregnant workers.

Exhibit 3-23 shows the breakdown of occurrences 

for radiation exposure by site for the 5-year period 

1999-2003. Seventy-four percent of the 2003 

radiation exposure occurrences were reported 

by six sites: Savannah River, Rocky Flats, Oak 

Ridge, Los Alamos, Mound, and Hanford. During 

2003, Hanford and Rocky Flats had increases in 

reported occurrences, Savannah River and Mound 

experienced decreases, and Los Alamos and Oak 

Ridge recorded the same number as 2002. 

Exhibit 3-23:

Radiation Exposure Occurrences by Site, 1999-2003.

3.4.4.2 Personnel Contamination Occurrences

Personnel contamination occurrences are reported 

whenever personnel, clothing, or personal items 

are contaminated above threshold levels, generally 

five times the unconditional release limits. The 

number of personnel contamination occurrences 

reported decreased 6% from 250 in 2002 to 235 

in 2003. The number of personnel contamination

occurrences reported has decreased by 22% from 

300 in 1999 to 235 in 2003 (see Exhibit 3-24). Four 

personnel contamination occurrences in 2003 were 

classified as an Unusual Event compared to one in 

2002. The first Unusual Event (Occurrence Report

ORO-BJC-X10ENVRES-2003-0016) occurred when 

Exhibit 3-24:

Number of Personnel Contamination Occurrences, 1999-2003.

two employees wore contaminated personal 

clothing home. Although the field trailer and 

vehicles used by the employees had surface 

contamination, no contamination was found in 

either of their homes or personal vehicles. The 

second Unusual Event (Occurrence Report

ORO-BWXT-Y12SITE-2003-0017) was a uranium 

fire inside a glovebox. The event was considered 

an Operational Emergency; therefore, everyone 

in the building was evacuated and sheltered in 

place. Two employees received clothing and shoe 

19 (26%)

13 (18%) 2 (3%)

9 (13%)

12 (17%)

12 (17%)

5 (7%)

Savannah

 River

Mound LANL

Rocky

Flats

Oak Ridge

Site

Hanford

All Other

1999 2000 2001 2002 2003

0

100

200

300

400

Number of Occurrences

Year

297

3

248

2

279

4

249

1

231

4

LEGEND

Unusual Occurrence

Off-Normal
3-22 DOE Occupational Radiation Exposure 

Exhibit 3-25:

Personnel Contaminations by Affected Area, 1999-2003.

contamination and one other received skin and 

hair contamination. The third Unusual Event 

(Occurrence Report RFO-KHLL-371OPS-2003-0011)

also involved a glovebox fire. Workers used 8-10

fire extinguishers to put out the fire, but it

re-ignited. Fire fighters were called in and four 

fire fighters received skin contamination. It was 

determined that contamination was spread from 

the fire fighter’s gear to exposed skin during the 

doffing process. The fire fighters were wearing 

“bunker gear” instead of the traditional anti-C 

clothing making doffing more difficult. The use 

of respirators prevented the fire fighters from 

receiving any radiological material intake or 

significant dose. Finally, the fourth Unusual Event 

(Occurrence Report RFO-KHLL-PUFAB-2003-0012) 

occurred when a release resulted in contamination 

in several areas of a building. Precautionary 

nasal/mouth smears were administered for 36 

individuals working without respiratory protection 

in areas nearby, and for six individuals wearing 

respirators in the immediate area. The six in the 

immediate area received contamination on their 

anti-C clothing and/or boots. However, due to 

excellent doffing techniques, there was no skin 

contamination. Bioassay samples indicated 12 

individuals received internal radiological uptakes; 

however, none exceeded the administrative control 

level of 750 mrem per year. 

In one case (ALO-LA-LANL-TA55-2003-0017) 

reported as a personnel contamination 

occurrence, two employees received an internal 

dose from plutonium. The two employees were 

performing inventories of items on shelves in a 

high-radiation area. The employees had completed 

two shelves, self monitoring after each, and no 

contamination was detected. While inventorying 

the third shelf, a continuous air monitor in the 

room alarmed. The two employees immediately 

exited the room, monitored themselves and 

upon finding contamination summoned the 

responsible RCT for assistance. The two employees 

received clothing and skin contamination and 

contamination was also found on the anti-c 

clothing of the RCT performing the whole-body 

survey. All three employees were placed on 

diagnostic bioassay. Initial nasal swipes indicated 

that the exposure could be in excess of 10 rem 

CEDE. The TEDE reported to DOE for two of the 

individuals was 8.170 rem and 10.197 rem as a 

result of the intake of plutonium (see Section 

3.3.1).

There was a Type B investigation of this incident 

that determined the direct cause of the accident 

was the release of airborne contamination from a 

degraded package containing cellulose material 

and Pu-238 residues. A CAP to address the Type 

B Board’s Judgement of Needs will be developed 

and implemented. The CAP will be submitted to 

Los Alamos Site Office (LASO) for approval and 

corrective actions will be tracked to completion 

and documented.

It should be noted that the totals for Exhibits 3-24,

3-25, and 3-26 are not equivalent because some 

occurrences involve more than one affected area, 

and some occurrences involve more than one 

individual. Exhibit 3-24 presents the total number 

of occurrences. Exhibit 3-25 presents the number of 

personnel contaminations by affected area and may 

count occurrences more than once if there is more 

than one affected area involved in the occurrence. 

Exhibit 3-26 shows the number of individuals by 

affected area. Individuals may be counted more 

than once if they have more than one affected area.

Exhibit 3-26:

Number of Individuals Contaminated by Affected Area in 2003.

0

100

200

300

Number of Occurrences

Affected Area

105

86

123 109

166

96 102 107

142

268

88 70

138 125

164

Skin Clothing Shoe

1999 2000 2001 2002 2003 1999 2000 2001 2002 2003 1999 2000 2001 2002 2003

����������������������� ��

�������������������������������������� ���

���������� ���

����������������� ��

�������������� ��

������������������ ��

������������������������� �

������������� �����������

������������
2003 Report Occupational Radiation Dose at DOE 3-23

Exhibit 3-27:

Personnel Contamination Occurrences by Site, 1999-2003.

Exhibit 3-25 compares the personnel 

contamination occurrences by the affected area. 

The combination of skin, clothing, and shoes 

decreased from 2002 to 2003 while all other areas 

of personnel contamination increased. Hand 

contaminations made up approximately 35% 

of the skin contamination incidents with right 

hand contamination slightly more than left. One 

case (RFO-KHLL-370OPS-2003-004) recorded 

hand and face contamination. After performing 

glovebox operations and before exiting the area, 

an employee self monitored anti-c gloves and 

detected no contamination. The employee went 

on break, returned to work in a different area, and 

upon exiting the area discovered contamination 

on his hands, face, and ink pen. Radiological 

surveys were performed in all areas the employee 

entered during break. Contamination was 

found only on the newspaper the employee had 

been reading. It was determined that due to 

inadequate self-monitoring of personal items, the 

contaminated “ink pen” transferred contamination 

to the hands, face, and newspaper.

Although 235 personnel contamination

occurrences were reported in 2003 (a 6% decline 

from 2002), 297 individuals were contaminated on 

the skin, clothing, and/or shoes as shown in Exhibit 

3-26, which represents a 4% decline from the 309 

individuals in 2002.

The combination of skin and clothing (and many 

of the skin, clothing, and shoe) contamination 

usually involved situations where the 

contamination on the outer protective clothing 

was inadvertently transferred to the skin. Three 

modes of contamination are common among 

these occurrences. The first is personnel error in 

“doffing” or removing protective clothing resulting 

in transferring contamination to exposed skin. 

The second involves the transference or “wicking” 

of contaminated liquid through the protective 

clothing to the skin. This can occur as a result 

of kneeling in or leaning against wet spots or 

from sweat-soaked clothing. The third common 

cause of skin contamination occurrences is 

from residual contamination remaining on the 

protective clothing after laundering. All of these 

problems have been reported in past years and the 

frequency of their occurrence has not changed 

significantly. 

Exhibit 3-27 shows the personnel contamination

occurrences for 1999-2003. The overall number of 

personnel contamination occurrences continued 

on a downward trend with two of the top five 

sights experiencing a decrease and the other three 

experiencing a slight increase from the previous 

year.

Idaho

LANL

Hanford

Savannah River

All Other

Oak Ridge Site

88 (7%)

132 (10%)

382 (29%)

188 (14%)

347 (26%)

180 (14%)
3-24 DOE Occupational Radiation Exposure 

Exhibit 3-28:

Radiation Exposure Occurrences by Root Cause, 2001-2003.

Exhibit 3-29:

Personnel Contamination Occurrences by Root Cause, 2001-2003.

0

2

4

6

8

10

Number of Occurrences

Root Cause

3 3

2

4

6

2

3

0 1

5

8

2

1 1

3

Management

Problem

Personnel

Error

Equipment/

Material

Unknown Source

of Radiation

All Other

2001 2002 2003 2001 2002 2003 2001 2002 2003 2001 2002 2003 2001 2002 2003

0

20

40

60

80

100

0

20

40

60

80

100

Number of Occurrences

Root Cause

93

61

70

40

56

34

10 9

24

96

73

49

44 51

58

Management

Problem

Personnel

Error

Equipment/

Material

Unknown Source

of Radiation

All Other

2001 2002 2003 2001 2002 2003 2001 2002 2003 2001 2002 2003 2001 2002 2003

3.4.4.3 Occurrence Cause

Exhibits 3-28 and 3-29 provide a breakdown of 

radiation exposure occurrences and personnel 

contamination occurrences by their root cause. 

For the ORPS, the “root-cause” is defined as that 

which, if corrected, would prevent recurrences. 

Only four significant root causes are considered 

here (management problem, personnel error, 

equipment/material, and unknown source of 

radiation); other causes are included in the 

category entitled “All Other.”

In 2003, three of the root cause categories 

(“Management Problem,” “Personnel Error,” and 

“Unknown Source of Radiation”) cited two 

occurrences each making up six (60%) of the 

radiation exposure occurrences reported. The 

number of radiation occurrences of “Equipment 

or Material” failure increased from zero in 2002 to 

one (10%) in 2003. The “All-Other” category made 

up 30% of the root causes and had the largest 

increase from one occurrence in 2002 to three in 

2003.

For personnel contamination occurrences, three 

categories reported increases in the “root cause” 

from 2002 to 2003. The largest increase occurred 

in “Equipment/Material” with an increase of 167% 

over 2002. The other areas that saw increases 

were “Management Problem” with a 15% increase 

and “All Other” with a 14% increase over the 

previous year. “All Other” includes the categories 

Design Problems, Procedure Inadequacy, Training 

Deficiency, and None (no root cause reported). 

The remaining “root cause” categories declined. 

“Personnel Error” had the largest decrease of 39% 

less than 2002. “Unknown Source of Radiation” 

decreased 33% from 2002 to 2003 and includes 

unknown sources, as well as known sources from 

“legacy” contamination. 

Further information concerning ORPS can be 

obtained by contacting Eugenia Boyle of EH-32, or 

the ORPS web page at:

http://www.eh.doe.gov/paa/orps.html
2003 Report Occupational Radiation Dose at DOE 3-25

Exhibit 3-30:

Activities Significantly Contributing to Collective TEDE in 2003 for Six Sites.

400

350

300

250

200

150

100

50

0

1999 2000 2001 2002 2003

����������������������������

������������������������������������������������������

��������

���������������������������������������������������������

�����������������������������������������������������

������� ������������������������������������������������

�����������������������������������������������������

�������������������������������������������� ����������������

��������������������������������������������������������

��������������������������������������������������������

����������������������������������������������������������

����������������������������������������������������

���������������������������������������������������������

����� �����������������������������������������������

��������������������������������������������������

���������������������������������������������������������

������������������������������������������������� �������

���������������������������������������������������������

����������������������������������������������������

������������������������������������������������������

��������������������������������������������������������

����������������������������������� ��������������������

������������������������������������������������

����������������������������������������������������

������������������������������������������������������

�����������������������������������������������������

�����������������������������������������������

�������������������������������������������������������

�������������������������������������������������������

����������������������� ����������������������������������

��������������������������������������������������������

��������������������������������������������������������

��������������������������������������������������

�������������������������������������������������������������

�������������� ���������������������������������������������

����������������������������������������������������������

��������������������������������������������������������������

������������������������������������������������������������

�����������������������������������������������������������

��������������

������������������������ �������������������������������������

��������������

��� ���� ���

����� ����

����������

����� ����

�������

�����

����

�������

3.5 Activities Significantly 

Contributing to Collective Dose

in 2003

In an effort to identify the reasons for changes in 

the collective dose at DOE, several of the larger 

sites were contacted to provide information on 

activities that significantly contributed to the 

collective dose for 2003. These sites (Hanford, 

Savannah River, Los Alamos, Rocky Flats, Oak 

Ridge, and Idaho) were the top six sites in their 

contribution to the collective TEDE for 2003 and 

comprised 80% of the total DOE dose. Four of 

the six sites reported increases in the collective 

TEDE, which resulted in a 6% increase in the

DOE collective dose from 1,360 person-rem

(13.60 person-Sv) in 2002 to 1,445 person-rem 

(14.45 person-Sv) in 2003. The six sites are shown 

in Exhibit 3-30, including a description of activities 

that contributed to the collective TEDE for 2003.
3-26 DOE Occupational Radiation Exposure 

Exhibit 3-30:

Activities Significantly Contributing to Collective TEDE in 2003 for Six Sites (continued).

400

350

300

250

200

150

100

50

0

1999 2000 2001 2002 2003

����������������������������

������������������������������������������������������

��������������������������������������������������������

���������������������������������������������������

�������������������������������������������������������

�����������������������������������������������������������

���������������������������������������������������������

���������������������������������������������������������

���������������������������������������������������

������������������������������������������������������������

������������������������������������������������������������

���������������������������������������������������������

�������������������������������������������������������

�������������������������������������������������������

��������������������������������������������������������

���������������������������������

400

350

300

250

200

150

100

50

0

1999 2000 2001 2002 2003

����������������������������

�������������������������������������

�����������������������������������������������������������

��������������������������������������������������������

����������������������������������������������������������

�������������������������������������������������������

������������������������

��������������������������������������������������������

��������������������������������������������������������

�����������������������������������������������������������

������������������������������������������������������������

�������������������������������������������������������������

��������������������������������

�������������������������������������������������������

������������������������������������������������������

��������������������������������������������������������

���������������������������������������������������������

�����������������������������������������������������������

���������������������������������������������������������

�������������������������������������������

������������������������������������������������������

���������������������������������������������������������

����������������������������������������������������������

������������������������������������������������������

�������������������������������������������������������

�����������������������������������������������

��������������

��������������

����� ����

����������

����� ����

�������

�����

����

�������

�������������������������������������

��������������

�������������������

��� ��� ���

����� ����

����������

����� ����

�������

�����

����

�������

�� �� ���
2003 Report Occupational Radiation Dose at DOE 3-27

Exhibit 3-30:

Activities Significantly Contributing to Collective TEDE in 2003 for Six Sites (continued). ����������������������������400

350

300

250

200

150

100

50

0

1999 2000 2001 2002 2003

����������������������������400

350

300

250

200

150

100

50

0

1999 2000 2001 2002 2003

���������������������������������������������������������

������������������������������������������������������������

����������������������������������������������������������

������������������������������������������������������������

��������������������������������������������������������������

�����������������������������������������������������������������

����������������������������������������������������������������

������������������������������������������������������

�������������������������������������������������������������

����������������������������������������������������������������

������������������������������������������������������������������

�����������������������������������������������������������������

�����������������������������������������������������������

�����������������������������������������������������������������

�������������������������������������������������������������

�����������������������������������������������������������

����������������������������������������������������������������

��������

����� ����� ������������������������������������� ����

����������

����� ����

�������

�����

����

�������

��������������

��� ��� ���

�������������������������������������

��������������

�����������������������������������������������������������

�����������������������������������������������������������������

���������������������������������������������������������������

��������������������������������������������������������������������

������������������������������������������������������������������

��������������������������������������������������������������

�������������������������������������������������������������

�����������������������������������������������������������

�����������������������������������������������������������������

���������������������������������

�����������������������������������������������������������������

������������������������������������������������������������

���������������������������������������������������������������

���������������������������������������������������������

����������������������������������������������������������������

���������������������������������������������������������

����������������������������������������������������������

�����������������������������������������������������������������

����������������������������������������������������������������

���������

�����������������������������������������������������������������

������������������������������������������������������������������

������������������������������������������������������������

����������������������������������������������������������

������������������������������������������������������������

��������������������������������������������������������������������

�������������������������������������������������������������

������������������

�������������������������������������������������������������

�������������������������������������������������������������

�����������������������������������������������������������

������������������������

�������

�� ��� ���

����� ����

����������

����� ����

�������

�����

����

�������
3-28 DOE Occupational Radiation Exposure 

Exhibit 3-30:

Activities Significantly Contributing to Collective TEDE in 2003 for Six Sites (continued). ����������������������������

400

350

300

250

200

150

100

50

0

1999 2000 2001 2002 2003

��������������������������������������������������������

����������������������������������������������������

���������������������������������������������������

�������������������������������������������������������

��������������������������������������������������

��������������������������������������������������������

��������������������������������������������������

�����������������������������������������������������������

���������������������������������������������������������

��������������������������������������������������������

�����������������������������������������������������������

��������������������������������������������������

����������������������������������������������

�����������������������������������������������������

�������������������������������������������������������

������������������ �����������������������������������������

�����������������������������������������������������������

��������������������������������������������������������

�����������������������������������������������������������

�������������������������������������������������������

���������������������������������������������������������

������������������������������������������������������

����������������������������������������������������������

����������������������������������������������������

������������������������������������������������������������

�����������������������������������������������������������

�����������������

����������� �������������������������������������

��������������

��� ��� ���

����� ����

����������

����� ����

�������

�����

����

�������
2003 Report Occupational Radiation Dose at DOE 3-29

Exhibit 3-31:

Dose Distribution of Transient Workers, 1999-2003.

3.6 Transient Individuals

Transient individuals, or transients, are defined 

as individuals who are monitored at more than 

one DOE site during the calendar year. For the 

purposes of this report, a DOE site is defined as 

a geographic location. The DOE sites are listed 

in Appendix Exhibit A-2 by operations office. 

During the year, some individuals perform work at 

multiple sites and, therefore, have more than one 

monitoring record reported to the repository. In 

addition, some individuals transfer from one site 

to another during the year. This section presents 

information on transient individuals to determine 

the extent to which individuals travel from site to 

site and to examine the dose received by these 

individuals.

Exhibit 3-31 shows the distribution and total 

number of transient individuals from 1999 to 2003. 

Over the past 5 years, on an average, transient 

individuals have accounted for 3.2% of the total 

number of records for monitored individuals at 

DOE and received,on an average, 2.7% of the 

collective dose. As shown in Exhibits 3-32 and 

3-33, the number of transients with measurable 

dose increased by 9% from 550 in 2002 to 602 in 

2003. The collective dose for transients increased 

by 54% from 36.5 person-rem (365 person-mSv) 

in 2002 to 56.1 person-rem (561 person-mSv) in 

2003. The average measurable TEDE increased by 

41% from 0.066 rem (0.66 mSv) in 2002 to 0.093 

rem (0.93 mSv) in 2003. The average measurable 

TEDE for transients in 2003 was 12% higher than 

the average measurable TEDE (0.083 rem) for 

all monitored DOE workers. This is the first year 

since the transient data has been analyzed that the 

average measurable TEDE to transients is higher 

than the value for all DOE workers. As shown in 

Exhibit 3-34, LANL was the site with the largest 

collective dose to transient workers from 1999 to 

2003. LANL has the largest percentage of dose to 

transients because workers at TA-55 (who generally 

receive elevated doses due to the nature of their 

work) tend to perform temporary work at sites 

such as Nevada Test Site (NTS), Rocky Flats, and 

Pantex, as part of their routine duties. In addition, 

the collective TEDE at LANL increased by 47% 

from 163.5 person-rem (1635 person-mSv) 2002 to 

240.0 person-rem (2400 person-mSv) 2003, which 

contributed to the 115% increase in the collective 

TEDE to transient workers at LANL.

�������������������������

����������������

�����������

����������

����������

����������

���������

��������������������������������������

���������������������������

����������������������

����������������������������

�����������������������������

�������������������������������������

�����������

����������������������

��������������������������������������

�������������������������������

����������������������

������������������������� ���� ����

�����

���

��

��

��

�

�

�����

���

���

������

�����

�������

������

����

����

���������� �������

����

�����

���

��

��

�

�

�����

���

���

������

�����

�������

������

����

����

�����

���

��

��

�

�����

���

���

������

�����

�������

������

����

����

����

�����

���

��

��

�

�

�

�����

���

���

������

�����

������

������

����

����

�����������������������������������������������������������������������������������������������������������

����

�����

���

��

��

�

�

��

�����

���

���

������

�����

�������

������

����

����
3-30 DOE Occupational Radiation Exposure 

Exhibit 3-32:

Individuals Monitored at More Than One Site (Transients) During the Year, 1999-2003.

Exhibit 3-33:

Collective and Average Measurable Dose to Transient Individuals, 

1999-2003.

One group of individuals who routinely travel from 

site to site is DOE employees from Headquarters 

or the Field Offices who visit or inspect multiple 

sites during the year. For 2003, this group accounts 

for 12% of the monitored transient individuals but 

only 1% of the collective dose to transients.

In 2003, 12% of the transient individuals 

were monitored at three or more sites. DOE 

Headquarters and Field Office personnel 

are included among these individuals. In 

2003, 14% of the individuals monitored at three 

or more sites were DOE Headquarters or Field 

Office employees, and 15% of the individuals 

monitored at four or more facilities were DOE 

Headquarters or Field Office employees. The 

maximum number of sites visited by one 

monitored individual during 2003 was six.

1999 2000 2001 2002 2003

0

1000

2000

3000

4000

5000

Number of Individuals

Year

4,597

721

3,058

521

3,183

487

2,848

550

2,665

602

Total Transient Individuals Monitored

Transients with Measurable Dose



 





1999 2000 2001 2002 2003

0

10

20

30

40

50

60

0.00

0.02

0.04

0.06

0.08

0.10

0.12

0.14

0.16

Collective Dose (person-rem)

Average Meas. TEDE (rem)

Year

39.5

23.6 25.1

36.5

56.1

DOE Overall Average Measurable TEDE

Transient Collective TEDE

Transient Average Measurable TEDE
2003 Report Occupational Radiation Dose at DOE 3-31

Exhibit 3-34:

Collective TEDE to Transient Workers by Site, 1999-2003.

1999 2000 2001 2002 2003

0

10

20

30

40

50

60

Collective TEDE (person-rem)

Year

10.6 (Rocky Flats)

5.1 (Hanford)

9.8 (Other)

17.4 (LANL)

8.5 (LLNL)

2.5 (Oak Ridge)

2.3 (SRS)

6.8 (LANL)

5.6 (Rocky Flats)

6.2 (Hanford)

2.3 (Oak Ridge)

4.9 (LLNL)

1.4 (SRS)

12.2 (Other) 0.8 (LLNL)

1.6 (SRS)

2.8 (Hanford)

3.1 (Rocky Flats)

6.9 (LANL)

4.7 (Other)

3.7 (Oak Ridge)

23.6

39.5

3.8 (LLNL)

1.8 (SRS)

1.4 (Hanford)

7.0 (LANL)

6.9 (Other)

1.4 (Oak Ridge)

25.1

2.7 (Rocky Flats)

2.9 (LLNL)

2.2 (SRS)

8.1 (LANL)

10.1 (Other)

2.5 (Oak Ridge)

36.5

8.6 (Rocky Flats)

2.2 (Hanford)

56.1

LANL has a larger percentage of dose to transients because workers at TA-55 (who generally 

receive elevated doses) tend to perform temporary work at sites such as NTS, Rocky Flats, and 

Pantex, as part of their routine duties.
3-32 DOE Occupational Radiation Exposure

Section 3.7 Historical Data Collection

In Section 3.7 of the 2000 and 2001 annual 

reports on occupational exposure, information 

was presented on historical data that have been 

collected to date from a request by the DOE Office 

of Environment, Safety and Health to the DOE sites 

to voluntarily provide historical exposure records. 

No additional sites have reported historical data 

during the year 2003.

Sites that have not yet reported historical dose 

records are encouraged to contact Ms. Nirmala 

Rao at DOE to obtain further information on 

reporting these records. This is a voluntary 

request to report historical data (records prior 

to 1987) that are available in electronic form 

in whatever format that is most convenient for 

the site to report. The data will be stored as 

reported in the REMS and wherever possible, 

data will be extracted and loaded into the REMS 

database for analysis and retrieval. For detailed 

analysis, read Section 3.7 of the 2000 report.

Sites that have voluntarily reported historical data are:

  Fernald

  Hanford

  Idaho

  Kansas City Plant

  Lawrence Berkeley National Laboratory

  Lawrence Livermore National Laboratory

  Nevada Test Site

  Oak Ridge K-25 Site

  Pantex

  Portsmouth

  Rocky Flats

  Sandia National Laboratory

  Savannah River Site
2003 Report ALARA Activities at DOE 4-1

Section Four ALARA Activities at DOE 4

This section on ALARA activities is a vehicle to 

ALARA Activities at DOE

document successes and to point all DOE sites to 

those programs whose managers have confronted 

radiation protection issues and used innovative 

techniques to solve problems common to most 

DOE sites. DOE program and site offices and 

contractors who are interested in benchmarks 

of success and continuous improvement in the 

context of Integrated Safety Management and 

quality are encouraged to provide input to be 

included in future reports.

4.1 ALARA Activities at the 

Hanford Site

4.1.1 Fluor Hanford, Inc. Implements 

ALARA During Open Air Demolition 

of 233S Plutonium Concentration 

Facility

The 233S Plutonium Concentration Facility 

(shown in Exhibit 4-1) was a part of the plutonium 

production processing facilities at the Hanford 

Site. Plutonium solutions from the 202-S REDOX 

building were transferred to the 233S facility, 

where the plutonium solution was concentrated 

and loaded into Product Receiver (PR) cans for 

transport to the Plutonium Finishing Plant for 

further processing. In 1962, operations at the 233S 

facility were expanded to include a Neptunium 

concentration and loadout process as well as an 

ion-exchange plutonium purification process. 

A plutonium spill in 1956 and a fire in 1963 resulted 

in the spread of gross levels of contamination 

within the process areas of the facility and lesser 

amounts of contamination in the non-process areas 

including the exterior roof of the facility. The 233S 

building was a reinforced concrete structure 37 feet 

high, 86 feet long and 43 feet wide, with 8-inch thick 

walls and 6-inch thick floors. 

In a previous contract, Bechtel Hanford, Inc. 

removed the process equipment and performed 

some stabilization of the contamination. Nonprocess areas were decontaminated to below 2,000 

dpm/100cm2 alpha. However, the process hood 

and viewing room remained at 50,000 – to more 

than 20,000,000 dpm/100 cm2 alpha. Resuspension 

of contamination caused airborne radioactivity 

levels between 10 and 100 DAC, requiring all 

entries to be made in Powered Air Purifying 

Respirators. 

The challenge for Fluor Hanford, Inc. (FHI) was 

to economically demolish a highly contaminated 

plutonium facility while maintaining exposures to 

internal and external radiation ALARA, protecting 

the workers, public, and the environment. To meet 

this challenge, FHI developed and implemented 

methods of controlling airborne radioactivity 

generation while demolishing the building in 

the open air in lieu of fully decontaminating the 

building prior to demolition.

 

The highly contaminated areas were partially 

decontaminated by hydrolasing. VAC TRAX®

Hydrolase System was used to reduce external 

and internal dose to workers and prepare the 

building for open air demolition. The VAC TRAX® 

is a remote-operated, track driven, rotating highpressure water jetting tool that directs Ultra 

High Pressure (UHP) water to remove material 

coverings from a variety of surfaces. The VAC 

TRAX® is capable of light scabbling or deep 

scarification of concrete surfaces, allowing for 

deeper cleaning. Additionally, the VAC TRAX®

is fully encapsulated. Water and debris are 

vacuumed to a Waste Barrel Containment 

System. After hydrolasing, area dose rates were 

Exhibit 4-1:

233S Prior to Demolition.

Photo Courtesy of Hanford.
4-2 DOE Occupational Radiation Exposure 

significantly reduced. Contact exposure levels in 

the northeast corner of the process hood were 

reduced from > 2,000 mrem/hr to approximately 

300 mrem/hr and general area dose rates were 

reduced to < 5 mrem/hr in most areas. 

To further reduce the dose rates, a 12-inch layer 

of grout was applied to the process hood and 

viewing room floors. Following grouting, dose 

rates were in the μrem/hr range. The lowering 

of the background allowed more accurate 

characterization to be performed, which allowed 

the majority of the process hood / viewing 

room walls to be designated for low-level 

waste. Grouting also further reduced airborne 

contamination levels within the facility.

Polymetric Barrier SystemTM (PBS) was used to fix 

the remaining contamination on surfaces of the 

interior of the building prior to demolition. PBS 

is a non-toxic, water-based system and is easily 

applied in the field to form a strong, impermeable 

barrier between hazardous materials and the 

environment.

Exhibit 4-2:

The Mechanical Shears Quickly Cut Up Reinforced Concrete Walls, Metal Sheet Walls, and Ventilation Ducting.

Photo Courtesy of Hanford.

Demolition of 233S was performed in two phases. 

Low- and medium-risk portions of the building 

were demolished using mechanical shears (see 

Exhibits 4-2 and 4-3). The high-risk portion of 

the building (the process hood) was demolished 

using wall saws (see Exhibits 4-4, 4-5, and 4-6). Fog 

cannons were used to control potential airborne 

radioactivity during the shearing operations and 

the mechanical shears had a fogging system built 

in as well (see Exhibits 4-7 and 4-8). Fixatives were 

incorporated into the fog cannon and mechanical 

shear fogging systems. For the wall saw operations, 

gutters were placed on the inside of the facility 

along the wall saw cut lines (Exhibit 4-9) to collect 

contaminated liquid and particles to prevent 

release during the cutting operations. 

These techniques each contributed to the 

successful completion of open air demolition of 

the 233S Plutonium Concentration Facility.
2003 Report ALARA Activities at DOE 4-3

Exhibit 4-4:

Wall Saw is Mounted on the Installed Track. The Concrete Roof 

was Cut Into Four Sections and Removed First.

Photo Courtesy of Hanford.

Photo Courtesy of Hanford.

Exhibit 4-6:

A Closeup of the Wall-Mounted Saw as it Cuts Through the Wall of 

the Process Hood Portion of 233S Plutonium Concentration Facility.

Exhibit 4-5:

Once the Roof was Removed, the Contractor Began Removing 

Sections of Wall.

Photo Courtesy of Hanford.

Exhibit 4-3:

Debris From the Shearing Operation is Scooped Up and Transported 

to the Environmental Restoration Disposal Facility.

Photo Courtesy of Hanford.
4-4 DOE Occupational Radiation Exposure 

Photo Courtesy of Hanford.

Exhibit 4-8:

The Mechanical Shear Also had a Fogger Attached. Water with Fixative Controls the Release of Airborne Radioactivity 

During Shearing Operations.

Exhibit 4-7:

Fog Cannon Operating During Shearing of the Low- and Medium-Risk Areas. Two Cannons were Staged to Provide 

Continuous Fogging During Shearing.

Photo Courtesy of Hanford.
2003 Report ALARA Activities at DOE 4-5

Exhibit 4-9:

Gutters were Installed on the Interior of the Building Where the Wall Saw Cuts were to be Made to Collect Water and Debris During the 

Cutting Operation and Control Release of Airborne Radioactivity.

Photo Courtesy of Hanford.
4-6 DOE Occupational Radiation Exposure 

4.1.2 Bechtel Hanford, Inc. Uses Rust 

Doctor® Fixative to Reduce Airborne 

Radioactivity During Demolition of 

1304N Emergency Dump Tank

The 1304N Emergency Dump Tank (EDT) was 

extensively corroded with gross quantities of 

flighty red rust on the inner steel surfaces of 

the tank. Pre-demolition surveys of the steel 

revealed removable contamination levels in 

excess of 500,000 dpm/100cm2 beta-gamma 

and approximately 3,500 dpm/100cm2 alpha. To 

effectively demolish and remove the tank structure, 

it was necessary to fix the contamination so that 

airborne radioactivity levels would not pose a 

significant threat to workers or the environment 

during demolition activities. A fixative satisfying 

the following criteria was needed:

• Fixes the radioactive rust to below 100,000 

dpm/100cm2 beta-gamma and 400 dpm/

100cm2 alpha removable contamination

• Environmentally friendly disposition with 

waste material

• Chemically compatible with the steel tank

• Feasible application requirements

• Reasonable availability and cost-effectiveness

After evaluating available options, Rust Doctor ®

rust converter and fixative was selected. The Rust 

Doctor ® changes the red flighty rust to black 

magnetite that re-adheres to the tank surface (see 

Exhibit 4-10). The latex component provides a 

primer coat that (in its intended use) could be 

painted with a top coat. 

Physically removable rust material was 

significantly reduced and in some cases 

eliminated entirely. A survey taken from a small 

section removed from the tank wall indicated 

removable contamination levels were reduced to 

approximately 8,000 dpm/100cm2 beta-gamma and 

<100 dpm/100cm2 alpha. Direct contamination 

levels were significantly higher. This indicated 

that the contamination was indeed fixed to the 

surfaces of the tank via the latex-based matrix that 

was associated with the fixative (see Exhibit 4-11). 

Air samples collected during demolition verified 

the fixative controlled potential generation of 

airborne radioactivity.

Photo Courtesy of Hanford.

Exhibit 4-10:

Inside Surface of the Tank. Rust Doctor ® Turned the Red Rust to Black. The Coverage Is Apparent. 
2003 Report ALARA Activities at DOE 4-7

Photo Courtesy of Hanford.

Exhibit 4-11:

The Spray Rig was a Counterweighted Arm About 28 Feet in Length Extending from the Center Shaft Toward the Wall of the Tank. 

Approximately 100 Gallons of Rust Doctor ® were used to Fix the Contamination in the Tank. The Top of the Spray Rig Can be Seen Leaning 

Up Against the Wall in the Left of the Photo.
4-8 DOE Occupational Radiation Exposure 

4.1.3 CH2M HILL Hanford Group, Inc. 

Saved 6.5 Person-Rem Using Cast 

Antimonial Lead Shielding During 

Sluice and Retrieval of Saltcake from 

S-112 Tank

CH2M HILL has begun the process of removing 

radioactive sludge from some of the Hanford 

underground single-shelled tanks in preparation 

for tank closures. Tank S-112 Saltcake Waste 

Retrieval Technology Demonstration Project 

used high-pressure spray nozzles to break up the 

saltcake waste forms in the single-shelled tank and 

then pumped it into a double-shelled tank.

The S-112 retrieval team had a problem: How do 

you shield 500 feet of transfer line in the S-Farm 

complex? The traditional solution was to dig a 

trench, place the pipe in the trench, and cover the 

trench with steel plating. A trench already existed 

for another temporary line that was being used 

to remove liquids from the tank in an operation 

called saltwell pumping. Using the existing 

trench would have required temporary shutdown 

of the saltwell pumping operation, causing a 

significant delay in that project and additional 

dose to workers installing the new line next to the 

previously active transfer line. 

The retrieval team went to the Hanford ALARA 

Center of Technology to look for an alternative. 

At the ALARA Center, the team found a sample of 

antimonial lead shielding made by Nuclear Lead 

Company of Oak Ridge, Tennessee. The shielding, 

containing 3 percent antimony, is stronger than 

regular lead shielding, holds it shape, but retains 

all the required shielding properties (see Exhibit 

4-12). 

Deciding to use the shielding was the easy 

part. Making the idea practical by designing 

interlocking shielding that could accommodate 

the curves of transfer lines and the uneven terrain 

in the tank farms took the engineering support of 

COGEMA. A dog house design was developed and 

the shielding was custom cast by Nuclear Lead 

Company at their Oak Ridge plant. Each shielding 

block, designed to sit over the top of the transfer 

line, is 24 inches long, weighs 270 pounds, and 

contains a lifting lug for installing and removing 

the shielding using a crane. Installation began in 

August on tank S-112 and later in the fall on S-102. 

For the initial application of the antimonial lead 

“dog house” style shielding, CH2M HILL saved 6.5 

person-rem for the project. Most of the savings is 

attributed to not having to bury, and then dig up, 

the transfer line following use. The antimonial 

lead shielding is also more effective than steel 

in reducing the gamma dose rates resulting in 

lower doses during operation. The shield blocks 

are easily installed and removed, resulting in 

considerable cost/schedule savings as well as 

dose savings. This shielding is also being applied 

to other tank waste retrieval projects and will be 

applied to future work evolutions for additional 

savings.

Exhibit 4-12:

Nuclear Lead Company Antimonial-lead Shielding was Placed Over a 

Temporary Above-ground Radioactive Waste Transfer Line. This Line is 

Adjacent to Another Temporary Transfer Line that was Buried in a Trench 

and Covered with Steel Plates. The New Method Saved 6.5 Person-rem 

and Significant Labor Costs.

Photo Courtesy of Hanford.
2003 Report ALARA Activities at DOE 4-9

4.2 ALARA Activities at the West 

Valley Demonstration Project

The West Valley Demonstration Project (WVDP) 

is the site of a former commercial nuclear fuel 

reprocessing plant. The WVDP Act, passed by 

Congress in 1980, directed DOE to solidify the 

liquid waste left from reprocessing activities, clean 

and close the facilities used, and dispose of lowlevel and TRU wastes left from project operations. 

The Project is unique in that the site property is 

owned by New York State.

Following the successful vitrification of liquid 

high-level radioactive waste in 2002, cleanup 

efforts are now focused on decontamination and 

dismantlement of some of the cells in the former 

nuclear fuel reprocessing plant. Three of these 

cells are the Product Purification Cell-South 

(PPC-S) and two Head End Cells (HECs).

4.2.1 Project Description of PPC-S

During former reprocessing operations, recovered 

uranium and plutonium were purified in the multilevel PPC. The cell measures 21 feet wide by 

16 feet long by 57 feet high and is divided into two 

sections by a 1-foot-thick concrete shield wall. The 

PPC-North section was used primarily to purify 

uranium and was decontaminated in the 1980s. 

The smaller south section was used primarily to 

purify plutonium. 

Decontamination of PPC-S was performed to 

significantly reduce the level of radiological 

hazard and risk associated with contaminated 

piping, valves, tanks, vessels, support structures, and 

components that were used during the product 

purification process (see Exhibit 4-13).

Photo Courtesy of WVDP.

Exhibit 4-13:

Removal of Slab Tank in PPC-S.

4.2.1.1 Radiological Concerns

The main challenges associated with removing 28 

separate vessels and more than 3,000 linear feet of 

piping in the cell included:

• high alpha contamination levels at >50 million 

disintegrations per minute (dpm)

• a silo-like cell configuration (57 feet tall, 

16 feet long and only 5 feet wide)

• lack of remote equipment capabilities or 

ability to readily install such equipment

• difficult access

• the residual fissile material potentially 

remaining in the cell’s pipes and vessels

Smear samples confirmed alpha contamination 

exceeding 50 million dpm. The cell’s general area 

exposure rate at the ground level varied from 5 to 

35 mR/hour gamma, with the majority of radiation 

coming from the floor. General area exposure rates 

at the upper regions of the cell were 1 to 2 mR/hour 

gamma.
4-10 DOE Occupational Radiation Exposure 

4.2.1.2 Implementation of Innovative ALARA 

Techniques

Project engineers designed a doorway in the cell's 

3-foot-thick concrete shield wall to provide the 

shortest path for in-cell equipment removal and 

to allow for installation of multiple containment 

barriers. The team also modified ventilation 

flowpaths into and out of the PPC-S to increase the 

number of air changes in the cell and to reduce 

the potential for spreading contamination during 

cell entries. Additionally, operators applied a 

strippable fixative coating to the in-cell surfaces.

The containment design, ventilation modification, 

and use of fixatives established safe conditions 

for workers. Radiological protection was also 

provided by selecting highly protective Personal 

Protective Equipment (PPE). Each operator wore 

two inner layers of anti-contamination clothing, an 

air-fed cooling vest, and a supplied air respirator 

and hood. Over this PPE, operators wore an air-fed 

vinyl suit and hood or bubble suit. To protect 

the bubble suit from being torn, cloth coveralls 

were worn over the top of the bubble suit. Each 

operator was equipped with a two-way radio for 

communication (transmitter and earpiece). 

To ensure the safe handling of residual liquids 

inside piping and vessels, more than 100 

sampling points were identified and a telltale 

(a custom-machined, stainless-steel block valve 

assembly) was installed on each point. The telltale 

assemblies were used to vent and drain the lines, 

and draw samples to determine the fissile content 

of the liquid. Approximately 17 gallons of liquid 

were removed from in-cell piping during the 

decontamination effort. All components 2 inches 

in diameter or larger were visually inspected to 

identify the presence of bulk solids. A total of 129 

telltales were performed on pipe ranging in size 

from 2 inches to 1.5 inches in diameter.

Project engineers conducted benchmarking at 

several DOE facilities that have handled and 

packaged Pu-contaminated wastes and established 

a method for determining fissile content that is 

recommended by the NRC. The team used an 

NaI (Tl) scintillation detector to screen piping. 

They also developed limits for packaging assayed 

piping, and prepared a strategy to stage the piping 

that facilitated batch accumulation and transfer 

during removal.

Specific criticality analyses were performed on 

each process vessel to ensure safe handling as 

the vessel was removed from the cell. Waste 

containers used to package the equipment were 

transported directly to separate criticality control 

zones to provide a safe staging area for the 

vessels until final characterization data needed to 

complete packaging were available.

Removal work was structured to clear the PPC-S of 

contaminated components beginning at the lowest 

level and progressing upward. Operators identified 

process and utility piping lines using line number 

tags and color coding to correspond with the 

system pipe (i.e., Pu, U, or utility piping). As entries 

were conducted, project engineers guided crew 

members using two-way communication and 

small-diameter video cameras. After confirming 

the correct identification of line numbers, 

workers vented and sampled the lines. More than 

3,000 feet of piping were removed from the cell 

following the sampling evolution.
2003 Report ALARA Activities at DOE 4-11

With only a 16-foot-long and 5-foot-wide area to 

work in, creative maneuvering was required to 

rig larger, heavier components and lower them 

down through the cell for removal. Contaminated 

equipment was rigged, detached from its structural 

supports, and layered in Herculite® prior to being 

lowered down through the cell. The largest vessels 

were as tall as 13 feet and weighed up to 1,000 

pounds.

Field work on the PPC-S project began in July 

2002 and the cell was partially decontaminated 

and dismantled by August 2003. An estimated 

2,300 curies of radioactivity, the majority of which 

was contained in process piping and vessels, 

were removed from the cell. Work crews made 

approximately 240 entries into the cell and logged 

more than 47,000 hours with no OSHA-recordable 

injuries or illnesses, no uptakes of radioactive 

material, no unplanned exposures greater than 

administrative control levels, and no airborne 

events exceeding permissible levels. The final 

radiological survey showed contamination levels 

on the walls were generally less than 10,000 dpm/

cm2 alpha, on the floor generally less than 30,000 

dpm/cm2 alpha, and exposure rates ranged from 

0.5 to 25 mR/hour.

4.2.1.3 Estimated Dose Avoided

The ALARA budget for the PPC-S project was 8.77 

rem. The project team received an actual dose 

(based on daily direct-reading dosimeters) of 6.98 

rem total. For more information on this project, 

contact Ken Schneider at 716-942-4671.

The team used a mast climber rather than 

conventional scaffolding to remove equipment 

and piping from the cell. The mast climber is a 

compact, single-mast and single-platform unit 

that was specifically designed for use in narrow, 

restricted spaces (see schematic drawing at Exhibit 

4-14). The length and width of the unit were 

adjusted to fit the PPC-S cell dimensions. The unit 

made it possible for operators to continue to work 

safely and efficiently as they moved higher into 

the cell. Prior to using the mast climber in the cell, 

team members installed it in a nonradioactive 

facility as part of mock-up training and to ensure 

that the work incorporated ALARA and industrial 

safety principles.

Exhibit 4-14:

Schematic Drawing of PPC-S.

Drawing Courtesy of WVDP.
4-12 DOE Occupational Radiation Exposure 

4.2.2 Project Description of HECs and 

Radiological Concerns

The HECs consist of two main cells: the Process 

Mechanical Cell (PMC) and General Purpose Cell 

(GPC). The cells are heavily contaminated with 

spent fuel and mixed-fission/activation products 

from former spent nuclear fuel reprocessing 

operations. At the start of the decontamination 

effort, radiation levels in the cells ranged from 

general area exposure rates of 100 R/hour to hot 

spots of 2,000 R/hour, with alpha and beta/gamma 

removable contamination levels on the order of 

billions of disintegrations per minute. The 2002 

DOE Occupational Radiation Exposure ALARA 

report provided information on initial cleanup 

of these cells and described shield window 

refurbishment, shield door repair, and replacement 

of remote handling equipment.

Decontamination work continues in the HECs 

with the packaging and removal of contaminated 

components from the two cells. Loose debris 

in the HECs include scrap from fuel and waste 

handling, fuel assembly hardware, leached fuel 

hulls, fine particles, and other materials. To 

maintain radiation exposure of workers on this 

project below ALARA limits, operations are being 

performed remotely (as shown in Exhibit 4-15).

4.2.2.1 Implementation of Innovative ALARA 

Techniques

The WVDP developed waste packaging plans 

for the HECs based on the Waste Isolation Pilot 

Plant (WIPP) Waste Acceptance Criteria (WAC). 

The former spent nuclear fuel reprocessing 

operations conducted on the site of the WVDP 

were considered commercial and were not 

included in the legislation that created the WIPP. 

However, in the absence of any other disposal 

facility capable of accepting WVDP TRU waste, the 

WVDP is using the WIPP WAC for HEC and other 

project waste. Two key factors were considered 

in project planning to ensure that the WIPP WAC 

were met: information on the chemical, physical, 

and radiological composition of the debris was 

critical, and WIPP WAC-compliant containers were 

to be used.

An innovative in-situ gamma spectroscopy unit 

was deployed in the HECs to aid in identifying 

gamma-emitting radionuclides in debris and 

equipment, and targeting specific areas for 

sampling. Thirty-gallon containers were selected 

for packaging debris, based on the size constraints 

of the HECs and to allow for the greatest degree 

of flexibility for packaging into final disposal 

containers. The containers can be placed readily 

into the proposed TRU waste canister or other 

containers.

Combustible materials were removed first from 

the HECs to reduce the potential for an in-cell 

fire. Materials including wood, plastics, and rubber 

were packaged and size-reduced using shears or 

bolt cutters that were modified for remote use. 

A variety of tooling was developed to handle 

the wide range of material inside the cells. They 

included off-the-shelf hand tools that could be 

easily modified for use with remote handling 

devices such as manipulators or robotic arms.

WVDP operators used bench-top band saws 

lowered into the cells from a crane hook to cut 

up waste debris. Hand-held band saws were used 

to cut broken manipulators left inside the cell. As 

cell cleanup efforts progressed, the dose rates of 

the packages began to increase. Initially, drums 

were loaded with general combustible waste that 

produced low exposure rates (<500 mR/hour) 

and could have been packaged using handson methods. Engineers developed methods to 

minimize contamination spread by covering waste 

Exhibit 4-15:

Remote Packaging of Waste from the HECs.

Photo Courtesy of WVDP.
2003 Report ALARA Activities at DOE 4-13

packages with a remotely removable covering. To 

remove the package from the contaminated area, 

the covering was removed while the drum was 

suspended in the air, and the drum was quickly 

transferred to a clean area. These inner drums 

were removed from areas where contamination 

levels are in the billions of counts per minute with 

minimal cross-contamination occurring on the 

outside of the packages.

Additional efforts to facilitate the overall dose 

reduction ALARA strategy were implemented 

in the Scrap Removal Room (SRR) adjacent to 

the HECs. The SRR was redesigned to permit 

drums to be brought out of the HECs in a lower 

background radiation level area. Engineering 

developed a method to remotely weigh and take 

dose readings on inner drums and then place 

them in shielded containers. A 55-gallon drum 

with prepositioned radiation probes on it served as 

the remote measurement device. It was mounted 

on a standard floor scale. Waste drums were lifted 

from the GPC through a hatchway where their 

contamination covers were removed. The waste 

drums were placed in the drum counter and their 

weight and exposure readings were transmitted 

to an indicator panel outside the cell. Finally, the 

drum was placed in a shielded container without 

exposing operators to the unshielded radiation 

field. In the final step, workers entered a lowexposure, low-contamination zone to bolt the 

outer lids on drums to permit their removal from 

the area.

The WVDP also explored other areas to help 

reduce exposure to workers while handling HEC 

waste. The Chemical Process Cell (CPC) had been 

cleaned out and racks installed in support of the 

high-level waste (HLW) vitrification project. When 

the vitrification process was completed and all of 

the available rack space had not been used, WVDP 

engineers reestablished the flow path between the 

GPC and the CPC to allow for temporary waste 

storage of higher-dose waste drums. This process 

allowed remote storage of the waste drums and 

ensured worker safety during the storage of TRU 

waste drums until the disposal path for this waste 

is determined.

For ease in removing some components from 

their mounts, impact wrenches were attached 

with manipulator-friendly handles on the base 

of the wrenches and telerobotic manipulator 

quick-disconnects for the air lines. An off-the-shelf 

saw with counter rotating cutoff saw blades was 

also adapted for remote use, as was an off-theshelf, battery-operated, automobile rescue tool 

modified for in-cell use. The rescue tool was used 

to quickly cut through various loose piping and 

rods (see Exhibit 4-16). When larger items required 

size reduction, the project team developed more 

aggressive remote cutting methods using generic 

cutoff saws with 9-inch and 14-inch blades, as well 

as hand-held circular saws.

Exhibit 4-16:

Automobile Rescue Tool Being Used to Cut Through Pipes and Rods.

Photo Courtesy of WVDP.

Remote visual access and lighting were issues 

throughout the project. Several innovative designs 

were developed to create acceptable means to 

allow for acceptable views and visual access 

to areas being worked. Traditional radiationhardened cameras proved to be expensive, and 

spare parts were difficult to find. The project team 

developed a technique to install cameras that were 

not radiation hardened through penetrations to 

the cells. The cameras were pushed into the cells 

to get the required views, then drawn back into 

the walls when not in use to shield them from high 

cell radiation fields. Inexpensive Aspy cameras 

were also used to view areas being worked by 

the robotic arms. These cameras gave very sharp 

pictures and lasted for days to weeks at a time.

Cleanup of the HECs is continuing in 2004; 

however, an ALARA budget of 6.258 rem was 

allotted for the project during 2003. Due to the use 

of innovative ALARA dose reduction techniques, 

the dose received (based on daily direct-reading 

dosimeters) for this project in 2003 was 1.287 rem. 

For more information about the HECs project, 

contact Scott Chase at 716-942-2184.
4-14 DOE Occupational Radiation Exposure 

4.3 ALARA Activities at 

Brookhaven National Laboratory 

4.3.1 Removal of the Brookhaven 

Graphite Research Reactor Below 

Ground Duct Outlet Air Filters

4.3.1.1 History and Description of the 

Brookhaven Graphite Research Reactor

The Brookhaven Graphite Research Reactor 

(BGRR) at Brookhaven National Laboratory (BNL) 

(Exhibit 4-17) was the first reactor built for the 

sole purpose of providing neutrons for research. 

Construction on the BGRR was completed in 

August 1950, and initial criticality of the reactor 

was achieved the same month. During its years 

of operation, it was one of the principal research 

reactors in the United States. The science mission 

of the BGRR concluded in 1963, and all operations 

ceased when operation of the reactor was 

terminated and deactivation of the facility was 

initiated. In March 1972, the last fuel element was 

removed from the reactor and shipment of the fuel 

to the Savannah River Site was completed shortly 

thereafter. The BGRR complex was described 

as being in a “safe shutdown” condition by the 

U.S. Atomic Energy Commission and became a 

“surplus facility” within the DOE complex.

The BGRR was a heterogeneous, enriched 

uranium-fueled graphite moderated and reflected, 

thermal neutron, air-cooled research reactor. The 

reactor consisted of a graphite cube, penetrated 

in the north-south direction by an array of parallel 

cylindricals, which held the cladded fuel elements. 

The graphite cube was built in two halves, 

separated by a vertical gap running east-west. 

Filtered cooling air was drawn into this gap and 

flowed through the individual channels, removing 

heat from the fuel elements and graphite. Hot 

air was collected in the plenum chambers at the 

north and south ends of the graphite cube and 

then flowed out of the building through two (north 

and south) underground concrete ducts. The air 

was filtered and cooled, and then drawn through 

fans and discharged into the stack. 

Each of the north and south Below Ground Ducts 

(BGDs) had one filter bank (Exhibit 4-18). The 

filter banks each contained a total of 320 filter 

elements, which were arranged in eight cells that 

formed a four “V” configuration. Each filter cell was 

five elements across and eight elements high. The 

concrete BGDs that housed the filter banks are 

approximately 20 feet wide and 18 feet high. Each 

concrete duct contains a primary steel liner.

Exhibit 4-17:

Brookhaven Graphite Research Reactor at Brookhaven National Laboratory.

Photo Courtesy of BNL.

Exhibit 4-18:

Filter Bank.

Photo Courtesy of BNL.
2003 Report ALARA Activities at DOE 4-15

Outlet air samples were taken as part of the BGRR 

characterization study. Due to the well-defined 

contamination associated with the filters located 

within the BGDs, and the poor condition of the 

equipment itself, the removal of the filters was 

determined necessary to prevent potential future 

contamination of the environment.

4.3.1.2 Radiological Condition of the BGD 

Outlet Air Filters

There were two filter banks; one located in 

the north BGD and a second located in the 

south BGD. The south filter bank contained 

approximately twice the activity as the north filter 

bank. The source of the filter activity was due to 

numerous fuel element failures.

Typical south filter bank contact gamma exposure 

rates ranged from 500 mR/h to 900 mR/h. Gamma 

exposure rates 6 feet from the filters indicated 100 

mR/h (contact beta dose rates were measured up 

to 1.8 Rad/h).

The principal radionuclides of concern and 

inventory in the south filter bank were 90Sr (7.09 

Curies), 137Cs (16.2 Curies), 238U (1.36E-3 Curies), 238Pu (3.32E-3 Curies), 239/240Pu (1.24E-01 Curies), 241Pu (1.39E-01 Curies), and 241Am (3.79E-02 

Curies).

4.3.1.3 Filter Removal Method

A key concept during the planning and 

engineering for removal of the filters was to use 

custom-designed and -built remote-controlled 

equipment: a Brokk machine for removing the 

filters, a hammer mill for shredding the filters, and 

a vacuum/separator/system, which carried the 

shredded filters directly from the BGD to the waste 

burial container.

A Duct Service Building (DSB) was constructed 

to house the vacuum/separator/system and waste 

container (Exhibit 4-19). A ventilation system 

was installed that maintained the BGD at negative 

pressure with respect to the DSB and that also 

kept the DSB negative with respect to the outside 

environment. Shielding was installed around the 

waste container inside the DSB. Dry runs and 

mock-ups were performed on all new systems.

Exhibit 4-19:

Separator Inside Duct Service Building.

Photo Courtesy of BNL.
4-16 DOE Occupational Radiation Exposure 

Prior to removal, a fixative was applied to the filter 

elements (Exhibit 4-20). This fixative significantly 

mitigated the radioactivity that was available for 

resuspension in air and also allowed the use of airpurifying respirators for personnel access into the 

BGD rather than the more limiting self-contained 

breathing apparatus (SCBA). The filter elements 

were then removed with a specially designed Filter 

Removal Tool (FRT) that was attached to a diesel 

powered, remote-controlled manipulator (Brokk 

330D). The FRT removed the filter elements and 

placed them into a hammer mill shredder (Exhibit 

4-21). The shredder rendered the filter media 

into nominal 1-inch cubes that were then carried 

through a vacuum hose to a waste liner. The Brokk 

manipulator was controlled remotely from a video 

control console (Exhibit 4-22).

Exhibit 4-20:

Application of Fixative.

Photo Courtesy of BNL.

Exhibit 4-21:

Brokk Machine Loading Filter Element Into Hammer Mill.

Exhibit 4-22:

Remote Video Display Terminal.

Photo Courtesy of BNL.

Photo Courtesy of BNL.
2003 Report ALARA Activities at DOE 4-17

The use of the remotely controlled Brokk 

manipulator reduced the number of personnel 

entries into the confined space, thereby 

minimizing personnel exposure to the industrial 

and radiological hazards associated with removal 

of the filters. The Brokk manipulator performed 

this work in a high-radiation, high-contamination 

area (contamination levels in excess of 1.0E+6 

disintegrations per minute per 100 square 

centimeters were routinely identified). The work, 

which involved two shifts per day over a 3-month 

period, was performed without a single personnel 

contamination or any loss of control of radioactive 

material. Removal of all the filters required 643 

Brokk operating hours.

4.3.1.4 Collective Dose

The collective dose for removal of the 640 

filter elements was 2.4 person-rem. The dose 

for performing the work without the Brokk 

Manipulator was estimated to exceed 20 personrem (the average BNL annual site dose over 

the last several years) and would have resulted 

in exposures that approached administrative 

control levels for most of the BGRR field workers. 

The savings in external and internal dose and 

minimization of personnel exposure to other BGD 

industrial hazards justified the purchase and use of 

the Brokk Manipulator, which continues to be used 

in removing the BGD primary liner.

Point of contact: Thomas Jernigan, Project 

Engineer, 631-344-8244.
4-18 DOE Occupational Radiation Exposure 

4.5 Submitting ALARA Success 

Stories for Future Annual 

Reports

Individual success stories should be submitted 

in writing to the DOE Office of Corporate 

Performance Assessment. The submittal should 

describe the process in sufficient detail to 

provide a basic understanding of the project, the 

radiological concerns, and the activities initiated 

to reduce dose. 

The submittal should address the following:

  Mission statement

  Project description

  Radiological concerns

  Information on how the process 

implemented ALARA techniques in an 

innovative or unique manner

  Estimated dose avoided

  Project staff involved

  Approximate cost of the ALARA effort

  Impact on work processes, in personhours if possible (may be negative or 

positive)

  Figures and/or photos of the project 

or equipment (electronic images if 

available)

  Point-of-contact for follow-up by 

interested professionals.

4.4 Hanford ALARA Center of 

Excellence

The Hanford ALARA Center of Excellence is 

committed to providing a centralized resource for 

others to gain insight into practical applications 

of the ALARA approach and to serve as a 

clearinghouse of ALARA information.

DOE’s Hanford Site (586 square miles located in 

southeastern Washington State) was established 

during World War II as part of the Manhattan 

Project and played a pivotal role in the nation’s 

defense for more than 50 years.

Currently, the Hanford Site is engaged in the 

world’s largest environmental cleanup effort with 

many challenges to be resolved in the face of 

overlapping technical, regulatory, and cultural 

interests. The cleanup effort focuses on three 

outcomes: restoring the Columbia River corridor 

for other uses, transitioning the central plateau 

to long-term waste treatment and storage, and 

preparing for the future.

Over the years, the center has gathered a great 

deal of information in the application of the 

ALARA approach to daily operations. In 1996, DOE 

established the ALARA Center of Technology to 

provide a common resource for Hanford workers 

in the practical aspects of ALARA.

The Hanford ALARA Center is centrally located 

on the Hanford site to provide an informational 

resource to workers in the application of the 

ALARA approach in daily operations. While 

the focus of the ALARA Center has been at 

the Hanford site, ALARA Center staff routinely 

exchange information and ideas with others 

throughout the DOE complex for the benefit of all. 

Access the Center’s web site for more information:

 http://www.hanford.gov/alara/index.cfm
2003 Report ALARA Activities at DOE 4-19

4.6 Lessons Learned Process

The Department of Energy has a mature lessons 

learned process that was initially developed in 

1994. The current DOE Lessons Learned process 

is described in DOE Technical Standard, DOESTD-7501-99. The purpose of the DOE Lessons 

Learned process is to facilitate the identification, 

documentation, sharing, and utilization of 

lessons learned from a review of actual operating 

experiences throughout the DOE complex. This 

is accomplished by lessons sharing between DOE 

sites through a common Corporate Database. A 

recent review of the Lessons Learned process 

has led to a redesign of the process to add a 

more corporate component to the process. This 

new corporate component, modeled after the 

Institute for Nuclear Power Operations (INPO) 

Significant Event Evaluation and Information 

Network (SEE-IN) program, has introduced an 

additional corporate role in the review of DOE 

Site performance and crosscutting operating 

experience and has started to provide additional 

Lessons Learned information to the DOE 

community, in addition to that already provided by 

DOE Field Sites. 

The collected information is currently located on 

an Internet web site as part of the Environmental 

Safety & Health (ES&H) web page. This system 

allows for shared access to lessons learned across 

the DOE complex. The information available 

on the system complements existing reporting 

systems presently used within DOE. DOE is 

taking this approach to enhance those existing http://www.eh.doe.gov

http://www.eh.doe.gov/ll

systems by providing a method to quickly share 

information among the field elements. Also, this 

approach goes beyond the typical occurrence 

reporting to identify good lessons learned. DOE 

uses the web site to openly disseminate such 

information so that not only DOE but also 

other entities will have a source of information 

to improve the health and safety aspects of 

operations at and within their facilities. Additional 

benefits include enhancing the workplace 

environment and reducing the number of 

accidents and injuries.

The web site contains several items that are 

related to health physics. Items range from offnormal occurrences to procedural and training 

issues. Documentation of occurrences includes 

the description of events, root-cause analysis, and 

corrective measures. Several of the larger sites 

have systems that are connected through this 

system. DOE organizations are encouraged to 

participate in this valuable effort.

The Web site address for DOE Corporate Operating 

Experience Review Lessons Learned web page is:

The specific web site address may be subject 

to change. ES&H information services can be 

accessed through the main Office of Environment, 

Safety, and Health web page at:
4-20 This page intentionally left blank. DOE Occupational Radiation Exposure
2003 Report Conclusions 5-1

Section Five Conclusions 5

5.1 Conclusions

Conclusions

The collective dose at DOE facilities has 

experienced a dramatic (83%) decrease since 

1986. The main reasons for this large decrease 

were the shutdown of facilities within the 

weapons complex and the end of the Cold War 

era, which shifted the DOE mission from weapons 

production to shutdown, stabilization, and D&D 

activities. The DOE weapons production sites 

have continued to contribute the majority of the 

collective dose over these years. Sites reporting 

under the category of weapons fabrication 

and testing account for the highest collective 

dose. Even though these sites are now primarily 

involved in nuclear materials stabilization and 

waste management, they still report under 

this facility type. As facilities are shut down or 

undergo transition from operation to stabilization 

or D&D, there are significant changes in the 

opportunities for worker radiation exposure. 

The collective TEDE increased 6% from1,360 

person-rem (13.60 person-Sv) in 2002 to 1,445 

person-rem (14.45 person-Sv) in 2003 due to 

increases in the collective dose at four of the 

six highest dose sites. These six sites accounted 

for 80% of the collective dose at DOE in 2003. 

Four of these sites attributed the increase in 

dose to thermal stabilization and repackaging of 

plutonium-bearing materials, processing of spent 

fuels, and accelerated cleanup of tank farms at 

Hanford, resumption of processing of radioactive 

material, special programs, and accelerated 

facility closure and waste processing activities at 

Savannah River, and work activities associated 

with the building 9204-4 Cleanup Project and the 

TVA Off-Specification Fuel repackaging project at 

Oak Ridge, and the processing of more materials 

containing americium, an upgrade to the material 

storage vault, and the decontamination and 

decommissioning of the Omega West reactor at 

LANL. A statistical analysis was performed to 

determine the trend in collective dose over the 

past 5 years. The analysis indicates that while 

the collective TEDE, neutron, and extremity 

dose increased between 2002 to 2003, it does 

not represent a statistically significant change in 

the dose received by individual workers at DOE. 

Further tests revealed fewer individuals received 

neutron doses above 0.500 rem (5 mSv). 

The collective internal dose (CEDE) increased 

by 38% from 69 person-rem (690 person-mSv) in 

2002 to 95 person-rem (950 person-mSv) in 2003. 

The increase was primarily due to a nearly fourfold increase in internal dose from plutonium. 

The main contributor to this increase was the 

two exposures in excess of 5 rem (50 mSv) at 

LANL (see Section 3.3.1). Mound and Rocky 

Flats also reported increases in internal dose 

from plutonium from 2002 to 2003. Internal dose 

from other radionuclides decreased or essentially 

remained the same from 2002 to 2003. Due 

to several factors, such as changes in internal 

dosimetry practices, monitoring and reporting 

procedures, changes in the dosimetry equipment, 

and the relatively small number of internal doses, 

care should be taken in examining trends in 

internal dose.
5-2 DOE Occupational Radiation Exposure

Exhibit 5-1:

2003 Radiation Exposure Fact Sheet.

 The collective TEDE increased by 6% (from 1,360 person-rem to 1,445 person-rem) (13,600 person-mSv

to 14,450 person-mSv) from 2002 to 2003.

 The six highest dose sites (in descending order of collective dose: Hanford, Savannah River, Los Alamos, 

Rocky Flats, Oak Ridge, and Idaho) accounted for 80% of the collective dose at DOE in 2003.

 Increases in collective dose at four of the top six sites were attributed to a thermal stabilization and 

repackaging of plutonium-bearing materials, processing of spent fuels, and accelerated cleanup of tank 

farms at Hanford, resumption of processing of radioactive material, special programs, and accelerated 

facility closure and waste processing activities at Savannah River, and work activities associated with the 

building 9204-4 Cleanup Project and the TVA Off-Specification Fuel repackaging project at Oak Ridge, and 

the processing of more materials containing americium, an upgrade to the material storage vault, and the 

decontamination and decommissioning of the Omega West reactor at LANL.

 A statistical analysis was performed to determine the trend in collective dose over the past 5 years. The 

analysis indicates that while the collective TEDE, neutron, and extremity dose increased between 2002 

to 2003, it does not represent a statistically significant change in the dose received by individual workers 

at DOE. Further tests revealed fewer individuals received neutron doses above 0.500 rem (5 mSv). This 

reflects a positive change in accordance with ALARA to reduce neutron dose to individuals at higher 

annual dose levels.

 The collective internal dose (CEDE) increased by 38% from 69 person-rem (690 person-mSv) in 2002 to 

95 person-rem (950 person-mSv) in 2003. The increase was primarily due to a nearly four-fold increase in 

internal dose from plutonium. 

 The number of transient workers monitored at DOE decreased from 2,848 in 2002 to 2,665 in 2003. 

However, the average measurable dose to transient workers increased by 41%. 

An analysis was performed on the transient 

workforce at DOE. A transient individual, or 

transient, is defined as an individual monitored 

at more than one DOE site in a year. The results 

of this analysis show that the number of transient 

workers monitored decreased from 2,848 in 2002 

to 2,665 in 2003. The collective dose for these 

transients increased by 54% from 36.5 person-rem 

(365 person-mSv) in 2002 to 56.1 person-rem (561 

person-mSv) in 2003, resulting in a 41% increase 

in the average measurable dose.

The detailed nature of the data available has 

made it possible to investigate distribution and 

trends in data and to identify and correlate 

parameters having an effect on occupational 

radiation exposure at DOE sites. A summary of 

the findings for 2003 is shown in Exhibit 5-1.
2003 Report Glossary G-1

Glossary

Glossary

Administrative Control Level (ACL) 

A dose level that is established below the DOE dose limit in order to administratively control exposures. ACLs 

are multi-tiered with increasing levels of authority required to approve a higher level of exposure.

ALARA

Acronym for “As Low As Reasonably Achievable,” which is the approach to radiation protection to manage 

and control exposures (both individual and collective) to the workforce and the general public to as low as is 

reasonable, taking into account social, technical, economic, practical, and public policy considerations. ALARA 

is not a dose limit but a process with the objective of attaining doses as far below the applicable limits as is 

reasonably achievable. 

Annual Effective Dose Equivalent (AEDE)

The summation for all tissues and organs of the products of the dose equivalent calculated to be received 

by each tissue or organ during the specified year from all internal depositions multiplied by the appropriate 

weighting factor. Annual effective dose equivalent is expressed in units of rem.

Average Measurable Dose 

Dose obtained by dividing the collective dose by the number of individuals who received a measurable dose. 

This is the average most commonly used in this and other reports when examining trends and comparing doses 

received by workers because it reflects the exclusion of those individuals receiving a less than measurable dose. 

Average measurable dose is calculated for TEDE, DDE, neutron dose, extremity dose, and other types of doses.

Collective Dose 

The sum of the total annual effective dose equivalent or total effective dose equivalent values for all individuals 

in a specified population. Collective dose is expressed in units of person–rem.

Committed Dose Equivalent (CDE) (HT,50)

The dose equivalent calculated to be received by a tissue or organ over a 50–year period after the intake of 

a radionuclide into the body. It does not include contributions from radiation sources external to the body. 

Committed dose equivalent is expressed in units of rem.

Committed Effective Dose Equivalent (CEDE) (HE,50)

The sum of the committed dose equivalents to various tissues in the body (HT,50), each multiplied by the 

appropriate weighting factor (wT)––i.e., HE,50 = ∑wTHT,50. Committed effective dose equivalent is expressed in 

units of rem.

CR

CR is defined by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as the 

ratio of the annual collective dose delivered at individual doses exceeding 1.5 rem (15 mSv) to the collective 

dose. UNSCEAR now uses SR15 to denote this ratio where the subscript indicates the dose value

(in mSv) used to calculate the ratio.

Deep Dose Equivalent (DDE)

The dose equivalent derived from external radiation at a depth of 1 cm in tissue.

DOE Site

A geographic location operated under the authority of the Department of Energy (DOE). The DOE sites 

considered in this report are listed in Appendix A by Operations Office. 

Glossary
G-2 DOE Occupational Radiation Exposure 

Effective Dose Equivalent (HE) 

The summation of the products of the dose equivalent received by specified tissues of the body (HT) and the 

appropriate weighting factor (wT)––i.e., HE = ∑wTHT. It includes the dose from radiation sources internal and/or external 

to the body. The effective dose equivalent is expressed in units of rem.

Exposure

As used in this report, exposure refers to individuals subjected to, or in the presence of, radioactive materials which may 

or may not result in occupational radiation dose.

Kruskall-Wallis Test

Uses a test statistic based on rank sums to determine whether two populations are significantly different.

Lens of the Eye Dose Equivalent (LDE)

The radiation dose for the lens of the eye is taken as the external equivalent at a tissue depth of 0.3 cm.

Logarithmic Mean

The mean calculated from log-transformed values.

Members of the Public

Individuals who are not occupationally exposed to radiation or radioactive material. This includes visitors and 

visiting dignitaries.

Minimum Detectable Activity (MDA)

The smallest quantity of radioactive material or level of radiation that can be distinguished from background 

with a specified degree of confidence. Often used synonymously with minimum detection level or lower limit of 

detection.

Non-parametric Procedures

Statistical tests that do not depend on a specific parent distribution.

Normal Log-transformed Data

Data that fit a normal distribution after being transformed to logarithms.

Number of Individuals with Measurable Dose

The subset of all monitored individuals who receive a measurable dose (greater than limit of detection for the 

monitoring system). Many personnel are monitored as a matter of prudence and may not receive a measurable 

dose. For this reason, the number of individuals with measurable dose is presented in this report as a more 

accurate indicator of the exposed workforce. The number of individuals represents the number of dose records 

reported. Some individuals may be counted more than once if multiple dose records are reported for the 

individual during the year.

Occupational Dose 

An individual’s ionizing radiation dose (external and internal) as a result of that individual’s work assignment.

Occupational dose does not include doses received as a medical patient or doses resulting from background

radiation or participation as a subject in medical research programs.

Pairwise T-tests

This test compares all possible pairs of means and uses a T-test to determine whether differences are significant.

Shallow Dose Equivalent (SDE) 

The dose equivalent deriving from external radiation at a depth of 0.007 cm in tissue.
2003 Report Glossary G-3

SR

SR is defined by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as the ratio of 

the annual collective dose delivered at individual doses exceeding a specified dose value to the collective dose. UNSCEAR uses a subscript to denote the dose value (in mSv) used in the calculation of the ratio. Therefore SR15 would be 

the ratio of the annual collective dose delivered at individual doses exceeding 1.5 rem (15 mSv) to the collective dose.

Statistical Normal Distribution

A distribution that is symmetric and can be described completely by the mean and variance. This property is 

required for many statistical tests.

Total Effective Dose Equivalent (TEDE)

The sum of the effective dose equivalent for external exposures and the committed effective dose equivalent for internal 

exposures. Deep dose equivalent to the whole body is typically used as effective dose equivalent for external exposures. 

The internal dose component of TEDE changed from the Annual Effective Dose Equivalent (AEDE) to the Committed 

Effective Dose Equivalent (CEDE) in 1993.

Total Number of Records for Monitored Individuals 

All individuals who are monitored and reported to the DOE Headquarters database system. This includes DOE 

employees, contractors, subcontractors, and members of the public monitored during a visit to a DOE site. The 

number of individuals represents the number of dose records reported. Some individuals may be counted more 

than once if multiple dose records are reported for the individual during the year.

Transient Individual 

An individual who is monitored at more than one DOE site during the calendar year.

T-test

A statistical test for comparing means from two populations based on the value of t, where

 and y1 = sample mean, population 1

 y2 = sample mean, population 2

 S y

1 – y2 = standard deviation appropriate to the difference between the two means.

t = y1 – y2

 S y

1 – y2
G-4 This page intentionally left blank. DOE Occupational Radiation Exposure
2003 Report References R-1

References

References

References

1. EPA (U.S. Environmental Protection Agency), 1987. “Radiation Protection Guidance to Federal Agencies 

for Occupational Exposure,” Federal Register 52, No. 17, 2822; with corrections published in the Federal 

Registers of Friday, January 30, and Wednesday, February 4, 1987.

2. ICRP (International Commission on Radiological Protection), 1977. “Recommendations of the 

International Commission on Radiological Protection,” ICRP Publication 26, Annals of the ICRP, Vol. 1, No. 3 

(Pergamon Press, New York).

3. NCRP (National Council on Radiation Protection and Measurements), 1987. “Recommendations on Limits 

for Exposure to Ionizing Radiation,” NCRP 91; superceded by NCRP Report No. 116.

4. DOE (U.S. Department of Energy), December 21, 1988, Order 5480.11, “Radiation Protection for 

Occupational Workers, ” Change 3, June 17, 1992.

5. DOE 1994. Radiological Control Manual. Revision 1, DOE/EH-0256T, Assistant Secretary for Environment, 

Safety and Health, April.

6. 10 CFR Part 835. “Occupational Radiation Protection.” Final Rule; DOE Federal Register, November 4, 1998.

7. DOE-STD-1098-99, “Radiological Control Standard,” July 1999.

8. The Price-Anderson Amendments Act of 1988, Public Law 100-408, August 20, 1988.

9. 10 CFR 820. “Procedural Rules for DOE Nuclear Activities,” August 17,1993.

10. DOE Notice 441.1, “Radiological Protection for DOE Activities,” September 29, 1995.

11. DOE Order 5484.1, “Environmental Protection Safety, and Health Protection Information Reporting 

Requirements,” February 24, 1981, Change 7, October 17, 1990.

12. DOE Order 231.1-1, “Environment, Safety and Health Reporting,” September 30, 1995.

Revised October 26, 1995. Revised November 7, 1996.

13. DOE M 231.1-1, “Environment, Safety and Health Reporting Manual,” September 30, 1995.

Revised November 7, 1996. Revised January 28, 2000.

14. DOE Order 231.1A, “Environment, Safety and Health Reporting,” August 19, 2003.

15. DOE M 231.1-1A, “Environment, Safety and Health Reporting Manual,” Approved March 19, 2004.

16. Munson, L.H., et al., 1988. Health Physics Manual of Good Practices for Reducing Radiation Exposures to 

Levels that are As Low As Reasonably Achievable (ALARA), PNL-6577, Pacific Northwest Lab.

17. United Nations, Sources and Effects of Ionizing Radiation, United Nations Scientific Committee on the Effects 

of Atomic Radiation UNSCEAR 2000 Report to the General Assembly, with scientific annexes, Volume I,

General Assembly of Official Records, United Nations, New York, 2000.
R-2 This page intentionally left blank. DOE Occupational Radiation Exposure
2003 Report DOE Reporting Sites and Reporting Codes A-1

Exhibit Title Page 

A-1 Labor Categories and Occupation Codes.........................................................................................A-2

A-2 Organizations Reporting to DOE REMS, 1999-2003...........................................................................A-3

A-3 Facility Type Codes ..............................................................................................................................A-7

Appendix A ADOE Reporting Sites and Reporting Codes

DOE Reporting Sites and Reporting Codes
A-2 DOE Occupational Radiation Exposure 

A.1 Labor Categories and 

Occupation Codes

The following is a list of the Occupation 

Codes that are reported with each 

individual’s dose record to the DOE 

Radiation Exposure Monitoring System 

(REMS) in accordance with DOE M 231.1-1 

[13]. Occupation Codes are grouped into 

Labor Categories for the purposes of

analysis and summary in this report. The 

occupation codes are listed in DOE M 

231.1-1, Appendix G, Table 2, and represent 

a subset of the occupations listed in the 

Department of Commerce’s Standard 

Occupational Classification (SOC) Manual 

(1980).

���������� �������������� ���� ���������������

�����������

������������

��������

����������

�����

����������

����������

�������

�����������

���������

�������

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

����

��������������

��������������

�����������������

�������������������

������

����������

������������

��������

�����������

���������������

�������������������������

�������������������������

�����������������������

�����

���������������������������

��������

�������������

����������

�������������������

�������������������������������

�����������������������

���������������������

��������������������������

��������

���������

����������������

������������������

������������������

������������

���������������

����������������������

��������

�������������

�����������

������������������

�����������������������

�������������������

�������������������������

�����������������

�������������

�����������

������

�������������������

���������������

�������

Exhibit A-1.

Labor Categories and Occupation Codes.
2003 Report DOE Reporting Sites and Reporting Codes A-3

A.2 Organizations Reporting to DOE REMS, 1999-2003

Twenty-seven sites reported occupational exposure data in 2003. The following is a list of all organizations reporting to 

the DOE REMS from 1999 to 2003. The list provides the Operations Field Office and Site groupings used in this report as 

well as the organization reporting code and name.

������������

���� �����������������

�����������

������������ ���� ��� ��� ��� ���

��������������

����������� ������������������������� ������ �����������������������������

������ �����������������������������������

������ �����������������������

������ �������������������������������������

������ ������������������������������������

������ ���������������������������������������

������� �����������������������������������������

�������������� ������ ������������

������ �������

������������������������������� ������ ����������������������

������ ������������������������������

������ ����������������������������������

������ ����������������������

����������������� ������ ��������������������

������ �����������������

������ ���������������

������ ��������������������������������

������ ���������������������������������

�������������������������� ������ ��������������������

������ ��������������������������

������� ������������������������� ������� ����������������������������

������� �������������������������

������� �������������������

������� �����������������������������������

������� �����������������������������������

������� �����������������������������������

��������������������������������� ������� ����������������������������������

��������������������������������� ������� ����������������������������������

��������������������������� ������� ������������������������������

������������������������������������ ������� ��������

������� ���������������� ������� ����������������

���������������� ������� �����������������������

������� ��������������������������

���������� ������� ����������������������

����� ���������� ������� ������������������

������� ������������

������� ����������������������������������

������� ���������������������������������������������

������� �������������������

������� ������������������������

������� �������������������������������������

���

   

  

    

    

    

    

    

  

  

    

    

    

    

    



    

  

   

  

    

    

    

   

   

    

    

    

    

    

    

   





 

    

 

    

    







Exhibit A-2.

Organizations Reporting to DOE REMS, 1999-2003.
A-4 DOE Occupational Radiation Exposure 

Exhibit A-2.

Organizations Reporting to DOE REMS, 1999-2003 (continued).

������������

���� �����������������

�����������

������������ ����

��������������

��� ��� ��� ��� ���

������ ���������������������� ������� �����������������

������� ��������������������������

������� ��������������������

������� �����������������������������������

������� ������������������������������������������

������� ����������������������������������������

������� �������������������

������� ��������������������������������

������� �������������������������������������

������� ������������������

������� ��������������������������������������

������� �����������������������������

��������� ������������������������� ������� �������������������������������������������

������� ����������������������

������� �������������������������

������� �����������������������������������������

������� �����������

�������������� ������� ���������������������������

������� ���������������������������������

������� ������������������������������

������� �������������������������������������������

������� ������������������������������������������

������� ������������������

������� ���������������������

������� ������������������

������� ��������������

������� ���������������������

������� ����������

������������������������������� ������� ���������������������������������

����������������������������������� ������� ���������������������������

������� ������������������������� ������� �������������������������

������� �������������������

������� ������������������������������������������

������� ��������������������

������������������������������������ ������� �������������������������������������

������������������������������ ������� ��������������������������������������

������ ������� �������������������

������� �������������

���������������������������������� ������� ����������������������������������

������� ��������������������������������

    



    

    

 

  



    



    

   

    

    

    

  

    







    

    

  

    

   

   

  

   

  

    

    

   



    



    

    

  

 

    


2003 Report DOE Reporting Sites and Reporting Codes A-5

���� �����������

������������

������������

���� �����������������

��������������

��� ��� ��� ��� ���

���� ������������������������� ������� �����������������

������� ��������������������������������������

������� ����������������

������� ��������������������������������������

��������������������� ������� �����������������������������������

������� ����������������������������������

������� ��������������������

������� �����������������������������

������� ����������������������������

����������� ������� ���������������������

������� ��������������������������������������

������� ���������������������������������������

������������������� ������� �����������������������

������� �����������������������������������������

������� ��������������������������

����������� ����������������������������������� ������� ������������������

������� �����������������������

������� �����������������������������

������� ��������������������������

�������� ������������ ������� ����������������������������

������� ��������������������������

������� �����������������������

������� ���������������������������������

������� ��������������������������������������

������� �����������������

������� ���������������������������������������

������� ��������������������������������������

������� ����������������������

������� ����������������������

������� �������������������������������

������� ����������������������

������� �������������������������������

������� ���������������������

������� �������������������������������

������� ���������������������������������

������� �������������������������������������������

������� ���������������

������� �����������������������

    

    

    

    

    

    

    

    

    

    

    

    



    

   

    

    

    

  



   

    

 

  

    



    

    

    

  



    

    

    

  

    



Exhibit A-2.

Organizations Reporting to DOE REMS, 1999-2003 (continued).
A-6 DOE Occupational Radiation Exposure 

����������������������������������������������������������������������������������������������������������������������������������������������

�������������������������������������������������������������������������������������������������������������������������������������������������������

�����������

������������

������������

���� ���� �����������������

�

��������������

��� ��� ��� ��� ���

�������� ������������ ������� ��������������������������������

������� ���������������

������� ��������������������������

������� ����������������

������� ���������������������

������� �������������

�������� ������������������������� ������� �������������������������

����� ������� �������������������������������

������� ��������������������������������

������� �������������������

������� ���������������������������

������� ����������������������������������

������� �������������������������

������� �������������������������������������

������� �����������������������������

���������� ������������������������������� ������� ����������������������

����� ������� ��������������������������������

������� ������� ����������������������������

������ ������� ���������������������������

����������� �������������������������������� ������� �����������������������������

����� ������� ��������������������

������� ������� ����������������������������������������

������ ������� ����������������

������� ���������������������

������� �����������������

������� ���������������������������������

������� �����������������������

    

  

    

    

    

    

    

    

    



    

    

 

    

    

��������������������������������������������

Exhibit A-2.

Organizations Reporting to DOE REMS, 1999-2003 (continued).
2003 Report DOE Reporting Sites and Reporting Codes A-7

A.3 Facility Type Codes

The following is the list of Facility Type Codes 

reported to REMS in accordance with

DOE M 231.1-1 [13]. A facility type code is 

reported with each individual’s dose record and 

indicates the facility type where the majority of 

the individual’s dose was accrued during the 

monitoring year.

Exhibit A-3. 

Facility Type Codes.

See complete Facility Type descriptions shown in

Appendix C.

�������������

���� �����������

��

��

��

��

��

��

��

��

��

��

��

�����������

�����������������������

����������������

���������������

�����������������������

��������������������

�������

�����������������

����������������

����������������������

������������������������

�����
A-8 This page intentionally left blank. DOE Occupational Radiation Exposure
2003 Report Additional Data B-1

Additional Data Appendix B BAdditional Data

B-1a Operations Office/Site Dose Data - 2001 ..............................................................................................B-2

B-1b Operations Office/Site Dose Data - 2002 ..............................................................................................B-3

B-1c Operations Office/Site Dose Data - 2003 ..............................................................................................B-4

B-2a Collective Dose and Average Measurable Dose 1974-2003................................................................B-5

B-2b Number with Measurable Dose and Average Measurable Dose 1974-2003.....................................B-6

B-3 Distribution of Deep Dose Equivalent (DDE) 1974-2003 and Total Effective Dose

 Equivalent (TEDE) 1990-2003 ................................................................................................................B-7

B-4 Internal Dose by Operations/Site, 2001-2003 ......................................................................................B-8

B-5 Neutron Dose Distribution by Operations/Site, 2003.........................................................................B-9

B-6a Distribution of TEDE by Facility Type - 2001 .......................................................................................B-10

B-6b Distribution of TEDE by Facility Type - 2002 .......................................................................................B-11

B-6c Distribution of TEDE by Facility Type - 2003 .......................................................................................B-12

B-7a Collective TEDE by Operations/Site and Facility Type - 2001...........................................................B-13

B-7b Collective TEDE by Operations/Site and Facility Type - 2002...........................................................B-14

B-7c Collective TEDE by Operations/Site and Facility Type - 2003...........................................................B-15

B-8 Distribution of TEDE by Facility Type Listed in Descending Order of 

 Average Measurable TEDE for Accelerator Facilities, 2003...............................................................B-16

B-9 Distribution of TEDE by Facility Type Listed in Descending Order of Average 

 Measurable TEDE for Fuel Facilities, 2003 ...........................................................................................B-17

B-10 Distribution of TEDE by Facility Type Listed in Descending Order of Average 

 Measurable TEDE for Maintenance and Support, 2003......................................................................B-19

B-11 Distribution of TEDE by Facility Type Listed in Descending Order of 

 Average Measurable TEDE for Reactor Facilities, 2003......................................................................B-21

B-12 Distribution of TEDE by Facility Type Listed in Descending Order of Average 

 Measurable TEDE for Research, General, 2003 ..................................................................................B-22

B-13 Distribution of TEDE by Facility Type Listed in Descending Order of Average

 Measurable TEDE for Research, Fusion, 2003 ....................................................................................B-24

B-14 Distribution of TEDE by Facility Type Listed in Descending Order of Average

 Measurable TEDE for Waste Processing, 2003 ....................................................................................B-25

B-15 Distribution of TEDE by Facility Type Listed in Descending Order of Average

 Measurable TEDE for Weapons Fabrication, 2003 ..............................................................................B-27

B-16 Distribution of TEDE by Facility Type Listed in Descending Order of Average 

 Measurable TEDE for Other, 2003 .........................................................................................................B-28

B-17 Internal Dose by Facility Type and Nuclide, 2001-2003 .....................................................................B-31

B-18a Distribution of TEDE by Labor Category - 2001 ..................................................................................B-32

B-18b Distribution of TEDE by Labor Category - 2002 ..................................................................................B-33

B-18c Distribution of TEDE by Labor Category - 2003 ..................................................................................B-34

B-19 Internal Dose by Labor Category, 2001-2003 .......................................................................................B-35

B-20 Dose Distribution by Labor Category and Occupation - 2003 ..........................................................B-36

B-21 Internal Dose Distribution by Site and Nuclide - 2003 .......................................................................B-37

B-22 Extremity Dose Distribution by Operations/Site - 2003.....................................................................B-38

Exhibit Title Page 
B-2 DOE Occupational Radiation Exposure 

Exhibit B-1a: Operations Office/Site Dose Data - 2001

�����������

�������

������

�����

������

�������

���������

����

�����������

��������

��������

�����

������

�������������������������

�������������������������������

�����������������

��������������������������

��������������

�������������������������

������������������������������������

������������������������������������

������������������������������

�������������������������������������

���������������������������������

�������������������

����������

����������

����������������������

�������������������������

��������������������������������������

���������������������������������������

�����������������������������������������

�������������������������

��������������

����������������������������������

��������������������������������������

�������������������������

��������������������������������������

�����������������������������������

�����������

�������������������

�����������������������������������

������������

�������������������������

���������������������������������������������������������������

�����������

������������ ���������������

������������

��������������

���������

�����������

����������

��������������

���������

��������������

���������

�������������������

����������

���������

��������������

���������

����

����

��� ���� � �� ���� � ����� ��� � �� ��

����� ���� � ����� ��� � ����� ���� � ��� ���� �

���� ��� � ��� �� � ����� ��� � ��� �� �

��� ���� � �� ��� � ����� ���� � �� ��� �

��� �� � � ���� � ����� ���� � �� ��

��� ���� � ��� ��� � ����� ��� � �� ��

���� ��� � ��� �� � ����� ��� � ��� ��� �

���� ��� � ��� ��� � ����� ���� � �� ��� �

���� ���� � ��� ���� � ����� ���� � �� ��� �

���� ���� � ��� ��� � ����� ��� � �� ��� �

��� ���� � � ���� � ����� ��� � �� ��

��� � �����

����� ��� � ����� ��� � ����� ��� � ��� ��� �

��� ���� � �� ��� � ����� ���� � �� ��

��� ��� � ��� �� � ����� ��� � �� ��

��� ���� � �� ���� � ����� ��� � �� ��

���� ��� � ��� �� � ����� ��� � ��� ��� �

��� ���� � �� ���� � ����� ���� � �� ��

��� ��� � ��� ��� � ����� ��� � �� ��

����� �� � ����� ��� � ����� ���� � ��� �� �

��� �� � ��� ��� � ����� ���� � �� ��

��� ���� � �� ���� � ����� ��� � �� ��

��� �� � �� ���� � ����� ��� � �� ��

���� ��� � �� ���� � ����� ��� � ��� ��� �

���� ���� � ��� ���� � ����� ���� � �� ��

��� ��� � �� ���� � ����� ��� � �� ��

���� ��� � ��� ��� � ����� ��� � �� �� �

����� ���� � ����� �� � ����� ���� � ��� ���� �

����� ��� � ����� ��� � ����� ���� � ��� ��� �

����� ��� � ����� �� � ����� ��� � ��� ��� �

������� ��� � ������ �� � ����� ��� � �� ���� �

���������������

�����

�������������������������������������������������������������������������������������������������������������������������

�����������������������������������������������������������������������������������������������������������������������

�����������������������������
2003 Report Additional Data B-3

Exhibit B-1b: Operations Office/Site Dose Data - 2002

�����������

�������

������

�����

������

�������

���������

����

�����������

��������

��������

�����

������

���������������������������������������������������������������

����������������������������������������������������������

�����������

������������ ���������������

������������

��������������

���������

�����������

����������

��������������

���������

���������������

�����

��������������

���������

�������������������

����������

���������

��������������

���������

����

����

��� ���� � ��� ��� � ����� ��� � �� ��

����� ��� � ����� ��� � ����� ��� � ��� �� �

���� �� � ��� �� ����� �� � ��� ��

��� ��� � ��� ��� � ����� ���� � �� ��

��� ���� � ��� ��� � ����� ���� � ��� ��� �

���� �� � ��� ��� � ����� ���� � ��� ��� �

���� ��� � ��� �� � ����� ��� � �� �� �

���� ��� � ��� ��� � ����� ��� � ��� ��� �

���� ��� � ��� �� � ����� ��� � �� ��

��� � ��� �� ��

��� � ��� �� ��

���� ���� � ����� �� ����� ���� � �� ���� �

��� ���� � �� ��� � ����� ���� � �� ��

��� ���� � �� ���� � ����� ���� � ��� ��� �

��� ��� � �� ��� � ����� ���� � �� ��

���� ��� � ��� �� � ����� ��� � ��� ��� �

��� ���� � �� ���� � ����� �� �� ��

��� ���� � ��� ���� � ����� ���� � �� ��

����� ���� � ����� ���� � ����� �� �� ��� �

��� ��� � ��� ��� � ����� ��� � �� ��

��� ���� � �� �� � ����� ���� � �� ��

��� ���� � �� ���� � ����� ���� � �� ��

���� ��� � ��� ��� � ����� �� � ��� ��� �

���� ��� � ��� ��� � ����� ��� � �� ��

��� ���� � ��� ���� � ����� �� � �� ��

���� ��� � ��� �� � ����� ��� � ��� ��� �

����� �� � ����� ���� � ����� ��� � ��� �� �

����� ��� � ����� ��� � ����� �� � ��� ��� �

����� ��� � ����� ���� � ����� �� � ��� ��� �

������� ��� � ������ �� � ����� �� � ��� ��� �

�������������������������

�������������������������������

�����������������

��������������������������

���������������

�������������������������

������������������������������������

������������������������������������

������������������������������

�������������������������������������

���������������������������������

��������������������������

����������

����������������������

�������������������������

��������������������������������������

���������������������������������������

�����������������������������������������

�������������������������

��������������

����������������������������������

��������������������������������������

�������������������������

��������������������������������������

�����������������������������������

�����������

�������������������

�����������������������������������

������������

�������������������������

�������������������������������������������������������������������������������������������������������������������

�������������������������������������������������������������������������������������������������������������������������

������������������������������������������������������������������������������������������������������������������

���������������������������������������������������������������������������
B-4 DOE Occupational Radiation Exposure 

Exhibit B-1c: Operations Office/Site Dose Data - 2003

���

�����

����

����

���

����

����

����

����

����

���

���

���

����

���

���

�����

���

���

���

����

����

���

����

�����

�����

�����

�������

����

���

����

����

����

���

���

����

����

����

����

����

���

���

��

���

��

����

����

���

����

���

����

���

����

��

���

��

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

���

�����

���

���

���

���

���

���

���

�����

��

��

��

���

���

��

�����

��

��

��

���

���

���

���

�����

�����

�����

������

���

���

���

����

����

���

��

����

���

��

����

����

����

���

���

���

��

����

����

���

���

���

���

����

����

��

��

��

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

�����

����

���

����

���

����

���

���

����

���

���

���

���

���

��

����

���

��

����

����

���

����

����

���

���

���

��

���

��

��

���

���

��

��

��

���

��

��

��

��

��

��

���

��

��

��

��

��

��

���

��

��

���

���

���

���

���

�

���

���

��

����

����

���

����

��

���

��

����

��

��

��

��

��

��

��

��

���

��

��

���

��

��

��

��

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�

�����������

�������

������

�����

������

�������

���������

����

�����������

��������

��������

�����

������

�������������������������

�������������������������������

�����������������

��������������������������

���������������

�������������������������

������������������������������������

������������������������������������

������������������������������

�������������������������������������

���������������������������������

�������������������

����������

����������������������

�������������������������

��������������������������������������

���������������������������������������

�����������������������������������������

�������������������������

��������������

����������������������������������

��������������������������������������

�������������������������

��������������������������������������

�����������������������������������

�����������

�������������������

�����������������������������������

������������

�������������������������

�����������

������������ ���������������

������������

��������������

���������

�����������

����������

��������������

���������

��������������

���������

�������������������

����������

���������

��������������

���������

����

����

���������������

�����

���������������������������������������������������������������

����������������������������������������������������������

���������������������������������������������������������������������������������������������������������������������������

���������������������������������������������������������������������������������������������������������������������

�������������������������������������������������������������������������������������������������������
2003 Report Additional Data B-5 Exhibit B-2a: Collective Dose and Average Measurable Dose 1974-2003 0 8,000 6,000 4,000 2,000 12,000 10,000 0.35 0.30 0.25 0.20 0.15 0.10 0.05 0.00

son-rem) Collective Dose* (per

verage Measurable Dose* (rem) A

Year

*

���� ���� ���� ���� ���� ���� ���� ����

1974-1989 Collective Dose=DDE1990-1992 Collective Dose=DDE+AEDE1993-2003 Collective Dose=DDE+CEDE

2001 197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000 2002

����

2003

Collective Dose* (person-rem)

Average Meas. Dose* (rem)
B-6 DOE Occupational Radiation Exposure 

Exhibit B-2b: Number with Measurable Dose and Average Measurable Dose 1974-2003 60,000 50,000 40,000 30,000 20,000 10,000 0.35 0.30 0.25 0.20 0.15 0.10 0.05 0.00

Number with Measurable Dose*

Average Measurable Dose* (rem)

Number with Measurable Dose

Average Meas. Dose* (rem)

1974-1989 Collective Dose=DDE1990-1992 Collective Dose=DDE+AEDE1993-2003 Collective Dose=DDE+CEDE

0

Year

*

2001

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2002

2003
2003 Report Additional Data B-7

Exhibit B-3: Distribution of Deep Dose Equivalent (DDE) 1974-2003 and

Total Effective Dose Equivalent (TEDE) 1990-2003

��������������������������

������������������������������������������������������������������������

��������������������������������������������������������� ������ ����������������������������������������������������������

���� �������������� ������� ��� ��� ��� ��� ��� ��� ��� ��� ���� � ����� ���� ���

�����

���������

��������

��������� ���������

������������

���� �����

���

���������������������������������������

����

���������

����� �������

�����

���������

��������

����������

���������� ��� ��� ��� ��� ��� ��� ��� ��� ���� � ����� ���� ��� ������������

����

�����

����

���� ������ ������ ��� �� � � � � � � ��������� ������ ����� �����

���������������� ��������� ��� �� � � � � � ������� ������ ����� �����

���������������� ���������������� �� � � � � � � ������� ������ ����� �����

���� ������� ������������������� � � � � �������� ������� ����� �����

���� ������ ������� �� � ������� ������ ����� �����

���� ������� ������ ��� � � ������� ������ ����� �����

���� ������� ������ �� � � � ������� ������ ����� �����

���� ������ ������ �� � � � ������� ������ ����� �����

���� ������ ������ �� � � ������� ������ ����� ������

���� ������ ������ �� � � � ������� ������ ����� �����

���� ������ ������ �� � � � ������� ������ ����� �����

���� ������ ������ �� � ������ ������ ����� �����

���� ������ ������ �� � ������� ������ ����� �����

���� ������ ������ �� � � � ������� ������ ����� �����

���� ������ ������ ����� ��� ��� �� � �������� ������ ������ �����

���� ������ ������ ����� ��� ��� �� � ����������� ������ ������ ����� �����

���� ������ ������ ����� ��� �� � � ���������� ������ ����� �����

���� ������ ������ ����� ��� ��� �� � � � ���������� ������ ������ �����

���� ������ ������ ����� ��� �� �� ���������� ������ ����� �����

���� ������ ������ ����� ��� �� �� � � ����������� ������ ����� �����

���� ������ ������ ����� ��� �� ���������� ������ ����� �����

���� ������ ������ ��� ��� �� � �������� ������ ����� �����

���� ������ ������ ��� ��� �� �� ���������� �������� ����� �����

���� ������ ������ ����� ��� �� �� ���������� ������ ����� �����

���� ������ ������ ����� ��� �� �� ��������� ������ ����� �����

���� ������ ������ ����� ��� �� � � ���������� ������ ����� �����

���� ������ ������ ����� ��� �� � � � ���������� ������ �������� �����

���� ������ ������ ����� ��� �� ����������� ������ ������� �����

���� ������ ������ ��� �� ���������� ������ �������� �����

���� ������ ������ ��� �� ��������� ������ �������� �����

���� ������ ������ ��� �� ��������� ������ ������� �����

���� ������ ������ �� ��������� ������� ��������� �����

���� ������ ������ �� �������� ������� ������� �����

���� ������� ������ �� � ������������ ������� ������ ��������� �����

���� ������ ������ �� ������� ������� �������� �����

���� ������� ������ ��� ������� ������ ����� �����

���� ������� ������ �� � ������� ������ ����� �����

���� ������ ������ �� ������� ������ ����� �����

���� ������ ������ �� ������� ������ ����� �����

���� ������ ������ �� ������� ������ ����� �����

���� ������ ������ �� ��������� ������ ����� �����

���� ������ ������ �� ������ ������ ����� �����

���� ������ ������ �� � ������� ������ ����� �����

���� ������ ������ �� � ������� ������ ����� �����
B-8 DOE Occupational Radiation Exposure 

Exhibit B-4: Internal Dose by Operations/Site, 2001-2003 ���� ���� ������ ������������������� �������������� ������������������������� ����� ����� ��� ���������� ���� ���� �������������� ������� ���������� ���������������� ������� ����������� ���� ����������� ������������ ������������������� ���������������� �������������������� ��� ����� ����� ����� ����� ����� ����� ������ ����� ����� ������ ������ ����� ����� ����� ����� ����� ������ ����� ����� ����� ������ ���������� ������ ������ ������ ������ ������� �������� ������ ���������� ������ ����� ����� ������ ������ ����� ������� ����� ������ ������ ����� ����������������� �������������� ��������� ��� ����� ����� ������� ����� ����� ����� ����� ����� ����� ����� ������ ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ������ ����� ������� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ���� ������ ����� ����� �������� ��� ��� ����� ���� ��� ���� ����� ������� ������ �������� ������� ������ ������� ������ ������ ������� ������ ������ ������ ������ ������ ������ ������ ������ ������ ����� ������ �������� ������� ������ ������� ������ ������ ������� ������ ������ ������ ������ ������ ������ ������ ������ ����� ���� ���� ���� ���� ���� ���� ����������� ������������ ������������������ ����������������� ��������������� ���������������� ������������ ������������ ����� ��������������������������������������������������������������������������������������������������������������������������������������������������� ����������������������������������������������������������������� ������������������������������������������������������������������������������������������������������������� ����������� ������� ����� ������� ��������� ���� ����������� �������� �������������� ������ ���� ���� ���� �������������������������������������������������������������������������������������������������������������������������������������������� ����������������������������������������������������������������������������������������������������������������������������������������������� ���������������������������������������������������������������������
2003 Report Additional Data B-9 ������������������������������������������������������������������������������������������������������������������������������������������������� ��������������������������������������������������������������������������������������������������������� ��� ��� ����� ����� ��� �� � � � ������ ����� ��� ������ ����� ����� �� �� � ����� ��� �� ����� ����� ����� ����� ��� �� ��� �� �� ����� ����� ����� ��� � ����� ��� �� ����� ����� ��� �� � ��� �� �� ����� ����� ����� �� ����� �� �� ����� ����� ����� ����� ����� �� � ����� �� �� ����� ����� ����� �� � ����� �� �� ����� ����� ��� ��� ����� � ����� � �� ����� ����� ����� �� �� �� � ����� �� �� ����� ����� ����� �� ����� �� �� ����� ����� ����� ����� ������ ��� �� � ������ ��� �� ����� ����� ����� �� � ����� �� �� ����� ����� ��� � ��� � �� ����� ����� ��� ��� ��� ��� ����� ����� ��� � ��� � �� ����� ����� ��� ��� ����� ��� �� �� �� ����� ��� ��� ������ ����� ����� ��� �� �� � � � ������ ��� �� ������ ����� ����� ��� ��� �� � � ����� ��� �� ������ ����� ������ ����� ��� ��� �� �� �� � ������� ����� �� ������� ����� ���������� ������� ����� ������� ���������� ����� ���������� ���� ������������������������������������������������������������������������������������������������������������������������������������������������ �������� ���� ����� ���� ���� ���� ����� ��� ���� ���� ����� ��� ��� �� ������ ����������� ���������� ���� � ���� ����������� ���������� ���� ���������� ������� ���� ������������ ����������� ������� ������ ����� ������ ������� ��������� ���� ����������� �������� �������� ����� ����������� ������������������������������� ����������������� �������������������������� ������������������ ���������������������������������� ���������������������������������� ���������������������������� ������������������������������������� ���������������� �������������������������� ���������� ���������������������� ������������������ �������������������������������������� ��������������������������������������� ����������������������������������������� �������������������� �������������� ���������������������������������� �������������������������������������� ����������������� �������������������������������������� ����������������������������������� ����������� ����������� ����������������������������������� ������������ ������������������������� ������ � ����������������������������������������������������������������� Exhibit B-5: Neutron Dose Distribution by Operations/Site, 2003
B-1

0 DOE Occupational Radiation Exposure 

Exhibit B-6a: Distribution of TEDE by Facility Type - 2001

��������������������������������������

������������������������������������������������������������������������

������ ����������������������������������������������������������

�������������

���������

�����

�����

����

�����

���� ��� ��� ���

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

�����

����

�����

���� ��� ��

��������

�����

����

����������

����

������������

������������������������������������������������������������������������������������������������������������������������������������������������������������

����������������������������������������������������������������������������������������������������������������������������������������������������������

����������������������������

���������������������������������������������������������������������������������������������������������������������������������������������������������������������

�

� � �

�������

������������������

��������������

������

�������

����

������

�������

������

������������

������������������

����

������

���

������������

������

����

������

������������

���

����

���

��������

�����

������

�

���

����

������

����

������

����

���

���

������������

�

������

���

�

���

���

���

��

���

��

������

��

�������

������������������

��������������

������

������

����

������

�������

������

��

���������������

���

��

���������

���

������������

������������������

����

������

����

������

������

������

����������������������������

��������

��������������

��������

������

��������

�������

���������

������������������������

�����

������������������������������������

����� �
2003 Report Additional Data B-11

Exhibit B-6b: Distribution of TEDE by Facility Type - 2002

��������������������������������������

������������������������������������������������������������������������

������ ����������������������������������������������������������

�������������

���������

�����

�����

����

�����

������ ��� ��� ���

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

�����

����

�����

���� ��� ��

��������

�����

����

����������

����

������������

������������������������������������������������������������������������������������������������������������������������������������������������������������

����������������������������������������������������������������������������������������������������������������������������������������������������������

����������������������������

���������������������������������������������������������������������������������������������������������������������������������������������������������������������

����� ��� �� �� � � ������ ��� ����� ������ ���������� ��� �� � � ����� ��� ��� ������ ���������� ��� �� � ����� ��� ��� ������ ���������� ����� �� �� ����� ��� ����� ������ �����

������ ����� ��� ��� �� �� �� ������ ��� ����� ������� ����������� ����� ��� �� �� � � � ������ ��� ����� ������ �����

����� ��� �� �� � � ����� ��� ��� ������� �����

������ ����� ��� ��� �� � �� ������ �� ����� ������� �����

��� ��� �� � ��� ��� ��� ����� �����

����� ����� ��� �� � � ����� ��� ����� ������� �����

������ ����� ��� ��� ��� �� �� ������ ��� ����� ������� �����

������ ������ ����� ��� ��� �� �� � ������� ��� ������ ��������� �����
B-1

2 DOE Occupational Radiation Exposure 

Exhibit B-6c: Distribution of TEDE by Facility Type - 2003

��������������������������������������

������������������������������������������������������������������������

������ ����������������������������������������������������������

�������������

���������

�����

�����

����

�����

������ ��� ��� ���

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

�����

����

�����

���� ��� ��

��������

�����

����

����������

����

������������

����� ����� �� �� � ������ ��� ����� ������ ���������� ��� �� �� � ����� ��� ��� ������ ���������� ��� �� � ����� ��� ��� ������ ���������� ��� ��� �� � ����� ��� ����� ������ �����

������ ����� ��� ��� �� �� �� � ������ ��� ����� ������� ����������� ����� ��� �� �� �� �� � ������ ��� ����� ������� �����

����� ��� �� �� � ����� ��� ��� ������ �����

������ ����� ��� ��� �� �� �� ������ �� ����� ������� �����

��� ��� ��� ��� ��� ����� �����

����� ����� ��� ��� �� � ����� ��� ����� ������� �����

������ ����� ��� ��� �� �� �� ������ ��� ����� ������� �����

������ ������ ����� ��� ��� ��� �� � � ������� ��� ������ ��������� �����

���������������������������������������������������������������������������������������������������������������������������������������������������������������������

���������������������������������������������������������������������������������������������������������������������������������������������������������

��������������������������������������������������������������������������������������������������������������������������������������������������������

����������������������������������������������������������������������������������������������������������������������������������������������������������

��������������������������������������������������������������������������������������������������������������������������������������
2003 Report Additional Data B-13

Exhibit B-7a: Collective TEDE by Operations / Site and Facility Type - 2001

�����

������������������������

����

�����

�����

�����

��������

������

����

����

����

�����

��������

����������

��������

���

����

�����

����

����

����������

�����

���

������

������������������

��������

����

�����

����

���

����

���

�����

����

�����

���

����

������������������������������

����

����

���

����

���

�����

����

���������

����������������

������

�����

���������

����

������

�����

���������

����

���

��������

���������������

�������

��������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������

����

����������������

�����

������������

����

����

��������

����

��������

����

��������

������������ ���������� ����������� ���� ��������������� ���������� ����������� ������������ ������� ��������� ������� ��������� ������ ����������������� ���������� ������������ ������������ ����������� ����

�����������������������������������������������������������������

����������������������������������������������������������������������������������������������������

���������������������������������������������������������������������������������������������������������������������������������������

���������������������������������������������������������������������������������������������������������������������������

������������������������������������������������������������������������������������������������������������������������������������������������������������������
B-1

4 DOE Occupational Radiation Exposure 

Exhibit B-7b: Collective TEDE by Operations / Site and Facility Type - 2002

���������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������

������������ ���������� ����������� ���� ��������������� ���������� ����������� ������������ ������� ��������� ������� ��������� ������ ����������������� ���������� ������������ ������������ ����������� ����

�����������������������������������������������������������������

����������������������������������������������������������������������������������������������������

��� ��� ��� ���

���� ���� ��� ���� ��� ��� ��� ���� �����

���� ����

��� ��� ��� ��� ��� ��� ��� ���

��� ��� ��� ���

��� ��� ���� ��� ����

��� ���� ����

���� ��� ��� ��� ��� ��� ����

���� ����

������

���� ���� ���� ��� ���� ��� ����

��� ���

��� ���

��� ��� ���

���� ����

��� ������ ��� ���

���� ���� ���� �����

��� ������ ���

��� ��� ��� ���

���� ����

���� ����

��� ��� ������ ���� ����

����� �����

����� ���� ���� ���� �����

���� ���� ��� ���� ���� ���� ��� �����

���� ���� ���� ���� ����� ���� ����� ��� ����� ����� ����� �������

���������������������������������������������������������������������������������������������������������������������������������������

��������������������������������������������������������������������������������������������������������������������������������

���������������������������������������������������������������������������������������������������������������������
2003 Report Additional Data B-15

Exhibit B-7c: Collective TEDE by Operations / Site and Facility Type - 2003

��� ��� ���

���� ���� ���� ��� ���� ���� �����

���� ����

��� ��� ��� ��� ��� ��� ��� ��� ������� ��� ��� ���

���� ����

��� ���� ����

��� ��� ��� ��� ��� ��� ����

���� ����

���� ��� ���� ��� ��� ��� ����

��� ���

��� ���

��� ��� ���

���� ����

��� ������ ��� ���

���� ���� ���� �����

��� ������ ���

��� ��� ���

���� ����

���� ����

��� ��� ��� ���

���� ����

����� �����

����� ���� ���� ���� �����

���� ���� ���� ���� ���� ���� ��� �����

���� ���� ���� ���� ����� ���� ����� ��� ����� ����� ����� �������

���������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������

������������ ���������� ����������� ���� ��������������� ���������� ����������� ������������ ������� ��������� ������� ��������� ������ ����������������� ���������� ������������ ������������ ����������� ����

�����������������������������������������������������������������

����������������������������������������������������������������������������������������������������

��������������������������������������������������������������������������������������������������������������������������������������������������������

�������������������������������������������������������������������������������������������������������������������������������������������������

�������������������������������������������������������������������������������������������������������������������������������
B-1

6 DOE Occupational Radiation Exposure 

Exhibit B-8: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Accelerator Facilities, 2003

������������

������������������������������������������������������������������������

���������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�� �������������������������������� ���������������������������� ���������� ��������������������������������� ������������������������������������ ��������������������������������������� ������������������������������ ��������������������������� ������������������������ ����������������������

������

����

������

�����

����

�����

����

�����

����

�����������������������������������������������������������������

��

�

���

���

������������

���

��

������

���

����

������������������������

����

���

�����

��

�

����

��

��

��

�

��

��

�

�

���

����

������������

�����

������

����

���

��

������ � �

���

��

���

��������

���

����

���

���

���

����

��������

���

��

������

������

�����

������

�����������������������������������

������

�����

���������������������������������������������

�����

������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������
2003 Report Additional Data B-17

Exhibit B-9: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Fuel Facilities, 2003

���������������

������������������������������������������������������������������������

���������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

����

������

�����

����

�����

����

�����

���� ��

����������

�����������������������������������������������������������������

�����������

���

����

���

���

���

�

�

���

������

�����

����

�

�����

���

���

������

���

���

���

���

���

�����

�����

���

������

�����

�����

���

�����

����������

����

�

�����

������

���

��

��

�

� � � � �

�� �������������������������� ����������������������� ����������������������� �������������������������������������������� ����������������������������� ����������������������� ������������������

������

�����

������

�����

������

���������������

������ �

������

����

������������

��������

���

�����

�

��

�

��

��

���

��

�������

������������

�����

��������

���

����� � �

��

���

��

���

������

���

�� ���������������������� ������������������������������������ ������������������������������������ ������������������������������ �����������������������������

������

�����

������������������������������

�����

��

���

��

���

��

�

���

�

�

�����������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������
B-1

8 DOE Occupational Radiation Exposure 

Exhibit B-9: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Fuel Facilities, 2003 (Continued)

���������������

������������������������������������������������������������������������

���������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

����

������

�����

����

�����

����

�����

���� ��

�� ������������������������������� ��������������������������������� ��������������������������� ����������������������������������� ������������������������������� ����������������������������� ���������������������������������� ������������������������ ������������������������������

������

����

������

����

���

����

������

��

�����

���������

��

���

���

����

��

���

���

��

������

�����

������������

������

��

�����

������

���

���

��

������

����

���

����

���

����

���

�����

�����

������

������

�����������������������������������

������

�����

����������������������������������������

�����

�

�

����������

�����������������������������������������������������������������

� � �

���������������������������������������������������������������������������������������������������
2003 Report Additional Data B-19

Exhibit B-10: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Maintenance and Support, 2003

��� �� � �� �� �� � ��� ��� ��� ������ �������� ��� �� �� �� � �� ����� ��� ��� ������ �����

����� ����� ��� ��� �� �� �� ����� ��� ����� ������� ���������� ��� �� �� � � ����� ��� ��� ������ �����

�� �� �� � �� ��� �� ����� ������� �� � � �� ��� �� ����� �����

��� ��� �� � ��� ��� ��� ������ �����

����� �� � ����� �� �� ����� �����

�� �� � ��� ��� �� ����� �����

��� ��� � � � ��� ��� ��� ����� �������� �� � � ��� ��� �� ����� �����

� � � ��� � ����� �����

� � �� ��� � ����� �����

�� � �� �� � ����� �����

��� �� � ��� ��� �� ����� �������� �� � ��� �� �� ����� �������� �� ��� �� �� ����� �����

� � ���� � ����� �����

�� � �� ��� � ����� �����

��� �� � ��� �� �� ����� �����

�� �� �� ��� �� ����� �����

� � � ��� � ����� �����

��� � ��� �� � ����� �����

�� �� �� ��� �� ����� �����

������ ����������������������������������������������������������

����

����

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

����

�����

����

�����������������������

������������������������������������������������������������������������

���������������

����

������

�����

����

�����

���� �����

�� ���������������������������������������� �������������������������������� ���������������������� ������������������������ �������������������������� ��������������������������� ��������������������������������� ���������������������� ������������������������������� ������������������������������� ������������������������������� �������������������������������� �������������������������������������� ����������������������� ����������������������������������������� �������������������������������� ���������������������������� ������������������������������������ ������������������������ ���������������������������� ������������������������ ������������������������������� ������������������� ���������������������������������
B-2

0 DOE Occupational Radiation Exposure 

Exhibit B-10: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Maintenance and Support, 2003 (Continued)

������ ����������������������������������������������������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

����

�����

����

�����

����

�����

���� �����

�����������������������

������������������������������������������������������������������������

���������������

����

������

�� ������������������������������������� ������������������������������������� �������������������������������� ���������������������������������� ������������������������������������ ������������������������ �������������������������������� ����������������� ��������������������������� ����������������� �������������������������������� �������������� ��������������������������������������� ����������������������������� ������������������ ��������������������������������� ������������������������������������ ���������������������������������� �������������������� ������������������� ����������������������������� �����������������������������

������

� � � ��� � ����� �����

�� �� �� ��� �� ����� ������� � �� ��� � ����� �����

� � � ��� � ����� �����

��� �� ��� ��� �� ����� �������� �� ��� ��� �� ����� �����

�� � �� ��� � ����� ������� � �� �� � ����� ������� �� �� ����� ������� �� �� ����� ������� �� �� ����� �����

� � �� ����� �����

�� �� �� ����� ������� �� �� ����� �����

� � �� ����� �����

�� �� �� ����� �����

� � �� ����� �����

�� �� �� ����� �����

� � �� ����� ������ � �� ����� �����

�� �� �� ����� �����

��� ��� �� ����� �����

������ ����� ��� ��� �� �� �� � � � ������ ��� ����� ������� �����

���������������������������������������������������������������������������������������������������������������������������������������������������������

�����������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������
2003 Report Additional Data B-21

Exhibit B-11: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE

for Reactor Facilities, 2003

������������������

������������������������������������������������������������������������

��� ��� �� �� � ��� ��� ��� ������ �����

�� �� � � �� ��� �� ����� �����

� �� � �� ��� �� ����� �����

��� ��� �� � ��� ��� ��� ����� �����

�� �� � �� ��� �� ����� ������� � �� ��� � ����� ������� �� ��� ��� �� ����� �����

��� �� ��� ��� �� ����� �����

� � �� ����� �����

� � �� ����� �����

� � �� ����� �����

� � �� ����� �����

� � �� ����� �����

� � �� ����� �����

����� ��� �� �� � ����� ��� ��� ������ �����

������ ����������������������������������������������������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

����

�����

���� �� ���������������

����

������

�� ������������������������������� ���������������������������� ����������������������������������� ��������������������������������� �������������������������������� ����������������������������� ��������������������������� ������������������������������� ������������������������������������ ����������������� ����������������� ��������������������������� �������������������������������� ��������������������������������

������

��������������������������������������������������������������������������������������������������������������������������������������������

���������������������������������������������������������������������������������������������������������������������������������������

������������������������
B-22 DOE Occupational Radiation Exposure 

Exhibit B-12: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE for Research, General, 2003 ����������������� ������������������������������������������������������������������������ ��������������� ���� ������ ��� ����������������������������� ����� ��� �� � �� � � ����� �� ��� ������ ����� �� ������������� ��� ��� �� � � � ��� ��� ��� ������ ����� �� �������������������������������� ��� ��� �� �� � � ��� ��� ��� ������ ����� �� ������������������������������ ����� ��� �� �� � � � ����� ��� ��� ������ ����� �� �������������������������������� ����� ��� �� �� � ����� ��� ��� ������ ����� �� ����������������� ����� ��� �� �� � � ����� �� ��� ������ ����� �� ������������������������������� ��� ��� �� �� � ��� ��� ��� ������ ����� ��� ���������������������������� ��� �� � � ��� �� �� ����� ����� �� �������������������������� ��� �� � � ��� �� �� ����� ����� �� ������������������������������ ��� �� � � ��� ��� �� ����� ����� ��� �������������������� ��� � ��� �� � ����� ����� �� ��������������������������� ��� ��� � � ��� ��� ��� ����� ����� �� ������������������������������� �� �� � �� ��� �� ����� ����� ��� ����������������������������������� ��� � ��� �� � ����� ����� �� ��������������������������������� �� � �� �� � ����� ����� �� ���������������������������� ��� �� ��� ��� �� ����� ����� �� ��������������������������� �� � �� ��� � ����� ����� ��� ������������������� ��� � ��� �� � ����� ����� ��� ����������������� ��� �� � ��� ��� �� ����� ����� ������ ���������������������������������������������������������� ��������� ����� ����� ���� ����� ����� ����� ��������� ���������� ��������� ���������� ���� ���� ����� ���� ����� ����� ���� �������� ����� ���� ���������� ���� ������������ ����� ���� ����� ���� ����� ���� ����� ���� ����� ���� �����
2003 Report Additional Data B-23 Exhibit B-12: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE for Research, General, 2003 (Continued) ���� ����� ���� ��� ��� ��� ���� ��� ��� ������� ��� ������ ����� �������� ���� ��� ����� ��� �� �� � � � ���� ����� ���� ��� ��� ��� ���� ��� ��� ������� ��� ������ �� ��� ������� ������� ��� ��� ��� ��������������� ����� �������� ���� �������� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ���������� ������� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ���������� ����� �� ��� ������������������� ��� ������������������� �� ������������������������� �� ��������������������������� �� ������������������������� �� �������������������������������� �� ������������������ �� ����������������������������������� �� ���������������������������������� �� ������������������� �� ��������������������������� �� ���������������������������������������� �� ��������������� �� ������������������������ �� ���������������������� �� ���������������������� �� ������������������������������������� ����� � ��� ������ ���������������������������������������������������������� ��������� ����� ����� ���� ����� ����� ����� ��������� ���������� ��������� ���������� ���� ���� ����� ���� ����� ����� ���� �������� ����� ���� ���������� ���� ������������ ����� ���� ����� ���� ����� ���� ����� ���� ����� ���� ����� ����������������� ������������������������������������������������������������������������ ��������������� ���� ������ �������������������������������������������������������������������������������������������������������������������������������������������
B-24 DOE Occupational Radiation Exposure 

Exhibit B-13: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Research, Fusion, 2003

����������������

������������������������������������������������������������������������

���������������

����

������

������ ����������������������������������������������������������

��������

����

���

�

���

����

���

�

���

��

���

���

��

��� �

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

����

�����

���� ��

��

���

�

���

��

���

���

��������������������������������������������������������������������������������������������������������������������������

�����

����������

�

����� � � � �

����������

�����

�

����� �

���������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������
2003 Report Additional Data B-25

Exhibit B-14: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Waste Processing, 2003

����������������

������������������������������������������������������������������������

���������������

����

������

�� ���������������������� � � ���� � ����� ������� ������������������������������ �� �� � � � � �� ��� �� ������ ������� ����������������������������� ��� ��� �� �� � ����� ��� ��� ������ ������� ������������������������������� ����� ��� ��� �� �� ����� ��� ����� ������ ������� ������������������������������ �� �� � � ��� ��� �� ����� ������� �������������������������� ��� �� � ��� ��� �� ����� ������� ����������������������� ��� ��� �� �� � ��� ��� ��� ������ ������� �������������������� � � � ��� � ����� ������� ���������� ��� ��� � ��� ��� ��� ����� ������� ��������������������������� ��� �� � ��� ��� �� ����� ������� �������������������������������� �� �� � �� ��� �� ����� ������� ������������������������������ � � ���� � ����� �����

������ ����������������������������������������������������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

����

�����

���� ��
B-2

6 DOE Occupational Radiation Exposure 

Exhibit B-14: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Waste Processing, 2003 (Continued)

����������������

������������������������������������������������������������������������

���������������

����

������

������ ����������������������������������������������������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

����

�����

���� ��

�� ��������������������������� �� �� � �� ��� �� ����� �����

�� ������������������������������� ��� �� ��� ��� �� ����� �����

�� ��������������������������������� � � � ��� � ����� �����

�� �������������������������������� �� �� �� ��� �� ����� �����

�� �������������� � � �� � � ��� ��������������� � � �� � � ��� ���������������������������� � � �� � � �

�� ���������������������� � � �� � � �

�� ����������������������������� � � �� � � ��� ���������������������������� � � �� � � �

�� ������������������������������������ �� �� �� � � �

������ ����� ����� ��� ��� �� � � � ����� ��� ����� ������� �����

��������������������������������������������������������������������������������������������������������� �������������������������������������

�������������������������� ���������������������������������������������������������������������������������������������������������������������

�������������������������������������������������
2003 Report Additional Data B-27

Exhibit B-15: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Weapons Fabrication, 2003

�������������������

������������������������������������������������������������������������

���������������

����

������

������ ����������������������������������������������������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

���

����

��� ��

����

���

����

������

���

������

���

������������

������

��������

���

�

������

��

���

���

������

��������

���

����

���

����

������

���

�

���������

��

���

��

�����

���

����

������������

����

���

���

���

����

�

���

�

������

���

����

��

��

��

��

���

�����

���

�����

��

�����

�����

����

������

��������

��

��

���

������

������

���

��

������������

��

���

��

������������������

��������

���

���

�����

������

��

���

�����

��

�

������

��

��

��

�����

������

�������

������������

�����

������������

��������������������������������������������������

����

�������

�����

��������������������������������������������������������������������������������

����

�����

�� ���������������������������������� ������������������������������� ������������������������������� ����������������� ���������������������������� ���������������������������� ������������ ����������������������������������� ���������������������������������� �������������������� ���������������������������� ������������������������ ���������������������������������� ����������������������������� ����������������������������������� ������������������������� ������������������������������������ ���������������������� �������������������������������� ������������������ �����������������

������ � �

�

��

��

��

��������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������
B-28 DOE Occupational Radiation Exposure 

Exhibit B-16: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE for Other, 2003

�����

������������������������������������������������������������������������

���������������

����

������

��� ��� �� �� �� �� ��� ��� ��� ������ �����

����� ��� �� �� �� �� �� � ����� ��� ��� ������ �����

�� � � �� ��� � ����� ������� � � � �� ��� � ����� ������� � � �� �� � ����� ������� � � �� �� � ����� �����

����� �� �� � � ����� �� �� ����� �����

�� �� �� � ��� ��� �� ����� ������� �� � �� ��� �� ����� ������� �� �� ��� �� ����� �����

��� �� � ��� ��� �� ����� �����

�� �� � �� ��� �� ����� �����

� �� � �� ��� �� ����� �����

��� �� � � ��� ��� �� ����� �����

�� � �� �� � ����� �����

��� �� � ��� ��� �� ����� �����

��������������������������������

������ ����������������������������������������������������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

����

�����

����

�����

����

������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������

�����

���� ��
2003 Report Additional Data B-29

Exhibit B-16: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Other, 2003 (Continued)

�����

������������������������������������������������������������������������

���������������

����

������

��������������������������������

����������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������

��� �� ��� ��� �� ����� �����

�� � �� ��� � ����� �����

��� �� � ��� �� �� ����� �������� �� � ��� �� �� ����� �����

�� � �� ��� � ����� �����

��� �� ��� �� �� ����� �������� �� ��� ��� �� ����� �����

� � � ��� � ����� �����

�� � �� ��� � ����� �����

��� �� ��� ��� �� ����� �����

� � ���� � ����� �����

�� � �� ��� � ����� ������� � �� ��� � ����� �����

� � �� ��� � ����� �����

�� � �� �� � ����� �����

� � � ��� � ����� �����

������ ����������������������������������������������������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

����

�����

����

�����

����

�����

���� ��
B-3

0 DOE Occupational Radiation Exposure 

Exhibit B-16: Distribution of TEDE by Facility Type Listed in Descending Order of Average Measurable TEDE 

for Other, 2003 (Continued)

�����

������������������������������������������������������������������������

���������������

����

������

������ ����������������������������������������������������������

���������

�����

�����

����

�����

�����

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

����

�����

����

�����

����

�����

���� ��

��������������������������

�������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������� � ��������������������������������������������������������

� � �� � � �

�� �� �� � � �

� � �� � � �� � �� � � �

�� �� �� � � �

� � �� � � �� � �� � � �� � �� � � �� � �� � � �� � �� � � �� � �� � � �

�� �� �� � � �

������ ����� ��� �� �� �� �� � � � ������ ��� ����� ������� �����

����������������������������������������������������������������������������������������������������������������������
2003 Report Additional Data B-31

Exhibit B-17: Internal Dose by Facility Type and Nuclide, 2001-2003

����������� ��������� � ����� �����

���������� � � � ����� ����� ����� ����� ����� �����

��������� � ����� �����

������� � � � ����� ����� ����� ����� ���� �����

����� � � � ����� ����� ����� ����� ����� �����

���������������� ������� �� �� �� ����� ����� ����� ����� ����� �����

������� �� � �� ����� ����� ����� ����� ����� �����

����� �� �� �� ����� ����� ����� ����� ����� �����

��������������� ��������� � � ����� ����� ����� �����

���������� �� �� ��� ����� ����� ����� ����� ����� �����

��������� � � � ����� ����� ����� ����� ����� �����

����� �� �� ��� ����� ����� ����� ����� ����� �����

����������������������� ��������� � � ����� ����� ����� �����

����� � � � ����� ����� ����� ����� ����� �����

������� � � � ����� ����� ����� ����� ����� �����

��������� � � ����� ����� ����� �����

������� ��� ��� ��� ����� ����� ����� ����� ����� �����

����� ��� ��� ��� ����� ����� ����� ����� ����� �����

����������������������� ��������� � �� �� ����� ����� ����� ����� ����� �����

���������� �� �� �� ����� ����� ����� ����� ����� �����

��������������� �� � ����� ����� ����� �����

��������� �� ��� ��� ����� ����� ����� ����� ����� �����

��������� � ����� �����

������� � �� �� ����� ����� ����� ����� ����� �����

������� �� �� �� ����� ����� ����� ����� ����� �����

����� ��� ��� ��� ����� ����� ����� ����� ����� �����

����� ��������� � �� � ����� ����� ����� ����� ����� �����

���������� �� �� �� ����� ����� ����� ����� ����� �����

��������������� � � ����� ����� ����� �����

��������� � �� �� ����� ����� ����� ����� ����� �����

��������� � �� �� ����� ����� ����� ����� ����� �����

������� �� �� �� ����� ����� ����� ����� ����� �����

����� �� ��� ��� ����� ����� ����� ����� ����� �����

������� ���������� �� �� �� ����� ����� ����� ����� ����� �����

��������� � ����� �����

����� �� �� �� ����� ����� ����� ����� ����� �����

���������������� ���������� �� �� � ����� ����� ����� ����� ����� �����

����� �� �� � ����� ����� ����� ����� ����� �����

����������������� ��������� � � �� ����� ����� ����� ����� ����� �����

���������� �� �� �� ����� ����� ����� ����� ����� �����

��������������� �� � � ����� ����� ����� ����� ����� �����

��������� �� �� �� ����� ����� ����� ����� �����

������� �� �� �� ����� ����� ����� ����� ����� �����

����� ��� �� ��� ����� ����� ����� ����� ����� �����

���������������� ��������� �� �� � ����� ����� ����� ����� ����� �����

���������� � � ����� ����� ����� �����

��������������� � � ����� ����� ����� �����

��������� �� � � ����� ����� ����� ����� ����� �����

������� � ����� �����

������� � � ����� ����� ����� �����

����� �� �� �� ����� ����� ����� ����� ����� �����

������������������������ ��������� � � �� ����� ����� ����� ����� ����� �����

���������� �� �� �� ����� ����� ����� ����� ����� �����

��������������� � � � ����� ����� ����� ����� ����� �����

��������� � ��� ��� ����� ����� ����� ����� ����� �����

������� �� �� �� ����� ����� ����� ����� ����� �����

������� ����� ����� ����� ������ ������ ������ ����� ����� �����

����� ����� ����� ����� ������ ������ ������ ����� ����� �����

������ ����� ����� ����� ������ ������ ������ ����� ����� �����

� �������������������������������������������������������������������������������������������

��� ����������������������������������������������������������������������������� �� ������������������������������������������ �����������������������������������������������������������������

�������������

������������������

������������������

���������������

������������ ������������������

�������� ���� ���� ���� ���� ���� ���� ���� ���� ����

���������������������������������������������������������������������������������������������������������������������������������

����������������������������������������������������������������������������������������������������������������������������������

��������������������������������������
B-32 DOE Occupational Radiation Exposure 

Exhibit B-18a: Distribution of TEDE by Labor Category - 2001 �������������������������������������� ������������������������������������������������������������������������ �������������� ����������� ������������ �������� ���������� ������������� ���������� ���������� ������� ����������� ��������� ������� ������ ������ ���������������������������������������������������������� ��������� ����� ����� ���� ����� ������ ����� ��������� ���������� ��������� ���������� ���� ���� ����� ���� ����� ����� ���� �������� ����� ���� ���������� ���� ������������ ����� ���� ����� ���� ��� ��� ��� �� �� ��� ������ ���� ������ ������ ������ ������� ������ ������ ���� ������� ������ �� ��� ��� ��� ��� ��� ��� ��� ��� ����� ��� ������ ���� ������ ������ ������ ������ ���� ������ ���� ������ ������ ���� ��� ���� ���� ���� ���� ��� ����� ���� ������ ��� ��� ��� ��� ���� ��� ��� ����� ���� ���� ���� ��� ��� ��� ���� ���� ��� ���� � ��� ����� ���� ��� ��� ���� ���� ��� �� ��� ������ ������ ������ ������ ������ ������� ������ ������� ������ ������� ������� � ����� ��� ����� ����� ����� ����� ��� ����� ��� ����� ������ � ������ ������ ������ ������� ������� ������� ������ ������� ����� ������� ��������� � ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� ����� � � � ����������������������������������������������������������������������������������������������������������������������������������� �������������������������������������������
2003 Report Additional Data B-33 Exhibit B-18b: Distribution of TEDE by Labor Category - 2002 �������������������������������������� ������������������������������������������������������������������������ �������������� ����������� ������������ �������� ���������� ������������� ���������� ���������� ������� ����������� ��������� ������� ������ ������ ���������������������������������������������������������� ��������� ����� ����� ���� ����� ������ ����� ��������� ���������� ��������� ���������� ���� ���� ����� ���� ����� ����� ���� �������� ����� ���� ���������� ���� ������������ ����� ���� ����� ���� ��� ��� ��� �� �� �� � �� �� � ����� ����� ����� ����� ��� �� �� � � ����� ��� ����� ������� ����� ����� ��� �� �� � ����� ��� ��� ������ ����� ����� ����� ��� �� � � ����� ��� ����� ������ ����� ����� ����� ��� ��� �� � � ����� ��� ����� ������� ����� ����� ����� ��� ��� �� �� �� ����� ��� ����� ������� ����� ������ ����� ��� �� �� � � ������ ��� ����� ������� ����� ����� ��� ��� �� � ����� ��� ��� ������ ����� ����� ����� ��� ��� �� �� �� ������ ��� ����� ������� ����� ����� ��� �� � ����� ��� ��� ������ ����� ������ ����� ��� ��� �� �� �� � ������ �� ����� ������� ����� ������ ������ ����� ��� ��� �� �� � � � � ������� ��� ������ ��������� ����� ������������������������������������������������������������������������������������������������������������������������������������ �����������������������������������������������
B-34 DOE Occupational Radiation Exposure 

Exhibit B-18c: Distribution of TEDE by Labor Category - 2003

��������������������������������������

������������������������������������������������������������������������

��������������

������������������������������������������������������������������������������������������������������������������

������ ����������������������������������������������������������

�� �� �� � � �

����� ����� ��� �� �� � ����� ��� ����� ������ ���������� ��� �� �� � ����� ��� ��� ������ ���������� ����� ��� �� �� � � ������ ��� ����� ������� ���������� ��� ��� �� �� � � ����� ��� ����� ������� ���������� ����� ��� ��� �� �� �� ����� ��� ����� ������� �����

������ ����� ��� �� �� � ������ ��� ����� ������� �����

����� ��� ��� �� � � ����� ��� ��� ������ ���������� ����� ��� ��� �� �� �� ������ ��� ����� ������� ���������� ��� �� � ����� ��� ��� ����� �����

������ ����� ��� ��� �� �� �� � � ������ �� ����� ������� �����

������ ������ ����� ��� ��� ��� �� � � � � ������� ��� ������ ��������� �����

���������

�����

�����

����

�����

������

�����

���������

����������

���������

����������

����

����

�����

����

�����

�����

����

��������

�����

����

����������

����

������������

�����

����

�����

���� ��� ��� ��� �� ��

������������������������������������������������������������������������������������������������������������������������������������������������������������������������������
2003 Report Additional Data B-35

Exhibit B-19: Internal Dose by Labor Category, 2001-2003

��������������

���������������������

�����������������

���������������

������������ ������������������

�������������������������������������������������������������������������������������������������������������

���� ���� ����

�����������������������������������������������������������������

���� ���� ���� ���� ���� ����

�������������������������������������������������������������������������������������������������������

���

��

���

��

���

���

��

���

�

���

�����

��������������������

������

�������������������������

������

�����

�����

����������������������������������������

�����

��������������������

������

�������������������������

������

�����

�����

����������������������������������������

�����

���

��

���

��

���

���

��

���

�

���

�����

��������������������

������

��������������������

������������

�����

�����

����������������������������������������

�����

���

��

������������

��

���

�

���

�����

����������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������

�������������������������������������������������������������������������������������������������������������������������������������������������

���������������
B-3

6 DOE Occupational Radiation Exposure 

Exhibit B-20: Dose Distribution by Labor Category and Occupation - 2003

����������� �������������� �� �� ��

����������������� �� �� ��

������������ ���������� ��� ��� � � ��� ��� ��� ����� �����

������������ ����� ��� �� � � � ����� ��� ��� ������ �����

������ �� � �� ��� � ����� �����

������������������� ��� ��� �� �� � ��� ��� ��� ������ �����

��������������� �� �� �� ��� �� ����� �����

������������������������� ����� ��� �� �� � ����� ��� ��� ������ �����

�������� ��� �� � � ��� ��� �� ����� �����

����������� ��� ��� �� �� � ��� ��� ��� ������ �����

�������� ������������������������� ����� ��� �� �� � ����� ��� ��� ������ ��������������� ���������������������������� ����� ��� ��� �� � ����� ��� ��� ������ �����

����������������������� ����� ����� ��� �� � � � ����� ��� ����� ������ �����

����� � � ��

����� �������� � � ��

������������� ����� ��� ��� �� �� � � ����� ��� ����� ������� �����

���������� ����������������������� ��� ��� �� � ��� ��� ��� ������ �����

���������� ��� �� � � � � ��� ��� �� ����� �����

�������������������������� ��� ��� �� �� �� �� � ����� ��� ��� ������ �����

����������������������������� ����� ����� ��� ��� �� �� �� ����� ��� ����� ������� �����

������������������� ��� �� � � ��� ��� �� ����� �������������������������� �� �� � � ��� ��� �� ����� �����

���������� ������������������ ��� � � ��� �� � ����� �����

�������� ����� ����� �� �� � � ����� ��� ����� ������ �����

���������������� ��� ��� �� � � ��� ��� ��� ����� �����

������������������ ����� ��� �� �� � � ����� ��� ��� ������ �������������� ����� ��� �� �� � ����� �� ��� ������ �����

������� ������������ ��� �� � ��� ��� �� ����� �����

���������������������� �� � �� ��� � ����� �����

�������� ��� �� �� � � ��� �� �� ����� �����

������������� ��� ��� �� � � ����� ��� ��� ������ �����

��������������� ����� ��� �� � � ����� ��� ��� ������ �����

����������� ����������������������� ����� ��� �� � � � � ����� ��� ��� ������ �����

������������������ ��� �� �� � � ��� ��� �� ����� �����

����������������� ����� ��� �� �� �� � � ����� ��� ��� ������ �����

������������������������� ����� ��� ��� ��� �� � � ����� ��� ����� ������� �����

������������������� ��� ��� �� � � � � ��� ��� ��� ������ ���������������� ��� ��� �� �� � � ����� ��� ��� ������ �����

��������� ����������� �� � �� ��� � ����� �����

������������������� ��� ��� �� � ��� ��� ��� ����� �����

��������������� ��� �� � ��� ��� �� ����� �����

������ � � ��

������������� ��� �� ��� ��� �� ����� �����

������� ������� ������ ����� ��� ��� �� �� �� � � ������ �� ����� ������� �����

������ ������ ������ ����� ��� ��� ��� �� � � � � ������� ��� ������ ��������� �����

�����

��������

�������

�����

����

����������

����

�����

���������� ����������

�����������������������������������������������������������������

����

����

�����

�����

�����

�����

����

�����

����

�����

����

�����

��� ��� ��� ��� ��

�������

����

�����

���

����

����� ���

���������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������

���������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������
2003 Report Additional Data B-37

Exhibit B-21: Internal Dose Distribution by Site and Nuclide - 2003

�����������

������������

���������������������

����������������������������������

���� ������� �����

����

�����

����

�����

����

�����

����

����

��� ����

�����

����

�����

�����

����������� ������������������������������ ��������� � � ����� �����

���������� �� � �� ����� �����

����� � � ����� �����

��������� �� �� � � � �� ������ �����

������� �� � �� ����� �����

������������ ������� �� � �� ����� �����

������� � � �� ����� �����

�������������������������� ��������� � � ����� �����

������� � � ����� �����

������� �������������������������������� ��������� �� � �� ����� �����

���������� � � ����� �����

��������� � �� � � �� ����� �����

������������������������������ ���������� � � ����� �����

����� � � ����� �����

����� ���������� ��������� � � ����� �����

��������� � � � ����� �����

��������� �� � � �� ����� �����

������� ������������������������������������� ���������� � � ����� �����

��������� �������������� ��������� � � � � ����� �����

���������� � � ����� �����

��������� � � � � � ����� �����

������� � � ����� �����

������� ��� ��� ��� �� ����� ������ �����

������� ��������� � � ����� �����

����� � � ����� �����

������� � � ����� �����

���� ������������������������� ���������� � � ����� �����

������� � � � ����� �����

�������������������������������� ��������� � � ����� �����

��������� �� �� ����� �����

������������������������������ ������� �� �� ����� �����

������� �� � �� ����� �����

����������� ��������� �� � �� ����� �����

���������� �� � �� ����� �����

����� � � ����� �����

��������� ��� �� � ��� ����� �����

������� � � �� ����� �����

������� � � ����� �����

���������������������������������� ��������� � � � ����� �����

������ ��������� � � � ����� �����

����������� ����������������������������������� ��������� �� �� �� � ��� ����� �����

�������� ������������ ��������� � � � � ����� �����

����� � � �� ����� �����

��������� �� � �� ����� �����

�������� ������������������������� ���������� ��� � ��� ����� �����

����� ����� � � ����� �����

��������� � � � ����� �����

������ ����� ��� ��� �� � � � � � � � ����� ������ �����

�������

����

�����

����������

����

������������

�����

�����������

����������

���� ����

���

����

���

����

���

�����������������������������������������������������������������

�������������������������������������������������������������������������������������������������������������

����������������������������������������������������������������������������������������������������������������

��������������������������������������������������������������������������������������������������������������

������������������������������������������������������������������������������������������������������������

����������������������������������������������������������������������������������
B-38 DOE Occupational Radiation Exposure Exhibit B-22: Extremity Dose Distribution by Operations/Site - 2003 ��� ��� � ��� ��� ����� ����� ����� ��� ��� ��� �� � � ������ ��� �� ������� ����� ����� �� �� �� � ����� ��� � ������� ����� ����� �� �� � ����� �� ������ ����� ��� �� � ��� �� ����� ����� ����� �� �� � ����� ��� ������ ����� ��� ��� �� �� � ��� ��� � ������ ����� ����� ��� �� � � � ����� ��� � ������ ����� ����� � � ����� � ����� ����� ����� ��� ��� � ����� ����� ������ ����� ����� �� � ����� �� ����� ����� ��� ��� ����� �� � � � ����� �� � ������ ����� ����� �� �� �� � � ����� �� � ������ ����� ����� ����� ��� ��� ��� �� �� �� ��� ��� ������ ����� ����� � � ����� � ����� ����� ��� ��� ��� ��� �� � ��� ��� ������ ����� ����� ����� ������ �� ��� �� ������ ��� ������� ����� ����� � ����� � ����� ����� ��� ��� ����� ����� ��� ��� �� ����� ����� �� ������� ����� ����� ���� ��� ��� �� �� �� ������ ����� �� ��������� ����� ����� ���� ��� ��� �� � ����� ����� �� ������� ����� ������ ����� ����� ��� ��� �� �� � ������� ������ ��� ��������� ����� ���������� ������� ����� ��������� ���������� ����� ���������� ���� ��������������������������������������������������������������������������������������������������������������������������������� �� ����� ���� ����� ���� ����� ��� �� �� �� � �� �������� ����� � ��������� ���������� ���������� ������� ���������� ��������� ���� ������������ ����������� ������� ������ ����� ������ ������� ���� ��������� ����������� �������� �������������� ����������� ������������������������������� ����������������� �������������������������� ������������������ ���������������������������������� ���������������������������������� ������������������������������ ������������������������������������� ���������������� ���������� ���������������������� ������������������ �������������������������������������� ������������������������������������� ����������������������������������������� ����������������� �������������������������������������� ����������������������������������� ����������� ����������� �������������������� �������������� ���������������������������������� �������������������������������������� ����������������������������������� ������������ ������������������������� ������ � �� � �� ��� �� ��������������������������������������������������������������������������������������������������������������������������������� ����������������������������������������������������������������������������������������������������������������������������������������� �� ����������������������������������������������������������������� �������������������������������������������������������������������������������������������������������������������������������������������������������� ������������������������������������������������������������������������������������������������������������������������������������������������������������������ ��������������������������������������������������������������������������������������������������������������������������������������
2003 Report Facility Type Code Descriptions C-1

Appendix C Facility Type Code Descriptions C

DOE M 231.1-1 [13] requires contractors to 

Facility Type Code Descriptions

indicate for each reported individual the facility 

contributing the predominant portion of that 

individual’s effective dose equivalent. In cases 

when this cannot be distinguished, the facility 

type indicated should represent the facility type 

wherein the greatest portion of work service was 

performed.

The facility type indicated must be one of 11 

general facility categories shown in Exhibit C-1.

Because it is not always a straightforward 

procedure to determine the appropriate facility 

type for each individual, the assignment of 

an individual to a particular facility type is a 

judgment by each contractor.

The facility descriptions that follow indicate the 

types of facilities included in each category. Also 

included are the types of work performed at the 

facilities and the sources of the majority of the 

radiation exposures.

Exhibit C-1:

Facility Type Codes.

Accelerator

The DOE administers approximately a dozen 

laboratories that perform significant acceleratorbased research. The accelerators range in size 

from small single-room electrostatic devices to 

a 4-mile circumference synchrotron, and their 

energies range from keV to TeV.

In general, radiation doses received by 

occupational workers at accelerator facilities 

are largely attributable to the beta/gamma 

radiation emitted from the activated structural 

and mechanical components. The nature 

of the radiation fields and the magnitude of 

dose rates inside the primary shielding vary 

considerably depending upon the operational 

parameters of the machine, the types of particles 

accelerated, and the energies achieved. Doses 

received by personnel who enter the accelerator 

enclosures are dependent upon these factors. In 

many cases dependent upon the radiological 

conditions, personnel are prevented from 

entering the accelerator enclosures when the 

beam is operational. Outside of the shielding, 

exposure rates due to prompt radiation from 

the accelerator are typically very low. Average 

annual doses of exposed personnel at these 

facilities are comparable to the overall average for 

DOE. However, the collective dose is lower than 

the collective dose for most other DOE facilities’ 

categories because of the relatively small number 

of employees at accelerator facilities who work on 

or around the activated components. Regarding 

internal exposures, tritium and short-lived airborne 

activation products exist at some accelerator 

facilities, although annual internal doses are 

generally quite low.

�������������

���� �����������

��

��

��

��

��

��

��

��

��

��

��

�����������

�����������������������

����������������

���������������

�����������������������

��������������������

�������

�����������������

����������������

����������������������

������������������������

�����
C-2 DOE Occupational Radiation Exposure 

Fuel/Uranium Enrichment

The DOE involvement in the nuclear fuel cycle 

generally begins with uranium enrichment 

operations and facilities. The current method 

of enrichment is isotopic separation using 

the gaseous diffusion process, which involves 

diffusing uranium through a porous membrane 

and using the different atomic weights of the 

uranium isotopes to achieve separation.

Although current facility designs and physical 

controls result in low doses from internally 

deposited uranium, the primary radiological 

hazard is the potential for inhalation of airborne 

uranium and transuranics from recycled uranium. 

Because of the low specific activity of uranium, 

external dose rates are usually a few millirem per 

hour or less. Most of the external doses that are 

received are attributable to gamma exposures, 

although neutron exposures can occur, especially 

when work is performed near highly enriched 

uranium.

Fuel Fabrication

Activities at fuel fabrication facilities involve the 

physical conversion of uranium compounds to 

usable forms, usually rod-shaped metal. Radiation 

exposures to personnel at these facilities are 

attributable almost entirely to gamma and beta 

radiation. However, beta radiation is considered 

the primary external radiation hazard because 

of high beta dose rates (up to several hundred 

mrad per hour) at the surface of uranium rods. 

For example, physical modification of uranium 

metal by various metalworking operations, such 

as machining and lathing operations, requires 

protection against beta radiation exposures to the 

skin, eyes, and extremities.

Fuel Processing

The DOE administers several facilities that 

reprocess spent reactor fuel. These facilities 

separate the plutonium produced in reactors. They 

also separate the fission products and uranium; the 

fission products are normally designated as 

radioactive waste products, while the uranium can 

be refabricated for further use as fuel.

Penetrating doses are attributable primarily 

to gamma photons, although some neutron 

exposures do occur. Skin and extremity doses can 

result from handling samples. Strict controls are 

in place at fuel reprocessing facilities to prevent 

internal depositions; however, several measurable 

intakes typically occur per year. Plutonium 

isotopes represent the majority of the internal 

depositions.

Maintenance and Support

Most DOE sites have facilities dedicated to 

maintaining and supporting the site. In addition, 

some employees may be classified under this 

facility type if their main function is to provide site 

maintenance and support, even though they may 

not be located at a single facility dedicated to that 

purpose.

The sources of ionizing radiation exposure are 

primarily gamma photons. However, variations in 

the types of work performed and work locations 

result in exposures of all types, including 

exposures to beta particles, x-rays, neutrons, and 

airborne radioactivity.
2003 Report Facility Type Code Descriptions C-3

Reactor

The DOE and its predecessors have built and 

operated dozens of nuclear reactors since 

the mid-1940s. These facilities have included 

plutonium and tritium production reactors; 

prototype reactors for energy production; research 

reactors; reactors designed for special purposes, 

such as production of medical radioisotopes; and 

reactors designed for the propulsion of naval 

vessels.

By 1992, many of the DOE reactors were not 

operating. As a result, personnel exposures at 

DOE reactor facilities were attributable primarily 

to gamma photons and beta particles from 

contaminated equipment and plant areas, spent 

reactor fuel, activated reactor components, and 

other areas containing fission or activation 

products encountered during plant maintenance 

and decommissioning operations. Neutron 

exposures do occur at operating reactors, although 

the resulting doses are a very small fraction of the 

collective penetrating doses. Gamma dose rates in 

some plant areas can be very high (up to several 

rems per hour), requiring extensive protective 

measures.

Research, General

The DOE contractors perform research at many 

DOE facilities, including all of the national 

laboratories. Research is performed in general 

areas, including biology, biochemistry, health 

physics, materials science, environmental science, 

epidemiology, and many others. Research is 

also performed in more specific areas, such as 

global warming, hazardous waste disposal, energy 

conservation, and energy production.

The spectrum of research involving ionizing 

radiation or radioactive materials being performed 

at DOE facilities results in a wide variety of 

radiological conditions. Depending on the 

research performed, personnel may be exposed to 

virtually any type of external radiation, including 

beta particles, gamma photons, x-rays, and 

neutrons. In addition, there is the potential for 

inhalation of radioactive material. Area dose rates 

and individual annual doses are highly variable.

Research, Fusion

DOE currently operates both major and small 

facilities that participate in research on fusion 

energy. In general, both penetrating and shallow 

radiation doses are minimal at these facilities 

because the dose rates near the equipment are 

both low and intermittent. The external doses that 

do occur are attributable primarily to x-rays from 

energized equipment.
C-4 DOE Occupational Radiation Exposure

Waste Processing/Management

Most DOE sites have facilities dedicated to the 

processing and disposal of radioactive waste. 

In general, the dose rates to employees when 

handling waste are very low because of the low 

specific activities or the effectiveness of shielding 

materials. As a result, very few employees at these 

facilities receive annual doses greater than

0.1 rem (1 mSv). At two DOE sites, however, largescale waste processing facilities exist to properly 

dispose of radioactive waste products generated 

during the nuclear fuel cycle. At these facilities, 

radiation doses to some employees can be 

elevated, sometimes exceeding 1 rem/year

(10 mSv/year). Penetrating doses at waste 

processing facilities are attributable primarily to 

gamma photons; however, neutron exposures also 

occur at the large-scale facilities.

Weapons Fabrication and Testing

The primary function of a facility in this category 

is to fabricate weapons-grade material for the 

production or testing of nuclear weapons. At these 

facilities, workers can receive neutron radiation 

dose when processing plutonium isotopes, as well 

as penetrating dose from gamma photons and 

plutonium x-rays, and skin and extremity dose 

from plutonium x-rays. An additional pathway 

for radiation exposure at these facilities is the 

inhalation of plutonium, where the inhalation 

of material can result in some of the highest 

individual doses based on the calculation of 

the 50-year committed effective dose equivalent. 

To prevent plutonium intakes, strict controls 

are in place, including process containment, 

contamination control procedures, and air 

monitoring and bioassay programs.

No DOE facilities currently are involved in 

weapons testing. Several of the sites reporting 

under this category are no longer actively involved 

in weapons fabrication and testing, but are in the 

process of stabilization and waste management.

Other

Individuals included in this facility type can be 

generally classified under three categories:

(1) those who worked in a facility that did not 

match one of the ten facility types described 

above; (2) those who did not work for any 

appreciable time at any specific facility, such as 

transient workers; or (3) those for whom facility 

type was not indicated on the report forms. 

Examples of a facility type not included in the 

ten types described above include construction 

and irradiation facilities. Although exposures 

to gamma photons are predominant, some 

individuals may be exposed to beta particles,

x-rays, neutrons, or airborne radioactive material.
2003 Report Limitations of Data D-1

Appendix D DLimitations of Data

Limitations of Data

The following is a description of the limitations of 

the data currently available in the DOE Radiation 

Exposure Monitoring System (REMS). While these 

limitations have been taken into consideration 

in the analysis presented in this report, readers 

should be alert to these limitations and consider 

their implications when drawing conclusions from 

these data.

Individual Dose Records vs 

Dose Distribution

Prior to 1987, exposure data were reported 

from each facility in terms of a statistical dose 

distribution wherein the number of individuals 

receiving a dose within specific dose ranges was 

reported. The collective dose was then calculated 

from the distribution by multiplying the number 

of individuals in each dose range by the midpoint 

value of the dose range. Starting in 1987, reports of 

individual exposures were collected that recorded 

the specific dose for each monitored individual. 

The collective dose can be accurately determined 

by summing the total dose for each individual. 

The dose distribution reporting method prior to 

1987 resulted in up to a 20% overestimation of 

collective dose. The reason is that the distribution 

of doses within a range is usually skewed toward 

the lower end of the range. If the midpoint of the 

range is multiplied by the number of people in 

the range, the product overestimates the collective 

dose. This overestimation only affects the data 

prior to 1987 presented in Appendix Exhibits B-2a,

B-2b, and B-3.

The dose distributions presented in this report are 

based on the individual dose records reported 

to REMS. Individuals may be counted more than 

once as some sites report multiple dose records 

for an individual who visits the site more than 

once, or the individual may visit more than one 

site during the year. (See Section 3.6.)

Monitoring Practices

Radiation monitoring practices vary from site 

to site and are based on the radiation hazards 

and work practices at each site. Sites use 

different dosimeters and have different policies 

to determine which workers are monitored. All 

sites have achieved compliance with the DOE 

Laboratory Accreditation Program (DOELAP), 

which standardizes the quality of dosimetry 

measurements. The number of monitored 

individuals can significantly impact the site’s 

collective dose. Some sites supply dosimeters to 

virtually all workers. While this tends to increase 

the number of monitored workers with no dose, it 

also can add an increased number of very low 

dose workers to the total number of workers 

with measurable dose, thereby lowering the site’s 

average measurable dose. Even at low doses, these 

workers increase the site’s collective dose. In 

contrast, other sites only monitor workers who 

exceed the monitoring requirement threshold 

(as specified in 10 CFR 835.402). This tends to 

reduce the number of monitored workers and 

reports only those workers receiving doses above 

the monitoring threshold. This can decrease the 

site’s collective dose while increasing the average 

measurable dose.

AEDE vs CEDE

Prior to 1989, intakes of radionuclides into the 

body were not reported as dose, but as body 

burden in units of activity of systemic burden. 

The implementation of DOE Order 5480.11 in 

1989 specified that the intakes of radionuclides 

be converted to internal dose and reported using 

the Annual Effective Dose Equivalent (AEDE) 

methodology. The AEDE methodology requires the 

calculation of the summation of dose for all tissues 

and organs multiplied by the appropriate weighting 

factor for a specified year. Note that per 5480.11, 

AEDE included components of internal and 

external dose. Therefore, the AEDE was analogous 

to the TEDE. However, 5480.11 does not define 

TEDE.
D-2 DOE Occupational Radiation Exposure 

With the implementation of the RadCon Manual in 

1993, the required methodology used to calculate 

and report internal dose was changed from the 

AEDE to the 50-year CEDE. The CEDE represents 

the dose equivalent delivered to all organs and 

tissues over the next 50 years and the 50-year 

CEDE is reported to REMS and assigned to the 

individual in the year of intake. The change was 

made to provide consistency with scientific 

recommendations, facilitate the transfer of workers 

between DOE- and NRC-regulated facilities, and 

simplify recordkeeping by recording all dose in 

the year of intake. The CEDE methodology is now 

codified in 10 CFR 835. From 1993 to the present, 

the TEDE is defined as the summation of the Deep 

Dose Equivalent (DDE) to the whole body and the 

CEDE.

This report primarily analyzes dose information for 

the past 5 years, from 1999 to 2003. During these 

years, the CEDE methodology was used to calculate internal dose; therefore, the change in methodology from AEDE to CEDE between 1992 and 

1993 does not affect the analysis contained in this 

report. Readers should keep in mind the change 

in methodology if analyzing TEDE data prior to 

1993 in Exhibits B-2a, B-2b, and B-3.

Occupation Codes

Each individual’s dose record includes the 

occupation code for the individual while he 

worked at the DOE site during the monitoring 

year. Occupational codes typically represent 

the occupation the individual held at the end 

of the calendar year and may not represent 

the occupation where the majority of dose 

was received if the individual held multiple 

occupations during the year. The occupation 

codes are very broad categorizations and are 

grouped into nine general categories. Each year a 

percentage (over 30%) of the occupations is listed 

as unknown, or as miscellaneous. The definitions 

of each of the labor categories are subject to 

interpretation by the reporting organization and/or 

the individual’s employer.

Facility Type

The facility type is also recorded with each dose 

record for the monitoring year. It is intended to 

reflect the type of facility where the individual 

received most of their occupational radiation 

exposure during the monitoring year. While the 

facility types are clearly defined (see Appendices 

A and C), the reporting organizations often have 

difficulty tracking which facility type contributed 

to the majority of the individual’s exposure. 

Certain individuals tend to work in the proximity 

of several different facility types throughout the 

monitoring year and are often included in the 

“Maintenance and Support (Site-wide)” facility 

type. The facility type for temporary contract 

workers and members of the public is often not 

reported and is defaulted to “unknown.” 

In addition to these uncertainties, the phase of 

operation of the facility types is not currently 

reported. A facility type of “accelerator” may 

be reported when, in fact, the accelerator has 

not been in operation for a considerable time 

and may be in the process of stabilization, 

decommissioning, or decontamination. In 

addition, several sites have commented that they 

have difficulty assigning the facility type, because 

many of the facilities are no longer operational. 

For example, some sites commented that a 

reactor that is being decommissioned is no longer 

considered a “reactor” facility type. Other sites 

continue to categorize a facility based on the 

original intent or design of the facility, regardless 

of its current status. 

DOE Headquarters will be reviewing the Facility 

Type codification scheme and modifying the 

reporting requirements to standardize the use of 

facility type classifications and improve the quality 

of the data and the data analysis. DOE will also 

pursue the usefulness of collecting data on the 

operational phase of facilities with end-users of 

this report.
2003 Report Limitations of Data D-3

Organization Code

Facilities report data to the central repository 

based on an “organization code.” This code 

identifies the Operations or Field Office, the 

reporting facility, and the contractor or 

subcontractor that is reporting the exposure 

information. The organization code changes 

over time as DOE Offices are reorganized. In 

some cases, new Operations or Field Offices are 

created. In other cases, a Field Office may change 

organizations and begin reporting with another 

Field Office.

Occurrence Reports

Occurrence reports involving radiation exposure 

and personnel contamination events are 

additional indicators of the effectiveness of 

radiation protection efforts at DOE. These events 

will continue to be analyzed and presented in this 

report.

Additional Data Requirements

To provide analysis of the activities at DOE sites 

with respect to radiation exposure (see Section 

3.5), it is necessary to augment the information 

reported to the REMS database. For the past

5 years, DOE Headquarters has requested 

additional information from the six sites with the 

highest collective dose. This information includes 

a summary of activities, project descriptions, and 

ALARA planning documentation. DOE 

Headquarters will continue to request 

this information in subsequent years. It is 

recommended that sites submit this information 

with their annual records.

Naval Reactor Facilities

The exposure information for the Schenectady 

and Pittsburgh Naval Reactor facilities is not 

included in this report. Readers should note that 

the dose information for the overall DOE complex 

presented in this report may differ from other 

reports or sources of information because of the 

exclusion of these data. 

Exposure information for Naval Reactor programs 

can be found in the most recent version of the 

following series of reports (where XX represents 

the report year):

 NT-XX-2 – “Occupational Radiation Exposure 

from U.S. Naval Nuclear Plants and Their 

Support Facilities,”

 NT-XX-3 – “Occupational Radiation Exposure 

from U.S. Naval Reactors’ Department of Energy 

Facilities.” 

Updates to the Data

The data in the REMS database are subject to 

correction and update on a continual basis. Data 

for prior years are subject to correction as well 

as the data for the most recent year included 

in this report. The most common reason for 

correction to a dose record is because of a final 

dose determination of an internal dose after the 

original dose record was submitted to REMS. This 

delay is due to the time needed to assess the 

bioassay results and determine the dose from 

long-lived radionuclides. It is recommended 

that sites review their dose record update and 

reporting process, specifically for internal dose 

determination, and consider the addition of a 

mechanism whereby they report dose updates 

to REMS in a timely fashion when updates occur. 

Corrections will be reflected in subsequent annual 

reports. For the most up-to-date status of radiation 

exposure information, contact:

Ms. Nirmala Rao

REMS Project Manager

U.S. Department of Energy

Office of Corporate Performance Assessment

(EH-32)

Germantown, MD 20874

nimi.rao@hq.doe.gov
D-4 DOE Occupational Radiation Exposure This page intentionally left blank.
2003 Report Access to Radiation Exposure Information E-1

Appendix E EAccess to Radiation Exposure Information

Access to Radiation Exposure Information

Radiation Exposure 

Monitoring System 

The data used to compile this report were obtained 

from the DOE Radiation Exposure Monitoring System 

(REMS), which serves as the central repository 

of radiation exposure information for DOE 

Headquarters. The database consists of individual 

monitoring records of occupational exposure for 

DOE workers from 1987 to the present. REMS also 

contains career exposure records for individuals 

who terminated employment between 1969 

and 1986, and additional historical records 

voluntarily submitted to REMS from the sites that 

participated in the epidemiologic surveillance 

pilot project. Over 3 million exposure records 

are contained in the REMS central repository. In 

1995, REMS underwent an extensive redesign 

effort in combination with the efforts involved in 

revising the annual report. One of the main goals 

of the redesign effort was to allow researchers 

better access to the REMS data. However, there 

is considerable diversity in the goals and needs 

of these researchers. For this reason, a multifaceted approach has been developed to allow 

researchers flexibility in accessing the REMS data.

Exhibit E-1 lists the various ways of accessing the 

DOE radiation exposure information contained 

in REMS. A description is given for each access 

method, as well as requirements for access. To 

obtain further information, a contact name and 

phone number are provided.

The data contained in the REMS system are 

subject to periodic update. Data for the current 

or previous years may be updated as corrections 

or additions are submitted by the sites. For this 

reason, the data presented in published reports 

may not agree with the current data in the REMS 

database. These updates typically have a relatively 

small impact on the data and should not affect 

the general conclusions and analysis of the data 

presented in this report.

REMS Web Page

As noted in Exhibit E-1, a web page has been 

established to disseminate radiation exposure 

information at DOE. The web site contains the 

latest published annual report on occupational 

exposure, information on reporting exposure 

data to DOE, points of contact for requesting 

information from REMS, DOE Orders and 

Standards related to radiation exposure, and 

links to other related sites. The site contains a 

web-based data query tool that allows users to 

obtain specific data reported to REMS from 1987 

to the most recent year available. The data can 

be selected and grouped by year, site, organizati

on, facility type, labor category, occupation, and 

monitoring status. The web page query tool allows 

access to summary information for over

1.9 million monitoring records.

Visit the REMS web page at:

 http://www.eh.doe.gov/rems/
E-2 DOE Occupational Radiation Exposure 

Comprehensive 

Epidemiologic Data Resource

Of interest to researchers in radiation exposure 

are the health effects associated with worker 

exposure to radiation. While the health effects 

from occupational exposure are not treated in this 

report, it has been extensively researched by DOE. 

The Comprehensive Epidemiologic Data Resource 

(CEDR) serves as a central resource for radiation 

health effects studies at the DOE.

Epidemiologic studies on health effects of 

radiation exposures have been supported by the 

DOE for more than 30 years. The results of these 

studies, which initially focused on the evaluation 

of mortality among workers employed in the 

nuclear weapons complex, have been published 

in scientific literature. However, the data collected 

during the conduct of the studies were not widely 

shared. CEDR has now been established as a 

public-use database to broaden independent 

access and use of these data. At its introduction 

in 1993, CEDR included primarily occupational 

studies of the DOE workforce, including 

demographic, employment, exposure, and 

mortality follow-up information on more than 

420,000 workers. The program’s holdings have 

been expanded to include data from both 

occupational and historical community health 

studies, such as those examining the impact 

of fallout from atmospheric nuclear weapons 

testing, community dose reconstructions, and data 

from the decades of follow-up on atomic bomb 

survivors. 

CEDR accomplishes this by a hierarchical 

structure that accommodates analysis and working 

files generated during a study, as well as files of 

documentation that are critical for understanding 

the data. CEDR provides easy access to its 

holdings through the Internet or phone and mail 

interchanges, and provides an extensive catalog of 

its holdings. CEDR has become a unique resource 

comprising the majority of data that exist on the 

health risks of occupational radiation exposure.

For further information about CEDR, access the 

CEDR internet web page at:

 http://cedr.lbl.gov

Or the CEDR Program Manager may be contacted at:

 barbara.brooks@hq.doe.gov
2003 Report Access to Radiation Exposure Information E-3 Exhibit E-1: Methods of Accessing REMS Information ���������������� ������������� ��������������������� �������� ������������ ����������� ������������ ������������� ���������������������� �������� ����������������������� ����� ����� ���������������������������������� ������������������������������ ������������������������������� ������������������������� ��������������������������� ����������������������� ������������������������� ������������������������������ ���������������������������� ������������������������ �������������������������������� ����� ����������������������������� ���������������� ��������������������������������� ������������������������������ ������������ �������������������� �������������������������� ������������������������������ ������������������������������������������������������������������������������������������������������������������������� ��������������������������������������������������������� ����������������������������������������������������������������������� ����������������������������������������� �������������������������������������������� ������������������������������������������� ���������������������������������� ����������������������������������������� ������������������ � ������������������������������������ �������������� � �������������������������������������� ������� � ������������������������������������� � ���������������������������������������� ���������� � ������������������������������������� ��������� � ����������������������������� �������������������������������������������� ������������������������������������� ���������������������������������������� ���������������������������������������� ��������������������������������� ������������������������������ �������������������������� �������������������� ���������� ��������������������������� ������������������������� ������� �
E-4 This page intentionally left blank. DOE Occupational Radiation Exposure
Prepared by:

Science Applications International Corporation

301 Laboratory Road • Oak Ridge, TN 37830