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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.
UN

TI ED STATES

NUCLEAR REGULATORY COMM SI S

OI N

Occupational Radiation

Exposure at Commercial

Nuclear Power Reactors

and Other Facilities

2003

NUREG-0713

Vol. 25

Thirty-Sixth Annual Report

Division of Systems Analysis and Regulatory Effectiveness

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

Manuscript Completed: October 2004

Date Published: October 2004

Prepared by:

Sheryl Burrows

D. A. Hagemeyer*

Oak Ridge Associated Universities

210 Badger Avenue

Oak Ridge, TN 37830

*
ii

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

 PREVIOUS REPORTS IN 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.

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 

 through 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.
iii NUREG-0713

ABSTRACT

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

reprocessors; manufacturers and distributors of byproduct material; independent spent fuel storage installations; facilities for land 

disposal of low-level waste; and geologic repositories for high-level waste. 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) Radiation Exposure Information and Reporting System 

(REIRS). The bulk of the information contained in the report was compiled from the 2003 annual 

reports submitted by fi ve 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 fi ve categories will be 

considered in this report. 

Annual reports for 2003 were received from a total of 223 NRC licensees, of which 104 were 

operators of nuclear power reactors in commercial operation. Compilations of the reports 

submitted by the 223 licensees indicated that 122,281 individuals were monitored, 63,424 of 

whom received a measurable dose (Table 3.1). The collective dose incurred by these individuals 

was 14,413 person-rem, which represents a 3% decrease from the 2002 value. The number 

of workers receiving a measurable dose increased, resulting in an average measurable dose of 

0.23 rem for 2003. The average measurable dose is defi ned as the total collective dose (TEDE) 

divided by the number of workers receiving a measurable dose.2 These fi gures have been 

adjusted to account for transient reactor workers.

In calendar year 2003, the annual collective dose per reactor for light water reactor (LWR) 

licensees was 115 person-rem. This represents a 2% decrease from the value reported for 2002 

(117). The annual collective dose per reactor for boiling water reactors (BWRs) was 162

person-rem and, for pressurized water reactors (PWRs), it was 91 person-rem.

Analyses of transient worker data indicate that 26,102 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 2003, the average 

measurable dose per worker for all licensees calculated from reported data was 0.18 rem. The 

corrected dose distribution resulted in an average measurable dose per worker for all licensees of 

0.23 rem.
NUREG-0713 iv

Mr. Charles Hinson assisted in the preparation of this NUREG, serv ing as 

the Offi ce of Nuclear Reactor Regulation tech ni cal reviewer. The NRC 

welcomes responses from readers.

 Comments should be di rect ed to: 

 Sheryl Burrows: (301) 415-6086

 E-Mail Address: sab2@nrc.gov

 REIRS Project Manager

 Offi ce of Nuclear Reg u la to ry Research

 U.S. Nuclear Regulatory Commission 

 Washington, DC 20555 

EDITOR’S NOTE
v

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

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

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

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

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

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

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.......................................................................................... 3-18

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

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

TABLE OF CONTENTS

Page
vi

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

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 .......................................................... 4-12

 4.6 Graphical Representation of Dose Trends in Appendix D................................................ 4-17

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..................................................................... 6-7

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

APPENDIX A - ANNUAL TEDE FOR NON-REACTOR NRC LICENSEES, 2003 ........................A-1

APPENDIX B - ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES, 2003.............................................................................................................B-1

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

1969 - 2003......................................................................................................................................C-1

APPENDIX D - DOSE PERFORMANCE INDICATORS BY REACTOR SITE,

1973 - 2003......................................................................................................................................D-1

TABLE OF CONTENTS (Continued)

Page
vii

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Figure 3.1 Average Annual Values at Industrial Radiography Facilities, 1973 - 2003............... 3-9

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

 Single Location Licensees, 1999 - 2003 ................................................................. 3-10

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

 Multiple Location Licensees, 1999 - 2003............................................................... 3-10

Figure 3.4 Average Annual Values at Manufacturing and Distribution

 Facilities, 1973 - 2003.............................................................................................. 3-12

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

 Manufacturing and Distribution Licensees, 1999 - 2003......................................... 3-13

Figure 3.6 Collective TEDE Distribution by Dose Range, Limited

 Manufacturing and Distribution Licensees, 1999 - 2003......................................... 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 - 2003.............................................................................................. 3-16

Figure 3.9 Collective TEDE Distribution by Dose Range, Independent Spent

 Fuel Storage Licensees, 1999 - 2003 ..................................................................... 3-17

Figure 3.10 Average Annual Values at Fuel Cycle Licensees, 1973 - 2003.............................. 3-19

Figure 3.11 Collective TEDE Distribution by Dose Range, Fuel Cycle

 Licensees, 1999 - 2003 ........................................................................................... 3-20

Figure 3.12 Collective TEDE Distribution by Dose Range, Reactor

 Licensees, 1999 - 2003 ........................................................................................... 3-21

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

 per Reactor, 1973 - 2003........................................................................................... 4-9

Figure 4.2 Number of Operating Reactors and Gross Electricity

 Generated, 1973 - 2003........................................................................................... 4-10

LIST OF FIGURES

Page
viii

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

Figure 4.3 Average Measurable Dose per Worker and Collective Dose per

 Megawatt-Year, 1973 - 2003.....................................................................................4-11

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

 Dose per Reactor, 1973 - 1986 ............................................................................... 4-13

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

 Dose per Reactor, 1987 - 2003 ............................................................................... 4-14

LIST OF FIGURES (Continued)

Table 3.1 Average Annual Exposure Data for Certain Categories of 

 NRC Licensees, 1994 - 2003 .................................................................................... 3-3

Table 3.2 Distribution of Annual Collective TEDE by License

 Category, 2003........................................................................................................... 3-5

Table 3.3 Summary of Annual Dose Distributions for Certain NRC

 Licensees, 1968 - 2003 ............................................................................................. 3-6

Table 3.4 Annual Exposure Information for Industrial 

 Radiographers, 2001 - 2003...................................................................................... 3-7

Table 3.5 Annual Exposure Information for Manufacturers and 

 Distributors, 2001 - 2003...........................................................................................3-11

Table 3.6 Annual Exposure Information for Fuel Cycle Licenses, 2001 - 2003 ..................... 3-18

Table 3.7 Intake by Licensee Type and Radionuclide

 Mode of Intake - Ingestion and Other, 2003............................................................ 3-23

Table 3.8 Intake by Licensee Type and Radionuclide

 Mode of Intake - Inhalation, 2003............................................................................ 3-24

Table 3.9 Collective and Average CEDE by Licensee, 2003.................................................. 3-26

Table 3.10 Internal Dose (CEDE) Distribution, 1994 - 2003..................................................... 3-27

LIST OF TABLES

Page
ix

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

LIST OF TABLES (Continued)

Table 4.1 Summary of Information Reported by Commercial

 Boiling Water Reactors, 1973 - 2003........................................................................ 4-2

Table 4.2 Summary of Information Reported by Commercial 

 Pressurized Water Reactors, 1973 - 2003 ................................................................ 4-3

Table 4.3 Summary of Information Reported by Commercial

 Light Water Reactors, 1973 - 2003............................................................................ 4-4

Table 4.4 Summary Distribution of Annual Whole Body Doses at

 Commercial Light Water Reactors, 1977 - 2003....................................................... 4-7

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

 of Collective TEDE per BWR, 2001 - 2003 ............................................................. 4-15

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

 of Collective TEDE per PWR, 2001 - 2003 ............................................................. 4-16

Table 5.1 Effects of Transient Workers on Annual Statistical Compilations, 2003................... 5-2

Table 6.1 Occupational Exposures in Excess of Regulatory Limits, 1994 - 2003.................... 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, 2003 ................. 6-7

Page
x

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

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xi

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

A number of 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 are used by the NRC staff as 

indicated below:

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, 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
xii

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

This page intentionally left blank.
xiii NUREG-0713

FOREWORD

This report is intended to provide accurate and timely information to the public about the safety 

performance of NRC licensees and to support openness in our regulatory process.

NUREG-0713, Volume 25, summarizes the 2003 occupational radiation exposure data 

maintained in the U. S. Nuclear Regulatory Commission’s (NRC’s) Radiation Exposure 

Information and Reporting System (REIRS) database. Seven categories of NRC licensees are 

required to annually report individual exposure in accordance with 10 CFR 20.2206. These 

include commercial nuclear power plants; industrial radiographers; fuel processors (including 

uranium enrichment facilities), fabricators, and reprocessors; manufacturers and distributors of 

byproduct material; independent spent fuel storage installations; facilities for land disposal of 

low-level waste; and geologic repositories for high-level waste. Because there are no geologic 

repositories for high-level waste currently licensed, and no low-level waste disposal facilities 

in operation, only fi ve categories are considered in this report. The occupational radiation 

exposure data were received from 223 NRC licensees, of which 104 were operators of nuclear 

power reactors in commercial operation. 

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

individual (122,281 individuals were monitored, and 63,424 received a measurable dose). 

These records are analyzed and presented in this report in terms of collective dose and the 

distribution of dose among the monitored individuals. The collective dose incurred by these 

individuals was 14,413 person-rem, which represents a 3% decrease from the 2002 value of 

14,844 person-rem. The average measurable dose was 0.23 rem, which is a small decrease 

from the 2002 value of 0.24 rem. 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 would generally be expected to be in the range of 0.1 rem 

to 1.0 rem, with 0.24 rem being the current average worldwide value. The average measurable 

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

This annual report is useful in the evaluation of trends in occupational radiation exposures to 

assess the effectiveness of licensee radiation protection programs to maintain exposures as 

low as reasonably achievable (ALARA). For example, 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.

 Farouk Eltawila, Director

Division of Systems Analysis and Regulatory Effectiveness

Offi ce of Nuclear Regulatory Research
xiv

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

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1-1

Thirty-Fifth Annual Report, 2002 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 exposure. 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 

Commission’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 at Science 

Applications International Corporation (SAIC) at 

Oak Ridge, Tennessee. 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 Department of Energy (DOE), 

is collected and published by DOE’s Office 

of Corporate Performance Assessment, a 

division of Environment, Safety and Health, in 

Germantown, Maryland. 

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

fabricators, and reprocessors; manufacturers and distributors of specified quantities of byproduct material.
1-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Fifth Annual Report, 2002

NUREG-0713 

In 1982 and 1983, paragraph 20.408(a) of 

Title 10 of the Code of Federal Regulations 

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. (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 for 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 and their 

technical specifications, 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 website (www.nrc.gov), or they 

may be purchased from the National Technical 

Information Service, as shown in the Reference 

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 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 of 1994.

Recommendations for further analysis or 

for different presentation of information are 

welcome. 
1-3

Thirty-Fifth Annual Report, 2002 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1.2 RADIATION EXPOSURE

INFORMATION ON THE

INTERNET

In May of 1995, the NRC began pursuing the 

dissemination of radiation exposure information 

via a World Wide Web site on the Internet. This 

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 (REMIT) System, is 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. Visit the site for more details. 

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 published hard-copy reports.

The main web URL address for the NRC is:

http://www.nrc.gov

The NRC radiation exposure information web 

URL address is:

http://www.reirs.com

Comments on this report or the NRC’s radiation 

exposure web page should be directed to:

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-Fifth Annual Report, 2002

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Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

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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 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 

tends to increase the number of individuals that 

one could consider to be radiation workers. 

In an effort to account for this, 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 facility. 

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. This 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 the 

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 short-term workers. 

Section 5 contains an analysis that corrects for 

individuals being counted more than once. 

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

Workers reported with zero dose, or no detectable dose, are included in the number of workers with no measurable exposure.
2-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Another fact that one should keep 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 would receive if involved 

in that activity for the full year. 

One should pay considerable attention 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 

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 as licensees may submit corrections 

or additions to data for previous years. For 

the 2003 report, data for prior years 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 

the total U.S. experience. This is not the 

case, however, for the remaining categories 

of industrial radiography, manufacturing 

and distribution of specified quantities of 

by-product material, and low-level 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 the 

number 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 

when received as a patient. 

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), divide 

the value in rem by 100. Therefore,

1 rem = 0.01 Sv. In order to convert rem into 

millisieverts (mSv), multiply the value in rem by 

10. Therefore, 1 rem = 10 mSv.

5 States that have entered into an agreement with the NRC that allows each state to license organizations using radioactive materials 

for certain purposes. As of March 2004, there are 33 Agreement States.
3-1

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 distribution 

(see Section 3.1.4). The TEDE includes the 

dose contribution from the committed effective 

dose equivalent (CEDE) for those workers 

who had intakes that required monitoring and 

reporting of internal dose.

3.1.2 Number of Monitored Workers

The number of monitored workers refers to the 

total number of workers that the NRC licensees 

(who are covered by 10 CFR 20.1502) reported 

as being monitored for exposure to external and 

internal radiation during the year. This number 

includes all workers for whom monitoring is 

required, and may include visitors, service 

representatives, contract workers, clerical 

workers, and any other workers for whom the 

licensee determines that monitoring devices 

should be provided.

For licensees submitting under 10 CFR 20.2206,

the total number of workers was determined 

from the number of unique personal identification 

numbers submitted per licensee. Uniqueness 

is defined by the combination of identification 

number and identification type. [Ref. 10]

3.1.3 Number of Workers with Measurable 

Dose

The number of workers with measurable dose 

includes any individual with a TEDE greater 

than zero rem. This does not include workers 

with a TEDE reported as zero, not detectable 

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

[Ref. 10]

3.1.4 Collective Dose

The concept of collective dose is used in this 

report to denote the summation of the TEDE 

received by all monitored workers and is reported 

in units of person-rem. 10 CFR 20.2206 requires 

that the TEDE be reported, so 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 doses. Care should be taken when 
3-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

comparing the actual collective dose calculated 

for 1994 to 2003 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. 

Although the contribution of internal dose to the 

TEDE is minimal for most licensees, it should be 

considered when comparing the 2003 collective 

dose 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 they are in an Agreement State or 

not. But the other types of Agreement State 

licensees are not required to submit exposure 

reports to the NRC and are not included in this 

report.

3.1.8 Collective TEDE Distribution

by Dose Range

The United Nations Scientific Committee on 

the Effects of Atomic Radiation’s (UNSCEAR) 

2000 report entitled “Report of the Scientific 

Committee on the Effects of Atomic Radiation” 

[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 

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

reprocessors; manufacturers and distributors of byproduct material; independent spent fuel storage installations; facilities for land 

disposal of low-level waste; and geologic repositories for high-level waste. There are currently no NRC licensees involved in

low-level waste disposal or geologic repositories for high-level waste.
3-3

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.1

Average Annual Exposure Data for Certain Categories of NRC Licensees

1994 - 2003

NRC License

Category* and

Program Code

Calendar

Year

Number of

Licensees

Reporting

Number of

Monitored

Individuals

Number of

Workers

With

Measurable

TEDE

Collective

TEDE

(person-rem)

Average

TEDE (rem)

Average

Measurable

TEDE per

Worker (rem)

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Industrial

Radiography

03310

03320

Manufacturing

and

Distribution

02500

03211

03212

03214

Low-Level

Waste

Disposal**

03231

Independent

Spent Fuel

Storage

23100

23200

Fuel

Cycle

Licenses -

 Fabrication

 Processing and

 Uranium Enrich.

21200

21210

Commercial

Light Water

Reactors***

41111

Grand Totals

and Averages

1994 139 2,886 2,007 1,415 0.49 0.71

1995 149 3,761 2,651 1,443 0.38 0.54

1996 148 3,766 2,639 1,449 0.38 0.55

1997 148 3,570 2,574 1,356 0.38 0.53

1998 142 4,952 3,446 1,863 0.38 0.54

1999 132 3,837 2,827 1,551 0.40 0.55

2000 129 3,368 2,542 1,528 0.45 0.60

2001 124 3,780 3,161 2,111 0.56 0.67

2002 100 3,420 2,842 1,729 0.51 0.61

2003 86 2,649 2,319 1,504 0.57 0.65

1994 44 2,941 1,251 580 0.20 0.46

1995 36 2,666 1,222 595 0.22 0.49

1996 38 2,631 1,241 556 0.21 0.45

1997 33 1,154 665 397 0.34 0.60

1998 31 1,986 654 402 0.20 0.61

1999 39 2,181 836 419 0.19 0.50

2000 39 2,461 1,188 415 0.17 0.35

2001 36 1,862 1,211 351 0.19 0.29

2002 29 1,437 1,052 328 0.23 0.31

2003 23 1,849 1,459 394 0.21 0.27

1994 2 202 83 22 0.11 0.27

1995 2 212 56 8 0.04 0.15

1996 2 165 67 8 0.05 0.12

1997 2 185 50 5 0.03 0.11

1998 1 27 13 1 0.05 0.10

1999 0 

1994 1 158 89 42 0.27 0.47

1995 1 104 49 51 0.49 1.04

1996 1 97 53 54 0.56 1.02

1997 1 55 24 6 0.11 0.24

1998 1 53 21 3 0.05 0.12

1999 2 86 33 5 0.06 0.16

2000 2 146 83 6 0.04 0.07

2001 2 154 107 13 0.08 0.12

2002 2 75 67 6 0.08 0.09

2003 2 55 46 3 0.05 0.06

1994 8 3,596 2,847 1,147 0.32 0.40

1995 8 4,106 2,959 1,217 0.30 0.41

1996 8 4,369 3,061 878 0.20 0.29

1997 10 11,214 3,910 1,006 0.09 0.26

1998 10 10,684 3,613 950 0.09 0.26

1999 9 9,693 3,927 1,020 0.11 0.26

2000 9 9,336 4,649 1,339 0.14 0.29

2001 9 8,145 3,980 1,162 0.14 0.29

2002 8 7,937 3,886 661 0.08 0.17

2003 8 7,738 3,633 556 0.07 0.15

1994 109 139,390 71,613 21,704 0.16 0.30

1995 109 132,266 70,821 21,688 0.16 0.31

1996 109 126,402 68,305 18,883 0.15 0.28

1997 109 126,781 68,372 17,149 0.14 0.25

1998 105 114,367 57,466 13,187 0.12 0.23

1999 104 114,154 59,216 13,666 0.12 0.23

2000 104 110,557 57,233 12,652 0.11 0.22

2001 104 104,928 52,292 11,109 0.11 0.21

2002 104 107,900 54,460 12,126 0.11 0.22

2003 104 109,990 55,967 11,956 0.11 0.21

1994 303 149,173 77,890 24,910 0.17 0.32

1995 305 143,115 77,758 25,003 0.17 0.32

1996 306 137,430 75,366 21,828 0.16 0.29

1997 303 142,959 75,595 19,919 0.14 0.26

1998 290 132,069 65,213 16,406 0.12 0.25

1999 286 129,951 66,839 16,661 0.13 0.25

2000 283 125,868 65,695 15,940 0.13 0.24

2001 275 118,869 60,751 14,746 0.12 0.24

2002 243 120,769 62,307 14,850 0.12 0.24

2003 223 122,281 63,424 14,413 0.12 0.23
3-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

collective 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 they recommend 

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 

rem, 0.25 rem, 0.50 rem, 1.0 rem, 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 a decimal fraction.

Figures 3.2, 3.3, 3.5, 3.6, 3.8, 3.10, 3.12, and 

3.13 show the collective TEDE distribution by 

dose range calculated in terms of percentages 

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 (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 level, a 

reduction in the percentage from one year to the 

next indicates that less dose is being received 

by workers above this level. Therefore, these 

graphs can be useful in qualifying the dose 

received in a given year and the trend 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 category, a large number of 

workers receive doses that are less than 

measurable, and very few doses exceed 4 

or 5 rem. Ninety-one percent of the reported 

workers with measurable doses were monitored 

by nuclear power facilities in 2003, where they 

received 83% 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 Commission 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 13 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. One individual 

received a dose above the 5 rem annual TEDE 

limit (actual TEDE dose received was 15.678 

rem) in 2003 at a multiple-location radiography 

licensee that is among the categories required 

to submit data to REIRS (see Section 6).
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Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.2

Distribution of Annual Collective TEDE by License Category

2003

No Meas. 0.10- 0.25- 0.50- 0.75- 1.00- 2.00- 3.00- 4.00- 5.00- 6.00-

Meas. <0.1 0.25 0.50 0.75 1.00 2.00 3.00 4.00 5.00 6.00 12.00 >12

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

License Category

(Number of sites reporting)

Total

Number

Monitored

Number

with Meas.

Dose

Total

Collective

Dose (TEDE)

(person-rem)

52 35 6 3 1 97 45 3.066

278 586 358 369 256 196 344 115 40 9 1 2,552 2,274 1,500.885330 621 364 372 257 196 344 115 40 9 1 2,649 2,319 1,503.951

89 83 48 60 40 37 55 25 1 438 349 228.922

301 782 203 64 15 13 19 7 5 2 1,411 1,110 165.315390 865 251 124 55 50 74 32 6 2 1,849 1,459 394.237

9 34 10 2 55 46 2.791

4,105 2,194 781 353 181 78 46 7,738 3,633 556.297

24,934 17,042 6,344 4,326 1,714 749 556 28 55,693 30,759 5,659.43452,955 25,678 10,887 5,263 1,425 484 308 9 97,009 44,054 6,296.13677,889 42,720 17,231 9,589 3,139 1,233 864 37 152,702 74,813 11,955.570

82,723 46,434 18,637 10,440 3,632 1,557 1,328 184 46 11 1 164,993 82,270 14,412.846

 INDUSTRIAL RADIOGRAPHY Single Location (12) Multiple Location (74)

Total (86)

 MANUFACTURING AND DISTRIBUTION "A" - Broad (3) Limited (20)

Total (23)

 LOW-LEVEL WASTE DISPOSAL

Total (0)**

 INDEPENDENT SPENT FUEL STORAGE

Total (2)

 FUEL CYCLE LICENSES***

Total (8)

COMMERCIAL POWER REACTORS****

 Boiling Water (35) Pressurized Water (69)

Total (104)

 GRAND TOTALS

3.2

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

** There are no NRC licensees currently involved in this activity. All facilities are now located in Agreement States.

*** Includes fabrication, processing and uranium enrichment plants (see Section 3.3.5).

**** Includes all reactors in commercial operation for a full year during 2003. These values have not been adjusted for the multiple counting of transient reactor workers (see Section 5).
3-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

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

 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 1977-2003 are based on the distribution of individual doses after adjusting for the multiple counting of transient reactor workers 

(see Section 5). The numbers of people exceeding both 2 and 5 rem are shown in parentheses from 1985-2003.

TABLE 3.3

Summary of Annual Dose Distributions for Certain* NRC Licensees

1968 - 2003

Total Number of Monitored 

Persons

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

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.4

Annual Exposure Information for Industrial Radiographers

2001 - 2003

Year Type of License

Number of

Licensees

Number of

Monitored

Individuals

Workers With

Measurable

Dose

Collective

Dose

(person-rem)

Average

Measurable

Dose (rem)

Single Location

Multiple Locations

Total

Single Location

Multiple Locations

Total

Single Location

Multiple Locations

Total

20

104

124

15

85

100

12

74

86

258

3,522

3,780

112

3,308

3,420

97

2,552

2,649

79

3,082

3,161

55

2,787

2,842

45

2,274

2,319

6

2,105

2,111

4

1,725

1,729

3

1,501

1,504

0.07

0.68

0.67

0.08

0.62

0.61

0.07

0.66

0.65

2001

2002

2003

3.4

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 

86 radiography licensees in 2003. Table 3.4 

summarizes the reported data for the two types 

of radiography licenses for 2003 and for the 

previous 2 years for comparison purposes.

The average measurable dose for workers 

performing radiography at a single location 

ranged from 10% to 13% 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 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 2003.

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 ALARA. 

Although these licensed activities usually result 

in average measurable doses that are higher 

than other licensees, they involve a relatively 

small number of exposed workers.
3-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

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 2003. The number of workers with 

measurable TEDE per licensee decreased from 

2002 to 2003, whereas the average measurable 

TEDE increased by 7% from 0.61 rem in 2002 

to 0.65 rem in 2003. 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 

dose in the higher dose ranges and routinely 

have 25% to 40% of the collective dose 

delivered to individuals above 2 rem. From 

1999 to 2001, for these licensees, there were 

increases in the percentage of dose for each 

dose range above 0.50 rem. However, for the 

past 2 years, the percentage of the collective 

dose delivered in each dose range above 0.50 

rem was less than the value in 2001. In 2003, 

for single location licensees, the percentage of 

individuals above all dose ranges decreased 

from the 2002 values.

3.3.2 Manufacturing and Distribution

Licenses, Type “A” Broad and Limited

Manufacturing and Distribution 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 persons 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 radio-chemicals for nonmedical 

research.
3-9

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 3.1. Average Annual Values at Industrial Radiography Facilities 1973 - 2003

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

1973

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

50

3025201510

1.000.900.800.700.600.500.400.300.200.100.00

No. of Workers w/ Measurable Dose per License

e

Collective TEDE per Licensee (person-rem)Average Meas. TEDE per Worker (rem)
3-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

2003 2002 2001 2000 1999

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

81%

60%

93%

26%

> 1.000

> 0.500

> 0.250

> 0.100

98%

85%

66%

94%

35%

98%

88%

70%

95%

37%

99%

87%

67%

95%

34%

99%

87%

66%

95%

31%

99%

Dose Range

FIGURE 3.2. Collective TEDE Distribution by Dose Range

Industrial Radiographer – Single Location Licensees

1999 - 2003

FIGURE 3.3. Collective TEDE Distribution by Dose Range

Industrial Radiographer – Multiple Location Licensees

1999 - 2003

2003 2002 2001 2000 1999

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

82%

76%

34%

0%

0% 0%

42%

74%

97%

90%

74%

43%

0%

> 1.000

> 0.500

> 0.250

> 0.100

18%

80%

57%

13%

12%

62%

80%

19%

60%

80%

92%

98%

Dose Range
3-11

Thirty-Sixth Annual Report, 2003 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 

2003 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 remain higher for the Broad 

licensees. However, when attempting 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 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. The number 

of Type A Broad licensees remained at 3 in 

2003, the same as in 2002.

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. The figures for Type 

A Broad licensees are primarily attributed to 

Mallinckrodt Medical, Inc., which accounted 

for 98% of the collective dose for this category 

of licensee in 2003. 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 

the Type A Broad licensees consistently have 

individuals receiving dose in the higher dose 

ranges. In 1999, 64% of the collective dose 

was received by individuals above 2 rem. In 

2003, this percentage decreased for the fourth 

consecutive year to 28%. Limited licensees 

exhibit a distribution of the collective dose where 

individuals below 0.50 rem receive over 50% of 

the collective dose. However, the percentage 

of the collective dose above 1 rem has been 

greater than or equal to 40% for the past 4 years.

TABLE 3.5

Annual Exposure Information for Manufacturers and Distributors

2001 - 2003

Year Type of License

Number of

Licensees

Number of

Monitored

Individuals

Workers With

Measurable

Dose

Collective

Dose

(person-rem)

Average

Measurable

Dose (rem)

M & D - “A” - Broad

M & D - Limited

Total

M & D - “A” - Broad

M & D - Limited

Total

M & D - “A” - Broad

M & D - Limited

Total

2001

2003

4

32

36

3

26

29

3

20

23

616

1,246

1,862

334

1,103

1,437

438

1,411

1,849

351

860

1,211

247

805

1,052

349

1,110

1,459

232

119

351

197

131

328

229

165

394

0.66

0.14

0.29

0.80

0.16

0.31

0.66

0.15

0.27

2002
3-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

FIGURE 3.4. Average Annual Values at Manufacturing and Distribution Facilities

1973 - 2003

1973

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

0

80604020

120100

1.000.900.800.700.600.500.400.300.200.100.00

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

No. of Workers w/ Measurable Dose per License

e

Collective TEDE per Licensee (person-rem)Average Meas. TEDE per Worker (rem)
3-13

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

2003 2002 2001 2000 1999

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

93%

85%

97%

64%

> 1.000

> 0.500

> 0.250

> 0.100

99%

92%

79%

96%

55%

99%

89%

74%

96%

40%

99%

90%

28%

95%

38%

99%

86%

61%

95%

99%

76%

Dose Range

2003 2002 2001 2000 1999

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

> 2.000

12%

> 1.000

> 0.500

> 0.250

> 0.100

85%

67%

28%

87%

 71%

52%

87%

40%

55%

53%

26%

68%

42%

39%

28%

54%

40%

56%

25%

88%

72%

87%

68%

42%

Dose Range

FIGURE 3.5. Collective TEDE Distribution by Dose Range

Type “A” Broad Manufacturing and Distribution Licensees

1999 - 2003

FIGURE 3.6. Collective TEDE Distribution by Dose Range

Limited Manufacturing and Distribution Licensees

1999 - 2003
3-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

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 2003.

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’ 

activity. 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 

Low-Level 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.

Fifty licenses were authorized to conduct 

these activities during 2003. Eighteen of these 

licenses are for activities involving cask design 

and storage systems. Twenty-seven are 

located at nuclear power plants allowing on-site 

temporary storage of fuel. These licensees 

report the dose from fuel storage activities along 

with the dose from reactor operations at these 

sites. Three additional licenses have been 

issued to the DOE for spent fuel storage. The 

two remaining licenses are located at facilities 

that are independent of a reactor site. One is 

the GE Morris facility located in Illinois. The 

second site was included for the first time in 

1999, and is a site in Idaho operated by DOE 

for the storage of fuel from Three Mile Island 

Unit 2. Only the two sites that possess spent 

fuel away from a reactor site are included 

in the data for this licensee category in this 

report. Appendix A summarizes the exposure 

information reported by these two installations.
3-15

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

1982 - 1998

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

0

50

400350300250200150100

0.700.600.500.400.300.200.100.00

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

No. of Workers w/ Measurable Dose per License

e

Collective TEDE per Licensee (person-rem)Average Meas. TEDE per Worker (rem)

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-Sixth Annual Report, 2003

NUREG-0713 

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

1982 - 2003

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

0

908070605040302010

100 2.00

1.801.601.401.201.000.800.600.400.200.00

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

No. of Workers w/ Measurable Dose per LicenseeCollective TEDE per Licensee (person-rem)Average Meas. TEDE per Worker (rem)
3-17

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 3.9. Collective TEDE Distribution by Dose Range

Independent Spent Fuel Storage Licensees

1999 - 2003

2003 2002 2001 2000 1999

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

> 2.000

> 1.000

> 0.500

> 0.250

> 0.100

 50%

6%

15%

0% 0%

0%

73%

72%

22%

28%

61%

83%

0%

0%

11%

72%

90%

0%

0%

12%

63%

0%

0%

0%

0%

0%

Dose Range

Figure 3.8 shows the number of workers

with measurable dose per licensee, the total 

collective dose per licensee, and the average 

measurable dose per worker for ISFSI facilities. 

The large increase in the collective dose per 

licensee and number of workers per licensee 

in 1994 was mainly because only one licensee 

reported separately for 1994 through 1998, 

rather than the two licensees that reported 

in prior years. All parameters decreased 

significantly from 1996 to 1999, but increased 

from 2000 to 2001, and have decreased from 

2001 to 2003. Figure 3.9 shows the collective 

dose distribution by dose range (see Section 

3.1.8) for ISFSI licensees from 1999 to 2003. 

The percentages for each dose range have 

fluctuated from year to year since 1998 due to 

the small number of licensees involved. No 

individual has received a dose above 1 rem at 

these facilities for the past 5 years.
3-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

TABLE 3.6

Annual Exposure Information for Fuel Cycle Licenses

2001- 2003

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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. For 1997 

to 2003, this category also includes the two 

uranium enrichment facilities at Portsmouth, 

Ohio, and Paducah, Kentucky. The regulatory 

oversight for these facilities was transferred 

from DOE to the NRC in 1997.

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 1999 to 2003. The percentage of the 

collective dose above each dose range 

increased in almost every dose range from 

1999 to 2001. However, from 2001 to 2003, 

there was a significant decrease in the 

percentage of the collective dose above each 

dose range. Most of the decrease is due to 

reductions in the collective dose reported by 

Westinghouse Electric Co., at the Commercial 

Nuclear Fuel Division in South Carolina. Both 

the external DDE and internal CEDE decreased 

from 2002 to 2003, with an 18% decrease in the 

collective CEDE at fuel cycle facilities.

Appendix A lists each of the licensees reporting 

in 2003, 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 8 licensed Fuel Cycle (Fabrication and 

Enrichment) facilities reporting in 2003.
3-19

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 3.10. Average Annual Values at Fuel Cycle Licensees 1973 - 2003

1973

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

0

50

650600550500450400350300250200150100

0.600.500.400.300.200.100.00

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

No. of Workers w/ Measurable Dose per LicenseeCollective DDE per Licensee (person-rem)Collective TEDE per Licensee (person-rem)Average Meas. DDE per Worker (rem)Average Meas. TEDE per Worker (rem)
3-20

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

FIGURE 3.11. Collective TEDE Distribution by Dose Range

Fuel Cycle Licensees

1999 - 2003

3.3.6 Light-Water-Cooled Power

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, total 

number of monitored workers, the number 

of workers with measurable dose, the total 

collective dose, and average dose per worker 

for reactor facilities that were in commercial 

operation for a full year for each of the years 

1994 through 2003. The values do not include 

reactors that have been permanently shut down 

or were not yet in commercial operation. These 

figures 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 2003 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 1999 to 2003. The 

distribution of collective dose has been fairly 

constant over the past 5 years, with a slight 

decrease noted from 2002 to 2003 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.

2003 2002 2001 2000 1999

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

12%

> 1.000

> 0.500

> 0.250

> 0.100

94%

84%

69%

45%

36%

89%

55%

68%

39%

82%

94%

67%

1%

0%

17%

10%

42%

64%

87%

72%

26%

51%

87%

95%

Dose Range
3-21

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 3.12. Collective TEDE Distribution by Dose Range

Reactor Licensees

1999 - 2003

2003 2002 2001 2000 1999

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

> 2.000

1%

> 1.000

> 0.500

> 0.250

> 0.100

90%

39%

11%

67%

1%

87%

34%

10%

 63%

2%

87%

37%

13%

 65%

1%

86%

36%

11%

 63%

1%

88%

38%

11%

66%

Dose Range
3-22

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

3.4 SUMMARY OF INTAKE DATA 

BY LICENSE CATEGORY

10 CFR 20 requires licensees to report 

additional data to the NRC concerning intakes 

of radioactive material. Licensees are required 

to list for each intake the radionuclide that was 

taken into the body, the 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 2003. 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 or other mode. 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 D, W, or Y corresponding to its 

clearance half-time in the order of days, weeks, 

or years 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 is 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 

(96%) in 2003 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 2003 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 is received by 

individuals working at fuel fabrication facilities.
3-23

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.7

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

2003

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries**

Collective

Intake in

Microcuries

Mode (sci. notation)

Absorption Power Reactors 41111 PU-241 1 0.000 2.59E-04

Ingestion Power Reactors 41111 AG-110M 2 0.038 3.83E-02

41111 AM-241 5 0.000 3.26E-05

41111 CM-242 5 0.000 2.21E-05

41111 CM-243 2 0.000 1.43E-05

41111 CM-244 3 0.000 1.29E-05

41111 CO-58 14 6.991 6.99E+00

41111 CO-60 19 9.853 9.85E+00

41111 CR-51 2 4.444 4.44E+00

41111 CS-134 2 0.034 3.41E-02

41111 CS-137 3 0.052 5.20E-02

41111 FE-55 5 3.603 3.60E+00

41111 FE-59 4 1.247 1.25E+00

41111 MN-54 4 1.784 1.78E+00

41111 NB-95 2 0.058 5.79E-02

41111 NI-63 5 0.152 1.52E-01

41111 PU-238 5 0.000 2.83E-05

41111 PU-239 4 0.000 1.27E-05

41111 PU-240 1 0.000 2.37E-06

41111 PU-241 5 0.002 1.90E-03

41111 SB-124 2 0.019 1.86E-02

41111 SR-89 2 0.005 5.46E-03

41111 SR-90 5 0.007 6.62E-03

41111 SR-92 2 0.013 1.34E-02

41111 ZN-65 3 0.626 6.26E-01

41111 ZR-95 2 0.030 3.00E-02

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

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

10 CFR 20.2206.

** A microcurie is one millionth of a Curie.
3-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

TABLE 3.8

Intake by Licensee Type and Radionuclide Mode of Intake – Inhalation

2003

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3-25

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.8 (continued)

Intake by Licensee Type and Radionuclide Mode of Intake – Inhalation

2003

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3-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

TABLE 3.9

Collective and Average CEDE by Licensee

2003

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3-27

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.10

Internal Dose (CEDE) Distribution

1994 - 2003

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3-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

This page intentionally left blank.
4-1

Thirty-Sixth Annual Report, 2003 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 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 defueling 

and decommissioning 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 includes the dose data 

for Unit 2 prior to 1986.

There were no changes to the count of 

operating reactors in 2003. The number of 

operating BWRs remains the same as in 2002 

at 35 and the number of operating PWRs 

remains the same at 69. The dose information 

for these reactors and 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 2003, the 
4-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

TABLE 4.1

Summary of Information Reported by Commercial Boiling Water Reactors

1973 - 2003

Average

Average No.

Average

Annual No. of

Average Collective Personnel Collective

Average

Average Percent of

Number Collective

Workers Measurable Dose Per With Dose Electricity Maximum Maximum

of Dose With Electricity Dose Per Reactor Measurable per MW-yr Generated Dependable Dependable

Reactors (person- Measurable Generated***

Worker (person- Doses (person-rem/ Per Reactor capacity Capacity

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

1973 12 4,564 5,340 3,393.9 0.86 380 445 1.35 283 438 65%1974 14 7,095 8,769 4,060.2 0.81 507 626 1.75 290 485 60%1975 18 12,633 17,350 5,786.4 0.73 702 964 2.18 321 595 54%1976 22 12,298 16,927 8,137.9 0.73 559 769 1.51 370 630 59%1977 23 19,054 21,515 9,102.5 0.89 828 935 2.09 396 637 62%1978 25 15,257 20,381 11,856.0 0.75 610 815 1.29 474 660 72%1979 25 18,251 25,425 11,671.0 0.72 730 1,017 1.56 467 660 71%1980 26 29,472 34,220 10,868.2 0.86 1,134 1,316 2.71 418 663 63%1981 26 25,490 34,873 10,899.2 0.73 980 1,341 2.34 419 663 63%1982 26 24,447 32,318 10,614.6 0.76 940 1,243 2.30 408 663 62%1983 26 27,467 33,581 9,730.1 0.82 1,056 1,292 2.82 374 663 56%1984 27 27,111 41,315 10,019.2 0.66 1,004 1,530 2.71 371 754 49%1985 29 20,578 38,336 12,284.0 0.54 710 1,322 1.68 424 775 55%1986 30 19,353 37,999 12,102.1 0.51 645 1,267 1.60 403 786 51%1987 32 16,722 41,806 15,109.0 0.40 523 1,306 1.11 472 832 57%1988 34 17,986 40,371 16,665.4 0.45 529 1,187 1.08 490 845 58%1989 36 15,550 44,384 17,543.5 0.35 432 1,233 0.89 487 857 57%1990 37 15,781 41,585 21,336.1 0.38 427 1,124 0.74 577 862 67%1991 37 12,007 38,508 21,505.8 0.31 325 1,041 0.56 581 860 68%1992 37 13,312 42,107 20,592.2 0.32 360 1,138 0.65 557 859 65%1993 37 12,221 39,352 21,995.6 0.31 330 1,064 0.56 594 798 74%1994 37 12,098 39,171 22,139.0 0.31 327 1,059 0.55 598 801 75%1995 37 9,471 35,686 24,737.0 0.27 256 964 0.38 669 835 80%1996 37 9,466 37,792 24,322.2 0.25 256 1,021 0.39 657 838 78%1997 37 7,603 34,021 22,866.1 0.22 205 919 0.33 618 845 73%1998 36 6,829 32,899 23,781.2 0.21 190 914 0.29 661 874 76%1999 35 6,434 31,482 26,962.6 0.20 184 899 0.24 770 885 87%2000 35 6,090 31,186 28,476.9 0.20 174 891 0.21 814 893 91%2001 35 4,835 28,797 28,730.4 0.17 138 823 0.17 821 895 92%2002 35 6,108 30,978 29,460.0 0.20 175 885 0.21 842 907 93%2003 35 5,659 30,759 29,094.4 0.18 162 879 0.19 831 912 91%

* Includes only those reactors that had been in commercial operation for at least one full year as of December 31 of each of the indicated years.

** Figures are not adjusted for the multiple reporting of transient individuals. See Section 5.

*** Electricity Generated reflects the gross electricity generated for the years 1973 - 1996. Beginning in 1997, it reflects the net electricity generated.
4-3

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Average

Average No.

Average

Annual No. of

Average Collective Personnel Collective

Average

Average Percent of

Number Collective

Workers Measurable Dose Per With Dose Electricity Maximum Maximum

of Dose With Electricity Dose Per Reactor Measurable per MW-yr Generated Dependable Dependable

Reactors (person- Measurable Generated***

Worker (person- Doses (person-rem/ Per Reactor capacity Capacity

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

1973 12 9,398 9,440 3,770.2 1.00 783 787 2.49 314 544 58%1974 19 6,555 9,370 6,530.7 0.70 345 493 1.00 344 591 58%1975 26 8,268 10,884 11,982.5 0.76 318 419 0.69 461 647 71%1976 30 13,807 17,588 13,325.0 0.79 460 586 1.04 444 701 63%1977 34 13,467 20,878 17,345.8 0.65 396 614 0.78 510 688 74%1978 39 16,528 25,700 19,840.5 0.64 424 659 0.83 509 706 72%1979 42 21,657 38,828 18,255.0 0.56 516 924 1.19 435 746 58%1980 42 24,267 46,237 18,289.3 0.53 578 1,101 1.33 435 746 58%1981 44 28,673 47,351 20,553.7 0.61 652 1,076 1.40 467 752 62%1982 48 27,754 52,149 22,140.6 0.53 578 1,086 1.25 461 777 59%1983 49 29,017 52,170 23,195.5 0.56 592 1,065 1.25 473 785 60%1984 51 28,140 56,994 26,478.4 0.49 552 1,118 1.06 519 809 64%1985 53 22,470 54,632 29,470.7 0.41 424 1,031 0.76 556 820 68%1986 60 23,033 62,998 33,593.0 0.37 384 1,050 0.69 560 878 64%1987 64 23,684 62,597 37,007.3 0.38 370 978 0.64 578 900 64%1988 68 22,786 62,923 42,929.7 0.36 335 925 0.53 631 885 71%1989 71 20,381 63,894 44,679.5 0.32 287 900 0.46 629 897 70%1990 73 20,821 67,082 46,955.6 0.31 285 919 0.44 643 907 71%1991 74 16,512 60,274 51,942.6 0.27 223 815 0.32 702 913 77%1992 73 15,985 61,048 53,419.8 0.26 219 836 0.30 732 923 79%1993 69 13,376 54,397 48,709.3 0.25 194 788 0.28 706 941 75%1994 70 9,574 44,283 52,397.6 0.22 137 633 0.18 749 928 81%1995 70 11,762 49,985 54,138.2 0.24 168 714 0.22 773 929 83%1996 72 9,417 46,852 55,337.8 0.20 131 651 0.17 769 935 82%1997 72 9,546 50,690 48,985.3 0.19 133 704 0.20 680 943 72%1998 69 6,358 38,586 53,288.7 0.17 92 559 0.12 772 942 82%1999 69 7,231 43,938 56,235.0 0.17 105 637 0.13 815 942 86%2000 69 6,562 42,922 57,529.9 0.15 95 622 0.11 834 943 88%2001 69 6,273 38,773 58,822.4 0.16 91 562 0.11 852 946 90%2002 69 6,018 42,264 59,369.7 0.14 87 613 0.10 860 947 91%2003 69 6,296 44,054 57,920.6 0.14 91 638 0.11 839 949 88%

* Includes only those reactors that had been in commercial operation for at least one full year as of December 31 of each of the indicated years.

** Figures are not adjusted for the multiple reporting of transient individuals. See Section 5.

*** Electricity Generated reflects the gross electricity generated for the years 1973 - 1996. Beginning in 1997, it reflects the net electricity generated.

TABLE 4.2

Summary of Information Reported by Commercial Pressurized Water Reactors

1973 - 2003
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NUREG-0713 

1973 24 13,962 14,780 7,164.1 0.95 582 616 1.95 299 491 61%1974 33 13,650 18,139 10,590.9 0.75 414 550 1.29 321 546 59%1975 44 20,901 28,234 17,768.9 0.74 475 642 1.18 404 626 65%1976 52 26,105 34,515 21,462.9 0.76 502 664 1.22 413 671 62%1977 57 32,521 42,393 26,448.3 0.77 571 744 1.23 464 667 70%1978 64 31,785 46,081 31,696.5 0.69 497 720 1.00 495 688 72%1979 67 39,908 64,253 29,926.0 0.62 596 959 1.33 447 714 63%1980 68 53,739 80,457 29,157.5 0.67 790 1,183 1.84 429 714 60%1981 70 54,163 82,224 31,452.9 0.66 774 1,175 1.72 449 719 63%1982 74 52,201 84,467 32,755.2 0.62 705 1,141 1.59 443 737 60%1983 75 56,484 85,751 32,925.6 0.66 753 1,143 1.72 439 743 59%1984 78 55,251 98,309 36,497.6 0.56 708 1,260 1.51 468 790 59%1985 82 43,048 92,968 41,754.7 0.46 525 1,134 1.03 509 804 63%1986 90 42,386 100,997 45,695.1 0.42 471 1,122 0.93 508 847 60%1987 96 40,406 104,403 52,116.3 0.39 421 1,088 0.78 543 877 62%1988 102 40,772 103,294 59,595.1 0.40 400 1,013 0.68 584 871 67%1989 107 35,931 108,278 62,223.0 0.33 336 1,012 0.58 582 883 66%1990 110 36,602 108,667 68,291.7 0.34 333 988 0.54 621 892 70%1991 111 28,519 98,782 73,448.4 0.29 257 890 0.39 662 895 74%1992 110 29,297 103,155 74,012.0 0.28 266 938 0.40 673 901 75%1993 106 25,597 93,749 70,704.9 0.27 241 884 0.36 667 891 75%1994 107 21,672 83,454 74,536.6 0.26 203 780 0.29 697 884 79%1995 107 21,233 85,671 78,875.2 0.25 198 801 0.27 737 896 82%1996 109 18,883 84,644 79,660.0 0.22 173 777 0.24 731 902 81%1997 109 17,149 84,711 71,851.4 0.20 157 777 0.24 659 910 72%1998 105 13,187 71,485 77,069.9 0.18 126 681 0.17 734 918 80%1999 104 13,666 75,420 83,197.6 0.18 131 725 0.16 800 923 87%2000 104 12,652 74,108 86,006.8 0.17 122 713 0.15 827 926 89%2001 104 11,109 67,570 87,552.8 0.16 107 650 0.13 842 929 91%2002 104 12,126 73,242 88,829.7 0.17 117 704 0.14 854 934 91%2003 104 11,956 74,813 87,015.0 0.16 115 719 0.14 837 936 89%

Average

Average No.

Average

Annual No. of

Average Collective Personnel Collective

Average

Average Percent of

Number Collective

Workers Measurable Dose Per With Dose Electricity Maximum Maximum

of Dose With Electricity Dose Per Reactor Measurable per MW-yr Generated Dependable Dependable

Reactors (person- Measurable Generated***

Worker (person- Doses (person-rem/ Per Reactor capacity Capacity

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

* Includes only those reactors that had been in commercial operation for at least one full year as of December 31 of each of the indicated years.

** Figures are not adjusted for the multiple reporting of transient individuals. See Section 5.

*** Electricity Generated reflects the gross electricity generated for the years 1973 - 1996. Beginning in 1997, it reflects the net electricity generated.

TABLE 4.3

Summary of Information Reported by Commercial Light Water Reactors

1973 - 2003
4-5

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NUREG-0713

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-yrs) 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. 

The number of megawatt hours of electricity 

produced each year was obtained from Ref. 12.

As shown in Table 4.3, there was a 2% 

decrease in the net electricity generated at 

LWRs in 2003. Contributors to the decrease 

included Sequoyah, South Texas, and Surry, 

which all had decreases of over 300 MW-yrs 

from 2002 to 2003. BWRs decreased net 

electricity generated by 1%. PWRs decreased 

net electric output by 2%.

4.2.3 Collective Dose per Megawatt-Year

The number of MW-yrs of electricity generated 

was used in determining the ratio of the average 

value of the annual collective dose (TEDE) to 

the number of MW-yrs of electricity generated. 

The ratio was calculated by dividing the total 

collective dose in person-rem by the electric 

energy generated in MW-yrs 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 2003, 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 remained at a value 

of 0.14 in 2003.

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-Sixth Annual Report, 2003

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 have 

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 decreased from 91% in 

2002 to 89% in 2003 due to the decrease in the 

net electricity generated.

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 2003. 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 2003 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 1% to a value of 11,956 

person-rem in 2003. A major contributor to this 

decrease was Quad Cities. Quad Cities 1,2 

had the highest collective dose per reactor of 

any site in 2002, but the annual collective dose 

decreased by 75% in 2003. The high doses 

at Quad Cities Units 1 and 2 in 2002 were 

attributed to the large number of outages (two 

planned outages and six unplanned outages) 

that were performed at Quad Cities in 2002 in 

combination with higher than normal dose rates. 
4-7

Thirty-Sixth Annual Report, 2003 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 - 2003

1977 22,688 12,436 6,056 4,538 2,905 2,230 5,660 2,858 1,290 661 186 89 47 23 6 - - 61,673 38,985 32,5211978 26,360 15,165 6,349 5,010 3,094 2,255 5,984 3,050 1,194 517 110 37 9 - 1 - 2 69,137 42,777 31,7851979 40,535 22,642 9,012 7,485 4,795 3,262 7,574 3,401 1,403 545 117 42 17 3 1 - - 100,834 60,299 39,9081980 44,716 26,990 10,697 8,913 5,573 4,139 10,672 4,607 1,816 831 235 119 29 7 1 - - 119,345 74,629 53,7391981 39,258 26,916 11,241 9,338 6,051 4,501 11,174 4,809 1,999 533 103 93 9 3 1 - 1 116,030 76,772 54,1631982 41,704 29,278 11,734 9,907 6,235 4,422 10,220 4,716 2,066 596 97 31 5 - 1 1 - 121,013 79,309 52,2011983 47,027 29,200 11,200 9,345 5,854 4,279 11,342 5,334 2,270 716 121 38 8 2 - - - 126,736 79,709 56,4841984 54,637 36,488 13,438 10,277 6,338 4,804 11,284 5,208 2,122 487 52 22 - - - - - 145,157 90,520 55,2511985 59,625 36,920 13,015 11,044 6,626 4,545 10,042 3,574 1,002 157 1 - - - - - - 146,551 86,926 43,0481986 67,677 41,536 14,574 11,842 7,017 4,693 10,241 3,062 868 146 - - - - - - - 161,656 93,979 42,3861987 85,170 41,283 15,842 12,838 7,586 5,333 10,611 2,192 477 69 - - - - - - - 181,401 96,231 40,4061988 87,281 40,290 15,915 13,152 7,905 5,461 10,310 2,442 511 26 - 1 - - - - - 183,294 96,013 40,7721989 83,954 45,302 17,270 13,778 7,944 5,138 8,633 1,615 370 34 - - - - - - - 184,038 100,084 35,9311990 83,875 42,612 17,526 14,199 8,226 5,261 8,594 1,791 337 21 - - - - - - - 182,442 98,567 36,6021991 87,247 42,603 16,770 13,182 7,188 4,192 5,977 938 219 17 - - - - - - - 178,333 91,086 28,5191992 87,717 41,943 17,821 14,779 8,135 4,521 6,076 808 85 4 - - - - - - - 181,889 94,172 29,2971993 83,066 37,332 17,235 13,734 7,562 4,289 5,322 638 76 5 - - - - - - - 169,259 86,193 26,3641994 67,777 30,185 15,010 11,823 6,185 3,620 4,242 508 40 - - - - - - - - 139,390 71,613 21,7041995 61,445 29,631 15,096 12,023 6,125 3,304 3,912 595 133 2 - - - - - - - 132,266 70,821 21,6881996 58,097 30,204 14,831 11,343 5,423 2,833 3,196 408 67 - - - - - - - - 126,402 68,305 18,8831997 58,409 31,955 14,890 10,913 5,233 2,455 2,599 286 41 - - - - - - - - 126,781 68,372 17,1491998 56,901 27,998 12,849 8,816 3,940 1,841 1,827 179 15 1 - - - - - - - 114,367 57,466 13,1871999 54,885 29,048 13,184 8,949 3,793 1,900 1,894 245 18 - - - - - - - - 113,916 59,031 13,5992000 53,324 28,480 12,921 8,679 3,571 1,644 1,734 186 18 - - - - - - - - 110,557 57,233 12,6522001 52,636 27,246 11,491 7,659 2,907 1,323 1,392 221 53 - - - - - - - - 104,928 52,292 11,1092002 53,440 28,523 11,610 7,668 3,004 1,479 1,820 320 35 1 - - - - - - - 107,900 54,460 12,1262003 54,023 29,164 11,978 8,199 3,249 1,524 1,651 184 18 - - - - - - - - 109,990 55,967 11,956

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

No Total with Collective

Measurable Measurable 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- 6.0- 7.0- 8.0- 9.0- 10.0- Number Measurable Dose

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

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

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

** The collective dose, when not reported by the licensee, was calculated by the NRC staff using methods described in Section 3.1.4.

**
4-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

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 

2003, the average collective dose per LWR 

dropped by 85%. Between 2002 and 2003, the 

collective dose per reactor for PWRs increased 

by 5% to 91 person-rem. The collective dose 

per reactor for BWRs decreased by 7% to

162 person-rem from 2002 to 2003. The overall 

collective dose per reactor for LWRs decreased 

by 2% to 115 person-rem in 2003. The number 

of workers with measurable dose per reactor 

decreased to 879 for BWRs and increased to 

638 for PWRs in 2003. 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 2003 the 

net electricity generated decreased to 87,015 

MW-yr while the number of operating reactors 

has remained constant for the past 5 years. 

The value for the total collective dose for all 

LWRs decreased by 1% from a value of 12,126 

person-rem in 2002 to 11,956 person-rem in 

2003. Together with the increase in the number 

of workers with measurable dose, this resulted 

in the average measurable dose per worker 

decreasing from 0.17 rem in 2002 to 0.16 

rem in 2003 (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 is continually being stressed, 

and most utilities have established programs to 

collect and share information relative to tasks, 

techniques, and exposures.
4-9

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 4.1. Average Collective Dose and Number of Workers

with Measurable Dose per Reactor

1973 - 2003

Average Annual Collective Dose

0

200

400

600

800

1000

1200

1400

1600

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

Year

BWR

PWR

LWR

Average Annual Number of Workers with Measurable Dose

Collective Dose per Reactor (Person-rem)

Workers per Reactor

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

Year

BWR

PWR

LWR
4-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

FIGURE 4.2. Number of Operating Reactors and Gross Electricity Generated

1973 - 2003

* Gross electricity 1973-1996, net electricity for 1997-2003 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983

19841985198619871988198919901991199219931994199519961997199819992000200120022003

0

10

20

30

40

50

60

70

80

90

100

110

120

Year

Number of Operating Reactors

BWR

PWR

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

10

20

30

40

50

60

70

80

90

Year

BWR

PWR

LWR

Electricity Generated*

Number of Reactors Megawatt-Years (Thousands)
4-11

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

1973 - 2003

* Gross electricity 1973-1996, net electricity for 1997-2003 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983

19841985198619871988198919901991199219931994199519961997199819992000200120022003

0.0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1.0

1.1

Year

BWR

PWR

LWR

Average Measurable Dose per Worker

Average Measurable Dose (rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0.0

0.2

0.4

0.6

0.8

1.0

1.2

1.4

1.6

1.8

2.0

2.2

2.4

2.6

2.8

3.0

Year

BWR

PWR

LWR

Collective Dose per Megawatt-Year*

Collective Dose (Person-rem) per MY-YR
4-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

7 The value at which 50% of the reactors reported greater collective doses, and the other 50% reported smaller collective doses.

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 2003. 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 remained 

unchanged at 75 person-rem in 2003. At 

BWRs, the median fluctuates more from year 

to year. The median collective dose increased 

from 130 person-rem in 2002 to 169 personrem in 2003. Figure 4.5 also shows that, in 

2003, 50% of the PWRs reported collective 

doses between 56 and 124 person-rem, while 

50% of the BWRs reported collective doses 

between 124 and 201 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).

4.5 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, 2003, and show the values 

of several parameters for each of the sites. 

They 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 158 person-rem, the average 

measurable TEDE per worker was 0.18 rem, 

and the average collective TEDE per MW-yr 

was 0.19 person-rem per MW-yr. The average 

3-year collective TEDE per reactor, the average 

measurable TEDE per worker, and the average 

collective TEDE per MW-yr decreased from 

2002 to 2003.

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 90 

person-rem, 0.15 rem, and 0.11 person-rem per 

MW-yr, respectively. The collective TEDE per 

reactor decreased, while the other two values 

remained the same as the previous 3-year 

period.
4-13

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

1973 - 1986

Collective Doses Per Reactor (person-rem)

500

1000

1500

2000

2500

3000

3500

4000

4500

5000

5500

0 1973 1974 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986

Year

M

A

M

A

M

A

M

A

A M

A

M

A

M

A

M

A

A

A

A

M

A

M

A

M

A

M

A

A

M

A

A

M

A

M

A

M

A

M

A

M

A M

A

A M

A

M

A

Middle 50% of BWRs

Middle 50% of PWRs

Average Collective Dose

M Median Collective Dose

A

M

M M

M M

M

M
4-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

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

1987 - 2003

A

M

A M

A

Collective Doses Per Reactor (person-rem)

200

0 1987 1988 1989 1990 1991 1992

A

M

A

A

M

A

A

A

M

A

M

A

M

A

1993

A

1994

A

M

A

M

1995

A

A

1996

M

A

1997

A

A

1998

A

1600

1400

1200

1000

800

600

400

M

M M

M

A

A M

M

M

M

M

A M

A M

M M

M

M

A M

Middle 50% of BWRs

Middle 50% of PWRs

Average Collective Dose

M Median Collective Dose

A

Year

1999

A M

A

M

A M

A

M

2000 2003

A M

A

M 124

56

201

124

2001 2002

A M

A M
4-15

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 4.5

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

2001- 2003

6 86 518 3,673 0.14 6,616.3 0.08

3 99 297 2,046 0.15 1,416.2 0.21

3 100 299 2,119 0.14 2,759.1 0.11

6 102 613 4,001 0.15 4,808.8 0.13

3 107 321 3,349 0.10 2,751.5 0.12

3 114 343 2,553 0.13 1,823.4 0.19

3 115 345 2,197 0.16 2,351.0 0.15

3 116 348 2,168 0.16 1,431.9 0.24

3 118 355 2,326 0.15 1,766.2 0.20

3 125 375 2,872 0.13 2,959.4 0.13

3 131 393 2,459 0.16 3,516.2 0.11

6 133 798 5,631 0.14 6,051.6 0.13

6 138 827 5,160 0.16 4,821.2 0.17

9 139 1,254 6,110 0.21 6,157.2 0.20

3 143 430 2,091 0.21 1,535.1 0.28

3 153 460 2,918 0.16 2,725.1 0.17

3 156 468 3,013 0.16 1,809.0 0.26

3 160 479 3,780 0.13 2,828.7 0.17

6 166 997 4,800 0.21 6,364.4 0.16

6 172 1,033 5,001 0.21 6,214.0 0.17

6 185 1,112 7,686 0.14 4,530.2 0.25

6 206 1,235 5,321 0.23 4,609.1 0.27

3 312 936 3,708 0.25 2,995.2 0.31

6 395 2,368 5,552 0.43 4,444.0 0.53

105 16,603 90,534 0.18 87,284.8 0.19

 158 862 831.3

LIMERICK 1, 2

DUANE ARNOLD

CLINTON

HATCH 1, 2

HOPE CREEK 1

COOPER STATION

FITZPATRICK

VERMONT YANKEE

OYSTER CREEK

FERMI

GRAND GULF

SUSQUEHANNA 1, 2

BRUNSWICK 1, 2

BROWNS FERRY 1, 2, 3**

MONTICELLO

RIVER BEND 1

PILGRIM

COLUMBIA GENERATING

LASALLE 1, 2

PEACH BOTTOM 2, 3

DRESDEN 2, 3

NINE MILE POINT 1, 2

PERRY

QUAD CITIES 1, 2

Totals and Averages

Averages per Reactor-Yr

Site Name*

Collective

TEDE per

Reactor

Collective

TEDE per

Site

Reactor

Years

Number of

Workers with

Measurable

TEDE

Average

TEDE per

Worker

Total

MW-Years

Average

TEDE per

MW-Year

* Sites where not all reactors had completed 3 full years of commercial operation as of 12/31/03 are not included.

** Browns Ferry 1 remains in the count of operating reactors, but was placed on Administrative Hold in June of 1985.
4-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

TABLE 4.6

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

2001 - 2003

Site Name*

Collective

TEDE per

Reactor

Collective

TEDE per

Site

Reactor

Years

Number of

Workers with

Measurable

TEDE

Average

TEDE per

Worker

Total

MW-Years

Average

TEDE per

MW-Year

* Sites where not all reactors had completed 3 full years of commercial operation as of 12/31/03 are not included.

SEABROOK

PRAIRIE ISLAND 1, 2

GINNA

BYRON 1, 2

PALO VERDE 1, 2, 3

WOLF CREEK 1

MCGUIRE 1, 2

POINT BEACH 1, 2

SUMMER 1

DIABLO CANYON 1, 2

COMANCHE PEAK 1, 2

CATAWBA 1, 2

WATERFORD 3

CALLAWAY 1

TURKEY POINT 3, 4

SAN ONOFRE 2, 3

BRAIDWOOD 1, 2

INDIAN POINT 3

VOGTLE 1, 2

ARKANSAS 1, 2

ROBINSON 2

COOK 1, 2

ST. LUCIE 1, 2

FARLEY 1, 2

WATTS BAR 1

BEAVER VALLEY 1, 2

KEWAUNEE

CRYSTAL RIVER 3

INDIAN POINT 2

SALEM 1, 2

NORTH ANNA 1, 2

HARRIS

CALVERT CLIFFS 1, 2

SEQUOYAH 1, 2

OCONEE 1, 2, 3

SOUTH TEXAS 1, 2

THREE MILE ISLAND 1

SURRY 1, 2

MILLSTONE 2, 3

PALISADES

FORT CALHOUN

DAVIS-BESSE

Totals and Averages

Averages per Reactor-Yr

3 49 146 2,499 0.06 3,103.5 0.05

6 52 314 2,254 0.14 2,893.8 0.11

3 55 165 1,185 0.14 1,365.9 0.12

6 57 342 2,830 0.12 6,800.9 0.05

9 59 533 4,647 0.11 10,048.0 0.05

3 65 194 1,741 0.11 3,220.7 0.06

6 65 389 2,971 0.13 6,320.3 0.06

6 66 397 2,312 0.17 2,741.6 0.14

3 67 200 1,916 0.10 2,446.4 0.08

6 67 402 3,094 0.13 5,897.9 0.07

6 68 407 2,598 0.16 5,993.9 0.07

6 68 408 3,253 0.13 6,341.2 0.06

3 70 209 1,612 0.13 3,061.3 0.07

3 70 211 2,108 0.10 3,013.6 0.07

6 70 422 3,062 0.14 3,951.3 0.11

6 72 432 3,498 0.12 5,867.4 0.07

6 73 436 3,428 0.13 6,750.2 0.06

3 74 221 2,072 0.11 2,730.1 0.08

6 76 458 2,828 0.16 6,353.3 0.07

6 78 470 3,636 0.13 5,018.6 0.09

3 80 240 1,766 0.14 1,999.2 0.12

6 86 515 3,455 0.15 5,108.3 0.10

6 88 526 3,304 0.16 4,685.2 0.11

6 88 528 3,370 0.16 4,534.9 0.12

3 88 265 2,498 0.11 3,102.8 0.09

6 92 552 3,873 0.14 4,485.4 0.12

3 93 278 1,651 0.17 1,376.3 0.20

3 93 280 1,991 0.14 2,321.7 0.12

3 94 282 2,001 0.14 2,700.5 0.10

6 95 570 5,035 0.11 5,852.4 0.10

6 107 639 3,186 0.20 4,616.8 0.14

3 109 327 2,517 0.13 2,327.1 0.14

6 113 677 4,148 0.16 4,493.5 0.15

6 114 684 5,033 0.14 6,040.3 0.11

9 117 1,049 5,905 0.18 6,700.0 0.16

6 118 710 3,744 0.19 6,232.0 0.11

3 119 358 2,598 0.14 2,155.7 0.17

6 124 742 3,670 0.20 4,254.0 0.17

6 132 789 4,149 0.19 5,296.5 0.15

3 197 590 2,078 0.28 1,694.4 0.35

3 201 602 2,426 0.25 1,234.4 0.49

3 209 628 3,149 0.20 981.4 0.64

207 18,588 125,091 0.15 176,112.7 0.11

90 604 850.8
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Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

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The average 3-year collective TEDE per BWR 

for 2001 - 2003 is 2% less than the average 

for 2000 - 2002. The average 3-year collective 

TEDE per PWR for 2001 - 2003 is 1% less than 

the average for 2000 - 2002. 

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 2003. 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 the plant’s first full 

year of commercial operation, and continuing 

through 2003. Data for years when the 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 the 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 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 gives a better idea 

of collective dose trends over the life of the 

plant. The annual average collective dose per 

reactor for all reactors of the same type is also 

shown on the graph.
4-18

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TRANSIENT WORKERS AND CAREER 

DOSES AT NRC-LICENSED FACILITIES

Section 5

5.1 TERMINATION REPORTS

Under 10 CFR 20, licensees are required to 

submit NRC Form 5s to the Commission 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 requirement for submitting 

“termination reports” in accordance with the old 

§ 20.408, which listed the individual’s completed 

dose history during employment at the facility, 

was eliminated in 1994.

However, the Form 5s 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 

and individual dose received by these “annual 

transients” 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 2003, 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-Sixth Annual Report, 2003

NUREG-0713 

TABLE 5.1

Effects of Transient Workers on Annual Statistical Compilations

2003

77,889 42,720 17,231 9,589 3,139 1,233 864 37 152,702 74,813 11,956 0.1630,902 20,235 9,457 5,129 1,752 715 452 19 68,661 37,759 6,428 0.17

7,036 6,679 4,204 3,739 1,862 1,006 1,239 166 18 25,949 18,913 6,428 0.34

54,023 29,164 11,978 8,199 3,249 1,524 1,651 184 18 109,990 55,967 11,956 0.21

82,723 46,434 18,637 10,440 3,632 1,557 1,328 184 46 11 1 164,993 82,270 14,413 0.1831,565 20,468 9,544 5,207 1,796 738 485 26 1 69,830 38,265 6,590 0.17

7,027 6,666 4,228 3,775 1,893 1,025 1,289 179 19 1 26,102 19,075 6,590 0.35

58,185 32,632 13,321 9,008 3,729 1,844 2,132 337 64 12 1 121,265 63,080 14,413 0.23

Average

Meas.

TEDE

(rem)

POWER REACTORS

1) Form 5 Summation

 2) 

Transients - As Reported

 3) 

Transients - Actual

Corrected Distribution (1-(2-3))

ALL LICENSEES

1) Form 5 Summation

 2) 

Transients - As Reported

 3) 

Transients - Actual

Corrected Distribution (1-(2-3))

Number of Individuals with TEDE in the Ranges (rem)

License Category

Total

Number

Monitored

Number

with

Measurable

Exposure

Collective

TEDE

(person-rem)

No

Measurable

Exposure

Measurable

<0.10

0.10-

0.25

3.0-

4.0

0.25-

0.50

0.50-

0.75

0.75-

1.0

1.0-

2.0

2.0-

3.0

4.0-

5.0

5.0-

6.0 >6
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Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

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Table 5.1 illustrates the impact that the multiple 

reporting of these transient individuals had on 

the summation of the exposure reports for 2003. 

Because each licensee reports the doses 

received by workers while monitored by the 

particular licensee during the year, one would 

expect 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 dose (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 2003, Table 5.1 shows that 

the summation of annual reports for reactor 

licensees indicated that 37 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 202 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 for transient 

workers by the summation of licensee records. 

The transient workers represent 30% of the 

workforce that receives measurable dose 

(for those licensees listed in Table 3.1). The 

correction for the transient workers increases 

the average measurable dose by a factor of 

2 from 0.17 rem to 0.35 rem for the transient 

workforce for all licensees. It should be noted 

that this analysis of transient workers does not 

include workers who may have been exposed 

at facilities that are not required to report to the 

NRC REIRS database (see Section 1), such as 

Agreement State licensees, or DOE facilities.

One purpose of the REIRS database, which 

tracks occupational radiation exposures at 

NRC-licensed facilities, is to identify individuals 

who may have exceeded the occupational 

radiation exposure limits because of multiple 

exposures at different facilities throughout the 

year. The REIRS database stores the radiation 

exposure information for an individual by their 

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 2003, one individual exceeded the 5 rem 

annual TEDE limit, but the individual received 

this dose at one radiography licensee and was 

therefore not a transient (see Section 6). So 

the individual is included in the distribution of all 

licensees as determined by the summation of 

Form 5 records.
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Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

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8 See 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. 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, 

red bone marrow, bone surfaces, lung, thyroid, 

and breast). 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. 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.

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.
6-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

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(3) Category C

10 CFR 20.2203 - In addition to the 

notification required by § 20.2202 

(category A and B occurrences), each 

licensee must submit a written report 

within 30 days after learning of any of the 

following occurrences:

(1) Any incident for which notification is 

required by § 20.2202; or

(2) Doses that exceed the limits in

§ 20.1201, § 20.1207, § 20.1208,

§ 20.1301 (for adults, minors, the embryo/

fetus of a declared pregnant worker, and 

the public, respectively), or any applicable 

limit in the license; or

(3) 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); or

(4) 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.
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Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

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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. 

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 “overexposure” 

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 Commission licensees pursuant 

to 10 CFR 20.2202 and 10 CFR 20.2203 

from 1994 to 2003. Table 6.2 shows the data 

reported under 10 CFR 20.403 and

10 CFR 20.405 for the period 1985-1993. Note 

that the categorization criteria changed effective 

with the revision of 10 CFR 20 in 1994.

For the period 1990-1993, Table 6.2 shows the 

number of individuals who exceeded various 

limits while employed by one of several types 

of licensees. For the period 1985-1989, 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 2003, there were no Category A occurrences, 

one Category B occurrence, and no Category C 

occurrences. 
6-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

TABLE 6.1

Occupational Exposures in Excess of Regulatory Limits

1994 - 2003

1 1

15.678 15.667

1

5.860

1 1 

5.606 80 

 1 3

 127 1260

2

11.373

2

10.636

2

2,562

1

115

1

5.67

1 

143 

4f 2f

423 1,080

4a 1 

34.8 50-200

5f 3f

675 1,115

1b

51.1

5f 3f

431 1,199

1

8.3

7c, f

 810.6

1

5.1

4d, f 1f

 782 255

2

12.2

1e

 180

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING & NO. OF PERSONS

MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING & NO. OF PERSONS

MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING & NO. OF PERSONS

MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING & NO. OF PERSONS

MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING & NO. OF PERSONS

MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO.OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO.OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO.OFPERSONS

SUM OF DOSES

INDUSTRIAL NO.OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO.OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO.OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

2001

2000

1999

1996

1995

1994

Types Of Exposures And Doses

Lens of the Eye (rem)

5 - 25

License Persons and

Year Category Doses (rem)

TEDE (rem) Skin/Extremity (rem)

a One of these individuals also received the extremity exposure as shown.

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

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

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

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

f These exposures have been added due to a reassessment of extremity

dose from the direct handling of vials containing Indium at a

radiopharmaceutical manufacturing licensee.

g These exposures were received by the same individual.

2003

>25 15 - 75 >75 50 - 250 >250 rad

2002

1997

1998

g g
6-5

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 6.2

Occupational Exposures in Excess of Regulatory Limits

1985 - 1993

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING & NO. OF PERSONS

MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING & NO. OF PERSONS

MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING & NO. OF PERSONS

MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING & NO. OF PERSONS

MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

ALL OTHER NO. OF PERSONS

SUM OF DOSES

1993

1985

1986

1987

1988

1989

1990

1991

1992

1

1.3

5

10.6

2a

4.0

1

1.9

1b

1.9

2

5.6

2

3.8

1

2.4

3

7.2

3e

8.9

1

2.3

3

8.1

4

6.6

3

8.1

7

19.34

1

3.1

2

2.8

2

4.4

3

9.6

6

16.7

7

11.8

1

61

4

143.6

1

40.5

1

22.3

1

48.8

1

72

2

105

1

58

3

72.0

1

41.2

3

60.2

a Same individual exceeded 1.25 rem/qtr limit twice during 1993.

b This 1992 exposure was reported in 1994.

c This individual received a whole-body dose of 24 rem in addition to a 6000 rem skin

dose.

Types Of Exposures And Doses

Whole Body (rem) License Persons and

Year Category Doses (rem)

Skin (rem) Extremity (rem)

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

d One of these individuals received a 9 rem whole-body dose in addition to a 1070 rem

extremity dose.

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

in one calendar year.

f An additional 1993 exposure was reported in 1994.

1a

5.4

3c, d

49.9

1

6.1

1

7.5

3

32.6

1

6

1

93

1

27.0

4

57.7

1

24.1

1

9.2

4

66.8

5

128.4

1

278

1c

6000

2

930

1

650

2d

3962

1

300-1000

1

275

1

272

1

111

1

178

1

118

1

127

1

180

1

115

1

288

1

93

3f

187.3
6-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

In September of 2003, a multi-location 

radiography licensee reported that a 

radiographer received an overexposure at a 

pipe fabrication facility in Charleston, West 

Virginia. Two radiographers were using an 

AEA Technology exposure device with a 762.2 

GBq (20.6 Ci) Ir-192 source. Following a 

radiography shot of a pipe weld, the equipment 

was set up for a shot of the next weld. Upon 

completion of the shot, the radiographer 

attempted to retract the source but nothing 

happened. The radiographer realized that the 

source had been exposed during setup for 

the shot and that he had retracted the source 

into the camera when he thought he was 

extending it for the shot. Both radiographers 

were wearing pocket dosimeters, which were 

off scale. The radiographers were also wearing 

alarming ratemeters set at 5 mSv/hour (500 

mrem/hour), which they said did not alarm. An 

investigation determined that the source was 

extended approximately 16 inches during the 

10-minute setup for the second shot. One of 

these individuals exceeded the 5 rem TEDE 

annual limit. The TEDE reported to REIRS for 

the individual was 15.68 rem. This incident was 

caused by the failure to perform an adequate 

radiation survey of the exposure device, the 

failure to properly lock the exposure device 

prior to moving it for the second shot, the 

failure to remove faulty equipment from service 

(the source crank assembly was missing two 

screws in the gear housing, allowing the cable 

to slip), and inadequate management oversight. 

The licensee returned the exposure device to 

the manufacturer for evaluation, where it was 

determined that the posilock was sluggish and 

the lock mechanism was operational but had 

significant friction due to dirt and grease. The 

alarming ratemeters were sent to the corporate 

office, where they were found to operate 

correctly. To prevent recurrence, the licensee 

held training meetings with all radiographic 

personnel, performed a maintenance inspection 

on all exposure devices and their associated 

equipment, reassigned the RSO duties, and 

contracted with an independent auditor to 

review their radiation safety program.

No individuals were reported to have exceeded 

the annual extremity, skin dose, or organ dose 

limits.
6-7

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

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 

2003, only 31 individuals exceeded 75% of 

the occupational dose limits. One individual 

exceeded both the 5 rem TEDE annual limit 

and the LDE annual limit at a multi-location 

radiographer as described above. The 

exposure in excess of the TEDE limit (15.68 

rem) is the highest TEDE recorded within the 

past 10 years. 

TABLE 6.3

Maximum Occupational Exposures for Each Exposure Category *

2003

Maximum Number of Number of Number of Number of Number of

Annual Exposure Max Dose Individuals with Individuals Individuals Individuals Individuals

Exposure Dose Limit Reported Percent of Measurable ≥ 25% of ≥ 50% of ≥ 75% of ≥ 95% of

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

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

of transient individuals.

** SDE-ME =shallow dose equivalent – maximally exposed extremity

SDE-WB =shallow dose equivalent – whole body

LDE =eye dose equivalent to the lens of the eye

CEDE =committed effective dose equivalent

CDE =committed dose equivalent

DDE =deep dose equivalent

TEDE =total effective dose equivalent

TODE =total organ dose equivalent

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

SDE-ME 50 rem 46.210 92% 73,752 182 40 8 0 0

SDE-WB 50 rem 14.936 30% 85,641 2 0 0 0 0

LDE 15 rem 15.667 104% 83,848 19 1 1 1 1

CEDE 1.546 3,893 

CDE 8.729 2,595 

DDE 15.678 84,704 

TEDE 5 rem 15.678 314% 85,599 934 124 21 2 1

TODE 50 rem 15.678 31% 73,270 1 0 0 0 0

Number of

Individuals

> Limit
6-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

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7-1

Thirty-Sixth Annual Report, 2003 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 (INEEL) 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, Virginia, 22161, and/or the 

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

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

This page intentionally left blank.
A-1

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ANNUAL TEDE FOR NON-REACTOR

NRC LICENSEES

2003

Appendix A
A-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

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APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2003

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

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2003 (continued)
A-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

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APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2003 (continued)

NOTE: The data values shown bolded and in boxes represent the highest value in each category.
A-5

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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����������������������������������������������������������������PROFESSIONAL NDE & WELDING SERVICES 52-25538-01 1 2 1 5 1 - - - - - - - - 10 9 2.815 0.313PROFESSIONAL WELDING ASSOC., INC. 48-25806-01 1 4 2 - - - - - - - - - - 7 6 0.453 0.076Q.C. LABORATORIES, INC. 09-11579-03 - 7 2 4 2 - - - - - - - - 15 15 3.207 0.214QSL PLUS, INC. 37-28085-01 7 9 7 11 5 4 7 9 2 1 - - - 62 55 56.420 1.026QUALITY INSPECTION SERVICES, INC. 31-30187-01 - 2 - - 1 3 - - - - - - - 6 6 3.342 0.557QUALITY TESTING SERVICE, INC. 24-32292-01 - 4 1 1 - - - - - - - - - 6 6 0.648 0.108SCIENTIFIC TECHNICAL, INC. 45-24882-01 7 5 - - - - - - - - - - - 12 5 0.198 0.040SHAW PIPELINE SERVICES, INC. 35-23193-01 3 12 15 25 18 13 8 1 - - - - - 95 92 47.373 0.515S.K. MCBRYDE, INC. 32-25137-01 - 1 4 3 1 - - - - - - - - 9 9 2.207 0.245SOUTHWEST X-RAY CORPORATION 49-27434-01 - 2 - 4 1 1 1 1 - - - - - 10 10 7.623 0.762ST. LOUIS TESTING LABS, INC. 24-00188-02 1 6 1 1 1 2 3 - - - - - - 15 14 7.233 0.517

T & K INSPECTION, INC. 33-27678-01 - - - 1 - - 4 2 2 - - - - 9 9 18.690 2.077

TEI ANALYTICAL SERVICES, INC. 37-28004-01 1 11 6 10 6 2 6 1 - - - - - 43 42 20.933 0.498TESTING TECHNOLOGIES, INC. 45-25007-01 - 5 6 6 3 4 2 - - - - - - 26 26 10.740 0.413TEST MASTER INSPECTION CO., INC. 34-24872-02 - 1 - 2 2 1 1 - - - - - - 7 7 5.090 0.727THERMAL ENGINEERING INT'L 24-19500-01 6 - - - - - - - - - - - - 6 - - -THREE RIVERS GAMMA 37-28367-01 - - - - - - 2 - - - - - - 2 2 2.840 1.420TMP WORLDWIDE, INC. 37-27891-01 2 6 7 - 2 1 5 - - - - - - 23 21 10.142 0.483TULSA GAMMA RAY, INC. 35-17178-01 2 7 3 11 12 10 24 8 7 4 - - - 88 86 115.864 1.347U.S. INSPECTION SERVICES 34-06943-02 7 58 23 19 17 16 21 9 1 - - - 1 172 165 107.871 0.654VALLEY INDUSTRIAL X-RAY 04-29076-01 25 11 11 6 13 5 12 - - - - - - 83 58 33.956 0.585VALLEY INSPECTION SERVICE, INC. 37-28385-01 2 2 1 1 2 1 1 1 - - - - - 11 9 6.864 0.763WESTERN X-RAY COMPANY 35-19993-01 - 2 3 - 2 - 9 1 2 - - - - 19 19 23.765 1.251WOS TESTING COMPANY, INC. 48-26385-01 1 2 - 1 - - 1 - - - - - - 5 4 1.909 0.477Total 74 278 586 358 369 256 196 344 115 40 9 - - 1 2,552 2,274 1500.885 0.660

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2003 (continued)

NOTE: The data values shown bolded and in boxes represent the highest value in each category.
A-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2003 (continued)

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

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��������������������������������������������������������������������CAPITAL PHARMACY, INC. 21-26597-01MD 4 11 3 1 - - - - - - - - - 19 15 1.038 0.069CARDINAL HEALTH 04-26507-01MD 114 534 128 42 7 3 2 - - 1 - - - 831 717 61.810 0.086EASTERN ISOTOPES, INC. 45-25221-01MD 30 78 19 9 5 9 17 7 5 1 - - - 180 150 82.070 0.547MALLINCKRODT, INC. 24-04206-08MD 4 11 5 - - - - - - - - - - 20 16 1.044 0.065MALLINCKRODT, INC. 24-04206-22MD 12 1 1 - - - - - - - - - - 14 2 0.169 0.085MALLINCKRODT MEDICAL, INC. 24-04206-01MD 13 8 1 - - - - - - - - - - 22 9 0.449 0.050MALLINCKRODT MEDICAL, INC. 24-04206-14MD 5 11 9 1 - - - - - - - - - 26 21 2.268 0.108MALLINCKRODT MEDICAL, INC. 24-04206-16MD 11 3 3 1 - - - - - - - - - 18 7 1.065 0.152MALLINCKRODT MEDICAL, INC. 24-04206-19MD 14 5 6 2 1 - - - - - - - - 28 14 2.869 0.205MALLINCKRODT MEDICAL, INC. 24-17450-02MD 10 8 2 1 - - - - - - - - - 21 11 0.980 0.089MID-AMERICA ISOTOPES, INC. 24-26241-01MD 16 7 2 - 1 1 - - - - - - - 27 11 1.987 0.181OKLAHOMA, UNIVERSITY OF 35-03176-04MD 10 15 7 - - - - - - - - - - 32 22 1.427 0.065PHARMALOGIC OF PENN LTD. 37-30219-01MD 1 5 6 1 - - - - - - - - - 13 12 1.490 0.124RADIOPHARMACY, INC. 13-26246-01MD 4 15 3 2 - - - - - - - - - 24 20 1.435 0.072SPECTRUM PHARMACY, INC. 13-26367-01MD 6 31 4 3 - - - - - - - - - 44 38 2.495 0.066SPECTRUM PHARMACY, INC.-FT. WAYNE 13-32053-01MD 12 15 1 - - - - - - - - - - 28 16 0.461 0.029Total 16 266 758 200 63 14 13 19 7 5 2 - - - 1,347 1,081 163.057 0.151
A-7

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2003 (continued)

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

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�����������������������������������������������������INTERNATIONAL ISOTOPES IDAHO, INC. 11-27680-01 7 2 1 4 - - 1 - - - - - - 15 8 3.298 0.412MALLINCKRODT, INC. 24-04206-01 76 54 46 56 40 37 54 25 1 - - - - 389 313 224.897 0.719NUCLEAR RESEARCH CORPORATION 29-04236-01 6 27 1 - - - - - - - - - - 34 28 0.727 0.026Total 3 89 83 48 60 40 37 55 25 1 - - - - 438 349 228.922 0.656��������������������������������������������������������������OHMART/VEGA CORP. 34-00639-04 33 17 1 1 1 - - - - - - - - 53 20 1.867 0.093Total 1 33 17 1 1 1 - - - - - - - - 53 20 1.867 0.093�������������������������������������������������������BMS-MEDICAL IMAGING 20-00320-19 - 1 1 - - - - - - - - - - 2 2 0.160 0.080MDS NORDION, INC. 54-28275-01 2 2 1 - - - - - - - - - - 5 3 0.217 0.072PHARMASAN LABS, INC. 48-26355-01 - 4 - - - - - - - - - - - 4 4 0.014 0.004Total 3 2 7 2 - - - - - - - - - - 11 9 0.391 0.043
A-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 APPENDIX A Annual TEDE for Non-Reactor NRC Licensees CY 2003 (continued)

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

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���������������������������������������������������DEPARTMENT OF ENERGY (TMI) SNM-2508 1 9 5 2 - - - - - - - - - 17 16 1.583 0.099GENERAL ELECTRIC COMPANY SNM-2500 8 25 5 - - - - - - - - - - 38 30 1.208 0.040Total 2 9 34 10 2 - - - - - - - - - 55 46 2.791 0.061����������������������������������������������USEC-PADUCAH GDP-1 2,027 251 26 1 - - - - - - - - - 2,305 278 11.209 0.040USEC-PORTSMOUTH GDP-2 1,091 249 23 18 - - - - - - - - - 1,381 290 17.595 0.061Total 2 3,118 500 49 19 - - - - - - - - - 3,686 568 28.804 0.051�����������������������������������������������BWX TECHNOLOGIES, INC. (NPD) SNM-0042 20 137 120 21 3 1 2 - - - - - - 304 284 38.077 0.134FRAMATOME ANP, INC. SNM-1168 586 159 30 6 3 - - - - - - - - 784 198 12.543 0.063FRAMATOME ANP, INC. SNM-1227 68 180 91 77 39 20 4 - - - - - - 479 411 95.123 0.231GLOBAL NUCLEAR FUEL-WILMINGTON, NC SNM-1097 255 338 182 46 3 - - - - - - - - 824 569 57.263 0.101NUCLEAR FUEL SERVICES, INC. SNM-0124 49 720 156 64 8 3 3 - - - - - - 1,003 954 78.995 0.083WESTINGHOUSE ELECTRIC COMPANY SNM-1107 9 160 153 120 125 54 37 - - - - - - 658 649 245.492 0.378Total 6 987 1,694 732 334 181 78 46 - - - - - - 4,052 3,065 527.493 0.172
B-1

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR 

POWER FACILITIES

2003

Appendix B
B-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

APPENDIX B

Annual Whole Body Doses at Licensed Nuclear Power Facilities

CY 2003

PLANT NAME TYPE

Number of Individuals with Whole Body Doses in the Ranges (rems)

No

Meas.

Exposure

Meas.

<0.10

0.10-

0.25

0.25-

0.50

0.50-

0.75

0.75-

1.00

1.00-

2.00

2.00-

3.00

3.00-

4.00

4.00-

5.00

5.00-

6.00

6.00-

7.00 >12.0

Total

Number

Monitored

Number

With

Meas.

Dose

Total

Collective

TEDE

(PersonRem) 7.00- 12.00

ARKANSAS 1, 2 PWR 1,169 688 187 68 20 7 3 - - - - - - - 2,142 973 99.003BEAVER VALLEY 1, 2 PWR 1,533 825 420 267 68 27 16 - - - - - - - 3,156 1,623 277.168BRAIDWOOD 1, 2 PWR 1,609 844 397 228 78 19 6 - - - - - - - 3,181 1,572 244.860BROWNS FERRY 1, 2, 3 BWR 2,168 1,163 548 514 257 86 39 1 - - - - - - 4,776 2,608 602.535BRUNSWICK 1, 2 BWR 1,355 1,183 294 193 86 27 11 - - - - - - - 3,149 1,794 248.622BYRON 1, 2 PWR 1,109 516 219 79 9 1 - - - - - - - - 1,933 824 87.129CALLAWAY 1 PWR 1,056 235 16 1 - - - - - - - - - - 1,308 252 8.297CALVERT CLIFFS 1, 2 PWR 1,333 811 518 254 73 14 1 - - - - - - - 3,004 1,671 265.164CATAWBA 1, 2 PWR 1,724 672 489 200 32 12 4 - - - - - - - 3,133 1,409 210.617CLINTON BWR 736 203 100 42 16 11 - - - - - - - - 1,108 372 57.118COLUMBIA GENERATING BWR 736 1,040 295 203 63 13 4 - - - - - - - 2,354 1,618 205.225COMANCHE PEAK 1, 2 PWR 1,317 416 163 51 8 1 - - - - - - - - 1,956 639 66.313COOK 1, 2 PWR 2,082 822 340 162 51 17 16 - - - - - - - 3,490 1,408 209.526COOPER STATION BWR 944 473 237 116 42 14 - - - - - - - - 1,826 882 135.249CRYSTAL RIVER 3 PWR 794 570 252 107 15 12 5 - - - - - - - 1,755 961 126.554DAVIS-BESSE PWR 1,113 539 235 140 70 35 28 - - - - - - - 2,160 1,047 219.696DIABLO CANYON 1, 2 PWR 1,217 590 244 128 33 8 1 - - - - - - - 2,221 1,004 135.482DRESDEN 2, 3 BWR 1,073 1,211 444 266 108 33 35 1 - - - - - - 3,171 2,098 356.572DUANE ARNOLD BWR 1,122 465 191 125 42 6 - - - - - - - - 1,951 829 124.402FARLEY 1, 2 PWR 1,062 479 195 83 12 3 16 - - - - - - - 1,850 788 111.016FERMI 2 BWR 1,382 692 279 181 46 9 - - - - - - - - 2,589 1,207 168.138FITZPATRICK BWR 725 146 76 54 16 3 3 - - - - - - - 1,023 298 51.156FORT CALHOUN PWR 578 402 213 169 76 41 13 - - - - - - - 1,492 914 212.422GINNA PWR 889 267 150 79 10 2 2 - - - - - - - 1,399 510 74.533GRAND GULF BWR 778 181 81 27 - 1 - - - - - - - - 1,068 290 31.250HARRIS PWR 1,002 540 185 56 5 - - - - - - - - - 1,788 786 68.463HATCH 1, 2 BWR 1,180 716 367 188 23 1 - - - - - - - - 2,475 1,295 168.281HOPE CREEK 1 BWR 433 1,184 226 137 30 14 6 - - - - - - - 2,030 1,597 139.295INDIAN POINT 2 PWR 1,504 214 22 4 1 - - - - - - - - - 1,745 241 11.778INDIAN POINT 3 PWR 1,477 567 239 84 11 1 - - - - - - - - 2,379 902 96.059KEWAUNEE PWR 604 217 116 75 26 4 1 - - - - - - - 1,043 439 73.108LASALLE 1, 2 BWR 1,498 1,255 387 311 161 90 47 2 - - - - - - 3,751 2,253 464.427LIMERICK 1, 2 BWR 1,737 870 270 111 34 9 4 - - - - - - - 3,035 1,298 147.047MCGUIRE 1, 2 PWR 1,660 620 170 44 7 - - - - - - - - - 2,501 841 71.323MILLSTONE 2, 3 PWR 1,007 686 263 160 62 33 66 4 - - - - - - 2,281 1,274 322.923MONTICELLO BWR 701 402 209 158 60 21 8 - - - - - - - 1,559 858 168.896NINE MILE POINT 1, 2 BWR 1,217 727 277 248 120 59 70 - - - - - - - 2,718 1,501 374.775NORTH ANNA 1, 2 PWR 2,172 588 230 131 45 24 21 2 - - - - - - 3,213 1,041 187.014
B-3

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX B

Annual Whole Body Doses at Licensed Nuclear Power Facilities

CY 2003 (continued)

PLANT NAME TYPE

Number of Individuals with Whole Body Doses in the Ranges (rems)

No

Meas.

Exposure

Meas.

<0.10

0.10-

0.25

0.25-

0.50

0.50-

0.75

0.75-

1.00

1.00-

2.00

2.00-

3.00

3.00-

4.00

4.00-

5.00

5.00-

6.00

6.00-

7.00 >12.0

Total

Number

Monitored

Number

With

Meas.

Dose

Total

Collective

TEDE

(PersonRem) 7.00- 12.00

OCONEE 1, 2, 3 PWR 2,226 1,235 729 205 10 1 - - - - - - - - 4,406 2,180 245.349OYSTER CREEK BWR 859 273 105 30 6 1 1 - - - - - - - 1,275 416 43.363PALISADES PWR 792 329 219 161 53 34 26 - - - - - - - 1,614 822 202.571PALO VERDE 1, 2, 3 PWR 1,907 1,331 408 140 38 15 11 - - - - - - - 3,850 1,943 210.842PEACH BOTTOM 2, 3 BWR 1,370 819 381 231 91 68 51 - - - - - - - 3,011 1,641 355.969PERRY BWR 780 733 333 371 196 109 136 2 - - - - - - 2,660 1,880 607.384PILGRIM BWR 597 821 288 202 68 37 21 - - - - - - - 2,034 1,437 250.192POINT BEACH 1, 2 PWR 827 327 204 80 16 - - - - - - - - - 1,454 627 84.965PRAIRIE ISLAND 1, 2 PWR 882 374 161 51 8 - - - - - - - - - 1,476 594 61.137QUAD CITIES 1, 2 BWR 772 373 171 132 107 83 110 22 - - - - - - 1,770 998 438.144RIVER BEND 1 BWR 777 674 312 221 63 20 6 - - - - - - - 2,073 1,296 216.950ROBINSON 2 PWR 746 98 11 - - - - - - - - - - - 855 109 4.838SALEM 1, 2 PWR 353 965 184 111 24 12 5 - - - - - - - 1,654 1,301 124.042SAN ONOFRE 2, 3 PWR 1,854 769 292 168 41 5 - - - - - - - - 3,129 1,275 163.804SEABROOK PWR 708 775 130 55 20 1 - - - - - - - - 1,689 981 70.953SEQUOYAH 1, 2 PWR 1,598 1,177 714 441 107 31 14 - - - - - - - 4,082 2,484 430.889SOUTH TEXAS 1, 2 PWR 1,228 509 210 121 46 19 4 - - - - - - - 2,137 909 143.495ST. LUCIE 1, 2 PWR 1,239 537 236 99 37 24 4 - - - - - - - 2,176 937 141.734SUMMER 1 PWR 1,007 527 148 58 11 1 - - - - - - - - 1,752 745 70.828SURRY 1, 2 PWR 2,647 839 338 272 115 35 26 3 - - - - - - 4,275 1,628 325.729SUSQUEHANNA 1, 2 BWR 1,296 1,219 411 209 68 24 3 - - - - - - - 3,230 1,934 250.096THREE MILE ISLAND 1 PWR 1,272 744 313 117 42 10 4 - - - - - - - 2,502 1,230 155.101TURKEY POINT 3, 4 PWR 1,184 696 421 224 70 21 10 - - - - - - - 2,626 1,442 247.053VERMONT YANKEE BWR 698 219 62 56 11 10 1 - - - - - - - 1,057 359 54.348VOGTLE 1, 2 PWR 1,107 500 229 71 5 1 - - - - - - - - 1,913 806 84.344

WATERFORD 3 PWR 1,079 446 144 85 28 5 2 - - - - - - - 1,789 710 95.332

WATTS BAR 1 PWR 1,281 854 354 142 35 5 2 - - - - - - - 2,673 1,392 165.741

WOLF CREEK 1 PWR 1,007 538 179 92 7 3 1 - - - - - - - 1,827 820 88.941

TOTALS BWRS 24,934 17,042 6,344 4,326 1,714 749 556 28 - - - - - - 55,693 30,759 5,659.434

TOTALS PWRS 52,955 25,678 10,887 5,263 1,426 484 308 9 - - - - - - 97,009 44,054 6,296.136

TOTALS LWRS 77,889 42,720 17,231 9,589 3,139 1,233 864 37 - - - - - - 152,702 74,813 11,955.570
B-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

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

CY 2003 (continued)

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

PLANT NAME TYPE

Number of Individuals with Whole Body Doses in the Ranges (rems)

No

Meas.

Exposure

Meas.

<0.10

0.10-

0.25

0.25-

0.50

0.50-

0.75

0.75-

1.00

1.00-

2.00

2.00-

3.00

3.00-

4.00

4.00-

5.00

5.00-

6.00

6.00-

7.00 >12.0

Total

Number

Monitored

Number

With

Meas.

Dose

Total

Collective

TEDE

(PersonRem) 7.00- 12.00

REACTORS NOT YET IN COMMERCIAL OPERATIONWATTS BAR 2 PWR Reported with Watts Bar 1REACTORS NO LONGER IN COMMERCIAL OPERATIONBIG ROCK POINT BWR 89 154 41 50 33 15 43 - - - - - - - 425 336 121.045HADDAM NECK PWR 584 201 102 45 22 17 13 - - - - - - - 984 400 82.022HUMBOLDT BAY BWR 103 14 - - - - - - - - - - - - 117 14 0.351LACROSSE BWR 6 59 6 - - - - - - - - - - - 71 65 1.836MAINE YANKEE PWR 288 239 56 29 7 6 5 - - - - - - - 630 342 43.775MILLSTONE 1 BWR 155 105 40 24 10 5 10 1 - - - - - - 350 195 10.675RANCHO SECO PWR 154 69 21 20 9 2 - - - - - - - - 275 121 18.300SAN ONOFRE 1 PWR 1,306 149 36 19 10 7 5 - - - - - - - 1,532 226 35.596TROJAN PWR 271 56 11 19 16 3 - - - - - - - - 376 105 23.996YANKEE-ROWE PWR 434 76 21 11 15 11 2 - - - - - - - 570 136 30.934ZION 1, 2 PWR 98 2 - - - - - - - - - - - - 100 2 0.049REACTORS NO LONGER IN COMMERCIAL OPERATION, REPORTED WITH OTHER UNITSBROWNS FERRY 1 BWR Reported with Browns Ferry 2, 3DRESDEN 1 BWR Reported with Dresden 2,3INDIAN POINT 1 PWR Reported with Indian Point 2THREE MILE ISLAND 2 PWR Reported with Three Mile Island 1; estimated dose from Unit 2 is 0.260 person-rem.Total Reporting* 12 3,488 1,124 334 217 122 66 78 1 - - - - - - 5,430 1,942 368.839
C-1

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

PERSONNEL, DOSE, AND POWER GENERATION 

SUMMARY

1969 - 2003

Appendix C*

* A discussion of the methods used to collect and calculate the information contained in this Appendix is given in Section 2.1.
C-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

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, 858 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

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, 831 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
C-3

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

1 Big Rock Point was shut down in 9/97 and is no longer included in the count of operating reactors. Parentheses indicate plant 

capacity when plant was operational.

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 ---

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, NPF-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 - 1161, 1154 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
C-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

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 - (1065), 1118, 1982 2,025.4 67.6 3,360 2,230 0.66 1.10

1118 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

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 - 872, 811 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

 2000 1,571.2 95.6 1,648 322 0.20 0.20

 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

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-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

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 - 1163, 1131 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

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 - 1125 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

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 - 825, 835 MWe 1982 1,238.3 73.7 1,805 1,057 0.59 0.85

 1983 1,397.2 81.6 1,915 668 0.35 0.48

 1984 1,389.4 79.3 1,369 479 0.35 0.34

 1985 1,189.8 68.4 1,598 694 0.43 0.58

 1986 1,530.0 87.2 1,296 347 0.27 0.23

 1987 1,207.3 71.8 1,384 412 0.30 0.34

 1988 1,397.7 81.0 1,296 291 0.22 0.21

 1989 333.6 20.1 1,786 346 0.19 1.04

 1990 161.1 11.0 2,019 304 0.15 1.89

 1991 1,085.0 64.7 1,974 132 0.07 0.12

 1992 1,271.2 73.9 1,979 330 0.17 0.26

 1993 1,462.1 83.9 1,462 405 0.28 0.28

 1994 1,342.1 79.4 1,482 454 0.31 0.34

 1995 1,542.8 89.9 1,203 235 0.20 0.15

 1996 1,438.5 82.4 1,167 239 0.20 0.17

 1997 1,499.6 89.1 1,091 229 0.21 0.15

 1998 1,523.1 89.3 1,042 187 0.18 0.12
C-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

CALVERT CLIFFS 1, 2 1999 1,521.4 90.1 1,134 192 0.17 0.13

(continued) 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

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, NPF-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 - 1129, 1129 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

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 - 1022 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

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 - 1107 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

3 Energy Northwest has changed the name of Washington Nuclear 2 to Columbia Generating Station.
C-7

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

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 - 1150, 1150 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

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 - 1000, 1060 MWe 1981 1,557.3 73.4 1,341 656 0.49 0.42

 1982 1,461.6 69.8 1,527 699 0.46 0.48

 1983 1,456.5 71.2 1,418 658 0.46 0.45

 1984 1,526.0 75.3 1,559 762 0.49 0.50

 1985 925.4 47.6 1,984 945 0.48 1.02

 1986 1,307.1 73.4 1,774 745 0.42 0.57

 1987 1,199.5 70.2 1,696 666 0.39 0.56

 1988 1,160.4 63.5 2,266 867 0.38 0.75

 1989 1,433.1 72.8 1,575 493 0.31 0.34

 1990 1,318.5 67.9 1,851 580 0.31 0.44

 1991 1,837.4 90.2 815 69 0.08 0.04

 1992 760.9 50.8 1,954 492 0.25 0.65

 1993 1,927.7 98.5 587 44 0.07 0.02

 1994 1,105.2 65.2 1,748 479 0.27 0.43

 1995 1,656.0 82.1 1,310 203 0.15 0.12

 1996 1,938.9 92.7 1,114 214 0.19 0.11

 1997 1,189.7 59.7 1,864 550 0.30 0.46

 1998 0.0 0.0 1,155 105 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

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 - 764 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
C-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

COOPER STATION 1992 731.0 96.4 463 84 0.18 0.11

(continued) 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

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 - 834 MWe 1982 589.8 76.0 780 177 0.23 0.30

 1983 452.1 58.8 1,720 552 0.32 1.22

 1984 774.2 94.5 549 49 0.09 0.06

 1985 344.2 47.6 1,976 689 0.35 2.00

 1986 319.5 41.8 1,057 472 0.45 1.48

 1987 436.0 60.9 1,384 488 0.35 1.12

 1988 690.2 84.0 569 64 0.11 0.09

 1989 352.8 48.8 880 234 0.27 0.66

 1990 497.8 63.8 1,441 476 0.33 0.96

 1991 654.6 82.0 821 116 0.14 0.18

 1992 632.1 76.1 1,403 424 0.30 0.67

 1993 722.4 85.0 683 60 0.09 0.08

 1994 711.9 84.3 1,079 228 0.21 0.32

 1995 866.3 100.0 209 8 0.04 0.01

 1996 290.8 37.7 1,192 353 0.30 1.21

 1997 0.0 0.0 973 179 0.18 ---

 1998 739.9 90.3 313 19 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

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
C-9

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

DAVIS-BESSE 1 1998 699.8 83.2 980 155 0.16 0.22

(continued) 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 ---

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 - 1087, 1087 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

 2003 1,970.7 91.6 1,004 135 0.13 0.07

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

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-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

DRESDEN 14 , 2, 3 2000 1,506.4 97.3 2,341 262 0.11 0.17

(continued) 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

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 - 566 MWe 1980 339.1 73.3 1,108 671 0.61 1.98

 1981 277.7 69.8 1,286 790 0.61 2.84

 1982 278.5 74.7 524 229 0.44 0.82

 1983 283.0 62.9 1,468 1,135 0.77 4.01

 1984 329.4 72.9 611 189 0.31 0.57

 1985 236.2 53.8 1,414 1,112 0.79 4.71

 1986 365.5 82.0 476 187 0.39 0.51

 1987 308.4 64.7 1,094 667 0.61 2.16

 1988 386.5 75.2 1,136 614 0.54 1.59

 1989 388.5 79.0 425 194 0.46 0.50

 1990 367.4 75.8 1,460 861 0.59 2.34

 1991 503.7 94.5 336 202 0.60 0.40

 1992 416.5 81.9 1,043 502 0.48 1.21

 1993 393.4 79.5 1,043 407 0.39 1.03

 1994 498.6 94.0 493 120 0.24 0.24

 1995 452.5 83.8 1,129 357 0.32 0.79

 1996 476.8 90.7 1,093 270 0.25 0.57

 1997 474.4 94.4 352 63 0.18 0.13

 1998 438.3 86.6 1,019 237 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

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 - 830, 839 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

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-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

FARLEY 1, 2 2000 1,430.1 88.6 1,683 360 0.21 0.25

(continued) 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

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 - 1089 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

 2002 1,059.0 98.7 463 38 0.08 0.04

 2003 925.3 86.9 1,207 168 0.14 0.18

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

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
C-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

FORT CALHOUN 1987 366.0 75.4 1,247 388 0.31 1.06

(continued) 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

 2001 401.2 88.3 770 226 0.29 0.56

 2002 434.0 92.3 742 164 0.22 0.38

 2003 399.6 87.0 914 212 0.23 0.53

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 - 480 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

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 - 1207 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
C-13

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

GRAND GULF 1996 1,096.2 88.7 1,564 357 0.23 0.33

(continued) 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

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 ---

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

5 Haddam Neck (also known as Connecticut Yankee) was shut down 12/4/96 and is no longer in the count of operating reactors. 

Parentheses indicate plant capacity when plant was operational.
C-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

HARRIS 1 2000 783.0 92.5 888 101 0.11 0.13

(continued) 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

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 - 856, 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

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 - 1049 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

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

6 Humboldt Bay had been shut down since 1976, and in 1984 it was decided that it would not be placed in operation again. 

Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was 

operational.
C-15

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

HUMBOLDT BAY6 1975 45.3 83.9 265 339 1.28 7.48

(continued) 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 ---

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), 951, 965 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

 1980 510.8 64.8 1,577 971 0.62 1.90

 1982 532.4 65.4 2,144 1,635 0.76 3.07

 1983 702.6 84.0 1,057 486 0.46 0.69

INDIAN POINT 2 1984 416.7 51.9 2,919 2,644 0.91 6.35

Docket 50-247; DPR-26 1985 791.4 95.7 708 192 0.27 0.24

1st commercial operation 8/74 1986 457.5 56.2 1,926 1,250 0.65 2.73

Type - PWR 1987 611.4 73.4 1,980 1,217 0.61 1.99

Capacity - 956 MWe 1988 719.3 86.9 890 235 0.26 0.33

 1989 532.5 64.6 2,093 1,436 0.69 2.70

 1990 618.0 66.6 1,061 608 0.57 0.98

 1991 461.2 55.7 1,810 1,468 0.81 3.18

 1992 930.9 99.1 489 97 0.20 0.10

 1993 702.1 75.7 1,514 675 0.45 0.96

 1994 903.8 100.0 381 48 0.13 0.05

 1995 582.4 70.8 1,690 548 0.32 0.94

 1996 927.8 94.8 388 54 0.14 0.06

 1997 360.6 45.1 1,340 367 0.27 1.02

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 Entergy since 2001, Indian Point 3 still reports separately.
C-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

INDIAN POINT 2 1998 282.8 31.5 1,154 290 0.25 1.03

(continued) 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 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 - 979 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

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 - 526 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

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

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

KEWAUNEE 1998 423.0 87.2 284 88 0.23 0.21

(continued) 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

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 ---

 1993 0.0 0.0 48 8 0.17 ---

 1994 0.0 0.0 65 8 0.12 ---

 1995 0.0 0.0 31 3 0.10 ---

 1996 0.0 0.0 25 4 0.15 ---

 1997 0.0 0.0 23 2 0.09 ---

 1998 0.0 0.0 27 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 ---

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 - 1111, 1111 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

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-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

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 - 1134, 1134 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

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 ---

10 Maine Yankee was shut down in 8/97 and is no longer included in the count of operating reactors. Parentheses indicate plant 

capacity when plant was operational.
C-19

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

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 - 1100, 1100 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

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 ---

11 Millstone Unit 1 was shut down 6/30/98 and 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-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

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 - 866, 1131 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

 1994 1,556.6 73.1 1,249 188 0.15 0.12

 1995 1,278.1 60.5 1,691 416 0.25 0.33

 1996 418.1 19.3 983 126 0.13 0.30

 1997 0.0 0.0 1,435 253 0.18 ---

 1998 374.9 20.9 1,179 113 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

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
C-21

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

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, 1120 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

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 - 925, 917 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

 2003 1,569.1 87.2 1,041 187 0.18 0.12
C-22

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

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

OYSTER CREEK 1970 413.6 95 63 0.66 0.15

Docket 50-219; DPR-16 1971 448.9 249 240 0.96 0.53

1st commercial operation 12/69 1972 515.0 339 582 1.72 1.13

Type - BWR 1973 424.6 782 1,236 1.58 2.91

Capacity - 619 MWe 1974 434.5 70.4 935 984 1.05 2.26

 1975 373.6 73.3 1,210 1,140 0.94 3.05

 1976 456.5 79.3 1,582 1,078 0.68 2.36

 1977 385.7 70.1 1,673 1,614 0.96 4.18

 1978 431.8 74.3 1,411 1,279 0.91 2.96

 1979 541.0 85.9 842 467 0.55 0.86

 1980 232.9 41.4 1,966 1,733 0.88 7.44

 1981 314.8 59.8 1,689 917 0.54 2.91

 1982 242.7 62.5 1,270 865 0.68 3.56

 1983 27.9 11.5 2,303 2,257 0.98 80.90

 1984 37.1 9.6 2,369 2,054 0.87 55.36

 1985 446.1 89.4 2,342 748 0.32 1.68

 1986 157.3 31.5 3,740 2,436 0.65 15.49

 1987 371.0 64.2 1,932 522 0.27 1.41

 1988 419.6 65.9 2,875 1,504 0.52 3.58

 1989 287.5 57.3 2,395 910 0.38 3.17

 1990 511.8 89.1 1,941 310 0.16 0.61

 1991 351.6 60.5 3,089 1,185 0.38 3.37

 1992 536.3 85.9 2,771 657 0.24 1.23

 1993 551.9 87.8 2,560 416 0.16 0.75

 1994 431.7 70.8 2,382 844 0.35 1.96

 1995 615.4 97.4 761 90 0.12 0.15

 1996 515.0 82.6 1,833 449 0.24 0.87

 1997 579.1 94.3 509 50 0.10 0.09

 1998 490.8 82.4 1,408 308 0.22 0.63
C-23

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

OYSTER CREEK 1999 615.1 100.0 466 42 0.09 0.07

(continued) 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

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

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, NPF-51, NPF-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 - 1243, 1243, 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

 2001 3,280.2 88.6 1,361 182 0.13 0.06

 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
C-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

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 - 1112, 1112 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

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 - 1235 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

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 ---
C-25

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

PILGRIM 1 1988 0.0 0.0 2,073 392 0.19 ---

(continued) 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

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

 2000 872.0 88.7 765 139 0.18 0.16

 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

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
C-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

PRAIRIE ISLAND 1, 2 1985 882.6 84.0 1,082 416 0.38 0.47

(continued) 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

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

 1995 1,002.5 70.4 2,041 736 0.36 0.73

 1996 876.6 60.1 2,248 1,025 0.46 1.17

 1997 935.3 66.5 2,474 654 0.26 0.70

 1998 794.8 55.1 2,177 761 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

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

12 Rancho Seco was shut down 6/89 and is no longer in the count of operating reactors. Parentheses indicate plant capacity when 

plant was operational.
C-27

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

RANCHO SECO12 1982 409.5 53.3 766 337 0.44 0.82

(continued) 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 ---

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 - 966 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

 2000 837.1 89.7 1,104 216 0.20 0.26

 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

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

12 Rancho Seco was shut down 6/89 and is no longer in the count of operating reactors. Parentheses indicate plant capacity when 

plant was operational.
C-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

ROBINSON 2 1988 385.0 65.9 1,351 564 0.42 1.46

(continued) 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

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 - 1096, 1116 MWe 1984 650.1 31.8 1,395 681 0.49 1.05

 1985 1,657.7 75.8 1,112 204 0.18 0.12

 1986 1,484.3 70.4 3,554 599 0.17 0.40

 1987 1,478.2 73.3 2,543 600 0.24 0.41

 1988 1,591.6 73.6 1,609 503 0.31 0.32

 1989 1,675.4 79.5 2,944 338 0.11 0.20

 1990 1,362.6 65.1 3,636 272 0.07 0.20

 1991 1,726.4 79.3 4,201 458 0.11 0.27

 1992 1,200.9 61.1 4,376 431 0.10 0.36

 1993 1,366.3 65.4 3,559 408 0.11 0.30

 1994 1,367.4 73.8 950 188 0.20 0.14

 1995 558.1 29.3 1,195 218 0.18 0.39

 1996 0.0 0.0 1,671 300 0.18 ---

 1997 279.3 17.8 894 175 0.20 0.63

 1998 1,629.3 79.1 408 41 0.10 0.03

 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

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, NPF-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), 1070, 1975 389.0 87.4 424 292 0.69 0.75

1080 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

13 San Onofre 1 was shut down 11/92 and is no longer in the count of operating reactors. Parentheses indicate plant capacity 

when plant was operational.
C-29

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

SAN ONOFRE 113, 2, 3 1982 61.6 15.7 3,055 832 0.27 13.51

(continued) 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

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, NPF-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 

Capacity - 1070, 1080 MWe 

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 - 1155 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

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 - 1125, 1126 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

13 San Onofre 1 was shut down 11/92 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-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

SEQUOYAH 1, 2 1992 1,849.0 85.4 1,714 465 0.27 0.25

(continued) 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

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 - 1251, 1251 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

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
C-31

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

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

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 - 810, 815 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

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; NPF-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 - 1105, 1140 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
C-32

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

SUSQUEHANNA 1, 2 1992 1,604.2 79.7 1,885 724 0.38 0.45

(continued) 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

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 - 786, (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

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 ---

14 Three Mile Island 1 resumed commercial power generation 10/85 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. Three Mile Island 2 no longer reports separately since 2001.
C-33

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

THREE MILE ISLAND 215 1996 0.0 0.0 122 2 0.02 ---

(continued) 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 --- ---

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 - (1080) 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 ---

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

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. Three Mile Island 2 no longer reports separately since 2001.

16 Trojan ended commercial operation as of 1/93, 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-34

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

TURKEY POINT 3, 4 1991 258.2 21.0 2,087 939 0.45 3.64

(continued) 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

 2001 1,324.1 95.0 827 102 0.12 0.08

 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

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 - 510 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

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 - 1152, 1149 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
C-35

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

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 - 1075 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

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 - 1121 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

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 - 1167 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

YANKEE ROWE17 1969 138.3 193 215 1.11 1.55

Docket 50-29; DPR-3 1970 146.1 355 255 0.72 1.75

1st commercial operation 7/61 1971 173.5 155 90 0.58 0.52

Type - PWR 1972 78.7 282 255 0.90 3.24

Capacity - (175) MWe 1973 127.1 133 99 0.74 0.78

 1974 111.3 243 205 0.84 1.84

 1975 145.1 82.4 249 116 0.47 0.80

 1976 152.2 89.8 152 59 0.39 0.39

 1977 124.6 73.9 725 356 0.49 2.86

 1978 145.0 81.0 565 282 0.50 1.94

 1979 149.0 81.6 441 127 0.29 0.85

17 Yankee Rowe ended commercial operation as of 10/91, 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-36

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

YANKEE ROWE17 1980 35.6 22.0 502 213 0.42 5.98

(continued) 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 ---

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 - (1040), (1040) MWe 1980 1,411.2 74.1 1,363 920 0.67 0.65

 1981 1,366.9 72.3 1,754 1,720 0.98 1.26

 1982 1,186.4 64.3 1,575 2,103 1.34 1.77

 1983 1,222.3 69.4 1,285 1,311 1.02 1.07

 1984 1,389.9 69.6 1,110 786 0.71 0.57

 1985 1,187.9 62.9 1,498 1,166 0.78 0.98

 1986 1,462.0 73.2 967 474 0.49 0.32

 1987 1,337.0 71.0 1,046 653 0.62 0.49

 1988 1,549.1 78.3 1,926 1,260 0.65 0.81

 1989 1,514.1 77.6 1,282 624 0.49 0.41

 1990 860.4 46.9 1,385 696 0.50 0.81

 1991 1,125.7 58.2 902 173 0.19 0.15

 1992 1,128.8 59.0 1,732 1,043 0.60 0.92

 1993 1,458.2 70.9 1,772 643 0.36 0.44

 1994 1,224.9 59.9 1,176 306 0.26 0.25

 1995 1,471.6 72.4 1,807 797 0.44 0.54

 1996 1,538.4 75.8 1,567 437 0.28 0.28

 1997 123.2 7.1 924 119 0.13 0.97

 1998 0.0 0.0 246 12 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 ---

17 Yankee Rowe ended commercial operation as of 10/91, 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 was shut down 12/97 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity 

when plant was operational.
D-1

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DOSE PERFORMANCE INDICATORS BY REACTOR SITE

1973 - 2003

Appendix D

NOTE: Appendix D only contains data on plants in operation during 2003.
D-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

ARKANSAS 1, 2

Dose-Performance Indicators

BEAVER VALLEY 1, 2

DOSE (Person-rem) DOSE (Person-rem)

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

Dose-Performance Indicators

197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR
D-3

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

500

1000

1500

2000

2500

3000

3500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

BRAIDWOOD 1, 2

Dose-Performance Indicators

BROWNS FERRY 1, 2, 3

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

198919901991199219931994199519961997199819992000200120022003

0

100

200

300

400

500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR
D-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

BRUNSWICK 1, 2

Dose-Performance Indicators

BYRON 1, 2

Dose-Performance Indicators

DOSE (Person-rem)

PWR

BWR

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

1000

2000

3000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

DOSE (Person-rem)
D-5

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

1985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

CALLAWAY 1

Dose-Performance Indicators

CALVERT CLIFFS 1, 2

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)
D-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

CATAWBA 1, 2

Dose-Performance Indicators

CLINTON

DOSE (Person-rem) DOSE (Person-rem)

Dose-Performance Indicators

1988198919901991199219931994199519961997199819992000200120022003

0

500

1000

0

200

400

600

800

1000

1200

MW-Yrs.

Year

MW-Years

BWR

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor
D-7

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1991199219931994199519961997199819992000200120022003

0

100

200

300

400

0

500

1000

1500

2000

2500

MW-Yrs.

Year

MW-Years

PWR

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

1985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

1400

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

COLUMBIA GENERATING

COMANCHE PEAK 1, 2

Dose-Performance Indicators

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)
D-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

COOK 1, 2

Dose-Performance Indicators

COOPER STATION

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)
D-9

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

19781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

200

400

600

800

1000

1200

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

19781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

250

500

750

1000

1250

MW-Yrs.

Year

MW-Years

PWR

CRYSTAL RIVER 3

Dose-Performance Indicators

DAVIS-BESSE

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor
D-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

DIABLO CANYON 1, 2

Dose-Performance Indicators

DRESDEN 2, 3

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

198619871988198919901991199219931994199519961997199819992000200120022003

0

100

200

300

400

500

600

700

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR
D-11

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

19781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

BWR

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

100

200

300

400

500

600

700

MW-Yrs.

Year

MW-Years

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

DUANE ARNOLD

Dose-Performance Indicators

FARLEY 1, 2

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)
D-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

FERMI 2

Dose-Performance Indicators

FITZPATRICK

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

198919901991199219931994199519961997199819992000200120022003

0

250

500

750

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

2500

3000

0

200

400

600

800

1000

MW-Yrs.

Year

MW-Years

BWR

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor
D-13

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FORT CALHOUN

Dose-Performance Indicators

PWR

GINNA

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

PWR

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

250

500

750

1000

0

250

500

750

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

250

500

750

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

GRAND GULF

Dose-Performance Indicators

PWR

HARRIS

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Yrs.

BWR

1988198919901991199219931994199519961997199819992000200120022003

0

250

500

750

0

200

400

600

800

1000

1200

MW-Yrs.

Year

MW-Years

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor
D-15

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

HATCH 1, 2

Dose-Performance Indicators

HOPE CREEK 1

Dose-Performance Indicators BWR

DOSE (Person-rem) DOSE (Person-rem)

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

19871988198919901991199219931994199519961997199819992000200120022003

0

250

500

750

1000

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years
D-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

PWR

INDIAN POINT 2

Dose-Performance Indicators

PWR

INDIAN POINT 3

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

1000

2000

3000

4000

5000

6000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

1979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

250

500

750

1000

1250

1500

1750

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-17

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

KEWAUNEE

Dose-Performance Indicators

BWR

LASALLE 1, 2

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

200

400

600

800

1000 MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

19841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years
D-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

LIMERICK 1, 2

Dose-Performance Indicators

PWR

MCGUIRE 1, 2

Dose-Performance Indicators

DOSE (Person-rem)

19871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

1982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-19

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

MILLSTONE UNIT 2, 3

Dose-Performance Indicators PWR

BWR

MONTICELLO

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

2500

3000

-500

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

2500

3000

3500

0

200

400

600

800

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years
D-20

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

BWR

NINE MILE POINT 1, 2

Dose-Performance Indicators

PWR

NORTH ANNA 1, 2

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

2500

0

200

400

600

800

1000

1200

1400

1600

1800

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

1979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-21

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

PWR

OCONEE 1, 2, 3

Dose-Performance Indicators

BWR

OYSTER CREEK

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

3000

3500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

2500

3000

3500

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years
D-22

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

PALISADES

Dose-Performance Indicators

PWR

PALO VERDE 1, 2, 3

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

250

500

750

1000

1250

1500

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

19871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

0

500

1000

1500

2000

2500

3000

3500

4000

4500

5000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-23

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

PEACH BOTTOM 2, 3

Dose-Performance Indicators BWR

PERRY

Dose-Performance Indicators

DOSE (Person-rem) DOSE (Person-rem)

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

2500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years
D-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

1000

2000

3000

4000

5000

6000

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

DOSE (Person-rem) DOSE (Person-rem)

PILGRIM

Dose-Performance Indicators

POINT BEACH 1, 2

Dose-Performance Indicators PWR

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

1400

1600

0

200

400

600

800

1000

1200

1400

MW-Yrs.

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-25

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DOSE (Person-rem) DOSE (Person-rem)

PWR

PRAIRIE ISLAND 1, 2

Dose-Performance Indicators

QUAD CITIES 1, 2

Dose-Performance Indicators BWR

197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

1000

2000

3000

4000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years
D-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

DOSE (Person-rem) DOSE (Person-rem)

RIVER BEND 1

Dose-Performance Indicators BWR

PWR

ROBINSON 2

Dose-Performance Indicators

19871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

2500

3000

3500

4000

4500

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-27

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DOSE (Person-rem) DOSE (Person-rem)

SALEM 1, 2

Dose-Performance Indicators PWR

PWR

SAN ONOFRE 1, 2, 3

Dose-Performance Indicators

19781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

MW-Years

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor
D-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

DOSE (Person-rem) DOSE (Person-rem)

SEABROOK

Dose-Performance Indicators

Year

PWR

PWR

SEQUOYAH 1, 2

Dose-Performance Indicators

1991199219931994199519961997199819992000200120022003

0

100

200

300

400

500

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

1982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

MW-Years

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor
D-29

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DOSE (Person-rem) DOSE (Person-rem)

SOUTH TEXAS 1, 2

Dose-Performance Indicators PWR

PWR

ST. LUCIE 1, 2

Dose-Performance Indicators

198919901991199219931994199519961997199819992000200120022003

0

100

200

300

400

500

0

500

1000

1500

2000

2500

3000

3500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-30

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

DOSE (Person-rem) DOSE (Person-rem)

SUMMER 1

Dose-Performance Indicators PWR

PWR

SURRY 1, 2

Dose-Performance Indicators

19841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

2500

3000

3500

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-31

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DOSE (Person-rem) DOSE (Person-rem)

SUSQUEHANNA 1, 2

Dose-Performance Indicators BWR

PWR

THREE MILE ISLAND 1*

Dose-Performance Indicators

* Graph includes data for Three Mile Island 2 for the years 1975 - 1985.

19841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

1000

1200

0

200

400

600

800

1000

1200

1400

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-32

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 

DOSE (Person-rem) DOSE (Person-rem)

TURKEY POINT 3, 4

Dose-Performance Indicators PWR

BWR

VERMONT YANKEE

Dose-Performance Indicators

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000200120022003

0

500

1000

1500

2000

2500

0

200

400

600

800

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years
D-33

Thirty-Sixth Annual Report, 2003 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DOSE (Person-rem) DOSE (Person-rem)

VOGTLE 1, 2

Dose-Performance Indicators PWR

WATERFORD 3

Dose-Performance Indicators PWR

1988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

0

500

1000

1500

2000

2500

3000

3500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

800

0

200

400

600

800

1000

1200

1400

1600

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
D-34

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Sixth Annual Report, 2003

NUREG-0713 DOSE (Person-rem) DOSE (Person-rem)

PWR

WATTS BAR 1

Dose-Performance Indicators

WOLF CREEK 1

Dose-Performance Indicators PWR

19961997199819992000200120022003

0

100

200

300

400

500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

198619871988198919901991199219931994199519961997199819992000200120022003

0

200

400

600

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years
BIBLIOGRAPHIC DATA SHEET

(See instructions on the reverse)

NRC FORM 335

(9-2004)

NRCMD 3.7

U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER

 (Assigned by NRC, Add Vol., Supp., Rev.,

 and Addendum Numbers, if any.)

NUREG-0713

Volume 25

3. DATE REPORT PUBLISHED

MONTH

October

YEAR

2004

4. FIN OR GRANT NUMBER

N6081

2. TITLE AND SUBTITLE

Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities

2003

Thirty-Sixth Annual Report

5. AUTHOR(S)

S. A. Burrows D.A. Hagemeyer*

6. TYPE OF REPORT

Final

7. PERIOD COVERED (Inclusive Dates)

01/01/03-12/31/03

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address; if contractor,

Division of Systems Analysis and Regulatory Effectiveness * Oak Ridge Associated Universities

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC, type "Same as above"; if contractor, provide NRC Division, Office or Region, U.S. Nuclear Regulatory Commission, 

Same as 8. above

provide name and mailing address.)

and mailing address.)

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 words or less)

This report summarizes the 2003 occupational radiation exposure data that are maintained in the U.S. Nuclear Regulatory

Commission's (NRC's) Radiation Exposure Information and Reporting System (REIRS) database. The bulk of the information

contained in the report was compiled from the 2003 annual reports submitted by five of the seven categories of NRC licensees

subject to the reporting requirements of 10 CFR 20.2206. Annual Reports of occupationsl radiation exposure for 2003 were

received from 223 NRC licensees, of which 104 were operators of nuclear power plants in commercial operation.

12. KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.)

occupational

radiation

exposure

dose

REIRS

14. SECURITY CLASSIFICATION

13. AVAILABILITY STATEMENT

unlimited

(This Page)

unclassified

(This Report)

unclassified

15. NUMBER OF PAGES

16. PRICE

NRC FORM 335 (9-2004) PRINTED ON RECYCLED PAPER

Office of Nuclear Regulatory Research 210 Badger Road

U. S. Nuclear Regulatory Commission Oak Ridge, TN 37830

Washington, DC 20555-0001
Printed 

on recycled 

paper

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