UN TI ED STATES NUCLEAR REGULATORY COMM SI S OI N

Occupational Radiation

Exposure at Commercial

Nuclear Power Reactors

and Other Facilities

2000

NUREG-0713

Vol. 22

Thirty-Third Annual Report

U.S. Nuclear Regulatory Commission

Office of Nuclear Regulatory Research

Washington, DC 20555-0001
AVAILABILITY OF REFERENCE MATERIALS

IN NRC PUBLICATIONS

Non-NRC Reference Material

Documents available from public and special

technical libraries include all open literature

items, such as books, journal articles, and

transactions, Federal Register notices, Federal

and State legislation, and congressional reports.

Such documents as theses, dissertations, foreign

reports and translations, and non-NRC

conference proceedings may be purchased from

their sponsoring organization.

Copies of industry codes and standards used in a

substantive manner in the NRC regulatory

process are maintained at—

The NRC Technical Library

Two White Flint North

11545 Rockville Pike

Rockville, MD 20852-2738

These standards are available in the library for

reference use by the public. Codes and

standards are usually copyrighted and may be

purchased from the originating organization or, if

they are American National Standards, from—

American National Standards Institute

11 West 42nd Street

New York, NY 10036-8002

www.ansi.org

212-642-4900

The NUREG series comprises (1) technical

and administrative reports and books

prepared by the staff (NUREG-XXXX) or

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

proceedings of conferences

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

from international agreements

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

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

legal decisions and orders of the Commission

and Atomic and Safety Licensing Boards and

of Directors’ decisions under Section 2.206 of

NRC’s regulations (NUREG-0750).

NRC Reference Material

As of November 1999, you may electronically

access NUREG-series publications and other

NRC records at NRC’s Public Electronic Reading

Room at www.nrc.gov/NRC/ADAMS/index.html.

Publicly released records include, to name a few,

NUREG-series publications; Federal Register

notices; applicant, licensee, and vendor

documents and correspondence; NRC

correspondence and internal memoranda;

bulletins and information notices; inspection and

investigative reports; licensee event reports; and

Commission papers and their attachments.

NRC publications in the NUREG series, NRC

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

Federal Regulations may also be purchased from

one of these two sources.

1. The Superintendent of Documents

U.S. Government Printing Office

P. 0. Box 37082

Washington, DC 20402-9328

www.access.gpo.gov/su-docs

202-512-1800

2. The National Technical Information Service

Springfield, VA 22161-0002

www.ntis.gov

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

A single copy of each NRC draft report for

comment is available free, to the extent of

supply, upon written request as follows:

Address: Office of the Chief Information Officer,

Reproduction and Distribution

Services Section

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

E-mail: DISTRIBUTION@nrc.gov

Facsimile: 301-415-2289

Some publications in the NUREG series that are

posted at NRC’s Web site address

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

are updated periodically and may differ from the

last printed version. Although references to

material found on a Web site bear the date the

material was accessed, the material available on

the date cited may subsequently be removed

from the site.
UN

TI ED STATES

NUCLEAR REGULATORY COMM SI S

OI N

Occupational Radiation Exposure

at Commercial Nuclear Power

Reactors and other Facilities

2000

NUREG-0713

Vol. 22

Thirty-Third 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: September 2001

Date Published: September 2001

Prepared by:

Sheryl Burrows, D. A. Hagemeyer*

Science Applications International Corporation

301 Laboratory Road

Oak Ridge, TN 37830

*
ii

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

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.

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-Third Annual Report, 2000 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.

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

doses reported as “not detectable.”

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

Regulatory Commission’s (NRC) Radiation Exposure Information and Reporting System

(REIRS). The bulk of the information contained in the report was compiled from the 2000

annual reports submitted by six 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 highlevel waste currently licensed, only six categories will be considered in this report.

Annual reports for 2000 were received from a total of 271 NRC licensees, of which 104 were

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

submitted by the 271 licensees indicated that 125,729 individuals were monitored, 65,584 of

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

individuals was 15,893 person-rem, which represents a 5% decrease from the 1999 value. The

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

measurable dose of 0.24 rem for 2000. The average measurable dose is defined as the total

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

 These

figures have been adjusted to account for transient reactor workers.

In calendar year 2000, the annual collective dose per reactor for light water reactor (LWR)

licensees was 122 person-rem. This represents a 7% decrease from the value reported for

1999. The annual collective dose per reactor for boiling water reactors (BWRs) was 174

person-rem and, for pressurized water reactors (PWRs), it was 95 person-rem.

Analyses of transient worker data indicate that 23,639 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 2000,

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

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

for all licensees of 0.24 rem.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Third Annual Report, 2000

NUREG-0713

The NRC currently has a 5-year contract with Science Applications

International Corporation (SAIC) to assist the NRC Staff in the

preparation of the NUREG-0713 series. Mr. Charles Hinson (NRR)

assisted in the preparation of this NUREG, serving as the NRC

Technical reviewer. SAIC will be suggesting changes in the

presentation of certain data in these reports. Readers should be alert

to these changes, and the NRC welcomes responses, especially

where these changes can be improved upon.

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
v

Thirty-Third Annual Report, 2000 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 .......................................................... 3-11

3.3.4 Independent Spent Fuel Storage Installation Licenses ..............................3-15

3.3.5 Fuel Cycle Licenses ...................................................................................3-17

3.3.6 Light-Water-Cooled Power Reactor Licenses ............................................3-18

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-Third Annual Report, 2000

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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 .......................................4-6

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...............................................................6-8

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

APPENDIX A - ANNUAL TEDE FOR NON-REACTOR NRC LICENSEES, 2000................... A-1

APPENDIX B - ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES, 2000..................................................................................................... B-1

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

1969-2000 ............................................................................................................................... C-1

APPENDIX D - DOSE PERFORMANCE INDICATORS BY REACTOR SITE,

1973-2000 ............................................................................................................................... D-1

TABLE OF CONTENTS (Continued)

Page
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Thirty-Third Annual Report, 2000 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Figure 3.1 Average Annual Values at Industrial Radiography Facilities, 1973 - 2000 ..........3-9

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

Single Location Licensees, 1996 - 2000............................................................3-10

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

Multiple Location Licensees, 1996 - 2000 .........................................................3-10

Figure 3.4 Average Annual Values at Manufacturing and Distribution

Facilities, 1973 - 2000 .......................................................................................3-12

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

Manufacturing and Distribution Licensees, 1996 - 2000 ...................................3-13

Figure 3.6 Collective TEDE Distribution by Dose Range, Limited

Manufacturing and Distribution Licensees, 1996 - 2000 ...................................3-13

Figure 3.7 Average Annual Values at Low-Level Waste Disposal

Facilities, 1982 - 2000 .......................................................................................3-14

Figure 3.8 Collective TEDE Distribution by Dose Range, Low-Level Waste

Disposal Licensees, 1996 - 2000 ......................................................................3-15

Figure 3.9 Average Annual Values at Independent Spent Fuel Storage

Facilities, 1982 - 2000 .......................................................................................3-16

Figure 3.10 Collective TEDE Distribution by Dose Range, Independent Spent

Fuel Storage Licensees, 1996 - 2000................................................................3-17

Figure 3.11 Average Annual Values at Fuel Cycle Licensees, 1973 - 2000 .........................3-19

Figure 3.12 Collective TEDE Distribution by Dose Range, Fuel Cycle

Licensees, 1996 - 2000 .....................................................................................3-20

Figure 3.13 Collective TEDE Distribution by Dose Range, Reactor

Licensees, 1996 - 2000 .....................................................................................3-21

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

per Reactor, 1973 - 2000 .....................................................................................4-9

Figure 4.2 Number of Operating Reactors and Gross Electricity

Generated, 1973 - 2000 ....................................................................................4-10

LIST OF FIGURES

Page
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Third Annual Report, 2000

NUREG-0713

Figure 4.3 Average Measurable Dose per Worker and Collective Dose per

Megawatt-Year, 1973 - 2000 ............................................................................. 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 - 2000 .........................................................................4-14

LIST OF FIGURES (Continued)

Page

Table 3.1 Average Annual Exposure Data for Certain Categories of

NRC Licensees, 1990 - 2000 ..............................................................................3-3

Table 3.2 Distribution of Annual Collective TEDE by License

Category, 2000 ....................................................................................................3-5

Table 3.3 Summary of Annual Dose Distributions for Certain NRC

Licensees, 1968 - 2000 .......................................................................................3-6

Table 3.4 Annual Exposure Information for Industrial

Radiographers, 1998 - 2000 ................................................................................3-7

Table 3.5 Annual Exposure Information for Manufacturers and

Distributors, 1998 - 2000 .....................................................................................3-8

Table 3.6 Annual Exposure Information for Fuel Cycle Licenses, 1998 - 2000.................3-18

Table 3.7 Intake by Licensee Type and Radionuclide

Mode of Intake - Ingestion and Other, 2000 ......................................................3-23

Table 3.8 Intake by Licensee Type and Radionuclide

Mode of Intake - Inhalation, 2000 ......................................................................3-24

Table 3.9 Collective and Average CEDE by Licensee, 2000.............................................3-26

Table 3.10 Internal Dose (CEDE) Distribution, 1994 - 2000................................................3-27

LIST OF TABLES
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Thirty-Third Annual Report, 2000 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 - 2000 ..................................................................4-2

Table 4.2 Summary of Information Reported by Commercial

Pressurized Water Reactors, 1973 - 2000 ..........................................................4-3

Table 4.3 Summary of Information Reported by Commercial

Light Water Reactors, 1973 - 2000......................................................................4-4

Table 4.4 Summary Distribution of Annual Whole Body Doses at

Commercial Light Water Reactors, 1977 - 2000 .................................................4-7

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

of Collective TEDE per BWR, 1998 - 2000........................................................4-15

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

of Collective TEDE per PWR, 1998 - 2000........................................................4-16

Table 5.1 Effects of Transient Workers on Annual Statistical Compilations, 2000 ..............5-2

Table 6.1 Occupational Exposures in Excess of Regulatory Limits, 1994 - 2000 ...............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, 2000 .............6-8

Page
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Thirty-Third Annual Report, 2000 Occupational Radiation Exposure at NRC Licensed Facilities

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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 and the annual

dose data reported by work function in accordance with Subsection 6.9.1.5 of the standard

technical specifications for nuclear power plants are used by the NRC staff. This is a very

appropriate inquiry that may be of importance to many affected licensees. 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, from the viewpoint of trends, of the effectiveness of the overall

NRC/licensee radiation protection and as low as reasonably achievable (ALARA) efforts by

certain licensees. They also provide for the identification (and subsequent correction) of

unfavorable trends.

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 provide for the monitoring of transient workers who may affect dose distribution

statistics through multiple counting.

4. 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?).

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

action for additional protection of the public involves worker exposures.

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

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

7. The data provide facts for answering Congressional and Administration inquiries and for

responding to questions raised by the public.

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

PREFACE
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xiii

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

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FOREWORD

NUREG-0713, Volume 22, summarizes the 2000 occupational radiation exposure data

maintained in the U.S. Nuclear Regulatory Commission's Radiation Exposure Information

Reporting System. Certain classes of licensees are required to annually report individual

exposure in accordance with 10 CFR 20.2206.

The occupational radiation exposure data contained in this volume of NUREG-0713 is a

compilation of the annual reports received from 271 licensees required to submit annual reports.

The collective dose incurred by these individuals was 15,893 person-rem, which represents a

5% decrease from the 1999 value.

Thomas L. King, Director

Division of Systems Analysis and Regulatory Effectiveness

Office of Nuclear Regulatory Research
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1-1

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

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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 at Science

Applications International Corporation (SAIC)

at Oak Ridge, Tennessee. The computerization

of these data ensures that they are kept

indefinitely and facilitates their retrieval and

analysis. The data maintained in REIRS have

been summarized and published in a report

every year since 1969. Annual reports for

each of the years 1969 through 1973

presented the data reported by both AEC

licensees and contractors and were published

in six documents designated as

WASH-1350-R1 through WASH-1350-R6.

In January 1975, with the separation of the

AEC into the Energy Research and

Development Administration (ERDA) and the

U.S. Nuclear Regulatory Commission (NRC),

each agency assumed responsibility for

collecting and maintaining occupational

radiation exposure information reported by the

facilities under its jurisdiction. The annual

reports published by the NRC on occupational

exposure for calendar year 1974 and

subsequent years do not contain information

pertaining to ERDA facilities or contractors.

Comparable information for facilities and

contractors under ERDA, now the Department

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

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

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

NUREG-0713

of Energy (DOE), is collected and published

by DOE’s Office of Safety and Health, a

division of Environment, Safety and Health, in

Germantown, Maryland.

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 new

categories are (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. Therefore, this document

presents the exposure information that was

reported by NRC licensees representing two

of these new categories. (There are no

geologic repositories for high-level waste

currently licensed.)

This report and each of the predecessors

summarize information reported for both the

current year and for previous years. More

licensee-specific data for previous years, such

as the annual reports submitted by each

commercial power reactor pursuant to 10 CFR

20.407 and their technical specifications, may

be found in those documents listed on the

inside of the front cover of this report for the

specific year desired. Additional operating

data and statistics for each power reactor for

the years 1973 through 1982 may be found in

a series of reports, “Nuclear Power Plant

Operating Experience” [Refs. 1-9]. These

documents are available for viewing at all

NRC public document rooms, or they may be

purchased from the National Technical

Information Service, as shown in the

Reference section.

In May of 1991, the revised 10 CFR 20

“Standards for Protection Against Radiation;

Final Rule” was published in the Federal

Register. The revision redefined the radiation

monitoring and reporting requirements of NRC

licensees. Instead of summary annual reports

(§ 20.407) and termination reports (§ 20.408),

licensees are now required to submit an

annual report of the dose received by each

monitored worker (§ 20.2206). Licensees

were required to implement the new

requirements on or before January of 1994.

This report is the seventh compilation of

radiation exposure information collected under

the revised 10 CFR 20. Certain sections of

the report have been modified to account for

the change in the reporting of exposure

information. Readers are encouraged to

comment on these changes.

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 of 1995, the NRC began pursuing the

dissemination of radiation exposure

information via a World Wide Web site on the

Internet. This allows interested parties with

the appropriate equipment to access the data

electronically rather than through the

published NUREG-0713 document. A web site

was created for radiation exposure and linked

into the main NRC web page. The web site

contains up-to-date information on radiation

exposure, as well as information and guidance

on reporting radiation exposure information to

the NRC. Interested parties may read the

documents online or download information to

their systems for further analysis. Software,

such as the Radiation Exposure Monitoring

and Information Transmittal (REMIT) System,

is also available for downloading via the web

site. There are also links to other web sites

dealing with the topics of radiation and health

physics. 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 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

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. 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-Third Annual Report, 2000

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Another fact that one should keep in mind

when examining the annual statistical data is

that all of the personnel included in the report

may not have been monitored throughout the

entire year. Many licensees, such as

radiography firms and nuclear power

facilities, may monitor numerous individuals

for periods much less than a year. The

average doses calculated from these data,

therefore, are less than the average dose

that an individual would receive if involved in

that activity for the full year.

One should pay considerable attention when

referencing the collective totals presented in

this report. The differences between the

totals presented for all licensees that

reported versus only those licensees that

are required to report should be noted.

Likewise, one should distinguish between

the doses attributed to the pressurized water

reactors (PWRs), and boiling water reactors

(BWRs). The totals may be inclusive or

exclusive of those licensees that were in

commercial operation for less than one full

year. These parameters vary throughout the

tables and appendices of this report. The

apparent discrepancies among the various

tables are a necessary side effect of this

endeavor.

The data contained in this report are subject

to change as licensees may submit

corrections or additions to data for previous

years. For the 2000 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 to report 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 U.S. experience. This

is not the case, however, for the remaining

categories of industrial radiography,

manufacturing and distribution of specified

quantities of by-product material, and

low-level waste disposal. Companies that

conduct these types of activities in

Agreement States are licensed by the state

and are not required to submit occupational

exposure reports to the NRC. Approximately

twice as many facilities are licensed in

Agreement States than the number licensed

by the NRC. In addition, this report does not

include non-occupational exposure, such as

exposure due to medical x-rays, fluoroscopy,

and accelerators when received as a patient.

All dose equivalent values in this report are

given in units of rem in accordance with the

general provisions for records,

10 CFR 20.2101(a). In order to convert rem

into the International System of Units (SI) unit

of sieverts (Sv), divide the value in rem by

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

to convert rem into millisieverts (mSv),

multiply the value in rem by 10. Therefore,

1 rem = 10 mSv.

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

for certain purposes. As of August 1999, there are 31 Agreement States.
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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, since 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

licenses, 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 feels that

monitoring devices should be provided.

For licensees submitting under the revised 10

CFR 20.2206, the total number of workers

was determined from the number of unique

personal identification numbers submitted per

ANNUAL PERSONNEL MONITORING

REPORTS - 10 CFR 20.2206

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. The revised

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

Section 3
3-2

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

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range. Past 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 comparing the actual

collective dose calculated for 1994 to 2000

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 taken

into consideration when comparing the 2000

collective dose with the collective dose for

years prior to 1994. One noted exception is

for fuel fabrication licensees where the CEDE

in some cases contributes the majority of the

TEDE (see Section 3.3.5).

3.1.5 Average Individual Dose

The average individual dose is obtained by

dividing the collective dose by the total

number of workers reported as being

monitored. This figure is usually less than the

average measurable dose because it includes

the number of those workers who received

zero or less than measurable doses.

3.1.6 Average Measurable Dose

The average measurable dose is obtained by

dividing the collective TEDE by the number of

workers who received a measurable dose.

This is the average most commonly used in

this and other reports when examining trends

and comparing doses received by workers in

various segments of the nuclear industry

because it deletes those workers receiving

zero or no detectable dose, many of whom

were monitored for convenience or

identification purposes.

3.1.7 Number of Licensees Reporting

The number of licensees refers to the NRC

licenses issued to use radioactive material for

certain activities that would place the

licensees in one of the six 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. Agreement

State licensees do not submit such 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)

1993 report entitled “Sources and Effects of

Ionizing 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

collective dose above 1.5 rem divided by the

total annual collective dose. The UNSCEAR

1993 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
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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)

Industrial 1991 248 6,820 4,649 2,160 0.32 0.46

Radiography 1992 246 6,703 4,265 1,864 0.28 0.44

1993 176 4,721 3,007 1,596 0.34 0.53

03310 1994 139 2,886 2,007 1,415 0.49 0.71

03320 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 123 3,287 2,477 1,488 0.45 0.60

Manufacturing 1991 59 4,930 1,952 722 0.15 0.37

and 1992 67 5,210 2,250 784 0.15 0.35

Distribution 1993 58 4,913 2,254 680 0.14 0.30

1994 44 2,941 1,251 580 0.20 0.46

02500 1995 36 2,666 1,222 595 0.22 0.49

03211 1996 38 2,631 1,241 556 0.21 0.45

03212 1997 33 1,154 665 397 0.34 0.60

03214 1998 31 1,986 654 402 0.20 0.61

1999 39 2,181 836 419 0.19 0.50

2000 33 2,403 1,142 408 0.17 0.36

Low-Level 1991 2 905 147 39 0.04 0.27

Waste 1992 2 467 82 37 0.08 0.45

Disposal*** 1993 2 432 76 21 0.05 0.27

1994 2 202 83 22 0.11 0.27

03231 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 

2000 0 

Independent 1991 2 41 24 4 0.10 0.17

Spent Fuel 1992 2 290 85 11 0.04 0.13

Storage 1993 2 135 52 14 0.10 0.26

1994 1 158 89 42 0.27 0.47

23100 1995 1 104 49 51 0.49 1.04

23200 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

Fuel 1991 11 11,702 3,929 378 0.03 0.10

Cycle 1992 11 8,439 5,061 545 0.06 0.11

Licenses - 1993 8 9,649 2,611 339 0.04 0.13

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

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

 Uranium Enrich. 1996 8 4,369 3,061 878 0.20 0.29

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

21210 1998 10 10,684 3,613 950 0.09 0.26

21200 1999 9 9,693 3,927 1,020 0.11 0.26

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

Commercial 1991 111 178,333 91,086 28,519 0.16 0.31

Light Water 1992 110 181,889 94,172 29,297 0.16 0.31

Reactors** 1993 108 169,259 86,193 26,364 0.16 0.31

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

41111 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

Grand Totals 1991 433 202,731 101,787 31,822 0.16 0.31

and Averages 1992 438 202,998 105,915 32,537 0.16 0.31

1993 354 189,109 94,193 29,013 0.15 0.31

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

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

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

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

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

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

2000 271 125,729 65,584 15,893 0.13 0.24

* These categories consist only of NRC licensees. Agreement State licensed organizations do not report occupational exposure data 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).

*** 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.

TABLE 3.1

Average Annual Exposure Data for Certain Categories of NRC Licensees

1990 - 2000
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Third Annual Report, 2000

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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 0.100 rem, 0.250 rem, 0.500

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 that received a TEDE

greater than or equal to the specified dose

range divided by the total collective TEDE. In

addition, the distribution is presented as a

percentage rather than a decimal fraction.

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

3.13 in Section 3 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 0.500 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. About 90% of the reported workers

with measurable doses were monitored by

nuclear power facilities in 2000, where they

received approximately 80% of the total

collective dose.

Under the regulatory limits of the revised

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 10 years, the

percentage of workers with <2 rem has been

≥99%. The number of workers receiving an

annual exposure in excess of 5 rem has been

<0.01% since 1985. Three individuals

received a dose above 5 rem in 2000 at a

licensee that is among the categories required

to submit data to REIRS (see Section 6).
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Thirty-Third Annual Report, 2000 Occupational Radiation Exposure at NRC Licensed Facilities

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TABLE 3.2

Distribution of Annual Collective TEDE by License Category

2000

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)

 180 63 8 1 3 2 1 258 78 7.894

 630 753 362 398 225 163 331 94 46 24 3 3,029 2,399 1,480.224

 810 816 370 399 228 165 332 94 46 24 3 3,287 2,477 1,488.118

932 181 40 35 37 19 49 34 24 1,351 419 297.568

 329 522 106 52 18 6 11 2 3 3 1,052 723 110.778

 1,261 703 146 87 55 25 60 36 27 3 2,403 1,142 408.346

63 61 20 2 146 83 5.571

4,687 2,700 621 553 286 127 233 101 24 4 9,336 4,649 1,339.398

25,007 16,397 6,805 4,634 1,847 806 685 12 56,193 31,186 6,089.676

48,786 23,904 10,793 5,676 1,678 569 291 11 91,708 42,922 6,562.006

73,793 40,301 17,598 10,310 3,525 1,375 976 23 147,901 74,108 12,651.682

80,614 44,581 18,755 11,351 4,094 1,692 1,601 254 97 31 3 163,073 82,459 15,893.115

 INDUSTRIAL RADIOGRAPHY

 Single Location (21)

 Multiple Location (102)

 Total (123)

 MANUFACTURING AND

 DISTRIBUTION

 "A" - Broad (4)

 Limited (29)

 Total (33)

 LOW-LEVEL WASTE DISPOSAL

 Total (0)**

 INDEPENDENT SPENT FUEL

 STORAGE

 Total (2)

 FUEL CYCLE LICENSES***

 Total (9)

 COMMERCIAL POWER REACTORS****

 Boiling Water (35)

 Pressurized Water (69)

 Total (104)

 GRAND TOTALS

* 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 2000. These values have not been adjusted for the multiple counting of transient reactor workers (see Section 5).
3-6

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

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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

197367,862 95.0% 99.5% 1

1974 85,097 96.4% 99.7% 1

1975 78,71394.8% 99.5% 1

1976 92,77395.0% 99.6% 3

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

1978 105,893100,818 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

1983172,927 164,239 94.6% 99.9% 0

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

1985 212,217 201,339 97.5% >99.99% (15) 2

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

1987 243,562 227,997 98.7% >99.99% (4) 1

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

1989 229,353 212,474 98.9% >99.99% (7) 1

1990 227,777 208,51398.9% >99.99% (3) 0

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

1992 220,717 202,998 99.4% >99.99% (1) 0

1993208,784 189,109 99.5% >99.99% (2) 0

1994 178,987 149,17399.5% >99.99% (1) 0

1995 179,406 143,115 99.5% >99.99% (1) 0

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

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

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

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

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

Total Number of Monitored

Persons

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

** Data for 1977-2000 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 is shown in parentheses from 1977-2000.

TABLE 3.3

Summary of Annual Dose Distributions for Certain* NRC Licensees

1968 - 2000
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Thirty-Third Annual Report, 2000 Occupational Radiation Exposure at NRC Licensed Facilities

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3.3 SUMMARY OF

OCCUPATIONAL EXPOSURE

DATA BY LICENSE CATEGORY

3.3.1 Industrial Radiography Licenses,

Single and Multiple Locations

Industrial Radiography licenses are issued to

allow the use of sealed radioactive materials,

usually in exposure devices or “cameras,” that

primarily emit gamma rays for nondestructive

testing of pipeline weld joints, steel structures,

boilers, aircraft and ship parts, and other

high-stress alloy parts. Some firms are

licensed to conduct such activities in one

location, usually in a permanent facility

designed and shielded for radiography, and

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 123 radiography

licensees in 2000. Table 3.4 summarizes the

reported data for the two types of radiography

licenses for 2000 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 25% 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 2000.

High exposures in radiography can be directly

attributable to the type and location of the

radiography field work. For example, locations

such as oil drilling platforms and aerial tanks

offer the radiographer little available shielding.

In these situations, there may not be an

opportunity to use distance as a means of

minimizing exposure and achieving ALARA.

Although these licensed activities usually result

in average measurable doses that are higher

than other licensees, they involve a relatively

small number of exposed workers.

TABLE 3.4

Annual Exposure Information for Industrial Radiographers

1998 - 2000

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

1998

1999

2000

26

116

142

21

111

132

21

102

123

369

4,583

4,952

266

3,571

3,837

258

3,029

3,287

84

3,362

3,446

50

2,777

2,827

78

2,399

2,477

8

1,855

1,863

7

1,544

1,551

8

1,480

1,488

0.09

0.55

0.54

0.14

0.56

0.55

0.10

0.62

0.60
3-8

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

NUREG-0713

Figure 3.1 shows the number of workers with

measurable dose per licensee, the total

collective dose per licensee, and the average

measurable dose per worker for both types of

Industrial Radiography facilities from 1973

through 2000. The collective TEDE and the

number of workers with measurable TEDE

decreased from 1999 to 2000. However, the

average measurable TEDE increased by 9%

from 0.55 rem in 1999 to 0.60 rem in 2000.

Figures 3.2 and 3.3 show the collective dose

distribution by dose range (see Section 3.1.8)

for single location and multiple location

radiography licensees. These graphs

demonstrate that multiple location licensees

consistently have individuals receiving dose in

the higher dose ranges and routinely have

20% to 35% of the collective dose delivered to

individuals above 2 rem.

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 Broad

license firms are medical suppliers that

process, package, or distribute such products

as diagnostic test kits; radioactive surgical

implants; and tagged radiochemicals for use

in medical research, diagnoses, and therapy.

The Limited licenses are usually issued to

smaller firms requiring a more restrictive

license. Limited firms are suppliers of

industrial radionuclides and are involved in

the processing, encapsulation, packaging,

and distribution of the radionuclides that they

have purchased in bulk quantities from

production reactors and cyclotrons. Major

products include gamma radiography

sources, cobalt irradiation sources,

well-logging sources, sealed sources for

gauges and smoke detectors, and radiochemicals for nonmedical research.

However, only those NRC licensees that

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

1998

1999

2000

5

26

31

5

34

39

4

29

33

1,177

809

1,986

1,261

920

2,181

1,351

1,052

2,403

380

274

654

352

484

836

419

723

1,142

367

35

402

347

72

419

298

111

408

0.97

0.13

0.61

0.99

0.15

0.50

0.71

0.15

0.36

TABLE 3.5

Annual Exposure Information for Manufacturers and Distributors

1998 - 2000
3-9

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

NUREG-0713 FIGURE 3.1. Average Annual Values at Industrial Radiography Facilities 1973- 2000

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

1973

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

5

0

30

25

20

15

10

1.00

0.90

0.80

0.70

0.60

0.50

0.40

0.30

0.20

0.10

0.00

No. of Workers w/ Measurable Dose per Licensee

Collective TEDE per Licensee (person-rem)

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

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

NUREG-0713

2000 1999 1998 1997 1996

2.0 rem

1.0 rem

0.5 rem

0.25 rem

0.1 rem

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

82%

76%

34%

0%

44%

0%

61%

87%

0%

0%

22%

61%

84%

78%

64%

25%

17%

0%

> 1.000

> 0.500

> 0.250

> 0.100

44%

96%

57%

13%

0%

62%

80%

2000 1999 1998 1997 1996

2.0 rem

1.0 rem

0.5 rem

0.25 rem

0.1 rem

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

81%

60%

93%

26%

> 1.000

> 0.500

> 0.250

> 0.100

98%

85%

66%

94%

35%

98%

82%

61%

93%

24%

98%

83%

58%

93%

24%

98%

83%

62%

94%

28%

99%

FIGURE 3.2. Collective TEDE Distribution by Dose Range

Industrial Radiographer – Single Location Licensees

1996 - 2000

FIGURE 3.3. Collective TEDE Distribution by Dose Range

Industrial Radiographer – Multiple Location Licensees

1996 - 2000
3-11

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

NUREG-0713

possess or use at any one time specified

quantities of the nuclides listed in paragraph

10CFR 20.2206(a)(7) are required to submit

reports to the NRC.

Table 3.5 presents the annual data that were

reported by the two types of licensees for

2000 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 all of the parameters remain

higher for the Broad licensees. However,

when attempting to examine trends in the data

presented for this category of licensees, it

should be noted that the types and quantities

of radionuclides may fluctuate from year to

year, and even during the year. For this

reason, some licensees may report dose data

one year and not the next and may be

included as a Broad licensee one year and a

Limited licensee at other times. Because the

number of reporting licensees is quite small,

these fluctuations may have a significant

impact on the values of the parameters.

Figure 3.4 shows the number of workers with

measurable dose per licensee, the total

collective dose per licensee, and the average

measurable dose per worker for both Type “A”

Broad and Limited Manufacturing and

Distribution facilities. The figures for Type “A”

Broad licensees are primarily attributed to

Mallinckrodt Medical, Inc., which accounted

for over 96% of the collective dose for this

category of licensee in 2000. Several of the

Type “A” Broad licensees that have reported

significant dose in prior years have been

transferred to Agreement State licensees.

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. For 1997 through

2000, over 55% of the collective dose was

received by individuals above 2 rem. Limited

licensees exhibit a distribution of the collective

dose where individuals below 0.500 rem

receive most 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 2000.

3.3.3 Low-Level Waste Disposal Licenses

Low-Level Waste Disposal licenses are issued

to allow the receipt, possession, and disposal

of low-level radioactive wastes at a land

disposal facility. The licensee has the

appropriate facilities to receive wastes from

such places as hospitals and laboratories, store

them for a short time, and dispose of them in a

properly prepared burial ground. The licensees

in this category are located in and licensed by

Agreement States which have primary

regulatory authority over the licensees’ activity.

Since 1999, there have been no licensees

conducting these activities that are not 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. Figure 3.8 shows the collective

dose distribution by dose range (see Section

3.1.8) for Low-Level Waste Disposal licensees

for the past 5 years.
3-12

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

NUREG-0713

FIGURE 3.4. Average Annual Values at Manufacturing and Distribution Facilities

1973- 2000

1973

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

0

80

60

40

20

120

100

1.00

0.90

0.80

0.70

0.60

0.50

0.40

0.30

0.20

0.10

0.00

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

No. of Workers w/ Measurable Dose per Licensee

Collective TEDE per Licensee (person-rem)

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

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

NUREG-0713

2000 1999 1998 1997 1996

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

93%

85%

97%

64%

> 1.000

> 0.500

> 0.250

> 0.100

99%

92%

79%

96%

55%

99%

88%

71%

93%

42%

97%

91%

61%

97%

66%

99%

93%

82%

97%

99%

84%

2000 1999 1998 1997 1996

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

> 2.000

12%

> 1.000

> 0.500

> 0.250

> 0.100

85%

67%

28%

87%

 71%

52%

85%

40%

55%

49%

26%

65%

28%

11%

0%

0%

0%

7%

30%

27%

82%

64%

84%

60%

FIGURE 3.5. Collective TEDE Distribution by Dose Range

Type “A” Broad Manufacturing and Distribution Licensees

1996 - 2000

FIGURE 3.6. Collective TEDE Distribution by Dose Range

Limited Manufacturing and Distribution Licensees

1996 - 2000
3-14

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

NUREG-0713

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

1982 - 2000

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

0

50

400

350

300

250

200

150

100

0.70

0.60

0.50

0.40

0.30

0.20

0.10

0.00

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

No. of Workers w/ Measurable Dose per Licensee

Collective TEDE per Licensee (person-rem)

Average Meas. TEDE per Worker (rem)

Note: As of 1999, there are no longer any NRC licensees involved in this activity. All low-level waste disposal facilities are now located in Agreement States and no longer report to the NRC.
3-15

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

NUREG-0713

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-nine licenses were authorized to

conduct these activities during 2000.

Eighteen of these licenses are for activities

involving cask design and storage systems.

Nineteen are located at nuclear power plants,

allowing on-site temporary storage of fuel.

These licensees report the dose from fuel

storage activities along with the dose from

reactor operations at these sites. 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 the

DOE for the storage of fuel from Three Mile

Island Unit 2. Appendix A summarizes the

exposure information reported by these two

installations.

Figure 3.9 shows the number of workers with

measurable dose per licensee, the total

collective dose per licensee, and the average

measurable dose per worker for ISFSI

facilities. The large increase in the collective

2000 1999 1998 1997 1996

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

> 2.000

> 1.000

> 0.500

> 0.250

> 0.100

0%

86%

41%

21%

0%

0%

0%

10%

80% 86%

0%

0%

0% 0%

0%

45%

0%

0%

0%

0% 0%

0%

0%

0%

0%

FIGURE 3.8. Collective TEDE Distribution by Dose Range

Low-Level Waste Disposal Licensees

1996 - 2000

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-Third Annual Report, 2000

NUREG-0713

FIGURE 3.9. Average Annual Values at Independent Spent Fuel Storage Facilities

1982 - 2000

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

0

90

80

70

60

50

40

30

20

10

100 2.00

1.80

1.60

1.40

1.20

1.00

0.80

0.60

0.40

0.20

0.00

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

No. of Workers w/ Measurable Dose per Licensee

Collective TEDE per Licensee (person-rem)

Average Meas. TEDE per Worker (rem)
3-17

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

NUREG-0713

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 have

decreased significantly from 1996 to 2000.

Figure 3.10 shows the collective dose

distribution by dose range (see Section 3.1.8)

for ISFSI licensees from 1996 to 2000. The

percentages for each dose range have

decreased significantly since 1996. The

percentages in all dose ranges have

decreased from 1999 to 2000, indicating that

fewer individuals received doses in the higher

ranges in 2000.

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 2000, this

2000 1999 1998 1997 1996

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

> 1.000

> 0.500

> 0.250

> 0.100

 81%

98%

61%

48%

0%

0%

0%

96%

85%

0% 0%

23%

74%

61%

99%

94%

0%

0%

11%

72%

90%

0%

0%

12%

63%

0%

FIGURE 3.10. Collective TEDE Distribution by Dose Range

Independent Spent Fuel Storage Licensees

1996 - 2000
3-18

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

NUREG-0713

category also includes the two uranium

enrichment facilities at Portsmouth, Ohio, and

Paducah, Kentucky. The regulatory oversight

for these facilities was transferred from the

DOE to the NRC in 1997.

Figure 3.11 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 3.12 shows the

collective dose distribution by dose range (see

Section 3.1.8) for Fuel Cycle licensees from

1996 to 2000. The distribution of collective

dose has been fairly constant with a

decreasing trend in the percentage in almost

every dose range until 2000. In 2000, there

was a three-fold increase in the number of

individuals over 2 rem at Westinghouse which

resulted in an increased percentage of the

dose in each dose range. Appendix A lists

each of the licensees reporting in 2000, 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 9

licensed Fuel Cycle (Fabrication and

Enrichment) facilities reporting in 2000.

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

1998 Fuel Cycle 10 10,684 3,613 946 0.26 2,412 204 0.08 2,520 742 0.29

1999 Fuel Cycle 9 9,693 3,927 1,020 0.26 3,207 247 0.08 2,462 773 0.31

2000 Fuel Cycle 9 9,336 4,649 1,339 0.29 3,582 406 0.11 2,784 934 0.34

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

TABLE 3.6

Annual Exposure Information for Fuel Cycle Licenses

1998 - 2000
3-19

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

NUREG-0713 FIGURE 3.11. Average Annual Values at Fuel Cycle Licensees 1973- 2000

1973

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

0

50

650

600

550

500

450

400

350

300

250

200

150

100

0.60

0.50

0.40

0.30

0.20

0.10

0.00

Average Number of Workers with Measurable Dose,

Collective TEDE per Licensee (person-rem)

Average Measurable Dose per Worker (rem)

Year

No. of Workers w/ Measurable Dose per Licensee

Collective DDE per Licensee (person-rem)

Collective TEDE per Licensee (person-rem)

Average Meas. DDE per Worker (rem)

Average Meas. TEDE per Worker (rem)
3-20

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

NUREG-0713

for reactor facilities that were in commercial

operation for a full year for each of the years

1991 through 2000. The values do not include

reactors that have been shut down or were

not yet in commercial operation. These

figures have been adjusted for the multiple

counting of transient workers (see Section 5).

The reported dose distribution of workers

monitored at each plant site for the year 2000

is presented in alphabetical order by site

name in Appendix B.

2000 1999 1998 1997 1996

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above Dose Range

Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

12%

> 1.000

> 0.500

> 0.250

> 0.100

94%

84%

71%

69%

9%

94%

44%

84%

39%

87%

95%

67%

10%

8%

39%

37%

68%

84%

94%

72%

26%

51%

87%

95%

FIGURE 3.12. Collective TEDE Distribution by Dose Range

Fuel Cycle Licensees

1996 - 2000

Figure 3.13 shows the collective dose

distribution by dose range (see Section 3.1.8)

for Reactor licensees from 1996 to 2000. The

distribution of collective dose has been fairly

constant with a decreasing trend in the

percentage in every dose range over the past

5 years.

More detailed presentations and analyses of

the annual exposure information reported by

nuclear power facilities can be found in

Sections 4 and 5.
3-21

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

NUREG-0713

FIGURE 3.13. Collective TEDE Distribution by Dose Range

Reactor Licensees

1996 - 2000

2000 1999 1998 1997 1996

100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

Percentage Above 

Dose 

Range

Dose Range

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

> 2.000

1%

> 1.000

> 0.500

> 0.250

> 0.100

90%

39%

11%

67%

6%

94%

59%

29%

 81%

5%

93%

56%

25%

 78%

4%

92%

52%

22%

 76%

1%

88%

38%

11%

66%
3-22

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

NUREG-0713

3.4 SUMMARY OF INTAKE DATA

BY LICENSE CATEGORY

With the revision of 10 CFR 20 in 1994,

licensees were required to report additional

data to the NRC concerning intakes of

radioactive material. Licensees were 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 2000. The data

are categorized by licensee type and are

listed in order of radionuclide and pulmonary

clearance class. Table 3.7 lists the intakes

where the mode of intake into the body was

recorded as ingestion. Table 3.8 lists the

intakes where the mode of intake was

inhalation from ambient airborne radioactive

material in the workplace. The pulmonary

clearance class is recorded as D, W, or Y

corresponding to its clearance half-time in the

order of days, weeks, or years from the

pulmonary region of the lung into the blood

and gastrointestinal tract. The amount of

material taken into the body is given in

microcuries, a unit of measure of the quantity

of radioactive material. For each category of

licensee, the maximum number of intake

records and the maximum intake is

highlighted in the table in bold for ease of

reference.

Table 3.9 lists the number of individuals with

measurable CEDE, the collective CEDE, and

the average measurable CEDE per individual

for each licensee category. Fuel fabrication

facilities have the majority of internal dose

(96%) 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 2000 for licensees

required to report under 10 CFR 20.2206. For

the purposes of this table, the definition of a

“measurable CEDE” is any reported value

greater than zero. As noted above, the vast

majority of the internal doses are received by

individuals working at fuel fabrication facilities.

In 2000, the highest CEDE was 4.134 rem,

received by an individual at Westinghouse

Electric Company, a fuel fabrication facility.

The individual received an intake of U-234,

U-235, and U-238. The highest CDE was

34.450 rem to this same individual.
3-23

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

NUREG-0713

TABLE 3.7

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

2000

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries

Collective

Intake in

Microcuries

(sci. notation)

* 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.

Mode

Ingestion Power Reactors 41111 ALPHA 1 0.000 4.05E-05

41111 AM-241 2 0.001 9.00E-04

41111 CO-58 17 7.548 7.55E+00

41111 CO-60 28 11.737 1.17E+01

41111 CS-134 1 0.480 4.80E-01

41111 CS-137 4 0.128 1.28E-01

41111 FE-59 1 0.360 3.60E-01

41111 MN-54 8 3.220 3.22E+00

41111 NB-95 1 0.199 1.99E-01

41111 PU-238 2 0.000 2.00E-04

41111 RU-103 1 0.009 8.57E-03

41111 ZR-95 2 0.740 7.40E-01

Absorption Power Reactors 41111 NI-63 1 0.007 6.73E-03
3-24

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

NUREG-0713

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries

Collective

Intake in

Microcuries

(sci. notation)

Radiopharmaceutical 02500 I-131 D 37 3.384 3.38E+00

02500 I-131 W 33 0.598 5.98E-01

02500 TC-99M D 22 12,515.000 1.25E+04

Manufacturing and Distribution 03211 CO-56 Y 1 1.760 1.76E+00

03211 CO-57 Y 1 0.560 5.60E-01

03211 I-131 D 9 4.363 4.36E+00

03211 TI-202 D 1 0.248 2.48E-01

03211 ZN-65 Y 1 2.200 2.20E+00

Uranium Enrichment 21200 TC-99 W 1 0.165 1.65E-01

21200 TH-230 W 49 0.001 1.11E-03

21200 U-234 D 98 0.078 7.82E-02

Fuel Fabrication 21210 AM-241 W 203 0.002 1.79E-03

21210 CO-60 Y 1 0.001 1.40E-03

21210 NP-237 W 29 0.000 2.13E-04

21210 PU-239 W 218 0.007 7.05E-03

21210 PU-239 Y 138 0.001 1.41E-03

21210 SR-90 Y 37 0.000 2.79E-06

21210 TC-99 W 13 0.001 5.04E-04

21210 TH-228 W 57 0.001 9.77E-04

21210 TH-228 Y 84 0.000 4.41E-06

21210 TH-230 W 46 0.001 9.78E-04

21210 TH-230 Y 70 0.000 2.53E-06

21210 TH-232 Y 260 0.004 3.73E-03

21210 U-234 D 762 0.621 6.21E-01

21210 U-234 W 458 0.076 7.56E-02

21210 U-234 Y 2,919 8.158 8.16E+00

21210 U-235 D 274 0.008 7.62E-03

21210 U-235 Y 1,586 0.214 2.14E-01

21210 U-236 D 274 0.000 2.50E-04

21210 U-236 Y 645 0.003 3.37E-03

21210 U-238 D 378 0.046 4.58E-02

21210 U-238 W 7 0.001 1.05E-03

21210 U-238 Y 2,418 0.992 9.92E-01

Power Reactors 41111 AG-110M Y 2 0.013 1.28E-02

41111 AM-241 D 1 0.000 3.00E-06

41111 AM-241 W 35 0.000 1.17E-04

41111 CM-242 W 16 0.001 5.81E-04

41111 CM-243/4 W 16 0.000 2.82E-04

41111 CO-57 Y 2 0.002 1.74E-03

Pulmonary

Clearance

Class

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

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

under 10 CFR 20.2206.

TABLE 3.8

Intake by Licensee Type and Radionuclide Mode of Intake – Inhalation

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

NUREG-0713

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries

Collective

Intake in

Microcuries

(sci. notation)

Power Reactors (continued) 41111 CO-58 D 1 0.254 2.54E-01

41111 CO-58 V 1 0.254 2.54E-01

41111 CO-58 Y 102 784.776 7.85E+02

41111 CO-60 D 1 1.000 1.00E+00

41111 CO-60 Y 222 547.314 5.47E+02

41111 CR-51 D 1 0.021 2.13E-02

41111 CR-51 Y 11 1.651 1.65E+00

41111 CS-134 D 3 0.059 5.90E-02

41111 CS-134 Y 1 0.005 4.83E-03

41111 CS-137 D 5 0.286 2.86E-01

41111 CS-137 W 1 0.250 2.50E-01

41111 CS-137 Y 24 0.435 4.35E-01

41111 FE-55 W 16 1.916 1.92E+00

41111 FE-59 D 2 0.187 1.87E-01

41111 FE-59 W 2 0.500 5.00E-01

41111 H-3 O 49 0.049 4.90E-02

41111 H-3 Y 1 176.000 1.76E+02

41111 I-131 D 28 1.305 1.31E+00

41111 I-133 D 10 1.276 1.28E+00

41111 MN-54 D 1 0.019 1.90E-02

41111 MN-54 W 77 65.815 6.58E+01

41111 NB-95 Y 7 0.167 1.67E-01

41111 NI-63 W 15 0.292 2.92E-01

41111 PU-238 Y 17 0.000 2.43E-04

41111 PU-239 Y 17 0.000 1.63E-04

41111 PU-241 W 10 0.004 4.21E-03

41111 PU-241 Y 19 0.003 3.28E-03

41111 SN-113 W 3 0.004 3.68E-03

41111 SR-90 D 1 0.001 1.28E-03

41111 Y-90 Y 1 0.001 1.28E-03

41111 ZN-65 Y 6 0.593 5.93E-01

41111 ZR-95 D 2 0.019 1.90E-02

41111 ZR-95 W 2 0.326 3.26E-01

41111 ZR-95 Y 1 0.122 1.22E-01

41111 ZRNB-95 W 7 0.148 1.48E-01

Pulmonary

Clearance

Class

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

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

under 10 CFR 20.2206.

TABLE 3.8 (continued)

Intake by Licensee Type and Radionuclide Mode of Intake – Inhalation

2000
3-26

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

NUREG-0713

TABLE 3.9

Collective and Average CEDE by Licensee

2000

Nuclear Pharmacies EASTERN ISOTOPES, INC. 45-25221-01MD 17 0.029 0.002

02500 SYNCOR INTERNATIONAL CORP. 04-26507-01MD 42 3.148 0.075

Total 59 3.177 0.054

Manufactuing and Distribution MALLINCKRODT INC. 24-04206-01 6 0.262 0.044

03211 Total 6 0.262 0.044

Uranium Enrichment U. S. ENRICHMENT CORP. - PADUCAH GDP-1 36 0.057 0.002

21200 U. S. ENRICHMENT CORP. - PORTSMOUTH GDP-2 33 0.530 0.016

Total 69 0.587 0.009

Fuel Fabrication GLOBAL NUCLEAR FUEL - AMERICAS, LLC SNM-1097 741 55.007 0.074

21210 WESTINGHOUSE ELECTRIC COMPANY LLC SNM-1107 460 394.587 0.858

FRAMATOME COGEMA FUELS SNM-1168 49 6.783 0.138

BWX TECHNOLOGIES, INC. SNM-42 292 153.105 0.524

NUCLEAR FUEL SERVICES, INC. SNM-124 514 55.628 0.108

SIEMENS POWER CORP. SNM-1227 391 89.615 0.229

CE NUCLEAR POWER LLC SNM-33 268 178.410 0.666

Total 2,715 933.135 0.344

Power Reactors ARKANSAS DPR-51 3 0.058 0.019

41111 BEAVER VALLEY DPR-66 3 0.066 0.022

BIG ROCK POINT DPR-06 2 0.026 0.013

BROWNS FERRY DPR-33 379 2.908 0.008

BRUNSWICK DPR-62 26 0.299 0.012

CALLAWAY NPF-30 1 0.002 0.002

CALVERT CLIFFS DPR-53 15 0.332 0.022

CATAWBA NPF-35 8 0.168 0.021

CLINTON NPF-62 2 0.036 0.018

COOK DPR-58 120 0.392 0.003

COOPER STATION DPR-46 10 0.047 0.005

DAVIS-BESSE NPF-03 71 0.861 0.012

DIABLO CANYON DPR-80 1 0.024 0.024

FARLEY NPF-02 1 0.011 0.011

FERMI NPF-43 1 0.039 0.039

GINNA DPR-18 1 0.053 0.053

HADDAM NECK DPR-61 60 1.040 0.017

HARRIS NPF-63 31 0.119 0.004

HATCH DPR-57 1 0.013 0.013

INDIAN POINT 1 DPR-05 15 0.425 0.028

LACROSSE DPR-45 7 0.384 0.055

LIMERICK NPF-39 16 0.113 0.007

MAINE YANKEE DPR-36 49 0.245 0.005

MILLSTONE POINT 1 DPR-21 1 0.017 0.017

MONTICELLO DPR-22 3 0.028 0.009

OCONEE DPR-38 4 0.131 0.033

OYSTER CREEK DPR-16 83 0.457 0.006

PALO VERDE NPF-41 1 0.002 0.002

PEACH BOTTOM DPR-44 13 0.100 0.008

POINT BEACH DPR-24 2 0.039 0.020

PRAIRIE ISLAND DPR-42 1 0.011 0.011

QUAD CITIES DPR-29 10 0.694 0.069

RANCHO SECO DPR-54 1 0.010 0.010

RIVER BEND NPF-47 25 0.674 0.027

SAN ONOFRE DPR-13 10 0.071 0.007

SEABROOK NPF-86 1 0.012 0.012

SEQUOYAH DPR-77 1,252 18.543 0.015

ST. LUCIE DPR-67 15 0.033 0.002

SUMMER NPF-12 1 0.014 0.014

SURRY DPR-32 5 0.026 0.005

SUSQUEHANNA NPF-14 149 0.427 0.003

THREE MILE ISLAND 1 DPR-50 93 0.511 0.005

TURKEY POINT DPR-31 40 0.090 0.002

VERMONT YANKEE DPR-28 13 0.186 0.014

VOGTLE NPF-68 4 0.063 0.016

WATERFORD NPF-38 4 0.058 0.015

WATTS BAR NPF-90 215 2.609 0.012

WNP 2 NPF-21 4 0.049 0.012

WOLF CREEK NPF-42 6 0.115 0.019

Total 2,779 32.631 0.012

Grand Totals 5,628 969.792 0.172

Licensee Type Licensee Name License Number

Number

with Meas.

CEDE

Collective

CEDE

(person-rem)

Average

Meas. CEDE

(rem)
3-27

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

NUREG-0713

TABLE 3.10

Internal Dose (CEDE) Distribution

1994 - 2000

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
3-28

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

NUREG-0713

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4-1

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

NUREG-0713

COMMERCIAL LIGHT WATER REACTORS –

FURTHER ANALYSIS

Section 4

4.1 INTRODUCTION

General trends in occupational radiation

exposures at nuclear power reactors are best

evaluated within the context of other pertinent

information. In this chapter, some of the

tables and appendices that summarize

exposure data also show the type, capacity,

amount of electricity generated, and age of

the reactor. Exposure data are then

presented as a function of these data.

4.2 DEFINITION OF TERMS

AND SOURCES OF DATA

4.2.1 Number of Reactors

The number of reactors shown in Tables 4.1,

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

and LWRs, respectively, that had been in

commercial operation for at least 1 full year as

of December 31 of each of the indicated

years. This is the number of reactors on

which the average number of workers with

measurable dose and average collective dose

per reactor is based. Excluded are those

reactors that had 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 had been included

in the compilation of data for commercially

operating reactors through 1988 even though

the reactor was shut down following the 1979

accident and has been in the process of

defueling and decommissioning since that

time. TMI 2 has not been included in the data

analysis since 1988. Data for this reactor,

however, will be listed in Appendix B for

reference purposes. The dose data presented

in Appendix D for TMI includes the dose data

for Unit 2 prior to 1986.

There were no changes to the count of

operating reactors in 2000. The number of

operating BWRs remains the same as in 1999

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 are

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 2000, the number
4-2

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

NUREG-0713Average 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 0.85 380 445 1.34 283 438 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 6,830 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%

* 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 4.1

Summary of Information Reported by Commercial Boiling Water Reactors

1973 - 2000
4-3

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

NUREG-0713

Average Average No. Average

Annual No. of Average Collective Personnel Collective Average Average Percent of

Number Collective Workers Measurable Dose Per With Dose Electricity Maximum Maximum

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

Reactors (person- Measurable Generated*** Worker (person- Doses (person-rem Per Reactor capacity Capacity

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

1973 12 9,398 9,440 3,770.2 1.00 783 787 2.49 314 544 58%

1974 19 6,555 9,370 6,530.7 0.70 345 493 1.00 344 591 58%

1975 26 8,268 10,884 11,982.5 0.76 318 419 0.69 461 647 71%

1976 30 13,807 17,588 13,325.0 0.79 460 586 1.04 444 701 63%

1977 34 13,467 20,878 17,345.8 0.65 396 614 0.78 510 688 74%

1978 39 16,528 25,700 19,840.5 0.64 424 659 0.83 509 706 72%

1979 42 21,657 38,828 18,255.0 0.56 516 924 1.19 435 746 58%

1980 42 24,267 46,237 18,289.3 0.52 578 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 71 14,143 56,590 50,480.6 0.25 199 797 0.28 711 945 75%

1994 72 9,606 44,811 54,618.3 0.21 133 622 0.18 759 932 81%

1995 72 12,217 51,899 55,825.1 0.24 170 721 0.22 775 933 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 0.19 680 943 72%

1998 69 6,358 38,586 53,288.7 0.16 92 559 0.12 772 942 82%

1999 69 7,231 43,938 56,235.0 0.16 105 637 0.13 815 942 86%

2000 69 6,562 42,922 57,529.9 0.15 95 622 0.11 834 943 88%

* 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 - 2000
4-4

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

NUREG-0713

1973 24 13,962 14,780 7,164.1 0.94 582 616 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 0.39 400 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 108 26,364 95,942 72,476.2 0.27 244 888 0.36 671 895 75%

1994 109 21,704 83,982 76,757.3 0.26 199 770 0.28 704 888 79%

1995 109 21,688 87,585 80,562.1 0.25 199 804 0.27 739 900 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 13,188 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%

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 - 2000
4-5

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

NUREG-0713

reflects the net electricity produced, which is

the gross electricity minus the amount the

plant uses for operations. This change is the

result of a change in the 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 2000. BWRs increased net electricity

generated by 6%. Contributors to this

increase include Lasalle 1, 2, which increased

net electric output by 28% in 2000, and River

Bend, which increased output by 29%. PWRs

increased net electric output by 2%.

4.2.3 Collective Dose per Megawatt-Year

The number of MW-yrs of electricity generated

was used in determining the ratio of the

average value of the annual collective dose

(TEDE) to the number of MW-yrs of electricity

generated. The ratio was calculated by

dividing the total collective dose in person-rem

by the electric energy generated in MW-yrs

and is a measure of the dose incurred by

workers at power plants in relation to the

electric energy produced. For the years 1973

to 1996, the electricity generated is the gross

electricity output of the reactor. For 1997 to

2000, 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 from 0.16 in 1999 to a

value of 0.15 in 2000.

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.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Third Annual Report, 2000

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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.

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 Three Mile Island,

reactor operations personnel concentrated on

improving safety systems and complying with

the new regulations for these systems. During

this time period, from 1979 to 1987, the

percent of maximum dependable capacity

remained around 61%. Following the

completion of most of these mandated repairs,

reactors have increased the percent of

maximum dependable capacity from 62% in

1987 to 81% in 1996, a gain of nearly 20% in

10 years. The decrease in maximum

dependable capacity from 1996 to 1997 was

due to the change from measuring the gross

electricity generated to the net electricity

generated. The percent of maximum

dependable capacity achieved has increased

by 2% from 1999 to 2000.

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 2000. 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 2000 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 7% to

a value of 12,652 person-rem in 2000.
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TABLE 4.4

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

1977 - 2000

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 32,521

1978 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 31,785

1979 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 39,908

1980 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 53,739

1981 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 54,163

1982 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 52,201

1983 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 56,484

1984 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 55,251

1985 59,625 36,920 13,015 11,044 6,626 4,545 10,042 3,574 1,002 157 1 - - - - - - 146,551 86,926 43,048

1986 67,677 41,536 14,574 11,842 7,017 4,693 10,241 3,062 868 146 - - - - - - - 161,656 93,979 42,386

1987 85,170 41,283 15,842 12,838 7,586 5,333 10,611 2,192 477 69 - - - - - - - 181,401 96,231 40,406

1988 87,281 40,290 15,915 13,152 7,905 5,461 10,310 2,442 511 26 - 1 - - - - - 183,294 96,013 40,772

1989 83,954 45,302 17,270 13,778 7,944 5,138 8,633 1,615 370 34 - - - - - - - 184,038 100,084 35,931

1990 83,875 42,612 17,526 14,199 8,226 5,261 8,594 1,791 337 21 - - - - - - - 182,442 98,567 36,602

1991 87,247 42,603 16,770 13,182 7,188 4,192 5,977 938 219 17 - - - - - - - 178,333 91,086 28,519

1992 87,717 41,943 17,821 14,779 8,135 4,521 6,076 808 85 4 - - - - - - - 181,889 94,172 29,297

1993 83,066 37,332 17,235 13,734 7,562 4,289 5,322 638 76 5 - - - - - - - 169,259 86,193 26,364

1994 67,777 30,185 15,010 11,823 6,185 3,620 4,242 508 40 - - - - - - - - 139,390 71,613 21,704

1995 61,445 29,631 15,096 12,023 6,125 3,304 3,912 595 133 2 - - - - - - - 132,266 70,821 21,688

1996 58,097 30,204 14,831 11,343 5,423 2,833 3,196 408 67 - - - - - - - - 126,402 68,305 18,883

1997 58,409 31,955 14,890 10,913 5,233 2,455 2,599 286 41 - - - - - - - - 126,781 68,372 17,149

1998 56,901 27,998 12,849 8,816 3,940 1,841 1,827 179 15 1 - - - - - - - 114,367 57,466 13,187

1999 54,885 29,048 13,184 8,949 3,793 1,900 1,894 245 18 - - - - - - - - 113,916 59,031 13,599

2000 53,324 28,480 12,921 8,679 3,571 1,644 1,734 186 18 - - - - - - - - 110,557 57,233 12,652

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 (since 1994) by only those plants that had been in commercial operation for at least 1 full year as of December 31 of each of

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

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

**
4-8

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

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 2000, the average

collective dose per LWR dropped by 84%.

Between 1999 and 2000, the collective dose

per reactor for PWRs decreased by 10% to 95

person-rem. The collective dose per reactor

for BWRs decreased by 5% to 174 personrem from 1999 to 2000. The overall collective

dose per reactor for LWRs decreased by 7%

to 122 person-rem in 2000. The number of

workers with measurable dose per reactor

decreased to 891 for BWRs and decreased to

622 for PWRs in 2000. 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. The value for the total collective

dose for all LWRs decreased by 7% from a

value of 13,666 person-rem in 1999 to 12,652

person-rem in 2000. Together with the

decrease in the number of workers with

measurable dose, this resulted in the average

measurable dose per worker decreasing from

0.18 rem in 1999 to 0.17 rem in 2000 (when

not adjusted for transient workers). Figure 4.2

shows that in 2000 the net electricity

generated increased to an all-time high of

86,007 MW-yr.

The fluctuations in the parameters for the

years following the accident at the TMI plant in

1979 may reflect some of the impact that this

incident had on the nuclear power industry.

The decrease seen in dose trends since 1983

may be attributable to several factors. Utilities

have completed most of the tasks initiated as

a result of the lessons learned from the TMI

accident, and they are increasing efforts to

avoid and reduce exposure. The importance

of exposure control and the concept of

keeping exposures to ALARA levels is

continually being stressed, and most utilities

have established programs to collect and

share information relative to tasks,

techniques, and exposures.
4-9

Thirty-Third Annual Report, 2000 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 - 2000

Collective Dose per Reactor (Person-rem)

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

Year

BWR

Average Annual Collective Dose

19731974

PWR

LWR

0

200

400

600

800

1000

1200

Workers per Reactor

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

Year

Average Annual Number of Workers with Measurable Dose

19731974

0

400

800

1000

1200

1400

1600

BWR

PWR

LWR

600

200
4-10

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

NUREG-0713

FIGURE 4.2. Number of Operating Reactors and Gross Electricity Generated

1973 - 2000

0

10

20

30

40

50

60

70

80

90

100

110

120

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

Number of Reactors

Year

Number of Operating Reactors

Megawatt-Years (Thousands)

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

Year

Electricity Generated*

19731974

0

BWR

PWR

LWR

20

BWR

PWR

30

40

50

60

70

80

90

10

*Gross electricity 1973-1996, net electricity for 1997-2000.
4-11

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

NUREG-0713

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

1973 - 2000

0.0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1.0

1.1

BWR

PWR

LWR

Average Measurable Dose (rem)

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

Year

Average Measurable Dose per Worker

19731974

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

Year

Collective Dose per Megawatt-Year

19731974

BWR

PWR

LWR

0.0

0.2

0.4

0.6

0.8

1.0

1.2

1.4

1.6

1.8

2.0

2.2

2.4

2.6

2.8

3.0

*Gross electricity 1973-1996, net electricity for 1997-2000.

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

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

NUREG-0713

6 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 median6

values of the collective dose per reactor for

BWRs and for PWRs for the years 1973

through 2000. 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. Since 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 experienced a decrease from 96

person-rem in 1999 to 91 person-rem in 2000.

At BWRs, the median fluctuates more from

year to year, and in 2000 the median

collective dose decreased to 146 person-rem.

Figure 4.5 also shows that, in 2000, 50% of

the PWRs reported collective doses between

53 and 116 person-rem, while 50% of the

BWRs reported collective doses between 130

and 201 person-rem. Nearly every year, the

median collective dose is less than the

average, which indicates that the collective

dose for most plants is less than the average

collective dose per reactor (the value that is

widely quoted).

4.5 THREE-YEAR AVERAGE

COLLECTIVE TEDE PER

REACTOR

The 3-year average collective dose per

reactor is one of the metrics that the NRC

uses in the Revised 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, 2000, 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 184 person-rem, the average

measurable TEDE per worker was 0.20 rem,

and the average collective TEDE per MW-yr

was 0.24 person-rem per MW-yr. All of these

values decreased from the previous 3-year

period.

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

97 person-rem, 0.16 rem, and 0.12 personrem per MW-yr, respectively.
4-13

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

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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-Third Annual Report, 2000

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

1987 - 2000

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

AM

A

M

2000

A M

A

M

116

53

201

130
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Thirty-Third Annual Report, 2000 Occupational Radiation Exposure at NRC Licensed Facilities

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TABLE 4.5

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

1998 - 2000

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

BROWNS FERRY 1,2,3** 9 128 1,148 5,010 0.23 6,196.7 0.19

FERMI 2 3 130 390 3,089 0.13 2,838.1 0.14

VERMONT YANKEE 3 138 413 1,996 0.21 1,364.6 0.30

PERRY 3 141 424 2,644 0.16 3,353.0 0.13

COOPER STATION 3 143 429 2,258 0.19 1,838.3 0.23

LIMERICK 1,2 6 148 889 4,933 0.18 6,151.7 0.14

HOPE CREEK 1 3 174 522 2,967 0.18 2,700.1 0.19

PILGRIM 3 155 466 2,174 0.21 1,788.7 0.26

DUANE ARNOLD 3 161 482 2,170 0.22 1,362.2 0.35

CLINTON 3 162 485 2,751 0.18 1,321.2 0.37

MONTICELLO 3 165 495 1,917 0.26 1,484.1 0.33

WASHINGTON NUCLEAR 2 3 165 494 2,948 0.17 2,463.8 0.20

PEACH BOTTOM 2,3 6 169 1,016 5,262 0.19 5,996.7 0.17

HATCH 1,2 6 175 1,050 5,389 0.19 4,460.8 0.24

NINE MILE POINT 1,2 6 185 1,108 5,236 0.21 4,240.7 0.26

SUSQUEHANNA 1,2 6 187 1,124 5,174 0.22 5,770.2 0.19

GRAND GULF 3 188 565 2,879 0.20 3,228.8 0.18

BRUNSWICK 1,2 6 189 1,136 5,471 0.21 4,586.9 0.25

RIVER BEND 1 3 206 618 2,897 0.21 2,382.5 0.26

LASALLE 1,2 6 210 1,259 6,619 0.19 4,191.4 0.30

DRESDEN 2,3 6 213 1,280 7,895 0.16 4,272.0 0.30

FITZPATRICK 3 242 727 3,606 0.20 1,998.4 0.36

QUAD CITIES 1,2 6 309 1,855 6,017 0.31 3,681.7 0.50

OYSTER CREEK 3 321 964 3,918 0.25 1,550.8 0.62

Grand Totals and Averages 105 19,339 95,220 0.20 79,223.4 0.24

Averages Per Reactor-Year 184 907 754.5 

* Sites where not all reactors had completed 3 full years of commercial operation as of 12/31/00 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-Third Annual Report, 2000

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TABLE 4.6

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

1998 - 2000

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

INDIAN POINT 3 3 47 141 1,249 0.11 2,663.8 0.05

PRAIRIE ISLAND 1,2 6 49 296 1,756 0.17 2,841.8 0.10

PALO VERDE 1,2,3 9 55 496 3,964 0.13 10,384.2 0.05

THREE MILE ISLAND 1 3 60 180 1,634 0.11 2,341.6 0.08

KEWAUNEE 3 64 193 881 0.22 1,360.7 0.14

SEABROOK 3 65 195 3,056 0.06 2,850.9 0.07

ST. LUCIE 1,2 6 68 410 3,267 0.13 4,771.6 0.09

NORTH ANNA 1,2 6 71 426 2,658 0.16 5,114.6 0.08

WATTS BAR 1 3 75 225 2,124 0.11 3,081.5 0.07

CATAWBA 1,2 6 78 467 3,332 0.14 6,091.4 0.08

BEAVER VALLEY 1,2 6 83 496 3,271 0.15 3,255.5 0.15

HARRIS 3 83 250 2,066 0.12 2,376.2 0.11

POINT BEACH 1,2 6 84 502 2,608 0.19 2,327.7 0.14

TURKEY POINT 3,4 6 84 503 3,256 0.15 3,959.2 0.13

MILLSTONE 2,3 6 85 507 4,252 0.12 3,687.0 0.14

VOGTLE 1,2 6 85 512 3,252 0.16 6,453.8 0.08

CALVERT CLIFFS 1,2 6 86 513 3,088 0.17 4,620.2 0.11

SURRY 1,2 6 87 520 3,357 0.15 4,449.2 0.12

GINNA 3 89 267 1,231 0.22 1,329.4 0.20

MCGUIRE 1,2 6 89 531 3,259 0.16 6,201.6 0.09

COMANCHE PEAK 1,2 6 93 561 3,042 0.18 6,124.0 0.09

OCONEE 1,2,3 9 93 841 4,949 0.17 6,574.6 0.13

SALEM 1,2 6 93 557 2,799 0.20 5,424.5 0.10

WATERFORD 3 3 93 279 1,940 0.14 2,798.7 0.10

CRYSTAL RIVER 3 3 95 285 1,894 0.15 2,286.8 0.12

ARKANSAS 1,2 6 99 593 4,689 0.13 4,301.1 0.14

BRAIDWOOD 1,2 6 100 599 4,584 0.13 6,276.3 0.10

SUMMER 1 3 100 301 2,045 0.15 2,500.7 0.12

ROBINSON 2 3 101 302 1,923 0.16 1,987.4 0.15

WOLF CREEK 1 3 101 302 1,857 0.16 3,265.3 0.09

COOK 1,2 6 102 614 5,323 0.12 560.1 1.10

SAN ONOFRE 2,3 6 111 665 3,641 0.18 5,965.0 0.11

SOUTH TEXAS 1,2 6 113 675 3,871 0.17 6,779.1 0.10

DAVIS-BESSE 3 117 351 2,486 0.14 2,311.9 0.15

BYRON 1,2 6 118 708 4,246 0.17 6,130.9 0.12

SEQUOYAH 1,2 6 131 788 4,915 0.16 6,210.4 0.13

DIABLO CANYON 1,2 6 134 802 3,936 0.20 5,798.0 0.14

FORT CALHOUN 3 139 418 1,713 0.24 1,240.7 0.34

PALISADES 3 154 462 2,089 0.22 1,855.2 0.25

FARLEY 1,2 6 164 982 4,165 0.24 4,180.0 0.24

CALLAWAY 1 3 179 538 2,271 0.24 3,091.0 0.17

INDIAN POINT 2 3 299 898 3,507 0.26 1,230.0 0.73

Grand Totals and Averages 207 20,151 125,446 0.16 167,053.6 0.12

Averages Per Reactor-Year 97 606 807.0 

* Sites where not all reactors had completed 3 full years of commercial operation as of 12/31/00 are not included.
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All of the dose values at both types of reactors

were lower than for the previous 3-year

period. The average 3-year collective TEDE

per BWR for 1998 -2000 is 6% less than the

average for 1997 -1999. The average 3-year

collective TEDE per PWR for 1998 -2000 is

12% less than the average for 1997 -1999.

The average MW-yr per reactor for BWRs and

PWRs was greater than the previous 3-year

average.

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 2000. 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 2000.

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 Revised

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 a 2- to 3-year

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.
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TRANSIENT WORKERS AND CAREER

DOSES AT NRC-LICENSED FACILITIES

Section 5

5.1 TERMINATION REPORTS

Under the revised 10 CFR 20, licensees are

required to submit NRC Form 5s to the

Commission for each individual who is

required to be monitored at the end of the

monitoring year or upon the individual’s

termination of employment at the facility. The

“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 5s submitted to the NRC

upon an individual’s termination of

employment serve the same function as the

previous requirements with regard to the

analysis of transient workers at NRC-licensed

facilities. The following analysis examines the

workers who had more than one Form 5 dose

record at more than one NRC-licensed facility

during the monitoring year. These workers

are defined as “transient” because they

worked at more than one facility during the

monitoring year.

The term “monitoring year” is used here in

accordance with the definition of a year given

in § 20.1003, which defines a year as “the

period of time beginning in January used to

determine compliance with the provisions of

this part. The licensee may change the start

date of the monitoring year used to determine

compliance provided that the change is made

at the beginning of the monitoring/calendar

year and that no day is omitted or duplicated

in consecutive years.”

5.2 TRANSIENT WORKERS AT

NRC FACILITIES

Examination of the data reported for workers

who began and terminated two or more

periods of employment with two or more

different facilities within one monitoring year is

useful in many ways. For example, the

number of and individual dose received by

these “annual transients” can be determined

from examining these data.

Additionally, the distribution of the doses

received by transient workers can be useful in

determining the impact that the inclusion of

these individuals in each of two or more

licensees’ annual reports has on the annual

summary (as reported in Appendix B) for all

nuclear power facilities, and all NRC licensees

combined (one of the problems mentioned in

Section 2). Table 5.1 shows the “actual

distribution” of transient worker doses as

determined from the NRC Form 5 termination

reports and compares it with the “reported

distribution” of the doses of these workers as

they would have appeared in a summation of

the annual reports submitted by each of the

licensees.

In 2000, 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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TABLE 5.1

Effects of Transient Workers on Annual Statistical Compilations

2000

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

Average

Meas.

TEDE

(rem)

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

73,793 40,301 17,598 10,310 3,525 1,375 976 23 147,901 74,108 12,652 0.17

26,599 17,552 8,552 5,092 1,751 734 524 18 60,822 34,223 6,320 0.18

 6,130 5,731 3,875 3,461 1,797 1,003 1,282 181 18 23,478 17,348 6,320 0.36

53,324 28,480 12,921 8,679 3,571 1,644 1,734 186 18 110,557 57,233 12,652 0.22

80,614 44,581 18,755 11,351 4,094 1,692 1,601 254 97 31 3 163,073 82,459 15,893 0.19

26,917 17,892 8,626 5,147 1,777 759 548 20 61,686 34,769 6,435 0.19

 6,109 5,786 3,895 3,481 1,821 1,017 1,322 189 19 23,639 17,530 6,435 0.37

59,806 32,475 14,024 9,685 4,138 1,950 2,375 423 116 31 3 125,026 65,220 15,893 0.24
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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 2000. Because each licensee reports the

doses received by workers while monitored by

the particular licensee during the year, one

would expect that a summation of these

reports would result in individuals being

counted several times in dose ranges lower

than the range in which their total

accumulated dose (the sum of the personnel

monitoring results incurred at each facility

during the year) would actually place them.

Thus, while the total collective dose would

remain the same, the number of workers, their

dose distribution, and average dose would be

affected by this multiple reporting. This was

found to be true because too few workers

were reported in the higher dose ranges. For

example, in 2000, Table 5.1 shows that the

summation of annual reports for reactor

licensees indicated that 23 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

204 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 27%

of the workforce that receives measurable

dose. The correction for the transient workers

increases the average measurable dose by a

factor of 2 from 0.19 rem to 0.37 rem for the

transient workforce. It should be noted that

this analysis of transient workers does not

include workers who may have been exposed

at facilities that are not required to report to

the NRC REIRS database (see Section 1),

such as Agreement State licensees, or DOE

facilities.

One purpose of the REIRS database, which

tracks occupational radiation exposures at

NRC-licensed facilities, is to identify

individuals who may have exceeded the

occupational radiation exposure limits

because of multiple exposures at different

facilities throughout the year. The REIRS

database stores the radiation exposure

information for an individual by their unique

identification number and identification type

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

for all facilities during the monitoring year. An

individual exceeding the TEDE 5 rem per year

regulatory limit would be identified in Table 5.1

in one of the dose ranges >5 rem. In 2000, no

individual was discovered to have exceeded

the limit as a result of the correction for

transient workers. Since 1985, there have

been no additional transient workers identified

as having received a dose of >5 rem that have

not appeared in the annual reports received

by the NRC. This reflects the industry’s

continuing concerted efforts to keep the total

annual doses of all workers under 5 rem and

shows that such reductions can be

accomplished without increasing the collective

dose because the collective dose has

decreased during this same time period.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Third Annual Report, 2000

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7 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. The revised

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). The revised 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. The

revised 10 CFR 20 no longer contains

quarterly exposure limits but has reporting

requirements for planned special exposures

(PSEs)7 . The annual TEDE limit for adult

workers is 5 rem.

The revised 10 CFR 20.2202 and

10 CFR 20.2203 require that all persons

licensed by the NRC 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-Third Annual Report, 2000

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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 2000. Table 6.2 shows the data

reported under 10 CFR 20.403 and

10 CFR 20.405 for the period 1985-1993.

Note that the categorization criteria changed

effective with the revised 10 CFR 20. The

dose reporting thresholds have been revised –

the skin of the whole body and the

extremities now have the same dose limits,

and a new set of dose limits has been added

for the lens of the eye.

For the period 1990-1993, Table 6.2 shows the

number of individuals who exceeded various

limits while employed by one of several types

of licensees. For the period 1985-1989, only

the exposures in excess of regulatory limits

reported by licensed industrial radiography

firms are shown separately. Most of the

occurrences included in the “Others” category

come from research facilities, universities, and

measuring and well-logging activities.

In 2000, there was one “Category A”

occurrence, one “Category B” occurrence, and

five “Category C” occurrences. The “Category

A” occurrence involved an individual who

received a dose of up to 2500 rem to the

extremities while handling an Mo-99/Tc-99m

generator column at a radio-pharmaceutical

licensee. The “Category B” occurrence

resulted in a dose of 115 rem to the

extremities from a contamination incident
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Third Annual Report, 2000

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TABLE 6.1

Occupational Exposures in Excess of Regulatory Limits

1994 - 2000

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.OFPERSONS

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

2f

1,080

1

143

4f

423

1

5.1

1

8.3

1b

51.1

1c

70.6

3f

1,199

4a

34.8

1

50-200

2

12.2

1e

180

1

5.67

1999

1998

1997

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)

3f

1,115

5f

675

5f

431

6f

740

4d, f

782

1f

255

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 These two 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.

2000

2

10.636

2

2,562

1

115

2

11.373

>25 15 - 75 >75 50 - 250 >250 rad
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Thirty-Third Annual Report, 2000 Occupational Radiation Exposure at NRC Licensed Facilities

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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.

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.

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

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-Third Annual Report, 2000

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involving C-14. In the five “Category C”

events, one individual received an extremity

dose in excess of the 50 rem annual limit,

while the other four events were due to whole

body doses in excess of the 5 rem annual

limit. A summary of these events follows.

In April of 2000, a licensee reported a

“Category A” event that caused a shallow

dose equivalent exceeding 10 CFR 20 limits

to an employee’s index finger and thumb of

the left hand. The ring badge from the right

index finger of the employee had a reading of

5.685 cSv (rem), but was not in position to

monitor the highest extremity exposure. The

individual, working at the rework and

packaging stations of the generator

manufacturing line, handled an Mo-99/Tc-99m

column containing 703 GBq (19 Ci) of Mo-99

and 296 GBq (8 Ci) of Tc-99m with his left

hand for 30 to 50 seconds. The individual was

supposed to use forceps to manipulate

needles inside the generator, but instead used

his fingers. The calculated dose to his right

index finger tip was 31 cSv (rem) at 1.5 inches

from the source of activity. As a result of

further investigation and a mockup of the

original event, the shallow dose equivalent

estimate to the worker’s index finger and

thumb of the left hand varies from 1000 cSv

(rem) to 2,500 cSv (rem). An Augmented

Inspection Team (AIT) was dispatched to the

licensee’s facility to gather information and

review the circumstances surrounding the

extremity exposures. The cause of these

events were determined to be a failure to

follow procedures, inadequate identification of

radiological hazards, and the failure to

recognize the radiological implications of

some work practices. Corrective actions

include procedure modification and

conducting training sessions to review all

applicable procedures. Improvements in the

licensee’s manufacturing process included

continuing emphasis on procedural

adherence, procedural changes for handling

radioactive material, modifications of the

In-111 product vial labeling, and engineering

changes to the Mo-99 generator

manufacturing line.

In July of 2000, a licensee reported a

“Category B” event where an employee

received an extremity exposure of 115 cSv

(rem) at a depth of 7 mg/cm2. A researcher in

the radiosynthesis group was labeling a

compound using 7.4 GBq (200 mCi) of C-14

(benzoquinone in dimethoxyethane). A drop

from the pipette tip dropped onto the

researcher’s glove. A fraction of the material

seeped through the glove and contaminated

the tip of his left index finger with between

74.0 and 185.0 kBq (2.0 and 5.0 uCi) of C-14.

The researcher reported the contamination to

the licensee’s Radiation Safety Officer (RSO).

Initially, the RSO calculated the dose to the

skin using a dose factor for skin contamination

from the licensee’s radiation safety manual

and estimated the dose to be 2 mSv (200

mrem). During followup, however, the RSO

became aware that the factor was incorrect

and the dose could be much higher. The RSO

reevaluated that dose and found that at a

depth of 7 mg/cm2 (as required by 10 CFR 20)

the dose was 115 cSv (rem). The licensee

determined that the event occurred because,

although the researcher employed standard

precautions when performing labeling

procedures, the precautions were not

sufficient for the particular procedure being

performed. The researcher wore only one pair
6-7

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

NUREG-0713

of gloves and wore gloves that were not

sufficiently protective for the compound being

used. The licensee also determined that initial

decontamination efforts were not sufficiently

aggressive due to concern about introducing

the material into the blood stream. To prevent

recurrence, the licensee modified their

procedures to require two pairs of gloves for

similar procedures and to emphasize that

users must select gloves that provide

protection against the material being used, if

possible. The licensee also examined whether

remote handling tools were appropriate to use

for these procedures. In addition, the licensee

provided additional training to all members of

the radiosynthesis group.

In June of 2000, a licensee reported a

“Category C” extremity overexposure to one of

their radiation workers at their radiopharmacy

in Harrisburg, Pennsylvania. The licensee

reported that an individual received a reported

extremity exposure of 62 cSv (rem) for the

period from January 2000 through June 2000.

The licensee’s RSO stated that the individual

received 8.3 cSv (rem) in February, 26.6 cSv

(rem) in March, 13.1 cSv (rem) in April, and

12.1 cSv (rem) in May. The licensee

conducted further review and concluded that

the actual exposure was 49.74 cSv (rem). The

NRC stated that they did not accept the

licensee contention that the overexposure did

not occur. This event was caused by

inadequate procedures, existing procedures

not followed, improper handling techniques

(including the lack of the use of forceps and

flange syringe shields), inadequate training,

and inadequate supervision (including the

failure to adequately evaluate the individual’s

dosimetry results). Corrective actions include

modifications to the licensee’s dosimetry and

surveillance procedures and improvements to

the training program.

Two other “Category C” events were reported

in 2000 involving external whole body doses

in excess of 5 rem. In March of 2001, a

licensee reported a Category C event that

occurred in November of 2000. A cardiologist

had received an exposure to the whole body

in excess of 5 cSv (rem) for calendar year

2000. The dose received for the year was

recorded by a badge placed on the

cardiologist’s collar as 5.401 cSv (rem) deep

dose equivalent (DDE). The DDE for the year

based on a badge worn beneath a lead apron

was 1.078 cSv (rem). The licensee believed

the dose was below the limit by using a

weighting factor allowed by the

Commonwealth of Pennsylvania, and the

individual was allowed to continue activities

while receiving additional dose. However, the

NRC does not allow the use of weighting

factors in determining external dose.

In another event, a licensee reported a

“Category C” exposure in February 2001 that

occurred in 2000. The individual received a

deep dose equivalent of 5.235 cSv (rem). The

individual is a radiologist and is involved in

complex interventional radiology procedures

on a daily basis. The licensee stated that the

individual is infrequently exposed to

radioactive material and believes that the

radiation exposure is the result of scatter

radiation during fluoroscopy.

In addition, there were two dose records

submitted by a multiple location radiography

licensee where the individuals received doses
6-8

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

NUREG-0713

in excess of the annual 5 cSv (rem) TEDE

limit. These doses were not the result of a

specific accident or event, but were received

throughout the calendar year during normal

work operations. The official cause of the

exposures was a failure by management to

aggressively assess the individual’s daily

dosimeter readings during the latter part of

November and throughout December. The

corrective action taken was the dismissal of

the Assistant RSO, whose duties

encompassed the assessment and

management of the radiation exposures to

personnel.

Of the seven events summarized above, only

two of the events occurred at licensees that

were required to report exposure records to

the NRC REIRS database in 2000 and are

included in the tables and figures in other

sections of this report. All seven events are

included in Table 6.1.

TABLE 6.3

Maximum Occupational Exposures for Each Exposure Category *

2000

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.

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

**

SDE-ME 50 rem 959.420 > limit 54,287 110 36 13 3 (2 > limit)

SDE-WB 50 rem 32.477 65% 67,372 1 1 0 0

LDE 15 rem 6.046 40% 64,853 38 0 0 0

CEDE 4.134 5,481 

CDE 34.450 3,188 

DDE 5.961 66,307 

TEDE 5 rem 5.961 > limit 67,471 1918 303 41 12 (4 > limit)

TODE 50 rem 34.821 70% 59,343 172 9 0 0

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 approach

the NRC limits.

As shown in Table 6.3, few exposures exceed

half of the NRC occupational annual limits. In

2000, twelve individuals came within 5% of

the TEDE limit in addition to the four

individuals who exceeded the limit. Two

individuals exceeded the 50 rem extremity

limit. No individuals were reported to have

exceeded the skin, eye, or organ dose limits.
7-1

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

NUREG-0713

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

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

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

1974-1975, USNRC Report NUREG-0227, April 1977.*

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

USNRC Report NUREG-0366, December 1977.*

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

NUREG-0483, February 1979.*

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

December 1979.*

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

May 1981.*

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

ORNL/NSIC-191, October 1982.*

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

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

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

ORNL/NSIC-215, Vol. 2, January 1985.*

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

Regulatory Guide 8.7, Rev. 1, June 1992.

11. United Nations, Report of the Scientific Committee on the Effects of Atomic Radiation,

General Assembly of Official Records, United Nations, New York, 1993.

12. Licensed Operating Reactors, Status Summary Report, USNRC Report NUREG-0020, Vol.

20, No. 1. Data for 1995 provided on diskette by D. Hartfield, USNRC Office of Information

Resources Management, Systems Development Branch.

REFERENCES

Section 7

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

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

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

NUREG-0713

This page intentionally left blank.
A-1

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

NUREG-0713

ANNUAL TEDE FOR NON-REACTOR

NRC LICENSEES

2000

Appendix A
A-2

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

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)

NUCLEAR PHARMACIES - 02500

CAPITAL PHARMACY INC. 21-26597-01MD 3 13 2 1 - - - - - - - - - 19 16 1.076 0.067

DIAGNOSTIC PHOTON CORPORATION 52-16345-02MD 4 11 2 1 - - - - - - - - - 18 14 0.930 0.066

EASTERN ISOTOPES, INC. 45-25221-01MD 31 60 14 2 6 2 8 1 3 3 - - - 130 99 47.970 0.485

MALLINCKRODT MEDICAL, INC. 24-04206-01MD 1 10 1 4 - 2 - - - - - - - 18 17 4.230 0.249

MALLINCKRODT MEDICAL, INC. 24-04206-08MD 3 11 6 2 - - - - - - - - - 22 19 1.875 0.099

MALLINCKRODT MEDICAL, INC. 24-04206-12MD 3 11 9 2 2 - - - - - - - - 27 24 3.462 0.144

MALLINCKRODT MEDICAL, INC. 24-04206-14MD 1 8 6 5 1 - - - - - - - - 21 20 3.175 0.159

MALLINCKRODT MEDICAL, INC. 24-04206-17MD 1 5 3 1 - - - - - - - - - 10 9 1.060 0.118

MALLINCKRODT MEDICAL, INC. 24-04206-19MD 7 7 8 9 2 1 1 - - - - - - 35 28 8.898 0.318

MALLINCKRODT MEDICAL, INC. 24-17450-02MD 4 15 3 3 - - - - - - - - - 25 21 1.825 0.087

MID-AMERICA ISOTOPES, INC. 24-26241-01 3 19 3 1 - - - - - - - - - 26 23 1.125 0.049

NUCLEAR DIAGNOSTIC PRODUCTS 29-30500-01MD 4 9 - - - - - - - - - - - 13 9 0.331 0.037

OKLAHOMA, UNIVERSITY OF 35-03176-04MD - 18 2 1 - - 1 - - - - - - 22 22 2.756 0.125

PHARMALOGIC LTD 44-30124-01MD 2 5 2 - - - - - - - - - - 9 7 0.416 0.059

RADIOPHARMACY, INC. 13-26246-01MD 4 22 3 2 - - - - - - - - - 31 27 1.704 0.063

SPECTRUM PHARMACY, INC. 13-26367-01 4 25 6 3 1 1 1 - - - - - - 41 37 5.514 0.149

SPECTRUM PHARMACY OF FT. WAYNE 13-32053-01MD 5 20 2 - - - - - - - - - - 27 22 0.635 0.029

SYNCOR INTERNATIONAL CORP. 04-26507-01MD 77 151 21 7 3 - - - - - - - - 259 182 12.170 0.067

Total 18 157 420 93 44 15 6 11 1 3 3 - - - 753 596 99.152 0.166

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2000

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

Thirty-Third Annual Report, 2000 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)

MANUFACTURING AND DISTRIBUTION - TYPE A BROAD - 03211

APTEC-NRC, INC. 29-04236-01 11 14 - 1 - - - - - - - - - 26 15 0.447 0.030

BRISTOL MYERS SQUIBB 29-00139-02 823 95 4 2 6 1 2 - - - - - - 933 110 10.169 0.092

DEFENSE LOGISTICS AGENCY 37-30062-01 15 - - - - - - - - - - - - 15 - - - 

MALLINCKRODT MEDICAL, INC. 24-04206-01 83 72 36 32 31 18 47 34 24 - - - - 377 294 286.952 0.976

Total 4 932 181 40 35 37 19 49 34 24 - - - - 1,351 419 297.568 0.710

MANUFACTURING AND DISTRIBUTION - TYPE B BROAD - 03212

BEST INDUSTRIES, INC. 45-19757-01 64 37 6 1 - - - - - - - - - 108 44 2.204 0.050 

OHMART CORP. 34-00639-04 32 33 4 2 3 - - 1 - - - - - 75 43 6.582 0.153 

Total 2 96 70 10 3 3 - - 1 - - - - - 183 87 8.786 0.101 

MANUFACTURING AND DISTRIBUTION - OTHER - 03214

ADVANZ MEASUREMENT & CONTROL 34-26683-03 - 8 - - - - - - - - - - - 8 8 0.089 0.011 

APTEC-NRC, INC. 37-02401-01 21 15 - - - - - - - - - - - 36 15 0.355 0.024 

CIS-US, INC. 20-20973-04 - - 1 2 - - - - - - - - - 3 3 1.001 0.334 

DU PONT MERCK PHARMACEUTICAL CO. 20-00320-19 - 2 1 1 - - - - - - - - - 4 4 0.538 0.135 

FAIRCHILD SEMICONDUCTOR 37-24841-02 9 - - - - - - - - - - - - 9 - - -

HALLIBURTON ENERGY SERVICES, INC. 35-00502-03 - - - 2 - - - - - - - - - 2 2 0.609 0.305 

INTERGRATED INDUSTRIAL SYSTEMS, INC. 06-21253-01 39 - - - - - - - - - - - - 39 - - - 

NORDION INTERNATIONAL, INC. 54-28275-01 6 5 1 - - - - - - - - - - 12 6 0.221 0.037 

PHARMASAN LABS, INC. 48-26355-01 1 2 - - - - - - - - - - - 3 2 0.027 0.014 

Total 9 76 32 3 5 - - - - - - - - - 116 40 2.840 0.071

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2000

NOTE: The data values shown bolded and in boxes represent the highest value in each category.
A-4

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

NUREG-0713 APPENDIX A Annual TEDE for Non-Reactor NRC Licensees CY 2000

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)

INDUSTRIAL RADIOGRAPHY - SINGLE LOCATION - 03310

ARMY, DEPARTMENT OF THE 13-18235-01 54 - - - - - - - - - - - - 54 - - - 

ARMY, DEPARTMENT OF THE 29-00047-06 2 - - - - - - - - - - - - 2 - - - 

ARROW TANK & ENGINEERING CO. 22-13253-01 2 1 1 1 1 - - - - - - - - 6 4 1.249 0.312 

BUCKEYE STEEL CASTINGS 34-06627-01 - 2 - - - - - - - - - - - 2 2 0.026 0.013 

BWX TECHNOLOGIES, INC. 34-02160-03 9 13 - - - - - - - - - - - 22 13 0.058 0.004 

CARONDELET FOUNDRY COMPANY 24-26136-01 4 3 2 - - - - - - - - - - 9 5 0.507 0.101 

DURALOY 37-02279-02 - 2 2 - - - - - - - - - - 4 4 0.389 0.097 

GREDE-PRYOR, INC. 35-18099-01 - 3 - - - - - - - - - - - 3 3 0.048 0.016 

HARRISON STEEL CASTINGS CO. 13-02141-01 5 3 - - - - - - - - - - - 8 3 0.112 0.037 

INTERMET - ARCHER CREEK 45-17464-01 3 2 - - - - - - - - - - - 5 2 0.032 0.016 

LAFAYETTE TESTING SERVICES, INC. 48-32158-01 - 2 1 - - - - - - - - - - 3 3 0.312 0.104

MINNESOTA VALLEY ENGINEERING 22-24393-01 - 5 - - - - - - - - - - - 5 5 0.239 0.048 

MISSOURI STEEL CASTINGS 24-15152-01 4 - - - - - - - - - - - - 4 - - - 

NILES STEEL TANK CO. 21-04741-01 3 1 - - - - - - - - - - - 4 1 0.002 0.002 

RIDGEWATER COLLEGE 22-15554-01 25 19 1 - - - - - - - - - - 45 20 0.679 0.034 

SHAW CONNEX, INC. 45-25521-01 - 2 - - - - - - - - - - - 2 2 0.086 0.043 

THE DURIRON COMPANY, INC. 34-06398-01 - 4 - - - - - - - - - - - 4 4 0.094 0.024 

THE WILLIAM POWELL CO. 34-02963-01 3 - - - - - - - - - - - - 3 - - - 

TRANS WORLD AIRLINES, INC. 24-05151-05 59 - - - - - - - - - - - - 59 - - - 

WAUKESHA FOUNDRY DIVISION 48-13776-01 5 - - - - - - - - - - - - 5 - - - 

WISCONSIN CENTRIFUGAL, INC. 48-11641-01 2 1 1 - 2 2 1 - - - - - - 9 7 4.061 0.580

Total 21 180 63 8 1 3 2 1 - - - - - - 258 78 7.894 0.101
A-5

Thirty-Third Annual Report, 2000 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

ACCURATE TECHNOLOGIES, INC. 29-28358-01 - 4 3 2 5 - 4 1 - - - - - 19 19 12.508 0.658 

ALASKA INDUSTRIAL X-RAY 50-16084-01 - 3 3 2 1 - 1 2 1 - - - - 13 13 11.698 0.900

ALLEGHENY LABORATORIES 37-20734-01 - 1 - - - - - - - - - - - 1 1 0.003 0.003 

ALLIED INSPECTION SERVICES, INC. 21-18428-01 - - - - - 3 1 - - - - - - 4 4 3.691 0.923 

ALONSO & CARUS IRON WORKS, INC. 52-21350-01 1 - 2 2 - - - - - - - - - 5 4 1.113 0.278 

AMERICAN AIRLINES, INC. 35-13964-01 - 31 1 1 - - - - - - - - - 33 33 1.230 0.037 

AMERICAN ENGINEERING TESTING 22-20271-02 1 7 3 - 2 - 4 - 1 - - - - 18 17 11.090 0.652 

ANVIL CORPORATION 46-23236-03 6 12 16 17 9 9 7 1 - - - - - 77 71 34.342 0.484 

APPLIED TECHNICAL SERVICES, INC. 45-25477-01 - 4 1 - 2 1 - - - - - - - 8 8 2.523 0.315 

ARCTIC SLOPE INSPECTION SVCS, INC. 50-29015-01 54 70 27 21 8 5 1 - - - - - - 186 132 23.935 0.181 

ARMY, DEPARTMENT OF THE 30-02405-05 - 2 - - - - - - - - - - - 2 2 0.113 0.057 

BARNETT INDUSTRIAL X-RAY 35-26953-01 2 - 2 2 1 2 3 2 - - - - - 14 12 12.400 1.033 

BILL MILLER, INC. 35-19048-01 3 1 6 5 3 1 2 - - - - - - 21 18 7.505 0.417 

BRANCH RADIOGRAPHIC LABS., INC. 29-03405-02 5 7 7 5 1 2 - - - - - - - 27 22 5.357 0.244 

BRAUN INTERTEC CORPORATION 22-16537-02 4 8 6 3 2 3 2 - - - - - - 28 24 8.652 0.361 

CALUMET TESTING SERVICES, INC. 13-16347-01 2 3 - 3 - - 2 - 3 2 - - - 15 13 22.764 1.751 

CAPITAL X-RAY SERVICES, INC. 35-11114-01 - 8 2 3 1 2 8 3 1 - - - - 28 28 28.337 1.012 

CENTURY INSPECTION, INC. 42-08456-02 9 12 18 16 8 3 5 - 1 - - - - 72 63 25.704 0.408 

CHICAGO BRIDGE AND IRON CO. 42-13553-02 12 14 1 1 1 1 - - - - - - - 30 18 2.492 0.138 

COLBY & THIELMEIER TESTING CO. 24-13737-01 - - 1 1 2 - 5 - - - - - - 9 9 9.002 1.000 

COMO TECH INSPECTION 15-26978-01 - 1 - 2 - - 3 1 - - - - - 7 7 6.647 0.950

CONAM INSPECTION 12-16559-02 14 10 10 11 5 3 2 - - - - - - 55 41 14.965 0.365 

CONNELL LIMITED PARTNERSHIP 35-13735-01 - 2 1 - - - - - - - - - - 3 3 0.195 0.065 

COOPERHEAT - MQS, INC. 42-32219-01 87 32 22 27 13 12 6 3 - - - - - 202 115 46.756 0.407 

CTI CORE DRILLING SERVICES, INC. 45-25383-01 2 2 - - 1 - - 1 - - - - - 6 4 3.104 0.776 

CURTIS INSPECTION SERVICES, INC. 35-27438-01 - 1 3 2 1 - 4 - - - - - - 11 11 7.325 0.666 

DIAMOND H TESTING COMPANY 11-27316-01 2 6 2 3 2 1 5 - - - - - - 21 19 11.234 0.591

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2000

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

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

NUREG-0713 APPENDIX A Annual TEDE for Non-Reactor NRC Licensees CY 2000

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)

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320 Continued

EASTERN TESTING & INSPECTION, INC. 29-09814-01 2 4 1 2 1 - - - - - - - - 10 8 1.714 0.214 

EDWARDS PIPELINE SERVICES, INC. 35-23193-01 13 11 12 25 20 10 8 - - - - - 99 86 42.405 0.493 

ELECTRIC BOAT CORPORATION 06-01781-08 - 7 3 - - - - - - - - - - 10 10 0.752 0.075 

ELITE INSPECTION, INC. 13-26712-01 1 6 2 6 2 3 5 2 - - - - - 27 26 18.476 0.711 

FROEHLING & ROBERTSON, INC. 45-08890-01 10 4 3 1 - - - - - - - - - 18 8 1.034 0.129 

GENERAL TESTING & INSPECTION CO. 47-32191-01 - 1 - 3 - 1 1 - - - - - - 6 6 3.484 0.581 

GLITSCH FIELD SERVICES/NDE,INC. 34-14071-02 8 16 8 4 2 - - - - - - - - 38 30 4.531 0.151 

GLOBE X-RAY SERVICES, INC. 35-15194-01 4 12 3 5 5 4 9 5 - - - - - 47 43 33.770 0.785 

GREAT LAKES TESTING, INC. 48-26484-01 1 3 2 - - 3 4 1 - - - - - 14 13 11.679 0.898 

HIGH MOUNTAIN INSPECTION SERVICES 49-26808-02 - 2 5 11 4 6 20 13 6 5 2 - - 74 74 124.905 1.688

HUNTINGTON TESTING & TECHNOLOGY 47-23076-01 6 2 - 7 4 2 6 3 2 - - - - 32 26 29.047 1.117

INDUSTRIAL NDT CO., INC. 39-24888-01 1 4 4 3 4 2 2 - - - - - - 20 19 8.513 0.448 

INTEGRATED TECHNOLOGIES, INC. 06-30317-01 2 9 7 2 4 2 - - - - - - - 26 24 6.439 0.268 

INT'L RADIOGRAPHY & INSPECT SVCS, INC. 35-30246-01 1 6 4 7 5 2 9 4 4 2 - - - 44 43 54.199 1.260 

INTERNATIONAL SCIENTIFIC RESEARCH 11-27661-01 4 1 - - - - - - - - - - - 5 1 0.092 0.092

JACOBS PAN-AMERICAN CORPORATION 55-25502-01 - 7 3 7 4 - 4 3 1 1 - - - 30 30 25.948 0.865 

JAN X-RAY SERVICES, INC. 21-16560-01 7 23 22 41 20 21 18 3 2 - - - - 157 150 87.728 0.585 

KAKIVIK ASSET MANAGEMENT 50-27667-01 18 15 6 4 1 - - - - - - - - 44 26 3.610 0.139

LAFAYETTE TESTING SERVICES, INC. 13-26583-01 1 1 2 - - - - - - - - - - 4 3 0.286 0.095 

LAW ENGINEERING & ENVIRON SVCS, INC. 34-25898-02 1 2 2 3 - - 3 - - - - - - 11 10 6.432 0.643 

LAW ENGINEERING & ENVIRON SERVICES 52-25461-01 - 1 1 2 1 2 - - - - - - - 7 7 2.985 0.426 

LONGVIEW INSPECTION, INC. 42-27593-01 9 17 5 11 8 9 23 1 2 - - - - 85 76 57.205 0.753 

LUCIUS PITKIN 29-27816-01 2 3 1 1 - - - - - - - - - 7 5 0.496 0.099 

MAGNA CHEK, INC. 21-19111-02 - 2 3 - - - - - - - - - - 5 5 0.361 0.072

MARTIN INDUSTRIAL TESTING, INC. 45-25452-01 - - - 1 - 1 - - - - - - - 2 2 1.224 0.612

MARYLAND Q.C. LABORATORIES 19-28683-01 2 16 3 1 2 - - - - - - - - 24 22 2.613 0.119 
A-7

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

NUREG-0713

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2000

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)

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320 Continued

MASSACHUSETTS MATERIALS RESEARCH 07-01173-03 - - - 2 1 1 - - - - - - - 4 4 2.131 0.533 

MATTINGLY TESTING SERVICES, INC. 25-21479-01 1 - 1 2 1 1 3 - - - - - - 9 8 5.961 0.745 

MID AMERICAN INSPECTION SERVICES, INC. 21-26060-01 - - 1 2 2 1 3 3 - - - - - 12 12 15.426 1.286 

MIDWEST INSPECTION SERVICES 35-27005-01 - 1 3 4 4 2 8 4 11 7 1 - - 45 45 103.775 2.306 

NAVY, DEPARTMENT OF THE* 45-23645-01NA 122 80 5 3 - - - - - - - - - 210 88 3.111 0.035 

NDT SPECIALISTS, INC. 48-25917-01 1 2 - 1 1 1 2 - 1 - - - - 9 8 7.885 0.986 

NEWPORT NEWS SHIPBUILDING 45-09428-02 1 23 6 6 - - - - - - - - - 36 35 4.036 0.115 

NON-DESTRUCTIVE INSPECTION SERVICES 47-11883-01 5 - - - - - - - - - - - - 5 - - - 

NON-DESTRUCTIVE TESTING 21-08606-03 6 7 4 5 3 - - - - - - - - 25 19 4.542 0.239 

NOOTER CORP. 24-03783-01 2 9 3 - - - - - - - - - - 14 12 0.824 0.069 

NOVA DATA TESTING LABS, INC. 45-24872-01 - 4 - 1 - 1 - - - - - - - 6 6 1.620 0.270

PACIFIC TESTING, INC. 53-29118-01 - - - 1 1 - 1 - - - - - - 3 3 2.669 0.890 

PENN INSPECTION CO. 35-21144-01 - 3 6 6 2 2 10 - - - - - - 29 29 20.505 0.707 

PHOENIX NATIONAL LABORATORIES 02-32183-01 2 3 1 - - - 2 - - - - - - 8 6 2.970 0.495 

PRECISION CALIBRATION & TESTING CO. 37-30546-01 1 3 3 3 - - - - - - - - - 10 9 1.584 0.176 

PRECISION COMPONENTS CORP. 37-16280-01 10 15 1 - - - - - - - - - - 26 16 0.494 0.031 

PRECISION TESTING & INSPECTION 45-25475-01 2 2 1 2 - - 1 - - - - - - 8 6 2.384 0.397

PRIME NDT SERVICES, INC. 37-23370-01 - 1 1 4 2 - 8 4 - - - - - 20 20 24.347 1.217 

PROFESSIONAL SERVICE INDUSTRIES 12-16941-03 3 6 5 4 - - 1 - - - - - - 19 16 3.660 0.229 

PROFESSIONAL WELDING ASSOC., INC. 48-25806-01 1 1 2 - - - - - - - - - - 4 3 0.306 0.102 

PROGRESS SERVICES, INC. 34-19592-02 4 5 1 - - - - - - - - - - 10 6 0.260 0.043 

Q. C. LABORATORIES, INC. 09-11579-03 - 9 4 5 - 2 - - - - - - - 20 20 4.706 0.235 

QSL INSPECTION, INC. 37-28085-01 3 13 7 5 1 8 16 7 4 1 - - - 65 62 70.058 1.130 

QUALITY INSPECTION SERVICES, INC. 31-30187-01 - 2 - - - 1 2 1 - - - - - 6 6 5.641 0.940 

SCIENTIFIC TECHNICAL, INC. 45-24882-01 1 3 4 2 3 - 1 - - - - - - 14 13 5.040 0.388 

SENCO CONSTRUCTION 12-32032-01 - 1 - - 1 - 2 2 - - - - - 6 6 8.179 1.363 

SENIOR ENGINEERING CO. 24-19500-01 5 - - - - - - - - - - - - 5 - - - 
A-8

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

NUREG-0713 APPENDIX A Annual TEDE for Non-Reactor NRC Licensees CY 2000

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)

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320 Continued

S. K. MCBRYDE, INC. 32-25137-01 1 2 1 1 1 - - - - - - - - 6 5 1.364 0.273 

SOUTHWEST X-RAY CORPORATION 49-27434-01 - 4 1 1 2 - 7 1 - 1 - - - 17 17 20.022 1.178 

SPEC CONSULTANTS, INC. 37-27891-01 - 7 7 2 4 1 5 1 - - - - - 27 27 15.604 0.578 

ST. LOUIS TESTING LABS., INC. 24-00188-02 2 6 5 1 - 1 3 - - - - - - 18 16 6.388 0.399 

T & K INSPECTION, INC. 33-27678-01 - 1 - 1 - - - 1 2 5 - - - 10 10 32.870 3.287 

TEI ANALYTICAL SERVICES, INC. 37-28004-01 - 8 6 4 4 2 8 - - - - - - 32 32 20.180 0.631 

TENNESSEE VALLEY AUTHORITY 41-06832-06 5 7 2 1 3 - - - - - - - - 18 13 2.777 0.214 

TESTING INSTITUTE OF ALASKA, INC. 50-17446-01 1 1 1 1 1 1 2 - - - - - - 8 7 4.690 0.670

TESTING TECHNOLOGIES, INC. 45-25007-01 4 3 3 4 - 1 12 4 - - - - - 31 27 29.160 1.080 

TESTMASTER INSPECTION CO., INC. 34-24872-01 - - - 2 1 - 3 2 - - - - - 8 8 9.595 1.199 

THREE RIVERS GAMMA SERVICES 37-28367-01 - - - 1 - - 1 - - - - - - 2 2 1.505 0.753 

TRI STATE INSPECTION & CONSULTANTS 37-19640-01 5 6 2 1 5 2 - - - - - - - 21 16 6.098 0.381 

TULSA GAMMA RAY, INC. 35-17178-01 3 14 10 9 8 6 16 8 3 - - - - 77 74 67.472 0.912

TWIN CITY TESTING CORPORATION 22-01376-02 4 3 4 5 2 1 5 2 - - - - - 26 22 16.425 0.747

TWIN PORTS TESTING, INC. 48-23476-01 8 1 2 3 2 1 1 - - - - - - 18 10 4.516 0.452

U.S. INSPECTION SERVICES 34-06943-02 23 45 14 20 10 6 6 2 - - - - - 126 103 37.509 0.364

VALLEY INDUSTRIAL X-RAY 04-29076-01 6 26 - 1 - - 9 1 - - - - - 43 37 17.211 0.465

VALLEY INSPECTION SERVICE, INC. 37-28385-01 - 2 1 1 - - 3 - 1 - - - - 8 8 7.470 0.934

WESTERN X-RAY COMPANY 35-19993-01 - - 5 4 5 5 12 2 - - - - - 33 33 30.100 0.912

WESTINGHOUSE GVT SVC CO, LLC 37-05809-02 - 3 - - - - - - - - - - - 3 3 0.087 0.029

WOS TESTING COMPANY, INC. 48-26385-01 1 4 - 1 - - 1 - - - - - - 7 6 2.449 0.408

X-R-I TESTING 21-05472-01 100 1 - - - - - - - - - - - 101 1 0.005 0.005

Total 102 630 753 362 398 225 163 331 94 46 24 3 - - 3,029 2,399 1,480.224 0.617 

* Reported under program code 03613 as a multi-site, multi-regional R&D broad scope licensee.
A-9

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

NUREG-0713

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 2000

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)

URANIUM ENRICHMENT PLANTS - 21200

USEC - PADUCAH GDP-1 2,306 312 29 - - - - - - - - - - 2,647 341 12.504 0.037

USEC - PORTSMOUTH GDP-2 1,708 635 26 - - - - - - - - - - 2,369 661 15.852 0.024

Total 2 4,014 947 55 - - - - - - - - - - 5,016 1,002 28.356 0.028

FUEL FABRICATION FACILITIES - 21210

BWX TECHNOLOGIES, INC. SNM-0042 4 50 46 106 76 33 29 2 - - - - - 346 342 168.428 0.492

FRAMATOME ANP, INC. SNM-1227 167 248 101 82 57 24 9 - - - - - - 688 521 122.137 0.234

FRAMATOME COGEMA FUELS SNM-1168 93 328 34 10 2 4 2 - - - - - - 473 380 23.188 0.061

GLOBAL NUCLEAR FUEL - AMERICAS SNM-1097 228 538 143 144 35 4 - - - - - - - 1,092 864 112.691 0.130

NUCLEAR FUEL SERVICES, INC. SNM-0124 155 377 62 55 15 4 8 - - - - - - 676 521 60.703 0.117

WESTINGHOUSE COMM NUCLEAR FUEL SNM-1107 4 115 152 112 68 36 129 79 20 3 - - - 718 714 615.467 0.862

WESTINGHOUSE ELECTRIC COMPANY SNM-0033 22 97 28 44 33 22 56 20 4 1 - - - 327 305 208.428 0.683

Total 7 673 1,753 566 553 286 127 233 101 24 4 - - - 4,320 3647 1,311.042 0.359

INDEPENDENT SPENT FUEL STORAGE INSTALLATION - 23200DEPARTMENT OF ENERGY SNM-2508 33 37 8 - - - - - - - - - - 78 45 2.932 0.065 

GENERAL ELECTRIC - MORRIS OPS SNM-2500 30 24 12 2 - - - - - - - - - 68 38 2.639 0.069

Total 2 63 61 20 2 - - - - - - - - - 146 83 5.571 0.067

NOTE: The data values shown bolded and in boxes represent the highest value in each category.
A-10

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

NUREG-0713

This page intentionally left blank.
B-1

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

NUREG-0713

ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES

2000

Appendix B
B-2

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

NUREG-0713 APPENDIX B Annual Whole Body Doses at Licensed Nuclear Power Facilities CY 2000

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 1,495 1,174 545 199 45 10 4 - - - - - - - 3,472 1,977 242.326

BEAVER VALLEY 1,2 PWR 1,125 828 457 275 102 38 30 - - - - - - - 2,855 1,730 337.867

BRAIDWOOD 1,2 PWR 1,446 921 418 178 42 2 1 - - - - - - - 3,008 1,562 194.126

BROWNS FERRY 1,2,3 BWR 1,066 818 377 271 120 43 28 - - - - - - - 2,723 1,657 333.215

BRUNSWICK 1,2 BWR 1,464 872 332 270 92 45 37 - - - - - - - 3,112 1,648 321.785

BYRON 1,2 PWR 1,273 459 256 162 39 18 25 - - - - - - - 2,232 959 193.871

CALLAWAY 1 PWR 935 192 43 9 - - - - - - - - - - 1,179 244 16.058

CALVERT CLIFFS 1,2 PWR 1,247 491 256 108 45 12 - - - - - - - - 2,159 912 134.689

CATAWBA 1,2 PWR 1,784 569 395 163 34 19 5 - - - - - - - 2,969 1,185 186.532

CLINTON BWR 1,479 566 333 221 78 28 22 - - - - - - - 2,727 1,248 253.382

COMANCHE PEAK 1,2 PWR 1,266 447 257 51 3 1 - - - - - - - - 2,025 759 77.679

COOK 1,2 PWR 2,871 1,540 582 257 79 28 20 - - - - - - - 5,377 2,506 337.584

COOPER STATION BWR 685 453 221 167 86 25 11 - - - - - - - 1,648 963 199.589

CRYSTAL RIVER 3 PWR 719 205 47 5 - - - - - - - - - - 976 257 14.649

DAVIS-BESSE PWR 742 581 325 140 49 12 2 - - - - - - - 1,851 1,109 168.044

DIABLO CANYON 1,2 PWR 1,182 547 268 156 64 18 4 - - - - - - - 2,239 1,057 180.792

DRESDEN 2,3 BWR 1,473 1,649 377 229 70 15 1 - - - - - - - 3,814 2,341 261.684

DUANE ARNOLD BWR 671 174 90 40 9 3 1 - - - - - - - 988 317 44.181

FARLEY 1,2 PWR 1,068 666 457 377 141 30 12 - - - - - - - 2,751 1,683 359.855

FERMI 2 BWR 1,233 801 283 150 32 - - - - - - - - - 2,499 1,266 145.964

FITZPATRICK BWR 955 601 257 225 111 40 29 4 - - - - - - 2,222 1,267 300.997

FORT CALHOUN PWR 534 142 57 42 8 - - - - - - - - - 783 249 35.215

GINNA PWR 631 193 134 69 25 6 2 - - - - - - - 1,060 429 76.435

GRAND GULF BWR 827 175 84 26 2 - 1 1 - - - - - - 1,116 289 34.877

HARRIS PWR 922 542 234 101 10 1 - - - - - - - - 1,810 888 100.981

HATCH 1,2 BWR 914 877 452 373 131 49 31 - - - - - - - 2,827 1,913 401.891

HOPE CREEK 1 BWR 791 761 218 140 68 31 18 - - - - - - - 2,027 1,236 188.295

INDIAN POINT 2 PWR 1,278 742 467 425 195 101 71 2 - - - - - - 3,281 2,003 567.224

INDIAN POINT 3 PWR 956 113 27 2 1 - - - - - - - - - 1,099 143 8.693

KEWAUNEE PWR 413 162 82 84 38 23 5 - - - - - - - 807 394 99.864

LASALLE 1,2 BWR 1,815 1,055 413 285 59 13 6 - - - - - - - 3,646 1,831 260.320

LIMERICK 1,2 BWR 1,816 658 266 198 91 46 20 - - - - - - - 3,095 1,279 260.611

MCGUIRE 1,2 PWR 1,480 502 297 103 23 13 2 - - - - - - - 2,420 940 132.513

MILLSTONE 2,3 PWR 1,281 936 283 122 25 15 4 - - - - - - - 2,666 1,385 142.664

MONTICELLO BWR 499 322 177 130 96 45 22 - - - - - - - 1,291 792 216.136

NINE MILE POINT 1,2 BWR 1,376 944 451 300 59 17 12 - - - - - - - 3,159 1,783 282.838

NORTH ANNA 1,2 PWR 1,809 522 146 57 3 2 - - - - - - - - 2,539 730 65.405

OCONEE 1,2,3 PWR 1,964 847 517 237 49 16 18 2 - - - - - - 3,650 1,686 272.697
B-3

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

NUREG-0713

APPENDIX B

Annual Whole Body Doses at Licensed Nuclear Power Facilities

CY 2000

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

OYSTER CREEK BWR 960 844 429 323 202 107 138 1 - - - - - - 3,004 2,044 614.379

PALISADES PWR 630 153 76 26 - - - - - - - - - - 885 255 26.305

PALO VERDE 1,2,3 PWR 1,329 814 273 134 42 11 5 - - - - - - - 2,608 1,279 158.105

PEACH BOTTOM 2,3 BWR 1,129 937 366 247 96 39 44 - - - - - - - 2,858 1,729 330.928

PERRY BWR 821 299 154 45 2 - 1 - - - - - - - 1,322 501 55.827

PILGRIM BWR 518 245 117 54 5 1 - - - - - - - - 940 422 50.797

POINT BEACH 1,2 PWR 698 386 172 149 39 14 5 - - - - - - - 1,463 765 138.989

PRAIRIE ISLAND 1,2 PWR 602 315 173 102 32 8 2 - - - - - - - 1,234 632 106.091

QUAD CITIES 1,2 BWR 1,308 1,248 547 400 225 189 225 6 - - - - - - 4,148 2,840 893.766

RIVER BEND 1 BWR 713 509 293 197 73 17 15 - - - - - - - 1,817 1,104 216.053

ROBINSON 2 PWR 738 117 18 1 1 1 - - - - - - - - 876 138 8.396

SALEM 1,2 PWR 761 733 210 134 66 30 18 - - - - - - - 1,952 1,191 198.068

SAN ONOFRE 2,3 PWR 2,523 716 241 91 14 4 7 - - - - - - - 3,596 1,073 115.499

SEABROOK PWR 904 944 149 61 4 - - - - - - - - - 2,062 1,158 70.091

SEQUOYAH 1,2 PWR 1,123 987 538 368 106 34 6 - - - - - - - 3,162 2,039 357.220

SOUTH TEXAS 1,2 PWR 1,303 695 324 255 86 12 - - - - - - - - 2,675 1,372 231.634

ST. LUCIE 1,2 PWR 1,125 670 249 45 15 9 2 - - - - - - - 2,115 990 98.691

SUMMER 1 PWR 798 535 224 110 28 9 20 7 - - - - - - 1,731 933 166.561

SURRY 1,2 PWR 2,065 637 307 181 47 15 10 - - - - - - - 3,262 1,197 193.169

SUSQUEHANNA 1,2 BWR 1,167 949 414 263 114 49 23 - - - - - - - 2,979 1,812 331.163

THREE MILE ISLAND 1 PWR 576 173 10 - - - - - - - - - - - 759 183 8.689

TURKEY POINT 3,4 PWR 1,106 665 343 196 55 27 6 - - - - - - - 2,398 1,292 219.852

VERMONT YANKEE BWR 823 88 56 36 14 4 - - - - - - - - 1,021 198 37.846

VOGTLE 1,2 PWR 1,062 487 267 121 20 4 - - - - - - - - 1,961 899 121.312

WASHINGTON NUCLEAR 2 BWR 504 552 98 44 12 - - - - - - - - - 1,210 706 53.152

WATERFORD 3 PWR 1,030 419 232 130 32 11 1 - - - - - - - 1,855 825 131.701

WATTS BAR 1 PWR 1,253 677 227 125 20 3 1 - - - - - - - 2,306 1,053 122.453

WOLF CREEK 1 PWR 739 460 210 125 51 12 3 - - - - - - - 1,600 861 143.417

TOTALS: 35 BWRs 25,007 16,397 6,805 4,634 1,847 806 685 12 - - - - - - 55,193 31,186 6,089.676

TOTALS: 69 PWRs 48,786 23,904 10,793 5,676 1,678 569 291 11 - - - - - - 91,708 42,922 6,562.006

TOTALS: 104 LWRs 73,793 40,301 17,598 10,310 3,525 1,375 976 23 - - - - - - 147,901 74,108 12,651.682
B-4

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

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

CY 2000

PLANT NAME TYPE

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

No

Meas.

Exposure

Meas.

<0.10

0.10-

0.25

0.25-

0.50

0.50-

0.75

0.75-

1.00

1.00-

2.00

2.00-

3.00

3.00-

4.00

4.00-

5.00

5.00-

6.00

6.00-

7.00 >12.0

Total

Number

Monitored

Number

With

Meas.

Dose

Total

Collective

TEDE

(PersonRem) 7.00- 12.00

REACTORS NOT YET IN COMMERCIAL OPERATION

WATTS BAR 2 PWR Reported with Watts Bar 1

REACTORS NO LONGER IN COMMERCIAL OPERATION

BIG ROCK POINT BWR 160 89 29 26 29 28 25 - - - - - - - 386 226 89.271

HADDAM NECK PWR 563 191 102 69 53 58 66 16 - - - - - - 1,118 555 262.192

HUMBOLDT BAY BWR 245 17 3 - - - - - - - - - - - 265 20 0.911

LACROSSE BWR 25 27 6 3 1 - - - - - - - - - 62 37 3.548

MAINE YANKEE PWR 290 230 96 76 50 20 18 - - - - - - - 780 490 121.133

MILLSTONE BWR 441 323 97 42 9 5 2 - - - - - - - 919 478 59.955

RANCHO SECO PWR 139 162 22 17 14 4 - - - - - - - - 358 219 25.795

SAN ONOFRE PWR 3,180 250 59 55 39 12 1 - - - - - - - 3,596 416 71.214

THREE MILE ISLAND PWR 221 66 4 - - - - - - - - - - - 291 70 0.401

TROJAN PWR 412 62 41 24 - - - - - - - - - - 539 127 17.631

YANKEE-ROWE PWR 394 29 8 1 - - - - - - - - - - 432 38 2.406

ZION PWR 146 17 4 5 - - - - - - - - - - 172 26 3.015

REACTORS NO LONGER IN COMMERCIAL OPERATION, REPORTED WITH OTHER UNITS

BROWNS FERRY 1 BWR Reported with Browns Ferry 2, 3 and still included in the count of operating reactors, although Unit 1 has been on Administrative Hold since June, 1985.

DRESDEN 1 BWR Reported with Dresden 2, 3. An estimated 12 person-rem was attributed to Unit 1.

INDIAN POINT 1 PWR Reported with Indian Point 2

TOTAL REPORTING: 13 6,216 1,463 471 318 195 127 112 16 - - - - - - 8,918 2,702 657.472
C-1

Thirty-Third Annual Report, 2000 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 - 2000

Appendix C*

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

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

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-61977 610.3 76.8 601 2560.43 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 58.61,608 803 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 8060.460.63

1985 1,192.3 73.61,262 2860.23 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 8760.28 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 3860.17 0.28

19961,596.0 89.5 1,441 203 0.14 0.13

1997 1,621.9 95.9 1,195 119 0.10 0.07

1998 1,494.688.1 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

BEAVER VALLEY 1, 2 1977 355.657.0 331 878 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 - 810, 820 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

1986581.3 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 1,514.688.6 487 44 0.09 0.03

1995 1,389.2 83.1 1,536453 0.29 0.33

19961,269.0 76.5 1,688 449 0.27 0.35

1997 1,159.3 72.1 1,391 3060.22 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
C-3

Thirty-Third Annual Report, 2000 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. 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.

BIG ROCK POINT1 1969 48.1 165 136 0.82 2.83

Docket 50-155; DPR-61970 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 2760.98 6.78

1975 35.1 59.8 300 180 0.60 5.13

197629.5 50.1 488 289 0.59 9.80

1977 43.673.4 465 334 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 43.670.8 521 328 0.63 7.52

1983 42.3 71.0 493 263 0.53 6.22

1984 50.3 78.6297 155 0.52 3.08

1985 43.8 73.5 435 291 0.67 6.64

198661.0 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 2260.52 3.82

1992 32.7 54.5 496277 0.568.47

1993 51.2 79.4 419 152 0.362.97

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 22689 0.40 ---

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 - 1100, 1100 MWe 1995 1,914.7 85.4 1,134 2360.21 0.12

19961,854.9 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

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

50-2961977 1,327.5 73.7 1,985 8760.44 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 73.62,838 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, 1118 MWe 1982 2,025.4 67.6 3,360 2,230 0.66 1.10

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

19860.0 0.0 3,074 1,054 0.34 ---
C-4

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

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 1987 0.0 0.0 3,184 1,1860.37 ---

(continued) 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 3560.19 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

19961,972.8 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 0.260.21

2000 2,143.8 97.1 1,657 333 0.20 0.16

BRUNSWICK 1, 2 1976297.2 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 - 820, 811 MWe 1982 540.3 50.3 4,957 3,792 0.767.02

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

19861,051.3 69.1 3,370 1,909 0.57 1.82

1987 1,152.4 80.63,052 1,419 0.461.23

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 991.667.8 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

19961,261.1 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 3960.20 0.26

1999 1,494.7 92.8 1,818 418 0.23 0.28

2000 1,571.2 95.61,648 322 0.20 0.20

BYRON 1, 2 1986894.5 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 1,812.690.2 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 - 1105, 1105 MWe 1992 1,888.4 90.1 1,021 199 0.19 0.11

1993 1,785.683.5 1,370 432 0.32 0.24

1994 1,953.3 90.7 962 280 0.29 0.14

1995 1,900.685.5 1,107 306 0.28 0.16

19961,758.4 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

2 Browns Ferry 1 remains in the count of operating reactors, but was placed on Administrative Hold in June of 1985. Parentheses

indicate plant capacity when plant was operational.
C-5

Thirty-Third Annual Report, 2000 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

CALLAWAY 1 1985 967.4 90.0 964 36 0.04 0.04

Docket 50-483; NPF-30 1986865.2 81.3 1,052 225 0.21 0.26

1st commercial operation 12/84 1987 759.0 71.1 1,082 393 0.360.52

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 989.684.7 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 99.8 244 160.07 0.01

CALVERT CLIFFS 1, 2 1976753.4 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 1,496677 0.45 0.52

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

Capacity - 825, 835MWe 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

19861,530.0 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 1,296291 0.22 0.21

1989 333.620.1 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

19961,438.5 82.4 1,167 239 0.20 0.17

1997 1,499.689.1 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

CATAWBA 1, 2 1986638.9 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

19961,879.1 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 0.160.09
C-6

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

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

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 - 930 MWe 1992 589.7 68.6 1,195 431 0.36 0.73

1993 701.5 79.61,253 498 0.40 0.71

1994 883.3 94.8 409 63 0.15 0.07

1995 731.1 83.0 1,182 3160.27 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

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

Docket 50-445; NPF-87 1992 830.8 84.0 1,128 188 0.17 0.23

1st commercial operation 1993 853.8 81.2 945 109 0.12 0.13

8/90, 8/93 1994 1,750.0 93.7 970 90 0.09 0.05

Type - PWR 1995 2,022.692.5 951 179 0.19 0.09

Capacity - 1150, 1150 MWe 19961,804.8 81.4 1,462 288 0.20 0.16

1997 2,002.4 93.4 870 1460.17 0.07

1998 2,037.8 94.9 967 232 0.24 0.11

1999 1,981.5 90.9 1,316251 0.19 0.13

2000 2,104.7 95.3 759 78 0.10 0.04

COOK 1, 2 1976807.4 83.1 395 116 0.29 0.14

Docket 5-315; DPR-58, -74 1977 573.0 76.1 802 300 0.37 0.52

1st commercial operation 1978 744.8 73.6778 3360.43 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 47.61,984 945 0.48 1.02

19861,307.1 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

19961,938.9 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

COOPER STATION 1975 456.4 83.6 579 117 0.20 0.26

Docket 50-298; DPR-461976433.3 75.5 763 350 0.460.81

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

Type - BWR 1978 576.0 91.0 297 158 0.53 0.27

Capacity - 764 MWe 1979 591.0 87.6 426 221 0.52 0.37

1980 448.3 71.2 785 859 1.09 1.92

1981 457.1 71.2 935 579 0.62 1.27

1982 622.3 84.6 743 542 0.73 0.87

1983 396.6 63.3 1,383 1,293 0.93 3.26

1984 411.9 67.2 1,598 799 0.50 1.94

1985 127.3 21.5 1,980 1,333 0.67 10.47
C-7

Thirty-Third Annual Report, 2000 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

COOPER STATION 1986480.0 74.7 895 320 0.36 0.67

(continued) 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

1996742.1 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

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 - 843 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 47.61,976 689 0.35 2.00

1986319.5 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

1996290.8 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 0.060.03

1999 727.5 87.8 1,324 251 0.19 0.35

2000 819.4 97.6257 15 0.060.02

DAVIS-BESSE 1 1978 326.4 48.7 421 48 0.11 0.15

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

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

Type - PWR 1981 531.4 67.4 578 58 0.10 0.11

Capacity - 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

19863.3 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 0.262.13

1989 880.0 98.6404 38 0.09 0.04

1990 500.0 56.7 1,377 489 0.36 0.98

1991 703.681.8 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 2567 0.03 0.01

1996775.8 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 95.6397 28 0.07 0.03

2000 770.8 87.3 1,109 168 0.15 0.22
C-8

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

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

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, 3/861990 1,952.691.0 1,441 323 0.22 0.17

Type - PWRs 1991 1,809.683.8 2,040 546 0.27 0.30

Capacity - 1073, 1087 MWe 1992 1,995.7 90.9 1,850 459 0.25 0.23

1993 2,008.691.4 1,508 281 0.19 0.14

1994 1,832.683.3 2,317 590 0.26 0.32

1995 1,950.3 90.0 1,615 286 0.18 0.15

19962,003.6 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

DRESDEN 13 , 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), 772, 773 MWe 1975 708.1 54.62,310 3,423 1.48 4.83

19761,127.2 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 1,9461,529 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 913.665.6 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

1986740.5 52.6 3,111 2,668 0.86 3.60

1987 933.9 74.0 2,052 1,145 0.561.23

1988 1,014.7 75.8 2,414 1,409 0.58 1.39

1989 1,184.2 83.1 2,259 1,131 0.50 0.96

1990 1,107.8 76.6 2,235 1,400 0.63 1.26

1991 675.2 60.7 2,044 1,005 0.49 1.49

1992 872.4 75.4 1,812 619 0.34 0.71

1993 960.1 68.5 2,751 1,655 0.60 1.72

1994 690.2 51.7 2,336 833 0.36 1.21

1995 643.1 49.8 2,482 875 0.35 1.36

1996612.647.7 1,788 456 0.26 0.74

1997 1,096.2 79.5 2,747 467 0.17 0.43

1998 1,354.7 90.62,311 427 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

DUANE ARNOLD 1976305.2 78.0 350 105 0.30 0.34

Docket 50-331; DPR-49 1977 353.678.9 538 299 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 0.360.78

Capacity - 520 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

3 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-9

Thirty-Third Annual Report, 2000 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

DUANE ARNOLD 1986365.5 82.0 476 187 0.39 0.51

(continued) 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 0.460.50

1990 367.4 75.8 1,460 861 0.59 2.34

1991 503.7 94.5 336202 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 498.694.0 493 120 0.24 0.24

1995 452.5 83.8 1,129 357 0.32 0.79

1996476.8 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

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 - 828, 838 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

19861,409.4 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 84.62,206 749 0.34 0.53

1990 1,464.0 86.7 1,700 457 0.27 0.31

1991 1,464.0 88.1 1,645 648 0.39 0.44

1992 1,331.7 81.8 2,018 805 0.40 0.60

1993 1,455.5 88.3 1,284 333 0.260.23

1994 1,587.2 93.0 1,035 250 0.24 0.16

1995 1,311.2 83.8 1,574 460 0.29 0.35

19961,549.2 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 88.61,683 360 0.21 0.25

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

1996577.5 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 939.687.6 1,266 146 0.12 0.15

FITZPATRICK 1976489.0 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 2,0562,040 0.99 4.00

1981 562.9 74.7 2,490 1,425 0.57 2.53

1982 583.675.0 2,322 1,190 0.51 2.04
C-10

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

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

FITZPATRICK 1983 546.2 70.6 1,715 1,090 0.64 2.00

(continued) 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

1986711.2 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 72.61,536 884 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 559.681.7 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

1996623.3 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

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 596410 0.69 1.20

Capacity - 478 MWe 1979 440.0 95.7 451 1260.28 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

1986431.8 94.3 756 74 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 99.6211 23 0.11 0.05

1995 402.8 83.2 627 139 0.22 0.35

1996374.9 79.5 740 226 0.31 0.60

1997 435.9 93.6258 41 0.160.09

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

GINNA 1971 327.8 340 430 1.261.31

Docket 50-244; DPR-18 1972 293.6677 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

1976248.8 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
C-11

Thirty-Third Annual Report, 2000 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 1986433.3 87.4 901 357 0.40 0.82

(continued) 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 418.686.7 947 328 0.35 0.78

1992 417.6 86.9 832 261 0.31 0.63

1993 419.686.3 856 193 0.23 0.46

1994 405.3 83.2 679 138 0.20 0.34

1995 437.0 89.6738 1360.18 0.31

1996347.9 71.1 976 168 0.17 0.48

1997 444.691.8 533 81 0.15 0.18

1998 491.8 100.0 161 15 0.09 0.03

1999 403.4 85.6641 175 0.27 0.43

2000 434.2 91.6429 760.18 0.18

GRAND GULF 1986494.7 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 932.680.0 1,972 498 0.25 0.53

Capacity - 1210 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

19961,096.2 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

HADDAM NECK4 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 515.6355 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

1976482.9 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 1,2261,162 0.95 2.36

1980 426.8 75.0 1,860 1,353 0.73 3.17

1981 487.5 84.3 1,554 1,0360.67 2.13

1982 543.9 93.4 559 1260.23 0.23

1983 453.7 77.8 1,645 1,384 0.84 3.05

1984 404.0 71.7 1,430 1,2160.85 3.01

1985 556.1 98.4 384 101 0.26 0.18

1986294.8 53.6 1,945 1,567 0.81 5.32

1987 304.654.0 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 448.681.6 1,004 408 0.41 0.91

1994 455.677.7 463 135 0.29 0.30

4 Haddam Neck 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-12

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

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 NECK4 1995 439.4 77.7 1,006442 0.44 1.01

(continued) 1996331.8 55.7 673 175 0.26 0.53

1997 -1.3 0.0 219 11 0.05 ---

1998 0.0 0.0 423 94 0.22 ---

1999 0.0 0.0 545 109 0.20 ---

2000 0.0 0.0 555 262 0.47 ---

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 2260.260.31

Capacity - 860 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

1996860.695.4 444 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 97.9 247 160.060.02

2000 783.0 92.5 888 101 0.11 0.13

HATCH 1, 2 1976496.3 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 54.62,131 582 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 - 863, 878 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 79.62,841 818 0.29 0.68

1986872.0 64.8 3,486 1,497 0.43 1.72

1987 1,295.4 89.7 2,202 8160.37 0.63

1988 1,001.4 70.4 2,509 1,401 0.561.40

1989 1,271.1 87.1 1,350 5560.41 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 88.61,615 550 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

19961,519.6 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

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 12/861989 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 - 1031 MWe 1991 882.5 84.2 1,700 373 0.22 0.42

1992 841.9 80.8 1,694 436 0.26 0.52

1993 1,049.2 97.8 688 98 0.14 0.09

1994 852.0 81.2 1,779 3260.18 0.38

1995 844.5 79.8 1,571 1960.12 0.23

1996806.9 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 1,236188 0.15 0.23

4 Haddam Neck 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-13

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

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

HUMBOLDT BAY5 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), 0 MWe 1973 50.1 210 266 1.27 5.31

1974 43.4 83.8 296318 1.07 7.33

1975 45.3 83.9 265 339 1.28 7.48

197623.5 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 ---

19960.0 0.0 66 5 0.08 ---

1997 0.0 0.0 105 160.15 ---

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 ---

INDIAN POINT 16, 2, 37 1969 206.2 298 1.45

Docket 50-3, 50-247, 50-286; 1970 43.3 1,639 37.85

DPR-5, -26, -64 1971 154.0 768 4.99

1st commercial operation 1972 142.3 967 6.80

10/62, 8/74, 8/76 1973 0.0 2,998 5,262 1.76 ---

Type - PWRs 1974 556.1 59.4 1,019 910 0.89 1.64

Capacity - (265), 951, 965 MWe 1975 584.4 74.8 891 705 0.79 1.21

1976273.9 34.8 1,590 1,950 1.23 7.12

1977 1,278.3 75.3 1,391 1,070 0.77 0.84

1978 1,172.3 67.8 1,909 2,006 1.05 1.71

INDIAN POINT 16, 2 1979 574.0 71.4 1,349 1,279 0.95 2.23

1980 510.8 64.8 1,577 971 0.62 1.90

1982 532.4 65.4 2,144 1,635 0.76 3.07

1983 702.684.0 1,057 486 0.46 0.69

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

Docket 50-247; DPR-261985 791.4 95.7 708 192 0.27 0.24

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

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

Capacity - 951 MWe 1988 719.3 86.9 890 235 0.26 0.33

1989 532.5 64.6 2,093 1,436 0.69 2.70

1990 618.0 66.6 1,061 608 0.57 0.98

1991 461.2 55.7 1,810 1,468 0.81 3.18

1992 930.9 99.1 489 97 0.20 0.10

1993 702.1 75.7 1,514 675 0.45 0.96

1994 903.8 100.0 381 48 0.13 0.05

1995 582.4 70.8 1,690 548 0.32 0.94

5 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.

6 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.

7 Indian Point 3 was purchased by a different utility and now reports separately. Parentheses indicate plant capacity when plant

was operational.
C-14

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

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

INDIAN POINT 2 1996927.8 94.8 388 54 0.14 0.06

(continued) 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

INDIAN POINT 37 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 1,2260.83 7.15

Capacity - 965 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

1986655.3 73.4 588 202 0.34 0.31

1987 574.662.7 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

1996695.3 74.8 289 22 0.08 0.03

1997 495.1 54.9 1,608 234 0.15 0.47

1998 874.0 95.3 213 15 0.07 0.02

1999 829.8 88.3 893 117 0.13 0.14

2000 960.0 99.3 143 9 0.06 0.01

KEWAUNEE 1975 401.9 88.2 104 28 0.27 0.07

Docket 50-305; DPR-43 1976405.9 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 - 511 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 87.6353 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 1760.34 0.40

1986461.7 85.8 502 169 0.34 0.37

1987 480.0 89.7 755 2260.30 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 475.688.8 364 72 0.20 0.15

1995 455.687.8 415 109 0.26 0.24

1996380.4 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 432.688.8 394 100 0.25 0.23

7 Indian Point 3 was purchased by a different utility and now reports separately.
C-15

Thirty-Third Annual Report, 2000 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

LACROSSE8 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), 0 MWe 1974 37.9 81.0 115 139 1.21 3.67

1975 32.0 69.6 165 234 1.42 7.31

197621.2 47.6 118 110 0.93 5.19

1977 11.3 33.7 141 225 1.60 19.91

1978 21.662.0 182 164 0.90 7.59

1979 24.0 71.8 153 1861.22 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 44.6148 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

198619.646.1 260 290 1.12 14.80

1987 0.0 0.0 127 68 0.54 ---

1993 0.0 0.0 48 8 0.17 ---

1994 0.0 0.0 65 8 0.12 ---

1995 0.0 0.0 31 3 0.10 ---

19960.0 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 ---

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 1986929.5 50.6 1,614 898 0.56 0.97

1st commercial operation 1987 1,030.0 59.3 1,744 1,3960.80 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 1,3860.560.92

Capacity - 1114, 1114 MWe 1990 1,754.3 84.61,830 948 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 77.61,812 7260.40 0.46

1995 1,696.6 82.1 1,623 512 0.32 0.30

19961,053.8 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 2,138.697.1 1,831 260 0.14 0.12

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 - 1143, 1143 MWe 1993 1,913.2 91.61,287 217 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

19962,026.2 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 2,089.694.2 1,800 272 0.15 0.13

2000 2,154.9 95.8 1,279 261 0.20 0.12

8

 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-16

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

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 YANKEE9 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 1976712.2 95.0 244 85 0.35 0.12

Capacity - (860) MWe 1977 617.6 82.2 508 245 0.48 0.40

1978 642.7 84.1 638 420 0.66 0.65

1979 537.0 68.4 393 154 0.39 0.29

1980 527.0 72.2 735 462 0.63 0.88

1981 624.2 78.2 868 424 0.49 0.68

1982 542.5 69.1 1,295 619 0.48 1.14

1983 677.1 83.6 592 165 0.28 0.24

1984 605.7 74.4 1,262 884 0.70 1.46

1985 635.4 79.2 1,009 700 0.69 1.10

1986737.687.8 495 100 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 0.260.12

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

1996602.9 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 ---

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 19861,360.0 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

19961,881.8 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

MILLSTONE UNIT 110 1972 377.6612 5960.97 1.58

Docket 50-245; DPR-21 1973 225.1 1,184 663 0.56 2.95

1st commercial operation 3/71 1974 430.3 79.1 2,477 1,430 0.58 3.32

Type - BWR 1975 465.4 75.6 2,587 2,022 0.78 4.34

Capacity - (641) MWe 1976 449.8 76.1 1,387 1,194 0.86 2.65

1977 575.7 89.61,075 394 0.37 0.68

1978 556.6 87.6 1,391 1,416 1.02 2.54

9 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.

10 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-17

Thirty-Third Annual Report, 2000 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

MILLSTONE UNIT 110 1979 505.0 77.3 2,001 1,795 0.90 3.55

(continued) 1980 405.8 69.0 3,024 2,157 0.71 5.32

1981 304.3 51.62,5061,4960.60 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 83.6732 608 0.83 1.11

1986626.8 95.4 389 150 0.39 0.24

1987 523.4 79.61,588 684 0.43 1.31

1988 658.8 98.6 327 144 0.44 0.22

1989 554.684.2 852 462 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 520.680.0 910 620 0.68 1.19

19960.0 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 ---

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, 4/861980 579.3 69.2 893 637 0.71 1.10

Type - PWRs 1981 722.4 82.6890 531 0.60 0.74

Capacity - 873, 1154 MWe 1982 595.9 70.62,083 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

19861,313.8 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

1996418.1 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

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 1976476.4 91.5 325 263 0.81 0.55

1977 425.679.9 860 1,000 1.16 2.35

1978 459.4 87.2 679 375 0.55 0.82

1979 522.0 97.6372 157 0.42 0.30

1980 411.8 78.2 1,114 531 0.48 1.29

1981 389.3 72.61,4461,004 0.69 2.58

10 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-18

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

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 1982 291.1 63.3 1,307 993 0.76 3.41

(continued) 1983 494.696.3 416 121 0.29 0.24

1984 33.7 9.2 1,872 2,462 1.32 73.06

1985 509.8 91.7 586327 0.560.64

1986402.7 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

1996461.686.9 757 240 0.32 0.52

1997 417.4 75.9 399 1060.27 0.25

1998 470.2 88.1 674 209 0.31 0.44

1999 530.7 92.9 451 70 0.160.13

2000 483.2 84.2 792 2160.27 0.45

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, 1123 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 542.693.3 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 84.62,352 633 0.27 0.46

1994 1,589.695.9 800 149 0.19 0.09

1995 1,382.2 82.5 2,304 759 0.33 0.55

19961,598.6 91.6 1,596 290 0.18 0.18

1997 1,321.5 74.8 1,425 429 0.30 0.32

1998 1,387.3 87.0 1,744 378 0.22 0.27

1999 1,409.5 81.3 1,709 447 0.260.32

2000 1,443.9 88.1 1,783 283 0.160.20

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 2,416680 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 - 893, 897 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

19861,484.5 83.0 2,831 722 0.26 0.49

1987 1,112.667.8 2,624 1,521 0.58 1.37

1988 1,772.7 96.7 992 112 0.11 0.06
C-19

Thirty-Third Annual Report, 2000 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

NORTH ANNA 1, 2 1989 1,226.8 72.5 2,861 1,471 0.51 1.20

(continued) 1990 1,590.4 90.5 2,161 590 0.27 0.37

1991 1,597.5 88.62,085 629 0.30 0.39

1992 1,403.2 84.1 2,159 5760.27 0.41

1993 1,428.4 80.1 2,768 908 0.33 0.64

1994 1,717.1 95.9 1,036193 0.19 0.11

1995 1,666.4 90.8 1,551 367 0.24 0.22

19961,569.6 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

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 1,1060.53 0.49

1985 2,036.3 80.5 2,729 1,304 0.48 0.64

19861,995.6 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 2,188.685.4 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 0.160.10

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

19961,847.9 70.3 1,479 257 0.17 0.14

1997 1,563.7 67.7 1,379 223 0.16 0.14

1998 1,989.1 81.3 1,695 366 0.22 0.18

1999 2,264.5 90.3 1,568 202 0.13 0.09

2000 2,321.0 91.61,686 273 0.160.12

OYSTER CREEK 1970 413.695 63 0.660.15

Docket 50-219; DPR-161971 448.9 249 240 0.960.53

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

Type - BWR 1973 424.6782 1,2361.58 2.91

Capacity - 619 MWe 1974 434.5 70.4 935 984 1.05 2.26

1975 373.673.3 1,210 1,140 0.94 3.05

1976456.5 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 9.62,369 2,054 0.87 55.36

1985 446.1 89.4 2,342 748 0.32 1.68

1986157.3 31.5 3,740 2,436 0.65 15.49

1987 371.0 64.2 1,932 522 0.27 1.41

1988 419.665.9 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 0.160.61
C-20

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

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

OYSTER CREEK 1991 351.660.5 3,089 1,185 0.38 3.37

(continued) 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

1996515.0 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

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 1976346.9 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

1986102.3 15.1 1,438 672 0.47 6.57

1987 319.2 48.2 1,122 4560.41 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 0.160.36

1992 581.9 76.1 1,267 295 0.23 0.51

1993 424.4 53.7 908 289 0.32 0.68

1994 541.8 67.0 397 60 0.15 0.11

1995 583.5 75.8 1,230 462 0.38 0.79

1996638.2 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

PALO VERDE 1, 2, 3 1987 1,638.1 66.1 1,792 669 0.37 0.41

Docket 50-528, 50-529; 50-530 1988 1,700.9 65.5 2,173 688 0.32 0.40

NPF-41, NPF-51, NPF-74 1989 965.3 26.5 2,615 720 0.28 0.75

1st commercial operation 1990 2,500.9 67.5 2,236 499 0.22 0.20

1/86,9/86,1/88 1991 3,043.9 78.9 2,242 605 0.27 0.20

Type - PWRs 1992 3,102.3 82.0 1,981 541 0.27 0.17

Capacity - 1243, 1243, 1247 1993 2,677.1 74.3 2,124 592 0.28 0.22

MWe 1994 2,827.679.1 2,048 462 0.23 0.16

1995 3,265.2 85.6 1,875 482 0.26 0.15

19963,482.7 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 1460.11 0.04

2000 3,458.693.0 1,279 158 0.12 0.05

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

Docket 50-277, 50-278; 19761,379.2 73.0 2,136 840 0.39 0.61

DPR-44, -561977 1,052.4 58.7 2,827 2,0360.72 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 2,2761,388 0.61 0.80

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

Capacity - 1093, 1093 MWe 1981 1,161.8 58.0 2,857 2,506 0.88 2.16
C-21

Thirty-Third Annual Report, 2000 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

PEACH BOTTOM 2, 3 1982 1,583.3 76.9 2,734 1,977 0.72 1.25

(continued) 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

19861,395.0 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

19962,012.4 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

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 - 1223 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 95.6587 64 0.11 0.06

1996895.677.2 1,622 307 0.19 0.34

1997 930.684.7 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 3260.19 0.31

2000 1,148.2 97.1 501 560.11 0.05

PILGRIM 1 1973 484.0 230 1260.55 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 1976287.8 60.7 1,317 2,648 2.01 9.20

Capacity - 670 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 2,3261,162 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

1986121.9 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 204.664.1 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 453.671.4 758 200 0.26 0.44

1995 531.7 80.7 1,294 482 0.37 0.91

1996631.3 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
C-22

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

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 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 1976857.3 86.7 313 370 1.18 0.43

Capacity - 510, 512 MWe 1977 873.9 87.3 417 430 1.03 0.49

1978 914.4 90.9 336320 0.95 0.35

1979 808.0 80.8 610 644 1.06 0.80

1980 727.2 82.5 561 598 1.07 0.82

1981 760.4 83.6 773 596 0.77 0.78

1982 757.2 84.3 767 609 0.79 0.80

1983 648.2 72.7 1,702 1,403 0.82 2.16

1984 788.9 78.61,372 789 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 88.6734 410 0.560.46

1989 847.8 85.5 736504 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 1860.33 0.20

1994 914.5 91.2 548 170 0.31 0.19

1995 858.4 86.1 548 190 0.35 0.22

1996831.684.7 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

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 546221 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 0.360.44

1981 844.9 80.5 836329 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 546147 0.27 0.15

1985 882.684.0 1,082 416 0.38 0.47

1986930.690.3 818 255 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 47699 0.21 0.10

1990 925.4 89.2 737 188 0.260.20

1991 1,023.3 95.658698 0.17 0.10

1992 811.676.2 845 211 0.25 0.26

1993 978.3 90.7 532 1060.20 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

1996992.1 91.4 558 112 0.20 0.11

1997 817.681.4 753 174 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
C-23

Thirty-Third Annual Report, 2000 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 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 1976951.2 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 88.61,207 1,618 1.34 1.44

Type - BWRs 1979 1,075.0 84.61,688 2,158 1.28 2.01

Capacity - 769, 769 MWe 1980 866.9 64.4 3,089 4,838 1.57 5.58

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

1982 1,018.7 76.0 2,314 3,757 1.62 3.69

1983 1,088.5 79.2 1,802 2,491 1.38 2.29

1984 994.665.7 1,678 1,579 0.94 1.59

1985 1,268.0 82.7 1,184 990 0.84 0.78

19861,093.2 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 1,486827 0.560.70

1989 1,196.3 85.9 1,721 900 0.52 0.75

1990 1,148.9 77.8 2,1861,028 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 7360.360.73

1996876.660.1 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

RANCHO SECO11 1976268.1 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), 0 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

19860.0 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 0.0 161 0.06---

19960.0 0.0 16 1 0.04 ---

1997 0.0 0.0 160 0.00 ---

1998 0.0 0.0 61 3 0.05 ---

1999 0.0 0.0 302 11 0.04 ---

2000 0.0 0.0 219 260.12 ---

11 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-24

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

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 - 936 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

1996836.1 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 2160.20 0.26

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 - 683 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 1,4260.71 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

1986577.1 80.3 1,571 539 0.34 0.93

1987 510.1 72.5 1,379 499 0.360.98

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

1996654.8 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 0.060.01

SALEM 1, 2 1978 546.4 55.6 574 122 0.21 0.22

Docket 50-272, -311; 1979 250.0 25.5 1,488 584 0.39 2.34

DPR-70, -75 1980 680.6 69.2 1,704 449 0.26 0.66

1st commercial operation 1981 743.0 78.1 1,652 254 0.15 0.34

6/77, 10/81 1982 1,440.4 72.6 3,228 1,203 0.37 0.84

Type - PWRs 1983 742.0 30.5 2,383 581 0.24 0.78

Capacity - 1106, 1106 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

19861,484.3 70.4 3,554 599 0.17 0.40

1987 1,478.2 73.3 2,543 600 0.24 0.41

1988 1,591.673.6 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
C-25

Thirty-Third Annual Report, 2000 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 1994 1,367.4 73.8 950 188 0.20 0.14

(continued) 1995 558.1 29.3 1,195 218 0.18 0.39

19960.0 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

SAN ONOFRE 112, 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 3262560.79 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, 1080 1975 389.0 87.4 424 292 0.69 0.75

MWe 1976297.9 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

19861,698.2 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 1,987.675.3 1,814 412 0.23 0.21

1992 2,228.687.1 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 0.060.01

1995 1,686.9 79.1 1,914 455 0.24 0.27

19962,089.3 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 112 1999 0.0 0.0 241 160.07 ---

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

DPR-13,

1st commercial operation 1/68

Type - PWR

Capacity - (436), 0 MWe

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

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

NPF-10, NPF-15

1st commercial operation

8/83, 4/84

Type - PWRs

Capacity - 1070, 1080 MWe

12 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-26

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

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

SEABROOK 1991 810.4 75.9 699 92 0.13 0.11

Docket 50-443; NPF-861992 932.4 81.3 806147 0.18 0.16

1st commercial operation 8/90 1993 1,071.5 93.6110 60.05 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

19961,168.6 99.6 206 10 0.05 0.01

1997 907.0 79.8 1,571 1860.12 0.21

1998 957.684.5 559 19 0.03 0.02

1999 991.5 87.5 1,339 1060.08 0.11

2000 901.8 79.3 1,158 70 0.060.08

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 - 1122, 1117 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

19962,003.9 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

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

19962,465.9 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 91.61,328 260 0.20 0.12

2000 2,180.0 89.7 1,372 232 0.17 0.11

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

19861,588.6 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 1,876777 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 1,227.677.7 1,462 492 0.34 0.40

1994 1,424.8 85.0 1,896505 0.27 0.35

1995 1,306.6 76.0 1,498 413 0.28 0.32
C-27

Thirty-Third Annual Report, 2000 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 19961,473.4 86.5 1,433 385 0.27 0.26

(continued) 1997 1,394.683.6 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

SUMMER 1 1984 504.661.1 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 1986853.7 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 3760.34 0.52

1991 642.5 82.9 984 291 0.30 0.45

1992 892.697.4 249 27 0.11 0.03

1993 728.3 84.0 1,121 297 0.260.41

1994 536.7 69.5 1,549 374 0.24 0.70

1995 899.8 97.2 257 13 0.05 0.01

1996850.4 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

SURRY 1, 2 1973 420.6936152 0.160.36

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 1976930.7 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 1,210.677.2 2,203 1,837 0.83 1.52

Capacity - 801, 801 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 907.659.3 3,753 4,244 1.13 4.68

1982 1,323.3 88.5 1,878 1,490 0.79 1.13

1983 916.2 61.3 2,754 3,220 1.17 3.51

1984 1,026.7 71.0 3,198 2,247 0.70 2.19

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

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

1987 1,132.7 72.7 2,675 712 0.27 0.63

1988 750.4 50.0 3,184 1,542 0.48 2.05

1989 489.3 33.0 3,100 8360.27 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 84.61,402 383 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 4060.22 0.30

19961,562.9 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 0.160.13

SUSQUEHANNA 1, 2 1984 719.9 72.62,827 308 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 - 1090, 1094 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
C-28

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

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

SUSQUEHANNA 1, 2 1993 1,602.1 77.3 1,488 335 0.23 0.21

(continued) 1994 1,814.4 85.4 1,580 442 0.28 0.24

1995 1,850.8 85.3 1,773 4760.27 0.26

19961,998.7 90.7 1,430 289 0.20 0.14

1997 1,918.9 89.61,646 433 0.260.23

1998 1,879.688.3 1,575 361 0.23 0.19

1999 1,896.0 89.6 1,787 431 0.24 0.23

2000 1,994.692.6 1,812 331 0.18 0.17

THREE MILE ISLAND 113, 214 1975 675.9 82.2 131 73 0.56 0.11

Docket 50-289, -320; 1976530.0 65.4 819 286 0.35 0.54

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

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

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

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

Capacity - 786, (880) MWe 1981 0.0 0.0 2,103 376 0.18 ---

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

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

1984 0.0 0.0 1,079 688 0.64 ---

1985 103.610.6 1,890 857 0.45 8.27

THREE MILE ISLAND 113 1986585.2 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 - 786 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 2060.11 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

1996857.4 100.0 267 16 0.06 0.02

1997 675.7 84.3 1,049 204 0.19 0.30

1998 805.8 100.0 280 17 0.060.02

1999 722.4 89.7 1,171 155 0.13 0.21

2000 813.4 100.0 183 9 0.05 0.01

THREE MILE ISLAND 214 19860.0 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), 0 MWe 1990 0.0 0.0 484 1360.28 ---

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 ---

19960.0 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 ---

13 Three Mile Island 1 resumed commercial power generation 10/85 after being under regulatory restraint since 1979. Parentheses

indicate plant capacity when plant was operational.

14 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.
C-29

Thirty-Third Annual Report, 2000 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

TROJAN15 1977 792.0 92.6591 174 0.29 0.22

Docket 50-344; NPF-1 1978 205.5 20.6711 319 0.45 1.55

1st commercial operation 5/761979 631.0 58.1 736 258 0.35 0.41

Type - PWR 1980 727.5 72.5 1,159 421 0.360.58

Capacity - (1080), 0 MWe 1981 775.674.1 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

1986852.4 79.7 1,321 381 0.29 0.45

1987 525.5 54.0 1,209 363 0.30 0.69

1988 758.667.5 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 181.616.1 1,496 567 0.38 3.12

1992 553.9 68.4 567 84 0.15 0.15

1993 0.0 68.4 54 21 0.39 ---

1994 0.0 0.0 51 9 0.18 ---

1995 0.0 0.0 141 44 0.31 ---

19960.0 0.0 112 41 0.37 ---

1997 0.0 0.0 227 41 0.18 ---

1998 0.0 0.0 283 460.16 ---

1999 0.0 0.0 274 52 0.19 ---

2000 0.0 0.0 127 18 0.14 ---

TURKEY POINT 3, 4 1973 401.9 444 78 0.18 0.19

Docket 50-250, 50-251; 1974 953.6794 454 0.57 0.48

DPR-31, -41 1975 1,003.7 74.9 1,1768760.74 0.87

1st commercial operation 1976974.2 71.2 1,647 1,184 0.72 1.22

12/72, 9/73 1977 979.5 72.1 1,319 1,0360.79 1.06

Type - PWRs 1978 1,000.2 78.8 1,3361,032 0.77 1.03

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

1980 990.673.6 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

1986754.1 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 4760.32 0.41

1995 1,320.3 94.61,142 215 0.19 0.16

19961,307.8 94.0 1,157 187 0.16 0.14

1997 1,220.9 88.61,581 414 0.260.34

1998 1,323.0 94.5 1,045 1560.15 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

15 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-30

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

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 1973 222.1 244 85 0.35 0.38

Docket 50-271; DPR-28 1974 303.5 357 2160.61 0.71

1st commercial operation 11/72 1975 429.0 87.8 282 153 0.54 0.36

Type - BWR 1976389.677.1 815 411 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 0.360.87

1979 414.0 82.1 1,220 1,170 0.962.83

1980 357.8 71.5 1,443 1,338 0.93 3.74

1981 429.1 84.61,264 731 0.58 1.70

1982 501.0 96.0 481 205 0.43 0.41

1983 346.1 69.3 1,316 1,527 1.16 4.41

1984 398.1 79.0 954 626 0.66 1.57

1985 361.4 71.8 1,392 1,051 0.76 2.91

1986248.1 48.9 1,389 1,188 0.86 4.79

1987 423.684.2 827 303 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 0.360.71

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 0.260.54

1994 515.8 98.7 220 38 0.17 0.07

1995 462.1 87.0 737 182 0.25 0.39

1996452.7 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 99.6198 38 0.19 0.07

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 - 1148, 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

19962,056.8 86.5 1,395 452 0.32 0.22

1997 2,121.1 91.4 994 158 0.160.07

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 95.6899 121 0.14 0.05

WASHINGTON NUCLEAR 216 1985 616.0 87.6 755 119 0.16 0.19

Docket 50-397; NPF-21 1986616.0 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 0.360.76

1992 682.3 65.6 1,489 612 0.41 0.90

1993 849.679.5 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

1996662.9 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 2860.23 0.36

1999 694.7 70.0 1,022 155 0.15 0.22

2000 979.696.3 706 53 0.08 0.05

16 Energy Northwest has changed the name of Washington Nuclear 2 to Columbia Generating Station.
C-31

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

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

WATERFORD 1986875.7 79.1 1,244 223 0.18 0.25

Docket 50-382; NPF-38 1987 891.8 82.5 959 1560.160.17

1st commercial operation 9/85 1988 784.3 75.4 1,246259 0.21 0.33

Type - PWR 1989 909.8 82.61,306 265 0.20 0.29

Capacity - 1075 MWe 1990 1,027.9 92.8 432 47 0.11 0.05

1991 870.679.8 1,301 364 0.28 0.42

1992 909.683.2 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

19961,064.8 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 79.6833 123 0.15 0.14

2000 965.1 88.8 825 132 0.16 0.14

WATTS BAR 1 1997 867.6 83.8 1,103 113 0.10 0.13

Docket 50-390; NPF-90 1998 1,105.1 99.1 963 0.03 0.00

1st commercial operation 5/961999 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 - 1118 MWe

WOLF CREEK 1 1986832.8 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 18618 0.10 0.02

Capacity - 1170 MWe 1990 940.2 81.0 798 195 0.24 0.21

1991 707.671.9 1,010 331 0.33 0.47

1992 1,010.8 86.7 446 78 0.17 0.08

1993 940.5 80.6975 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 0.060.01

1996980.681.2 986 171 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

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 1160.47 0.80

1976152.2 89.8 152 59 0.39 0.39

1977 124.673.9 725 356 0.49 2.86

1978 145.0 81.0 565 282 0.50 1.94

1979 149.0 81.6441 127 0.29 0.85

1980 35.622.0 502 213 0.42 5.98

1981 109.0 74.4 515 302 0.59 2.77

1982 108.673.4 814 474 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

1986169.7 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 49662 0.12 0.39

17 Yankee Rowe ended commercial operation as of 10/91, and will not be put in commercial operation again. It is no longer in the

count of operating reactors. Parentheses indicate plant capacity when plant was operational.
C-32

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

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 1990 101.1 61.5 702 246 0.35 2.43

(continued) 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 1560.70 ---

1995 0.0 0.0 191 78 0.41 ---

19960.0 0.0 239 95 0.40 ---

1997 0.0 0.0 323 65 0.20 ---

1998 0.0 0.0 125 5 0.04 ---

1999 0.0 0.0 83 2 0.02 ---

2000 0.0 0.0 38 2 0.06---

ZION 118, 218 1974 425.3 71.1 306560.18 0.13

Docket 50-295; 50-304; 1975 1,181.5 74.9 436127 0.29 0.11

DPR-39, -48 19761,134.9 61.9 774 571 0.74 0.50

1st commercial operation 1977 1,358.675.0 784 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

19861,462.0 73.2 967 474 0.49 0.32

1987 1,337.0 71.0 1,046653 0.62 0.49

1988 1,549.1 78.3 1,9261,260 0.65 0.81

1989 1,514.1 77.61,282 624 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 1,1763060.260.25

1995 1,471.672.4 1,807 797 0.44 0.54

19961,538.4 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 24612 0.05 ---

1999 0.0 0.0 67 4 0.06 ---

2000 0.0 0.0 263 0.12 ---

17 Yankee Rowe ended commercial operation as of 10/91, and will not be put in commercial operation again. It is no longer in the

count of operating reactors. Parentheses indicate plant capacity when plant was operational.

18 Zion 1, 2 was shut down 12/97 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity

when plant was operational.
D-1

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

NUREG-0713

DOSE PERFORMANCE INDICATORS BY REACTOR SITE

1973 - 2000

Appendix D

NOTE: Appendix D contains data on operating plants as well as plants which are no longer in commercial operation.
D-2

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

NUREG-0713 DOSE (person-rem) 1975 1976

197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

ARKANSAS 1, 2

Dose-Performance Indicators PWR

BEAVER VALLEY 1, 2

Dose-Performance Indicators

197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DOSE (person-rem)
D-3

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

NUREG-0713

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

20

40

60

80

100 MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BIG ROCK POINT

Dose-Performance Indicators BWR

DOSE (person-rem)

198919901991199219931994199519961997199819992000

0

100

200

300

400

500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

BRAIDWOOD 1, 2

Dose-Performance Indicators
D-4

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

NUREG-0713 DOSE (person-rem) 1975 1976

197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

500

1000

1500

2000

2500

3000

3500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BROWNS FERRY 1, 2, 3

Dose-Performance Indicators BWR

DOSE (person-rem)

BRUNSWICK 1, 2

Dose-Performance Indicators BWR

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

1000

2000

3000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years
D-5

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

NUREG-0713

DOSE (person-rem)

BYRON 1, 2

Dose-Performance Indicators

198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DOSE (person-rem)

1985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

CALLAWAY 1

Dose-Performance Indicators
D-6

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

NUREG-0713 DOSE (person-rem)

CALVERT CLIFFS 1, 2

Dose-Performance Indicators

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DOSE (person-rem)

198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

CATAWBA 1, 2

Dose-Performance Indicators
D-7

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

NUREG-0713

DOSE (person-rem)

1988198919901991199219931994199519961997199819992000

0

500

1000

0

200

400

600

800

1000

1200

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

CLINTON

Dose-Performance Indicators

DOSE (person-rem)

1991199219931994199519961997199819992000

0

100

200

300

400

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

COMANCHE PEAK 1, 2

Dose-Performance Indicators
D-8

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

NUREG-0713 DOSE (person-rem) 1975 1976

197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

COOPER STATION

Dose-Performance Indicators

DOSE (person-rem)

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

COOK 1, 2

Dose-Performance Indicators
D-9

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

NUREG-0713

DOSE (person-rem)

19781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

200

400

600

800

1000

1200

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

CRYSTAL RIVER 3

Dose-Performance Indicators

DOSE (person-rem)

19781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

250

500

750

1000

1250

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DAVIS-BESSE

Dose-Performance Indicators
D-10

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

NUREG-0713 DOSE (person-rem) 1986

19871988198919901991199219931994199519961997199819992000

0

100

200

300

400

500

600

700

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DIABLO CANYON 1, 2

Dose-Performance Indicators

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

DRESDEN 2, 3

Dose-Performance Indicators
D-11

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

NUREG-0713

DOSE (person-rem)

BWR

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

100

200

300

400

500

600

700

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

DUANE ARNOLD

Dose-Performance Indicators

DOSE (person-rem)

197819791980198119821983

1984

1985198619871988

1989

1990199119921993

1994

199519961997199819992000

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

FARLEY 1, 2

Dose-Performance Indicators
D-12

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

NUREG-0713 DOSE (person-rem) 1989

19901991199219931994199519961997199819992000

0

250

500

750

0

500

1000

1500 MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

FERMI 2

Dose-Performance Indicators

DOSE (person-rem)

FITZPATRICK

Dose-Performance Indicators

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

3000

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR
D-13

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

NUREG-0713

DOSE (person-rem)

PWR

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

250

500

750

1000

0

250

500

750 MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

FORT CALHOUN

Dose-Performance Indicators

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

250

500

750

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

GINNA

Dose-Performance Indicators
D-14

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

NUREG-0713 DOSE (person-rem) 1986

19871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Yrs.

BWR

GRAND GULF

Dose-Performance Indicators

DOSE (person-rem)

1988198919901991199219931994199519961997199819992000

0

250

500

750

0

200

400

600

800

1000

1200

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

HARRIS

Dose-Performance Indicators
D-15

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

NUREG-0713

DOSE (person-rem)

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

HATCH 1, 2

Dose-Performance Indicators

DOSE (person-rem)

19871988198919901991199219931994199519961997199819992000

0

250

500

750

1000

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

HOPE CREEK 1

Dose-Performance Indicators
D-16

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

NUREG-0713 DOSE (person-rem) 1979 1980

19811982198319841985198619871988198919901991199219931994199519961997199819992000

0

250

500

750

1000

1250

1500

1750

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

INDIAN POINT 3

Dose-Performance Indicators

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

1000

2000

3000

4000

5000

6000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

INDIAN POINT 2

Dose-Performance Indicators
D-17

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

NUREG-0713

DOSE (person-rem)

19841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

LASALLE 1, 2

Dose-Performance Indicators

DOSE (person-rem)

KEWAUNEE

Dose-Performance Indicators

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

200

400

600

800

1000 MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR
D-18

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

NUREG-0713 DOSE (person-rem)

LIMERICK 1, 2

Dose-Performance Indicators

19871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

DOSE (person-rem)

MAINE YANKEE

Dose-Performance Indicators

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

1400

0

200

400

600

800

1000

1200

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR
D-19

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

NUREG-0713

DOSE (person-rem)

1982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

MCGUIRE 1, 2

Dose-Performance Indicators

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

3000

3500

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

MILLSTONE UNIT 1

Dose-Performance Indicators
D-20

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

NUREG-0713 DOSE (person-rem)

MILLSTONE UNIT 2, 3

Dose-Performance Indicators

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

3000

-500

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

3000

3500

0

200

400

600

800

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

MONTICELLO

Dose-Performance Indicators
D-21

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

NUREG-0713

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

0

200

400

600

800

1000

1200

1400

1600

1800

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

NINE MILE POINT 1, 2

Dose-Performance Indicators

DOSE (person-rem)

1979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

NORTH ANNA 1, 2

Dose-Performance Indicators
D-22

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

NUREG-0713 DOSE (person-rem) 1974 1975

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

3000

3500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

OCONEE 1, 2, 3

Dose-Performance Indicators

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

3000

3500

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

OYSTER CREEK

Dose-Performance Indicators
D-23

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

NUREG-0713

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

250

500

750

1000

1250

1500

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

PALISADES

Dose-Performance Indicators

DOSE (person-rem)

19871988198919901991199219931994199519961997199819992000

0

200

400

600

800

0

500

1000

1500

2000

2500

3000

3500

4000

4500

5000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

PALO VERDE 1, 2, 3

Dose-Performance Indicators
D-24

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

NUREG-0713 DOSE (person-rem)

PEACH BOTTOM 2, 3

Dose-Performance Indicators

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

DOSE (person-rem)

1988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

PERRY

Dose-Performance Indicators
D-25

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

NUREG-0713

DOSE (person-rem)

PILGRIM

Dose-Performance Indicators

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

1000

2000

3000

4000

5000

6000

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

DOSE (person-rem)

POINT BEACH 1, 2

Dose-Performance Indicators

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

1400

1600

0

200

400

600

800

1000

1200

1400

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR
D-26

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

NUREG-0713 DOSE (person-rem) 1974 1975

1976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

PRAIRIE ISLAND 1, 2

Dose-Performance Indicators

DOSE (person-rem)

QUAD CITIES 1, 2

Dose-Performance Indicators

197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

1000

2000

3000

4000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR
D-27

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

NUREG-0713

DOSE (person-rem)

RIVER BEND 1

Dose-Performance Indicators

19871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

500

1000

1500 MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

3000

3500

4000

4500

0

200

400

600

800

1000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

ROBINSON 2

Dose-Performance Indicators
D-28

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

NUREG-0713 DOSE (person-rem) 1978 1979

198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

SALEM 1, 2

Dose-Performance Indicators PWR

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

SAN ONOFRE 1, 2, 3

Dose-Performance Indicators
D-29

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

NUREG-0713

DOSE (person-rem)

SEABROOK

Dose-Performance Indicators

1991199219931994199519961997199819992000

0

100

200

300

400

500

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DOSE (person-rem)

1982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

SEQUOYAH 1, 2

Dose-Performance Indicators
D-30

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

NUREG-0713 DOSE (person-rem)

SOUTH TEXAS 1, 2

Dose-Performance Indicators

198919901991199219931994199519961997199819992000

0

100

200

300

400

500

0

500

1000

1500

2000

2500

3000

3500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DOSE (person-rem)

197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

ST. LUCIE 1, 2

Dose-Performance Indicators
D-31

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

NUREG-0713

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

3000

3500

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

SURRY 1, 2

Dose-Performance Indicators

DOSE (person-rem)

SUMMER 1

Dose-Performance Indicators

19841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR
D-32

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

NUREG-0713 DOSE (person-rem)

SUSQUEHANNA 1, 2

Dose-Performance Indicators

19841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

DOSE (person-rem)

19751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

0

200

400

600

800

1000

1200

1400

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

THREE MILE ISLAND 1

Dose-Performance Indicators
D-33

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

NUREG-0713

DOSE (person-rem)

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

2500

0

200

400

600

800

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

VERMONT YANKEE

Dose-Performance Indicators

DOSE (person-rem)

TURKEY POINT 3, 4

Dose-Performance Indicators

1973197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

500

1000

1500

2000

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR
D-34

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

NUREG-0713 DOSE (person-rem)

VOGTLE 1, 2

Dose-Performance Indicators

1988198919901991199219931994199519961997199819992000

0

200

400

600

800

0

500

1000

1500

2000

2500

3000

3500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DOSE (person-rem)

1985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

1400

0

500

1000

1500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

BWR Average Collective Dose Per Reactor

MW-Years

BWR

WASHINGTON NUCLEAR 2

Dose-Performance Indicators
D-35

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

NUREG-0713

DOSE (person-rem)

WATERFORD 3

Dose-Performance Indicators

198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

0

200

400

600

800

1000

1200

1400

1600

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DOSE (person-rem)

19961997199819992000

0

100

200

300

400

500

0

500

1000

1500

2000

2500

3000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

WATTS BAR 1

Dose-Performance Indicators
D-36

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

NUREG-0713 DOSE (person-rem)

WOLF CREEK 1

Dose-Performance Indicators

198619871988198919901991199219931994199519961997199819992000

0

200

400

600

0

500

1000

1500

2000

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR

DOSE (person-rem)

ZION 1, 2

Dose-Performance Indicators

197419751976197719781979198019811982198319841985198619871988198919901991199219931994199519961997199819992000

0

200

400

600

800

1000

1200

1400

1600

0

500

1000

1500

2000

2500

MW-Yrs.

Year

3-Year Average Collective Dose Per Reactor

Collective Dose Per Reactor

PWR Average Collective Dose Per Reactor

MW-Years

PWR