NUREG-0713 

Vol. 30

Occupational Radiation 

Exposure at Commercial 

Nuclear Power Reactors 

and Other Facilities 

2008 

Forty-First Annual Report 

Office of Nuclear Regulatory Research 
AVAILABILITY OF REFERENCE MATERIALS

IN NRC PUBLICATIONS

Non-NRC Reference Material

Documents available from public and special 

technical libraries include all open literature

items, such as books, journal articles, and 

transactions, Federal Register notices, Federal 

and State legislation, and congressional reports. 

Such documents as theses, dissertations, 

foreign reports and translations, and non-NRC 

conference proceedings may be purchased from 

their sponsoring organization.

Copies of industry codes and standards used 

in a substantive manner in the NRC regulatory 

process are maintained at—

 The NRC Technical Library

 Two White Flint North

 11545 Rockville Pike

 Rockville, MD 20852-2738

These standards are available in the library 

for reference use by the public. Codes and 

standards are usually copyrighted and may be 

purchased from the originating organization or, if 

they are American National Standards, from—

 American National Standards Institute

 11 West 42nd Street

 New York, NY 10036-8002

 www.ansi.org

 212-642-4900

The NUREG series comprises (1) technical 

and administrative reports and books 

prepared by the staff (NUREG-XXXX) or 

agency contractors (NUREG/CR-XXXX), (2) 

proceedings of conferences 

(NUREG/CP-XXXX), (3) reports resulting 

from international agreements 

(NUREG/IA-XXXX), (4) brochures 

(NUREG/BR-XXXX), and (5) compilations of 

legal decisions and orders of the Commission 

and Atomic and Safety Licensing Boards and 

of Directors’ decisions under Section 2.206 of 

NRC’s regulations (NUREG-0750).

NRC Reference Material

As of November 1999, you may electronically 

access NUREG-series publications and other 

NRC records at NRC’s Public Electronic 

Reading Room at www.nrc.gov/NRC/ADAMS/

index.html. Publicly released records include, 

to name a few, NUREG-series publications; 

Federal Register notices; applicant, licensee, 

and vendor documents and correspondence; 

NRC correspondence and internal memoranda; 

bulletins and information notices; inspection and 

investigative reports; licensee event reports; and 

Commission papers and their attachments.

NRC publications in the NUREG series, NRC 

regulations, and Title 10, Energy, in the Code of 

Federal Regulations may also be purchased from 

one of these two sources.

1. The Superintendent of Documents 

U.S. Government Printing Office

P. 0. Box 37082

Washington, DC 20402-9328 www.access.

gpo.gov/su-docs

202-512-1800

2. The National Technical Information Service 

Springfield, VA 22161-0002

www.ntis.gov

1-800-533-6847 or, locally, 703-805-6000

A single copy of each NRC draft report for 

comment is available free, to the extent of 

supply, upon written request as follows:

Address: Office of the Chief Information Officer,

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 Services Section

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E-mail: DISTRIBUTION@nrc.gov

Facsimile: 301-415-2289

Some publications in the NUREG series that are 

posted at NRC’s Web site address 

www.nrc.gov/NRC/NUREGS/indexnum.html 

are updated periodically and may differ from 

the last printed version. Although references to 

material found on a Web site bear the date the 

material was accessed, the material available 

on the date cited may subsequently be removed 

from the site.
NUREG-0713 

Vol. 30 

Occupational Radiation 

Exposure at Commercial 

Nuclear Power Reactors 

and Other Facilities 

2008 

Forty-First Annual Report 

Manuscript Completed: January 2010 

Date Published: January 2010 

Prepared by 

D.E. Lewis 

D.A. Hagemeyer* 

________ 

* Oak Ridge Associated Universities 

 210 Badger Avenue 

 Oak Ridge, TN 37830 

Office of Nuclear Regulatory Research 
ii

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

PREVIOUS REPORTS IN THIS SERIES

WASH-1311	 A Compilation of Occupational Radiation Exposure from Light Water Cooled Nuclear Power Plants, 1969–

1973, U.S. Atomic Energy Commission, May 1974.

NUREG-75/032	 Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969–1974, U.S. Nuclear Regulatory Commission, June 1975.

NUREG-0109	 Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969–1975, U.S. Nuclear Regulatory Commission, August 1976.

NUREG-0323	 Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969–1976, U.S. Nuclear Regulatory Commission, March 1978.

NUREG-0482	 Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1977, U.S. Nuclear Regulatory Commission, May 1979.

NUREG-0594	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1978, U.S. Nuclear Regulatory Commission, November 1979.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1979, Vol. 1, U.S. Nuclear

Regulatory Commission, March 1981.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1980, Vol. 2, U.S. Nuclear

Regulatory Commission, December 1981.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1981, Vol. 3, U.S. Nuclear

Regulatory Commission, November 1982.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1982, Vol. 4, U.S. Nuclear

Regulatory Commission, December 1983.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1983, Vol. 5, U.S. Nuclear

Regulatory Commission, March 1985.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1984, Vol. 6,

U.S. Nuclear Regulatory Commission, October 1986.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1985, Vol. 7,

U.S. Nuclear Regulatory Commission, April 1988.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1986, Vol. 8,

U.S. Nuclear Regulatory Commission, August 1989.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1987, Vol. 9,

U.S. Nuclear Regulatory Commission, November 1990.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1988, Vol. 10,

U.S. Nuclear Regulatory Commission, July 1991.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1989, Vol. 11,

U.S. Nuclear Regulatory Commission, April 1992.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1990, Vol. 12,

U.S. Nuclear Regulatory Commission, January 1993.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1991, Vol. 13,

U.S. Nuclear Regulatory Commission, July 1993.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1992, Vol. 14,

U.S. Nuclear Regulatory Commission, December 1993.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1993, Vol. 15,

U.S. Nuclear Regulatory Commission, January 1995.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1994, Vol. 16,

U.S. Nuclear Regulatory Commission, January 1996.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1995, Vol. 17,

U.S. Nuclear Regulatory Commission, January 1997.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1996, Vol. 18,

U.S. Nuclear Regulatory Commission, February 1998.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1997, Vol. 19,

U.S. Nuclear Regulatory Commission, November 1998.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1998, Vol. 20,

U.S. Nuclear Regulatory Commission, November 1999.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1999, Vol. 21,

U.S. Nuclear Regulatory Commission, October 2000.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2000, Vol. 22,

U.S. Nuclear Regulatory Commission, September 2001.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2001, Vol. 23,

U.S. Nuclear Regulatory Commission, September 2002.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2002, Vol. 24,

U.S. Nuclear Regulatory Commission, October 2003.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2003, Vol. 25,

U.S. Nuclear Regulatory Commission, October 2004.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2004, Vol. 26,

U.S. Nuclear Regulatory Commission, December 2005.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2005, Vol. 27,

U.S. Nuclear Regulatory Commission, December 2006.

NUREG-0713	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2006, Vol. 28,

U.S. Nuclear Regulatory Commission, November 2007.

NUREG-0713 	 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2007, Vol. 29,

U.S. Nuclear Regulatory Commission, December 2008.

Previous reports in the NUREG-0714 series, which are now combined with NUREG-0713, are as follows:

WASH-1350-R1	 First through Sixth Annual Reports of the Operation of the U.S. AEC’s Centralized Ionizing Radiation

Exposure Records and Reporting System, U.S. Atomic Energy Commission.

WASH-1350 R6

NUREG-75/108	 Seventh Annual Occupational Radiation Exposure Report for Certain NRC Licensees, 1974, U.S. Nuclear

Regulatory Commission, October 1975.

NUREG-0119	 Eighth Annual Occupational Radiation Exposure Report for 1975, U.S. Nuclear Regulatory Commission,

October 1976.

NUREG-0322	 Ninth Annual Occupational Radiation Exposure Report for 1976, U.S. Nuclear Regulatory Commission,

October 1977.

NUREG-0463	 Tenth Annual Occupational Radiation Exposure Report for 1977, U.S. Nuclear Regulatory Commission,

October 1978.

NUREG-0593	 Eleventh Annual Occupational Radiation Exposure Report for 1978, U.S. Nuclear Regulatory Commission,

January 1981.

NUREG-0714	 Twelfth Annual Occupational Radiation Exposure Report for 1979, Vol. 1, U.S. Nuclear Regulatory Commission, August 1982.

NUREG-0714	 Occupational Radiation Exposure, Thirteenth and Fourteenth Annual Reports, 1980 and 1981, Vols. 2 and 3,

U.S. Nuclear Regulatory Commission, October 1983.

NUREG-0714	 Occupational Radiation Exposure, Fifteenth and Sixteenth Annual Reports, 1982 and 1983, Vols. 4 and 5, U.S.

Nuclear Regulatory Commission, October 1985.

through
iii

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

abstract

1

Commercial nuclear power reactors and test reactor facilities, industrial radiographers; fuel processors (including uranium 

enrichment facilities), fabricators, and reprocessors; manufacturing and distribution of byproduct material; independent spent 

fuel storage installations; facilities for land disposal of low-level waste; and geologic repositories for high-level waste. There are 

currently no NRC licensees involved in low-level waste disposal or geologic repositories for high-level waste.

2

The number of workers with measurable dose includes any individual with a dose greater than zero rem and does not include 

doses reported as “not detectable.”

This report summarizes the occupational exposure data that are maintained in the U.S. 

Nuclear Regulatory Commission (NRC) Radiation Exposure Information and Reporting System 

(REIRS). The bulk of the information contained in the report was compiled from the 2008 annual 

reports submitted by five of the seven categories1

 of NRC licensees subject to the reporting 

requirements of 10 CFR 20.2206. The annual reports submitted by these licensees consist of 

radiation exposure records for each monitored individual. These records are analyzed for trends 

and presented in this report in terms of collective dose and the distribution of dose among the 

monitored individuals. Because there are no geologic repositories for high-level waste currently 

licensed and no low-level waste disposal facilities in operation, only five categories will be 

considered in this report. 

Annual reports for 2008 were received from a total of 194 NRC licensees. Compilations of 

the reports submitted by the 194 licensees indicated that 181,462 individuals were monitored, 

86,169 of whom received a measurable dose (Table 3.2). The collective dose incurred by these 

individuals was 11,301 person-rem, which represents a 7% decrease from the 2007 value. 

The number of workers receiving a measurable dose also decreased, resulting in an average 

measurable dose of 0.13 rem for 2008. The average measurable dose is defined as the total 

effective dose equivalent (TEDE) divided by the number of workers receiving a measurable dose.2

The figures and tables for commercial reactors in this report have been adjusted to account for 

transient reactor workers where specifically noted in footnotes. 

In calendar year 2008, the average annual collective dose per reactor for light water reactor 

(LWR) licensees was 88 person-rem. This represents a 9% decrease from the value reported for 

2007 (97 person-rem). The annual collective dose per reactor for boiling water reactors (BWRs) 

was 129 person-rem for 35 BWRs, and for pressurized water reactors (PWRs), it was 68 personrem for 69 PWRs. Analyses of transient worker data indicate that 28,780 individuals completed 

work assignments at two or more licensees during the monitoring year. The dose distributions 

are adjusted each year to account for the duplicate reporting of transient workers by multiple 

licensees. In 2008, the average measurable dose per worker for all licensees calculated from 

reported data was 0.13 rem. The corrected dose distribution resulted in an average measurable 

dose per worker for all licensees of 0.18 rem. 
iv

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Charles Hinson, Ronald LaVera, Steven Garry, Gregory Chapman, Richard Struckmeyer, Sami 

Sherbini, Janine Katanic, and Vincent Holahan assisted in the preparation of this NUREG, 

serving as technical reviewers. The U.S. Nuclear Regulatory Commission welcomes responses 

from readers.

Comments should be directed to:

Doris E. Lewis

REIRS Project Manager

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

Phone: 301-251-7559

E-mail Address: Doris.Lewis@nrc.gov

Paperwork Reduction Act Statement

The information collections contained in this NUREG are subject to the Paperwork Reduction 

Act of 1995 (44 U.S.C. 3501 et seq.), which were approved by the Office of Management and 

Budget, approval number 3150-0014.

Public Protection Notification

The NRC may not conduct or sponsor, and a person is not required to respond to, a request for 

information or an information collection requirement unless the requesting document displays a 

currently valid OMB control number.

EDITOR’S NOTE
v

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

PREVIOUS REPORTS IN THIS SERIES...........................................................................................ii

ABSTRACT........................................................................................................................................iii

EDITOR’S NOTE ...............................................................................................................................iv

TABLE OF CONTENTS......................................................................................................................v

PREFACE ..........................................................................................................................................xi

FOREWORD ...................................................................................................................................xiii

ABBREVIATIONS ...........................................................................................................................xv

1 INTRODUCTION......................................................................................................................... 1‐1

 1.1 Background ................................................................................................................... 1-1

 1.2 Radiation Exposure Information on the Internet........................................................... 1‐3

2 LIMITATIONS OF THE DATA..................................................................................................... 2‐1

3 ANNUAL PERSONNEL MONITORING REPORTS – 10 CFR 20.2206................................... 3‐1

3.1 Definition of Terms and Sources of Data........................................................................ 3‐1

 3.1.1 Statistical Summary Reports .............................................................................. 3‐1

 3.1.2 Number of Monitored Workers ........................................................................... 3‐1

 3.1.3 Number of Workers with Measurable Dose ....................................................... 3‐1

 3.1.4 Collective Dose................................................................................................... 3‐1

 3.1.5 Average Individual Dose..................................................................................... 3‐2

 3.1.6 Average Measurable Dose ................................................................................. 3‐2

 3.1.7 Number of Licensees Reporting......................................................................... 3‐2

 3.1.8 Collective TEDE Distribution by Dose Range.................................................... 3‐2

3.2 Annual TEDE Dose Distributions .................................................................................... 3‐4

3.3 Summary of Occupational Dose Data by License Category.......................................... 3‐7

 3.3.1 Industrial Radiography Licenses, Fixed Locations and Temporary Job Sites... 3‐7

 3.3.2 Manufacturing and Distribution Licenses, Type “A” Broad, Type “B” Broad, 

 Other, and Nuclear Pharmacies ........................................................................ 3‐8

 3.3.3 Low‐Level Waste Disposal Licenses................................................................ 3‐14

 3.3.4 Independent Spent Fuel Storage Installation Licenses ................................... 3‐14

 3.3.5 Fuel Cycle Licenses.......................................................................................... 3‐16

 3.3.6 Light Water Reactor Licenses........................................................................... 3‐17

 3.3.7 Other Facilities Reporting to NRC..................................................................... 3-19

 3.4 Summary of Intake Data by Licensee Category........................................................... 3‐20

table of contents

Page
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

4 COMMERCIAL LIGHT WATER REACTORS – FURTHER ANALYSIS................................... 4‐1

 4.1 Introduction......................................................................................................................... 4‐1

4.2 Definition of Terms and Sources of Data ........................................................................... 4‐1

 4.2.1 Number of Reactors.................................................................................................. 4‐1

 4.2.2 Electric Energy Generated........................................................................................ 4‐1

 4.2.3 Collective Dose per Megawatt‐Year ......................................................................... 4‐5

 4.2.4 Average Maximum Dependable Capacity................................................................ 4‐5

 4.2.5 Percent of Maximum Dependable Capacity Achieved............................................. 4‐5

4.3 Annual TEDE Distributions................................................................................................. 4‐6

4.4 Average Annual TEDE Doses............................................................................................ 4‐6

4.5 Three-Year Average Collective TEDE per Reactor ............................................................ 4‐9

4.6 Graphical Representation of Dose Trends in Appendix D................................................ 4‐19

 4.7 Decontamination and Decommissioning of Nuclear Power Plants.................................. 4‐19

5 TRANSIENT WORKERS AND CAREER DOSES AT NRC-LICENSED FACILITIES............. 5-1

 5.1 Termination Reports ........................................................................................................... 5‐1

5.2 Transient Workers at NRC Facilities.................................................................................. 5‐1

6 EXPOSURES TO PERSONNEL IN EXCESS OF REGULATORY LIMITS.............................. 6‐1

 6.1 Reporting Categories ......................................................................................................... 6‐1

6.2 Limitations of the Data........................................................................................................ 6‐2

6.3 Summary of Occupational Radiation Doses in Excess of NRC Regulatory Limits .......... 6‐3

6.4 Maximum Occupational Radiation Doses Below NRC Regulatory Limits........................ 6-6

7 REFERENCES............................................................................................................................ 7‐1

APPENDIX A – ANNUAL TEDE FOR NONREACTOR NRC LICENSEES AND OTHER FACILITIES 

REPORTING TO THE NRC, 2008..................................................................................................A‐1

APPENDIX B – ANNUAL WHOLE-BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES, 2008.............................................................................................................B‐1

APPENDIX C – PERSONNEL, DOSE, AND POWER GENERATION SUMMARY, 

1969–2008 .......................................................................................................................................C‐1

APPENDIX D – DOSE PERFORMANCE INDICATORS BY REACTOR SITE,

1973–2008 .......................................................................................................................................D‐1

APPENDIX E – GLOSSARY, 2008.................................................................................................E-1

table of contents (Continued)

Page
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Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Figure 3.1 Average Annual Values for Industrial Radiography Licensees, 1973–2008............. 3-9

Figure 3.2 Collective TEDE Distribution by Dose Range Industrial Radiographer— 

Fixed Location Licensees, 2004–2008.................................................................... 3-10

Figure 3.3 Collective TEDE Distribution by Dose Range Industrial Radiographer— 

Temporary Job Site Licensees, 2004–2008............................................................ 3-10

Figure 3.4 Average Annual Values for Manufacturing and Distribution

Licensees, 1973–2008............................................................................................. 3-12

Figure 3.5 Collective TEDE Distribution by Dose Range, Type “A” Broad

Manufacturing and Distribution Licensees, 2004–2008.......................................... 3-13

Figure 3.6 Collective TEDE Distribution by Dose Range, Type “B” Broad, 

Other, and Nuclear Pharmacy Licensees, 2004–2008........................................... 3-13

Figure 3.7 Average Annual Values for Independent Spent Fuel Storage

Installations, 1982–2008.......................................................................................... 3-15

Figure 3.8 Collective TEDE Distribution by Dose Range, Independent Spent

Fuel Storage Installation Licensees, 2004–2008.................................................... 3-16

Figure 3.9 Average Annual Values for Fuel Cycle Licensees, 1973–2008.............................. 3-18

Figure 3.10 Collective TEDE Distribution by Dose Range, Fuel Cycle

Licensees, 2004–2008............................................................................................. 3-19

Figure 3.11 Collective TEDE Distribution by Dose Range, Reactor

Licensees, 2004–2008............................................................................................. 3-20

Figure 4.1 Average Collective Dose and Number of Workers with Measurable Dose

per Reactor, 1973–2008 .......................................................................................... 4-10

Figure 4.2 Number of Operating Reactors and Electricity Generated, 1973–2008..................4-11

Figure 4.3 Average Measurable Dose per Worker and Collective Dose per

Megawatt-Year, 1973–2008..................................................................................... 4-12

Figure 4.4 Average, Median, and Extreme Values of the Collective Dose 

per Reactor, 1973–1991 .......................................................................................... 4-13

Figure 4.5 Average, Median, and Extreme Values of the Collective Dose 

per Reactor, 1992–2008 .......................................................................................... 4-14

list of figures

Page
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Table 3.1 Average Annual Exposure Data for Certain Categories of 

NRC Licensees, 1998–2008...................................................................................... 3-3

Table 3.2 Distribution of Annual Collective TEDE by License

Category, 2008........................................................................................................... 3-5

Table 3.3 Summary of Annual Dose Distributions for Certain NRC

Licensees, 1998–2008............................................................................................... 3-6

Table 3.4 Annual Exposure Information for Industrial 

Radiographers, 2006–2008....................................................................................... 3-7

Table 3.5 Annual Exposure Information for 

Manufacturing and Distribution, 2006–2008 ............................................................3-11

Table 3.6 Annual Exposure Information for Fuel Cycle Licensees, 2006–2008 .................... 3-17

Table 3.7 Intake by Licensee Category and Radionuclide Mode of 

Intake—Ingestion, 2008........................................................................................... 3-21

Table 3.8 Intake by Licensee Category and Radionuclide Mode of 

Intake—Inhalation, 2008.......................................................................................... 3-22

Table 3.9 Collective and Average CEDE by Licensee Category, 2008 .................................. 3-23

Table 3.10 Internal Dose (CEDE) Distribution, 1994–2008 ...................................................... 3-24

Table 4.1 Summary of Information Reported by Commercial

Boiling Water Reactors, 1973–2008.......................................................................... 4-2

Table 4.2 Summary of Information Reported by Commercial 

Pressurized Water Reactors, 1973–2008 ................................................................. 4-3

Table 4.3 Summary of Information Reported by Commercial

Light Water Reactors, 1973–2008............................................................................. 4-4

Table 4.4 Summary Distribution of Annual Whole-Body Doses at Commercial 

Light Water Reactors, 1977–2008............................................................................. 4-7

Table 4.5 Three-Year Totals and Averages Listed in Ascending Order of Collective 

TEDE per BWR, 2006–2008 ................................................................................... 4-15

list of tables

Page
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Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

list of tables (Continued)

Table 4.6 Three-Year Totals and Averages Listed in Ascending Order of Collective 

TEDE per PWR, 2006–2008 ................................................................................... 4-16

Table 4.7. Three-Year Collective TEDE per Reactor-Year for BWRs, 2006-2008 .................. 4-17

Table 4.8. Three-Year Collective TEDE per Reactor-Year for PWRs, 2006-2008 .................. 4-18

Table 4.9. Plants No Longer in Operation, 2008...................................................................... 4-20

Table 5.1 Effects of Transient Workers on Annual Statistical Compilations, 2008................... 5-2

Table 6.1 Occupational Doses in Excess of Regulatory Limits, 1994–2008............................ 6-4

Table 6.2 Occupational Doses in Excess of Regulatory Limits, 1985–1993............................ 6-5

Table 6.3 Maximum Occupational Doses for Each Exposure Category, 2008 ........................ 6-6

Page
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A number of U.S. Nuclear Regulatory Commission (NRC) licensees have inquired as to how 

the occupational radiation exposure data that are compiled from the individual exposure reports 

required by §20.2206 are used by the NRC staff. In combination with other sources of information, 

the principal uses of the data are to provide facts regarding routine occupational exposures to 

radiation and radioactive material that occur in connection with certain NRC-licensed activities. 

These facts, as indicated below, are used by the NRC staff: 

1. The data permit evaluation of trends, both favorable and unfavorable, from the viewpoint 

of the effectiveness of overall NRC/licensee radiation protection and as low as reasonably 

achievable (ALARA) efforts by licensees. 

2. The external dose data assist in the evaluation of the radiological risk associated with certain 

categories of NRC-licensed activities and are used for comparative analyses of radiation 

protection performance: U.S./foreign, boiling water reactors/pressurized water reactors 

(BWRs/PWRs), civilian/military, facility/facility, nuclear industry/other industries, etc. 

3. The data are used as one of the metrics of the NRC Reactor Oversight Program to evaluate 

the effectiveness of the licensees’ ALARA programs and also for inspection planning purposes. 

4. The data provide for the monitoring of transient workers who may affect dose distribution 

statistics through multiple counting. 

5. The data help provide facts for evaluating the adequacy of the current risk limitation system 

(e.g., are individual lifetime dose limits, worker population collective dose limits, and 

requirements for optimization needed). 

6. The data permit comparisons of occupational radiation risks with potential public risks when 

action for additional protection of the public involves worker exposures. 

7. The data are used in the establishment of priorities for the utilization of NRC health physics 

resources: research, standards development, and regulatory program development. 

8. The data provide facts for answering Congressional and administration inquiries and for 

responding to questions raised by the public. 

9. The data are used to provide radiation exposure histories to individuals who were exposed to 

radiation at NRC-licensed facilities. 

10. The data provide information that may be used in the planning of epidemiological studies. 

preface
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Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

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foreword

Through this annual report, the U.S. Nuclear Regulatory Commission (NRC) supports 

openness in its regulatory process by providing the public with accurate and timely information 

about the radiation protection program of NRC’s licensees. Toward that end, NUREG-0713, 

Volume 30, summarizes the 2008 occupational radiation exposure data maintained in the 

NRC Radiation Exposure Information and Reporting System (REIRS) database.

Seven categories of NRC licensees are required to report annually on individual exposure 

in accordance with Title 10, Section 20.2206, of the Code of Federal Regulations (10 CFR 

20.2206, “Reports of Individual Monitoring”). Specifically, these categories include commercial 

nuclear power plants; industrial radiographers; fuel processors (including uranium enrichment 

facilities), fabricators, and reprocessors; manufacturing and distribution of byproduct material; 

independent spent fuel storage installations; facilities for land disposal of low-level waste; 

and geologic repositories for high-level waste. Because NRC has not licensed any geologic 

repositories for high-level waste and no NRC-licensed low-level waste disposal facilities are 

currently in operation, this report considers only the first five categories of NRC licensees. As 

such, this report reflects the occupational radiation exposure data that NRC received from 194 

licensees.

The data submitted by licensees consist of radiation exposure records for each monitored 

individual. In 2008, 130,830 individuals were monitored and 64,075 received a measurable 

dose (when adjusted for transient workers). This report analyzes and presents these 

records in terms of collective dose and the distribution of dose among the monitored 

individuals. During 2008, these individuals incurred a collective dose of 11,301 person-rem, 

which represents a 7% decrease from the 2007 value of 12,157 person-rem. The average 

measurable dose is the total collective dose divided by the number of workers receiving a 

measurable dose. The average measurable dose decreased from 0.19 rem in 2007 to 0.18 

rem in 2008. This value can be compared with the 0.30 rem that the average person in 

the United States receives annually from natural background radiation. Worldwide annual 

exposures to natural radiation are generally expected to be in the range of 0.1 rem to 1.0 rem, 

with 0.24 rem [Ref. 12] being the current average worldwide value.

This annual report is useful in evaluating trends in occupational radiation exposure to assess 

the effectiveness of licensees’ radiation protection programs to maintain exposures as low 

as reasonably achievable (ALARA). For example, the NRC staff uses the data presented 

in this report as one of the metrics of the NRC Reactor Oversight Program to evaluate the 

effectiveness of licensees’ ALARA programs. 
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ABBREVIATIONS

AEC U.S. Atomic Energy Commission

ALARA as low as reasonably achievable

BWR boiling water reactor

CDE committed dose equivalent

CEDE committed effective dose equivalent

CFR Code of Federal Regulations

D&D decontamination and decommissioning

DDE deep dose equivalent

DOE U. S. Department of Energy

ERDA Energy Research and Development Administration

ISFSI independent spent fuel storage installation

LDE lens dose equivalent

LWR light water reactor

M&D manufacturing and distribution

mSv millisievert

MWe megawatts electric

MW-yr megawatt-year

ND not detectable

NR not required to be reported

NRC U.S. Nuclear Regulatory Commission

NRR Office of Nuclear Reactor Regulation

PSE planned special exposures

PWR pressurized water reactor

REIRS Radiation Exposure Information and Reporting System

RES Office of Nuclear Regulatory Research

SDE-ME shallow dose equivalent maximum extremity

SDE-WB shallow dose equivalent whole body

SI international system of units

SR collective dose ratio

Sv sieverts

TEDE total effective dose equivalent

TMI Three Mile Island

TODE total organ dose equivalent

UF6

 uranium hexafluoride

UNSCEAR United Nations Scientific Committee on the Effects of Atomic Radiation

USEC United States Enrichment Corporation
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INTRODUCTION

Section 1

1.1 background

One of the basic purposes of the Atomic Energy 

Act and the implementing regulations in Title 10, 

Code of Federal Regulations (CFR), Chapter I, 

Part 20, is to protect the health and safety of the 

public, including the employees of the licensees 

conducting operations under those regulations. 

Among the regulations designed to ensure that 

the standards for protection against radiation 

set out in 10 CFR 20 are met is a requirement 

that licensees provide individuals likely to be 

exposed to radiation with devices to monitor 

their exposures. Each licensee is also required 

to maintain indefinitely records of the results of 

such monitoring. However, there was no initial 

provision that these records or any summary of 

them be transmitted to a central location where 

the data could be retrieved and analyzed. 

On November 4, 1968, the U.S. Atomic Energy 

Commission (AEC) published an amendment 

to 10 CFR 20 requiring the reporting of certain 

occupational radiation exposure information 

to a central repository at AEC Headquarters. 

This information was required of the four 

categories3

 of AEC licensees that were 

considered to involve the greatest potential 

for significant occupational doses and of AEC 

facilities and contractors exempt from licensing. 

A procedure was established whereby the 

appropriate occupational exposure data were 

extracted from these reports and entered 

into the AEC Radiation Exposure Information 

and Reporting System (REIRS), a computer 

system that was maintained at the Oak Ridge 

National Laboratory Computer Technology 

Center in Oak Ridge, Tennessee, until May 

1990. At that time, the data were transferred 

to a database management system and are 

now maintained at the Oak Ridge Institute 

for Science and Energy, which is managed 

by Oak Ridge Associated Universities. The 

computerization of these data ensures that they 

are kept indefinitely and facilitates their retrieval 

and analysis. The data maintained in REIRS 

have been summarized and published in a 

report every year since 1969. Annual reports for 

each of the years 1969 through 1973 presented 

the data reported by both AEC licensees 

and contractors and were published in six 

documents designated as WASH-1350-R1 

through WASH-1350-R6. 

In January 1975, with the separation of AEC 

into the Energy Research and Development 

Administration (ERDA) and the U.S. Nuclear 

Regulatory Commission (NRC), each agency 

assumed responsibility for collecting and 

maintaining occupational radiation exposure 

information reported by the facilities under its 

jurisdiction. The annual reports published by 

NRC on occupational exposure for calendar 

year 1974 and subsequent years do not 

contain information pertaining to ERDA facilities 

or contractors. Comparable information for 

facilities and contractors under ERDA, now the 

U.S. Department of Energy (DOE), is collected 

and published by the DOE Office of Corporate 

Safety Analysis, a division of Health, Safety and 

Security, in Germantown, Maryland. 

3

Commercial nuclear power reactors; industrial radiographers; fuel processors (including uranium enrichment facilities as of 1997), 

fabricators, and reprocessors; and manufacturing and distribution of specified quantities of byproduct material.
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

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In 1982 and 1983, Paragraph 20.408(a) of 

10 CFR 20 was amended to require three 

additional categories of NRC licensees to 

submit annual statistical exposure reports 

and individual termination exposure reports. 

The three additional NRC licensee categories 

were: (1) geologic repositories for high-level 

radioactive waste, (2) independent spent 

fuel storage installations, and (3) facilities 

for the land disposal of low-level radioactive 

waste. This document presents the exposure 

information that was reported by NRC licensees 

representing two of these categories; there are 

no geologic repositories for high-level waste 

currently licensed. 

This report and each of the predecessors 

summarize information reported for both the 

current year and previous years. More licenseespecific data for previous years, such as the 

annual reports submitted by each commercial 

power reactor pursuant to 10 CFR 20.407 

and 20.2206 (after 1993) and their technical 

specifications (prior to Volume 20 of this report), 

may be found in the documents listed on the 

inside of the front cover of this report for the 

specific year desired. Additional operating 

data and statistics for each commercial power 

reactor for the years 1973 through 1982 may 

be found in a series of reports, Nuclear Power 

Plant Operating Experience [Refs. 1–9]. 

These documents are available for viewing at 

all NRC public document rooms, as well as 

on the NRC public Web site (www.nrc.gov), 

or they may be purchased from the National 

Technical Information Service, as shown in the 

References section. 

In May 1991, 10 CFR 20 Standards for 

Protection Against Radiation; Final Rule was 

revised. The revision redefined the radiation 

monitoring and reporting requirements of NRC 

licensees. Instead of submitting summary 

annual reports (§20.407) and termination 

reports (§20.408), licensees are now required 

to submit an annual report of the dose received 

by each monitored worker (§20.2206). 

Licensees were required to implement the new 

requirements no later than January 1994. 

 

 
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The main Web address for NRC is 

The NRC radiation exposure information Web 

URL is 

Comments on this report or the NRC’s radiation 

exposure Web page should be directed to 

1.2 Radiation Exposure

Information on the

Internet

In May 1995, NRC began pursuing the 

dissemination of radiation exposure information 

via a Web site on the Internet. This site 

allows interested parties with the appropriate 

equipment to access the data electronically 

rather than through the published NUREG-0713 

document. A Web site was created for radiation 

exposure and linked into the main NRC Web 

page. The Web site contains up-to-date 

information on radiation exposure, as well as 

information and guidance on reporting radiation 

exposure information to NRC. Interested parties 

may read the documents online or download 

information to their systems for further analysis. 

Software, such as the Radiation Exposure 

Monitoring and Information Transmittal System, 

a software application designed to maintain 

licensee dose records, and REIRView, a 

software package designed to validate a 

licensee’s annual data submittal, are also 

available for downloading via the Web site. 

There are also links to other Web sites dealing 

with the topics of radiation and health physics. 

Individuals and organizations may also submit 

requests for dose records contained in REIRS 

on this Web site. 

NRC intends to continue pursuing the 

dissemination of radiation exposure information 

via the Web and will focus more resources on 

the electronic distribution of information rather 

than the publication of hard-copy reports.

http://www.nrc.gov 

http://www.reirs.com 

Doris E. Lewis

REIRS Project Manager 

Office of Nuclear Regulatory Research 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555 

Phone: 301-251-7559

E-mail Address: Doris.Lewis@nrc.gov
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limitations of the data

Section 2

All of the figures compiled in this report relating 

to exposures and occupational doses are 

based on the results and interpretations of 

the readings of various types of personnelmonitoring devices employed by each licensee. 

This information, obtained from routine 

personnel-monitoring programs, is sufficient to 

characterize the radiation exposure incident to 

individuals’ work and is used in evaluating the 

radiation protection program. 

Monitoring requirements are specified in 10 

CFR 20.1502, which requires licensees to 

monitor individuals who receive or are likely to 

receive a dose in a year in excess of 10% of the 

applicable limits. For most adults, the annual 

limit for the whole body is 5 rem, so 0.5 rem 

per year is the level above which monitoring 

is required. Separate dose limits have been 

established for minors and declared pregnant 

workers. Monitoring is also required for any 

individual entering a high or very high radiation 

area. Depending on the administrative policy 

of each licensee, persons such as visitors and 

clerical workers may also be provided with 

monitoring devices, even though the probability 

of their exposure to measurable levels of 

radiation is extremely small. Licensees must 

report the dose records of those individuals for 

whom monitoring is required. Many licensees 

elect to report the doses for every individual for 

whom they provided monitoring. This practice 

increases the number of individuals that are 

considered to be radiation workers. 

In an effort to account for this increase, the 

number of individuals reported as having 

“no measurable dose”4

 has been subtracted 

from the total number of individuals monitored 

in order to calculate an average dose per 

individual receiving a measurable dose, as well 

as the average dose per monitored individual. 

The average dose per individual, as well as 

the dose distributions shown for groups of 

licensees, also can be affected by the multiple 

reporting of individuals who were monitored 

by two or more licensees during the year. 

Licensees are only required to report the 

doses received by individuals at their licensed 

facilities. A dose distribution for a single licensee 

does not consider that some of the individuals 

may have received doses at other facilities. 

When the data are summed to determine the 

total number of individuals monitored by a 

group of licensees, individuals may be counted 

more than once if they have worked at more 

than one facility during the calendar year. These 

occurrences can also affect the distribution of 

doses because individuals may be counted 

multiple times in the lower dose ranges rather 

than one time in the higher range corresponding 

to the actual accumulated dose for the year 

(the sum of an individual’s dose accrued at all 

facilities). This source of error has the greatest 

potential impact on the data reported by nuclear 

power reactors since they employ many shortterm workers. Section 5 contains an analysis 

that corrects for individuals being counted more 

than once. 

When examining the annual statistical data it 

is important to note that all of the personnel 

included in the report may not have been 

4 The number of workers with measurable dose includes any individual with a total effective dose equivalent greater than zero rem. 

Workers reported with zero dose, or no detectable dose, are included in the number of workers with no measurable exposure.
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

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monitored throughout the entire year. Many 

licensees, such as radiography firms and 

nuclear power reactors, may monitor numerous 

individuals for periods much less than a year. 

The average doses calculated from these data, 

therefore, are less than the average dose that 

an individual involved in that activity for the full 

year would receive. 

Considerable attention should be given when 

referencing the collective totals presented 

in this report. The differences between the 

totals presented for all licensees that reported 

versus only those licensees that are required to 

report should be noted. Likewise, one should 

distinguish between the doses attributed 

to the pressurized water reactors (PWRs) 

and the doses attributed to boiling water 

reactors (BWRs). The totals may be inclusive 

or exclusive of those licensees that were in 

commercial operation for less than one full year. 

These parameters vary throughout the tables 

and appendices of this report. The apparent 

discrepancies among the various tables are a 

necessary side effect of this endeavor. 

The data contained in this report are subject 

to change because licensees may submit 

corrections or additions to data for previous 

years. For the 2008 report, data for prior years 

may have been updated to account for these 

corrections and additions. Users should be 

aware of these changes, which are italicized for 

easy identification. 

This report contains information reported by 

NRC licensees and some Agreement State5

 

licensees. Since NRC licenses all commercial 

nuclear power reactors, fuel processors and 

fabricators, and independent spent fuel storage 

installations, information shown for these 

categories reflect all relevant activity in the 

United States. This is not the case, however, 

for the remaining categories of industrial 

radiography, manufacturing and distribution of 

specified quantities of byproduct material, and 

low-level waste disposal. Many companies that 

conduct these types of activities are located 

in Agreement States. More than three times 

as many facilities are regulated by Agreement 

States than are licensed by NRC. Agreement 

States are not required to adopt the reporting 

requirements in 10 CFR 20.2206. As a result, 

Agreement State licensees are not required to 

submit occupational dose reports to the NRC. 

Although some Agreement State licensees 

voluntarily submit occupational dose reports 

to NRC, these results are not included in the 

analyses presented in Sections 3, 5, and 6 of 

this report. The data are, however, included 

in Appendix A for completeness. In addition, 

this report does not include compilations of 

nonoccupational exposure, such as exposure 

received by medical patients from X-rays, 

fluoroscopy, or accelerators. 

All dose equivalent values in this report are 

given in units of rem in accordance with 

the general provisions for records, 10 CFR 

20.2101(a). In order to convert rem into the 

International System of Units (SI) unit of sieverts 

(Sv), readers should divide the value in rem 

by 100. Therefore, 1 rem = 0.01 Sv. In order to 

convert rem into millisieverts (mSv), readers 

should multiply the value in rem by 10.

 5Agreement States are States that have entered into formal agreement with NRC under which the State regulates the use of certain 

byproduct, source, and small quantities of special nuclear material in that State. In 2008, there were 35 Agreement States.
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ANNUAL PERSONNEL MONITORING 

REPORTS – 10 CFR 20.2206

Section 3

3.1 DEFINITION OF TERMS 

AND SOURCES OF DATA

3.1.1 Statistical Summary Reports 

The total effective dose equivalent (TEDE) 

is summed per individual and tabulated into 

the appropriate dose range to generate the 

dose distribution for each licensee. The total 

collective dose is more accurate using this 

method, because the licensee reported the 

dose to each individual and the total collective 

dose was calculated from the sum of these 

doses and not statistically derived from the 

dose distribution (see Section 3.1.4). The 

TEDE includes the dose contribution from the 

committed effective dose equivalent (CEDE) for 

those workers who had intakes that required 

monitoring and reporting of internal dose. 

3.1.2 Number of Monitored Workers 

The number of monitored workers refers to the 

total number of workers that the NRC licensees 

(who are covered by 10 CFR 20.1502) reported 

as being monitored for exposure to external and 

internal radiation during the year. This number 

includes all workers for whom monitoring is 

required and may include visitors, service 

representatives, contract workers, clerical 

workers, and any other workers for whom the 

licensee determines that monitoring devices 

should be provided. 

For licensees submitting under 10 CFR 

20.2206, the total number of workers was 

determined from the number of unique personal 

identification numbers submitted per licensee. 

Uniqueness is defined by the combination of 

identification number and identification type 

[Ref. 10]. 

3.1.3 Number of Workers with Measurable 

Dose

The number of workers with measurable dose 

includes any individual with a TEDE greater 

than zero rem. This does not include workers 

with a TEDE reported as zero, not detectable 

(ND), or not required to be reported (NR) 

[Ref. 10]. 

3.1.4 Collective Dose 

The concept of collective dose is used in this 

report to denote the summation of the TEDE 

received by all monitored workers and is 

reported in units of person-rem. Since 10 CFR 

20.2206 requires that the TEDE be reported, 

the collective dose is calculated by summing 

the TEDE for all monitored workers. The phrase 

“collective dose” is used throughout this report 

to mean the collective TEDE, unless otherwise 

specified. 

It should be noted that, prior to the 

implementation of the revised dose reporting 

requirements of 10 CFR 20.2206 in 1994, the 

collective dose was, in some cases, calculated 

from the dose distributions by summing the 

products obtained from multiplying the number 

of workers reported in each of the dose ranges 

by the midpoint of the corresponding dose 

range. This assumes that the midpoint of the 

range is equal to the arithmetic mean of the 

individual doses in the range. Experience has 

shown that the actual mean dose of workers 

reported in each dose range is less than the 

midpoint of the range. For this reason, the 

resultant calculated collective doses shown 

in this report for these licensees may be 

approximately 10% higher than the sum of the 
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

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actual individual doses. Care should be taken 

when comparing the actual collective dose 

calculated for 1994 to 2008 with the collective 

dose for years prior to 1994 because of this 

change in methodology. In addition, prior to 

1994, doses only included the external wholebody dose with no internal dose contribution. 

Although the contribution of internal dose to the 

TEDE is minimal for most licensees, it should 

be considered when comparing collective doses 

for 1994 and later with the collective dose for 

years prior to 1994. One noted exception is 

for fuel fabrication licensees where the CEDE, 

in some cases, contributes the majority of the 

TEDE (see Section 3.3.5). 

3.1.5 Average Individual Dose

The average individual dose is obtained by 

dividing the collective dose by the total number 

of workers reported as being monitored. 

This figure is usually less than the average 

measurable dose because it includes the 

number of those workers who received zero or 

less than measurable doses. 

3.1.6 Average Measurable Dose

The average measurable dose is obtained by 

dividing the collective TEDE by the number 

of workers 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 

in various segments of the nuclear industry, 

because it deletes those workers receiving zero 

or no detectable dose, many of whom were 

monitored for convenience or identification 

purposes. 

3.1.7 Number of Licensees Reporting

The number of licensees refers to the NRC 

licenses issued to use radioactive material for 

certain activities that would place the licensees 

in one of the seven5

 categories that are required 

to report pursuant to 10 CFR 20.2206. The 

third column in Table 3.1 shows the number of 

licensees that have filed such reports during 

the last 11 years. All nuclear power plants, fuel 

processors and fabricators, and independent 

spent fuel storage installations are required to 

report occupational exposure to NRC, whether 

or not they are in an Agreement State. The 

other types of Agreement State licensees are 

not required to submit exposure reports to NRC. 

3.1.8 Collective TEDE Distribution 

by Dose Range 

The United Nations Scientific Committee on the 

Effects of Atomic Radiation (UNSCEAR) 2000 

report, entitled Sources and Effects of Ionizing 

Radiation, United Nations Scientific Committee 

on the Effects of Atomic Radiation UNSCEAR 

2000 Report to the General Assembly, 

Volume I [Ref. 11], recommends the calculation 

of a parameter, SR (collective distribution ratio), 

to aid in the examination of the distribution 

of radiation exposure among workers. SR is 

defined as the ratio of the annual collective 

dose incurred by workers whose annual doses 

exceed a certain dose level to the total annual 

collective dose. UNSCEAR uses a subscript to 

denote the specific dose level in millisieverts. 

Therefore, SR15 is the notation for the collective 

dose for individuals who received 15 mSv (1.5 

rem) or more in the year, divided by the total 

annual collective dose. The UNSCEAR 2000 

6

These categories are commercial nuclear power reactors; industrial radiographers; fuel processors (including uranium enrichment 

facilities), fabricators, and reprocessors; manufacturing and distribution of byproduct material; independent spent fuel storage 

installations; facilities for land disposal of low-level waste; and geologic repositories for high-level waste. There are currently no 

NRC licensees involved in low-level waste disposal or geologic repositories for high-level waste.
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TABLE 3.1

Average Annual Exposure Data for Certain Categories of NRC Licensees

1998–2008

NRC License

Category* and

Program Code

Calendar

Year

Number of

Licensees

Reporting

Number of

Monitored

Individuals

Number of

Workers

with

Measurable

TEDE

Collective

TEDE

(person-rem)

Average

TEDE (rem)

Average

Measurable

TEDE per

Worker (rem)

1998 141 4,940 3,439 1,858.775 0.38 0.54

1999 131 3,557 2,689 1,548.110 0.44 0.58

2000 128 3,157 2,454 1,525.143 0.48 0.62

2001 123 3,560 3,040 2,106.213 0.59 0.69

2002 100 3,420 2,842 1,729.222 0.51 0.61

2003 118 3,115 2,651 1,584.249 0.51 0.60

2004 113 3,568 3,014 1,603.591 0.45 0.53

2005 90 3,009 2,623 1,504.575 0.50 0.57

2006 78 2,388 1,981 1,109.347 0.46 0.56

2007 74 2,607 2,224 1,315.171 0.50 0.59

2008 61 2,967 2,587 1,460.757 0.49 0.56

1998 28 1,922 644 401.356 0.21 0.62

1999 40 2,205 836 418.993 0.19 0.50

2000 39 2,460 1,187 415.402 0.17 0.35

2001 35 1,705 1,184 344.743 0.20 0.29

2002 29 1,437 1,052 328.092 0.23 0.31

2003 33 2,372 1,796 436.660 0.18 0.24

2004 28 2,539 1,787 347.258 0.14 0.19

2005 23 2,566 1,557 388.547 0.15 0.25

2006 23 1,391 903 284.556 0.20 0.32

2007 23 2,106 1,463 291.326 0.14 0.20

2008 18 1,934 1,341 222.123 0.11 0.17

1998 1 53 21 2.561 0.05 0.12

1999 2 86 33 5.172 0.06 0.16

2000 2 146 83 5.571 0.04 0.07

2001 2 154 107 13.088 0.08 0.12

2002 2 75 67 6.013 0.08 0.09

2003 2 55 46 2.791 0.05 0.06

2004 1 37 27 1.257 0.03 0.05

2005 2 59 30 0.769 0.01 0.03

2006 2 59 26 2.108 0.04 0.08

2007 2 57 26 1.697 0.03 0.07

2008 2 53 21 1.248 0.02 0.05

1998 10 10,684 3,613 949.865 0.09 0.26

1999 10 9,773 3,935 1,020.333 0.10 0.26

2000 9 9,336 4,649 1,339.398 0.14 0.29

2001 9 8,145 3,980 1,162.262 0.14 0.29

2002 8 7,937 3,886 660.899 0.08 0.17

2003 8 7,738 3,633 556.297 0.07 0.15

2004 8 7,562 3,813 513.929 0.07 0.13

2005 9 7,695 3,370 496.502 0.06 0.15

2006 9 7,417 3,415 521.525 0.07 0.15

2007 9 7,536 3,225 428.717 0.06 0.13

2008 9 7,184 2,770 420.898 0.06 0.15 

1998 104 114,367 57,466 13,187.392 0.12 0.23

1999 104 113,916 59,031 13,665.711 0.12 0.23

2000 104 110,557 57,233 12,651.682 0.11 0.22

2001 104 104,928 52,292 11,108.552 0.11 0.21

2002 104 107,900 54,460 12,126.190 0.11 0.22

2003 104 109,990 55,967 11,955.570 0.11 0.21

2004 104 110,290 52,873 10,367.897 0.09 0.20

2005 104 114,344 57,566 11,455.807 0.10 0.20

2006 104 116,354 58,788 11,021.186 0.09 0.19

2007 104 114,583 57,267 10,120.013 0.09 0.18

2008 104 118,692 57,356 9,195.940 0.08 0.16

1998 284 131,966 65,183 16,399.949 0.12 0.25

1999 287 129,537 66,524 16,658.319 0.13 0.25

2000 282 125,656 65,606 15,937.196 0.13 0.24

2001 273 118,492 60,603 14,734.858 0.12 0.24

2002 243 120,769 62,307 14,850.416 0.12 0.24

2003 265 123,270 64,093 14,535.567 0.12 0.23

2004 254 123,996 61,514 12,833.932 0.10 0.21

2005 228 127,673 65,146 13,846.200 0.11 0.21

2006 216 127,609 65,113 12,938.722 0.10 0.20

2007 212 126,889 64,205 12,156.924 0.10 0.19

2008 194 130,830 64,075 11,300.966 0.09 0.18

 * These categories consist only of NRC licensees. Agreement State licensed organizations are not required to report occupational 

exposure data to NRC.

 ** This category includes all LWRs in commercial operation for a full year for each of the years indicated. Reactor data have been 

corrected to account for the multiple counting of transient reactor workers (see Section 5).

Grand Totals

and Averages

Commercial

Light Water

Reactors (LWRs)**

41111

Fuel

Cycle

Licenses –

 Fabrication

 Processing and

 Uranium Enrich.

21200

21210

Independent

Spent Fuel

Storage

23100

23200

Manufacturing

and

Distribution

02500

03211

03212

03214

Industrial

Radiography

03310

03320
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

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report notes that the 1.5 rem dose level may not 

be useful where doses are consistently lower 

than this level, and UNSCEAR recommends 

that research organizations report SR values 

lower than 1.5 rem where appropriate. For 

this reason, NRC has adopted the policy of 

calculating and tracking the collective TEDE 

distribution by dose range at dose levels 

of 0.10, 0.25, 0.50, 1.0, and 2.0 rem. The 

collective TEDE distribution by dose range 

values in this report was calculated by summing 

the TEDE to each individual who received a 

TEDE greater than or equal to the specified 

dose range divided by the total collective TEDE. 

In addition, the distribution is presented as a 

percentage rather than as a decimal fraction.

Figures 3.2, 3.3, 3.5, 3.6, 3.8, 3.10, and 3.11 

show the collective TEDE distribution by dose 

range calculated in terms of percentage of the 

collective dose delivered above the specified 

dose levels for each of the categories of NRC 

licensees. Two properties of these graphs help 

to further reveal the nature of the distribution of 

dose and dose trends at NRC licensees. The 

first is that the percentage of dose in the higher 

dose ranges (i.e., above 0.50 rem) should be 

relatively small. This would indicate that fewer 

workers are exposed at these higher levels 

of individual risk. The second property is the 

ability to track the shift in dose over time. For a 

given dose value, a reduction in the percentage 

from one year to the next indicates that less 

dose is being received by workers above this 

value. Therefore, these graphs can be useful in 

qualifying the dose received in a given year and 

the trends in doses from year to year.

3.2 Annual TEDE Dose

Distributions

Table 3.2 provides a statistical compilation of 

the occupational dose reports by categories of 

licensees (see Section 3.3 for a description of 

each licensee category). The dose distributions 

are generated by summing the TEDE for 

each individual and counting the number of 

individuals in each dose range. In nearly every 

licensee category, a large number of workers 

receive doses that are less than measurable, 

and very few doses exceed 4 rem. Ninetytwo percent of the reported workers with 

measurable doses (shown in Table 3.2) were 

monitored by nuclear power facilities in 2008, 

where they received 82% of the total collective 

dose. 

Under the regulatory limits in 10 CFR 20.1201, 

an annual TEDE greater than 5 rem, for an 

adult occupational worker, is a dose that 

exceeds the regulatory limits (see Section 6). 

Table 3.3 gives a summary of the annual 

occupational dose records reported to NRC, 

as required by 10 CFR 20.2206, by certain 

categories of NRC licensees. Table 3.3 shows 

that for the past 11 years, the percentage of 

workers with <2 rem has been greater than 

99%. The number of workers receiving an 

annual dose greater than 5 rem has been 

<0.01% since 1998. No individual monitored 

at any of the five NRC licensee categories 

included in this report received a dose above 

the 5 rem annual TEDE limit during the past 5 

years (see Section 6). 
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TABLE 3.2

Distribution of Annual Collective TEDE by License Category

2008

 No Meas. 0.10- 0.25- 0.50- 0.75- 1.00- 2.00- 3.00- 4.00- 5.00- 6.00-  Meas. <0.1 0.25 0.50 0.75 1.00 2.00 3.00 4.00 5.00 6.00 12.00 >12 

Number of Individuals with TEDE in the Ranges (rem)*

License Category (Number of sites reporting)

Total

Number

Monitored

Number

with Meas.

Dose

Total

Collective

Dose (TEDE)

(person-rem)

 35 26 61 26 0.509 345 667 429 452 298 229 371 93 20 2 2,906 2,561 1,460.248

380 693 429 452 298 229 371 93 20 2 0 0 0 2,967 2,587 1,460.757

 153 122 60 50 43 22 14 1 465 312 95.790 91 91 15 7 1 0 0 0 0 205 114 8.421 349 680 149 43 17 4 10 5 6 1 1,264 915 117.912 593 893 224 100 61 26 24 6 6 1 0 0 0 1,934 1,341 222.123

32 17 3 1 53 21 1.248

4,414 1,515 648 416 164 24 3 7,184 2,770 420.898

 27,150 21,809 7,276 3,841 1,098 392 221 5 61,792 34,642 4,522.413 62,724 30,022 10,061 3,737 749 191 48 107,532 44,808 4,673.527 89,874 51,831 17,337 7,578 1,847 583 269 5 0 0 0 0 0 169,324 79,450 9,195.940

 95,293 54,949 18,641 8,547 2,370 862 667 104 26 3 0 0 0 181,462 86,169 11,300.966

 INDUSTRIAL RADIOGRAPHY Fixed Locations (3) Temporary Job Sites (58)

Total (61)

 MANUFACTURING AND DISTRIBUTION Type "A" Broad (2) Type "B" Broad and Other (4) Nuclear Pharmacies (12)

Total (18)

 INDEPENDENT SPENT FUEL STORAGE

Total (2)

 FUEL CYCLE**

Total (9)

 COMMERCIAL POWER  REACTORS*** Boiling Water (35) Pressurized Water (69)

Total (104)

 GRAND TOTALS

3.2

 * Dose values exactly equal to the values separating ranges are reported in the next higher range. ** This category includes fabrication, processing, and uranium enrichment plants (see Section 3.3.5). *** This category includes all reactors in commercial operation for a full year during 2008. Although Brown’s Ferry 1 was placed on administrative hold in 1985, it remains in the count of operating reactors 

and has resumed operation as of June, 2007. These values have not been adjusted for the multiple counting of transient reactor workers (see Section 5).
3-6

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

1998 166,127 132,069 99.6% (489) >99.99% (6) 1

1999 166,084 129,117 99.6% (534) >99.99% (1) 0

2000 163,073 125,026 99.5% (573) >99.99% (3) 0

2001 154,717 118,150 99.4% (734) >99.99% (1) 0

2002 162,381 119,694 99.5% (582) >99.99% (1) 0

2003 165,941 122,213 99.7% (419) >99.99% (1) 1

2004 164,017 122,975 99.7% (368) 100% (0) 0

2005 174,021 126,627 99.7% (370) 100% (0) 0

2006 176,071 126,726 99.8% (258) 100% (0) 0

2007 176,367 125,869 99.8% (243) 100% (0) 0

2008 181,368 129,796 99.9% (167) 100% (0) 0

Percent of Percent of Number of

 Individuals Individuals Individuals

Reported Corrected with Doses with Doses with Doses 

Year Number Number <2 rem <5 rem >12 rem

* Licensees required to submit radiation exposure reports to the NRC under 10 CFR 20.2206.

** This column lists the actual number of persons who may have been counted more than once because they worked at more than one facility 

during the calendar year (see Section 5).

*** Data for 1998–2008 are based on the distribution of individual doses after adjusting for the multiple counting of transient workers (see Section 

5). The number of people exceeding both 2 and 5 rem are shown in parentheses from 1998–2008.

TABLE 3.3

Summary of Annual Dose Distributions for Certain* NRC Licensees

1998–2008

Total Number of Monitored Persons

** *** *** ***
3-7

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.4

Annual Exposure Information for Industrial Radiographers

2006–2008

Year Type of License

Number of

Licensees

Number of

Monitored

Individuals

Workers with

Measurable

Dose

Collective

Dose

(person-rem)

Average

Measurable

Dose (rem)

Fixed Location

Temporary Job Sites

Total

Fixed Location

Temporary Job Sites

Total

Fixed Location

Temporary Job Sites

Total

8

70

78

5

69

74

3

58

61

122

2,266

2,388

59

2,548

2,607

61

2,906

2,967

22

1,959

1,981

20

2,204

2,224

26

2,561

2,587

0.784

1,108.563

1,109.347

0.623

1,314.548

1,315.171

0.509

1,460.248

1,460.757

0.04

0.57

0.56

0.03

0.60

0.59

0.02

0.57

0.56

2006

2007

2008

3.3 Summary of

Occupational Dose

Data by License Category

3.3.1 Industrial Radiography Licenses, Fixed 

Locations and Temporary Job Sites

Industrial radiography licenses are issued to 

allow the use of sealed radioactive materials, 

usually in exposure devices or “cameras,” that 

primarily emit gamma rays for nondestructive 

testing of pipeline weld joints, steel structures, 

boilers, aircraft and ship parts, and other highstress alloy parts. Some firms are licensed 

to conduct such activities in one location, 

usually in a permanent facility designed and 

shielded for radiography; others perform 

radiography at temporary job sites in the 

field. The radioisotopes most commonly used 

are cobalt-60 and iridium-192. As shown in 

Table 3.1, annual reports were received for 

61 radiography licensees in 2008. Table 3.4 

summarizes the reported data for the two types 

of industrial radiography licenses for 2008 

and for the previous 2 years for comparison 

purposes. 

The average measurable dose for workers 

performing radiography at a fixed location 

ranged from 5% to 10% of the average 

measurable dose of workers at temporary job 

sites over the past 3 years. This is because it 

is more difficult for workers to avoid exposure 

to radiation at temporary job sites in the field, 

where conditions are not optimal and may 

change daily. To view the contribution that 

each radiography licensee made to the total 

collective dose, see Appendix A which presents 

a summary of the information reported by each 

of these licensees in 2008. 

High exposures in radiography can be directly 

attributable to the type and location of the 

radiography field work. For example, locations 

such as oil drilling platforms and aerial tanks 

offer the radiographer little available shielding. 

In these situations, there may not be an 

opportunity to use distance as a means of 

minimizing exposure and achieving doses 

that are as low as is reasonably achievable 

(ALARA). Although these licensed activities 
3-8

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

usually result in average measurable doses 

that are higher than those received by other 

licensees, they involve a relatively small number 

of exposed workers. 

Figure 3.1 shows the number of workers 

with measurable dose per licensee, the total 

collective dose per licensee, and the average 

measurable dose per worker for both types 

of industrial radiography licensees from 1973 

through 2008. While the number of workers 

with measurable TEDE per licensee increased 

from 2007 to 2008, the collective TEDE also 

increased, resulting in the average measurable 

TEDE remaining nearly the same for the past 3 

years.

Figures 3.2 and 3.3 show the collective dose 

distribution by dose range (see Section 

3.1.8) for fixed location and temporary job 

site radiography licensees. These graphs 

demonstrate that temporary job site licensees 

consistently have individuals receiving doses 

in the higher dose ranges and routinely have 

20% to 30% of the collective dose delivered 

to individuals above 2 rem. It should be noted 

that the 2006 distribution for fixed location 

radiographers in Figure 3.2 has been adjusted 

due to a change in status for a radiographer 

who was initially identified as a fixed location 

radiographer and who was later determined to 

be a temporary job site radiographer. 

3.3.2 Manufacturing and Distribution 

Licenses, Type “A” Broad, Type “B” Broad, 

Other, and Nuclear Pharmacies

Manufacturing and distribution (M&D) licenses 

are issued to allow the manufacture and 

distribution of radionuclides in various forms for 

a number of diverse purposes. The products 

are usually distributed to organizations/

companies specifically licensed by NRC or 

an Agreement State. Type “A” Broad licenses 

are issued to larger organizations that may 

use many different radionuclides in many 

different ways and that have a comprehensive 

radiation protection program. Some Type “A” 

Broad license firms are medical suppliers 

that process, package, or distribute such 

products as diagnostic test kits, radioactive 

surgical implants, and tagged radiochemicals 

for use in medical research, diagnosis, and 

therapy. Type “B” Broad and Other licenses 

are usually issued to smaller firms requiring 

a more restrictive license. These firms are 

suppliers of industrial radionuclides and are 

involved in the processing, encapsulation, 

packaging, and distribution of the radionuclides 

that they have purchased in bulk quantities 

from production reactors and cyclotrons. 

Major products include gamma radiography 

sources, cobalt irradiation sources, well-logging 

sources, sealed sources for gauges and smoke 

detectors, and radiochemicals for nonmedical 

research. Nuclear pharmacies are involved in 

the compounding and dispensing of radioactive 

materials for use in nuclear medicine 

procedures.

Table 3.5 presents the annual data that were 

reported by the three types of licensees for 

2008 and the previous 2 years. Looking at 

the information shown separately for the Type 
3-9

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 3.1. Average Annual Values for Industrial Radiography Licensees 1973–2008
3-10

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

2008 2007 2006 2005 2004

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

>2.000

98%

90%

67%

40%

4%

>1.000

>0.500

>0.250

>0.100 Dose Range (rem)

95%

86%

67%

28%

5%

0%

0%

0%

45%

57%

0%

0%

0%

41%

41%

0%

0%

0%

0%

0%

FIGURE 3.2. Collective TEDE Distribution by Dose Range

Industrial Radiographer—Fixed Location Licensees

2004–2008

FIGURE 3.3. Collective TEDE Distribution by Dose Range

Industrial Radiographer—Temporary Job Site Licensees

2004–2008

2008 2007 2006 2005 2004

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

>2.000

98%

93%

83%

58%

26%

59%

83%

24%

>1.000

>0.500

>0.250

>0.100

25%

93%

83%

60%

93%

98% 98%

Dose Range (rem)

59%

83%

24%

93%

98%

56%

82%

21%

93%

98%
3-11

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

“A” Broad licensees, it can be seen that the 

average measurable dose generally remains 

higher for the Type “A” Broad licensees. Only 

two Type “A” Broad licensees reported in 2008. 

Figure 3.4 shows the number of workers 

with measurable dose per licensee, the total 

collective dose per licensee, and the average 

measurable dose per worker for Type “A” 

Broad, Type “B” Broad, Other, and Nuclear 

Pharmacy licensees. The number of workers 

with measurable dose per licensee increased 

and the collective TEDE per licensee decreased 

slightly in 2008. The average measurable dose 

decreased by 15% to 0.17 rem. The figures 

for Type “A” Broad licensees are primarily 

attributed to Mallinckrodt, Inc., which accounted 

for 86% of the collective dose, in 2008, for this 

licensee category.

Figure 3.5 shows the collective dose distribution 

by dose range (see Section 3.1.8) for Type 

“A” Broad licensees and Figure 3.6 shows the 

collective dose distribution by dose range for 

Type “B” Broad, Other, and Nuclear Pharmacy 

licensees. These graphs show that, for 2005 

through 2008, the Type "B" Broad, Other, 

and Nuclear Pharmacy manufacturing and 

distribution licensees have more individuals 

receiving dose in the higher dose ranges.

For Type “A” Broad licensees, the decrease 

in values for 2005 through 2008 has been 

due to one licensee decreasing its collective 

TEDE by 45% from the 2007 value and 

accounted for 49% of the collective dose in this 

licensee category in 2008. Appendix A lists the 

contribution that each of these licensees made 

toward the total values of the number of workers 

monitored, number of workers, and collective 

dose for 2008.

.

TABLE 3.5

Annual Exposure Information for Manufacturing and Distribution

2006–2008

Year

Type of 

Manufacturing 

and Distribution

Number of

Licensees

Number of

Monitored

Individuals

Workers with

Measurable

Dose

Collective

Dose

(person-rem)

Average

Measurable

Dose (rem)

Type “A” Broad

Type "B" Broad and Other

Nuclear Pharmacies

Total

Type “A” Broad

Type "B" Broad and Other

Nuclear Pharmacies

Total

Type “A” Broad

Type "B" Broad and Other

Nuclear Pharmacies

Total

2007

2

4

17

23

2

3

18

23

2

4

12

18

501

245

645

1,391

504

83

1,519

2,106

465

205

1,264

1,934

363

161

379

903

352

58

1,053

1,463

312

114

915

1,341

153.846

15.291

115.419

284.556

113.354

5.447

172.525

291.326

95.790

8.421

117.912

222.123

0.42

0.09

0.30

0.32

0.32

0.09

0.16

0.20

0.31

0.07

0.13

0.17

2006

2008
3-12

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

FIGURE 3.4. Average Annual Values for Manufacturing and Distribution Licensees

1973–2008
3-13

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 3.5. Collective TEDE Distribution by Dose Range

Type “A” Broad Manufacturing and Distribution Licensees

2004–2008

FIGURE 3.6. Collective TEDE Distribution by Dose Range

Type "B" Broad, Other, and Nuclear Pharmacy Licensees

2004–2008

2008 2007 2006 2005 2004

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

>2.000

>1.000

>0.500

>0.250

>0.100

Dose Range (rem)

77%

55%

91%

22%

97%

72%

42%

89%

5%

98%

98%

92%

74%

50%

28%

95%

67%

34%

83%

0%

95%

67%

20%

85%

2%

2008 2007 2006 2005 2004

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

>2.000

19%

>1.000

>0.500

>0.250

>0.100

89%

67%

37%

50%

73%

32%

94%

47%

60%

87%

70%

85%

Dose Range (rem)

44%

59%

72%

84%

94%

62%

44%

29%

40%

50%

83%

62%
3-14

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

3.3.3 Low-Level Waste Disposal Licenses

Low-level waste disposal licenses are 

issued to allow the receipt, possession, and 

disposal of low-level radioactive wastes at a 

land disposal facility. The licensee has the 

appropriate facilities to receive wastes from 

such places as hospitals and laboratories, 

store them for a short time, and dispose of 

them in a properly prepared burial ground. The 

licensees in this category are located in and 

licensed by Agreement States, which have 

primary regulatory authority over the licensees’ 

activities. Since 1999, all licensees that have 

conducted these activities have been located in 

Agreement States; therefore, there are no NRC 

low-level waste licensees reporting radiation 

exposure data to REIRS. 

3.3.4 Independent Spent Fuel Storage 

Installation Licenses

Independent spent fuel storage installation 

(ISFSI) licenses are issued to allow the 

possession of power reactor spent fuel and 

other associated radioactive materials for the 

purpose of storage of such fuel in an ISFSI. 

Here, the spent fuel, which has undergone 

at least 1 year of decay since being used 

as a source of energy in a power reactor, 

is provided interim storage, protection, and 

safeguarding for a limited time, pending its 

ultimate disposal. 

The majority of ISFSI facilities are located 

onsite at commercial power reactors. Since 

the doses from these ISFSI facilities are 

usually included with the doses reported by 

the power reactors, the doses from these 

ISFSI facilities are not reported separately 

to NRC. The doses from the two ISFSI 

licensees that are not associated with power 

reactors are reported here for 2008. One is 

the GE Morris facility located in Illinois, and 

the second is the Trojan ISFSI. The Trojan 

nuclear power plant is no longer in commercial 

operation and has been decommissioned. 

However, the ISFSI facility at Trojan remains 

in operation and the occupational dose 

information is reported to NRC under the 

ISFSI license. Appendix A summarizes the 

occupational dose information reported by 

these licensees. 

Figure 3.7 shows the number of workers 

with measurable dose per licensee, the total 

collective dose per licensee, and the average 

measurable dose per worker for ISFSI 

facilities. The large increase in the collective 

dose per licensee and number of workers per 

licensee in 1994 was mainly because only one 

licensee reported separately for 1994 through 

1998, rather than the two licensees that 

reported in prior years. The number of workers 

with measurable dose and collective TEDE 

per licensee have decreased between 2001 

and 2008. Figure 3.8 shows the collective 

dose distribution by dose range (see Section 

3.1.8) for ISFSI licensees from 2004 to 2008. 

In 2008, the percentages were similar to those 

of 2004 and 2007. 
3-15

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 3.7. Average Annual Values for Independent Spent Fuel Storage Installations 1982–2008
3-16

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

FIGURE 3.8. Collective TEDE Distribution by Dose Range

Independent Spent Fuel Storage Installation Licensees

2004–2008

3.3.5 Fuel Cycle Licenses

Fuel cycle licenses are issued to allow the 

processing, enrichment, and fabrication of 

reactor fuels. In most uranium facilities where 

light water reactor (LWR) fuels are fabricated, 

enriched uranium hexafluoride is converted to 

solid uranium dioxide pellets and inserted into 

zirconium alloy tubes. The tubes are fabricated 

into fuel assemblies that are shipped to nuclear 

power plants. Some facilities also perform 

chemical operations to recover the uranium 

from scrap and other off-specification materials 

prior to disposal of these materials. In 1997, the 

regulatory oversight for the uranium enrichment 

facilities at Portsmouth, Ohio and Paducah, 

Kentucky was transferred from DOE to NRC 

and were added to the NRC’s fuel cycle license 

category. In 2005, a third uranium enrichment 

facility, the United States Enrichment 

Corporation (USEC), Inc., was also added to 

this category. 

Figure 3.9 shows the number of workers 

with measurable dose per licensee, the total 

collective dose per licensee, and the average 

measurable dose per worker for fuel cycle 

licensees. In addition to the collective TEDE 

and average measurable dose, the deep dose 

equivalent (DDE) collective dose and DDE 

2008 2007 2006 2005 2004

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

>2.000

>1.000

>0.500

>0.250

>0.100 Dose Range (rem)

70%

0%

72%

21%

82%

21%

68%

0%

0%

0%

0%

0%

0%

29%

21%

0%

0%

0%

0%

0%

0%

0%

0%

0%

63%
3-17

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.6

Annual Exposure Information for Fuel Cycle Licensees

2006–2008

2006 Fuel Cycle 9 7,417 3,413 521.525 0.15 2,475 283 0.11 2,131 238.139 0.112 

 

2007 Fuel Cycle 9 7,536 3,225 428.717 0.13 2,254 230 0.10 1,983 198.914 0.100 

 

2008 Fuel Cycle 9 7,184 2,770 420.899 0.15 1,849 221 0.12 1,786 199.949 0.112

Year

Type of

License

Number

of

Licensees

Number of

Monitored

Individuals

Workers

with

Meas.

TEDE

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

Collective

DDE

(personrem)

Average

Meas.

DDE

(rem)

Collective

CEDE

(personrem)

Average

Meas.

CEDE

(rem)

Workers

with

Meas.

DDE

Workers

with

Meas.

CEDE

average measurable dose are also shown since 

the CEDE is a significant contribution to the 

TEDE for fuel fabrication facilities. 

Figure 3.10 shows the collective dose 

distribution by dose range (see Section 3.1.8) 

for fuel cycle licensees from 2004 to 2008. From 

2004 to 2005, the percentages remained fairly 

constant, and in 2006, there was an increase 

in the dose range above 1.00 rem. Although in 

2007 there was a decrease in all dose ranges, 

in 2008 the dose increased in the dose ranges 

0.100 rem to 0.250 rem and was attributable to 

Westinghouse Electric Co. at the Commercial 

Nuclear Fuel Division in South Carolina. 

As shown in Table 3.6, the collective DDE 

decreased by 4%, while the collective CEDE 

increased by less than 1% in 2008. 

Table 3.6 shows that there were nine licensed 

fuel cycle (fabrication and enrichment) facilities 

reporting in 2008. Appendix A lists each of the 

nine licensees with the number of workers 

monitored, the number of workers receiving 

measurable external doses, and the collective 

dose for each licensee.

3.3.6 Light Water Reactor Licenses

LWR licenses are issued to utilities to allow 

them to use special nuclear material in a reactor 

that produces heat to generate electricity to be 

sold to consumers. There are two major types of 

commercial LWRs in the United States, PWRs 

and BWRs, each of which uses water as the 

primary coolant. 

Table 3.1 shows the number of licensees, 

number of monitored individuals, number of 

workers with measurable dose, total collective 

dose, and average dose per worker for reactor 

facilities that were in commercial operation 

for at least a full year for each of the years 
3-18

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

FIGURE 3.9. Average Annual Values for Fuel Cycle Licensees

1973–2008
3-19

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

2008 2007 2006 2005 2004

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

>2.000

0%

>1.000

>0.500

>0.250

>0.100

86%

64%

65%

15%

44%

42%

9%

Dose Range (rem)

87%

64%

39%

8%

0%

86%

0%

0%

3%

30%

61%

86%

0%

1%

29%

65%

89%

FIGURE 3.10. Collective TEDE Distribution by Dose Range

Fuel Cycle Licensees

2004–2008

1998 through 2008. The values do not include 

reactors that have been permanently shut down 

or reactors that have not been in commercial 

operation for a full year. The figures for reactors 

have been adjusted for the multiple counting of 

transient workers (see Section 5). 

The reported dose distribution of workers 

monitored at each plant site for the year 2008 is 

presented in alphabetical order by plant name in 

Appendix B. 

Figure 3.11 shows the collective dose 

distribution by dose range (see Section 3.1.8) 

for reactor licensees from 2004 to 2008. The 

distribution of collective dose has been fairly 

constant over the past 5 years, with a slight 

decrease noted from 2004 to 2008 in each dose 

range. 

More detailed presentations and analyses of 

the annual dose information reported by nuclear 

power facilities can be found in Sections 4 and 5.

3.3.7 Other Facilities Reporting to NRC

The end of Appendix A contains additional 

facilities that reported occupational radiation 

dose reports to NRC in 2008. These facilities 

are not among the seven categories of 

licensees required to report under 10 CFR 

20.2206 (see Section 3.1.7) and are not 

included in the analysis presented in this report. 

However, these facilities may be of interest to 

researchers, and since they are not included in 

any other published reports, they are included 

here in the interest of completeness. The 

facility with the largest collective dose for these 

additional facilities reported under the category 

of uranium hexafluoride (UF6

) production plants. 
3-20

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

2008 2007 2006 2005 2004

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

>2.000

>1.000

>0.500

>0.250

>0.100 6%

27%

56%

0%

82%

26%

5%

54%

0%

84%

32%

8%

60%

Dose Range (rem)

0%

84%

58%

30%

7%

83%

0%

0%

79%

21%

4%

49%

FIGURE 3.11. Collective TEDE Distribution by Dose Range

Reactor Licensees

2004–2008

3.4 Summary of Intake

Data by LicenseE Category

Licensees are required for each intake to list 

the radionuclide that was taken into the body, 

pulmonary clearance class, intake mode, and 

amount of the intake in microcuries. An NRC 

Form 5 report containing this information is 

required to be completed and submitted to 

NRC under 10 CFR 20.2206. Tables 3.7 and 

3.8 summarize the intake data reported to 

NRC during 2008. The data are categorized 

by licensee type and are listed in order of 

radionuclide and pulmonary clearance class. 

Table 3.7 lists the intakes where the mode of 

intake into the body was recorded as ingestion. 

Table 3.8 lists the intakes where the mode of 

intake was inhalation from ambient airborne 

radioactive material in the workplace. The 

pulmonary clearance class is recorded as F, M, 

S, D, W, or Y (fast, medium, slow, days, weeks, 

or years), corresponding to the clearance 

half-time from the pulmonary region of the 

lung into the blood and gastrointestinal tract. 

The pulmonary clearance class designation 

depends on whether the licensee is using 

10 CFR 20 (D, W, Y) or ICRP 68 (F, M, S) 

nomenclature. [Ref. 12] The amount of material 

taken into the body is given in microcuries, a 

unit of measure of the quantity of radioactive 

material. For each category of licensee, the 

maximum number of intake records and the 

maximum intake are highlighted in the table in 

bold for ease of reference. 
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Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.7

Intake by Licensee Category and Radionuclide Mode of Intake—Ingestion

2008

Licensee Category

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries

Mode (sci. notation)

Ingestion Fuel Fabrication 21210 U-234 1 4.32E-04

 Power Reactors 41111 C-14 1 3.61E-02

 41111 CO-58 5 2.14E-01

 41111 CO-60 4 7.02E-01

 41111 FE-55 1 2.21E-01

 41111 H-3 1 3.36E-03

 41111 MN-54 2 2.06E-01

 41111 NB-95 2 8.01E-01

 41111 NI-63 1 4.46E-02

 41111 RU-103 1 1.58E-01

 41111 ZR-95 1 2.79E+00

NOTE: The data values shown bolded and in boxes represent the highest value in each category.

 * An intake event may involve multiple nuclides, and individuals may incur multiple intakes during the year. The number of intake 

records given here indicates the number of separate intake reports that were submitted on NRC Form 5 reports under

10 CFR 20.2206.

Table 3.9 lists the number of individuals with 

measurable CEDE, the collective CEDE, and 

the average measurable CEDE per individual 

for each licensee category. Fuel fabrication 

facilities have the majority of internal dose 

(97%) in 2008 and the highest average CEDE 

per individual. This is due to the workers’ 

exposure to uranium during the processing and 

fabrication of the uranium fuel.

Table 3.10 shows the distribution of internal 

dose (CEDE) from 1994 to 2008 for licensees 

required to report under 10 CFR 20.2206. For 

the purposes of this table, the definition of a 

“measurable CEDE” is any reported value 

greater than zero. As noted above, the vast 

majority of the internal doses are received by 

individuals working at fuel fabrication facilities. 
3-22

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

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TABLE 3.8

Intake by Licensee Category and Radionuclide Mode of Intake—Inhalation

2008

 Manufacturing 02500 I-123 W 23 2.10E+01

 and Distribution 02500 I-131 D 10 1.24E+00

 02500 I-131 W 100 3.35E+01

 03211 I-131 D 4 1.77E+00

 Uranium Enrichment 21200 NP-237 W 3 2.74E-05

 21200 U-234 D 43 4.43E-02

 Fuel Fabrication 21210 AM-241 M 14 1.68E-04

 21210 CO-60 Y 31 3.91E-01

 21210 MN-54 W 1 4.10E-02

 21210 PU-239 M 14 4.70E-04

 21210 RA-224 M 14 1.99E-04

 21210 SR-90 S 196 5.71E-01

 21210 TH-228 M 103 6.83E-04

 21210 TH-228 S 77 6.49E-04

 21210 TH-232 M 14 3.00E-04

 21210 U-232 F 89 4.36E-04

 21210 U-232 S 105 7.53E-04

 21210 U-232 Y 141 2.06E-04

 21210 U-234 D 358 1.47E-01

 21210 U-234 F 158 3.78E-01

 21210 U-234 M 207 4.04E-02

 21210 U-234 S 885 3.37E+00

 21210 U-234 W 79 1.66E-02

 21210 U-234 Y 1,016 3.40E+00

 21210 U-235 D 133 3.64E-03

 21210 U-235 F 89 1.25E-03

 21210 U-235 M 5 1.49E-05

 21210 U-235 S 478 8.56E-02

 21210 U-235 W 79 6.15E-04

 21210 U-235 Y 263 5.56E-02

 21210 U-236 D 296 2.51E-04

 21210 U-236 F 89 1.89E-02

 21210 U-236 M 5 1.86E-04

 21210 U-236 S 115 3.29E-02

 21210 U-236 W 79 2.53E-05

 21210 U-236 Y 263 2.84E-02

 21210 U-238 D 191 2.16E-02

 21210 U-238 F 6 3.94E-07

 21210 U-238 M 181 1.45E-02

 21210 U-238 S 375 2.94E-01

 21210 U-238 W 79 2.30E-03

 21210 U-238 Y 1,016 5.12E-01

 Power Reactors 41111 AM-241 Y 2 1.68E-04

 41111 CO-58 Y 11 1.03E+00

 41111 CO-60 Y 10 1.50E+00

 41111 CS-137 D 4 5.95E-01

 41111 H-3 W 1 2.40E+05

 41111 I-131 D 202 9.22E+01

 41111 MN-54 W 11 5.77E-01

Licensee Category

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries

(sci. notation)

Pulmonary

Clearance

Class

NOTE: The data values shown bolded and in boxes represent the highest value in each category.

 * An intake event may involve multiple nuclides, and individuals may incur multiple intakes during the year. The number of intake 

records given here indicates the number of separate intake reports that were submitted on NRC Form 5 reports under 10 CFR 

20.2206. 
3-23

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

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TABLE 3.9

Collective and Average CEDE by Licensee Category

2008

 Manufacturing and Distribution 

02500 CARDINAL HEALTH 34-29200-01MD 72 0.831 0.012 

02500 GE HEALTHCARE - ST. LOUIS/OVERLAND 24-32462-01MD 1 0.003 0.003 

02500 GE HEALTHCARE - KENTWOOD 21-26707-01MD 5 0.015 0.003 

02500 IBA MOLECULAR NORTH AMERICA, INC. 45-25221-01MD 7 0.019 0.003 

03211 INTERNATIONAL ISOTOPES IDAHO, INC. 11-27680-01 4 0.044 0.011 

Total 89 0.912 0.010

Uranium Enrichment 

 21200 U. S. ENRICHMENT CORP. - PADUCAH GDP-1 30 0.135 0.005 

Total 30 0.135 0.005 

Fuel Fabrication 

 21210 B&W NUCLEAR OPERATIONS GROUP SNM-0042 196 20.245 0.103 

AREVA NP, INC. SNM-1168 36 1.334 0.037 

AREVA NP, INC. SNM-1227 225 45.374 0.202

NUCLEAR FUEL SERVICES, INC. SNM-0124 336 13.039 0.039 

GLOBAL NUCLEAR FUEL - AMERICAS, LLC SNM-1097 614 57.757 0.094 

WESTINGHOUSE ELECTRIC COMPANY SNM-1107 349 62.065 0.178 

Total 1,756 199.814 0.114

Power Reactors 

 41111 ARKANSAS DPR-51 4 0.033 0.008 

MILLSTONE NPF-49 1 0.008 0.008 

SEQUOYAH DPR-77 2 0.002 0.001 

NINE MILE POINT DPR-63 3 0.037 0.012 

VERMONT YANKEE DPR-28 1 0.025 0.025 

HUMBOLDT BAY DPR-07 2 0.054 0.027 

MONTICELLO DPR-22 1 0.002 0.002 

PALO VERDE NPF-41 201 3.069 0.015 

WOLF CREEK NPF-42 8 0.010 0.001 

RIVER BEND NPF-47 8 0.304 0.038 

DIABLO CANYON DPR-80 2 0.049 0.025 

BROWNS FERRY DPR-33 25 0.858 0.034 

SAN ONOFRE DPR-13 2 0.043 0.022 

BRAIDWOOD NPF-72 1 0.015 0.015 

COMANCHE PEAK NPF-87 3 0.059 0.020 

LIMERICK NPF-39 1 0.014 0.014 

SOUTH TEXAS NPF-76 2 0.018 0.009 

CALLAWAY NPF-30 3 0.014 0.005 

Total 270 4.614 0.017

Grand Totals 2,145 205.475 0.096

Licensee Category Licensee Name License Number

Number

with Meas.

CEDE

Collective

CEDE

(person-rem)

Average

Meas. CEDE

(rem)

NOTE: The data values shown bolded and in boxes represent the highest value in each category.
3-24

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

TABLE 3.10

Internal Dose (CEDE) Distribution

1994–2008

Year

Meas.

0.020

Total with

Meas.

CEDE

Collective

CEDE

(personrem)

Average

Meas.

CEDE

(rem)

0.020–

0.100

0.100–

0.250

0.250 –

0.500

0.500–

0.750

0.750–

1.000 1– 2 2–3 3–4 4 – 5

Number of Individuals with CEDE in the Ranges (rem)*

1994 3,425 577 287 351 196 138 293 69 2 - 5,338 1,033.688 0.194

1995 2,868 691 338 362 216 145 288 49 2 - 4,959 1,019.045 0.205

1996 3,096 598 305 317 190 121 185 22 2 2 4,838 741.373 0.153

1997 3,835 869 381 366 242 148 169 30 - - 6,040 826.280 0.137

1998 3,310 932 426 355 230 140 153 21 2 - 5,569 779.148 0.140

1999 3,399 630 402 425 206 117 173 29 - - 5,381 792.586 0.147

2000 3,248 891 514 373 214 98 224 58 7 1 5,628 969.792 0.172

2001 1,767 766 572 277 109 51 146 82 15 1 3,786 810.128 0.214

2002 1,759 739 555 370 95 20 23 3 - - 3,564 377.016 0.106

2003 2,208 727 572 271 98 13 4 - - - 3,893 311.641 0.080

2004 1,987 738 440 252 90 14 3 - - - 3,524 274.606 0.078

2005 1,204 633 432 223 89 25 2 - - - 2,608 263.857 0.101

2006 1,294 583 383 245 80 13 3 - - - 2,601 245.743 0.094

2007 1,418 524 415 228 38 1 3 - - - 2,627 207.121 0.079

2008 900 547 411 254 29 3 1 - - - 2,145 205.475 0.096

 * Dose values exactly equal to the values separating ranges are reported in the next higher range.
4-1

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

commercial light water 

reactors – FURTHER ANALYSIS

Section 4

4.1 Introduction

General trends in occupational radiation 

exposures at nuclear power reactors are best 

evaluated within the context of other pertinent 

information. In this Section, some of the tables 

and appendices that summarize dose data also 

show the type, capacity, amount of electricity 

generated, and age of the reactor. Dose data 

are then presented as a function of these data. 

4.2 DEFINITION OF TERMS

AND SOURCES OF DATA

4.2.1 Number of Reactors

The number of reactors shown in Tables 4.1, 

4.2, and 4.3 is the number of BWRs, PWRs, 

and LWRs, respectively, that had been in 

commercial operation for at least 1 full year as 

of December 31 of each of the indicated years. 

This is the number of reactors in which the 

average number of workers with measurable 

dose and average collective dose per reactor is 

based. Excluded are reactors that have been in 

commercial operation for less than 12 months 

during the first year and reactors that have been 

permanently defueled. This technique yields 

conservative values for many of the averages 

shown in the tables. The date that each reactor 

was declared to be in commercial operation was 

taken from Ref. 13. 

Three Mile Island (TMI) 2 was included in the 

compilation of data for commercially operating 

reactors from 1975 through 1988 and has not 

been included in the data analysis since 1988. 

TMI 1 and 2 reported data separately beginning 

in 1986. 

Browns Ferry Unit 1 (BWR) was restarted in 

2007 and was in commercial power production 

operation during 2008. From 1985 to 2007, 

Browns Ferry Unit 1 was on administrative 

hold, and although not producing electric 

power, it remained in the count of operating 

reactors. Therefore, its return to commercial 

power production does not officially change the 

number of operating BWRs in 2008. 

There were no changes to the count of 

operating reactors in 2008. The number of 

operating BWRs remains the same as in 2007 

at 35, and the number of operating PWRs 

remains the same at 69. The dose information 

for these reactors and for others that are no 

longer in commercial operation is listed at the 

end of Appendix B. 

4.2.2 Electric Energy Generated

The electric energy generated in megawatt 

years (MW-yr) each year by each reactor is 

graphically represented in Appendix D. This 

number was obtained by dividing the megawatt 

hours of electricity annually produced by each 

facility by 8,760, the number of hours in the 

year, except for leap years, when the number 

is 8,784 hours. The number of megawatt hours 

of electricity produced each year was obtained 

from Ref. 13. For the years 1973 to 1996, the 

electricity generated is the gross electricity 

output of the reactor. For 1997 to 2008, the 

number reflects the net electricity produced, 

which is the gross electricity minus the amount 

the plant uses for operations. This change is 

the result of a change in NRC power generation 

reporting requirements. The electricity 

generated (in MW-yr) that is presented in Tables 

4.1, 4.2, and 4.3 is the summation of electricity 
4-2

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713 TABLE 4.1 Summary of Information Reported by Commercial Boiling Water Reactors 1973–2008 Average Average No. Average Annual No. of Average Collective Personnel Collective Average Average 

 Number Collective Workers Measurable Dose per with Dose Electricity Maximum Maximum

of Dose with Electricity Dose per Reactor Measurable per MW-yr Generated Dependable Dependable

 Reactors (person- Measurable Generated*** Worker (person- Doses (person-rem/ per Reactor Capacity Capacity

Year Included* rem) Dose** (MW-yr) (rem)** rem) per Reactor** MW-yr) (MW-yr) Net (MWe) Achieved

1973 12 4,564 5,340 3,393.9 0.86 380 445 1.35 283 438 65%1974 14 7,095 8,769 4,060.2 0.81 507 626 1.75 290 485 60%1975 18 12,633 17,350 5,786.4 0.73 702 964 2.18 321 595 54%1976 22 12,298 16,927 8,137.9 0.73 559 769 1.51 370 630 59%1977 23 19,054 21,515 9,102.5 0.89 828 935 2.09 396 637 62%1978 25 15,257 20,381 11,856.0 0.75 610 815 1.29 474 660 72%1979 25 18,251 25,425 11,671.0 0.72 730 1,017 1.56 467 660 71%1980 26 29,472 34,220 10,868.2 0.86 1,134 1,316 2.71 418 663 63%1981 26 25,490 34,873 10,899.2 0.73 980 1,341 2.34 419 663 63%1982 26 24,447 32,318 10,614.6 0.76 940 1,243 2.30 408 663 62%1983 26 27,467 33,581 9,730.1 0.82 1,056 1,292 2.82 374 663 56%1984 27 27,111 41,315 10,019.2 0.66 1,004 1,530 2.71 371 754 49%1985 29 20,578 38,336 12,284.0 0.54 710 1,322 1.68 424 775 55%1986 30 19,353 37,999 12,102.1 0.51 645 1,267 1.60 403 786 51%1987 32 16,722 41,806 15,109.0 0.40 523 1,306 1.11 472 832 57%1988 34 17,986 40,371 16,665.4 0.45 529 1,187 1.08 490 845 58%1989 36 15,550 44,384 17,543.5 0.35 432 1,233 0.89 487 857 57%1990 37 15,781 41,585 21,336.1 0.38 427 1,124 0.74 577 862 67%1991 37 12,007 38,508 21,505.8 0.31 325 1,041 0.56 581 860 68%1992 37 13,312 42,107 20,592.2 0.32 360 1,138 0.65 557 859 65%1993 37 12,221 39,352 21,995.6 0.31 330 1,064 0.56 594 798 74%1994 37 12,098 39,171 22,139.0 0.31 327 1,059 0.55 598 801 75%1995 37 9,471 35,686 24,737.0 0.27 256 964 0.38 669 835 80%1996 37 9,466 37,792 24,322.2 0.25 256 1,021 0.39 657 838 78%1997 37 7,603 34,021 22,866.1 0.22 205 919 0.33 618 845 73%1998 36 6,829.296 32,899 23,781.2 0.21 190 914 0.29 661 874 76%1999 35 6,434.430 31,482 26,962.6 0.20 184 899 0.24 770 885 87%2000 35 6,089.676 31,186 28,476.9 0.20 174 891 0.21 814 893 91%2001 35 4,835.397 28,797 28,730.4 0.17 138 823 0.17 821 895 92%2002 35 6,107.767 30,978 29,460.0 0.20 175 885 0.21 842 907 93%2003 35 5,659.434 30,759 29,094.4 0.18 162 879 0.19 831 912 91%2004 35 5,450.982 33,948 29,424.8 0.16 156 970 0.19 841 893 94%2005 35 5,995.975 33,544 29,386.8 0.18 171 958 0.20 840 946 89%2006 35 4,989.761 34,159 30,238.4 0.15 143 976 0.17 864 954 91%2007 35 5,388.416 37,515 30,189.3 0.14 154 1,072 0.18 863 955 90%2008 35 4,522.413 34,642 31,248.3 0.13 129 990 0.14 893 957 93%

 * Includes only those reactors that had been in commercial operation for at least one full year as of December 31 of each of the indicated years. ** Figures are not adjusted for the multiple reporting of transient individuals (see section 5). *** Electricity generated reflects the gross electricity generated for the years 1973–1996. Beginning in 1997, it reflects the net electricity generated.
4-3

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

 Average Average No. Average

Annual No. of Average Collective Personnel Collective Average Average 

 Number Collective Workers Measurable Dose per with Dose Electricity Maximum Maximum

of Dose with Electricity Dose per Reactor Measurable per MW-yr Generated Dependable Dependable

 Reactors (person- Measurable Generated*** Worker (person- Doses (person-rem/ per Reactor Capacity Capacity

Year Included* rem) Dose** (MW-yr) (rem)** rem) Per Reactor** MW-yr) (MW-yr) Net (MWe) Achieved

1973 12 9,398 9,440 3,770.2 1.00 783 787 2.49 314 544 58%1974 19 6,555 9,370 6,530.7 0.70 345 493 1.00 344 591 58%1975 26 8,268 10,884 11,982.5 0.76 318 419 0.69 461 647 71%1976 30 13,807 17,588 13,325.0 0.79 460 586 1.04 444 701 63%1977 34 13,467 20,878 17,345.8 0.65 396 614 0.78 510 688 74%1978 39 16,528 25,700 19,840.5 0.64 424 659 0.83 509 706 72%1979 42 21,657 38,828 18,255.0 0.56 516 924 1.19 435 746 58%1980 42 24,267 46,237 18,289.3 0.53 578 1,101 1.33 435 746 58%1981 44 28,673 47,351 20,553.7 0.61 652 1,076 1.40 467 752 62%1982 48 27,754 52,149 22,140.6 0.53 578 1,086 1.25 461 777 59%1983 49 29,017 52,170 23,195.5 0.56 592 1,065 1.25 473 785 60%1984 51 28,140 56,994 26,478.4 0.49 552 1,118 1.06 519 809 64%1985 53 22,470 54,632 29,470.7 0.41 424 1,031 0.76 556 820 68%1986 60 23,033 62,998 33,593.0 0.37 384 1,050 0.69 560 878 64%1987 64 23,684 62,597 37,007.3 0.38 370 978 0.64 578 900 64%1988 68 22,786 62,923 42,929.7 0.36 335 925 0.53 631 885 71%1989 71 20,381 63,894 44,679.5 0.32 287 900 0.46 629 897 70%1990 73 20,821 67,082 46,955.6 0.31 285 919 0.44 643 907 71%1991 74 16,512 60,274 51,942.6 0.27 223 815 0.32 702 913 77%1992 73 15,985 61,048 53,419.8 0.26 219 836 0.30 732 923 79%1993 69 13,376 54,397 48,709.3 0.25 194 788 0.28 706 941 75%1994 70 9,574 44,283 52,397.6 0.22 137 633 0.18 749 928 81%1995 70 11,762 49,985 54,138.2 0.24 168 714 0.22 773 929 83%

1996 72 9,417 46,852 55,337.8 0.20 131 651 0.17 769 935 82%1997 72 9,546 50,690 48,985.3 0.19 133 704 0.20 680 943 72%1998 69 6,358.096 38,586 53,288.7 0.17 92 559 0.12 772 942 82%1999 69 7,231.281 43,938 56,235.0 0.17 105 637 0.13 815 942 86%2000 69 6,562.006 42,922 57,529.9 0.15 95 622 0.11 834 943 88%2001 69 6,273.155 38,773 58,822.4 0.16 91 562 0.11 852 946 90%2002 69 6,018.423 42,264 59,369.7 0.14 87 613 0.10 860 947 91%2003 69 6,296.136 44,054 57,920.6 0.14 91 638 0.11 839 949 88%2004 69 4,916.915 35,901 60,398.7 0.14 71 520 0.08 875 943 93%2005 69 5,459.832 44,583 59,790.9 0.12 79 646 0.09 867 955 91%2006 69 6,031.425 46,106 59,751.3 0.13 87 668 0.10 866 960 90%2007 69 4,731.597 42,015 61,955.6 0.11 69 609 0.08 898 961 93%2008 69 4,673.527 44,808 60,586.0 0.10 68 649 0.08 878 964 91%

 * Includes only those reactors that had been in commercial operation for at least one full year as of December 31 of each of the indicated years. ** Figures are not adjusted for the multiple reporting of transient individuals (see section 5). *** Electricity generated reflects the gross electricity generated for the years 1973–1996. Beginning in 1997, it reflects the net electricity generated.

TABLE 4.2

Summary of Information Reported by Commercial Pressurized Water Reactors

1973–2008
4-4

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

1973 24 13,962 14,780 7,164.1 0.95 582 616 1.95 299 491 61%1974 33 13,650 18,139 10,590.9 0.75 414 550 1.29 321 546 59%1975 44 20,901 28,234 17,768.9 0.74 475 642 1.18 404 626 65%1976 52 26,105 34,515 21,462.9 0.76 502 664 1.22 413 671 62%1977 57 32,521 42,393 26,448.3 0.77 571 744 1.23 464 667 70%1978 64 31,785 46,081 31,696.5 0.69 497 720 1.00 495 688 72%1979 67 39,908 64,253 29,926.0 0.62 596 959 1.33 447 714 63%1980 68 53,739 80,457 29,157.5 0.67 790 1,183 1.84 429 714 60%1981 70 54,163 82,224 31,452.9 0.66 774 1,175 1.72 449 719 63%1982 74 52,201 84,467 32,755.2 0.62 705 1,141 1.59 443 737 60%1983 75 56,484 85,751 32,925.6 0.66 753 1,143 1.72 439 743 59%1984 78 55,251 98,309 36,497.6 0.56 708 1,260 1.51 468 790 59%1985 82 43,048 92,968 41,754.7 0.46 525 1,134 1.03 509 804 63%1986 90 42,386 100,997 45,695.1 0.42 471 1,122 0.93 508 847 60%1987 96 40,406 104,403 52,116.3 0.39 421 1,088 0.78 543 877 62%1988 102 40,772 103,294 59,595.1 0.40 400 1,013 0.68 584 871 67%1989 107 35,931 108,278 62,223.0 0.33 336 1,012 0.58 582 883 66%1990 110 36,602 108,667 68,291.7 0.34 333 988 0.54 621 892 70%1991 111 28,519 98,782 73,448.4 0.29 257 890 0.39 662 895 74%1992 110 29,297 103,155 74,012.0 0.28 266 938 0.40 673 901 75%1993 106 25,597 93,749 70,704.9 0.27 241 884 0.36 667 891 75%1994 107 21,672 83,454 74,536.6 0.26 203 780 0.29 697 884 79%1995 107 21,233 85,671 78,875.2 0.25 198 801 0.27 737 896 82%1996 109 18,883 84,644 79,660.0 0.22 173 777 0.24 731 902 81%1997 109 17,149 84,711 71,851.4 0.20 157 777 0.24 659 910 72%1998 105 13,187.392 71,485 77,069.9 0.18 126 681 0.17 734 918 80%1999 104 13,665.711 75,420 83,197.6 0.18 131 725 0.16 800 923 87%2000 104 12,651.682 74,108 86,006.8 0.17 122 713 0.15 827 926 89%2001 104 11,108.552 67,570 87,552.8 0.16 107 650 0.13 842 929 91%2002 104 12,126.190 73,242 88,829.7 0.17 117 704 0.14 854 934 91%2003 104 11,955.570 74,813 87,015.0 0.16 115 719 0.14 837 936 89%2004 104 10,367.897 69,849 89,823.5 0.15 100 672 0.12 864 926 93%2005 104 11,455.807 78,127 89,177.7 0.15 110 751 0.13 857 952 90%2006 104 11,021.186 80,265 89,989.7 0.14 106 772 0.12 865 958 90%2007 104 10,120.013 79,530 92,144.9 0.13 97 765 0.11 886 959 92%2008 104 9,195.940 79,450 91,834.3 0.12 88 764 0.10 883 961 92%

 Average Average No. Average

Annual No. of Average Collective Personnel Collective Average Average 

 Number Collective Workers Measurable Dose per with Dose Electricity Maximum Maximum

of Dose with Electricity Dose per Reactor Measurable per MW-yr Generated Dependable Dependable

 Reactors (person- Measurable Generated*** Worker (person- Doses (person-rem/ per Reactor Capacity Capacity

Year Included* rem) Dose** (MW-yr) (rem)** rem) Per Reactor** MW-yr) (MW-yr) Net (MWe) Achieved

 * Includes only those reactors that had been in commercial operation for at least one full year as of December 31 of each of the indicated years. ** Figures are not adjusted for the multiple reporting of transient individuals (see section 5). *** Electricity generated reflects the gross electricity generated for the years 1973–1996. Beginning in 1997, it reflects the net electricity generated.

TABLE 4.3

Summary of Information Reported by Commercial Light Water Reactors

1973–2008
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generated by the number of reactors included 

in each year. These sums are divided by the 

number of operating reactors included in each 

year to yield the average amount of electric 

energy generated per reactor, which is also 

shown in Tables 4.1, 4.2, and 4.3. 

As shown in Table 4.3, there was a less than 

0.3% decrease in the net electricity generated 

at LWRs in 2008. Contributors to this decrease 

included North Anna and Cook for PWRs and 

Fermi 2 for BWRs. These plants experienced 

the largest decreases in power production 

(in MW-yr) from 2007 to 2008. The return 

of Browns Ferry Unit 1 to power production 

in 2007 contributed significantly to the 4% 

increase in the electricity generated from BWRs 

in 2008. 

4.2.3 Collective Dose per Megawatt-Year 

The number of MW-yr of electricity generated 

was used in determining the ratio of the average 

value of the annual collective dose (TEDE) to 

the number of MW-yr of electricity generated. 

The ratio was calculated by dividing the total 

collective dose in person-rem by the electric 

energy generated in MW-yr and is a measure of 

the dose incurred by workers at power plants in 

relation to the electric energy produced. For the 

years 1973 to 1996, the electricity generated 

is the gross electricity output of the reactor. 

For 1997 to 2008, the number reflects the net 

electricity produced. This ratio, calculated by 

year for BWRs, PWRs, and LWRs is presented 

in Tables 4.1, 4.2, and 4.3. This ratio was also 

calculated for each reactor site (see Appendix 

C). The average collective dose per MW-yr for 

LWRs decreased to a value of 0.10 rem/MW-yr 

in 2008 from a value of 0.11 rem/MW-yr in 2007 

due to a combination of a 9% decrease in the 

collective dose and a 0.3% decrease in power 

production.

4.2.4 Average Maximum Dependable 

Capacity 

Average maximum dependable capacity 

as shown in Tables 4.1, 4.2, and 4.3 was 

calculated by dividing the sum of the net 

maximum dependable capacities of the reactors 

in megawatts (net MWe) by the number of 

reactors included each year. The net maximum 

dependable capacity is defined as the gross 

electrical output as measured at the output 

terminals of the turbine generator during the 

most restrictive seasonal conditions less the 

normal station service loads. This “capacity” of 

each plant was found in Ref. 13. 

4.2.5 Percent of Maximum Dependable 

Capacity Achieved 

The percent of maximum dependable capacity 

achieved is shown for all LWRs in Table 4.3. 

This parameter gives an indication of the 

overall power generation performance of LWRs 

as compared with the maximum dependable 

capacity that could be obtained in a given year. 

It is calculated by dividing the average electricity 

generated per reactor by the average maximum 

dependable capacity for each year. 

From 1973 to 1978, this indicator exhibited 

an increasing trend as a number of new 

reactors began producing power at higher 

efficiencies. Following the accident at TMI, 

reactor operations personnel concentrated on 

improving safety systems and complying with 
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the new regulations for these systems. During 

this time period, from 1979 to 1987, the percent 

of maximum dependable capacity remained 

around 61%. Following the completion of most 

of these mandated repairs, reactors increased 

the percent of maximum dependable capacity 

from 62% in 1987 to 81% in 1996, a gain 

of nearly 20% in 10 years. The decrease in 

maximum dependable capacity from 1996 to 

1997 was due to the change from measuring 

the gross electricity generated to the net 

electricity generated. The percent of maximum 

dependable capacity for LWRs remained the 

same at 92% in 2008. 

4.3 Annual TEDE

Distributions

Table 4.4 summarizes the distribution of the 

annual TEDE doses received by workers at 

all commercial LWRs during each of the years 

1977 through 2008. This distribution is the sum 

of the annual dose distributions reported by 

each licensed LWR each year. As previously 

noted, the distribution reported by each LWR 

site for 2008 is shown in Appendix B. Table 4.4 

shows the reported dose distributions corrected 

for the number of transient workers that were 

reported by more than one site (see Section 5). 

Table 4.4 includes only those reactors in 

operation for a full year for each year presented 

in the table. In 2008, the total collective dose 

decreased by 9% to a value of 9,196 personrem. The PWR with the largest decrease in 

the collective dose was Ft. Calhoun. TMI1 

experienced the highest increase in collective 

dose among PWRs. The BWR with the largest 

decrease in the collective dose was Cooper 

Station. Pilgrim experienced the highest 

increase in collective dose among BWRs.

4.4 Average Annual

TEDE Doses

Some of the data presented in Tables 4.1, 4.2, 

and 4.3 are graphically displayed in Figure 4.1, 

where it can be seen that the average collective 

dose and average number of workers per BWR 

have been higher than those for PWRs since 

1974 and that the values of both parameters, 

in general, continued to rise at both types of 

facilities until 1983. Between 1983 and 2008, 

the annual collective dose per LWR dropped by 

84%. Between 2007 and 2008, the collective 

dose per reactor for PWRs decreased by 1% to 

68 person-rem. The collective dose per reactor 

for BWRs decreased by 16% to 129 personrem from 2007 to 2008. The overall collective 

dose per reactor for LWRs decreased by 9% 

from 97 person-rem in 2007 to 88 personrem in 2008. This is the second year that this 

value has been below 100 person-rem since 

tracking began in 1973. The overall decreasing 

trend in average reactor collective doses since 

1983 indicates that licensees are continuing to 

successfully implement ALARA dose reduction 

processes at their facilities. In 2008 the number 

of workers with measurable dose per reactor 

increased to 649 for PWRs and decreased to 

990 for BWRs. 

Figures 4.2 and 4.3 are plots of most of the 

other information that is given in Tables 4.1, 

4.2, and 4.3. Figure 4.2 shows that in 2008 the 

net electricity generated decreased slightly to 

91,834 MW-yr while the number of operating 
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TABLE 4.4

Summary Distribution of Annual Whole-Body Doses at Commercial Light Water Reactors*

1977–2008

1977 22,688 12,436 6,056 4,538 2,905 2,230 5,660 2,858 1,290 661 186 89 47 23 6 - - 61,673 38,985 32,5211978 26,360 15,165 6,349 5,010 3,094 2,255 5,984 3,050 1,194 517 110 37 9 - 1 - 2 69,137 42,777 31,7851979 40,535 22,642 9,012 7,485 4,795 3,262 7,574 3,401 1,403 545 117 42 17 3 1 - - 100,834 60,299 39,9081980 44,716 26,990 10,697 8,913 5,573 4,139 10,672 4,607 1,816 831 235 119 29 7 1 - - 119,345 74,629 53,7391981 39,258 26,916 11,241 9,338 6,051 4,501 11,174 4,809 1,999 533 103 93 9 3 1 - 1 116,030 76,772 54,1631982 41,704 29,278 11,734 9,907 6,235 4,422 10,220 4,716 2,066 596 97 31 5 - 1 1 - 121,013 79,309 52,2011983 47,027 29,200 11,200 9,345 5,854 4,279 11,342 5,334 2,270 716 121 38 8 2 - - - 126,736 79,709 56,4841984 54,637 36,488 13,438 10,277 6,338 4,804 11,284 5,208 2,122 487 52 22 - - - - - 145,157 90,520 55,2511985 59,625 36,920 13,015 11,044 6,626 4,545 10,042 3,574 1,002 157 1 - - - - - - 146,551 86,926 43,0481986 67,677 41,536 14,574 11,842 7,017 4,693 10,241 3,062 868 146 - - - - - - - 161,656 93,979 42,3861987 85,170 41,283 15,842 12,838 7,586 5,333 10,611 2,192 477 69 - - - - - - - 181,401 96,231 40,4061988 87,281 40,290 15,915 13,152 7,905 5,461 10,310 2,442 511 26 - 1 - - - - - 183,294 96,013 40,7721989 83,954 45,302 17,270 13,778 7,944 5,138 8,633 1,615 370 34 - - - - - - - 184,038 100,084 35,9311990 83,875 42,612 17,526 14,199 8,226 5,261 8,594 1,791 337 21 - - - - - - - 182,442 98,567 36,6021991 87,247 42,603 16,770 13,182 7,188 4,192 5,977 938 219 17 - - - - - - - 178,333 91,086 28,5191992 87,717 41,943 17,821 14,779 8,135 4,521 6,076 808 85 4 - - - - - - - 181,889 94,172 29,2971993 83,066 37,332 17,235 13,734 7,562 4,289 5,322 638 76 5 - - - - - - - 169,259 86,193 26,3641994 67,777 30,185 15,010 11,823 6,185 3,620 4,242 508 40 - - - - - - - - 139,390 71,613 21,7041995 61,445 29,631 15,096 12,023 6,125 3,304 3,912 595 133 2 - - - - - - - 132,266 70,821 21,6881996 58,097 30,204 14,831 11,343 5,423 2,833 3,196 408 67 - - - - - - - - 126,402 68,305 18,8831997 58,409 31,955 14,890 10,913 5,233 2,455 2,599 286 41 - - - - - - - - 126,781 68,372 17,1491998 56,901 27,998 12,849 8,816 3,940 1,841 1,827 179 15 1 - - - - - - - 114,367 57,466 13,187.3921999 54,885 29,048 13,184 8,949 3,793 1,900 1,894 245 18 - - - - - - - - 113,916 59,031 13,665.7112000 53,324 28,480 12,921 8,679 3,571 1,644 1,734 186 18 - - - - - - - - 110,557 57,233 12,651.6822001 52,636 27,246 11,491 7,659 2,907 1,323 1,392 221 53 - - - - - - - - 104,928 52,292 11,108.5522002 53,440 28,523 11,610 7,668 3,004 1,479 1,820 320 35 1 - - - - - - - 107,900 54,460 12,126.1902003 54,023 29,164 11,978 8,199 3,249 1,524 1,651 184 18 - - - - - - - - 109,990 55,967 11,955.5702004 57,417 28,863 11,179 7,334 2,873 1,233 1,190 188 13 - - - - - - - - 110,290 52,873 10,367.8972005 56,778 31,043 12,427 7,815 3,104 1,537 1,490 147 3 - - - - - - - - 114,344 57,566 11,455.8072006 57,566 32,426 12,685 7,796 2,975 1,416 1,406 82 2 - - - - - - - - 116,354 58,788 11,021.1862007 57,316 32,706 11,961 7,396 2,714 1,283 1,101 97 9 - - - - - - - - 114,583 57,267 10,120.0132008 61,336 33,832 12,324 6,786 2,429 1,026 921 38 - - - - - - - - - 118,692 57,356 9,195.940

Number of Individuals with Whole-Body Doses in the Ranges (rem)** Number 

No Total with Collective

 Measurable Measurable 0.10– 0.25– 0.50– 0.75– 1.0– 2.0– 3.0– 4.0– 5.0– 6.0– 7.0– 8.0– 9.0– 10.0– Number Measurable DoseYear Exposure <0.10 0.25 0.5 0.75 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 12.0 >12 Monitored Exposure (person-rem)

 * Summary of reports submitted in accordance with 10 CFR 20.407 or 20.2206 by BWRs and PWRs that had been in commercial operation for at least 1 full year as of December 31 of each of the indicated 

years. Figures shown have been adjusted for the multiple reporting of transient individuals (see section 5).

 ** Dose values exactly equal to the values separating ranges are reported in the next higher range. *** The collective dose, when not reported by the licensee, was calculated by the NRC staff using methods described in section 3.1.4.

***
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reactors has remained constant for the past 10 

years. Figure 4.3 shows that the value for the 

total collective dose for all LWRs decreased 

by 9% from a value of 10,120 person-rem in 

2007 to 9,196 person-rem in 2008. The average 

measurable dose per worker also decreased 

to 0.12 rem in 2008 (not adjusted for transient 

workers). 

The fluctuations in the parameters for the 

years following the accident at the TMI plant in 

1979 may reflect some of the impact that this 

incident had on the nuclear power industry. 

The decrease seen in dose trends since 1983 

may be attributable to several factors. Utilities 

have completed the tasks initiated as a result 

of the lessons learned from the TMI accident, 

and they are increasing efforts to avoid and 

reduce exposure. The importance of exposure 

control and the concept of keeping exposures 

to ALARA levels are continually being stressed, 

and most utilities have established programs to 

collect and share information relative to tasks, 

techniques, and exposures.

To further assist in the identification of any 

trends that might exist, Figures 4.4 and 4.5 

together display the average and median7

 

values of the collective dose per reactor for 

BWRs and for PWRs for the years 1973 

through 2008. The ranges of the values 

reported each year are shown by the vertical 

lines with a small bar at each end marking the 

two extreme values. The rectangles indicate the 

range of values of the collective dose exhibited 

by those plants ranked in the 25th through the 

75th percentiles. The median collective dose for 

PWRs increased from 60 person-rem in 2007 to 

63 person-rem in 2008. The median collective 

dose for BWRs decreased from 145 personrem in 2007 to 109 person-rem in 2008. Figure 

4.5 also shows that, in 2008, 50% of the PWRs 

reported collective doses between 43 and 84 

person-rem, while 50% of the BWRs reported 

collective doses between 95 and 168 personrem. (Note that these values are based on an 

annual average, not the 3-year rolling average 

that is presented in Section 4.5.) Nearly every 

year the median collective dose is less than 

the average, which indicates that the collective 

dose for most plants is less than the average 

collective dose per reactor (the value that is 

widely quoted).

7

The median is the value at which 50% of the reactors reported greater collective doses and the other 50% reported smaller collective 

doses.
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4.5 Three-year average

collective tede per 

reactor

The 3-year average collective dose per reactor 

is one of the metrics that the NRC uses in the 

Reactor Oversight Program to evaluate the 

effectiveness of the licensee’s ALARA program. 

Tables 4.5 and 4.6 list the sites that had been 

in commercial operation for at least 3 years as 

of December 31, 2008, and show the values of 

several parameters for each of the sites. These 

tables also give averages for the two types of 

reactors. 

Based on the 105 reactor-years of operation 

accumulated over a three-year period by the 

35 BWRs listed, the average 3-year collective 

TEDE per reactor was found to be 142 personrem, the average measurable TEDE per worker 

was 0.14 rem, and the average collective 

TEDE per MW-yr was 0.16 person-rem per 

MW-yr. All values decreased slightly from 2007 

to 2008. 

Based on the 207 reactor-years of operation 

accumulated over a three-year period at the 

69 PWRs listed, the average annual collective 

TEDE per reactor, average measurable TEDE 

per worker, and average collective TEDE 

per MW-yr were found to be 75 person-rem, 

0.12 rem, and 0.08 person-rem per MW-yr, 

respectively. For PWRs from 2007 to 2008, all 

values either decreased slightly or remained 

the same. 

In addition to the listings provided in Tables 

4.5 and 4.6, considerable attention is paid to 

the quartile ranking of reactors for the 3-year 

average dose per reactor. The quartile ranking 

is used by the NRC as a factor in planning 

the number of inspection hours assigned 

per reactor. For this reason, Tables 4.7 and 

4.8 have been included in the 2008 annual 

report. These tables show the plant name, 

3-year collective TEDE per reactor, the percent 

change in the 3-year average from the previous 

3-year period, and the quartile ranking from the 

previous period if the ranking has changed.
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FIGURE 4.1. Average Collective Dose and Number of Workers

with Measurable Dose per Reactor

1973–2008
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FIGURE 4.2. Number of Operating Reactors and Electricity Generated

1973–2008

* Gross electricity is shown for 1973–1996, net electricity is shown for 1997–2008.
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FIGURE 4.3. Average Measurable Dose per Worker and Collective Dose per Megawatt-Year

1973–2008

* Not adjusted for transient workers. See Section 5.

** Gross electricity is shown for 1973–1996, net electricity is shown for 1997–2008.
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FIGURE 4.4. Average, Median, and Extreme Values of the Collective Dose per Reactor

1973–1991

Middle 50% of BWRs

Middle 50% of PWRs

Average Collective Dose

M Median Collective Dose

A
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FIGURE 4.5. Average, Median, and Extreme Values of the Collective Dose per Reactor

1992–2008

1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008

84

43

168

95

Middle 50% of BWRs

Middle 50% of PWRs

Average Collective Dose

M Median Collective Dose

A
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TABLE 4.5

Three-Year Totals and Averages Listed in Ascending Order of Collective TEDE per BWR

2006–2008

 3 79.063 237.188 1,592 0.15 1,698.9 0.14 

 3 89.530 269.591 1,699 0.16 1,613.0 0.17 

 6 94.560 567.358 4,472 0.13 6,562.2 0.09 

 6 97.670 586.019 4,143 0.14 4,815.4 0.12 

 3 102.208 306.625 2,438 0.13 1,918.0 0.16 

 6 106.802 640.814 6,071 0.11 6,303.7 0.10 

 6 115.732 694.394 6,361 0.11 6,493.8 0.11 

 3 119.716 359.148 5,355 0.07 3,052.2 0.12 

 6 127.170 763.017 6,659 0.11 4,945.8 0.15 

 3 135.226 405.678 4,609 0.09 3,376.3 0.12 

 3 136.842 410.525 3,374 0.12 2,900.6 0.14 

 3 139.072 417.217 3,485 0.12 3,045.8 0.14 

 6 140.869 845.212 5,235 0.16 6,448.2 0.13 

 6 143.447 860.682 4,347 0.20 4,887.5 0.18 

 3 144.806 434.417 2,973 0.15 1,677.2 0.26 

 3 149.491 448.472 3,418 0.13 1,640.9 0.27 

 6 154.128 924.770 6,835 0.14 5,070.6 0.18 

 3 159.313 477.938 3,483 0.14 2,323.3 0.21 

 3 177.141 531.424 3,340 0.16 2,962.1 0.18 

 6 180.622 1,084.733 6,339 0.17 4,794.6 0.23 

 9 186.399 1,678.595 9,278 0.18 7,297.7 0.23 

 3 207.444 622.331 2,666 0.23 3,331.4 0.19 

 3 219.160 657.479 4,434 0.15 2,401.5 0.27 

 3 226.654 679.963 3,710 0.18 2,115.3 0.32 

 105 14,901.590 106,316 0.14 91,676.0 0.16 

 141.910 1,013 873.1 

DUANE ARNOLD 

MONTICELLO 

LIMERICK 1,2

HATCH 1,2

PILGRIM 

SUSQUEHANNA 1,2

LASALLE 1,2

HOPE CREEK 1

DRESDEN 2,3

GRAND GULF 

FERMI 2

COLUMBIA GENERATING 

PEACH BOTTOM 2,3

NINE MILE POINT 1,2

VERMONT YANKEE 

OYSTER CREEK 

BRUNSWICK 1,2

FITZPATRICK 

CLINTON 

QUAD CITIES 1,2

BROWNS FERRY 1,2,3**

PERRY 

RIVER BEND 1

COOPER STATION 

Totals and Averages 

Average per Reactor-Year 

Plant Name *

Collective

TEDE per

Reactor

Year

Collective

TEDE per

Site

Reactor

Years

Number of

Workers with

Measurable

TEDE

Average

TEDE per

Worker

Total

MW-Yr

Average

TEDE per

MW-Yr

 * Sites where not all reactors had completed three full years of commercial operation as of December 31, 2008, are 

not included.

 ** Although Brown’s Ferry 1 was placed on administrative hold in 1985, it remains in the count of operating reactors 

and has resumed operation as of June, 2007.
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TABLE 4.6

Three-Year Totals and Averages Listed in Ascending Order of Collective TEDE per PWR

2006–2008

Plant Name *

Collective

TEDE per

Reactor 

Year

Collective

TEDE per

Site

Reactor

Years

Number of

Workers with

Measurable

TEDE

Average

TEDE per

Worker

Total

MW-Yr

Average

TEDE per

MW-Yr

 * Sites where not all reactors had completed three full years of commercial operation as of December 31, 2008, are not 

included.

INDIAN POINT 3

SUMMER 1

POINT BEACH 1,2

THREE MILE ISLAND 1

FARLEY 1,2

CALLAWAY 1

PRAIRIE ISLAND 1,2

GINNA 

ROBINSON 2

PALO VERDE 1,2,3

SEABROOK 

HARRIS 

TURKEY POINT 3,4

KEWAUNEE 

VOGTLE 1,2

WOLF CREEK 1

BRAIDWOOD 1,2

BYRON 1,2

CRYSTAL RIVER 3

DIABLO CANYON 1,2

SOUTH TEXAS 1,2

MCGUIRE 1,2

CALVERT CLIFFS 1,2

OCONEE 1,2,3

CATAWBA 1,2

ARKANSAS 1,2

COMANCHE PEAK 1,2

SEQUOYAH 1,2

NORTH ANNA 1,2

WATERFORD 3

SAN ONOFRE 2,3

SALEM 1,2

BEAVER VALLEY 1,2

SURRY 1,2

MILLSTONE 2,3

COOK 1,2

DAVIS-BESSE 

ST. LUCIE 1,2

FORT CALHOUN 

WATTS BAR 1

INDIAN POINT 2

PALISADES 

Totals and Averages 

Average per Reactor-Year 

 3 36.266 108.798 2,072 0.05 2,957.7 0.04 

 3 37.705 113.115 1,374 0.08 2,643.7 0.04 

 6 39.274 235.641 1,946 0.12 2,825.1 0.08 

 3 40.526 121.577 1,455 0.08 2,422.1 0.05 

 6 41.123 246.738 2,642 0.09 4,701.1 0.05 

 3 41.761 125.282 2,033 0.06 3,290.1 0.04 

 6 45.059 270.351 2,293 0.12 2,865.5 0.09 

 3 50.329 150.988 1,601 0.09 1,574.7 0.10 

 3 50.818 152.453 1,764 0.09 2,008.6 0.08 

 9 51.121 460.089 5,663 0.08 9,129.6 0.05 

 3 51.969 155.907 2,892 0.05 3,365.9 0.05 

 3 54.130 162.389 1,979 0.08 2,537.9 0.06 

 6 59.028 354.166 3,473 0.10 3,828.2 0.09 

 3 59.604 178.811 1,282 0.14 1,446.9 0.12 

 6 62.274 373.644 3,028 0.12 6,162.6 0.06 

 3 65.364 196.092 1,791 0.11 3,219.4 0.06 

 6 66.731 400.388 4,117 0.10 6,730.6 0.06 

 6 67.351 404.103 3,957 0.10 6,579.1 0.06 

 3 68.379 205.138 1,555 0.13 2,352.4 0.09 

 6 71.525 429.148 4,476 0.10 6,192.5 0.07 

 6 71.539 429.231 3,140 0.14 7,419.0 0.06 

 6 71.681 430.087 4,206 0.10 6,054.9 0.07 

 6 71.879 431.274 3,151 0.14 4,894.1 0.09 

 9 73.388 660.493 5,698 0.12 6,921.1 0.10 

 6 73.645 441.868 4,301 0.10 6,191.4 0.07 

 6 74.109 444.653 4,362 0.10 5,123.9 0.09 

 6 74.766 448.594 3,339 0.13 6,612.3 0.07 

 6 74.881 449.286 3,909 0.11 6,337.6 0.07 

 6 75.385 452.309 3,125 0.14 4,962.8 0.09 

 3 88.009 264.028 2,928 0.09 3,220.2 0.08 

 6 88.659 531.952 3,711 0.14 5,269.8 0.10 

 6 89.484 536.906 6,173 0.09 6,368.6 0.08 

 6 90.023 540.135 4,120 0.13 4,719.9 0.11 

 6 98.730 592.377 3,407 0.17 4,479.8 0.13 

 6 101.802 610.811 3,787 0.16 5,534.7 0.11 

 6 104.584 627.503 4,061 0.15 5,486.0 0.11 

 3 105.964 317.892 2,505 0.13 2,385.0 0.13 

 6 107.026 642.155 4,800 0.13 4,411.0 0.15 

 3 129.748 389.245 2,530 0.15 1,254.2 0.31 

 3 132.581 397.744 3,085 0.13 2,838.6 0.14 

 3 144.533 433.600 2,989 0.15 2,854.8 0.15 

 3 173.254 519.762 2,219 0.23 2,119.5 0.25 

 207 15,436.723 132,939 0.12 182,292.9 0.08 

 74.574 642 880.6 
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TABLE 4.7

Three-Year Collective TEDE per Reactor-Year for BWRs

2006-2008

Plant Name

Three-Year 

Coll. TEDE per 

Reactor Year

2006-2008

Percent Change 

From

2005-2007

2005 - 2007 

Quartile 

(if changed)

 1st Quartile

DUANE ARNOLD 79.063 -33%▼

MONTICELLO 89.530 -33%▼ 2

LIMERICK 1, 2 94.670 -2%▼

HATCH 1, 2 97.670 -3%▼

PILGRIM 102.208 -37%▼ 4

SUSQUEHANNA 1, 2 106.802 2%▲

 2nd Quartile

LASALLE 1, 2 115.732 -14%▼

HOPE CREEK 1 119.716 -8%▼

DRESDEN 2, 3 127.170 -7%▼ 3

GRAND GULF 135.226 0%▲

FERMI 2 136.842 -6%▼ 3

COLUMBIA GENERATING 139.072 -39%▼ 4

PEACH BOTTOM 2, 3 140.869 -10%▼ 3

3rd Quartile 

NINE MILE POINT 1, 2 143.447 -10%▼

VERMONT YANKEE 144.806 4%▲

OYSTER CREEK 149.491 70%▲ 1

BRUNSWICK 1, 2 154.128 6%▲

FITZPATRICK 159.313 34%▲ 1

 4th Quartile 

CLINTON 177.141 47%▲ 2

QUAD CITIES 1, 2 180.622 -39%▼

BROWNS FERRY 1, 2, 3 186.399 -8%▼

PERRY 207.444 -37%▼

RIVER BEND 1 219.160 64%▲ 2

COOPER STATION 226.654 14%▲

Average per Reactor-Year 141.910 -9%▼

< Average 141.9
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

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Plant Name

Three-Year 

Coll. TEDE per 

Reactor Year

2006-2008

Percent Change 

From

2005-2007

2005 - 2007 

Quartile 

(if changed)

 1st Quartile

INDIAN POINT 3 36.266 -39%▼ 2

SUMMER 1 37.705 -17%▼

POINT BEACH 1, 2 39.274 7%▲

THREE MILE ISLAND 1 40.526 -34%▼ 2

FARLEY 1, 2 41.123 -10%▼

CALLAWAY 1 41.761 -59%▼ 4

PRAIRIE ISLAND 1, 2 45.059 19%▲

GINNA 50.329 24%▲

ROBINSON 2 50.818 3%▲

PALO VERDE 1,2,3 51.121 -8%▼

SEABROOK 51.969 17%▲

 2nd Quartile 

HARRIS 54.130 1%▲ 1

TURKEY POINT 3, 4 59.028 -3%▼

KEWAUNEE 59.604 99%▲ 1

VOGTLE 1, 2 62.274 -3%▼

WOLF CREEK 1 65.364 -6%▼

BRAIDWOOD 1, 2 66.731 4%▲

BYRON 1, 2 67.351 -13%▼ 3

CRYSTAL RIVER 3 68.379 -34%▼ 4

DIABLO CANYON 1, 2 71.525 35%▲ 1

SOUTH TEXAS 1, 2 71.539 -12%▼ 3

 3rd Quartile

MCGUIRE 1, 2 71.681 -2%▼ 2

CALVERT CLIFFS 1, 2 71.879 -18%▼

OCONEE 1, 2, 3 73.388 6%▲ 2

CATAWBA 1, 2 73.645 0%▲ 2

ARKANSAS 1, 2 74.109 -39%▼ 4

COMANCHE PEAK 1, 2 74.766 -14%▼

SEQUOYAH 1, 2 74.881 -2%▼

NORTH ANNA 1, 2 75.385 0%▲

WATERFORD 3 88.009 -1%▼

SAN ONOFRE 2, 3 88.659 27%▲ 2

 4th Quartile

SALEM 1, 2 89.484 20%▲ 3

BEAVER VALLEY 1, 2 90.023 1%▲

SURRY 1, 2 98.730 12%▲ 3

MILLSTONE 2, 3 101.802 13%▲

COOK 1, 2 104.584 -2%▼

DAVIS-BESSE 105.964 21%▲ 3

ST. LUCIE 1, 2 107.026 -31%▼

FORT CALHOUN 129.748 -31%▼

WATTS BAR 1 132.581 -15%▼

INDIAN POINT 2 144.533 42%▲

PALISADES 173.254 3%▲

Average per Reactor-Year 74.574 -4%▼

TABLE 4.8

Three-Year Collective TEDE per Reactor-Year for PWRs

2006-2008

< Average 74.6
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Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

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4.6 graphical 

representation of dose 

trends in appendix d

Each page of Appendix D presents a graph 

of selected dose performance indicators from 

1973 through 2008. The dose and performance 

indicators illustrate the history of the collective 

dose per reactor for the site, the rolling 3-year 

average collective dose per reactor, and the 

electricity generated at the site. These data are 

plotted, beginning with each plant’s first full year 

of commercial operation and continuing through 

2008. Data for years when a plant was not in 

commercial operation have been included when 

available. However, any data reported prior 

to 1973 are not included. The 3-year average 

collective dose per reactor data are included 

because they provide an overall indication of 

each plant’s general trend in collective dose. 

The 3-year average collective dose per reactor 

is also one of the metrics used by NRC in the 

Reactor Oversight Program to evaluate a plant’s 

ALARA program. This average is determined by 

summing the collective dose for the current year 

and the previous 2 years and then dividing this 

sum by the number of reactors reporting during 

those years. Depicting dose trends by using a 

3-year average reduces the sporadic effects on 

annual doses of refueling operations (usually 

an 18- to 24-month cycle) and occasional 

high-dose maintenance activities and provides 

a more representative depiction of collective 

dose trends over the life of a plant. The annual 

average collective dose per reactor for all 

reactors of the same type is also shown on the 

graph. 

4.7 DECONTAMINATION 

AND DECOMMISSIONG OF 

NUCLEAR POWER PLANTS

While 104 nuclear power plants are currently 

in commercial operation, several have 

undergone the process of decontamination 

and decommissioning (D&D), which involves 

the cleanup, dismantlement, and closure of the 

site. As more nuclear power plants reach the 

end of their operating license, there will be a 

commensurate increase in activities involving 

radiation exposure related to D&D. For this 

reason, there is an increased need to provide 

further information on plants undergoing D&D. 

Appendix B contains a list of the plants that 

are no longer in commercial operation along 

with the dose distribution and collective dose 

for these plants. It should be noted that these 

plants may be in different stages of D&D, so 

that a comparison of dose at one plant versus 

another would not be meaningful. In addition, 

Appendix B lists the plant units that are no 

longer in commercial operation but report along 

with other units at the site. Under the licensing 

conditions and reporting requirements, it is 

permitted to report this information together in 

one report. Table 4.9 lists the plants that have 

ceased operation and have changed the status 

to “Decommissioned” as of the date shown.
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Plant Name

Date of First 

Commercial Operation Decommissioning Date

BIG ROCK POINT 3/29/1963 9/20/1997

DRESDEN 1 8/1/1960 8/31/1978

FORT ST. VRAIN 7/1/1979 8/29/1989

HADDAM NECK 1/1/1968 12/4/1996

HUMBOLDT BAY 3 8/1/1963 7/1/1983

LACROSSE 11/1/1969 4/30/1987

MAINE YANKEE 12/28/1972 8/6/1997

MILLSTONE 1 3/1/1971 6/30/1998

RANCHO SECO 4/17/1975 6/7/1989

SAN ONOFRE 1 1/1/1968 11/30/1992

SHOREHAM 6/6/1987

THREE MILE ISLAND 2 12/30/1978 3/28/1979

TROJAN 5/20/1976 12/31/1992

YANKEE-ROWE 7/1/1961 2/26/1992

ZION 1 12/31/1973 12/31/1997

ZION 2 9/17/1974 12/31/1997

TABLE 4.9

Plants No Longer in Operation

2008
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TRANSIENT WORKERS AND CAREER 

DOSES AT NRC-LICENSED FACILITIES

Section 5

5.1 Termination Reports

Under 10 CFR 20, licensees are required 

to submit an NRC Form 5 to NRC for each 

individual who is required to be monitored at 

the end of the monitoring year or upon the 

individual’s termination of employment at 

the facility. The termination report submitted 

in accordance with the old §20.408, listing 

the individual’s complete dose history during 

employment at the facility, is no longer required. 

However, the Form 5 submitted to NRC upon 

an individual’s termination of employment 

serves the same function as the previous 

requirements with regard to the analysis of 

transient workers at NRC-licensed facilities. 

The following analysis examines the workers 

who had more than one Form 5 dose record at 

more than one NRC-licensed facility during the 

monitoring year. These workers are defined as 

“transient” because they worked at more than 

one facility during the monitoring year. 

The term “monitoring year” is used here in 

accordance with the definition of a year given 

in §20.1003, which defines a year as “the 

period of time beginning in January used to 

determine compliance with the provisions of 

Part 20. The licensee may change the start 

date of the monitoring year used to determine 

compliance provided that the change is made 

at the beginning of the monitoring/calendar 

year and that no day is omitted or duplicated in 

consecutive years.” 

5.2 Transient Workers at

NRC Facilities

Examination of the data reported for workers 

who began and terminated two or more periods 

of employment with two or more different 

facilities within one monitoring year is useful 

in many ways. For example, the number of 

transients and the individual doses received by 

them can be determined from examining these 

data. 

Additionally, the distribution of the doses 

received by transient workers can be useful 

in determining the impact that the inclusion 

of these individuals in each of two or more 

licensees’ annual reports has on the annual 

summary (as reported in Appendix B) for all 

nuclear power facilities and all NRC licensees 

combined (one of the issues mentioned 

in Section 2). Table 5.1 shows the actual 

distribution of transient worker doses as 

determined from the NRC Form 5 termination 

reports and compares it with the reported 

distribution of the doses of these workers as 

they would have appeared in a summation of 

the annual reports submitted by each of the 

licensees. 

In 2008, over 99% of the transient individuals 

were reported by nuclear power facilities. For 

this reason, these data are shown separately in 

Table 5.1. 
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

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TABLE 5.1

Effects of Transient Workers on Annual Statistical Compilations

2008

Average

Meas.

TEDE

(rem)

POWER REACTORS ( 1) Form 5 Summation

(2) Transients, As Reported(3) Transients, Actual

Corrected Distribution (1-[2-3])ALL LICENSEES

 (1) Form 5 Summation (2) Transients, As Reported(3) Transients, Actual

Corrected Distribution (1-[2-3])

Number of Individuals with TEDE in the Ranges (rem)*

License Category

Total

Number

Monitored

Number

with

Measurable

Exposure

Collective

TEDE

(person-rem)

No

Measurable

Exposure

Measurable

<0.10

0.10 -

0.25

3.0 -

4.0

0.25 -

0.50

0.50 -

0.75

0.75 -

1.0

1.0 -

2.0

2.0 -

3.0

4.0 -

5.0

5.0 -

6.0 >6

* Dose values exactly equal to the values separating ranges are reported in the next higher range.

 89,874 51,831 17,337 7,578 1,847 583 269 5 169,324 79,450 9,195.940 0.12 36,342 26,509 10,214 4,564 1,076 360 148 1 79,214 42,872 5,362.857 0.13 7,804 8,510 5,201 3,772 1,658 803 800 34 28,582 20,778 5,362.857 0.26 61,336 33,832 12,324 6,786 2,429 1,026 921 38 118,692 57,356 9,195.940 0.16 95,293 54,949 18,641 8,547 2,370 862 667 104 26 3 181,462 86,169 11,300.966 0.13 36,932 26,741 10,338 4,666 1,121 378 169 7 80,352 43,420 5,650.483 0.13 7,767 8,528 5,246 3,823 1,704 833 838 40 1 28,780 21,013 5,650.483 0.27 66,128 36,736 13,549 7,704 2,953 1,317 1,336 137 27 3 129,890 63,762 11,300.966 0.18
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Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

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 Table 5.1 illustrates the impact that the multiple 

reporting of these transient individuals had on 

the summation of the dose reports for 2008. 

Because each licensee reports the doses 

received by workers while they are monitored 

by the particular licensee during the year, it is 

expected that a summation of these reports 

would result in individuals being counted several 

times in dose ranges lower than the range in 

which their total accumulated doses (the sum 

of the personnel monitoring results incurred 

at each facility during the year) would actually 

place them. Thus, while the total collective dose 

would remain the same, the number of workers, 

their dose distributions, and average doses 

would be affected by this multiple reporting. 

This was found to be true because too few 

workers were reported in the higher dose 

ranges. For example, in 2008, Table 5.1 shows 

that the summation of annual reports for reactor 

licensees indicated that 5 individuals received 

doses greater than 2 rem. After accounting 

for those individuals who were reported more 

than once, the corrected distribution indicated 

that there were really 38 transient workers who 

received doses greater than 2 rem. Correcting 

for the multiple counting of individuals also has 

a significant effect on the average measurable 

dose for these workers. The corrected average 

measurable dose for transient workers is 

twice as high as the value calculated by the 

summation of licensee records. The transient 

workers represent 33% of the workforce that 

receives measurable dose. The correction for 

the transient workers increases the average 

measurable dose by a factor of 2 from 0.13 rem 

to 0.26 rem for the transient workforce for all 

licensees. It should be noted that this analysis 

of transient workers does not include workers 

who may have been exposed at facilities that 

are not required to report to the NRC REIRS 

database (see Section 1), such as Agreement 

State licensees or DOE facilities. 

One purpose of the REIRS database, which 

tracks occupational radiation exposures at 

NRC-licensed facilities, is to identify individuals 

who may have exceeded the occupational 

radiation dose limits because of multiple 

exposures at different facilities throughout the 

year. The REIRS database stores the radiation 

dose information for an individual by his/her 

unique identification number and identification 

type [Ref. 10, Section 1.5] and sums the dose 

for all facilities during the monitoring year. An 

individual exceeding the TEDE 5 rem per year 

regulatory limit would be identified in Table 5.1 

in one of the dose ranges >5 rem. In 2008, 

there were no individuals reported by NRC 

licensees that exceeded the 5 rem annual 

TEDE limit.
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

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8See 10 CFR 20.1206, 20.2204, and Regulatory Guide 8.35 for more information on PSEs and their reporting requirements.

exposures to personnel in excess 

of regulatory limits

Section 6

6.1 REPORTING CATEGORIES

Doses in excess of regulatory limits are

sometimes referred to as “overexposures.” The

phrase “doses in excess of regulatory limits” is

preferred to “overexposures” because the latter

suggests that a worker has been subjected to

an unacceptable biological risk, which may or

may not be the case.

The implementation date for the revised 10

CFR 20 was January 1, 1994. Section 10 CFR

20 includes requirements for summing internal

and external dose equivalents to yield TEDEs

and to implement a similar limitation system

for organs and tissues (such as the gonads,

red bone marrow, bone surfaces, lung, thyroid,

and breast). Section 10 CFR 20.1201 limits

the TEDE of workers to ionizing radiation from

licensed material and other sources of radiation

within the licensee’s control. Section 10 CFR

20 no longer contains quarterly dose limits but

has reporting requirements for planned special

exposures (PSEs).8

The annual TEDE limit for

adult occupational radiation workers is 5 rem.

Sections 10 CFR 20.2202 and 10 CFR 20.2203

require that all licensees submit reports of

all occurrences involving personnel radiation

doses that exceed certain control levels, thus

providing for investigations and corrective

actions as necessary. Based on the magnitude

of the dose, the occurrence may be placed into

one of three categories as follows:

1. Category A

10 CFR 20.2202(a)(1)—a TEDE to any

individual of 25 rem or more, a lens

dose equivalent of 75 rem or more, or

a shallow-dose equivalent to the skin

or extremities of 250 rad or more. The

Commission must be notified immediately

of these events.

2. Category B

10 CFR 20.2202(b)(1)— In a 24-hour

period, the Commission must be notified

of the following events: a TEDE to any

individual exceeding 5 rem, a lens dose

equivalent exceeding 15 rem, or a

shallow-dose equivalent to the skin or

extremities exceeding 50 rem.

3. Category C

10 CFR 20.2203—In addition to the

notification required by 10 CFR 20.2202

(Category A or B events), each licensee

must submit a written report within 30

days after learning of any of the following

occurrences:

a. Any incident for which notification is

required by 10 CFR 20.2202

b. Doses that exceed the limits in

§20.1201, §20.1207, §20.1208, or

§20.1301 (for adults, minors, the

embryo/fetus of a declared pregnant

worker, and the public, respectively), or

any applicable limit in the license
6-2

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

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c. Levels of radiation or concentrations

of radioactive material that exceed any

applicable license limit for restricted

areas or that, for unrestricted areas, are

in excess of 10 times any applicable

limit set forth in 10 CFR 20 or in the

license (whether or not involving dose

of any individual in excess of the limits

in §20.1301)

d. For licensees subject to the provisions

of the Environmental Protection

Agency’s generally applicable

environmental radiation standards in 40

CFR 190, levels of radiation or releases

of radioactive material in excess of

those standards or license conditions

related to those standards

6.2 Limitations of the 

Data

It is important to note that this summary of

events includes only

• Occupational radiation doses in excess of the

regulatory limits

• Events at NRC-licensed facilities

• Final dose of record assigned to an individual

It does not include

• Medical events as defined in 10 CFR 35

• Doses in excess of the regulatory limits to the

general public

• Agreement State-licensed activities or DOE

facilities

• Other radiation-related violations, such as

high dose-rate areas or effluent limits

• Exposures to dosimeters that, upon

evaluation, have been determined to be high

dosimeter readings only and are not assigned

to an individual as the dose of record by the

licensee

Care should be taken when comparing the

summary information presented here with other

reports and analyses published by NRC or

other agencies. Various reports may include

other types of “overexposure” events; therefore,

the distinctions should be noted.

The analysis and summary of incidents

presented here involving doses in excess of

regulatory limits represent the status of events

as of the publication of this report. 

Exposure events of this type typically undergo

a long review and evaluation process by the

licensee, the NRC inspector for the regional

office, and NRC Headquarters. Preliminary

dose estimates submitted by licensees are often

conservatively high and do not represent the

final (record) dose assigned for the event. It is,

therefore, not uncommon for a dose in excess

of a regulatory limits event to be reassessed

and the final assigned dose to be categorized

as not having been in excess of the regulatory

limits. In other cases, the exposure event may

not be identified until a later date, such as

during the next scheduled audit or inspection of

the licensee’s exposure event records.
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For these reasons, an attempt is made to keep

the exposure events summary presented here

current. An event that has been reassessed and

determined not to be a dose in excess of the

regulatory limits is not included in this report. In

addition, events that occurred in prior years are

added to the summary in the appropriate year

of occurrence. The reader should note that the

summary presented here represents a snapshot

of the status of events as of the publication

date of this report. Previous or future reports

may not correlate in the exact number of events

because of the review cycle and reassessment

of the events.

6.3 Summary of 

OCCUPATIONAL RADIATION

DOSES in Excess of NRC

Regulatory Limits

Table 6.1 summarizes the occupational

radiation doses in excess of regulatory limits

as reported by NRC licensees pursuant to 10

CFR 20.2202 and 10 CFR 20.2203 from 1994

to 2008. Table 6.2 shows the data reported

under 10 CFR 20.403 and 10 CFR 20.405

for the period 1985 to 1993. Note that the

categorization criteria changed with the revision

of 10 CFR 20 in 1994.

For the period 1990 to 1993, Table 6.2 shows

the number of individuals who exceeded

various regulatory limits while employed by one

of several types of licensees. For the period

1985 to 1989, only the doses in excess of

regulatory limits reported by licensed industrial

radiography firms are shown separately.

Most of the occurrences included in the “All

Other” category come from research facilities,

universities, and measuring and well-logging

activities.

In 2008, there were no category A, B, or C

occurrences reported under the licensed

activities included in this report.
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Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

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INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

NUCLEAR NO. OF PERSONS

PHARMACIES SUM OF DOSES

MANUFACTURING NO. OF PERSONS

AND DISTRIBUTION SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

2002

2000

1999

1996

1995

1994

Types of Exposures and Doses

Lens of the Eye (rem)

5–25

License Persons and

Year Category Doses (rem)

TEDE (rem) Skin/Extremity (rem)

aOne of these individuals also received the extremity exposure as shown.

bThis exposure was from a hot particle to a localized area of the skin.

cThis exposure was from a hot particle to a localized area of the skin.

dTwo of these exposures (230 rem and 342 rem) were the result of hot particles. 

eThis exposure was from a hot particle to a localized area of the skin.

f

These exposures have been added due to a reassessment of extremity 

dose from the direct handling of vials containing indium at a 

radiopharmaceutical manufacturing licensee.

gThese exposures were received by the same individual.

 

2005

>25 15–75 >75 50–250 >250 rad

2004

1997

1998

2003

2001

2007

2006

2008

1g

15,678

1

5.860

1

5.606

2

11.373

2

10.636

1

5.67

4a

34.8

1

8.3

1

5.1

2

12.2

1g

15,667

2

154

1

80

1

127

5f

566

1

50-200

5f

675

1b

51.1

5f

431

7c,f

810.6

4d,f

782

1e

180

3

1,260

3

2,677

2f

1,080

3f

1,115

3f

1,199

1f

255

TABLE 6.1

Occupational Doses in Excess of Regulatory Limits

1994–2008

NONE REPORTED

NONE REPORTED

NONE REPORTED

NONE REPORTED
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Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

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INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

1993

1985

1986

1987

1988

1989

1990

1991

1992

3

8.1

4

6.6

3

8.1

7

19.34

1

3.1

2

2.8

2

4.4

3

9.6

6

16.7

7

11.8 

1

61

aSame individual exceeded 1.25 rem/qtr limit twice during 1993.

bThis 1992 exposure was reported in 1994.

cThis individual received a whole-body dose of 24 rem in addition to a 6,000 rem 

skin dose.

Types of Exposures and Doses

Whole-Body (rem) License Persons and

Year Category Doses (rem)

Skin (rem) Extremity (rem)

<5 5– 25 >25 <7.5<30 30–50 >150 >18.75>75 75–375 >375

dOne of these individuals received a 9 rem whole-body dose in addition to a 1,070 

rem extremity dose.

eOne of these individuals exceeded the quarterly whole-body dose limits three times 

in one calendar year.

f

An additional 1993 exposure was reported in 1994.

1a

5.4

3c, d

49.9

1

6.1

1

7.5

3

32.6

1

6

2b

3.8

8a

15.9

1

93

1

27.0

5

81.8

2

5.6

3

6.2

3

7.2

4e

11.2

5

184.1

1

48.8

1

272

1

22.3

1

9.2

1

72

2

105

4

66.8

5

128.4

1

278

1

58

3

72.0

1

41.2

3

60.2

1c

6,000

2

930

1

650

1

300-1,000

4f

462.3

1

178

1

118

1

127

1

180

1

115

1

288

1

93

TABLE 6.2

Occupational Doses in Excess of Regulatory Limits

1985–1993
6-6

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

6.4 Maximum 

OCCUPATIONAL RADIATION

DOSES Below NRC

Regulatory Limits

Because few radiation doses exceed the NRC

occupational radiation dose limits, certain

researchers have expressed an interest in

a listing of the maximum radiation doses

received at NRC licensees that do not exceed

the regulatory limits. This would allow an

examination of doses that approach, but do not

exceed, the regulatory limits. Table 6.3 shows

the maximum doses for each dose category

required to be reported to the NRC. In addition,

the number of doses in certain dose ranges

is shown to reflect the number of doses that

approach NRC regulatory limits. As shown in

Table 6.3, few doses exceed half of the NRC

occupational annual limits. In 2008, seven

individuals exceeded 75% of the TEDE dose

limit, but no individual exceeded the 5 rem

TEDE annual limit or any other annual limit.

TABLE 6.3

Maximum Occupational Doses for Each Exposure Category *

2008

 Maximum Number of Number of Number of Number of Number of

Annual Dose Max Dose Individuals with Individuals Individuals Individuals Individuals

Dose Dose Limit Reported Percent of Measurable >25% of >50% of >75% of >95% of

Category** 10CFR20*** (rem) the Limit Dose the Limit the Limit the Limit the Limit

 * Only records reported by licensees required to report under 10 CFR 20.2206 are included. Numbers have been adjusted for the multiple reporting 

of transient individuals.

 **SDE-ME = shallow dose equivalent to the maximally exposed extremity

 SDE-WB = shallow dose equivalent to the whole body

 LDE = eye dose equivalent to the lens of the eye

 CEDE = committed effective dose equivalent

 CDE = committed dose equivalent

 DDE = deep dose equivalent

 TEDE = total effective dose equivalent

 TODE = total organ dose equivalent

 *** Shaded boxes represent dose categories that do not have specific dose limits defined in 10 CFR 20.

SDE-ME 50 rem 49.270 99% 59,187 141 30 7 1 0

SDE-WB 50 rem 5.470 10% 63,933 0 0 0 0 0

LDE 15 rem 4.270 28% 62,064 7 0 0 0 0

CEDE 1.028 2,145 

CDE 8.564 1,877 

DDE 4.198 62,709 

TEDE 5 rem 4.198 84% 63,621 836 58 7 0 0

TODE 50 rem 8.716 17% 62,963 0 0 0 0 0

Number of

Individuals

> Limit
7-1

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1.	 U.S. Atomic Energy Commission, Nuclear Power Plant Operating Experience During 1973,

USAEC Report 00E‐ES‐004, December 1974.*

2.	 U.S. Nuclear Regulatory Commission, Nuclear Power Plant Operating Experience 1974–

1975, USNRC Report NUREG‐0227, April 1977.*

3.	 U.S. Nuclear Regulatory Commission, Nuclear Power Plant Operating Experience 1976, 

USNRC Report NUREG‐0366, December 1977.*

4.	 M. R. Beebe, Nuclear Power Plant Operating Experience – 1977, USNRC Report

NUREG‐0483, February 1979.*

5.	 Nuclear Power Plant Operating Experience – 1978, USNRC Report NUREG‐0618,

December 1979.*

6.	 Nuclear Power Plant Operating Experience – 1979, USNRC Report NUREG/CR‐1496,

May 1981.*

7.	 Nuclear Power Plant Operating Experience – 1980, USNRC Report NUREG/CR‐2378,

ORNL/NSIC‐191, October 1982.*

8.	 Nuclear Power Plant Operating Experience – 1981, USNRC Report NUREG/CR‐3430,

ORNL/NSIC‐215, Vol. 1, December 1983.*

9.	 Nuclear Power Plant Operating Experience – 1982, USNRC Report NUREG/CR‐3430,

ORNL/NSIC‐215, Vol. 2, January 1985.*

10.	 Instructions for Recording and Reporting Occupational Radiation Exposure Data, USNRC

Regulatory Guide 8.7, Rev. 2, November 2005.

11.	 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, Volume I, General Assembly of Official Records, United Nations, New York, 2000.

12.	 International Commission on Radiological Protection Publication 68, Dose Coefficients for 

Intakes of Radionuclides by Workers, Annals of the ICRP Volume 24/4, December 1994.

13.	 Licensed Operating Reactors, Status Summary Report, compiled from reactor monthly

operating reports submitted to the NRC. Data provided electronically from the Idaho

National Engineering and Environmental Laboratory Risk, Reliability and Regulatory Support

Department under contract to the NRC in support of NRC’s Performance Indicator Project.

references

Section 7

*Report is available for purchase from the National Technical Information Service, Springfield, VA, 22161, and/or the Superintendent

of Documents, U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328.
7-2

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

This page intentionally left blank.
A-1

Forty First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

anNUAL TEDE FOR NONREACTOR NRC LICENSEES 

AND OTHER FACILITIES REPORTING TO THE nrc

2008

Appendix A
A-2

Occupational Radiation Exposure at NRC Licensed Facilities Forty First Annual Report, 2008

NUREG-0713

PROGRAM CODE –LICENSEE NAME LICENSE#

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10–

0.25

0.25–

0.50

0.50–

0.75

0.75–

1.00

1.00–

2.00

2.00–

3.00

3.00–

4.00

4.00–

5.00

5.00–

6.00

6.00–12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

INDUSTRIAL RADIOGRAPHY – FIXED LOCATION – 03310DEPARTMENT OF THE ARMY 13-18235-01 26 25 - - - - - - - - - - - 51 25 0.484 0.019

HARRISON STEEL CASTINGS CO. 13-02141-01 6 - - - - - - - - - - - - 6 - - -INTERMET - ARCHER CREEK 45-17464-01 3 1 - - - - - - - - - - - 4 1 0.025 0.025Total 3 35 26 0 0 0 0 0 0 0 0 0 0 0 61 26 0.509 0.020

INDUSTRIAL RADIOGRAPHY – TEMPORARY JOB SITE – 03320ACUREN INSPECTION, INC. 42-27593-01 1 12 6 4 5 3 4 2 - - - - - 37 36 18.815 0.523ACUREN USA, INC. 42-32443-01 22 80 42 30 13 5 5 - - - - - - 197 175 38.220 0.218ALASKA INDUSTRIAL X-RAY 50-16084-01 - 1 1 4 2 1 1 1 1 - - - - 12 12 11.405 0.950ALLIED INSPECTION SERVICES, INC. 21-18428-01 - - - 1 1 1 1 - - - - - - 4 4 2.958 0.740ALONSO & CARUS IRON WORKS, INC. 52-21350-01 1 1 1 1 - - 1 - - - - - - 5 4 2.091 0.523AMERICAN ENGINEERING TESTING, INC. 22-20271-02 - 3 - 1 1 2 1 1 1 - - - - 10 10 9.829 0.983APPLIED TECHNICAL SERVICES, INC. 45-25477-01 6 26 6 7 2 2 6 1 - - - - - 56 50 17.005 0.340BRANCH RADIOGRAPHIC LABS. 29-03405-02 4 7 3 2 6 3 1 - - - - - - 26 22 9.532 0.433CALUMET TESTING SERVICES 13-16347-01 3 5 4 3 - - 5 2 - - - - - 22 19 14.858 0.782CAPITAL X-RAY SERVICES, INC. 35-11114-01 7 8 1 1 3 2 6 4 1 - - - - 33 26 26.071 1.003CENTURY INSPECTION, INC. 42-08456-02 34 28 14 9 6 4 3 - 1 - - - - 99 65 20.341 0.313CERTIFIED TESTING LABS., INC 29-14150-01 4 10 4 1 - - 1 - - - - - - 20 16 2.938 0.184COLBY-THIELMEIER TESTING CO. 24-13737-01 - 2 - 4 1 - 4 - - - - - - 11 11 8.762 0.797COMO TECH INSPECTION 15-26978-01 - - - 3 1 - 1 - - - - - - 5 5 3.427 0.685CONAM INSPECTION 12-16559-02 2 20 18 13 9 6 9 2 - - - - - 79 77 35.736 0.464CONCRETE IMAGING, INC. 47-31316-01 2 - - 2 - 1 - - - - - - - 5 3 1.492 0.497CONSUMERS ENERGY LAB SERVICES 21-08606-03 13 2 2 9 3 - 1 - - - - - - 30 17 6.566 0.386DBI, INC. QUALITY INSPECTION 49-29301-01 1 3 5 3 2 4 18 2 - - - - - 38 37 39.396 1.065EASTERN TESTING & INSPECTION, INC. 29-09814-01 3 1 3 4 2 - - - - - - - - 13 10 3.368 0.337

APPENDIX A

Table A1 - Annual TEDE for Nonreactor NRC Licensees

2008

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5). *Dose values exactly equal to the values separating ranges are reported in the next higher range.
A-3

Forty First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Table A1 - Annual TEDE for Nonreactor NRC Licensees

2008 (continued)

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5). *Dose values exactly equal to the values separating ranges are reported in the next higher range.

PROGRAM CODE –LICENSEE NAME LICENSE#

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10–

0.25

0.25–

0.50

0.50–

0.75

0.75–

1.00

1.00–

2.00

2.00–

3.00

3.00–

4.00

4.00–

5.00

5.00–

6.00

6.00–12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

FROEHLING & ROBERTSON, INC. 45-08890-01 3 1 2 - - - - - - - - - - 6 3 0.339 0.113G. E. INSPECTION SERVICES, INC. 39-24888-01 9 28 8 10 2 - 1 - - - - - - 58 49 8.662 0.177GENERAL DYNAMICS CORP - ELEC BOAT 06-01781-08 5 23 7 - - - - - - - - - - 35 30 1.867 0.062GENERAL TESTING & INSPECTION CO. 47-32191-01 - 2 - - - - - - - - - - - 2 2 0.024 0.012H & H X-RAY SERVICES, INC. 17-19236-01 5 15 37 61 60 34 50 10 3 - - - - 275 270 200.159 0.741HIGH MOUNTAIN INSPECTION SERVICES 49-26808-02 - 5 4 4 6 6 23 10 2 - - - - 60 60 75.395 1.257HUDSON GLOBAL RESOURCES 37-27891-02 4 6 5 5 - 1 3 - - - - - - 24 20 7.468 0.373HUNTINGTON TESTING & TECHNOLOGY 47-23076-01 5 7 9 3 1 6 5 2 - - - - - 38 33 20.309 0.615INTEGRITY TESTING AND INSPECTION 16-31189-01 - 2 2 5 6 2 5 1 - - - - - 23 23 16.823 0.731INTEGRITY TESTLAB 07-30791-01 1 4 3 3 3 7 7 2 1 - - - - 31 30 27.949 0.932JANX INTEGRITY GROUP 21-16560-01 82 63 54 68 52 43 85 8 1 - - - - 456 374 245.700 0.657J CORE DRILLING, INC. 45-30846-01 1 2 1 - - 1 - - - - - - - 5 4 1.029 0.257KAKIVIK ASSET MANAGEMENT 50-27667-01 37 38 29 32 10 13 6 2 - - - - - 167 130 49.210 0.379LKS INSPECTION SERVICES, LLC 53-27795-01 - 2 2 - - - - 1 - - - - - 5 5 2.490 0.498MARTIN INDUSTRIAL TESTING, INC. 45-25452-01 - 1 - - 1 - 1 - - - - - - 3 3 1.594 0.531MARYLAND Q.C. LABORATORIES, INC. 19-28683-01 5 7 3 2 1 - - - - - - - - 18 13 1.760 0.135MASSACHUSETTS MATERIALS RESEARCH 07-01173-03 1 3 - - - - - - - - - - - 4 3 0.012 0.004MECHANICAL INTEGRITY SOLUTIONS 52-25615-01 - 5 8 1 - - - - - - - - - 14 14 1.792 0.128MID AMERICAN INSPECTION SERVICES, INC. 21-26060-01 - 2 3 2 1 - 6 4 - - - - - 18 18 20.433 1.135NEWPORT NEWS SHIPBUILDING & DRY DOCK CO. 45-09428-02 3 22 4 - - - - - - - - - - 29 26 1.155 0.044

PACIFIC TESTING SERVICES, INC. 53-29118-01 - 8 - - - - - - - - - - - 8 8 0.018 0.002POLE BROTHERS IMAGING COMPANY 45-25383-01 - - - - 2 - 2 - - - - - - 4 4 3.841 0.960PRECISION CUSTOM COMPONENTS, LLC. 37-16280-01 12 7 - - - - - - - - - - - 19 7 0.024 0.003PRIME NDT SERVICES, INC. 37-23370-01 1 9 8 9 12 6 8 5 - - - - - 58 57 40.988 0.719

INDUSTRIAL RADIOGRAPHY – TEMPORARY JOB SITE – 03320 (Continued)
A-4

Occupational Radiation Exposure at NRC Licensed Facilities Forty First Annual Report, 2008

NUREG-0713 APPENDIX A Table A1 - Annual TEDE for Nonreactor NRC Licensees 2008 (continued)

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5). *Dose values exactly equal to the values separating ranges are reported in the next higher range.

>12.0

PROGRAM CODE –LICENSEE NAME LICENSE#

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10–

0.25

0.25–

0.50

0.50–

0.75

0.75–

1.00

1.00–

2.00

2.00–

3.00

3.00–

4.00

4.00–

5.00

5.00–

6.00

6.00–12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

PROFESSIONAL SERVICE INDUSTRIES 12-16941-03 2 1 1 1 1 - 4 - - - - - - 10 8 8.060 1.008QUALITY INSPECTION SERVICES, INC. 31-30187-01 7 26 13 15 8 3 9 - - - - - - 81 74 27.117 0.366QUALITY TESTING SERVICE, INC. 24-32292-01 - 12 3 - - - 1 - - - - - - 16 16 2.145 0.134SCIENTIFIC TECHNICAL, INC. 45-24882-01 6 2 - - - - - - - - - - - 8 2 0.087 0.044SHAW PIPELINE SERVICES 35-23193-01 12 46 55 73 35 35 32 4 1 - - - - 293 281 144.569 0.514SOUTHWEST X-RAY CORP 49-29277-01 - 2 2 2 - 1 - - - - - - - 7 7 1.771 0.253T & K INSPECTION, INC. 33-27678-01 - - 1 3 2 - 9 3 - - - - - 18 18 22.582 1.255TEAM INDUSTRIAL SERVICES, INC. 42-32219-01 20 47 19 27 10 7 10 7 - - - - - 147 127 57.858 0.456TEI ANALYTICAL SERVICES, INC. 37-28004-01 - 9 9 5 5 13 13 4 - - - - - 58 58 44.688 0.770TESTING TECHNOLOGIES, INC. 45-25007-01 - 4 8 4 3 4 2 - - - - - - 25 25 10.774 0.431TESTMASTER INSPECTION COMPANY 34-24872-02 - - 1 1 3 1 1 - - - - - - 7 7 4.651 0.664TULSA GAMMA RAY, INC. 35-17178-01 6 14 16 14 17 12 17 13 8 2 - - - 119 113 122.565 1.085TVA - INSPECTION SERVICES ORG 41-06832-06 10 5 - - - - - - - - - - - 15 5 0.117 0.023VALLEY INSPECTION SERVICE, INC. 37-28385-01 - - 1 - - - 3 2 - - - - - 6 6 10.486 1.748WASHINGTON GROUP INTERNATIONAL 29-27761-01 5 28 1 - - - - - - - - - - 34 29 0.927 0.032Total 58 345 667 429 452 298 229 371 93 20 2 0 0 0 2,906 2,561 1,460.248 0.570

INDUSTRIAL RADIOGRAPHY – TEMPORARY JOB SITE – 03320 (Continued)
A-5

Forty First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Table A1 - Annual TEDE for Nonreactor NRC Licensees

2008 (continued)

PROGRAM CODE –LICENSEE NAME LICENSE#

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10-

0.25

0.25-

0.50

0.50-

0.75

0.75-

1.00

1.00-

2.00

2.00-

3.00

3.00-

4.00

4.00-

5.00

5.00-

6.00

6.00-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

MANUFACTURING AND DISTRIBUTION - NUCLEAR PHARMACIES - 02500CAPITAL PHARMACY INCORPORATED 21-26597-01MD 8 7 2 - - - - - - - - - - 17 9 0.521 0.058CARDINAL HEALTH 34-29200-01MD 185 564 108 26 11 1 3 - - - - - - 898 713 50.665 0.071GE HEALTHCARE - KENTWOOD 21-26707-01MD 18 7 - - - - - - - - - - - 25 7 0.266 0.038GE HEALTHCARE - LIVINGSTON, NJ 29-28341-02MD 21 8 10 5 - - - - - - - - - 44 23 3.564 0.155GE HEALTHCARE - LIVONIA 21-24828-01MD 14 15 2 1 - - - - - - - - - 32 18 1.114 0.062GE HEALTHCARE - ST. LOUIS/OVERLAND 24-32462-01MD 6 12 - - - - - - - - - - - 18 12 0.361 0.030IBA MOLECULAR NORTH AMERICA, INC. 45-25221-01MD 13 42 23 10 5 2 7 5 6 1 - - - 114 101 58.082 0.575MALLINCKRODT, INC. 24-04206-08MD 10 7 - - - - - - - - - - - 17 7 0.312 0.045MALLINCKRODT MEDICAL, INC. 24-04206-01MD 15 2 1 - - - - - - - - - - 18 3 0.217 0.072MALLINCKRODT MEDICAL, INC. 24-04206-10MD 15 5 - - - - - - - - - - - 20 5 0.101 0.020MALLINCKRODT MEDICAL, INC. 24-04206-13MD 9 5 - - - - - - - - - - - 14 5 0.145 0.029MID-AMERICA ISOTOPES, INC. 24-26241-01MD 35 6 3 1 1 1 - - - - - - - 47 12 2.564 0.214Total 12 349 680 149 43 17 4 10 5 6 1 0 0 0 1,264 915 117.912 0.129

MANUFACTURING AND DISTRIBUTION - TYPE “A” BROAD - 03211 INTERNATIONAL ISOTOPES IDAHO, INC. 11-27680-01 6 12 6 3 7 2 2 1 - - - - - 39 33 13.456 0.408MALLINCKRODT MEDICAL, INC. 24-04206-01 147 110 54 47 36 20 12 - - - - - - 426 279 82.334 0.295

Total 2 153 122 60 50 43 22 14 1 0 0 0 0 0 465 312 95.790 0.307

MANUFACTURING AND DISTRIBUTION - TYPE "B" BROAD - 03212 BEST MEDICAL INTERNATIONAL, INC. 45-19757-01 65 85 13 6 1 - - - - - - - - 170 105 7.610 0.072Total 1 65 85 13 6 1 0 0 0 0 0 0 0 0 170 105 7.610 0.072

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5). *Dose values exactly equal to the values separating ranges are reported in the next higher range.
A-6

Occupational Radiation Exposure at NRC Licensed Facilities Forty First Annual Report, 2008

NUREG-0713 APPENDIX A Table A1 - Annual TEDE for Nonreactor NRC Licensees 2008 (continued)

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5). *Dose values exactly equal to the values separating ranges are reported in the next higher range.

MANUFACTURING AND DISTRIBUTION - OTHER - 03214 BEST THERATRONICS 45-31299-01 - 1 - 1 - - - - - - - - - 2 2 0.427 0.214INTERGRATED INDUSTRIAL SYSTEMS, INC. 06-21253-01 17 2 2 - - - - - - - - - - 21 4 0.358 0.090PRINCETON GAMMA-TECH, INC. 29-12783-01 9 3 - - - - - - - - - - - 12 3 0.026 0.009Total 3 26 6 2 1 0 0 0 0 0 0 0 0 0 35 9 0.811 0.090FUEL CYCLE URANIUM ENRICHMENT PLANTS - 21200 USEC, INC. SNM-7003 467 30 - - - - - - - - - - - 497 30 0.472 0.016USEC - PADUCAH GDP GDP-1 1,614 98 17 3 - - - - - - - - - 1,732 118 6.600 0.056

USEC - PORTSMOUTH GDP GDP-2 1,188 211 20 1 - - - - - - - - - 1,420 232 8.555 0.037Total 3 3,269 339 37 4 0 0 0 0 0 0 0 0 0 3,649 380 15.627 0.041

INDEPENDENT SPENT FUEL STORAGE INSTALLATION - 23200 GENERAL ELECTRIC - MORRIS OPERATION SNM-2500 2 17 3 1 - - - - - - - - - 23 21 1.248 0.059

TROJAN ISFSI SNM-2509 30 - - - - - - - - - - - - 30 - - -

Total 2 32 17 3 1 0 0 0 0 0 0 0 0 0 53 21 1.248 0.059

PROGRAM CODE –LICENSEE NAME LICENSE#

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10-

0.25

0.25-

0.50

0.50-

0.75

0.75-

1.00

1.00-

2.00

2.00-

3.00

3.00-

4.00

4.00-

5.00

5.00-

6.00

6.00-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

FUEL CYCLE FUEL FABRICATION FACILITIES - 21210 AREVA NP, INC. SNM-1168 575 129 54 30 7 - - - - - - - - 795 220 27.504 0.125AREVA NP, INC. SNM-1227 84 136 59 41 44 12 2 - - - - - - 378 294 66.884 0.227B&W NUCLEAR OPERATIONS GROUP SNM-0042 23 142 55 17 2 2 1 - - - - - - 242 219 24.347 0.111GLOBAL NUCLEAR FUEL AMERICAS SNM-1097 384 417 169 101 4 - - - - - - - - 1,075 691 73.459 0.106NUCLEAR FUEL SERVICES, INC. SNM-0124 - 163 110 42 16 6 - - - - - - - 337 337 54.363 0.161WESTINGHOUSE ELECTRIC COMPANY SNM-1107 79 189 164 181 91 4 - - - - - - - 708 629 158.714 0.252Total 6 1,145 1,176 611 412 164 24 3 0 0 0 0 0 0 3,535 2,390 405.271 0.170
A-7

Forty First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Table A2 - Other Facilities Reporting to the NRC

2008

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5). *Dose values exactly equal to the values separating ranges are reported in the next higher range.

PROGRAM CODE –LICENSEE NAME LICENSE#

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10-

0.25

0.25-

0.50

0.50-

0.75

0.75-

1.00

1.00-

2.00

2.00-

3.00

3.00-

4.00

4.00-

5.00

5.00-

6.00

6.00-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

MEASURING SYSTEMS FIXED GAUGES - 03120TRANSCANADA 21-29258-01 1 - - - - - - - - - - - - 1 - - -

TVA - CUMBERLAND FOSSIL PLANT 41-25219-01 12 - - - - - - - - - - - - 12 - - -TVA - PARADISE FOSSIL PLANT 16-25243-01 15 - - - - - - - - - - - - 15 - - -

TVA - WIDOWS CREEK FOSSIL PLANT 01-25207-01 28 - - - - - - - - - - - - 28 - - -Total 4 56 0 0 0 0 0 0 0 0 0 0 0 0 56 0 0.000 0

INSTRUMENT CALIBRATION SERVICE ONLY - SOURCE > 100 CURIES - 03222GENERAL DYNAMICS CORP - ELEC BOAT 06-01781-03 1 6 - - - - - - - - - - - 7 6 0.036 0.006Total 1 1 6 0 0 0 0 0 0 0 0 0 0 0 7 6 0.036 0.006OTHER SERVICES - 03225TVA - POWER SERVICE CENTER 41-08165-08 69 2 - - - - - - - - - - - 71 2 0.040 0.020TVA - WESTERN AREA RADIOLOGICAL LAB 01-06113-04 15 - - - - - - - - - - - - 15 - - - Total 2 84 2 0 0 0 0 0 0 0 0 0 0 0 86 2 0.040 0.020INDUSTRIAL RADIOGRAPHY - TEMPORARY JOB SITES - 03320BRAUN INTERTEC CORP. MN-1082-100-27 4 7 3 6 3 5 3 2 - - - - - 33 29 18.129 0.625VALLEY INDUSTRIAL X-RAY & INSPECTION CA-4182-15 9 40 14 15 15 16 29 7 1 - - - - 146 137 91.811 0.670WYLE LABORATORIES FL-2953-1 20 9 - - - - - - - - - - - 29 9 0.203 0.023YUBA HEAT TRANSFER OK-13735-01 - 1 3 - - - - - - - - - - 4 4 0.347 0.087Total 4 33 57 20 21 18 21 32 9 1 0 0 0 0 212 179 110.490 0.617
A-8

Occupational Radiation Exposure at NRC Licensed Facilities Forty First Annual Report, 2008

NUREG-0713

IRRADIATORS OTHER GREATER THAN 10000 CURIES - 03521ARMED FORCES RADIOBIO. RES. INST. 19-08330-03 58 13 - - - - - - - - - - - 71 13 0.161 0.012Total 1 58 13 0 0 0 0 0 0 0 0 0 0 0 71 13 0.161 0.012MULTI-SITE, MULTI-REGIONAL MATERIALS LICENSE - 03613DEPARTMENT OF THE NAVY 45-23645-01NA 97 98 3 2 - - - - - - - - - 200 103 2.964 0.029Total 1 97 98 3 2 0 0 0 0 0 0 0 0 0 200 103 2.964 0.029

PROGRAM CODE –LICENSEE NAME LICENSE#

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10-

0.25

0.25-

0.50

0.50-

0.75

0.75-

1.00

1.00-

2.00

2.00-

3.00

3.00-

4.00

4.00-

5.00

5.00-

6.00

6.00-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

BYPRODUCT MATERIAL STANDBY - NO OPERATIONS - 03810TVA - ERC MIXED WASTE STORAGE 01-25284-01 5 - - - - - - - - - - - - 5 - - -

Total 1 5 0 0 0 0 0 0 0 0 0 0 0 0 5 0 0.000 0

URANIUM HEXAFLUORIDE (UF6) PRODUCTION PLANTS - 11400HONEYWELL INTERNATIONAL, INC. SUB-0526 29 370 137 79 40 13 15 - - - - - - 683 654 117.303 0.179Total 1 29 370 137 79 40 13 15 0 0 0 0 0 0 683 654 117.303 0.179

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5). *Dose values exactly equal to the values separating ranges are reported in the next higher range.

APPENDIX A

Table A2 - Other Facilities Reporting to the NRC

2008 (continued)
A-9

Forty First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Table A2 - Other Facilities Reporting to the NRC

2008 (continued)

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5). *Dose values exactly equal to the values separating ranges are reported in the next higher range. **Test reactor facilities are required to report to NRC, but only two facilities report under this category and one of the facilities is in decommissioning.

PROGRAM CODE –LICENSEE NAME LICENSE#

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10-

0.25

0.25-

0.50

0.50-

0.75

0.75-

1.00

1.00-

2.00

2.00-

3.00

3.00-

4.00

4.00-

5.00

5.00-

6.00

6.00-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

NUCLEAR REACTOR - 41111 (INTERNATIONAL)TOMARI NPP TOMARI-1 - 27 36 58 10 - - - - - - - - 131 131 32.541 0.248Total 1 0 27 36 58 10 0 0 0 0 0 0 0 0 131 131 32.541 0.248PROGRAM CODE - 42150UNIVERSITY OF ARIZONA R-52 6 - - - - - - - - - - - - 6 - - -Total 1 6 0 0 0 0 0 0 0 0 0 0 0 0 6 0 0.000 0TEST REACTOR FACILITIES - 42140**NAT'L AERONAUTICS AND SPACE ADMIN TR-3 142 21 - - - - - - - - - - - 163 21 0.225 0.011NAT'L INSTITUTE OF STANDARDS & TECH TR-5 8 131 18 11 - - - - - - - - - 168 160 9.831 0.061Total 2 150 152 18 11 0 0 0 0 0 0 0 0 0 331 181 10.056 0.056PROGRAM CODE - NONEAEROTEST OPERATIONS, INC. R-98 - - - 1 1 5 5 7 2 - - - - 21 21 36.238 1.726ENVIRONMENTAL MANAGEMENT & CONTROL 3546-50 - - 2 2 1 - - - - - - - - 5 5 1.717 0.343

WELDSONIX, INC. L05718 7 15 23 21 17 7 5 1 1 - - - - 97 90 41.157 0.457

Total 3 7 15 25 24 19 12 10 8 3 0 0 0 0 123 116 79.112 0.682
A-10

Occupational Radiation Exposure at NRC Licensed Facilities Forty First Annual Report, 2008

NUREG-0713

This page intentionally left blank.
B-1

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ANNUAL WHOLE-BODY DOSES AT LICENSED NUCLEAR 

POWER FACILITIES

2008

Appendix B
B-2

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713 APPENDIX B Annual Whole-Body Doses at Licensed Nuclear Power Facilities 2008

ARKANSAS 1, 2 PWR 1,386 1,201 374 158 37 18 3 - - - - - - - 3,177 1,791 196.047BEAVER VALLEY 1, 2 PWR 1,669 713 210 64 4 - - - - - - - - - 2,660 991 83.394BRAIDWOOD 1, 2 PWR 1,844 852 333 50 - - - - - - - - - - 3,079 1,235 103.180BROWNS FERRY 1, 2, 3 BWR 1,947 1,384 566 422 171 67 23 - - - - - - - 4,580 2,633 482.127BRUNSWICK 1, 2 BWR 1,394 1,586 508 308 94 34 16 - - - - - - - 3,940 2,546 354.212BYRON 1, 2 PWR 1,990 996 355 118 13 1 - - - - - - - - 3,473 1,483 140.809CALLAWAY 1 PWR 1,216 602 105 19 3 - - - - - - - - - 1,945 729 45.738CALVERT CLIFFS 1,2 PWR 1,404 503 171 61 9 1 - - - - - - - - 2,149 745 74.149CATAWBA 1, 2 PWR 2,431 837 221 46 5 1 - - - - - - - - 3,541 1,110 85.080CLINTON BWR 1,610 706 399 216 51 8 1 - - - - - - - 2,991 1,381 205.086COLUMBIA GENERATING BWR 938 519 159 35 2 - - - - - - - - - 1,653 715 54.957COMANCHE PEAK 1, 2 PWR 1,465 566 227 184 34 21 5 - - - - - - - 2,502 1,037 168.836COOK 1, 2 PWR 2,299 695 238 35 3 - - - - - - - - - 3,270 971 76.460COOPER STATION BWR 620 990 291 178 127 73 51 5 - - - - - - 2,335 1,715 359.926CRYSTAL RIVER 3 PWR 953 229 47 6 - - - - - - - - - - 1,235 282 16.110DAVIS-BESSE 1 PWR 1,201 616 248 115 6 - - - - - - - - - 2,186 985 106.603DIABLO CANYON 1, 2 PWR 1,910 1,314 558 212 32 5 - - - - - - - - 4,031 2,121 235.034DRESDEN 2, 3 BWR 1,402 1,688 457 144 18 - - - - - - - - - 3,709 2,307 198.153DUANE ARNOLD BWR 912 187 74 14 1 - - - - - - - - - 1,188 276 24.187FARLEY 1, 2 PWR 1,173 537 127 5 - - - - - - - - - - 1,842 669 40.833FERMI 2 BWR 1,075 328 115 17 - - - - - - - - - - 1,535 460 35.186FITZPATRICK BWR 607 899 275 194 45 10 7 - - - - - - - 2,037 1,430 184.772FT CALHOUN PWR 808 531 215 62 26 5 - - - - - - - - 1,647 839 96.155GINNA PWR 1,134 633 220 106 16 - 1 - - - - - - - 2,110 976 101.996GRAND GULF BWR 892 1,316 333 163 25 6 - - - - - - - - 2,735 1,843 167.859HARRIS 1 PWR 972 159 27 6 - - - - - - - - - - 1,164 192 10.356HATCH 1, 2 BWR 985 765 386 208 29 7 2 - - - - - - - 2,382 1,397 189.433HOPE CREEK 1 BWR 127 734 167 78 17 3 - - - - - - - - 1,126 999 34.510INDIAN POINT 2 PWR 12 604 232 116 47 12 2 - - - - - - - 1,025 1,013 139.683INDIAN POINT 3 PWR 151 443 - - - - - - - - - - - - 594 443 3.045KEWAUNEE PWR 1,001 346 115 98 29 7 3 - - - - - - - 1,599 598 92.951LASALLE 1, 2 BWR 1,481 1,777 403 179 33 4 6 - - - - - - - 3,883 2,402 217.567LIMERICK 1, 2 BWR 1,758 833 323 198 35 4 - - - - - - - - 3,151 1,393 176.825MCGUIRE 1, 2 PWR 1,940 1,007 464 128 12 2 - - - - - - - - 3,553 1,613 165.767MILLSTONE 2, 3 PWR 1,949 737 371 217 92 38 12 - - - - - - - 3,416 1,467 272.693MONTICELLO BWR 1,115 188 110 49 3 1 - - - - - - - - 1,466 351 43.777NINE MILE POINT 1, 2 BWR 1,269 636 353 219 105 42 36 - - - - - - - 2,660 1,391 301.824NORTH ANNA 1, 2 PWR 2,960 603 163 24 4 1 - - - - - - - - 3,755 795 61.003

PLANT NAME TYPE

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10–

0.25

0.25–

0.50

0.50–

0.75

0.75–

1.00

1.00–

2.00

2.00-

3.00

3.00–

4.00

4.00–

5.00

5.00–

6.00

6.00–

7.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem) 7.00– 12.00

Note: Totals corrected for transients on page B-3.* Dose values exactly equal to the values separating ranges are reported in the next higher range.
B-3

Forty-First Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX B

Annual Whole-Body Doses at Licensed Nuclear Power Facilities

2008 (continued)

Totals BWRs BWRs 27,150 21,809 7,276 3,841 1,098 392 221 5 - - - - - - 61,792 34,642 4,522.413Totals PWRs PWRs 62,724 30,022 10,061 3,737 749 191 48 - - - - - - - 107,532 44,808 4,673.527Total LWR LWRs 89,874 51,831 17,337 7,578 1,847 583 269 5 - - - - - - 169,324 79,450 9,195.940

OCONEE 1, 2, 3 

Corrected for Transients LWRs 61,336 33,832 12,324 6,786 2,429 1,026 921 38 - - - - - - 118,692 57,356 9,195.940

PWR 2,589 1,269 516 124 15 - - - - - - - - - 4,513 1,924 186.335

OYSTER CREEK BWR 1,600 899 351 185 47 19 10 - - - - - - - 3,111 1,511 211.932PALISADES PWR 849 178 80 13 1 - - - - - - - - - 1,121 272 23.478PALO VERDE 1, 2, 3 PWR 2,492 1,171 377 144 12 1 1 - - - - - - - 4,198 1,706 159.913PEACH BOTTOM 2, 3 BWR 1,593 1,222 364 167 40 17 6 - - - - - - - 3,409 1,816 212.741PERRY BWR 1,003 338 142 45 3 - - - - - - - - - 1,531 528 52.058PILGRIM 1 BWR 238 294 68 14 1 - - - - - - - - - 615 377 22.568POINT BEACH 1, 2 PWR 1,378 527 239 141 42 6 3 - - - - - - - 2,336 958 144.021PRAIRIE ISLAND 1, 2 PWR 911 650 274 106 24 3 3 - - - - - - - 1,971 1,060 126.723QUAD CITIES 1, 2 BWR 1,582 1,203 503 299 53 4 3 - - - - - - - 3,647 2,065 274.444RIVER BEND 1 BWR 794 1,116 276 225 103 49 40 - - - - - - - 2,603 1,809 311.697ROBINSON 2 PWR 1,105 534 218 35 1 - - - - - - - - - 1,893 788 68.381SALEM 1, 2 PWR 425 2,469 562 262 57 10 2 - - - - - - - 3,787 3,362 328.761SAN ONOFRE 2, 3 PWR 2,547 671 177 115 42 7 2 - - - - - - - 3,561 1,014 125.320SEABROOK PWR 889 1,101 138 45 8 5 - - - - - - - - 2,186 1,297 74.992SEQUOYAH 1, 2 PWR 1,553 670 227 55 5 3 - - - - - - - - 2,513 960 83.730SOUTH TEXAS 1, 2 PWR 1,507 642 279 177 65 12 6 - - - - - - - 2,688 1,181 187.295ST. LUCIE 1, 2 PWR 1,750 747 264 106 8 2 - - - - - - - - 2,877 1,127 112.234SUMMER 1 PWR 1,257 467 120 35 1 - - - - - - - - - 1,880 623 49.091SURRY 1, 2 PWR 3,101 560 354 118 25 8 4 - - - - - - - 4,170 1,069 150.269SUSQUEHANNA 1, 2 BWR 1,811 1,306 396 148 35 8 2 - - - - - - - 3,706 1,895 192.892THREE MILE ISLAND 1 PWR 1,128 62 2 - - - - - - - - - - - 1,192 64 2.219 TURKEY POINT 3, 4 PWR 1,783 753 237 66 11 - - - - - - - - - 2,850 1,067 97.357VERMONT YANKEE BWR 397 895 257 136 60 36 18 - - - - - - - 1,799 1,402 213.680VOGTLE 1, 2 PWR 1,251 720 312 137 12 3 1 - - - - - - - 2,436 1,185 137.620WATERFORD 3 PWR 902 856 257 113 29 13 - - - - - - - - 2,170 1,268 134.221WATTS BAR 1 PWR 2,550 649 198 35 5 - - - - - - - - - 3,437 887 70.648 WOLF CREEK 1 PWR 889 602 209 80 14 6 - - - - - - - - 1,800 911 94.997 

PLANT NAME TYPE

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10–

0.25

0.25–

0.50

0.50–

0.75

0.75–

1.00

1.00-

2.00

2.00–

3.00

3.00–

4.00

4.00–

5.00

5.00–

6.00

6.00–

7.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem) 7.00– 12.00

Note: Totals corrected for transients on page B-3.* Dose values exactly equal to the values separating ranges are reported in the next higher range.
B-4

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713 APPENDIX B Annual Whole-Body Doses at Licensed Nuclear Power Facilities 2008 (continued)

REACTORS NOT YET IN COMMERCIAL OPERATION

WATTS BAR 2 PWR Reported with Watts Bar 1

REACTORS NO LONGER IN COMMERCIAL OPERATIONREACTORS NO LONGER IN COMMERCIAL OPERATION, REPORTED WITH OTHER UNITSDRESDEN 1 BWR Reported with Dresden 2,3MILLSTONE 1 BWR Reported with Millstone Units 2 & 3; estimated dose from Unit 1 is 0.222 person-rem.THREE MILE ISLAND 2 PWR Reported with Three Mile Island 1; estimated dose from Unit 2 is 0.138 person-rem.TROJAN PWR Reported with ISFSITotal Reporting** 11 1,212 399 22 5 - - - - - - - - - 1,638 426 10.799

Note: Totals corrected for transients on page B-3.* Dose values exactly equal to the values separating ranges are reported in the next higher range.** These numbers are for the reactors no longer in commercial operation that report their doses separately (i.e., do not report their doses with other units).

BIG ROCK POINT BWR 26 - - - - - - - - - - - - 26 - - 

HADDAM NECK PWR 35 1 - - - - - - - - - - - 36 1 0.011

HUMBOLDT BAY BWR 211 52 4 - - - - - - - - - - 267 56 2.051INDIAN POINT 1 PWR 72 227 2 5 - - - - - - - - - 306 234 4.322LACROSSE BWR 30 34 6 - - - - - - - - - - 70 40 1.759

MAINE YANKEE PWR 31 1 - - - - - - - - - - - 32 1 0.013

RANCHO SECO PWR 88 74 10 - - - - - - - - - - 172 84 2.434SAN ONOFRE 1 PWR 490 2 - - - - - - - - - - - 492 2 0.043

YANKEE-ROWE PWR 48 1 - - - - - - - - - - - 49 1 0.019

ZION 1, 2 PWR 181 7 - - - - - - - - - - - 188 7 0.147

PLANT NAME TYPE

Number of Individuals with Whole-Body Doses in the Ranges (rem)*

No

Meas.

Exposure

Meas.

<0.10

0.10–

0.25

0.25–

0.50

0.50–

0.75

0.75–

1.00

1.00–

2.00

2.00–

3.00

3.00–

4.00

4.00–

5.00

5.00–

6.00

6.00–

7.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem) 7.00– 12.00
C-1

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

PERSONNeL, DOSE, AND POWER GENERATION 

SUMMARY

1969–2008

Appendix C*

*A discussion of the methods used to collect and calculate the information contained in this appendix is given in sections 3.1 

and 4.2.
C-2

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

ARKANSAS 1, 2 1975 588.0 76.5 147 21 0.14 0.04

Docket 50-313, 50-368; 1976 464.6 56.6 476 289 0.61 0.62

DPR-51; NPF-6 1977 610.3 76.8 601 256 0.43 0.42

1st commercial operation 1978 627.2 77.5 722 189 0.26 0.30

12/74, 3/80 1979 397.0 55.3 1,321 369 0.28 0.93

Type - PWRs 1980 452.8 63.7 1,233 342 0.28 0.76

Capacity - 836, 988 MWe 1981 1,104.7 68.3 2,225 1,102 0.50 1.00

1982 905.4 58.6 1,608 803 0.50 0.89

1983 915.0 54.7 2,109 1,397 0.66 1.53

1984 1,289.1 77.4 1,742 806 0.46 0.63

1985 1,192.3 73.6 1,262 286 0.23 0.24

1986 1,070.3 66.9 2,135 1,141 0.53 1.07

1987 1,366.1 88.9 1,123 382 0.34 0.28

1988 1,070.3 69.4 2,421 1,387 0.57 1.30

1989 1,066.3 72.0 2,063 711 0.34 0.67

1990 1,351.9 84.2 2,493 762 0.31 0.56

1991 1,515.8 88.4 2,064 351 0.17 0.23

1992 1,352.1 77.4 3,114 876 0.28 0.65

1993 1,606.0 91.3 1,981 268 0.14 0.17

1994 1,662.8 93.6 1,361 172 0.13 0.10

1995 1,397.0 82.7 2,259 386 0.17 0.28

1996 1,596.0 89.5 1,441 203 0.14 0.13

1997 1,621.9 95.9 1,195 119 0.10 0.07

1998 1,494.6 88.1 1,249 166.599 0.13 0.11

1999 1,477.3 86.9 1,463 183.997 0.13 0.12

2000 1,329.2 79.5 1,977 242.326 0.12 0.18

2001 1,684.0 95.8 1,082 106.040 0.10 0.06

2002 1,659.0 91.8 1,581 265.337 0.17 0.16

2003 1,675.8 93.1 973 99.003 0.10 0.06

2004 1,759.5 95.0 1,227 106.172 0.09 0.06

2005 1,560.0 84.5 2,335 475.784 0.20 0.31 

2006 1,739.8 95.0 1,184 143.296 0.12 0.08

2007 1,769.3 96.0 1,387 105.310 0.08 0.06

2008 1,614.8 89.7 1,791 196.047 0.11 0.12

BEAVER VALLEY 1, 2 1977 355.6 57.0 331 87 0.26 0.24

Docket 50-334, 50-412; 1978 304.2 40.8 646 190 0.29 0.62

DPR-66; NPF-73 1979 221.0 40.0 704 132 0.19 0.60

1st commercial operation 1980 39.8 6.8 1,817 553 0.30 13.89

10/76, 11/87 1981 573.4 73.6 1,237 229 0.19 0.40

Type - PWRs 1982 326.7 41.6 1,755 599 0.34 1.83

Capacity - 892, 846 MWe 1983 561.2 68.2 1,485 772 0.52 1.38

1984 576.7 71.8 1,393 504 0.36 0.87

1985 717.7 91.9 619 60 0.10 0.08

1986 581.3 70.7 1,575 627 0.40 1.08

1987 684.1 83.8 1,282 210 0.16 0.31

1988 1,386.1 87.4 1,764 530 0.30 0.38

1989 1,017.4 69.6 2,349 1,378 0.59 1.35

1990 1,271.0 85.3 1,675 348 0.21 0.27

1991 1,267.5 78.6 1,689 495 0.29 0.39

1992 1,441.9 89.1 1,414 289 0.20 0.20

1993 1,157.9 73.1 2,087 621 0.30 0.54

1994 1,514.6 88.6 487 44 0.09 0.03

1995 1,389.2 83.1 1,536 453 0.29 0.33

1996 1,269.0 76.5 1,688 449 0.27 0.35

1997 1,159.3 72.1 1,391 306 0.22 0.26

1998 523.1 33.5 700 59.311 0.08 0.11

1999 1,353.7 85.9 841 99.461 0.12 0.07

2000 1,378.7 87.3 1,730 337.867 0.20 0.24

2001 1,500.8 92.3 1,202 184.361 0.15 0.12

2002 1,548.0 95.4 1,048 90.479 0.09 0.06

2003 1,437.0 88.4 1,623 277.168 0.17 0.19

2004 1,593.1 96.3 1,270 156.509 0.12 0.10
C-3

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

BEAVER VALLEY 1, 2 2005 1,590.4 96.7 978 79.055 0.08 0.05 

(continued) 2006 1,385.6 84.0 2,174 370.146 0.17 0.27

2007 1,664.1 96.0 955 86.595 0.09 0.05

2008 1,670.2 94.4 991 83.394 0.08 0.05

BIG ROCK POINT1 1969 48.1 165 136 0.82 2.83

Docket 50-155; DPR-6 1970 43.5 290 194 0.67 4.46

1st commercial operation 3/63 1971 44.4 260 184 0.71 4.14

Type - BWR 1972 43.5 195 181 0.93 4.16

Capacity - (67) MWe 1973 50.9 241 285 1.18 5.60

1974 40.7 70.3 281 276 0.98 6.78

1975 35.1 59.8 300 180 0.60 5.13

1976 29.5 50.1 488 289 0.59 9.80

1977 43.6 73.4 465 334 0.72 7.66

1978 48.5 77.9 285 175 0.61 3.61

1979 13.0 23.5 623 455 0.73 35.00

1980 48.9 79.0 599 354 0.59 7.24

1981 56.9 90.6 479 160 0.33 2.81

1982 43.6 70.8 521 328 0.63 7.52

1983 42.3 71.0 493 263 0.53 6.22

1984 50.3 78.6 297 155 0.52 3.08

1985 43.8 73.5 435 291 0.67 6.64

1986 61.0 95.5 202 84 0.42 1.38

1987 45.3 71.0 251 222 0.88 4.90

1988 46.1 72.8 303 170 0.56 3.69

1989 50.2 79.0 418 177 0.42 3.53

1990 51.3 77.2 351 232 0.66 4.52

1991 59.1 85.2 435 226 0.52 3.82

1992 32.7 54.5 496 277 0.56 8.47

1993 51.2 79.4 419 152 0.36 2.97

1994 49.5 75.3 310 119 0.38 2.40

1995 62.2 95.0 205 54 0.26 0.87

1996 1,265.6 76.5 1,688 449 0.27 0.36

1997 22.4 54.1 258 55 0.21 2.46

1998 0.0 0.0 432 104.130 0.24 ---

1999 0.0 0.0 285 86.577 0.31 ---

2000 0.0 0.0 226 89.271 0.40 ---

2001 0.0 0.0 167 47.556 0.28 ---

2002 0.0 0.0 170 43.538 0.26 ---

2003 0.0 0.0 336 121.045 0.36 ---

2004 0.0 0.0 227 57.599 0.25 ---

2005 0.0 0.0 223 20.227 0.09 --- 

2006 0.0 0.0 27 0.382 0.01 ---

2007 0.0 0.0 0 0.000 --- ---

2008 0.0 0.0 0 0.000 --- ---

BRAIDWOOD 1, 2 1989 1,381.8 75.4 1,460 296 0.20 0.21

Docket 50-456, 50-457; 1990 1,740.2 84.1 1,081 186 0.17 0.11

NPF-72, -77 1991 1,377.2 68.9 1,641 550 0.34 0.40

1st commercial operation 1992 1,885.9 89.0 1,059 228 0.22 0.12

7/88, 10/88 1993 1,899.3 86.9 1,043 273 0.26 0.14

Type - PWRs 1994 1,666.1 77.2 1,237 298 0.24 0.18

Capacity - 1,156, 1,131 MWe 1995 1,914.7 85.4 1,134 236 0.21 0.12

1996 1,854.9 82.1 1,356 334 0.25 0.18

1997 1,863.3 85.4 1,693 321 0.19 0.17

1998 1,979.1 88.9 1,869 259.236 0.14 0.13

1999 2,161.6 95.8 1,153 145.976 0.13 0.07

2000 2,142.8 94.9 1,562 194.126 0.12 0.09

2001 2,186.4 95.8 881 100.570 0.11 0.05

2002 2,284.0 96.8 975 90.716 0.09 0.04

1 Big Rock Point was shut down in September 1997 and is no longer included in the count of operating reactors. Parentheses 

indicate plant capacity when plant was operational.
C-4

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

BRAIDWOOD 1, 2 2003 2,279.9 95.6 1,572 244.860 0.16 0.11

(continued) 2004 2,277.8 97.3 986 94.942 0.10 0.04

2005 2,253.7 96.6 926 88.084 0.10 0.04 

2006 2,234.1 95.0 1,624 199.168 0.12 0.09

2007 2,244.0 96.0 1,258 98.040 0.08 0.04

2008 2,252.5 96.3 1,235 103.180 0.08 0.05

BROWNS FERRY 12

, 2, 3 1975 161.7 17.8 2,743 347 0.13 2.15

Docket 50-259, 50-260, 1976 337.6 26.9 2,530 232 0.09 0.69

50-296 1977 1,327.5 73.7 1,985 876 0.44 0.66

DPR -33, -52, -68 1978 1,992.1 73.5 2,479 1,776 0.72 0.89

1st commercial operation 1979 2,393.0 79.1 2,869 1,593 0.56 0.67

8/74, 3/75, 3/77 1980 2,182.1 73.6 2,838 1,768 0.62 0.81

Type - BWRs 1981 2,132.9 69.5 3,497 2,398 0.69 1.12

Capacity - 1,079, 1,104, 1982 2,025.4 67.6 3,360 2,230 0.66 1.10

1,105 MWe 1983 1,641.0 54.3 3,410 3,375 0.99 2.06

1984 1,431.9 54.2 3,172 1,954 0.62 1.36

1985 368.2 11.9 2,854 1,164 0.41 3.16

1986 0.0 0.0 3,074 1,054 0.34 ---

1987 0.0 0.0 3,184 1,186 0.37 ---

1988 0.0 0.0 3,390 1,158 0.34 ---

1989 0.0 0.0 2,707 657 0.24 ---

1990 0.0 0.0 2,725 1,311 0.48 ---

1991 445.0 17.7 1,831 356 0.19 0.80

1992 979.9 32.2 2,670 519 0.19 0.53

1993 675.1 66.8 3,594 870 0.24 1.29

1994 860.2 83.4 3,362 861 0.26 1.00

1995 1,165.8 98.6 2,567 413 0.16 0.35

1996 1,972.8 93.0 1,904 389 0.20 0.20

1997 1,928.8 90.2 2,268 522 0.23 0.27

1998 1,961.9 87.7 1,612 367.716 0.23 0.19

1999 2,091.0 85.1 1,741 446.941 0.26 0.21

2000 2,143.8 97.1 1,657 333.215 0.20 0.16

2001 2,074.0 90.7 1,525 293.879 0.19 0.14

2002 2,069.0 95.4 1,977 357.573 0.18 0.17 

2003 2,014.5 93.6 2,608 602.535 0.23 0.30

2004 2,104.7 95.5 3,242 672.714 0.21 0.32

2005 2,044.2 94.3 3,743 636.282 0.17 0.31 

2006 2,040.1 94.0 3,618 641.154 0.18 0.31

2007 2,420.2 90.0 3,027 554.314 0.18 0.23

2008 2,837.4 88.5 2,633 482.127 0.18 0.17

BRUNSWICK 1, 2 1976 297.2 56.0 1,265 326 0.26 1.10

Docket 50-324, 50-325; 1977 291.1 55.7 1,512 1,120 0.74 3.85

DPR-62, -71 1978 1,173.1 83.7 1,458 1,004 0.69 0.86

1st commercial operation 1979 810.0 60.1 2,891 2,602 0.90 3.21

3/77, 11/75 1980 687.2 52.2 3,788 3,870 1.02 5.63

Type - BWRs 1981 925.2 56.9 3,854 2,638 0.68 2.85

Capacity - 938, 937 MWe 1982 540.3 50.3 4,957 3,792 0.76 7.02

1983 636.7 44.3 5,602 3,475 0.62 5.46

1984 761.3 51.5 5,046 3,260 0.65 4.28

1985 822.2 58.4 4,057 2,804 0.69 3.41

1986 1,051.3 69.1 3,370 1,909 0.57 1.82

1987 1,152.4 80.6 3,052 1,419 0.46 1.23

1988 990.8 70.1 2,648 1,747 0.66 1.76

1989 990.9 65.8 3,844 1,786 0.46 1.80

1990 991.6 67.8 3,182 1,548 0.49 1.56

1991 952.8 64.5 2,586 778 0.30 0.82

1992 375.9 27.9 2,690 623 0.23 1.66

1993 470.0 33.8 2,921 872 0.30 1.86

2 All three Brown's Ferry units were placed on administrative hold in 1985. Units 2 & 3 were restarted in 1991 and 1995, 

respectively. Brown's Ferry Unit 1 was restarted during 2007. 
C-5

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

BRUNSWICK 1, 2 1994 1,268.4 83.0 3,049 999 0.33 0.79

(continued) 1995 1,411.7 92.9 2,657 683 0.26 0.48

1996 1,261.1 85.9 2,784 716 0.26 0.57

1997 1,474.0 94.1 2,212 411 0.19 0.28

1998 1,521.0 94.3 2,005 395.526 0.20 0.26

1999 1,494.7 92.8 1,818 418.417 0.23 0.28

2000 1,571.2 95.6 1,648 321.785 0.20 0.20

2001 1,576.0 95.8 1,623 302.812 0.19 0.19

2002 1,568.0 94.5 1,743 275.534 0.16 0.18

2003 1,676.9 95.6 1,794 248.622 0.14 0.15

2004 1,690.6 94.5 2,140 244.577 0.11 0.14

2005 1,654.9 92.2 1,944 305.978 0.16 0.19 

2006 1,661.2 90.0 2,103 280.465 0.13 0.17

2007 1,714.9 92.0 2,186 290.093 0.13 0.17

2008 1,694.5 91.7 2,546 354.212 0.14 0.21

BYRON 1, 2 1986 894.5 88.6 1,081 76 0.07 0.08

Docket 50-454, 50-455; 1987 650.9 70.9 1,826 769 0.42 1.18

NPF-37, NPF-66 1988 1,534.7 86.3 1,222 459 0.38 0.30

1st commercial operation 1989 1,812.6 90.2 1,109 172 0.16 0.09

9/85, 8/87 1990 1,567.3 78.8 1,396 434 0.31 0.28

Type - PWRs 1991 1,816.3 89.9 1,077 268 0.25 0.15

Capacity - 1,152, 1,125 MWe 1992 1,888.4 90.1 1,021 199 0.19 0.11

1993 1,785.6 83.5 1,370 432 0.32 0.24

1994 1,953.3 90.7 962 280 0.29 0.14

1995 1,900.6 85.5 1,107 306 0.28 0.16

1996 1,758.4 79.3 1,610 455 0.28 0.26

1997 1,856.7 86.6 1,546 241 0.16 0.13

1998 1,869.8 85.9 1,809 275.221 0.15 0.15

1999 2,064.2 92.3 1,478 239.102 0.16 0.12

2000 2,196.9 97.4 959 193.871 0.20 0.09

2001 2,301.5 97.8 719 59.451 0.08 0.03

2002 2,205.0 93.8 1,287 195.013 0.15 0.09

2003 2,294.8 97.2 824 87.129 0.11 0.04

2004 2,277.4 97.7 906 89.147 0.10 0.04

2005 2,175.6 94.2 1,542 199.812 0.13 0.09 

2006 2,223.3 95.0 1,163 134.497 0.12 0.06

2007 2,152.1 93.0 1,311 128.797 0.10 0.06

2008 2,203.7 94.6 1,483 140.809 0.09 0.06

CALLAWAY 1 1985 967.4 90.0 964 36 0.04 0.04

Docket 50-483; NPF-30 1986 865.2 81.3 1,052 225 0.21 0.26

1st commercial operation 12/84 1987 759.0 71.1 1,082 393 0.36 0.52

Type - PWR 1988 1,069.2 93.4 353 27 0.08 0.03

Capacity - 1,190 MWe 1989 1,000.3 85.4 1,055 283 0.27 0.28

1990 960.7 84.1 1,134 442 0.39 0.46

1991 1,193.1 99.7 280 21 0.07 0.02

1992 967.5 83.0 1,133 336 0.30 0.35

1993 1,002.9 86.4 1,126 225 0.20 0.22

1994 1,196.4 100.0 191 14 0.07 0.01

1995 989.6 84.7 1,062 187 0.18 0.19

1996 1,066.0 90.5 980 248 0.25 0.23

1997 1,022.2 100.0 248 12 0.05 0.01

1998 972.2 91.3 929 200.729 0.22 0.21

1999 981.3 88.7 1,098 320.554 0.29 0.33

2000 1,137.5 99.8 244 16.058 0.07 0.01

2001 954.5 86.7 873 106.782 0.12 0.11

2002 955.0 86.2 983 95.648 0.10 0.10

2003 1,104.3 96.2 252 8.297 0.03 0.01

2004 892.8 78.9 1,124 120.621 0.11 0.14

2005 913.2 80.7 1,600 222.629 0.14 0.24 

2006 1,152.8 95.0 225 6.308 0.03 0.01

2007 1,069.7 89.0 1,079 73.236 0.07 0.07

2008 1,067.6 89.8 729 45.738 0.06 0.04
C-6

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

CALVERT CLIFFS 1, 2 1976 753.4 95.2 507 74 0.15 0.10

Docket 50-317, 50-318; 1977 583.0 72.1 2,265 547 0.24 0.94

DPR-53, -69 1978 1,188.5 75.8 1,391 500 0.36 0.42

1st commercial operation 1979 1,161.0 74.0 1,428 805 0.56 0.69

5/75, 4/77 1980 1,309.9 84.1 1,496 677 0.45 0.52

Type - PWRs 1981 1,379.7 83.1 1,555 607 0.39 0.44

Capacity - 870, 858 MWe 1982 1,238.3 73.7 1,805 1,057 0.59 0.85

1983 1,397.2 81.6 1,915 668 0.35 0.48

1984 1,389.4 79.3 1,369 479 0.35 0.34

1985 1,189.8 68.4 1,598 694 0.43 0.58

1986 1,530.0 87.2 1,296 347 0.27 0.23

1987 1,207.3 71.8 1,384 412 0.30 0.34

1988 1,397.7 81.0 1,296 291 0.22 0.21

1989 333.6 20.1 1,786 346 0.19 1.04

1990 161.1 11.0 2,019 304 0.15 1.89

1991 1,085.0 64.7 1,974 132 0.07 0.12

1992 1,271.2 73.9 1,979 330 0.17 0.26

1993 1,462.1 83.9 1,462 405 0.28 0.28

1994 1,342.1 79.4 1,482 454 0.31 0.34

1995 1,542.8 89.9 1,203 235 0.20 0.15

1996 1,438.5 82.4 1,167 239 0.20 0.17

1997 1,499.6 89.1 1,091 229 0.21 0.15

1998 1,523.1 89.3 1,042 186.887 0.18 0.12

1999 1,521.4 90.1 1,134 191.778 0.17 0.13

2000 1,575.7 92.7 912 134.689 0.15 0.09

2001 1,554.7 91.7 895 166.864 0.19 0.11

2002 1,380.0 81.7 1,582 245.075 0.16 0.18

2003 1,558.4 90.9 1,671 265.164 0.16 0.17

2004 1,653.7 95.7 1,205 143.944 0.12 0.09

2005 1,678.1 97.2 942 168.390 0.18 0.10 

2006 1,581.8 92.0 1,215 203.790 0.17 0.13

2007 1,641.6 95.0 1,191 153.335 0.13 0.09

2008 1,670.7 97.4 745 74.149 0.10 0.04

CATAWBA 1, 2 1986 638.9 49.9 1,724 286 0.17 0.45

Docket 50-413, 50-414; 1987 1,651.2 75.9 1,865 449 0.24 0.27

NPF-35, -52 1988 1,675.2 77.2 2,009 556 0.28 0.33

1st commercial operation 1989 1,733.6 79.5 1,660 334 0.20 0.19

6/85, 8/86 1990 1,616.3 70.8 2,174 809 0.37 0.50

Type - PWRs 1991 1,691.5 74.6 1,871 462 0.25 0.27

Capacity - 1,129, 1,129 MWe 1992 1,962.8 83.9 1,515 414 0.27 0.21

1993 1,896.1 81.5 1,564 396 0.25 0.21

1994 2,105.2 90.2 1,268 207 0.16 0.10

1995 2,011.9 85.3 1,892 462 0.24 0.23

1996 1,879.1 80.5 1,588 302 0.19 0.16

1997 2,028.2 89.3 1,561 266 0.17 0.13

1998 2,006.4 89.6 1,123 162.068 0.14 0.08

1999 2,046.7 90.2 1,024 118.662 0.12 0.06

2000 2,038.3 90.3 1,185 186.532 0.16 0.09

2001 2,119.9 92.9 960 116.241 0.12 0.06

2002 2,238.0 97.2 884 81.325 0.09 0.04

2003 1,991.8 89.2 1,409 210.617 0.15 0.11

2004 2,111.4 93.0 1,123 122.831 0.11 0.06

2005 2,194.5 96.0 1,019 83.679 0.08 0.04 

2006 1,928.6 85.0 1,792 212.570 0.12 0.11

2007 2,102.5 92.0 1,399 144.218 0.10 0.07

2008 2,160.3 93.5 1,110 85.080 0.08 0.04

CLINTON 1988 701.3 84.2 769 130 0.17 0.19

Docket 50-461; NPF-62 1989 348.3 48.5 1,196 372 0.31 1.07

1st commercial operation 11/87 1990 435.8 55.1 1,390 553 0.40 1.27

Type - BWR 1991 722.7 80.8 1,010 233 0.23 0.32

Capacity - 1,022 MWe 1992 589.7 68.6 1,195 431 0.36 0.73

1993 701.5 79.6 1,253 498 0.40 0.71
C-7

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

CLINTON 1994 883.3 94.8 409 63 0.15 0.07

(continued) 1995 731.1 83.0 1,182 316 0.27 0.43

1996 634.7 66.7 1,154 350 0.30 0.55

1997 0.0 0.0 738 172 0.23 ---

1998 0.0 0.0 866 144.140 0.17 ---

1999 537.0 63.5 637 87.489 0.14 0.16

2000 784.2 87.8 1,248 253.382 0.20 0.32

2001 896.8 98.5 329 33.770 0.10 0.04

2002 872.0 90.5 1,418 208.094 0.15 0.24

2003 990.5 99.1 372 57.118 0.15 0.06

2004 910.8 92.6 1,622 282.833 0.17 0.31

2005 989.1 97.4 298 36.019 0.12 0.04 

2006 939.9 92.0 1,649 295.720 0.18 0.32

2007 1,049.2 100.0 310 30.618 0.10 0.03

2008 973.0 93.3 1,381 205.086 0.15 0.21

COLUMBIA GENERATING3 1985 616.0 87.6 755 119 0.16 0.19

Docket 50-397; NPF-21 1986 616.0 74.4 1,013 222 0.22 0.36

1st commercial operation 12/84 1987 639.0 70.8 1,201 406 0.34 0.64

Type - BWR 1988 707.7 71.8 1,050 353 0.34 0.50

Capacity - 1,107 MWe 1989 727.2 78.3 1,299 492 0.38 0.68

1990 684.7 67.5 1,348 536 0.40 0.78

1991 508.5 50.3 1,088 387 0.36 0.76

1992 682.3 65.6 1,489 612 0.41 0.90

1993 849.6 79.5 1,385 469 0.34 0.55

1994 803.8 75.2 1,870 866 0.46 1.08

1995 824.7 83.8 1,694 456 0.27 0.55

1996 662.9 82.2 1,453 373 0.26 0.56

1997 697.0 72.7 1,218 251 0.21 0.36

1998 789.5 75.3 1,220 286.020 0.23 0.36

1999 694.7 70.0 1,022 155.109 0.15 0.22

2000 979.6 96.3 706 53.152 0.08 0.05

2001 939.3 88.1 1,515 226.675 0.15 0.24

2002 1,023.0 97.5 647 46.650 0.07 0.05

2003 866.9 81.8 1,618 205.225 0.13 0.24

2004 1,022.5 94.6 716 66.130 0.09 0.06

2005 938.3 87.3 1,718 325.025 0.19 0.35 

2006 1,064.9 98.0 623 55.817 0.09 0.05

2007 925.6 87.0 2,147 306.443 0.14 0.33

2008 1,055.3 98.3 715 54.957 0.08 0.05

COMANCHE PEAK 1, 2 1991 644.4 82.2 985 148 0.15 0.23

Docket 50-445, 50-446; 1992 830.8 84.0 1,128 188 0.17 0.23

NPF-87, 89 1993 853.8 81.2 945 109 0.12 0.13

1st commercial operation 1994 1,750.0 93.7 970 90 0.09 0.05

8/90, 8/93 1995 2,022.6 92.5 951 179 0.19 0.09

Type - PWR 1996 1,804.8 81.4 1,462 288 0.20 0.16

Capacity - 1,150, 1,150 MWe 1997 2,002.4 93.4 870 146 0.17 0.07

1998 2,037.8 94.9 967 232.026 0.24 0.11

1999 1,981.5 90.9 1,316 251.276 0.19 0.13

2000 2,104.7 95.3 759 77.679 0.10 0.04

2001 2,085.9 94.7 853 114.968 0.13 0.06

2002 1,887.0 86.9 1,106 225.317 0.20 0.12

2003 2,020.6 91.6 639 66.313 0.10 0.03

2004 2,169.5 95.1 864 135.388 0.16 0.06

2005 2,099.6 91.5 1,365 242.481 0.18 0.12

2006 2,271.3 97.0 686 59.959 0.09 0.03

2007 2,151.3 93.0 1,616 219.799 0.14 0.10

2008 2,189.7 94.3 1,037 168.836 0.16 0.08

3 Energy Northwest has changed the name of Washington Nuclear 2 to Columbia Generating Station.
C-8

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

COOK 1, 2 1976 807.4 83.1 395 116 0.29 0.14

Docket 50-315; DPR-58, -74 1977 573.0 76.1 802 300 0.37 0.52

1st commercial operation 1978 744.8 73.6 778 336 0.43 0.45

8/75, 7/78 1979 1,373.0 65.3 1,445 718 0.50 0.52

Type - PWRs 1980 1,552.4 74.1 1,345 493 0.37 0.32

Capacity - 1,030, 1,077 MWe 1981 1,557.3 73.4 1,341 656 0.49 0.42

1982 1,461.6 69.8 1,527 699 0.46 0.48

1983 1,456.5 71.2 1,418 658 0.46 0.45

1984 1,526.0 75.3 1,559 762 0.49 0.50

1985 925.4 47.6 1,984 945 0.48 1.02

1986 1,307.1 73.4 1,774 745 0.42 0.57

1987 1,199.5 70.2 1,696 666 0.39 0.56

1988 1,160.4 63.5 2,266 867 0.38 0.75

1989 1,433.1 72.8 1,575 493 0.31 0.34

1990 1,318.5 67.9 1,851 580 0.31 0.44

1991 1,837.4 90.2 815 69 0.08 0.04

1992 760.9 50.8 1,954 492 0.25 0.65

1993 1,927.7 98.5 587 44 0.07 0.02

1994 1,105.2 65.2 1,748 479 0.27 0.43

1995 1,656.0 82.1 1,310 203 0.15 0.12

1996 1,938.9 92.7 1,114 214 0.19 0.11

1997 1,189.7 59.7 1,864 550 0.30 0.46

1998 0.0 0.0 1,155 104.638 0.09 ---

1999 0.0 0.0 1,662 171.479 0.10 ---

2000 560.1 28.1 2,506 337.584 0.14 0.60

2001 1,794.3 89.2 423 27.290 0.06 0.02

2002 1,756.0 87.3 1,624 278.001 0.17 0.16

2003 1,557.6 75.7 1,408 209.526 0.15 0.13

2004 1,909.2 91.4 1,015 156.213 0.15 0.08

2005 1,989.0 95.0 852 91.192 0.11 0.05 

2006 1,790.5 86.0 1,780 312.214 0.18 0.17

2007 1,983.7 93.0 1,310 238.829 0.18 0.12

2008 1,711.8 80.8 971 76.460 0.08 0.05

COOPER STATION 1975 456.4 83.6 579 117 0.20 0.26

Docket 50-298; DPR-46 1976 433.3 75.5 763 350 0.46 0.81

1st commercial operation 7/74 1977 538.2 86.2 315 198 0.63 0.37

Type - BWR 1978 576.0 91.0 297 158 0.53 0.27

Capacity - 769 MWe 1979 591.0 87.6 426 221 0.52 0.37

1980 448.3 71.2 785 859 1.09 1.92

1981 457.1 71.2 935 579 0.62 1.27

1982 622.3 84.6 743 542 0.73 0.87

1983 396.6 63.3 1,383 1,293 0.93 3.26

1984 411.9 67.2 1,598 799 0.50 1.94

1985 127.3 21.5 1,980 1,333 0.67 10.47

1986 480.0 74.7 895 320 0.36 0.67

1987 652.3 96.2 549 103 0.19 0.16

1988 493.4 67.9 942 251 0.27 0.51

1989 564.3 76.2 1,202 343 0.29 0.61

1990 602.0 79.4 1,174 379 0.32 0.63

1991 566.3 78.8 1,099 405 0.37 0.72

1992 731.0 96.4 463 84 0.18 0.11

1993 436.1 58.8 1,130 391 0.35 0.90

1994 262.2 35.1 333 79 0.24 0.30

1995 486.5 66.8 1,095 228 0.21 0.47

1996 742.1 97.9 468 48 0.10 0.06

1997 622.8 84.4 1,125 174 0.16 0.28

1998 555.9 75.9 977 181.858 0.19 0.33

1999 743.2 98.1 318 47.815 0.15 0.06

2000 539.2 74.2 963 199.589 0.21 0.37

2001 592.7 80.9 1,309 168.665 0.13 0.28

2002 719.0 98.6 362 38.739 0.11 0.05
C-9

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

COOPER STATION 2003 511.4 74.1 882 135.249 0.15 0.26

(continued) 2004 702.6 94.7 481 47.064 0.10 0.07

2005 670.8 89.4 1,266 275.652 0.22 0.41 

2006 674.7 90.0 1,265 270.135 0.21 0.40

2007 761.6 99.0 730 49.902 0.07 0.07

2008 679.0 89.9 1,715 359.926 0.21 0.53

CRYSTAL RIVER 3 1978 311.5 41.4 643 321 0.50 1.03

Docket 50-302; DPR-72 1979 453.0 58.9 1,150 495 0.43 1.09

1st commercial operation 3/77 1980 404.1 53.2 1,053 625 0.59 1.55

Type - PWR 1981 490.4 62.2 1,120 408 0.36 0.83

Capacity - 838 MWe 1982 589.8 76.0 780 177 0.23 0.30

1983 452.1 58.8 1,720 552 0.32 1.22

1984 774.2 94.5 549 49 0.09 0.06

1985 344.2 47.6 1,976 689 0.35 2.00

1986 319.5 41.8 1,057 472 0.45 1.48

1987 436.0 60.9 1,384 488 0.35 1.12

1988 690.2 84.0 569 64 0.11 0.09

1989 352.8 48.8 880 234 0.27 0.66

1990 497.8 63.8 1,441 476 0.33 0.96

1991 654.6 82.0 821 116 0.14 0.18

1992 632.1 76.1 1,403 424 0.30 0.67

1993 722.4 85.0 683 60 0.09 0.08

1994 711.9 84.3 1,079 228 0.21 0.32

1995 866.3 100.0 209 8 0.04 0.01

1996 290.8 37.7 1,192 353 0.30 1.21

1997 0.0 0.0 973 179 0.18 ---

1998 739.9 90.3 313 19.298 0.06 0.03

1999 727.5 87.8 1,324 251.077 0.19 0.35

2000 819.4 97.6 257 14.649 0.06 0.02

2001 741.6 89.2 902 147.946 0.16 0.20

2002 831.0 99.4 128 5.039 0.04 0.01

2003 749.0 90.8 961 126.554 0.13 0.17

2004 831.4 98.1 131 4.044 0.03 0.0

2005 723.0 88.5 939 122.608 0.13 0.17 

2006 793.8 95.0 138 4.474 0.03 0.01

2007 761.7 91.0 1,135 184.554 0.16 0.24

2008 796.9 93.7 282 16.110 0.06 0.02

DAVIS-BESSE 1 1978 326.4 48.7 421 48 0.11 0.15

Docket 50-346; NPF-3 1979 381.0 67.0 304 30 0.10 0.08

1st commercial operation 7/78 1980 256.4 36.2 1,283 154 0.12 0.60

Type - PWR 1981 531.4 67.4 578 58 0.10 0.11

Capacity - 879 MWe 1982 390.8 51.5 1,350 164 0.12 0.42

1983 592.1 73.0 718 80 0.11 0.14

1984 518.5 62.5 1,088 177 0.16 0.34

1985 238.3 31.2 718 71 0.10 0.30

1986 3.3 1.3 981 124 0.13 37.58

1987 618.0 89.6 625 47 0.08 0.08

1988 144.1 27.1 1,183 307 0.26 2.13

1989 880.0 98.6 404 38 0.09 0.04

1990 500.0 56.7 1,377 489 0.36 0.98

1991 703.6 81.8 1,000 216 0.22 0.31

1992 915.2 100.0 287 19 0.07 0.02

1993 729.5 83.4 1,244 348 0.28 0.48

1994 768.4 88.0 861 144 0.17 0.19

1995 920.4 100.0 256 7 0.03 0.01

1996 775.8 85.3 949 167 0.18 0.22

1997 820.0 94.0 213 10 0.05 0.01

1998 699.8 83.2 980 155.269 0.16 0.22

1999 841.3 95.6 397 27.951 0.07 0.03

2000 770.8 87.3 1,109 168.044 0.15 0.22

2001 875.6 100.0 119 5.505 0.05 0.01

2002 106.0 12.6 1,983 402.766 0.20 3.81
C-10

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

DAVIS-BESSE 1 2003 0.0 0.0 1,047 219.696 0.21 ---

(continued) 2004 657.8 77.6 161 6.594 0.04 0.01

2005 817.1 93.3 577 51.332 0.09 0.06 

2006 727.8 84.0 1,331 204.201 0.15 0.28

2007 879.7 100.0 189 7.088 0.04 0.01

2008 777.5 89.4 985 106.603 0.11 0.14

DIABLO CANYON 1, 2 1986 641.5 80.6 1,260 304 0.24 0.47

Docket 50-275, 50-323; 1987 1,688.6 83.0 1,170 336 0.29 0.20

DPR-80, DPR-82 1988 1,386.1 67.6 1,826 877 0.48 0.63

1st commercial operation 1989 1,899.0 87.5 1,646 465 0.28 0.24

5/85, 3/86 1990 1,952.6 91.0 1,441 323 0.22 0.17

Type - PWRs 1991 1,809.6 83.8 2,040 546 0.27 0.30

Capacity - 1,122, 1,118 MWe 1992 1,995.7 90.9 1,850 459 0.25 0.23

1993 2,008.6 91.4 1,508 281 0.19 0.14

1994 1,832.6 83.3 2,317 590 0.25 0.32

1995 1,950.3 90.0 1,615 286 0.18 0.15

1996 2,003.6 90.7 1,462 176 0.12 0.09

1997 1,948.7 92.7 1,331 219 0.17 0.11

1998 1,955.1 92.8 1,313 173.238 0.13 0.09

1999 1,902.8 90.1 1,566 448.634 0.29 0.24

2000 1,940.1 92.0 1,057 180.792 0.17 0.09

2001 2,067.7 96.4 1,074 117.804 0.11 0.06

2002 1,860.0 88.4 1,016 148.690 0.15 0.08

2003 1,970.7 91.6 1,004 135.482 0.13 0.07

2004 1,736.3 83.5 1,230 254.367 0.21 0.15

2005 2,022.4 94.8 955 124.469 0.13 0.06 

2006 2,109.0 94.0 1,086 82.248 0.08 0.04

2007 2,131.4 95.0 1,269 111.866 0.09 0.05

2008 1,952.1 87.7 2,121 235.034 0.11 0.12

DRESDEN 14

, 2, 3 1969 99.7 286 2.87

Docket 50-010, 50-237, 50-249; 1970 163.1 143 0.88

DPR-2, -19, -25 1971 394.5 715 1.81

1st commercial operation 7/60, 1972 1,243.7 728 0.59

6/70, 11/71 1973 1,112.2 1,341 939 0.70 0.84

Type - BWRs 1974 842.5 54.9 1,594 1,662 1.04 1.97

Capacity - (197), 850, 850 MWe 1975 708.1 54.6 2,310 3,423 1.48 4.83

1976 1,127.2 80.8 1,746 1,680 0.96 1.49

1977 1,132.9 77.0 1,862 1,694 0.91 1.50

1978 1,242.2 79.5 1,946 1,529 0.79 1.23

1979 1,013.0 74.7 2,407 1,800 0.75 1.78

1980 1,074.4 55.0 2,717 2,105 0.77 1.96

1981 1,035.7 51.5 2,331 2,802 1.20 2.71

1982 1,085.3 77.9 2,572 2,923 1.14 2.69

1983 913.6 65.6 2,854 3,582 1.26 3.92

1984 789.8 55.3 2,261 1,774 0.78 2.25

1985 903.0 64.5 2,817 1,686 0.60 1.87

1986 740.5 52.6 3,111 2,668 0.86 3.60

1987 933.9 74.0 2,052 1,145 0.56 1.23

1988 1,014.7 75.8 2,414 1,409 0.58 1.39

1989 1,184.2 83.1 2,259 1,131 0.50 0.96

1990 1,107.8 76.6 2,235 1,400 0.63 1.26

1991 675.2 60.7 2,044 1,005 0.49 1.49

1992 872.4 75.4 1,812 619 0.34 0.71

1993 960.1 68.5 2,751 1,655 0.60 1.72

1994 690.2 51.7 2,336 833 0.36 1.21

1995 643.1 49.8 2,482 875 0.35 1.36

1996 612.6 47.7 1,788 456 0.26 0.74

1997 1,096.2 79.5 2,747 467 0.17 0.43

4 Dresden 1 has been shut down since 1978, and in 1985, it was decided that it would not be put in commercial operation again. 

Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was 

operational.
C-11

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

DRESDEN 14, 2, 3 1998 1,354.7 90.6 2,311 426.918 0.18 0.32

(continued) 1999 1,410.9 92.5 3,243 591.443 0.18 0.42

2000 1,506.4 97.3 2,341 261.684 0.11 0.17

2001 1,427.4 94.5 2,769 400.702 0.14 0.28

2002 1,547.0 95.7 2,819 355.011 0.13 0.23

2003 1,555.9 93.5 2,098 356.572 0.17 0.23

2004 1,405.5 84.8 2,044 381.054 0.19 0.27

2005 1,550.8 92.0 2,006 258.799 0.13 0.17 

2006 1,649.0 96.0 2,042 289.167 0.14 0.18

2007 1,658.8 97.0 2,310 275.697 0.12 0.17

2008 1,638.0 95.9 2,307 198.153 0.09 0.12

DUANE ARNOLD 1976 305.2 78.0 350 105 0.30 0.34

Docket 50-331; DPR-49 1977 353.6 78.9 538 299 0.56 0.85

1st commercial operation 2/75 1978 149.2 33.2 1,112 974 0.88 6.53

Type - BWR 1979 352.0 78.0 757 275 0.36 0.78

Capacity - 593 MWe 1980 339.1 73.3 1,108 671 0.61 1.98

1981 277.7 69.8 1,286 790 0.61 2.84

1982 278.5 74.7 524 229 0.44 0.82

1983 283.0 62.9 1,468 1,135 0.77 4.01

1984 329.4 72.9 611 189 0.31 0.57

1985 236.2 53.8 1,414 1,112 0.79 4.71

1986 365.5 82.0 476 187 0.39 0.51

1987 308.4 64.7 1,094 667 0.61 2.16

1988 386.5 75.2 1,136 614 0.54 1.59

1989 388.5 79.0 425 194 0.46 0.50

1990 367.4 75.8 1,460 861 0.59 2.34

1991 503.7 94.5 336 202 0.60 0.40

1992 416.5 81.9 1,043 502 0.48 1.21

1993 393.4 79.5 1,043 407 0.39 1.03

1994 498.6 94.0 493 120 0.24 0.24

1995 452.5 83.8 1,129 357 0.32 0.79

1996 476.8 90.7 1,093 270 0.25 0.57

1997 474.4 94.4 352 63 0.18 0.13

1998 438.3 86.6 1,019 236.693 0.23 0.54

1999 416.6 84.3 834 201.196 0.24 0.48

2000 507.3 98.4 317 44.181 0.14 0.09

2001 439.5 86.8 898 137.564 0.15 0.31

2002 522.0 94.4 319 35.061 0.11 0.07

2003 455.2 84.8 829 124.402 0.15 0.27 

2004 561.2 98.3 220 18.993 0.09 0.03

2005 517.4 90.5 879 139.622 0.16 0.27 

2006 581.7 99.0 254 29.392 0.12 0.05

2007 515.8 88.0 1,062 183.609 0.17 0.36

2008 601.4 100.0 276 24.187 0.09 0.04

FARLEY 1, 2 1978 713.8 86.5 527 108 0.20 0.15

Docket 50-348, 50-364; 1979 211.0 28.6 1,227 643 0.52 3.05

NPF-2, -8 1980 557.3 69.3 1,330 435 0.33 0.78

1st commercial operation 1981 310.2 41.4 1,331 512 0.38 1.65

12/77, 7/81 1982 1,271.5 79.2 1,453 484 0.33 0.38

Type - PWRs 1983 1,356.5 83.0 1,938 1,021 0.53 0.75

Capacity - 851, 860 MWe 1984 1,447.0 86.6 2,046 902 0.44 0.62

1985 1,368.2 81.1 2,551 799 0.31 0.58

1986 1,409.4 83.8 2,314 858 0.37 0.61

1987 1,369.7 84.7 1,871 598 0.32 0.44

1988 1,567.7 92.3 1,840 552 0.30 0.35

1989 1,402.9 84.6 2,206 749 0.34 0.53

1990 1,464.0 86.7 1,700 457 0.27 0.31

1991 1,464.0 88.1 1,645 648 0.39 0.44

4 Dresden 1 has been shut down since 1978, and in 1985, it was decided that it would not be put in commercial operation again. 

Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was 

operational.
C-12

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

FARLEY 1, 2 1992 1,331.7 81.8 2,018 805 0.40 0.60

(continued) 1993 1,455.5 88.3 1,284 333 0.26 0.23

1994 1,587.2 93.0 1,035 250 0.24 0.16

1995 1,311.2 83.8 1,574 460 0.29 0.35

1996 1,549.2 90.9 1,150 232 0.20 0.15

1997 1,449.7 89.0 1,105 278 0.25 0.19

1998 1,313.9 80.9 1,380 431.821 0.31 0.33

1999 1,436.0 91.4 1,102 190.463 0.17 0.13

2000 1,430.1 88.6 1,683 359.855 0.21 0.25

2001 1,384.3 84.4 1,810 320.509 0.18 0.23

2002 1,558.0 93.5 772 96.431 0.13 0.06

2003 1,592.6 95.3 788 111.016 0.14 0.07

2004 1,496.8 89.4 1,141 107.227 0.09 0.07

2005 1,564.2 93.3 810 67.826 0.08 0.04 

2006 1,602.7 94.0 747 66.189 0.09 0.04

2007 1,495.8 88.0 1,226 139.716 0.11 0.09

2008 1,602.6 94.4 669 40.833 0.06 0.03

FERMI 2 1989 624.0 68.5 1,270 255 0.20 0.41

Docket 50-341; NPF-43 1990 848.2 84.7 462 83 0.18 0.10

1st commercial operation 1/88 1991 739.0 77.0 1,223 228 0.19 0.31

Type - BWR 1992 874.3 81.3 1,213 245 0.20 0.28

Capacity - 1,087 MWe 1993 984.3 92.9 360 35 0.10 0.04

1994 0.0 2.2 1,130 213 0.19 ---

1995 618.3 86.9 390 28 0.07 0.05

1996 577.5 69.1 1,402 157 0.11 0.27

1997 637.0 66.6 623 49 0.08 0.08

1998 815.8 79.9 1,362 207.593 0.15 0.25

1999 1,082.7 99.5 461 36.152 0.08 0.03

2000 939.6 87.6 1,266 145.964 0.12 0.15

2001 975.0 90.9 1,202 168.689 0.14 0.17

2002 1,059.0 98.7 463 38.235 0.08 0.04

2003 925.3 86.9 1,207 168.138 0.14 0.18

2004 962.3 90.0 1,302 145.090 0.11 0.15

2005 998.1 91.7 538 61.626 0.11 0.06 

2006 855.9 83.0 1,430 181.300 0.13 0.21

2007 950.2 87.0 1,484 194.039 0.13 0.20

2008 1,094.5 99.5 460 35.186 0.08 0.03

FITZPATRICK 1976 489.0 71.6 600 202 0.34 0.41

Docket 50-333; DPR-59 1977 460.5 68.4 1,380 1,080 0.78 2.35

1st commercial operation 7/75 1978 497.0 72.1 904 909 1.01 1.83

Type - BWR 1979 349.0 50.8 850 859 1.01 2.46

Capacity - 813 MWe 1980 509.5 70.3 2,056 2,040 0.99 4.00

1981 562.9 74.7 2,490 1,425 0.57 2.53

1982 583.6 75.0 2,322 1,190 0.51 2.04

1983 546.2 70.6 1,715 1,090 0.64 2.00

1984 576.2 76.8 1,610 971 0.60 1.69

1985 492.3 63.7 1,845 1,051 0.57 2.13

1986 711.2 90.6 1,185 411 0.35 0.58

1987 496.2 70.3 1,578 940 0.60 1.89

1988 514.0 69.0 1,553 786 0.51 1.53

1989 727.5 92.3 1,027 377 0.37 0.52

1990 543.8 72.6 1,536 884 0.58 1.63

1991 399.7 53.4 1,269 333 0.26 0.83

1992 0.0 0.0 2,374 674 0.28 ---

1993 559.6 81.7 1,427 232 0.16 0.41

1994 588.4 83.2 1,595 322 0.20 0.55

1995 569.8 74.5 1,249 327 0.26 0.57

1996 623.3 83.1 1,384 357 0.26 0.57

1997 756.2 95.9 662 91 0.14 0.12

1998 562.8 78.0 1,781 357.826 0.20 0.64

1999 749.7 95.5 558 68.409 0.12 0.09

2000 685.9 88.4 1,267 300.997 0.24 0.44
C-13

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

FITZPATRICK 2001 807.2 98.9 665 63.229 0.10 0.08

(continued) 2002 751.0 93.3 1,234 230.523 0.19 0.31

2003 793.0 97.9 298 51.156 0.17 0.06

2004 735.0 92.1 1,091 186.055 0.17 0.25

2005 802.9 96.3 382 62.697 0.16 0.08

2006 771.5 93.0 1,527 234.425 0.15 0.30 

2007 790.1 96.0 526 58.741 0.11 0.07

2008 761.7 92.9 1,430 184.772 0.13 0.24

FORT CALHOUN 1975 252.3 67.4 469 294 0.63 1.17

Docket 50-285; DPR-40 1976 265.9 69.5 516 313 0.61 1.18

1st commercial operation 6/74 1977 351.8 79.4 535 297 0.56 0.84

Type - PWR 1978 342.3 75.1 596 410 0.69 1.20

Capacity - 482 MWe 1979 440.0 95.7 451 126 0.28 0.29

1980 242.3 60.4 891 668 0.75 2.76

1981 260.9 72.3 822 458 0.56 1.76

1982 418.0 89.7 604 217 0.36 0.52

1983 330.4 73.1 860 433 0.50 1.31

1984 279.2 59.9 913 563 0.62 2.02

1985 367.0 73.7 982 373 0.38 1.02

1986 431.8 94.3 756 75 0.10 0.17

1987 366.0 75.4 1,247 388 0.31 1.06

1988 315.5 74.1 1,594 272 0.17 0.86

1989 395.7 89.2 1,210 93 0.08 0.24

1990 290.0 64.2 760 290 0.38 1.00

1991 391.1 91.7 284 57 0.20 0.15

1992 303.4 65.9 802 272 0.34 0.90

1993 369.7 80.8 713 157 0.22 0.42

1994 492.8 99.6 211 23 0.11 0.05

1995 402.8 83.2 627 139 0.22 0.35

1996 374.9 79.5 740 226 0.31 0.60

1997 435.9 93.6 258 41 0.16 0.09

1998 387.7 82.5 788 223.847 0.28 0.58

1999 409.2 89.2 676 158.843 0.24 0.39

2000 443.8 93.5 249 35.215 0.14 0.08

2001 401.2 88.3 770 225.891 0.29 0.56

2002 434.0 92.3 742 163.806 0.22 0.38

2003 399.6 87.0 914 212.422 0.23 0.53

2004 463.5 97.0 215 21.574 0.10 0.05

2005 332.4 72.2 1,069 272.876 0.26 0.82 

2006 353.9 75.0 1,591 289.100 0.18 0.82

2007 499.9 100.0 100 3.990 0.04 0.01

2008 400.4 82.2 839 96.155 0.11 0.24

GINNA 1971 327.8 340 430 1.26 1.31

Docket 50-244; DPR-18 1972 293.6 677 1,032 1.52 3.51

1st commercial operation 7/70 1973 409.5 319 224 0.70 0.55

Type - PWR 1974 253.7 62.4 884 1,225 1.39 4.83

Capacity - 560 MWe 1975 365.2 76.7 685 538 0.79 1.47

1976 248.8 58.2 758 636 0.84 2.56

1977 365.6 85.5 530 401 0.76 1.10

1978 386.5 80.6 657 450 0.68 1.16

1979 355.0 72.8 878 592 0.67 1.67

1980 370.5 76.0 1,073 708 0.66 1.91

1981 399.0 82.1 925 655 0.71 1.64

1982 289.0 58.8 1,117 1,140 1.02 3.94

1983 365.0 74.6 969 855 0.88 2.34

1984 378.1 77.2 713 395 0.55 1.04

1985 436.7 87.9 845 426 0.50 0.98

1986 433.3 87.4 901 357 0.40 0.82

1987 459.0 91.5 773 344 0.45 0.75

1988 423.1 87.4 897 295 0.33 0.70

1989 369.2 75.9 1,254 605 0.48 1.64

1990 414.3 84.4 991 347 0.35 0.84
C-14

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

GINNA 1991 418.6 86.7 947 328 0.35 0.78

(continued) 1992 417.6 86.9 832 261 0.31 0.63

1993 419.6 86.3 856 193 0.23 0.46

1994 405.3 83.2 679 138 0.20 0.34

1995 437.0 89.6 738 136 0.18 0.31

1996 347.9 71.1 976 168 0.17 0.48

1997 444.6 91.8 533 81 0.15 0.18

1998 491.8 100.0 161 14.892 0.09 0.03

1999 403.4 85.6 641 175.173 0.27 0.43

2000 434.2 91.6 429 76.435 0.18 0.18

2001 488.0 100.0 140 10.156 0.07 0.02

2002 438.0 91.3 535 80.432 0.15 0.18

2003 440.4 91.1 510 74.533 0.15 0.17

2004 490.5 99.5 111 7.486 0.07 0.02

2005 455.0 93.9 564 72.841 0.13 0.16 

2006 470.2 94.0 514 44.580 0.09 0.10

2007 564.4 99.0 111 4.412 0.04 0.01

2008 540.1 94.5 976 101.996 0.10 0.19

GRAND GULF 1986 494.7 60.9 1,486 436 0.29 0.88

Docket 50-416; NPF-29 1987 920.7 82.2 1,358 420 0.31 0.46

1st commercial operation 7/85 1988 1,136.6 96.7 692 147 0.21 0.13

Type - BWR 1989 932.6 80.0 1,972 498 0.25 0.53

Capacity - 1,266 MWe 1990 883.5 78.9 1,765 482 0.27 0.55

1991 1,085.2 94.0 699 94 0.13 0.09

1992 969.0 83.7 2,032 484 0.24 0.50

1993 936.4 81.5 1,807 332 0.18 0.35

1994 1,143.2 96.6 455 56 0.12 0.05

1995 952.9 80.4 1,589 342 0.22 0.36

1996 1,096.2 88.7 1,564 357 0.23 0.33

1997 1,234.9 100.0 514 105 0.20 0.09

1998 1,049.2 88.9 1,410 303.695 0.22 0.29

1999 962.1 81.3 1,180 226.277 0.19 0.23

2000 1,217.5 99.4 289 34.877 0.12 0.03

2001 1,129.8 93.0 1,109 185.214 0.17 0.16

2002 1,145.0 93.6 1,060 176.396 0.17 0.15

2003 1,241.2 98.6 290 31.250 0.11 0.03

2004 1,165.2 92.2 1,243 158.112 0.13 0.14

2005 1,147.3 91.9 1,326 167.914 0.13 0.15

2006 1,233.7 98.0 1,016 59.935 0.06 0.05

2007 1,070.5 88.0 1,750 177.884 0.10 0.17

2008 1,072.1 89.5 1,843 167.859 0.09 0.16

HADDAM NECK5 1969 438.5 138 106 0.77 0.24

Docket 50-213; DPR-61 1970 424.7 734 689 0.94 1.62

1st commercial operation 1/68 1971 502.2 289 342 1.18 0.68

Type - PWR 1972 515.6 355 325 0.91 0.63

Capacity - (560) MWe 1973 293.1 951 697 0.73 2.38

1974 521.4 91.2 550 201 0.37 0.39

1975 494.3 89.9 795 703 0.88 1.42

1976 482.9 82.5 644 449 0.70 0.93

1977 480.7 83.9 894 641 0.72 1.33

1978 563.4 98.6 216 117 0.54 0.21

1979 493.0 87.5 1,226 1,162 0.95 2.36

1980 426.8 75.0 1,860 1,353 0.73 3.17

1981 487.5 84.3 1,554 1,036 0.67 2.13

1982 543.9 93.4 559 126 0.23 0.23

1983 453.7 77.8 1,645 1,384 0.84 3.05

1984 404.0 71.7 1,430 1,216 0.85 3.01

1985 556.1 98.4 384 101 0.26 0.18

5 Haddam Neck (also known as Connecticut Yankee) was shut down on December 4, 1996, and is no longer in the count of 

operating reactors. Parentheses indicate plant capacity when plant was operational.
C-15

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

HADDAM NECK5 1986 294.8 53.6 1,945 1,567 0.81 5.32

(continued) 1987 304.6 54.0 1,763 750 0.43 2.46

1988 397.4 70.3 735 237 0.32 0.60

1989 356.4 67.2 1,455 596 0.41 1.67

1990 142.7 32.2 979 421 0.43 2.95

1991 444.4 76.4 1,168 590 0.51 1.33

1992 465.2 80.1 797 202 0.25 0.43

1993 448.6 81.6 1,004 408 0.41 0.91

1994 455.6 77.7 463 135 0.29 0.30

1995 439.4 77.7 1,006 442 0.44 1.01

1996 331.8 55.7 673 175 0.26 0.53

1997 -1.3 0.0 219 11 0.05 ---

1998 0.0 0.0 423 93.743 0.22 ---

1999 0.0 0.0 545 108.602 0.20 ---

2000 0.0 0.0 555 262.192 0.47 ---

2001 0.0 0.0 361 95.348 0.26 ---

2002 0.0 0.0 258 51.668 0.20 ---

2003 0.0 0.0 400 82.022 0.21 ---

2004 0.0 0.0 564 91.981 0.16 ---

2005 0.0 0.0 350 36.479 0.10 --- 

2006 0.0 0.0 124 11.883 0.10 --- 

2007 0.0 0.0 0 0.000 --- --- 

2008 0.0 0.0 1 0.011 0.01 ---

HARRIS 1 1988 652.9 75.0 721 169 0.23 0.26

Docket 50-400; NPF-63 1989 690.6 79.5 929 156 0.17 0.23

1st commercial operation 5/87 1990 776.4 89.6 453 85 0.19 0.11

Type - PWR 1991 724.8 81.5 872 226 0.26 0.31

Capacity - 900 MWe 1992 661.8 74.9 930 213 0.23 0.32

1993 913.0 99.7 327 31 0.09 0.03

1994 740.8 82.7 1,089 222 0.20 0.30

1995 731.1 83.8 1,068 174 0.16 0.24

1996 860.6 95.4 444 17 0.04 0.02

1997 673.6 80.4 1,131 149 0.13 0.22

1998 766.2 90.4 931 133.497 0.14 0.17

1999 827.0 97.9 247 15.538 0.06 0.02

2000 783.0 92.5 888 100.981 0.11 0.13

2001 611.2 72.4 1,586 252.241 0.16 0.41

2002 892.0 99.4 145 6.674 0.05 0.01

2003 823.9 93.2 786 68.463 0.09 0.08

2004 797.9 88.2 747 57.103 0.08 0.07

2005 902.9 99.5 164 8.483 0.05 0.01 

2006 802.4 89.0 917 87.225 0.10 0.11

2007 845.1 94.0 870 64.808 0.07 0.08

2008 890.4 97.4 192 10.356 0.05 0.01

HATCH 1, 2 1976 496.3 83.8 630 134 0.21 0.27

Docket 50-321, 50-366; 1977 446.8 66.3 1,303 465 0.36 1.04

DPR-57; NPF-05 1978 513.0 72.8 1,304 248 0.19 0.48

1st commercial operation 1979 401.0 54.6 2,131 582 0.27 1.45

12/75, 9/79 1980 1,008.7 70.9 1,930 449 0.23 0.45

Type - BWRs 1981 870.9 64.3 2,899 1,337 0.46 1.54

Capacity - 876, 883 MWe 1982 768.0 56.6 3,418 1,460 0.43 1.90

1983 934.7 68.6 3,428 1,299 0.38 1.39

1984 658.6 47.3 4,110 2,218 0.54 3.37

1985 1,211.0 79.6 2,841 818 0.29 0.68

1986 872.0 64.8 3,486 1,497 0.43 1.72

1987 1,295.4 89.7 2,202 816 0.37 0.63

1988 1,001.4 70.4 2,509 1,401 0.56 1.40

1989 1,271.1 87.1 1,350 556 0.41 0.44

5 Haddam Neck (also known as Connecticut Yankee) was shut down on December 4, 1996, and is no longer in the count of 

operating reactors. Parentheses indicate plant capacity when plant was operational.
C-16

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

HATCH 1, 2 1990 1,268.0 83.5 2,902 1,455 0.50 1.15

(continued) 1991 1,152.4 77.4 2,508 1,161 0.46 1.01

1992 1,293.8 88.6 1,615 550 0.34 0.43

1993 1,189.6 85.5 1,733 669 0.39 0.56

1994 1,289.0 87.1 2,243 864 0.39 0.67

1995 1,376.3 90.6 1,458 488 0.33 0.35

1996 1,519.6 94.0 1,495 441 0.29 0.29

1997 1,374.7 88.1 1,945 722 0.37 0.53

1998 1,458.4 91.7 1,610 320.469 0.20 0.22

1999 1,487.4 90.0 1,866 328.583 0.18 0.22

2000 1,515.0 88.7 1,913 401.891 0.21 0.26

2001 1,603.0 93.5 1,407 230.242 0.16 0.14

2002 1,600.0 94.0 1,299 214.441 0.17 0.13

2003 1,606.3 94.5 1,295 168.281 0.13 0.10

2004 1,641.3 95.3 1,209 180.129 0.15 0.11

2005 1,562.1 91.3 1,288 207.295 0.16 0.13 

2006 1,604.9 94.0 1,405 259.313 0.18 0.16

2007 1,626.5 94.0 1,341 137.273 0.10 0.08

2008 1,584.0 92.7 1,397 189.433 0.14 0.12

HOPE CREEK 1 1987 869.2 86.4 589 117 0.20 0.13

Docket 50-354; NPF-57 1988 832.7 80.7 1,734 287 0.17 0.34

1st commercial operation 12/86 1989 791.1 77.8 1,873 465 0.25 0.59

Type - BWR 1990 966.4 91.6 1,394 196 0.14 0.20

Capacity - 1,049 MWe 1991 882.5 84.2 1,700 373 0.22 0.42

1992 841.9 80.8 1,694 436 0.26 0.52

1993 1,049.2 97.8 688 98 0.14 0.09

1994 852.0 81.2 1,779 326 0.18 0.38

1995 844.5 79.8 1,571 196 0.12 0.23

1996 806.9 77.4 1,069 158 0.15 0.20

1997 731.8 77.8 1,747 350 0.20 0.48

1998 993.2 98.0 620 54.816 0.09 0.06

1999 879.1 86.7 1,111 279.063 0.25 0.32

2000 827.8 87.9 1,236 188.295 0.15 0.23

2001 918.2 91.1 1,532 156.180 0.10 0.17

2002 1,007.0 99.2 220 25.922 0.12 0.03

2003 826.6 84.6 1,597 139.295 0.09 0.17

2004 688.6 71.3 2,440 239.540 0.10 0.35

2005 874.9 88.6 881 67.063 0.08 0.08 

2006 983.8 93.0 2,135 133.570 0.06 0.14

2007 929.3 91.0 2,221 191.068 0.09 0.21

2008 1,139.1 100.0 999 34.510 0.03 0.03

HUMBOLDT BAY6 1969 44.6 125 164 1.31 3.68

Docket 50-133; DPR-7 1970 49.3 115 209 1.82 4.24

1st commercial operation 8/63 1971 39.6 140 292 2.09 7.37

Type - BWR 1972 43.1 127 253 1.99 5.87

Capacity - (63) MWe 1973 50.1 210 266 1.27 5.31

1974 43.4 83.8 296 318 1.07 7.33

1975 45.3 83.9 265 339 1.28 7.48

1976 23.5 46.4 523 683 1.31 29.06

1977 0.0 0.0 1,063 1,905 1.79 ---

1978 0.0 0.0 320 335 1.05 ---

1979 0.0 0.0 135 31 0.23 ---

1980 0.0 0.0 142 22 0.15 ---

1981 0.0 0.0 75 9 0.12 ---

1982 0.0 0.0 71 19 0.27 ---

1983 0.0 0.0 84 17 0.20 ---

1984 "Data not available" 

1985 0.0 0.0 178 51 0.29 ---

6 Humboldt Bay had been shut down since 1976, and in 1984, it was decided that it would not be placed in operation again.

 Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was

 operational.
C-17

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

HUMBOLDT BAY6 1986 0.0 0.0 115 50 0.43 ---

(continued) 1987 "Data not available"

1988 0.0 0.0 10 1 0.10 ---

1989 0.0 0.0 0 0 0.00 ---

1990 0.0 0.0 0 0 0.00 ---

1991 0.0 0.0 0 0 0.00 ---

1992 0.0 0.0 8 0 0.00 ---

1993 0.0 0.0 24 1 0.04 ---

1994 0.0 0.0 21 1 0.05 ---

1995 0.0 0.0 42 2 0.05 ---

1996 0.0 0.0 66 5 0.08 ---

1997 0.0 0.0 105 16 0.15 ---

1998 0.0 0.0 38 201.000 0.03 ---

1999 0.0 0.0 28 0.720 0.04 ---

2000 0.0 0.0 20 0.911 0.05 ---

2001 0.0 0.0 10 0.360 0.04 ---

2002 0.0 0.0 18 1.504 0.08 ---

2003 0.0 0.0 14 0.351 0.03 ---

2004 0.0 0.0 11 0.454 0.04 ---

2005 0.0 0.0 11 0.547 0.05 --- 

2006 0.0 0.0 40 4.086 0.10 --- 

2007 0.0 0.0 45 3.271 0.07 ---

2008 0.0 0.0 56 2.051 0.04 ---

INDIAN POINT 17

, 2, 38 1969 206.2 298 1.45

Docket 50-3, 50-247, 50-286; 1970 43.3 1,639 37.85

DPR-5, -26, -64 1971 154.0 768 4.99

1st commercial operation 1972 142.3 967 6.80

10/62, 8/74, 8/76 1973 0.0 2,998 5,262 1.76 ---

Type - PWRs 1974 556.1 59.4 1,019 910 0.89 1.64

Capacity - (265), 998, 1,030 MWe 1975 584.4 74.8 891 705 0.79 1.21

1976 273.9 34.8 1,590 1,950 1.23 7.12

1977 1,278.3 75.3 1,391 1,070 0.77 0.84

1978 1,172.3 67.8 1,909 2,006 1.05 1.71

INDIAN POINT 17

, 2 1979 574.0 71.4 1,349 1,279 0.95 2.23

Docket 50-3, 50-247; DPR-05, -26 1980 510.8 64.8 1,577 971 0.62 1.90

1st commercial operation 1981 367.5 46.0 2,595 2,731 1.05 7.43

10/62, 8/74 1982 532.4 65.4 2,144 1,635 0.76 3.07

Type - PWRs 1983 702.6 84.0 1,057 486 0.46 0.69

Capacity - (265), 998 MWe 1984 416.7 51.9 2,919 2,644 0.91 6.35

1985 791.4 95.7 708 192 0.27 0.24

1986 457.5 56.2 1,926 1,250 0.65 2.73

1987 611.4 73.4 1,980 1,217 0.61 1.99

1988 719.3 86.9 890 235 0.26 0.33

1989 532.5 64.6 2,093 1,436 0.69 2.70

1990 618.0 66.6 1,061 608 0.57 0.98

1991 461.2 55.7 1,810 1,468 0.81 3.18

1992 930.9 99.1 489 97 0.20 0.10

1993 702.1 75.7 1,514 675 0.45 0.96

1994 903.8 100.0 381 48 0.13 0.05

1995 582.4 70.8 1,690 548 0.32 0.94

1996 927.8 94.8 388 54 0.14 0.06

6 Humboldt Bay had been shut down since 1976, and, in 1984, it was decided that it would not be placed in operation again.

 Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was

 operational.

7 Indian Point 1 was defueled in 1975, and in 1984, it was decided that it would not be placed in operation again. Therefore, it is no 

longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

8 Indian Point 3 was purchased by a different utility in 1979 and, subsequently, reported its dose separately. Although Indian Point 1, 

2, and 3 have been owned by the same utility since 2001, Indian Point 3 still reports separately.
C-18

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

INDIAN POINT 17, 2 1997 360.6 45.1 1,340 367 0.27 1.02

(continued) 1998 282.8 31.5 1,154 289.600 0.25 1.03

1999 831.8 88.2 350 40.931 0.12 0.05

2000 115.4 13.0 2,003 567.224 0.28 4.92

2001 887.2 97.2 399 22.067 0.06 0.02

2002 860.0 91.3 1,361 248.487 0.18 0.29

2003 953.0 98.9 241 11.778 0.05 0.01

INDIAN POINT 17 2004 0.0 0.0 156 3 0.02 ---

Docket 50-3; DPR-05 2005 0.0 0.0 151 6.692 0.04 --- 

1st commercial operation 10/62 2006 0.0 0.0 193 7.670 0.04 --- 

Type - PWR 2007 0.0 0.0 210 2.554 0.01 ---

Capacity - (265) MWe 2008 0.0 0.0 234 4.322 0.02 ---

INDIAN POINT 2 2004 855.3 91.0 1,136 195.630 0.17 0.23

Docket 50-247; DPR-26 2005 1,007.2 100.0 470 11.418 0.02 0.01 

1st commercial operation 8/74 2006 911.5 91.0 1,327 286.908 0.22 0.32

Type - PWR 2007 1,009.2 100.0 649 7.009 0.01 0.01

Capacity - 998 MWe 2008 934.1 92.6 1,013 139.683 0.14 0.15

INDIAN POINT 38 1979 574.0 66.5 808 636 0.79 1.11

Docket 50-286; DPR-64 1980 367.3 53.2 977 308 0.32 0.84

1st commercial operation 8/76 1981 367.5 59.8 677 364 0.54 0.99

Type - PWR 1982 171.5 22.5 1,477 1,226 0.83 7.15

Capacity - 1,030 MWe 1983 7.8 2.6 941 607 0.65 77.82

1984 714.4 76.3 658 230 0.35 0.32

1985 566.5 66.0 1,093 570 0.52 1.01

1986 655.3 73.4 588 202 0.34 0.31

1987 574.6 62.7 1,308 500 0.38 0.87

1988 792.5 83.3 451 93 0.21 0.12

1989 587.8 61.1 1,800 876 0.49 1.49

1990 595.3 62.9 1,066 358 0.34 0.60

1991 862.8 87.5 299 40 0.13 0.05

1992 561.7 61.4 1,003 212 0.21 0.38

1993 140.5 14.9 478 60 0.13 0.43

1994 0.0 0.0 529 58 0.11 ---

1995 174.8 21.4 638 67 0.11 0.38

1996 695.3 74.8 289 22 0.08 0.03

1997 495.1 54.9 1,608 234 0.15 0.47

1998 874.0 95.3 213 14.774 0.07 0.02

1999 829.8 88.3 893 116.920 0.13 0.14

2000 960.0 99.3 143 8.693 0.06 0.00

2001 903.9 93.1 1,014 118.115 0.12 0.13

2002 960.0 98.5 156 6.797 0.04 0.01

2003 866.2 89.8 902 96.059 0.11 0.11

2004 995.8 100.0 234 4.232 0.02 0.00

2005 915.0 91.7 893 73.862 0.08 0.08 

2006 1,024.5 100.0 307 2.793 0.01 0.00

2007 890.1 88.0 1,322 102.960 0.08 0.12

2008 1,043.1 100.0 443 3.045 0.01 0.00

KEWAUNEE 1975 401.9 88.2 104 28 0.27 0.07

Docket 50-305; DPR-43 1976 405.9 78.9 381 270 0.71 0.67

1st commercial operation 6/74 1977 425.0 79.9 312 140 0.45 0.33

Type - PWR 1978 466.6 89.5 335 154 0.46 0.33

Capacity - 556 MWe 1979 412.0 79.0 343 127 0.37 0.31

1980 433.8 82.1 401 165 0.41 0.38

1981 451.8 86.7 383 141 0.37 0.31

7 Indian Point 1 was defueled in 1975, and in 1984, it was decided that it would not be placed in operation again. Therefore, it is no 

longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

8 Indian Point 3 was purchased by a different utility in 1979 and, subsequently, reported its dose separately. Although Indian Point 1, 

2, and 3 have been owned by the same utility since 2001, Indian Point 3 still reports separately.
C-19

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

KEWAUNEE 1982 458.4 87.6 353 101 0.29 0.22

(continued) 1983 444.1 83.7 445 165 0.37 0.37

1984 455.3 85.7 482 139 0.29 0.31

1985 443.1 82.4 519 176 0.34 0.40

1986 461.7 85.8 502 169 0.34 0.37

1987 480.0 89.7 755 226 0.30 0.47

1988 467.5 88.3 705 210 0.30 0.45

1989 449.1 84.9 570 239 0.42 0.53

1990 468.8 87.9 490 145 0.30 0.31

1991 441.8 83.4 495 221 0.45 0.50

1992 471.4 88.0 450 122 0.27 0.26

1993 457.1 86.8 436 106 0.24 0.23

1994 475.6 88.8 364 72 0.20 0.15

1995 455.6 87.8 415 109 0.26 0.24

1996 380.4 71.8 474 126 0.27 0.33

1997 269.8 56.0 278 56 0.20 0.21

1998 423.0 87.2 384 88.205 0.23 0.21

1999 505.1 100.0 103 5.055 0.05 0.01

2000 432.6 88.8 394 99.864 0.25 0.23

2001 394.1 80.8 1,110 200.245 0.18 0.51

2002 509.0 97.4 102 4.449 0.04 0.01

2003 473.5 90.5 439 73.108 0.17 0.15

2004 441.0 81.0 565 91.168 0.16 0.21

2005 346.4 62.7 97 4.000 0.04 0.01 

2006 419.4 77.0 539 74.734 0.14 0.18

2007 528.0 95.0 145 11.126 0.08 0.02

2008 499.5 88.9 598 92.951 0.16 0.19

LACROSSE9 1970 15.3 111 7.25

Docket 50-409; DPR-45 1971 33.1 218 158 0.72 0.49

1st commercial operation 11/69 1972 29.2 151 172 1.14 5.17

Type - BWR 1973 24.4 157 221 1.41 6.43

Capacity - (48) MWe 1974 37.9 81.0 115 139 1.21 3.67

1975 32.0 69.6 165 234 1.42 7.31

1976 21.2 47.6 118 110 0.93 5.19

1977 11.3 33.7 141 225 1.60 19.91

1978 21.6 62.0 182 164 0.90 7.59

1979 24.0 71.8 153 186 1.22 7.75

1980 26.4 68.5 124 218 1.76 8.26

1981 29.6 76.0 187 123 0.66 4.16

1982 17.2 44.6 148 205 1.39 11.92

1983 24.8 59.7 160 313 1.96 12.62

1984 38.5 80.5 288 252 0.88 6.55

1985 39.2 86.7 373 173 0.46 4.41

1986 19.6 46.1 260 290 1.12 14.80

1987 0.0 0.0 127 68 0.54 ---

1988 0.0 0.0 49 31 0.63 ---

1989 0.0 0.0 60 15 0.25 ---

1990 0.0 0.0 51 9 0.18 ---

1991 0.0 0.0 42 8 0.19 ---

1992 0.0 0.0 28 6 0.21 ---

1993 0.0 0.0 48 8 0.17 ---

1994 0.0 0.0 65 8 0.12 ---

1995 0.0 0.0 31 3 0.10 ---

1996 0.0 0.0 25 4 0.15 ---

1997 0.0 0.0 23 2 0.09 ---

1998 0.0 0.0 27 1.530 0.07 ---

1999 0.0 0.0 66 3.725 0.06 ---

2000 0.0 0.0 37 3.548 0.10 ---

9 LaCrosse ended commercial operation in 1987 and will not be put in commercial operation again. Therefore, it is no longer 

included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.
C-20

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

LACROSSE9 2001 0.0 0.0 45 2.782 0.06 ---

(continued) 2002 0.0 0.0 47 2.314 0.05 ---

2003 0.0 0.0 65 1.836 0.03 ---

2004 0.0 0.0 56 0.918 0.02 ---

2005 0.0 0.0 51 8.139 0.16 --- 

2006 0.0 0.0 0 0.000 --- --- 

2007 0.0 0.0 86 37.092 0.43 ---

2008 0.0 0.0 40 1.759 0.04 ---

LASALLE 1, 2 1984 677.8 77.8 1,245 252 0.20 0.37

Docket 50-373, -374; 1985 987.9 53.0 1,635 685 0.42 0.69

NPF-11, -18 1986 929.5 50.6 1,614 898 0.56 0.97

1st commercial operation 1987 1,030.0 59.3 1,744 1,396 0.80 1.36

1/84, 6/84 1988 1,317.6 71.6 2,737 2,471 0.90 1.88

Type - BWRs 1989 1,503.5 73.1 2,475 1,386 0.56 0.92

Capacity - 1,111, 1,111 MWe 1990 1,754.3 84.6 1,830 948 0.52 0.54

1991 1,837.0 86.7 1,985 806 0.41 0.44

1992 1,447.4 72.0 2,418 1,167 0.48 0.81

1993 1,542.0 76.0 1,701 854 0.50 0.55

1994 1,580.0 77.6 1,812 726 0.40 0.46

1995 1,696.6 82.1 1,623 512 0.32 0.30

1996 1,053.8 54.3 2,782 819 0.29 0.78

1997 0.0 0.0 1,661 316 0.19 ---

1998 380.9 19.3 2,099 422.249 0.20 1.11

1999 1,671.9 81.8 2,689 576.354 0.21 0.34

2000 2,138.6 97.1 1,831 260.320 0.14 0.12

2001 2,223.8 98.9 535 82.721 0.15 0.04

2002 2,040.0 92.1 2,012 449.587 0.22 0.22

2003 2,100.2 94.8 2,253 464.427 0.21 0.22

2004 2,162.1 96.0 2,366 359.470 0.15 0.17

2005 2,130.4 95.0 2,097 334.558 0.16 0.16 

2006 2,181.3 97.0 2,006 248.454 0.12 0.11

2007 2,166.7 98.0 1,953 228.373 0.12 0.11

2008 2,145.8 96.4 2,402 217.567 0.09 0.10

LIMERICK 1, 2 1987 636.1 70.2 2,156 174 0.08 0.27

Docket 50-352, 50-353; 1988 794.9 96.5 950 52 0.05 0.07

NPF-39, -85 1989 628.4 66.0 1,818 266 0.15 0.42

1st commercial operation 1990 1,527.7 78.2 1,422 175 0.12 0.11

2/86, 1/90 1991 1,810.9 86.8 1,151 106 0.09 0.06

Type - BWRs 1992 1,741.4 84.8 1,559 330 0.21 0.19

Capacity - 1,134, 1,134 MWe 1993 1,913.2 91.6 1,287 217 0.17 0.11

1994 1,944.4 94.9 1,543 275 0.18 0.14

1995 1,957.1 93.0 1,581 260 0.16 0.13

1996 2,026.2 93.3 1,654 234 0.14 0.12

1997 2,001.7 95.8 1,463 234 0.16 0.12

1998 1,907.2 89.5 1,854 357.139 0.19 0.19

1999 2,089.6 94.2 1,800 271.547 0.15 0.13

2000 2,154.9 95.8 1,279 260.611 0.20 0.12

2001 2,205.9 97.3 1,127 210.336 0.19 0.10

2002 2,197.0 97.1 1,248 160.324 0.13 0.07

2003 2,213.6 97.2 1,298 147.047 0.11 0.07

2004 2,218.9 97.6 1,265 149.433 0.12 0.07

2005 2,168.9 96.3 1,460 187.609 0.13 0.09 

2006 2,207.2 97.0 1,509 193.429 0.13 0.09

2007 2,185.8 96.0 1,570 197.104 0.13 0.09

2008 2,169.2 96.0 1,393 176.825 0.13 0.08

9 LaCrosse ended commercial operation in 1987 and will not be put in commercial operation again. Therefore, it is no longer 

included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.
C-21

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

MAINE YANKEE10 1973 408.7 782 117 0.15 0.29

Docket 50-309; DPR-36 1974 432.6 68.7 619 420 0.68 0.97

1st commercial operation 12/72 1975 542.9 79.9 440 319 0.72 0.59

Type - PWR 1976 712.2 95.0 244 85 0.35 0.12

Capacity - (860) MWe 1977 617.6 82.2 508 245 0.48 0.40

1978 642.7 84.1 638 420 0.66 0.65

1979 537.0 68.4 393 154 0.39 0.29

1980 527.0 72.2 735 462 0.63 0.88

1981 624.2 78.2 868 424 0.49 0.68

1982 542.5 69.1 1,295 619 0.48 1.14

1983 677.1 83.6 592 165 0.28 0.24

1984 605.7 74.4 1,262 884 0.70 1.46

1985 635.4 79.2 1,009 700 0.69 1.10

1986 737.6 87.8 495 100 0.20 0.14

1987 478.1 65.3 1,100 722 0.66 1.51

1988 591.9 79.1 1,058 725 0.69 1.22

1989 819.2 93.7 375 99 0.26 0.12

1990 573.0 71.0 1,359 682 0.50 1.19

1991 738.1 86.6 426 105 0.25 0.14

1992 631.7 79.1 1,189 461 0.39 0.73

1993 674.8 79.8 1,016 377 0.37 0.56

1994 782.8 90.9 297 84 0.28 0.11

1995 23.6 3.7 1,167 653 0.56 27.67

1996 602.9 78.1 408 56 0.14 0.09

1997 0.0 0.0 991 153 0.15 ---

1998 0.0 0.0 438 163.008 0.37 ---

1999 0.0 0.0 365 135.057 0.37 ---

2000 0.0 0.0 490 121.133 0.25 ---

2001 0.0 0.0 412 68.121 0.17 ---

2002 0.0 0.0 452 66.226 0.15 ---

2003 0.0 0.0 342 43.775 0.13 ---

2004 0.0 0.0 190 21.313 0.11 ---

2005 0.0 0.0 2 0.048 0.02 --- 

2006 0.0 0.0 0 0.000 --- ---

2007 0.0 0.0 0 0.000 --- ---

2008 0.0 0.0 1 0.013 0.01 ---

MCGUIRE 1, 2 1982 524.9 80.4 1,560 169 0.11 0.32

Docket 50-369, -370; 1983 558.3 55.4 1,751 521 0.30 0.93

NPF-9, -17 1984 764.1 68.5 1,663 507 0.30 0.66

1st commercial operation 1985 808.4 77.0 2,217 771 0.35 0.95

12/81, 3/84 1986 1,360.0 60.1 2,326 1,015 0.44 0.75

Type - PWRs 1987 1,774.7 79.2 2,865 1,043 0.36 0.59

Capacity - 1,100, 1,100 MWe 1988 1,830.7 80.2 2,808 1,104 0.39 0.60

1989 1,810.2 80.8 1,994 620 0.31 0.34

1990 1,340.3 61.3 2,289 727 0.32 0.54

1991 1,945.1 85.0 1,723 361 0.21 0.19

1992 1,696.8 74.4 1,619 418 0.26 0.25

1993 1,470.4 66.2 1,685 463 0.27 0.31

1994 1,848.0 80.2 1,637 397 0.24 0.21

1995 2,132.3 92.9 1,259 138 0.11 0.06

1996 1,881.8 82.8 1,622 238 0.15 0.13

1997 1,558.2 73.0 2,193 492 0.22 0.32

1998 2,139.8 95.1 1,045 142.245 0.14 0.07

1999 1,961.7 88.9 1,274 256.524 0.20 0.13

2000 2,100.1 94.2 940 132.513 0.14 0.06

2001 2,113.3 93.9 963 136.581 0.14 0.06

2002 2,051.0 91.7 1,167 180.618 0.16 0.09

10 Maine Yankee was shut down in August 1997 and is no longer included in the count of operating reactors. Parentheses indicate 

plant capacity when plant was operational.
C-22

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

MCGUIRE 1, 2 2003 2,156.2 96.0 841 71.323 0.08 0.03

(continued) 2004 2,075.7 91.8 1,116 196.193 0.18 0.09

2005 1,993.9 89.2 1,401 173.972 0.12 0.09 

2006 2,100.2 93.0 1,218 108.285 0.09 0.05

2007 2,011.4 89.0 1,375 156.035 0.11 0.08

2008 1,943.3 86.2 1,613 165.767 0.10 0.09

MILLSTONE 111 1972 377.6 612 596 0.97 1.58

Docket 50-245; DPR-21 1973 225.1 1,184 663 0.56 2.95

1st commercial operation 3/71 1974 430.3 79.1 2,477 1,430 0.58 3.32

Type - BWR 1975 465.4 75.6 2,587 2,022 0.78 4.34

Capacity - (641) MWe 1976 449.8 76.1 1,387 1,194 0.86 2.65

1977 575.7 89.6 1,075 394 0.37 0.68

1978 556.6 87.6 1,391 1,416 1.02 2.54

1979 505.0 77.3 2,001 1,795 0.90 3.55

1980 405.8 69.0 3,024 2,157 0.71 5.32

1981 304.3 51.6 2,506 1,496 0.60 4.92

1982 490.2 79.9 1,370 929 0.68 1.90

1983 640.1 95.6 309 244 0.79 0.38

1984 516.1 78.8 1,992 836 0.42 1.62

1985 548.5 83.6 732 608 0.83 1.11

1986 626.8 95.4 389 150 0.39 0.24

1987 523.4 79.6 1,588 684 0.43 1.31

1988 658.8 98.6 327 144 0.44 0.22

1989 554.6 84.2 852 462 0.54 0.83

1990 608.3 91.6 365 131 0.36 0.22

1991 213.1 35.4 1,154 409 0.35 1.92

1992 431.8 68.1 348 99 0.28 0.23

1993 627.9 96.8 305 81 0.27 0.13

1994 394.0 63.6 1,321 391 0.30 0.99

1995 520.6 80.0 910 620 0.68 1.19

1996 0.0 0.0 747 431 0.58 ---

1997 -2.9 0.0 1,053 195 0.19 ---

1998 -2.7 0.0 347 12.741 0.04 ---

1999 0.0 0.0 397 9.790 0.02 ---

2000 0.0 0.0 478 59.955 0.13 ---

2001 0.0 0.0 414 14.946 0.04 ---

2002 0.0 0.0 185 4.151 0.02 ---

2003 0.0 0.0 195 10.675 0.05 ---

2004 0.0 0.0 147 11.152 0.08 ---

2005 0.0 0.0 145 0.897 0.01 --- 

2006 0.0 0.0 4 0.607 0.15 --- 

2007 0.0 0.0 33 0.901 0.03 ---

2008 0.0 0.0 0 0.000 --- ---

MILLSTONE 2, 3 1976 545.7 78.7 620 168 0.27 0.31

Docket 50-336, 50-423; 1977 518.7 65.7 667 242 0.36 0.47

DPR-65; NPF-49 1978 536.6 67.3 1,420 1,444 1.02 2.69

1st commercial operation 1979 520.0 62.8 525 471 0.90 0.91

12/75, 4/86 1980 579.3 69.2 893 637 0.71 1.10

Type - PWRs 1981 722.4 82.6 890 531 0.60 0.74

Capacity - 878, 1,148 MWe 1982 595.9 70.6 2,083 1,413 0.68 2.37

1983 294.0 34.2 2,383 1,881 0.79 6.40

1984 782.7 93.5 285 120 0.42 0.15

1985 417.8 49.4 1,905 1,581 0.83 3.78

1986 1,313.8 80.4 2,393 993 0.41 0.76

1987 1,624.5 84.1 1,441 505 0.35 0.31

1988 1,594.8 83.2 1,827 804 0.44 0.50

1989 1,428.3 72.9 1,984 1,079 0.54 0.76

1990 1,614.9 87.1 1,652 593 0.36 0.37

11Millstone 1 was shut down on June 30, 1998, and is no longer included in the count of operating reactors. Parentheses indicate 

plant capacity when plant was operational.
C-23

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

MILLSTONE 2, 3 1991 819.5 69.7 1,084 381 0.35 0.46

(continued) 1992 1,115.1 59.9 3,190 1,280 0.40 1.15

1993 1,525.2 79.7 2,064 557 0.27 0.37

1994 1,556.6 73.1 1,249 188 0.15 0.12

1995 1,278.1 60.5 1,691 416 0.25 0.33

1996 418.1 19.3 983 126 0.13 0.30

1997 0.0 0.0 1,435 253 0.18 ---

1998 374.9 20.9 1,179 112.543 0.10 0.30

1999 1,446.3 73.3 1,688 252.138 0.15 0.17

2000 1,865.8 92.4 1,385 142.664 0.10 0.08

2001 1,759.3 92.0 1,327 174.238 0.13 0.10

2002 1,703.0 87.5 1,548 292.197 0.19 0.17

2003 1,834.6 91.0 1,274 322.923 0.25 0.18

2004 1,887.5 95.0 803 136.459 0.17 0.07

2005 1,777.1 88.8 1,329 202.490 0.15 0.11 

2006 1,898.5 93.0 1,160 174.164 0.15 0.09

2007 1,875.1 94.0 1,150 163.780 0.14 0.09

2008 1,761.1 87.7 1,467 272.693 0.18 0.16

MONTICELLO 1972 424.4 99 61 0.62 0.14

Docket 50-263; DPR-22 1973 389.5 401 176 0.44 0.45

1st commercial operation 6/71 1974 349.3 74.9 842 349 0.41 1.00

Type - BWR 1975 344.8 72.2 1,353 1,353 1.00 3.92

Capacity - 578 MWe 1976 476.4 91.5 325 263 0.81 0.55

1977 425.6 79.9 860 1,000 1.16 2.35

1978 459.4 87.2 679 375 0.55 0.82

1979 522.0 97.6 372 157 0.42 0.30

1980 411.8 78.2 1,114 531 0.48 1.29

1981 389.3 72.6 1,446 1,004 0.69 2.58

1982 291.1 63.3 1,307 993 0.76 3.41

1983 494.6 96.3 416 121 0.29 0.24

1984 33.7 9.2 1,872 2,462 1.32 73.06

1985 509.8 91.7 586 327 0.56 0.64

1986 402.7 79.1 895 596 0.67 1.48

1987 422.5 81.9 941 568 0.60 1.34

1988 542.5 99.8 375 110 0.29 0.20

1989 318.2 76.2 1,102 507 0.46 1.59

1990 536.0 96.9 336 94 0.28 0.18

1991 429.4 80.8 964 465 0.48 1.08

1992 528.3 97.5 454 114 0.25 0.22

1993 458.1 84.4 954 494 0.52 1.08

1994 471.3 87.0 788 395 0.50 0.84

1995 564.7 100.0 200 44 0.22 0.08

1996 461.6 86.9 757 240 0.32 0.52

1997 417.4 75.9 399 106 0.27 0.25

1998 470.2 88.1 674 209.137 0.31 0.44

1999 530.7 92.9 451 70.075 0.16 0.13

2000 483.2 84.2 792 216.136 0.27 0.45

2001 441.3 78.5 834 220.683 0.26 0.50

2002 571.0 99.0 399 40.030 0.10 0.07

2003 522.8 91.7 858 168.896 0.20 0.32

2004 573.2 99.2 279 35.081 0.13 0.06

2005 509.4 90.0 919 175.201 0.19 0.34 

2006 579.1 100.0 273 33.416 0.12 0.06

2007 478.6 85.0 1,075 191.398 0.18 0.40

2008 555.3 95.8 351 43.777 0.12 0.08

NINE MILE POINT 1, 2 1970 227.0 821 44 0.05 0.19

Docket 50-220, 50-410; 1971 346.5 1,006 195 0.19 0.56

DPR-63; NPF-69 1972 381.8 735 285 0.39 0.75

1st commercial operation 1973 411.0 550 567 1.03 1.38

12/69, 4/88 1974 385.9 70.5 740 824 1.11 2.14

Type - BWRs 1975 359.0 72.1 649 681 1.05 1.90

Capacity - 565, 1,120 MWe 1976 484.6 88.2 392 428 1.09 0.88
C-24

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

NINE MILE POINT 1, 2 1977 347.4 59.2 1,093 1,383 1.27 3.98

(continued) 1978 527.7 95.1 561 314 0.56 0.60

1979 354.0 66.1 1,326 1,497 1.13 4.23

1980 533.9 92.3 1,174 591 0.50 1.11

1981 385.2 66.0 2,029 1,592 0.78 4.13

1982 133.5 21.4 1,352 1,264 0.93 9.47

1983 329.8 56.2 1,405 860 0.61 2.61

1984 426.8 71.9 1,530 890 0.58 2.09

1985 580.9 96.4 1,007 265 0.26 0.46

1986 371.0 65.3 1,878 1,275 0.68 3.44

1987 542.6 93.3 1,190 141 0.12 0.26

1988 0.0 0.0 2,626 854 0.33 ---

1989 527.5 29.7 2,737 564 0.21 1.07

1990 656.2 46.6 2,405 699 0.29 1.07

1991 1,250.8 79.7 1,543 292 0.19 0.23

1992 965.9 61.8 1,800 563 0.31 0.58

1993 1,380.2 84.6 2,352 633 0.27 0.46

1994 1,589.6 95.9 800 149 0.19 0.09

1995 1,382.2 82.5 2,304 759 0.33 0.55

1996 1,598.6 91.6 1,596 290 0.18 0.18

1997 1,321.5 74.8 1,425 429 0.30 0.32

1998 1,387.3 87.0 1,744 378.484 0.22 0.27

1999 1,409.5 81.3 1,709 446.699 0.26 0.32

2000 1,443.9 88.1 1,783 282.838 0.16 0.20

2001 1,506.9 88.9 1,371 343.197 0.25 0.23

2002 1,517.0 90.4 2,449 516.663 0.21 0.34

2003 1,585.6 91.4 1,501 374.775 0.25 0.24

2004 1,551.9 92.0 1,362 448.509 0.33 0.29

2005 1,656.5 94.5 1,366 401.719 0.29 0.24 

2006 1,647.1 96.0 1,130 229.551 0.20 0.14

2007 1,598.3 93.0 1,826 329.307 0.18 0.21

2008 1,642.1 95.8 1,391 301.824 0.22 0.18

NORTH ANNA 1, 2 1979 507.0 61.7 2,025 449 0.22 0.89

Docket 50-338; NPF-04, -07 1980 681.8 86.5 2,086 218 0.10 0.32

1st commercial operation 1981 1,241.9 71.5 2,416 680 0.28 0.55

6/78, 12/80 1982 777.7 45.8 2,872 1,915 0.67 2.46

Type - PWRs 1983 1,338.4 76.1 2,228 665 0.30 0.50

Capacity - 903, 903 MWe 1984 1,021.3 58.8 3,062 1,945 0.64 1.90

1985 1,516.9 86.1 2,436 838 0.34 0.55

1986 1,484.5 83.0 2,831 722 0.26 0.49

1987 1,112.6 67.8 2,624 1,521 0.58 1.37

1988 1,772.7 96.7 992 112 0.11 0.06

1989 1,226.8 72.5 2,861 1,471 0.51 1.20

1990 1,590.4 90.5 2,161 590 0.27 0.37

1991 1,597.5 88.6 2,085 629 0.30 0.39

1992 1,403.2 84.1 2,159 576 0.27 0.41

1993 1,428.4 80.1 2,768 908 0.33 0.64

1994 1,717.1 95.9 1,036 193 0.19 0.11

1995 1,666.4 90.8 1,551 367 0.24 0.22

1996 1,569.6 89.1 1,203 291 0.24 0.19

1997 1,711.5 96.2 856 103 0.12 0.06

1998 1,632.8 92.7 1,201 265.922 0.22 0.16

1999 1,747.7 96.1 727 94.402 0.13 0.05

2000 1,734.1 95.8 730 65.405 0.09 0.04

2001 1,491.0 84.8 1,231 308.907 0.25 0.21

2002 1,557.0 84.3 914 143.312 0.16 0.09

2003 1,569.1 87.2 1,041 187.014 0.18 0.12

2004 1,685.6 92.0 965 129.686 0.13 0.08

2005 1,751.5 96.0 686 58.844 0.09 0.03 

2006 1,723.0 95.0 749 82.069 0.11 0.05

2007 1,596.7 88.0 1,581 309.237 0.20 0.19

2008 1,643.1 91.2 795 61.003 0.08 0.04
C-25

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

OCONEE 1, 2, 3 1974 650.6 60.1 844 517 0.61 0.79

Docket 50-269, 50-270, 1975 1,838.3 75.5 829 497 0.60 0.27

50-287; 1976 1,561.4 63.0 1,215 1,026 0.84 0.66

DPR-38, -47, -55 1977 1,566.4 65.9 1,595 1,329 0.83 0.85

1st commercial operation 1978 1,909.0 75.8 1,636 1,393 0.85 0.73

7/73, 9/74, 12/74 1979 1,708.0 67.7 2,100 1,001 0.48 0.59

Type - PWRs 1980 1,703.7 70.1 2,124 1,055 0.50 0.62

Capacity - 846, 846, 846 MWe 1981 1,661.5 66.8 2,445 1,211 0.50 0.73

1982 1,293.1 52.5 2,445 1,792 0.73 1.39

1983 2,141.5 82.2 1,902 1,207 0.63 0.56

1984 2,242.9 85.7 2,085 1,106 0.53 0.49

1985 2,036.3 80.5 2,729 1,304 0.48 0.64

1986 1,995.6 79.0 2,499 949 0.38 0.48

1987 1,962.6 82.4 2,672 1,142 0.43 0.58

1988 2,228.9 87.2 2,672 871 0.33 0.39

1989 2,188.6 85.4 2,205 684 0.31 0.31

1990 2,405.2 91.4 1,948 404 0.21 0.17

1991 2,275.0 86.7 1,966 551 0.28 0.24

1992 2,110.7 82.0 1,954 612 0.31 0.29

1993 2,399.2 91.3 1,499 237 0.16 0.10

1994 2,144.3 82.2 1,923 537 0.28 0.25

1995 2,366.1 89.5 1,586 304 0.19 0.13

1996 1,847.9 70.3 1,479 257 0.17 0.14

1997 1,563.7 67.7 1,379 223 0.16 0.14

1998 1,989.1 81.3 1,695 366.028 0.22 0.18

1999 2,264.5 90.3 1,568 202.025 0.13 0.09

2000 2,321.0 91.6 1,686 272.697 0.16 0.12

2001 2,167.6 86.8 2,002 579.209 0.29 0.27

2002 2,355.0 92.5 1,723 224.672 0.13 0.10

2003 2,177.7 86.3 2,180 245.349 0.11 0.11

2004 2,125.2 84.1 2,295 367.891 0.16 0.17

2005 2,349.5 92.3 1,516 148.694 0.10 0.06 

2006 2,274.8 90.0 1,859 221.222 0.12 0.10

2007 2,347.8 92.0 1,915 252.936 0.13 0.11

2008 2298.5 90.9 1,924 186.335 0.10 0.08

OYSTER CREEK 1970 413.6 95 63 0.66 0.15

Docket 50-219; DPR-16 1971 448.9 249 240 0.96 0.53

1st commercial operation 12/69 1972 515.0 339 582 1.72 1.13

Type - BWR 1973 424.6 782 1,236 1.58 2.91

Capacity - 619 MWe 1974 434.5 70.4 935 984 1.05 2.26

1975 373.6 73.3 1,210 1,140 0.94 3.05

1976 456.5 79.3 1,582 1,078 0.68 2.36

1977 385.7 70.1 1,673 1,614 0.96 4.18

1978 431.8 74.3 1,411 1,279 0.91 2.96

1979 541.0 85.9 842 467 0.55 0.86

1980 232.9 41.4 1,966 1,733 0.88 7.44

1981 314.8 59.8 1,689 917 0.54 2.91

1982 242.7 62.5 1,270 865 0.68 3.56

1983 27.9 11.5 2,303 2,257 0.98 80.90

1984 37.1 9.6 2,369 2,054 0.87 55.36

1985 446.1 89.4 2,342 748 0.32 1.68

1986 157.3 31.5 3,740 2,436 0.65 15.49

1987 371.0 64.2 1,932 522 0.27 1.41

1988 419.6 65.9 2,875 1,504 0.52 3.58

1989 287.5 57.3 2,395 910 0.38 3.17

1990 511.8 89.1 1,941 310 0.16 0.61

1991 351.6 60.5 3,089 1,185 0.38 3.37

1992 536.3 85.9 2,771 657 0.24 1.23

1993 551.9 87.8 2,560 416 0.16 0.75

1994 431.7 70.8 2,382 844 0.35 1.96

1995 615.4 97.4 761 90 0.12 0.15

1996 515.0 82.6 1,833 449 0.24 0.87
C-26

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

OYSTER CREEK 1997 579.1 94.3 509 50 0.10 0.09

(continued) 1998 490.8 82.4 1,408 308.323 0.22 0.63

1999 615.1 100.0 466 41.664 0.09 0.07

2000 444.9 83.3 2,044 614.379 0.30 1.38

2001 595.0 97.6 442 45.817 0.10 0.08

2002 573.0 94.0 1,468 265.810 0.18 0.46

2003 598.4 97.2 416 43.363 0.10 0.07

2004 551.8 91.6 1,346 226.880 0.17 0.41

2005 611.9 99.5 316 27.813 0.09 0.05 

2006 530.2 90.0 1,443 189.950 0.13 0.36

2007 579.7 97.0 464 46.590 0.10 0.08

2008 531.0 91.0 1,511 211.932 0.14 0.40

PALISADES 1972 216.8 78 0.36

Docket 50-255; DPR-20 1973 286.8 975 1,133 1.16 3.95

1st commercial operation 12/71 1974 10.7 5.5 774 627 0.81 58.60

Type - PWR 1975 302.0 64.5 495 306 0.62 1.01

Capacity - 730 MWe 1976 346.9 55.2 742 696 0.94 2.01

1977 616.6 91.4 332 100 0.30 0.16

1978 320.2 49.7 849 764 0.90 2.39

1979 415.0 59.9 1,599 854 0.53 2.06

1980 288.3 42.9 1,307 424 0.32 1.47

1981 418.2 57.2 2,151 902 0.42 2.16

1982 404.3 54.7 1,554 330 0.21 0.82

1983 454.4 60.3 2,167 977 0.45 2.15

1984 98.7 15.2 1,344 573 0.43 5.81

1985 639.2 83.8 1,355 507 0.37 0.79

1986 102.3 15.1 1,438 672 0.47 6.57

1987 319.2 48.2 1,122 456 0.41 1.43

1988 413.4 56.8 1,472 730 0.50 1.77

1989 442.8 69.1 1,026 314 0.31 0.71

1990 366.7 58.7 2,414 766 0.32 2.09

1991 587.0 78.1 1,315 211 0.16 0.36

1992 581.9 76.1 1,267 295 0.23 0.51

1993 424.4 53.7 908 289 0.32 0.68

1994 541.8 67.0 397 60 0.15 0.11

1995 583.5 75.8 1,230 462 0.38 0.79

1996 638.2 81.4 1,109 318 0.29 0.50

1997 662.5 89.9 338 48 0.14 0.07

1998 615.4 83.5 895 216.563 0.24 0.35

1999 585.4 80.2 939 218.451 0.23 0.37

2000 654.4 88.0 255 26.305 0.10 0.04

2001 268.2 36.3 1,032 362.723 0.35 1.35

2002 725.0 94.8 224 24.380 0.11 0.03

2003 701.1 90.7 822 202.571 0.25 0.29

2004 608.6 82.3 974 370.895 0.38 0.61

2005 756.6 98.0 156 10.459 0.07 0.01 

2006 675.5 86.0 882 239.652 0.27 0.36

2007 665.6 85.0 1,065 256.632 0.24 0.39

2008 778.4 98.2 272 23.478 0.09 0.03

PALO VERDE 1, 2, 3 1987 1,638.1 66.1 1,792 669 0.37 0.41

Docket 50-528, 50-529, 50-530; 1988 1,700.9 65.5 2,173 688 0.32 0.40

NPF-41, -51, -74 1989 965.3 26.5 2,615 720 0.28 0.75

1st commercial operation 1990 2,500.9 67.5 2,236 499 0.22 0.20

1/86, 9/86, 1/88 1991 3,043.9 78.9 2,242 605 0.27 0.20

Type - PWRs 1992 3,102.3 82.0 1,981 541 0.27 0.17

Capacity - 1,311, 1,314, 1993 2,677.1 74.3 2,124 592 0.28 0.22

1,317 MWe 1994 2,827.6 79.1 2,048 462 0.23 0.16

1995 3,265.2 85.6 1,875 482 0.26 0.15

1996 3,482.7 90.0 1,717 302 0.18 0.09

1997 3,369.2 92.2 1,585 246 0.16 0.07

1998 3,454.4 93.2 1,410 192.425 0.14 0.06

1999 3,471.2 93.2 1,275 146.328 0.11 0.04
C-27

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

PALO VERDE 1, 2, 3 2000 3,458.6 93.0 1,279 158.105 0.12 0.05

(continued) 2001 3,280.2 88.6 1,361 182.043 0.13 0.06

2002 3,513.0 94.0 1,343 140.057 0.10 0.04

2003 3,254.4 88.6 1,943 210.842 0.11 0.06

2004 3,201.4 86.3 1,324 199.016 0.15 0.06

2005 2,937.6 80.4 2,014 200.300 0.10 0.07 

2006 2,741.1 79.0 1,585 151.516 0.10 0.06

2007 3,058.5 81.0 2,372 148.660 0.06 0.05

2008 3,330.0 86.1 1,706 159.913 0.09 0.05

PEACH BOTTOM 2, 3 1975 1,234.3 80.9 971 228 0.23 0.18

Docket 50-277, 50-278; 1976 1,379.2 73.0 2,136 840 0.39 0.61

DPR-44, -56 1977 1,052.4 58.7 2,827 2,036 0.72 1.93

1st commercial operation 1978 1,636.3 84.0 2,244 1,317 0.59 0.80

7/74, 12/74 1979 1,740.0 84.5 2,276 1,388 0.61 0.80

Type - BWRs 1980 1,374.2 66.3 2,774 2,302 0.83 1.68

Capacity - 1,112, 1,112 MWe 1981 1,161.8 58.0 2,857 2,506 0.88 2.16

1982 1,583.3 76.9 2,734 1,977 0.72 1.25

1983 824.7 41.0 3,107 2,963 0.95 3.59

1984 1,165.8 57.5 3,313 2,450 0.74 2.10

1985 682.7 37.5 4,209 3,354 0.80 4.91

1986 1,395.0 71.7 2,454 1,080 0.44 0.77

1987 365.7 20.3 4,363 2,195 0.50 6.00

1988 0.0 0.0 4,204 2,327 0.55 ---

1989 491.0 35.0 2,301 728 0.32 1.48

1990 1,684.0 85.7 1,585 377 0.24 0.22

1991 1,210.9 62.3 2,702 934 0.35 0.77

1992 1,516.6 78.7 1,911 502 0.26 0.33

1993 1,654.0 81.9 1,757 552 0.31 0.33

1994 1,927.4 93.8 2,133 579 0.27 0.30

1995 1,955.9 95.1 1,940 398 0.21 0.20

1996 2,012.4 96.9 1,657 282 0.17 0.14

1997 1,956.3 95.0 1,872 490 0.26 0.25

1998 1,881.2 93.2 1,903 366.040 0.19 0.19

1999 2,057.2 96.0 1,630 319.307 0.20 0.16

2000 2,058.3 96.7 1,729 330.928 0.19 0.16

2001 2,037.1 95.8 1,445 344.283 0.24 0.17

2002 2,105.0 96.7 1,915 333.056 0.17 0.16

2003 2,072.4 94.9 1,641 355.969 0.22 0.17

2004 2,148.8 96.4 1,422 264.727 0.19 0.12

2005 2,102.0 95.6 1,801 306.201 0.17 0.15 

2006 2,169.1 97.0 1,513 247.676 0.16 0.11

2007 2,163.8 97.0 1,906 384.795 0.20 0.18

2008 2,115.3 95.1 1,816 212.741 0.12 0.10

PERRY 1988 869.3 79.0 782 105 0.13 0.12

Docket 50-440; NPF-58 1989 642.2 57.0 1,883 767 0.41 1.19

1st commercial operation 11/87 1990 792.7 67.1 1,537 638 0.42 0.80

Type - BWR 1991 1,074.2 91.9 600 146 0.24 0.14

Capacity - 1,245 MWe 1992 856.2 75.5 1,487 571 0.38 0.67

1993 479.2 48.2 1,235 278 0.23 0.58

1994 550.8 50.2 2,098 691 0.33 1.25

1995 1,090.9 95.6 587 64 0.11 0.06

1996 895.6 77.2 1,622 307 0.19 0.34

1997 930.6 84.7 1,524 272 0.18 0.29

1998 1,163.1 99.3 385 41.945 0.11 0.04

1999 1,041.7 89.9 1,758 326.014 0.19 0.31

2000 1,148.2 97.1 501 55.827 0.11 0.05

2001 885.9 79.6 1,392 258.268 0.19 0.29

2002 1,136.0 95.0 436 70.258 0.16 0.06

2003 973.7 83.8 1,880 607.384 0.32 0.62

2004 1,164.3 95.9 496 73.481 0.15 0.06

2005 872.9 73.8 1,734 416.608 0.24 0.48 

2006 1,195.8 99.0 488 65.152 0.13 0.05
C-28

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

PERRY 2007 919.7 79.0 1,650 505.121 0.31 0.55

(continued) 2008 1,215.9 97.9 528 52.058 0.10 0.04

PILGRIM 1 1973 484.0 230 126 0.55 0.26

Docket 50-293; DPR-35 1974 234.1 39.2 454 415 0.91 1.77

1st commercial operation 12/72 1975 308.1 71.3 473 798 1.69 2.59

Type - BWR 1976 287.8 60.7 1,317 2,648 2.01 9.20

Capacity - 685 MWe 1977 316.6 61.4 1,875 3,142 1.68 9.92

1978 519.5 83.1 1,667 1,327 0.80 2.55

1979 574.0 89.4 2,458 1,015 0.41 1.77

1980 360.3 56.2 3,549 3,626 1.02 10.06

1981 408.9 65.9 2,803 1,836 0.66 4.49

1982 389.9 63.9 2,854 1,539 0.54 3.95

1983 559.5 87.2 2,326 1,162 0.50 2.08

1984 1.4 0.4 4,542 4,082 0.90 2,915.71

1985 587.3 91.5 2,209 893 0.40 1.52

1986 121.9 18.8 2,635 874 0.33 7.17

1987 0.0 0.0 4,710 1,579 0.34 ---

1988 0.0 0.0 2,073 392 0.19 ---

1989 204.6 64.1 1,797 207 0.12 1.01

1990 503.5 82.1 1,898 225 0.12 0.45

1991 406.3 65.8 2,836 605 0.21 1.49

1992 561.0 85.4 1,332 281 0.21 0.50

1993 513.7 80.9 1,328 435 0.33 0.85

1994 453.6 71.4 758 200 0.26 0.44

1995 531.7 80.7 1,294 482 0.37 0.91

1996 631.3 95.4 517 116 0.22 0.18

1997 492.1 80.7 1,655 588 0.36 1.19

1998 650.5 100.0 530 71.446 0.13 0.11

1999 510.7 84.4 1,222 344.270 0.28 0.67

2000 627.5 98.3 422 50.797 0.12 0.08

2001 585.6 91.0 1,113 179.585 0.16 0.31

2002 657.0 100.0 463 38.280 0.08 0.06

2003 566.6 87.5 1,437 250.192 0.17 0.44

2004 676.1 99.5 427 41.109 0.10 0.06

2005 623.2 93.7 1,212 206.089 0.17 0.33 

2006 665.4 100.0 654 43.531 0.07 0.07

2007 584.5 90.0 1,407 240.526 0.17 0.41

2008 668.1 99.0 377 22.568 0.06 0.03

POINT BEACH 1, 2 1971 393.4 164 0.42

Docket 50-266, 50-301; 1972 378.3 580 1.53

DPR-24, -27 1973 693.7 501 588 1.17 0.85

1st commercial operation 1974 760.2 81.3 400 295 0.74 0.39

12/70, 10/72 1975 801.2 82.9 339 459 1.35 0.57

Type - PWRs 1976 857.3 86.7 313 370 1.18 0.43

Capacity - 516, 518 MWe 1977 873.9 87.3 417 430 1.03 0.49

1978 914.4 90.9 336 320 0.95 0.35

1979 808.0 80.8 610 644 1.06 0.80

1980 727.2 82.5 561 598 1.07 0.82

1981 760.4 83.6 773 596 0.77 0.78

1982 757.2 84.3 767 609 0.79 0.80

1983 648.2 72.7 1,702 1,403 0.82 2.16

1984 788.9 78.6 1,372 789 0.58 1.00

1985 831.3 82.5 671 482 0.72 0.58

1986 858.9 85.7 664 402 0.61 0.47

1987 857.5 85.5 720 554 0.77 0.65

1988 899.3 88.6 734 410 0.56 0.46

1989 847.8 85.5 736 504 0.68 0.59

1990 875.5 86.5 617 378 0.61 0.43

1991 874.8 87.1 724 265 0.37 0.30

1992 866.7 85.8 617 256 0.41 0.30

1993 911.0 90.0 559 186 0.33 0.20

1994 914.5 91.2 548 170 0.31 0.19
C-29

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

POINT BEACH 1, 2 1995 858.4 86.1 548 190 0.35 0.22

(continued) 1996 831.6 84.7 1,029 276 0.27 0.33

1997 186.8 21.8 670 92 0.14 0.49

1998 649.7 69.7 881 169.253 0.19 0.26

1999 806.0 83.1 962 194.489 0.20 0.24

2000 872.0 88.7 765 138.989 0.18 0.16

2001 915.9 93.4 740 131.667 0.18 0.14

2002 909.0 91.1 945 180.654 0.19 0.20

2003 917.2 92.1 627 84.965 0.14 0.09

2004 912.3 90.1 627 109.515 0.17 0.12

2005 782.5 78.1 851 128.646 0.15 0.16

2006 977.2 96.0 453 39.597 0.09 0.04

2007 958.5 94.0 535 52.023 0.10 0.05

2008 889.4 87.8 958 144.021 0.15 0.16

PRAIRIE ISLAND 1, 2 1974 181.9 43.9 150 18 0.12 0.10

Docket 50-282, 50-306; 1975 836.0 83.3 477 123 0.26 0.15

DPR-42, -60 1976 725.2 76.6 818 447 0.55 0.62

1st commercial operation 1977 922.9 87.2 718 300 0.42 0.33

12/73, 12/74 1978 941.1 92.2 546 221 0.40 0.23

Type - PWRs 1979 865.0 86.0 594 180 0.30 0.21

Capacity - 522, 522 MWe 1980 800.7 79.9 983 353 0.36 0.44

1981 844.9 80.5 836 329 0.39 0.39

1982 944.9 90.4 645 229 0.36 0.24

1983 921.1 86.8 654 233 0.36 0.25

1984 972.4 91.7 546 147 0.27 0.15

1985 882.6 84.0 1,082 416 0.38 0.47

1986 930.6 90.3 818 255 0.31 0.27

1987 969.6 91.6 593 135 0.23 0.14

1988 932.0 89.1 732 199 0.27 0.21

1989 1,001.8 94.7 476 99 0.21 0.10

1990 925.4 89.2 737 188 0.26 0.20

1991 1,023.3 95.6 586 98 0.17 0.10

1992 811.6 76.2 845 211 0.25 0.26

1993 978.3 90.7 532 106 0.20 0.11

1994 996.9 91.5 478 109 0.10 0.11

1995 1,023.2 93.9 499 107 0.21 0.10

1996 992.1 91.4 558 112 0.20 0.11

1997 817.6 81.4 753 174 0.23 0.21

1998 860.3 83.4 582 116.649 0.20 0.14

1999 989.3 93.8 542 72.496 0.13 0.07

2000 992.2 93.1 632 106.091 0.17 0.11

2001 900.8 85.8 691 124.708 0.18 0.14

2002 987.0 93.6 969 127.713 0.13 0.13

2003 1,006.1 96.4 594 61.137 0.10 0.06

2004 940.4 89.9 1,186 143.806 0.12 0.15

2005 952.5 90.8 782 84.337 0.11 0.09

2006 926.4 89.0 1,103 137.352 0.12 0.15

2007 1,014.8 98.0 130 6.276 0.05 0.01

2008 924.3 88.9 1,060 126.723 0.12 0.14

QUAD CITIES 1, 2 1974 958.1 72.3 678 482 0.71 0.50

Docket 50-254, 50-265; 1975 833.6 68.4 1,083 1,618 1.49 1.94

DPR-29, -30 1976 951.2 73.1 1,225 1,651 1.35 1.74

1st commercial operation 1977 970.1 84.0 907 1,031 1.14 1.06

 2/73, 3/73 1978 1,124.5 88.6 1,207 1,618 1.34 1.44

Type - BWRs 1979 1,075.0 84.6 1,688 2,158 1.28 2.01

Capacity - 866, 871 MWe 1980 866.9 64.4 3,089 4,838 1.57 5.58

1981 1,156.9 81.1 2,246 3,146 1.40 2.72

1982 1,018.7 76.0 2,314 3,757 1.62 3.69

1983 1,088.5 79.2 1,802 2,491 1.38 2.29

1984 994.6 65.7 1,678 1,579 0.94 1.59

1985 1,268.0 82.7 1,184 990 0.84 0.78

1986 1,093.2 71.0 1,451 950 0.65 0.87
C-30

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

QUAD CITIES 1, 2 1987 1,126.6 75.3 1,429 720 0.50 0.64

(continued) 1988 1,173.7 84.1 1,486 827 0.56 0.70

1989 1,196.3 85.9 1,721 900 0.52 0.75

1990 1,148.9 77.8 2,186 1,028 0.47 0.89

1991 1,044.5 73.2 1,722 509 0.30 0.49

1992 960.8 68.0 2,413 1,157 0.48 1.20

1993 974.9 67.0 2,150 849 0.39 0.87

1994 681.5 48.7 2,163 1,128 0.52 1.66

1995 1,002.5 70.4 2,041 736 0.36 0.73

1996 876.6 60.1 2,248 1,025 0.46 1.17

1997 935.3 66.5 2,474 654 0.26 0.70

1998 794.8 55.1 2,177 760.596 0.35 0.96

1999 1,476.5 95.9 1,000 200.556 0.20 0.14

2000 1,410.4 93.9 2,840 893.766 0.32 0.63

2001 1,478.2 95.9 736 143.849 0.20 0.10

2002 1,396.0 89.0 3,818 1,786.021 0.47 1.28

2003 1,569.4 93.1 998 438.144 0.44 0.28

2004 1,443.8 95.5 2,334 510.521 0.22 0.35

2005 1,516.2 94.2 2,869 961.026 0.33 0.63 

2006 1,524.9 93.0 2,329 559.362 0.24 0.37

2007 1,650.3 97.0 1,945 249.927 0.13 0.15

2008 1,619.4 95.2 2,065 274.444 0.13 0.17

RANCHO SECO12 1976 268.1 30.4 297 58 0.20 0.22

Docket 50-312; DPR-54 1977 706.4 77.1 515 391 0.76 0.55

1st commercial operation 4/75 1978 607.7 80.5 508 323 0.64 0.53

Type - PWR 1979 687.0 91.1 287 126 0.44 0.18

Capacity - (873) MWe 1980 530.9 60.4 890 412 0.46 0.78

1981 321.2 40.2 772 402 0.52 1.25

1982 409.5 53.3 766 337 0.44 0.82

1983 347.9 46.8 1,338 787 0.59 2.26

1984 460.0 58.3 802 222 0.28 0.48

1985 238.7 30.8 1,764 756 0.43 3.17

1986 0.0 0.0 1,513 402 0.27 ---

1987 0.0 0.0 1,533 300 0.20 ---

1988 355.8 63.1 693 78 0.11 0.22

1989 179.9 54.7 603 81 0.13 0.45

1990 0.0 0.0 111 13 0.12 ---

1991 0.0 0.0 101 9 0.09 ---

1992 0.0 0.0 70 7 0.10 ---

1993 0.0 0.0 35 4 0.11 ---

1994 0.0 0.0 18 1 0.23 --- 

1995 0.0 0.0 16 1 0.06 ---

1996 0.0 0.0 16 1 0.04 ---

1997 0.0 0.0 16 0 0.00 ---

1998 0.0 0.0 61 2.661 0.05 ---

1999 0.0 0.0 302 11.191 0.04 ---

2000 0.0 0.0 219 25.795 0.12 ---

2001 0.0 0.0 210 18.432 0.09 ---

2002 0.0 0.0 193 27.346 0.14 ---

2003 0.0 0.0 121 18.300 0.15 ---

2004 0.0 0.0 122 14.890 0.12 ---

2005 0.0 0.0 157 33.444 0.21 --- 

2006 0.0 0.0 143 31.793 0.22 --- 

2007 0.0 0.0 129 12.524 0.10 ---

2008 0.0 0.0 84 2.434 0.03 ---

12 Rancho Seco was shut down in June 1989 and is no longer in the count of operating reactors. Parentheses indicate plant 

capacity when plant was operational.
C-31

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

RIVER BEND 1 1987 605.2 68.4 1,268 378 0.30 0.62

Docket 50-458; NPF-47 1988 880.7 94.3 513 107 0.21 0.12

1st commercial operation 6/86 1989 584.5 69.1 1,566 558 0.36 0.95

Type - BWR 1990 682.2 78.0 1,616 489 0.30 0.72

Capacity - 967 MWe 1991 814.7 87.2 780 144 0.18 0.18

1992 336.1 39.7 2,022 710 0.35 2.11

1993 640.0 71.6 847 180 0.21 0.28

1994 595.7 64.9 2,209 519 0.23 0.87

1995 967.1 99.6 667 85 0.13 0.09

1996 836.1 85.3 2,093 473 0.23 0.57

1997 778.8 86.3 1,671 347 0.21 0.45

1998 894.2 96.2 466 57.749 0.12 0.06

1999 651.2 75.2 1,327 343.858 0.26 0.53

2000 837.1 89.7 1,104 216.053 0.20 0.26

2001 889.3 93.6 1,249 207.614 0.17 0.23

2002 965.0 98.5 373 35.145 0.09 0.04

2003 871.3 92.7 1,296 216.950 0.17 0.25

2004 845.6 90.1 1,378 235.749 0.17 0.28

2005 890.5 94.4 498 55.816 0.11 0.06 

2006 853.7 92.0 1,494 214.409 0.14 0.25

2007 823.0 92.0 1,131 131.373 0.12 0.16

2008 724.8 78.7 1,809 311.697 0.17 0.43

ROBINSON 2 1972 580.0 245 215 0.88 0.37

Docket 50-261; DPR-23 1973 455.1 831 695 0.84 1.53

1st commercial operation 3/71 1974 578.1 83.3 853 672 0.79 1.16

Type - PWR 1975 501.8 72.7 849 1,142 1.35 2.28

Capacity - 710 MWe 1976 585.5 84.7 597 715 1.20 1.22

1977 511.5 85.2 634 455 0.72 0.89

1978 480.5 72.0 943 963 1.02 2.00

1979 482.0 70.8 1,454 1,188 0.82 2.46

1980 387.3 62.2 2,009 1,852 0.92 4.78

1981 426.6 73.0 1,462 733 0.50 1.72

1982 277.5 48.9 2,011 1,426 0.71 5.14

1983 409.8 75.5 2,244 923 0.41 2.25

1984 28.0 7.0 4,127 2,880 0.70 102.86

1985 629.5 87.9 1,378 311 0.23 0.49

1986 577.1 80.3 1,571 539 0.34 0.93

1987 510.1 72.5 1,379 499 0.36 0.98

1988 385.0 65.9 1,351 564 0.42 1.46

1989 336.6 48.7 1,098 195 0.18 0.58

1990 400.3 64.8 1,626 437 0.27 1.09

1991 575.1 81.4 885 193 0.22 0.34

1992 487.2 66.8 1,267 352 0.28 0.72

1993 502.7 70.7 1,221 337 0.28 0.67

1994 560.3 79.5 420 63 0.15 0.11

1995 618.7 84.7 1,058 215 0.20 0.35

1996 654.8 88.6 1,031 167 0.16 0.26

1997 707.5 99.0 304 13 0.04 0.02

1998 628.5 88.9 978 170.476 0.17 0.27

1999 648.9 91.8 807 123.952 0.15 0.19

2000 710.0 99.7 138 8.396 0.06 0.01

2001 627.9 90.6 827 124.750 0.15 0.20

2002 638.0 91.2 830 110.631 0.13 0.17

2003 733.1 100.0 109 4.838 0.04 0.01

2004 653.7 89.3 952 118.159 0.12 0.18

2005 656.9 89.7 791 64.662 0.08 0.10 

2006 735.5 100.0 86 3.320 0.04 0.01

2007 655.0 90.0 890 80.752 0.09 0.12

2008 618.1 84.6 788 68.381 0.09 0.11
C-32

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

SALEM 1, 2 1978 546.4 55.6 574 122 0.21 0.22

Docket 50-272, -311; 1979 250.0 25.5 1,488 584 0.39 2.34

DPR-70, -75 1980 680.6 69.2 1,704 449 0.26 0.66

1st commercial operation 1981 743.0 78.1 1,652 254 0.15 0.34

6/77, 10/81 1982 1,440.4 72.6 3,228 1,203 0.37 0.84

Type - PWRs 1983 742.0 30.5 2,383 581 0.24 0.78

Capacity - 1,116, 1,134 MWe 1984 650.1 31.8 1,395 681 0.49 1.05

1985 1,657.7 75.8 1,112 204 0.18 0.12

1986 1,484.3 70.4 3,554 599 0.17 0.40

1987 1,478.2 73.3 2,543 600 0.24 0.41

1988 1,591.6 73.6 1,609 503 0.31 0.32

1989 1,675.4 79.5 2,944 338 0.11 0.20

1990 1,362.6 65.1 3,636 272 0.07 0.20

1991 1,726.4 79.3 4,201 458 0.11 0.27

1992 1,200.9 61.1 4,376 431 0.10 0.36

1993 1,366.3 65.4 3,559 408 0.11 0.30

1994 1,367.4 73.8 950 188 0.20 0.14

1995 558.1 29.3 1,195 218 0.18 0.39

1996 0.0 0.0 1,671 300 0.18 ---

1997 279.3 17.8 894 175 0.20 0.63

1998 1,629.3 79.1 408 41.100 0.10 0.03

1999 1,821.8 86.8 1,200 317.545 0.27 0.17

2000 1,973.4 93.0 1,191 198.068 0.17 0.10

2001 1,961.2 91.1 1,274 153.088 0.12 0.08

2002 1,934.0 89.4 2,460 292.692 0.12 0.15

2003 1,957.2 90.7 1,301 124.042 0.10 0.06

2004 1,850.2 85.8 1,496 148.694 0.10 0.08

2005 2,086.4 91.7 3,162 240.567 0.08 0.12 

2006 2,211.8 97.0 1,446 90.541 0.06 0.04

2007 2,158.2 96.0 1,365 117.604 0.09 0.05

2008 1,998.6 87.8 3,362 328.761 0.10 0.16

SAN ONOFRE 113, 2, 3 1969 314.1 123 42 0.34 0.13

Docket 50-206, -361, -362; 1970 365.9 251 155 0.62 0.42

DPR-13; NPF-10, -15 1971 362.1 121 50 0.41 0.14

1st commercial operation 1972 338.5 326 256 0.79 0.76

1/68, 8/83, 4/84 1973 273.7 570 353 0.62 1.29

Type - PWRs 1974 377.8 86.1 219 71 0.32 0.19

Capacity - (436), 1,070, 1975 389.0 87.4 424 292 0.69 0.75

1,080 MWe 1976 297.9 70.2 1,330 880 0.66 2.95

1977 281.2 63.7 985 847 0.86 3.01

1978 323.2 80.2 764 401 0.52 1.24

1979 401.0 90.2 521 139 0.27 0.35

1980 97.3 22.3 3,063 2,386 0.78 24.52

1981 95.9 26.7 2,902 3,223 1.11 33.61

1982 61.6 15.7 3,055 832 0.27 13.51

1983 0.0 0.0 1,701 155 0.09 ---

1984 670.4 68.3 7,514 986 0.13 1.47

1985 1,381.8 132.9 5,742 722 0.13 0.52

1986 1,698.2 61.1 3,594 824 0.23 0.49

1987 1,983.0 78.8 2,138 696 0.33 0.35

1988 1,982.3 68.4 2,324 781 0.34 0.39

1989 1,840.8 64.9 2,237 567 0.25 0.31

1990 1,980.5 69.1 2,224 885 0.40 0.45

1991 1,987.6 75.3 1,814 412 0.23 0.21

1992 2,228.6 87.1 1,651 324 0.20 0.15

1993 1,771.3 79.9 2,193 767 0.35 0.43

1994 2,220.7 100.0 528 32 0.06 0.01

1995 1,686.9 79.1 1,914 455 0.24 0.27

13 San Onofre 1 was shut down in November 1992 and is no longer in the count of operating reactors. Parentheses indicate plant 

capacity when plant was operational.
C-33

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

SAN ONOFRE 113, 2, 3 1996 2,089.3 93.2 1,272 129 0.10 0.06

(continued) 1997 1,533.9 72.9 1,652 341 0.21 0.22

1998 1,996.4 92.0 1,091 195.600 0.18 0.10

SAN ONOFRE 113 1999 0.0 0.0 241 15.863 0.07 ---

Docket 50-206; 2000 0.0 0.0 416 71.214 0.17 ---

DPR-13 2001 0.0 0.0 338 57.785 0.17 ---

1st commercial operation 1/68 2002 0.0 0.0 308 61.214 0.20 ---

Type - PWR 2003 0.0 0.0 226 35.596 0.16 ---

Capacity - (436) MWe 2004 0.0 0.0 169 14.899 0.09 ---

2005 0.0 0.0 198 20.624 0.10 --- 

2006 0.0 0.0 183 22.490 0.12 ---

2007 0.0 0.0 20 0.417 0.02 ---

2008 0.0 0.0 2 0.043 0.02 ---

SAN ONOFRE 2, 3 1999 1,901.4 86.9 1,477 353.765 0.24 0.19

Docket 50-361, -362; 2000 2,067.2 94.7 1,073 115.499 0.11 0.06

NPF-10, -15 2001 1,727.2 78.9 1,083 131.384 0.12 0.08

1st commercial operation 2002 2,056.0 93.4 1,140 136.443 0.12 0.07

8/83, 4/84 2003 2,084.3 94.0 1,275 163.804 0.13 0.08

Type - PWRs 2004 1,713.8 79.1 1,761 407.063 0.23 0.24

Capacity - 1,070, 1,080 MWe 2005 2,094.7 96.0 305 11.332 0.04 0.01 

2006 1,552.2 73.0 1,632 315.087 0.19 0.20

2007 1,964.6 89.0 1,065 91.545 0.09 0.05

2008 1,753.0 82.7 1,014 125.320 0.12 0.07

SEABROOK 1991 810.4 75.9 699 92 0.13 0.11

Docket 50-443; NPF-86 1992 932.4 81.3 806 147 0.18 0.16

1st commercial operation 8/90 1993 1,071.5 93.6 110 6 0.05 0.01

Type - PWR 1994 736.4 63.5 852 113 0.13 0.15

Capacity - 1,243 MWe 1995 995.5 87.5 800 102 0.13 0.10

1996 1,168.6 99.6 206 10 0.05 0.01

1997 907.0 79.8 1,571 186 0.12 0.21

1998 957.6 84.5 559 18.509 0.03 0.02

1999 991.5 87.5 1,339 105.723 0.08 0.11

2000 901.8 79.3 1,158 70.091 0.06 0.08

2001 989.6 89.1 423 8.672 0.02 0.01

2002 1,058.0 92.8 1,095 66.583 0.06 0.06

2003 1,055.9 93.6 981 70.953 0.07 0.07

2004 1,158.6 100.0 291 5.858 0.02 0.01

2005 1,076.4 91.5 1,034 52.216 0.05 0.05

2006 1,072.8 89.0 1,246 76.583 0.06 0.07

2007 1,228.7 100.0 349 4.332 0.01 0.00

2008 1,064.4 86.9 1,297 74.992 0.06 0.07

SEQUOYAH 1, 2 1982 583.5 52.8 1,968 570 0.29 0.98

Docket 50-327, -328; 1983 1,663.7 75.1 1,769 491 0.28 0.30

DPR-77, -79 1984 1,481.9 69.0 2,373 1,119 0.47 0.76

1st commercial operation 1985 1,151.3 51.3 1,853 1,072 0.58 0.93

7/81, 6/82 1986 0.0 0.0 1,738 527 0.30 ---

Type - PWR 1987 0.0 0.0 2,080 420 0.20 ---

Capacity - 1,148, 1,126 MWe 1988 490.8 31.8 2,441 678 0.28 1.38

1989 1,851.7 85.7 2,007 657 0.33 0.35

1990 1,662.6 77.2 2,935 1,687 0.57 1.01

1991 1,965.4 88.0 1,933 700 0.36 0.36

1992 1,849.0 85.4 1,714 465 0.27 0.25

1993 405.7 21.8 1,631 373 0.23 0.92

1994 1,418.7 66.3 1,702 295 0.17 0.21

1995 1,864.2 86.1 1,650 368 0.22 0.20

1996 2,003.9 87.9 1,444 269 0.19 0.13

1997 1,946.1 89.0 1,962 420 0.21 0.22

1998 2,135.3 95.3 1,530 265.980 0.17 0.12

13 San Onofre 1 was shut down in November 1992 and is no longer in the count of operating reactors. Parentheses indicate plant 

capacity when plant was operational.
C-34

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

SEQUOYAH 1, 2 1999 2,165.1 97.0 1,346 164.569 0.12 0.08

(continued) 2000 1,910.0 86.8 2,039 357.220 0.18 0.19

2001 2,158.3 95.7 1,292 145.066 0.11 0.07

2002 2,106.0 94.1 1,257 108.252 0.09 0.05

2003 1,776.4 80.0 2,484 430.889 0.17 0.24

2004 2,135.2 93.9 1,161 85.941 0.07 0.04

2005 2,162.9 94.9 1,125 95.133 0.08 0.04 

2006 2,054.9 91.0 1,752 242.016 0.14 0.12

2007 2,129.1 94.0 1,197 123.540 0.10 0.06

2008 2,153.6 94.3 960 83.730 0.09 0.04

SOUTH TEXAS 1, 2 1989 769.3 65.6 989 161 0.16 0.21

Docket 50-498, 50-499; 1990 1,504.1 65.9 1,136 206 0.18 0.14

NPF -76, -80 1991 1,741.5 72.4 1,144 257 0.22 0.15

1st commercial operation 1992 2,096.0 83.8 923 147 0.16 0.07

8/88, 6/89 1993 163.1 8.3 1,138 251 0.22 1.54

Type - PWRs 1994 1,700.2 70.6 661 47 0.07 0.03

Capacity - 1,251, 1,251 MWe 1995 2,294.2 89.9 1,485 291 0.20 0.13

1996 2,465.9 95.0 1,145 137 0.12 0.06

1997 2,265.5 93.6 1,583 273 0.17 0.12

1998 2,379.4 96.9 1,171 183.977 0.16 0.08

1999 2,219.7 91.6 1,328 259.770 0.20 0.12

2000 2,180.0 89.7 1,372 231.634 0.17 0.11

2001 2,262.7 92.2 1,325 237.645 0.18 0.11

2002 2,173.0 87.5 1,510 329.091 0.22 0.15

2003 1,796.3 72.1 909 143.495 0.16 0.08

2004 2,437.1 96.0 842 119.834 0.14 0.05

2005 2,258.5 90.0 1,268 247.655 0.20 0.11 

2006 2,439.6 95.0 1,078 150.323 0.14 0.06

2007 2,527.3 96.0 881 91.613 0.10 0.04

2008 2,452.1 92.3 1,181 187.295 0.16 0.08

ST. LUCIE 1, 2 1977 649.1 84.7 445 152 0.34 0.23

Docket 50-335, -389; 1978 606.4 76.5 797 337 0.42 0.56

DPR-67; NPF-16 1979 592.0 74.0 907 438 0.48 0.74

1st commercial operation 1980 627.9 77.5 1,074 532 0.50 0.85

12/76, 8/83 1981 599.1 72.7 1,473 929 0.63 1.55

Type - PWRs 1982 816.8 94.0 1,045 272 0.26 0.33

Capacity - 839, 839 MWe 1983 290.3 15.4 2,211 1,204 0.54 4.15

1984 1,183.0 69.6 2,090 1,263 0.60 1.07

1985 1,445.8 82.5 1,971 1,344 0.68 0.93

1986 1,588.6 89.1 1,279 491 0.38 0.31

1987 1,407.9 81.9 2,012 951 0.47 0.68

1988 1,639.7 93.0 1,448 611 0.42 0.37

1989 1,493.1 85.1 1,414 495 0.35 0.33

1990 1,188.4 70.0 1,876 777 0.41 0.65

1991 1,592.8 90.8 1,282 479 0.37 0.30

1992 1,511.9 87.3 1,251 264 0.21 0.17

1993 1,227.6 77.7 1,462 492 0.34 0.40

1994 1,424.8 85.0 1,896 505 0.27 0.35

1995 1,306.6 76.0 1,498 413 0.28 0.32

1996 1,473.4 86.5 1,433 385 0.27 0.26

1997 1,394.6 83.6 2,314 646 0.28 0.46

1998 1,572.5 94.2 1,170 134.459 0.11 0.09

1999 1,569.1 93.8 1,107 176.878 0.16 0.11

2000 1,630.0 96.0 990 98.691 0.10 0.06

2001 1,527.5 91.6 1,375 228.071 0.17 0.15

2002 1,633.0 96.6 992 155.946 0.16 0.10

2003 1,524.7 91.5 937 141.734 0.15 0.09

2004 1,492.0 89.3 1,157 159.436 0.14 0.11

2005 1,408.4 85.1 2,262 406.171 0.18 0.29 

2006 1,542.4 93.0 1,226 119.963 0.10 0.08

2007 1,302.1 78.0 2,447 409.958 0.17 0.32

2008 1,566.5 92.7 1,127 112.234 0.10 0.07
C-35

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

SUMMER 1 1984 504.6 61.1 1,120 295 0.26 0.58

Docket 50-395; NPF-12 1985 627.7 71.6 1,201 379 0.32 0.60

1st commercial operation 1/84 1986 853.7 95.3 392 23 0.06 0.03

Type - PWR 1987 618.7 71.0 1,075 560 0.52 0.91

Capacity - 966 MWe 1988 605.3 69.1 1,127 511 0.45 0.84

1989 652.4 83.1 374 52 0.14 0.08

1990 730.0 83.9 1,090 376 0.34 0.52

1991 642.5 82.9 984 291 0.30 0.45

1992 892.6 97.4 249 27 0.11 0.03

1993 728.3 84.0 1,121 297 0.26 0.41

1994 536.7 69.5 1,549 374 0.24 0.70

1995 899.8 97.2 257 13 0.05 0.01

1996 850.4 90.3 701 97 0.14 0.11

1997 829.7 89.8 820 163 0.20 0.20

1998 934.8 98.8 285 13.513 0.05 0.01

1999 842.0 89.4 827 120.172 0.15 0.14

2000 723.9 76.6 933 166.561 0.18 0.23

2001 769.3 83.3 486 69.398 0.14 0.09

2002 840.0 87.9 685 59.644 0.09 0.07

2003 837.0 87.4 745 70.828 0.10 0.08

2004 938.4 96.8 200 10.085 0.05 0.01

2005 850.3 88.9 734 72.454 0.10 0.09 

2006 858.6 90.0 676 61.333 0.09 0.07

2007 967.9 100.0 75 2.691 0.04 0.00

2008 817.2 84.8 623 49.091 0.08 0.06

SURRY 1, 2 1973 420.6 936 152 0.16 0.36

Docket 50-280, 50-281; 1974 717.4 49.8 1,715 884 0.52 1.23

DPR-32, -37 1975 1,079.0 70.8 1,948 1,649 0.85 1.53

1st commercial operation 1976 930.7 60.4 2,753 3,165 1.15 3.40

12/72, 5/73 1977 1,139.0 72.2 1,860 2,307 1.24 2.03

Type - PWRs 1978 1,210.6 77.2 2,203 1,837 0.83 1.52

Capacity - 799, 799 MWe 1979 343.0 42.3 5,065 3,584 0.71 10.45

1980 568.2 40.3 5,317 3,836 0.72 6.75

1981 907.6 59.3 3,753 4,244 1.13 4.68

1982 1,323.3 88.5 1,878 1,490 0.79 1.13

1983 916.2 61.3 2,754 3,220 1.17 3.51

1984 1,026.7 71.0 3,198 2,247 0.70 2.19

1985 1,166.4 78.2 3,206 1,815 0.57 1.56

1986 1,080.5 69.0 3,763 2,356 0.63 2.18

1987 1,132.7 72.7 2,675 712 0.27 0.63

1988 750.4 50.0 3,184 1,542 0.48 2.05

1989 489.3 33.0 3,100 836 0.27 1.71

1990 1,276.4 83.9 1,947 575 0.30 0.45

1991 1,271.9 84.5 1,547 510 0.33 0.40

1992 1,396.3 88.9 1,660 539 0.32 0.39

1993 1,283.1 84.6 1,402 383 0.27 0.30

1994 1,320.9 85.2 1,530 378 0.25 0.29

1995 1,333.0 84.2 1,883 406 0.22 0.30

1996 1,562.9 93.1 983 209 0.21 0.13

1997 1,380.3 87.1 1,335 320 0.24 0.23

1998 1,476.2 91.6 1,165 188.831 0.16 0.13

1999 1,483.0 93.5 995 137.891 0.14 0.09

2000 1,490.0 92.7 1,197 193.169 0.16 0.13

2001 1,441.5 89.5 1,243 328.650 0.26 0.23

2002 1,557.0 96.0 799 87.778 0.11 0.06

2003 1,255.9 79.7 1,628 325.729 0.20 0.26

2004 1,537.9 94.6 1,028 119.654 0.12 0.08

2005 1,506.7 94.2 877 87.717 0.10 0.06 

2006 1,427.0 90.0 1,227 234.978 0.19 0.17

2007 1,516.2 94.0 1,111 207.130 0.19 0.14

2008 1,536.6 95.7 1,069 150.269 0.14 0.10
C-36

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

SUSQUEHANNA 1, 2 1984 719.9 72.6 2,827 308 0.11 0.43

Docket 50-387, 50-388; 1985 1,452.2 76.4 3,669 1,106 0.30 0.76

NPF-14; -22 1986 1,344.8 67.0 2,996 828 0.28 0.62

1st commercial operation 1987 1,749.5 85.3 2,548 621 0.24 0.35

6/83, 2/85 1988 1,691.0 83.5 1,904 516 0.27 0.31

Type - BWRs 1989 1,572.5 77.1 2,063 704 0.34 0.45

Capacity - 1,185, 1,140 MWe 1990 1,746.9 85.4 1,691 440 0.26 0.25

1991 1,878.0 89.8 1,844 507 0.27 0.27

1992 1,604.2 79.7 1,885 724 0.38 0.45

1993 1,602.1 77.3 1,488 335 0.23 0.21

1994 1,814.4 85.4 1,580 442 0.28 0.24

1995 1,850.8 85.3 1,773 476 0.27 0.26

1996 1,998.7 90.7 1,430 289 0.20 0.14

1997 1,918.9 89.6 1,646 433 0.26 0.23

1998 1,879.6 88.3 1,575 360.778 0.23 0.19

1999 1,896.0 89.6 1,787 431.397 0.24 0.23

2000 1,994.6 92.6 1,812 331.163 0.18 0.17

2001 2,027.6 94.2 1,807 288.413 0.16 0.14

2002 1,973.0 91.6 1,890 259.968 0.14 0.13

2003 2,050.8 93.4 1,934 250.096 0.13 0.12

2004 2,058.8 92.7 2,144 272.202 0.13 0.13

2005 2,086.6 93.5 1,898 181.360 0.10 0.09 

2006 2,040.4 91.0 1,873 184.901 0.10 0.09

2007 2,089.2 93.0 2,303 263.021 0.11 0.13

2008 2,174.1 94.2 1,895 192.892 0.10 0.09

THREE MILE ISLAND 114, 215 1975 675.9 82.2 131 73 0.56 0.11

Docket 50-289, -320; 1976 530.0 65.4 819 286 0.35 0.54

DPR-50, -73 1977 664.5 80.9 1,122 360 0.32 0.54

1st commercial operation 1978 690.0 85.1 1,929 504 0.26 0.73

9/74, 12/78 1979 266.0 21.9 3,975 1,392 0.35 5.23

Type - PWRs 1980 0.0 0.0 2,328 394 0.17 ---

Capacity - 802, (880) MWe 1981 0.0 0.0 2,103 376 0.18 ---

1982 0.0 0.0 2,123 1,004 0.47 ---

1983 0.0 0.0 1,592 1,159 0.73 ---

1984 0.0 0.0 1,079 688 0.64 ---

1985 103.6 10.6 1,890 857 0.45 8.27

THREE MILE ISLAND 114 1986 585.2 70.9 1,360 213 0.16 0.36

Docket 50-289; DPR-50 1987 610.7 73.6 1,259 149 0.12 0.24

1st commercial operation 9/74 1988 661.0 77.8 1,012 210 0.21 0.32

Type - PWR 1989 871.3 100.0 670 54 0.08 0.06

Capacity - 802 MWe 1990 645.5 84.6 1,319 264 0.20 0.41

1991 688.7 86.4 1,542 198 0.13 0.29

1992 836.8 100.0 558 34 0.06 0.04

1993 722.0 88.5 1,835 206 0.11 0.29

1994 798.7 95.5 434 40 0.09 0.05

1995 772.9 90.8 1,220 213 0.17 0.28

1996 857.4 100.0 267 16 0.06 0.02

1997 675.7 84.3 1,049 204 0.19 0.30

1998 805.8 100.0 280 16.722 0.06 0.02

1999 722.4 89.7 1,171 154.936 0.13 0.21

2000 813.4 100.0 183 8.689 0.05 0.01

2001 616.7 84.2 1,196 196.699 0.16 0.32

2002 833.0 100.0 172 6.533 0.04 0.01

2003 706.4 87.1 1,230 155.101 0.13 0.22

14 Three Mile Island 1 resumed commercial power generation in October 1985 after being under regulatory restraint since 1979.

15 Three Mile Island 2 has been shut down since the 1979 accident but was still included in the count of reactors through 1988 

since dose was still being accumulated to defuel and decontaminate the unit during this time period. Parentheses indicate plant 

capacity when plant was operational. Since 2001, the dose breakdowns for Three Mile Island 2 have been reported with those for 

Unit 1. 
C-37

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

THREE MILE ISLAND 114 2004 828.0 100.0 105 3.573 0.03 0.00

(continued) 2005 769.1 93.2 955 65.576 0.07 0.09 

2006 825.0 99.0 125 5.155 0.04 0.01

2007 758.6 92.0 1,266 114.203 0.09 0.15

2008 838.5 100.0 64 2.219 0.03 0.00

THREE MILE ISLAND 215 1986 0.0 0.0 1,497 915 0.61 ---

Docket 50-320; DPR-73 1987 0.0 0.0 1,378 977 0.71 ---

1st commercial operation 12/78 1988 0.0 0.0 1,247 917 0.74 ---

Type - PWR 1989 0.0 0.0 1,014 639 0.63 ---

Capacity - (880) MWe 1990 0.0 0.0 484 136 0.28 ---

1991 0.0 0.0 153 37 0.24 ---

1992 0.0 0.0 315 157 0.50 ---

1993 0.0 0.0 167 33 0.20 ---

1994 0.0 0.0 259 7 0.03 ---

1995 0.0 0.0 191 2 0.01 ---

1996 0.0 0.0 122 2 0.02 ---

1997 0.0 0.0 232 1 0.00 ---

1998 0.0 0.0 105 0.697 0.01 ---

1999 0.0 0.0 203 0.512 0.00 ---

2000 0.0 0.0 70 0.401 0.01 ---

2001 0.0 0.0 0 0.228 --- ---

2002 0.0 0.0 0 --- ---

2003 0.0 0.0 0 0.260 --- ---

2004 0.0 0.0 0 0.216 --- ---

2005 0.0 0.0 0 --- ---

2006 0.0 0.0 0 0.372 --- ---

2007 0.0 0.0 0 0.082 --- ---

2008 0.0 0.0 0 0.138 --- ---

TROJAN16 1977 792.0 92.6 591 174 0.29 0.22

Docket 50-344; NPF-1 1978 205.5 20.6 711 319 0.45 1.55

1st commercial operation 5/76 1979 631.0 58.1 736 258 0.35 0.41

Type - PWR 1980 727.5 72.5 1,159 421 0.36 0.58

Capacity - (1,080) MWe 1981 775.6 74.1 1,311 609 0.46 0.79

1982 579.5 60.8 977 419 0.43 0.72

1983 494.2 62.4 969 307 0.32 0.62

1984 567.0 54.4 1,042 433 0.42 0.76

1985 829.1 76.7 852 363 0.43 0.44

1986 852.4 79.7 1,321 381 0.29 0.45

1987 525.5 54.0 1,209 363 0.30 0.69

1988 758.6 67.5 1,408 401 0.28 0.53

1989 666.8 61.9 1,360 421 0.31 0.63

1990 732.4 66.3 1,169 258 0.22 0.35

1991 181.6 16.1 1,496 567 0.38 3.12

1992 553.9 68.4 567 84 0.15 0.15

1993 0.0 68.4 54 21 0.39 ---

1994 0.0 0.0 51 9 0.18 ---

1995 0.0 0.0 141 44 0.31 ---

1996 0.0 0.0 112 41 0.37 ---

1997 0.0 0.0 227 41 0.18 ---

1998 0.0 0.0 283 46.417 0.16 ---

1999 0.0 0.0 274 51.504 0.19 ---

14 Three Mile Island 1 resumed commercial power generation in October 1985 after being under regulatory restraint since 1979.

15 Three Mile Island 2 has been shut down since the 1979 accident but was still included in the count of reactors through 1988 

since dose was still being accumulated to defuel and decontaminate the unit during this time period. Parentheses indicate plant 

capacity when plant was operational. Since 2001, the dose breakdowns for Three Mile Island 2 have been reported with those for 

Unit 1.

16 Trojan ended commercial operation as of January 1993 and will not be put in commercial operation again. It is no longer in 

the count of operating reactors. Parentheses indicate plant capacity when plant was operational. As of 2005, Trojan no longer 

reports under its reactor license but does report under its ISFSI license (see Appendix A). 
C-38

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

TROJAN16 2000 0.0 0.0 127 17.631 0.14 ---

(continued) 2001 0.0 0.0 14 1.091 0.08 ---

2002 0.0 0.0 13 0.536 0.04 ---

2003 0.0 0.0 105 23.996 0.23 ---

2004 0.0 0.0 5 0.079 0.02 ---

2005 0.0 0.0 0 0.000 --- --- 

2006 0.0 0.0 0 0.000 --- --- 

2007 0.0 0.0 0 0.000 --- ---

 2008 0.0 0.0 0 0.000 --- ---

TURKEY POINT 3, 4 1973 401.9 444 78 0.18 0.19

Docket 50-250, 50-251; 1974 953.6 794 454 0.57 0.48

DPR-31, -41 1975 1,003.7 74.9 1,176 876 0.74 0.87

1st commercial operation 1976 974.2 71.2 1,647 1,184 0.72 1.22

12/72, 9/73 1977 979.5 72.1 1,319 1,036 0.79 1.06

Type - PWRs 1978 1,000.2 78.8 1,336 1,032 0.77 1.03

Capacity - 693, 693 MWe 1979 811.0 62.4 2,002 1,680 0.84 2.07

1980 990.6 73.6 1,803 1,651 0.92 1.67

1981 654.0 46.8 2,932 2,251 0.77 3.44

1982 915.7 65.2 2,956 2,119 0.72 2.31

1983 878.4 62.8 2,930 2,681 0.92 3.05

1984 946.7 68.5 2,010 1,255 0.62 1.33

1985 1,034.9 74.7 1,905 1,253 0.66 1.21

1986 754.1 54.9 1,808 946 0.52 1.25

1987 431.3 36.6 1,980 1,371 0.69 3.18

1988 809.8 59.5 1,841 738 0.40 0.91

1989 689.9 56.8 1,625 433 0.27 0.63

1990 933.1 69.0 2,099 730 0.35 0.78

1991 258.2 21.0 2,087 939 0.45 3.64

1992 968.9 75.5 1,374 325 0.24 0.34

1993 1,244.8 91.0 1,271 275 0.22 0.22

1994 1,172.9 87.2 1,489 476 0.32 0.41

1995 1,320.3 94.6 1,142 215 0.19 0.16

1996 1,307.8 94.0 1,157 187 0.16 0.14

1997 1,220.9 88.6 1,581 414 0.26 0.34

1998 1,323.0 94.5 1,045 156.415 0.15 0.12

1999 1,352.5 96.5 919 127.567 0.14 0.09

2000 1,283.7 92.2 1,292 219.852 0.17 0.17

2001 1,324.1 95.0 827 101.575 0.12 0.08

2002 1,374.0 97.9 793 73.764 0.09 0.05

2003 1,253.2 91.6 1,442 247.053 0.17 0.20

2004 1,231.0 89.9 1,089 117.404 0.11 0.10

2005 1,143.0 84.9 1,136 109.996 0.10 0.10 

2006 1,251.8 90.0 1,321 149.208 0.11 0.12

2007 1,281.5 91.0 1,085 107.601 0.10 0.08

2008 1,294.9 92.0 1,067 97.357 0.09 0.08

VERMONT YANKEE 1973 222.1 244 85 0.35 0.38

Docket 50-271; DPR-28 1974 303.5 357 216 0.61 0.71

1st commercial operation 11/72 1975 429.0 87.8 282 153 0.54 0.36

Type - BWR 1976 389.6 77.1 815 411 0.50 1.05

Capacity - 605 MWe 1977 423.5 85.1 641 258 0.40 0.61

1978 387.5 75.9 934 339 0.36 0.87

1979 414.0 82.1 1,220 1,170 0.96 2.83

1980 357.8 71.5 1,443 1,338 0.93 3.74

1981 429.1 84.6 1,264 731 0.58 1.70

1982 501.0 96.0 481 205 0.43 0.41

1983 346.1 69.3 1,316 1,527 1.16 4.41

1984 398.1 79.0 954 626 0.66 1.57

1985 361.4 71.8 1,392 1,051 0.76 2.91

16 Trojan ended commercial operation as of January 1993 and will not be put in commercial operation again. It is no longer in 

the count of operating reactors. Parentheses indicate plant capacity when plant was operational. As of 2005, Trojan no longer 

reports under its reactor license but does report under its ISFSI license (see Appendix A). 
C-39

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

VERMONT YANKEE 1986 248.1 48.9 1,389 1,188 0.86 4.79

(continued) 1987 423.6 84.2 827 303 0.37 0.72

1988 492.1 95.7 379 124 0.33 0.25

1989 432.8 84.7 832 288 0.35 0.67

1990 433.1 85.9 849 307 0.36 0.71

1991 492.3 94.3 310 118 0.38 0.24

1992 446.8 88.1 921 381 0.41 0.85

1993 402.3 80.1 833 217 0.26 0.54

1994 515.8 98.7 220 38 0.17 0.07

1995 462.1 87.0 737 182 0.25 0.39

1996 452.7 85.2 951 231 0.24 0.51

1997 487.1 96.0 260 57 0.22 0.12

1998 383.4 77.9 944 199.399 0.21 0.52

1999 463.4 91.0 854 175.795 0.21 0.38

2000 517.8 99.6 198 37.846 0.19 0.07

2001 474.9 93.5 863 143.010 0.17 0.30

2002 451.0 91.7 946 150.446 0.16 0.33

2003 505.9 98.8 359 54.348 0.15 0.11

2004 439.2 87.2 1,379 211.529 0.15 0.48

2005 467.5 94.2 1,105 198.003 0.18 0.42 

2006 582.9 100.0 380 49.537 0.13 0.09

2007 537.0 93.0 1,191 171.200 0.14 0.32

2008 557.3 94.1 1,402 213.680 0.15 0.38

VOGTLE 1, 2 1988 820.4 77.7 1,108 138 0.12 0.17

Docket 50-424; 50-425; 1989 1,045.8 96.0 427 32 0.07 0.03

NPF-68, -81 1990 1,710.9 82.7 1,602 466 0.29 0.27

1st commercial operation 1991 1,966.5 89.2 1,357 362 0.27 0.18

6/87, 5/89 1992 2,047.9 90.0 1,262 426 0.34 0.21

Type - PWRs 1993 2,060.4 88.3 1,338 367 0.27 0.18

Capacity - 1,143, 1,140 MWe 1994 2,170.1 91.3 1,048 217 0.21 0.10

1995 2,285.4 95.2 953 199 0.21 0.09

1996 2,056.8 86.5 1,395 452 0.32 0.22

1997 2,121.1 91.4 994 158 0.16 0.07

1998 2,123.9 92.3 994 162.210 0.16 0.08

1999 2,106.0 91.5 1,359 228.942 0.17 0.11

2000 2,223.9 95.6 899 121.312 0.14 0.05

2001 2,231.5 96.2 870 129.270 0.15 0.06

2002 1,942.0 85.3 1,152 243.957 0.21 0.13

2003 2,179.9 94.8 806 84.344 0.10 0.04

2004 2,200.7 95.7 765 80.763 0.11 0.04

2005 2,027.9 88.6 1,099 151.096 0.14 0.08 

2006 2,048.8 89.0 892 115.509 0.13 0.06

2007 2,089.9 92.0 951 120.515 0.13 0.06

2008 2,023.9 89.3 1,185 137.620 0.12 0.07

WATERFORD 3 1986 875.7 79.1 1,244 223 0.18 0.25

Docket 50-382; NPF-38 1987 891.8 82.5 959 156 0.16 0.17

1st commercial operation 9/85 1988 784.3 75.4 1,246 259 0.21 0.33

Type - PWR 1989 909.8 82.6 1,306 265 0.20 0.29

Capacity - 1,152 MWe 1990 1,027.9 92.8 432 47 0.11 0.05

1991 870.6 79.8 1,301 364 0.28 0.42

1992 909.6 83.2 1,213 226 0.19 0.25

1993 1,088.3 99.4 195 15 0.08 0.01

1994 949.1 87.0 1,167 191 0.16 0.20

1995 927.4 83.4 1,092 153 0.14 0.16

1996 1,064.8 94.2 342 27 0.08 0.03

1997 767.2 71.2 1,186 148 0.13 0.19

1998 984.1 91.9 282 24.032 0.09 0.02

1999 849.5 79.6 833 123.198 0.15 0.14

2000 965.1 88.8 825 131.701 0.16 0.14

2001 1,086.0 99.6 91 4.677 0.05 0.00

2002 1,007.0 93.2 811 109.439 0.13 0.11
C-40

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

WATERFORD 3 2003 968.0 90.9 710 95.332 0.13 0.10

(continued) 2004 1,099.1 100.0 60 2.517 0.04 0.00

2005 900.9 80.2 902 136.318 0.15 0.15 

2006 1,059.3 92.0 1,190 109.682 0.09 0.10

2007 1,130.2 96.0 469 20.125 0.04 0.02

2008 1,030.7 88.0 1,268 134.221 0.11 0.13

WATTS BAR 1 1997 867.6 83.8 1,103 113 0.10 0.13

Docket 50-390; NPF-90 1998 1,105.1 99.1 96 3.106 0.03 0.00

1st commercial operation 5/96 1999 943.1 87.2 975 98.946 0.10 0.10

Type - PWR 2000 1,033.3 92.8 1,053 122.453 0.12 0.12

Capacity - 1,121 MWe 2001 1,095.9 96.5 197 5.912 0.03 0.01

2002 1,034.0 92.1 909 93.598 0.10 0.09

2003 973.3 86.7 1,392 165.741 0.12 0.17

2004 1,122.1 99.1 220 5.893 0.03 0.01

2005 1,003.7 90.0 1,244 143.506 0.12 0.14 

2006 764.5 70.0 2,070 322.682 0.16 0.42

2007 1,150.6 100.0 128 4.414 0.03 0.00

2008 923.5 83.2 887 70.648 0.08 0.08

WOLF CREEK 1 1986 832.8 73.3 682 143 0.21 0.17

Docket 50-482; NPF-42 1987 778.8 71.1 675 138 0.20 0.18

1st commercial operation 9/85 1988 794.7 70.7 1,010 297 0.29 0.37

Type - PWR 1989 1,108.4 99.5 186 18 0.10 0.02

Capacity - 1,160 MWe 1990 940.2 81.0 798 195 0.24 0.21

1991 707.6 71.9 1,010 331 0.33 0.47

1992 1,010.8 86.7 446 78 0.17 0.08

1993 940.5 80.6 975 183 0.19 0.19

1994 1,017.2 86.8 1,082 235 0.22 0.23

1995 1,198.0 98.7 242 14 0.06 0.01

1996 980.6 81.2 986 171 0.17 0.17

1997 964.3 83.8 989 265 0.27 0.27

1998 1,187.3 100.0 184 10.382 0.05 0.01

1999 1,045.3 90.1 812 147.704 0.18 0.14

2000 1,032.7 89.5 861 143.417 0.17 0.14

2001 1,177.9 100.0 105 5.176 0.05 0.00

2002 1,029.0 88.7 816 99.987 0.12 0.10

2003 1,013.5 87.2 820 88.941 0.11 0.09

2004 1,153.5 98.8 93 3.388 0.04 0.00

2005 1,004.2 86.7 856 106.870 0.12 0.11 

2006 1,067.4 91.0 789 96.788 0.12 0.09

2007 1,183.7 100.0 91 4.307 0.05 0.00

2008 968.3 83.1 911 94.997 0.10 0.10

YANKEE ROWE17 1969 138.3 193 215 1.11 1.55

Docket 50-29; DPR-3 1970 146.1 355 255 0.72 1.75

1st commercial operation 7/61 1971 173.5 155 90 0.58 0.52

Type - PWR 1972 78.7 282 255 0.90 3.24

Capacity - (175) MWe 1973 127.1 133 99 0.74 0.78

1974 111.3 243 205 0.84 1.84

1975 145.1 82.4 249 116 0.47 0.80

1976 152.2 89.8 152 59 0.39 0.39

1977 124.6 73.9 725 356 0.49 2.86

1978 145.0 81.0 565 282 0.50 1.94

1979 149.0 81.6 441 127 0.29 0.85

1980 35.6 22.0 502 213 0.42 5.98

1981 109.0 74.4 515 302 0.59 2.77

1982 108.6 73.4 814 474 0.58 4.36

1983 163.5 91.4 395 68 0.17 0.42

1984 124.8 71.4 654 348 0.53 2.79

1985 144.3 85.3 653 211 0.32 1.46

17 Yankee Rowe ended commercial operation as of October 1991 and will not be put in commercial operation again. It is no longer 

in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.
C-41

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

YANKEE ROWE17 1986 169.7 95.0 384 45 0.12 0.27

(continued) 1987 138.7 82.7 593 217 0.37 1.56

1988 136.4 85.2 738 227 0.31 1.66

1989 159.4 92.9 496 62 0.13 0.39

1990 101.1 61.5 702 246 0.35 2.43

1991 121.2 72.3 162 40 0.25 0.33

1992 0.0 0.0 324 94 0.29 ---

1993 0.0 0.0 313 163 0.52 ---

1994 0.0 0.0 222 156 0.70 ---

1995 0.0 0.0 191 78 0.41 ---

1996 0.0 0.0 239 95 0.40 ---

1997 0.0 0.0 323 65 0.20 ---

1998 0.0 0.0 125 4.603 0.04 ---

1999 0.0 0.0 83 2.291 0.02 ---

2000 0.0 0.0 38 2.406 0.06 ---

2001 0.0 0.0 48 3.969 0.08 ---

2002 0.0 0.0 128 20.024 0.16 ---

2003 0.0 0.0 136 30.934 0.23 ---

2004 0.0 0.0 70 6.502 0.09 ---

2005 0.0 0.0 63 1.456 0.02 --- 

2006 0.0 0.0 45 0.975 0.02 ---

2007 0.0 0.0 0 0.000 --- --- 

2008 0.0 0.0 1 0.019 0.02 ---

ZION 118, 2 1974 425.3 71.1 306 56 0.18 0.13

Docket 50-295; 50-304; 1975 1,181.5 74.9 436 127 0.29 0.11

DPR-39, -48 1976 1,134.9 61.9 774 571 0.74 0.50

1st commercial operation 1977 1,358.6 75.0 784 1,003 1.28 0.74

12/73, 9/74 1978 1,613.5 80.2 1,104 1,017 0.92 0.63

Type - PWRs 1979 1,238.0 67.6 1,472 1,274 0.87 1.03

Capacity - (1,040), (1,040) MWe 1980 1,411.2 74.1 1,363 920 0.67 0.65

1981 1,366.9 72.3 1,754 1,720 0.98 1.26

1982 1,186.4 64.3 1,575 2,103 1.34 1.77

1983 1,222.3 69.4 1,285 1,311 1.02 1.07

1984 1,389.9 69.6 1,110 786 0.71 0.57

1985 1,187.9 62.9 1,498 1,166 0.78 0.98

1986 1,462.0 73.2 967 474 0.49 0.32

1987 1,337.0 71.0 1,046 653 0.62 0.49

1988 1,549.1 78.3 1,926 1,260 0.65 0.81

1989 1,514.1 77.6 1,282 624 0.49 0.41

1990 860.4 46.9 1,385 696 0.50 0.81

1991 1,125.7 58.2 902 173 0.19 0.15

1992 1,128.8 59.0 1,732 1,043 0.60 0.92

1993 1,458.2 70.9 1,772 643 0.36 0.44

1994 1,224.9 59.9 1,176 306 0.26 0.25

1995 1,471.6 72.4 1,807 797 0.44 0.54

1996 1,538.4 75.8 1,567 437 0.28 0.28

1997 123.2 7.1 924 119 0.13 0.97

1998 0.0 0.0 246 12.417 0.05 ---

1999 0.0 0.0 67 4.194 0.06 ---

2000 0.0 0.0 26 3.015 0.12 ---

2001 0.0 0.0 6 0.274 0.05 ---

2002 0.0 0.0 12 0.276 0.02 ---

2003 0.0 0.0 2 0.049 0.02 ---

2004 0.0 0.0 6 0.167 0.03 ---

17 Yankee Rowe ended commercial operation as of October 1991 and will not be put in commercial operation again. It is no longer 

in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

18 Zion 1, 2 were shut down in December 1997 and are no longer included in the count of operating reactors. Parentheses indicate 

plant capacity when plant was operational.
C-42

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Annual Report, 2008

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rem)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

ZION 118, 2 2005 0.0 0.0 5 0.109 0.02 --- 

(continued) 2006 0.0 0.0 7 0.109 0.02 --- 

2007 0.0 0.0 8 0.224 0.03 ---

2008 0.0 0.0 7 0.147 0.02 ---

18 Zion 1, 2 were shut down in December 1997 and are no longer included in the count of operating reactors. Parentheses indicate 

plant capacity when plant was operational.
D-1

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DOSE PERFORMANCE INDICATORS BY 

REACTOR site

1973– 2008

Appendix D*

* Appendix D only contains data on plants in operation during 2008.
D-2

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

ARKANSAS 1, 2

Dose Performance Indicators

BEAVER VALLEY 1, 2

Dose Performance Indicators
D-3

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

BRAIDWOOD 1, 2

Dose Performance Indicators

BROWNS FERRY 1, 2, 3

Dose Performance Indicators

NOTE: Browns Ferry resumed power generation in 2007.
D-4

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

BRUNSWICK 1, 2

Dose Performance Indicators

BYRON 1, 2

Dose Performance Indicators
D-5

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

CALLAWAY 1

Dose Performance Indicators

CALVERT CLIFFS 1, 2

Dose Performance Indicators
D-6

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

CATAWBA 1, 2

Dose Performance Indicators

CLINTON

Dose Performance Indicators
D-7

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

COLUMBIA GENERATING

Dose Performance Indicators

COMANCHE PEAK 1, 2

Dose Performance Indicators
D-8

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

COOK 1, 2

Dose Performance Indicators

COOPER STATION 

Dose Performance Indicators
D-9

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

CRYSTAL RIVER 3

Dose Performance Indicators

DAVIS-BESSE 1

Dose Performance Indicators
D-10

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

DIABLO CANYON 1, 2

Dose Performance Indicators

DRESDEN 2, 3

Dose Performance Indicators
D-11

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DUANE ARNOLD

Dose Performance Indicators

FARLEY 1, 2

Dose Performance Indicators
D-12

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

FERMI 2

Dose Performance Indicators

FITZPATRICK

Dose Performance Indicators
D-13

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FORT CALHOUN

Dose Performance Indicators

GINNA

Dose Performance Indicators
D-14

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

GRAND GULF

Dose Performance Indicators

HARRIS 1

Dose Performance Indicators
D-15

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

HATCH 1, 2

Dose Performance Indicators

HOPE CREEK 1

Dose Performance Indicators
D-16

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

INDIAN POINT 2

Dose Performance Indicators

INDIAN POINT 3

Dose Performance Indicators
D-17

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

KEWAUNEE

Dose Performance Indicators

LASALLE 1, 2

Dose Performance Indicators
D-18

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

LIMERICK 1, 2

Dose Performance Indicators

MCGUIRE 1, 2

Dose Performance Indicators
D-19

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

MONTICELLO

Dose Performance Indicators

MILLSTONE 2, 3

Dose Performance Indicators
D-20

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

NORTH ANNA 1, 2

Dose Performance Indicators

NINE MILE POINT 1, 2

Dose Performance Indicators
D-21

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

OYSTER CREEK

Dose Performance Indicators

OCONEE 1, 2, 3

Dose Performance Indicators
D-22

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

PALO VERDE 1, 2, 3

Dose Performance Indicators

PALISADES

Dose Performance Indicators
D-23

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

PERRY 1

Dose Performance Indicators

PEACH BOTTOM 2, 3

Dose Performance Indicators
D-24

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

POINT BEACH 1, 2

Dose Performance Indicators

PILGRIM 1

Dose Performance Indicators
D-25

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

QUAD CITIES 1, 2

Dose Performance Indicators

PRAIRIE ISLAND 1, 2

Dose Performance Indicators
D-26

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

ROBINSON 2

Dose Performance Indicators

RIVER BEND 1

Dose Performance Indicators
D-27

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

SAN ONOFRE 1, 2, 3

Dose Performance Indicators

SALEM 1, 2

Dose Performance Indicators

NOTE: Since 2001, data only includes San Onofre units 2 and 3.
D-28

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

SEABROOK

Dose Performance Indicators

SEQUOYAH 1, 2

Dose Performance Indicators
D-29

Forty-First Annual Report, 2008 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ST. LUCIE 1, 2

Dose Performance Indicators

SOUTH TEXAS 1, 2

Dose Performance Indicators
D-30

Occupational Radiation Exposure at NRC Licensed Facilities Forty-First Report, 2008

NUREG-0713

SURRY 1, 2

Dose Performance Indicators

SUMMER

Dose Performance Indicators
D-31

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SUSQUEHANNA 1, 2

Dose Performance Indicators

*Graph includes data for Three Mile Island 2 for the years 1975 – 1985.

THREE MILE ISLAND 1*

Dose Performance Indicators
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TURKEY POINT 3, 4

Dose Performance Indicators

VERMONT YANKEE

Dose Performance Indicators
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VOGTLE 1, 2

Dose Performance Indicators

WATERFORD 3 

Dose Performance Indicators
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WOLF CREEK 1

Dose Performance Indicators

WATTS BAR 1

Dose Performance Indicators
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GLOSSARY

2008

Appendix E
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GLOSSARY

Appendix E

Agreement State: as defined in 10 CFR 20.1003, means any state with which the Atomic Energy 

Commission or the Nuclear Regulatory Commission has entered into an effective agreement 

under subsection 274b. of the [Atomic Energy] Act [of 1954, including any amendments thereto]. 

To simplify subsection 274b., an Agreement State is a state that has signed an agreement with the 

NRC under which the state regulates the use of byproduct, source, and small quantities of special 

nuclear material in that state.

As low as reasonably achievable (ALARA): as defined in 10 CFR 20.1003, means making every 

reasonable effort to maintain exposures to radiation as far below the dose limits in 10 CFR 20 

as is practical consistent with the purpose for which the licensed activity is undertaken, taking 

into account the state of technology, the economics of improvements in relation to the state of 

technology, the economics of improvements in relation to benefits to the public health and safety, 

and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy 

and licensed materials in the public interest.

Average measurable dose: the 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 

excludes those individuals receiving a less than measurable dose. 

Boiling water reactor (BWR): reactor in which the water, used as both coolant and moderator, is 

allowed to boil in the core. The resulting steam can be used directly to drive a turbine and electrical 

generator, thereby producing electricity. 

Byproduct material: as partially defined in 10 CFR 20.1003, means any radioactive material 

(except special nuclear material) yielded in, or made radioactive by, exposure to the radiation 

incident to the process of producing or using special nuclear material; and the tailings or wastes 

produced by the extraction or concentration of uranium or thorium from ore processed primarily for 

its source material content.

Class (or lung class or inhalation class): as defined in 10 CFR 20.1003, means a classification 

scheme for inhaled material according to its rate of clearance from the pulmonary region of the 

lung. Materials are classified as D, W, or Y, which applies to a range of clearance half-times: for 

Class D (Days) of less than 10 days, for Class W (Weeks) from 10 to 100 days, and for Y (Years) of 

greater than 100 days.

Collective dose: as defined in 10 CFR 20.1003, is the sum of the individual doses received in a 

given period of time by a specified population from exposure to a specified source of radiation.
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Committed dose equivalent: as defined in 10 CFR 20.1003, means the dose equivalent to organs 

or tissues of reference that will be received from an intake of radioactive material by an individual 

during the 50-year period following the intake. The acronym CDE is an NRC acronym used for this 

term.

Committed effective dose equivalent: as defined in 10 CFR 20.1003, is the sum of the products of 

the weighting factors applicable to each of the body organs or tissues that are irradiated and the 

committed dose equivalent to these organs or tissues. The acronym CEDE is an NRC acronym 

used for this term.

Exposure: as defined in 10 CFR 20.1003, means being exposed to ionizing radiation or to 

radioactive material.

Independent Spent Fuel Storage Installation (ISFSI): as defined in 10 CFR 72.3 means a complex 

designed and constructed for the interim storage of spent nuclear fuel, solid reactor-related GTCC 

waste, and other radioactive materials associated with spent fuel and reactor-related GTCC waste 

storage. An ISFSI which is located on the site of another facility licensed under 10 CFR 72 or a 

facility licensed under 10 CFR 50 of [Title 10 of the Code of Federal Regulations] and which shares 

common utilities and services with that facility or is physically connected with that other facility may 

still be considered independent.

Lens dose equivalent (LDE): as defined in 10 CFR 20.1003, applies to the external exposure of 

the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeter (300 mg/

cm2).

License: as defined in 10 CFR 20.1003, means a license issued under the regulations in 10 

CFR parts 30 through 36, 39, 40, 50, 60, 61, 63, 70, or 72 of [Title 10 of the Code of Federal 

Regulations].

Licensee: as defined in 10 CFR 20.1003, means the holder of the NRC license.

Licensed material: as defined in 10 CFR 20.1003, means source material, special nuclear material, 

or byproduct material received, possessed, used, transferred, or disposed of under a general or 

specific license issued by the [Nuclear Regulatory] Commission.

Light water reactor (LWR): the term used in this report to describe commercial nuclear reactors 

that use ordinary water as a coolant and are operated for the purposes of generating electricity. 

Light water reactors include boiling water reactors (BWRs) and pressurized water reactors (PWRs). 

Measurable dose: a dose greater than zero rem (not including doses reported as “not detectable”).
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Megawatt-year: unit of electric energy, equal to the energy from a power of 1,000,000 watts over a 

period of one year.

Mode of Intake: the manner of intake into the body: inhalation (H), absorption through the skin (B), 

oral ingestion (G), and injection (J).

Monitoring year: interval during which the radiation exposure monitoring was performed.

Non-reactor licensees: NRC licensees that are not commercial nuclear power reactors. 

These licensees are industrial radiographers, fuel processors, fabricators, and reprocessors; 

manufacturers and distributors of byproduct material; independent spent fuel storage installations; 

facilities for land disposal of low-level waste; and geologic repositories for high-level waste.

Number of individuals with measurable dose: the count of unique individuals who received 

measurable dose during the monitoring year. In some instances in this report, the number of 

individuals with measurable dose may include individuals who are counted more than once since 

they may be monitored at more than one licensee during the year. (See Section 5 on the effect 

of transient individuals.) Tables that have been adjusted for transient workers are noted in the 

appropriate footnotes to the tables.

Occupational dose: as defined in 10 CFR 20.1003, means the dose received by an individual in 

the course of employment in which the individual’s assigned duties involve exposure to radiation 

and to radioactive material from licensed and unlicensed sources of radiation, whether in the 

possession of the licensee or other person. Occupational dose does not include doses received 

from background radiation, from any medical administration the individual has received, from 

exposure to individuals administered radioactive material and released under [10 CFR] 35.75, from 

voluntary participation in medical research programs, or as a member of the public.

Pressurized water reactor (PWR): power reactor in which heat is transferred from the core to an 

exchanger by high temperature water kept under high pressure in the primary system. Steam 

used to turn a turbine and electrical generator is generated in a secondary circuit. The majority of 

reactors producing electric power in the United States are pressurized water reactors. 

Radionuclide: a radioisotope.

REM: as defined in 10 CFR 20.1004, is the special unit of any of the quantities expressed as dose 

equivalent. The dose equivalent in rems is equal to the absorbed dose in rads multiplied by the 

quality factor (1 rem = 0.01 sievert).

Shallow dose equivalent, maximum extremity (SDE-ME): the external exposure of an extremity, 

taken as the dose equivalent at a tissue depth of 0.007 centimeter. 
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Shallow dose equivalent, whole body (SDE-WB): the external exposure of the skin, taken as the 

dose equivalent at a tissue depth of 0.007 centimeter. 

Sievert: as defined in 10 CFR 20.1004, is the SI unit of any of the quantities expressed as dose 

equivalent. The dose equivalent in sieverts is equal to the absorbed dose in grays multiplied by the 

quality factor (1 Sv = 100 rems).

Special nuclear material (SNM): as defined in 10 CFR 20.1003, means plutonium, uranium-233, 

uranium enriched in the isotope 233 or in the isotope 235, and any other material that the [Nuclear 

Regulatory] Commission, pursuant to the provisions of section 51 of the [Atomic Energy] Act 

[of 1954, as amended], determines to be special nuclear material, but does not include source 

material. Any material artificially enriched by any of the foregoing but does not include source 

material.

Total effective dose equivalent (TEDE): as defined in 10 CFR 20.1003, means the sum of the 

effective dose equivalent (for external exposures) and the committed effective dose equivalent (for 

internal exposures). 

Transient individual: one who is monitored at more than one licensed site during the calendar year.

Unit availability factor: the unit available hours (the total clock hours in the report period during 

which the unit operated online or was capable of such operation) times 100 divided by the period 

hours.
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