UN TI ED STATES NUCLEAR REGULATORY COMM SI S OI N

Occupational Radiation

Exposure at Commercial

Nuclear Power Reactors

and Other Facilities

1999

NUREG-0713

Vol. 21

Thirty-Second Annual Report

U.S. Nuclear Regulatory Commission

Office 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

1999

NUREG-0713

Vol. 21

Thirty-Second Annual Report

Division of Regulatory Applications

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

Manuscript Completed: September 22, 2000

Date Published: October 2000

Prepared by:

H. Karagiannis, D. A. Hagemeyer*

Science Applications International Corporation

301 Laboratory Road

Oak Ridge, TN 37830

*
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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.

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-Second Annual Report, 1999 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 1999

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 1999 were received from a total of 286 NRC licensees, of which 104 were

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

submitted by the 286 licensees indicated that 129,951 individuals were monitored, 67,839 of

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

individuals was 16,661 person-rem, which represents a 2% increase from the 1998 value. The

number of workers receiving a measurable dose increased, resulting in the average measurable

dose of 0.25 rem for 1999. The average measurable dose is defined to be 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 1999, the annual collective dose per reactor for light water reactor (LWR) licensees was 131

person-rem. This represents a 4% increase from the value reported for 1998. The annual

collective dose per reactor for boiling water reactors (BWRs) was 184 person-rem and, for

pressurized water reactors (PWRs), it was 105 person-rem.

Analyses of transient worker data indicate that 23,077 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 1999,

the average measurable dose calculated from reported data was 0.20 rem. The corrected dose

distribution resulted in an average measurable dose of 0.25 rem.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

EDITOR’S NOTE

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:

Harriet Karagiannis: (301) 415-6377

E-Mail Address: hxk@nrc.gov

REIRS Project Manager

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, D.C. 20555
v

Thirty-Second Annual Report, 1999 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 ...................................................................................3-18

3.3.6 Light-Water-Cooled Power Reactor Licenses ............................................3-21

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

TABLE OF CONTENTS

Page
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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4 COMMERCIAL LIGHT WATER REACTORS - FURTHER ANALYSIS...............................4-1

4.1 Introduction .................................................................................................................4-1

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

4.2.1 Number of Reactors ...........................................................................................4-1

4.2.2 Electric Energy Generated .................................................................................4-1

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

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

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

4.3 Annual TEDE Distributions ..........................................................................................4-6

4.4 Average Annual TEDE Doses .....................................................................................4-8

4.5 Three-Year Average Collective TEDE Per Reactor ....................................................4-12

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

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

5.1 Termination Reports ....................................................................................................5-1

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

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

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

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

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

6.4 Maximum Exposures Below the NRC Limits...............................................................6-7

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

APPENDIX A - ANNUAL TEDE FOR NON-REACTOR NRC LICENSEES, 1999................... A-1

APPENDIX B - ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES, 1999..................................................................................................... B-1

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

1969-1999 ............................................................................................................................... C-1

APPENDIX D - DOSE PERFORMANCE INDICATORS BY REACTOR SITE,

1973-1999 ............................................................................................................................... D-1

TABLE OF CONTENTS (Continued)

Page
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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Figure 3.1 Average Annual Values at Industrial Radiography Facilities 1973-1999 .............3-9

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

Single Location Licensees 1995-1999...............................................................3-10

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

Multiple Location Licensees 1995-1999 ............................................................3-10

Figure 3.4 Average Annual Values at Manufacturing and Distribution

Facilities 1973-1999 ..........................................................................................3-12

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

Manufacturing and Distribution Licensees 1995-1999 ......................................3-13

Figure 3.6 Collective TEDE Distribution by Dose Range, Limited

Manufacturing and Distribution Licensees 1995-1999 ......................................3-13

Figure 3.7 Average Annual Values at Low-Level Waste Disposal

Facilities 1982-1999 ..........................................................................................3-14

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

Disposal Licensees 1995-1999 ........................................................................3-15

Figure 3.9 Average Annual Values at Independent Spent Fuel Storage

Facilities 1982-1999 ..........................................................................................3-16

Figure 3.10 Collective TEDE Distribution by Dose Range, Independent Spent

Fuel Storage Licensees 1995-1999..................................................................3-17

Figure 3.11 Average Annual Values at Fuel Cycle Licensees 1973-1999 ............................3-19

Figure 3.12 Collective TEDE Distribution by Dose Range, Fuel Cycle

Licensees 1995-1999 .......................................................................................3-20

Figure 3.13 Collective TEDE Distribution by Dose Range, Reactor

Licensees 1995-1999 .......................................................................................3-20

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

per Reactor 1973-1999........................................................................................4-9

Figure 4.2 Number of Operating Reactors and Gross Electricity

Generated 1973-1999 .......................................................................................4-10

LIST OF FIGURES

Page
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

Figure 4.3 Average Measurable Dose per Worker and Collective Dose per

Megawatt-Year 1973-1999 ................................................................................ 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 1987-1999 ............................................................................4-14

LIST OF FIGURES (Continued)

Page

Table 3.1 Average Annual Exposure Data for Certain Categories of

NRC Licensees 1990-1999 .................................................................................3-3

Table 3.2 Distribution of Annual Collective TEDE by License

Category 1999 .....................................................................................................3-5

Table 3.3 Summary of Annual Dose Distributions for Certain NRC

Licensees 1968-1999 ..........................................................................................3-6

Table 3.4 Annual Exposure Information for Industrial

Radiographers 1997-1999 ...................................................................................3-7

Table 3.5 Annual Exposure Information for Manufacturers and

Distributors 1997-1999 ........................................................................................3-8

Table 3.6 Annual Exposure Information for Fuel Cycle Licenses 1997-1999....................3-18

Table 3.7 Intake by Licensee Type and Radionuclide

Mode of Intake - Ingestion and Other 1999 ......................................................3-23

Table 3.8 Intake by Licensee Type and Radionuclide

Mode of Intake - Inhalation 1999 ......................................................................3-24

Table 3.9 Collective and Average CEDE by Licensee 1999.............................................3-26

Table 3.10 Internal Dose (CEDE) Distribution, 1994 - 1999................................................3-27

LIST OF TABLES
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Thirty-Second Annual Report, 1999 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 1973-1999......................................................................4-2

Table 4.2 Summary of Information Reported by Commercial

Pressurized Water Reactors 1973-1999 .............................................................4-3

Table 4.3 Summary of Information Reported by Commercial

Light Water Reactors 1973-1999 .........................................................................4-4

Table 4.4 Summary Distribution of Annual Whole Body Doses at

Commercial Light Water Reactors 1977-1999 ....................................................4-7

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

of Collective TEDE per BWR 1997-1999...........................................................4-15

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

of Collective TEDE per PWR 1997-1999...........................................................4-16

Table 5.1 Effects of Transient Workers on Annual Statistical Compilations, 1999 ..............5-2

Table 6.1 Occupational Exposures in Excess of Regulatory Limits, 1994-1999 .................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 1999 ..............6-7

Page
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Thirty-Second Annual Report, 1999 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: US/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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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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FOREWORD

NUREG-0713, Volume 21, summarizes the 1999 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 286 licensees required to submit annual

reports. The collective dose incurred by these individuals was 16,661 person-rem, which

represents a 2% increase from the 1998 value.

Thomas L. King, Director

Division of Risk Analysis and Applications

Office of Nuclear Regulatory Research
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1-1

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

INTRODUCTION

Section 1

1.1 BACKGROUND

One of the basic purposes of the Atomic

Energy Act and the implementing regulations

in Title 10, Code of Federal Regulations

(CFR), Chapter I, Part 20, is to protect the

health and safety of the public, including the

employees of the licensees conducting

operations under those regulations. Among

the regulations designed to ensure that the

standards for protection against radiation set

out in 10 CFR 20 are met is a requirement

that licensees provide individuals likely to be

exposed to radiation with devices to monitor

their exposure. Each licensee is also

required to maintain indefinitely records of

the results of such monitoring. However,

there was no initial provision that these

records or any summary of them be

transmitted to a central location where the

data could be retrieved and analyzed.

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

Energy Commission (AEC) published an

amendment to 10 CFR 20 requiring the

reporting of certain occupational radiation

exposure information to a central repository at

AEC Headquarters. This information was

required of the four categories3 of AEC

licensees that were considered to involve the

greatest potential for significant occupational

doses and of AEC facilities and contractors

exempt from licensing. A procedure was

established whereby the appropriate

occupational exposure data were extracted

from these reports and entered into the

Commission’s Radiation Exposure Information

and Reporting System (REIRS), a computer

system that was maintained at the Oak Ridge

National Laboratory Computer Technology

Center in Oak Ridge, Tennessee, until May

1990. At that time, the data were transferred

to a database management system at Science

Applications International Corporation (SAIC)

at Oak Ridge, Tennessee. The computerization

of these data ensures that they are kept

indefinitely and facilitates their retrieval and

analysis. The data maintained in REIRS have

been summarized and published in a report

every year since 1969. Annual reports for

each of the years 1969 through 1973

presented the data reported by both AEC

licensees and contractors and were published

in six documents designated as

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

In January 1975, with the separation of the

AEC into the Energy Research and

Development Administration (ERDA) and the

U.S. Nuclear Regulatory Commission (NRC),

each agency assumed responsibility for

collecting and maintaining occupational

radiation exposure information reported by the

facilities under its jurisdiction. The annual

reports published by the NRC on occupational

exposure for calendar year 1974 and

subsequent years do not contain information

pertaining to ERDA facilities or contractors.

Comparable information for facilities and

contractors under ERDA, now the Department

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-Second Annual Report, 1999

NUREG-0713

of Energy (DOE), is collected and published

by DOE’s Office of Worker Health and Safety,

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 sixth 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 World Wide 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.
2-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Another fact that should be kept in mind

when examining the annual statistical data is

that all of the personnel included in the report

may not have been monitored throughout the

entire year. Many licensees, such as

radiography firms and nuclear power

facilities, may monitor numerous individuals

for periods much less than a year. The

average doses calculated from these data,

therefore, are less than the average dose

that an individual would receive if involved in

that activity for the full year.

Considerable attention should also be given

when referencing the collective totals

presented in this report. The differences

between the totals presented for all

licensees that reported versus only those

licensees that are required to report should

be noted. Likewise, one should distinguish

between the doses attributed to the

pressurized water reactors (PWRs), and

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 1999 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 Statement

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 States5 are licensed by the state

and are not required to submit occupational

exposure reports to the NRC. Approximately

twice as many facilities are licensed to

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 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

SI unit of sieverts (Sv), one should 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 8/99, 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

ANNUAL PERSONNEL MONITORING

REPORTS - 10 CFR 20.2206

personal identification numbers submitted per

licensee. Uniqueness is defined by the

combination of identification number and

identification type. [Ref. 10]

3.1.3 Number of Workers with Measurable

Dose

The number of workers with measurable dose

includes any individual with a TEDE greater

than zero rem. This does not include workers

with a TEDE reported as zero, not detectable

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

[Ref. 10]

3.1.4 Collective Dose

The concept of collective dose is used in this

report to denote the summation of the TEDE

received by all monitored workers and has the

units 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

Section 3
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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arithmetic mean of the individual doses in the

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, and therefore 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 1999

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 1999

collective dose with the collective dose for

prior years. 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 them 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 to be 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 SR values lower than 1.5 rem where
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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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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)

TABLE 3.1

Average Annual Exposure Data for Certain Categories of NRC Licensees

1990 - 1999

* 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.

Industrial 1990 258 6,5234,458 2,120 0.33 0.48

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

1992 246 6,7034,265 1,864 0.28 0.44

3310 1993176 4,721 3,007 1,596 0.34 0.53

3320 1994 139 2,886 2,007 1,415 0.49 0.71

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

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

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

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

1999 132 3,837 3,827 1,551 0.40 0.41

Manufacturing 1990 58 4,2032,279 693 0.16 0.30

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

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

199358 4,9132,254 680 0.14 0.30

2500 1994 44 2,941 1,251 580 0.20 0.46

3211 1995 36 2,666 1,222 595 0.22 0.49

3212 1996 38 2,631 1,241 556 0.21 0.45

3214 1997 33 1,154 665 397 0.34 0.60

1998 31 1,986 654 402 0.20 0.61

1999 39 2,181 836 419 0.19 0.50

Low-Level 1990 2 784 115 26 0.030.23

Waste 1991 2 905 147 39 0.04 0.27

Disposal*** 1992 2 467 82 37 0.08 0.45

19932 432 76 21 0.05 0.27

3231 1994 2 202 8322 0.11 0.27

1995 2 212 56 8 0.04 0.15

1996 2 165 67 8 0.05 0.12

1997 2 185 50 5 0.030.11

1998 1 27 131 0.05 0.10

1999

Independent 1990 2 56 22 6 0.11 0.27

Spent Fuel 1991 2 41 24 4 0.10 0.17

Storage 1992 2 290 85 11 0.04 0.13

19932 135 52 14 0.10 0.26

23100 1994 1 158 89 42 0.27 0.47

23200 1995 1 104 49 51 0.49 1.04

1996 1 97 5354 0.56 1.02

1997 1 55 24 6 0.11 0.24

1998 1 5321 30.05 0.12

1999 2 86 33 5 0.06 0.16

Fuel 1990 11 14,505 3,871 422 0.03 0.11

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

Licenses - 1992 11 8,439 5,061 545 0.06 0.11

 Fabrication 1993 8 9,649 2,611 339 0.04 0.13

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

 Uranium Enrich. 1995 8 4,106 2,959 1,217 0.30 0.41

1996 8 4,369 3,061 878 0.20 0.29

21210 1997 10 11,214 3,910 1,006 0.09 0.26

21200 1998 10 10,684 3,613 950 0.09 0.26

1999 9 9,6933,927 1,020 0.11 0.26

Commercial 1990 110 182,442 98,567 36,602 0.20 0.37

Light Water 1991 111 178,333 91,086 28,519 0.16 0.31

Reactors** 1992 110 181,889 94,172 29,297 0.16 0.31

1993108 169,259 86,19326,364 0.16 0.31

41111 1994 109 139,390 71,613 21,704 0.16 0.30

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

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

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

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

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

Grand Totals 1990 441 208,513109,312 39,869 0.19 0.36

and Averages 1991 433 202,731 101,787 31,822 0.16 0.31

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

1993354 189,109 94,19329,0130.15 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 67,839 16,661 0.13 0.25
3-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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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.

The collective TEDE distribution by dose range

in 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. There are two

properties of these graphs that help to qualify

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 is 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 92% of the reported workers

with measurable doses were monitored by

nuclear power facilties in 1999, where they

received approximately 84% 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 ~ 95% of the exposures consistently

remained <2 rem between 1968 and 1984.

For the past 14 years the percentage of

workers with <2 rem has been ≥ 98%. The

number of workers receiving an annual

exposure in excess of 5 rem has been <0.01%

since 1985. One individual received a dose

above 5 rem in 1999 (see Section 6).
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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)

216 35 3 8 4 266 50 7.033

794 835 464 474 309 181 372 100 32 9 1 3,571 2,777 1,543.992

1,010 870 467 482 313 181 372 100 32 9 1 3,837 2,827 1,551.025

909 113 37 40 23 16 51 31 37 4 1,261 352 347.461

436 333 84 30 15 10 9 2 1 920 484 71.532

1,345 446 121 70 38 26 60 33 38 4 2,181 836 418.993

53 17 6 9 1 86 33 5.172

5,766 2,144 639 486 265 139 205 47 2 9,693 3,927 1,019.880

26,252 16,000 6,937 4,880 2,021 922 705 17 57,734 31,482 6,434.430

48,615 23,663 11,126 6,084 1,973 647 436 7 2 92,553 43,938 7,231.281

74,867 39,663 18,063 10,964 3,994 1,569 1,141 24 2 150,287 75,420 13,665.711

83,041 43,140 19,296 12,011 4,611 1,915 1,778 204 74 13 1 166,084 83,043 16,660.781

 INDUSTRIAL RADIOGRAPHY

 Single Location (21)

 Multiple Location (111)

 Total (132)

 MANUFACTURING AND

 DISTRIBUTION

 "A" - Broad (5)

 Limited (34)

 Total (39)

 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 1999.

These values have not been adjusted for the multiple counting of transient reactor workers (see Section 5)

TABLE 3.2

Distribution of Annual Collective TEDE by License Category

1999
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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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

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 1977-1999 are based on the distribution of individual doses after adjusting for the multiple

counting of transient reactor workers (see Section 5). The number of people exceeding 5

rem is shown in parentheses from 1985-1999.

TABLE 3.3

Summary of Annual Dose Distributions for Certain* NRC Licensees

1968 - 1999
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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 that

was 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 132 radiography

licensees in 1999. Table 3.4 summarizes the

reported data for the two types of radiography

licenses for 1999 and for the previous 2 years

for comparison purposes.

The average measurable dose for workers

performing radiography at a single location

ranged from 15 to 20% 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 see the contribution that each

radiography licensee made to the total

collective dose, a summary of the information

reported by each of these licensees in 1999 is

presented in Appendix A.

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

1997 - 1999

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

1997

1998

1999

27

121

148

26

116

142

21

111

132

296

3,274

3,570

369

4,583

4,952

266

3,571

3,837

84

2,490

2,574

84

3,362

3,446

50

2,777

2,827

10

1,346

1,356

8

1,855

1,863

7

1,544

1,551

0.12

0.54

0.53

0.09

0.55

0.54

0.14

0.56

0.55
3-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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 1999. The collective TEDE, the

number of workers with measurable TEDE, and

average measurable TEDE decreased from

1998 to 1999. 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 30% 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 possess or use at any one time specified

quantities of the nuclides listed in paragraph

20.2206(a)(7) are required to submit reports to

the NRC.

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

1997

1998

1999

5

28

33

5

26

31

5

34

39

496

658

1,154

1,177

809

1,986

1,261

920

2,181

386

279

665

380

274

654

352

484

836

364

33

397

367

35

402

347

72

419

0.94

0.12

0.60

0.97

0.13

0.61

0.99

0.15

0.50

TABLE 3.5

Annual Exposure Information for Manufacturers and Distributors

1997 - 1999
3-9

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 3.1. Average Annual Values at Industrial Radiography Facilities 1973- 1999

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

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-Second Annual Report, 1999

NUREG-0713

1999 1998 1997 1996 1995

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%

63%

88%

0%

0%

61%

87%

0%

0%

22%

61%

84%

78%

64%

25%

17%

0%

> 1.000

> 0.500

> 0.250

> 0.100

44%

96%

0%

0%

1999 1998 1997 1996 1995

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%

60%

93%

26%

> 1.000

> 0.500

> 0.250

> 0.100

98%

83%

62%

93%

30%

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

1995 - 1999

FIGURE 3.3. Collective TEDE Distribution by Dose Range

Industrial Radiographer – Multiple Location Licensees

1995 - 1999
3-11

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Table 3.5 presents the annual data that were

reported by the two types of licensees for

1999 and the previous 2 years. Looking at the

information shown separately for the Type "A"

Broad and Limited licensees, it can be seen

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, so that 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

98% of the collective dose for this category of

licensee in 1999. 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 1999, over 60% 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.

For the contribution that each of these

licensees made toward the total values of the

number of workers monitored, number of

workers, and collective dose, see Appendix A,

which lists the values of these parameters for

each licensee for 1999.

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 its

activity. However, these licensees also have an

NRC license that covers certain special nuclear

material they might receive. The annual dose

reports submitted by these licensees include all

doses received during the year regardless of

whether they were the result of NRC or

Agreement State licensed material.

The requirement for this category of NRC

licensee to file annual reports became effective

in January 1983. There was only one licensee

in this category in 1982 and 1983 and two

licensees in this category from 1984 to 1997.

In 1998 and 1999, only one licensee reported

in this category since Chem Nuclear is an

Agreement State licensee. Table 3.1

summarizes the data reported for 1990 through

1999. Appendix A summarizes the exposure

information reported by this licensee in 1999.
3-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

FIGURE 3.4. Average Annual Values at Manufacturing and Distribution Facilities

1973- 1999

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

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-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1999 1998 1997 1996 1995

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%

89%

76%

94%

47%

98%

88%

71%

93%

42%

97%

91%

61%

97%

66%

98%

93%

82%

97%

99%

84%

1999 1998 1997 1996 1995

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%

82%

 62%

52%

85%

18%

39%

49%

0%

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

1995 - 1999

FIGURE 3.6. Collective TEDE Distribution by Dose Range

Limited Manufacturing and Distribution Licensees

1995 - 1999
3-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

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

1982 - 1999

1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999

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-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

1999. The values for the number of workers

with measurable dose, average collective

TEDE per licensee, and average measurable

TEDE per worker have continued a general

decreasing trend since 1992. The average

measurable TEDE per worker decreased by

40% from 1998 to 1999. Figure 3.8 shows the

collective dose distribution by dose range (see

Section 3.1.8) for Low-Level Waste Disposal

licensees. This graph shows that relatively

small percentages of the collective dose are

delivered in the higher dose ranges, and that

the percentages of individuals receiving above

0.100 rem have been decreasing since 1995.

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.

Fourteen licenses are currently issued for

these activities. Twelve are 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

1999 1998 1997 1996 1995

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%

87%

 67%

86%

39%

41%

0%

21%

0%

0%

0%

0%

10%

80% 86%

0%

0%

0% 0%

0%

45%

0%

0%

0%

0%

FIGURE 3.8. Collective TEDE Distribution by Dose Range

Low-Level Waste Disposal Licensees

1995 - 1999

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-Second Annual Report, 1999

NUREG-0713

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

1982 - 1999

1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999

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-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 is 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 Independent

Spent Fuel Storage facilities. The large

increase in the collective dose per licensee

and number of workers per licensee in 1994

was mainly because only one licensee

reported separately for 1994 through 1998,

rather than the two licensees that reported in

prior years. All parameters have decreased

significantly from 1996 to 1998. Figure 3.10

shows the collective dose distribution by dose

range (see Section 3.1.8) for ISFSI licensees

from 1995 to 1999. The percentages for each

dose range have decreased significantly since

1995. The percentages in the lower dose

ranges have increased from 1998 to 1999

indicating that more individuals received

doses in these ranges in 1999.

1999 1998 1997 1996 1995

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

92%

70%

 81%

88%

98%

61%

48%

0%

0%

0%

96%

85%

0% 0%

23%

74%

61%

99%

99%

97%

94%

0%

0%

11%

72%

90%

FIGURE 3.10. Collective TEDE Distribution by Dose Range

Independent Spent Fuel Storage Licensees

1995 - 1999
3-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

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 1999, this

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

1995 to 1999. The distribution of collective

dose has been fairly constant with a decreasing

trend in the percentage in almost every dose

range over the past 5 years. Appendix A lists

each of the licensees reporting in 1999, 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 10

licensed Fuel Cycle (Fabrication and

Enrichment) facilities in 1999.

Year

Type of

License

Number

of

Licensees

Number of

Monitored

Individuals

Workers

With

Meas.

TEDE

Fuel Cycle

Fuel Cycle

Fuel Cycle

1997

1998

1999

10

10

9

11,214

10,684

9,693

3,910

3,613

3,927

Collective

TEDE

(personrem)

998

946

1,020

Average

Meas.

TEDE

(rem)

Collective

DDE

(personrem)

Average

Meas.

DDE

(rem)

Collective

CEDE

(personrem)

Average

Meas.

CEDE

(rem)

0.26

0.26

0.26

198

204

247

0.08

0.08

0.08

800

742

773

0.30

0.29

0.31

Workers

With

Meas.

DDE

Workers

With

Meas.

CEDE

2,545

2,412

3,207

2,684

2,520

2,462

TABLE 3.6

Annual Exposure Information for Fuel Cycle Licenses

1997 - 1999
3-19

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 3.11. Average Annual Values at Fuel Cycle Licensees 1973 - 1999

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

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-Second Annual Report, 1999

NUREG-0713

1999 1998 1997 1996 1995

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%

89%

84%

47%

71%

8%

69%

9%

94%

44%

84%

39%

87%

95%

67%

96%

74%

10%

8%

39%

37%

68%

84%

94%

FIGURE 3.12. Collective TEDE Distribution by Dose Range

Fuel Cycle Licensees

1995 - 1999

FIGURE 3.13. Collective TEDE Distribution by Dose Range

Reactor Licensees

1995 - 1999

1999 1998 1997 1996 1995

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%

9%

95%

63%

33%

 83%

6%

94%

59%

29%

 81%

5%

93%

56%

25%

 78%

4%

92%

52%

22%

 76%
3-21

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

3.3.6 Light-Water-Cooled Power

Reactor Licenses

LWR licenses are issued to utilities to allow

them to use special nuclear material in a

reactor that produces heat to generate

electricity to be sold to consumers. There are

two major types of commercial LWRs in the

United States - PWRs and BWRs - each of

which uses water as the primary coolant.

Table 3.1 shows the number of licensees, total

number of monitored workers, the number of

workers with measurable dose, the total

collective dose, and average dose per worker

for reactor facilities that were in commercial

operation for a full year for each of the years

1990 through 1999. 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 is presented in

alphabetical order by site name in Appendix B.

Figure 3.13 shows the collective dose

distribution by dose range (see Section 3.1.8)

for Reactor licensees from 1995 to 1999. 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.
3-22

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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 1999. 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 for each

licensee category. Fuel fabrication facilities

have the majority of internal dose (99%) 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 1999 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 1999, the highest CEDE was 2.693 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

23.417 rem to this same individual.
3-23

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.7

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

1999

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries

Collective

Intake in

Microcuries

(sci. notation)

Fuel Cycle Licensees

Power Reactors

21200

21210

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

PU-238

PU-239

AM-241

CE-144

CM-243/24

CM-244

CO-57

CO-58

CO-60

CR-51

CS-134

CS-137

FE-55

FE-59

MN-54

NB-95

NI-59

NI-63

PU-238

PU-239/24

PU-241

SR-90

ZN-65

ZR-95

1

1

3

2

1

2

2

17

44

3

1

10

2

2

7

2

1

1

1

1

1

2

1

3

0.000

0.002

0.000

0.010

0.000

0.000

0.004

4.679

3.973

2.006

0.168

0.162

0.630

0.067

0.398

0.097

0.001

0.114

0.000

0.000

0.000

0.005

0.025

0.249

8.20E-05

1.70E-03

2.68E-04

1.01E-02

9.00E-07

6.14E-05

4.38E-03

4.68E+00

3.97E+00

2.01E+00

1.68E-01

1.62E-01

6.30E-01

6.66E-02

3.98E-01

9.70E-02

1.12E-03

1.14E-01

1.90E-06

7.00E-07

3.92E-05

4.69E-03

2.48E-02

2.49E-01

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

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

reports under 10 CFR 20.2206.

*
3-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries

Collective

Intake in

Microcuries

(sci. notation)

Nuclear Pharmacies

Manufacturing and Distribution

Uranium Enrichment

Fuel Fabrication

02500

02500

03211

21200

21200

21200

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

21210

55

14

1

2

11

42

260

46

1

34

121

2

221

238

120

2

132

1

1

126

10

71

190

77

185

316

735

503

2588

245

1417

244

605

318

68

2143

1

4.904

13,340.000

0.474

0.000

0.000

0.027

0.001

0.234

0.000

0.000

0.000

0.000

0.002

0.019

0.000

0.000

0.002

0.000

0.000

0.001

0.002

0.002

0.002

0.002

0.000

0.008

0.634

0.100

6.207

0.005

0.163

0.000

0.004

0.036

0.057

0.757

0.000

4.90E+00

1.33E+04

4.74E-01

4.65E-04

3.74E-04

2.70E-02

1.26E-03

2.34E-01

1.13E-07

1.82E-04

1.92E-05

4.80E-04

2.32E-03

1.94E-02

7.11E-05

2.18E-06

1.95E-03

9.00E-10

5.66E-07

8.42E-04

1.77E-03

2.48E-03

1.96E-03

1.55E-03

4.08E-04

7.53E-03

6.34E-01

1.00E-01

6.21E+00

5.24E-03

1.63E-01

1.69E-04

4.07E-03

3.60E-02

5.66E-02

7.57E-01

6.08E-06

Pulmonary

Clearance

Class

I-131

Tc-99m

I-131

Np-237

Th-230

U-234

Am-241

Co-60

Cs-137

Np-237

Pu-238

Pu-238

Pu-239

Pu-239

Pu-240

Pu-240

Ra-224

Ru-239

Sr-90

Sr-90

Tc-99

Th-228

Th-228

Th-230

Th-230

Th-232

U-234

U-234

U-234

U-235

U-235

U-236

U-236

U-238

U-238

U-238

U-243

D

D

D

W

W

D

W

Y

D

W

W

Y

W

Y

W

Y

W

W

D

Y

W

W

Y

W

Y

Y

D

W

Y

D

Y

D

Y

D

W

Y

Y

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

1999
3-25

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Collective

Intake in

Microcuries

Collective

Intake in

Microcuries

Licensee Type (sci. notation)

Program

Code Radionuclide

Number of

Intake

Records*

Power Reactors 41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

38

6

23

25

5

4

168

2

233

3

2

72

3

1

6

2

12

14

216

1

1

1

58

2

24

14

5

29

4

5

14

5

22

1

1

11

2

2

16

2

0.000

0.057

0.000

0.000

0.000

0.000

1,106.827

0.030

336.963

0.838

0.008

1.707

0.060

0.027

0.756

0.172

0.012

227.200

19.274

0.019

0.022

0.008

4.103

0.085

129.734

0.000

0.000

0.000

0.000

0.000

0.000

0.001

0.016

0.040

0.005

1.712

0.063

0.209

129.522

0.146

Pulmonary

Clearance

Class

Am-241

Ce-137

Cm-242

Cm-243

Cm-243/24

Cm-243/4

Co-58

Co-60

Co-60

Cr-51

Cs-134

Cs-137

Cs-137

Fe-59

Fe-59

Fe-59

H-3

H-3

I-131

I-132

I-133

Mn-54

Mn-54

Mn-54

Nb-95

Np-237

Pu-238

Pu-238

Pu-239

Pu-239/24

Pu-240

Pu-241

Pu-241

Sb-125

Sn-117m

Zn-65

Zr-95

Zr-95

Zr-95

Zrnb-95

W

Y

W

W

W

W

Y

W

Y

Y

D

D

Y

D

W

Y

O

Y

D

D

D

D

W

Y

Y

W

W

Y

Y

W

Y

W

Y

Y

W

Y

D

W

Y

W

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

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

10 CFR 20.2206.

*

3.98E-04

5.70E-02

1.68E-04

2.25E-04

1.37E-05

3.00E-05

1.11E+03

2.95E-02

3.37E+02

8.38E-01

8.00E-03

1.71E+00

6.00E-02

2.70E-02

7.56E-01

1.72E-01

1.20E-02

2.27E+02

1.93E+01

1.90E-02

2.20E-02

8.00E-03

4.10E+00

8.45E-02

1.30E+02

2.30E-07

2.85E-05

3.05E-04

3.60E-05

9.95E-06

4.88E-05

5.88E-04

1.59E-02

3.99E-02

5.37E-03

1.71E+00

6.30E-02

2.09E-01

1.30E+02

1.46E-01

TABLE 3.8 (continued)

Intake by Licensee Type and Radionuclide Mode of Intake – Inhalation

1999
3-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

TABLE 3.9

Collective and Average CEDE by Licensee

1999

Nuclear Pharmacies NORTHERN VIRGINIA ISOTOPES, INC. 45-25221-01MD 26 0.113 0.004

2500 SYNCOR DE PUERTO RICO, INC. 52-16345-02MD 3 0.031 0.010

SYNCOR INTERNATIONAL CORPORATION 04-26507-01MD 24 0.390 0.016

Total 53 0.534 0.010

Manufactuing and Distribution MALLINCKRODT INCORPORATED 24-04206-01 1 0.016 0.016

3211 Total 1 0.016 0.016

Uranium Enrichment Paducah GDP-1 13 0.274 0.021

21200 Portsmouth GDP-2 9 0.171 0.019

Total 22 0.445 0.020

Fuel Fabrication B&W FUEL CO. SNM-1168 62 14.133 0.228

21210 BABCOCK & WILCOX CO. SNM-0042 270 141.869 0.525

COMBUSTION ENGINEERING, INC. SNM-0033 161 125.472 0.779

GENERAL ELECTRIC CO. SNM-1097 762 137.271 0.180

NUCLEAR FUEL SERVICES, INC. SNM-0124 490 37.562 0.077

SIEMENS POWER CORP. SNM-1227 362 93.105 0.257

WESTINGHOUSE ELECTRIC CORP. SNM-1107 334 223.049 0.668

Total 2,441 772.461 0.316

Power Reactors ARKANSAS DPR-51 3 0.075 0.025

41111 BROWNS FERRY DPR-33 940 5.978 0.006

BRUNSWICK DPR-62 19 0.197 0.010

CALLAWAY NPF-30 15 0.376 0.025

CALVERT CLIFFS DPR-53 6 0.185 0.031

CATAWBA NPF-35 2 0.023 0.012

COOK DPR-58 1 0.001 0.001

DRESDEN DPR-19 3 0.272 0.091

FARLEY NPF-02 1 0.012 0.012

GINNA DPR-18 3 0.050 0.017

GRAND GULF NPF-29 3 0.036 0.012

HADDAM NECK DPR-61 5 0.063 0.013

HARRIS NPF-63 12 0.147 0.012

HATCH DPR-57 1 0.011 0.011

INDIAN POINT DPR-05 1 0.037 0.037

INDIAN POINT 3 DPR-64 13 0.254 0.020

LIMERICK NPF-39 6 0.112 0.019

MAINE YANKEE DPR-36 37 0.265 0.007

MILLSTONE UNIT 1 DPR-21 6 0.084 0.014

MONTICELLO DPR-22 1 0.010 0.010

NINE MILE POINT DPR-63 26 0.386 0.015

NORTH ANNA NPF-04 2 0.017 0.009

OCONEE DPR-38 11 0.196 0.018

OYSTER CREEK DPR-16 11 0.053 0.005

PALISADES DPR-20 10 0.171 0.017

PEACH BOTTOM DPR-44 4 0.084 0.021

PILGRIM DPR-35 33 0.621 0.019

POINT BEACH DPR-24 2 0.026 0.013

RIVER BEND NPF-47 32 0.402 0.013

ROBINSON DPR-23 1 0.001 0.001

SAN ONOFRE DPR-13 24 0.240 0.010

SEQUOYAH DPR-77 494 2.614 0.005

ST. LUCIE DPR-67 208 0.765 0.004

SUMMER NPF-12 2 0.032 0.016

SURRY DPR-32 1 0.131 0.131

SUSQUEHANNA NPF-14 63 0.228 0.004

THREE MILE ISLAND 1 DPR-50 441 2.122 0.005

TURKEY POINT DPR-31 55 0.205 0.004

VERMONT YANKEE DPR-28 47 0.527 0.011

VOGTLE NPF-68 14 0.223 0.016

WATERFORD NPF-38 2 0.039 0.020

WATTS BAR NPF-90 292 1.833 0.006

WOLF CREEK NPF-42 11 0.026 0.002

Total 2,864 19.130 0.007

Grand Totals 5,381 792.586 0.147

Licensee Type Licensee Name License Number

Number

with Meas.

CEDE

Collective

CEDE

(person-rem)

Average

Meas. CEDE

(rem)
3-27

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.10

Internal Dose (CEDE) Distribution

1994 - 1999

Year

Meas.

0.020

1994

1995

1996

1997

1998

1999

Total with

Meas.

CEDE

Collective

CEDE

(personrem)

Average

Meas.

CEDE

(rem)

3,425

2,868

3,096

3,835

3,310

3,399

0.020-

0.100

577

691

598

869

932

630

0.100-

0.250

287

338

305

381

426

402

0.250-

0.500

351

362

317

366

355

425

0.500-

0.750

196

216

190

242

230

206

0.750-

1.000

138

145

121

148

140

117

1-2

293

288

185

169

153

173

2-3 3-4 4-5

69

49

22

30

21

29

2

2

2

-

2

-

-

-

2

-

-

-

5,338

4,959

4,838

6,040

5,569

5,381

1,033.688

1,019.045

741.373

826.280

779.148

792.586

0.194

0.205

0.153

0.137

0.140

0.147

Number of Individuals with CEDE in the Ranges (rem)
3-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

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4-1

Thirty-Second Annual Report, 1999 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 Reference 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.

In 1999, Millstone Unit 1 (a BWR) was

removed from the count of operating reactors.

This brings the count of operating BWRs in

1999 to 35. The count of operating PWRs

remains the same as in 1998 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 C. 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 1999, the number

reflects the net electricity produced which is

the gross electricity minus the amount the

plant uses for operations. This change is the

result of a change in the NRC power

generation reporting requirements. The

electricity generated (in megawatt-years) that

is presented in Tables 4.1, 4.2, and 4.3 is the
4-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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%

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 - 1999
4-3

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 4.2

Summary of Information Reported by Commercial Pressurized Water Reactors

1973 - 1999

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%

*

**

***

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

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

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

*

**

***
4-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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%

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 - 1999
4-5

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 Reference 12.

As shown in Table 4.3, there was an 8%

increase in the net electricity generated at

LWRs in 1999. BWRs increased by 13% in

net electricity generated, despite the fact that

Millstone Unit 1 is no longer in operation.

Clinton Power Station generated power in

1999 after being off-line in 1997 and 1998.

PWRs increased net electric output by 9%,

despite the fact that Cook 1, 2 produced no

power due to design basis concerns.

Millstone Unit 2, 3 significantly increased

power output from 1998.

4.2.3 Collective Dose per Megawatt-Year

The number of megawatt-years of electricity

generated was used in determining the ratio of

the average value of the annual collective

dose (TEDE) to the number of

megawatt-years of electricity generated. The

ratio was calculated by dividing the total

collective dose in person-rem by the electric

energy generated in megawatt-years 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 1999, 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-year for

LWRs decreased by 6% in 1999 to a value of

0.16, which is an all-time low and is ten times

less than the value in 1983.

4.2.4 Average Maximum Dependable

Capacity

Average maximum dependable capacity,

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 Reference 12.

4.2.5 Percent of Maximum Dependable

Capacity Achieved

The percent of maximum dependable capacity

achieved is shown for all LWRs in Table 4.3.

This parameter gives an indication of the

overall power generation performance of

LWRs as compared to the maximum

dependable capacity that could be obtained in

a given year. It is calculated by dividing the

average electricity generated per reactor by

the average maximum dependable capacity

for each year.

From 1973 to 1978 this indicator exhibited an

increasing trend as a number of new reactors

began producing power at higher efficiencies.
4-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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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 7% from 1998 to 1999.

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 1999. 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 1999 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). For the 1999

report, the data for all years have been

updated to account for corrections and

additional exposure records submitted by

reactor licensees in accordance with Generic

Letter 94-04. In addition, Table 4.4 now

includes only those reactors in operation for a

full year for each year presented in the table.

The total collective dose increased by 4% to a

value of 13,666 person-rem in 1999, the first

increase in collective dose since 1992.
4-7

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

*

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 2,266 716 121 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 8,134 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 54,938 29,128 13,208 8,988 3,803 1,916 1,908 247 18 114,154 59,216 13,666

**

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.

**

TABLE 4.4

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

1977 - 1999
4-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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 1999, the average

collective dose per reactor dropped by 83%.

Between 1998 and 1999, the collective dose

per reactor for PWRs increased by 14% to

105 person-rem. The collective dose per

reactor for BWRs decreased by 3% to 184

person-rem from 1998 to 1999. The overall

collective dose per reactor for LWRs

increased by 4% to 131 person-rem in 1999.

The number of workers with measurable dose

per reactor decreased to 899 for BWRs and

increased to 637 for PWRs in 1999. 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. 1999 is the first year since

1992 where there has been an increase in the

average collective dose per reactor.

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 increased by 4% from a

value of 13,188 person-rem in 1998 to 13,666

person-rem in 1999. Together with the

increase in the number of workers with

measurable dose, this resulted in the average

measurable dose per worker remaining the

same at 0.18 rem in 1999. Figure 4.2 shows

that in 1999 the net electricity generated

increased to an all-time high of 83,198 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-Second Annual Report, 1999 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 - 1999
4-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

FIGURE 4.2. Number of Operating Reactors and Gross Electricity Generated

1973 - 1999

* Gross electricity 1973-1996, net electricity for 1997-1998.

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

0

10

20

30

40

50

60

70

80

90

100

110

120

Number of Reactors

Year

BWR

PWR

Number of Operating Reactors

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

0

10

20

30

40

50

60

70

80

90

Megawatt-Years (Thousands)

Year

BWR

PWR

LWR

Electricity Generated*
4-11

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

1973 - 1999

* Gross electricity 1973-1996, net electricity for 1997-1999.
4-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

To further assist in the identification of any

trends that might exist, Figures 4.4 and 4.5

display the average and median6 values of the

collective dose per reactor for BWRs and for

PWRs for the years 1973 through 1999. 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 twenty-fifth through the

seventy-fifth 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

an increase from 85 person-rem in 1998 to 96

person-rem in 1999. At BWRs, the median

fluctuates more from year to year, and in 1999

the median collective dose decreased to 164

person-rem. Figure 4.5 also shows that, in

1999, 50% of the PWRs reported collective

doses between 67 and 126 person-rem while

50% of the BWRs reported collective doses

between 136 and 223 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

Tables 4.5 and 4.6 list the sites that had been

in commercial operation for at least 3 years

as of December 31, 1999, 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 reactoryears of operation accumulated by the 35

BWRs listed, the average 3-year collective

TEDE per reactor was found to be 198

person-rem, the average measurable TEDE

per worker was 0.22 rem, and the average

collective TEDE per megawatt-year was 0.28

person-rem per MW-yr.

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 megawatt-year were

found to be 110 person-rem, 0.17 rem, and

0.14 person-rem per MW-yr, respectively.

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 1997 -1999 is 10% less than the

average for 1996 -1998. The average 3-year

collective TEDE per PWR for 1997 -1999 is

8% less than the average for 1996 -1998. The

average megawatt-year per reactor for BWRs

and PWRs was greater than the previous

3-year average.

6 The value at which 50% of the reactors reported greater collective doses and the other 50% reported smaller collective doses.
4-13

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

1973 - 1986

Collective Doses Per Reactor (person-rem)

500

1000

1500

2000

2500

3000

3500

4000

4500

5000

5500

0

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

Year

M

A

M

A

M

A

M

A

A M

A

M

A

M

A

M

A

A

A

A

M

A

M

A

M

A

M

A

A

M

A

A

M

A

M

A

M

A

M

A

M

A M

A

A M

A

M

A

Middle 50% of BWRs

Middle 50% of PWRs

Average Collective Dose

M Median Collective Dose

A

M

M M

M M

M

M
4-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

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

1987 - 1999

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

126

67

223

136
4-15

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

FERMI 2 3 98 293 2,446 0.12 2,535.5 0.12

MONTICELLO 3 128 385 1,524 0.25 1,418.3 0.27

OYSTER CREEK 3 133 400 2,383 0.17 1,685.0 0.24

CLINTON 3 134 403 2,241 0.18 537.0 0.75

COOPER STATION 3 135 404 2,420 0.17 1,921.9 0.21

LIMERICK 1, 2 6 144 863 5,117 0.17 5,998.5 0.14

VERMONT YANKEE 3 144 432 2,058 0.21 1,333.9 0.32

BROWNS FERRY 1, 2, 3 9 149 1,337 5,621 0.24 5,981.7 0.22

DUANE ARNOLD 3 167 501 2,205 0.23 1,329.3 0.38

FITZPATRICK 3 172 517 3,001 0.17 2,068.7 0.25

PEACH BOTTOM 2, 3 6 196 1,175 5,405 0.22 5,894.7 0.20

BRUNSWICK 1, 2 6 204 1,225 6,035 0.20 4,489.7 0.27

SUSQUEHANNA 1, 2 6 204 1,225 5,008 0.24 5,694.5 0.22

NINE MILE POINT 1, 2 6 209 1,254 4,878 0.26 4,118.3 0.30

GRAND GULF 3 212 635 3,104 0.20 3,246.2 0.20

PERRY 3 213 640 3,667 0.17 3,135.4 0.20

LASALLE 1, 2 6 219 1,314 6,449 0.20 2,052.8 0.64

HATCH 1, 2 6 228 1,371 5,421 0.25 4,320.5 0.32

HOPE CREEK 13 228 684 3,478 0.20 2,604.10.26

WASHINGTON NUCLEAR 2 3 231 692 3,460 0.20 2,181.2 0.32

DRESDEN 2, 3 6 248 1,485 8,301 0.18 3,861.8 0.38

RIVER BEND 13 250 749 3,464 0.22 2,324.2 0.32

QUAD CITIES 1, 2 6 269 1,616 5,651 0.29 3,206.6 0.50

PILGRIM 3 334 1,003 3,407 0.29 1,653.3 0.61

Grand Totals and Averages 105 20,604 96,744 0.21 73,593.1 0.28

Averages Per Reactor-Year 196 921 700.9

* Sites where not all reactors had completed 3 full years of commercial operation as of 12/31/99 are not included.

TABLE 4.5

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

1997 - 1999
4-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

TABLE 4.6

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

1997 - 1999

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

KEWAUNEE 3 50 149 765 0.19 1,197.9 0.12

PRAIRIE ISLAND 1, 2 6 61 363 1,877 0.19 2,667.2 0.14

DAVIS-BESSE 3 64 193 1,590 0.12 2,361.1 0.08

PALO VERDE 1, 2, 3 9 65 584 4.270 0.14 10,294.8 0.06

WATTS BAR 1 3 72 215 2,174 0.10 2,915.8 0.07

POINT BEACH 1, 2 6 76 455 2,513 0.18 1,642.5 0.28

BEAVER VALLEY 1, 2 6 77 464 2,932 0.16 3,036.1 0.15

NORTH ANNA 1, 2 6 77 463 2,784 0.17 5,092.0 0.09

ARKANSAS 1, 2 6 78 470 3,907 0.12 4,593.8 0.10

OCONEE 1, 2, 3 9 88 791 4,642 0.17 5,817.3 0.14

SALEM 1, 2 6 89 534 2,502 0.21 3,730.4 0.14

GINNA 3 90 271 1,335 0.20 1,339.8 0.20

CATAWBA 1, 2 6 91 547 3,708 0.15 6,081.3 0.09

VOGTLE 1, 2 6 91 549 3,347 0.16 6,351.0 0.09

WATERFORD 3 3 98 295 2,301 0.13 2,600.8 0.11

HARRIS 3 99 298 2,309 0.13 2,266.8 0.13

SUMMER 1 3 99 297 1,932 0.15 2,606.5 0.11

CALVERT CLIFFS 1, 2 6 101 608 3,267 0.19 4,544.1 0.13

ROBINSON 2 3 102 307 2,089 0.15 1,984.9 0.15

MILLSTONE UNIT 2, 3 6 103 618 4,302 0.14 1,811.8 0.34

SEABROOK 3 104 311 3,469 0.09 2,856.1 0.11

COMANCHE PEAK 1, 2 6 105 629 3,153 0.20 6,021.7 0.10

SURRY 1, 2 6 108 647 3,495 0.19 4,339.5 0.15

TURKEY POINT 3, 4 6 116 698 3,545 0.20 3,896.4 0.18

SOUTH TEXAS 1, 2 6 119 717 4,082 0.18 6,864.6 0.10

BRAIDWOOD 1, 2 6 121 726 4,715 0.15 5,996.8 0.12

INDIAN POINT 3 3 122 366 2,714 0.13 2,198.9 0.17

THREE MILE ISLAND 1 3 125 376 2,500 0.15 2,203.9 0.17

BYRON 1, 2 6 126 755 4,833 0.16 5,790.7 0.13

COOK 1, 2 6 138 826 4,681 0.18 1,189.7 0.69

DIABLO CANYON 1, 2 6 140 841 4,210 0.20 5,806.6 0.14

FORT CALHOUN 3 141 424 1,722 0.25 1,232.8 0.34

WOLF CREEK 1 3 141 423 1,985 0.21 3,196.9 0.13

SEQUOYAH 1, 2 6 142 851 4,838 0.18 6,246.5 0.14

MCGUIRE 1, 2 6 148 891 4,512 0.20 5,659.7 0.16

SAN ONOFRE 2, 3 6 148 891 4,220 0.21 5,431.7 0.16

CRYSTAL RIVER 3 3 150 449 2,610 0.17 1,467.4 0.31

FARLEY 1, 2 6 150 900 3,587 0.25 4,199.6 0.21

ST. LUCIE 1, 2 6 159 957 4,591 0.21 4,536.2 0.21

PALISADES 3 161 483 2,172 0.22 1,863.3 0.26

CALLAWAY 1 3 178 534 2,275 0.23 2,975.7 0.18

INDIAN POINT 2 3 233 698 2,844 0.25 1,475.2 0.47

Grand Totals and Averages 207 22,864 131,299 0.17 158,385.8 0.14

Averages Per Reactor-Year 110 634 765.1

* Sites where not all reactors had completed 3 full years of commercial operation as of 12/31/99 are not included.
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4.6 GRAPHICAL

REPRESENTATION OF DOSE

TRENDS IN APPENDIX D

Each page of Appendix D presents a graph of

selected dose-performance indicators from

1973 through 1999. 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 1999. 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 is

included because it provides a better 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 to

be transient in that 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 and average dose for 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 above-mentioned 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.

Because >95% of these transients are

reported by nuclear power facilities, these

data were considered separately. Table 5.1

shows that the power reactor transient data

constitute the vast majority of the transient

worker exposure. The nonreactor licensees

account for only 2% of the transient workforce.
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TABLE 5.1

Effects of Transient Workers on Annual Statistical Compilations

1999

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

TEDE

(rem)

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

74,867 39,663 18,063 10,964 3,994 1,569 1,141 24 2 150,287 75,420 13,666 0.09 0.18

26,087 16,136 8,429 5,107 1,938 728 588 13 1 59,027 32,940 6,417 0.11 0.19

6,158 5,601 3,574 3,131 1,747 1,075 1,355 236 17 22,894 16,736 6,417 0.28 0.38

54,938 29,128 13,208 8,988 3,803 1,916 1,908 247 18 114,154 59,216 13,666 0.12 0.23

83,041 43,140 19,296 12,011 4,611 1,915 1,778 204 74 13 1 166,084 83,043 16,661 0.10 0.20

26,587 16,392 8,545 5,179 1,972 742 608 17 2 60,044 33,457 6,543 0.11 0.20

6,159 5,620 3,607 3,167 1,786 1,088 1,389 240 21 23,077 16,918 6,543 0.28 0.39

62,613 32,368 14,358 9,999 4,425 2,261 2,559 427 93 13 1 129,117 66,504 16,661 0.13 0.25
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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 1999. 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 1999, Table 5.1 shows that the

summation of annual reports for reactor

licensees indicated that 26 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

265 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 nearly twice as high as

the value calculated by the summation of

licensee records. The transient workers

represent 25% of the workforce that receives

measurable dose and increases the average

measurable dose for all licensees by 25% from

0.20 rem to 0.25 rem. 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 1999, 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 Commission. 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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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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(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 current the exposure events summary

presented here. 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 1999. 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.

There were six “Category B” occurrences in

1999. One radiography worker received a

dose that exceeded the 5 rem TEDE regulatory

limit, one occurrence where an individual

exceeded the 50 rem limit for the skin, and four

instances where extremity exposures have

been re-assessed and exceeded the 50 rem

limit for extremities. There were two additional

occurrences in which individuals received

“Category A” exposures due to the extremity

exposure re-assessment.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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TABLE 6.1

Occupational Exposures in Excess of Regulatory Limits

1994 - 1999

2

1,080

1

143

4

423

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

& MANUFACTING 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

& MANUFACTING 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

& MANUFACTING 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

1

5.1

1

8.3

1b

51.1

1c

70.6

3

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

License Persons and

Year Category Doses (rem)

TEDE (rem) Skin/Extremity (rem)

f f

3

1,115

5

675

f f

5 f

431

f

6

740

f

4d, f

782

1

255

f

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.
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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

1

275

1986

1987

1988

1989

1990

1991

1992

4

57.7

1a

5.4

3c, d

49.9

1

6.1

1

7.5

3

32.6

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

93

1

27.0

1

24.1

1

9.2

4

66.8

5

128.4

1

61

1

278

1c

6000

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

1

272

1

111

1

178

1

118

1

127

1

180

1

115

1

288

1

93

2

930

1

650

2d

3962

1

300-1000

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.

1

6

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

3f

187.3

TABLE 6.2

Occupational Exposures in Excess of Regulatory Limits

1985 - 1993
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In July 1999, a multi-location radiography

licensee was notified by the dosimetry

processor company of an exposure exceeding

5 rem. The exposure apparently occurred in

May of 1999. The radiographer had been

performing radiography using an Iridium-192

source at three sites in Texas, New Mexico,

and California. The individual stated that, at

one point, he had trouble with a 50-foot crank

assembly that may have been the cause of

the exposure. At the time, the individual noted

that his self-reading dosimeter was off-scale.

The individual had been working extended

hours and his judgment may have been

impaired by a lack of sleep. Upon receipt of

the notification of the dosimeter reading by the

dosimetry processor, the individual was

removed from performing radiography. The

licensee reported a dose of 5.670 rem TEDE

to the NRC. An investigation by the State of

California is ongoing because a portion of the

work was performed in California.

In October 1999, a nuclear medicine

technologist working at a broad license

medical institution received a dose to the skin

in excess of the 50 rem annual limit. The

technologist contaminated a small area on the

tip of one finger with approximately 0.11 MBq

(3 uCi) of I-131 meta-iodobenzylguanidine

(MIBG). The contamination occurred

immediately following the administration of a

9.25 GBq (250 mCi) dose of I-131 MIBG to a

pediatric patient. The event occurred because

the technologist drew too much I-131 MIBG

into the syringe and had to return the material

to the sealed vial through the vial septum. The

technologist should have removed some air

from the vial or vented the vial before

returning the material to the sealed vial.

Because she did not, after returning the

material to the vial, a positive pressure existed

and some material was atomized and expelled

through the septum of the vial when the

needle was removed.

Although the contamination was promptly

identified and decontamination efforts were

begun immediately, the contamination was

difficult to remove and a shallow dose

equivalent of 143 cSv (rem) was estimated

(final estimate). The radiopharmaceutical

appeared to be bound to a small localized

area and, based on bioassay results, it did

not appear to be biologically available as no

significant thyroid uptake was detected. The

licensee is not one of the categories of

licensees required to report to the NRC under

10 CFR 20.2206, and therefore is not

included in the dose values presented

elsewhere in this report. This exposure,

however, is included in Table 6.2 under the

category of Medical Facilities.

The four “Category B” and two “Category A”

extremity exposures occurred at a

radiopharmaceutical manufacturing licensee.

The exposures were a result of the direct

handling of vials containing radioactive

Indium. The licensee’s extremity monitoring

practices were found to have underestimated

the dose to the hands during the manipulation

of the vials. A subsequent re-assessment of

the exposures concluded that the doses were

in excess of the annual extremity limit as

shown in Table 6.1. The revised extremity

dose records have not yet been reported to

REIRS. An investigation by the NRC is

ongoing.
6-7

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

6.4 MAXIMUM EXPOSURES

BELOW THE NRC LIMITS

Because few exposures exceed the NRC

occupational exposure limits, certain

researchers have expressed an interest in a

listing of the maximum exposures received at

NRC licensees that do not exceed the limits.

This would allow an examination of exposures

that approach, but do not exceed the limits.

Table 6.3 shows the maximum exposures for

each dose category required to be reported to

the NRC. In addition, the number of

TABLE 6.3

Maximum Occupational Exposures for Each Exposure Category *

1999

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.

*** Extremity exposures do not include the exposures in excess of the extremity limits shown in Table 6.1 as these revised dose records have not

yet been reported to REIRS.

SDE-ME 50 rem 43.600 87% 57,143 122 38 8 0

SDE-WB 50 rem 28.823 58% 68,658 2 1 0 0

LDE 15 rem 4.920 33% 66,572 21 0 0 0

CEDE 2.693 5,243

CDE 23.417 3,037

DDE 5.670 67,955

TEDE 5 rem 5.670 > limit 68,850 1,965 235 29 5 (1>limit)

TODE 50 rem 23.765 48% 60,233 99 0 0 0

**

***

exposures in certain dose ranges is shown to

reflect the number of exposures that approach

the NRC limits.

As can be seen from Table 6.3, few exposures

exceed half of the NRC occupational annual

limits. In 1999, five individuals came within

5% of the TEDE limit in addition to the one

individual who exceeded the limit. No

individuals were reported to have exceeded

the extremity, skin, eye, or organ dose limits.
6-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

This page intentionally left blank.
7-1

Thirty-Second Annual Report, 1999 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-Second Annual Report, 1999

NUREG-0713

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A-1

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ANNUAL TEDE FOR NON-REACTOR

NRC LICENSEES

1999

Appendix A
A-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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 7 6 1 1 - - - - - - - - - 15 8 0.570 0.071

DIAGNOSTIC PHOTON CORPORATION 52-16345-02MD 5 7 2 2 - - - - - - - - - 16 11 1.291 0.117

EASTERN ISOTOPES - ASHBURN 45-25221-01MD 14 19 4 3 5 3 5 2 1 - - - - 56 42 22.491 0.536

HEARTLAND DIAGNOSTIC SERVICES, INC. 48-26585-01MD 3 6 - 1 - 1 - - - - - - - 11 8 1.422 0.178

LAKESHORE ISOTOPES 37-28520-02MD - 8 5 1 - - - - - - - - - 14 14 1.814 0.130

MALLINCKRODT, INC. 24-04206-00MD 1 6 2 - - - - - - - - - - 9 8 0.670 0.084

MALLINCKRODT MEDICAL, INC. 24-04206-01MD 4 5 3 - 2 - - - - - - - - 14 10 1.840 0.184

MALLINCKRODT, INC. 24-04206-08MD 6 9 3 - - - - - - - - - - 18 12 0.820 0.068

MALLINCKRODT, INC. 24-04206-12MD 2 23 1 1 2 - - - - - - - - 29 27 2.780 0.103

MALLINCKRODT MEDICAL INC. 24-04206-14MD 2 10 2 5 3 1 - - - - - - - 23 21 5.210 0.248

MALLINCKRODT MEDICAL, INC. 24-04206-19MD 2 6 4 5 2 - 1 - - - - - - 20 18 5.390 0.299

MALLINCKRODT MEDICAL, INC. 24-17450-02MD 11 10 1 1 - - - - - - - - - 23 12 0.770 0.064

MID-AMERICA ISOTOPES, INC. 24-26241-01 21 1 2 - - - - - - - - - - 24 3 0.330 0.110

NUCLEAR DIAGNOSTIC PRODUCTS 29-30500-01MD - 3 - - - - - - - - - - - 3 3 0.053 0.018

OKLAHOMA, UNIVERSITY OF 35-03176-04MD 6 7 3 - - - - - - - - - - 16 10 0.630 0.063

PHARMALOGIC OF PENN, LTD 37-30219-01MD 1 7 4 - - - - - - - - - - 12 11 0.846 0.077

PHARMALOGIC MI, LLC 21-32190-01 - 5 - - - - - - - - - - - 5 5 0.106 0.021

PHARMALOGIC LTD 44-30124-01MD 3 3 2 - - - - - - - - - - 8 5 0.330 0.066

SPECTRUM PHARMACY INC. 13-26367-01 7 26 6 1 - 2 1 - - - - - - 43 36 5.070 0.141

SPECTRUM PHARMACY OF FT. WAYNE 13-32053-01MD 17 3 1 - - - - - - - - - - 21 4 0.230 0.058

SYNCOR INTERNATIONAL CORP. 04-26507-01MD 95 60 11 2 - - - - - - - - - 168 73 3.930 0.054

Total 21 207 230 57 23 14 7 7 2 1 - - - - 548 341 56.593 0.166

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1999

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

Thirty-Second Annual Report, 1999 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

ABB AUTOMATION, INC. 34-00255-03 2 1 - - - - - - - - - - - 3 1 0.050 0.050

ADVANCED MEDICAL SYSTEMS, INC. 34-19089-01 - 1 - - - - - - - - - - - 1 1 0.014 0.014

APTEC-NRC, INC. 29-04236-01 7 25 1 - - - - - - - - - - 33 26 0.835 0.032

BRISTOL-MEYER SQ 29-00139-02 842 40 5 3 1 1 3 - - - - - - 895 53 8.258 0.156

MALLINCKRODT MEDICAL INC. 24-04206-01 58 46 31 37 22 15 48 31 37 4 - - - 329 271 338.304 1.248

Total 5 909 113 37 40 23 16 51 31 37 4 - - - 1,261 352 347.461 0.987

MANUFACTURING AND DISTRIBUTION - TYPE B BROAD - 03212

BEST INDUSTRIES, INC. 45-19757-01 41 12 4 3 1 2 2 - - - - - - 65 24 6.611 0.275

OHMART CORP. 34-00639-01 57 15 10 3 - - - - - - - - - 85 28 3.410 0.122

Total 2 98 27 14 6 1 2 2 - - - - - - 150 52 10.021 0.193

MANUFACTURING AND DISTRIBUTION - OTHER - 03214

ADVANZ MEASUREMENT & CONTROL 34-26683-03 8 3 - - - - - - - - - - - 11 3 0.100 0.033

APTEC-NRC, INC. 37-02401-01 15 11 3 - - - - - - - - - - 29 14 0.610 0.044

BICRON: SAINT-GOBAIN/NORTON 34-06558-05 38 15 - - - - - - - - - - - 53 15 0.290 0.019

CIS-US, INC. 20-20973-04 1 3 - - - - - - - - - - - 4 3 0.120 0.040

CP CLARE CORPORATION 24-26366-01 3 3 - - - - - - - - - - - 6 3 0.006 0.002

DIAGNOSTECH INT'L, INC. 48-26355-01 2 - - - - - - - - - - - - 2 - - -

DU PONT MERCK PHARMACEUTICAL CO. 20-00320-19 - 4 6 - - - - - - - - - - 10 10 1.063 0.106

FUJIREBIO DIAGNOSTICS, INC. 37-30487-01 29 29 2 - - - - - - - - - - 60 31 0.900 0.029

HALLIBURTON CO. 35-00502-03 - - 1 1 - - - - - - - - - 2 2 0.569 0.285

INTERSIL CORPORATION 37-24841-02 30 - - - - - - - - - - - - 30 - - -

THERATRONICS INTERNATIONAL LTD. 54-28315-01 5 8 1 - - 1 - - - - - - - 15 10 1.260 0.126

Total 11 131 76 13 1 - 1 - - - - - - - 222 91 4.918 0.054

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1999

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-Second Annual Report, 1999

NUREG-0713 APPENDIX A Annual TEDE for Non-Reactor NRC Licensees CY 1999

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 51 5 - - - - - - - - - - - 56 5 0.068 0.014

ARMY, DEPARTMENT OF THE 29-00047-06 - 1 - - - - - - - - - - - 1 1 0.024 0.024

ARROW TANK & ENGINEERING CO. 22-13253-01 1 2 - 2 1 - - - - - - - - 6 5 1.490 0.298

BUCKEYE STEEL CASTINGS 34-06627-01 2 1 - - - - - - - - - - - 3 1 0.020 0.020

BWX TECHNOLOGIES, INC. 34-02160-03 14 4 - - - - - - - - - - - 18 4 0.040 0.010

CARONDELET FOUNDRY COMPANY 24-26136-01 4 5 - - - - - - - - - - - 9 5 0.342 0.068

CHART INDUSTRIES, INC. 22-24393-01 2 4 - - - - - - - - - - - 6 4 0.210 0.053

DURALOY 37-02279-02 - 2 1 1 - - - - - - - - - 4 4 0.660 0.165

ELECTROALLOYS 34-24346-01 4 3 - - - - - - - - - - - 7 3 0.080 0.027

GENERAL MOTORS CORP. 21-08678-05 4 - - - - - - - - - - - - 4 - - -

GREDE-PRYOR, INC. 35-18099-01 3 1 - - - - - - - - - - - 4 1 0.015 0.015

HARRISON STEEL CASTINGS CO. 13-02141-01 5 2 - - - - - - - - - - - 7 2 0.050 0.025

INTERMET CORPORATION 45-17464-01 7 - - - - - - - - - - - - 7 - - -

MISSOURI STEEL CASTINGS 24-15152-01 2 1 - - - - - - - - - - - 3 1 0.039 0.039

NILES STEEL TANK CO. 21-04741-01 4 - - - - - - - - - - - - 4 - - -

PELTON CASTEEL, INC. 48-02669-02 3 - - - - - - - - - - - - 3 - - -

RIDGEWATER COLLEGE 22-15554-01 46 1 - - - - - - - - - - - 47 1 0.010 0.010

THE DURIRON COMPANY, INC. 34-06398-01 - 2 2 - - - - - - - - - - 4 4 0.362 0.091

TRANS WORLD AIRLINES, INC. 24-05151-05 60 - - - - - - - - - - - - 60 - - -

WAUKESHA FOUNDRY DIVISION 48-13776-01 3 - - 1 - - - - - - - - - 4 1 0.260 0.260

WISCONSIN CENTRIFUGAL, INC. 48-11641-01 1 1 - 4 3 - - - - - - - - 9 8 3.363 0.420

Total 21 216 35 3 8 4 - - - - - - - - 266 50 7.033 0.141
A-5

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1999

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

ACCURATE TECHNOLOGIES, INC. 29-28358-01 1 3 2 4 1 2 1 1 2 - - - - 17 16 14.480 0.905ADVANCED INSPECTION TECHNOLOGIES 35-27588-01 - 1 - 2 5 1 - 5 - - - - - 14 14 16.757 1.197

AIR FORCE, DEPARTMENT OF THE * 42-23539-01AF 9 - - - - - - - - - - - - 9 - - -

AKRON INDUSTRIAL SERVICES, INC. 34-24673-01 1 - - 1 1 - - - - - - - - 3 2 0.959 0.480

ALASKA INDUSTRIAL X-RAY, INC. 50-16084-01 3 4 1 2 - 2 2 - - - - - - 14 11 6.620 0.602

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

ALLIED INSPECTION SERVICES, INC. 21-18428-01 - - - 1 - - 3 - - - - - - 4 4 3.683 0.921

ALONSO & CARUS IRON WORKS, INC. 52-21350-01 1 3 1 - 1 - - - - - - - - 6 5 0.739 0.148

AMERICAN AIRLINES, INC. 35-13964-01 - 32 - - - - - - - - - - - 32 32 0.641 0.020

AMERICAN ENGINEERING TESTING 22-20271-02 - 4 2 2 - - 1 - - - - - - 9 9 2.523 0.280

ANVIL CORPORATION 46-23236-03 2 15 14 20 7 10 10 2 - - - - - 80 78 41.267 0.529

APPLIED TECHNICAL SERVICES, INC. 45-25477-01 1 1 1 2 1 - - - - - - - - 6 5 1.660 0.332

ARCTIC SLOPE INSPECTION SVCS, INC. 50-29015-01 50 30 32 33 18 5 7 - - - - - - 175 125 44.900 0.359

ARMY, DEPARTMENT OF THE 30-02405-05 1 1 - - - - - - - - - - - 2 1 0.049 0.049

ARROW NDE CO., INC. 35-23198-01 1 - - - - - - - - - - - - 1 - - -

BARNETT INDUSTRIAL X-RAY 35-26953-01 1 1 - 3 2 1 4 3 - - - - - 15 14 15.865 1.133

BIG STATE X-RAY, INC. 35-21144-01 - 3 4 7 7 - 6 - - - - - - 27 27 16.275 0.603

BILL MILLER, INC. 35-19048-01 4 3 10 10 11 3 7 1 - - - - - 49 45 25.050 0.557

BRANCH RADIOGRAPHIC LABS., INC. 29-03405-02 4 11 7 1 5 1 - - - - - - - 29 25 5.763 0.231

BRAUN INTERTEC CORPORATION 22-16537-02 5 7 6 5 2 2 1 - - - - - - 28 23 7.467 0.325

CALUMET TESTING SERV., INC. 13-16347-01 7 3 1 2 3 - 2 4 - - - - - 22 15 16.349 1.090

CAPITAL X-RAY SERV., INC. 35-11114-01 - 1 11 1 3 - 7 4 2 - - - - 29 29 32.723 1.128

CENTURY INSPECTION, INC. 42-08456-02 12 18 19 15 11 5 11 - - - - - - 91 79 34.018 0.431

CHICAGO BRIDGE AND IRON CO. 42-13553-02 2 10 4 4 2 1 - - - - - - - 23 21 4.320 0.206

COLBY & THIELMEIER TESTING CO. 24-13737-01 - - 2 - 1 2 4 - - - - - - 9 9 8.985 0.998

COMO TECH INSPECTION 15-26978-01 1 - 1 1 - 3 1 - - - - - - 7 6 4.195 0.699

CONAM INSPECTION 12-16559-01 77 67 39 51 26 12 29 4 1 - - - - 306 229 105.517 0.461

CONNELL LIMITED PARTNERSHIP 35-13735-01 2 - - 1 - - - - - - - - - 3 1 0.280 0.280
A-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713 APPENDIX A Annual TEDE for Non-Reactor NRC Licensees CY 1999

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

COOPERHEAT - MQS, INC. 12-00622-07 62 28 22 20 12 3 6 - - - - - - 153 91 29.160 0.320

CTI CORE DRILLING SERVICES, INC. 45-25383-01 3 - 2 - - - 1 - - - - - - 6 3 1.870 0.623

DIAMOND H TESTING COMPANY 11-27316-01 2 10 2 5 2 - - - - - - - - 21 19 3.933 0.207

EASTERN TESTING & INSPECTION, INC. 29-09814-01 - 3 2 1 2 - - - - - - - - 8 8 1.819 0.227

EDWARDS PIPELINE TESTING, INC. 35-23193-01 9 48 35 33 7 4 1 - - - - - - 137 128 28.778 0.225

ELECTRIC BOAT CORPORATION 06-01781-08 - 6 4 - - - - - - - - - - 10 10 0.609 0.061

ELITE INSPECTION, INC. 13-26712-01 4 2 2 4 3 4 6 - - - - - - 25 21 15.240 0.726

FROEHLING & ROBERTSON, INC. 45-08890-01 4 7 1 1 - - - - - - - - - 13 9 0.814 0.090

G. E. INSPECTION SERVICES, INC. 39-24888-01 12 8 2 3 2 2 1 - - - - - - 30 18 5.730 0.318

GENERAL TESTING & INSPECTION CO. 47-32191-01 - 1 2 1 1 - - - - - - - - 5 5 1.570 0.314

GLITSCH FIELD SERVICES/NDE,INC. 34-14071-01 9 12 8 3 3 1 - - - - - - - 36 27 5.316 0.197

GLOBE X-RAY SERVICES, INC. 35-15194-01 1 13 10 3 6 7 8 1 - - - - - 49 48 27.372 0.570

GREAT LAKES TESTING, INC. 48-26484-01 1 3 - - 4 1 4 - - - - - - 13 12 9.251 0.771

GRINNELL CORPORATION 38-28750-01 1 3 1 - - - - - - - - - - 5 4 0.240 0.060

H & G INSPECTION CO., INC. 42-26838-01 1 1 1 1 2 4 6 1 1 - - - - 18 17 20.693 1.217

HIGH MOUNTAIN INSPECTION SERVICES 49-26808-02 19 5 4 7 6 14 13 8 3 2 - - - 81 62 76.685 1.237

HUNTINGTON TESTING & TECH. 47-23076-01 1 3 3 6 2 1 7 1 - - - - - 24 23 17.650 0.767

INSPECTION MANAGEMENT CORP. 35-26824-01 1 1 - 1 1 - 4 - 1 - - - - 9 8 10.464 1.308

INTEGRATED TECHNOLOGIES, INC. 06-30317-01 3 8 3 6 1 - - - - - - - - 21 18 3.545 0.197

INT'L RADIOGRAPHY & INSPECTION SVCS 35-30246-01 1 3 5 8 4 3 9 3 2 5 - - - 43 42 61.910 1.474

JAN X-RAY SERVICES, INC. 21-16560-01 2 12 9 14 13 10 17 2 - - - - - 79 77 52.010 0.675

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

LAW ENG & ENV SVCS/SAM-SON INSP. 34-25898-01 2 5 1 5 1 - 3 - - - - - - 17 15 6.852 0.457

LONGVIEW INSPECTION, INC. 42-27593-01 24 23 16 15 27 12 24 2 - - - - - 143 119 72.102 0.606

LUCIUS PITKIN 29-27816-01 2 - 4 2 1 - - - - - - - - 9 7 2.027 0.290

MAGNA CHEK 21-19111-02 11 2 - - - - - - - - - - - 13 2 0.070 0.035

MARTIN INDUSTRIAL TESTING, INC. 45-25452-01 - - - 1 - - 1 - - - - - - 2 2 1.499 0.750

MARYLAND Q.C. LABORATORIES 19-28683-01 4 12 2 1 2 - - - - - - - - 21 17 2.085 0.123
A-7

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1999

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 RES. 07-01173-03 1 - 2 1 - 1 - - - - - - - 5 4 1.488 0.372

MATTINGLY TESTING SERVICES, INC. 25-21479-01 - 1 4 4 1 - 1 - - - - - - 11 11 3.895 0.354

MET-CHEM TESTING LABS., INC. 43-27362-01 6 6 2 1 2 - 4 2 - - - - - 23 17 12.821 0.754

MID AMERICAN INSPECTION SERV, INC 21-26060-01 - - 5 4 1 2 1 3 - - - - - 16 16 13.610 0.851

MIDWEST INDUSTRIAL X-RAY, INC. 33-27427-01 - 1 1 1 1 1 3 5 - - - - - 13 13 18.727 1.441

MIDWEST INSPECTION SERVICES 35-27005-01 7 8 5 8 4 2 12 12 5 - - - - 63 56 73.017 1.304

NAVY, DEPARTMENT OF THE* 45-23645-01NA 142 132 6 - - - - - - - - - - 280 138 2.915 0.021

NDT SPECIALISTS, INC. 48-25917-01 1 1 1 1 2 2 1 - - - - - - 9 8 4.880 0.610

NEWPORT NEWS SHIPBUILDING 45-09428-02 - 20 8 4 - - - - - - - - - 32 32 3.447 0.108

NONDESTRUCTIVE INSPECTION SVCS 47-11883-01 3 3 2 - 1 - - - - - - - - 9 6 0.993 0.166

NON-DESTRUCTIVE TESTING 21-08606-03 6 8 5 2 1 - - - - - - - - 22 16 2.438 0.152

NOOTER CORP. 24-03783-01 4 10 3 - - 1 - - - - - - - 18 14 1.680 0.120

NORTHWEST INSP. & TESTING SERV. INC 11-27394-01 2 - - - - - - - - - - - - 2 - - -

NOVA DATA TESTING LABS, INC. 45-24872-01 - 2 2 1 1 - - - - - - - - 6 6 1.420 0.237

PACIFIC TESTING, INC. 53-29118-01 - 2 - 1 - - 1 - - - - - - 4 4 1.820 0.455

PETROCHEM INSPECTION SERVICES 04-29067-02 22 18 15 7 6 3 3 2 4 - 1 - - 81 59 39.337 0.667

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

PITT-DES MOINES, INC. 37-27878-01 2 6 5 7 1 - 4 - - - - - - 25 23 9.270 0.403

PRECISION COMPONENTS CORP. 37-16280-01 9 14 1 3 - 2 - - - - - - - 29 20 2.942 0.147

PRIME NDT SERVICES, INC. 37-23370-01 1 1 1 4 3 4 7 1 - - - - - 22 21 19.000 0.905

PROFESSIONAL SERVICE INDUSTRIES 12-16941-03 6 4 3 6 5 1 2 - - - - - - 27 21 9.690 0.461

PROFESSIONAL WELDING ASSOC.,INC. 48-25806-01 3 1 - - - - - - - - - - - 4 1 0.005 0.005

PROGRESS SERVICES, INC. 34-19592-01 2 7 2 - - - - - - - - - - 11 9 0.473 0.053

PSI INSPECTION 24-26628-01 - 3 - - - - - - - - - - - 3 3 0.028 0.009

Q. C. LABORATORIES, INC. 09-11579-03 4 8 3 6 - - - - - - - - - 21 17 2.650 0.156

QSL INSPECTION, INC. 37-28085-01 1 6 7 9 7 6 12 8 3 - - - - 59 58 60.820 1.049

QUALITY ENERGY SERV. & TESTS CORP. 35-26815-01 2 1 - 5 3 - 10 4 - - - - - 25 23 28.485 1.238

QUALITY INSPECTION & TESTING 50-29038-01 - 1 - - 1 - 1 - - - - - - 3 3 2.140 0.713
A-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713 APPENDIX A Annual TEDE for Non-Reactor NRC Licensees CY 1999

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

RAYTHEON ENGINEERS & CONST. 42-30336-01 3 3 1 2 2 1 1 - - - - - - 13 10 4.310 0.431

RIVEST TESTING USA, INC. 35-27438-01 - 1 1 1 1 1 4 - - - - - - 9 9 8.141 0.905

SCIENTIFIC TECHNICAL, INC. 45-24882-01 - 3 2 2 4 - 1 - - - - - - 12 12 4.750 0.396

SENCO CONSTRUCTION 12-32032-01 - 1 1 - - - 1 3 - - - - - 6 6 7.670 1.278

S. K. MCBRYDE, INC. 32-25137-01 - 2 2 1 1 - - - - - - - - 6 6 1.370 0.228

SOUTHWEST X-RAY CORPORATION 49-27434-01 1 8 2 3 3 3 2 1 2 - - - - 25 24 17.824 0.743

SPEC CONSULTANTS, INC. 37-27891-01 2 10 5 3 3 1 3 2 - - - - - 29 27 14.367 0.532

ST. LOUIS TESTING LABS., INC. 24-00188-02 1 4 1 2 1 1 4 1 - - - - - 15 14 10.039 0.717

TECHNICAL WELDING LABORATORY, INC. 42-25214-01 - - - - 2 - 2 2 2 2 - - - 10 10 25.235 2.524

TEI ANALYTICAL SERVICES, INC. 37-28004-01 8 3 4 13 5 5 12 - - - - - - 50 42 29.577 0.704

TENNESSEE VALLEY AUTHORITY 41-06832-06 7 7 6 3 - - - - - - - - - 23 16 2.533 0.158

TESTING INST. OF ALASKA, INC. 50-17446-01 2 2 3 1 - 1 1 - - - - - - 10 8 3.895 0.487

TESTING TECHNOLOGIES, INC. 45-25007-01 - 5 3 4 8 4 11 - 1 - - - - 36 36 29.929 0.831

TESTMASTER INSPECTION CO.,INC. 34-24872-01 - 1 2 - 1 3 3 - - - - - - 10 10 7.945 0.795

THERMAL ENGINEERING, INT'L. 24-19500-01 5 - - - - - - - - - - - - 5 - - -

TRI STATE INSPECTION & CONSULTANTS 37-19640-01 9 2 2 - - - 2 - - - - - - 15 6 2.785 0.464

TULSA GAMMA RAY, INC. 35-17178-01 5 12 17 18 11 5 23 4 1 - - - - 96 91 67.270 0.739

TWIN CITY TESTING CORPORATION 22-01376-02 3 9 6 6 3 3 4 - - - - - - 34 31 13.477 0.435

TWIN PORTS TESTING, INC. 48-23476-01 7 3 2 1 4 - - 1 - - - - - 18 11 5.369 0.488

U.S. INSPECTION SERVICES 34-06943-01 19 22 12 18 4 3 1 - - - - - - 79 60 16.195 0.270

VALLEY INDUSTRIAL X-RAY 04-29076-01 4 1 2 4 5 5 11 2 - - - - - 34 30 29.395 0.980

VALLEY INSPECTION SERVICE, INC. 37-28385-01 1 - 1 3 - 1 2 - - - - - - 8 7 5.170 0.771

WESTERN X-RAY COMPANY 35-19993-01 - 3 1 2 2 3 12 3 2 - - - - 28 28 37.125 1.326

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

WORLDWIDE INSPECTION SERVICES 52-25461-01 - 3 - 1 - - - - - - - - - 4 4 0.460 0.115

WOS TESTING COMPANY, INC. 48-26385-01 1 5 - 1 - - 1 1 - - - - - 9 8 3.640 0.455

X-R-I TESTING 21-05472-01 121 20 4 1 - - - 1 - - - - - 147 26 3.895 0.150

Total 111 794 835 464 474 309 181 372 100 32 9 1 - - 3,571 2,777 1,543.992 0.556
A-9

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1999

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)

URANIUM ENRICHMENT PLANTS - 21200

USEC - Paducah GDP-1 2,674 278 23 2 - - - - - - - - - 2,977 303 13.617 0.045

USEC - Portsmouth GDP-2 2,445 115 22 - - - - - - - - - - 2,582 137 6.507 0.047

Total 2 5,119 393 45 2 - - - - - - - - - 5,559 440 20.124 0.046FUEL FABRICATION FACILITIES - 21210

ABB COMBUSTION ENGINEERING INC. SNM-0033 31 55 26 29 15 7 54 14 - - - - - 231 200 143.136 0.716

BWX TECHNOLOGIES, INC. - NNFD SNM-0042 5 44 57 93 60 32 32 - - - - - - 323 318 152.089 0.478

FRAMATOME COGEMA FUELS SNM-1168 223 191 44 17 3 1 3 3 - - - - - 485 262 31.683 0.121

GENERAL ATOMICS SNM-0696 72 7 1 - - - - - - - - - - 80 8 0.453 0.057

GLOBAL NUCLEAR FUEL - AMERICAS SNM-1097 163 401 174 167 88 28 11 - - - - - - 1,032 869 189.777 0.218

NUCLEAR FUEL SERVICES, INC. SNM-0124 58 559 68 38 15 2 - - - - - - - 740 682 46.227 0.068

SIEMENS POWER CORP. NUCLEAR DIV. SNM-1227 128 312 133 70 48 30 16 - - - - - - 737 609 131.905 0.217

WESTINGHOUSE COMM NUCLEAR FUEL SNM-1107 39 189 92 70 36 39 89 30 2 - - - - 586 547 304.939 0.557

Total 8 719 1,758 595 484 265 139 205 47 2 - - - - 4,214 3,495 1,000.209 0.286

INDEPENDENT SPENT FUEL STORAGE INSTALLATION - 23200

DEPARTMENT OF ENERGY SNM-2508 4 9 1 - - - - - - - - - - 14 10 0.414 0.041

GENERAL ELECTRIC - MORRIS OPS SNM-2500 49 8 5 9 1 - - - - - - - - 72 23 4.758 0.207

Total 2 53 17 6 9 1 - - - - - - - - 86 33 5.172 0.157
A-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

This page intentionally left blank.
B-1

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES

1999

Appendix B
B-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713 APPENDIX B Annual Whole Body Doses at Licensed Nuclear Power Facilities CY 1999

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)

ARKANSAS 1,2 PWR

BEAVER VALLEY 1,2 PWR

BRAIDWOOD 1,2 PWR

BROWNS FERRY 1,2,3 BWR

BRUNSWICK 1,2 BWR

BYRON 1,2 PWR

CALLAWAY 1 PWR

CALVERT CLIFFS 1,2 PWR

CATAWBA 1,2 PWR

CLINTON BWR

COMANCHE PEAK 1,2 PWR

COOK 1,2 PWR

COOPER STATION BWR

CRYSTAL RIVER 3 PWR

DAVIS-BESSE PWR

DIABLO CANYON 1,2 PWR

DRESDEN 2,3 BWR

DUANE ARNOLD BWR

FARLEY 1,2 PWR

FERMI 2 BWR

FITZPATRICK BWR

FORT CALHOUN PWR

GINNA PWR

GRAND GULF BWR

HARRIS PWR

HATCH 1,2 BWR

HOPE CREEK 1 BWR

INDIAN POINT 2 PWR

INDIAN POINT 3 PWR

KEWAUNEE PWR

LASALLE 1,2 BWR

LIMERICK 1,2 BWR

MCGUIRE 1,2 PWR

MILLSTONE UNIT 2,3 PWR

MONTICELLO BWR

NINE MILE POINT 1,2 BWR

NORTH ANNA 1,2 PWR

7.00-

12.00

1,559

1,201

1,117

1,029

1,363

1,481

767

1,260

1,637

1,642

1,273

3,368

778

1,061

627

1,137

1,317

784

936

1,292

725

484

627

1,073

862

848

998

918

1,178

335

2,378

2,188

1,470

1,348

579

1,229

1,908

892

500

652

739

970

678

384

634

584

363

594

1,168

187

706

321

582

1,871

368

560

351

367

284

234

587

206

1,015

477

259

500

89

1,321

1,032

568

1,078

267

778

433

344

239

330

373

351

466

260

247

334

161

377

333

66

293

61

385

681

207

281

78

96

132

183

296

29

374

240

54

257

10

559

482

367

339

76

375

189

178

83

142

337

211

266

252

155

92

91

237

101

49

192

13

285

343

148

181

23

77

154

132

189

11

307

204

24

110

4

459

177

222

197

74

267

73

38

18

27

157

126

58

92

62

11

15

64

40

8

71

1

177

170

61

60

9

12

88

37

73

1

128

103

7

22

-

197

70

71

52

24

116

23

11

1

2

72

72

9

64

19

3

7

28

18

4

30

1

68

98

20

11

-

4

17

27

17

-

32

46

1

4

-

100

17

18

15

9

92

4

-

-

-

61

88

1

46

17

-

-

16

2

4

31

-

65

80

24

9

-

2

1

26

15

-

10

41

3

-

-

53

21

28

7

1

79

5

-

-

-

2

-

-

-

-

-

-

-

-

-

1

-

4

-

6

-

-

-

-

1

3

-

-

-

1

-

-

-

1

-

-

-

2

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

3,022

2,042

2,270

2,770

3,181

2,959

1,865

2,394

2,661

2,279

2,589

5,030

1,096

2,385

1,024

2,703

4,560

1,618

2,038

1,753

1,283

1,160

1,268

2,253

1,109

2,714

2,109

1,268

2,071

438

5,067

3,988

2,744

3,036

1,030

2,938

2,635

1,463

841

1,153

1,741

1,818

1,478

1,098

1,134

1,024

637

1,316

1,662

318

1,324

397

1,566

3,243

834

1,102

461

558

676

641

1,180

247

1,866

1,111

350

893

103

2,689

1,800

1,274

1,688

451

1,709

727

183.997

99.461

145.976

446.941

418.417

239.102

320.554

191.778

118.662

87.489

251.276

171.479

47.815

251.077

27.951

448.634

591.443

201.196

190.463

36.152

68.409

158.843

175.173

226.277

15.538

328.583

279.063

40.931

116.920

5.055

576.354

271.547

256.524

252.138

70.075

446.699

94.402
B-3

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX B

Annual Whole Body Doses at Licensed Nuclear Power Facilities

CY 1999

OCONEE 1, 2, 3 PWR

OYSTER CREEK BWR

PALISADES PWR

PALO VERDE 1, 2, 3 PWR

PEACH BOTTOM 2, 3 BWR

PERRY BWR

PILGRIM BWR

POINT BEACH 1, 2 PWR

PRAIRIE ISLAND 1, 2 PWR

QUAD CITIES 1, 2 BWR

RIVER BEND 1 BWR

ROBINSON 2 PWR

SALEM 1, 2 PWR

SAN ONOFRE 2, 3 PWR

SEABROOK PWR

SEQUOYAH 1, 2 PWR

SOUTH TEXAS 1, 2 PWR

ST. LUCIE 1, 2 PWR

SUMMER 1 PWR

SURRY 1, 2 PWR

SUSQUEHANNA 1, 2 BWR

THREE MILE ISLAND 1 PWR

TURKEY POINT 3, 4 PWR

VERMONT YANKEE BWR

VOGTLE 1,2 PWR

WASHINGTON NUCLEAR 2 BWR

WATERFORD 3 PWR

WATTS BAR 1 PWR

WOLF CREEK 1 PWR

PLANT NAME TYPE

TOTALS: 35 BWRs

TOTALS: 69 PWRs

TOTALS: 104 LWRs

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

1,821

548

591

1,353

1,367

529

541

758

517

926

797

685

1,077

2,835

804

1,172

1,326

1,017

698

1,752

1,228

619

888

976

1,049

1,117

982

1,362

755

26,252

48,615

74,867

838

322

398

838

838

805

499

459

323

571

540

404

514

670

991

777

622

585

445

557

863

740

486

311

608

558

476

647

379

16,000

23,663

39,663

513

110

255

260

351

457

251

230

115

163

309

234

260

302

232

376

356

306

226

286

365

274

299

276

462

240

198

224

208

6,937

11,126

18,063

181

27

153

135

278

351

208

171

88

135

285

131

220

267

98

165

214

143

115

108

269

120

97

200

211

171

107

95

161

4,880

6,084

10,964

33

6

78

24

97

113

151

63

15

61

94

30

111

143

18

23

79

52

35

31

134

26

30

52

60

44

40

9

53

2,021

1,973

3,994

1

1

26

11

33

22

73

24

1

49

43

8

50

56

-

5

44

12

6

6

88

10

7

14

12

9

8

-

9

922

647

1,569

2

-

29

7

33

10

39

15

-

21

54

-

45

39

-

-

13

9

-

7

68

1

-

1

6

-

4

-

2

705

436

1,141

-

-

-

-

-

-

1

-

-

-

2

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

17

7

24

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

2

2

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

3,389

1,014

1,530

2,628

2,997

2,287

1,763

1,720

1,059

1,926

2,124

1,492

2,277

4,312

2,143

2,518

2,654

2,124

1,525

2,747

3,015

1,790

1,807

1,830

2,408

2,139

1,815

2,337

1,567

57,734

92,553

150,287

1,568

466

939

1,275

1,630

1,758

1,222

962

542

1,000

1,327

807

1,200

1,477

1,339

1,346

1,328

1,107

827

995

1,787

1,171

919

854

1,359

1,022

833

975

812

31,482

43,938

75,420

202.025

41.664

218.451

146.328

319.307

326.014

344.270

194.489

72.496

200.556

343.858

123.952

317.545

353.765

105.728

164.569

259.770

176.878

120.172

137.891

431.397

154.936

127.567

175.795

228.942

155.109

123.198

98.946

147.704

6,434.430

7,231.281

13,665.711

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-
B-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

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

HADDAM NECK PWR

HUMBOLDT BAY BWR

LACROSSE BWR

MAINE YANKEE PWR

MILLSTONE UNIT 1 BWR

RANCHO SECO PWR

SAN ONOFRE 1 PWR

THREE MILE ISLAND 2 PWR

TROJAN PWR

YANKEE-ROWE PWR

ZION 1, 2 PWR

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

INDIAN POINT 1 PWR Reported with Indian Point 2

TOTAL REPORTING: 13 7,521 1,846 438 272 143 79 68 9 1 - - - - - 10,377 2,856 430.026

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

187

852

174

8

465

317

72

4,071

107

491

527

250

121

323

27

50

182

253

274

203

128

153

80

52

49

88

1

14

53

80

25

19

47

46

3

13

47

59

-

2

40

46

3

10

21

42

-

2

31

40

-

-

26

12

-

7

5

22

-

0

22

21

-

-

22

4

-

2

2

6

-

-

15

14

-

-

32

2

-

-

-

5

-

-

-

-

-

-

9

-

-

-

-

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

472

1,397

202

74

830

714

374

4,312

310

765

610

317

285

545

28

66

365

397

302

241

203

274

83

67

86.577

108.602

0.720

3.725

135.057

9.790

11.191

15.863

0.512

51.504

2.291

4.194

-

-

-

-

-

-

-

-

-

-

-

-

APPENDIX B

Annual Whole Body Doses at Licensed Nuclear Power Facilities

CY 1999
C-1

Thirty-Second Annual Report, 1999 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 - 1999

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-Second Annual Report, 1999

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

Docket 50-313, 50-368;

DPR-51; NPF-6

1st commercial

operation 12/74, 3/80

Type - PWRs

Capacity - 836, 858 MWe

BEAVER VALLEY 1, 2

Docket 50-334, 50-412;

DPR-66, NPF-73

1st commercial operation

10/76, 11/87

Type - PWRs

Capacity - 810, 820

BIG ROCK POINT1

Docket 50-155; DPR-6

1st commercial operation 3/63

Type - BWR

Capacity - (67) MWe

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

1975 588.0 76.5 147 21 0.14 0.04

1976 464.6 56.6 476 289 0.61 0.62

1977 610.376.8 601 256 0.430.42

1978 627.2 77.5 722 189 0.26 0.30

1979 397.0 55.3 1,321 369 0.28 0.93

1980 452.8 63.7 1,233 342 0.28 0.76

1981 1,104.7 68.32,225 1,102 0.50 1.00

1982 905.4 58.6 1,608 8030.50 0.89

1983915.0 54.7 2,109 1,397 0.66 1.53

1984 1,289.1 77.4 1,742 806 0.46 0.63

1985 1,192.373.6 1,262 286 0.230.24

1986 1,070.366.9 2,135 1,141 0.531.07

1987 1,366.1 88.9 1,123 382 0.34 0.28

1988 1,070.369.4 2,421 1,387 0.57 1.30

1989 1,066.372.0 2,063711 0.34 0.67

1990 1,351.9 84.2 2,493 762 0.31 0.56

1991 1,515.8 88.4 2,064 351 0.17 0.23

1992 1,352.1 77.4 3,114 876 0.28 0.65

19931,606.0 91.3 1,981 268 0.14 0.17

1994 1,662.8 93.6 1,361 172 0.13 0.10

1995 1,397.0 82.7 2,259 386 0.17 0.28

1996 1,596.0 89.5 1,441 2030.14 0.13

1997 1,621.9 95.9 1,195 119 0.10 0.07

1998 1,494.6 88.1 1,249 167 0.130.11

1999 1,477.386.9 1,463184 0.130.12

1977 355.6 57.0 331 878 0.26 2.47

1978 304.2 40.8 646 190 0.29 0.62

1979 221.0 40.0 704 132 0.19 0.60

1980 39.8 6.8 1,817 553 0.30 13.89

1981 573.4 73.6 1,237 229 0.19 0.40

1982 326.7 41.6 1,755 599 0.34 1.83

1983561.2 68.2 1,485 772 0.52 1.38

1984 576.7 71.8 1,393 504 0.36 0.87

1985 717.7 91.9 619 60 0.10 0.08

1986 581.370.7 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 85.31,675 348 0.21 0.27

1991 1,267.5 78.6 1,689 495 0.29 0.39

1992 1,441.9 89.1 1,414 289 0.20 0.20

1993 1,157.9 73.1 2,087 621 0.30 0.54

1994 1,514.6 88.6 487 44 0.09 0.03

1995 1,389.2 83.1 1,536 453 0.29 0.33

1996 1,269.0 76.5 1,688 449 0.27 0.35

1997 1,159.372.1 1,391 306 0.22 0.26

1998 523.1 33.5 700 59 0.08 0.11

1999 1,353.7 85.9 841 99 0.12 0.07

1969 48.1 165 136 0.82 2.83

1970 43.5 290 194 0.67 4.46

1971 44.4 260 184 0.71 4.14

1972 43.5 195 181 0.93 4.16

197350.9 241 285 1.18 5.60

1974 40.7 70.3281 276 0.98 6.78

1975 35.1 59.8 300 180 0.60 5.13

1976 29.5 50.1 488 289 0.59 9.80
C-3

Thirty-Second Annual Report, 1999 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

BIG ROCK POINT1

(continued)

BRAIDWOOD 1, 2

Docket 50-456, 50-457;

NPF-72, NPF-77

1st commercial operation

7/88, 10/88

Type - PWRs

Capacity - 1100, 1100 MWe

BROWNS FERRY 12

, 2, 3

Docket 50-259, 50-260,

50-296

DPR - 33, - 52, - 68

1st commercial operation

8/74, 3/75, 3/77

Type - BWRs

Capacity - (1065), 1118, 1118 MWe

1 Big Rock Point was shut down in 9/97 and is no longer included in the count of operating reactors. 2 Browns Ferry 1 remains in the count of operating reactors, but was placed on Administrative Hold in June of 1985.

1977 43.6 73.4 465 334 0.72 7.66

1978 48.5 77.9 285 175 0.61 3.61

1979 13.0 23.5 623 455 0.73 35.00

1980 48.9 79.0 599 354 0.59 7.24

1981 56.9 90.6 479 160 0.33 2.81

1982 43.6 70.8 521 328 0.63 7.52

198342.371.0 493263 0.536.22

1984 50.378.6 297 155 0.52 3.08

1985 43.8 73.5 435 291 0.67 6.64

1986 61.0 95.5 202 84 0.42 1.38

1987 45.371.0 251 222 0.88 4.90

1988 46.1 72.8 303 170 0.56 3.69

1989 50.2 79.0 418 177 0.42 3.53

1990 51.3 77.2 351 232 0.66 4.52

1991 59.1 85.2 435 226 0.52 3.82

1992 32.7 54.5 496 277 0.56 8.47

199351.2 79.4 419 152 0.36 2.97

1994 49.5 75.3310 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 0.0 866 144 0.17 ---

1999 0.0 0.0 285 87 0.31 ---

1989 1,381.8 75.4 1,460 296 0.20 0.21

1990 1,740.2 84.1 1,081 186 0.17 0.11

1991 1,377.2 68.9 1,641 550 0.34 0.40

1992 1,885.9 89.0 1,059 228 0.22 0.12

19931,899.3 86.9 1,043 273 0.26 0.14

1994 1,666.1 77.2 1,237 298 0.24 0.18

1995 1,914.7 85.4 1,134 236 0.21 0.12

1996 1,854.9 82.1 1,356 334 0.25 0.18

1997 1,863.3 85.4 1,693 321 0.19 0.17

1998 1,979.1 88.9 1,869 259 0.14 0.13

1999 2,161.6 95.8 1,153146 0.130.07

1975 161.7 17.8 2,743347 0.132.15

1976 337.6 26.9 2,530 232 0.09 0.69

1977 1,327.5 73.7 1,985 876 0.44 0.66

1978 1,992.1 73.5 2,479 1,776 0.72 0.89

1979 2,393.0 79.1 2,869 1,593 0.56 0.67

1980 2,182.1 73.6 2,838 1,768 0.62 0.81

1981 2,132.9 69.5 3,497 2,398 0.69 1.12

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

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

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

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

1989 0.0 0.0 2,707 657 0.24 ---

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

1991 445.0 17.7 1,831 356 0.19 0.80

1992 979.9 32.2 2,670 519 0.19 0.53

1993675.1 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 4130.16 0.35

1996 1,972.8 93.0 1,904 389 0.20 0.20

1997 1,928.8 90.2 2,268 522 0.230.27
C-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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

(continued)

BRUNSWICK 1,2

Docket 50-324, 50-325;

DPR-62, -71

1st commercial operation

3/77, 11/75

Type - BWRs

Capacity - 820, 811 MWe

BYRON 1, 2

Docket 50-454, 50-455;

NPF-37, NPF-66

1st commercial operation

9/85, 8/87

Type - PWRS

Capacity - 1105, 1105 MWe

CALLAWAY 1

Docket 50-483; NPF-30

1st commercial operation 12/84

Type - PWR

Capacity - 1125 MWe

1998 1,961.9 87.7 1,612 368 0.23 0.19

1999 2,091.0 85.1 1,741 447 0.26 0.21

1976 297.2 56.0 1,265 326 0.26 1.10

1977 291.1 55.7 1,512 1,120 0.74 3.85

1978 1,173.1 83.7 1,458 1,004 0.69 0.86

1979 810.0 60.1 2,891 2,602 0.90 3.21

1980 687.2 52.2 3,788 3,870 1.02 5.63

1981 925.2 56.9 3,854 2,638 0.68 2.85

1982 540.350.3 4,957 3,792 0.76 7.02

1983 636.7 44.3 5,602 3,475 0.62 5.46

1984 761.351.5 5,046 3,260 0.65 4.28

1985 822.2 58.4 4,057 2,804 0.69 3.41

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

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

1988 990.8 70.1 2,648 1,747 0.66 1.76

1989 990.9 65.8 3,844 1,786 0.46 1.80

1990 991.6 67.8 3,182 1,548 0.49 1.56

1991 952.8 64.5 2,586 778 0.30 0.82

1992 375.9 27.9 2,690 623 0.23 1.66

1993 470.0 33.8 2,921 872 0.30 1.86

1994 1,268.4 83.0 3,049 999 0.70 0.79

1995 1,411.7 92.9 2,657 6830.26 0.48

1996 1,261.1 85.9 2,784 716 0.26 0.57

1997 1,474.0 94.1 2,212 411 0.19 0.28

1998 1,521.0 94.32,005 396 0.20 0.26

1999 1,494.7 92.8 1,818 418 0.230.28

1986 894.5 88.6 1,081 76 0.07 0.08

1987 650.9 70.9 1,826 769 0.42 1.18

1988 1,534.7 86.3 1,222 459 0.38 0.30

1989 1,812.6 90.2 1,109 172 0.16 0.09

1990 1,567.378.8 1,396 434 0.31 0.28

1991 1,816.389.9 1,077 268 0.25 0.15

1992 1,888.4 90.1 1,021 199 0.19 0.11

1993 1,785.6 83.5 1,370 432 0.32 0.24

1994 1,953.3 90.7 962 280 0.29 0.14

1995 1,900.6 85.5 1,107 306 0.28 0.16

1996 1,758.4 79.31,610 455 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 92.31,478 239 0.16 0.12

1985 967.4 90.0 964 36 0.04 0.04

1986 865.2 81.31,052 225 0.21 0.26

1987 759.0 71.1 1,082 393 0.36 0.52

1988 1,069.2 93.4 353 27 0.08 0.03

1989 1,000.385.4 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

19931,002.9 86.4 1,126 225 0.20 0.22

1994 1,196.4 100.0 191 14 0.07 0.01

1995 989.6 84.7 1,062 187 0.18 0.19

1996 1,066.0 90.5 980 248 0.25 0.23

1997 1,022.2 100.0 248 12 0.05 0.01

1998 972.2 91.3929 201 0.22 0.21

1999 981.388.7 1,098 321 0.29 0.33

2 Browns Ferry 1 remains in the count of operating reactors, but was placed on Administrative Hold in June of 1985.
C-5

Thirty-Second Annual Report, 1999 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

CALVERT CLIFFS 1, 2

Docket 50-317, 50-318;

DPR-53, -69

1st commercial operation

5/75, 4/77

Type - PWRs

Capacity - 835, 840 MWe

CATAWBA 1, 2

Docket 50-413, 50-414;

NPF-35, NPF-52

1st commercial operation

6/85, 8/86

Type - PWR

Capacity - 1129, 1129 MWe

CLINTON

Docket 50-461; NPF-62

1st commercial operation 11/87

Type - BWR

Capacity - 930 MWe

COMANCHE PEAK 1, 2

Docket 50-445; NPF-87

1st commercial operation

8/90, 8/93

Type - PWR

Capacity - 1150, 1150 MWe

1976 753.4 95.2 507 74 0.15 0.10

1977 583.0 72.1 2,265 547 0.24 0.94

1978 1,188.5 75.8 1,391 500 0.36 0.42

1979 1,161.0 74.0 1,428 805 0.56 0.69

1980 1,309.9 84.1 1,496 677 0.45 0.52

1981 1,379.7 83.1 1,555 607 0.39 0.44

1982 1,238.3 73.7 1,805 1,057 0.59 0.85

19831,397.2 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 0.430.58

1986 1,530.0 87.2 1,296 347 0.27 0.23

1987 1,207.3 71.8 1,384 412 0.30 0.34

1988 1,397.7 81.0 1,296 291 0.22 0.21

1989 333.6 20.1 1,786 346 0.19 1.04

1990 161.1 11.0 2,019 304 0.15 1.89

1991 1,085.0 64.7 1,974 132 0.07 0.12

1992 1,271.2 73.9 1,979 330 0.17 0.26

19931,462.1 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 1,203235 0.20 0.15

1996 1,438.5 82.4 1,167 239 0.20 0.17

1997 1,499.6 89.1 1,091 229 0.21 0.15

1998 1,523.1 89.3 1,042 187 0.18 0.12

1999 1,521.4 90.1 1,134 192 0.17 0.13

1986 638.9 49.9 1,724 286 0.17 0.45

1987 1,651.2 75.9 1,865 449 0.24 0.27

1988 1,675.2 77.2 2,009 556 0.28 0.33

1989 1,733.6 79.5 1,660 334 0.20 0.19

1990 1,616.370.8 2,174 809 0.37 0.50

1991 1,691.5 74.6 1,871 462 0.25 0.27

1992 1,962.8 83.9 1,515 414 0.27 0.21

19931,896.1 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 85.31,892 462 0.24 0.23

1996 1,879.1 80.5 1,588 302 0.19 0.16

1997 2,028.2 89.31,561 266 0.17 0.13

1998 2,006.4 89.6 1,123162 0.14 0.08

1999 2,046.7 90.2 1,024 119 0.12 0.06

1988 701.384.2 769 130 0.17 0.19

1989 348.3 48.5 1,196 372 0.31 1.07

1990 435.8 55.1 1,390 553 0.40 1.27

1991 722.7 80.8 1,010 233 0.23 0.32

1992 589.7 68.6 1,195 431 0.36 0.73

1993701.5 79.6 1,253 498 0.40 0.71

1994 883.3 94.8 409 63 0.15 0.07

1995 731.1 83.0 1,182 316 0.27 0.43

1996 634.7 66.7 1,154 350 0.30 0.55

1997 0.0 0.0 738 172 0.23 ---

1998 0.0 0.0 866 177 0.17 ---

1999 537.0 63.5 637 87 0.14 0.16

1991 644.4 82.2 985 148 0.15 0.23

1992 830.8 84.0 1,128 188 0.17 0.23

1993853.8 81.2 945 109 0.12 0.13

1994 1,750.0 93.7 970 90 0.09 0.05

1995 2,022.6 92.5 951 179 0.19 0.09

1996 1,804.8 81.4 1,462 288 0.20 0.16

1997 2,002.4 93.4 870 146 0.17 0.07

1998 2,037.8 94.9 967 232 0.24 0.11

1999 1,981.5 90.9 1,316 251 0.19 0.13
C-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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

COOK 1, 2

Docket 5-315; DPR-58, -74

1st commercial operation

8/75, 7/78

Type - PWRs

Capacity - 1000, 1060 MWe

COOPER STATION

Docket 50-298; DPR-46

1st commercial operation

7/74

Type - BWR

Capacity - 764 MWe

CRYSTAL RIVER 3

Docket 50-302; DPR-72

1st commercial operation 3/77

Type - PWR

Capacity - 818 MWe

1976 807.4 83.1 395 116 0.29 0.14

1977 573.0 76.1 802 300 0.37 0.52

1978 744.8 73.6 778 336 0.43 0.45

1979 1,373.0 65.3 1,445 718 0.50 0.52

1980 1,552.4 74.1 1,345 493 0.37 0.32

1981 1,557.373.4 1,341 656 0.49 0.42

1982 1,461.6 69.8 1,527 699 0.46 0.48

19831,456.5 71.2 1,418 658 0.46 0.45

1984 1,526.0 75.31,559 762 0.49 0.50

1985 925.4 47.6 1,984 945 0.48 1.02

1986 1,307.1 73.4 1,774 745 0.42 0.57

1987 1,199.5 70.2 1,696 666 0.39 0.56

1988 1,160.4 63.5 2,266 867 0.38 0.75

1989 1,433.1 72.8 1,575 493 0.31 0.34

1990 1,318.5 67.9 1,851 580 0.31 0.44

1991 1,837.4 90.2 815 69 0.08 0.04

1992 760.9 50.8 1,954 492 0.25 0.65

19931,927.7 98.5 587 44 0.07 0.02

1994 1,105.2 65.2 1,748 479 0.27 0.43

1995 1,656.0 82.1 1,310 203 0.15 0.12

1996 1,938.9 92.7 1,114 214 0.19 0.11

1997 1,189.7 59.7 1,864 550 0.30 0.46

1998 0.0 0.0 1,155 105 0.09 ---

1999 0.0 0.0 1,662 171 0.10 ---

1975 456.4 83.6 579 117 0.20 0.26

1976 433.3 75.5 763 350 0.46 0.81

1977 538.2 86.2 315 198 0.63 0.37

1978 576.0 91.0 297 158 0.530.27

1979 591.0 87.6 426 221 0.52 0.37

1980 448.371.2 785 859 1.09 1.92

1981 457.1 71.2 935 579 0.62 1.27

1982 622.384.6 743542 0.730.87

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 127.321.5 1,980 1,333 0.67 10.47

1986 480.0 74.7 895 320 0.36 0.67

1987 652.396.2 549 103 0.19 0.16

1988 493.4 67.9 942 251 0.27 0.51

1989 564.376.2 1,202 343 0.29 0.61

1990 602.0 79.4 1,174 379 0.32 0.63

1991 566.378.8 1,099 405 0.37 0.72

1992 731.0 96.4 463 84 0.18 0.11

1993436.1 58.8 1,130 391 0.35 0.90

1994 262.2 35.1 333 79 0.24 0.30

1995 486.5 66.8 1,095 228 0.21 0.47

1996 742.1 97.9 468 48 0.10 0.06

1997 622.8 84.4 1,125 174 0.16 0.28

1998 555.9 75.9 977 182 0.19 0.33

1999 743.2 98.1 318 48 0.15 0.06

1978 311.5 41.4 643 321 0.50 1.03

1979 453.0 58.9 1,150 495 0.43 1.09

1980 404.1 53.2 1,053 625 0.59 1.55

1981 490.4 62.2 1,120 408 0.36 0.83

1982 589.8 76.0 780 177 0.230.30

1983452.1 58.8 1,720 552 0.32 1.22

1984 774.2 94.5 549 49 0.09 0.06

1985 344.2 47.6 1,976 689 0.35 2.00

1986 319.5 41.8 1,057 472 0.45 1.48

1987 436.0 60.9 1,384 488 0.35 1.12

1988 690.2 84.0 569 64 0.11 0.09
C-7

Thirty-Second Annual Report, 1999 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

CRYSTAL RIVER 3

(continued)

DAVIS-BESSE 1

Docket 50-346; NPF-3

1st commercial operation 7/78

Type - PWR

Capacity - 873 MWe

DIABLO CANYON 1, 2

Docket 50-275, 50-323;

DPR-80, DPR-82

1st commercial operation

5/85, 3/86

Type - PWRs

Capacity - 1073, 1087 MWe

DRESDEN 13

 , 2, 3

Docket 50-010, 50-237, 50-249;

DPR-2, -19, -25

1st commercial operation 7/60,

6/70, 11/71

Type - BWRs

Capacity - (197), 772, 773 MWe

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.

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

1993722.4 85.0 683 60 0.09 0.08

1994 711.9 84.31,079 228 0.21 0.32

1995 866.3100.0 209 8 0.04 0.01

1996 290.8 37.7 1,192 353 0.30 1.21

1997 0.0 0.0 973179 0.18 ---

1998 739.9 90.3 313 19 0.06 0.03

1999 727.5 87.8 1,324 251 0.19 0.35

1978 326.4 48.7 421 48 0.11 0.15

1979 381.0 67.0 304 30 0.10 0.08

1980 256.4 36.2 1,283 154 0.12 0.60

1981 531.4 67.4 578 58 0.10 0.11

1982 390.8 51.5 1,350 164 0.12 0.42

1983592.1 73.0 718 80 0.11 0.14

1984 518.5 62.5 1,088 177 0.16 0.34

1985 238.3 31.2 718 71 0.10 0.30

1986 3.3 1.3 981 124 0.13 37.58

1987 618.0 89.6 625 47 0.08 0.08

1988 144.1 27.1 1,183307 0.26 2.13

1989 880.0 98.6 404 38 0.09 0.04

1990 500.0 56.7 1,377 489 0.36 0.98

1991 703.6 81.8 1,000 216 0.22 0.31

1992 915.2 100.0 287 19 0.07 0.02

1993729.5 83.4 1,244 348 0.28 0.48

1994 768.4 88.0 861 144 0.17 0.19

1995 920.4 100.0 256 7 0.030.01

1996 775.8 85.3949 167 0.18 0.22

1997 820.0 94.0 21310 0.05 0.01

1998 699.8 83.2 980 155 0.16 0.22

1999 841.395.6 397 28 0.07 0.03

1986 641.5 80.6 1,260 304 0.24 0.47

1987 1,688.6 83.0 1,170 336 0.29 0.20

1988 1,386.1 67.6 1,826 877 0.48 0.63

1989 1,899.0 87.5 1,646 465 0.28 0.24

1990 1,952.6 91.0 1,441 323 0.22 0.17

1991 1,809.6 83.8 2,040 546 0.27 0.30

1992 1,995.7 90.9 1,850 459 0.25 0.23

19932,008.6 91.4 1,508 281 0.19 0.14

1994 1,832.6 83.3 2,317 590 0.26 0.32

1995 1,950.390.0 1,615 286 0.18 0.15

1996 2,003.6 90.7 1,462 176 0.12 0.09

1997 1,948.7 92.7 1,331 219 0.17 0.11

1998 1,955.1 92.8 1,313 173 0.13 0.09

1999 1,902.8 90.1 1,566 449 0.29 0.24

1969 99.7 286 2.87

1970 163.1 143 0.88

1971 394.5 715 1.81

1972 1,243.7 728 0.59

19731,112.2 1,341 939 0.70 0.84

1974 842.5 54.9 1,594 1,662 1.04 1.97

1975 708.1 54.6 2,310 3,423 1.48 4.83

1976 1,127.2 80.8 1,746 1,680 0.96 1.49
C-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

DRESDEN 13

 , 2, 3

(continued)

DUANE ARNOLD

Docket 50-331; DPR-49

1st commercial operation 2/75

Type - BWR

Capacity - 520 MWe

FARLEY 1, 2

Docket 50-348, 50-364;

NPF-2, -8

1st commercial operation

12/77, 7/81

Type - PWR

Capacity - 847, 852 MWe

1977 1,132.9 77.0 1,862 1,694 0.91 1.50

1978 1,242.2 79.5 1,946 1,529 0.79 1.23

1979 1,013.0 74.7 2,407 1,800 0.75 1.78

1980 1,074.4 55.0 2,717 2,105 0.77 1.96

1981 1,035.7 51.5 2,331 2,802 1.20 2.71

1982 1,085.377.9 2,572 2,923 1.14 2.69

1983 913.6 65.6 2,854 3,582 1.26 3.92

1984 789.8 55.32,261 1,774 0.78 2.25

1985 903.0 64.5 2,817 1,686 0.60 1.87

1986 740.5 52.6 3,111 2,668 0.86 3.60

1987 933.9 74.0 2,052 1,145 0.56 1.23

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

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

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

1991 675.2 60.7 2,044 1,005 0.49 1.49

1992 872.4 75.4 1,812 619 0.34 0.71

1993960.1 68.5 2,751 1,655 0.60 1.72

1994 690.2 51.7 2,336 833 0.36 1.21

1995 643.1 49.8 2,482 875 0.35 1.36

1996 612.6 47.7 1,788 456 0.26 0.74

1997 1,096.2 79.5 2,747 467 0.17 0.43

1998 1,354.7 90.6 2,311 427 0.18 0.32

1999 1,410.9 92.5 3,243 591 0.18 0.42

1976 305.2 78.0 350 105 0.30 0.34

1977 353.6 78.9 538 299 0.56 0.85

1978 149.2 33.2 1,112 974 0.88 6.53

1979 352.0 78.0 757 275 0.36 0.78

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

1983283.0 62.9 1,468 1,135 0.77 4.01

1984 329.4 72.9 611 189 0.31 0.57

1985 236.2 53.8 1,414 1,112 0.79 4.71

1986 365.5 82.0 476 187 0.39 0.51

1987 308.4 64.7 1,094 667 0.61 2.16

1988 386.5 75.2 1,136 614 0.54 1.59

1989 388.5 79.0 425 194 0.46 0.50

1990 367.4 75.8 1,460 861 0.59 2.34

1991 503.7 94.5 336 202 0.60 0.40

1992 416.5 81.9 1,043502 0.48 1.21

1993393.4 79.5 1,043 407 0.39 1.03

1994 498.6 94.0 493120 0.24 0.24

1995 452.5 83.8 1,129 357 0.32 0.79

1996 476.8 90.7 1,093270 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 84.3834 201 0.24 0.48

1978 713.8 86.5 527 108 0.20 0.15

1979 211.0 28.6 1,227 6430.52 3.05

1980 557.3 69.3 1,330 435 0.33 0.78

1981 310.2 41.4 1,331 512 0.38 1.65

1982 1,271.5 79.2 1,453 484 0.33 0.38

19831,356.5 83.0 1,938 1,021 0.53 0.75

1984 1,447.0 86.6 2,046 902 0.44 0.62

1985 1,368.2 81.1 2,551 799 0.31 0.58

1986 1,409.4 83.8 2,314 858 0.37 0.61

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.
C-9

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

FARLEY 1, 2

(continued)

FERMI 2

Docket 50-341; NPF-43

1st commercial operation 1/88

Type - BWR

Capacity - 1080 MWe

FITZPATRICK

Docket 50-333; DPR-59

1st commercial operation 7/75

Type - BWR

Capacity - 813 MWe

FORT CALHOUN

Docket 50-285; DPR-40

1st commercial operation 6/74

Type - PWR

Capacity - 478 MWe

1987 1,369.7 84.7 1,871 598 0.32 0.44

1988 1,567.7 92.3 1,840 552 0.30 0.35

1989 1,402.9 84.6 2,206 749 0.34 0.53

1990 1,464.0 86.7 1,700 457 0.27 0.31

1991 1,464.0 88.1 1,645 648 0.39 0.44

1992 1,331.7 81.8 2,018 805 0.40 0.60

1993 1,455.5 88.3 1,284 333 0.26 0.23

1994 1,587.2 93.0 1,035 250 0.24 0.16

1995 1,311.2 83.8 1,574 460 0.29 0.35

1996 1,549.2 90.9 1,150 232 0.20 0.15

1997 1,449.7 89.0 1,105 278 0.25 0.19

1998 1,313.9 80.9 1,380 432 0.31 0.33

1999 1,436.0 91.4 1,102 190 0.17 0.13

1989 624.0 68.5 1,270 255 0.20 0.41

1990 848.2 84.7 462 830.18 0.10

1991 739.0 77.0 1,223 228 0.19 0.31

1992 874.381.3 1,213245 0.20 0.28

1993984.3 92.9 360 35 0.10 0.04

1994 0.0 2.2 1,130 213 0.19 ---

1995 618.386.9 390 28 0.07 0.05

1996 577.5 69.1 1,402 157 0.11 0.27

1997 637.0 66.6 623 49 0.08 0.08

1998 815.8 79.9 1,362 208 0.15 0.25

1999 1,082.7 99.5 461 36 0.08 0.03

1976 489.0 71.6 600 202 0.34 0.41

1977 460.5 68.4 1,380 1,080 0.78 2.35

1978 497.0 72.1 904 909 1.01 1.83

1979 349.0 50.8 850 859 1.01 2.46

1980 509.5 70.32,056 2,040 0.99 4.00

1981 562.9 74.7 2,490 1,425 0.57 2.53

1982 583.6 75.0 2,322 1,190 0.51 2.04

1983546.2 70.6 1,715 1,090 0.64 2.00

1984 576.2 76.8 1,610 971 0.60 1.69

1985 492.363.7 1,845 1,051 0.57 2.13

1986 711.2 90.6 1,185 411 0.35 0.58

1987 496.2 70.31,578 940 0.60 1.89

1988 514.0 69.0 1,553786 0.51 1.53

1989 727.5 92.31,027 377 0.37 0.52

1990 543.8 72.6 1,536 884 0.58 1.63

1991 399.7 53.4 1,269 333 0.26 0.83

1992 0.0 0.0 2,374 674 0.28 ---

1993559.6 81.7 1,427 232 0.16 0.41

1994 588.4 83.2 1,595 322 0.20 0.55

1995 569.8 74.5 1,249 327 0.26 0.57

1996 623.3 83.1 1,384 357 0.26 0.57

1997 756.2 95.9 662 91 0.14 0.12

1998 562.8 78.0 1,781 358 0.20 0.64

1999 749.7 95.5 558 68 0.12 0.09

1975 252.367.4 469 294 0.631.17

1976 265.9 69.5 516 313 0.61 1.18

1977 351.8 79.4 535 297 0.56 0.84

1978 342.3 75.1 596 410 0.69 1.20

1979 440.0 95.7 451 126 0.28 0.29

1980 242.360.4 891 668 0.75 2.76

1981 260.9 72.3822 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 913563 0.62 2.02

1985 367.0 73.7 982 373 0.38 1.02
C-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

FORT CALHOUN

(continued)

GINNA

Docket 50-244; DPR-18

1st commercial operation 7/70

Type - PWR

Capacity - 480 MWe

GRAND GULF

Docket 50-416; NPF-29

1st commercial operation 7/85

Type - BWR

Capacity - 1204 MWe

1986 431.8 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

1993369.7 80.8 713 157 0.22 0.42

1994 492.8 99.6 211 230.11 0.05

1995 402.8 83.2 627 139 0.22 0.35

1996 374.9 79.5 740 226 0.31 0.60

1997 435.9 93.6 258 41 0.16 0.09

1998 387.7 82.5 788 224 0.28 0.58

1999 409.2 89.2 676 159 0.24 0.39

1971 327.8 340 430 1.26 1.31

1972 293.6 677 1,032 1.52 3.51

1973409.5 319 224 0.70 0.55

1974 253.7 62.4 884 1,225 1.39 4.83

1975 365.2 76.7 685 538 0.79 1.47

1976 248.8 58.2 758 636 0.84 2.56

1977 365.6 85.5 530 401 0.76 1.10

1978 386.5 80.6 657 450 0.68 1.16

1979 355.0 72.8 878 592 0.67 1.67

1980 370.5 76.0 1,073 708 0.66 1.91

1981 399.0 82.1 925 655 0.71 1.64

1982 289.0 58.8 1,117 1,140 1.02 3.94

1983365.0 74.6 969 855 0.88 2.34

1984 378.1 77.2 713 395 0.55 1.04

1985 436.7 87.9 845 426 0.50 0.98

1986 433.3 87.4 901 357 0.40 0.82

1987 459.0 91.5 773344 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 414.384.4 991 347 0.35 0.84

1991 418.6 86.7 947 328 0.35 0.78

1992 417.6 86.9 832 261 0.31 0.63

1993419.6 86.3 856 193 0.230.46

1994 405.3 83.2 679 138 0.20 0.34

1995 437.0 89.6 738 136 0.18 0.31

1996 347.9 71.1 976 168 0.17 0.48

1997 444.6 91.8 533 81 0.15 0.18

1998 491.8 100.0 161 15 0.09 0.03

1999 403.4 85.6 641 175 0.27 0.43

1986 494.7 60.9 1,486 436 0.29 0.88

1987 920.7 82.2 1,358 420 0.31 0.46

1988 1,136.6 96.7 692 147 0.21 0.13

1989 932.6 80.0 1,972 498 0.25 0.53

1990 883.5 78.9 1,765 482 0.27 0.55

1991 1,085.2 94.0 699 94 0.130.09

1992 969.0 83.7 2,032 484 0.24 0.50

1993 936.4 81.5 1,807 332 0.18 0.35

1994 1,143.2 96.6 455 56 0.12 0.05

1995 952.9 80.4 1,589 342 0.22 0.36

1996 1,096.2 88.7 1,564 357 0.23 0.33

1997 1,234.9 100.0 514 105 0.20 0.09

1998 1,049.2 88.9 1,410 304 0.22 0.29

1999 962.1 81.31,180 226 0.19 0.23
C-11

Thirty-Second Annual Report, 1999 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

HADDAM NECK4

Docket 50-213; DPR-61

1st commercial operation 1/68

Type - PWR

Capacity - (560) MWe

HARRIS 1

Docket 50-400; NPF-63

1st commercial operation 5/87

Type - PWR

Capacity - 860 MWe

HATCH 1, 2

Docket 50-321, 50-366;

DPR-57; NPF-05

1st commercial operation

12/75, 9/79

Type - BWRs

Capacity - 838, 855 MWe

4 Haddam Neck was shut down 12/4/96 and is no longer in the count of operating reactors.

1969 438.5 138 106 0.77 0.24

1970 424.7 734 689 0.94 1.62

1971 502.2 289 342 1.18 0.68

1972 515.6 355 325 0.91 0.63

1973293.1 951 697 0.732.38

1974 521.4 91.2 550 201 0.37 0.39

1975 494.389.9 795 703 0.88 1.42

1976 482.9 82.5 644 449 0.70 0.93

1977 480.7 83.9 894 641 0.72 1.33

1978 563.4 98.6 216 117 0.54 0.21

1979 493.0 87.5 1,226 1,162 0.95 2.36

1980 426.8 75.0 1,860 1,353 0.73 3.17

1981 487.5 84.31,554 1,036 0.67 2.13

1982 543.9 93.4 559 126 0.23 0.23

1983453.7 77.8 1,645 1,384 0.84 3.05

1984 404.0 71.7 1,430 1,216 0.85 3.01

1985 556.1 98.4 384 101 0.26 0.18

1986 294.8 53.6 1,945 1,567 0.81 5.32

1987 304.6 54.0 1,763 750 0.43 2.46

1988 397.4 70.3 735 237 0.32 0.60

1989 356.4 67.2 1,455 596 0.41 1.67

1990 142.7 32.2 979 421 0.43 2.95

1991 444.4 76.4 1,168 590 0.51 1.33

1992 465.2 80.1 797 202 0.25 0.43

1993448.6 81.6 1,004 408 0.41 0.91

1994 455.6 77.7 463135 0.29 0.30

1995 439.4 77.7 1,006 442 0.44 1.01

1996 331.8 55.7 673 175 0.26 0.53

1997 -1.30.0 219 11 0.05 ---

1998 0.0 0.0 1,249 167 0.13---

1999 0.0 0.0 545 109 0.20 ---

1988 652.9 75.0 721 169 0.230.26

1989 690.6 79.5 929 156 0.17 0.23

1990 776.4 89.6 45385 0.19 0.11

1991 724.8 81.5 872 226 0.26 0.31

1992 661.8 74.9 930 213 0.23 0.32

1993913.0 99.7 327 31 0.09 0.03

1994 740.8 82.7 1,089 222 0.20 0.30

1995 731.1 83.8 1,068 174 0.16 0.24

1996 860.6 95.4 444 17 0.04 0.02

1997 673.6 80.4 1,131 149 0.13 0.22

1998 766.2 90.4 931 133 0.14 0.17

1999 827.0 97.9 247 16 0.06 0.02

1976 496.3 83.8 630 134 0.21 0.27

1977 446.8 66.31,303465 0.36 1.04

1978 513.0 72.8 1,304 248 0.19 0.48

1979 401.0 54.6 2,131 582 0.27 1.45

1980 1,008.7 70.9 1,930 449 0.23 0.45

1981 870.9 64.32,899 1,337 0.46 1.54

1982 768.0 56.6 3,418 1,460 0.43 1.90

1983 934.7 68.6 3,428 1,299 0.38 1.39

1984 658.6 47.3 4,110 2,218 0.54 3.37

1985 1,211.0 79.6 2,841 818 0.29 0.68

1986 872.0 64.8 3,486 1,497 0.43 1.72

1987 1,295.4 89.7 2,202 816 0.37 0.63

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

1989 1,271.1 87.1 1,350 556 0.41 0.44

1990 1,268.0 83.5 2,902 1,455 0.50 1.15
C-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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

HATCH 1, 2

(continued)

HOPE CREEK 1

Docket 50-354; NPF-57

1st commercial operation 12/86

Type - BWR

Capacity - 1031 MWe

HUMBOLDT BAY5

Docket 50-133; DPR-7

1st commercial operation 8/63

Type - BWR

Capacity - (63) MWe

INDIAN POINT 16

, 2, 37

Docket 50-3, 50-247, 50-286;

DPR-5, -26, -64

1st commercial operation 10/62,

8/74, 8/76

Type - PWR

Capacity - (265), 951, 965 MWe

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

1992 1,293.8 88.6 1,615 550 0.34 0.43

19931,189.6 85.5 1,733 669 0.39 0.56

1994 1,289.0 87.1 2,243864 0.39 0.67

1995 1,376.3 90.6 1,458 488 0.33 0.35

1996 1,519.6 94.0 1,495 441 0.29 0.29

1997 1,374.7 88.1 1,945 722 0.37 0.53

1998 1,458.4 91.7 1,610 320 0.20 0.22

1999 1,487.4 90.0 1,866 329 0.18 0.22

1987 869.2 86.4 589 117 0.20 0.13

1988 832.7 80.7 1,734 287 0.17 0.34

1989 791.1 77.8 1,873465 0.25 0.59

1990 966.4 91.6 1,394 196 0.14 0.20

1991 882.5 84.2 1,700 373 0.22 0.42

1992 841.9 80.8 1,694 436 0.26 0.52

19931,049.2 97.8 688 98 0.14 0.09

1994 852.0 81.2 1,779 326 0.18 0.38

1995 844.5 79.8 1,571 196 0.12 0.23

1996 806.9 77.4 1,069 158 0.15 0.20

1997 731.8 77.8 1,747 350 0.20 0.48

1998 993.2 98.0 620 55 0.09 0.06

1999 879.1 86.7 1,111 279 0.25 0.32

1969 44.6 125 164 1.31 3.68

1970 49.3115 209 1.82 4.24

1971 39.6 140 292 2.09 7.37

1972 43.1 127 253 1.99 5.87

197350.1 210 266 1.27 5.31

1974 43.4 83.8 296 318 1.07 7.33

1975 45.3 83.9 265 339 1.28 7.48

1976 23.5 46.4 523 683 1.31 29.06

1977 0.0 0.0 1,0631,905 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 ---

19830.0 0.0 84 17 0.20 ---

19930.0 0.0 24 1 0.04 ---

1994 0.0 0.0 21 1 0.05 ---

1995 0.0 0.0 42 2 0.05 ---

1996 0.0 0.0 66 5 0.08 ---

1997 0.0 0.0 105 16 0.15 ---

1998 0.0 0.0 929 201 0.22 ---

1999 0.0 0.0 28 1 0.04 ---

1969 206.2 298 1.45

1970 43.3 1,639 37.85

1971 154.0 768 4.99

1972 142.3967 6.80

19730.0 2,998 5,262 1.76 ---

1974 556.1 59.4 1,019 910 0.89 1.64

1975 584.4 74.8 891 705 0.79 1.21

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.

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.

7 Indian Point 3 was purchased by a different utility and now reports separately.
C-13

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

INDIAN POINT 16

, 2, 37

(continued)

INDIAN POINT 16

, 2

INDIAN POINT 2

Docket 50-247; DPR-26

1st commercial operation 8/74

Type - PWR

Capacity - 951 MWe

INDIAN POINT 37

Docket 50-286; DPR-64

1st commercial operation 8/76

Type - PWR

Capacity - 965 MWe

KEWAUNEE

Docket 50-305; DPR-43

1st commercial operation 6/74

Type - PWR

Capacity - 511 MWe

1976 273.9 34.8 1,590 1,950 1.23 7.12

1977 1,278.375.3 1,391 1,070 0.77 0.84

1978 1,172.367.8 1,909 2,006 1.05 1.71

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

1983702.6 84.0 1,057 486 0.46 0.69

1984 416.7 51.9 2,919 2,644 0.91 6.35

1985 791.4 95.7 708 192 0.27 0.24

1986 457.5 56.2 1,926 1,250 0.65 2.73

1987 611.4 73.4 1,980 1,217 0.61 1.99

1988 719.386.9 890 235 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

1993702.1 75.7 1,514 675 0.45 0.96

1994 903.8 100.0 381 48 0.13 0.05

1995 582.4 70.8 1,690 548 0.32 0.94

1996 927.8 94.8 388 54 0.14 0.06

1997 360.6 45.1 1,340 367 0.27 1.02

1998 282.8 31.5 1,154 290 0.25 1.03

1999 831.8 88.2 350 41 0.12 0.05

1979 574.0 66.5 808 636 0.79 1.11

1980 367.3 53.2 977 308 0.32 0.84

1981 367.5 59.8 677 364 0.54 0.99

1982 171.5 22.5 1,477 1,226 0.837.15

19837.8 2.6 941 607 0.65 77.82

1984 714.4 76.3 658 230 0.35 0.32

1985 566.5 66.0 1,093570 0.52 1.01

1986 655.3 73.4 588 202 0.34 0.31

1987 574.6 62.7 1,308 500 0.38 0.87

1988 792.5 83.3 451 93 0.21 0.12

1989 587.8 61.1 1,800 876 0.49 1.49

1990 595.362.9 1,066 358 0.34 0.60

1991 862.8 87.5 299 40 0.130.05

1992 561.7 61.4 1,003212 0.21 0.38

1993140.5 14.9 478 60 0.130.43

1994 0.0 0.0 529 58 0.11 ---

1995 174.8 21.4 638 67 0.11 0.38

1996 695.374.8 289 22 0.08 0.03

1997 495.1 54.9 1,608 234 0.15 0.47

1998 874.0 95.321315 0.07 0.02

1999 829.8 88.3893117 0.130.14

1975 401.9 88.2 104 28 0.27 0.07

1976 405.9 78.9 381 270 0.71 0.67

1977 425.0 79.9 312 140 0.45 0.33

1978 466.6 89.5 335 154 0.46 0.33

1979 412.0 79.0 343 127 0.37 0.31

1980 433.8 82.1 401 165 0.41 0.38

1981 451.8 86.7 383 141 0.37 0.31

1982 458.4 87.6 353 101 0.29 0.22

1983 444.1 83.7 445 165 0.37 0.37

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.

7 Indian Point 3 was purchased by a different utility and now reports separately.
C-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

KEWAUNEE

(continued)

LACROSSE8

Docket 50-409; DPR-45

1st commercial operation 11/69

Type - BWR

Capacity - (48) MWe

LASALLE 1, 2

Docket 50-373, -374;

NPF-11, -18

1st commercial operation

1/84, 6/84

Type - BWR

Capacity - 1036, 1036 MWe

1984 455.385.7 482 139 0.29 0.31

1985 443.1 82.4 519 176 0.34 0.40

1986 461.7 85.8 502 169 0.34 0.37

1987 480.0 89.7 755 226 0.30 0.47

1988 467.5 88.3705 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

1993457.1 86.8 436 106 0.24 0.23

1994 475.6 88.8 364 72 0.20 0.15

1995 455.6 87.8 415 109 0.26 0.24

1996 380.4 71.8 474 126 0.27 0.33

1997 269.8 56.0 278 56 0.20 0.21

1998 423.0 87.2 284 88 0.23 0.21

1999 505.1 100.0 1035 0.05 0.01

1970 15.3111 7.25

1971 323.1 218 158 0.72 0.49

1972 29.2 151 1.14 5.17

197324.4 157 1.41 6.43

1974 37.9 81.0 115 139 1.21 3.67

1975 32.0 69.6 165 234 1.42 7.31

1976 21.2 47.6 118 110 0.935.19

1977 11.3 33.7 141 225 1.60 19.91

1978 21.6 62.0 182 164 0.90 7.59

1979 24.0 71.8 153186 1.22 7.75

1980 26.4 68.5 124 218 1.76 8.26

1981 29.6 76.0 187 1230.66 4.16

1982 17.2 44.6 148 205 1.39 11.92

198324.8 59.7 160 313 1.96 12.62

1984 38.5 80.5 288 252 0.88 6.55

1985 39.2 86.7 373 173 0.46 4.41

1986 19.6 46.1 260 290 1.12 14.80

1987 0.0 0.0 127 68 0.54 ---

19930.0 0.0 48 8 0.17 ---

1994 0.0 0.0 65 8 0.12 ---

1995 0.0 0.0 31 3 0.10 ---

1996 0.0 0.0 25 4 0.15 ---

1997 0.0 0.0 232 0.09 ---

1998 0.0 0.0 1,155 105 0.09 ---

1999 0.0 0.0 66 4 0.06 ---

1984 677.8 77.8 1,245 252 0.20 0.37

1985 987.9 53.0 1,635 685 0.42 0.69

1986 929.5 50.6 1,614 898 0.56 0.97

1987 1,030.0 59.3 1,744 1,396 0.80 1.36

1988 1,317.6 71.6 2,737 2,471 0.90 1.88

1989 1,503.5 73.1 2,475 1,386 0.56 0.92

1990 1,754.384.6 1,830 948 0.52 0.54

1991 1,837.0 86.7 1,985 806 0.41 0.44

1992 1,447.4 72.0 2,418 1,167 0.48 0.81

19931,542.0 76.0 1,701 854 0.50 0.55

1994 1,580.0 77.6 1,812 726 0.40 0.46

1995 1,696.6 82.1 1,623 512 0.32 0.30

1996 1,053.8 54.3 2,782 819 0.29 0.78

1997 0.0 0.0 1,661 316 0.19 ---

1998 380.9 19.3 2,099 422 0.20 1.11

1999 1,671.9 81.8 2,689 576 0.21 0.34

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.
C-15

Thirty-Second Annual Report, 1999 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

LIMERICK 1, 2

Docket 50-352, 50-353;

NPF-39,-85

1st commercial operation

2/86, 1/90

Type - BWRs

Capacity - 1134, 1150 MWe

MAINE YANKEE9

Docket 50-309; DPR-36

1st commercial operation 12/72

Type - PWR

Capacity - (860) MWe

MCGUIRE 1, 2

Docket 50-369, -370;

NPF-9, -17

1st commercial operation

12/81, 3/84

Type - PWRS

Capacity - 1100, 1100 MWe

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

1987 636.1 70.2 2,156 174 0.08 0.27

1988 794.9 96.5 950 52 0.05 0.07

1989 628.4 66.0 1,818 266 0.15 0.42

1990 1,527.7 78.2 1,422 175 0.12 0.11

1991 1,810.9 86.8 1,151 106 0.09 0.06

1992 1,741.4 84.8 1,559 330 0.21 0.19

19931,913.2 91.6 1,287 217 0.17 0.11

1994 1,944.4 94.9 1,543275 0.18 0.14

1995 1,957.1 93.0 1,581 260 0.16 0.13

1996 2,026.2 93.3 1,654 234 0.14 0.12

1997 2,001.7 95.8 1,463234 0.16 0.12

1998 1,907.2 89.5 1,854 357 0.19 0.19

1999 2,089.6 94.2 1,800 272 0.15 0.13

1973408.7 782 117 0.15 0.29

1974 432.6 68.7 619 420 0.68 0.97

1975 542.9 79.9 440 319 0.72 0.59

1976 712.2 95.0 244 85 0.35 0.12

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

1983677.1 83.6 592 165 0.28 0.24

1984 605.7 74.4 1,262 884 0.70 1.46

1985 635.4 79.2 1,009 700 0.69 1.10

1986 737.6 87.8 495 100 0.20 0.14

1987 478.1 65.31,100 722 0.66 1.51

1988 591.9 79.1 1,058 725 0.69 1.22

1989 819.2 93.7 375 99 0.26 0.12

1990 573.0 71.0 1,359 682 0.50 1.19

1991 738.1 86.6 426 105 0.25 0.14

1992 631.7 79.1 1,189 461 0.39 0.73

1993674.8 79.8 1,016 377 0.37 0.56

1994 782.8 90.9 297 84 0.28 0.11

1995 23.6 3.7 1,167 653 0.56 27.67

1996 602.9 78.1 408 56 0.14 0.09

1997 0.0 0.0 991 1530.15 ---

1998 0.0 0.0 1,313 173 0.13 ---

1999 0.0 0.0 365 135 0.37 ---

1982 524.9 80.4 1,560 169 0.11 0.32

1983558.3 55.4 1,751 521 0.30 0.93

1984 764.1 68.5 1,663507 0.30 0.66

1985 808.4 77.0 2,217 771 0.35 0.95

1986 1,360.0 60.1 2,326 1,015 0.44 0.75

1987 1,774.7 79.2 2,865 1,0430.36 0.59

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 1,723361 0.21 0.19

1992 1,696.8 74.4 1,619 418 0.26 0.25

19931,470.4 66.2 1,685 463 0.27 0.31

1994 1,848.0 80.2 1,637 397 0.24 0.21

1995 2,132.3 92.9 1,259 138 0.11 0.06

1996 1,881.8 82.8 1,622 238 0.15 0.13

1997 1,558.2 73.0 2,193 492 0.22 0.32
C-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

MCGUIRE 1, 2

(continued)

MILLSTONE UNIT 110

Docket 50-245; DPR-21

1st commercial operation 3/71

Type - BWR

Capacity - (641) MWe

MILLSTONE UNIT 2, 3

Docket 50-336, 50-423;

DPR-65, NPF-49

1st commercial operation

12/75, 4/86

Type - PWR

Capacity - 871, 1140 MWe

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

1972 377.6 612 596 0.97 1.58

1973225.1 1,184 663 0.56 2.95

1974 430.3 79.1 2,477 1,430 0.58 3.32

1975 465.4 75.6 2,587 2,022 0.78 4.34

1976 449.8 76.1 1,387 1,194 0.86 2.65

1977 575.7 89.6 1,075 394 0.37 0.68

1978 556.6 87.6 1,391 1,416 1.02 2.54

1979 505.0 77.32,001 1,795 0.90 3.55

1980 405.8 69.0 3,024 2,157 0.71 5.32

1981 304.3 51.6 2,506 1,496 0.60 4.92

1982 490.2 79.9 1,370 929 0.68 1.90

1983640.1 95.6 309 244 0.79 0.38

1984 516.1 78.8 1,992 836 0.42 1.62

1985 548.5 83.6 732 608 0.83 1.11

1986 626.8 95.4 389 150 0.39 0.24

1987 523.4 79.6 1,588 684 0.43 1.31

1988 658.8 98.6 327 144 0.44 0.22

1989 554.6 84.2 852 462 0.54 0.83

1990 608.3 91.6 365 131 0.36 0.22

1991 213.1 35.4 1,154 409 0.35 1.92

1992 431.8 68.1 348 99 0.28 0.23

1993627.9 96.8 305 81 0.27 0.13

1994 394.0 63.6 1,321 391 0.30 0.99

1995 520.6 80.0 910 620 0.68 1.19

1996 0.0 0.0 747 431 0.58 ---

1997 -2.9 0.0 1,053195 0.19 ---

1998 -2.7 0.0 347 13 0.04 ---

1999 0.0 0.0 397 10 0.02 ---

1976 545.7 78.7 620 168 0.27 0.31

1977 518.7 65.7 667 242 0.36 0.47

1978 536.6 67.3 1,420 1,444 1.02 2.69

1979 520.0 62.8 525 471 0.90 0.91

1980 579.369.2 893637 0.71 1.10

1981 722.4 82.6 890 531 0.60 0.74

1982 595.9 70.6 2,0831,413 0.68 2.37

1983294.0 34.2 2,3831,881 0.79 6.40

1984 782.7 93.5 285 120 0.42 0.15

1985 417.8 49.4 1,905 1,581 0.833.78

1986 1,313.8 80.4 2,393 993 0.41 0.76

1987 1,624.5 84.1 1,441 505 0.35 0.31

1988 1,594.8 83.2 1,827 804 0.44 0.50

1989 1,428.372.9 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

19931,525.2 79.7 2,064 557 0.27 0.37

1994 1,556.6 73.1 1,249 188 0.15 0.12

1995 1,278.1 60.5 1,691 416 0.25 0.33

1996 418.1 19.3983126 0.130.30

1997 0.0 0.0 1,435 253 0.18 ---

1998 374.9 20.9 1,179 113 0.10 0.30

1999 1,446.373.3 1,688 252 0.15 0.17

10 Millstone Unit 1 was shut down 6/30/98 and is no longer included in the count of operating reactors.
C-17

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

MONTICELLO

Docket 50-263; DPR-22

1st commercial operation 6/71

Type - BWR

Capacity - 578 MWe

NINE MILE POINT 1, 2

Docket 50-220, 50-410;

DPR-63, NPF-69

1st commercial operation

12/69, 4/88

Type - BWR

Capacity - 565, 1123 MWe

1972 424.4 99 61 0.62 0.14

1973389.5 401 176 0.44 0.45

1974 349.3 74.9 842 349 0.41 1.00

1975 344.8 72.2 1,353 1,353 1.00 3.92

1976 476.4 91.5 325 263 0.81 0.55

1977 425.6 79.9 860 1,000 1.16 2.35

1978 459.4 87.2 679 375 0.55 0.82

1979 522.0 97.6 372 157 0.42 0.30

1980 411.8 78.2 1,114 531 0.48 1.29

1981 389.3 72.6 1,446 1,004 0.69 2.58

1982 291.1 63.3 1,307 993 0.76 3.41

1983494.6 96.3 416 121 0.29 0.24

1984 33.7 9.2 1,872 2,462 1.32 73.06

1985 509.8 91.7 586 327 0.56 0.64

1986 402.7 79.1 895 596 0.67 1.48

1987 422.5 81.9 941 568 0.60 1.34

1988 542.5 99.8 375 110 0.29 0.20

1989 318.2 76.2 1,102 507 0.46 1.59

1990 536.0 96.9 336 94 0.28 0.18

1991 429.4 80.8 964 465 0.48 1.08

1992 528.397.5 454 114 0.25 0.22

1993458.1 84.4 954 494 0.52 1.08

1994 471.387.0 788 395 0.50 0.84

1995 564.7 100.0 200 44 0.22 0.08

1996 461.6 86.9 757 240 0.32 0.52

1997 417.4 75.9 399 106 0.27 0.25

1998 470.2 88.1 674 209 0.31 0.44

1999 530.7 92.9 451 70 0.16 0.13

1970 227.0 821 44 0.05 0.19

1971 346.5 1,006 195 0.19 0.56

1972 381.8 735 285 0.39 0.75

1973411.0 550 567 1.031.38

1974 385.9 70.5 740 824 1.11 2.14

1975 359.0 72.1 649 681 1.05 1.90

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

1983329.8 56.2 1,405 860 0.61 2.61

1984 426.8 71.9 1,530 890 0.58 2.09

1985 580.9 96.4 1,007 265 0.26 0.46

1986 371.0 65.3 1,878 1,275 0.68 3.44

1987 542.6 93.3 1,190 141 0.12 0.26

1988 0.0 0.0 2,626 854 0.33 ---

1989 527.5 29.7 2,737 564 0.21 1.07

1990 656.2 46.6 2,405 699 0.29 1.07

1991 1,250.8 79.7 1,543292 0.19 0.23

1992 965.9 61.8 1,800 5630.31 0.58

19931,380.2 84.6 2,352 633 0.27 0.46

1994 1,589.6 95.9 800 149 0.19 0.09

1995 1,382.2 82.5 2,304 759 0.33 0.55

1996 1,598.6 91.6 1,596 290 0.18 0.18

1997 1,321.5 74.8 1,425 429 0.30 0.32

1998 1,387.3 87.0 1,744 378 0.22 0.27

1999 1,409.5 81.31,709 447 0.26 0.32
C-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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

Docket 50-338; NPF-04, -09

1st commercial operation

6/78, 12/80

Type - PWRs

Capacity - 893, 897 MWe

OCONEE 1, 2, 3

Docket 50-269, 50-270,

50-287;

DPR-38, -47, -55

1st commercial operation 7/73,

9/74, 12/74

Type - PWRs

Capacity - 846, 846, 846 MWe

OYSTER CREEK

Docket 50-219; DPR-16

1st commercial operation 12/69

Type - BWR

Capacity - 619 MWe

1979 507.0 61.7 2,025 449 0.22 0.89

1980 681.8 86.5 2,086 218 0.10 0.32

1981 1,241.9 71.5 2,416 680 0.28 0.55

1982 777.7 45.8 2,872 1,915 0.67 2.46

1983 1,338.4 76.1 2,228 665 0.30 0.50

1984 1,021.358.8 3,062 1,945 0.64 1.90

1985 1,516.9 86.1 2,436 838 0.34 0.55

1986 1,484.5 83.0 2,831 722 0.26 0.49

1987 1,112.6 67.8 2,624 1,521 0.58 1.37

1988 1,772.7 96.7 992 112 0.11 0.06

1989 1,226.8 72.5 2,861 1,471 0.51 1.20

1990 1,590.4 90.5 2,161 590 0.27 0.37

1991 1,597.5 88.6 2,085 629 0.30 0.39

1992 1,403.2 84.1 2,159 576 0.27 0.41

19931,428.4 80.1 2,768 908 0.33 0.64

1994 1,717.1 95.9 1,036 193 0.19 0.11

1995 1,666.4 90.8 1,551 367 0.24 0.22

1996 1,569.6 89.1 1,203291 0.24 0.19

1997 1,711.5 96.2 856 1030.12 0.06

1998 1,632.8 92.7 1,201 266 0.22 0.16

1999 1,747.7 96.1 727 94 0.130.05

1974 650.6 60.1 844 517 0.61 0.79

1975 1,838.3 75.5 829 497 0.60 0.27

1976 1,561.4 63.0 1,215 1,026 0.84 0.66

1977 1,566.4 65.9 1,595 1,329 0.83 0.85

1978 1,909.0 75.8 1,636 1,393 0.85 0.73

1979 1,708.0 67.7 2,100 1,001 0.48 0.59

1980 1,703.7 70.1 2,124 1,055 0.50 0.62

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

19832,141.5 82.2 1,902 1,207 0.63 0.56

1984 2,242.9 85.7 2,085 1,106 0.530.49

1985 2,036.3 80.5 2,729 1,304 0.48 0.64

1986 1,995.6 79.0 2,499 949 0.38 0.48

1987 1,962.6 82.4 2,672 1,142 0.430.58

1988 2,228.9 87.2 2,672 871 0.33 0.39

1989 2,188.6 85.4 2,205 684 0.31 0.31

1990 2,405.2 91.4 1,948 404 0.21 0.17

1991 2,275.0 86.7 1,966 551 0.28 0.24

1992 2,110.7 82.0 1,954 612 0.31 0.29

19932,399.2 91.3 1,499 237 0.16 0.10

1994 2,144.382.2 1,923537 0.28 0.25

1995 2,366.1 89.5 1,586 304 0.19 0.13

1996 1,847.9 70.31,479 257 0.17 0.14

1997 1,563.7 67.7 1,379 223 0.16 0.14

1998 1,989.1 81.31,695 366 0.22 0.18

1999 2,264.5 90.31,568 202 0.130.09

1970 413.6 95 63 0.66 0.15

1971 448.9 249 240 0.96 0.53

1972 515.0 339 582 1.72 1.13

1973424.6 782 1,236 1.58 2.91

1974 434.5 70.4 935 984 1.05 2.26

1975 373.6 73.3 1,210 1,140 0.94 3.05

1976 456.5 79.31,582 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
C-19

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

OYSTER CREEK

(continued)

PALISADES

Docket 50-255; DPR-20

1st commercial operation 12/71

Type - PWR

Capacity - 730 MWe

PALO VERDE 1, 2, 3

Docket 50-528, 50-529; 50-530;

NPF-41, NPF-51, NPF-74

1st commercial operation

1/86,9/86,1/88

Type - PWRs

Capacity - 1243, 1243, 1247

MWe

198327.9 11.5 2,3032,257 0.98 80.90

1984 37.1 9.6 2,369 2,054 0.87 55.36

1985 446.1 89.4 2,342 748 0.32 1.68

1986 157.331.5 3,740 2,436 0.65 15.49

1987 371.0 64.2 1,932 522 0.27 1.41

1988 419.6 65.9 2,875 1,504 0.52 3.58

1989 287.5 57.3 2,395 910 0.38 3.17

1990 511.8 89.1 1,941 310 0.16 0.61

1991 351.6 60.5 3,089 1,185 0.38 3.37

1992 536.3 85.9 2,771 657 0.24 1.23

1993551.9 87.8 2,560 416 0.16 0.75

1994 431.7 70.8 2,382 844 0.35 1.96

1995 615.4 97.4 761 90 0.12 0.15

1996 515.0 82.6 1,833 449 0.24 0.87

1997 579.1 94.3509 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

1972 216.8 78 0.36

1973286.8 975 1,133 1.16 3.95

1974 10.7 5.5 774 627 0.81 58.60

1975 302.0 64.5 495 306 0.62 1.01

1976 346.9 55.2 742 696 0.94 2.01

1977 616.6 91.4 332 100 0.30 0.16

1978 320.2 49.7 849 764 0.90 2.39

1979 415.0 59.9 1,599 854 0.532.06

1980 288.342.9 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

1983454.4 60.3 2,167 977 0.45 2.15

1984 98.7 15.2 1,344 573 0.43 5.81

1985 639.2 83.8 1,355 507 0.37 0.79

1986 102.315.1 1,438 672 0.47 6.57

1987 319.2 48.2 1,122 456 0.41 1.43

1988 413.4 56.8 1,472 730 0.50 1.77

1989 442.8 69.1 1,026 314 0.31 0.71

1990 366.7 58.7 2,414 766 0.32 2.09

1991 587.0 78.1 1,315 211 0.16 0.36

1992 581.9 76.1 1,267 295 0.230.51

1993 424.4 53.7 908 289 0.32 0.68

1994 541.8 67.0 397 60 0.15 0.11

1995 583.5 75.8 1,230 462 0.38 0.79

1996 638.2 81.4 1,109 318 0.29 0.50

1997 662.5 89.9 338 48 0.14 0.07

1998 615.4 83.5 895 217 0.24 0.35

1999 585.4 80.2 939 218 0.23 0.37

1987 1,638.1 66.1 1,792 669 0.37 0.41

1988 1,700.9 65.5 2,173688 0.32 0.40

1989 965.326.5 2,615 720 0.28 0.75

1990 2,500.9 67.5 2,236 499 0.22 0.20

1991 3,043.9 78.9 2,242 605 0.27 0.20

1992 3,102.3 82.0 1,981 541 0.27 0.17

19932,677.1 74.3 2,124 592 0.28 0.22

1994 2,827.6 79.1 2,048 462 0.230.16

1995 3,265.2 85.6 1,875 482 0.26 0.15

1996 3,482.7 90.0 1,717 302 0.18 0.09

1997 3,369.2 92.2 1,585 246 0.16 0.07

1998 3,454.4 93.2 1,410 192 0.14 0.06

1999 3,471.2 93.2 1,275 146 0.11 0.04
C-20

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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

Docket 50-277, 50-278;

DPR-44, -56

1st commercial operation

7/74, 12/74

Type - BWR

Capacity - 1093, 1093 MWe

PERRY

Docket 50-440; NPF-58

1st commercial operation 11/87

Type - BWR

Capacity - 1160 MWe

PILGRIM 1

Docket 50-293; DPR-35

1st commercial operation 12/72

Type - BWR

Capacity - 670 MWe

1975 1,234.3 80.9 971 228 0.23 0.18

1976 1,379.2 73.0 2,136 840 0.39 0.61

1977 1,052.4 58.7 2,827 2,036 0.72 1.93

1978 1,636.3 84.0 2,244 1,317 0.59 0.80

1979 1,740.0 84.5 2,276 1,388 0.61 0.80

1980 1,374.2 66.3 2,774 2,302 0.83 1.68

1981 1,161.8 58.0 2,857 2,506 0.88 2.16

1982 1,583.3 76.9 2,734 1,977 0.72 1.25

1983824.7 41.0 3,107 2,963 0.95 3.59

1984 1,165.8 57.5 3,313 2,450 0.74 2.10

1985 682.7 37.5 4,209 3,354 0.80 4.91

1986 1,395.0 71.7 2,454 1,080 0.44 0.77

1987 365.7 20.3 4,363 2,195 0.50 6.00

1988 0.0 0.0 4,204 2,327 0.55 ---

1989 491.0 35.0 2,301 728 0.32 1.48

1990 1,684.0 85.7 1,585 377 0.24 0.22

1991 1,210.9 62.32,702 934 0.35 0.77

1992 1,516.6 78.7 1,911 502 0.26 0.33

1993 1,654.0 81.9 1,757 552 0.31 0.33

1994 1,927.4 93.8 2,133 579 0.27 0.30

1995 1,955.9 95.1 1,940 398 0.21 0.20

1996 2,012.4 96.9 1,657 282 0.17 0.14

1997 1,956.395.0 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

1988 869.379.0 782 105 0.130.12

1989 642.2 57.0 1,883767 0.41 1.19

1990 792.7 67.1 1,537 638 0.42 0.80

1991 1,074.2 91.9 600 146 0.24 0.14

1992 856.2 75.5 1,487 571 0.38 0.67

1993479.2 48.2 1,235 278 0.230.58

1994 550.8 50.2 2,098 691 0.33 1.25

1995 1,090.9 95.6 587 64 0.11 0.06

1996 895.6 77.2 1,622 307 0.19 0.34

1997 930.6 84.7 1,524 272 0.18 0.29

1998 1,163.1 99.3 385 42 0.11 0.04

1999 1,041.7 89.9 1,758 326 0.19 0.31

1973484.0 230 126 0.55 0.26

1974 234.1 39.2 454 415 0.91 1.77

1975 308.1 71.3 473 798 1.69 2.59

1976 287.8 60.7 1,317 2,648 2.01 9.20

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 2,8031,836 0.66 4.49

1982 389.9 63.9 2,854 1,539 0.54 3.95

1983559.5 87.2 2,326 1,162 0.50 2.08

1984 1.4 0.4 4,542 4,082 0.90 2915.71

1985 587.391.5 2,209 893 0.40 1.52

1986 121.9 18.8 2,635 874 0.33 7.17

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

1988 0.0 0.0 2,073392 0.19 ---

1989 204.6 64.1 1,797 207 0.12 1.01

1990 503.5 82.1 1,898 225 0.12 0.45

1991 406.365.8 2,836 605 0.21 1.49

1992 561.0 85.4 1,332 281 0.21 0.50

1993513.7 80.9 1,328 435 0.330.85

1994 453.6 71.4 758 200 0.26 0.44

1995 531.7 80.7 1,294 482 0.37 0.91
C-21

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

PILGRIM 1

(continued)

POINT BEACH 1, 2

Docket 50-266, 50-301;

DPR-24, -27

1st commercial operation

12/70, 10/72

Type - PWRs

Capacity - 510, 512 MWe

PRAIRIE ISLAND 1, 2

Docket 50-282, 50-306;

DPR-42, -60

1st commercial operation 12/73,

12/74

Type - PWRs

Capacity - 522, 522 MWe

1996 631.3 95.4 517 116 0.22 0.18

1997 492.1 80.7 1,655 588 0.36 1.19

1998 650.5 100.0 530 71 0.13 0.11

1999 510.7 84.4 1,222 344 0.28 0.67

1971 393.4 164 0.42

1972 378.3 580 1.53

1973693.7 501 588 1.17 0.85

1974 760.2 81.3400 295 0.74 0.39

1975 801.2 82.9 339 459 1.35 0.57

1976 857.3 86.7 313 370 1.18 0.43

1977 873.9 87.3 417 430 1.03 0.49

1978 914.4 90.9 336 320 0.95 0.35

1979 808.0 80.8 610 644 1.06 0.80

1980 727.2 82.5 561 598 1.07 0.82

1981 760.4 83.6 773 596 0.77 0.78

1982 757.2 84.3767 609 0.79 0.80

1983648.2 72.7 1,702 1,403 0.82 2.16

1984 788.9 78.6 1,372 789 0.58 1.00

1985 831.3 82.5 671 482 0.72 0.58

1986 858.9 85.7 664 402 0.61 0.47

1987 857.5 85.5 720 554 0.77 0.65

1988 899.388.6 734 410 0.56 0.46

1989 847.8 85.5 736 504 0.68 0.59

1990 875.5 86.5 617 378 0.61 0.43

1991 874.8 87.1 724 265 0.37 0.30

1992 866.7 85.8 617 256 0.41 0.30

1993911.0 90.0 559 186 0.330.20

1994 914.5 91.2 548 170 0.31 0.19

1995 858.4 86.1 548 190 0.35 0.22

1996 831.6 84.7 1,029 276 0.27 0.33

1997 186.8 21.8 670 92 0.14 0.49

1998 649.7 69.7 881 169 0.19 0.26

1999 806.0 83.1 962 194 0.20 0.24

1974 181.9 43.9 150 18 0.12 0.10

1975 836.0 83.3 477 123 0.26 0.15

1976 725.2 76.6 818 447 0.55 0.62

1977 922.9 87.2 718 300 0.42 0.33

1978 941.1 92.2 546 221 0.40 0.23

1979 865.0 86.0 594 180 0.30 0.21

1980 800.7 79.9 983353 0.36 0.44

1981 844.9 80.5 836 329 0.39 0.39

1982 944.9 90.4 645 229 0.36 0.24

1983921.1 86.8 654 233 0.36 0.25

1984 972.4 91.7 546 147 0.27 0.15

1985 882.6 84.0 1,082 416 0.38 0.47

1986 930.6 90.3 818 255 0.31 0.27

1987 969.6 91.6 593135 0.230.14

1988 932.0 89.1 732 199 0.27 0.21

1989 1,001.8 94.7 476 99 0.21 0.10

1990 925.4 89.2 737 188 0.26 0.20

1991 1,023.3 95.6 586 98 0.17 0.10

1992 811.6 76.2 845 211 0.25 0.26

1993978.3 90.7 532 106 0.20 0.11

1994 996.9 91.5 478 109 0.10 0.11

1995 1,023.2 93.9 499 107 0.21 0.10

1996 992.1 91.4 558 112 0.20 0.11

1997 817.6 81.4 753174 0.230.21

1998 860.383.4 582 117 0.20 0.14

1999 989.393.8 542 72 0.130.07
C-22

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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

Docket 50-254, 50-265;

DPR-29, -30

1st commercial operation 2/73,

3/73

Type - BWRs

Capacity - 769, 769 MWe

RANCHO SECO11

Docket 50-312; DPR-54

1st commercial operation 4/75

Type - PWR

Capacity - (873) MWe

RIVER BEND 1

Docket 50-458; NPF-47

1st commercial operation 6/86

Type - BWR

Capacity - 936 MWe

1974 958.1 72.3678 482 0.71 0.50

1975 833.6 68.4 1,083 1,618 1.49 1.94

1976 951.2 73.1 1,225 1,651 1.35 1.74

1977 970.1 84.0 907 1,031 1.14 1.06

1978 1,124.5 88.6 1,207 1,618 1.34 1.44

1979 1,075.0 84.6 1,688 2,158 1.28 2.01

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

19831,088.5 79.2 1,802 2,491 1.38 2.29

1984 994.6 65.7 1,678 1,579 0.94 1.59

1985 1,268.0 82.7 1,184 990 0.84 0.78

1986 1,093.2 71.0 1,451 950 0.65 0.87

1987 1,126.6 75.31,429 720 0.50 0.64

1988 1,173.7 84.1 1,486 827 0.56 0.70

1989 1,196.385.9 1,721 900 0.52 0.75

1990 1,148.9 77.8 2,186 1,028 0.47 0.89

1991 1,044.5 73.2 1,722 509 0.30 0.49

1992 960.8 68.0 2,4131,157 0.48 1.20

1993974.9 67.0 2,150 849 0.39 0.87

1994 681.5 48.7 2,1631,128 0.52 1.66

1995 1,002.5 70.4 2,041 736 0.36 0.73

1996 876.6 60.1 2,248 1,025 0.46 1.17

1997 935.3 66.5 2,474 654 0.26 0.70

1998 794.8 55.1 2,177 761 0.35 0.96

1999 1,476.5 95.9 1,000 201 0.20 0.14

1976 268.1 30.4 297 58 0.20 0.22

1977 706.4 77.1 515 391 0.76 0.55

1978 607.7 80.5 508 323 0.64 0.53

1979 687.0 91.1 287 126 0.44 0.18

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 58.3802 222 0.28 0.48

1985 238.7 30.8 1,764 756 0.43 3.17

1986 0.0 0.0 1,513402 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 60381 0.130.45

1990 0.0 0.0 111 130.12 ---

1991 0.0 0.0 101 9 0.09 ---

1992 0.0 0.0 70 7 0.10 ---

19930.0 0.0 35 4 0.11 ---

1994 0.0 0.0 18 1 0.06 ---

1995 0.0 0.0 16 1 0.06 ---

1996 0.0 0.0 16 1 0.04 ---

1997 0.0 0.0 16 0 0.00 ---

1998 0.0 0.0 408 41 0.10 ---

1999 0.0 0.0 302 11 0.04 ---

1987 605.2 68.4 1,268 378 0.30 0.62

1988 880.7 94.3513107 0.21 0.12

1989 584.5 69.1 1,566 558 0.36 0.95

1990 682.2 78.0 1,616 489 0.30 0.72

1991 814.7 87.2 780 144 0.18 0.18

1992 336.1 39.7 2,022 710 0.35 2.11

1993640.0 71.6 847 180 0.21 0.28

1994 595.7 64.9 2,209 519 0.24 0.87

11 Rancho Seco was shut down 6/89 and is no longer in the count of operating reactors.
C-23

Thirty-Second Annual Report, 1999 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

RIVER BEND 1

(continued)

ROBINSON 2

Docket 50-261; DPR-23

1st commercial operation 3/71

Type - PWR

Capacity - 683 MWe

SALEM 1, 2

Docket 50-272, -311;

DPR-70, -75

1st commercial operation 6/77,

10/81

Type - PWRs

Capacity - 1106, 1106 MWe

1995 967.1 99.6 667 85 0.130.09

1996 836.1 85.3 2,093 473 0.23 0.57

1997 778.8 86.31,671 347 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

1972 580.0 245 215 0.88 0.37

1973455.1 831 695 0.84 1.53

1974 578.1 83.3 853 672 0.79 1.16

1975 501.8 72.7 849 1,142 1.35 2.28

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 943963 1.02 2.00

1979 482.0 70.8 1,454 1,188 0.82 2.46

1980 387.3 62.2 2,009 1,852 0.92 4.78

1981 426.6 73.0 1,462 733 0.50 1.72

1982 277.5 48.9 2,011 1,426 0.71 5.14

1983409.8 75.5 2,244 923 0.41 2.25

1984 28.0 7.0 4,127 2,880 0.70 102.86

1985 629.5 87.9 1,378 311 0.23 0.49

1986 577.1 80.31,571 539 0.34 0.93

1987 510.1 72.5 1,379 499 0.36 0.98

1988 385.0 65.9 1,351 564 0.42 1.46

1989 336.6 48.7 1,098 195 0.18 0.58

1990 400.364.8 1,626 437 0.27 1.09

1991 575.1 81.4 885 1930.22 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 560.379.5 420 63 0.15 0.11

1995 618.7 84.7 1,058 215 0.20 0.35

1996 654.8 88.6 1,031 167 0.16 0.26

1997 707.5 99.0 304 13 0.04 0.02

1998 628.5 88.9 978 170 0.17 0.27

1999 648.9 91.8 807 124 0.15 0.19

1978 546.4 55.6 574 122 0.21 0.22

1979 250.0 25.5 1,488 584 0.39 2.34

1980 680.6 69.2 1,704 449 0.26 0.66

1981 743.0 78.1 1,652 254 0.15 0.34

1982 1,440.4 72.6 3,228 1,203 0.37 0.84

1983742.0 30.5 2,383 581 0.24 0.78

1984 650.1 31.8 1,395 681 0.49 1.05

1985 1,657.7 75.8 1,112 204 0.18 0.12

1986 1,484.370.4 3,554 599 0.17 0.40

1987 1,478.2 73.3 2,543 600 0.24 0.41

1988 1,591.6 73.6 1,609 503 0.31 0.32

1989 1,675.4 79.5 2,944 338 0.11 0.20

1990 1,362.6 65.1 3,636 272 0.07 0.20

1991 1,726.4 79.34,201 458 0.11 0.27

1992 1,200.9 61.1 4,376 431 0.10 0.36

19931,366.3 65.4 3,559 408 0.11 0.30

1994 1,367.4 73.8 950 188 0.20 0.14

1995 558.1 29.31,195 218 0.18 0.39

1996 0.0 0.0 1,671 300 0.18 ---

1997 279.317.8 894 175 0.20 0.63

1998 1,629.379.1 408 41 0.10 0.03

1999 1,821.8 86.8 1,200 318 0.27 0.17
C-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

SAN ONOFRE 112, 2, 3

Docket 50-206, -361, -362;

DPR-13, NPF-10, NPF-15

1st commercial operation 1/68,

8/83,4/84

Type - PWR

Capacity - (436), 1070, 1080

MWe

SAN ONOFRE 112

Docket 50-206;

DPR-13,

1st commercial operation 1/68

Type - PWR

Capacity - (436) MWe

SAN ONOFRE 2, 3

Docket 50-361, -362;

NPF-10, NPF-15

1st commercial operation 8/83,

4/84

Type - PWR

Capacity - 1070, 1080 MWe

SEABROOK

Docket 50-443; NPF-86

1st commercial operation 8/90

Type - PWR

Capacity - 1155 Mwe

1969 314.1 123 42 0.34 0.13

1970 365.9 251 155 0.62 0.42

1971 362.1 121 50 0.41 0.14

1972 338.5 326 256 0.79 0.76

1973273.7 570 353 0.62 1.29

1974 377.8 86.1 219 71 0.32 0.19

1975 389.0 87.4 424 292 0.69 0.75

1976 297.9 70.2 1,330 880 0.66 2.95

1977 281.2 63.7 985 847 0.86 3.01

1978 323.2 80.2 764 401 0.52 1.24

1979 401.0 90.2 521 139 0.27 0.35

1980 97.322.3 3,0632,386 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

19830.0 0.0 1,701 155 0.09 ---

1984 670.4 68.37,514 986 0.27 1.47

1985 1,381.8 132.9 5,742 722 0.24 0.52

1986 1,698.2 61.1 3,594 824 0.24 0.49

1987 1,983.0 78.8 2,138 696 0.33 0.35

1988 1,982.3 68.4 2,324 781 0.34 0.39

1989 1,840.8 64.9 2,237 567 0.25 0.31

1990 1,980.5 69.1 2,224 885 0.40 0.45

1991 1,987.6 75.31,814 412 0.230.21

1992 2,228.6 87.1 1,651 324 0.20 0.15

19931,771.3 79.9 2,193 767 0.35 0.43

1994 2,220.7 100.0 528 32 0.06 0.01

1995 1,686.9 79.1 1,914 455 0.24 0.27

1996 2,089.393.2 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

1999 0 0 241 16 0.07 ---

1999 1,901.4 86.9 1,477 354 0.24 0.19

1991 810.4 75.9 699 92 0.130.11

1992 932.4 81.3 806 147 0.18 0.16

19931,071.5 93.6 110 6 0.05 0.01

1994 736.4 63.5 852 113 0.13 0.15

1995 995.5 87.5 800 102 0.130.10

1996 1,168.6 99.6 206 10 0.05 0.01

1997 907.0 79.8 1,571 186 0.12 0.21

1998 957.6 84.5 559 19 0.030.02

1999 991.5 87.5 1,339 106 0.08 0.11

12 San Onofre 1 was shut down 11/92 and is no longer in the count of operating reactors.
C-25

Thirty-Second Annual Report, 1999 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

SEQUOYAH 1, 2

Docket 50-327, -328;

DPR-77, -79

1st commercial operation 7/81,

6/82

Type - PWR

Capacity - 1122, 1117 MWe

SOUTH TEXAS 1, 2

Docket 50-498, 50-499;

NPF -76,-80

1st commercial operation

8/88, 6/89

Type - PWRs

Capacity - 1251, 1251 MWe

ST. LUCIE 1, 2

Docket 50-335, -389; DPR-67;

NPF-16

1st commercial operation

12/76, 8/83

Type - PWRs

Capacity - 839, 839 MWe

SUMMER 1

Docket 50-395; NPF-12

1st commercial operation 1/84

Type - PWR

Capacity - 945 MWe

1982 583.5 52.8 1,968 570 0.29 0.98

19831,663.7 75.1 1,769 491 0.28 0.30

1984 1,481.9 69.0 2,373 1,119 0.47 0.76

1985 1,151.351.3 1,8531,072 0.58 0.93

1986 0.0 0.0 1,738 527 0.30 ---

1987 0.0 0.0 2,080 420 0.20 ---

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

1993405.7 21.8 1,631 373 0.230.92

1994 1,418.7 66.31,702 295 0.17 0.21

1995 1,864.2 86.1 1,650 368 0.22 0.20

1996 2,003.9 87.9 1,444 269 0.19 0.13

1997 1,946.1 89.0 1,962 420 0.21 0.22

1998 2,135.3 95.3 1,530 266 0.17 0.12

1999 2,165.1 97.0 1,346 165 0.12 0.08

1989 769.365.6 989 161 0.16 0.21

1990 1,504.1 65.9 1,136 206 0.18 0.14

1991 1,741.5 72.4 1,144 257 0.22 0.15

1992 2,096.0 83.8 923 147 0.16 0.07

1993 163.1 8.3 1,138 251 0.22 1.54

1994 1,700.2 70.6 661 47 0.07 0.03

1995 2,294.2 89.9 1,485 291 0.20 0.13

1996 2,465.9 95.0 1,145 137 0.12 0.06

1997 2,265.5 93.6 1,583 273 0.17 0.12

1998 2,379.4 96.9 1,171 184 0.16 0.08

1999 2,219.7 91.6 1,328 260 0.20 0.12

1977 649.1 84.7 445 152 0.34 0.23

1978 606.4 76.5 797 337 0.42 0.56

1979 592.0 74.0 907 438 0.48 0.74

1980 627.9 77.5 1,074 532 0.50 0.85

1981 599.1 72.7 1,473929 0.631.55

1982 816.8 94.0 1,045 272 0.26 0.33

1983290.3 15.4 2,211 1,204 0.54 4.15

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

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

1986 1,588.6 89.1 1,279 491 0.38 0.31

1987 1,407.9 81.9 2,012 951 0.47 0.68

1988 1,639.7 93.0 1,448 611 0.42 0.37

1989 1,493.1 85.1 1,414 495 0.35 0.33

1990 1,188.4 70.0 1,876 777 0.41 0.65

1991 1,592.8 90.8 1,282 479 0.37 0.30

1992 1,511.9 87.31,251 264 0.21 0.17

19931,227.6 77.7 1,462 492 0.34 0.40

1994 1,424.8 85.0 1,896 505 0.27 0.35

1995 1,306.6 76.0 1,498 413 0.28 0.32

1996 1,473.4 86.5 1,433 385 0.27 0.26

1997 1,394.6 83.6 2,314 646 0.28 0.46

1998 1,572.5 94.2 1,170 134 0.11 0.09

1999 1,569.1 93.8 1,107 177 0.16 0.11

1984 504.6 61.1 1,120 295 0.26 0.58

1985 627.7 71.6 1,201 379 0.32 0.60

1986 853.7 95.3 392 23 0.06 0.03

1987 618.7 71.0 1,075 560 0.52 0.91

1988 605.369.1 1,127 511 0.45 0.84

1989 652.4 83.1 374 52 0.14 0.08

1990 730.0 83.9 1,090 376 0.34 0.52

1991 642.5 82.9 984 291 0.30 0.45

1992 892.6 97.4 249 27 0.11 0.03
C-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

SUMMER 1

(continued)

SURRY 1, 2

Docket 50-280, 50-281;

DPR-32, -37

1st commercial operation

12/72, 5/73

Type - PWRs

Capacity - 801, 801 MWe

SUSQUEHANNA 1, 2

Docket 50-387, 50-388;

NPF-14; NPF-22

1st commercial operation

6/83, 2/85

Type - BWR

Capacity - 1090, 1094 MWe

1993728.3 84.0 1,121 297 0.26 0.41

1994 536.7 69.5 1,549 374 0.24 0.70

1995 899.8 97.2 257 130.05 0.01

1996 850.4 90.3701 97 0.14 0.11

1997 829.7 89.8 820 1630.20 0.20

1998 934.8 98.8 285 14 0.05 0.01

1999 842.0 89.4 827 120 0.15 0.14

1973420.6 936 152 0.16 0.36

1974 717.4 49.8 1,715 884 0.52 1.23

1975 1,079.0 70.8 1,948 1,649 0.85 1.53

1976 930.7 60.4 2,753 3,165 1.15 3.40

1977 1,139.0 72.2 1,860 2,307 1.24 2.03

1978 1,210.6 77.2 2,2031,837 0.83 1.52

1979 343.0 42.3 5,065 3,584 0.71 10.45

1980 568.2 40.3 5,317 3,836 0.72 6.75

1981 907.6 59.33,7534,244 1.134.68

1982 1,323.3 88.5 1,878 1,490 0.79 1.13

1983916.2 61.3 2,754 3,220 1.17 3.51

1984 1,026.7 71.0 3,198 2,247 0.70 2.19

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

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

1987 1,132.7 72.7 2,675 712 0.27 0.63

1988 750.4 50.0 3,184 1,542 0.48 2.05

1989 489.3 33.0 3,100 836 0.27 1.71

1990 1,276.4 83.9 1,947 575 0.30 0.45

1991 1,271.9 84.5 1,547 510 0.33 0.40

1992 1,396.3 88.9 1,660 539 0.32 0.39

19931,283.1 84.6 1,402 383 0.27 0.30

1994 1,320.9 85.2 1,530 378 0.25 0.29

1995 1,333.0 84.2 1,883 406 0.22 0.30

1996 1,562.9 93.1 983 209 0.21 0.13

1997 1,380.3 87.1 1,335 320 0.24 0.23

1998 1,476.2 91.6 1,165 189 0.16 0.13

1999 1,483.0 93.5 995 138 0.14 0.09

1984 719.9 72.6 2,827 308 0.11 0.43

1985 1,452.2 76.4 3,669 1,106 0.30 0.76

1986 1,344.8 67.0 2,996 828 0.28 0.62

1987 1,749.5 85.32,548 621 0.24 0.35

1988 1,691.0 83.5 1,904 516 0.27 0.31

1989 1,572.5 77.1 2,063704 0.34 0.45

1990 1,746.9 85.4 1,691 440 0.26 0.25

1991 1,878.0 89.8 1,844 507 0.27 0.27

1992 1,604.2 79.7 1,885 724 0.38 0.45

1993 1,602.1 77.3 1,488 335 0.23 0.21

1994 1,814.4 85.4 1,580 442 0.28 0.24

1995 1,850.8 85.31,773476 0.27 0.26

1996 1,998.7 90.7 1,430 289 0.20 0.14

1997 1,918.9 89.6 1,646 433 0.26 0.23

1998 1,879.6 88.31,575 361 0.230.19

1999 1,896.0 89.6 1,787 431 0.24 0.23
C-27

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

THREE MILE ISLAND 113, 214

Docket 50-289, -320;

DPR-50, -73

1st commercial operation 9/74,

12/78

Type - PWRs

Capacity - 786, (880) MWe

THREE MILE ISLAND 113

Docket 50-289; DPR-50

1st commercial operation 9/74

Type - PWR

Capacity - 786 MWe

THREE MILE ISLAND 214

Docket 50-320; DPR-73

1st commercial operation 12/78

Type - PWR

Capacity - (880) MWe

TROJAN15

Docket 50-344; NPF-1

1st commercial operation 5/76

Type - PWR

Capacity - (1080) MWe

1975 675.9 82.2 131 73 0.56 0.11

1976 530.0 65.4 819 286 0.35 0.54

1977 664.5 80.9 1,122 360 0.32 0.54

1978 690.0 85.1 1,929 504 0.26 0.73

1979 266.0 21.9 3,975 1,392 0.35 5.23

1980 0.0 0.0 2,328 394 0.17 ---

1981 0.0 0.0 2,103376 0.18 ---

1982 0.0 0.0 2,1231,004 0.47 ---

19830.0 0.0 1,592 1,159 0.73---

1984 0.0 0.0 1,079 688 0.64 ---

1985 103.6 10.6 1,890 857 0.45 8.27

1986 585.2 70.9 1,360 213 0.16 0.36

1987 610.7 73.6 1,259 149 0.12 0.24

1988 661.0 77.8 1,012 210 0.21 0.32

1989 871.3100.0 670 54 0.08 0.06

1990 645.5 84.6 1,319 264 0.20 0.41

1991 688.7 86.4 1,542 198 0.130.29

1992 836.8 100.0 558 34 0.06 0.04

1993722.0 88.5 1,835 206 0.11 0.29

1994 798.7 95.5 434 40 0.09 0.05

1995 772.9 90.8 1,220 2130.17 0.28

1996 857.4 100.0 267 16 0.06 0.02

1997 675.7 84.31,049 204 0.19 0.30

1998 805.8 100.0 280 17 0.06 0.02

1999 722.4 89.7 1,171 155 0.130.21

1986 0.0 0.0 1,497 915 0.61 ---

1987 0.0 0.0 1,378 977 0.71 ---

1988 0.0 0.0 1,247 917 0.74 ---

1989 0.0 0.0 1,014 639 0.63 ---

1990 0.0 0.0 484 136 0.28 ---

1991 0.0 0.0 15337 0.24 ---

1992 0.0 0.0 315 157 0.50 ---

19930.0 0.0 167 330.20 ---

1994 0.0 0.0 259 7 0.03---

1995 0.0 0.0 191 2 0.01 ---

1996 0.0 0.0 122 2 0.02 ---

1997 0.0 0.0 232 1 0.00 ---

1998 0.0 0.0 184 10 0.05 ---

1999 0.0 0.0 2031 0.00 ---

1977 792.0 92.6 591 174 0.29 0.22

1978 205.5 20.6 711 319 0.45 1.55

1979 631.0 58.1 736 258 0.35 0.41

1980 727.5 72.5 1,159 421 0.36 0.58

1981 775.6 74.1 1,311 609 0.46 0.79

1982 579.5 60.8 977 419 0.430.72

1983494.2 62.4 969 307 0.32 0.62

1984 567.0 54.4 1,042 433 0.42 0.76

1985 829.1 76.7 852 363 0.43 0.44

1986 852.4 79.7 1,321 381 0.29 0.45

1987 525.5 54.0 1,209 363 0.30 0.69

13 Three Mile Island 1 resumed commercial power generation 10/85 after being under regulatory restraint since 1979.

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.

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.
C-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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

(continued)

TURKEY POINT 3, 4

Docket 50-250, 50-251;

DPR-31, -41

1st commercial operation

12/72, 9/73

Type - PWRs

Capacity - 693, 693 MWe

VERMONT YANKEE

Docket 50-271; DPR-28

1st commercial operation 11/72

Type - BWR

Capacity - 510 MWe

1988 758.6 67.5 1,408 401 0.28 0.53

1989 666.8 61.9 1,360 421 0.31 0.63

1990 732.4 66.3 1,169 258 0.22 0.35

1991 181.6 16.1 1,496 567 0.38 3.12

1992 553.9 68.4 567 84 0.15 0.15

19930.0 68.4 54 21 0.39 ---

1994 0.0 0.0 51 9 0.18 ---

1995 0.0 0.0 141 44 0.31 ---

1996 0.0 0.0 112 41 0.37 ---

1997 0.0 0.0 227 41 0.18 ---

1998 0.0 0.0 246 12 0.05 ---

1999 0.0 0.0 274 52 0.19 ---

1973401.9 444 78 0.18 0.19

1974 953.6 794 454 0.57 0.48

1975 1,003.7 74.9 1,176 876 0.74 0.87

1976 974.2 71.2 1,647 1,184 0.72 1.22

1977 979.5 72.1 1,319 1,036 0.79 1.06

1978 1,000.2 78.8 1,336 1,032 0.77 1.03

1979 811.0 62.4 2,002 1,680 0.84 2.07

1980 990.6 73.6 1,803 1,651 0.92 1.67

1981 654.0 46.8 2,932 2,251 0.77 3.44

1982 915.7 65.2 2,956 2,119 0.72 2.31

1983878.4 62.8 2,930 2,681 0.92 3.05

1984 946.7 68.5 2,010 1,255 0.62 1.33

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

1986 754.1 54.9 1,808 946 0.52 1.25

1987 431.3 36.6 1,980 1,371 0.69 3.18

1988 809.8 59.5 1,841 738 0.40 0.91

1989 689.9 56.8 1,625 433 0.27 0.63

1990 933.1 69.0 2,099 730 0.35 0.78

1991 258.2 21.0 2,087 939 0.45 3.64

1992 968.9 75.5 1,374 325 0.24 0.34

19931,244.8 91.0 1,271 275 0.22 0.22

1994 1,172.9 87.2 1,489 476 0.32 0.41

1995 1,320.3 94.6 1,142 215 0.19 0.16

1996 1,307.8 94.0 1,157 187 0.16 0.14

1997 1,220.9 88.6 1,581 414 0.26 0.34

1998 1,323.0 94.5 1,045 156 0.15 0.12

1999 1,352.5 96.5 919 128 0.14 0.09

1973 222.1 244 85 0.35 0.38

1974 303.5 357 216 0.61 0.71

1975 429.0 87.8 282 1530.54 0.36

1976 389.6 77.1 815 411 0.50 1.05

1977 423.5 85.1 641 258 0.40 0.61

1978 387.5 75.9 934 339 0.36 0.87

1979 414.0 82.1 1,220 1,170 0.96 2.83

1980 357.8 71.5 1,443 1,338 0.93 3.74

1981 429.1 84.6 1,264 731 0.58 1.70

1982 501.0 96.0 481 205 0.430.41

1983 346.1 69.3 1,316 1,527 1.16 4.41

1984 398.1 79.0 954 626 0.66 1.57

1985 361.4 71.8 1,392 1,051 0.76 2.91

1986 248.1 48.9 1,389 1,188 0.86 4.79

1987 423.6 84.2 827 303 0.37 0.72

1988 492.1 95.7 379 124 0.33 0.25

1989 432.8 84.7 832 288 0.35 0.67

1990 433.1 85.9 849 307 0.36 0.71

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.
C-29

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

VERMONT YANKEE

(continued)

VOGTLE 1, 2

Docket 50-424; 50-425;

NPF-68, -81

1st commercial operation

6/87, 5/89

Type - PWRs

Capacity - 1151, 1154 MWe

WASHINGTON NUCLEAR 2

Docket 50-397; NPF-21

1st commercial operation 12/84

Type - BWR

Capacity - 1107 MWe

WATERFORD

Docket 50-382; NPF-38

1st commercial operation 9/85

Type - PWR

Capacity - 1075 MWe

WATTS BAR 1

Docket 50-390

1st commercial operation 5/96

Type - PWR

Capacity - 1118 MWe

1991 492.394.3 310 118 0.38 0.24

1992 446.8 88.1 921 381 0.41 0.85

1993402.3 80.1 833 217 0.26 0.54

1994 515.8 98.7 220 38 0.17 0.07

1995 462.1 87.0 737 182 0.25 0.39

1996 452.7 85.2 951 231 0.24 0.51

1997 487.1 96.0 260 57 0.22 0.12

1998 383.4 77.9 944 199 0.21 0.52

1999 463.4 91.0 854 176 0.21 0.38

1988 820.4 77.7 1,108 138 0.12 0.17

1989 1,045.8 96.0 427 32 0.07 0.03

1990 1,710.9 82.7 1,602 466 0.29 0.27

1991 1,966.5 89.2 1,357 362 0.27 0.18

1992 2,047.9 90.0 1,262 426 0.34 0.21

19932,060.4 88.3 1,338 367 0.27 0.18

1994 2,170.1 91.31,048 217 0.21 0.10

1995 2,285.4 95.2 953199 0.21 0.09

1996 2,056.8 86.5 1,395 452 0.32 0.22

1997 2,121.1 91.4 994 158 0.16 0.07

1998 2,123.9 92.3 994 162 0.16 0.08

1999 2,106.0 91.5 1,359 229 0.17 0.11

1985 616.0 87.6 755 119 0.16 0.19

1986 616.0 74.4 1,013222 0.22 0.36

1987 639.0 70.8 1,201 406 0.34 0.64

1988 707.7 71.8 1,050 353 0.34 0.50

1989 727.2 78.31,299 492 0.38 0.68

1990 684.7 67.5 1,348 536 0.40 0.78

1991 508.5 50.31,088 387 0.36 0.76

1992 682.365.6 1,489 612 0.41 0.90

1993849.6 79.5 1,385 469 0.34 0.55

1994 803.8 75.2 1,870 866 0.46 1.08

1995 824.7 83.8 1,694 456 0.27 0.55

1996 662.9 82.2 1,453373 0.26 0.56

1997 697.0 72.7 1,218 251 0.21 0.36

1998 789.5 75.31,220 286 0.230.36

1999 694.7 70.0 1,022 155 0.15 0.22

1986 875.7 79.1 1,244 2230.18 0.25

1987 891.8 82.5 959 156 0.16 0.17

1988 784.375.4 1,246 259 0.21 0.33

1989 909.8 82.6 1,306 265 0.20 0.29

1990 1,027.9 92.8 432 47 0.11 0.05

1991 870.6 79.8 1,301 364 0.28 0.42

1992 909.6 83.2 1,213 226 0.19 0.25

19931,088.3 99.4 195 15 0.08 0.01

1994 949.1 87.0 1,167 191 0.16 0.20

1995 927.4 83.4 1,092 153 0.14 0.16

1996 1,064.8 94.2 342 27 0.08 0.03

1997 767.2 71.2 1,186 148 0.130.19

1998 984.1 91.9 282 24 0.09 0.02

1999 849.5 79.6 833 123 0.15 0.14

1997 867.6 83.8 1,103 113 0.10 0.13

1998 1,105.1 99.1 96 30.030.00

1999 943.1 87.2 975 99 0.10 0.10
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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

WOLF CREEK 1

Docket 50-482; NPF-42

1st commercial operation 9/85

Type - PWR

Capacity - 1163 MWe

YANKEE ROWE16

Docket 50-29; DPR-3

1st commercial operation 7/61

Type - PWR

Capacity - (175) MWe

ZION 117, 217

Docket 50-295; 50-304;

DPR-39, -48

1st commercial operation

12/73, 9/74

Type - PWRs

Capacity - (1040), (1040) MWe

1986 832.8 73.3 682 143 0.21 0.17

1987 778.8 71.1 675 138 0.20 0.18

1988 794.7 70.7 1,010 297 0.29 0.37

1989 1,108.4 99.5 186 18 0.10 0.02

1990 940.2 81.0 798 195 0.24 0.21

1991 707.6 71.9 1,010 331 0.33 0.47

1992 1,010.8 86.7 446 78 0.17 0.08

1993940.5 80.6 975 183 0.19 0.19

1994 1,017.2 86.8 1,082 235 0.22 0.23

1995 1,198.0 98.7 242 14 0.06 0.01

1996 980.6 81.2 986 171 0.17 0.17

1997 964.383.8 989 265 0.27 0.27

1998 1,187.3100.0 184 10 0.05 0.01

1999 1,045.390.1 812 148 0.18 0.14

1969 138.3 193 215 1.11 1.55

1970 146.1 355 255 0.72 1.75

1971 173.5 155 90 0.58 0.52

1972 78.7 282 255 0.90 3.24

1973127.1 133 99 0.74 0.78

1974 111.3243205 0.84 1.84

1975 145.1 82.4 249 116 0.47 0.80

1976 152.2 89.8 152 59 0.39 0.39

1977 124.6 73.9 725 356 0.49 2.86

1978 145.0 81.0 565 282 0.50 1.94

1979 149.0 81.6 441 127 0.29 0.85

1980 35.6 22.0 502 213 0.42 5.98

1981 109.0 74.4 515 302 0.59 2.77

1982 108.6 73.4 814 474 0.58 4.36

1983163.5 91.4 395 68 0.17 0.42

1984 124.8 71.4 654 348 0.53 2.79

1985 144.385.3 653211 0.32 1.46

1986 169.7 95.0 384 45 0.12 0.27

1987 138.7 82.7 593 217 0.37 1.56

1988 136.4 85.2 738 227 0.31 1.66

1989 159.4 92.9 496 62 0.12 0.39

1990 101.1 61.5 702 246 0.35 2.43

1991 121.2 72.3162 40 0.25 0.33

1992 0.0 0.0 324 94 0.29 ---

19930.0 0.0 3131630.52 ---

1994 0.0 0.0 222 156 0.70 ---

1995 0.0 0.0 191 78 0.41 ---

1996 0.0 0.0 239 95 0.40 ---

1997 0.0 0.0 323 65 0.20 ---

1998 0.0 0.0 28346 0.16 ---

1999 0.0 0.0 832 0.02 ---

1974 425.371.1 306 56 0.18 0.13

1975 1,181.5 74.9 436 127 0.29 0.11

1976 1,134.9 61.9 774 571 0.74 0.50

1977 1,358.6 75.0 784 1,003 1.28 0.74

1978 1,613.5 80.2 1,104 1,017 0.92 0.63

1979 1,238.0 67.6 1,472 1,274 0.87 1.03

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 64.31,575 2,103 1.34 1.77

16 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.

17 Zion 1, 2 was shut down 12/97 and is no longer included in the count of operating reactors.
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Thirty-Second Annual Report, 1999 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

19831,222.3 69.4 1,285 1,311 1.02 1.07

1984 1,389.9 69.6 1,110 786 0.71 0.57

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

1986 1,462.0 73.2 967 474 0.49 0.32

1987 1,337.0 71.0 1,046 653 0.62 0.49

1988 1,549.1 78.31,926 1,260 0.65 0.81

1989 1,514.1 77.6 1,282 624 0.49 0.41

1990 860.4 46.9 1,385 696 0.50 0.81

1991 1,125.7 58.2 902 1730.19 0.15

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

19931,458.2 70.9 1,772 643 0.36 0.44

1994 1,224.9 59.9 1,176 306 0.26 0.25

1995 1,471.6 72.4 1,807 797 0.44 0.54

1996 1,538.4 75.8 1,567 437 0.28 0.28

1997 123.2 7.1 924 119 0.13 0.97

1998 0.0 0.0 246 12 0.05 ---

1999 0.0 0.0 67 4 0.06 ---

ZION 117, 217

(continued)

17 Zion 1, 2 was shut down 12/97 and is no longer included in the count of operating reactors.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

This page intentionally left blank.
D-1

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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DOSE PERFORMANCE INDICATORS BY REACTOR SITE

1973 - 1999

Appendix D

NOTE: Appendix D contains data on operating plants as well as plants which are no longer in commercial operation.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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D-7

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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D-9

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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D-11

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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D-13

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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D-15

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-20

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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D-21

Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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D-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Thirty-Second Annual Report, 1999 Occupational Radiation Exposure at NRC Licensed Facilities

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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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D-36

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-Second Annual Report, 1999

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