Occupational Radiation

Exposure at Commercial

Nuclear Power Reactors

and Other Facilities

2004

NUREG-0713

Vol. 26

Thirty-Seventh Annual Report

U.S. Nuclear Regulatory Commission

Office of Nuclear Regulatory Research

Washington, DC 20555-0001 UN TI ED STATES NUCLEAR REGULATORY COMM SI S OI N


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

NUREG-0713

UN

TI ED STATES

NUCLEAR REGULATORY COMM SI S

OI N

Occupational Radiation Exposure

at Commercial Nuclear Power

Reactors and Other Facilities

2004

NUREG-0713

Vol. 26

Thirty-Seventh 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: November 2005

Date Published: November 2005

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-Seventh Annual Report, 2004

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.

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

Nuclear Regulatory Commission, October 2004.

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

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

NUREG-0713

abstract

1

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

reprocessors; manufacturers and distributors of 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’s) Radiation Exposure Information and Reporting System

(REIRS). The bulk of the information contained in the report was compiled from the 2004 an‐

nual reports submitted by five of the seven categories1 of NRC licensees subject to the reporting

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

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

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

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

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

ered in this report. 

Annual reports for 2004 were received from a total of 227 NRC licensees, of which 104 were op‐

erators of nuclear power reactors in commercial operation. Compilations of the reports submitted

by the 227 licensees indicated that 123,332 individuals were monitored, 61,060 of whom received

a measurable dose (Table 3.1). The collective dose incurred by these individuals was 12,774

person-rem, which represents a 12% decrease from the 2003 value. The number of workers

receiving a measurable dose decreased, resulting in an average measurable dose of 0.21 rem for

2004. The average measurable dose is defined as the total collective dose (TEDE) divided by the 

number of workers receiving a measurable dose.2 The figures for commercial reactors have been 

adjusted to account for transient reactor workers.

In calendar year 2004, the annual collective dose per reactor for light water reactor (LWR) licens‐

ees was 100 person-rem. This represents a 13% decrease from the value reported for 2003

(115). The annual collective dose per reactor for boiling water reactors (BWRs) was 156 personrem, and, for pressurized water reactors (PWRs), it was 71 person-rem.

Analyses of transient worker data indicate that 24,251 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 2004, the aver‐

age measurable dose per worker for all licensees calculated from reported data was 0.16 rem. 

The corrected dose distribution resulted in an average measurable dose per worker for all licens‐

ees of 0.21 rem.
iv

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

NUREG-0713

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

the Office of Nuclear Reactor Regulation technical reviewer. The NRC 

welcomes responses from readers.

Comments should be directed to:

	 Sheryl Burrows: (301) 415-6086

	 E-Mail Address: sab2@nrc.gov

	 REIRS Project Manager

Office of Nuclear Regulatory Research

	 U.S. Nuclear Regulatory Commission

	 Washington, DC 20555

EDITOR’S NOTE
Thirty-Seventh Annual Report, 2004 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
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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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..................................................................... 6-6

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

APPENDIX A ‐ ANNUAL TEDE FOR NON-REACTOR NRC LICENSEES, 2004 ........................A‐1

APPENDIX B ‐ ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES, 2004.............................................................................................................B‐1

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

1969 - 2004......................................................................................................................................C‐1

APPENDIX D ‐ DOSE PERFORMANCE INDICATORS BY REACTOR SITE,

1973 - 2004......................................................................................................................................D‐1

table of contents (Continued)

Page
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Thirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

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Figure 3.1	 Average Annual Values at Industrial Radiography Facilities, 1973 - 2004............... 3-9

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

Single Location Licensees, 2000 - 2004 ................................................................. 3-10

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

Multiple Location Licensees, 2000 - 2004............................................................... 3-10

Figure 3.4	 Average Annual Values at Manufacturing and Distribution

Facilities, 1973 - 2004.............................................................................................. 3-12

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

Manufacturing and Distribution Licensees, 2000 - 2004......................................... 3-13

Figure 3.6	 Collective TEDE Distribution by Dose Range, Limited

Manufacturing and Distribution Licensees, 2000 - 2004......................................... 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 - 2004.............................................................................................. 3-16

Figure 3.9	 Collective TEDE Distribution by Dose Range, Independent Spent

Fuel Storage Licensees, 2000 - 2004 ..................................................................... 3-17

Figure 3.10	 Average Annual Values at Fuel Cycle Licensees, 1973 - 2004.............................. 3-19

Figure 3.11	 Collective TEDE Distribution by Dose Range, Fuel Cycle

Licensees, 2000 - 2004 ........................................................................................... 3-20

Figure 3.12	 Collective TEDE Distribution by Dose Range, Reactor

Licensees, 2000 - 2004 ........................................................................................... 3-21

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

per Reactor, 1973 - 2004........................................................................................... 4‐9

Figure 4.2	 Number of Operating Reactors and Gross Electricity

Generated, 1973 - 2004........................................................................................... 4‐10

list of figures

Page
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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Figure 4.3	 Average Measurable Dose per Worker and Collective Dose per

Megawatt-Year, 1973 - 2004.....................................................................................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 - 2004 ............................................................................... 4‐14

list of FIGUREs (Continued)

Table 3.1	 Average Annual Exposure Data for Certain Categories of

NRC Licensees, 1995 - 2004 .................................................................................... 3‐3

Table 3.2	 Distribution of Annual Collective TEDE by License

Category, 2004........................................................................................................... 3-5

Table 3.3	 Summary of Annual Dose Distributions for Certain NRC

Licensees, 1968 - 2004 ............................................................................................. 3‐6

Table 3.4	 Annual Exposure Information for Industrial

Radiographers, 2002 - 2004...................................................................................... 3‐7

Table 3.5	 Annual Exposure Information for Manufacturers and

Distributors, 2002 - 2004...........................................................................................3‐11

Table 3.6	 Annual Exposure Information for Fuel Cycle Licenses, 2002 - 2004 ..................... 3‐18

Table 3.7	 Intake by Licensee Type and Radionuclide

Mode of Intake - Ingestion and Other, 2004............................................................ 3‐23

Table 3.8	 Intake by Licensee Type and Radionuclide

Mode of Intake - Inhalation, 2004............................................................................ 3‐24

Table 3.9	 Collective and Average CEDE by Licensee, 2004.................................................. 3‐26

Table 3.10	 Internal Dose (CEDE) Distribution, 1994 - 2004..................................................... 3‐27

list of tables

Page
ix

Thirty-Seventh Annual Report, 2004 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 - 2004......................................................................... 4‐2

Table 4.2	 Summary of Information Reported by Commercial

Pressurized Water Reactors, 1973 - 2004................................................................ 4‐3

Table 4.3	 Summary of Information Reported by Commercial

Light Water Reactors, 1973 - 2004............................................................................ 4‐4

Table 4.4	 Summary Distribution of Annual Whole Body Doses at

Commercial Light Water Reactors, 1977 - 2004....................................................... 4‐7

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

of Collective TEDE per BWR, 2002 - 2004 ............................................................. 4‐15

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

of Collective TEDE per PWR, 2002 - 2004 ............................................................. 4‐16

Table 5.1	 Effects of Transient Workers on Annual Statistical Compilations, 2004................... 5-2

Table 6.1	 Occupational Exposures in Excess of Regulatory Limits, 1994 - 2004.................... 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, 2004 ................. 6-6

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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
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foreword

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

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

the safety performance of the agency’s licensees. Toward that end, NUREG-0713, Volume

26, summarizes the 2004 occupational radiation exposure data maintained in 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 Title 10,

Section 20.2206, of the Code of Federal Regulations (10 CFR 20.2206). Specifically, these 

categories 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 the NRC

has not yet licensed any geologic repositories for high-level waste, and no NRC-licensed lowlevel waste disposal facilities are currently in operation, this report considers only the first five 

categories of NRC licensees. As such, this report reflects the occupational radiation exposure 

data that the NRC received from 227 licensees, of which 104 were operators of nuclear power

reactors in commercial operation.

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

individual. (In 2004, 123,332 individuals were monitored, and 61,060 received a measurable

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

distribution of dose among the monitored individuals. During 2004, these individuals incurred

a collective dose of 12,774 person-rem, which represents a 12% decrease from the 2003 value

of 14,567 person-rem. The average measurable dose was 0.21 rem which represents a 9%

decrease from the 2003 value of 0.23 rem. (The average measurable dose is the total collective

dose divided by the number of workers receiving a measurable dose.) This value can be

compared to the 0.30 rem that the average person in the United States receives annually from

natural background radiation. Worldwide annual exposures to natural radiation are generally

expected to be in the range of 0.1 rem to 1.0 rem, with 0.24 rem being the current average

worldwide value.

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

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

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

this report as one of the metrics of the agency’s Reactor Oversight Program to evaluate the

effectiveness of licensees’ ALARA programs.

	 	 	 	 	 	 Carl J. Paperiello, Director

Office of Nuclear Regulatory Research

	 	 	 	 	 	 U.S. Nuclear Regulatory Commission 
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INTRODUCTION

Section 1

1.1 background

One of the basic purposes of the Atomic Energy 

Act and the implementing regulations in Title 10, 

Code of Federal Regulations (CFR), Chapter I, 

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

public, including the employees of the licensees 

conducting operations under those regulations. 

Among the regulations designed to ensure that 

the standards for protection against radiation 

set out in 10 CFR 20 are met is a requirement 

that licensees provide individuals likely to be 

exposed to radiation with devices to monitor 

their 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 and are 

now maintained at the Oak Ridge Institute 

for Science and Energy (ORISE), which is 

managed by Oak Ridge Associated Universities 

(ORAU). 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-

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

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, since 

there are no geologic repositories for high‐level 

waste currently licensed.

This report and each of the predecessors 

summarize information reported for both the 

current year and 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 (after 1993) and their 

technical specifications (prior to Volume 20 of 

this report), may be found in those documents 

listed on the inside of the front cover of this 

report for the specific year desired. Additional 

operating data and statistics for each power 

reactor for the years 1973 through 1982 may 

be found in a series of reports, “Nuclear Power 

Plant Operating Experience” [Refs. 1‐9]. 

These documents are available for viewing at 

all NRC public document rooms, as well as on 

the NRC public web site (www.nrc.gov), or they 

may be purchased from the National Technical 

Information Service, as shown in the 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 submitting summary 

annual reports (§ 20.407) and termination 

reports (§ 20.408), licensees are now required 

to submit an annual report of the dose received 

by each monitored worker (§ 20.2206). 

Licensees were required to implement the new 

requirements no later than January 1994.

Recommendations for further analysis or 

for different presentation of information are 

welcome. 
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1.2 Radiation Exposure

Information on the

Internet

In May 1995, the NRC began pursuing the 

dissemination of radiation exposure information 

via a web site on the Internet. This 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, a software 

application designed to maintain licensee 

exposure records, and REIRView, a software 

package designed to validate a licensee’s 

annual data submittal, are also available for 

downloading via the web site. There are also 

links to other web sites dealing with the topics 

of radiation and health physics. Individuals 

and organizations may also submit requests for 

dose records contained in REIRS on this web 

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

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Another fact that should be kept in mind when 

examining the annual statistical data is that 

all of the personnel included in the report may 

not have been monitored throughout the entire 

year. Many licensees, such as radiography 

firms and nuclear power facilities, may monitor 

numerous individuals for periods much less 

than a year. The average doses calculated from 

these data, therefore, are less than the average 

dose that an individual involved in that activity 

for the full year would receive. 

Considerable attention should be paid when 

referencing the collective totals presented 

in this report. The differences between the 

totals presented for all licensees that reported 

versus only those licensees that are required to 

report should be noted. Likewise, one should 

distinguish between the doses attributed 

to the pressurized water reactors (PWRs) 

and the doses attributed to boiling water 

reactors (BWRs). The totals may be inclusive 

or exclusive of those licensees that were in 

commercial operation for less than one full year. 

These parameters vary throughout the tables 

and appendices of this report. The apparent 

discrepancies among the various tables are a 

necessary side effect of this endeavor.

The data contained in this report are subject to 

change as licensees may submit corrections 

or additions to data for previous years. For 

the 2004 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 

byproduct 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 are licensed by the NRC. In addition, this 

report does not include compilations of nonoccupational exposure, such as exposure 

due to medical X-rays, fluoroscopy, and 

accelerators, received by patients. 

All dose equivalent values in this report are 

given in units of rem in accordance with 

the general provisions for records, 10 CFR 

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

International System of Units (SI) unit of sieverts 

(Sv), 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.
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ANNUAL PERSONNEL MONITORING 

REPORTS ‐ 10 CFR 20.2206

Section 3

3.1 Definition of Terms

and Sources of Data

3.1.1 Statistical Summary Reports

The total effective dose equivalent (TEDE) 

is summed per individual and tabulated into 

the appropriate dose range to generate the 

dose distribution for each licensee. The total 

collective dose is more accurate using this 

method because the licensee reported the dose 

to each individual, and the total collective dose 

was calculated from the sum of these doses 

and not statistically derived from the 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 
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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comparing the actual collective dose calculated 

for 1994 to 2004 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 collective doses for 

1994 and later with the collective dose for years 

prior to 1994. One noted exception is for fuel 

fabrication licensees where the CEDE in some 

cases contributes the majority of the TEDE 

(see Section 3.3.5).

3.1.5 Average Individual Dose

The average individual dose is obtained by 

dividing the collective dose by the total number 

of workers reported as being monitored. 

This figure is usually less than the average 

measurable dose because it includes the 

number of those workers who received zero or 

less than measurable doses.

3.1.6 Average Measurable Dose

The average measurable dose is obtained by 

dividing the collective TEDE by the number 

of workers who received a measurable dose. 

This is the average most commonly used 

in this and other reports when examining 

trends and comparing doses received by 

workers in various segments of the nuclear 

industry because it deletes those workers 

receiving zero or no detectable dose, many 

of whom were monitored for convenience or 

identification purposes.

3.1.7 Number of Licensees Reporting

The number of licensees refers to the NRC 

licenses issued to use radioactive material for 

certain activities that would place the licensees 

in one of the seven6 categories that are required 

to report pursuant to 10 CFR 20.2206. The 

third column in Table 3.1 shows the number of 

licensees that have filed such reports during 

the last 10 years. All nuclear power plants, fuel 

processors and fabricators, and independent 

spent fuel storage facilities are required to 

report occupational exposure to the NRC, 

whether 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's) 

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.
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TABLE 3.1

Average Annual Exposure Data for Certain Categories of NRC Licensees

1995-2004

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)

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 107 2,918 2,541 1,632 0.56 0.64

2004 93 3,192 2,766 1,567 0.49 0.57

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 31 2,146 1,668 420 0.20 0.25

2004 21 2,251 1,580 324 0.14 0.21

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 

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

2004 1 37 27 1 0.03 0.05

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

2004 8 7,562 3,814 514 0.07 0.13

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

2004 104 110,290 52,873 10,368 0.09 0.20

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 252 122,847 63,855 14,567 0.12 0.23

2004 227 123,332 61,060 12,774 0.10 0.21

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

to the NRC.

** 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.

*** Includes all LWRs in commercial operation for a full year for each of the years indicated. Reactor data have been corrected to account for the

multiple counting of transient reactor workers (see Section 5).

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

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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, 3.9, 3.11, and 3.12 

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 percent of the reported workers 

with measurable doses were monitored by 

nuclear power facilities in 2004, where they 

received 81% 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 14 years, the 

percentage of workers with <2 rem has been 

greater than 99%. The number of workers 

receiving an annual exposure in excess of 

5 rem has been <0.01% since 1985. No 

individual received a dose above the 5 rem 

annual TEDE limit in 2004 (see Section 6).
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TABLE 3.2

Distribution of Annual Collective TEDE by License Category

2004

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)

101 34 7 4 146 45 3.145325 751 450 454 319 235 377 98 30 7 0 3,046 2,721 1,564.355426 785 457 458 319 235 377 98 30 7 0 3,192 2,766 1,567.500109 117 59 63 32 17 37 14 448 339 157.680562 885 215 77 23 8 22 6 4 1 1,803 1,241 166.193671 1,002 274 140 55 25 59 20 4 1 2,251 1,580 323.873

10 22 4 1 37 27 1.257

3,748 2,493 716 324 149 91 41 7,562 3,814 513.725

26,043 19,678 7,101 4,546 1,690 572 353 8 59,991 33,948 5,450.98254,430 21,905 8,525 3,699 1,043 406 315 8 90,331 35,901 4,916.91580,473 41,583 15,626 8,245 2,733 978 668 16 150,322 69,849 10,367.89785,328 45,885 17,077 9,168 3,256 1,329 1,145 134 34 8 163,364 78,036 12,774.252

 INDUSTRIAL RADIOGRAPHY Single Location (12) Multiple Location (81)

Total (93)

 MANUFACTURING AND DISTRIBUTION "A" - Broad (3) Limited (18)

Total (21)

 LOW-LEVEL WASTE DISPOSAL

Total (0)**

 INDEPENDENT SPENT FUEL STORAGE

Total (1)

 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 2004. These values have not been adjusted for the multiple counting of transient reactor workers (see Section 5).
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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1968 36,836 97.2% 99.5% 3

1969 31,176 96.5% 99.5% 7

1970 36,164 96.1% 99.4% 0

1971 36,311 96.3% 99.3% 1

1972 44,690 95.7% 99.5% 8

1973 67,862 95.0% 99.5% 1

1974 85,097 96.4% 99.7% 1

1975 78,713 94.8% 99.5% 1

1976 92,773 95.0% 99.6% 3

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

2003 164,993 121,265 99.7% (414) >99.99% (1) 1

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

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 1977-2004 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 1985-2004.

TABLE 3.3

Summary of Annual Dose Distributions for Certain* NRC Licensees

1968-2004

Total Number of Monitored 

Persons

** *** *** ***
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TABLE 3.4

Annual Exposure Information for Industrial Radiographers

2002-2004

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

15

85

100

12

95

107

12

81

93

112

3,308

3,420

97

2,821

2,918

146

3,046

3,192

55

2,787

2,842

45

2,496

2,541

45

2,721

2,766

4

1,725

1,729

4

1,725

1,729

3

1,564

1,567

0.08

0.62

0.61

0.07

0.65

0.64

0.07

0.57

0.57

2002

2003

2004

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 

93 radiography licensees in 2004. Table 3.4 

summarizes the reported data for the two types 

of radiography licenses for 2004 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 12% 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 2004.

High exposures in radiography can be directly 

attributable to the type and location of the 

radiography field work. For example, locations 

such as oil drilling platforms and aerial tanks 

offer the radiographer little available shielding. 

In these situations, there may not be an 

opportunity to use distance as a means of 

minimizing exposure and achieving doses 

as low as reasonably achievable (ALARA). 
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NUREG-0713

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.

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 2004. The number of workers with 

measurable TEDE per licensee increased from 

2003 to 2004, and the average measurable 

TEDE decreased by 10% from 0.64 rem in 

2003 to 0.57 rem in 2004. Figures 3.2 and 3.3 

show the collective dose distribution by dose 

range (see Section 3.1.8) for single location and 

multiple location radiography licensees. These 

graphs demonstrate that multiple location 

licensees consistently have individuals receiving 

doses in the higher dose ranges and routinely 

have 25% to 40% of the collective dose 

delivered to individuals above 2 rem. From 

2000 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 3 years, the percentage of the collective 

dose delivered in each dose range above 0.50 

rem was less than the value in 2001. For single 

location licensees, the percentage of individuals 

in all dose ranges decreased for the second 

year in a row 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.
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Thirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 3.1. Average Annual Values at Industrial Radiography Facilities 1973-2004
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

NUREG-0713

FIGURE 3.2. Collective TEDE Distribution by Dose Range

Industrial Radiographer–Single Location Licensees

2000 - 2004

FIGURE 3.3. Collective TEDE Distribution by Dose Range

Industrial Radiographer–Multiple Location Licensees

2000 - 2004
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Thirty-Seventh Annual Report, 2004 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 

2004 and the previous 2 years. Looking at 

the information shown separately for the Type 

A Broad and Limited licensees, one can see 

that the values of collective and average 

measurable dose generally remain higher for 

the Broad licensees. However, to examine 

trends in the data presented for this category of 

licensees, it should be noted that the types and 

quantities of radionuclides may fluctuate from 

year to year, and even during the year. For this 

reason, some licensees may report dose data 

one year and not the next and may be included 

as a 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 2004, 

the same as in 2002 and 2003.

Figure 3.4 shows the number of workers 

with measurable dose per licensee, the total 

collective dose per licensee, and the average 

measurable dose per worker for both Type 

A Broad and Limited Manufacturing and 

Distribution facilities. Although the number of 

workers with measurable dose per licensee 

has been steadily increasing since 1999, the 

collective TEDE per licensee has remained 

relatively level during this same time period. 

The figures for Type A Broad licensees are 

primarily attributed to Mallinckrodt Medical, 

Inc., which accounted for 97% of the collective 

dose for this category of licensee in 2004. 

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 2000, 55% of the 

collective dose was received by individuals 

above 2 rem. In 2004, this percentage 

TABLE 3.5

Annual Exposure Information for Manufacturers and Distributors

2002-2004

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

2002

2004

3

26

29

3

28

31

3

18

21

334

1,103

1,437

438

1,708

2,146

448

1,803

2,251

247

805

1,052

349

1,319

1,668

339

1,241

1,580

197

131

328

229

191

420

158

166

324

0.80

0.16

0.31

0.66

0.14

0.25

0.47

0.13

0.21

2003
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

NUREG-0713

FIGURE 3.4. Average Annual Values at Manufacturing and Distribution Facilities

1973-2004
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NUREG-0713

FIGURE 3.5. Collective TEDE Distribution by Dose Range

Type “A” Broad Manufacturing and Distribution Licensees

2000 - 2004

FIGURE 3.6. Collective TEDE Distribution by Dose Range

Limited Manufacturing and Distribution Licensees

2000 - 2004
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

NUREG-0713

decreased for the fifth consecutive year to 22%. 

Limited licensees exhibit a distribution of the 

collective dose where individuals below 0.50 

rem receive over 50% of the collective dose.

 

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 2004.

3.3.3 Low-Level Waste Disposal Licenses

Low-Level Waste Disposal licenses are 

issued to allow the receipt, possession, and 

disposal of low-level radioactive wastes at a 

land disposal facility. The licensee has the 

appropriate facilities to receive wastes from 

such places as hospitals and laboratories, 

store them for a short time, and dispose of 

them in a properly prepared burial ground. The 

licensees in this category are located in and 

licensed by Agreement States, which have 

primary regulatory authority over the licensees’ 

activities. Since 1999, all licensees that have 

conducted these activities have been located 

in Agreement States; therefore, there are no 

licensees reporting radiation exposure data 

to REIRS. Figure 3.7 shows the number of 

workers with measurable dose per licensee, 

the total collective dose per licensee, and 

the average measurable dose per worker for 

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.

Thirty-four licenses were authorized to conduct 

these activities during 2004. Nine of these 

licenses are for activities involving cask 

design and storage systems. Twenty-three 

are located at nuclear power plants allowing 

on-site temporary storage of fuel. These 

twenty-three licensees report the dose from 

fuel storage activities along with the dose from 

reactor operations at these sites. 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 

GE Morris facility reported and is included in 

the 2004 data for this licensee category in this 

report. Appendix A summarizes the exposure 

information reported by this licensee.
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NUREG-0713

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

1982-1998

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

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

NUREG-0713

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

1982-2004
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Thirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 3.9. Collective TEDE Distribution by Dose Range

Independent Spent Fuel Storage Licensees

2000 - 2004

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 2004. The number 

of workers with measurable dose per licensee 

increase in 2004 since only one licensee 

reported. Figure 3.9 shows the collective 

dose distribution by dose range (see Section 

3.1.8) for ISFSI licensees from 2000 to 2004. 

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

NUREG-0713

TABLE 3.6

Annual Exposure Information for Fuel Cycle Licenses

2002-2004

2002 Fuel Cycle 8 7,937 3,886 661 0.17 3,021 296 0.10 2,404 365 0.15

2003 Fuel Cycle 8 7,738 3,633 556 0.15 2,815 258 0.09 2,255 298 0.13

2004 Fuel Cycle 8 7,562 3,814 514 0.13 2,933 258 0.09 2,327 256 0.11

Year

Type of

License

Number

of

Licensees

Number of

Monitored

Individuals

Workers

with

Meas.

TEDE

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rem)

Collective

DDE

(personrem)

Average

Meas.

DDE

(rem)

Collective

CEDE

(personrem)

Average

Meas.

CEDE

(rem)

Workers

with

Meas.

DDE

Workers

with

Meas.

CEDE

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 2004, 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 2000 to 2004. The percentage of the 

collective dose above each dose range 

increased in almost every dose range from 

2000 to 2001. However, from 2001 to 2004, 

there was a 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. As shown in Table 

3.6, the collective DDE remained the same 

between 2003 and 2004, while the collective 

CEDE decreased by 14%. 

Appendix A lists each of the licensees reporting 

in 2004, 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 2004.
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NUREG-0713 FIGURE 3.10. Average Annual Values at Fuel Cycle Licensees 1973-2004
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

NUREG-0713

FIGURE 3.11. Collective TEDE Distribution by Dose Range

Fuel Cycle Licensees

2000 - 2004

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 

1995 through 2004. The values do not include 

reactors that have been permanently shut down 

or reactors that have not been in commercial 

operation for a full year. The figures for reactors 

have been adjusted for the multiple counting of 

transient workers (see Section 5).

The reported dose distribution of workers 

monitored at each plant site for the year 2004 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 2000 to 2004. The 

distribution of collective dose has been fairly 

constant over the past 5 years, with a slight 

decrease noted from 2002 to 2004 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.
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Thirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 3.12. Collective TEDE Distribution by Dose Range

Reactor Licensees

2000-2004
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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 2004. 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 

(93%) in 2004 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 2004 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.
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Thirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.7

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

2004

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries**

Collective

Intake in

Microcuries

Mode (sci. notation)

Ingestion Power Reactors 41111 AM-241 5 0.000 3.28E-04

41111 CM-242 5 0.000 1.26E-06

41111 CM-243 5 0.000 1.13E-04

41111 CO-58 4 0.119 1.19E-01

41111 CO-60 6 0.778 7.78E-01

41111 CS-137 4 0.011 1.12E-02

41111 PU-238 5 0.000 2.29E-04

41111 PU-239 5 0.000 7.79E-05

41111 PU-241 5 0.003 3.44E-03

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

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

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

10 CFR 20.2206.

** A microcurie is one millionth of a Curie.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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TABLE 3.8

Intake by Licensee Type and Radionuclide Mode of Intake – Inhalation

2004

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries**

Collective

Intake in

Microcuries

(sci. notation)

Radiopharmaceutical 02500 I-123 D 32 7.436 7.44E+00

02500 I-131 D 3 0.077 7.70E-02

02500 I-131 W 130 47.811 4.78E+01

03211 I-131 D 4 0.000 1.77E-06

Uranium Enrichment 21200 NP-237 W 2 0.000 2.11E-05

21200 TC-99 D 1 2.140 2.14E-00

21200 TH-230 W 9 0.000 8.13E-05

21200 U-234 D 41 0.042 4.20E-02

Fuel Fabrication 21210 AM-241 M 166 0.000 1.29E-04

21210 CO-58 Y 2 0.246 2.46E-01

21210 CO-60 Y 48 0.268 2.68E-01

21210 PU-239 M 175 0.001 5.19E-04

21210 RA-224 M 166 0.001 6.50E-04

21210 RN-220 D 112 2,340.972 2.34E+03

21210 TH-228 M 192 0.001 7.88E-04

21210 TH-228 S 54 0.000 2.15E-04

21210 TH-232 M 166 0.001 9.75E-04

21210 U-232 F 55 0.000 9.02E-05

21210 U-232 S 71 0.000 2.80E-04

21210 U-232 Y 273 0.000 3.76E-04

21210 U-234 D 229 0.217 2.17E-01

21210 U-234 F 243 0.129 1.29E+01

21210 U-234 M 305 0.058 5.80E-02

21210 U-234 S 1,561 4.801 4.80E+00

21210 U-234 W 80 0.053 5.32E-02

21210 U-234 Y 1,042 3.686 3.69E+00

21210 U-235 D 191 0.005 5.24E-03

21210 U-235 F 55 0.000 2.59E-04

21210 U-235 M 32 0.000 5.52E-05

21210 U-235 S 932 0.157 1.57E-01

21210 U-235 W 80 0.002 2.00E-03

21210 U-235 Y 328 0.068 6.80E-02

21210 U-236 D 191 0.000 2.17E-04

21210 U-236 F 55 0.004 3.88E-03

21210 U-236 M 32 0.001 6.90E-04

21210 U-236 S 304 0.016 1.65E-02

21210 U-236 W 80 0.000 8.30E-05

21210 U-236 Y 328 0.022 2.19E-02

21210 U-238 D 229 0.032 3.23E-02

21210 U-238 F 98 0.000 9.66E-05

21210 U-238 M 240 0.002 2.32E-03

21210 U-238 S 818 0.490 4.90E-01

21210 U-238 W 80 0.007 7.32E-03

21210 U-238 Y 1,042 0.553 5.53E-01

Pulmonary

Clearance

Class

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

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

records given here indicates the number of separate intake reports that were submitted on NRC Form 5 reports under 10 CFR 20.2206.

** A microcurie is one millionth of a Curie.
3-25

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

NUREG-0713

TABLE 3.8 (continued)

Intake by Licensee Type and Radionuclide Mode of Intake – Inhalation

2004

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries**

Collective

Intake in

Microcuries

(sci. notation)

Power Reactors 41111 AM-241 W 92 0.001 9.68E-04

41111 AM-241 Y 1 0.461 4.61E-01

41111 BA-140 D 1 0.270 2.70E-01

41111 CM-242 W 79 0.000 2.86E-04

41111 CM-243 W 83 0.001 6.86E-04

41111 CO-58 Y 51 695.413 6.95E+02

41111 CO-58 Y 5 0.387 3.87E-01

41111 CO-60 Y 82 710.072 7.10E+02

41111 CO-60 W 1 0.078 7.80E-02

41111 CO-60 Y 13 1.035 1.03E+00

41111 CS-134 D 2 0.186 1.86E-01

41111 CS-137 D 47 4.632 4.63E+00

41111 CS-137 Y 4 0.117 1.17E-01

41111 CS-137 D 1 0.008 8.00E-03

41111 FE-55 D 7 5.306 5.31E+00

41111 FE-55 W 2 0.661 6.61E-01

41111 FE-59 D 1 0.110 1.10E-01

41111 FE-59 W 1 0.220 2.20E-01

41111 H-3 D 22 29.880 2.99E+01

41111 H-3 V 3 347.002 3.47E+02

41111 I-130 D 1 0.021 2.13E-02

41111 I-131 D 106 5.074 5.07E+00

41111 I-132 D 1 0.222 2.22E-01

41111 I-133 D 2 0.634 6.34E-01

41111 MN-54 W 22 1.158 1.16E+00

41111 MN-54 Y 2 912.000 9.12E+02

41111 NB-95 W 1 0.044 4.36E-02

41111 NB-95 Y 1 0.011 1.11E-02

41111 NI-63 W 2 0.627 6.27E-01

41111 NP-237 W 1 0.000 2.02E-08

41111 NP-239 W 1 0.000 4.20E-09

41111 PU-238 W 12 0.000 2.28E-04

41111 PU-238 Y 71 0.001 1.04E-03

41111 PU-239 W 9 0.000 5.83E-05

41111 PU-239 Y 69 0.000 4.27E-04

41111 PU-240 W 1 0.000 1.40E-04

41111 PU-240 Y 2 0.000 4.21E-06

41111 PU-241 W 8 0.002 2.27E-03

41111 PU-241 Y 14 0.003 3.50E-03

41111 SR-90 D 3 0.000 1.43E-04

41111 ZN-65 Y 6 0.638 6.38E-01

41111 ZR-95 W 2 0.143 1.43E-01

Pulmonary

Clearance

Class

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

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

records given here indicates the number of separate intake reports that were submitted on NRC Form 5 reports under 10 CFR 20.2206.

** A microcurie is one millionth of a Curie.
3-26

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

NUREG-0713

TABLE 3.9

Collective and Average CEDE by Licensee

2004

Radiopharmaceuticals EASTERN ISOTOPES, INC. 45-25221-01MD 10 0.019 0.002

02500 MALLINCKRODT INC. 24-04206-10MD 4 0.121 0.030

CARDINAL HEALTH, INC. 47-25322-01MD 1 0.006 0.006

CARDINAL HEALTH, INC. 13-26367-01MD 2 0.021 0.011

CARDINAL HEALTH, INC. 13-32053-01MD 3 0.011 0.004

CARDINAL HEALTH, INC. 04-26507-01MD 79 1.131 0.014

03211 INTERNATIONAL ISOTOPES IDAHO INC. 11-27680-01 5 0.049 0.010

Total 104 1.358 0.013

Industrial Radiography CLEARWATER ENVIRONMENTAL, INC. 11-27746-01 1 0.045 0.045

03320 Total 1 0.045 0.045

Uranium Enrichment U. S. ENRICHMENT CORP. - PADUCAH GDP-1 22 0.107 0.005

21200 U. S. ENRICHMENT CORP. - PORTSMOUTH GDP-2 9 0.047 0.005

Total 31 0.154 0.005

Fuel Fabrication BWX TECHNOLOGIES, INC. SNM-0042 252 24.603 0.098

21210 FRAMATOME ANP, INC. SNM-1168 82 6.121 0.075

FRAMATOME ANP, INC. SNM-1227 261 54.763 0.210

GLOBAL NUCLEAR FUEL - AMERICAS, LLC SNM-1097 592 57.840 0.098

NUCLEAR FUEL SERVICES, INC. SNM-0124 725 13.194 0.018

WESTINGHOUSE ELECTRIC COMPANY LLC SNM-1107 384 99.148 0.258

Total 2,296 255.669 0.111

Power Reactors BEAVER VALLEY DPR-66 3 0.032 0.011

41111 BIG ROCK POINT DPR-06 1 0.016 0.016

BRAIDWOOD NPF-72 2 0.022 0.011

BROWNS FERRY DPR-33 593 13.367 0.023

BRUNSWICK DPR-62 1 0.015 0.015

CALLAWAY NPF-30 49 0.130 0.003

CALVERT CLIFFS DPR-53 4 0.074 0.019

CLINTON DPF-62 7 0.159 0.023

COLUMBIA GENERATING NPF-21 1 0.007 0.007

DIABLO CANYON DPR-80 4 0.069 0.017

DRESDEN DPR-19 7 0.091 0.013

FITZPATRICK DPR-59 2 0.040 0.020

GINNA DPR-18 2 0.081 0.041

HADDAM NECK DPR-61 13 0.439 0.034

HUMBOLDT BAY DPR-07 3 0.035 0.012

LASALLE NPF-11 1 0.011 0.011

LIMERICK NPF-39 3 0.012 0.004

MAINE YANKEE DPR-36 2 0.005 0.003

MILLSTONE 1 DPR-21 3 0.153 0.051

NINE MILE POINT DPR-63 7 0.114 0.016

OCONEE DPR-38 65 1.094 0.017

OYSTER CREEK DPR-16 2 0.037 0.019

PALISADES DPR-20 1 0.023 0.023

PALO VERDE NPF-41 4 0.040 0.010

PEACH BOTTOM DPR-44 1 0.014 0.014

QUAD CITIES DPR-29 2 0.024 0.012

RIVER BEND NPF-47 8 0.118 0.015

ROBINSON DPR-23 1 0.022 0.022

SAN ONOFRE DPR-13 28 0.0131 0.005

SEQUOYAH DPR-77 56 0.093 0.002

ST. LUCIE DPR-67 14 0.090 0.006

SURRY DPR-32 1 0.011 0.011

SUSQUEHANNA NPF-14 3 0.026 0.009

VERMONT YANKEE DPR-28 23 0.178 0.008

VOGTLE NPF-68 2 0.022 0.011

WATTS BAR NPF-90 173 0.585 0.003

Total 1,092 17.380 0.016

Grand Totals 3,524 274.606 0.078

Licensee Type Licensee Name License Number

Number

with Meas.

CEDE

Collective

CEDE

(person-rem)

Average

Meas. CEDE

(rem)
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TABLE 3.10

Internal Dose (CEDE) Distribution

1994-2004

Year

Meas.

0.020

Total with

Meas.

CEDE

Collective

CEDE

(personrem)

Average

Meas.

CEDE

(rem)

0.020-

0.100

0.100-

0.250

0.250-

0.500

0.500-

0.750

0.750-

1.000 1-2 2-3 3-4 4-5

Number of Individuals with CEDE in the Ranges (rem)

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

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

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

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

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

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

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

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

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

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

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

dose data for Unit 2 prior to 1986.

There were no changes to the count of 

operating reactors in 2004. The number of 

operating BWRs remains the same as in 2003 

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 2004, the 

number reflects the net electricity produced, 
4-

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

NUREG-0713 TABLE 4.1 Summary of Information Reported by Commercial Boiling Water Reactors 1973-2004

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%2004 35 5,451 33,948 29,424.8 0.16 156 970 0.19 841 893 94%

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

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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%2004 69 4,917 35,901 60,398.7 0.14 71 520 0.08 875 943 93%

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

** Figures are not adjusted for the multiple reporting of transient individuals (see Section 5).

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

TABLE 4.2

Summary of Information Reported by Commercial Pressurized Water Reactors

1973-2004
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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%2004 104 10,368 69,849 89,823.5 0.15 100 672 0.12 864 926 93%

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

1973-2004
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NUREG-0713

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 3% increase 

in the net electricity generated at LWRs in 2004. 

Contributors to this increase included Davis 

Besse (restarted), South Texas, Surry, and 

Cook for PWRs and Cooper Station and Duane 

Arnold for BWRs. These plants had increases 

of over 20% in power production from 2003 to 

2004.

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 2004, the number 

reflects the net electricity produced. This ratio, 

calculated by year for BWRs, PWRs, and 

LWRs, is presented in Tables 4.1, 4.2, and 4.3. 

This ratio was also calculated for each reactor 

site (see Appendix C). The average collective 

dose per MW-yr for LWRs decreased to a value 

of 0.12 rem/MW-yr in 2004 from a value of 0.14 

rem/MW-yr in 2003 due to a combination of the 

reduction in the collective dose and an increase 

in power production.

4.2.4 Average Maximum Dependable

Capacity

Average maximum dependable capacity as 

shown in Tables 4.1, 4.2, and 4.3 was found 

by dividing the sum of the net maximum 

dependable capacities of the reactors in 

megawatts (net MWe) by the number of 

reactors included each year. The net maximum 

dependable capacity is defined as the gross 

electrical output as measured at the output 

terminals of the turbine generator during the 

most restrictive seasonal conditions less the 

normal station service loads. This “capacity” of 

each plant was found in Ref. 12.

4.2.5 Percent of Maximum Dependable 

Capacity Achieved

The percent of maximum dependable capacity 

achieved is shown for all LWRs in Table 4.3. 

This parameter gives an indication of the 

overall power generation performance of LWRs 

as compared to the maximum dependable 

capacity that could be obtained in a given year. 

It is calculated by dividing the average electricity 

generated per reactor by the average maximum 

dependable capacity for each year.
4-

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

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From 1973 to 1978 this indicator exhibited 

an increasing trend as a number of new 

reactors began producing power at higher 

efficiencies. Following the accident at TMI, 

reactor operations personnel concentrated on 

improving safety systems and complying with 

the new regulations for these systems. During 

this time period, from 1979 to 1987, the percent 

of maximum dependable capacity remained 

around 61%. Following the completion of most 

of these mandated repairs, reactors increased 

the percent of maximum dependable capacity 

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

nearly 20% in 10 years. The decrease in 

maximum dependable capacity from 1996 to 

1997 was due to the change from measuring 

the gross electricity generated to the net 

electricity generated. The percent of maximum 

dependable capacity has continued to increase 

since 1997 to an all-time high of 93% in 2004.

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 2004. 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 2004 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 13% to a value of 10,368 person-rem in 

2004. The PWRs with the largest decreases 

in the collective dose were Sequoyah, Davis 

Besse, and Surry. San Onofre experienced 

the highest increase in collective dose among 

PWRs. The BWRs with the largest decreases 

in the collective dose were Perry and Pilgrim. 

Clinton experienced the highest increase in 

collective dose among BWRs. 
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TABLE 4.4

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

1977-2004

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 11,9562004 57,417 28,863 11,179 7,334 2,873 1,233 1,190 188 13 - - - - - - - - 110,290 52,873 10,368

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.

**
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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 

2004, the average collective dose per LWR 

dropped by 87%. Between 2003 and 2004, the 

collective dose per reactor for PWRs decreased 

by 22% to 71 person-rem. The collective dose 

per reactor for BWRs decreased by 4% to 156 

person-rem from 2003 to 2004. The overall 

collective dose per reactor for LWRs decreased 

by 13% to 100 person-rem in 2004. This is 

the lowest average LWR dose per reactor 

ever recorded. The number of workers with 

measurable dose per reactor increased to 970 

for BWRs and decreased to 520 for PWRs in 

2004. 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 2004 

the net electricity generated increased to 

89,824 MW-yr while the number of operating 

reactors has remained constant for the past 6 

years. The value for the total collective dose 

for all LWRs decreased by 13% from a value of 

11,956 person-rem in 2003 to 10,368 personrem in 2004. Together with the decrease in 

the number of workers with measurable dose, 

this resulted in the average measurable dose 

per worker decreasing from 0.16 rem in 2003 

to 0.15 rem in 2004 (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-

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

NUREG-0713

FIGURE 4.1. Average Collective Dose and Number of Workers

with Measurable Dose per Reactor

1973-2004

Collective Dose per Reactor (Person-rem) Workers per Reactor
4-10

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

NUREG-0713

FIGURE 4.2. Number of Operating Reactors and Gross Electricity Generated

1973-2004

* Gross electricity 1973-1996, net electricity for 1997-2004.

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

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

NUREG-0713

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

1973-2004

* Gross electricity 1973-1996, net electricity for 1997-2004.

Average Measurable Dose (rem) Collective Dose (person-rem) per MY-YR
4-12

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

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 2004. 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 

decreased to 65 person-rem in 2004. At BWRs, 

the median fluctuates more from year to year. 

The median collective dose decreased from 

169 person-rem in 2003 to 158 person-rem in 

2004. Figure 4.5 also shows that, in 2004, 50% 

of the PWRs reported collective doses between 

47 and 78 person-rem, while 50% of the BWRs 

reported collective doses between 90 and 224 

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, 2004, 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 164 person-rem, the average 

measurable TEDE per worker was 0.18 rem, 

and the average collective TEDE per MW-yr 

was 0.21 person-rem per MW-yr. The average 

3-year collective TEDE per reactor and the 

average collective TEDE per MW-yr increased 

from 2003 to 2004, while the average 

measurable TEDE per worker remained the 

same.

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 

83 person-rem, 0.14 rem, and 0.10 personrem per MW-yr, respectively. All three values 

decreased from the previous 3-year period.
4-13

Thirty-Seventh Annual Report, 2004 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-Seventh Annual Report, 2004

NUREG-0713

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

1987-2004

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

A M

A

M

2001 2002

A M

A M

2003

78

47

224

90

A M

A M

2004
4-15

Thirty-Seventh Annual Report, 2004 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

2002-2004

3 59 178 1,368 0.13 2,473.5 0.07

3 74 221 1,725 0.13 2,062.1 0.11

6 76 457 3,811 0.12 4,410.4 0.10

3 81 244 1,536 0.16 2645.7 0.09

6 94 563 3,803 0.15 3,894.4 0.14

3 106 318 2,981 0.11 4,058.9 0.08

3 110 330 2,327 0.14 2,135.7 0.15

3 117 351 2,972 0.12 2,719.4 0.13

3 122 366 2,593 0.14 2,386.4 0.15

6 128 769 5,677 0.14 4,935.8 0.16

6 130 782 5,968 0.13 4,852.0 0.16

3 135 405 4,257 0.10 1,833.3 0.22

3 139 416 2,684 0.16 3,157.7 0.13

3 156 468 2,623 0.18 2,007.3 0.23

6 159 954 4,978 0.19 5,341.2 0.18

3 163 488 3,047 0.16 2,489.5 0.20

3 179 536 3,230 0.17 1,779.8 0.30

9 181 1,633 7,827 0.21 6,187.9 0.26

6 182 1,093 6,961 0.16 3,664.0 0.30

3 183 548 3,412 0.16 2,773.1 0.20

6 212 1,273 6,631 0.19 6.359.5 0.20

6 223 1,340 5,312 0.25 4,787.8 0.28

3 250 751 2,812 0.27 2,785.4 0.27

6 456 2,735 7,150 0.38 2,965.8 0.92

105 17,218 95,685 0.18 82,706.6 0.21

164 911 787.7

DUANE ARNOLD

COOPER STATION

LIMERICK 1,2

MONTICELLO

HATCH 1,2

COLUMBIA GENERATING

PILGRIM

FERMI 2

GRAND GULF

BRUNSWICK 1,2

SUSQUEHANNA 1,2

HOPE CREEK 1

VERMONT YANKEE

FITZPATRICK

PEACH BOTTOM 2,3

RIVER BEND 1

OYSTER CREEK

BROWNS FERRY 1,2,3**

DRESDEN 2,3

CLINTON

LASALLE 1,2

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 12/31/04 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-Seventh Annual Report, 2004

NUREG-0713

TABLE 4.6

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

2002-2004

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 12/31/04 are not included.

INDIAN POINT 3

HARRIS

CRYSTAL RIVER 3

SUMMER 1

SEABROOK

FARLEY 1,2

GINNA

THREE MILE ISLAND 1

PRAIRIE ISLAND 1,2

KEWAUNEE

PALO VERDE 1,2,3

BYRON 1,2

POINT BEACH 1,2

WOLF CREEK 1

VOGTLE 1,2

WATERFORD 3

CATAWBA 1,2

COMANCHE PEAK 1,2

BRAIDWOOD 1,2

TURKEY POINT 3,4

MCGUIRE 1,2

CALLAWAY 1

ST. LUCIE 1,2

NORTH ANNA 1,2

ROBINSON 2

ARKANSAS 1,2

BEAVER VALLEY 1,2

WATTS BAR 1

SURRY 1,2

DIABLO CANYON 1,2

OCONEE 1,2,3

SALEM 1,2

SOUTH TEXAS 1,2

SEQUOYAH 1,2

COOK 1,2

CALVERT CLIFFS 1,2

SAN ONOFRE 2,3

MILLSTONE 2,3

FORT CALHOUN

INDIAN POINT 2

PALISADES

DAVIS-BESSE

Totals and Averages

Averages per Reactor-Yr

3 36 107 1,292 0.08 2,267.2 0.11

3 44 132 1,678 0.08 3.357.2 0.17

3 45 136 1,220 0.11 2,237.9 0.16

3 47 141 1,630 0.09 3,215.0 0.15

3 48 143 2,367 0.06 4,249.1 0.12

6 52 315 2,701 0.12 4,112.9 0.21

3 54 162 1,156 0.14 2,043.1 0.33

3 55 165 1,507 0.11 1539.0 0.20

6 55 333 2,749 0.12 3,436.8 0.35

3 56 169 1,106 0.15 982.2 0.38

9 61 550 4,610 0.12 8,916.6 0.17

6 62 371 3,017 0.12 6,776.8 0.16

6 63 375 2,199 0.17 2,766.1 0.41

3 64 192 1,729 0.11 3,196.3 0.17

6 68 409 2,723 0.15 5,144.3 0.19

3 69 207 1,581 0.13 3,074.4 0.19

6 69 415 3,416 0.12 6,340.7 0.20

6 71 427 2,609 0.16 5,817.2 0.20

6 72 431 3,533 0.12 6,841.6 0.19

6 73 438 3,324 0.13 3,066.4 0.36

6 75 448 3,124 0.14 4,207.0 0.22

3 75 225 2,359 0.10 2,951.9 0.25

6 76 457 3,086 0.15 4,096.1 0.31

6 77 460 2,920 0.16 5,251.0 0.27

3 78 234 1,891 0.12 3,221.5 0.36

6 78 471 3,781 0.12 5,094.1 0.27

6 87 524 3,941 0.13 4,577.7 0.33

3 88 265 2,521 0.11 3,129.0 0.24

6 89 533 3,455 0.15 4,871.3 0.35

6 90 539 3,250 0.17 5,235.7 0.31

9 93 838 6,198 0.14 5,084.2 0.39

6 94 565 5,257 0.11 3,891.2 0.31

6 99 592 3,261 0.18 5,461.3 0.24

6 104 625 4,902 0.13 3,882.0 0.29

6 107 644 4,047 0.16 4,016.6 0.34

6 109 654 4,458 0.15 4,592.5 0.40

6 118 707 4,176 0.17 5,298.8 0.41

6 125 752 3,625 0.21 4,110.4 0.40

3 133 398 1,871 0.21 833.2 0.86

3 152 456 2,738 0.17 2,809.1 0.53

3 199 598 2,020 0.30 4,627.6 0.98

3 210 629 3,191 0.20 1,842.1 0.96

207 17,231 122,219 0.14 168,465.1 0.10

83 590 813.8
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Thirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

The average 3-year collective TEDE per 

BWR for 2002 to 2004 is 4% more than the 

average for 2001 to 2003. The average 3-year 

collective TEDE per PWR for 2002 to 2004 is 

8% less than the average for 2001 to 2003. 

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 2004. 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 

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

NUREG-0713

TRANSIENT WORKERS AND CAREER 

DOSES AT NRC-LICENSED FACILITIES

Section 5

5.1 Termination Reports

Under 10 CFR 20, licensees are required to 

submit NRC Form 5's to the 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 “termination reports” submitted 

in accordance with the old § 20.408, listing

the individual’s complete dose history during 

employment at the facility, are no longer 

required.

However, the Form 5's submitted to the NRC 

upon an individual’s termination of employment 

serve the same function as the previous 

requirements with regard to the analysis of 

transient workers at NRC-licensed facilities. 

The following analysis examines the workers 

who had more than one Form 5 dose record at 

more than one NRC-licensed facility during the 

monitoring year. These workers are defined as 

“transient” because they worked at more than 

one facility during the monitoring year.

The term “monitoring year” is used here in 

accordance with the definition of a year given 

in § 20.1003, which defines a year as “the 

period of time beginning in January used to 

determine compliance with the provisions of 

this part. The licensee may change the start 

date of the monitoring year used to determine 

compliance provided that the change is made 

at the beginning of the monitoring/calendar 

year and that no day is omitted or duplicated in 

consecutive years.”

5.2 Transient Workers at

NRC Facilities

Examination of the data reported for workers 

who began and terminated two or more periods 

of employment with two or more different 

facilities within one monitoring year is useful 

in many ways. For example, the number of 

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 2004, over 99% of the transient individuals 

were reported by nuclear power facilities. For 

this reason, these data are shown separately in 

Table 5.1.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

NUREG-0713

TABLE 5.1

Effects of Transient Workers on Annual Statistical Compilations

2004

80,473 41,583 15,626 8,245 2,733 978 668 16 150,322 69,849 10,368 0.1529,785 19,152 8,432 4,346 1,452 526 409 4 64,106 34,321 5,513 0.16

 6,729 6,432 3,985 3,435 1,592 781 931 176 13 24,074 17,345 5,513 0.32

57,417 28,863 11,179 7,334 2,873 1,233 1,190 188 13 110,290 52,873 10,368 0.20

85,328 45,885 17,077 9,168 3,256 1,329 1,145 134 34 8 163,364 78,036 12,774 0.1630,274 19,545 8,566 4,432 1,490 548 431 6 1 65,293 35,019 5,659 0.16

6,671 6,469 4,029 3,463 1,650 804 968 182 15 24,251 17,580 5,659 0.32

61,725 32,809 12,540 8,199 3,416 1,585 1,682 310 48 8 122,322 60,597 12,774 0.21

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
5-

Thirty-Seventh Annual Report, 2004 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 2004. 

Because each licensee reports the doses 

received by workers while monitored by the 

particular licensee during the year, it is expected 

that a summation of these reports would result 

in individuals being counted several times in 

dose ranges lower than the range in which 

their total accumulated 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 2004, Table 5.1 shows that 

the summation of annual reports for reactor 

licensees indicated that 16 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 201 transient workers who 

received doses greater than 2 rem. Correcting 

for the multiple counting of individuals also has 

a significant effect on the average measurable 

dose for these workers. The corrected average 

measurable dose for transient workers is 

twice as high as the value calculated by the 

summation of licensee records. The transient 

workers represent 29% of the workforce that 

receives measurable dose. The correction for 

the transient workers increases the average 

measurable dose by a factor of 2 from 0.16 rem 

to 0.32 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 his/her 

unique identification number and identification 

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

exposure for all facilities during the monitoring 

year. An individual exceeding the TEDE 5 rem 

per year regulatory limit would be identified in 

Table 5.1 in one of the dose ranges >5 rem. In 

2004, there were no individuals that exceeded 

the 5 rem annual TEDE limit.
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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.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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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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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 2004. Table 6.2 shows the data

reported under 10 CFR 20.403 and

10 CFR 20.405 for the period 1985 to 1993. 

Note that the categorization criteria changed

effective with the revision of 10 CFR 20 in 1994.

For the period 1990 to 1993, Table 6.2 shows

the number of individuals who exceeded various

limits while employed by one of several types

of licensees. For the period 1985 to 1989, only

the exposures in excess of regulatory limits

reported by licensed industrial radiography firms 

are shown separately. Most of the occurrences

included in the “All Other” category come from

research facilities, universities, and measuring

and well-logging activities.

In 2004, there were no Category A, B, or C

occurrences. No individuals were reported to

have exceeded the annual extremity, skin dose,

or organ dose limits.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

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TABLE 6.1

Occupational Exposures in Excess of Regulatory Limits

1994-2004

  

1g 1g

15.678 15.667

1

5.860   

  

   

   

  

1  1 

5.606  80 

  

 1   3

 127   1260

2

11.373

2 3

10.636 2,677

1

5.67

5f   2f

566 1080 

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

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO.OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO.OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO.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.

2004

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

2003

1997

1998

2002
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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.

1

  

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

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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

2004, only 8 individuals exceeded 75% of the

TEDE dose limit. No individual exceeded the 5

rem TEDE annual limit.

TABLE 6.3

Maximum Occupational Exposures for Each Exposure Category *

2004

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  55.773 112% 54,020 197 46 4 - 0

SDE-WB 50 rem  7.913 16% 61,962 - - - - 0

LDE 15 rem  4.408 29%  59,950 7 - - - 0

CEDE  1.235  3,513

CDE  10.244  2,910

DDE  4.392  61,011

TEDE 5 rem  4.392 88%  62,032 1,275 158 8 - 0

TODE 50 rem  10.605 21%  55,122 - - - - 0

Number of

Individuals

> Limit
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Thirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

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

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ANNUAL TEDE FOR NON-REACTOR

NRC LICENSEES

2004

Appendix A
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Seventh Annual Report, 2004

NUREG-0713

PROGRAM CODE -LICENSEE NAME LICENSE#

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-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rems)

INDUSTRIAL RADIOGRAPHY - SINGLE LOCATION - 03310AMERICAN	CASTINGS,	LLC 35-18099-01 - 2 - - - - - - - - - - - 2 2 0.008 0.004ARMY,	DEPARTMENT	OF	THE 29-00047-06 2 1 - - - - - - - - - - - 3 1 0.004 0.004ARMY,	DEPARTMENT	OF	THE	(CRANE) 13-18235-01 23 3 - - - - - - - - - - - 26 3 0.058 0.019ARROW	TANK	&	ENGINEERING	CO. 22-13253-01 - 3 - 3 - - - - - - - - - 6 6 1.026 0.171CHART	INDUSTRIES,	INC. 22-24393-01 - 4 1 - - - - - - - - - - 5 5 0.192 0.038DURALOY	TECHNOLOGIES,	INC. 37-02279-02 - 1 3 - - - - - - - - - - 4 4 0.599 0.150HARRISON	STEEL	CASTINGS	CO. 13-02141-01 5 - - - - - - - - - - - - 5 - - -HUTCHINSON	TECHNICAL	COLLEGE 22-15554-01 61 13 1 - - - - - - - - - - 75 14 0.478 0.034INTERMET-ARCHER	CREEK 45-17464-01 - 4 1 - - - - - - - - - - 5 5 0.155 0.031NILES	STEEL	TANK	CO. 21-04741-01 2 1 - - - - - - - - - - - 3 1 0.015 0.015TESTWELL	LABORATORIES,	INC. 31-30653-02 4 2 1 1 - - - - - - - - - 8 4 0.610 0.153WAUKESHA	FOUNDRY,	INC. 48-13776-01 4 - - - - - - - - - - - - - - - 4Total 12 101 34 7 4 146 45 3.145 0.070

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2004

	 NOTE: The data values shown bolded and in boxes represent the highest value in each category.
AThirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

PROGRAM CODE -LICENSEE NAME LICENSE#

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-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rems)

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320ALASKA	INDUSTRIAL	X-RAY,	INC. 50-16084-01 - 4 1 1 1 1 - - 1 - - - - 9 9 5.727 0.636ALLIED	INSPECTION	SERVICES,	INC. 21-18428-01 - - - 3 1 1 - - - - - - - 5 5 2.558 0.512ALONSO	&	CARUS	IRON	WORKS,	INC. 52-21350-01 - - 1 2 - - - - - - - - - 3 3 0.824 0.275AMERICAN	ENGINEERING	TESTING,	INC. 22-20271-02 - 7 3 2 3 - 8 2 2 - - - - 27 27 26.472 0.980ANVIL	CORPORATION 46-23236-03 3 23 17 12 12 6 2 - - - - - - 75 72 22.896 0.318APPLIED	TECHNICAL	SERVICES,	INC. 45-25477-01 2 11 5 4 - 1 1 - - - - - - 24 22 5.072 0.231BILL	MILLER,	INC. 35-19048-01 1 2 4 5 4 1 1 - - - - - - 18 17 7.619 0.448BRANCH	RADIOGRAPHIC	LABS.,	INC. 29-03405-02 6 4 7 6 2 1 - - - - - - - 26 20 5.821 0.291BRAUN	INTERTEC	CORPORATION 22-16537-02 3 3 3 2 4 4 1 - - - - - - 20 17 8.600 0.506CALUMET	TESTING	SERVICES,	INC. 13-16347-017 4 3 1 - 1 3 1 - - - - - 20 13 9.617 0.740CANSPEC	(USA),	INC. 42-32443-01 1 13 17 14 12 5 1 - - - - - - 63 62 20.983 0.338CAPITAL	X-RAY	SERVICES,	INC. 35-11114-01 - 11 1 1 1 3 4 2 1 - - - - 24 24 19.278 0.803CENTURY	INSPECTION,	INC. 42-08456-02 16 13 4 10 7 3 10 1 2 - - - - 66 50 35.521 0.710CERTIFIED	TESTING	LABS,	INC. 29-14150-01 2 16 4 - 1 - - - - - - - - 23 21 1.766 0.084COLBY	&	THIELMEIER	TESTING	CO. 24-13737-01 - 1 1 2 1 1 4 - - - - - - 10 10 8.674 0.867COMO	TECH	INSPECTION 15-26978-01 - - - 1 3 1 1 - - - - - - 6 6 4.216 0.703CONAM	INSPECTION 12-16559-02 23 118 85 85 60 44 70 13 3 - - - - 501 478 265.229 0.555CONSUMERS	ENERGY	LAB.	SERVICES 21-08606-03 7 4 1 5 5 2 - - - - - - - 24 17 6.726 0.396COOPER	HEAT-MQS 42-32219-01 7 43 19 23 13 12 9 1 - - - - - 127 120 44.666 0.372CTL	-	ASTROTECH	DIVISION 37-09928-01 13 14 2 - - - - - - - - - - 29 16 0.743 0.046CURTISS-WRIGHT	ELECTRO-MECH.	CORP. 37-05809-02 - 5 - - - - - - - - - - - 5 5 0.035 0.007ELITE	INSPECTION,	INC. 13-26712-01 2 4 7 5 1 6 5 5 1 - - - - 36 34 29.300 0.862ENGINEERING	&	INSPECTIONS,	HAWAII 53-27731-01 - - 5 4 - - 3 - - - - - - 12 12 7.482 0.624FINLAY	TESTING	LABORATORIES 53-27716-02 3 2 3 2 1 - 2 - - - - - - 13 10 5.060 0.506FROEHLING	&	ROBERTSON,	INC. 45-08890-01 10 2 1 - - - - - - - - - - 13 3 0.240 0.080G.	E.	INSPECTION	SERVICES,	INC. 39-24888-01 1 11 4 1 - 1 - - - - - - - 18 17 2.266 0.133GENERAL TESTING	&	INSPECTION	CO. 47-32191-01 1 1 3 1 - - - - - - - - - 6 5 0.954 0.191

	 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 2004 (continued)
A-

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

NUREG-0713

PROGRAM CODE -LICENSEE NAME LICENSE#

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-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rems)

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320 ContinuedGLOBE	X-RAY	SERVICES,	INC. 35-15194-01 1 8 3 3 1 4 6 3 - - - - - 29 28 21.696 0.775H	&	G	INSPECTION	COMPANY,	INC. 42-26838-01 - 6 6 10 6 6 7 1 - - - - - 42 42 25.674 0.611H	&	H	X-RAY	SERVICES,	INC. 17-19236-01 6 31 25 31 26 23 45 10 1 - - - - 198 192 145.656 0.759HIGH	MOUNTAIN	INSPECTION	SERVICES 49-26808-02 - 7 15 10 8 14 23 12 - 2 - - - 91 91 97.196 1.068HUDSON	GLOBAL	RESOURCES,	INC. 37-27891-01 2 6 1 1 4 2 2 - - - - - - 18 16 7.478 0.467HUNTINGTON	TESTING	&	TECHNOLOGY 47-23076-01 1 9 10 6 4 2 3 - - - - - - 35 34 12.645 0.372INSPECTION	SERVICES	ORGANIZATION 41-06832-06 10 3 2 - - - - - - - - - - 15 5 0.423 0.085INTEGRITY	TESTLAB 07-30791-01 1 1 2 3 3 2 2 2 - - - - - 16 15 12.555 0.837INT'L	RADIOGRAPHY	&	INSPEC.	SERVICES 35-30246-01 2 15 9 7 10 4 10 8 4 1 - - - 70 68 66.023 0.971JAN	X-RAY	SERVICES,	INC 21-16560-01 77 30 34 46 23 18 23 3 1 - - - - 255 178 94.571 0.531KAKIVIK	ASSET	MANAGEMENT 50-27667-01 10 21 16 18 15 5 9 1 - - - - - 95 85 37.146 0.437LONGVIEW	INSPECTION,	INC. 42-27593-01 12 19 10 7 2 1 9 2 - 1 - - - 63 51 29.301 0.575LUCIUS	PITKIN,	INC. 31-30821-01 - 3 1 - - - - - - - - - - 4 4 0.255 0.064MARTIN	INDUSTRIAL	TESTING,	INC. 45-25452-01 - 1 - - 1 - 1 - - - - - - 3 3 1.729 0.576MARYLAND	Q.C.	LABORATORIES,	INC. 19-28683-01 2 13 1 2 1 1 1 - - - - - - 21 19 3.807 0.200MASSACHUSETTS	MATERIALS	RESEARCH 07-01173-03 1 2 1 - - - - - - - - - - 4 3 0.252 0.084MATERIALS	INTEGRITY,	INC. 50-27722-01 - 3 2 - - - - - - - - - - 5 5 0.396 0.079MATTINGLY	TESTING	SERVICES,	INC. 25-21479-01 3 4 - 1 2 2 2 - - - - - - 14 11 6.024 0.548MET-CHEM	TESTING	LABS	OF	UTAH,	INC. 43-27362-01 7 5 - 1 - - 2 - - - - - - 15 8 2.705 0.338MIDWEST	INDUSTRIAL	X-RAY,	INC. 33-27427-01 1 - 1 2 4 1 3 3 6 1 22 21 42.212 2.010NEWPORT	NEWS	SHIP	BLDG.	&	DRY	DOCK	CO. 45-09428-02 2 31 9 5 - - - - - - - - - 47 45 4.067 0.090NON-DESTRUCTIVE	TESTING	GROUP 21-32340-01 2 10 2 - 1 2 1 - - - - - - 18 16 3.793 0.237NOVA	DATA	TESTING	LABS,	INC. 45-24872-01 - 4 1 1 - - - - - - - - - 6 6 0.594 0.099PACIFIC	TESTING,	INC. 53-29118-01 - 6 - 3 - - - - - - - - - 9 9 1.187 0.132PRECISION	CALIBRATION	&	TESTING	CO. 37-30546-01 4 4 - - - - - - - - - - - 8 4 0.048 0.012PRECISION	CUSTOM	COMPONENTS,	LLC. 37-16280-01 13 7 - 1 - - - - - - - - - 21 8 0.302 0.038PRECISION	TESTING	&	INSPECTION 45-25475-01 - - - 1 2 - 3 - - - - - - 6 6 5.973 0.996

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2004 (continued)

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

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

NUREG-0713

PROGRAM CODE -LICENSEE NAME LICENSE#

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-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rems)

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320 Continued PRIME	NDT	SERVICES,	INC. 37-23370-01 - 6 1 3 1 1 9 2 - - - - - 23 23 20.465 0.890PROFESSIONAL	NDE	&	WELDING	SERVICES 52-25538-01 - 5 - 5 1 - - - - - - - - 11 11 2.482 0.226PROFESSIONAL	SERVICE	INDUSTRIES 12-16941-03 1 2 1 1 - 1 - - - - - - - 6 5 1.508 0.302Q.C.	LABORATORIES,	INC. 09-11579-03 - 6 4 1 2 - - - - - - - - 13 13 2.387 0.184QUALITY	INSPECTION	SERVICES,	INC. 31-30187-01 2 2 1 1 1 - 1 - - - - - - 8 6 2.621 0.437SCHNABEL	ENGINEERING	ASSOCIATES,	INC.45-19703-01 1 4 3 1 2 - - - - - - - - 11 10 2.435 0.244SCIENTIFIC	TECHNICAL,	INC. 45-24882-01 4 5 - 1 - - - - - - - - - 10 6 0.473 0.079SHAW	PIPELINE	SERVICES,	INC. 35-23193-01 4 13 10 18 12 7 7 2 - - - - - 73 69 37.161 0.539S.K.	MCBRYDE,	INC. 32-25137-01 - 2 3 1 - - - - - - - - - 6 6 0.911 0.152SOUTHWEST	X-RAY	CORPORATION 49-27434-01 - 1 1 1 2 - - 1 - - - - - 6 6 3.923 0.654ST.	LOUIS	TESTING	LABS,	INC. 24-00188-02 1 6 1 1 1 2 3 - - - - - - 15 14 7.173 0.512STORK	TWIN	CITY	TESTING	CORP. 22-01376-02 1 5 2 - 1 - - - - - - - - 9 8 1.054 0.132T	&	K	INSPECTION,	INC. 33-27678-01 - - 2 - 1 - 2 4 1 1 - - - 11 11 20.954 1.905TEI	ANALYTICAL	SERVICES,	INC. 37-28004-01 2 17 6 5 4 4 4 - - - - - - 42 40 14.912 0.373TESTING	INSTITUTE	OF	ALASKA,	INC. 50-17446-01 6 1 3 1 1 - - - - - - - - 12 6 1.464 0.244TESTING	TECHNOLOGIES,	INC. 45-25007-01 - 6 - 6 4 3 2 - - - - - - 21 21 9.450 0.450TESTMASTER	INSPECTION	CO. 34-24872-02 - 2 - 1 1 1 3 - - - - - - 8 8 5.490 0.686THERMAL	ENGINEERING	INT'L 24-19500-01 4 1 - - - - - - - - - - - 5 1 0.065 0.065THREE	RIVERS	GAMMA 37-28367-01 - - - - - 1 1 - - - - - - 2 2 2.513 1.257TULSA	GAMMA	RAY,	INC. 35-17178-01 2 8 11 10 5 7 23 17 5 1 - - - 89 87 110.254 1.267TWIN	PORTS	TESTING,	INC. 48-23476-01 4 5 1 2 2 - 1 - - - - - - 15 11 3.690 0.335U.S.	INSPECTION	SERVICES 34-06943-02 11 55 28 24 13 13 21 1 1 - - - - 167 156 68.617 0.440VALLEY	INDUSTRIAL	X-RAY 04-29076-01 14 16 8 9 13 8 11 1 - - - - - 80 66 37.585 0.569VALLEY	INSPECTION	SERVICE,	INC. 37-28385-01 - 2 - 3 - 1 1 - 1 - - - - 8 8 6.820 0.853WASHINGTON	GROUP	INERNATIONAL 29-27761-01 1 10 9 4 1 - - - - - - - - 25 24 3.284 0.137WESTERN	X-RAY	COMPANY 35-19993-01 - 1 2 4 5 5 11 - - - - - - 28 28 23.560 0.841WOS	TESTING	COMPANY,	INC. 48-26385-01 2 5 1 - 1 - - - - - - - - 9 7 1.051 0.150Total 81 325 751 450 454 319 235 377 98 30 7 3046 2721 1564.355 0.575

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2004 (continued)

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

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

NUREG-0713 APPENDIX A Annual TEDE for Non-Reactor NRC Licensees CY 2004 (continued)

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

PROGRAM CODE -LICENSEE NAME LICENSE#

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-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rems)

MANUFACTURING AND DISTRIBUTION - LIMITED NUCLEAR PHARMACIES - 02500CAPITAL	PHARMACY,	INC. 21-26597-01MD 7 15 3 - - - - - - - - - - 25 18 0.674 0.037CARDINAL	HEALTH,	INC. 04-26507-01MD 394 624 132 42 12 5 1 - - - - - - 1,210 816 63.110 0.077EASTERN	ISOTOPES,	INC. 45-25221-01MD 25 114 17 9 7 2 19 6 4 1 - - - 204 179 72.753 0.406MALLINCKRODT,	INC. 24-04206-00MD 3 7 6 1 - - - - - - - - - 17 14 1.563 0.112MALLINCKRODT,	INC. 24-04206-22MD 16 2 1 - - - - - - - - - - 19 3 0.253 0.084MALLINCKRODT	MEDICAL,	INC. 24-04206-01MD 13 7 - - - - - - - - - - - 20 7 0.283 0.040MALLINCKRODT	MEDICAL,	INC. 24-04206-10MD 12 7 4 - - - - - - - - - - 23 11 0.780 0.071MALLINCKRODT	MEDICAL,	INC. 24-04206-14MD 9 10 9 - - - - - - - - - - 28 19 1.728 0.091MALLINCKRODT	MEDICAL,	INC. 24-04206-16MD 8 7 1 2 - - - - - - - - - 18 10 1.118 0.112MALLINCKRODT	MEDICAL,	INC. 24-04206-19MD 18 7 6 6 1 - - - - - - - - 38 20 3.748 0.187MALLINCKRODT	MEDICAL,	INC. 24-17450-02MD 8 3 5 1 - - - - - - - - - 17 9 1.035 0.115MID-AMERICA	ISOTOPES,	INC. 24-26241-01MD 18 5 4 - 1 - - - - - - - - 28 10 1.588 0.159NUCLEAR	DIAGNOSTICS	PRODUCTS 29-30500-01MD 8 32 14 9 1 - 1 - - - - - - 65 57 9.470 0.166PSI,	INC. 11-27705-01MD - - 5 1 - 1 1 - - - - - - 8 8 3.321 0.415RADIOPHARMACY,	INC. 13-26246-01MD 6 16 3 3 - - - - - - - - - 28 22 1.712 0.078Total 15 545 856 210 74 22 8 22 6 4 1 1,748 1,203 163.136 0.136
AThirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2004 (continued)

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

PROGRAM CODE -LICENSEE NAME LICENSE#

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-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rems)

MANUFACTURING AND DISTRIBUTION - TYPE A BROAD - 03211CANBERRA	DOVER,	INC. 29-04236-01 14 26 - - - - - - - - - - - 40 26 0.341 0.013INTERNATIONAL	ISOTOPES	IDAHO,	INC. 11-27680-01 6 3 2 2 2 - 1 - - - - - - 16 10 3.953 0.395MALLINCKRODT,	INC. 24-04206-01 89 88 57 61 30 17 36 14 - - - - - 392 303 153.386 0.506Total 3 109 117 59 63 32 17 37 14 448 339 157.680 0.465MANUFACTURING AND DISTRIBUTION - LIMITED TYPE B BROAD - 03212OHMART/VEGA	CORP. 34-00639-04 17 27 3 3 1 - - - - - - - - 51 34 2.633 0.077Total 1 17 27 3 3 1 51 34 2.633 0.077MANUFACTURING AND DISTRIBUTION - LIMITED OTHER- 03214BMS-MEDICAL	IMAGING 20-00320-19 - 1 1 - - - - - - - - - - 2 2 0.232 0.116MDS	NORDION,	INC. 54-28275-01 - 1 1 - - - - - - - - - - 2 2 0.192 0.096Total 2 2 2 4 4 0.424 0.106
A-

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

NUREG-0713 APPENDIX A Annual TEDE for Non-Reactor NRC Licensees CY 2004 (continued)

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

PROGRAM CODE -LICENSEE NAME LICENSE#

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-

12.00 >12.0

Total

Number

Monitored

Number

with

Meas.

Dose

Total

Collective

TEDE

(personrem)

Average

Meas.

TEDE

(rems)

INDEPENDENT SPENT FUEL STORAGE INSTALLATION - 23200GENERAL	ELECTRIC	COMPANY SNM-2500 10 22 4 1 - - - - - - - - - 37 37 1.257 0.047Total 1 10 22 4 1 37 37 1.257 0.047FUEL CYCLE URANIUM ENRICHMENT PLANTS - 21200USEC-PADUCAH GDP-1 1,663 183 24 1 - - - - - - - - - 1,871 208 8.816 0.042USEC-PORTSMOUTH GDP-2 1,260 276 17 12 - - - - - - - - - 1,565 305 13.559 0.044Total 2 2,923 459 41 13 3,436 513 22.375 0.044FUEL CYCLE FUEL FABRICATION FACILITIES - 21210BWX	TECHNOLOGIES,	INC.	(NPD) SNM-0042 33 179 89 22 1 1 - - - - - - - 325 292 30.229 0.104FRAMATOME	ANP,	INC. SNM-1168 320 356 50 17 2 1 4 - - - - - - 750 430 27.574 0.064FRAMATOME	ANP,	INC. SNM-1227 59 185 62 63 38 19 5 - - - - - - 431 372 85.538 0.230GLOBAL	NUCLEAR	FUEL-WILMINGTON,	NC SNM-1097 284 387 188 87 - - - - - - - - - 946 662 70.070 0.106NUCLEAR	FUEL	SERVICES,	INC. SNM-0124 112 712 135 15 - - - - - - - - - 974 862 42.003 0.049WESTINGHOUSE	ELECTRIC	COMPANY SNM-1107 18 214 151 107 108 70 32 - - - - - - 700 682 236.140 0.346Total 6 826 2,033 675 311 149 91 41 4,126 3,300 491.554 0.149
B-

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

NUREG-0713

ANNUAL WHOLE BODY DOSES AT LICENSED 

NUCLEAR POWER FACILITIES

2004

Appendix B
B-

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

NUREG-0713 APPENDIX B Annual Whole Body Doses at Licensed Nuclear Power Facilities CY 2004

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 1,264 857 294 72 4 - - - - - - - - - 2,491 1,227 106.172BEAVER VALLEY 1, 2 PWR 1,662 773 301 163 30 3 - - - - - - - - 2,932 1,270 156.509BRAIDWOOD 1, 2 PWR 1,444 663 239 78 6 - - - - - - - - - 2,430 986 94.942BROWNS FERRY 1, 2, 3 BWR 2,501 1,537 691 596 318 92 8 - - - - - - - 5,743 3,242 672.714BRUNSWICK 1, 2 BWR 1,287 1,480 387 186 57 21 9 - - - - - - - 3,427 2,140 244.577BYRON 1, 2 PWR 1,352 612 229 53 10 1 1 - - - - - - - 2,258 906 89.147CALLAWAY 1 PWR 1,325 745 259 93 20 7 - - - - - - - - 2,449 1,124 120.621CALVERT CLIFFS 1, 2 PWR 1,152 824 200 113 49 15 4 - - - - - - - 2,357 1,205 143.944CATAWBA 1, 2 PWR 1,717 703 315 78 24 3 - - - - - - - - 2,840 1,123 122.831CLINTON BWR 1,173 852 389 243 96 25 17 - - - - - - - 2,795 1,622 282.833COLUMBIA GENERATING BWR 849 523 115 61 13 4 - - - - - - - - 1,565 716 66.130COMANCHE PEAK 1, 2 PWR 1,310 498 230 87 20 9 20 - - - - - - - 2,174 864 135.388COOK 1, 2 PWR 1,643 572 250 129 35 20 9 - - - - - - - 2,658 1,015 156.213COOPER STATION BWR 1,042 322 107 46 5 1 - - - - - - - - 1,523 481 47.064CRYSTAL RIVER 3 PWR 690 126 5 - - - - - - - - - - - 821 131 4.044DAVIS-BESSE PWR 1,033 150 10 1 - - - - - - - - - - 1,194 161 6.594DIABLO CANYON 1, 2 PWR 1,438 550 346 206 81 24 23 - - - - - - - 2,668 1,230 254.367DRESDEN 2, 3 BWR 1,094 1,064 456 314 144 34 32 - - - - - - - 3,138 2,044 381.054DUANE ARNOLD BWR 808 147 62 11 - - - - - - - - - - 1,028 220 18.993FARLEY 1, 2 PWR 987 768 291 73 9 - - - - - - - - - 2,128 1,141 107.227FERMI 2 BWR 1,450 835 292 150 25 - - - - - - - - - 2,752 1,302 145.090FITZPATRICK BWR 826 581 257 166 60 16 11 - - - - - - - 1,917 1,091 186.055FORT CALHOUN PWR 754 147 48 17 3 - - - - - - - - - 969 215 21.574GINNA PWR 884 88 20 2 1 - - - - - - - - - 995 111 7.486GRAND GULF BWR 881 764 286 138 42 10 3 - - - - - - - 2,124 1,243 158.112HARRIS PWR 1,012 552 164 30 1 - - - - - - - - - 1,759 747 57.103HATCH 1, 2 BWR 1,000 653 313 182 43 14 4 - - - - - - - 2,209 1,209 180.129HOPE CREEK 1 BWR 386 1,849 288 191 66 25 21 - - - - - - - 2,826 2,440 239.540INDIAN POINT 2 PWR 1,550 600 267 185 52 22 9 1 - - - - - - 2,686 1,136 195.630INDIAN POINT 3 PWR 1,550 223 10 1 - - - - - - - - - - 1,784 234 4.232KEWAUNEE PWR 670 305 132 93 26 5 4 - - - - - - - 1,235 565 91.168LASALLE 1, 2 BWR 1,358 1,432 464 314 99 36 21 - - - - - - - 3,724 2,366 359.470LIMERICK 1, 2 BWR 1,617 802 300 123 31 3 6 - - - - - - - 2,882 1,265 149.433MCGUIRE 1, 2 PWR 1,283 623 292 109 39 24 29 - - - - - - - 2,399 1,116 196.193MILLSTONE 2, 3 PWR 1,388 428 198 128 37 9 3 - - - - - - - 2,191 803 136.459MONTICELLO BWR 734 166 63 43 6 1 - - - - - - - - 1,013 279 35.081NINE MILE POINT 1, 2 BWR 1,062 490 304 251 140 69 103 5 - - - - - - 2,424 1,362 448.509NORTH ANNA 1, 2 PWR 2,441 562 278 83 28 8 5 1 - - - - - - 3,406 965 129.686
BThirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX B

Annual Whole Body Doses at Licensed Nuclear Power Facilities

CY 2004 (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 2,221 1,092 733 339 104 26 1 - - - - - - - 4,516 2,295 367.891OYSTER CREEK BWR 1,150 754 275 217 63 29 8 - - - - - - - 2,496 1,346 226.880PALISADES PWR 765 298 215 198 103 75 79 6 - - - - - - 1,739 974 370.895PALO VERDE 1, 2, 3 PWR 1,695 853 246 123 49 19 34 - - - - - - - 3,019 1,324 199.016PEACH BOTTOM 2, 3 BWR 1,508 759 318 214 83 25 20 3 - - - - - - 2,930 1,422 264.727PERRY BWR 861 256 133 88 16 3 - - - - - - - - 1,357 496 73.481PILGRIM BWR 475 282 110 33 2 - - - - - - - - - 902 427 41.109POINT BEACH 1, 2 PWR 836 301 168 112 37 7 2 - - - - - - - 1,463 627 109.515PRAIRIE ISLAND 1, 2 PWR 919 674 364 133 13 2 - - - - - - - - 2,105 1,186 143.806QUAD CITIES 1, 2 BWR 991 1,155 486 373 184 92 44 - - - - - - - 3,325 2,334 510.521RIVER BEND 1 BWR 881 725 328 228 61 19 17 - - - - - - - 2,259 1,378 235.749ROBINSON 2 PWR 995 535 282 121 11 3 - - - - - - - - 1,947 952 118.159SALEM 1, 2 PWR 238 1,138 178 117 40 16 7 - - - - - - - 1,734 1,496 148.694SAN ONOFRE 2, 3 PWR 2,379 895 397 213 114 64 78 - - - - - - - 4,140 1,761 407.063SEABROOK PWR 830 278 12 1 - - - - - - - - - - 1121 291 5.858SEQUOYAH 1, 2 PWR 1,663 907 199 47 7 1 - - - - - - - - 2,824 1,161 85.941SOUTH TEXAS 1, 2 PWR 1,237 496 200 93 31 20 2 - - - - - - - 2,079 842 119.834ST. LUCIE 1, 2 PWR 1,547 618 346 152 29 12 - - - - - - - - 2,704 1,157 159.436SUMMER 1 PWR 902 171 26 3 - - - - - - - - - - 1,102 200 10.085SURRY 1, 2 PWR 2,482 650 259 90 20 6 3 - - - - - - - 3,510 1,028 119.654SUSQUEHANNA 1, 2 BWR 1,244 1,433 391 203 69 28 20 - - - - - - - 3,388 2,144 272.202THREE MILE ISLAND 1 PWR 1,071 101 4 - - - - - - - - - - - 1,176 105 3.573TURKEY POINT 3, 4 PWR 1,779 687 288 105 9 - - - - - - - - - 2,868 1,089 117.404VERMONT YANKEE BWR 865 817 286 175 67 25 9 - - - - - - - 2,244 1,379 211.529VOGTLE 1, 2 PWR 1,160 499 202 56 1 5 2 - - - - - - - 1,925 765 80.763WATERFORD 3 PWR 1,023 56 4 - - - - - - - - - - - 1,083 60 2.517WATTS BAR 1 PWR 1,218 202 16 2 - - - - - - - - - - 1,438 220 5.893WOLF CREEK 1 PWR 921 85 8 - - - - - - - - - - - 1,014 93 3.388TOTALS BWRS 26,043 19,678 7,101 4,546 1,690 572 353 8 - - - - - - 59,991 33,948 5,450.982TOTALS PWRS 54,430 21,905 8,525 3,699 1,043 406 315 8 - - - - - - 90,331 35,901 4,916.915TOTALS LWRS 80,473 41,583 15,626 8,245 2,733 978 668 16 - - - - - - 150,322 69,849 10,367.897
B-

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

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

CY 2004 (continued)

REACTORS NOT YET IN COMMERCIAL OPERATIONWATTS BAR 2 PWR Reported with Watts Bar 1REACTORS NO LONGER IN COMMERCIAL OPERATIONBIG ROCK POINT BWR 161 135 31 17 13 18 13 - - - - - - - 388 227 57.599HADDAM NECK PWR 658 306 153 72 16 9 8 - - - - - - - 1222 564 91.981HUMBOLDT BAY BWR 107 11 - - - - - - - - - - - - 118 11 0.454INDIAN POINT 1 PWR 1,550 149 2 5 - - - - - - - - - - 1706 156 2.916LACROSSE BWR 12 56 - - - - - - - - - - - - 68 56 0.918MAINE YANKEE PWR 252 132 38 11 6 1 2 - - - - - - - 442 190 21.313MILLSTONE 1 BWR 255 78 36 23 7 2 1 - - - - - - - 402 147 11.152RANCHO SECO PWR 142 88 17 8 3 6 - - - - - - - - 264 122 14.890SAN ONOFRE 1 PWR 1454 117 39 13 - - - - - - - - - - 1623 169 14.899TROJAN PWR 215 5 - - - - - - - - - - - - 220 5 0.079YANKEE-ROWE PWR 360 54 7 8 1 - - - - - - - - - 430 70 6.502ZION 1, 2 PWR 87 6 - - - - - - - - - - - - 93 6 0.167REACTORS NO LONGER IN COMMERCIAL OPERATION, REPORTED WITH OTHER UNITSBROWNS FERRY 1** BWR Reported with Browns Ferry 2, 3DRESDEN 1 BWR Reported with Dresden 2,3THREE MILE ISLAND 2 PWR Reported with Three Mile Island 1; estimated dose from Unit 2 is 0.216 person-rem.Total Reporting* 12 5,253 1,137 323 157 46 36 24 - - - - - - - 6,976 1,723 222.870

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

* These numbers are for the reactors no longer in commercial operation that report their doses separately (i.e., do not report their doses with other units).**Browns Ferry 1 remains in the count of operating reactors but was placed on Administrative Hold in June 1985.
C-

Thirty-Seventh Annual Report, 2004 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 - 2004

Appendix C*

*	A discussion of the methods used to collect and calculate the information contained in this Appendix is given in Section 3.1.
C-

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

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

2004	 1,759.5	 95.0	 1,227	 106	 0.09	 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	

2004	 1,593.1	 96.3	 1,270	 157	 0.12	 0.10
CThirty-Seventh Annual Report, 2004 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	 ---

2004	 0.0	 0.0	 227	 58	 0.25	 ---

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, 1129 MWe	 1995	 1,914.7	 85.4	 1,134	 236	 0.21	 0.12

1996	 1,854.9	 82.1	 1,356	 334	 0.25	 0.18

1997	 1,863.3	 85.4	 1,693	 321	 0.19	 0.17

1998	 1,979.1	 88.9	 1,869	 259	 0.14	 0.13

1999	 2,161.6	 95.8	 1,153	 146	 0.13	 0.07

2000	 2,142.8	 94.9	 1,562	 194	 0.12	 0.09

2001	 2,186.4	 95.8	 881	 101	 0.11	 0.05

2002	 2,284.0	 96.8	 975	 91	 0.09	 0.04

2003	 2,279.9	 95.6	 1,572	 245	 0.16	 0.11

2004	 2,277.8	 97.3	 986	 95	 0.10	 0.04
C-

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

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

2004	 2,104.7	 95.5	 3,242	 673	 0.21	 0.32

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, 900 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

2004	 1,690.6	 94.5	 2,140	 245	 0.11	 0.14	

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-

Thirty-Seventh Annual Report, 2004 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 - 1152, 1125 MWe	 1992	 1,888.4	 90.1	 1,021	 199	 0.19	 0.11

1993	 1,785.6	 83.5	 1,370	 432	 0.32	 0.24

1994	 1,953.3	 90.7	 962	 280	 0.29	 0.14

1995	 1,900.6	 85.5	 1,107	 306	 0.28	 0.16

1996	 1,758.4	 79.3	 1,610	 455	 0.28	 0.26

1997	 1,856.7	 86.6	 1,546	 241	 0.16	 0.13

1998	 1,869.8	 85.9	 1,809	 275	 0.15	 0.15

1999	 2,064.2	 92.3	 1,478	 239	 0.16	 0.12

2000	 2,196.9	 97.4	 959	 194	 0.20	 0.09

2001	 2,301.5	 97.8	 719	 59	 0.08	 0.03

2002	 2,205.0	 93.8	 1,287	 195	 0.15	 0.09

2003	 2,294.8	 97.2	 824	 87	 0.11	 0.04

2004	 2,277.4	 97.7	 906	 89	 0.10	 0.04

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

2004	 892.8	 78.9	 1,124	 121	 0.11	 0.14

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

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

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

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

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

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

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

1983	 1,397.2	 81.6	 1,915	 668	 0.35	 0.48

1984	 1,389.4	 79.3	 1,369	 479	 0.35	 0.34

1985	 1,189.8	 68.4	 1,598	 694	 0.43	 0.58

1986	 1,530.0	 87.2	 1,296	 347	 0.27	 0.23

1987	 1,207.3	 71.8	 1,384	 412	 0.30	 0.34

1988	 1,397.7	 81.0	 1,296	 291	 0.22	 0.21

1989	 333.6	 20.1	 1,786	 346	 0.19	 1.04

1990	 161.1	 11.0	 2,019	 304	 0.15	 1.89

1991	 1,085.0	 64.7	 1,974	 132	 0.07	 0.12

1992	 1,271.2	 73.9	 1,979	 330	 0.17	 0.26

1993	 1,462.1	 83.9	 1,462	 405	 0.28	 0.28

1994	 1,342.1	 79.4	 1,482	 454	 0.31	 0.34

1995	 1,542.8	 89.9	 1,203	 235	 0.20	 0.15
C-

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

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	 1996	 1,438.5	 82.4	 1,167	 239	 0.20	 0.17

(continued)	 1997	 1,499.6	 89.1	 1,091	 229	 0.21	 0.15

1998	 1,523.1	 89.3	 1,042	 187	 0.18	 0.12

1999	 1,521.4	 90.1	 1,134	 192	 0.17	 0.13

2000	 1,575.7	 92.7	 912	 135	 0.15	 0.09

2001	 1,554.7	 91.7	 895	 167	 0.19	 0.11

2002	 1,380.0	 81.7	 1,582	 245	 0.16	 0.18

2003	 1,558.4	 90.9	 1,671	 265	 0.16	 0.17	 	

2004	 1,653.7	 95.7	 1,205	 144	 0.12	 0.09

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

2004	 2,111.4	 93.0	 1,123	 123	 0.11	 0.06

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

2004	 910.8	 92.6	 1,622	 283	 0.17	 0.31

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

3 Energy Northwest has changed the name of Washington Nuclear 2 to Columbia Generating Station.
CThirty-Seventh Annual Report, 2004 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

COLUMBIA GENERATING3	 1999	 694.7	 70.0	 1,022	 155	 0.15	 0.22

(continued)	 2000	 979.6	 96.3	 706	 53	 0.08	 0.05

2001	 939.3	 88.1	 1,515	 227	 0.15	 0.24

2002	 1,023.0	 97.5	 647	 47	 0.07	 0.05

2003	 866.9	 81.8	 1,618	 205	 0.13	 0.24

2004	 1,022.5	 94.6	 716	 66	 0.09	 0.06

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

2004	 2,169.5	 95.1	 864	 135	 0.16	 0.06

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

2004	 1,909.2	 91.4	 1,015	 156	 0.15	 0.08

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

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

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

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 1985	 127.3	 21.5	 1,980	 1,333	 0.67	 10.47

(continued)	 1986	 480.0	 74.7	 895	 320	 0.36	 0.67

1987	 652.3	 96.2	 549	 103	 0.19	 0.16

1988	 493.4	 67.9	 942	 251	 0.27	 0.51

1989	 564.3	 76.2	 1,202	 343	 0.29	 0.61

1990	 602.0	 79.4	 1,174	 379	 0.32	 0.63

1991	 566.3	 78.8	 1,099	 405	 0.37	 0.72

1992	 731.0	 96.4	 463	 84	 0.18	 0.11

1993	 436.1	 58.8	 1,130	 391	 0.35	 0.90

1994	 262.2	 35.1	 333	 79	 0.24	 0.30	 	

1995	 486.5	 66.8	 1,095	 228	 0.21	 0.47

1996	 742.1	 97.9	 468	 48	 0.10	 0.06

1997	 622.8	 84.4	 1,125	 174	 0.16	 0.28

1998	 555.9	 75.9	 977	 182	 0.19	 0.33

1999	 743.2	 98.1	 318	 48	 0.15	 0.06

2000	 539.2	 74.2	 963	 200	 0.21	 0.37

2001	 592.7	 80.9	 1,309	 169	 0.13	 0.28

2002	 719.0	 98.6	 362	 39	 0.11	 0.05

2003	 511.4	 74.1	 882	 135	 0.15	 0.26

2004	 702.6	 94.7	 481	 47	 0.10	 0.07

CRYSTAL RIVER 3 1978	 311.5	 41.4	 643	 321	 0.50	 1.03

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

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

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

Capacity - 838 MWe	 1982	 589.8	 76.0	 780	 177	 0.23	 0.30

1983	 452.1	 58.8	 1,720	 552	 0.32	 1.22

1984	 774.2	 94.5	 549	 49	 0.09	 0.06

1985	 344.2	 47.6	 1,976	 689	 0.35	 2.00

1986	 319.5	 41.8	 1,057	 472	 0.45	 1.48

1987	 436.0	 60.9	 1,384	 488	 0.35	 1.12

1988	 690.2	 84.0	 569	 64	 0.11	 0.09

1989	 352.8	 48.8	 880	 234	 0.27	 0.66

1990	 497.8	 63.8	 1,441	 476	 0.33	 0.96

1991	 654.6	 82.0	 821	 116	 0.14	 0.18

1992	 632.1	 76.1	 1,403	 424	 0.30	 0.67

1993	 722.4	 85.0	 683	 60	 0.09	 0.08

1994	 711.9	 84.3	 1,079	 228	 0.21	 0.32

1995	 866.3	 100.0	 209	 8	 0.04	 0.01

1996	 290.8	 37.7	 1,192	 353	 0.30	 1.21

1997	 0.0	 0.0	 973	 179	 0.18	 ---

1998	 739.9	 90.3	 313	 19	 0.06	 0.03

1999	 727.5	 87.8	 1,324	 251	 0.19	 0.35

2000	 819.4	 97.6	 257	 15	 0.06	 0.02

2001	 741.6	 89.2	 902	 148	 0.16	 0.20

2002	 831.0	 99.4	 128	 5	 0.04	 0.01

2003	 749.0	 90.8	 961	 127	 0.13	 0.17

2004	 831.4	 98.1	 131	 4	 0.03	 ---

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
C-

Thirty-Seventh Annual Report, 2004 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 1989	 880.0	 98.6	 404	 38	 0.09	 0.04

(continued)	 1990	 500.0	 56.7	 1,377	 489	 0.36	 0.98

1991	 703.6	 81.8	 1,000	 216	 0.22	 0.31

1992	 915.2	 100.0	 287	 19	 0.07	 0.02

1993	 729.5	 83.4	 1,244	 348	 0.28	 0.48

1994	 768.4	 88.0	 861	 144	 0.17	 0.19

1995	 920.4	 100.0	 256	 7	 0.03	 0.01

1996	 775.8	 85.3	 949	 167	 0.18	 0.22

1997	 820.0	 94.0	 213	 10	 0.05	 0.01

1998	 699.8	 83.2	 980	 155	 0.16	 0.22

1999	 841.3	 95.6	 397	 28	 0.07	 0.03

2000	 770.8	 87.3	 1,109	 168	 0.15	 0.22

2001	 875.6	 100.0	 119	 6	 0.05	 0.01

2002	 106.0	 12.6	 1,983	 403	 0.20	 3.81

2003	 0.0	 0.0	 1,047	 220	 0.21	 ---

2004	 657.8	 77.6	 161	 7	 0.04	 0.01

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

2004	 1,736.3	 83.5	 1,230	 254	 0.21	 0.15

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

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-Seventh Annual Report, 2004

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 1992	 872.4	 75.4	 1,812	 619	 0.34	 0.71

(continued)	 1993	 960.1	 68.5	 2,751	 1,655	 0.60	 1.72

1994	 690.2	 51.7	 2,336	 833	 0.36	 1.21

1995	 643.1	 49.8	 2,482	 875	 0.35	 1.36

1996	 612.6	 47.7	 1,788	 456	 0.26	 0.74

1997	 1,096.2	 79.5	 2,747	 467	 0.17	 0.43

1998	 1,354.7	 90.6	 2,311	 427	 0.18	 0.32

1999	 1,410.9	 92.5	 3,243	 591	 0.18	 0.42

2000	 1,506.4	 97.3	 2,341	 262	 0.11	 0.17

2001	 1,427.4	 94.5	 2,769	 401	 0.14	 0.28

2002	 1,547.0	 95.7	 2,819	 355	 0.13	 0.23

2003	 1,555.9	 93.5	 2,098	 357	 0.17	 0.23

2004	 1,405.5	 84.8	 2,044	 381	 0.19	 0.27

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

2004	 561.2	 98.3	 220	 19	 0.09	 0.03

FARLEY 1, 2 1978	 713.8	 86.5	 527	 108	 0.20	 0.15

Docket 50-348, 50-364;	 1979	 211.0	 28.6	 1,227	 643	 0.52	 3.05

NPF-2, -8	 1980	 557.3	 69.3	 1,330	 435	 0.33	 0.78

1st commercial operation	 1981	 310.2	 41.4	 1,331	 512	 0.38	 1.65

12/77, 7/81	 1982	 1,271.5	 79.2	 1,453	 484	 0.33	 0.38

Type - PWRs	 1983	 1,356.5	 83.0	 1,938	 1,021	 0.53	 0.75

Capacity - 851, 849 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

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-Seventh Annual Report, 2004 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 1993	 1,455.5	 88.3	 1,284	 333	 0.26	 0.23

(continued)	 1994	 1,587.2	 93.0	 1,035	 250	 0.24	 0.16

1995	 1,311.2	 83.8	 1,574	 460	 0.29	 0.35

1996	 1,549.2	 90.9	 1,150	 232	 0.20	 0.15

1997	 1,449.7	 89.0	 1,105	 278	 0.25	 0.19

1998	 1,313.9	 80.9	 1,380	 432	 0.31	 0.33

1999	 1,436.0	 91.4	 1,102	 190	 0.17	 0.13

2000	 1,430.1	 88.6	 1,683	 360	 0.21	 0.25

2001	 1,384.3	 84.4	 1,810	 321	 0.18	 0.23

2002	 1,558.0	 93.5	 772	 96	 0.13	 0.06	 	

2003	 1,592.6	 95.3	 788	 111	 0.14	 0.07

2004	 1,496.8	 89.4	 1,141	 107	 0.09	 0.07

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

2004	 962.3	 90.0	 1,302	 145	 0.11	 0.15

FITZPATRICK 1976	 489.0	 71.6	 600	 202	 0.34	 0.41

Docket 50-333; DPR-59	 1977	 460.5	 68.4	 1,380	 1,080	 0.78	 2.35

1st commercial operation 7/75	 1978	 497.0	 72.1	 904	 909	 1.01	 1.83

Type - BWR	 1979	 349.0	 50.8	 850	 859	 1.01	 2.46

Capacity - 813 MWe	 1980	 509.5	 70.3	 2,056	 2,040	 0.99	 4.00

1981	 562.9	 74.7	 2,490	 1,425	 0.57	 2.53

1982	 583.6	 75.0	 2,322	 1,190	 0.51	 2.04

1983	 546.2	 70.6	 1,715	 1,090	 0.64	 2.00

1984	 576.2	 76.8	 1,610	 971	 0.60	 1.69

1985	 492.3	 63.7	 1,845	 1,051	 0.57	 2.13

1986	 711.2	 90.6	 1,185	 411	 0.35	 0.58

1987	 496.2	 70.3	 1,578	 940	 0.60	 1.89

1988	 514.0	 69.0	 1,553	 786	 0.51	 1.53

1989	 727.5	 92.3	 1,027	 377	 0.37	 0.52

1990	 543.8	 72.6	 1,536	 884	 0.58	 1.63

1991	 399.7	 53.4	 1,269	 333	 0.26	 0.83

1992	 0.0	 0.0	 2,374	 674	 0.28	 ---

1993	 559.6	 81.7	 1,427	 232	 0.16	 0.41

1994	 588.4	 83.2	 1,595	 322	 0.20	 0.55

1995	 569.8	 74.5	 1,249	 327	 0.26	 0.57

1996	 623.3	 83.1	 1,384	 357	 0.26	 0.57

1997	 756.2	 95.9	 662	 91	 0.14	 0.12

1998	 562.8	 78.0	 1,781	 358	 0.20	 0.64

1999	 749.7	 95.5	 558	 68	 0.12	 0.09

2000	 685.9	 88.4	 1267	 301	 0.24	 0.44

2001	 807.2	 98.9	 665	 63	 0.10	 0.08

2002	 751.0	 93.3	 1,234	 231	 0.19	 0.31	 	

2003	 793.0	 97.9	 298	 51	 0.17	 0.06

2004	 735.0	 92.1	 1,091	 186	 0.17	 0.25
C-12

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

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 1975	 252.3	 67.4	 469	 294	 0.63	 1.17

Docket 50-285; DPR-40	 1976	 265.9	 69.5	 516	 313	 0.61	 1.18

1st commercial operation 6/74	 1977	 351.8	 79.4	 535	 297	 0.56	 0.84

Type - PWR	 1978	 342.3	 75.1	 596	 410	 0.69	 1.20

Capacity - 478 MWe	 1979	 440.0	 95.7	 451	 126	 0.28	 0.29

1980	 242.3	 60.4	 891	 668	 0.75	 2.76

1981	 260.9	 72.3	 822	 458	 0.56	 1.76

1982	 418.0	 89.7	 604	 217	 0.36	 0.52

1983	 330.4	 73.1	 860	 433	 0.50	 1.31

1984	 279.2	 59.9	 913	 563	 0.62	 2.02

1985	 367.0	 73.7	 982	 373	 0.38	 1.02

1986	 431.8	 94.3	 756	 75	 0.10	 0.17

1987	 366.0	 75.4	 1,247	 388	 0.31	 1.06

1988	 315.5	 74.1	 1,594	 272	 0.17	 0.86

1989	 395.7	 89.2	 1,210	 93	 0.08	 0.24

1990	 290.0	 64.2	 760	 290	 0.38	 1.00

1991	 391.1	 91.7	 284	 57	 0.20	 0.15

1992	 303.4	 65.9	 802	 272	 0.34	 0.90

1993	 369.7	 80.8	 713	 157	 0.22	 0.42

1994	 492.8	 99.6	 211	 23	 0.11	 0.05

1995	 402.8	 83.2	 627	 139	 0.22	 0.35

1996	 374.9	 79.5	 740	 226	 0.31	 0.60

1997	 435.9	 93.6	 258	 41	 0.16	 0.09

1998	 387.7	 82.5	 788	 224	 0.28	 0.58

1999	 409.2	 89.2	 676	 159	 0.24	 0.39

2000	 443.8	 93.5	 249	 35	 0.14	 0.08

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

2004	 463.5	 97.0	 215	 22	 0.10	 0.05

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
C-13

Thirty-Seventh Annual Report, 2004 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

GINNA 1998	 491.8	 100.0	 161	 15	 0.09	 0.03

(continued)	 1999	 403.4	 85.6	 641	 175	 0.27	 0.43

2000	 434.2	 91.6	 429	 76	 0.18	 0.18

2001	 488.0	 100.0	 140	 10	 0.07	 0.02

2002	 438.0	 91.3	 535	 80	 0.15	 0.18	 	

2003	 440.4	 91.1	 510	 75	 0.15	 0.17

2004	 490.5	 99.5	 111	 7	 0.07	 0.02

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

1996	 1,096.2	 88.7	 1,564	 357	 0.23	 0.33

1997	 1,234.9	 100.0	 514	 105	 0.20	 0.09

1998	 1,049.2	 88.9	 1,410	 304	 0.22	 0.29

1999	 962.1	 81.3	 1,180	 226	 0.19	 0.23

2000	 1,217.5	 99.4	 289	 35	 0.12	 0.03

2001	 1,129.8	 93.0	 1,109	 185	 0.17	 0.16

2002	 1,145.0	 93.6	 1,060	 176	 0.17	 0.15	

2003	 1,241.2	 98.6	 290	 31	 0.11	 0.03

2004	 1,165.2	 92.2	 1,243	 158	 0.13	 0.14

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	 ---

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-Seventh Annual Report, 2004

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

HADDAM NECK5 2000	 0.0	 0.0	 555	 262	 0.47	 ---

(continued)	 2001	 0.0	 0.0	 361	 95	 0.26	 ---

2002	 0.0	 0.0	 258	 52	 0.20	 ---	 	

2003	 0.0	 0.0	 400	 82	 0.21	 ---

2004	 0.0	 0.0	 564	 92	 0.16	 ---

HARRIS 1 1988	 652.9	 75.0	 721	 169	 0.23	 0.26

Docket 50-400; NPF-63	 1989	 690.6	 79.5	 929	 156	 0.17	 0.23

1st commercial operation 5/87	 1990	 776.4	 89.6	 453	 85	 0.19	 0.11

Type - PWR	 1991	 724.8	 81.5	 872	 226	 0.26	 0.31

Capacity - 900 MWe	 1992	 661.8	 74.9	 930	 213	 0.23	 0.32

1993	 913.0	 99.7	 327	 31	 0.09	 0.03

1994	 740.8	 82.7	 1,089	 222	 0.20	 0.30

1995	 731.1	 83.8	 1,068	 174	 0.16	 0.24

1996	 860.6	 95.4	 444	 17	 0.04	 0.02

1997	 673.6	 80.4	 1,131	 149	 0.13	 0.22

1998	 766.2	 90.4	 931	 133	 0.14	 0.17

1999	 827.0	 97.9	 247	 16	 0.06	 0.02

2000	 783.0	 92.5	 888	 101	 0.11	 0.13	 	

2001	 611.2	 72.4	 1,586	 252	 0.16	 0.41

2002	 892.0	 99.4	 145	 7	 0.05	 0.01	 	

2003	 823.9	 93.2	 786	 68	 0.09	 0.08

2004	 797.9	 88.2	 747	 57	 0.08	 0.07

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 - 869, 883 MWe	 1982	 768.0	 56.6	 3,418	 1,460	 0.43	 1.90

1983	 934.7	 68.6	 3,428	 1,299	 0.38	 1.39

1984	 658.6	 47.3	 4,110	 2,218	 0.54	 3.37

1985	 1,211.0	 79.6	 2,841	 818	 0.29	 0.68

1986	 872.0	 64.8	 3,486	 1,497	 0.43	 1.72

1987	 1,295.4	 89.7	 2,202	 816	 0.37	 0.63

1988	 1,001.4	 70.4	 2,509	 1,401	 0.56	 1.40

1989	 1,271.1	 87.1	 1,350	 556	 0.41	 0.44

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

1991	 1,152.4	 77.4	 2,508	 1,161	 0.46	 1.01

1992	 1,293.8	 88.6	 1,615	 550	 0.34	 0.43

1993	 1,189.6	 85.5	 1,733	 669	 0.39	 0.56

1994	 1,289.0	 87.1	 2,243	 864	 0.39	 0.67

1995	 1,376.3	 90.6	 1,458	 488	 0.33	 0.35

1996	 1,519.6	 94.0	 1,495	 441	 0.29	 0.29

1997	 1,374.7	 88.1	 1,945	 722	 0.37	 0.53

1998	 1,458.4	 91.7	 1,610	 320	 0.20	 0.22

1999	 1,487.4	 90.0	 1,866	 329	 0.18	 0.22

2000	 1,515.0	 88.7	 1,913	 402	 0.21	 0.26

2001	 1,603.0	 93.5	 1,407	 230	 0.16	 0.14

2002	 1,600.0	 94.0	 1,299	 214	 0.17	 0.13	 	

2003	 1,606.3	 94.5	 1,295	 168	 0.13	 0.10

2004	 1,641.3	 95.3	 1,209	 180	 0.15	 0.11

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

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-15

Thirty-Seventh Annual Report, 2004 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

HOPE CREEK 1 1994	 852.0	 81.2	 1,779	 326	 0.18	 0.38

(continued)	 1995	 844.5	 79.8	 1,571	 196	 0.12	 0.23

1996	 806.9	 77.4	 1,069	 158	 0.15	 0.20

1997	 731.8	 77.8	 1,747	 350	 0.20	 0.48

1998	 993.2	 98.0	 620	 55	 0.09	 0.06

1999	 879.1	 86.7	 1,111	 279	 0.25	 0.32

2000	 827.8	 87.9	 1,236	 188	 0.15	 0.23

2001	 918.2	 91.1	 1,532	 156	 0.10	 0.17

2002	 1,007.0	 99.2	 220	 26	 0.12	 0.03	 	

2003	 826.6	 84.6	 1,597	 139	 0.09	 0.17

2004	 688.6	 71.3	 2,440	 240	 0.10	 0.35

HUMBOLDT BAY6 1969	 44.6	 	 125	 164	 1.31	 3.68

Docket 50-133; DPR-7	 1970	 49.3	 	 115	 209	 1.82	 4.24

1st commercial operation 8/63	 1971	 39.6	 	 140	 292	 2.09	 7.37

Type - BWR	 1972	 43.1	 	 127	 253	 1.99	 5.87

Capacity - (63) MWe	 1973	 50.1	 	 210	 266	 1.27	 5.31

1974	 43.4	 83.8	 296	 318	 1.07	 7.33

1975	 45.3	 83.9	 265	 339	 1.28	 7.48

1976	 23.5	 46.4	 523	 683	 1.31	 29.06

1977	 0.0	 0.0	 1,063	 1,905	 1.79	 ---

1978	 0.0	 0.0	 320	 335	 1.05	 ---

1979	 0.0	 0.0	 135	 31	 0.23	 ---

1980	 0.0	 0.0	 142	 22	 0.15	 ---

1981	 0.0	 0.0	 75	 9	 0.12	 ---

1982	 0.0	 0.0	 71	 19	 0.27	 ---

1983	 0.0	 0.0	 84	 17	 0.20	 ---

1993	 0.0	 0.0	 24	 1	 0.04	 ---

1994	 0.0	 0.0	 21	 1	 0.05	 ---

1995	 0.0	 0.0	 42	 2	 0.05	 ---

1996	 0.0	 0.0	 66	 5	 0.08	 ---

1997	 0.0	 0.0	 105	 16	 0.15	 ---

1998	 0.0	 0.0	 38	 1	 0.03	 ---

1999	 0.0	 0.0	 28	 1	 0.04	 ---

2000	 0.0	 0.0	 20	 1	 0.05	 ---

2001	 0.0	 0.0	 10	 0	 0.04	 ---

2002	 0.0	 0.0	 18	 2	 0.08	 ---	 	

2003	 0.0	 0.0	 14	 0	 0.03	 ---

2004	 0.0	 0.0	 11	 0	 0.04	 ---

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), 956, 979 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

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

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

operational.

7 Indian Point 1 was defueled in 1975, and in 1984 it was decided that it would not be placed in operation again. Therefore,

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

8 Indian Point 3 was purchased by a different utility in 1979 and subsequently reported its dose separately. Although Indian

Point 1, 2, and 3 have been owned by the same utlity since 2001, Indian Point 3 still reports separately.
C-16

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

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 17, 2 1979	 574.0	 71.4	 1,349	 1,279	 0.95	 2.23

Docket 50-3, 50-247; DPR-05, -26	 1980	 510.8	 64.8	 1,577	 971	 0.62	 1.90

1st commercial operation	 1982	 532.4	 65.4	 2,144	 1,635	 0.76	 3.07

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

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

Capacity - (265), 956 MWe	 1985	 791.4	 95.7	 708	 192	 0.27	 0.24

1986	 457.5	 56.2	 1,926	 1,250	 0.65	 2.73

1987	 611.4	 73.4	 1,980	 1,217	 0.61	 1.99

1988	 719.3	 86.9	 890	 235	 0.26	 0.33

1989	 532.5	 64.6	 2,093	 1,436	 0.69	 2.70

1990	 618.0	 66.6	 1,061	 608	 0.57	 0.98

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

1998	 282.8	 31.5	 1,154	 290	 0.25	 1.03

1999	 831.8	 88.2	 350	 41	 0.12	 0.05

2000	 115.4	 13.0	 2,003	 567	 0.28	 4.90

2001	 887.2	 97.2	 399	 22	 0.06	 0.02

2002	 860.0	 91.3	 1,361	 248	 0.18	 0.29	 	

2003	 953.0	 98.9	 241	 12	 0.05	 0.01

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

Docket 50-3; DPR-05	

1st commercial operation 10/62	

Type - PWR	

Capacity - (265) MWe

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

Docket 50-247; DPR-26

1st commercial operation 8/74	

Type - PWR	

Capacity - 956 MWe

INDIAN POINT 38 1979	 574.0	 66.5	 808	 636	 0.79	 1.11

Docket 50-286; DPR-64	 1980	 367.3	 53.2	 977	 308	 0.32	 0.84

1st commercial operation 8/76	 1981	 367.5	 59.8	 677	 364	 0.54	 0.99

Type - PWR	 1982	 171.5	 22.5	 1,477	 1,226	 0.83	 7.15

Capacity - 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

7 Indian Point 1 was defueled in 1975, and in 1984 it was decided that it would not be placed in operation again. Therefore,

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

8 Indian Point 3 was purchased by a different utility in 1979 and subsequently reported its dose separately. Although Indian

Point 1, 2, and 3 have been owned by the same utlity since 2001, Indian Point 3 still reports separately.
C-17

Thirty-Seventh Annual Report, 2004 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

INDIAN POINT 38 2000	 960.0	 99.3	 143	 9	 0.06	 0.01

(continued) 2001	 903.9	 93.1	 1,014	 118	 0.12	 0.13

2002	 960.0	 98.5	 156	 7	 0.04	 0.01	 	

2003	 866.2	 89.8	 902	 96	 0.11	 0.11

2004	 995.8	 100.0	 234	 4	 0.02	 ---

KEWAUNEE 1975	 401.9	 88.2	 104	 28	 0.27	 0.07

Docket 50-305; DPR-43	 1976	 405.9	 78.9	 381	 270	 0.71	 0.67

1st commercial operation 6/74	 1977	 425.0	 79.9	 312	 140	 0.45	 0.33

Type - PWR	 1978	 466.6	 89.5	 335	 154	 0.46	 0.33

Capacity - 556 MWe	 1979	 412.0	 79.0	 343	 127	 0.37	 0.31

1980	 433.8	 82.1	 401	 165	 0.41	 0.38

1981	 451.8	 86.7	 383	 141	 0.37	 0.31

1982	 458.4	 87.6	 353	 101	 0.29	 0.22

1983	 444.1	 83.7	 445	 165	 0.37	 0.37

1984	 455.3	 85.7	 482	 139	 0.29	 0.31

1985	 443.1	 82.4	 519	 176	 0.34	 0.40

1986	 461.7	 85.8	 502	 169	 0.34	 0.37

1987	 480.0	 89.7	 755	 226	 0.30	 0.47

1988	 467.5	 88.3	 705	 210	 0.30	 0.45

1989	 449.1	 84.9	 570	 239	 0.42	 0.53

1990	 468.8	 87.9	 490	 145	 0.30	 0.31

1991	 441.8	 83.4	 495	 221	 0.45	 0.50

1992	 471.4	 88.0	 450	 122	 0.27	 0.26

1993	 457.1	 86.8	 436	 106	 0.24	 0.23

1994	 475.6	 88.8	 364	 72	 0.20	 0.15

1995	 455.6	 87.8	 415	 109	 0.26	 0.24

1996	 380.4	 71.8	 474	 126	 0.27	 0.33

1997	 269.8	 56.0	 278	 56	 0.20	 0.21

1998	 423.0	 87.2	 284	 88	 0.23	 0.21

1999	 505.1	 100.0	 103	 5	 0.05	 0.01

2000	 432.6	 88.8	 394	 100	 0.25	 0.23

2001	 394.1	 80.8	 1,110	 200	 0.18	 0.51

2002	 509.0	 97.4	 102	 4	 0.04	 0.01	 	

2003	 473.5	 90.5	 439	 73	 0.17	 0.15

2004	 441.0	 81.0	 565	 91	 0.16	 0.21

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	 ---

8 Indian Point 3 was purchased by a different utility in 1979 and subsequently reported its dose separately. Although Indian

Point 1, 2, and 3 have been owned by the same utlity since 2001, Indian Point 3 still reports separately.

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-Seventh Annual Report, 2004

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

LACROSSE9 1995	 0.0	 0.0	 31	 3	 0.10	 ---

(continued)	 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	 ---

2004	 0.0	 0.0	 56	 1	 0.02	 ---

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

2004	 2,162.1	 96.0	 2,366	 359	 0.15	 0.17

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

2004	 2,218.9	 97.6	 1,265	 149	 0.12	 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

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.

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-Seventh Annual Report, 2004 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

MAINE YANKEE10 1978	 642.7	 84.1	 638	 420	 0.66	 0.65

(continued) 1979	 537.0	 68.4	 393	 154	 0.39	 0.29

1980	 527.0	 72.2	 735	 462	 0.63	 0.88

1981	 624.2	 78.2	 868	 424	 0.49	 0.68

1982	 542.5	 69.1	 1,295	 619	 0.48	 1.14

1983	 677.1	 83.6	 592	 165	 0.28	 0.24

1984	 605.7	 74.4	 1,262	 884	 0.70	 1.46

1985	 635.4	 79.2	 1,009	 700	 0.69	 1.10

1986	 737.6	 87.8	 495	 100	 0.20	 0.14

1987	 478.1	 65.3	 1,100	 722	 0.66	 1.51

1988	 591.9	 79.1	 1,058	 725	 0.69	 1.22

1989	 819.2	 93.7	 375	 99	 0.26	 0.12

1990	 573.0	 71.0	 1,359	 682	 0.50	 1.19

1991	 738.1	 86.6	 426	 105	 0.25	 0.14

1992	 631.7	 79.1	 1,189	 461	 0.39	 0.73

1993	 674.8	 79.8	 1,016	 377	 0.37	 0.56

1994	 782.8	 90.9	 297	 84	 0.28	 0.11

1995	 23.6	 3.7	 1,167	 653	 0.56	 27.67

1996	 602.9	 78.1	 408	 56	 0.14	 0.09

1997	 0.0	 0.0	 991	 153	 0.15	 ---

1998	 0.0	 0.0	 438	 163	 0.37	 ---

1999	 0.0	 0.0	 365	 135	 0.37	 ---

2000	 0.0	 0.0	 490	 121	 0.25	 ---

2001	 0.0	 0.0	 412	 68	 0.17	 ---

2002	 0.0	 0.0	 452	 66	 0.15	 ---	 	

2003	 0.0	 0.0	 342	 44	 0.13	 ---

2004	 0.0	 0.0	 190	 21	 0.11	 ---

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

2004	 2,075.7	 91.8	 1,116	 196	 0.18	 0.09

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

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.

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-Seventh Annual Report, 2004

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 111 1977	 575.7	 89.6	 1,075	 394	 0.37	 0.68

(continued) 1978	 556.6	 87.6	 1,391	 1,416	 1.02	 2.54

1979	 505.0	 77.3	 2,001	 1,795	 0.90	 3.55

1980	 405.8	 69.0	 3,024	 2,157	 0.71	 5.32

1981	 304.3	 51.6	 2,506	 1,496	 0.60	 4.92

1982	 490.2	 79.9	 1,370	 929	 0.68	 1.90

1983	 640.1	 95.6	 309	 244	 0.79	 0.38

1984	 516.1	 78.8	 1,992	 836	 0.42	 1.62

1985	 548.5	 83.6	 732	 608	 0.83	 1.11

1986	 626.8	 95.4	 389	 150	 0.39	 0.24

1987	 523.4	 79.6	 1,588	 684	 0.43	 1.31

1988	 658.8	 98.6	 327	 144	 0.44	 0.22

1989	 554.6	 84.2	 852	 462	 0.54	 0.83

1990	 608.3	 91.6	 365	 131	 0.36	 0.22

1991	 213.1	 35.4	 1,154	 409	 0.35	 1.92

1992	 431.8	 68.1	 348	 99	 0.28	 0.23

1993	 627.9	 96.8	 305	 81	 0.27	 0.13

1994	 394.0	 63.6	 1,321	 391	 0.30	 0.99

1995	 520.6	 80.0	 910	 620	 0.68	 1.19

1996	 0.0	 0.0	 747	 431	 0.58	 ---

1997	 -2.9	 0.0	 1,053	 195	 0.19	 ---

1998	 -2.7	 0.0	 347	 13	 0.04	 ---

1999	 0.0	 0.0	 397	 10	 0.02	 ---

2000	 0.0	 0.0	 478	 60	 0.13	 ---

2001	 0.0	 0.0	 414	 15	 0.04	 ---

2002	 0.0	 0.0	 185	 4	 0.02	 ---

2003	 0.0	 0.0	 195	 11	 0.05	 ---

2004	 0.0	 0.0	 147	 11	 0.08	 ---

MILLSTONE UNIT 2, 3 1976	 545.7	 78.7	 620	 168	 0.27	 0.31

Docket 50-336, 50-423;	 1977	 518.7	 65.7	 667	 242	 0.36	 0.47

DPR-65, NPF-49	 1978	 536.6	 67.3	 1,420	 1,444	 1.02	 2.69

1st commercial operation	 1979	 520.0	 62.8	 525	 471	 0.90	 0.91

12/75, 4/86	 1980	 579.3	 69.2	 893	 637	 0.71	 1.10

Type - PWRs	 1981	 722.4	 82.6	 890	 531	 0.60	 0.74

Capacity - 878, 1148 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

2004	 1,887.5	 95.0	 803	 136	 0.17	 0.07

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-21

Thirty-Seventh Annual Report, 2004 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

MONTICELLO 1972	 424.4	 99	 61	 0.62	 0.14

Docket 50-263; DPR-22	 1973	 389.5	 	 401	 176	 0.44	 0.45

1st commercial operation 6/71	 1974	 349.3	 74.9	 842	 349	 0.41	 1.00

Type - BWR	 1975	 344.8	 72.2	 1,353	 1,353	 1.00	 3.92

Capacity - 578 MWe	 1976	 476.4	 91.5	 325	 263	 0.81	 0.55

1977	 425.6	 79.9	 860	 1,000	 1.16	 2.35

1978	 459.4	 87.2	 679	 375	 0.55	 0.82

1979	 522.0	 97.6	 372	 157	 0.42	 0.30

1980	 411.8	 78.2	 1,114	 531	 0.48	 1.29

1981	 389.3	 72.6	 1,446	 1,004	 0.69	 2.58

1982	 291.1	 63.3	 1,307	 993	 0.76	 3.41

1983	 494.6	 96.3	 416	 121	 0.29	 0.24

1984	 33.7	 9.2	 1,872	 2,462	 1.32	 73.06

1985	 509.8	 91.7	 586	 327	 0.56	 0.64

1986	 402.7	 79.1	 895	 596	 0.67	 1.48

1987	 422.5	 81.9	 941	 568	 0.60	 1.34

1988	 542.5	 99.8	 375	 110	 0.29	 0.20

1989	 318.2	 76.2	 1,102	 507	 0.46	 1.59

1990	 536.0	 96.9	 336	 94	 0.28	 0.18

1991	 429.4	 80.8	 964	 465	 0.48	 1.08

1992	 528.3	 97.5	 454	 114	 0.25	 0.22

1993	 458.1	 84.4	 954	 494	 0.52	 1.08

1994	 471.3	 87.0	 788	 395	 0.50	 0.84

1995	 564.7	 100.0	 200	 44	 0.22	 0.08

1996	 461.6	 86.9	 757	 240	 0.32	 0.52

1997	 417.4	 75.9	 399	 106	 0.27	 0.25

1998	 470.2	 88.1	 674	 209	 0.31	 0.44

1999	 530.7	 92.9	 451	 70	 0.16	 0.13

2000	 483.2	 84.2	 792	 216	 0.27	 0.45

2001	 441.3	 78.5	 834	 221	 0.26	 0.50

2002	 571.0	 99.0	 399	 40	 0.10	 0.07

2003	 522.8	 91.7	 858	 169	 0.20	 0.32

2004	 573.2	 99.2	 279	 35	 0.13	 0.06

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
C-22

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

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	 1997	 1,321.5	 74.8	 1,425	 429	 0.30	 0.32

(continued)	 1998	 1,387.3	 87.0	 1,744	 378	 0.22	 0.27

1999	 1,409.5	 81.3	 1,709	 447	 0.26	 0.32

2000	 1,443.9	 88.1	 1,783	 283	 0.16	 0.20

2001	 1,506.9	 88.9	 1,371	 343	 0.25	 0.23

2002	 1,517.0	 90.4	 2,449	 517	 0.21	 0.34

2003	 1,585.6	 91.4	 1,501	 375	 0.25	 0.24

2004	 1,551.9	 92.0	 1,362	 449	 0.33	 0.29

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

2004	 1,685.6	 92.0	 965	 130	 0.13	 0.08

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
C-23

Thirty-Seventh Annual Report, 2004 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

OCONEE 1, 2, 3 2000	 2,321.0	 91.6	 1,686	 273	 0.16	 0.12

(continued)	 2001	 2,167.6	 86.8	 2,002	 579	 0.29	 0.27

2002	 2,355.0	 92.5	 1,723	 225	 0.13	 0.10

2003	 2,177.7	 86.3	 2,180	 245	 0.11	 0.11

2004	 2,125.2	 84.1	 2,295	 368	 0.16	 0.17

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

1999	 615.1	 100.0	 466	 42	 0.09	 0.07

2000	 444.9	 83.3	 2,044	 614	 0.30	 1.38

2001	 595.0	 97.6	 442	 46	 0.10	 0.08

2002	 573.0	 94.0	 1,468	 266	 0.18	 0.46	 	

2003	 598.4	 97.2	 416	 43	 0.10	 0.07

2004	 551.8	 91.6	 1,346	 227	 0.17	 0.41

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
C-24

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

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

PALISADES 1992	 581.9	 76.1	 1,267	 295	 0.23	 0.51

(continued)	 1993	 424.4	 53.7	 908	 289	 0.32	 0.68

1994	 541.8	 67.0	 397	 60	 0.15	 0.11

1995	 583.5	 75.8	 1,230	 462	 0.38	 0.79

1996	 638.2	 81.4	 1,109	 318	 0.29	 0.50

1997	 662.5	 89.9	 338	 48	 0.14	 0.07

1998	 615.4	 83.5	 895	 217	 0.24	 0.35

1999	 585.4	 80.2	 939	 218	 0.23	 0.37

2000	 654.4	 88.0	 255	 26	 0.10	 0.04

2001	 268.2	 36.3	 1,032	 363	 0.35	 1.35

2002	 725.0	 94.8	 224	 24	 0.11	 0.03	 	

2003	 701.1	 90.7	 822	 203	 0.25	 0.29

2004	 608.6	 82.3	 974	 371	 0.38	 0.61

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, 1335, 	 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

2004	 3,201.4	 86.3	 1,324	 199	 0.15	 0.06

PEACH BOTTOM 2, 3	 1975	 1,234.3	 80.9	 971	 228	 0.23	 0.18

Docket 50-277, 50-278;	 1976	 1,379.2	 73.0	 2,136	 840	 0.39	 0.61

DPR-44, -56	 1977	 1,052.4	 58.7	 2,827	 2,036	 0.72	 1.93

1st commercial operation	 1978	 1,636.3	 84.0	 2,244	 1,317	 0.59	 0.80

7/74, 12/74	 1979	 1,740.0	 84.5	 2,276	 1,388	 0.61	 0.80

Type - BWRs	 1980	 1,374.2	 66.3	 2,774	 2,302	 0.83	 1.68

Capacity - 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

2004	 2,148.8	 96.4	 1,422	 265	 0.19	 0.12
C-25

Thirty-Seventh Annual Report, 2004 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

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

2004	 1,164.3	 95.9	 496	 73	 0.15	 0.06

PILGRIM 1 1973	 484.0	 	 230	 126	 0.55	 0.26

Docket 50-293; DPR-35	 1974	 234.1	 39.2	 454	 415	 0.91	 1.77

1st commercial operation 12/72	 1975	 308.1	 71.3	 473	 798	 1.69	 2.59

Type - BWR	 1976	 287.8	 60.7	 1,317	 2,648	 2.01	 9.20

Capacity - 685 MWe	 1977	 316.6	 61.4	 1,875	 3,142	 1.68	 9.92

1978	 519.5	 83.1	 1,667	 1,327	 0.80	 2.55

1979	 574.0	 89.4	 2,458	 1,015	 0.41	 1.77

1980	 360.3	 56.2	 3,549	 3,626	 1.02	 10.06

1981	 408.9	 65.9	 2,803	 1,836	 0.66	 4.49

1982	 389.9	 63.9	 2,854	 1,539	 0.54	 3.95

1983	 559.5	 87.2	 2,326	 1,162	 0.50	 2.08

1984	 1.4	 0.4	 4,542	 4,082	 0.90	 2915.71

1985	 587.3	 91.5	 2,209	 893	 0.40	 1.52

1986	 121.9	 18.8	 2,635	 874	 0.33	 7.17

1987	 0.0	 0.0	 4,710	 1,579	 0.34	 ---

1988	 0.0	 0.0	 2,073	 392	 0.19	 ---

1989	 204.6	 64.1	 1,797	 207	 0.12	 1.01

1990	 503.5	 82.1	 1,898	 225	 0.12	 0.45

1991	 406.3	 65.8	 2,836	 605	 0.21	 1.49

1992	 561.0	 85.4	 1,332	 281	 0.21	 0.50

1993	 513.7	 80.9	 1,328	 435	 0.33	 0.85

1994	 453.6	 71.4	 758	 200	 0.26	 0.44

1995	 531.7	 80.7	 1,294	 482	 0.37	 0.91

1996	 631.3	 95.4	 517	 116	 0.22	 0.18

1997	 492.1	 80.7	 1,655	 588	 0.36	 1.19

1998	 650.5	 100.0	 530	 71	 0.13	 0.11

1999	 510.7	 84.4	 1,222	 344	 0.28	 0.67

2000	 627.5	 98.3	 422	 51	 0.12	 0.08

2001	 585.6	 91.0	 1,113	 180	 0.16	 0.31

2002	 657.0	 100.0	 463	 38	 0.08	 0.06	 	

2003	 566.6	 87.5	 1,437	 250	 0.17	 0.44

2004	 676.1	 99.5	 427	 41	 0.10	 0.06

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
C-26

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

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

POINT BEACH 1, 2 1983	 648.2	 72.7	 1,702	 1,403	 0.82	 2.16

(continued)	 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

2004	 912.3	 90.1	 627	 110	 0.17	 0.12

PRAIRIE ISLAND 1, 2 1974	 181.9	 43.9	 150	 18	 0.12	 0.10

Docket 50-282, 50-306;	 1975	 836.0	 83.3	 477	 123	 0.26	 0.15

DPR-42, -60	 1976	 725.2	 76.6	 818	 447	 0.55	 0.62

1st commercial operation 	 1977	 922.9	 87.2	 718	 300	 0.42	 0.33

12/73, 12/74	 1978	 941.1	 92.2	 546	 221	 0.40	 0.23

Type - PWRs	 1979	 865.0	 86.0	 594	 180	 0.30	 0.21

Capacity - 522, 522 MWe	 1980	 800.7	 79.9	 983	 353	 0.36	 0.44

1981	 844.9	 80.5	 836	 329	 0.39	 0.39

1982	 944.9	 90.4	 645	 229	 0.36	 0.24

1983	 921.1	 86.8	 654	 233	 0.36	 0.25

1984	 972.4	 91.7	 546	 147	 0.27	 0.15

1985	 882.6	 84.0	 1,082	 416	 0.38	 0.47

1986	 930.6	 90.3	 818	 255	 0.31	 0.27

1987	 969.6	 91.6	 593	 135	 0.23	 0.14

1988	 932.0	 89.1	 732	 199	 0.27	 0.21

1989	 1,001.8	 94.7	 476	 99	 0.21	 0.10

1990	 925.4	 89.2	 737	 188	 0.26	 0.20

1991	 1,023.3	 95.6	 586	 98	 0.17	 0.10

1992	 811.6	 76.2	 845	 211	 0.25	 0.26

1993	 978.3	 90.7	 532	 106	 0.20	 0.11

1994	 996.9	 91.5	 478	 109	 0.10	 0.11

1995	 1,023.2	 93.9	 499	 107	 0.21	 0.10

1996	 992.1	 91.4	 558	 112	 0.20	 0.11

1997	 817.6	 81.4	 753	 174	 0.23	 0.21

1998	 860.3	 83.4	 582	 117	 0.20	 0.14

1999	 989.3	 93.8	 542	 72	 0.13	 0.07

2000	 992.2	 93.1	 632	 106	 0.17	 0.11

2001	 900.8	 85.8	 691	 125	 0.18	 0.14

2002	 987.0	 93.6	 969	 128	 0.13	 0.13

2003	 1,006.1	 96.4	 594	 61	 0.10	 0.06

2004	 940.4	 89.9	 1,186	 144	 0.12	 0.15

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
C-27

Thirty-Seventh Annual Report, 2004 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

QUAD CITIES 1, 2 1981	 1,156.9	 81.1	 2,246	 3,146	 1.40	 2.72

(continued) 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

2004	 1,443.8	 95.5	 2,334	 511	 0.22	 0.35

RANCHO SECO12 1976	 268.1	 30.4	 297	 58	 0.20	 0.22

Docket 50-312; DPR-54	 1977	 706.4	 77.1	 515	 391	 0.76	 0.55

1st commercial operation 4/75	 1978	 607.7	 80.5	 508	 323	 0.64	 0.53

Type - PWR	 1979	 687.0	 91.1	 287	 126	 0.44	 0.18

Capacity - (873) MWe	 1980	 530.9	 60.4	 890	 412	 0.46	 0.78

1981	 321.2	 40.2	 772	 402	 0.52	 1.25

1982	 409.5	 53.3	 766	 337	 0.44	 0.82

1983	 347.9	 46.8	 1,338	 787	 0.59	 2.26

1984	 460.0	 58.3	 802	 222	 0.28	 0.48

1985	 238.7	 30.8	 1,764	 756	 0.43	 3.17

1986	 0.0	 0.0	 1,513	 402	 0.27	 ---

1987	 0.0	 0.0	 1,533	 300	 0.20	 ---

1988	 355.8	 63.1	 693	 78	 0.11	 0.22

1989	 179.9	 54.7	 603	 81	 0.13	 0.45

1990	 0.0	 0.0	 111	 13	 0.12	 ---

1991	 0.0	 0.0	 101	 9	 0.09	 ---

1992	 0.0	 0.0	 70	 7	 0.10	 ---

1993	 0.0	 0.0	 35	 4	 0.11	 ---

1994	 0.0	 0.0	 18	 1	 0.06	 ---

1995	 0.0	 0.0	 16	 1	 0.06	 ---

1996	 0.0	 0.0	 16	 1	 0.04	 ---

1997	 0.0	 0.0	 16	 0	 0.00	 ---

1998	 0.0	 0.0	 61	 3	 0.05	 ---

1999	 0.0	 0.0	 302	 11	 0.04	 ---

2000	 0.0	 0.0	 219	 26	 0.12	 ---

2001	 0.0	 0.0	 210	 18	 0.09	 ---

2002	 0.0	 0.0	 193	 27	 0.14	 ---	 	

2003	 0.0	 0.0	 121	 18	 0.15	 ---

2004	 0.0	 0.0	 122	 15	 0.12	 ---

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-Seventh Annual Report, 2004

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

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

2004	 845.6	 90.1	 1,378	 236	 0.17	 0.28

ROBINSON 2 1972	 580.0	 	 245	 215	 0.88	 0.37

Docket 50-261; DPR-23	 1973	 455.1	 	 831	 695	 0.84	 1.53

1st commercial operation 3/71	 1974	 578.1	 83.3	 853	 672	 0.79	 1.16

Type - PWR	 1975	 501.8	 72.7	 849	 1,142	 1.35	 2.28

Capacity - 710 MWe	 1976	 585.5	 84.7	 597	 715	 1.20	 1.22

1977	 511.5	 85.2	 634	 455	 0.72	 0.89

1978	 480.5	 72.0	 943	 963	 1.02	 2.00

1979	 482.0	 70.8	 1,454	 1,188	 0.82	 2.46

1980	 387.3	 62.2	 2,009	 1,852	 0.92	 4.78

1981	 426.6	 73.0	 1,462	 733	 0.50	 1.72

1982	 277.5	 48.9	 2,011	 1,426	 0.71	 5.14

1983	 409.8	 75.5	 2,244	 923	 0.41	 2.25

1984	 28.0	 7.0	 4,127	 2,880	 0.70	 102.86

1985	 629.5	 87.9	 1,378	 311	 0.23	 0.49

1986	 577.1	 80.3	 1,571	 539	 0.34	 0.93

1987	 510.1	 72.5	 1,379	 499	 0.36	 0.98

1988	 385.0	 65.9	 1,351	 564	 0.42	 1.46

1989	 336.6	 48.7	 1,098	 195	 0.18	 0.58

1990	 400.3	 64.8	 1,626	 437	 0.27	 1.09

1991	 575.1	 81.4	 885	 193	 0.22	 0.34

1992	 487.2	 66.8	 1,267	 352	 0.28	 0.72

1993	 502.7	 70.7	 1,221	 337	 0.28	 0.67

1994	 560.3	 79.5	 420	 63	 0.15	 0.11

1995	 618.7	 84.7	 1,058	 215	 0.20	 0.35

1996	 654.8	 88.6	 1,031	 167	 0.16	 0.26

1997	 707.5	 99.0	 304	 13	 0.04	 0.02

1998	 628.5	 88.9	 978	 170	 0.17	 0.27

1999	 648.9	 91.8	 807	 124	 0.15	 0.19

2000	 710.0	 99.7	 138	 8	 0.06	 0.01

2001	 627.9	 90.6	 827	 125	 0.15	 0.20

2002	 638.0	 91.2	 830	 111	 0.13	 0.17	 	

2003	 733.1	 100.0	 109	 5	 0.04	 0.01

2004	 653.7	 89.3	 952	 118	 0.12	 0.18

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 - 1159, 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
C-29

Thirty-Seventh Annual Report, 2004 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

SALEM 1, 2 1987	 1,478.2	 73.3	 2,543	 600	 0.24	 0.41

(continued)	 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

2004	 1,850.2	 85.8	 1,496	 149	 0.10	 0.08

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

1982	 61.6	 15.7	 3,055	 832	 0.27	 13.51

1983	 0.0	 0.0	 1,701	 155	 0.09	 ---

1984	 670.4	 68.3	 7,514	 986	 0.27	 1.47

1985	 1,381.8	 132.9	 5,742	 722	 0.24	 0.52

1986	 1,698.2	 61.1	 3,594	 824	 0.24	 0.49

1987	 1,983.0	 78.8	 2,138	 696	 0.33	 0.35

1988	 1,982.3	 68.4	 2,324	 781	 0.34	 0.39

1989	 1,840.8	 64.9	 2,237	 567	 0.25	 0.31

1990	 1,980.5	 69.1	 2,224	 885	 0.40	 0.45

1991	 1,987.6	 75.3	 1,814	 412	 0.23	 0.21

1992	 2,228.6	 87.1	 1,651	 324	 0.20	 0.15

1993	 1,771.3	 79.9	 2,193	 767	 0.35	 0.43

1994	 2,220.7	 100.0	 528	 32	 0.06	 0.01

1995	 1,686.9	 79.1	 1,914	 455	 0.24	 0.27

1996	 2,089.3	 93.2	 1,272	 129	 0.10	 0.06

1997	 1,533.9	 72.9	 1,652	 341	 0.21	 0.22

1998	 1,996.4	 92.0	 1,091	 196	 0.18	 0.10

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

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

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

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

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

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

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-Seventh Annual Report, 2004

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 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	 2004	 1,713.8	 79.1	 1,761	 407	 0.23	 0.24

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

2004	 1,158.6	 100.0	 291	 6	 0.02	 0.01

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 - 1148, 1124 MWe	 1988	 490.8	 31.8	 2,441	 678	 0.28	 1.38

1989	 1,851.7	 85.7	 2,007	 657	 0.33	 0.35

1990	 1,662.6	 77.2	 2,935	 1,687	 0.57	 1.01

1991	 1,965.4	 88.0	 1,933	 700	 0.36	 0.36

1992	 1,849.0	 85.4	 1,714	 465	 0.27	 0.25

1993	 405.7	 21.8	 1,631	 373	 0.23	 0.92

1994	 1,418.7	 66.3	 1,702	 295	 0.17	 0.21

1995	 1,864.2	 86.1	 1,650	 368	 0.22	 0.20

1996	 2,003.9	 87.9	 1,444	 269	 0.19	 0.13

1997	 1,946.1	 89.0	 1,962	 420	 0.21	 0.22

1998	 2,135.3	 95.3	 1,530	 266	 0.17	 0.12

1999	 2,165.1	 97.0	 1,346	 165	 0.12	 0.08

2000	 1,910.0	 86.8	 2,039	 357	 0.18	 0.19

2001	 2,158.3	 95.7	 1,292	 145	 0.11	 0.07

2002	 2,106.0	 94.1	 1,257	 108	 0.09	 0.05	 	

2003	 1,776.4	 80.0	 2,484	 431	 0.17	 0.24

2004	 2,135.2	 93.9	 1,161	 86	 0.07	 0.04

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

2004	 2,437.1	 96.0	 842	 120	 0.14	 0.05
C-31

Thirty-Seventh Annual Report, 2004 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

ST. LUCIE 1, 2 1977	 649.1	 84.7	 445	 152	 0.34	 0.23

Docket 50-335, -389; 1978	 606.4	 76.5	 797	 337	 0.42	 0.56

DPR-67; NPF-16	 1979	 592.0	 74.0	 907	 438	 0.48	 0.74

1st commercial operation	 1980	 627.9	 77.5	 1,074	 532	 0.50	 0.85

12/76, 8/83	 1981	 599.1	 72.7	 1,473	 929	 0.63	 1.55

Type - PWRs	 1982	 816.8	 94.0	 1,045	 272	 0.26	 0.33

Capacity - 839, 839 MWe	 1983	 290.3	 15.4	 2,211	 1,204	 0.54	 4.15

1984	 1,183.0	 69.6	 2,090	 1,263	 0.60	 1.07

1985	 1,445.8	 82.5	 1,971	 1,344	 0.68	 0.93

1986	 1,588.6	 89.1	 1,279	 491	 0.38	 0.31

1987	 1,407.9	 81.9	 2,012	 951	 0.47	 0.68

1988	 1,639.7	 93.0	 1,448	 611	 0.42	 0.37

1989	 1,493.1	 85.1	 1,414	 495	 0.35	 0.33

1990	 1,188.4	 70.0	 1,876	 777	 0.41	 0.65

1991	 1,592.8	 90.8	 1,282	 479	 0.37	 0.30

1992	 1,511.9	 87.3	 1,251	 264	 0.21	 0.17

1993	 1,227.6	 77.7	 1,462	 492	 0.34	 0.40

1994	 1,424.8	 85.0	 1,896	 505	 0.27	 0.35

1995	 1,306.6	 76.0	 1,498	 413	 0.28	 0.32

1996	 1,473.4	 86.5	 1,433	 385	 0.27	 0.26

1997	 1,394.6	 83.6	 2,314	 646	 0.28	 0.46

1998	 1,572.5	 94.2	 1,170	 134	 0.11	 0.09

1999	 1,569.1	 93.8	 1,107	 177	 0.16	 0.11

2000	 1,630.0	 96.0	 990	 99	 0.10	 0.06

2001	 1,527.5	 91.6	 1,375	 228	 0.17	 0.15

2002	 1,633.0	 96.6	 992	 156	 0.16	 0.10	 	

2003	 1,524.7	 91.5	 937	 142	 0.15	 0.09

2004	 1,492.0	 89.3	 1,157	 159	 0.14	 0.11

SUMMER 1 1984	 504.6	 61.1	 1,120	 295	 0.26	 0.58

Docket 50-395; NPF-12	 1985	 627.7	 71.6	 1,201	 379	 0.32	 0.60

1st commercial operation 1/84	 1986	 853.7	 95.3	 392	 23	 0.06	 0.03

Type - PWR	 1987	 618.7	 71.0	 1,075	 560	 0.52	 0.91

Capacity - 966 MWe	 1988	 605.3	 69.1	 1,127	 511	 0.45	 0.84

1989	 652.4	 83.1	 374	 52	 0.14	 0.08

1990	 730.0	 83.9	 1,090	 376	 0.34	 0.52

1991	 642.5	 82.9	 984	 291	 0.30	 0.45

1992	 892.6	 97.4	 249	 27	 0.11	 0.03

1993	 728.3	 84.0	 1,121	 297	 0.26	 0.41

1994	 536.7	 69.5	 1,549	 374	 0.24	 0.70

1995	 899.8	 97.2	 257	 13	 0.05	 0.01

1996	 850.4	 90.3	 701	 97	 0.14	 0.11

1997	 829.7	 89.8	 820	 163	 0.20	 0.20

1998	 934.8	 98.8	 285	 14	 0.05	 0.01

1999	 842.0	 89.4	 827	 120	 0.15	 0.14

2000	 723.9	 76.6	 933	 167	 0.18	 0.23

2001	 769.3	 83.3	 486	 69	 0.14	 0.09

2002	 840.0	 87.9	 685	 60	 0.09	 0.07	 	

2003	 837.0	 87.4	 745	 71	 0.10	 0.08

2004	 938.4	 96.8	 200	 10	 0.05	 0.01

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
C-32

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

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

SURRY 1, 2 1983	 916.2	 61.3	 2,754	 3,220	 1.17	 3.51

(continued) 1984	 1,026.7	 71.0	 3,198	 2,247	 0.70	 2.19

1985	 1,166.4	 78.2	 3,206	 1,815	 0.57	 1.56

1986	 1,080.5	 69.0	 3,763	 2,356	 0.63	 2.18

1987	 1,132.7	 72.7	 2,675	 712	 0.27	 0.63

1988	 750.4	 50.0	 3,184	 1,542	 0.48	 2.05

1989	 489.3	 33.0	 3,100	 836	 0.27	 1.71

1990	 1,276.4	 83.9	 1,947	 575	 0.30	 0.45

1991	 1,271.9	 84.5	 1,547	 510	 0.33	 0.40

1992	 1,396.3	 88.9	 1,660	 539	 0.32	 0.39

1993	 1,283.1	 84.6	 1,402	 383	 0.27	 0.30

1994	 1,320.9	 85.2	 1,530	 378	 0.25	 0.29

1995	 1,333.0	 84.2	 1,883	 406	 0.22	 0.30

1996	 1,562.9	 93.1	 983	 209	 0.21	 0.13

1997	 1,380.3	 87.1	 1,335	 320	 0.24	 0.23

1998	 1,476.2	 91.6	 1,165	 189	 0.16	 0.13

1999	 1,483.0	 93.5	 995	 138	 0.14	 0.09

2000	 1,490.0	 92.7	 1,197	 193	 0.16	 0.13

2001	 1,441.5	 89.5	 1,243	 329	 0.26	 0.23

2002	 1,557.0	 96.0	 799	 88	 0.11	 0.06	 	

2003	 1,255.9	 79.7	 1,628	 326	 0.20	 0.26

2004	 1,537.9	 94.6	 1,028	 120	 0.12	 0.08

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 - 1135, 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

1992	 1,604.2	 79.7	 1,885	 724	 0.38	 0.45

1993	 1,602.1	 77.3	 1,488	 335	 0.23	 0.21

1994	 1,814.4	 85.4	 1,580	 442	 0.28	 0.24

1995	 1,850.8	 85.3	 1,773	 476	 0.27	 0.26

1996	 1,998.7	 90.7	 1,430	 289	 0.20	 0.14

1997	 1,918.9	 89.6	 1,646	 433	 0.26	 0.23

1998	 1,879.6	 88.3	 1,575	 361	 0.23	 0.19

1999	 1,896.0	 89.6	 1,787	 431	 0.24	 0.23

2000	 1,994.6	 92.6	 1,812	 331	 0.18	 0.17

2001	 2,027.6	 94.2	 1,807	 288	 0.16	 0.14

2002	 1,973.0	 91.6	 1,890	 260	 0.14	 0.13	 	

2003	 2,050.8	 93.4	 1,934	 250	 0.13	 0.12

2004	 2,058.8	 92.7	 2,144	 272	 0.13	 0.13

THREE MILE ISLAND 114, 215 1975	 675.9	 82.2	 131	 73	 0.56	 0.11

Docket 50-289, -320;	 1976	 530.0	 65.4	 819	 286	 0.35	 0.54

DPR-50, -73	 1977	 664.5	 80.9	 1,122	 360	 0.32	 0.54

1st commercial operation	 1978	 690.0	 85.1	 1,929	 504	 0.26	 0.73

9/74, 12/78	 1979	 266.0	 21.9	 3,975	 1,392	 0.35	 5.23

Type - PWRs	 1980	 0.0	 0.0	 2,328	 394	 0.17	 ---

Capacity - 802, (880) MWe	 1981	 0.0	 0.0	 2,103	 376	 0.18	 ---

1982	 0.0	 0.0	 2,123	 1,004	 0.47	 ---

1983	 0.0	 0.0	 1,592	 1,159	 0.73	 ---

1984	 0.0	 0.0	 1,079	 688	 0.64	 ---

1985	 103.6	 10.6	 1,890	 857	 0.45	 8.27

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. Since 2001 the dose breakdowns for Three Mile Island 2 have been reported with those for Unit 1.
C-33

Thirty-Seventh Annual Report, 2004 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 114 1986	 585.2	 70.9	 1,360	 213	 0.16	 0.36

Docket 50-289; DPR-50	 1987	 610.7	 73.6	 1,259	 149	 0.12	 0.24

1st commercial operation 9/74	 1988	 661.0	 77.8	 1,012	 210	 0.21	 0.32

Type - PWR	 1989	 871.3	 100.0	 670	 54	 0.08	 0.06

Capacity - 802 MWe	 1990	 645.5	 84.6	 1,319	 264	 0.20	 0.41

1991	 688.7	 86.4	 1,542	 198	 0.13	 0.29

1992	 836.8	 100.0	 558	 34	 0.06	 0.04

1993	 722.0	 88.5	 1,835	 206	 0.11	 0.29

1994	 798.7	 95.5	 434	 40	 0.09	 0.05

1995	 772.9	 90.8	 1,220	 213	 0.17	 0.28

1996	 857.4	 100.0	 267	 16	 0.06	 0.02

1997	 675.7	 84.3	 1,049	 204	 0.19	 0.30

1998	 805.8	 100.0	 280	 17	 0.06	 0.02

1999	 722.4	 89.7	 1,171	 155	 0.13	 0.21

2000	 813.4	 100.0	 183	 9	 0.05	 0.01

2001	 616.7	 84.2	 1,196	 197	 0.16	 0.32

2002	 833.0	 100.0	 172	 7	 0.04	 0.01	 	

2003	 706.4	 87.1	 1,230	 155	 0.13	 0.22

2004	 828.0	 100.0	 ---	 ---	 0.00	 0.00	

THREE MILE ISLAND 215 1986	 0.0	 0.0	 1,497	 915	 0.61	 ---

Docket 50-320; DPR-73	 1987	 0.0	 0.0	 1,378	 977	 0.71	 ---

1st commercial operation 12/78	 1988	 0.0	 0.0	 1,247	 917	 0.74	 ---

Type - PWR	 1989	 0.0	 0.0	 1,014	 639	 0.63	 ---

Capacity - (880) MWe	 1990	 0.0	 0.0	 484	 136	 0.28	 ---

1991	 0.0	 0.0	 153	 37	 0.24	 ---

1992	 0.0	 0.0	 315	 157	 0.50	 ---

1993	 0.0	 0.0	 167	 33	 0.20	 ---

1994	 0.0	 0.0	 259	 7	 0.03	 ---

1995	 0.0	 0.0	 191	 2	 0.01	 ---

1996	 0.0	 0.0	 122	 2	 0.02	 ---

1997	 0.0	 0.0	 232	 1	 0.00	 ---

1998	 0.0	 0.0	 105	 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	 ---	 ---

2004	 0.0	 0.0	 105	 4	 0.03	 ---

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

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. Since 2001 the dose breakdowns for Three Mile Island 2 have been reported with those for Unit 1.

16	 Trojan ended commercial operation as of 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-Seventh Annual Report, 2004

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

TROJAN16 1992	 553.9	 68.4	 567	 84	 0.15	 0.15

(continued) 1993	 0.0	 68.4	 54	 21	 0.39	 ---

1994	 0.0	 0.0	 51	 9	 0.18	 ---

1995	 0.0	 0.0	 141	 44	 0.31	 ---

1996	 0.0	 0.0	 112	 41	 0.37	 ---

1997	 0.0	 0.0	 227	 41	 0.18	 ---

1998	 0.0	 0.0	 283	 46	 0.16	 ---

1999	 0.0	 0.0	 274	 52	 0.19	 ---

2000	 0.0	 0.0	 127	 18	 0.14	 ---

2001	 0.0	 0.0	 14	 1	 0.08	 ---

2002	 0.0	 0.0	 13	 1	 0.04	 ---	 	

2003	 0.0	 0.0	 105	 24	 0.23	 ---

2004	 0.0	 0.0	 5	 0	 0.02	 ---

TURKEY POINT 3, 4 1973	 401.9	 	 444	 78	 0.18	 0.19

Docket 50-250, 50-251;	 1974	 953.6	 	 794	 454	 0.57	 0.48

DPR-31, -41	 1975	 1,003.7	 74.9	 1,176	 876	 0.74	 0.87

1st commercial operation	 1976	 974.2	 71.2	 1,647	 1,184	 0.72	 1.22

12/72, 9/73	 1977	 979.5	 72.1	 1,319	 1,036	 0.79	 1.06

Type - PWRs	 1978	 1,000.2	 78.8	 1,336	 1,032	 0.77	 1.03

Capacity - 693, 693 MWe	 1979	 811.0	 62.4	 2,002	 1,680	 0.84	 2.07

1980	 990.6	 73.6	 1,803	 1,651	 0.92	 1.67

1981	 654.0	 46.8	 2,932	 2,251	 0.77	 3.44

1982	 915.7	 65.2	 2,956	 2,119	 0.72	 2.31

1983	 878.4	 62.8	 2,930	 2,681	 0.92	 3.05

1984	 946.7	 68.5	 2,010	 1,255	 0.62	 1.33

1985	 1,034.9	 74.7	 1,905	 1,253	 0.66	 1.21

1986	 754.1	 54.9	 1,808	 946	 0.52	 1.25

1987	 431.3	 36.6	 1,980	 1,371	 0.69	 3.18

1988	 809.8	 59.5	 1,841	 738	 0.40	 0.91

1989	 689.9	 56.8	 1,625	 433	 0.27	 0.63

1990	 933.1	 69.0	 2,099	 730	 0.35	 0.78

1991	 258.2	 21.0	 2,087	 939	 0.45	 3.64

1992	 968.9	 75.5	 1,374	 325	 0.24	 0.34

1993	 1,244.8	 91.0	 1,271	 275	 0.22	 0.22

1994	 1,172.9	 87.2	 1,489	 476	 0.32	 0.41

1995	 1,320.3	 94.6	 1,142	 215	 0.19	 0.16

1996	 1,307.8	 94.0	 1,157	 187	 0.16	 0.14

1997	 1,220.9	 88.6	 1,581	 414	 0.26	 0.34

1998	 1,323.0	 94.5	 1,045	 156	 0.15	 0.12

1999	 1,352.5	 96.5	 919	 128	 0.14	 0.09

2000	 1,283.7	 92.2	 1,292	 220	 0.17	 0.17

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

2004	 1,231.0	 89.9	 1,089	 117	 0.11	 0.10

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

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-35

Thirty-Seventh Annual Report, 2004 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

VERMONT YANKEE 1984	 398.1	 79.0	 954	 626	 0.66	 1.57

(continued)	 1985	 361.4	 71.8	 1,392	 1,051	 0.76	 2.91

1986	 248.1	 48.9	 1,389	 1,188	 0.86	 4.79

1987	 423.6	 84.2	 827	 303	 0.37	 0.72

1988	 492.1	 95.7	 379	 124	 0.33	 0.25

1989	 432.8	 84.7	 832	 288	 0.35	 0.67

1990	 433.1	 85.9	 849	 307	 0.36	 0.71

1991	 492.3	 94.3	 310	 118	 0.38	 0.24

1992	 446.8	 88.1	 921	 381	 0.41	 0.85

1993	 402.3	 80.1	 833	 217	 0.26	 0.54

1994	 515.8	 98.7	 220	 38	 0.17	 0.07

1995	 462.1	 87.0	 737	 182	 0.25	 0.39

1996	 452.7	 85.2	 951	 231	 0.24	 0.51

1997	 487.1	 96.0	 260	 57	 0.22	 0.12

1998	 383.4	 77.9	 944	 199	 0.21	 0.52

1999	 463.4	 91.0	 854	 176	 0.21	 0.38

2000	 517.8	 99.6	 198	 38	 0.19	 0.07

2001	 474.9	 93.5	 863	 143	 0.17	 0.30

2002	 451.0	 91.7	 946	 150	 0.16	 0.33	 	

2003	 505.9	 98.8	 359	 54	 0.15	 0.11

2004	 439.2	 87.2	 1,379	 212	 0.15	 0.48

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

2004	 2,200.7	 95.7	 765	 81	 0.11	 0.04

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

2004	 1,099.1	 100.0	 60	 3	 0.04	 ---
C-36

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

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

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

2004	 1,122.1	 99.1	 220	 6	 0.03	 0.01

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 - 1166 MWe	 1990	 940.2	 81.0	 798	 195	 0.24	 0.21

1991	 707.6	 71.9	 1,010	 331	 0.33	 0.47

1992	 1,010.8	 86.7	 446	 78	 0.17	 0.08

1993	 940.5	 80.6	 975	 183	 0.19	 0.19

1994	 1,017.2	 86.8	 1,082	 235	 0.22	 0.23

1995	 1,198.0	 98.7	 242	 14	 0.06	 0.01

1996	 980.6	 81.2	 986	 171	 0.17	 0.17

1997	 964.3	 83.8	 989	 265	 0.27	 0.27

1998	 1,187.3	 100.0	 184	 10	 0.05	 0.01

1999	 1,045.3	 90.1	 812	 148	 0.18	 0.14

2000	 1,032.7	 89.5	 861	 143	 0.17	 0.14

2001	 1,177.9	 100.0	 105	 5	 0.05	 0.00

2002	 1,029.0	 88.7	 816	 100	 0.12	 0.10	 	

2003	 1,013.5	 87.2	 820	 89	 0.11	 0.09

2004	 1,153.5	 98.8	 93	 3	 0.04	 ---

YANKEE ROWE17 1969	 138.3	 	 193	 215	 1.11	 1.55

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

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

Type - PWR	 1972	 78.7	 	 282	 255	 0.90	 3.24

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

1974	 111.3	 	 243	 205	 0.84	 1.84

1975	 145.1	 82.4	 249	 116	 0.47	 0.80

1976	 152.2	 89.8	 152	 59	 0.39	 0.39

1977	 124.6	 73.9	 725	 356	 0.49	 2.86

1978	 145.0	 81.0	 565	 282	 0.50	 1.94

1979	 149.0	 81.6	 441	 127	 0.29	 0.85

1980	 35.6	 22.0	 502	 213	 0.42	 5.98

1981	 109.0	 74.4	 515	 302	 0.59	 2.77

1982	 108.6	 73.4	 814	 474	 0.58	 4.36

1983	 163.5	 91.4	 395	 68	 0.17	 0.42

1984	 124.8	 71.4	 654	 348	 0.53	 2.79

1985	 144.3	 85.3	 653	 211	 0.32	 1.46

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	 ---

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.
C-37

Thirty-Seventh Annual Report, 2004 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

YANKEE ROWE17 1997	 0.0	 0.0	 323	 65	 0.20	 ---

(continued)	 1998	 0.0	 0.0	 125	 5	 0.04	 ---

1999	 0.0	 0.0	 83	 2	 0.02	 ---

2000	 0.0	 0.0	 38	 2	 0.06	 ---

2001	 0.0	 0.0	 48	 4	 0.08	 ---

2002	 0.0	 0.0	 128	 20	 0.16	 ---	 	

2003	 0.0	 0.0	 136	 31	 0.23	 ---

2004	 0.0	 0.0	 70	 7	 0.09	 ---

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	 ---

2004	 0.0	 0.0	 6	 0	 0.03	 ---

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.
C-38

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

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

This page intentionally left blank.
D-

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

NUREG-0713

DOSE PERFORMANCE INDICATORS BY REACTOR site

1973 - 2004

Appendix D*

* Appendix D only contains data on plants in operation during 2004.
D-

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

NUREG-0713

ARKANSAS 1, 2

Dose Performance Indicators

BEAVER VALLEY 1, 2

Dose Performance Indicators
DThirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

BRAIDWOOD 1, 2

Dose Performance Indicators

BROWNS FERRY 1, 2, 3

Dose Performance Indicators
D-

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

NUREG-0713

BRUNSWICK 1, 2

Dose Performance Indicators

BYRON 1, 2

Dose Performance Indicators
D-

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

NUREG-0713

CALLAWAY 1

Dose Performance Indicators

CALVERT CLIFFS 1, 2

Dose Performance Indicators
D-

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

NUREG-0713

CATAWBA 1, 2

Dose Performance Indicators

CLINTON

Dose Performance Indicators
DThirty-Seventh Annual Report, 2004 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

COLUMBIA GENERATING

Dose Performance Indicators

COMANCHE PEAK 1, 2

Dose Performance Indicators
D-

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

NUREG-0713

COOK 1, 2

Dose-Performance Indicators

COOPER STATION

Dose-Performance Indicators
D-

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

NUREG-0713

CRYSTAL RIVER 3

Dose-Performance Indicators

DAVIS-BESSE

Dose-Performance Indicators
D-10

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

NUREG-0713

DIABLO CANYON 1, 2

Dose Performance Indicators

DRESDEN 2, 3

Dose Performance Indicators
D-11

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

NUREG-0713

DUANE ARNOLD

Dose Performance Indicators

FARLEY 1, 2

Dose Performance Indicators
D-12

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

NUREG-0713

FERMI 2

Dose-Performance Indicators

FITZPATRICK

Dose-Performance Indicators
D-13

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

NUREG-0713

FORT CALHOUN

Dose-Performance Indicators

GINNA

Dose-Performance Indicators
D-14

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

NUREG-0713

GRAND GULF

Dose-Performance Indicators

HARRIS

Dose-Performance Indicators
D-15

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

NUREG-0713

HATCH 1, 2

Dose-Performance Indicators

HOPE CREEK 1

Dose-Performance Indicators
D-16

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

NUREG-0713

INDIAN POINT 2

Dose-Performance Indicators

INDIAN POINT 3

Dose-Performance Indicators
D-17

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

NUREG-0713

KEWAUNEE

Dose-Performance Indicators

LASALLE 1, 2

Dose-Performance Indicators
D-18

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

NUREG-0713

LIMERICK 1, 2

Dose-Performance Indicators

MCQUIRE 1, 2

Dose-Performance Indicators
D-19

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

NUREG-0713

MONTICELLO

Dose-Performance Indicators

MILLSTONE UNIT 2, 3

Dose-Performance Indicators
D-20

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

NUREG-0713

NORTH ANNA 1, 2

Dose-Performance Indicators

NINE MILE POINT 1, 2

Dose-Performance Indicators
D-21

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

NUREG-0713

OYSTER CREEK

Dose-Performance Indicators

OCONEE 1, 2, 3

Dose-Performance Indicators
D-22

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

NUREG-0713

PALO VERDE 1, 2, 3

Dose-Performance Indicators

PALISADES

Dose-Performance Indicators
D-23

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

NUREG-0713

PERRY

Dose-Performance Indicators

PEACH BOTTOM 2, 3

Dose-Performance Indicators
D-24

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

NUREG-0713

POINT BEACH 1, 2

Dose-Performance Indicators

PILGRIM

Dose-Performance Indicators
D-25

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

NUREG-0713

QUAD CITIES 1, 2

Dose-Performance Indicators

PRAIRIE ISLAND 1, 2

Dose-Performance Indicators
D-26

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

NUREG-0713

ROBINSON 2

Dose-Performance Indicators

RIVER BEND 1

Dose-Performance Indicators
D-27

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

NUREG-0713

NOTE: Since 2001, data only includes Units 2 and 3.

SAN ONOFRE 1, 2, 3

Dose-Performance Indicators

SALEM 1, 2

Dose-Performance Indicators
D-28

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

NUREG-0713

SEABROOK

Dose-Performance Indicators

SEQUOYAH 1, 2

Dose-Performance Indicators
D-29

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

NUREG-0713

ST. LUCIE 1, 2

Dose-Performance Indicators

SOUTH TEXAS 1, 2

Dose-Performance Indicators
D-30

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

NUREG-0713

SURRY 1, 2

Dose-Performance Indicators

SUMMER 1

Dose-Performance Indicators
D-31

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

NUREG-0713

SUSQUEHANNA 1, 2

Dose-Performance Indicators

THREE MILE ISLAND 1*

Dose-Performance Indicators

*Graph includes data for Three Mile Island 2 for the years 1975 - 1985.
D-32

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

NUREG-0713

TURKEY POINT 3, 4

Dose-Performance Indicators

VERMONT YANKEE

Dose-Performance Indicators
D-33

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

NUREG-0713

VOGTLE 1, 2

Dose-Performance Indicators

WATERFORD 3

Dose-Performance Indicators
D-34

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

NUREG-0713

WOLF CREEK 1

Dose-Performance Indicators

WATTS BAR 1

Dose-Performance Indicators