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,

Reproduction and Distribution

 Services Section

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

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.
i

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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ii

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

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.

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

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

abstract

1

Commercial nuclear power reactors; industrial radiographers; fuel processors (including uranium enrichment), fabricators, and

 reprocessors; manufacturers and distributors of by-product 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’s (NRC’s) Radiation Exposure Information and Reporting System 

(REIRS). The bulk of the information contained in the report was compiled from the 2006 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 2006 were received from a total of 199 NRC licensees, of which 104 were 

commercial operators of nuclear power reactors. Compilations of the reports submitted by the 

199 licensees indicated that 127,074 individuals were monitored, 64,743 of whom received a 

measurable dose (Table 3.1). The collective dose incurred by these individuals was 12,846

person-rem, which represents a 7% decrease from the 2005 value. The number of workers 

receiving a measurable dose also decreased, resulting in an average measurable dose of 0.20

rem for 2006. 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 for 

commercial reactors have been adjusted to account for transient reactor workers.

In calendar year 2006, the annual collective dose per reactor for light water reactor (LWR) 

licensees was 106 person-rem. This represents a 4% decrease from the value reported for 2005 

(110). The annual collective dose per reactor for boiling water reactors (BWRs) was 143 personrem, and, for pressurized water reactors (PWRs), it was 87 person-rem.

Analyses of transient worker data indicate that 27,799 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 2006, 

the average measurable dose per worker for all licensees calculated from reported data was 0.15

rem. The corrected dose distribution resulted in an average measurable dose per worker for all 

licensees of 0.20 rem.
iv

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Mr. Charles Hinson assisted in the preparation of this NUREG, serving as technical reviewer. 

The U.S. Nuclear Regulatory Commission welcomes responses from readers.

Comments should be directed to: 

REIRS Project Managers

Elijah D. Dickson: 301-415-6704

E-mail Address: EDD@nrc.gov

Doris E. Lewis: 301-415-0256

E-mail Address: DEL1@nrc.gov

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission 

Washington, DC 20555

EDITOR’S NOTE
v

Thirty-Ninth Annual Report, 2006 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 Exposure Data by License Category................................... 3-7

 3.3.1 Industrial Radiography Licenses, Single and Multiple Locations ...................... 3-7

 3.3.2 Manufacturing and Distribution Licenses, Type “A” Broad and Limited ............ 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.......................................................................................... 3-17

 3.3.6 Light Water Reactor Licenses........................................................................... 3-20

 3.3.7 Other Facilities Reporting to the NRC.............................................................. 3-21

 3.4 Summary of Intake Data by License Category............................................................. 3-22

table of contents

Page
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

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............................................................................................ 4-8

 4.5 Three-Year Average Collective TEDE per Reactor .......................................................... 4-15

 4.6 Graphical Representation of Dose Trends in Appendix D................................................ 4-18

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 Control Levels..................................................................................................................... 6-1

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

 6.3 Summary of Exposures in Excess of Regulatory Limits.................................................... 6-3

 6.4 Maximum Exposures Below the NRC Limits..................................................................... 6-6

7 REFERENCES............................................................................................................................ 7-1

8 GLOSSARY ............................................................................................................................. 8-1

APPENDIX A - ANNUAL TEDE FOR NONREACTOR NRC LICENSEES, 2006 .........................A-1

APPENDIX B - ANNUAL WHOLE-BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES, 2006.............................................................................................................B-1

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

1969–2006 .......................................................................................................................................C-1

APPENDIX D - DOSE PERFORMANCE INDICATORS BY REACTOR SITE,

1973–2006 .......................................................................................................................................D-1

table of contents (Continued)

Page
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Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Figure 3.1 Average Annual Values at Industrial Radiography Facilities, 1973–2006 ................ 3-9

Figure 3.2 Collective TEDE Distribution by Dose Range, Industrial Radiographer— 

Single Location Licensees, 2002–2006 .................................................................. 3-10

Figure 3.3 Collective TEDE Distribution by Dose Range, Industrial Radiographer— 

Multiple Location Licensees, 2002–2006................................................................ 3-10

Figure 3.4 Average Annual Values at Manufacturing and Distribution

Facilities, 1973–2006............................................................................................... 3-12

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

Manufacturing and Distribution Licensees, 2002–2006.......................................... 3-13

Figure 3.6 Collective TEDE Distribution by Dose Range, Limited

Manufacturing and Distribution Licensees, 2002–2006.......................................... 3-13

Figure 3.7 Average Annual Values at Low-Level Waste Disposal

Facilities, 1982–1998............................................................................................... 3-15

Figure 3.8 Average Annual Values at Independent Spent Fuel Storage

Facilities, 1982–2006............................................................................................... 3-16

Figure 3.9 Collective TEDE Distribution by Dose Range, Independent Spent

Fuel Storage Licensees, 2002–2006 ...................................................................... 3-17

Figure 3.10 Average Annual Values at Fuel Cycle Licensees, 1973–2006 ............................... 3-18

Figure 3.11 Collective TEDE Distribution by Dose Range, Fuel Cycle

Licensees, 2002–2006............................................................................................. 3-20

Figure 3.12 Collective TEDE Distribution by Dose Range, Reactor

Licensees, 2002–2006............................................................................................. 3-21

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

per Reactor, 1973–2006 .......................................................................................... 4-10

Figure 4.2 Number of Operating Reactors and Electricity Generated, 1973–2006..................4-11

list of figures

Page
viii

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Figure 4.3 Average Measurable Dose per Worker and Collective Dose per

Megawatt-Year, 1973–2006..................................................................................... 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, 1992–2006 .......................................................................................... 4-14

Table 3.1 Average Annual Exposure Data for Certain Categories of 

NRC Licensees, 1997–2006...................................................................................... 3-3

Table 3.2 Distribution of Annual Collective TEDE by License

Category, 2006........................................................................................................... 3-5

Table 3.3 Summary of Annual Dose Distributions for Certain NRC

Licensees, 1968–2006............................................................................................... 3-6

Table 3.4 Annual Exposure Information for Industrial 

Radiographers, 2004–2006....................................................................................... 3-7

Table 3.5 Annual Exposure Information for Manufacturers and 

Distributors, 2004–2006............................................................................................3-11

Table 3.6 Annual Exposure Information for Fuel Cycle Licensees, 2004–2006 .................... 3-19

Table 3.7 Intake by Licensee Type and Radionuclide Mode of Intake—

Ingestion and Other, 2006 ....................................................................................... 3-22

Table 3.8 Intake by Licensee Type and Radionuclide Mode of Intake—

Inhalation, 2006........................................................................................................ 3-23

Table 3.9 Collective and Average CEDE by Licensee, 2006.................................................. 3-25

Table 3.10 Internal Dose (CEDE) Distribution, 1994–2006 ...................................................... 3-26

Table 4.1 Summary of Information Reported by Commercial

Boiling Water Reactors, 1973–2006.......................................................................... 4-2

list of FIGUREs (Continued)

list of tables

Page
ix

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

list of tables (Continued)

Table 4.2 Summary of Information Reported by Commercial 

Pressurized Water Reactors, 1973–2006 ................................................................. 4-3

Table 4.3 Summary of Information Reported by Commercial

Light Water Reactors, 1973–2006............................................................................. 4-4

Table 4.4 Summary Distribution of Annual Whole Body Doses at Commercial 

Light Water Reactors, 1977–2006............................................................................. 4-7

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

TEDE per BWR, 2004–2006 ................................................................................... 4-16

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

TEDE per PWR, 2004–2006 ................................................................................... 4-17

Table 5.1 Effects of Transient Workers on Annual Statistical Compilations, 2006................... 5-2

Table 6.1 Occupational Exposures in Excess of Regulatory Limits, 1994–2006..................... 6-4

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

Table 6.3 Maximum Occupational Exposures for Each Exposure Category, 2006 ................. 6-6

Page
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Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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’s Reactor Oversight Program to evaluate 

the effectiveness of the licensee’s ALARA program 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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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

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Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

foreword

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

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

information about the safety performance of the NRC’s licensees. Toward that end, NUREG0713, Volume 28, summarizes the 2006 occupational radiation exposure data maintained 

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

Seven categories of NRC licensees are required to report annually 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; manufacturers and distributors of by-product 

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

waste; and geologic repositories for high-level waste. Because the NRC has not yet 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 the 

NRC received from 199 licensees, of which 104 were commercial operators of nuclear power 

reactors. 

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

individual. In 2006, 127,074 individuals were monitored, and 64,743 received a measurable 

dose. This report analyzes and presents these records in terms of collective dose and the 

distribution of dose among the monitored individuals. During 2006, these individuals incurred 

a collective dose of 12,846 person-rem, which represents a 7% decrease from the 2005 value 

of 13,840 person-rem. The average measurable dose decreased from 0.21 rem in 2005 to 

0.20 rem in 2006. The average measurable dose is the total collective dose divided by the 

number of workers receiving a measurable dose. This value can be compared to 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 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’s Reactor Oversight Program to evaluate the 

effectiveness of licensees’ ALARA programs.

 

 Farouk Eltawila, Director

 Division of Systems Analysis 

Office of Nuclear Regulatory Research

 U.S. Nuclear Regulatory Commission 
xiv

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Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ABBREVIATIONS

AEC Atomic Energy Commission

ALARA As low as is reasonably achievable

BWR Boiling water reactor

CDE Committed dose equivalent

CEDE Committed effective dose equivalent

DOE U. S. Department of Energy

ERDA Energy Research and Development Administration

ISFSI Independent spent fuel storage installation

LDE Lens dose equivalent

MW-yr Megawatt-year

ND Not detectable

NR Not required to be reported

NRC Nuclear Regulatory Commission

NRR Nuclear Regulatory Research 

PWR Pressurized water reactor

REIRS Radiation Exposure Information and Reporting System

SDE-ME Shallow dose equivalent maximum extremity

SDE-WB Shallow dose equivalent whole body

TEDE Total effective dose equivalent

UF6 Uranium Hexaflouride

UNSCEAR United Nations Scientific Committee on the Effects of Atomic Radiation

USEC United States Enrichment Corporation
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

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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's 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 the 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 

the 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 DOE’s 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 as of 1997),

 fabricators, and reprocessors; and manufacturers and distributors of specified quantities of by-product material.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

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In 1982 and 1983, Paragraph 20.408(a) of 

Title 10 of the CFR was amended to require 

three additional categories of NRC licensees to 

submit annual statistical exposure reports and 

individual termination exposure reports. The 

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, since 

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 

licensee-specific 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 those documents 

listed on the inside of the front cover of this 

report for the specific year desired. Additional 

operating data and statistics for each 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 of 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.

Recommendations for further analysis or 

for different presentation of information are 

welcome. 

 
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Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

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The main Web address for the 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, the 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 NUREG0713 document. A Web site was created for 

radiation exposure and linked into the main 

NRC Web page. The Web site contains upto-date information on radiation exposure, as 

well as information and guidance on reporting 

radiation exposure information to the 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 exposure 

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. 

The 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

REIRS Project Manager

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

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limitations of the data

Section 2

All of the figures compiled in this report relating 

to exposures and doses are based on the 

results and interpretations of the readings of 

various types of personnel-monitoring 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 although the probability of 

their being exposed 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 radiation workers. 

In an effort to account for this increase, the 

number of individuals reported as having “no 

measurable exposure”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 

(for example, see Table 3.1).

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 power 

reactor facilities since they employ many shortterm workers. Section 5 contains an analysis 

that corrects for individuals' being counted more 

than once. 

 4The 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 Thirty-Ninth Annual Report, 2006

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Another fact that should be kept in mind when 

examining the annual statistical data is that 

all of the personnel included in the report may 

not have been monitored throughout the entire 

year. Many licensees, such as radiography 

firms and nuclear power facilities, 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 paid 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 2006 report, data for prior years 

may have been updated to account for these 

corrections and additions. Users should be 

alert to these changes.

It should again be pointed out that this report 

contains information reported by NRC licensees 

and some Agreement State5 licensees who 

also have reported to the NRC. Since the 

NRC licenses all commercial nuclear power 

reactors, fuel processors and fabricators, 

and independent spent fuel storage facilities, 

information shown for these categories 

reflects 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 by-product material, and lowlevel waste disposal. Companies that conduct 

these types of activities in Agreement States 

are licensed by the state and are not required 

to submit occupational exposure reports to 

the NRC. More than three times as many 

facilities are regulated by Agreement States 

than are licensed by the NRC. In addition, 

this report does not include compilations of 

nonoccupational exposure, such as exposure 

due to medical X-rays, fluoroscopy, and 

accelerators, received by patients. 

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. 

Therefore, 1 rem = 10 mSv.

 5

Agreement states are states that have entered into an agreement with the NRC which allows each state to license organizations

using radioactive materials for certain purposes. Currently, there are 34 Agreement States. (Minnesota became the 34th Agreement 

State on March 31, 2006).
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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 licenses 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 about 

10% higher than the sum of the actual individual 
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

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doses. Care should be taken when comparing 

the actual collective dose calculated for 1994 to 

2006 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 whole-body 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 seven6 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 10 years. All nuclear power plants, fuel 

processors and fabricators, and independent 

spent fuel storage facilities are required to 

report occupational exposure to the 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 

the NRC.

3.1.8 Collective TEDE Distribution

by Dose Range

The United Nations Scientific Committee on 

the Effects of Atomic Radiation’s (UNSCEAR's) 

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, with scientific annexes, 

Volume I, [Ref. 11] recommends the calculation 

of a parameter, SR (previously referred to 

as CR or MR), 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 annual collective 

6

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

 fabricators, and reprocessors; manufacturers and distributors of by-product 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

1997–2006

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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

dose above 1.5 rem divided by the total annual 

collective dose. The UNSCEAR 2000 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, the 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, 3.9, 3.11, and 3.12 

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 

licensee. 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 exposure reports submitted by six 

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. 

Ninety-three percent of the reported workers 

with measurable doses (shown in Table 3.2) 

were monitored by nuclear power facilities in 

2006, where they received 86% of the total 

collective dose.

Under the regulatory limits of 10 CFR 

20.1201, annual TEDE in excess of 5 rem for 

occupationally exposed adults is, by definition, 

an exposure in excess of regulatory limits (see 

Section 6).

Table 3.3 gives a summary of the annual 

exposures reported to the NRC by certain 

categories of NRC licensees as required 

by 10 CFR 20.2206. Table 3.3 shows 

that approximately 95% of the exposures 

consistently remained <2 rem between 

1968 and 1984. For the past 16 years, the 

percentage of workers with <2 rem has been 

greater than 99%. The number of workers 

receiving an annual exposure in excess of 

5 rem has been <0.01% since 1985. No 

individual monitored at any of the six NRC 

licensee categories included in this report 

received a dose above the 5 rem annual TEDE 

limit during the past 3 years (see Section 6).
3-5

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.2

Distribution of Annual Collective TEDE by License Category

2006

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3-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

1968 36,836 97.2% 99.5% 3

1969 31,176 96.5% 99.5% 7

1970 36,164 96.1% 99.4% 0

1971 36,311 96.3% 99.3% 1

1972 44,690 95.7% 99.5% 8

1973 67,862 95.0% 99.5% 1

1974 85,097 96.4% 99.7% 1

1975 78,713 94.8% 99.5% 1

1976 92,773 95.0% 99.6% 3

1977 98,212 93,438 93.8% 99.6% 1

1978 105,893 100,818 94.6% 99.8% 3

1979 131,027 125,316 95.2% 99.8% 1

1980 159,177 150,675 94.6% 99.7% 0

1981 157,874 149,314 94.6% 99.8% 1

1982 162,456 154,117 94.9% 99.9% 0

1983 172,927 164,239 94.6% 99.9% 0

1984 181,627 168,899 95.1% 99.9% 0

1985 212,217 201,339 97.6% (4,734) >99.99% (15) 2

1986 225,582 213,017 98.0% (4,076) >99.99% (8) 0

1987 243,562 227,997 98.8% (2,738) >99.99% (4) 1

1988 231,234 215,662 98.6% (2,980) >99.99% (8) 0

1989 229,353 212,474 99.1% (2,018) >99.99% (7) 1

1990 227,777 208,513 98.9% (2,150) >99.99% (3) 0

1991 218,519 202,731 99.4% (1,174) >99.99% (2) 0

1992 220,717 202,998 99.6% (897) >99.99% (1) 0

1993 208,784 189,109 99.5% (719) >99.99% (2) 0

1994 178,987 149,173 99.5% (818) >99.99% (1) 0

1995 179,406 143,115 99.3% (1,049) >99.99% (1) 0

1996 173,674 137,430 99.5% (730) >99.99% (1) 0

1997 180,814 142,959 99.5% (666) 100% (0) 0

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 164,993 121,265 99.7% (414) >99.99% (1) 1

2004 163,364 122,322 99.7% (366) 100% (0) 0

2005 172,419 125,025 99.7% (342) 100% (0) 0

2006 175,540 126,195 99.8% (204) 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 1977–2006 are based on the distribution of individual doses after adjusting for the multiple counting of transient reactor workers (see

 Section 5). The number of people exceeding both 2 and 5 rem are shown in parentheses from 1985–2006.

TABLE 3.3

Summary of Annual Dose Distributions for Certain* NRC Licensees

1968–2006

Total Number of Monitored Persons

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

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.4

Annual Exposure Information for Industrial Radiographers

2004–2006

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3.3 Summary of

Occupational Exposure

Data by License Category

3.3.1 Industrial Radiography Licenses, 

Single and Multiple Locations

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 multiple temporary 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 

69 radiography licensees in 2006. Table 3.4 

summarizes the reported data for the two types 

of Industrial radiography licenses for 2006 

and for the previous 2 years for comparison 

purposes.

The average measurable dose for workers 

performing radiography at a single location 

ranged from 12% to 15% of the average 

measurable dose of workers at multiple location 

facilities over the past 3 years. This is because 

it is more difficult for workers to avoid exposure 

to radiation at temporary 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 2006.

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 reasonably achievable (ALARA). 

Although these licensed activities usually result 
3-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

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 facilities from 1973 

through 2006. While the number of workers 

with measurable TEDE per licensee decreased 

from 2005 to 2006, the average measurable 

TEDE remained at 0.57 rem. Figures 3.2 

and 3.3 show the collective dose distribution 

by dose range (see Section 3.1.8) for single 

location and multiple location radiography 

licensees. These graphs demonstrate that 

multiple location licensees consistently have 

individuals receiving doses in the higher dose 

ranges and routinely have 25% to 35% of the 

collective dose delivered to individuals above 

2 rem. For single location licensees, the 

percentage of individuals in 4 of the 5 dose 

ranges increased from the 2005 values. The 

percentage of the dose accrued to individuals 

above 2 rem in this category increased in 2006 

after a decreasing trend for the past 4 years.

3.3.2 Manufacturing and Distribution

Licenses, Type “A” Broad and Limited

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 the 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, diagnoses, and 

therapy. The Limited licenses are usually 

issued to smaller firms requiring a more 

restrictive license. Limited 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.
3-9

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 3.1. Average Annual Values at Industrial Radiography Facilities 1973–2006
3-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

FIGURE 3.2. Collective TEDE Distribution by Dose Range

Industrial Radiographer—Single Location Licensees

2002–2006

FIGURE 3.3. Collective TEDE Distribution by Dose Range

Industrial Radiographer—Multiple Location Licensees

2002–2006
3-11

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Table 3.5 presents the annual data that were 

reported by the two types of licensees for 

2006 and the previous 2 years. Looking at 

the information shown separately for the Type 

"A" Broad and Limited licensees, one can 

see that the values of collective and average 

measurable dose generally remain higher for 

the Type "A" Broad licensees. However, to 

examine trends in the data presented for this 

category of licensees, it should be noted that 

the types and quantities of radionuclides may 

fluctuate from year to year and even during 

the year. For this reason, some licensees 

may report dose data one year and not the 

next and may be included as a Type "A" Broad 

licensee one year and a Limited licensee at 

other times. Because the number of reporting 

licensees is quite small, these fluctuations may 

have a significant impact on the values of the 

parameters. Only two Type "A" Broad licensees 

reported in 2006.

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 both Type 

"A" Broad and Limited Manufacturing and 

Distribution facilities. Although the number of 

workers with measurable dose per licensee 

steadily increased between 1999 and 2004 and 

then dropped in 2005 and 2006, the collective 

TEDE per licensee has remained relatively 

level during this same time period. The figures 

for Type "A" Broad licensees are primarily 

attributed to Mallinckrodt, Inc., which accounted 

for 91% of the collective dose for this category 

of licensee in 2006. Figures 3.5 and 3.6 

show the collective dose distribution by dose 

range (see Section 3.1.8) for Type "A" Broad 

and Limited Manufacturing and Distribution 

licensees. These graphs clearly show that, 

in past years, the Type "A" Broad licensees 

consistently have individuals receiving dose in 

the higher dose ranges. However, in 2005 and 

2006, the percentages for Limited licensees 

in each dose range increased significantly 

and exceeded the values for the Type "A" 

Broad licensees for doses above 0.50 rem. 

The average measurable dose for Limited 

licensees more than doubled compared to the 

TABLE 3.5

Annual Exposure Information for Manufacturers and Distributors

2004–2006

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3-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

FIGURE 3.4. Average Annual Values at Manufacturing and Distribution Facilities

1973–2006
3-13

Thirty-Ninth Annual Report, 2006 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

2002–2006

FIGURE 3.6. Collective TEDE Distribution by Dose Range

Limited Manufacturing and Distribution Licensees

2002–2006
3-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

value for 2004. Most of the increases in this 

category for 2005 and 2006 were due to IBA 

Molecular, Inc. (formerly known as Eastern 

Isotopes). This licensee accounted for 86% 

of the collective dose in this licensee category 

in 2006. 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 

2006.

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 

licensees reporting radiation exposure data 

to REIRS. 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 lowlevel waste disposal facilities from 1982 through 

1998.

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 on 

site at commercial power reactors. Since the 

doses from these ISFSI facilities are usually 

included with the doses reported to the NRC 

by the power reactors, the doses from these 

ISFSI facilities are not reported separately 

to the NRC. The doses from the two ISFSI 

licensees that are not associated with power 

reactors are reported here for 2006. 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 and, 

therefore, no longer reports radiation exposure 

under a power reactor license. However, the 

ISFSI facility at Trojan remains in operation 

and occupational radiation exposure is, 

therefore, reported under the ISFSI license. 

Appendix A summarizes the exposure 

information reported by these licensees. 

(Note that from 1999 to 2003, the DOE facility 

in Idaho that stores fuel from Three Mile Island 

Unit 2 reported in this category.)

Figure 3.8 shows the number of workers 

with measurable dose per licensee, the total 

collective dose per licensee, and the average 
3-15

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 3.7. Average Annual Values at Low-Level Waste Disposal Facilities

1982–1998

Note: As of 1999, there are no longer any NRC licensees involved in this activity. All low-level waste disposal facilities are now located in Agreement States and no longer report to the NRC.
3-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

FIGURE 3.8. Average Annual Values at Independent Spent Fuel Storage Facilities

1982–2006
3-17

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 3.9. Collective TEDE Distribution by Dose Range

Independent Spent Fuel Storage Licensees

2002–2006

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 2006. Figure 3.9 shows the 

collective dose distribution by dose range 

(see Section 3.1.8) for ISFSI licensees from 

2002 to 2006. The percentages for each dose 

range have generally decreased over the past 

5 years, with an increase in the percentage 

above 0.10 rem and 0.25 rem ranges in 2006.

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. Starting in 1997, 

this category also includes the two uranium 

enrichment facilities at Portsmouth, Ohio, and 

Paducah, Kentucky. The regulatory oversight 
3-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

FIGURE 3.10. Average Annual Values at Fuel Cycle Licensees

1973–2006
3-19

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.6

Annual Exposure Information for Fuel Cycle Licensees

2004–2006

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for these facilities was transferred from DOE 

to the NRC in 1997. In 2005, a third uranium 

enrichment facility, the United States Enrichment 

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

category. 

Figure 3.10 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 TEDE collective 

and average measurable dose, the deep dose 

equivalent (DDE) collective dose and DDE 

average measurable dose are shown. Both 

doses are shown since the CEDE is a significant 

contribution to the TEDE for fuel fabrication 

facilities. 

Figure 3.11 shows the collective dose 

distribution by dose range (see Section 3.1.8) 

for fuel cycle licensees from 2002 to 2006. 

From 2002 to 2005, there was a decrease in the 

percentage of the collective dose above each 

dose range, and in 2006, there was an increase 

in the next three dose ranges above 0.10 

rem. Most of the increase in the higher dose 

ranges is due to Westinghouse Electric Co. at 

the Commercial Nuclear Fuel Division in South 

Carolina, where the collective dose increased by 

37% from 2005 to 2006. As shown in Table 3.6, 

the collective DDE increased by 19%, while the 

collective CEDE decreased by 8% in 2006. 

Appendix A lists each of the licensees reporting 

in 2006, with the number of workers monitored, 

the number of workers receiving measurable 

external doses, and the collective dose for each 

licensee. Table 3.6 shows that there were nine 

licensed fuel cycle (fabrication and enrichment) 

facilities reporting in 2006.
3-20

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

FIGURE 3.11. Collective TEDE Distribution by Dose Range

Fuel Cycle Licensees

2002–2006

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 1997 

through 2006. 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 2006 is 

presented in alphabetical order by site name in 

Appendix B.

Figure 3.12 shows the collective dose 

distribution by dose range (see Section 3.1.8) 

for reactor licensees from 2002 to 2006. The 

distribution of collective dose has been fairly 

constant over the past 5 years, with a slight 

decrease noted from 2002 to 2006 in each dose 

range.

More detailed presentations and analyses of 

the annual exposure information reported by 

nuclear power facilities can be found in Sections 

4 and 5.
3-21

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 3.12. Collective TEDE Distribution by Dose Range

Reactor Licensees

2002–2006

3.3.7 Other Facilities Reporting to the NRC

For this year’s annual report, a listing has been 

added to the end of Appendix A that contains the 

dose distribution from additional facilities that 

reported occupational radiation exposure to the 

NRC in 2006. These facilities are not among 

the seven categories of licensees required 

to report to the NRC 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 

Hexaflouride (UF6) Production Plants.
3-22

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

TABLE 3.7

Intake by Licensee Type and Radionuclide Mode of Intake—Ingestion and Other

2006

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3.4 Summary of Intake

Data by License Category

Licensees are required to list for each intake 

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 the 

NRC under 10 CFR 20.2206. Tables 3.7 and 

3.8 summarize the intake data reported to the 

NRC during 2006. 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 

and other means. 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 its clearance half-time from the pulmonary 

region of the lung into the blood and 

gastrointestinal tract. 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.

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 (over 

99%) in 2006 and the highest average CEDE 

per individual. This is due to the worker’s 

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 2006 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.
3-23

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.8

Intake by Licensee Type and Radionuclide Mode of Intake—Inhalation

2006

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3-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

TABLE 3.8 (continued)

Intake by Licensee Type and Radionuclide Mode of Intake—Inhalation

2006

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3-25

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.9

Collective and Average CEDE by Licensee

2006

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3-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

TABLE 3.10

Internal Dose (CEDE) Distribution

1994–2006

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4-1

Thirty-Ninth Annual Report, 2006 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 chapter, some of the tables 

and appendices that summarize exposure data 

also show the type, capacity, amount of electricity 

generated, and age of the reactor. Exposure 

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 on 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. 12.

Three Mile Island (TMI) 2 was included in the 

compilation of data for commercially operating 

reactors through 1988, even though the reactor 

was shut down following the 1979 accident, since 

TMI 2 was in the process of being defueled and 

decommissioned during those years. 

TMI 2 has not been included in the data analysis 

since 1988. Data for this reactor, however, will 

be listed in Appendix B for reference purposes. 

The dose data presented in Appendix D for TMI 

include the dose data for Unit 2 prior to 1986.

There were no changes to the count of 

operating reactors in 2006. The number of 

operating BWRs remains the same as in 2006 

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. For the years 1973 to 1996, 

the electricity generated is the gross electricity 

output of the reactor. For 1997 to 2006, 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 

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. 
4-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713 TABLE 4.1 Summary of Information Reported by Commercial Boiling Water Reactors 1973–2006 ������� ����������� ������� ������ ������ ������� ���������� ��������� ���������� ������� �������

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

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

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

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

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

�������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������������
4-3

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

������� ����������� �������

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

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

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

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

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

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

TABLE 4.2

Summary of Information Reported by Commercial Pressurized Water Reactors

1973–2006
4-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

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

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

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

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

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

TABLE 4.3

Summary of Information Reported by Commercial Light Water Reactors

1973–2006
4-5

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

The number of megawatt hours of electricity 

produced each year was obtained from Ref. 12.

As shown in Table 4.3, there was a <1% 

increase in the net electricity generated at 

LWRs in 2006. Contributors to this increase 

included Callaway for PWRs and Perry for 

BWRs. These plants experienced the largest 

increases in power production (in MW-yr) from 

2005 to 2006.

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 2006, 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 0.12 rem/MWyr in 2006 from a value of 0.13 rem/MW-yr in 

2005 due to a combination of the decrease in 

the collective dose and an increase 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 found 

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. 12.

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 to 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.
4-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

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 

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 remained unchanged at 

90% from 2005 to 2006.

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 2006. 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 2006 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. The total collective dose decreased 

by 4% to a value of 11,021 person-rem in 2006. 

The PWRs with the largest decreases in the 

collective dose were Arkansas and St. Lucie. 

San Onofre experienced the highest increase 

in collective dose among PWRs. This was 

due, in part, to the fact that San Onofre 2 and 3 

had no refueling outages in the previous year. 

The BWRs with the largest decreases in the 

collective dose were Quad Cities and Perry. 

Although Quad Cities experienced a large drop 

in collective dose in 2006, Quad Cities had 

six outages in 2006 to support a steam dryer 

replacement as part of a planned power uprate. 

The collective dose for Quad Cities 2 and 3 in 

2006 was 559 person-rem. Clinton experienced 

the highest increase in collective dose among 

BWRs. 
4-7

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 4.4

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

1977–2006

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

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4-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

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 

2006, the average collective dose per LWR 

dropped by 86%. Between 2005 and 2006, the 

collective dose per reactor for PWRs increased 

by 10% to 87 person-rem. The collective dose 

per reactor for BWRs decreased by 16% to 143 

person-rem from 2005 to 2006. The overall 

collective dose per reactor for LWRs decreased 

by 4% from last year's value to 106 personrem in 2006. The number of workers with 

measurable dose per reactor increased to 976 

for BWRs and increased to 668 for PWRs in 

2006. The overall decreasing trend in average 

reactor collective doses since 1983 indicates 

that licensees are continuing to successfully 

implement ALARA dose reduction features at 

their facilities. 

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 2006 the 

net electricity generated increased to 89,990 

MW-yr while the number of operating reactors 

has remained constant for the past 8 years. 

The value for the total collective dose for all 

LWRs decreased by 4% from a value of 11,456 

person-rem in 2005 to 11,021 person-rem in 

2006. Together with the increase in the number 

of workers with measurable dose, this decline 

resulted in the average measurable dose per 

worker decreasing to 0.14 rem in 2006 (when 

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 most of 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 2006. 

7

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

 doses.
4-9

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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. 

Because the median values usually are not as 

greatly affected by the extreme values of the 

collective doses, they do not normally fluctuate 

as much from year to year as do the average 

values. The median collective dose for PWRs 

increased to 74 person-rem in 2006. At BWRs, 

the median fluctuates more from year to year. 

The median collective dose decreased from 153 

person-rem in 2005 to 130 person-rem in 2006. 

Figure 4.5 also shows that, in 2006, 50% of the 

PWRs reported collective doses between 45 

and 106 person-rem, while 50% of the BWRs 

reported collective doses between 97 and 214 

person-rem. 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).
4-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

FIGURE 4.1. Average Collective Dose and Number of Workers

with Measurable Dose per Reactor

1973–2006
4-11

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 4.2. Number of Operating Reactors and Electricity Generated

1973–2006

* Gross electricity is shown for 1973–1996, net electricity is shown for 1997–2006.
4-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

FIGURE 4.3. Average Measurable Dose per Worker and Collective Dose per Megawatt-Year

1973–2006

* Gross electricity is shown for 1973–1996, net electricity is shown for 1997–2006.
4-13

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 4.4. Average, Median, and Extreme Values of the Collective Dose per Reactor

1973–1991
4-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

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

1992–2006
4-15

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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, 2006, 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 by the 35 BWRs listed, the 

average 3-year collective TEDE per reactor 

was found to be 157 person-rem, the average 

measurable TEDE per worker was 0.16 rem, 

and the average collective TEDE per MW-yr 

was 0.18 person-rem per MW-yr. The values 

for all three parameters decreased from 2005 

to 2006.

Based on the 207 reactor-years of operation 

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 

79 person-rem, 0.13 rem, and 0.09 person-rem 

per MW-yr, respectively. 

The average 3-year collective TEDE per 

BWR for 2004 to 2006 is 4% less than the 

average for 2003 to 2005. The average 3-year 

collective TEDE per PWR for 2004 to 2006 is 

2% less than the average for 2003 to 2005. 
4-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

TABLE 4.5

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

2004–2006

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4-17

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 4.6

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

2004–2006

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4-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

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 2006. 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 

2006. 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 the 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 each graph.
5-1

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TRANSIENT WORKERS AND CAREER 

DOSES AT NRC-LICENSED FACILITIES

Section 5

5.1 Termination Reports

Under 10 CFR 20, licensees are required to 

submit NRC Form 5’s to the 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 reports submitted 

in accordance with the old § 20.408, listing 

the individual’s complete dose history during 

employment at the facility, are no longer 

required.

However, the Form 5’s submitted to the NRC 

upon an individual’s termination of employment 

serve 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 

this part. 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 problems 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 2006, over 99% of the transient individuals 

were reported by nuclear power facilities. For 

this reason, these data are shown separately in 

Table 5.1.
5-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

TABLE 5.1

Effects of Transient Workers on Annual Statistical Compilations

2006

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5-3

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Table 5.1 illustrates the impact that the multiple 

reporting of these transient individuals had on 

the summation of the exposure reports for 2006. 

Because each licensee reports the doses 

received by workers while 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 distribution, and average dose 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 2006, Table 5.1 shows that 

the summation of annual reports for reactor 

licensees indicated that 2 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 84 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 32% of the workforce that 

receives measurable dose. The correction for 

the transient workers increases the average 

measurable dose by a factor of 2 from 0.15 rem 

to 0.31 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's 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 exposure limits because of multiple 

exposures at different facilities throughout the 

year. The REIRS database stores the radiation 

exposure information for an individual by his/her 

unique identification number and identification 

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

exposure 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 

2006, there were no individuals reported by 

NRC licensees that exceeded the 5 rem annual 

TEDE limit.
5-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

This page intentionally left blank.
6-

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 Control Levels

Exposures in excess of regulatory limits

are sometimes referred to as “overexposures.”

The phrase “exposures 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

TEDE and to implement a similar limitation

system for organs and tissues (such as the

gonads, redbone 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

exposure limits, but has reporting requirements

for planned special exposures (PSEs)8. The

annual TEDE limit for adult 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

exposures that exceed certain control levels,

thus, providing for investigations and corrective

actions as necessary. Based on the magnitude

of the exposure, the occurrence may be placed

into one of three categories:

1. Category A

10 CFR 20.2202(a)(1)—a TEDE to any

individual of 25 rem or more, an eye

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)—a TEDE to

any individual of 5 rem or more, an eye

dose equivalent of 15 rem or more, or

a shallow-dose equivalent to the skin or

extremities of 50 rem or more in a 24-hour

period. The Commission must be notified 

within 24 hours of these events.
6-

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

3. Category C

10 CFR 20.2203—In addition to the

notification required by § 20.2202 

(Category A or B occurrences), 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 § 20.2202

b. Doses that exceed the limits in

§ 20.1201, § 20.1207, § 20.1208, and

§ 20.1301 (for adults, minors, the embryo/

fetus of a declared pregnant worker, and

the public, respectively), or any applicable

limit in the license

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 this part or in the license (whether

or not involving exposure 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 of 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 exposures in excess of 

regulatory limits

• Events at NRC-licensed facilities

• Final dose of record assigned to an individual

It does not include:

• Medical misadministrations to medical 

patients

• Exposures in excess of 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

NRC

Care should be taken when comparing the

summary information presented here with other

reports and analyses published by the 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 exposures in excess

of regulatory limits represent the status of

events as of the publication of this report. 
6-

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 an exposure

in excess of 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

may not be identified until a later date, such as 

during the next scheduled audit or inspection of

the licensee’s exposure records.

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 an exposure in

excess of the 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 Exposures 

in Excess of Regulatory 

Limits

Table 6.1 summarizes the occupational

exposures in excess of regulatory limits as

reported by NRC licensees pursuant to 10

CFR 20.2202 and 10 CFR 20.2203 from 1994

to 2006. 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 effective 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

limits while employed by one of several types

of licensees. For the period 1985 to 1989, only

the exposures 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 2006, there were no Category A, B, or C

occurrences reported under the licensed

activities included in this report.
6-

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

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TABLE 6.1

Occupational Exposures in Excess of Regulatory Limits

1994–2006
6-

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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TABLE 6.2

Occupational Exposures in Excess of Regulatory Limits

1985–1993
6-

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

6.4 Maximum Exposures 

Below the NRC Limits

Because few exposures exceed the NRC

occupational exposure limits, certain

researchers have expressed an interest in a

listing of the maximum exposures received at

NRC licensees that do not exceed the limits. 

This would allow an examination of exposures

that approach, but do not exceed, the limits. 

Table 6.3 shows the maximum exposures for

each dose category required to be reported to

the NRC. In addition, the number of exposures

in certain dose ranges is shown to reflect the 

number of exposures that approaches the NRC

limits.

As shown in Table 6.3, few exposures exceed

half of the NRC occupational annual limits. In

2006, only 14 individuals exceeded 75% of the

TEDE dose limit. No individual exceeded the 5

rem TEDE annual limit or any other annual limit. 

TABLE 6.3

Maximum Occupational Exposures for Each Exposure Category *

2006

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7-

Thirty-Seventh Annual Report, 2004 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. 1, June 1992.

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, with scientific annexes, Volume I, General Assembly of Official Records, United 

Nations, New York, 2000.

12.	 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 the 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.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

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GLOSSARY

Section 8

Agreement State: 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 is reasonably achievable (ALARA): making every reasonable effort to maintain 

exposures to radiation as far below the dose limits in this part 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 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): A 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. 

By-product material: 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 (as in a reactor); and the tailings or wastes produced by the extraction or 

concentration of uranium or thorium from ore.

Collective dose: 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.

Committed dose equivalent (CDE): 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.

Committed effective dose equivalent (CEDE): 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.

Exposure: being exposed to ionizing radiation or to radioactive material.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Independent Spent Fuel Storage Installation (ISFSI): a complex designed and constructed for the 

interim storage of spent nuclear fuel, solid reactor-related waste, and other radioactive materials 

associated with spent fuel and reactor-related waste storage. An ISFSI which is located on the 

site of another facility licensed by the NRC or a facility licensed under 10 CFR Part 50 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): the external exposure of the lens of the eye and is taken as the dose 

equivalent at a tissue depth of 0.3 centimeter.

License: a license issued under the regulations in 10 CFR parts 30 through 35, 39, 40, 50, 60, 61, 

70, or 72.

Licensee: the holder of the NRC license.

Licensed material: source material, special nuclear material, or byproduct material received, 

possessed, used, transferred or disposed of under a general or specific license issued by the 

Commission.

Light water reactor (LWR): A term used to describe reactors using ordinary water as coolant, 

including boiling water reactors (BWRs) and pressurized water reactors (PWRs), the most common 

types used in the United States. 

Measurable dose: a dose greater than zero rem (does not include doses reported as ‘not 

detectable’.)

Megawatt-year: A unit of electric energy, equal to the energy from a power of 1,000,000 watts over 

a period of 1 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 by-product material; independent spent fuel storage installations; 

facilities for land disposal of low-level waste; and geologic repositories for high-level waste.
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Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Number of individuals with measurable dose: the count of unique individuals that received 

measurable dose during the monitoring year. In some instances in this report, the number of 

individuals with measurable dose may include individuals that 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: the dose received by an individual in a restricted area or 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. 

Pressurized water reactor (PWR): A 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 

is generated in a secondary circuit. The majority of reactors producing electric power in the United 

States are pressurized water reactors. 

Pulmonary clearance class: a classification scheme for inhaled material according to its rate of 

clearance from the pulmonary region of the lung. 

Radionuclide: a radioisotope.

REM: 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 

and is taken as the dose equivalent at a tissue depth of 0.007 centimeter. 

Shallow dose equivalent, Whole body (SDE-WB): the external exposure of the skin and is taken as 

the dose equivalent at a tissue depth of 0.007 centimeter. 

Sievert: 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): plutonium, uranium-233, uranium enriched in the isotope 233 or in 

the isotope 235, and any other material that the Commission, pursuant to the provisions of section 

51 of the Act, determines to be special nuclear material, but does not include source material. 

Total effective dose equivalent (TEDE): the sum of the deep-dose equivalent (for external 

exposures) and the committed effective dose equivalent (for internal exposures). 
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Transient individual: one who is monitored at more than one 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 on-line or was capable of such operation) times 100 divided by the period 

hours
A-1

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ANNUAL TEDE FOR NONREACTOR 

NRC LICENSEES

2006

Appendix A
A-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713 APPENDIX A Annual TEDE for Nonreactor NRC Licensees 2006

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. *Dose values exactly equal to the values separating ranges are reported in the next higher range.

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A-3

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Annual TEDE for Nonreactor NRC Licensees

2006 (continued)

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. *Dose values exactly equal to the values separating ranges are reported in the next higher range.
A-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713 APPENDIX A Annual TEDE for Nonreactor NRC Licensees 2006 (continued)

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. *Dose values exactly equal to the values separating ranges are reported in the next higher range.
A-5

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Annual TEDE for Nonreactor NRC Licensees

2006 (continued)

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A-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713 APPENDIX A Annual TEDE for Nonreactor NRC Licensees 2006 (continued)

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A-7

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Annual TEDE for Nonreactor NRC Licensees

2006 (continued)

 NOTE: The data values shown bolded and in boxes represent the highest value in each category. *Dose values exactly equal to the values separating ranges are reported in the next higher range.
A-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713 APPENDIX A Other Facilities Reporting to the NRC 2006 (continued)

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 NOTE: The data values shown bolded and in boxes represent the highest value in each category. *Dose values exactly equal to the values separating ranges are reported in the next higher range. ** Not listed as an active NRC licensee for 2006.

**
A-9

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 67 85 50 21 25 60 20 5 3 372 305 220.364 0.723 36 NOTE: The data values shown bolded and in boxes represent the highest value in each category. *Dose values exactly equal to the values separating ranges are reported in the next higher range.

APPENDIX A

Other Facilities Reporting to the NRC

2006 (continued)
A-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

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 NOTE: The data values shown bolded and in boxes represent the highest value in each category. *Dose values exactly equal to the values separating ranges are reported in the next higher range.

APPENDIX A

Other Facilities Reporting to the NRC

2006 (continued)
B-1

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ANNUAL WHOLE-BODY DOSES AT LICENSED 

NUCLEAR POWER FACILITIES

2006

Appendix B
B-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713 APPENDIX B Annual Whole-Body Doses at Licensed Nuclear Power Facilities 2006

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B-3

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX B

Annual Whole-Body Doses at Licensed Nuclear Power Facilities

2006 (continued)
B-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713 APPENDIX B Annual Whole-Body Doses at Licensed Nuclear Power Facilities 2006 (continued)

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C-1

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

PERSONNeL, DOSE, AND POWER GENERATION 

SUMMARY

1969–2006

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 Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

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 1,249 167 0.13 0.11

1999 1,477.3 86.9 1,463 184 0.13 0.12

2000 1,329.2 79.5 1,977 242 0.12 0.18

2001 1,684.0 95.8 1,082 106 0.10 0.06

2002 1,659.0 91.8 1,581 265 0.17 0.16

2003 1,675.8 93.1 973 99 0.10 0.06

2004 1,759.5 95.0 1,227 106 0.09 0.06

2005 1,560.0 84.5 2,335 476 0.20 0.31 

2006 1,739.8 95.0 1,184 143 0.12 0.08

BEAVER VALLEY 1, 2 1977 355.6 57.0 331 878 0.26 2.47

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 - 821, 821 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 0.08 0.11

1999 1,353.7 85.9 841 99 0.12 0.07

2000 1,378.7 87.3 1,730 338 0.20 0.24

2001 1,500.8 92.3 1,202 184 0.15 0.12

 2002 1,548.0 95.4 1,048 90 0.09 0.06

2003 1,437.0 88.4 1,623 277 0.17 0.19

2004 1,593.1 96.3 1,270 157 0.12 0.10

2005 1,590.4 96.7 978 79 0.08 0.0 

2006 1,385.6 84.0 2,174 370 0.17 0.27
C-3

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

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

1997 22.4 54.1 258 55 0.21 2.46

1998 0.0 0.0 432 104 0.24 ---

1999 0.0 0.0 285 87 0.31 ---

2000 0.0 0.0 226 89 0.40 ---

2001 0.0 0.0 167 48 0.28 ---

2002 0.0 0.0 170 44 0.26 ---

2003 0.0 0.0 336 121 0.36 ---

2004 0.0 0.0 227 58 0.25 ---

2005 0.0 0.0 223 20 0.09 --- 

2006 0.0 0.0 27 0 0.01 ---

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 0.14 0.13

1999 2,161.6 95.8 1,153 146 0.13 0.07

2000 2,142.8 94.9 1,562 194 0.12 0.09

2001 2,186.4 95.8 881 101 0.11 0.05

2002 2,284.0 96.8 975 91 0.09 0.04

2003 2,279.9 95.6 1,572 245 0.16 0.11

2004 2,277.8 97.3 986 95 0.10 0.04

2005 2,253.7 96.6 926 88 0.10 0.04 

2006 2,234.1 95.0 1,624 199 0.12 0.09

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 Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

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 - (1,065), 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 1,612 368 0.23 0.19

1999 2,091.0 85.1 1,741 447 0.26 0.21

2000 2,143.8 97.1 1,657 333 0.20 0.16

2001 2,074.0 90.7 1,525 294 0.19 0.14

2002 2,069.0 95.4 1,977 358 0.18 0.17 

2003 2,014.5 93.6 2,608 603 0.23 0.30

2004 2,104.7 95.5 3,242 673 0.21 0.32

2005 2,044.2 94.3 3,743 636 0.17 0.31 

2006 2,040.1 94.0 3,618 641 0.18 0.31

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

1994 1,268.4 83.0 3,049 999 0.70 0.79

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 2,005 396 0.20 0.26

1999 1,494.7 92.8 1,818 418 0.23 0.28

2

Browns Ferry 1 remains in the count of operating reactors, but was placed on administrative hold in June of 1985. Parentheses 

indicate plant capacity when plant was operational.
C-5

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

BRUNSWICK 1, 2 2000 1,571.2 95.6 1,648 322 0.20 0.20

(continued) 2001 1,576.0 95.8 1,623 303 0.19 0.19

2002 1,568.0 94.5 1,743 276 0.16 0.18 

2003 1,676.9 95.6 1,794 249 0.14 0.15

2004 1,690.6 94.5 2,140 245 0.11 0.14

2005 1,654.9 92.2 1,944 306 0.16 0.19 

2006 1,661.2 90.0 2,103 280 0.13 0.17

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 0.15 0.15

1999 2,064.2 92.3 1,478 239 0.16 0.12

2000 2,196.9 97.4 959 194 0.20 0.09

2001 2,301.5 97.8 719 59 0.08 0.03

2002 2,205.0 93.8 1,287 195 0.15 0.09

2003 2,294.8 97.2 824 87 0.11 0.04

2004 2,277.4 97.7 906 89 0.10 0.04

2005 2,175.6 94.2 1,542 200 0.13 0.09 

2006 2,223.3 95.0 1,163 134 0.12 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 91.3 929 201 0.22 0.21

1999 981.3 88.7 1,098 321 0.29 0.33

2000 1,137.5 99.8 244 16 0.07 0.01

2001 954.5 86.7 873 107 0.12 0.11

2002 955.0 86.2 983 96 0.10 0.10

2003 1,104.3 96.2 252 8 0.03 0.01

2004 892.8 78.9 1,124 121 0.11 0.14

2005 913.2 80.7 1,600 223 0.14 0.24 

2006 1,152.8 95.0 225 6 0.03 0.01

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
C-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

CALVERT CLIFFS 1, 2 1987 1,207.3 71.8 1,384 412 0.30 0.34

(continued) 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 1,042 187 0.18 0.12

1999 1,521.4 90.1 1,134 192 0.17 0.13

2000 1,575.7 92.7 912 135 0.15 0.09

2001 1,554.7 91.7 895 167 0.19 0.11

2002 1,380.0 81.7 1,582 245 0.16 0.18

2003 1,558.4 90.9 1,671 265 0.16 0.17 

2004 1,653.7 95.7 1,205 144 0.12 0.09

2005 1,678.1 97.2 942 168 0.18 0.10 

2006 1,581.8 92.0 1,215 204 0.17 0.13

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 0.14 0.08

1999 2,046.7 90.2 1,024 119 0.12 0.06

2000 2,038.3 90.3 1,185 187 0.16 0.09

2001 2,119.9 92.9 960 116 0.12 0.06

2002 2,238.0 97.2 884 81 0.09 0.04

2003 1,991.8 89.2 1,409 211 0.15 0.11

2004 2,111.4 93.0 1,123 123 0.11 0.06

2005 2,194.5 96.0 1,019 84 0.08 0.04 

2006 1,928.6 85.0 1,792 213 0.12 0.11

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

1994 883.3 94.8 409 63 0.15 0.07

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 0.0 866 177 0.17 ---

1999 537.0 63.5 637 87 0.14 0.16

2000 784.2 87.8 1,248 253 0.20 0.32

2001 896.8 98.5 329 34 0.10 0.04

2002 872.0 90.5 1,418 208 0.15 0.24

2003 990.5 99.1 372 57 0.15 0.06

2004 910.8 92.6 1,622 283 0.17 0.31

2005 989.1 97.4 298 36 0.12 0.04 

2006 939.9 92.0 1,649 296 0.18 0.32
C-7

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

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 0.23 0.36

1999 694.7 70.0 1,022 155 0.15 0.22

2000 979.6 96.3 706 53 0.08 0.05

2001 939.3 88.1 1,515 227 0.15 0.24

2002 1,023.0 97.5 647 47 0.07 0.05

2003 866.9 81.8 1,618 205 0.13 0.24

2004 1,022.5 94.6 716 66 0.09 0.06

2005 938.3 87.3 1,718 325 0.19 0.35 

2006 1,064.9 98.0 623 56 0.09 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 0.24 0.11

1999 1,981.5 90.9 1,316 251 0.19 0.13

2000 2,104.7 95.3 759 78 0.10 0.04

2001 2,085.9 94.7 853 115 0.13 0.06

2002 1,887.0 86.9 1,106 225 0.20 0.12

2003 2,020.6 91.6 639 66 0.10 0.03

2004 2,169.5 95.1 864 135 0.16 0.06

2005 2,099.6 91.5 1,365 242 0.18 0.12

2006 2,271.3 97.0 686 60 0.09 0.03 

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 - 1,016, 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

3

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

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

COOK 1, 2 1994 1,105.2 65.2 1,748 479 0.27 0.43

(continued) 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 1,155 105 0.09 ---

1999 0.0 0.0 1,662 171 0.10 ---

2000 560.1 28.1 2,506 338 0.14 0.60

2001 1,794.3 89.2 423 27 0.06 0.02

2002 1,756.0 87.3 1,624 278 0.17 0.16

2003 1,557.6 75.7 1,408 210 0.15 0.13

2004 1,909.2 91.4 1,015 156 0.15 0.08

2005 1,989.0 95.0 852 91 0.11 0.05 

2006 1,790.5 86.0 1,780 312 0.18 0.17

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 - 757 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 75.9 977 182 0.19 0.33

1999 743.2 98.1 318 48 0.15 0.06

2000 539.2 74.2 963 200 0.21 0.37

2001 592.7 80.9 1,309 169 0.13 0.28

2002 719.0 98.6 362 39 0.11 0.05

2003 511.4 74.1 882 135 0.15 0.26

2004 702.6 94.7 481 47 0.10 0.07

2005 670.8 89.4 1,266 276 0.22 0.41 

2006 674.7 90.0 1,265 270 0.21 0.40

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
C-9

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

CRYSTAL RIVER 3 1993 722.4 85.0 683 60 0.09 0.08

(continued) 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 0.06 0.03

1999 727.5 87.8 1,324 251 0.19 0.35

2000 819.4 97.6 257 15 0.06 0.02

2001 741.6 89.2 902 148 0.16 0.20

2002 831.0 99.4 128 5 0.04 0.01

2003 749.0 90.8 961 127 0.13 0.17

2004 831.4 98.1 131 4 0.03 ---

2005 723.0 88.5 939 123 0.13 0.17 

2006 793.8 95.0 138 4 0.03 0.01

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 - 882 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 0.16 0.22

1999 841.3 95.6 397 28 0.07 0.03

2000 770.8 87.3 1,109 168 0.15 0.22

2001 875.6 100.0 119 6 0.05 0.01

2002 106.0 12.6 1,983 403 0.20 3.81

2003 0.0 0.0 1,047 220 0.21 ---

2004 657.8 77.6 161 7 0.04 0.01

2005 817.1 93.3 577 51 0.09 0.06 

2006 727.8 84.0 1,331 204 0.15 0.28

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, 1,087 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 0.26 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 0.13 0.09

1999 1,902.8 90.1 1,566 449 0.29 0.24

2000 1,940.1 92.0 1,057 181 0.17 0.09

2001 2,067.7 96.4 1,074 118 0.11 0.06

2002 1,860.0 88.4 1,016 149 0.15 0.08
C-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

DIABLO CANYON 1, 2 2003 1,970.7 91.6 1,004 135 0.13 0.07

(continued) 2004 1,736.3 83.5 1,230 254 0.21 0.15

2005 2,022.4 94.8 955 124 0.13 0.06 

2006 2,109.0 94.0 1,086 82 0.08 0.04

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

1998 1,354.7 90.6 2,311 427 0.18 0.32

1999 1,410.9 92.5 3,243 591 0.18 0.42

2000 1,506.4 97.3 2,341 262 0.11 0.17

2001 1,427.4 94.5 2,769 401 0.14 0.28

2002 1,547.0 95.7 2,819 355 0.13 0.23

2003 1,555.9 93.5 2,098 357 0.17 0.23

2004 1,405.5 84.8 2,044 381 0.19 0.27

2005 1,550.8 92.0 2,006 259 0.13 0.17 

2006 1,649.0 96.0 2,042 289 0.14 0.18

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 - 582 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

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

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

DUANE ARNOLD 1988 386.5 75.2 1,136 614 0.54 1.59

(continued) 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 1,019 237 0.23 0.54

1999 416.6 84.3 834 201 0.24 0.48

2000 507.3 98.4 317 44 0.14 0.09

2001 439.5 86.8 898 138 0.15 0.31

2002 522.0 94.4 319 35 0.11 0.07 

2003 455.2 84.8 829 124 0.15 0.27 

2004 561.2 98.3 220 19 0.09 0.03

2005 517.4 90.5 879 140 0.16 0.27 

2006 581.7 99.0 254 29 0.12 0.05

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

1992 1,331.7 81.8 2,018 805 0.40 0.60

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 1,380 432 0.31 0.33

1999 1,436.0 91.4 1,102 190 0.17 0.13

2000 1,430.1 88.6 1,683 360 0.21 0.25

2001 1,384.3 84.4 1,810 321 0.18 0.23

2002 1,558.0 93.5 772 96 0.13 0.06 

2003 1,592.6 95.3 788 111 0.14 0.07

2004 1,496.8 89.4 1,141 107 0.09 0.07

2005 1,564.2 93.3 810 68 0.08 0.04 

2006 1,602.7 94.0 747 66 0.09 0.04

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 - 1,098 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 1,362 208 0.15 0.25

1999 1,082.7 99.5 461 36 0.08 0.03

2000 939.6 87.6 1,266 146 0.12 0.15

2001 975.0 90.9 1,202 169 0.14 0.17
C-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

FERMI 2 2002 1,059.0 98.7 463 38 0.08 0.04 

(continued) 2003 925.3 86.9 1,207 168 0.14 0.18

2004 962.3 90.0 1,302 145 0.11 0.15

2005 998.1 91.7 538 62 0.11 0.06 

2006 855.9 83.0 1,430 181 0.13 0.21

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 1,781 358 0.20 0.64

1999 749.7 95.5 558 68 0.12 0.09

2000 685.9 88.4 1267 301 0.24 0.44

2001 807.2 98.9 665 63 0.10 0.08

2002 751.0 93.3 1,234 231 0.19 0.31 

2003 793.0 97.9 298 51 0.17 0.06

2004 735.0 92.1 1,091 186 0.17 0.25

2005 802.9 96.3 382 63 0.16 0.08

2006 771.5 93.0 1,527 234 0.15 0.30 

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 - 478 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 82.5 788 224 0.28 0.58

1999 409.2 89.2 676 159 0.24 0.39

2000 443.8 93.5 249 35 0.14 0.08
C-13

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

FORT CALHOUN 2001 401.2 88.3 770 226 0.29 0.56

(continued) 2002 434.0 92.3 742 164 0.22 0.38 

2003 399.6 87.0 914 212 0.23 0.53

2004 463.5 97.0 215 22 0.10 0.05

2005 332.4 72.2 1,069 273 0.26 0.82 

2006 353.9 75.0 1,591 289 0.18 0.82

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

1991 418.6 86.7 947 328 0.35 0.78

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 15 0.09 0.03

1999 403.4 85.6 641 175 0.27 0.43

2000 434.2 91.6 429 76 0.18 0.18

2001 488.0 100.0 140 10 0.07 0.02

2002 438.0 91.3 535 80 0.15 0.18 

2003 440.4 91.1 510 75 0.15 0.17

2004 490.5 99.5 111 7 0.07 0.02

2005 455.0 93.9 564 73 0.13 0.16 

2006 470.2 94.0 514 45 0.09 0.10

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 1,410 304 0.22 0.29

1999 962.1 81.3 1,180 226 0.19 0.23

2000 1,217.5 99.4 289 35 0.12 0.03

2001 1,129.8 93.0 1,109 185 0.17 0.16

2002 1,145.0 93.6 1,060 176 0.17 0.15

2003 1,241.2 98.6 290 31 0.11 0.03

2004 1,165.2 92.2 1,243 158 0.13 0.14

2005 1,147.3 91.9 1,326 168 0.13 0.15

2006 1,233.7 98.0 1,016 60 0.06 0.05 
C-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

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

1986 294.8 53.6 1,945 1,567 0.81 5.32

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 94 0.22 ---

1999 0.0 0.0 545 109 0.20 ---

2000 0.0 0.0 555 262 0.47 ---

2001 0.0 0.0 361 95 0.26 ---

2002 0.0 0.0 258 52 0.20 --- 

2003 0.0 0.0 400 82 0.21 ---

2004 0.0 0.0 564 92 0.16 ---

2005 0.0 0.0 350 36 0.10 --- 

2006 0.0 0.0 124 12 0.10 --- 

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 0.14 0.17

1999 827.0 97.9 247 16 0.06 0.02

2000 783.0 92.5 888 101 0.11 0.13 

2001 611.2 72.4 1,586 252 0.16 0.41

2002 892.0 99.4 145 7 0.05 0.01 

2003 823.9 93.2 786 68 0.09 0.08

2004 797.9 88.2 747 57 0.08 0.07

2005 902.9 99.5 164 8 0.05 0.01 

2006 802.4 89.0 917 87 0.10 0.11 

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

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

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

1990 1,268.0 83.5 2,902 1,455 0.50 1.15

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 0.20 0.22

1999 1,487.4 90.0 1,866 329 0.18 0.22

2000 1,515.0 88.7 1,913 402 0.21 0.26

2001 1,603.0 93.5 1,407 230 0.16 0.14

2002 1,600.0 94.0 1,299 214 0.17 0.13 

2003 1,606.3 94.5 1,295 168 0.13 0.10

2004 1,641.3 95.3 1,209 180 0.15 0.11

2005 1,562.1 91.3 1,288 207 0.16 0.13 

2006 1,604.9 94.0 1,405 259 0.18 0.16

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 55 0.09 0.06

1999 879.1 86.7 1,111 279 0.25 0.32

2000 827.8 87.9 1,236 188 0.15 0.23

2001 918.2 91.1 1,532 156 0.10 0.17

2002 1,007.0 99.2 220 26 0.12 0.03 

2003 826.6 84.6 1,597 139 0.09 0.17

2004 688.6 71.3 2,440 240 0.10 0.35

2005 874.9 88.6 881 67 0.08 0.08 

2006 983.8 93.0 2,135 134 0.06 0.14 
C-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

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 ---

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 1 0.03 ---

1999 0.0 0.0 28 1 0.04 ---

2000 0.0 0.0 20 1 0.05 ---

2001 0.0 0.0 10 0 0.04 ---

2002 0.0 0.0 18 2 0.08 --- 

2003 0.0 0.0 14 0 0.03 ---

2004 0.0 0.0 11 0 0.04 ---

2005 0.0 0.0 11 1 0.05 --- 

2006 0.0 0.0 40 4 0.10 --- 

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, 1,016 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 1982 532.4 65.4 2,144 1,635 0.76 3.07

10/62, 8/74 1983 702.6 84.0 1,057 486 0.46 0.69

Type - PWRs 1984 416.7 51.9 2,919 2,644 0.91 6.35

Capacity - (265), 998 MWe 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

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 utlity since 2001, Indian Point 3 still reports separately.
C-17

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

INDIAN POINT 17, 2 1991 461.2 55.7 1,810 1,468 0.81 3.18

(continued) 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

1997 360.6 45.1 1,340 367 0.27 1.02

1998 282.8 31.5 1,154 290 0.25 1.03

1999 831.8 88.2 350 41 0.12 0.05

2000 115.4 13.0 2,003 567 0.28 4.90

2001 887.2 97.2 399 22 0.06 0.02

2002 860.0 91.3 1,361 248 0.18 0.29 

2003 953.0 98.9 241 12 0.05 0.01

INDIAN POINT 17 2004 0 0 156 3 0.02 ---

Docket 50-3; DPR-05 2005 0.0 0.0 151 7 0.04 --- 

1st commercial operation 10/62 2006 193 8 0.04 --- 

Type - PWR 

Capacity - (265) MWe

INDIAN POINT 2 2004 855.3 91.0 1,136 196 0.17 0.23

Docket 50-247; DPR-26 2005 1,007.2 100.0 470 11 0.02 0.01 

1st commercial operation 8/74 2006 911.5 91.0 1,327 287 0.22 0.32

Type - PWR 

Capacity - 998 MWe

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 - 1,016 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 15 0.07 0.02

1999 829.8 88.3 893 117 0.13 0.14

2000 960.0 99.3 143 9 0.06 0.01

2001 903.9 93.1 1,014 118 0.12 0.13

2002 960.0 98.5 156 7 0.04 0.01 

2003 866.2 89.8 902 96 0.11 0.11

2004 995.8 100.0 234 4 0.02 ---

2005 915.0 91.7 893 74 0.08 0.08 

2006 1,024.5 100.0 307 3 0.01 0.00 

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 utlity since 2001, Indian Point 3 still reports separately.
C-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

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

1982 458.4 87.6 353 101 0.29 0.22

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 87.2 284 88 0.23 0.21

1999 505.1 100.0 103 5 0.05 0.01

2000 432.6 88.8 394 100 0.25 0.23

2001 394.1 80.8 1,110 200 0.18 0.51

2002 509.0 97.4 102 4 0.04 0.01 

2003 473.5 90.5 439 73 0.17 0.15

2004 441.0 81.0 565 91 0.16 0.21

2005 346.4 62.7 97 4 0.04 0.01 

2006 419.4 77.0 539 75 0.14 0.18

LACROSSE9 1970 15.3 111 7.25

Docket 50-409; DPR-45 1971 323.1 218 158 0.72 0.49

1st commercial operation 11/69 1972 29.2 151 1.14 5.17

Type - BWR 1973 24.4 157 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 ---

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-19

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

LACROSSE9 1996 0.0 0.0 25 4 0.15 ---

(continued) 1997 0.0 0.0 23 2 0.09 ---

1998 0.0 0.0 27 2 0.07 ---

1999 0.0 0.0 66 4 0.06 ---

2000 0.0 0.0 37 4 0.10 ---

2001 0.0 0.0 45 3 0.06 ---

2002 0.0 0.0 47 2 0.05 --- 

2003 0.0 0.0 65 2 0.03 ---

2004 0.0 0.0 56 1 0.02 ---

2005 0.0 0.0 51 8 0.16 --- 

2006 0.0 0.0 0 0.00 --- 

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 0.20 1.11

1999 1,671.9 81.8 2,689 576 0.21 0.34

2000 2,138.6 97.1 1,831 260 0.14 0.12

2001 2,223.8 98.9 535 83 0.15 0.04

2002 2,040.0 92.1 2,012 450 0.22 0.22 

2003 2,100.2 94.8 2,253 464 0.21 0.22

2004 2,162.1 96.0 2,366 359 0.15 0.17 

2005 2,130.4 95.0 2,097 335 0.16 0.16 

2006 2,181.3 97.0 2,006 248 0.12 0.11

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 0.19 0.19

1999 2,089.6 94.2 1,800 272 0.15 0.13

2000 2,154.9 95.8 1,279 261 0.20 0.12

2001 2,205.9 97.3 1,127 210 0.19 0.10

2002 2,197.0 97.1 1,248 160 0.13 0.07 

2003 2.213.6 97.2 1,298 147 0.11 0.07

2004 2,218.9 97.6 1,265 149 0.12 0.07

2005 2,168.9 96.3 1,460 188 0.13 0.09 

2006 2,207.2 97.0 1,509 193 0.13 0.09

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 Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

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 0.37 ---

1999 0.0 0.0 365 135 0.37 ---

2000 0.0 0.0 490 121 0.25 ---

2001 0.0 0.0 412 68 0.17 ---

2002 0.0 0.0 452 66 0.15 --- 

2003 0.0 0.0 342 44 0.13 ---

2004 0.0 0.0 190 21 0.11 ---

2005 0.0 0.0 2 0 0.02 --- 

2006 0.0 0.0 0 0 0.00 ---

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 0.14 0.07

1999 1,961.7 88.9 1,274 257 0.20 0.13

2000 2,100.1 94.2 940 133 0.14 0.06

2001 2,113.3 93.9 963 137 0.14 0.06

2002 2,051.0 91.7 1,167 181 0.16 0.09 

2003 2,156.2 96.0 841 71 0.08 0.03

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-21

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

MCGUIRE 1, 2 2004 2,075.7 91.8 1,116 196 0.18 0.09

(continued) 2005 1,993.9 89.2 1,401 174 0.12 0.09 

2006 2,100.2 93.0 1,218 108 0.09 0.05

MILLSTONE UNIT 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 13 0.04 ---

1999 0.0 0.0 397 10 0.02 ---

2000 0.0 0.0 478 60 0.13 ---

2001 0.0 0.0 414 15 0.04 ---

2002 0.0 0.0 185 4 0.02 ---

2003 0.0 0.0 195 11 0.05 ---

2004 0.0 0.0 147 11 0.08 ---

2005 0.0 0.0 145 1 0.01 --- 

2006 0.0 0.0 4 1 0.15 --- 

MILLSTONE UNIT 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

1991 819.5 69.7 1,084 381 0.35 0.46

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

11Millstone Unit 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-22

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

MILLSTONE UNIT 2, 3 1994 1,556.6 73.1 1,249 188 0.15 0.12

(continued) 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 1,179 113 0.10 0.30

1999 1,446.3 73.3 1,688 252 0.15 0.17

2000 1,865.8 92.4 1,385 143 0.10 0.08

2001 1,759.3 92.0 1,327 174 0.13 0.10

2002 1,703.0 87.5 1,548 292 0.19 0.17

2003 1,834.6 91.0 1,274 323 0.25 0.18

2004 1,887.5 95.0 803 136 0.17 0.07

2005 1,777.1 88.8 1,329 202 0.15 0.11 

2006 1,898.5 93.0 1,160 174 0.15 0.09

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 0.31 0.44

1999 530.7 92.9 451 70 0.16 0.13

2000 483.2 84.2 792 216 0.27 0.45

2001 441.3 78.5 834 221 0.26 0.50

2002 571.0 99.0 399 40 0.10 0.07

2003 522.8 91.7 858 169 0.20 0.32

2004 573.2 99.2 279 35 0.13 0.06

2005 509.4 90.0 919 175 0.19 0.34 

2006 579.1 100.0 273 33 0.12 0.06 
C-23

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

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

1977 347.4 59.2 1,093 1,383 1.27 3.98

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 0.22 0.27

1999 1,409.5 81.3 1,709 447 0.26 0.32

2000 1,443.9 88.1 1,783 283 0.16 0.20

2001 1,506.9 88.9 1,371 343 0.25 0.23

2002 1,517.0 90.4 2,449 517 0.21 0.34

2003 1,585.6 91.4 1,501 375 0.25 0.24

2004 1,551.9 92.0 1,362 449 0.33 0.29

2005 1,656.5 94.5 1,366 402 0.29 0.24 

2006 1,647.1 96.0 1,130 230 0.20 0.14

NORTH ANNA 1, 2 1979 507.0 61.7 2,025 449 0.22 0.89

Docket 50-338; NPF-04, -09 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 - 924, 910 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 1,201 266 0.22 0.16

1999 1,747.7 96.1 727 94 0.13 0.05

2000 1,734.1 95.8 730 65 0.09 0.04

2001 1,491.0 84.8 1,231 309 0.25 0.21

2002 1,557.0 84.3 914 143 0.16 0.09
C-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

NORTH ANNA 1, 2 2003 1,569.1 87.2 1,041 187 0.18 0.12

(continued) 2004 1,685.6 92.0 965 130 0.13 0.08

2005 1,751.5 96.0 686 59 0.09 0.03 

2006 1,723.0 95.0 749 82 0.11 0.05

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 0.22 0.18

1999 2,264.5 90.3 1,568 202 0.13 0.09

2000 2,321.0 91.6 1,686 273 0.16 0.12

2001 2,167.6 86.8 2,002 579 0.29 0.27

2002 2,355.0 92.5 1,723 225 0.13 0.10

2003 2,177.7 86.3 2,180 245 0.11 0.11

2004 2,125.2 84.1 2,295 368 0.16 0.17

2005 2,349.5 92.3 1,516 149 0.10 0.06 

2006 2,274.8 90.0 1,859 221 0.12 0.10

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
C-25

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

OYSTER CREEK 1994 431.7 70.8 2,382 844 0.35 1.96

(continued) 1995 615.4 97.4 761 90 0.12 0.15

1996 515.0 82.6 1,833 449 0.24 0.87

1997 579.1 94.3 509 50 0.10 0.09

1998 490.8 82.4 1,408 308 0.22 0.63

1999 615.1 100.0 466 42 0.09 0.07

2000 444.9 83.3 2,044 614 0.30 1.38

2001 595.0 97.6 442 46 0.10 0.08

2002 573.0 94.0 1,468 266 0.18 0.46 

2003 598.4 97.2 416 43 0.10 0.07

2004 551.8 91.6 1,346 227 0.17 0.41

2005 611.9 99.5 316 28 0.09 0.05 

2006 530.2 90.0 1,443 190 0.13 0.36

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 83.5 895 217 0.24 0.35

1999 585.4 80.2 939 218 0.23 0.37

2000 654.4 88.0 255 26 0.10 0.04

2001 268.2 36.3 1,032 363 0.35 1.35

2002 725.0 94.8 224 24 0.11 0.03 

2003 701.1 90.7 822 203 0.25 0.29

2004 608.6 82.3 974 371 0.38 0.61

2005 756.6 98.0 156 10 0.07 0.01 

2006 675.5 86.0 882 240 0.27 0.36

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 - 1,314, 1,314, 1993 2,677.1 74.3 2,124 592 0.28 0.22

1247 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 0.14 0.06

1999 3,471.2 93.2 1,275 146 0.11 0.04

2000 3,458.6 93.0 1,279 158 0.12 0.05
C-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

PALO VERDE 1, 2, 3 2001 3,280.2 88.6 1,361 182 0.13 0.06

(continued) 2002 3,513.0 94.0 1,343 140 0.10 0.04 

2003 3,254.4 88.6 1,943 211 0.11 0.06

2004 3,201.4 86.3 1,324 199 0.15 0.06

2005 2,937.6 80.4 2,014 200 0.10 0.07 

2006 2,741.1 79.0 1,585 152 0.10 0.06

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 0.19 0.19

1999 2,057.2 96.0 1,630 319 0.20 0.16

2000 2,058.3 96.7 1,729 331 0.19 0.16

2001 2,037.1 95.8 1,445 344 0.24 0.17

2002 2,105.0 96.7 1,915 333 0.17 0.16 

2003 2,072.4 94.9 1,641 356 0.22 0.17

2004 2,148.8 96.4 1,422 265 0.19 0.12

2005 2,102.0 95.6 1,801 306 0.17 0.15 

2006 2,169.1 97.0 1,513 248 0.16 0.11

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 - 1,235 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 42 0.11 0.04

1999 1,041.7 89.9 1,758 326 0.19 0.31

2000 1,148.2 97.1 501 56 0.11 0.05

2001 885.9 79.6 1,392 258 0.19 0.29

2002 1,136.0 95.0 436 70 0.16 0.06 

2003 973.7 83.8 1,880 607 0.32 0.62

2004 1,164.3 95.9 496 73 0.15 0.06

2005 872.9 73.8 1,734 417 0.24 0.48 

2006 1,195.8 99.0 488 65 0.13 0.05 
C-27

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

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 2915.71

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 0.13 0.11

1999 510.7 84.4 1,222 344 0.28 0.67

2000 627.5 98.3 422 51 0.12 0.08

2001 585.6 91.0 1,113 180 0.16 0.31

2002 657.0 100.0 463 38 0.08 0.06 

2003 566.6 87.5 1,437 250 0.17 0.44

2004 676.1 99.5 427 41 0.10 0.06

2005 623.2 93.7 1,212 206 0.17 0.33 

2006 665.4 100.0 654 44 0.07 0.07

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

1995 858.4 86.1 548 190 0.35 0.22

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 0.19 0.26

1999 806.0 83.1 962 194 0.20 0.24
C-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

POINT BEACH 1, 2 2000 872.0 88.7 765 139 0.18 0.16

(continued) 2001 915.9 93.4 740 132 0.18 0.14

2002 909.0 91.1 945 181 0.19 0.20 

2003 917.2 92.1 627 85 0.14 0.09

2004 912.3 90.1 627 110 0.17 0.12

2005 782.5 78.1 851 129 0.15 0.16

2006 977.2 96.0 453 40 0.09 0.04 

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 83.4 582 117 0.20 0.14

1999 989.3 93.8 542 72 0.13 0.07

2000 992.2 93.1 632 106 0.17 0.11

2001 900.8 85.8 691 125 0.18 0.14

2002 987.0 93.6 969 128 0.13 0.13

2003 1,006.1 96.4 594 61 0.10 0.06

2004 940.4 89.9 1,186 144 0.12 0.15

2005 952.5 90.8 782 84 0.11 0.09

2006 926.4 89.0 1,103 137 0.12 0.15

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 - 855, 855 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

1987 1,126.6 75.3 1,429 720 0.50 0.64

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
C-29

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

QUAD CITIES 1, 2 1995 1,002.5 70.4 2,041 736 0.36 0.73

(continued) 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 2,177 761 0.35 0.96

1999 1,476.5 95.9 1,000 201 0.20 0.14

2000 1,410.4 93.9 2,840 894 0.32 0.63

2001 1,478.2 95.9 736 144 0.20 0.10

2002 1,396.0 89.0 3,818 1,786 0.47 1.28 

2003 1,569.4 93.1 998 438 0.44 0.28

2004 1,443.8 95.5 2,334 511 0.22 0.35

2005 1,516.2 94.2 2,869 961 0.33 0.63 

2006 1,524.9 93.0 2,329 559 0.24 0.37

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 0.06 --- 

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 3 0.05 ---

1999 0.0 0.0 302 11 0.04 ---

2000 0.0 0.0 219 26 0.12 ---

2001 0.0 0.0 210 18 0.09 ---

2002 0.0 0.0 193 27 0.14 --- 

2003 0.0 0.0 121 18 0.15 ---

2004 0.0 0.0 122 15 0.12 ---

2005 0.0 0.0 157 33 0.21 --- 

2006 0.0 0.0 143 32 0.22 --- 

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 0.24 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 58 0.12 0.06

1999 651.2 75.2 1,327 344 0.26 0.53

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-30

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

RIVER BEND 1 2000 837.1 89.7 1,104 216 0.20 0.26

(continued) 2001 889.3 93.6 1,249 208 0.17 0.23

2002 965.0 98.5 373 35 0.09 0.04 

2003 871.3 92.7 1,296 217 0.17 0.25

2004 845.6 90.1 1,378 236 0.17 0.28

2005 890.5 94.4 498 56 0.11 0.06 

2006 853.7 92.0 1,494 214 0.14 0.25

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 0.17 0.27

1999 648.9 91.8 807 124 0.15 0.19

2000 710.0 99.7 138 8 0.06 0.01

2001 627.9 90.6 827 125 0.15 0.20

2002 638.0 91.2 830 111 0.13 0.17 

2003 733.1 100.0 109 5 0.04 0.01

2004 653.7 89.3 952 118 0.12 0.18

2005 656.9 89.7 791 65 0.08 0.10 

2006 735.5 100.0 86 3 0.04 0.01

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 - 1,096, 1,092 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
C-31

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

SALEM 1, 2 1998 1,629.3 79.1 408 41 0.10 0.03

(continued) 1999 1,821.8 86.8 1,200 318 0.27 0.17

2000 1,973.4 93.0 1,191 198 0.17 0.10

2001 1,961.2 91.1 1,274 153 0.12 0.08

2002 1,934.0 89.4 2,460 293 0.12 0.15 

2003 1,957.2 90.7 1,301 124 0.10 0.06

2004 1,850.2 85.8 1,496 149 0.10 0.08

2005 2,086.4 91.7 3,162 241 0.08 0.12 

2006 2,211.8 97.0 1,446 91 0.06 0.04

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 0.27 1.47

1985 1,381.8 132.9 5,742 722 0.24 0.52

1986 1,698.2 61.1 3,594 824 0.24 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

1996 2,089.3 93.2 1,272 129 0.10 0.06

 1997 1,533.9 72.9 1,652 341 0.21 0.22

1998 1,996.4 92.0 1,091 196 0.18 0.10

SAN ONOFRE 113 1999 0.0 0.0 241 16 0.07 ---

Docket 50-206; 2000 0.0 0.0 416 71 0.17 ---

DPR-13 2001 0.0 0.0 338 58 0.17 ---

1st commercial operation 1/68 2002 0.0 0.0 308 61 0.20 ---

Type - PWR 2003 0.0 0.0 226 36 0.16 ---

Capacity - (436) MWe 2004 0.0 0.0 169 15 0.09 ---

2005 0.0 0.0 198 21 0.10 --- 

2006 0.0 0.0 183 22 0.12 ---

SAN ONOFRE 2, 3 1999 1,901.4 86.9 1,477 354 0.24 0.19

Docket 50-361, -362; 2000 2,067.2 94.7 1,073 115 0.11 0.06

NPF-10, -15 2001 1,727.2 78.9 1,083 131 0.12 0.08

1st commercial operation 2002 2,056.0 93.4 1,140 136 0.12 0.07

8/83, 4/84 2003 2,084.3 94.0 1,275 164 0.13 0.08

Type - PWRs 2004 1,713.8 79.1 1,761 407 0.23 0.24

Capacity - 1,070, 1,080 MWe 2005 2,094.7 96.0 305 11 0.04 0.01 

2006 1,552.2 73.0 1,632 315 0.19 0.20 

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-32

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

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 19 0.03 0.02

1999 991.5 87.5 1,339 106 0.08 0.11

2000 901.8 79.3 1,158 70 0.06 0.08

2001 989.6 89.1 423 9 0.02 0.01

2002 1,058.0 92.8 1,095 67 0.06 0.06 

2003 1,055.9 93.6 981 71 0.07 0.07

2004 1,158.6 100.0 291 6 0.02 0.01

2005 1,076.4 91.5 1,034 52 0.05 0.05 

2006 1,072.8 89.0 1,246 77 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 1,530 266 0.17 0.12

1999 2,165.1 97.0 1,346 165 0.12 0.08

2000 1,910.0 86.8 2,039 357 0.18 0.19

2001 2,158.3 95.7 1,292 145 0.11 0.07

2002 2,106.0 94.1 1,257 108 0.09 0.05 

2003 1,776.4 80.0 2,484 431 0.17 0.24

2004 2,135.2 93.9 1,161 86 0.07 0.04

2005 2,162.9 94.9 1,125 95 0.08 0.04 

2006 2,054.9 91.0 1,752 242 0.14 0.12

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 1,171 184 0.16 0.08

1999 2,219.7 91.6 1,328 260 0.20 0.12

2000 2,180.0 89.7 1,372 232 0.17 0.11

2001 2,262.7 92.2 1,325 238 0.18 0.11

2002 2,173.0 87.5 1,510 329 0.22 0.15 

2003 1,796.3 72.1 909 143 0.16 0.08

2004 2,437.1 96.0 842 120 0.14 0.05

2005 2,258.5 90.0 1,268 248 0.20 0.11 

2006 2,439.6 95.0 1,078 150 0.14 0.06 
C-33

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

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 0.11 0.09

1999 1,569.1 93.8 1,107 177 0.16 0.11

2000 1,630.0 96.0 990 99 0.10 0.06

2001 1,527.5 91.6 1,375 228 0.17 0.15

2002 1,633.0 96.6 992 156 0.16 0.10 

2003 1,524.7 91.5 937 142 0.15 0.09

2004 1,492.0 89.3 1,157 159 0.14 0.11

2005 1,408.4 85.1 2,262 406 0.18 0.29 

2006 1,542.4 93.0 1,226 120 0.10 0.08

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 14 0.05 0.01

1999 842.0 89.4 827 120 0.15 0.14

2000 723.9 76.6 933 167 0.18 0.23

2001 769.3 83.3 486 69 0.14 0.09

2002 840.0 87.9 685 60 0.09 0.07 

2003 837.0 87.4 745 71 0.10 0.08

2004 938.4 96.8 200 10 0.05 0.01

2005 850.3 88.9 734 72 0.10 0.09 

2006 858.6 90.0 676 61 0.09 0.07 
C-34

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

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 1,165 189 0.16 0.13

1999 1,483.0 93.5 995 138 0.14 0.09

2000 1,490.0 92.7 1,197 193 0.16 0.13

2001 1,441.5 89.5 1,243 329 0.26 0.23

2002 1,557.0 96.0 799 88 0.11 0.06 

2003 1,255.9 79.7 1,628 326 0.20 0.26

2004 1,537.9 94.6 1,028 120 0.12 0.08

2005 1,506.7 94.2 877 88 0.10 0.06 

2006 1,427.0 90.0 1,227 235 0.19 0.17

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 - 1,135, 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 1,575 361 0.23 0.19

1999 1,896.0 89.6 1,787 431 0.24 0.23

2000 1,994.6 92.6 1,812 331 0.18 0.17

2001 2,027.6 94.2 1,807 288 0.16 0.14

2002 1,973.0 91.6 1,890 260 0.14 0.13 

2003 2,050.8 93.4 1,934 250 0.13 0.12

2004 2,058.8 92.7 2,144 272 0.13 0.13

2005 2,086.6 93.5 1,898 181 0.10 0.09 

2006 2,040.4 91.0 1,873 185 0.10 0.09 
C-35

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

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 17 0.06 0.02

1999 722.4 89.7 1,171 155 0.13 0.21

2000 813.4 100.0 183 9 0.05 0.01

2001 616.7 84.2 1,196 197 0.16 0.32

2002 833.0 100.0 172 7 0.04 0.01 

2003 706.4 87.1 1,230 155 0.13 0.22

2004 828.0 100.0 105 4 0.03 0.00

2005 769.1 93.2 955 66 0.07 0.09 

2006 825.0 99.0 125 5 0.04 0.01

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 1 0.01 ---

1999 0.0 0.0 203 1 0.00 ---

2000 0.0 0.0 70 0 0.01 ---

2001 0.0 0.0 0 0 --- ---

2002 --- --- --- --- --- ---

2003 --- --- --- --- --- ---

2004 --- --- --- --- --- ---

2005 --- --- --- --- --- ---

2006 0.0 0.0 --- 0.4 --- --- 

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-36

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

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 0.16 ---

1999 0.0 0.0 274 52 0.19 ---

2000 0.0 0.0 127 18 0.14 ---

2001 0.0 0.0 14 1 0.08 ---

2002 0.0 0.0 13 1 0.04 --- 

2003 0.0 0.0 105 24 0.23 ---

2004 0.0 0.0 5 0 0.02 ---

2005 --- --- --- --- --- --- 

 2006 --- --- --- --- --- --- 

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 0.15 0.12

1999 1,352.5 96.5 919 128 0.14 0.09

2000 1,283.7 92.2 1,292 220 0.17 0.17

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-37

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

TURKEY POINT 3, 4 2001 1,324.1 95.0 827 102 0.12 0.08

(continued) 2002 1,374.0 97.9 793 74 0.09 0.05 

2003 1,253.2 91.6 1,442 247 0.17 0.20

2004 1,231.0 89.9 1,089 117 0.11 0.10

2005 1,143.0 84.9 1,136 110 0.10 0.10 

2006 1,251.8 90.0 1,321 149 0.11 0.12

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

1986 248.1 48.9 1,389 1,188 0.86 4.79

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 0.21 0.52

1999 463.4 91.0 854 176 0.21 0.38

2000 517.8 99.6 198 38 0.19 0.07

2001 474.9 93.5 863 143 0.17 0.30

2002 451.0 91.7 946 150 0.16 0.33 

2003 505.9 98.8 359 54 0.15 0.11

2004 439.2 87.2 1,379 212 0.15 0.48

2005 467.5 94.2 1,105 198 0.18 0.42 

2006 582.9 100.0 380 50 0.13 0.09

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 - 1,152, 1,149 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 0.16 0.08

1999 2,106.0 91.5 1,359 229 0.17 0.11

2000 2,223.9 95.6 899 121 0.14 0.05

2001 2,231.5 96.2 870 129 0.15 0.06

2002 1,942.0 85.3 1,152 244 0.21 0.13 

2003 2,179.9 94.8 806 84 0.10 0.04

2004 2,200.7 95.7 765 81 0.11 0.04

2005 2,027.9 88.6 1,099 151 0.14 0.08 

2006 2,048.8 89.0 892 116 0.13 0.06 
C-38

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

WATERFORD 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 0.09 0.02

1999 849.5 79.6 833 123 0.15 0.14

2000 965.1 88.8 825 132 0.16 0.14

2001 1,086.0 99.6 91 5 0.05 0.00

2002 1,007.0 93.2 811 109 0.14 0.11 

2003 968.0 90.9 710 95 0.13 0.10

2004 1,099.1 100.0 60 3 0.04 ---

2005 900.9 80.2 902 136 0.15 0.15 

2006 1,059.3 92.0 1,190 110 0.09 0.10

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 0.03 0.00

1st commercial operation 5/96 1999 943.1 87.2 975 99 0.10 0.10

Type - PWR 2000 1,033.3 92.8 1,053 122 0.12 0.12

Capacity - 1,121 MWe 2001 1,095.9 96.5 197 6 0.03 0.01

2002 1,034.0 92.1 909 94 0.10 0.09 

2003 973.3 86.7 1,392 166 0.12 0.17

2004 1,122.1 99.1 220 6 0.03 0.01

2005 1,003.7 90.0 1,244 144 0.12 0.14 

2006 764.5 70.0 2,070 323 0.16 0.42

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 - 1,166 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 0.05 0.01

1999 1,045.3 90.1 812 148 0.18 0.14

2000 1,032.7 89.5 861 143 0.17 0.14

2001 1,177.9 100.0 105 5 0.05 0.00

2002 1,029.0 88.7 816 100 0.12 0.10 

2003 1,013.5 87.2 820 89 0.11 0.09

2004 1,153.5 98.8 93 3 0.04 ---

2005 1,004.2 86.7 856 107 0.12 0.11 

2006 1,067.4 91.0 789 97 0.12 0.09

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

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-39

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

Collective 

Dose

(personrem)

YANKEE ROWE17 1974 111.3 243 205 0.84 1.84

(continued) 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

1986 169.7 95.0 384 45 0.12 0.27

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 0.12 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 5 0.04 ---

1999 0.0 0.0 83 2 0.02 ---

2000 0.0 0.0 38 2 0.06 ---

2001 0.0 0.0 48 4 0.08 ---

2002 0.0 0.0 128 20 0.16 --- 

2003 0.0 0.0 136 31 0.23 ---

2004 0.0 0.0 70 7 0.09 ---

2005 0.0 0.0 63 1 0.02 --- 

2006 0.0 0.0 45 1 0.02 --- 

ZION 118, 218 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

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-40

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

Reporting Organization Year

Megawatt 

Years 

(MW-yr)

Unit 

Availability

Factor

Collective 

Dose

(personrem)

Average 

Measurable 

Dose

(rems)

Collective

Dose/

MW-yr

Total 

Personnel 

with

Measurable

Doses

ZION 118, 218 1997 123.2 7.1 924 119 0.13 0.97

(continued) 1998 0.0 0.0 246 12 0.05 ---

1999 0.0 0.0 67 4 0.06 ---

2000 0.0 0.0 26 3 0.12 ---

2001 0.0 0.0 6 0 0.05 ---

2002 0.0 0.0 12 0 0.02 --- 

2003 0.0 0.0 2 0 0.02 ---

2004 0.0 0.0 6 0 0.03 ---

2005 0.0 0.0 5 0 0.02 --- 

2006 0.0 0.0 7 0 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-

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DOSE PERFORMANCE INDICATORS BY 

REACTOR site

1973–2006

Appendix D*

* Appendix D only contains data on plants in operation during 2006.
D-

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

ARKANSAS 1, 2

Dose Performance Indicators

BEAVER VALLEY 1, 2

Dose Performance Indicators
DThirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

BRAIDWOOD 1, 2

Dose Performance Indicators

BROWNS FERRY 1, 2, 3

Dose Performance Indicators
D-

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

BRUNSWICK 1, 2

Dose Performance Indicators

BYRON 1, 2

Dose Performance Indicators
D-

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

CALLAWAY 1

Dose Performance Indicators

CALVERT CLIFFS 1, 2

Dose Performance Indicators
D-

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

CATAWBA 1, 2

Dose Performance Indicators

CLINTON

Dose Performance Indicators
DThirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

COLUMBIA GENERATING

Dose Performance Indicators

COMANCHE PEAK 1, 2

Dose Performance Indicators
D-

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

COOK 1, 2

Dose Performance Indicators

COOPER STATION

Dose Performance Indicators
D-

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

CRYSTAL RIVER 3

Dose Performance Indicators

DAVIS-BESSE

Dose Performance Indicators
D-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

DIABLO CANYON 1, 2

Dose Performance Indicators

DRESDEN 2, 3

Dose Performance Indicators
D-11

Thirty-Ninth Annual Report, 2006 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 Thirty-Ninth Annual Report, 2006

NUREG-0713

FERMI 2

Dose Performance Indicators

FITZPATRICK

Dose Performance Indicators
D-13

Thirty-Ninth Annual Report, 2006 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 Thirty-Ninth Annual Report, 2006

NUREG-0713

GRAND GULF

Dose Performance Indicators

HARRIS 1

Dose Performance Indicators
D-15

Thirty-Ninth Annual Report, 2006 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 Thirty-Ninth Annual Report, 2006

NUREG-0713

INDIAN POINT 2

Dose Performance Indicators

INDIAN POINT 3

Dose Performance Indicators
D-17

Thirty-Ninth Annual Report, 2006 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 Thirty-Ninth Annual Report, 2006

NUREG-0713

LIMERICK 1, 2

Dose Performance Indicators

MCQUIRE 1, 2

Dose Performance Indicators
D-19

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

MONTICELLO

Dose Performance Indicators

MILLSTONE UNIT 2, 3

Dose Performance Indicators
D-20

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

NORTH ANNA 1, 2

Dose Performance Indicators

NINE MILE POINT 1, 2

Dose Performance Indicators
D-21

Thirty-Ninth Annual Report, 2006 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 Thirty-Ninth Annual Report, 2006

NUREG-0713

PALO VERDE 1, 2, 3

Dose Performance Indicators

PALISADES

Dose Performance Indicators
D-23

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

PERRY

Dose Performance Indicators

PEACH BOTTOM 2, 3

Dose Performance Indicators
D-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

POINT BEACH 1, 2

Dose Performance Indicators

PILGRIM 1

Dose Performance Indicators
D-25

Thirty-Ninth Annual Report, 2006 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 Thirty-Ninth Annual Report, 2006

NUREG-0713

ROBINSON 2

Dose Performance Indicators

RIVER BEND 1

Dose Performance Indicators
D-27

Thirty-Ninth Annual Report, 2006 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 Units 2 and 3.
D-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

SEABROOK

Dose Performance Indicators

SEQUOYAH 1, 2

Dose Performance Indicators
D-29

Thirty-Ninth Annual Report, 2006 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 Thirty-Ninth Annual Report, 2006

NUREG-0713

SURRY 1, 2

Dose Performance Indicators

SUMMER 1

Dose Performance Indicators
D-31

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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
D-32

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

TURKEY POINT 3, 4

Dose Performance Indicators

VERMONT YANKEE

Dose Performance Indicators
D-33

Thirty-Ninth Annual Report, 2006 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

VOGTLE 1, 2

Dose Performance Indicators

WATERFORD 

Dose Performance Indicators
D-34

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Ninth Annual Report, 2006

NUREG-0713

WOLF CREEK 1

Dose Performance Indicators

WATTS BAR 1

Dose Performance Indicators