Occupational Radiation

Exposure at Commercial

Nuclear Power Reactors

and Other Facilities

1998

NUREG-0713

Vol. 20

Thirty-First Annual Report

U.S. Nuclear Regulatory Commission

Office Nuclear Regulatory Research

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

TI ED STATES

NUCLEAR REGULATORY COMM SI S

OI N

Occupational Radiation Exposure

at Commercial Nuclear Power

Reactors and other Facilities

1998

NUREG-0713

Vol. 20

Thirty-First Annual Report

Division of Regulatory Applications

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

Manuscript Completed: December 1999

Date Published: December 1999

Prepared by:

M. L. Thomas, D. A. Hagemeyer*

Science Applications International Corporation

301 Laboratory Road

Oak Ridge, TN 37830

*
ii

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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.

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-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ABSTRACT

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 1998

annual reports submitted by six of the seven categories1 of NRC licensees subject to the

reporting requirements of 10 CFR 20.2206. Because there are no geologic repositories for

high-level waste currently licensed, only six categories will be considered in this report.

Annual reports for 1998 were received from a total of 288 NRC licensees, of which 105 were

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

submitted by the 288 licensees indicated that 132,032 individuals were monitored, 65,070 of

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

individuals was 16,383 person-rem which represents a 17% decrease from the 1997 value.

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

measurable dose of 0.25 rem for 1998. 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 1998, the annual collective dose per reactor for light water reactor (LWRs) licensees was 125

person-rem. This represents a 26% decrease from the value reported for 1997. The annual

collective dose per reactor for boiling water reactors (BWRs) was 190 person-rem and, for

pressurized water reactors (PWRs), it was 92 person-rem.

Analyses of transient worker data indicate that 23,061 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 1998,

the average measurable dose calculated from reported data was 0.21 rem. The corrected dose

distribution resulted in an average measurable dose of 0.25 rem.

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”.
iv

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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:

Mary L. Thomas: (301) 415-6230

E-Mail Address: mlt1@nrc.gov

REIRS Project Manager

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, D.C. 20555
v

Thirty-First Annual Report, 1998 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 (LWR) 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-First Annual Report, 1998

NUREG-0713

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

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

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

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

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

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

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

4.2.5 Percent of Maximum Dependable Capacity Achieved .......................................4-6

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

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

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

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

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

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

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

5.3 Career Dose Statistics 1977-1998 ..............................................................................5-5

5.3.1 Compilation of the Data ......................................................................................5-5

5.3.2 Limitations of the Data........................................................................................5-6

5.4 Career Dose Distributions by Dose and Career Length ..............................................5-7

5.5 Career Dose Distributions by Age and Sex .................................................................5-9

5.6 Patterns of Accumulation of Career Doses at Reactor Facilities ...............................5-14

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

TABLE OF CONTENTS (Continued)

Page
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Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE OF CONTENTS (Continued)

Page

APPENDIX A - ANNUAL TEDE FOR NON-REACTOR NRC LICENSEES, 1998................... A-1

APPENDIX B - ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES, 1998..................................................................................................... B-1

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

1969-1998 ............................................................................................................................... C-1

APPENDIX D - DOSE PERFORMANCE INDICATORS BY REACTOR SITE ........................ D-1
viii

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

Figure 3.1 Average Annual Values at Industrial Radiography Facilities 1973-1998 .............3-9

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

Single Location Licensees 1994-1998 .................................................................3-10

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

Multiple Location Licensees 1994-1998 ...............................................................3-10

Figure 3.4 Average Annual Values at Manufacturing and Distribution

Facilities 1973-1998 .............................................................................................3-12

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

Manufacturing and Distribution Licensees 1994-1998 ......................................3-13

Figure 3.6 Collective TEDE Distribution by Dose Range, Limited

Manufacturing and Distribution Licensees 1994-1998 ......................................3-13

Figure 3.7 Average Annual Values at Low-Level Waste Disposal

Facilities 1982-1998 ..........................................................................................3-14

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

Disposal Licensees 1994-1998 ........................................................................3-15

Figure 3.9 Average Annual Values at Independent Spent Fuel Storage

Facilities 1982-1998 ..........................................................................................3-16

Figure 3.10 Collective TEDE Distribution by Dose Range, Independent Spent

Fuel Storage Licensees 1994-1998..................................................................3-17

Figure 3.11 Average Annual Values at Fuel Cycle Licenses 1973-1998 ..............................3-19

Figure 3.12 Collective TEDE Distribution by Dose Range, Fuel Cycle

Licensees 1994-1998 .......................................................................................3-20

Figure 3.13 Collective TEDE Distribution by Dose Range, Reactor

Licensees 1994-1998 .......................................................................................3-20

Figure 4.1 Average Collective Dose and Number of Workers per

Reactor 1973-1998 ..............................................................................................4-9

Figure 4.2 Number of Operating Reactors and Gross Electricity

Generated 1973-1998 .......................................................................................4-10

LIST OF FIGURES

Page
ix

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Figure 4.3 Average Measurable Dose per Worker and Collective Dose per

Megawatt-Year 1973-1998 ................................................................................ 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 1987-1998 ............................................................................4-14

Figure 5.1 Mean Annual Dose to Workers with Measurable Dose at

Reactor Licensees by Age Group 1986-1998....................................................5-15

Figure 5.2 Average Age of Workers with Measurable Dose at Reactor

Licensees From 1969-1998 with Projections to 2020........................................5-17

LIST OF FIGURES (Continued)

Page

Table 3.1 Annual Exposure Data for Certain Categories of

Licensees 1989-1998 .............................................................................................3-3

Table 3.2 Distribution of Annual Collective TEDE by License

Category 1998 ........................................................................................................3-5

Table 3.3 Summary of Annual Dose Distributions for Certain NRC

Licensees 1968-1998 .............................................................................................3-6

Table 3.4 Annual Exposure Information for Industrial

Radiographers 1996-1998 ......................................................................................3-7

Table 3.5 Annual Exposure Information for Manufacturers and

Distributors 1996-1998 ...........................................................................................3-8

Table 3.6 Annual Exposure Information for Fuel Cycle Licenses 1996-1998 ......................3-18

Table 3.7 Intakes by Licensee Type and Radionuclide

Mode of Intake - Ingestion and Other 1998 .........................................................3-22

Table 3.8 Intakes by Licensee Type and Radionuclide

Mode of Intake - Inhalation 1998 .........................................................................3-23

LIST OF TABLES
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

LIST OF TABLES (Continued)

Table 3.9 Collective and Average CEDE by Licensee 1998................................................3-25

Table 3.10 Internal Dose (CEDE) Distribution, 1994 - 1998 ..................................................3-26

Table 4.1 Summary of Information Reported by Commercial

Boiling Water Reactors 1973-1998.........................................................................4-2

Table 4.2 Summary of Information Reported by Commercial

Pressurized Water Reactors 1973-1998 .............................................................4-3

Table 4.3 Summary of Information Reported by Commercial

Light Water Reactors 1973-1998.........................................................................4-4

Table 4.4 Summary Distribution of Annual Whole Body Doses at

Commercial Light Water Reactors 1977-1998 ....................................................4-7

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

of Collective TEDE per BWR 1996-1998...........................................................4-15

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

of Collective TEDE per PWR 1996-1998...........................................................4-16

Table 5.1 Effects of Transient Workers on Annual Statistical Compilations, 1998 ..............5-2

Table 5.2 Career Dose Distributions by Dose and Career Length at

Reactor Facilities, 1977-1998 ..............................................................................5-8

Table 5.3 Average Career Lengths and Doses by Career Length, 1977-1998 ...................5-9

Table 5.4(a) Career Dose Distributions by Age and Year of Termination

For Personnel with Measurable Dose, 1977-1998 ............................................5-10

Table 5.4(b) Career Dose Distributions by Age and Year of Termination

For Personnel with Measurable Dose, 1977-1998 ............................................ 5-11

Table 5.5 Average Career Values by Sex and Year of Termination

For Personnel of Known Age with Measurable Dose, 1977-1998 .....................5-13

Table 6.1 Occupational Exposures in Excess of Regulatory Limits, 1994-1998 .................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 1998 ..............6-8
xi

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

A number of NRC licensees have inquired as to how the occupational radiation exposure data

that are compiled from the individual exposure reports required by § 20.2206 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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xiii

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FOREWORD

NUREG-0713, Volume 20, summarizes the 1998 occupational radiation exposure data

maintained in the U.S. Nuclear Regulatory Commission’s Radiation Exposures Information

Reporting System (REIRS). Certain classes of licensees are required to annually report

individual exposures in accordance with 10 CFR 20.2206.

This volume also contains an updated analysis of the career dose distribution from the 1989

NUREG-0713, Volume 11. This analysis is in sections 5.3, 5.4, 5.5, and 5.6, and now includes

those individuals who had terminated their employment before 1994, those individuals for whom

individual exposure reports were submitted after 1994, and individuals for whom historical data

were submitted as a result of voluntary generic letter 94-04.

With the publication of this volume information on collective dose and number of personnel by

work function and employee type will no longer be included. In addition, the analysis of high

dose plants or plant rankings by collective dose per reactor will no longer be included. These

decisions were made after publication of the 1996 report in order to produce a more timely and

efficient document. These data are available from Nuclear Energy Agency’s (NEA) Information

System on Occupational Exposure by plant and are included by country in NEA’s annual report,

“Occupational Exposure at Nuclear Power Plants.”

Thomas L. King, Director

Division of Risk Analysis and Applications

Office of Nuclear Regulatory Research
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Thirty-First Annual Report, 1998 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,

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

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-First Annual Report, 1998

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of Energy (DOE), is collected and published

by DOE’s Office of Health, a division of

Environment, Safety and Health, in

Germantown, Maryland.

In 1982 and 1983, paragraph 20.408(a) of

Title 10 of the Code of Federal Regulations

was amended to require three additional

categories of NRC licensees to submit annual

statistical exposure reports and individual

termination exposure reports. The new

categories are (1) geologic repositories for

high-level radioactive waste, (2) independent

spent fuel storage installations, and (3)

facilities for the land disposal of low-level

radioactive waste. Therefore, this document

presents the exposure information that was

reported by NRC licensees representing two

of these new categories. (There are no

geologic repositories for high-level waste

currently licensed.)

This report and each of the predecessors

summarizes 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 fifth 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 on-line or download information to

their systems for further analysis. Software,

such as REMIT, 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.saic.com/home/

nrc_rad

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 environment in

which 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”* 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.

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

* The number of workers with measurable dose includes any individual with a TEDE 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-First Annual Report, 1998

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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 in order

to provide the most comprehensive analysis of

all the data available. The apparent

discrepancies among the various tables are a

necessary side-effect of this endeavor.

Also, it should again be pointed out that this

report contains information reported by NRC

licensees only. 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

States4 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 nonoccupational 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.

4 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 12/31/98, there are 30 Agreement States.
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3.1 DEFINITION OF TERMS

AND SOURCES OF DATA

3.1.1 Statistical Summary Reports

The individual’s total effective dose equivalent

(TEDE, as defined in § 20.1003) is reported,

so that the dose distributions may be

determined directly from the individual’s

exposure. The 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.

ANNUAL PERSONNEL MONITORING

REPORTS - 10 CFR 20.2206

For licensees submitting under the revised 10

CFR 20.2206, the total number of workers

was determined from the number of unique

personal identification numbers submitted per

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

Section 3
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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each of the dose ranges by the midpoint of the

corresponding dose range. This assumes that

the midpoint of the range is equal to the

arithmetic mean of the individual doses in the

range. 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 1998 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 1998

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
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Thirty-First Annual Report, 1998 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

1989 - 1998

Industrial 1989 276 6,745 4,352 2,067 0.31 0.47

Radiography 1990 258 6,523 4,458 2,120 0.33 0.48

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

 03310 1992 246 6,703 4,265 1,864 0.28 0.44

 03320 1993 176 4,721 3,007 1,596 0.34 0.53

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

1995 139 3,530 2,465 1,338 0.38 0.54

1996 144 3,631 2,537 1,385 0.38 0.55

1997 143 3,436 2,454 1,291 0.38 0.53

1998 141 4,940 3,439 1,859 0.38 0.54

Manufacturing 1989 48 4,554 2,345 770 0.17 0.33

and Distribution 1990 58 4,203 2,279 693 0.16 0.30

1991 59 4,930 1,952 722 0.15 0.37

1992 67 5,210 2,250 784 0.15 0.35

 02500 1993 58 4,913 2,254 680 0.14 0.30

 03211 1994 44 2,941 1,251 580 0.20 0.46

 03212 1995 36 2,666 1,222 595 0.22 0.49

 03214 1996 36 2,628 1,239 556 0.21 0.45

1997 31 1,151 665 397 0.34 0.60

1998 30 1,963 645 401 0.20 0.62

Low-Level 1989 2 925 119 35 0.04 0.29

Waste Disposal 1990 2 784 115 26 0.03 0.23

1991 2 905 147 39 0.04 0.27

1992 2 467 82 37 0.08 0.45

 03231 1993 2 432 76 21 0.05 0.27

1994 2 202 83 22 0.11 0.27

1995 2 212 56 8 0.04 0.15

1996 2 165 67 8 0.05 0.12

1997 2 185 50 5 0.03 0.11

1998 1 27 13 1 0.05 0.10

Independent 1989 2 190 102 33 0.17 0.32

Spent Fuel 1990 2 56 22 6 0.11 0.27

Storage 1991 2 41 24 4 0.10 0.17

1992 2 290 85 11 0.04 0.13

 23100 1993 2 135 52 14 0.10 0.26

1994 1 158 89 42 0.27 0.47

1995 1 104 49 51 0.49 1.04

1996 1 97 53 54 0.56 1.02

1997 1 55 24 6 0.11 0.24

1998 1 53 21 3 0.05 0.12

Fuel Cycle 1989 8 11,583 2,992 243 0.02 0.08

 Licenses - 1990 11 14,505 3,871 422 0.03 0.11

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

 Processing and 1992 11 8,439 5,061 545 0.06 0.11

 Uranium Enrich. 1993 8 9,649 2,611 339 0.04 0.13

1994 8 3,596 2,847 1,147 0.00 0.40

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

 21210 1996 8 4,369 3,061 878 0.20 0.29

 21200 1997 10 11,214 3,910 1,006 0.09 0.26

1998 10 10,684 3,613 950 0.09 0.26

Commercial 1989 113 188,477 100,080 35,930 0.19 0.36

Light Water 1990 116 187,081 98,802 36,607 0.20 0.37

Reactors** 1991 115 179,043 91,085 28,528 0.16 0.31

1992 114 183,900 94,317 29,298 0.16 0.31

 41111 1993 114 169,862 86,187 26,365 0.16 0.31

1994 109 138,595 69,668 21,695 0.16 0.31

1995 109 133,066 70,986 21,674 0.16 0.31

1996 109 127,420 68,182 18,874 0.15 0.28

1997 109 126,689 68,188 17,136 0.14 0.25

1998 105 114,365 57,339 13,169 0.12 0.23

Grand Totals 1989 449 212,474 109,990 39,078 0.18 0.36

and Averages 1990 447 213,152 109,547 39,874 0.19 0.36

1991 437 203,441 101,786 31,831 0.16 0.31

1992 442 205,009 106,060 32,538 0.16 0.31

1993 360 189,712 94,187 29,014 0.15 0.31

1994 303 148,378 75,945 24,901 0.17 0.33

1995 295 143,684 77,737 24,884 0.17 0.32

1996 300 138,310 75,139 21,755 0.16 0.29

1997 296 142,730 75,291 19,841 0.14 0.26

1998 288 132,032 65,070 16,383 0.12 0.25

* 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, although some of them may not have been in operation for a full year. 1994 - 1998 data are only for

reactors that completed a full year of operation during the year. Reactor data have been corrected to account for the multiple counting of

transient reactor workers. (see Section 5).
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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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

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 were 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 90% of the reported workers

continue to be monitored by nuclear power

facilities where they received approximately

80% of the total collective dose in 1998.

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 13 years the percentage of

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

number of workers receiving an annual

exposure in excess of 5 rem had been

<0.01% since 1985. 1998 is the first year in

the last 10 years where an individual received

a TEDE or whole body dose in excess of 12

rem. This incident occurred at a multi-site

radiographer licensee and is discussed in

Section 6.
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INDUSTRIAL RADIOGRAPHY

Single Location (26)

Multiple Location (115)

Total (141)

MANUFACTURING AND

DISTRIBUTION

“A” - Broad (5)

Limited (25)

Total (30)

LOW-LEVEL WASTE DISPOSAL

Total (1)

INDEPENDENT SPENT FUEL

STORAGE

Total (1)

FUEL CYCLE LICENSES**

Total (10)

COMMERCIAL POWER REACTORS***

Boiling Water (36)

Pressurized Water (69)

Total (105)

GRAND TOTALS

369 84 8

4,571 3,355 1,851

4,940 3,439 1,859

1,177 380 367

786 265 34

1,963 645 401

27 13 1

53 21 3

10,684 3,613 950

61,583 32,864 6,822

86,841 38,480 6,347

148,424 71,344 13,169

166,091 79,075 16,383

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

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

***Includes all reactors in commercial operation for a full year during 1998.

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

285 64 10 8 1 1

1,216 1,037 560 584 329 236 435 118 36 14 4 1 1

1,501 1,101 570 592 330 236 436 118 36 14 4 1 1

797 111 39 46 24 28 53 47 32

521 166 54 30 10 5

1,318 277 93 76 34 33 53 47 32

14 5 8

32 9 10 2

7,071 1,937 601 444 225 170 204 28 4

28,719 16,077 7,623 5,321 2,209 921 700 13

48,361 20,962 9,566 5,146 1,720 640 427 19

77,080 37,039 17,189 10,467 3,929 1,561 1,127 32

87,016 40,368 18,471 11,581 4,518 2,000 1,820 225 72 14 4 1 1

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 7.00 >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)

TABLE 3.2

Distribution of Annual Collective TEDE by License Category

1998
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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1968 36,836 97.2% 99.5% 3

1969 31,176 96.5% 99.5% 7

1970 36,164 96.1% 99.4% 0

1971 36,311 96.3% 99.3% 1

1972 44,690 95.7% 99.5% 8

1973 67,862 95.0% 99.5% 1

1974 85,097 96.4% 99.7% 1

1975 78,713 94.8% 99.5% 1

1976 92,773 95.0% 99.6% 3

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

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

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

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

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

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

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

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

1985 212,217 201,339 97.5% >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 234,045 214,781 98.9% >99.99% (3) 0

1991 219,229 206,732 99.4% >99.99% (2) 0

1992 222,728 205,009 99.4% >99.99% (1) 0

1993 209,386 189,711 99.5% >99.99% (2) 0

1994 179,803 152,834 99.5% >99.99% (1) 0

1995 179,176 143,684 99.5% >99.99% (1) 0

1996 173,536 137,968 99.5% >99.99% (1) 0

1997 180,677 128,466 99.5% 100% (0) 0

1998 166,091 130,852 99.6% >99.99% (6) 1

Percent of Percent of Number of

 Individuals Individuals Individuals

Reported Corrected With Doses With Doses With Doses

Year Number Number < 2 rem** < 5 rem** >12 rem**

Total Number of Monitored

Persons

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

** Data for 1977-1998 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 1985-1998.

TABLE 3.3

Summary of Annual Dose Distributions for Certain* NRC Licensees

1968 - 1998
3-7

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 141 radiography

licensees in 1998. Table 3.4 summarizes the

reported data for the two types of radiography

licenses for 1998 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 30% 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 1998 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

1996 - 1998

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

1996

1997

1998

27

117

144

27

116

143

26

115

141

291

3,340

3,631

296

3,140

3,436

369

4,571

4,940

60

2,477

2,537

84

2,370

2,454

84

3,355

3,439

10

1,375

1,385

10

1,281

1,291

8

1,851

1,859

0.17

0.56

0.55

0.12

0.54

0.53

0.09

0.55

0.54
3-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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 1998. Both the collective TEDE and

the number of workers with measurable TEDE

increased from 1997 to 1998, resulting in only

a small increase in the average measurable

TEDE. 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 up

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. The Limited licenses are usually

issued to smaller firms requiring a more

restrictive license. Some 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,

diagnosis, and therapy. 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.

Table 3.5 presents the annual data that were

reported by the two types of licensees for

1998 and the previous 2 years. Looking at the

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

1996

1997

1998

7

29

36

5

26

31

5

25

30

2,018

610

2,628

496

655

1,151

1,177

786

1,963

987

252

1,239

386

279

665

380

265

645

522

34

556

364

33

397

367

34

401

0.53

0.13

0.45

0.94

0.12

0.60

0.97

0.13

0.62

TABLE 3.5

Annual Exposure Information for Manufacturers and Distributors

1996 - 1998
3-9

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 3.1. Average Annual Values at Industrial Radiography Facilities 1973 - 1998

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

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-First Annual Report, 1998

NUREG-0713

1998 1997 1996 1995 1994

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

89%

57%

23%

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%

1998 1997 1996 1995 1994

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

83%

62%

94%

30%

> 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

FIGURE 3.3. Collective TEDE Distribution by Dose Range

Industrial Radiographer – Multiple Location Licensees
3-11

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 1998. 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 and 1998,

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 1998.

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, only one licensee reported in this

category since Chem Nuclear is now an

Agreement State licensee. Table 3.1

summarizes the data reported for 1989

through 1998. Appendix A summarizes the

exposure information reported by this licensee

in 1998.
3-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

FIGURE 3.4. Average Annual Values at Manufacturing and Distribution Facilities

1973 - 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

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-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1998 1997 1996 1995 1994

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%

81%

97%

56%

> 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%

1998 1997 1996 1995 1994

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

0%

> 1.000

>0.500

> 0.250

> 0.100

79%

62%

7%

82%

 62%

36%

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 Licenses

FIGURE 3.6. Collective TEDE Distribution by Dose Range

Limited Manufacturing and Distribution Licensees
3-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

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

1982 - 1998

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

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)
3-15

Thirty-First Annual Report, 1998 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

1998. Because only two licensees have been

involved in this activity over the past 10 years,

the numbers have remained fairly stable from

1984 through 1998 with the exception of the

average measurable TEDE, which peaked in

1992 and has decreased by 75% since then.

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

above 0.100 rem have been decreasing in

every dose range since 1994.

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.

Eighteen licenses have been issued for these

activities. Eleven are at nuclear power plants,

allowing on-site temporary storage of fuel.

These licensees report the dose from fuel

1998 1997 1996 1995 1994

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

0%

> 1.000

>0.500

> 0.250

> 0.100

92%

79%

34%

87%

 67%

65%

86%

39%

41%

0%

21%

0%

0%

0%

0%

10%

80% 86%

0%

0%

0% 0%

0%

45%

FIGURE 3.8. Collective TEDE Distribution by Dose Range

Low-Level Waste Disposal Licensees
3-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

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

1982 - 1998

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

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-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

storage activities along with the dose from

reactor operations at these sites. Out of the

seven remaining licenses, only one is active

and is located at a facility that is independent

of a reactor site. Only this licensee is included

in this analysis of ISFSI facilities for 1998.

Appendix A summarizes the exposure

information reported by this installation.

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 1994 to 1998. The percentages for each

dose range have decreased significantly since

1996.

1998 1997 1996 1995 1994

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

26%

> 1.000

>0.500

> 0.250

> 0.100

97%

92%

70%

88%

 81%

88%

98%

61%

48%

0%

0%

0%

96%

85%

0% 0%

23%

74%

61%

99%

99%

 83%

97%

94%

FIGURE 3.10. Collective TEDE Distribution by Dose Range

Independent Spent Fuel Storage Licensees
3-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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 and 1998, 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

1994 to 1998. 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 1998, 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 1998.

Year

Type of

License

Number

of

Licensees

Number of

Monitored

Individuals

Workers

With

Meas.

TEDE

Fuel Cycle

Fuel Cycle

Fuel Cycle

1996

1997

1998

8

10

10

4,369

11,214

10,684

3,061

3,910

3,613

Collective

TEDE

(personrem)

878

1,006

950

Average

Meas.

TEDE

(rem)

Collective

DDE

(personrem)

Average

Meas.

DDE

(rem)

Collective

CEDE

(personrem)

Average

Meas.

CEDE

(rem)

0.29

0.26

0.26

161

197

204

0.08

0.08

0.08

711

800

742

0.32

0.30

0.29

Workers

With

Meas.

DDE

Workers

With

Meas.

CEDE

1,907

2,545

2,412

2,260

2,684

2,520

TABLE 3.6

Annual Exposure Information for Fuel Cycle Licenses

1996 - 1998
3-19

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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

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-First Annual Report, 1998

NUREG-0713

1998 1997 1996 1995 1994

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

20%

> 1.000

>0.500

> 0.250

> 0.100

96%

89%

90%

47%

71%

8%

69%

9%

94%

44%

84%

57%

87%

95%

 79%

96%

74%

10%

8%

39%

37%

68%

84%

94%

FIGURE 3.12. Collective TEDE Distribution by Dose Range

Fuel Cycle Licensees

FIGURE 3.13. Collective TEDE Distribution by Dose Range

Reactor Licensees

1998 1997 1996 1995 1994

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

6%

> 1.000

>0.500

> 0.250

> 0.100

95%

64%

32%

 83%

9%

95%

63%

33%

 83%

6%

94%

59%

29%

 81%

5%

93%

56%

25%

 78%

4%

92%

52%

22%

 76%
3-21

Thirty-First Annual Report, 1998 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 all reports received from reactor facilities

that were in commercial operation for the

years 1989 through 1998. This table includes

reactors that may not have been in

commercial operation for a full year. Data for

1989 through 1998 do not include reactors

that have been shut down. 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 1994 to 1998. 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.

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-First Annual Report, 1998

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 1998. The data

are categorized by licensee type and are

listed in order of radionuclide and pulmonary

clearance class. Table 3.7 lists the intakes

Mode Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries

Collective

Intake in

Microcuries

(sci. notification)

Power Reactors

Manufacturer and Distributor

Fuel Cycle Licensees

Power Reactors

Injection

Ingestion

41111

03211

21200

21210

21210

21200

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

41111

Co-60

Mo-99

U-234

U-234

U-235

U-238

Alpha

Am-241

Ce-141

Cm-242

Cm-243/242

Co-57

Co-58

Co-60

Cr-51

Cs-137

Fe-55

Fe-59

Mn-54

Nb-95

Pu-238

Pu-239/240

Pu-241

Ru-106

Zn-65

Zr-95

1

1

2

1

1

1

4

2

1

2

2

2

8

25

2

3

1

1

10

1

2

2

2

1

1

1

0.449

4.080

0.006

0.003

0.000

0.000

0.002

0.000

0.004

0.000

0.000

0.000

1.071

352.000

851.000

0.090

0.014

1.000

127.067

0.063

0.000

0.000

0.005

0.780

1.600

0.048

4.49E-01

4.08E+00

6.00E-03

3.03E-03

1.18E-04

4.25E-04

1.90E-03

3.73E-04

3.68E-03

2.74E-06

1.29E-04

3.70E-05

1.07E+00

3.52E+02

8.51E+02

9.00E-02

1.41E-02

1.00E+00

1.27E+02

6.30E-02

2.67E-04

9.36E-05

5.43E-03

7.80E-01

1.60E+00

4.80E-02

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

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

10 CFR 20.2206.

*

TABLE 3.7

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

1998
3-23

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Licensee Type

Program

Code Radionuclide

Number of

Intake

Records*

Collective

Intake in

Microcuries

Collective

Intake in

Microcuries

(sci. notification)

Nuclear Pharmacies

Manufacturing and Distribution

Uranium Enrichment

Fuel Fabrication

02500

03211

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

21210

44

1

8

46

97

1

94

502

3

35

1

1

1

94

160

1

94

94

2

164

1

2

1

156

1

156

1

181

1

548

445

2564

10

1035

226

141

80

1799

5.653

0.238

4.141

0.000

0.055

0.000

0.000

0.486

0.000

0.000

0.000

0.000

0.000

0.000

0.000

0.000

0.000

0.001

0.000

0.000

0.000

0.000

0.000

0.001

0.000

0.000

0.000

0.001

0.000

0.828

0.104

6.100

0.001

0.140

0.003

0.047

0.156

0.542

5.65E+00

2.38E-01

4.14E+00

2.86E-04

5.45E-02

7.03E-06

6.37E-05

4.86E-01

2.45E-06

1.48E-04

2.74E-08

5.78E-07

1.42E-07

1.46E-05

2.62E-04

1.42E-04

4.39E-05

5.03E-04

1.21E-05

1.73E-04

2.27E-06

1.20E-04

2.64E-09

5.11E-04

1.16E-07

2.43E-04

5.28E-09

9.88E-04

2.28E-07

8.28E-01

1.04E-01

6.10E+00

8.85E-04

1.40E-01

3.06E-03

4.67E-02

1.56E-01

5.42E-01

Pulmonary

Clearance

Class

I-131

I-125

I-131

Th-230

U-234

U-234

Am-241

Co-60

Cs-137

Eu-152

Np-237

Pa-234

Pu-234

Pu-238

Pu-239

Pu-239

Pu-240

Ra-224

Sr-90

Sr-90

Tc-99

Tc-99

Th-228

Th-228

Th-230

Th-230

Th-232

Th-232

Th-234

U-234

U-234

U-234

U-235

U-235

U-236

U-238

U-238

U-238

D

D

D

W

D

Y

W

Y

D

W

W

W

W

W

W

Y

W

W

D

Y

D

W

W

Y

W

Y

W

Y

Y

D

W

Y

D

Y

Y

D

W

Y

TABLE 3.8

Intake by Licensee Type and Radionuclide Mode of Intake – Inhalation

1998
3-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

Collective

Intake in

Microcuries

Collective

Intake in

Microcuries

Licensee Type (sci. notification)

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

41111

41111

41111

41111

3

3

43

1

2

1

35

35

8

2

97

1

1

281

2

4

10

69

19

2

2

88

2

1

26

5

2

18

22

6

37

4

7

2

22

6

29

1

6

2

11

3

6

14

0.062

0.001

0.139

0.023

0.030

0.288

0.057

0.310

0.000

0.000

2,128.836

0.065

0.027

26,983.911

0.523

1.037

0.125

70.353

0.362

0.243

0.134

1,488.324

0.085

0.028

61.118

10,120.060

0.165

134.959

0.000

0.000

0.359

0.000

0.000

0.000

0.067

0.003

16.308

0.000

0.001

0.000

0.423

1.063

32.559

0.624

Pulmonary

Clearance

Class

Ag-110m

Alpha

Am-241

Ba-140

Ce-141

Ce-141

Cm-242

Cm-243

Cm-243/244

Co-57

Co-58

Co-60

Co-60

Co-60

Cr-51

Cr-51

Cs-134

Cs-137

Cs-137

Fe-55

Fe-59

I-131

I-133

La-140

Mn-54

Mn-54

Nb-95

Nb-95

Np-237

Pu-238

Pu-238

Pu-239

Pu-239

Pu-239/240

Pu-240

Pu-241

Pu-241

Pu-242

Sr-90

TOTAL

Zn-65

Zr-95

Zr-95

Zr-95

Y

Y

W

D

W

Y

W

W

W

Y

Y

D

O

Y

W

Y

D

D

Y

D

W

D

D

W

W

Y

W

Y

W

W

Y

W

Y

W

Y

W

Y

W

D

D

Y

D

W

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.

*

6.20E-02

1.47E-03

1.39E-01

2.30E-02

3.03E-02

2.88E-01

5.67E-02

3.10E-01

2.03E-04

4.11E-06

2.13E+03

6.50E-02

2.70E-02

2.70E+04

5.23E-01

1.04E+00

1.25E-01

7.04E+01

3.62E-01

2.43E-01

1.34E-01

1.49E+03

8.50E-02

2.80E-02

6.11E+01

1.01E+04

1.65E-01

1.35E+02

3.80E-04

4.28E-05

3.59E-01

3.66E-05

1.27E-04

1.04E-05

6.70E-02

2.50E-03

1.63E+01

2.00E-08

1.09E-03

6.10E-05

4.23E-01

1.06E+00

3.26E+01

6.24E-01

TABLE 3.8 (continued)

Intake by Licensee Type and Radionuclide Mode of Intake – Inhalation

1998
3-25

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 3.9

Collective and Average CEDE by Licensee

1998

Nuclear Pharmacies EASTERN ISOTOPES, MD MD-03-068-01* 6 0.010 0.002

02500 NORTHERN VIRGINIA ISOTOPES, INC. 45-25221-01MD 7 0.008 0.001

SYNCOR INTERNATIONAL CORPORATION 04-26507-01MD 13 0.296 0.023

Total 26 0.314 0.012

Manufacturing and Distribution MALLINCKRODT MEDICAL INC. 24-04206-01 8 0.164 0.021

03211 Total 8 0.164 0.021

Uranium Enrichment USEC - PADUCAH GDP-1 28 0.040 0.001

21200 USEC - PORTSMOUTH GDP-2 30 0.202 0.007

Total 58 0.242 0.004

Fuel Fabrication FRAMATOME COGEMA FUEL SNM-1168 107 8.433 0.079

21210 BWX TECHNOLOGIES, INC. SNM-0042 237 163.865 0.691

COMBUSTION ENGINEERING INC. SNM-0033 164 121.155 0.739

GE NUCLEAR ENERGY SNM-1097 810 148.546 0.183

NUCLEAR FUEL SERVICES, INC. SNM-0124 483 56.751 0.117

SIEMENS POWER CORP. NUCLEAR DIVISION SNM-1227 366 90.994 0.249

WESTINGHOUSE ELECTRIC COMPANY SNM-1107 295 152.009 0.515

Total 2,462 741.753 0.301

Independent Spent Fuel GENERAL ELECTRIC CO. SNM-2500 1 0.001 0.001

Storage Installation

23100 Total 1 0.001 0.001

Reactors ARKANSAS DPR-51 5 0.222 0.044

41111 BIG ROCK POINT DPR-06 2 0.024 0.012

BROWNS FERRY DPR-33 12 0.761 0.063

BRUNSWICK DPR-62 80 0.387 0.005

CALLAWAY NPF-30 40 0.589 0.015

CALVERT CLIFFS DPR-53 8 0.537 0.067

CATAWBA NPF-35 6 0.085 0.014

COMANCHE PEAK NPF-87 1 0.023 0.023

COOPER STATION DPR-46 19 0.053 0.003

DAVIS-BESSE NPF-03 19 0.300 0.016

DRESDEN DPR-19 2 0.193 0.097

DUANE ARNOLD DPR-49 1 0.011 0.011

FARLEY NPF-02 6 0.077 0.013

FERMI NPF-43 1 0.015 0.015

FT. CALHOUN DPR-40 1 0.023 0.023

HADDAM NECK DPR-61 2 0.046 0.023

HARRIS NPF-63 9 0.083 0.009

HATCH DPR-57 3 0.058 0.019

INDIAN POINT DPR-26 1 0.030 0.030

LIMERICK NPF-39 4 0.220 0.055

MAINE YANKEE DPR-36 31 0.375 0.012

MILLSTONE POINT 1 DPR-21 3 0.030 0.010

MONTICELLO DPR-22 5 0.101 0.020

NINE MILE POINT DPR-63 37 0.641 0.017

NORTH ANNA NPF-07 3 0.047 0.016

OCONEE DPR-38 8 0.121 0.015

OYSTER CREEK DPR-16 126 0.650 0.005

PALISADES DPR-20 55 1.851 0.034

PEACH BOTTOM DPR-44 1 0.010 0.010

PILGRIM DPR-35 1 0.001 0.001

POINT BEACH DPR-24 3 0.053 0.018

RIVER BEND NPF-47 3 0.037 0.012

ROBINSON DPR-23 1 0.002 0.002

SAN ONOFRE DPR-13 14 0.182 0.013

SEQUOYAH DPR-77 95 8.676 0.091

SOUTH TEXAS NPF-76 1 0.017 0.017

ST. LUCIE DPR-67 7 0.073 0.010

SURRY DPR-32 4 0.128 0.032

SUSQUEHANNA NPF-14 105 0.435 0.004

THREE MILE ISLAND 1 DPR-50 126 0.798 0.006

TURKEY POINT DPR-31 3 0.084 0.028

VERMONT YANKEE DPR-28 65 0.482 0.007

VOGTLE NPF-68 10 0.227 0.023

WASHINGTON NUCLEAR 2 NPF-21 9 0.110 0.012

WOLF CREEK NPF-42 5 0.024 0.005

Total 943 18.892 0.020

Grand Totals 3,498 761.366 0.218

Licensee Type Licensee Name License Number

Number

with Meas.

CEDE

Collective

CEDE

(person-rem)

Average

Meas. CEDE

(rem)

* This license is also an Agreement State license.
3-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

where the mode of intake into the body was

recorded as ingestion. In 1998, one record

was reported as an ‘injection’ of cobalt-60 and

is included in Table 3.7. 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

TABLE 3.10

Internal Dose (CEDE) Distribution

1994 - 1998

licensee category. Fuel fabrication facilities

have the majority of internal dose (97%) 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 1998 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 1998, the highest CEDE was 3.402 rem,

received by an individual at Combustion

Engineering, Inc., a fuel fabrication facility.

The individual received an intake of uranium

U-234, U-235, and U-238. The highest CDE

was 28.345 rem to this same individual.

Year

Meas.

0.020

1994

1995

1996

1997

1998

Total with

Meas.

CEDE

Collective

CEDE

(personrem)

Average

Meas.

CEDE

(rem)

1,379

1,417

1,345

1,611

1,507

0.020-

0.100

528

473

567

694

663

0.100-

0.250

288

295

306

381

427

0.250-

0.500

353

315

317

366

355

0.500-

0.750

197

180

190

242

230

0.750-

1.000

140

112

121

148

140

1-2

294

192

185

169

153

2-3 3-4 4-5

69

18

22

30

21

2

-

2

-

2

-

-

-

-

-

3,250

3,002

3,055

3,641

3,498

1,029.515

709.566

723.208

811.912

761.366

0.317

0.236

0.237

0.223

0.218

Number of Individuals with CEDE in the Ranges (rem)
4-1

Thirty-First Annual Report, 1998 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 Three Mile Island includes

the dose data for Unit 2 prior to 1986.

In 1998, Big Rock Point (a BWR) was

removed from the count of operating reactors.

Zion 1 and 2 (two PWRs) and Maine Yankee

(a PWR) were also removed from the count of

operating reactors. This brings the count of

operating BWRs in 1998 to 36, and the count

of operating PWRs to 69. This is the first

reduction in the number of operating BWRs in

9 years, and the first reduction in the number

of operating PWRs in 5 years. 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
4-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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 12,611 14,607 5,786.4 0.86 701 812 2.18 321 595 54%

1976 22 12,300 16,6048,137.9 0.74 559 755 1.51 370 630 59%

1977 23 19,041 21,388 9,102.5 0.89 828 930 2.09 396 637 62%

1978 25 15,273 20,278 11,856.0 0.75 611 811 1.29 474 660 72%

1979 25 18,325 25,245 11,671.0 0.73 733 1,010 1.57 467 660 71%

1980 26 29,530 34,094 10,868.2 0.87 1,136 1,311 2.72 418 663 63%

1981 26 25,472 34,755 10,899.2 0.73 980 1,337 2.34 419 663 63%

1982 26 24,437 32,235 10,614.6 0.76 940 1,240 2.30 408 663 62%

1983 26 27,455 33,473 9,730.1 0.82 1,056 1,287 2.82 374 663 56%

1984 27 27,097 41,105 10,019.2 0.66 1,004 1,522 2.70 371 754 49%

1985 29 20,573 38,237 12,284.0 0.54 709 1,319 1.67 424 775 55%

1986 30 19,349 37,928 12,102.1 0.51 645 1,264 1.60 403 786 51%

1987 32 16,717 41,737 15,109.0 0.40 522 1,304 1.11 472 832 57%

1988 34 17,983 40,305 16,665.4 0.45 529 1,185 1.08 490 845 58%

1989 36 15,549 44,360 17,543.5 0.35 432 1,232 0.89 487 857 57%

1990 37 15,780 41,577 21,336.1 0.38 426 1,124 0.74 577 862 67%

1991 37 12,005 38,492 21,505.8 0.31 324 1,040 0.56 581 860 68%

1992 37 13,309 42,095 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 1,0640.56 594 798 74%

199437 12,092 39,108 22,139.0 0.31 327 1,057 0.55 598 801 75%

1995 37 9,467 35,659 24,737.0 0.27 256 964 0.38 669 835 80%

1996 37 9,461 37,637 24,322.2 0.25 256 1,017 0.39 657 838 78%

1997 37 7,597 33,845 22,866.1 0.22 205 915 0.33 618 845 73%

1998 36 6,823 32,86423,781.2 0.21 190 913 0.29 661 874 76%

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 - 1998
4-3

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

TABLE 4.2

Summary of Information Reported by Commercial Pressurized Water Reactors

1973 - 1998

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 52,146 22,140.6 0.53 578 1,086 1.25 461 777 59%

1983 49 29,017 52,173 23,195.5 0.56 592 1,065 1.25 473 785 60%

1984 51 28,138 56,994 26,478.4 0.49 552 1,118 1.06 519 809 64%

1985 53 22,469 54,633 29,470.7 0.41 424 1,031 0.76 556 820 68%

1986 60 23,032 62,995 33,593.0 0.37 3841,050 0.69 560 878 64%

1987 6423,68462,597 37,007.3 0.38 370 978 0.64 578 900 64%

1988 68 22,786 62,921 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 20,812 67,081 46,955.6 0.31 285 919 0.44 643 907 71%

1991 7416,510 60,269 51,942.6 0.27 223 814 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 14,142 56,588 50,480.6 0.25 199 797 0.28 711 945 75%

1994 72 9,603 44,766 54,618.3 0.21 133 622 0.18 759 932 81%

1995 72 12,207 51,867 55,825.1 0.24170 720 0.22 775 933 83%

1996 72 9,413 46,812 55,337.8 0.20 131 650 0.17 769 935 82%

1997 72 9,539 50,628 48,985.3 0.19 132 703 0.19 680 943 72%

1998 69 6,347 38,480 53,288.7 0.16 92 558 0.12 772 942 82%

*

**

***

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-First Annual Report, 1998

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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 20,879 25,491 17,768.9 0.82 475 579 1.18 404 626 65%

1976 52 26,107 34,192 21,462.9 0.76 502 658 1.22 413 671 62%

1977 57 32,508 42,266 26,448.3 0.77 570 742 1.23 464 667 70%

1978 64 31,801 45,978 31,696.5 0.69 497 718 1.00 495 688 72%

1979 67 39,982 64,073 29,926.0 0.62 597 956 1.34 447 714 63%

1980 68 53,797 80,331 29,157.5 0.67 791 1,181 1.85 429 714 60%

1981 70 54,145 82,106 31,452.9 0.66 774 1,173 1.72 449 719 63%

1982 74 52,191 84,381 32,755.2 0.62 705 1,140 1.59 443 737 60%

1983 75 56,472 85,646 32,925.6 0.66 753 1,142 1.72 439 743 59%

1984 78 55,235 98,099 36,497.6 0.56 708 1,258 1.51 468 790 59%

1985 82 43,042 92,870 41,754.7 0.46 525 1,133 1.03 509 804 63%

1986 90 42,381 100,923 45,695.1 0.42 471 1,121 0.93 508 847 60%

1987 96 40,401 104,334 52,116.3 0.39 421 1,087 0.78 543 877 62%

1988 102 40,769 103,226 59,595.1 0.39 400 1,012 0.68 584 871 67%

1989 107 35,930 108,25462,223.0 0.33 336 1,012 0.58 582 883 66%

1990 110 36,592 108,658 68,291.7 0.34333 988 0.54 621 892 70%

1991 111 28,515 98,761 73,448.4 0.29 257 890 0.39 662 895 74%

1992 110 29,294 103,143 74,012.0 0.28 266 938 0.40 673 901 75%

1993 108 26,363 95,940 72,476.2 0.27 244 888 0.36 671 895 75%

1994109 21,695 83,874 76,757.3 0.26 199 769 0.28 704 888 79%

1995 109 21,67487,526 80,562.1 0.25 199 803 0.27 739 900 82%

1996 109 18,874 84,449 79,660.0 0.22 173 775 0.24 731 902 81%

1997 109 17,136 84,473 71,851.4 0.20 157 775 0.24 659 910 72%

1998 105 13,169 71.344 77,069.9 0.18 125 679 0.17 734 918 80%

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 - 1998
4-5

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 and 1998, 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

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 a 7%

increase in the net electricity generated at

LWRs in 1998. BWRs increased by 4% in net

electricity generated, despite the fact that

Clinton produced no power due to refueling,

and Millstone Point 1 produced no power due

to regulatory restriction. PWRs increased net

electric output by 9%, despite the fact that

Cook 1, 2 produced no power due to design

basis concerns, and there were significant

reductions at Beaver Valley 1, 2 and Millstone

Point 2, 3. Crystal River generated power in

1998 after being off-line in 1997 and Salem 1,

2 also significantly increased power output

from 1997.

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. In 1997, the number

reflects the net electricity produced. This ratio

was also calculated for each reactor site and

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

average collective dose per MW-year for

LWRs decreased by 29% in 1998 to a value of

0.17, 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.
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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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4.2.5 Percent of Maximum Dependable

Capacity Achieved

The percent of maximum dependable capacity

achieved is shown for all LWRs in Table 4.3.

This parameter gives an indication of the

overall power generation performance of

LWRs as compared to the maximum capacity

that could be obtained in a given year. It is

calculated by dividing the average electricity

generated per reactor by the average

maximum dependable capacity for each year.

From 1973 to 1978 this indicator exhibited an

increasing trend as a number of new reactors

began producing power at higher efficiencies.

Following the accident at Three Mile Island,

reactor operations personnel concentrated on

improving safety systems and complying with

the new regulations for these systems. During

this time period, from 1979 to 1987, the

percent of maximum dependable capacity

remained around 61%. Following the

completion of most of these mandated repairs,

reactors have increased the percent of

maximum dependable capacity from 62% in

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

10 years. The number increased to 80% in

1998 from 72% in 1997. One reason for the

drop in maximum dependable capacity in

1997 was due to the change from measuring

the gross electricity generated to the net

electricity generated.

4.3 ANNUAL TEDE

DISTRIBUTIONS

Table 4.4 summarizes the distribution of the

annual TEDE doses received by workers at all

commercial LWRs during each of the years

1977 through 1998. 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 1998 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). The total

collective dose decreased by 23% to a value

of 13,169 person-rem in 1998.
4-7

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

*

1977 23,562 12,395 6,030 4,518 2,890 2,220 5,649 2,856 1,288 661 186 89 47 23 6 62,420 38,858 32,508

1978 28,372 15,101 6,342 4,998 3,088 2,247 5,995 3,034 1,197 514 109 37 9 0 1 0 2 71,046 42,674 31,801

1979 43,330 22,508 8,985 7,469 4,797 3,259 7,572 3,404 1,400 545 117 42 17 3 1 103,449 60,119 39,982

1980 50,873 26,903 10,676 8,904 5,570 4,134 10,671 4,607 1,816 831 235 119 29 7 1 125,376 74,503 53,795

1981 39,265 26,836 11,226 9,330 6,042 4,497 11,170 4,811 1,999 533 103 93 9 3 1 0 1 115,919 76,654 54,144

1982 41,713 29,225 11,713 9,903 6,229 4,420 10,220 4,716 2,066 596 97 31 5 0 1 1 120,936 79,223 52,190

1983 47,048 29,107 11,195 9,344 5,851 4,276 11,345 5,332 2,269 716 121 38 8 2 126,652 79,604 56,472

1984 54,670 36,296 13,427 10,275 6,336 4,804 11,283 5,206 2,122 487 52 22 144,980 90,310 55,235

1985 59,634 36,831 13,008 11,041 6,627 4,547 10,040 3,575 1,001 157 1 146,462 86,828 43,042

1986 67,701 41,467 14,570 11,842 7,016 4,693 10,241 3,062 868 146 161,606 93,905 42,381

1987 85,181 41,222 15,834 12,839 7,586 5,332 10,611 2,192 477 69 181,343 96,162 40,401

1988 87,254 40,225 15,913 13,153 7,903 5,461 10,310 2,442 511 26 1 183,199 95,945 40,769

1989 83,947 45,282 17,267 13,777 7,945 5,137 8,634 1,614 370 34 184,007 100,060 35,930

1990 83,873 42,607 17,529 14,192 8,226 5,260 8,594 1,794 335 21 182,431 98,558 36,592

1991 87,250 42,587 16,764 13,184 7,187 4,194 5,975 938 219 17 178,315 91,065 28,527

1992 87,717 41,934 17,822 14,777 8,134 4,520 6,076 808 85 4 181,877 94,160 29,294

1993 83,069 37,331 17,235 13,733 7,562 4,289 5,322 638 76 5 169,260 86,191 26,363

1994 68,927 31,100 15,750 12,386 6,362 3,655 4,092 415 20 142,707 73,780 21,695

1995 62,080 29,681 15,152 12,083 6,146 3,306 3,905 590 121 2 133,066 70,986 21,674

1996 59,238 30,432 14,626 11,248 5,389 2,823 3,186 409 69 127,420 68,182 18,874

1997 58,501 31,832 14,875 10,910 5,246 2,407 2,575 299 44 126,689 68,188 17,136

1998 57,026 27,912 12,832 8,808 3,929 1,838 1,825 179 15 1 114,365 57,339 13,169

**

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 - 1998
4-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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 1998, the average

collective dose per reactor dropped by 83%.

In 1998, the collective dose per reactor for

PWRs decreased by 30% to 92 person-rem.

The collective dose per reactor for BWRs

decreased by 7% to 190 person-rem in 1998.

The overall collective dose per reactor for

LWRs decreased by 20% to 125 person-rem

in 1998. The number of workers with

measurable dose per reactor decreased to

913 for BWRs and decreased to 558 for

PWRs in 1998. The overall decreasing trend

in average reactor collective doses since 1983

indicates that licensees are continuing to

successfully implement ALARA dose reduction

features at their facilities.

Figures 4.2 and 4.3 are plots of most of the

other information that is given in Tables 4.1,

4.2, and 4.3. The value for the total collective

dose for all LWRs decreased by 23% from a

value of 17,136 person-rem in 1997 to 13,169

person-rem in 1998. Together with the

decrease in the number of workers with

measurable dose, this resulted in the average

measurable dose per worker decreasing to

0.18 rem in 1998. Figure 4.2 shows that in

1998 the net electricity generated was 77,070

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 Three

Mile Island 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-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

FIGURE 4.1. Average Collective Dose and Number of Workers per Reactor

1973 - 1998
4-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

FIGURE 4.2. Number of Operating Reactors and Gross Electricity Generated

1973 - 1998

* Gross electricity 1973-1996, net electricity for 1997-1998.
4-11

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

1973 - 1998

* Gross electricity 1973-1996, net electricity for 1997-1998.
4-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

To further assist in the identification of any

trends that might exist, Figures 4.4 and 4.5

display the average and median5 values of the

collective dose per reactor for BWRs and for

PWRs for the years 1973 through 1998. 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

a decrease from 121 person-rem in 1997 to

85 person-rem in 1998. At BWRs, the median

fluctuates more from year to year, and in 1998

the median collective dose decreased to 189

person-rem. Figure 4.5 also shows that, in

1998, 50% of the PWRs reported collective

doses between 59 and 122 person-rem while

50% of the BWRs reported collective doses

between 160 and 214 person-rem. Nearly

every year, the median collective dose is less

than the average, which indicates that the

collective dose for most plants is less than the

average collective dose per reactor (the value

that is widely quoted).

4.5 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, 1998, 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 108 reactor-years of

operation accumulated by the 36 BWRs listed,

the average 3-year collective TEDE per

reactor was found to be 219 person-rem, the

average measurable TEDE per worker was

0.23 rem, and the average collective TEDE

per megawatt-year was 0.33.

Based on the 204 reactor-years of operation

at the 68 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 119 person-rem, 0.19 rem, and

0.16 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 1996 -1998 is 8% less

than the average for 1995 -1997. The average

3-year collective TEDE per PWR for 1996 -

1998 is 17% less than the average for 1995 -

1997. The average megawatt-year per reactor

for BWRs and PWRs was greater than the

previous 3-year average.

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

Thirty-First Annual Report, 1998 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-First Annual Report, 1998

NUREG-0713

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

1987 - 1998

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
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Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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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

COOPER STATION 3 135 404 2,570 0.16 1,918.7 0.21

FERMI 2 3 138 414 3,387 0.12 2,028.7 0.20

LIMERICK 1, 2 6 138 825 4,971 0.17 5,929.6 0.14

BROWNS FERRY 1, 2, 3 9 140 1,261 5,418 0.23 5,858.1 0.22

VERMONT YANKEE 3 162 487 2,155 0.23 1,322.0 0.37

SUSQUEHANNA 1, 2 6 181 1,083 4,651 0.23 5,791.7 0.19

NINE MILE POINT 1, 2 6 183 1,097 4,765 0.23 4,303.1 0.25

MONTICELLO 3 185 555 1,830 0.30 1,347.9 0.41

HOPE CREEK 1 3 188 563 3,436 0.16 2,529.7 0.22

DUANE ARNOLD 3 190 570 2,464 0.23 1,388.2 0.41

PEACH BOTTOM 2, 3 6 190 1,138 5,432 0.21 5,844.4 0.19

PERRY 3 207 621 3,531 0.18 2,986.9 0.21

MILLSTONE POINT 1 3 213 639 2,147 0.30 - ---

CLINTON 3 222 666 2,758 0.24632.9 1.05

DRESDEN 2, 3 6 225 1,350 6,846 0.20 3,061.8 0.44

HATCH 1, 2 6 247 1,483 5,050 0.29 4,348.5 0.34

BRUNSWICK 1, 2 6 2541,523 7,001 0.22 4,252.6 0.36

GRAND GULF 3 255 766 3,488 0.22 3,377.3 0.23

PILGRIM 3 258 775 2,702 0.29 1,772.2 0.44

LASALLE 1, 2 6 260 1,557 6,542 0.24 1,431.8 1.09

FITZPATRICK 3 269 806 3,827 0.21 1,940.6 0.42

OYSTER CREEK 3 269 807 3,750 0.22 1,583.5 0.51

RIVER BEND 1 3 293 878 4,230 0.21 2,506.8 0.35

WASHINGTON NUCLEAR 2 3 303 910 3,891 0.23 2,147.6 0.42

QUAD CITIES 1, 2 6 407 2,440 6,899 0.35 2,604.3 0.94

Grand Totals and Averages 108 23,618 103,741 0.23 70,908.9 0.33

Averages Per Reactor-Year 219 961 656.6

* Sites where not all reactors had completed 3 full years of commercial operation as of 12/31/98 are not included.

TABLE 4.5

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

1996 - 1998
4-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

TABLE 4.6

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

1996 - 1998

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

WATERFORD 3 3 66 199 1,810 0.11 2,813.2 0.07

PRAIRIE ISLAND 1, 2 6 67 403 1,893 0.21 2,667.3 0.15

SEABROOK 3 72 215 2,336 0.09 3,030.0 0.07

THREE MILE ISLAND 1 3 79 237 1,596 0.15 2,336.6 0.10

ARKANSAS 1, 2 6 82 489 3,885 0.13 4,708.1 0.10

MILLSTONE POINT 2, 3 6 82 492 3,598 0.14 782.5 0.63

PALO VERDE 1, 2, 3 9 82 740 4,712 0.16 10,296.8 0.07

SALEM 1, 2 6 86 516 2,973 0.17 1,908.6 0.27

GINNA 3 88 2641,670 0.16 1,283.40.21

INDIAN POINT 3 3 90 271 2,110 0.13 2,062.5 0.13

KEWAUNEE 3 90 270 1,136 0.241,072.2 0.25

POINT BEACH 1, 2 6 90 537 2,580 0.21 1,665.8 0.32

SUMMER 1 3 91 2741,806 0.15 2,612.6 0.10

OCONEE 1, 2, 3 9 94 846 4,553 0.19 5,395.6 0.16

DIABLO CANYON 1, 2 6 95 568 4,106 0.14 5,901.9 0.10

SOUTH TEXAS 1, 2 6 99 5943,899 0.15 7,104.0 0.08

HARRIS 3 100 299 2,506 0.12 2,298.1 0.13

CALVERT CLIFFS 1, 2 6 109 655 3,300 0.20 4,457.3 0.15

NORTH ANNA 1, 2 6 110 660 3,260 0.20 4,909.6 0.13

COMANCHE PEAK 1, 2 6 111 666 3,299 0.20 5,840.0 0.11

DAVIS-BESSE 3 111 332 2,142 0.15 2,293.5 0.14

SAN ONOFRE 2, 3 6 111 666 4,015 0.17 5,613.9 0.12

ROBINSON 2 3 117 350 2,313 0.15 1,989.0 0.18

SURRY 1, 2 6 120 718 3,483 0.21 4,415.1 0.16

CATAWBA 1, 2 6 122 730 4,272 0.17 5,908.6 0.12

TURKEY POINT 3, 46 126 757 3,783 0.20 3,848.2 0.20

VOGTLE 1, 2 6 129 772 3,383 0.23 6,296.2 0.12

BEAVER VALLEY 1, 2 6 136 8143,779 0.22 2,948.0 0.28

COOK 1, 2 6 145 869 4,133 0.21 3,123.3 0.28

MCGUIRE 1, 2 6 145 872 4,860 0.18 5,574.7 0.16

WOLF CREEK 1 3 149 446 2,159 0.21 3,129.5 0.14

BRAIDWOOD 1, 2 6 152 9144,918 0.19 5,685.0 0.16

CALLAWAY 1 3 154461 2,157 0.21 3,057.5 0.15

SEQUOYAH 1, 2 6 156 9344,776 0.20 6,085.3 0.15

FARLEY 1, 2 6 157 942 3,635 0.26 4,308.6 0.22

BYRON 1, 2 6 162 971 4,965 0.20 5,480.1 0.18

FORT CALHOUN 3 164 491 1,786 0.27 1,197.5 0.41

CRYSTAL RIVER 3 3 184551 2,478 0.22 1,030.0 0.53

PALISADES 3 194 583 2,342 0.25 1,914.3 0.30

ST. LUCIE 1, 2 6 194 1,165 4,917 0.24 4,436.5 0.26

INDIAN POINT 2 3 237 711 2,882 0.25 1,568.6 0.45

Grand Totals and Averages 204 24,244 130,206 0.19 153,049.5 0.16

Averages Per Reactor-Year 119 638 750.2

* Sites where not all reactors had completed 3 full years of commercial operation as of 12/31/98 are not included.
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Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

4.6 GRAPHICAL

REPRESENTATION OF DOSE

TRENDS IN APPENDIX D

Each page of Appendix D presents a graph of

selected dose-performance indicators from

1973 through 1998. 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 1998. 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.

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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Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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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.
5-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

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

77,080 37,039 17,189 10,467 3,929 1,561 1,127 32 148,424 71,344 13,169 0.09 0.18

26,496 14,598 7,798 4,777 1,761 744 495 11 56,680 30,184 6,154 0.11 0.20

6,442 5,471 3,441 3,118 1,761 1,021 1,193 158 15 1 22,621 16,179 6,154 0.27 0.38

57,026 27,912 12,832 8,808 3,929 1,838 1,825 179 15 1 114,365 57,339 13,169 0.12 0.23

87,016 40,368 18,471 11,581 4,518 2,000 1,820 225 72 14 4 2 166,091 79,075 16,383 0.10 0.21

27,283 14,920 7,977 4,941 1,831 787 541 20 58,300 31,017 8,722 0.15 0.28

6,539 5,522 3,468 3,190 1,826 1,057 1,267 172 18 2 23,061 16,522 8,722 0.38 0.53

66,272 30,970 13,962 9,830 4,513 2,270 2,546 377 90 16 4 2 130,852 64,580 16,383 0.13 0.25

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

TABLE 5.1

Effects of Transient Workers on Annual Statistical Compilations

1998
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NUREG-0713

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.

Table 5.1 illustrates the impact that the

multiple reporting of these transient individuals

had on the summation of the exposure reports

for 1998. 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

The summation of the TEDE from each of the Form 5s submitted

for the monitoring year. This is the summation of each dose

record grouped by licensee and individual. This distribution takes

into account multiple Form 5s for an individual at one NRClicensed facility but not multiple exposures at multiple licensees.

This distribution represents the population of transient workers as

they were reported by each licensee. This distribution is the

subset of all Form 5s where individuals were monitored at more

than one licensee during the monitoring year. This is the

summation of dose records grouped by individual and by licensee,

so the distribution represents how the transient worker population

would appear within the total distribution of all workers. This

distribution takes into account multiple Form 5s for an individual at

one NRC-licensed facility but not multiple exposures at multiple

licensees.

This is the actual distribution for transient workers summed per

individual. This represents the true number of individuals and

places each individual in the correct dose range. This distribution

accounts for multiple records per individual and multiple licensees.

This distribution represents the correction of the reported

distribution by subtracting the difference in the reported and actual

distribution for transient workers. This represents the most

accurate dose distribution for the licensee category and accounts

for the multiple reporting of individuals.

Form 5 Summation

Transients -

As Reported

Transients - Actual

Corrected

Distribution

The following definitions apply to Table 5.1:
5-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

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 1998, Table 5.1 shows that the

summation of annual reports for reactor

licensees indicated that 32 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

195 workers who received doses greater than

2 rem. Correcting for the multiple counting of

individuals also has a significant effect on the

average measurable dose for these workers.

The corrected average measurable dose for

transient workers is twice as high as the value

calculated by the summation of licensee

records. The transient workers represent 26%

of the workforce that receives measurable

dose and increases the average measurable

dose for all licensees by 19% from 0.21 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 1998, 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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NUREG-0713

5.3 CAREER DOSE STATISTICS

1977 - 1998

An analysis of career doses was presented in

the 1989 annual NUREG-0713. This analysis

applied only to those individuals who had

terminated their employment from licensees.

This analysis has been updated and now

includes those individuals who had terminated

their employment before 1994, those

individuals for whom individual exposure

reports were submitted after 1994, and those

individuals for whom we have historical data

that were submitted as a result of voluntary

generic letter 94-04. The reporting

requirements and their effective dates are

given in the table below.

5.3.1 Compilation of the Data

The data were compiled from reports

submitted by licensees for each individual in

the REIRS database. The first recorded date

of exposure monitoring was used as the “start”

date for that individual. Likewise, the last

recorded date of exposure monitoring was

used for the individual’s “end” or termination

date. All whole body doses attributed to

licensees for an individual were summed

during this “career” time period. Whole body

dose was used before 1994, and the TEDE

was used from 1994 to 1998. For most of the

data presented, only workers who received

measurable dose were included in the

statistics. This eliminates the majority of

visitors or individuals who were simply

monitored for administrative purposes.

Information on the individual’s sex and age

was also compiled from reports where such

information was available.

10 CFR § 20.408 Required licensees to report the doses 1968 – 1994

received by individuals upon termination

from NRC-licensed facilities.

10 CFR § 20.2206 Requires the reporting of annual 1994 – current

monitoring records.

Generic Letter 94-04 Requested reactor licensees to report

radiation exposure records for individuals

who had not been reported previously

under 10 CFR § 20.408 and who

remained employed and monitored as

of 1/1/94. 1994

NRC Document Requirement or Request Effective Dates
5-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

The total numbers and percentages of

workers in each category reflect the level of

completeness of data presented in these

analyses. The total number of individuals

included in the career dose analysis was

825,021; out of this total, 495,945 (60%) of the

individuals received measurable dose. For

this analysis, measurable dose is considered

to be any recorded dose greater than zero.

The birthdate, and therefore the age at

termination, was known for 84% of the

individuals with measurable dose. The sex

was recorded for 93% of the individuals with

measurable dose. The age and sex were

known for 78% of the total number of workers

with measurable dose.

 5.3.2 Limitations of the Data

When analyzing and drawing conclusions

from these data, it is important to note several

limitations of the data. When possible,

attempts have been made to minimize these

limitations.

A large number of the individuals reported in

1998 have not completed their careers. Many

of these individuals will most likely continue

employment in 1999. Therefore, these data

do not accurately reflect true career length

and career dose.

Before 1994, the sex of the individual was

often assumed from the first name or “Sir” title

in the submittal’s letterhead or salutation.

Where the first name was not indicative of the

sex of the individual, a null value was

recorded and it was treated as “unknown”. In

1994, the revised Part 20 required the

reporting of the sex of the monitored

individual. This new requirement resulted in

updated personnel records for most of the

individuals in the REIRS database and allows

for a more complete analysis of the dose

based on the sex of the individual.

Another problem has been the licensee’s

practice of reporting incremental periods of

exposure and then reporting all or part of the

individual’s exposure when the individual

actually terminates employment, or as a

correction to a previous report. This practice

may allow an overlap for some periods of

exposure and double the dose recorded for

that individual at that facility during the

overlapping time period. Considerable effort

has gone into eliminating this problem from

the data. New data entering the system were

run through extensive verification procedures

to identify data that overlap or were otherwise

inconsistent with data already in the system.

However, such procedures were not applied in

the past and it has proven difficult to identify

and correct for overlapping exposure records.

While this only affects a small percentage of

the records, it is an additional source of error

for any conclusions drawn from the career

data.
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Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

5.4 CAREER DOSE

DISTRIBUTIONS BY DOSE AND

CAREER LENGTH

Table 5.2 presents the career dose distribution

data based on dose and length of career for

individuals who terminated from reactor

facilities from 1977 to 1998. The first table

shows the number of individuals who

accumulated a career dose for each of the

dose ranges indicated. An individual whose

career dose exactly equals one of the endpoints of a range is included in the higher

dose range. The column on the far left of the

table indicates the “career length” or period of

time the individual was monitored during his or

her career. The second table (lower half)

shows the total collective dose received by

individuals in each dose range.

Table 5.2 shows data for more than 825,000

individuals monitored during the period

1977 - 1998. The number of these workers

with measurable dose was 495,945. Of the

total monitored workforce, 95% received

career doses less than 5 rem, while 88% of

this group received career doses less than 2

rem. Measurable doses less than 5 rem were

received by 91% of workers, whereas 79% of

workers received doses less than 2 rem; the

vast majority for both categories of workers. It

is important to note that this dose is received

during the entire career of the worker, and can

be compared favorably to the current 5 rem

per year regulatory limit. As anticipated, Table

5.2 shows that the longer the career, the

higher the career dose for most workers.
5-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

<=30 days

31 days-6 mo.

6 mo. - 1 yr.

1-2 yrs.

2-3 yrs.

3-4 yrs.

4-5 yrs.

5-10 yrs.

10-15 yrs.

15-20 yrs.

20-25 yrs.

25-30 yrs.

30-35 yrs.

>35 yrs.

Totals

Number of Personnel in Each Dose Range (remS)

Career Length

Number with

Measurable

Dose

No

Meas.

.001-

0.1

Total

Monitored

135,694

69,887

30,077

29,669

13,012

8,978

7,200

18,250

11,497

3,901

528

141

86

156

329,076

0.1-0.5

0.5-

1.0

1.0-

2.0

2.0-

3.0

3.0-

4.0

4.0-

5.0

5.0-

10.0

10.0-

15.0

15.0-

20.0

20.0-

25.0

25.0-

30.0

30.0-

50.0 >50.0

<=30 days

31 days-6 mo.

6 mo. - 1 yr.

1-2 yrs.

2-3 yrs.

3-4 yrs.

4-5 yrs.

5-10 yrs.

10-15 yrs.

15-20 yrs.

20-25 yrs.

25-30 yrs.

30-35 yrs.

>35 yrs.

Totals

Collective Dose of Personnel in each Dose Range (rems)

Career Length

Collective

Dose

No

Meas.

.001-

0.1

Average

Career

Dose

0

0

0

0

0

0

0

0

0

0

0

0

0

0

-

0.1-0.5

0.5-

1.0

1.0-

2.0

2.0-

3.0

3.0-

4.0

4.0-

5.0

5.0-

10.0

10.0-

15.0

15.0-

20.0

20.0-

25.0

25.0-

30.0

30.0-

50.0 >50.0

658

1,411

572

649

383

289

265

728

523

272

66

16

11

20

5,863

24,042

39,758

17,032

19,014

11,051

8,142

7,313

20,150

13,788

6,598

1,526

428

304

538

169,684

1,901

6,249

2,412

3,141

1,997

1,605

1,499

4,275

3,180

1,963

597

85

42

65

29,011

8,071

25,534

9,964

12,671

7,938

6,336

5,947

16,642

12,356

7,582

2,264

340

182

283

116,110

1,959

6,634

2,605

3,971

2,678

2,309

2,266

6,644

4,792

2,981

1,014

155

61

96

38,165

2,749

9,349

3,653

5,536

3,699

3,199

3,132

9,150

6,588

4,084

1,388

213

82

129

52,951

3,390

7,566

3,104

4,814

3,646

3,279

3,329

10,363

7,985

4,839

1,621

250

98

110

54,394

5,115

10,819

4,401

6,818

5,212

4,738

4,859

15,057

11,601

7,044

2,364

369

143

162

78,702

1,185

2,673

1,418

2,107

1,870

1,707

1,903

6,204

4,997

3,326

1,082

163

70

85

28,790

2,645

6,394

3,449

5,114

4,564

4,163

4,670

15,259

12,313

8,226

2,687

404

172

207

70,267

66

1,249

747

1,176

1,005

944

1,136

4,043

3,444

2,505

893

126

56

51

17,441

229

4,288

2,584

4,059

3,455

3,272

3,932

14,019

11,953

8,721

3,083

443

198

179

60,415

9

323

339

684

639

562

719

2,711

2,761

2,018

760

103

36

42

11,706

39

1,406

1,485

3,054

2,856

2,514

3,197

12,113

12,367

9,032

3,410

457

162

190

52,282

1

6

5

39

116

193

256

1,557

2,560

3,062

1,307

171

50

62

9,385

12

76

57

445

1,342

2,226

3,055

18,752

31,018

37,515

16,148

2,144

597

763

114,150

2

1

2

1

6

23

181

407

847

577

97

30

16

2,190

46

22

46

23

134

507

4,019

8,998

18,838

12,928

2,163

671

359

48,754

1

3

1

4

12

38

45

522

967

1,563

806

136

35

38

4,171

16

50

15

69

196

638

761

8,895

16,600

27,049

13,906

2,362

593

669

71,819

8

58

273

844

1,051

1,120

1,312

5,869

7,148

6,139

2,297

333

119

123

26,694

47

358

1,641

5,384

7,107

7,544

8,909

40,536

50,445

44,171

16,585

2,395

875

886

186,883

2

1

1

3

3

66

189

463

308

60

24

9

1,129

50

29

26

79

83

1,781

5,140

12,653

8,438

1,638

670

237

30,824

1

1

1

1

2

30

127

421

413

106

34

14

1,151

43

31

34

33

68

1,068

4,447

14,959

14,945

3,980

1,276

503

41,387

1

2

7

11

34

54

30

9

1

149

220

110

2,045

791

2,166

3,353

1,929

663

59

11,336

39,524

86,524

36,538

46,892

31,029

25,530

25,122

77,495

63,328

43,481

15,296

2,556

1,229

1,501

495,945

12,884

37,812

19,272

32,776

29,847

29,544

34,181

145,191

174,168

195,590

99,524

18,540

6,134

4,395

839,858

175,218

156,411

66,615

76,561

44,041

34,508

32,322

95,745

74,825

47,382

15,824

2,697

1,215

1,657

825,021

0.326

0.437

0.527

0.699

0.962

1.157

1.361

1.874

2.750

4.498

6.507

7.254

5.433

2.928

1.693

TABLE 5.2

Career Dose Distributions by Dose and Career Length at Reactor Facilities

1997 - 1998
5-9

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Table 5.3 shows the average career doses,

average annual dose, and average career

lengths for all monitored individuals and those

monitored individuals with measurable dose

by career length. The highest average career

doses were accumulated by individuals who

worked between 25 and 30 years. The

average annual dose was calculated from the

total collective dose of individuals in each

career length range divided by the total

collective career length (in years) for these

individuals. This resulted in an overall (1977 -

1998) average annual dose for workers with

measurable dose of 0.264 rem.

5.5 CAREER DOSE

DISTRIBUTIONS BY AGE

AND SEX

Table 5.4 presents the data for the 84% of

workers with measurable dose for which the

age of the worker is known. The analysis is

based on age and year of termination for all

workers with measurable dose from 1977

through 1998. The average values for age at

termination, career length, and career dose

are included to examine the trends over time

for these workers. The analysis indicates an

aging population of workers with the average

TABLE 5.3

Average Career Lengths and Doses by Career Length

1977 - 1998

<=30 days

31 days-6 mo.

6 mo. - 1 yr.

1-2 yrs.

2 -3 yrs.

3 - 4 yrs.

4-5 yrs.

5 -10 yrs.

10 -15 yrs.

15 -20 yrs.

20 -25 yrs.

25-30 yrs.

30-35 yrs.

>35 yrs.

Overall Average

Average Career Dose

Career Length

Total

Monitored

(rems)

0.074

0.242

0.289

0.428

0.678

0.856

1.058

1.516

2.328

4.128

6.289

6.874

5.049

2.653

1.018

0.326

0.437

0.527

0.699

0.962

1.157

1.361

1.874

2.750

4.498

6.507

7.253

5.433

2.928

1.693

Number with

Measurable

Dose (rems)

Average Annual Dose

Total

Monitored

(rems)

-

-

0.379

0.286

0.274

0.245

0.231

0.208

0.187

0.240

0.290

0.253

0.155

0.065

0.225

-

-

0.698

0.470

0.389

0.331

0.297

0.255

0.221

0.261

0.300

0.267

0.167

0.072

0.264

Number with

Measurable

Dose (rems)

Average Career Length

Total

Monitored

(rems)

0.025

0.235

0.762

1.495

2.476

3.499

4.580

7.306

12.458

17.195

21.677

27.215

32.573

40.834

4.308

0.043

0.233

0.756

1.487

2.475

3.492

4.581

7.336

12.461

17.242

21.684

27.202

32.560

40.680

6.062

Number with

Measurable

Dose (rems)
5-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713 TABLE 5.4(a) Career Dose Distributions by Age and Year of Termination for Personnel with Measurable Dose 1977 - 1998

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

Total

Total Number of Personnel in Each Age Range

Year 18 - 20

Average

Age at

Term (yrs.)

Average

Career

Length (yrs.) 20 - 25 25 - 30 30 - 35 35 - 40 40 - 45 45 - 50 50 - 55 55 - 60 >60 Total

238

179

238

241

239

184

180

194

171

189

231

208

239

193

149

139

145

177

174

188

211

297

4,404

1,620

1,524

1,791

2,052

2,635

1,607

1,709

1,940

1,643

1,640

1,807

1,529

1,519

1,402

1,220

1,357

1,406

1,406

1,419

1,259

1,390

2,565

36,440

1,526

1,478

1,857

2,104

2,760

2,020

2,244

2,534

2,526

2,645

2,781

2,216

2,158

2,047

1,639

1,847

2,080

2,150

2,151

1,916

2,201

5,444

50,324

1,195

1,198

1,563

1,899

2,294

1,830

1,971

2,191

2,272

2,381

2,807

2,320

2,437

2,472

2,113

2,442

3,208

2,812

2,712

2,508

2,776

9,999

57,400

809

821

1,039

1,353

1,608

1,487

1,686

1,868

1,946

2,203

2,435

2,041

2,228

2,332

2,011

2,482

3,954

2,993

3,015

3,018

3,678

19,117

64,124

595

611

700

975

1,059

1,074

1,200

1,284

1,423

1,541

1,883

1,672

1,873

1,937

1,813

2,241

3,838

2,691

2,839

2,970

3,943

23,440

61,602

567

499

600

776

947

835

837

1,035

1,030

1,051

1,361

1,134

1,353

1,314

1,276

1,886

3,236

2,299

2,414

2,722

3,592

20,534

51,298

600

525

618

808

845

728

741

768

841

890

948

810

970

1,017

962

1,323

2,295

1,700

1,964

1,951

3,002

14,906

39,212

638

653

666

907

781

689

665

786

785

838

965

828

843

855

832

1,107

1,812

1,418

1,338

1,441

1,911

7,754

28,512

503

467

498

645

658

665

650

690

777

865

886

759

820

858

867

976

2,068

1,060

1,015

925

1,164

3,351

21,167

8,291

7,955

9,570

11,760

13,826

11,119

11,883

13,290

13,414

14,243

16,104

13,517

14,440

14,427

12,882

15,800

24,042

18,706

19,041

18,898

23,868

107,407

414,483

36.6

36.7

36.0

36.9

35.8

37.4

37.0

36.9

37.6

37.8

37.9

38.0

38.5

38.9

39.6

40.3

42.4

41.0

40.9

41.2

42.0

43.5

40.2

2.4

2.5

2.4

2.4

1.8

2.1

2.3

2.6

3.1

3.6

3.8

4.3

4.5

4.7

5.4

6.1

7.8

6.6

6.8

7.2

8.0

11.8

6.6
5-11

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

Total

Total Collective Dose of Personnel in Each Age Range (rems)

Year 18 - 20

Average

Career

Dose 20 - 25 25 - 30 30 - 35 35 - 40 40 - 45 45 - 50 50 - 55 55 - 60 >60 Total Dose

125

74

99

112

88

78

69

69

28

28

56

33

64

41

33

30

30

37

23

38

34

62

1,251

1,402

1,376

1,410

1,878

2,979

1,322

1,706

1,977

1,317

1,076

822

760

734

637

542

551

665

588

560

528

592

1,337

24,759

1,400

1,709

1,674

2,173

3,332

2,084

2,620

3,553

3,091

2,900

3,033

2,347

2,262

1,899

1,374

1,339

1,548

1,762

1,669

1,605

1,762

6,474

51,610

1,393

1,354

1,571

2,105

2,674

2,254

2,641

3,146

3,292

3,428

3,819

3,437

3,520

3,404

2,962

3,124

4,313

3,649

3,468

3,028

3,691

19,029

81,302

895

955

1,133

1,429

1,955

1,871

2,269

2,355

2,830

3,118

3,077

2,871

3,382

3,808

3,355

3,882

6,394

5,361

5,404

5,149

6,941

54,434

122,868

601

624

634

1,009

1,233

1,463

1,354

2,080

1,574

2,550

2,485

2,211

2,649

2,928

2,645

3,608

6,688

5,026

5,829

6,574

8,731

82,313

144,809

663

686

756

807

1,096

1,005

1,188

1,295

1,381

1,559

1,823

1,355

1,741

1,828

1,888

3,027

5,278

4,806

4,651

5,752

8,580

73,908

125,073

837

760

727

900

1,023

891

852

897

1,834

1,309

1,342

1,130

1,281

1,485

1,564

2,064

3,807

3,277

4,622

4,588

7,421

52,277

94,888

1,198

901

1,099

1,565

1,074

1,069

840

1,166

1,149

1,338

1,618

1,344

1,293

1,716

1,530

2,343

3,523

3,830

3,398

3,516

4,857

25,026

65,393

703

904

755

1,069

913

1,244

990

1,506

1,014

1,661

1,300

1,421

1,425

1,673

1,835

2,213

3,576

2,211

2,425

2,159

2,697

9,863

43,557

9,217

9,344

9,857

13,046

16,366

13,281

14,528

18,043

17,508

18,968

19,375

16,909

18,350

19,420

17,729

22,182

35,823

30,547

32,046

32,937

45,306

324,723

755,505

1.112

1.175

1.030

1.109

1.184

1.194

1.223

1.358

1.305

1.332

1.203

1.251

1.271

1.346

1.376

1.404

1.490

1.633

1.683

1.743

1.898

3.023

1.832

TABLE 5.4(b)

Career Dose Distributions by Age and Year of Termination for Personnel with Measurable Dose

1977 - 1998
5-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

career length increasing from about 2 years in

1977 to 8 years in 1997. During this period,

the average career doses also increased, but

at a slower rate, from 1.112 rem in 1977 to

1.898 rems in 1997. From 1977 to1997, the

average career length increased by 233%

while the average career dose has increased

by 71%. Apart from the 1998 data, the

average career dose remained less than 2

rem for each year. The average age at

termination increased by 15% from 36.6 years

in 1977 to 42.0 years in 1997.

Table 5.5 presents the averages of age at

termination, career length, and career dose

broken down by sex and year of termination

for all workers receiving measurable dose

from 1977 through 1998. The sex of the

workers was assumed as discussed in Section

5.3.2, and the sex and age were known for

78% of the workers with measurable dose.

The table shows that female workers were, on

average, 8 years younger than male workers

in 1977. This average age difference

decreased to about 5 years from 1977 to

1998. The career doses of females averaged

about one-third of the male career doses,

while career lengths for women averaged

about three-fourths of the career lengths for

males. Females increased from about 2% of

the total in 1977 to 8% in 1998. The average

age of females increased 28% from 1977 to

1997 while the average age for males

increased by 15%.

The data for workers of known age and

unknown sex are included in Table 5.5 to

indicate the values for workers not included in

the analysis by age and sex. The average

age at termination was between that for the

male and female workers. The average

career length and career dose for this group

were usually lower than that for males or

females, indicating that this group may have

more short-term workers with less complete

personnel files. The number of individuals of

unknown sex in 1994 decreased significantly

as licensees were required to begin reporting

the sex of the individual under the revised

Part 20.
5-13

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

Females of Known Age

Year

Number

with

Meas.

Average

Age

at Term.

(yrs.)

154

193

268

457

645

576

595

848

824

938

1,038

906

970

1,016

996

1,203

1,373

958

95

1,564

1,824

8,461

Average

Career

Length

(yrs.)

Average

Career

Dose

(rem)

28.70

29.81

30.65

30.56

31.27

31.63

31.43

31.40

31.39

32.04

32.11

33.08

33.52

33.86

35.09

35.45

37.16

36.75

34.86

36.88

36.82

40.20

1.46

1.21

1.49

1.60

1.53

1.79

2.25

2.08

2.47

2.81

2.99

3.11

3.31

3.68

4.43

5.08

6.62

5.83

6.01

5.52

5.67

8.97

0.705

0.498

0.576

0.458

0.428

0.294

0.339

0.452

0.347

0.323

0.344

0.385

0.459

0.429

0.465

0.459

0.622

0.572

0.838

0.542

0.626

1.099

Males of Known Age

Number

with

Meas.

Average

Age

at Term.

(yrs.)

5,824

5,888

7,204

9,637

11,391

8,851

9,630

11,428

10,976

11,745

13,156

11,074

12,208

12,005

10,487

13,484

20,796

17,093

18,912

17,257

22,038

98,902

Average

Career

Length

(yrs.)

Average

Career

Dose

(rem)

36.84

37.23

36.30

37.53

36.06

38.02

37.47

37.29

38.32

38.41

38.55

38.57

38.98

39.46

40.19

40.77

42.80

41.18

40.95

41.63

42.47

43.75

2.79

2.74

2.68

2.54

1.79

2.07

2.35

2.60

3.10

3.70

3.98

4.43

4.63

4.92

5.58

6.27

7.97

6.57

6.84

7.34

8.22

12.06

1.292

1.262

1.119

1.199

1.310

1.334

1.364

1.469

1.445

1.442

1.324

1.393

1.361

1.469

1.509

1.527

1.605

1.708

1.688

1.856

2.004

3.189

Known Age, Sex Unknown

Number

with

Meas.

Average

Age

at Term.

(yrs.)

3,334

3,378

3,381

2,880

3,197

2,781

3,208

2,049

3,150

3,120

3,849

3,333

2,362

2,537

2,851

2,651

3,673

873

35

14

6

45

Average

Career

Length

(yrs.)

Average

Career

Dose

(rem)

37.06

36.25

36.07

34.69

35.32

36.04

36.88

37.26

35.84

36.56

36.87

36.63

36.50

37.31

38.23

38.80

42.51

41.39

39.05

29.99

33.88

42.09

1.34

1.28

1.10

1.04

1.23

1.62

1.31

1.74

1.84

2.06

1.86

2.28

2.89

2.72

2.69

2.82

6.09

6.81

7.42

1.42

2.17

8.83

0.475

0.539

0.486

0.446

0.366

0.468

0.370

0.425

0.431

0.553

0.415

0.338

0.549

0.533

0.507

0.394

0.434

0.927

1.416

0.224

0.563

1.231

Total Personnel

Number

with

Meas.

Average

Age

at Term.

(yrs.)

8,291

7,955

9,570

11,760

13,826

11,119

11,883

13,290

13,414

14,243

16,104

13,517

14,440

14,427

12,882

15,800

24,042

18,706

19,041

18,898

23,868

107,407

Average

Career

Length

(yrs.)

Average

Career

Dose

(rem)

36.55

36.67

36.04

36.91

35.78

37.35

36.98

36.93

37.57

37.79

37.88

38.02

38.46

38.85

39.61

40.26

42.41

40.97

40.92

41.21

42.04

43.47

2.43

2.51

2.39

2.35

1.78

2.08

2.28

2.58

3.05

3.60

3.80

4.25

4.52

4.74

5.37

6.10

7.81

6.56

6.83

7.18

8.02

11.82

1.112

1.175

1.030

1.109

1.184

1.194

1.223

1.358

1.305

1.332

1.203

1.251

1.271

1.346

1.376

1.404

1.490

1.633

1.683

1.743

1.898

3.023

TABLE 5.5

Average Career Values by Sex and Year of Termination for Personnel of Known Age with Measurable Dose

1977 - 1998
5-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

5.6 PATTERNS OF ACCUMULATION OF CAREER DOSES AT

REACTOR FACILITIES

UNSCEAR reports on ionizing radiation for

1982 and 1993 identify the need for

information and analysis of information

concerning the accumulation of dose over the

career of an individual. While organizations

regularly monitor radiation exposure among

their workers and report this information on an

annual basis, little information is published on

how those exposures accumulate over an

individual’s career. It has been suggested that

workers accumulate the majority of their

lifetime dose early in their careers, and

gradually reduce their exposure as they age.

Statistical analysis of more than 30 years of

exposure data at commercial reactor

licensees supports this view.

Figure 5.1 shows the mean annual dose by

age group among commercial nuclear power

plant workers aged 18 to 69 from 1986

through 1998. As the graph shows, workers

aged 20-29 obtained the highest mean doses

at just under 0.05 rem, while mean exposure

declined for each age group thereafter. With

two exceptions, all the differences between

age group means were significant at the 95

percent confidence level, and the pattern

remained consistent for each of the years

analyzed. The two exceptions were 1) the

difference between 20-24 and 25-29 year

olds, and 2) the difference between 50-54 and

55-59 year olds. The pattern may reflect the

fact that many workers move into supervisory

or administrative positions as they get older,

and perform less of the hands-on work that

results in radiation exposure.

The analysis considered 218,754 individuals

who worked at commercial nuclear power

plants between 1986 and 1998 and had

received some measurable radiation exposure

during their careers (1,030,353 person-years).

Since dose values do not fit a statistically

normal distribution, the calculations presented

here used log-transformed data, which were

approximately normal. For the years in which

an individual had a zero dose, the records

were assigned a value of 0.0005 rem (half of

the smallest value in the data) in order to

obtain a usable logarithmic value. This is a

common technique that may slightly

overestimate the average exposure, but

provides a more accurate result than omitting

zero values entirely.6 The analysis considered

only the years after 1985 in order to

accurately reflect current conditions. Industrywide exposure levels were much higher in

many of the years from 1979 to 1985,

reflecting cleanup activities at Three Mile

Island and retrofits required by changes in

regulations.

6 A similar analysis that omitted zero values showed the same pattern, but with much higher mean values, from 0.23 rem for

those aged 20-29 to 0.09 rem for those aged 65-69.
5-15

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713 FIGURE 5.1. Mean Annual Dose to Workers with Measurable Dose at Reactor Licensees by Age Group 1986 - 1998

18-19 20-24 25-29 30-34 35-39 40-44 45-49 50-54 55-59 60-64 65-69

0.05

0.04

0.03

0.02

0.01

0.00

Log. Mean Dose 1986-98Upper 95% Confidence LevelLower 95% Confidence Level

Mean Annual Dose (rem)

Age Group
5-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

If these aggregate patterns accurately reflect

individual exposure patterns, individuals with

high exposure levels in one year should have

similarly high exposure levels in later years;

those with low early exposure levels should

show a similar pattern. The decline in

exposure with age should also remain

significant, even when the data are adjusted

for initial high or low exposure rates. A

multiple regression analysis suggests that

both conditions are true7 . Current dosage is

positively related to dosage for the past 3

years – in fact it is the best predictor of the

next year’s exposure. Age is still a significant

factor, even after adjusting for a 3-year

exposure history and variation in site

characteristics. The regression equation

explained 54% of the variation in annual dose

rates – a relatively high percentage for labor

market analyses, in which the differences

among individuals are often large compared to

the effects of other factors.

The regression also examined the influence of

site characteristics, including site age

(average age of reactors at a site), type of

reactor (PWR or BWR), reactor size, total site

capacity, and power produced during the year

(megawatt-years). All factors except

megawatt-years were significant at the 95

percent confidence level. Current dosage is

negatively related to site age, site capacity,

and reactor size larger than 1000 megawatts.

After adjusting for the other factors, dosage is

also lower at PWR than BWR sites. The

results parallel findings from an earlier study

that estimated collective doses at commercial

reactor sites based on these characteristics8 .

Figure 5.2 shows the average age of workers

who received measurable career doses by

monitoring year for 1969 – 1998, and

projections for 1999 - 20209 . While the

average age of the workers in commercial

power plants remained between 34 and 36

years from 1969 to 1985, in the years since

1985 this population has been aging steadily.

The average age in 1998 was 43.0. If present

trends continue, the average age will rise to

49.5 by 2010, and to 55.1 by 2020. This

suggests that a limited number of new people

are entering the industry, and raises questions

about whether the industry will soon have a

shortage of workers who are able and willing

to perform routine refueling and maintenance

functions. Any decommissioning tasks

expected over the next 2 decades would

further compound such a shortage.

7 Due to incomplete data, the regression analysis could include only a subset of the full study group – 102,987 individuals, and

476,391 person-years.

8 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities – 1995, USNRC

NUREG-0713, Vol. 17, Section 4.10, “Estimation of Future Occupational Radiation Exposure at Commercial Reactor Sites,”

January 1997.

9 The projections are based on a simple regression of average age by calendar year for 1986 – 1998. The equation captures

99% of the variation in age for this period.
5-17

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

1969

1970

1971

1972

1973

1974

1975

1976

1977

1978

1979

1980

1981

1982

1983

1984

1985

1986

1987

1988

1989

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

2004

2005

2006

2007

2008

2009

2010

2011

2012

2013

2014

2015

2016

2017

2018

2019

2020

60

55

50

45

40

35

30

25

20

Year

Age (in years)Projected Age (in years)Lower 95% Confidence LevelUpper 95% Confidence Level

34.82

43.04

48.93

55.08

Average Age in Years

FIGURE 5.2. Average Age of Workers with Measurable Dose at Reactor Licensees

from 1969-1998 with Projections to 2020
5-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

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Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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10 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)10 . 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.
6-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

(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.
6-3

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 1998. 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.
6-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING NO. OF PERSONS

& MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO.OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO.OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING NO.OF PERSONS

& MANUFACT. SUM OF DOSES

OTHER NO.OF PERSONS

SUM OF DOSES

INDUSTRIAL NO. OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING NO.OFPERSONS

& MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO.OF PERSONS

RADIOGRAPHY SUM OF DOSES

POWER NO. OF PERSONS

REACTORS SUM OF DOSES

MEDICAL NO. OF PERSONS

FACILITIES SUM OF DOSES

MARKETING NO. OF PERSONS

& MANUFACT. SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

INDUSTRIAL NO.OF PERSONS

RADIOGRAPHY SUM OF DOSES

OTHER NO. OF PERSONS

SUM OF DOSES

Types Of Exposures And Doses

TEDE (rem) Lens of the Eye (rem) Skin/Extremity (rem)

<5 5 - 25 >25 <15 15 - 75 >75 <50 50 - 250 >250 rad

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.

LICENSE PERSONS AND

Year CATEGORY DOSES (REM)

1998

1997

1996

1995

2

12.2

1

8.3

1b

51.1

1c

70.6

2d

572

1e

180

1

34

1

5.1

1

533.9

4a

34.8

1994

1

50-200

TABLE 6.1

Occupational Exposures in Excess of Regulatory Limits

1994 - 1998
6-5

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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 those 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
6-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

In 1998, six radiography workers received

doses that exceeded the 5 rem TEDE

regulatory limit. Five of the exposures were

“Category B” occurrences, and one was a

“Category C” occurrence. There were no

occurrences in which individuals received a

“Category A” exposure.

In November of 1998, a multi-location

radiographer in Montana reported that one

individual received a deep dose of 12.916 rem

and another received a dose of 5.830 rem.

The two radiographers were involved in the

same incident. While setting up for a

radiography shot, it was noticed that the slider

on the camera had not engaged properly from

the previous shot, leaving the source

unshielded. The individuals were able to turn

the crank handle another one half turn, and it

went in to the locked position. It was noted

that the individual’s dosimeters were off scale.

The individuals involved estimated that the

slider was not locked back for a duration of

approximately 3 minutes, but subsequent

calculations based on film badge results

indicated the duration of the event was

approximately 6 minutes. The licensee has

removed both individuals from activities

involving radioactive materials, and has

attributed the occurrence to a failure to follow

procedures in verifying that the source was

not locked in the shielded position.

Also in November of 1998, a multi-location

radiographer in Oklahoma reported an

exposure of an individual in excess of the 5

rem TEDE limit. A radiographer and an

assistant radiographer were performing

radiography on a large diameter pipe. The

setup required that the camera and source

guide tube be positioned inside the pipe to get

a panoramic radiograph of the welds. While

the radiographer was absent, the assistant

repositioned the radiography equipment to

complete the next set of radiographs. The

assistant failed to perform a survey of the

camera and source guide tube to confirm that

the source was returned to its shielded

position. In addition, the assistant was not

wearing an alarming ratemeter. The source

was found to be in the unshielded position

during these adjustments. The assistant’s

pocket dosimeter had fallen off and was

subsequently found to be off-scale. A

preliminary reading of the TLD indicated a

deep dose of 10.8 rem. The licensee sent the

assistant radiographer to a physician for a

blood sample, and the individual’s white cell

count was found to be slightly above normal.

A subsequent NRC inspection determined that

the assistant received a deep dose equivalent

between 6.4 rem and 14 rem and an extremity

dose to the right hand between 50 rem and

200 rem. The final reported deep dose

equivalent was 11.439 rem. The licensee’s

corrective actions included: 1) the immediate

suspension and eventual termination of both

the radiographer and the assistant, 2) the

performance of an emergency radiation safety

meeting with all staff to review the event, 3) a

plan to conduct field audits of all personnel

and, 4) a review of the incident during

orientation of new personnel.

In August of 1998, a multi-location

radiographer in Oklahoma reported that an

individual had received a year-to-date deep

dose equivalent of 5.64 rem. The dosimetry
6-7

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

processor notified the licensee that an

individual’s film badge indicated a 1-month

dose of 2.95 rem, bringing his annual total to

5.64 rem. Subsequent investigation revealed

that a dosimeter and rate alarm the individual

was wearing did not indicate an exposure of

this magnitude and that these devices were

within calibration requirements and were

operating properly during this period.

However, the dose of 5.64 rem could not be

disproved and therefore the dose was

assigned to the radiographer.

In January of 1999, two individuals at a multiIocation radiography licensee in Texas were

determined to have exceeded the 5 rem TEDE

limit for 1998. In one instance, the individual

received a dose of 4.56 rem during the

December 1998 monitoring period, bringing

the total TEDE for the year to 5.50 rem. In the

other instance at this licensee, the individual

reported a lost dosimeter during three

separate monitoring periods. The licensee

assigned an administrative dose of 0.416 rem

for each of these periods, bringing the

individual’s annual TEDE to 5.18 rem. An

investigation determined that poor work

practices caused the exposure, and the

licensee counseled the radiographer.

Although the licensee reported these

exposures under an NRC license number,

they were designated as events that occurred

in an Agreement State (Texas) and were

therefore investigated by the Texas

Department of Health.

6.4 MAXIMUM EXPOSURES

BELOW THE NRC LIMITS

Because few exposures exceed the NRC

occupational exposure limits, certain

researchers have expressed an interest in a

listing of the maximum exposures received at

NRC licensees that do not exceed the limits.

This would allow an examination of exposures

that approach, but do not exceed the limits.

Table 6.3 shows the maximum exposures for

each dose category required to be reported to

the NRC. In addition, the number of

exposures in certain dose ranges is shown to

reflect the number of exposures that approach

the NRC limits.

As can be seen from Table 6.3, few exposures

exceed half of the NRC occupational annual

limits. In 1998, four individuals came within

5% of the TEDE limit in addition to the four

individuals who exceeded the limit. One

individual was reported to have exceeded the

extremity limit in addition to having exceeded

the TEDE limit. This individual is not shown in

Table 6.3 because the exposure is still under

evaluation and has not yet been reported to

REIRS.
6-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

SDE-ME 50 rem 41.560 83% 53,558 98 17 3 0

SDE-WB 50 rem 12.705 25% 65,730 1 0 0 0

LDE15 rem 12.926 86% 64,731 12 1 1 0

CEDE 3.402 3,907

CDE28.345 2,898

DDE12.916 66,183

TEDE 5 rem 12.916 > limit 67,221 1,834 209 17 8 (4>limit)

TODE50 rem 28.555 57% 56,310 88 2 0 0

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

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

TABLE 6.3

Maximum Occupational Exposures for Each Exposure Category

1998
7-1

Thirty-First Annual Report, 1998 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-First Annual Report, 1998

NUREG-0713

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Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ANNUAL TEDE FOR NON-REACTOR

NRC LICENSEES

1998

Appendix A
A-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

2

1

31

58

19

111

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)

7

12

4

10

5

-

3

-

-

20

17

32

146

256

CAPITAL PHARMACY INC. 21-26597-01MD

EASTERN ISOTOPES 45-25221-01MD

MALLINCKRODT MEDICAL, INC. 24-04206-01MD

MALLINCKRODT MEDICAL, INC. 24-17450-02MD

MALLINCKRODT, INC. 24-04206-08MD

MALLINCKRODT, INC. 24-04206-12MD

MALLINCKRODT MEDICAL INC. 24-04206-14MD

MALLINCKRODT MEDICAL, INC. 24-04206-17MD

MALLINCKRODT MEDICAL, INC. 24-04206-19MD

MID-AMERICA ISOTOPES, INC. 24-26241-01

OKLAHOMA, UNIVERSITY OF 35-03176-04MD

SPECTRUM PHARMACY INC. 13-26367-01

SYNCOR INTERNATIONAL CORP. 04-26507-01MD

Total 13

ABB INDUSTRIAL SYSTEMS INC. 34-00255-03

ADVANCED MEDICAL SYS., INC. 34-19089-01

BRISTOL-MEYER SQ 29-00139-02

MALLINCKRODT MEDICAL INC. 24-04206-01

NUCLEAR RESEARCH CORP. 29-04236-01

NUCLEAR PHARMACIES - 02500

MANUFACTURING AND DISTRIBUTION - TYPE A BROAD - 03211

Total 5

5

10

7

9

8

5

8

-

5

4

7

5

40

113

1

1

752

31

12

797

-

-

5

34

-

39

-

2

-

2

3

4

8

3

2

-

4

1

6

35

-

-

1

45

-

46

1

5

2

1

-

3

4

-

7

-

-

-

1

24

-

-

3

21

-

24

-

1

1

-

-

-

-

-

1

-

-

1

1

5

-

-

4

24

-

28

-

-

-

-

-

1

-

-

1

-

-

2

-

4

-

-

-

53

-

53

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

47

-

47

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

32

-

32

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

13

30

14

22

16

13

23

3

16

24

28

41

194

437

3

2

796

345

31

1,177

6

18

10

12

11

13

20

3

16

4

11

9

48

181

2

1

44

314

19

380

0.530

2.621

1.540

0.820

0.670

2.840

2.970

0.440

4.180

0.190

0.810

2.860

2.796

23.267

0.080

0.050

7.170

359.829

0.234

367.363

0.088

0.146

0.154

0.068

0.061

0.218

0.149

0.147

0.261

0.048

0.074

0.318

0.058

0.129

0.040

0.050

0.163

1.146

0.012

0.967

MANUFACTURING AND DISTRIBUTION - TYPE B BROAD - 03212

48

53

101

11

25

36

5

6

11

3

2

5

3

2

5

1

-

1

-

-

-

71

88

159

23

35

58

5.146

3.540

8.686

0.224

0.101

0.150

BEST INDUSTRIES 45-19757-01

OHMART CORP. 34-00639-01

Total 1

-

-

-

-

-

-

47

-

47

-

-

-

-

-

-

32

-

32

-

-

-

-

-

-

-

-

-

-

-

-

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

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1998
A-3

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

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

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1998

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)

9

48

2

-

-

31

39

23

2

10

164

MANUFACTURING AND DISTRIBUTION - OTHER - 03214

10

54

2

6

3

31

39

29

2

14

190

1

6

-

6

3

-

-

6

-

4

26

0.010

0.260

-

0.940

0.370

-

-

0.170

-

0.300

2.050

0.018

0.043

-

0.157

0.123

-

-

0.028

-

0.075

0.079

ADVANZ MEASUREMENT & CONTROL 34-26683-01

BICRON: SAINT-GOBAIN/NORTON 34-06558-05

DIAGNOSTECH INT’L., INC. 48-26355-01

DU PONT MERCK PHARMACEUTICAL CO. 20-00320-19

HALLIBURTON CO. 35-00502-03

HARRIS SEMICONDUCTORS 37-24841-02

INTERGRATED INDUSTRIAL SYS., INC. 06-21253-01

NUCLEAR RESEARCH CORPORATION 37-02401-01

SEIMENS BUILDING TECHNOLOGIES, INC. 29-08864-03

THERATRONICS INTERNATIONAL LTD. 54-28315-01

Total 10

LOW LEVEL WASTE DISPOSAL FACILITIES - 03231

U.S. ECOLOGY WN-I019-2

Total 1

14

14

1

5

-

1

1

-

-

6

-

3

17

5

5

-

1

-

4

2

-

-

-

-

1

8

8

8

-

-

-

1

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

27

27

13

13

1.355

1.355

0.104

0.104
A-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

AMERICAN FOUNDRY GROUP, INC. 35-26893-01

ARMY, DEPARTMENT OF THE 13-18235-01

ARMY, DEPARTMENT OF THE 29-00047-06

ARROW TANK & ENGINEERING CO. 22-13253-01

BUCKEYE STEEL CASTINGS 34-06627-01

BWX TECHNOLOGIES, INC. 34-02160-03

CARONDELET FOUNDRY COMPANY 24-26136-01

CONNEX PIPE SYSTEMS INC. 45-26591-01

DURALOY 37-02279-02

GENERAL MOTORS CORP. 21-08678-05

GENERAL MOTORS CORP.-DEFIANCE 34-15315-02

GREDE-PRYOR, INC. 35-18099-01

HARRISON STEEL CASTINGS CO. 13-02141-01

HIGH STEEL STRUCTURES, INC. 37-17534-01

INTERMET CORPORATION 45-17464-01

IRONTON IRON, INC. 34-24800-02

MANOIR - ELECTRO ALLOYS, INC. 34-24346-01

MINNESOTA VALLEY ENGINEERING 22-24393-01

MISSOURI STEEL CASTINGS 24-15152-01

NILES STEEL TANK CO. 21-04741-01

PELTON CASTEEL, INC. 48-02669-02

RIDGEWATER COLLEGE 22-15554-01

THE FLOWSERVE CORPORATION 34-06398-01

TRANS WORLD AIRLINES, INC. 24-05151-05

WAUKESHA FOUNDRY DIVISION 48-13776-01

WISCONSIN CENTRIFUGAL, INC. 48-11641-01

PROGRAM CODE -

LICENSEE NAME LICENSE#

Total 26

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)

2

43

-

2

1

10

6

2

1

4

3

1

3

3

7

1

7

-

5

2

3

93

2

81

2

1

285

-

5

1

1

1

8

8

2

1

-

-

1

4

10

1

3

3

6

-

2

-

3

2

-

2

-

64

2

48

1

5

2

18

14

4

4

4

3

2

7

14

8

4

13

9

5

4

3

97

4

81

4

9

369

-

5

1

3

1

8

8

2

3

-

-

1

4

11

1

3

6

9

-

2

-

4

2

-

2

8

84

-

0.042

0.018

1.120

0.010

0.110

0.293

0.014

0.600

-

-

0.010

0.182

0.580

0.010

0.060

0.540

0.490

-

0.040

-

0.190

0.107

-

0.090

3.349

7.855

-

0.008

0.018

0.373

0.010

0.014

0.037

0.007

0.200

-

-

0.010

0.046

0.053

0.010

0.020

0.090

0.054

-

0.020

-

0.048

0.054

-

0.045

0.419

0.094

INDUSTRIAL RADIOGRAPHY - SINGLE LOCATION - 03310

-

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

3

3

-

-

-

1

-

-

-

2

10

-

-

-

1

-

-

-

-

1

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

5

8

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

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

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1998
A-5

Thirty-First Annual Report, 1998 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)

1

-

-

-

-

1

-

2

33

2

10

-

38

5

-

6

8

3

11

1

11

7

-

-

51

2

19

9

5

12

7

2

2

1

-

1

-

1

3

4

1

14

2

14

3

6

-

4

4

2

3

20

13

-

2

58

-

7

18

5

11

5

20

6

8

2

17

1

5

7

38

8

87

2

158

20

32

44

23

24

25

40

94

30

10

10

257

3

117

34

21

35

17

19

6

8

2

17

-

5

5

5

6

77

2

120

15

32

38

15

21

14

39

83

23

10

10

206

1

98

25

16

23

10

18.785

1.054

7.002

1.730

22.150

-

2.280

1.088

0.180

3.440

50.378

0.049

66.913

11.450

23.312

19.088

4.638

10.091

27.163

39.110

35.667

4.170

8.609

6.180

81.125

0.250

58.328

1.609

3.675

2.530

1.725

0.989

0.176

0.875

0.865

1.303

-

0.456

0.218

0.036

0.573

0.654

0.025

0.558

0.763

0.729

0.502

0.309

0.481

1.940

1.003

0.430

0.181

0.861

0.618

0.394

0.250

0.595

0.064

0.230

0.110

0.173

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320

4

3

-

-

4

-

1

1

1

-

25

-

22

2

4

8

2

5

-

4

22

4

1

2

45

-

20

6

4

11

3

-

-

1

-

4

-

-

-

-

3

15

-

38

2

4

12

7

5

1

12

14

4

4

1

53

1

20

1

5

1

1

2

1

-

1

1

-

2

-

-

1

6

-

12

2

3

11

2

1

1

2

11

-

-

-

24

-

20

-

2

-

1

4

-

3

-

1

-

1

1

-

-

2

-

16

1

4

5

-

2

1

2

8

1

1

2

10

-

13

-

-

-

-

3

-

3

1

2

-

-

-

-

1

13

-

14

5

10

2

-

4

2

8

7

1

4

3

11

-

18

-

-

-

-

4

-

-

-

1

-

-

-

-

-

-

-

4

-

1

-

-

-

3

6

1

-

-

-

3

-

-

-

-

-

-

-

-

-

-

2

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

3

2

-

-

-

-

2

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

ACCURATE TECHNOLOGIES, INC. 29-28358-01

ADAMS INDUSTRIAL SERVICES, INC. 45-25355-01

ADVANCED INSPECTION TECH 35-27588-01

AKRON INDUSTRIAL SERVICES, INC. 34-24673-01

ALASKA INDUSTRIAL X-RAY, INC. 50-16084-01

ALLEGHENY LABORATORIES 37-20734-01

ALLIED INSPECTION SERV., INC. 21-18428-01

ALONSO & CARUS IRON WORKS, INC. 52-21350-01

AMERICAN AIRLINES, INC. 35-13964-01

AMERICAN ENGINEERING TESTING 22-20271-02

ANVIL CORPORATION 46-23236-03

ARMY, DEPARTMENT OF THE 30-02405-05

ASCG INSPECTION SERVICES 50-29015-01

BARNETT INDUSTRIAL X-RAY 35-26953-01

BIG STATE X-RAY, INC. 35-21144-01

BILL MILLER, INC. 35-19048-01

BRANCH RADIOGRAPHIC LABS., INC. 29-03405-02

BRAUN INTERTEC CORPORATION 22-16537-02

CALUMET TESTING SERV., INC. 13-16347-01

CAPITAL X-RAY SERV., INC. 35-11114-01

CENTURY INSPECTION, INC. 42-08456-02

CHICAGO BRIDGE AND IRON CO. 42-13553-02

COLBY & THIELMEIER TESTING CO. 24-13737-01

COMO TECH INSPECTION 15-26978-01

CONAM INSPECTION 12-16559-01

CONNELL LIMITED PARTNERSHIP 35-13735-01

CONSOLIDATED NDE 29-21452-01

CONSTRUCTION ENGINEERING CONS. 37-18456-01

CONSUMERS ENERGY CO./NON-DEST TE 21-08606-03

CRAMER & LINDELL ENGINEERS, INC. 06-20794-01

CTI ALASKA, INC. 50-19202-01

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

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1998
A-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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)

5

186

1

1

4

8

-

-

6

2

-

11

2

1

2

-

-

5

-

9

-

2

1

1

2

3

-

8

8

6

1

4

145

10

3

22

25

18

3

8

7

1

12

5

5

3

1

-

2

5

7

1

-

2

6

13

6

6

12

-

8

-

13

344

22

8

209

33

33

20

16

31

6

40

53

17

6

10

7

43

29

17

18

2

20

39

80

17

16

82

8

24

4

8

158

21

7

205

25

33

20

10

29

6

29

51

16

4

10

7

38

29

8

18

-

19

38

78

14

16

74

-

18

3

0.988

4.317

7.506

1.510

105.692

0.069

3.728

17.410

0.671

16.290

2.970

7.210

39.822

7.333

0.280

7.650

7.230

41.064

25.170

0.914

22.390

-

22.406

56.634

47.400

5.600

6.390

48.275

-

3.330

2.040

0.124

0.027

0.357

0.216

0.516

0.003

0.113

0.871

0.067

0.562

0.495

0.249

0.781

0.458

0.070

0.765

1.033

1.081

0.868

0.114

1.244

-

1.179

1.490

0.608

0.400

0.587

0.652

-

0.185

0.680

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320 Continued

3

10

2

2

38

-

11

3

2

4

2

6

7

2

1

2

2

3

5

-

2

-

1

5

14

3

3

10

-

4

-

1

3

4

1

62

-

4

3

-

7

1

9

12

4

-

1

-

3

6

-

5

-

-

5

11

1

2

17

-

5

2

-

-

2

1

38

-

-

-

-

3

1

-

7

-

-

1

-

4

3

1

-

-

4

3

15

1

-

10

-

1

-

-

-

-

-

15

-

-

1

-

3

-

-

2

3

-

2

1

6

-

-

2

-

3

2

9

1

-

7

-

-

-

-

-

3

-

29

-

-

9

-

4

1

2

15

2

-

3

4

16

6

-

4

-

6

7

14

1

5

14

-

-

1

-

-

-

-

1

-

-

1

-

1

-

-

3

-

-

-

-

4

3

-

2

-

2

4

1

1

-

4

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

-

2

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

1

-

1

3

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

CTL - ASTROTECH DIVISION 37-09928-01

DEPARTMENT OF THE NAVY 45-23645-01NA

DIAMOND H TESTING COMPANY 11-27316-01

EASTERN TESTING & INSPECTION, INC. 29-09814-01

EDWARDS PIPELINE TESTING, INC. 35-23193-01

EG&G FLORIDA, INC. FL-1219-1

ELECTRIC BOAT CORPORATION 06-01781-08

ELITE INSPECTION, INC. 13-26712-01

FROEHLING & ROBERTSON, INC. 45-08890-01

G.E. INSPECTION SERVICES, INC. 39-24888-01

GENERAL TESTING & INSP. CO. 34-09037-01

GLITSCH FIELD SERVICES/NDE,INC. 34-14071-01

GLOBE X-RAY SERVICES INC. 35-15194-01

GREAT LAKES TESTING, INC. 48-26484-01

GRINNELL CORPORATION 38-28750-01

H&G INSPECTION CO., INC. 42-26838-01

H. R. INSPECTION SERVICES INC. 15-06209-01

HIGH MOUNTAIN INSPECTION SERVICES 49-26808-02

HUNTINGTON TESTING & TECH. 47-23076-01

INDUSTRIAL NDT SERVICES DIVISION 13-06147-04

INSPECTION MANAGEMENT CORP. 35-26824-01

INSPECTION TECH/PSI 24-26628-01

INTERMOUNTAIN TESTING CO. 05-07872-01

INTERNATIONAL RADIOGRAPHY & INSP. 35-30246-01

JAN X-RAY SERVICES, INC. 21-16560-01

LAW ENG. & ENV. SVCS./SAM-SON INSP. & TE 34-25898-01

LONGVIEW INSPECTION, INC. 45-25279-01

LONGVIEW INSPECTION, INC. 45-27593-01

LUCIUS PITKIN 29-27816-01

MARYLAND QC LABORATORIES 19-28683-01

MASSACHUSETTS MATERIALS RES. 07-01173-03

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

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1998
A-7

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713NOTE: 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)

3

1

2

1

2

-

2

1

144

186

6

1

-

7

2

-

-

12

29

-

6

4

6

4

4

3

3

-

3

1

3

3

8

10

3

3

4

-

76

145

1

1

19

10

8

-

3

5

12

3

5

-

2

-

7

6

2

-

5

5

7

14

36

20

27

16

58

1

384

344

8

8

35

19

12

2

11

22

46

24

42

4

10

5

20

52

24

8

11

8

4

13

34

19

25

16

56

-

240

158

2

7

35

12

10

2

11

10

17

24

36

-

4

1

16

49

21

8

8

7

0.350

7.843

18.370

6.457

16.780

17.220

85.326

-

94.980

4.317

0.240

5.430

4.277

0.890

0.417

0.579

2.450

1.930

1.864

18.840

22.000

-

0.580

0.110

3.210

45.605

26.636

6.530

1.110

1.595

0.088

0.603

0.540

0.340

0.671

1.076

1.524

-

0.396

0.027

0.120

0.776

0.122

0.074

0.042

0.290

0.223

0.193

0.110

0.785

0.611

-

0.145

0.110

0.201

0.931

1.268

0.816

0.139

0.228

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320 Continued

1

1

6

1

3

2

5

-

48

10

1

-

9

1

2

1

5

2

1

4

7

-

1

1

4

6

-

3

1

-

-

-

6

4

6

-

3

-

45

3

-

1

7

1

-

1

1

2

4

5

7

-

1

-

3

7

2

2

1

-

-

4

3

-

3

3

4

-

30

-

-

3

-

-

-

-

2

1

-

1

7

-

-

-

2

6

2

1

1

1

-

3

4

2

5

2

8

-

14

-

-

-

-

-

-

-

-

-

-

2

5

-

-

-

-

5

6

-

-

1

-

2

7

2

4

4

14

-

23

-

-

2

-

-

-

-

-

-

-

8

3

-

-

-

-

13

3

-

-

-

-

-

-

-

1

1

10

-

4

4

-

-

-

-

-

-

-

-

-

1

2

-

-

-

-

4

6

2

-

-

-

-

-

-

-

1

3

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

5

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

2

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

MATERIAL TESTING LABS, INC. 45-17151-01

MATTINGLY TESTING SERVICES, INC. 25-21479-01

MAXIM TECHNOLOGIES, INC. 22-01376-02

MET-CHEM TESTING LABS., INC. 43-27362-01

MID AMERICAN INSPECTION SERV, INC 21-26060-01

MIDWEST INDUSTRIAL X-RAY, INC. 33-27427-01

MIDWEST INSPECTION SERVICES 35-27005-01

MONTANA X-RAY, INC. 25-21134-01

MQS INSPECTION, INC. 12-00622-07

NAVY, DEPARTMENT OF THE* 45-23645-01

NDT SERVICES, INC. 52-19438-01

NDT SPECIALISTS, INC. 48-25917-01

NEWPORT NEWS SHIPBUILDING 45-09428-02

NOOTER CORP. 24-03783-01

NORFOLK SHIPBUILDING CO. 45-12042-01

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

NOVA DATA TESTING LABS, INC. 45-24872-01

PITT-DES MOINES, INC. 37-27878-01

PRECISION COMPONENTS CORP. 37-16280-01

PRIME NDT SERVICES, INC. 37-23370-01

PROFESSIONAL SERVICE INDUSTRIES 12-16941-03

PROFESSIONAL WELDING ASSOC., INC. 48-25806-01

PROGRESS SERV., INC. 34-19592-01

PSI ENERGY, INC. 13-15544-06

Q. C. LABORATORIES, INC. 09-11579-03

QSL INSPECTION, INC. 37-28085-01

QUALITY ENERGY SERV. & TESTS CORP. 35-26815-01

QUALITY INSPECTION & TESTING 50-29038-01

RAYTHEON ENGINEERS & CONST. 42-30336-01

RIVEST TESTING 35-27438-01

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

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1998
A-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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)

15

2

3

6

3

6

4

7

1

10

-

5

5

2

10

8

5

-

7

-

50

1

114

1,216

10

2

2

13

3

6

7

4

5

6

1

-

4

13

1

15

-

1

-

2

22

3

22

1,037

49

6

30

27

13

86

46

19

11

35

8

5

17

90

21

52

54

7

7

23

72

8

145

4,571

INDUSTRIAL RADIOGRAPHY - MULTIPLE LOCATION - 03320 ContinuedSGS INDUSTRIAL SERVICES 04-29067-02

S.K. MCBRYDE, INC. 32-25137-01

SOUTHWEST X-RAY CORPORATION 49-27434-01

SPEC CONSULTANTS, INC. 37-27891-01

ST. LOUIS TESTING LABS., INC. 24-00188-02

TECHNICAL WELDING LAB, INC. 42-25214-01

TEI ANALYTICAL SERVICES, INC. 37-28004-01

TENNESSEE VALLEY AUTHORITY 41-06832-06

TESTING INST. OF ALASKA, INC. 50-17446-01

TESTING TECHNOLOGIES, INC. 45-25007-01

TESTMASTER INSPECTION CO.,INC. 34-24872-01

THERMAL ENGINEERING, INT’L. 24-19500-01

TRI STATE INSPECTION 37-19640-01

TULSA GAMMA RAY, INC. 35-17178-01

TWIN PORTS TESTING, INC. 48-23476-01

U.S. INSPECTIONS SERVICES 34-06943-01

VALLEY INDUSTRIAL X-RAY 04-29076-01

VALLEY INSPECTION SERVICE, INC. 37-28385-01

VOITH HYDRO, INC. 37-16280-03

WESTERN X-RAY COMPANY 35-19993-01

WESTINGHOUSE ELECTRIC CORP. 37-05809-02

WOS TESTING COMPANY, INC. 48-26385-01

X-R-I TESTING 21-05472-01

Total 115

6

1

4

2

1

8

7

3

2

3

1

-

3

12

3

7

10

-

-

4

-

1

5

560

8

1

5

2

1

9

10

5

-

7

1

-

2

17

3

7

11

-

-

2

-

2

1

584

4

-

5

3

2

6

6

-

-

3

2

1

1

6

1

6

4

2

-

2

-

-

1

329

4

-

2

1

2

7

3

-

-

3

1

-

1

6

2

6

6

-

-

-

-

-

-

236

2

-

7

-

1

17

5

-

2

3

2

-

1

20

1

2

14

2

-

11

-

-

2

435

-

-

1

-

-

11

3

-

-

-

-

-

-

12

-

1

4

2

-

2

-

1

-

118

-

-

1

-

-

10

1

-

1

-

-

-

-

1

-

-

-

-

-

-

-

-

-

36

-

-

-

-

-

4

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

14

-

-

-

-

-

2

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

4

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

1

34

4

27

21

10

80

42

12

10

25

8

-

12

88

11

44

49

7

-

23

22

7

31

3,355

13.695

0.640

23.890

4.520

4.846

123.840

30.080

2.457

6.750

11.389

5.585

-

4.695

82.340

5.515

18.998

44.700

8.780

-

22.880

0.569

3.092

6.665

1,850.920

0.403

0.160

0.885

0.215

0.485

1.548

0.716

0.250

0.675

0.456

0.698

-

0.391

0.936

0.501

0.432

0.912

1.254

-

0.995

0.026

0.442

0.215

0.552

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

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1998
A-9

Thirty-First Annual Report, 1998 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)

14

44

260

215

482

126

171

46

1,358

FUEL FABRICATION FACILITIES - 21210BWX TECHNOLOGIES, INC. SNM-0042

COMBUSTION ENGINEERING INC. SNM-0033

FRAMATOME COGEMA FUELS SNM-1168

GE NUCLEAR ENERGY SNM-1097

GENERAL ATOMICS SNM-0696

NUCLEAR FUEL SERVICES, INC. SNM-0124

SIEMENS POWER CORP. NUCLEAR DIV. SNM-1227

WESTINGHOUSE ELECTRIC COMPANY SNM-1107

Total 8

42

56

200

440

46

387

276

135

1,582

URANIUM ENRICHMENT PLANTS - 21200USEC - Paducah GDP-1

USEC - Portsmouth GDP-2

Total 2

INDEPENDENT SPENT FUEL STORAGE INSTALLATION - 23200GENERAL ELECTRIC - MORRIS OPS SNM-2500

Total 1

2,832

2,881

5,713

32

32

179

176

355

9

9

41

18

27

176

13

66

104

82

527

35

39

74

10

10

58

27

19

141

1

45

75

70

436

7

1

8

2

2

58

12

3

68

-

16

33

35

225

-

-

-

-

-

25

14

5

35

-

13

34

44

170

-

-

-

-

-

53

40

2

11

-

7

23

68

204

-

-

-

-

-

7

15

-

-

-

-

-

6

28

-

-

-

-

-

-

4

-

-

-

-

-

-

4

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

298

230

516

1,086

542

660

716

486

4,534

3,053

3,097

6,150

53

53

284

186

256

871

60

534

545

440

3,176

221

216

437

21

21

175.195

139.059

25.273

174.185

3.582

64.951

131.711

212.288

926.244

13.462

10.159

23.621

2.561

2.561

0.617

0.748

0.099

0.200

0.060

0.122

0.242

0.482

0.292

0.061

0.047

0.054

0.122

0.122

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

APPENDIX A

Annual TEDE for Non-Reactor NRC Licensees

CY 1998
A-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

This page intentionally left blank.
B-1

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR

POWER FACILITIES

1998

Appendix B
B-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713 APPENDIX B Annual Whole Body Doses at Licensed Nuclear Power Facilities CY 1998

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 POINT 1 BWR

MILLSTONE POINT 2,3 PWR

MONTICELLO BWR

NINE MILE POINT 1,2 BWR

NORTH ANNA 1,2 PWR

7.00-

12.00

1,527

1,131

1,633

1,404

1,136

1,655

727

1,588

1,742

1,867

1,233

1,925

926

1,155

664

1,464

1,459

753

857

1,354

989

542

734

1,036

941

950

1,340

774

1,036

313

2,285

2,121

1,581

488

1,659

516

1,332

1,362

750

490

991

691

1,048

943

354

521

557

418

453

876

521

253

489

778

1,178

433

476

739

881

291

113

669

519

778

431

544

166

169

1,047

1,022

578

256

868

258

768

553

310

183

564

361

461

489

290

268

365

240

224

179

213

53

273

344

543

234

322

344

390

179

34

345

246

385

125

276

36

82

444

365

310

65

219

120

448

313

137

21

264

330

269

300

182

159

158

156

143

63

144

7

168

129

348

212

289

194

298

144

12

216

115

275

57

152

11

86

377

282

113

23

79

134

338

202

31

4

41

119

118

62

68

58

35

37

62

33

56

-

37

43

170

90

146

80

135

109

1

111

47

124

7

75

-

27

131

98

34

3

11

83

104

69

14

-

8

42

59

10

28

25

8

12

49

3

26

-

10

12

64

31

77

5

56

45

1

38

3

30

-

44

-

8

65

40

9

-

2

46

50

26

7

2

1

32

50

5

7

11

-

3

35

1

17

-

3

7

8

19

61

-

21

20

-

31

1

17

-

61

-

12

35

44

1

-

-

33

36

31

-

-

-

2

-

-

-

-

-

-

1

-

-

-

-

-

-

-

9

-

-

-

-

-

-

1

-

2

-

-

-

3

-

-

-

-

-

7

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

2,776

1,831

3,502

2,981

3,141

3,464

1,656

2,630

2,865

2,733

2,200

3,080

1,903

1,468

1,644

2,777

3,770

1,772

2,237

2,716

2,770

1,330

895

2,446

1,872

2,560

1,960

1,928

1,249

697

4,384

3,975

2,626

835

2,838

1,190

3,076

2,563

1,249

700

1,869

1,577

2,005

1,809

929

1,042

1,123

866

967

1,155

977

313

980

1,313

2,311

1,019

1,380

1,362

1,781

788

161

1,410

931

1,610

620

1,154

213

384

2,099

1,854

1,045

347

1,179

674

1,744

1,201

166.599

59.311

259.236

360.676

395.526

275.221

200.729

186.887

161.703

144.140

232.026

104.638

181.858

19.298

155.269

173.238

426.918

236.693

431.821

207.593

357.826

223.847

14.892

303.695

133.497

320.469

54.816

289.600

14.774

88.205

422.249

357.139

142.245

12.741

112.543

209.137

378.484

265.922
B-3

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

APPENDIX B

Annual Whole Body Doses at Licensed Nuclear Power Facilities

CY 1998

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: 36 BWRs

TOTALS: 69 PWRs

TOTALS: 105 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

2,045

547

657

1,268

1,464

799

358

828

493

1,089

765

687

886

3,090

718

1,217

1,446

1,358

697

1,260

1,658

483

1,057

1,068

946

1,015

896

1,254

832

28,719

48,361

77,080

723

695

372

865

973

210

309

463

273

955

283

444

285

587

518

720

662

754

254

638

691

247

517

299

487

524

190

76

155

16,077

20,962

37,039

502

295

235

296

473

142

117

187

144

394

113

293

82

246

32

357

273

290

26

269

380

27

345

370

297

256

77

4

25

7,623

9,566

17,189

283

222

173

163

261

33

95

128

105

279

56

186

37

148

9

245

154

96

5

183

277

6

134

189

141

256

13

-

3

5,321

5,146

10,467

94

115

51

64

95

-

8

63

33

169

11

39

4

71

-

99

50

10

-

48

136

-

37

69

62

140

1

-

1

2,209

1,721

3,930

48

48

31

18

64

-

-

29

17

133

3

13

-

26

-

16

19

11

-

13

66

-

9

14

7

29

1

-

-

921

641

1,562

45

33

33

4

36

-

1

11

10

241

-

3

-

13

-

3

13

9

-

14

25

-

3

3

-

15

-

-

-

700

429

1,129

-

-

-

-

1

-

-

-

-

6

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

13

22

35

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

3,740

1,955

1,552

2,678

3,367

1,184

888

1,709

1,075

3,266

1,231

1,665

1,294

4,181

1,277

2,657

2,617

2,528

982

2,425

3,233

763

2,102

2,012

1,940

2,235

1,178

1,334

1,016

61,583

86,849

148,424

1,695

1,408

895

1,410

1,903

385

530

881

582

2,177

466

978

408

1,091

559

1,440

1,171

1,170

285

1,165

1,575

280

1,045

944

994

1,220

282

80

184

32,864

38,487

71,344

366.028

308.323

216.563

192.425

366.040

41.945

71.446

169.253

116.649

760.596

57.749

170.476

41.100

195.600

18.509

255.295

183.977

134.459

13.513

188.959

360.778

16.722

156.415

199.399

162.210

286.020

24.032

3.042

10.382

6,822.256

6,347.110

13,169.366

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-
B-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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

RANCHO SECO 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

SAN ONOFRE 1 PWR Reported with San Onofre 2, 3

TOTAL REPORTING: 11 4,324 1,343 368 213 107 50 78 17 2 - - - - - 6,502 2,178 430.135

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

213

741

254

41

654

270

182

333

681

955

225

227

37

23

223

55

93

137

117

206

75

91

1

4

62

4

10

77

8

36

54

45

-

-

55

2

2

51

-

4

43

18

-

-

28

-

-

18

-

-

16

19

-

-

15

-

-

-

-

-

19

23

-

-

36

-

-

-

-

-

-

-

-

-

17

-

-

-

-

-

-

-

-

-

2

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

645

1,164

292

68

1,092

331

287

616

806

1,201

432

423

38

27

438

61

105

283

125

246

104.130

93.743

0.929

1.530

163.008

2.661

0.697

46.417

4.603

12.417

-

-

-

-

-

-

-

-

-

-

APPENDIX B

Annual Whole Body Doses at Licensed Nuclear Power Facilities

CY 1998
C-1

Thirty-First Annual Report, 1998 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

DOSE PERFORMANCE INDICATORS

BY REACTOR SITE

1969 - 1998

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-First Annual Report, 1998

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

1975 588.0 76.5 147 21 0.14 0.0

1976 464.6 56.6 476 289 0.61 0.6

1977 610.3 76.8 601 256 0.43 0.4

1978 627.2 77.5 722 189 0.26 0.3

1979 397.0 55.3 1,321 369 0.28 0.9

1980 452.8 63.7 1,233 342 0.28 0.8

1981 1,104.7 68.3 2,225 1,102 0.50 1.0

1982 905.4 58.61,608 803 0.50 0.9

1983 915.0 54.7 2,109 1,397 0.66 1.5

1984 1,289.1 77.4 1,742 8060.460.6

1985 1,192.3 73.61,262 286 0.23 0.2

1986 1,070.3 66.9 2,135 1,141 0.53 1.1

1987 1,366.1 88.9 1,123 382 0.34 0.3

1988 1,070.3 69.4 2,421 1,387 0.57 1.3

1989 1,066.3 72.0 2,063 711 0.34 0.7

1990 1,351.9 84.2 2,493 762 0.31 0.6

1991 1,515.8 88.4 2,064 351 0.17 0.2

1992 1,352.1 77.4 3,114 8760.28 0.6

1993 1,606.0 91.3 1,981 268 0.14 0.2

1994 1,662.8 93.6 1,361 172 0.13 0.1

1995 1,397.0 82.7 2,259 3860.17 0.3

19961,596.0 89.5 1,441 203 0.14 0.1

1997 1,621.9 95.9 1,195 119 0.10 0.07

1998 1,494.688.1 1,249 167 0.13 0.11

1977 355.657.0 331 878 0.26 0.2

1978 304.2 40.8 646 190 0.29 0.6

1979 221.0 40.0 704 132 0.19 0.6

1980 39.8 6.8 1,817 553 0.30 13.9

1981 573.4 73.61,237 229 0.19 0.4

1982 326.7 41.6 1,755 599 0.34 1.8

1983 561.2 68.2 1,485 772 0.52 1.4

1984 576.7 71.8 1,393 504 0.36 0.9

1985 717.7 91.9 619 60 0.10 0.1

1986581.3 70.7 1,575 627 0.40 1.1

1987 684.1 83.8 1,282 210 0.16 0.3

1988 1,386.1 87.4 1,764 530 0.30 0.4

1989 1,017.4 69.6 2,349 1,378 0.59 1.4

1990 1,271.0 85.3 1,675 348 0.21 0.3

1991 1,267.5 78.6 1,689 495 0.29 0.4

1992 1,441.9 89.1 1,414 289 0.20 0.2

1993 1,157.9 73.1 2,087 621 0.30 0.5

1994 1,514.688.6 487 44 0.09 0.0

1995 1,389.2 83.1 1,536453 0.29 0.3

19961,269.0 76.5 1,688 449 0.27 0.4

1997 1,159.3 72.1 1,391 3060.22 0.26

1998 523.1 33.5 700 59 0.08 0.11

1969 48.1 165 136 0.82 2.8

1970 43.5 290 194 0.67 4.5

1971 44.4 260 184 0.71 4.1

1972 43.5 195 181 0.93 4.2

1973 50.9 241 285 1.18 5.6

1974 40.7 70.3 281 2760.98 6.8

1975 35.1 59.8 300 180 0.60 5.1

197629.5 50.1 488 289 0.59 9.8

1977 43.673.4 465 334 0.72 7.7

1978 48.5 77.9 285 175 0.61 3.6

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 commercial reactors.
C-3

Thirty-First Annual Report, 1998 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

1979 13.0 23.5 623 455 0.73 35.0

1980 48.9 79.0 599 354 0.59 7.2

1981 56.9 90.6 479 160 0.33 2.8

1982 43.670.8 521 328 0.63 7.5

1983 42.3 71.0 493 263 0.53 6.2

1984 50.3 78.6297 155 0.52 3.1

1985 43.8 73.5 435 291 0.67 6.6

198661.0 95.5 202 84 0.42 1.4

1987 45.3 71.0 251 222 0.88 4.9

1988 46.1 72.8 303 170 0.56 3.7

1989 50.2 79.0 418 177 0.42 3.5

1990 51.3 77.2 351 232 0.66 4.5

1991 59.1 85.2 435 2260.52 3.8

1992 32.7 54.5 496277 0.56 8.5

1993 51.2 79.4 419 152 0.363.0

1994 49.5 75.3 310 119 0.38 2.4

1995 62.2 95.0 205 54 0.26 0.9

1997 22.4 54.1 258 55 0.21 2.46

1998 0.0 0.0 866 144 0.17 ---

1989 1,381.8 75.4 1,460 296 0.20 0.2

1990 1,740.2 84.1 1,081 1860.17 0.1

1991 1,377.2 68.9 1,641 550 0.34 0.4

1992 1,885.9 89.0 1,059 228 0.22 0.1

1993 1,899.3 86.9 1,043 273 0.26 0.1

1994 1,666.1 77.2 1,237 298 0.24 0.1

1995 1,914.7 85.4 1,134 2360.21 0.1

19961,854.9 82.1 1,356 334 0.25 0.2

1997 1,863.3 85.4 1,693 321 0.19 0.17

1998 1,971.9 88.9 1,869 259 0.14 0.13

1975 161.7 17.8 2,380 325 0.14 2.0

1976337.6 26.9 2,207 234 0.11 0.7

1977 1,327.5 73.7 1,858 863 0.46 0.7

1978 1,992.1 73.5 2,3761,792 0.75 0.9

1979 2,393.0 79.1 2,689 1,667 0.62 0.7

1980 2,182.1 73.62,712 1,826 0.67 0.8

1981 2,132.9 69.5 3,379 2,380 0.70 1.1

1982 2,025.4 67.6 3,277 2,220 0.68 1.1

1983 1,641.0 54.3 3,302 3,363 1.02 2.0

1984 1,431.9 54.2 2,962 1,940 0.65 1.4

1985 368.2 11.9 2,755 1,159 0.42 3.1

19860.0 0.0 3,003 1,050 0.35 ---

1987 0.0 0.0 3,115 1,181 0.38 ---

1988 0.0 0.0 3,324 1,155 0.35 ---

1989 0.0 0.0 2,683 656 0.24 ---

1990 0.0 0.0 2,717 1,310 0.48 ---

1991 445.0 17.7 1,815 354 0.20 0.8

1992 979.9 32.2 2,658 516 0.19 0.5

1993 675.1 66.8 3,594 870 0.24 1.3

1994 860.2 83.4 3,299 855 0.26 0.9

1995 1,165.8 98.6 2,540 409 0.16 0.4

19961,972.8 93.0 1,749 384 0.22 0.2

1997 1,928.8 90.2 2,092 5160.25 0.27

1998 1,961.9 87.7 1,577 361 0.23 0.18

BIG ROCK POINT

(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 - 0, 1065, 1118 MWe

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

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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

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

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

1976297.2 56.0 1,265 326 0.26 1.1

1977 291.1 55.7 1,512 1,120 0.74 3.8

1978 1,173.1 83.7 1,458 1,004 0.69 0.9

1979 810.0 60.1 2,891 2,602 0.90 3.2

1980 687.2 52.2 3,788 3,870 1.02 5.6

1981 925.2 56.9 3,854 2,638 0.68 2.9

1982 540.3 50.3 4,957 3,792 0.767.0

1983 636.7 44.3 5,602 3,475 0.62 5.5

1984 761.3 51.5 5,046 3,260 0.65 4.3

1985 822.2 58.4 4,057 2,804 0.69 3.4

19861,051.3 69.1 3,370 1,909 0.57 1.8

1987 1,152.4 80.63,052 1,419 0.461.2

1988 990.8 70.1 2,648 1,747 0.66 1.8

1989 990.9 65.8 3,844 1,786 0.46 1.8

1990 991.667.8 3,182 1,548 0.49 1.6

1991 952.8 64.5 2,586 778 0.30 0.8

1992 375.9 27.9 2,690 623 0.23 1.7

1993 470.0 33.8 2,921 872 0.30 1.9

1994 1,268.4 83.0 3,049 999 0.70

1995 1,411.7 92.9 2,657 683 0.26 0.5

19961,261.1 85.9 2,784 716 0.26 0.6

1997 1,474.0 94.1 2,212 411 0.19 0.28

1998 1,521.0 94.3 2,005 3960.20 0.26

1986894.5 88.6 1,081 76 0.07 0.1

1987 650.9 70.9 1,826 769 0.42 1.2

1988 1,534.7 86.3 1,222 459 0.38 0.3

1989 1,812.690.2 1,109 172 0.16 0.1

1990 1,567.3 78.8 1,396 434 0.31 0.3

1991 1,816.3 89.9 1,077 268 0.25 0.1

1992 1,888.4 90.1 1,021 199 0.19 0.1

1993 1,785.683.5 1,370 432 0.32 0.2

1994 1,953.3 90.7 962 280 0.29 0.1

1995 1,900.685.5 1,107 306 0.28 0.2

19961,758.4 79.3 1,610 455 0.28 0.3

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

1985 967.4 90.0 964 36 0.04 0.0

1986865.2 81.3 1,052 225 0.21 0.3

1987 759.0 71.1 1,082 393 0.360.5

1988 1,069.2 93.4 353 27 0.08 0.0

1989 1,000.3 85.4 1,055 283 0.27 0.3

1990 960.7 84.1 1,134 442 0.39 0.5

1991 1,193.1 99.7 280 21 0.07 0.0

1992 967.5 83.0 1,133 336 0.30 0.3

1993 1,002.9 86.4 1,126 225 0.20 0.2

1994 1,196.4 100.0 191 14 0.07 0.0

1995 989.684.7 1,062 187 0.18 0.2

1996 1,066.0 90.5 980 248 0.25 0.2

1997 1,022.2 100.0 248 12 0.05 0.01

1998 972.2 91.3 929 201 0.22 0.21

1976753.4 95.2 507 74 0.15 0.1

1977 583.0 72.1 2,265 547 0.24 0.9

1978 1,188.5 75.8 1,391 500 0.360.4

1979 1,161.0 74.0 1,428 805 0.56 0.7

1980 1,309.9 84.1 1,496677 0.45 0.5

1981 1,379.7 83.1 1,555 607 0.39 0.4

1982 1,238.3 73.7 1,805 1,057 0.59 0.9

1983 1,397.2 81.61,915 668 0.35 0.5

1984 1,389.4 79.3 1,369 479 0.35 0.3
C-5

Thirty-First Annual Report, 1998 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

1985 1,189.8 68.4 1,598 694 0.43 0.6

19861,530.0 87.2 1,296 347 0.27 0.2

1987 1,207.3 71.8 1,384 412 0.30 0.3

1988 1,397.7 81.0 1,296291 0.22 0.2

1989 333.620.1 1,786346 0.19 1.0

1990 161.1 11.0 2,019 304 0.15 1.9

1991 1,085.0 64.7 1,974 132 0.07 0.1

1992 1,271.2 73.9 1,979 330 0.17 0.3

1993 1,462.1 83.9 1,462 405 0.28 0.3

1994 1,342.1 79.4 1,482 454 0.31 0.3

1995 1,542.8 89.9 1,203 235 0.20 0.2

19961,438.5 82.4 1,167 239 0.20 0.2

1997 1,499.689.1 1,091 229 0.21 0.15

1998 1,523.1 89.3 1,042 187 0.18 0.12

1986638.9 49.9 1,724 286 0.17 0.4

1987 1,651.2 75.9 1,865 449 0.24 0.3

1988 1,675.2 77.2 2,009 556 0.28 0.3

1989 1,733.6 79.5 1,660 334 0.20 0.2

1990 1,616.3 70.8 2,174 809 0.37 0.5

1991 1,691.5 74.6 1,871 462 0.25 0.3

1992 1,962.8 83.9 1,515 414 0.27 0.2

1993 1,896.1 81.5 1,564 396 0.25 0.2

1994 2,105.2 90.2 1,268 207 0.16 0.1

1995 2,011.9 85.3 1,892 462 0.24 0.2

19961,879.1 80.5 1,588 302 0.19 0.2

1997 2,028.2 89.3 1,561 266 0.17 0.13

1998 2,006.4 89.6 1,123 162 0.14 0.08

1988 701.3 84.2 769 130 0.17 0.2

1989 348.3 48.5 1,196372 0.31 1.1

1990 435.8 55.1 1,390 553 0.40 1.3

1991 722.7 80.8 1,010 233 0.23 0.3

1992 589.7 68.6 1,195 431 0.36 0.7

1993 701.5 79.61,253 498 0.40 0.7

1994 883.3 94.8 409 63 0.15 0.0

1995 731.1 83.0 1,182 3160.27 0.4

1996 634.7 66.7 1,154 350 0.30 0.6

1997 0.0 0.0 738 172 0.23 ---

1998 0.0 0.0 866 144 0.17 ---

1991 644.4 82.2 985 148 0.15 0.2

1992 830.8 84.0 1,128 188 0.17 0.2

1993 853.8 81.2 945 109 0.12 0.1

1994 1,750.0 93.7 970 90 0.09 0.1

1995 2,022.692.5 951 179 0.19 0.1

19961,804.8 81.4 1,462 288 0.20 0.2

1997 2,002.4 93.4 870 1460.17 0.07

1998 2,037.8 94.9 967 232 0.24 0.11

1976807.4 83.1 395 116 0.29 0.1

1977 573.0 76.1 802 300 0.37 0.5

1978 744.8 73.6778 3360.43 0.5

1979 1,373.0 65.3 1,445 718 0.50 0.5

1980 1,552.4 74.1 1,345 493 0.37 0.3

1981 1,557.3 73.4 1,341 656 0.49 0.4

1982 1,461.6 69.8 1,527 699 0.46 0.5

1983 1,456.5 71.2 1,418 658 0.46 0.5

1984 1,526.0 75.3 1,559 762 0.49 0.5

1985 925.4 47.61,984 945 0.48 1.0

19861,307.1 73.4 1,774 745 0.42 0.6

1987 1,199.5 70.2 1,696 666 0.39 0.6

CALVERT CLIFFS 1, 2

(continued)

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

COOK 1, 2

Docket 5-315; DPR-58, -74

1st commercial operation

8/75, 7/78

Type - PWRs

Capacity - 1000, 1060 MWe
C-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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 (continued)

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

1988 1,160.4 63.5 2,266 867 0.38 0.7

1989 1,433.1 72.8 1,575 493 0.31 0.3

1990 1,318.5 67.9 1,851 580 0.31 0.4

1991 1,837.4 90.2 815 69 0.08 0.0

1992 760.9 50.8 1,954 492 0.25 0.6

1993 1,927.7 98.5 587 44 0.07 0.0

1994 1,105.2 65.2 1,748 479 0.27 0.4

1995 1,656.0 82.1 1,310 203 0.15 0.1

19961,938.9 92.7 1,114 214 0.19 0.1

1997 1,189.7 59.7 1,864 550 0.30 0.46

1998 0.0 0.0 1,155 105 0.09 ---

1975 456.4 83.6 579 117 0.20 0.3

1976433.3 75.5 763 350 0.46 0.8

1977 538.2 86.2 315 198 0.63 0.4

1978 576.0 91.0 297 158 0.53 0.3

1979 591.0 87.6426221 0.52 0.4

1980 448.3 71.2 785 859 1.09 1.9

1981 457.1 71.2 935 579 0.62 1.3

1982 622.3 84.6 743 542 0.73 0.9

1983 396.6 63.3 1,383 1,293 0.93 3.3

1984 411.9 67.2 1,598 799 0.50 1.9

1985 127.3 21.5 1,980 1,333 0.67 10.5

1986480.0 74.7 895 320 0.36 0.7

1987 652.3 96.2 549 103 0.19 0.2

1988 493.4 67.9 942 251 0.27 0.5

1989 564.3 76.2 1,202 343 0.29 0.6

1990 602.0 79.4 1,174 379 0.32 0.6

1991 566.3 78.8 1,099 405 0.37 0.7

1992 731.0 96.4 463 84 0.18 0.1

1993 436.1 58.8 1,130 391 0.35 0.9

1994 262.2 35.1 333 79 0.24 0.3

1995 486.5 66.8 1,095 228 0.21 0.5

1996742.1 97.9 468 48 0.10 0.1

1997 622.8 84.4 1,125 174 0.16 0.28

1998 555.9 75.9 977 182 0.19 0.33

1978 311.5 41.4 643 321 0.50 1.0

1979 453.0 58.9 1,150 495 0.43 1.1

1980 404.1 53.2 1,053 625 0.59 1.5

1981 490.4 62.2 1,120 408 0.36 0.8

1982 589.8 76.0 780 177 0.23 0.3

1983 452.1 58.8 1,720 552 0.32 1.2

1984 774.2 94.5 549 49 0.09 0.1

1985 344.2 47.61,976689 0.35 2.0

1986319.5 41.8 1,057 472 0.45 1.5

1987 436.0 60.9 1,384 488 0.35 1.1

1988 690.2 84.0 569 64 0.11 0.1

1989 352.8 48.8 880 234 0.27 0.7

1990 497.8 63.8 1,441 476 0.33 1.0

1991 654.6 82.0 821 116 0.14 0.2

1992 632.1 76.1 1,403 424 0.30 0.7

1993 722.4 85.0 683 60 0.09 0.1

1994 711.9 84.3 1,079 228 0.21 0.3

1995 866.3 100.0 209 8 0.04 0.0

1996290.8 37.7 1,192 353 0.30 1.2

1997 0.0 0.0 973 179 0.18 ---

1998 739.9 90.3 313 19 0.060.03
C-7

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

DAVIS-BESSE 1

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

1978 326.4 48.7 421 48 0.11 0.1

1979 381.0 67.0 304 30 0.10 0.1

1980 256.4 36.2 1,283 154 0.12 0.6

1981 531.4 67.4 578 58 0.10 0.1

1982 390.8 51.5 1,350 164 0.12 0.4

1983 592.1 73.0 718 80 0.11 0.1

1984 518.5 62.5 1,088 177 0.16 0.3

1985 238.3 31.2 718 71 0.10 0.3

19863.3 1.3 981 124 0.13 37.6

1987 618.0 89.6 625 47 0.08 0.1

1988 144.1 27.1 1,183 307 0.262.1

1989 880.0 98.6404 38 0.09 0.0

1990 500.0 56.7 1,377 489 0.36 1.0

1991 703.681.8 1,000 216 0.22 0.3

1992 915.2 100.0 287 19 0.07 0.0

1993 729.5 83.4 1,244 348 0.28 0.5

1994 768.4 88.0 861 144 0.17 0.2

1995 920.4 100.0 2567 0.03 0.0

1996775.8 85.3 949 167 0.18 0.2

1997 820.0 94.0 213 10 0.05 0.01

1998 699.8 83.2 980 155 0.16 0.22

1986 641.5 80.6 1,260 304 0.24 0.5

1987 1,688.6 83.0 1,170 336 0.29 0.2

1988 1,386.1 67.6 1,826 877 0.48 0.6

1989 1,899.0 87.5 1,646 465 0.28 0.2

1990 1,952.691.0 1,441 323 0.22 0.2

1991 1,809.683.8 2,040 546 0.27 0.3

1992 1,995.7 90.9 1,850 459 0.25 0.2

1993 2,008.691.4 1,508 281 0.19 0.1

1994 1,832.683.3 2,317 590 0.26 0.3

1995 1,950.3 90.0 1,615 286 0.18 0.1

19962,003.6 90.7 1,462 176 0.12 0.1

1997 1,948.7 92.7 1,331 219 0.17 0.09

1998 1,955.1 92.8 1,313 173 0.13 0.09

1969 99.7 286 2.9

1970 163.1 143 0.9

1971 394.5 715 1.8

1972 1,243.7 728 0.6

1973 1,112.2 1,341 939 0.70 0.8

1974 842.5 54.9 1,594 1,662 1.04 2.0

1975 708.1 54.62,310 3,423 1.48 4.8

19761,127.2 80.8 1,746 1,680 0.96 1.5

1977 1,132.9 77.0 1,862 1,694 0.91 1.5

1978 1,242.2 79.5 1,9461,529 0.79 1.2

1979 1,013.0 74.7 2,407 1,800 0.75 1.8

1980 1,074.4 55.0 2,717 2,105 0.77 2.0

1981 1,035.7 51.5 2,331 2,802 1.20 2.7

1982 1,085.3 77.9 2,572 2,923 1.14 2.7

1983 913.665.6 2,854 3,582 1.26 3.9

1984 789.8 55.3 2,261 1,774 0.78 2.2

1985 903.0 64.5 2,817 1,686 0.60 1.9

1986 740.5 52.6 3,111 2,668 0.86 3.6

1987 933.9 74.0 2,052 1,145 0.561.2

1988 1,014.7 75.8 2,414 1,409 0.58 1.4

1989 1,184.2 83.1 2,259 1,131 0.50 1.0

1990 1,107.8 76.6 2,235 1,400 0.63 1.3

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 commercial reactors.
C-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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

(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 - 822, 852 MWe

FERMI 2

Docket 50-341; NPF-43

1st commercial operation 1/88

Type - BWR

Capacity - 1098 MWe

1991 675.2 60.7 2,044 1,005 0.49 1.5

1992 872.4 75.4 1,812 619 0.34 0.7

1993 960.1 68.5 2,751 1,655 0.60 1.7

1994 690.2 51.7 2,336 833 0.36 1.2

1995 643.1 49.8 2,482 875 0.35 1.4

1996612.6 47.7 1,788 456 0.26 0.7

1997 1,096.2 79.5 2,747 467 0.17 0.43

1998 1,354.7 90.62,311 427 0.18 0.32

1976305.2 78.0 350 105 0.30 0.3

1977 353.678.9 538 299 0.56 0.8

1978 149.2 33.2 1,112 974 0.88 6.5

1979 352.0 78.0 757 275 0.360.8

1980 339.1 73.3 1,108 671 0.61 2.0

1981 277.7 69.8 1,286 790 0.61 2.8

1982 278.5 74.7 524 229 0.44 0.8

1983 283.0 62.9 1,468 1,135 0.77 4.0

1984 329.4 72.9 611 189 0.31 0.6

1985 236.2 53.8 1,414 1,112 0.79 4.7

1986365.5 82.0 476 187 0.39 0.5

1987 308.4 64.7 1,094 667 0.61 2.2

1988 386.5 75.2 1,136 614 0.54 1.6

1989 388.5 79.0 425 194 0.460.5

1990 367.4 75.8 1,460 861 0.59 2.3

1991 503.7 94.5 336202 0.60 0.4

1992 416.5 81.9 1,043 502 0.48 1.2

1993 393.4 79.5 1,043 407 0.39 1.0

1994 498.694.0 493 120 0.24 0.2

1995 452.5 83.8 1,129 357 0.32 0.8

1996476.8 90.7 1,093 270 0.25 0.6

1997 474.4 94.4 352 63 0.18 0.13

1998 438.3 86.6 1,019 237 0.23 0.54

1978 713.8 86.5 527 108 0.20 0.2

1979 211.0 28.61,227 643 0.52 3.0

1980 557.3 69.3 1,330 435 0.33 0.8

1981 310.2 41.4 1,331 512 0.38 1.7

1982 1,271.5 79.2 1,453 484 0.33 0.4

1983 1,356.5 83.0 1,938 1,021 0.53 0.8

1984 1,447.0 86.6 2,046 902 0.44 0.6

1985 1,368.2 81.1 2,551 799 0.31 0.6

19861,409.4 83.8 2,314 858 0.37 0.6

1987 1,369.7 84.7 1,871 598 0.32 0.4

1988 1,567.7 92.3 1,840 552 0.30 0.4

1989 1,402.9 84.62,206749 0.34 0.5

1990 1,464.0 86.7 1,700 457 0.27 0.3

1991 1,464.0 88.1 1,645 648 0.39 0.4

1992 1,331.7 81.8 2,018 805 0.40 0.6

1993 1,455.5 88.3 1,284 333 0.260.2

1994 1,587.2 93.0 1,035 250 0.24 0.2

1995 1,311.2 83.8 1,574 460 0.29 0.4

19961,549.2 90.9 1,150 232 0.20 0.1

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

1989 624.0 68.5 1,270 255 0.20 0.4

1990 848.2 84.7 462 83 0.18 0.1

1991 739.0 77.0 1,223 228 0.19 0.3

1992 874.3 81.3 1,213 245 0.20 0.3

1993 984.3 92.9 360 35 0.10 0.0

1994 0.0 2.2 1,130 213 0.19 ---

1995 618.3 86.9 390 28 0.07 0.0
C-9

Thirty-First Annual Report, 1998 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

FERMI

(continued)

FITZPATRICK

Docket 50-333; DPR-59

1st commercial operation 7/75

Type - BWR

Capacity - 785 MWe

FORT CALHOUN

Docket 50-285; DPR-40

1st commercial operation 6/74

Type - PWR

Capacity - 478 MWe

GINNA

Docket 50-244; DPR-18

1st commercial operation 7/70

Type - PWR

Capacity - 480 MWe

1996577.5 69.1 1,402 157 0.11 0.3

1997 637.0 66.6 623 49 0.08 0.08

1998 815.8 79.9 1,362 208 0.15 0.25

1976489.0 71.6 600 202 0.34 0.4

1977 460.5 68.4 1,380 1,080 0.78 2.3

1978 497.0 72.1 904 909 1.01 1.8

1979 349.0 50.8 850 859 1.01 2.5

1980 509.5 70.3 2,0562,040 0.99 4.0

1981 562.9 74.7 2,490 1,425 0.57 2.5

1982 583.675.0 2,322 1,190 0.51 2.0

1983 546.2 70.6 1,715 1,090 0.64 2.0

1984 576.2 76.8 1,610 971 0.60 1.7

1985 492.3 63.7 1,845 1,051 0.57 2.1

1986711.2 90.6 1,185 411 0.35 0.6

1987 496.2 70.3 1,578 940 0.60 1.9

1988 514.0 69.0 1,553 786 0.51 1.5

1989 727.5 92.3 1,027 377 0.37 0.5

1990 543.8 72.61,536884 0.58 1.6

1991 399.7 53.4 1,269 333 0.26 0.8

1992 0.0 0.0 2,374 674 0.28 ---

1993 559.681.7 1,427 232 0.16 0.4

1994 588.4 83.2 1,595 322 0.20 0.5

1995 569.8 74.5 1,249 327 0.26 0.6

1996623.3 83.1 1,384 357 0.26 0.6

1997 756.2 95.9 662 91 0.14 0.12

1998 562.8 78.0 1,781 358 0.20 0.64

1975 252.3 67.4 469 294 0.63 1.2

1976 265.9 69.5 516 313 0.61 1.2

1977 351.8 79.4 535 297 0.560.8

1978 342.3 75.1 596410 0.69 1.2

1979 440.0 95.7 451 1260.28 0.3

1980 242.3 60.4 891 668 0.75 2.8

1981 260.9 72.3 822 458 0.56 1.8

1982 418.0 89.7 604 217 0.36 0.5

1983 330.4 73.1 860 433 0.50 1.3

1984 279.2 59.9 913 563 0.62 2.0

1985 367.0 73.7 982 373 0.38 1.0

1986431.8 94.3 756 74 0.10 0.2

1987 366.0 75.4 1,247 388 0.31 1.1

1988 315.5 74.1 1,594 272 0.17 0.9

1989 395.7 89.2 1,210 93 0.08 0.2

1990 290.0 64.2 760 290 0.38 1.0

1991 391.1 91.7 284 57 0.20 0.1

1992 303.4 65.9 802 272 0.34 0.9

1993 369.7 80.8 713 157 0.22 0.4

1994 492.8 99.6211 23 0.11 0.0

1995 402.8 83.2 627 139 0.22 0.3

1996374.9 79.5 740 226 0.31 0.6

1997 435.9 93.6258 41 0.160.09

1998 387.7 82.5 788 224 0.28 0.58

1971 327.8 340 430 1.261.3

1972 293.6677 1,032 1.52 3.5

1973 409.5 319 224 0.70 0.5

1974 253.7 62.4 884 1,225 1.39 4.8

1975 365.2 76.7 685 538 0.79 1.5

1976248.8 58.2 758 636 0.84 2.6

1977 365.6 85.5 530 401 0.76 1.1

1978 386.5 80.6 657 450 0.68 1.2

1979 355.0 72.8 878 592 0.67 1.7
C-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

GINNA (continued)

GRAND GULF

Docket 50-416; NPF-29

1st commercial operation 7/85

Type - BWR

Capacity - 1204 MWe

HADDAM NECK4

Docket 50-213; DPR-61

1st commercial operation 1/68

Type - PWR

Capacity - 560 MWe

1980 370.5 76.0 1,073 708 0.66 1.9

1981 399.0 82.1 925 655 0.71 1.6

1982 289.0 58.8 1,117 1,140 1.02 3.9

1983 365.0 74.6 969 855 0.88 2.3

1984 378.1 77.2 713 395 0.55 1.0

1985 436.7 87.9 845 426 0.50 1.0

1986433.3 87.4 901 357 0.40 0.8

1987 459.0 91.5 773 344 0.45 0.7

1988 423.1 87.4 897 295 0.33 0.7

1989 369.2 75.9 1,254 605 0.48 1.6

1990 414.3 84.4 991 347 0.35 0.8

1991 418.686.7 947 328 0.35 0.8

1992 417.686.9 832 261 0.31 0.6

1993 419.686.3 856193 0.23 0.5

1994 405.3 83.2 679 138 0.20 0.3

1995 437.0 89.6738 1360.18 0.3

1996347.9 71.1 976 168 0.17 0.5

1997 444.691.8 533 81 0.15 0.18

1998 491.8 100.0 161 15 0.09 0.03

1986494.7 60.9 1,486 436 0.29 0.9

1987 920.7 82.2 1,358 420 0.31 0.5

1988 1,136.6 96.7 692 147 0.21 0.1

1989 932.680.0 1,972 498 0.25 0.5

1990 883.5 78.9 1,765 482 0.27 0.5

1991 1,085.2 94.0 699 94 0.13 0.1

1992 969.0 83.7 2,032 484 0.24 0.5

1993 936.4 81.5 1,807 332 0.18 0.4

1994 1,143.2 96.6 455 56 0.12 0.0

1995 952.9 80.4 1,589 342 0.22 0.4

19961,096.2 88.7 1,564 357 0.23 0.3

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

1969 438.5 138 106 0.77 0.2

1970 424.7 734 689 0.94 1.6

1971 502.2 289 342 1.18 0.7

1972 515.6355 325 0.91 0.6

1973 293.1 951 697 0.73 2.4

1974 521.4 91.2 550 201 0.37 0.4

1975 494.3 89.9 795 703 0.88 1.4

1976482.9 82.5 644 449 0.70 0.9

1977 480.7 83.9 894 641 0.72 1.3

1978 563.4 98.6 216 117 0.54 0.2

1979 493.0 87.5 1,2261,162 0.95 2.4

1980 426.8 75.0 1,860 1,353 0.73 3.2

1981 487.5 84.3 1,554 1,0360.67 2.1

1982 543.9 93.4 559 1260.23 0.2

1983 453.7 77.8 1,645 1,384 0.84 3.1

1984 404.0 71.7 1,430 1,2160.85 3.0

1985 556.1 98.4 384 101 0.26 0.2

1986294.8 53.6 1,945 1,567 0.81 5.3

1987 304.654.0 1,763 750 0.43 2.5

1988 397.4 70.3 735 237 0.32 0.6

1989 356.4 67.2 1,455 596 0.41 1.7

1990 142.7 32.2 979 421 0.43 3.0

1991 444.4 76.4 1,168 590 0.51 1.3

1992 465.2 80.1 797 202 0.25 0.4

4 Haddam Neck was shutdown 12/4/96 and is no longer in the count of operating reactors.
C-11

Thirty-First Annual Report, 1998 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 NECK

(continued)

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 - 800, 855 MWe

HOPE CREEK 1

Docket 50-354; NPF-57

1st commercial operation 12/86

Type - BWR

Capacity - 1031 MWe

1993 448.681.6 1,004 408 0.41 0.9

1994 455.677.7 463 135 0.29 0.3

1995 439.4 77.7 1,006442 0.44 1.0

1996331.8 55.7 673 175 0.26 0.5

1997 -1.3 0.0 219 11 0.05 -8.46

1998 0.0 0.0 1,249 167 0.13 ---

1988 652.9 75.0 721 169 0.23 0.3

1989 690.6 79.5 929 156 0.17 0.2

1990 776.4 89.6 453 85 0.19 0.1

1991 724.8 81.5 872 2260.260.3

1992 661.8 74.9 930 213 0.23 0.3

1993 913.0 99.7 327 31 0.09 0.0

1994 740.8 82.7 1,089 222 0.20 0.3

1995 731.1 83.8 1,068 174 0.16 0.2

1996860.6 95.4 444 17 0.04 0.0

1997 673.6 80.4 1,131 149 0.13 0.22

1998 766.2 90.4 931 133 0.14 0.17

1976496.3 83.8 630 134 0.21 0.3

1977 446.8 66.3 1,303 465 0.36 1.0

1978 513.0 72.8 1,304 248 0.19 0.5

1979 401.0 54.62,131 582 0.27 1.5

1980 1,008.7 70.9 1,930 449 0.23 0.4

1981 870.9 64.3 2,899 1,337 0.46 1.5

1982 768.0 56.6 3,418 1,460 0.43 1.9

1983 934.7 68.6 3,428 1,299 0.38 1.4

1984 658.6 47.3 4,110 2,218 0.54 3.4

1985 1,211.0 79.62,841 818 0.29 0.7

1986872.0 64.8 3,4861,497 0.43 1.7

1987 1,295.4 89.7 2,202 8160.37 0.6

1988 1,001.4 70.4 2,509 1,401 0.561.4

1989 1,271.1 87.1 1,350 5560.41 0.4

1990 1,268.0 83.5 2,902 1,455 0.50 1.1

1991 1,152.4 77.4 2,508 1,161 0.46 1.0

1992 1,293.8 88.61,615 550 0.34 0.4

1993 1,189.685.5 1,733 669 0.39 0.6

1994 1,289.0 87.1 2,243 864 0.39 0.7

1995 1,376.3 90.6 1,458 488 0.33 0.4

19961,519.6 94.0 1,495 441 0.29 0.3

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

1987 869.2 86.4 589 117 0.20 0.1

1988 832.7 80.7 1,734 287 0.17 0.3

1989 791.1 77.8 1,873 465 0.25 0.6

1990 966.4 91.6 1,394 196 0.14 0.2

1991 882.5 84.2 1,700 373 0.22 0.4

1992 841.9 80.8 1,694 436 0.26 0.5

1993 1,049.2 97.8 688 98 0.14 0.1

1994 852.0 81.2 1,779 3260.18 0.3

1995 844.5 79.8 1,571 1960.12 0.2

1996 806.9 77.4 1,069 158 0.15 0.2

1997 731.8 77.8 1,747 350 0.20 0.06

1998 993.2 98.0 620 55 0.09 0.06
C-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

HUMBOLDT BAY5

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 - 0, 951, 965 MWe

INDIAN POINT 16

, 2

INDIAN POINT 2

Docket 50-247; DPR-26

1st commercial operation 8/74

Type - PWR

Capacity - 951 MWe

1969 44.6 125 164 1.31 3.7

1970 49.3 115 209 1.82 4.2

1971 39.6140 292 2.09 7.4

1972 43.1 127 253 1.99 5.9

1973 50.1 210 266 1.27 5.3

1974 43.4 83.8 296318 1.07 7.3

1975 45.3 83.9 265 339 1.28 7.5

197623.5 46.4 523 683 1.31 29.1

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

1978 0.0 0.0 320 335 1.05 ---

1979 0.0 0.0 135 31 0.23 ---

1980 0.0 0.0 142 22 0.15 ---

1981 0.0 0.0 75 9 0.12 ---

1982 0.0 0.0 71 19 0.27 ---

1983 0.0 0.0 84 17 0.20 ---

1993 0.0 0.0 24 1 0.04 ---

1994 0.0 0.0 21 1 0.05 ---

1995 0.0 0.0 42 2 0.05 ---

19960.0 0.0 66 5 0.08 ---

1997 0.0 0.0 105 160.15 ---

1998 0.0 0.0 929 201 0.22 ---

1969 206.2 298 1.4

1970 43.3 1,639 37.8

1971 154.0 768 5.0

1972 142.3 967 6.8

1973 0.0 2,998 5,262 1.76 ---

1974 556.1 59.4 1,019 910 0.89 1.6

1975 584.4 74.8 891 705 0.79 1.2

1976273.9 34.8 1,590 1,950 1.23 7.1

1977 1,278.3 75.3 1,391 1,070 0.77 0.8

1978 1,172.3 67.8 1,909 2,006 1.05 1.7

1979 574.0 71.4 1,349 1,279 0.95 2.2

1980 510.8 64.8 1,577 971 0.62 1.9

1982 532.4 65.4 2,144 1,635 0.76 3.1

1983 702.684.0 1,057 486 0.46 0.7

1984 416.7 51.9 2,919 2,644 0.91 6.3

1985 791.4 95.7 708 192 0.27 0.2

1986 457.5 56.2 1,926 1,250 0.65 2.7

1987 611.4 73.4 1,980 1,217 0.61 2.0

1988 719.3 86.9 890 235 0.26 0.3

1989 532.5 64.6 2,093 1,436 0.69 2.7

1990 618.0 66.6 1,061 608 0.57 1.0

1991 461.2 55.7 1,810 1,468 0.81 3.2

1992 930.9 99.1 489 97 0.20 0.1

1993 702.1 75.7 1,514 675 0.45 1.0

1994 903.8 100.0 381 48 0.13 0.1

1995 582.4 70.8 1,690 548 0.32 0.9

1996927.8 94.8 388 54 0.14 0.1

1997 360.6 45.1 1,340 367 0.27 1.02

1998 282.8 31.5 1,154 290 0.25 1.03

5 Humboldt Bay had been shutdown 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 commercial 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 commercial reactors.

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

Thirty-First Annual Report, 1998 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

1979 574.0 66.5 808 636 0.79 1.1

1980 367.3 53.2 977 308 0.32 0.8

1981 367.5 59.8 677 364 0.54 1.0

1982 171.5 22.5 1,477 1,2260.83 7.1

1983 7.8 2.6941 607 0.65 77.8

1984 714.4 76.3 658 230 0.35 0.3

1985 566.5 66.0 1,093 570 0.52 1.0

1986655.3 73.4 588 202 0.34 0.3

1987 574.662.7 1,308 500 0.38 0.9

1988 792.5 83.3 451 93 0.21 0.1

1989 587.8 61.1 1,800 876 0.49 1.5

1990 595.3 62.9 1,066 358 0.34 0.6

1991 862.8 87.5 299 40 0.13 0.0

1992 561.7 61.4 1,003 212 0.21 0.4

1993 140.5 14.9 478 60 0.13 0.4

1994 0.0 0.0 529 58 0.11 ---

1995 174.8 21.4 638 67 0.11 0.4

1996695.3 74.8 289 22 0.08 0.0

1997 495.1 54.9 1,608 234 0.15 0.47

1998 874.0 95.3 213 15 0.07 0.02

1975 401.9 88.2 104 28 0.27 0.1

1976405.9 78.9 381 270 0.71 0.7

1977 425.0 79.9 312 140 0.45 0.3

1978 466.6 89.5 335 154 0.46 0.3

1979 412.0 79.0 343 127 0.37 0.3

1980 433.8 82.1 401 165 0.41 0.4

1981 451.8 86.7 383 141 0.37 0.3

1982 458.4 87.6353 101 0.29 0.2

1983 444.1 83.7 445 165 0.37 0.4

1984 455.3 85.7 482 139 0.29 0.3

1985 443.1 82.4 519 1760.34 0.4

1986461.7 85.8 502 169 0.34 0.4

1987 480.0 89.7 755 2260.30 0.5

1988 467.5 88.3 705 210 0.30 0.4

1989 449.1 84.9 570 239 0.42 0.5

1990 468.8 87.9 490 145 0.30 0.3

1991 441.8 83.4 495 221 0.45 0.5

1992 471.4 88.0 450 122 0.27 0.3

1993 457.1 86.8 436 106 0.24 0.2

1994 475.688.8 364 72 0.20 0.2

1995 455.687.8 415 109 0.26 0.2

1996380.4 71.8 474 126 0.27 0.3

1997 269.8 56.0 278 56 0.20 0.21

1998 423.0 87.2 384 88 0.23 0.21

1970 15.3 111 7.2

1971 323.1 218 158 0.72 4.8

1972 29.2 151 1.14 5.9

1973 24.4 157 1.41 9.1

1974 37.9 81.0 115 139 1.21 3.7

1975 32.0 69.6 165 234 1.42 7.3

197621.2 47.6 118 110 0.93 5.2

1977 11.3 33.7 141 225 1.60 19.9

1978 21.662.0 182 164 0.90 7.6

1979 24.0 71.8 153 1861.22 7.8

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

LACROSSE8

Docket 50-409; DPR-45

1st commercial operation 11/69

Type - BWR

Capacity - 48 MWe

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

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 commercial reactors.
C-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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

LACROSSE

(continued)

LASALLE 1, 2

Docket 50-373, -374;

NPF-11, -18

1st commercial operation

1/84, 6/84

Type - BWR

Capacity - 1036, 1036 MWe

LIMERICK 1, 2

Docket 50-352, 50-353;

NPF-39,-85

1st commercial operation

2/86, 1/90

Type - BWRs

Capacity - 1134, 1115 MWe

MAINE YANKEE9

Docket 50-309; DPR-36

1st commercial operation 12/72

Type - PWR

Capacity - 860 MWe

1980 26.4 68.5 124 218 1.76 8.3

1981 29.6 76.0 187 123 0.66 4.2

1982 17.2 44.6148 205 1.39 11.9

1983 24.8 59.7 160 313 1.96 12.6

1984 38.5 80.5 288 252 0.88 6.5

1985 39.2 86.7 373 173 0.46 4.4

198619.646.1 260 290 1.12 14.8

1987 0.0 0.0 127 68 0.54 ---

1993 0.0 0.0 48 8 0.17 ---

1994 0.0 0.0 65 8 0.12 ---

1995 0.0 0.0 31 3 0.10 ---

19960.0 0.0 25 4 0.15 ---

1997 0.0 0.0 23 2 0.09 ---

1998 0.0 0.0 1,155 105 0.09 ---

1984 677.8 77.8 1,245 252 0.20 0.4

1985 987.9 53.0 1,635 685 0.42 0.7

1986929.5 50.6 1,614 898 0.56 1.0

1987 1,030.0 59.3 1,744 1,3960.80 1.4

1988 1,317.671.6 2,737 2,471 0.90 1.9

1989 1,503.5 73.1 2,475 1,3860.560.9

1990 1,754.3 84.61,830 948 0.52 0.5

1991 1,837.0 86.7 1,985 806 0.41 0.4

1992 1,447.4 72.0 2,418 1,167 0.48 0.8

1993 1,542.0 76.0 1,701 854 0.50 0.6

1994 1,580.0 77.61,812 726 0.40 0.5

1995 1,696.6 82.1 1,623 512 0.32 0.3

19961,053.8 54.3 2,782 819 0.29 0.8

1997 0.0 0.0 1,661 316 0.19 ---

1998 380.9 19.3 2,099 422 0.20 1.11

1987 636.1 70.2 2,156 174 0.08 0.3

1988 794.9 96.5 950 52 0.05 0.1

1989 628.4 66.0 1,818 266 0.15 0.4

1990 1,527.7 78.2 1,422 175 0.12 0.1

1991 1,810.9 86.8 1,151 106 0.09 0.1

1992 1,741.4 84.8 1,559 330 0.21 0.2

1993 1,913.2 91.61,287 217 0.17 0.1

1994 1,944.4 94.9 1,543 275 0.18 0.1

1995 1,957.1 93.0 1,581 260 0.16 0.1

19962,026.2 93.3 1,654 234 0.14 0.1

1997 2,001.7 95.8 1,463 234 0.16 0.12

1998 1,907.2 89.5 1,854 357 0.19 0.19

1973 408.7 782 117 0.15 0.3

1974 432.6 68.7 619 420 0.68 1.0

1975 542.9 79.9 440 319 0.72 0.6

1976712.2 95.0 244 85 0.35 0.1

1977 617.6 82.2 508 245 0.48 0.4

1978 642.7 84.1 638 420 0.66 0.7

1979 537.0 68.4 393 154 0.39 0.3

1980 527.0 72.2 735 462 0.63 0.9

1981 624.2 78.2 868 424 0.49 0.7

1982 542.5 69.1 1,295 619 0.48 1.1

1983 677.1 83.6 592 165 0.28 0.2

1984 605.7 74.4 1,262 884 0.70 1.5

1985 635.4 79.2 1,009 700 0.69 1.1

1986737.6 87.8 495 100 0.20 0.1

1987 478.1 65.3 1,100 722 0.66 1.5

9 Maine Yankee was shut down in 8/97 and is no longer included in the count of commercial reactors.
C-15

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

MAINE YANKEE

(continued)

MCGUIRE 1, 2

Docket 50-369, -370;

NPF-9, -17

1st commercial operation

12/81, 3/84

Type - PWRS

Capacity - 1100, 1100 MWe

MILLSTONE POINT 1

Docket 50-245; DPR-21

1st commercial operation 3/71

Type - BWR

Capacity - 641 MWe

1988 591.9 79.1 1,058 725 0.69 1.2

1989 819.2 93.7 375 99 0.260.1

1990 573.0 71.0 1,359 682 0.50 1.2

1991 738.1 86.6 426 105 0.25 0.1

1992 631.7 79.1 1,189 461 0.39 0.7

1993 674.8 79.8 1,016 377 0.37 0.6

1994 782.8 90.9 297 84 0.28 0.1

1995 23.63.7 1,167 653 0.5627.7

1996602.9 78.1 408 56 0.14 0.1

1997 0.0 0.0 991 153 0.15 ---

1998 0.0 0.0 1,313 173 0.13 ---

1982 524.9 80.4 1,560 169 0.11 0.3

1983 558.3 55.4 1,751 521 0.30 0.9

1984 764.1 68.5 1,663 507 0.30 0.7

1985 808.4 77.0 2,217 771 0.35 1.0

19861,360.0 60.1 2,326 1,015 0.44 0.7

1987 1,774.7 79.2 2,865 1,043 0.36 0.6

1988 1,830.7 80.2 2,808 1,104 0.39 0.6

1989 1,810.2 80.8 1,994 620 0.31 0.3

1990 1,340.3 61.3 2,289 727 0.32 0.5

1991 1,945.1 85.0 1,723 361 0.21 0.2

1992 1,696.8 74.4 1,619 418 0.26 0.2

1993 1,470.4 66.2 1,685 463 0.27 0.3

1994 1,848.0 80.2 1,637 397 0.24 0.2

1995 2,132.3 92.9 1,259 138 0.11 0.1

19961,881.8 82.8 1,622 238 0.15 0.1

1997 1,558.2 73.0 2,193 492 0.22 0.32

1998 2,139.8 95.1 1,045 142 0.14 0.07

1972 377.6612 5960.97 1.6

1973 225.1 1,184 663 0.56 2.9

1974 430.3 79.1 2,477 1,430 0.58 3.3

1975 465.4 75.6 2,587 2,022 0.78 4.3

1976449.8 76.1 1,387 1,194 0.86 2.7

1977 575.7 89.61,075 394 0.37 0.7

1978 556.6 87.6 1,391 1,416 1.02 2.5

1979 505.0 77.3 2,001 1,795 0.90 3.6

1980 405.8 69.0 3,024 2,157 0.71 5.3

1981 304.3 51.62,5061,496 0.60 4.9

1982 490.2 79.9 1,370 929 0.68 1.9

1983 640.1 95.6 309 244 0.79 0.4

1984 516.1 78.8 1,992 836 0.42 1.6

1985 548.5 83.6732 608 0.83 1.1

1986 626.8 95.4 389 150 0.39 0.2

1987 523.4 79.61,588 684 0.43 1.3

1988 658.8 98.6 327 144 0.44 0.2

1989 554.684.2 852 462 0.54 0.8

1990 608.3 91.6 365 131 0.36 0.2

1991 213.1 35.4 1,154 409 0.35 1.9

1992 431.8 68.1 348 99 0.28 0.2

1993 627.9 96.8 305 81 0.27 0.1

1994 394.0 63.6 1,321 391 0.30 1.0

1995 520.680.0 910 620 0.68 1.2

19960.0 0.0 747 431 0.58 ---

1997 -2.9 0.0 1,053 195 0.19 -67.24

1998 -2.7 0.0 347 13 0.04 -4.81
C-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

MILLSTONE POINT 2, 3

Docket 50-336, 50-423;

DPR-65, NPF-49

1st commercial operation

12/75, 4/86

Type - PWR

Capacity - 871, 1137 MWe

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, 1105 MWe

1976 545.7 78.7 620 168 0.27 0.3

1977 518.7 65.7 667 242 0.36 0.5

1978 536.6 67.3 1,420 1,444 1.02 2.7

1979 520.0 62.8 525 471 0.90 0.9

1980 579.3 69.2 893 637 0.71 1.1

1981 722.4 82.6890 531 0.60 0.7

1982 595.9 70.62,083 1,413 0.68 2.4

1983 294.0 34.2 2,383 1,881 0.79 6.4

1984 782.7 93.5 285 120 0.42 0.2

1985 417.8 49.4 1,905 1,581 0.83 3.8

19861,313.8 80.4 2,393 993 0.41 0.8

1987 1,624.5 84.1 1,441 505 0.35 0.3

1988 1,594.8 83.2 1,827 804 0.44 0.5

1989 1,428.3 72.9 1,984 1,079 0.54 0.8

1990 1,614.9 87.1 1,652 593 0.36 0.4

1991 819.5 69.7 1,084 381 0.35 0.5

1992 1,115.1 59.9 3,190 1,280 0.40 1.1

1993 1,525.2 79.7 2,064 557 0.27 0.4

1994 1,556.6 73.1 1,249 188 0.15 0.1

1995 1,278.1 60.5 1,691 416 0.25 0.3

1996418.1 19.3 983 126 0.13 0.3

1997 0.0 0.0 1,435 253 0.18 ---

1998 374.9 20.9 1,179 113 0.10 0.30

1972 424.4 99 61 0.62 0.1

1973 389.5 401 1760.44 0.5

1974 349.3 74.9 842 349 0.41 1.0

1975 344.8 72.2 1,353 1,353 1.00 3.9

1976476.4 91.5 325 263 0.81 0.6

1977 425.679.9 860 1,000 1.16 2.3

1978 459.4 87.2 679 375 0.55 0.8

1979 522.0 97.6372 157 0.42 0.3

1980 411.8 78.2 1,114 531 0.48 1.3

1981 389.3 72.61,4461,004 0.69 2.6

1982 291.1 63.3 1,307 993 0.76 3.4

1983 494.696.3 416121 0.29 0.2

1984 33.7 9.2 1,872 2,462 1.32 73.1

1985 509.8 91.7 586327 0.56 0.6

1986402.7 79.1 895 596 0.67 1.5

1987 422.5 81.9 941 568 0.60 1.3

1988 542.5 99.8 375 110 0.29 0.2

1989 318.2 76.2 1,102 507 0.46 1.6

1990 536.0 96.9 336 94 0.28 0.2

1991 429.4 80.8 964 465 0.48 1.1

1992 528.3 97.5 454 114 0.25 0.2

1993 458.1 84.4 954 494 0.52 1.1

1994 471.3 87.0 788 395 0.50 0.8

1995 564.7 100.0 200 44 0.22 0.1

1996461.6 86.9 757 240 0.32 0.5

1997 417.4 75.9 399 1060.27 0.25

1998 470.2 88.1 674 209 0.31 0.44

1970 227.0 821 44 0.05 0.2

1971 346.5 1,006 195 0.19 0.6

1972 381.8 735 285 0.39 0.7

1973 411.0 550 567 1.03 1.4

1974 385.9 70.5 740 824 1.11 2.1

1975 359.0 72.1 649 681 1.05 1.9

1976484.6 88.2 392 428 1.09 0.9

1977 347.4 59.2 1,093 1,383 1.27 4.0

1978 527.7 95.1 561 314 0.56 0.6

1979 354.0 66.1 1,326 1,497 1.13 4.2
C-17

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

NINE MILE POINT 1, 2

(continued)

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

1980 533.9 92.3 1,174 591 0.50 1.1

1981 385.2 66.0 2,029 1,592 0.78 4.1

1982 133.5 21.4 1,352 1,264 0.93 9.5

1983 329.8 56.2 1,405 860 0.61 2.6

1984 426.8 71.9 1,530 890 0.58 2.1

1985 580.9 96.4 1,007 265 0.26 0.5

1986 371.0 65.3 1,878 1,275 0.68 3.4

1987 542.693.3 1,190 141 0.12 0.3

1988 0.0 0.0 2,626 854 0.33 ---

1989 527.5 29.7 2,737 564 0.21 1.1

1990 656.2 46.6 2,405 699 0.29 1.1

1991 1,250.8 79.7 1,543 292 0.19 0.2

1992 965.9 61.8 1,800 563 0.31 0.6

1993 1,380.2 84.62,352 633 0.27 0.5

1994 1,589.695.9 800 149 0.19 0.1

1995 1,382.2 82.5 2,304 759 0.33 0.5

19961,598.6 91.6 1,596 290 0.18 0.2

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

1979 507.0 61.7 2,025 449 0.22 0.9

1980 681.8 86.5 2,086 218 0.10 0.3

1981 1,241.9 71.5 2,416680 0.28 0.5

1982 777.7 45.8 2,872 1,915 0.67 2.5

1983 1,338.4 76.1 2,228 665 0.30 0.5

1984 1,021.3 58.8 3,062 1,945 0.64 1.9

1985 1,516.9 86.1 2,436 838 0.34 0.6

19861,484.5 83.0 2,831 722 0.26 0.5

1987 1,112.667.8 2,624 1,521 0.58 1.4

1988 1,772.7 96.7 992 112 0.11 0.1

1989 1,226.8 72.5 2,861 1,471 0.51 1.2

1990 1,590.4 90.5 2,161 590 0.27 0.4

1991 1,597.5 88.62,085 629 0.30 0.4

1992 1,403.2 84.1 2,159 5760.27 0.4

1993 1,428.4 80.1 2,768 908 0.33 0.6

1994 1,717.1 95.9 1,036193 0.19 0.1

1995 1,666.4 90.8 1,551 367 0.24 0.2

19961,569.6 89.1 1,203 291 0.24 0.2

1997 1,711.5 96.2 856 103 0.12 0.06

1998 1,632.8 92.7 1,201 266 0.22 0.16

1974 650.6 60.1 844 517 0.61 0.8

1975 1,838.3 75.5 829 497 0.60 0.3

19761,561.4 63.0 1,215 1,026 0.84 0.7

1977 1,566.4 65.9 1,595 1,329 0.83 0.8

1978 1,909.0 75.8 1,636 1,393 0.85 0.7

1979 1,708.0 67.7 2,100 1,001 0.48 0.6

1980 1,703.7 70.1 2,124 1,055 0.50 0.6

1981 1,661.5 66.8 2,445 1,211 0.50 0.7

1982 1,293.1 52.5 2,445 1,792 0.73 1.4

1983 2,141.5 82.2 1,902 1,207 0.63 0.6

1984 2,242.9 85.7 2,085 1,1060.53 0.5

1985 2,036.3 80.5 2,729 1,304 0.48 0.6

19861,995.6 79.0 2,499 949 0.38 0.5

1987 1,962.6 82.4 2,672 1,142 0.43 0.6

1988 2,228.9 87.2 2,672 871 0.33 0.4

1989 2,188.685.4 2,205 684 0.31 0.3

1990 2,405.2 91.4 1,948 404 0.21 0.2

1991 2,275.0 86.7 1,966 551 0.28 0.2

1992 2,110.7 82.0 1,954 612 0.31 0.3

1993 2,399.2 91.3 1,499 237 0.160.1

1994 2,144.3 82.2 1,923 537 0.28 0.2
C-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

OCONEE 1, 2, 3

(continued)

OYSTER CREEK

Docket 50-219; DPR-16

1st commercial operation 12/69

Type - BWR

Capacity - 619 MWe

PALISADES

Docket 50-255; DPR-20

1st commercial operation 12/71

Type - PWR

Capacity - 730 MWe

1995 2,366.1 89.5 1,586 304 0.19 0.1

19961,847.9 70.3 1,479 257 0.17 0.1

1997 1,563.7 67.7 1,379 223 0.16 0.14

1998 1,989.1 81.3 1,695 366 0.22 0.18

1970 413.695 63 0.660.1

1971 448.9 249 240 0.960.5

1972 515.0 339 582 1.72 1.1

1973 424.6782 1,2361.58 2.9

1974 434.5 70.4 935 984 1.05 2.3

1975 373.673.3 1,210 1,140 0.94 3.1

1976456.5 79.3 1,582 1,078 0.68 2.4

1977 385.7 70.1 1,673 1,614 0.96 4.2

1978 431.8 74.3 1,411 1,279 0.91 3.0

1979 541.0 85.9 842 467 0.55 0.9

1980 232.9 41.4 1,966 1,733 0.88 7.4

1981 314.8 59.8 1,689 917 0.54 2.9

1982 242.7 62.5 1,270 865 0.68 3.6

1983 27.9 11.5 2,303 2,257 0.98 80.9

1984 37.1 9.62,369 2,054 0.87 55.4

1985 446.1 89.4 2,342 748 0.32 1.7

1986157.3 31.5 3,740 2,436 0.65 15.5

1987 371.0 64.2 1,932 522 0.27 1.4

1988 419.665.9 2,875 1,504 0.52 3.6

1989 287.5 57.3 2,395 910 0.38 3.2

1990 511.8 89.1 1,941 310 0.160.6

1991 351.660.5 3,089 1,185 0.38 3.4

1992 536.3 85.9 2,771 657 0.24 1.2

1993 551.9 87.8 2,560 416 0.16 0.8

1994 431.7 70.8 2,382 844 0.35 2.0

1995 615.4 97.4 761 90 0.12 0.1

1996515.0 82.6 1,833 449 0.24 0.9

1997 579.1 94.3 509 50 0.10 0.63

1998 490.8 82.4 1,408 308 0.22 0.63

1972 216.8 78 0.4

1973 286.8 975 1,133 1.16 4.0

1974 10.7 5.5 774 627 0.81 58.6

1975 302.0 64.5 495 306 0.62 1.0

1976346.9 55.2 742 696 0.94 2.0

1977 616.6 91.4 332 100 0.30 0.2

1978 320.2 49.7 849 764 0.90 2.4

1979 415.0 59.9 1,599 854 0.53 2.1

1980 288.3 42.9 1,307 424 0.32 1.5

1981 418.2 57.2 2,151 902 0.42 2.2

1982 404.3 54.7 1,554 330 0.21 0.8

1983 454.4 60.3 2,167 977 0.45 2.2

1984 98.7 15.2 1,344 573 0.43 5.8

1985 639.2 83.8 1,355 507 0.37 0.8

1986102.3 15.1 1,438 672 0.47 6.6

1987 319.2 48.2 1,122 4560.41 1.4

1988 413.4 56.8 1,472 730 0.50 1.8

1989 442.8 69.1 1,026 314 0.31 0.7

1990 366.7 58.7 2,414 766 0.32 2.1

1991 587.0 78.1 1,315 211 0.160.4

1992 581.9 76.1 1,267 295 0.23 0.5

1993 424.4 53.7 908 289 0.32 0.7

1994 541.8 67.0 397 60 0.15 0.1

1995 583.5 75.8 1,230 462 0.38 0.8

1996638.2 81.4 1,109 318 0.29 0.5

1997 662.5 89.9 338 48 0.14 0.07

1998 615.4 83.5 895 217 0.24 0.35
C-19

Thirty-First Annual Report, 1998 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

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

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

1987 1,638.1 66.1 1,792 669 0.37 0.4

1988 1,700.9 65.5 2,173 688 0.32 0.4

1989 965.3 26.5 2,615 720 0.28 0.7

1990 2,500.9 67.5 2,236 499 0.22 0.2

1991 3,043.9 78.9 2,242 605 0.27 0.2

1992 3,102.3 82.0 1,981 541 0.27 0.2

1993 2,677.1 74.3 2,124 592 0.28 0.2

1994 2,827.679.1 2,048 462 0.23 0.2

1995 3,265.2 85.6 1,875 482 0.26 0.1

19963,482.7 90.0 1,717 302 0.18 0.1

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

1975 1,234.3 80.9 971 228 0.23 0.2

19761,379.2 73.0 2,136 840 0.39 0.6

1977 1,052.4 58.7 2,827 2,0360.72 1.9

1978 1,636.3 84.0 2,244 1,317 0.59 0.8

1979 1,740.0 84.5 2,2761,388 0.61 0.8

1980 1,374.2 66.3 2,774 2,302 0.83 1.7

1981 1,161.8 58.0 2,857 2,506 0.88 2.2

1982 1,583.3 76.9 2,734 1,977 0.72 1.2

1983 824.7 41.0 3,107 2,963 0.95 3.6

1984 1,165.8 57.5 3,313 2,450 0.74 2.1

1985 682.7 37.5 4,209 3,354 0.80 4.9

19861,395.0 71.7 2,454 1,080 0.44 0.8

1987 365.7 20.3 4,363 2,195 0.50 6.0

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

1989 491.0 35.0 2,301 728 0.32 1.5

1990 1,684.0 85.7 1,585 377 0.24 0.2

1991 1,210.9 62.3 2,702 934 0.35 0.8

1992 1,516.6 78.7 1,911 502 0.26 0.3

1993 1,654.0 81.9 1,757 552 0.31 0.3

1994 1,927.4 93.8 2,133 579 0.27 0.3

1995 1,955.9 95.1 1,940 398 0.21 0.2

19962,012.4 96.9 1,657 282 0.17 0.1

1997 1,956.3 95.0 1,872 490 0.26 0.25

1998 1,881.2 93.2 1,903 366 0.19 0.19

1988 869.3 79.0 782 105 0.13 0.1

1989 642.2 57.0 1,883 767 0.41 1.2

1990 792.7 67.1 1,537 638 0.42 0.8

1991 1,074.2 91.9 600 146 0.24 0.1

1992 856.2 75.5 1,487 571 0.38 0.7

1993 479.2 48.2 1,235 278 0.23 0.6

1994 550.8 50.2 2,098 691 0.33 1.3

1995 1,090.9 95.6587 64 0.11 0.1

1996895.6 77.2 1,622 307 0.19 0.3

1997 930.684.7 1,524 272 0.18 0.29

1998 1,163.1 99.3 385 42 0.11 0.04

1973 484.0 230 1260.55 0.3

1974 234.1 39.2 454 415 0.91 1.8

1975 308.1 71.3 473 798 1.69 2.6

1976287.8 60.7 1,317 2,648 2.01 9.2

1977 316.6 61.4 1,875 3,142 1.68 9.9

1978 519.5 83.1 1,667 1,327 0.80 2.6

1979 574.0 89.4 2,458 1,015 0.41 1.8

1980 360.3 56.2 3,549 3,626 1.02 10.1

1981 408.9 65.9 2,803 1,836 0.66 4.5

1982 389.9 63.9 2,854 1,539 0.54 3.9

1983 559.5 87.2 2,3261,162 0.50 2.1

1984 1.4 0.4 4,542 4,082 0.90 15.7
C-20

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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 - 485, 485 MWe

PRAIRIE ISLAND 1, 2

Docket 50-282, 50-306;

DPR-42, -60

1st commercial operation 12/73,

12/74

Type - PWRs

Capacity - 526, 512 MWe

1985 587.3 91.5 2,209 893 0.40 1.5

1986121.9 18.8 2,635 874 0.33 7.2

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

1988 0.0 0.0 2,073 392 0.19 ---

1989 204.664.1 1,797 207 0.12 1.0

1990 503.5 82.1 1,898 225 0.12 0.4

1991 406.3 65.8 2,836 605 0.21 1.5

1992 561.0 85.4 1,332 281 0.21 0.5

1993 513.7 80.9 1,328 435 0.33 0.8

1994 453.671.4 758 200 0.26 0.4

1995 531.7 80.7 1,294 482 0.37 0.9

1996631.3 95.4 517 116 0.22 0.2

1997 492.1 80.7 1,655 588 0.36 1.19

1998 650.5 100.0 530 71 0.13 0.11

1971 393.4 164 0.4

1972 378.3 580 1.5

1973 693.7 501 588 1.17 0.8

1974 760.2 81.3 400 295 0.74 0.4

1975 801.2 82.9 339 459 1.35 0.6

1976857.3 86.7 313 370 1.18 0.4

1977 873.9 87.3 417 430 1.03 0.5

1978 914.4 90.9 336320 0.95 0.3

1979 808.0 80.8 610 644 1.06 0.8

1980 727.2 82.5 561 598 1.07 0.8

1981 760.4 83.6 773 596 0.77 0.8

1982 757.2 84.3 767 609 0.79 0.8

1983 648.2 72.7 1,702 1,403 0.82 2.2

1984 788.9 78.61,372 789 0.58 1.0

1985 831.3 82.5 671 482 0.72 0.6

1986858.9 85.7 664 402 0.61 0.5

1987 857.5 85.5 720 554 0.77 0.6

1988 899.3 88.6734 410 0.560.5

1989 847.8 85.5 736504 0.68 0.6

1990 875.5 86.5 617 378 0.61 0.4

1991 874.8 87.1 724 265 0.37 0.3

1992 866.7 85.8 617 256 0.41 0.3

1993 911.0 90.0 559 1860.33 0.2

1994 914.5 91.2 548 170 0.31 0.2

1995 858.4 86.1 548 190 0.35 0.2

1996831.6 84.7 1,029 276 0.27 0.3

1997 186.8 21.8 670 92 0.14 0.49

1998 649.7 69.7 881 169 0.19 0.26

1974 181.9 43.9 150 18 0.12 0.1

1975 836.0 83.3 477 123 0.26 0.1

1976725.2 76.6 818 447 0.55 0.6

1977 922.9 87.2 718 300 0.42 0.3

1978 941.1 92.2 546221 0.40 0.2

1979 865.0 86.0 594 180 0.30 0.2

1980 800.7 79.9 983 353 0.360.4

1981 844.9 80.5 836329 0.39 0.4

1982 944.9 90.4 645 229 0.36 0.2

1983 921.1 86.8 654 233 0.36 0.3

1984 972.4 91.7 546147 0.27 0.2

1985 882.684.0 1,082 416 0.38 0.5

1986930.6 90.3 818 255 0.31 0.3

1987 969.6 91.6 593 135 0.23 0.1

1988 932.0 89.1 732 199 0.27 0.2

1989 1,001.8 94.7 47699 0.21 0.1

1990 925.4 89.2 737 188 0.260.2
C-21

Thirty-First Annual Report, 1998 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

PRAIRIE ISLAND 1, 2

(continued)

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 SECO10

Docket 50-312; DPR-54

1st commercial operation 4/75

Type - PWR

Capacity - 873 MWe

1991 1,023.3 95.658698 0.17 0.1

1992 811.676.2 845 211 0.25 0.3

1993 978.3 90.7 532 1060.20 0.1

1994 996.9 91.5 478 109 0.10

1995 1,023.2 93.9 499 107 0.21 0.1

1996992.1 91.4 558 112 0.20 0.1

1997 817.681.4 753 174 0.23 0.21

1998 860.3 83.4 582 117 0.20 0.14

1974 958.1 72.3 678 482 0.71 0.5

1975 833.668.4 1,083 1,618 1.49 1.9

1976951.2 73.1 1,225 1,651 1.35 1.7

1977 970.1 84.0 907 1,031 1.14 1.1

1978 1,124.5 88.61,207 1,618 1.34 1.4

1979 1,075.0 84.61,688 2,158 1.28 2.0

1980 866.9 64.4 3,089 4,838 1.57 5.6

1981 1,156.9 81.1 2,246 3,146 1.40 2.7

1982 1,018.7 76.0 2,314 3,757 1.62 3.7

1983 1,088.5 79.2 1,802 2,491 1.38 2.3

1984 994.665.7 1,678 1,579 0.94 1.6

1985 1,268.0 82.7 1,184 990 0.84 0.8

19861,093.2 71.0 1,451 950 0.65 0.9

1987 1,126.6 75.3 1,429 720 0.50 0.6

1988 1,173.7 84.1 1,486827 0.56 0.7

1989 1,196.3 85.9 1,721 900 0.52 0.8

1990 1,148.9 77.8 2,1861,028 0.47 0.9

1991 1,044.5 73.2 1,722 509 0.30 0.5

1992 960.8 68.0 2,413 1,157 0.48 1.2

1993 974.9 67.0 2,150 849 0.39 0.9

1994 681.5 48.7 2,163 1,128 0.52 1.7

1995 1,002.5 70.4 2,041 7360.360.7

1996876.6 60.1 2,248 1,025 0.46 1.2

1997 935.3 66.5 2,474 654 0.26 0.70

1998 794.8 55.1 2,177 761 0.35 0.96

1976268.1 30.4 297 58 0.20 0.2

1977 706.4 77.1 515 391 0.76 0.6

1978 607.7 80.5 508 323 0.64 0.5

1979 687.0 91.1 287 126 0.44 0.2

1980 530.9 60.4 890 412 0.46 0.8

1981 321.2 40.2 772 402 0.52 1.3

1982 409.5 53.3 766 337 0.44 0.8

1983 347.9 46.8 1,338 787 0.59 2.3

1984 460.0 58.3 802 222 0.28 0.5

1985 238.7 30.8 1,764 756 0.43 3.2

19860.0 0.0 1,513 402 0.27 ---

1987 0.0 0.0 1,533 300 0.20 ---

1988 355.8 63.1 693 78 0.11 0.2

1989 179.9 54.7 603 81 0.13 0.5

1990 0.0 0.0 111 13 0.12 ---

1991 0.0 0.0 101 9 0.09 ---

1992 0.0 0.0 70 7 0.10 ---

1993 0.0 0.0 35 4 0.11 ---

1994 0.0 0.0 18 1 0.06---

1995 0.0 0.0 161 0.06---

19960.0 0.0 16 1 0.04 ---

1997 0.0 0.0 160 0.00 ---

1998 0.0 0.0 408 41 0.10 ---

10 Rancho Seco has been permanently shutdown.
C-22

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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

Docket 50-458; NPF-47

1st commercial operation 6/86

Type - BWR

Capacity - 936 MWe

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

1987 605.2 68.4 1,268 378 0.30 0.6

1988 880.7 94.3 513 107 0.21 0.1

1989 584.5 69.1 1,566 558 0.36 1.0

1990 682.2 78.0 1,616 489 0.30 0.7

1991 814.7 87.2 780 144 0.18 0.2

1992 336.1 39.7 2,022 710 0.35 2.1

1993 640.0 71.6 847 180 0.21 0.3

1994 595.7 64.9 2,209 519 0.24 0.9

1995 967.1 99.6 667 85 0.13 0.1

1996836.1 85.3 2,093 473 0.23 0.6

1997 778.8 86.3 1,671 347 0.21 0.45

1998 894.2 96.2 466 58 0.12 0.06

1972 580.0 245 215 0.88 0.4

1973 455.1 831 695 0.84 1.5

1974 578.1 83.3 853 672 0.79 1.2

1975 501.8 72.7 849 1,142 1.35 2.3

1976585.5 84.7 597 715 1.20 1.2

1977 511.5 85.2 634 455 0.72 0.9

1978 480.5 72.0 943 963 1.02 2.0

1979 482.0 70.8 1,454 1,188 0.82 2.5

1980 387.3 62.2 2,009 1,852 0.92 4.8

1981 426.6 73.0 1,462 733 0.50 1.7

1982 277.5 48.9 2,011 1,4260.71 5.1

1983 409.8 75.5 2,244 923 0.41 2.3

1984 28.0 7.0 4,127 2,880 0.70 102.9

1985 629.5 87.9 1,378 311 0.23 0.5

1986577.1 80.3 1,571 539 0.34 0.9

1987 510.1 72.5 1,379 499 0.361.0

1988 385.0 65.9 1,351 564 0.42 1.5

1989 336.6 48.7 1,098 195 0.18 0.6

1990 400.3 64.8 1,626 437 0.27 1.1

1991 575.1 81.4 885 193 0.22 0.3

1992 487.2 66.8 1,267 352 0.28 0.7

1993 502.7 70.7 1,221 337 0.28 0.7

1994 560.3 79.5 420 63 0.15 0.1

1995 618.7 84.7 1,058 215 0.20 0.3

1996654.8 88.6 1,031 167 0.16 0.3

1997 707.5 99.0 304 13 0.04 0.02

1998 628.5 88.9 978 170 0.17 0.27

1978 546.4 55.6 574 122 0.21 0.2

1979 250.0 25.5 1,488 584 0.39 2.3

1980 680.6 69.2 1,704 449 0.26 0.7

1981 743.0 78.1 1,652 254 0.15 0.3

1982 1,440.4 72.63,228 1,203 0.37 0.8

1983 742.0 30.5 2,383 581 0.24 0.8

1984 650.1 31.8 1,395 681 0.49 1.0

1985 1,657.7 75.8 1,112 204 0.18 0.1

19861,484.3 70.4 3,554 599 0.17 0.4

1987 1,478.2 73.3 2,543 600 0.24 0.4

1988 1,591.673.6 1,609 503 0.31 0.3

1989 1,675.4 79.5 2,944 338 0.11 0.2

1990 1,362.6 65.1 3,636 272 0.07 0.2

1991 1,726.4 79.3 4,201 458 0.11 0.3

1992 1,200.9 61.1 4,376 431 0.10 0.4

1993 1,366.3 65.4 3,559 408 0.11 0.3

1994 1,367.4 73.8 950 188 0.20 0.1

1995 558.1 29.3 1,195 218 0.18 0.4

19960.0 0.0 1,671 300 0.18 ---

1997 279.3 17.8 894 175 0.20 0.63

1998 1,629.3 79.1 408 41 0.10 0.03
C-23

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

SAN ONOFRE 111, 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

SEABROOK

Docket 50-443; NPF-86

1st commercial operation 8/90

Type - PWR

Capacity - 1158 Mwe

SEQUOYAH 1, 2

Docket 50-327, -328;

DPR-77, -79

1st commercial operation 7/81,

6/82

Type - PWR

Capacity - 1122, 1117 MWe

1969 314.1 123 42 0.34 0.1

1970 365.9 251 155 0.62 0.4

1971 362.1 121 50 0.41 0.1

1972 338.5 326256 0.79 0.8

1973 273.7 570 353 0.62 1.3

1974 377.8 86.1 219 71 0.32 0.2

1975 389.0 87.4 424 292 0.69 0.8

1976297.9 70.2 1,330 880 0.66 3.0

1977 281.2 63.7 985 847 0.86 3.0

1978 323.2 80.2 764 401 0.52 1.2

1979 401.0 90.2 521 139 0.27 0.3

1980 97.3 22.3 3,063 2,386 0.78 24.5

1981 95.9 26.7 2,902 3,223 1.11 33.6

1982 61.6 15.7 3,055 832 0.27 13.5

1983 0.0 0.0 1,701 155 0.09 ---

1984 670.4 68.3 7,514 986 0.27 1.5

1985 1,381.8 132.9 5,742 722 0.24 15.5

19861,698.2 61.1 3,594 824 0.24 1.1

1987 1,983.0 78.8 2,138 696 0.33 0.4

1988 1,982.3 68.4 2,324 781 0.34 0.4

1989 1,840.8 64.9 2,237 567 0.25 0.3

1990 1,980.5 69.1 2,224 885 0.40 0.4

1991 1,987.675.3 1,814 412 0.23 0.2

1992 2,228.687.1 1,651 324 0.20 0.1

1993 1,771.3 79.9 2,193 767 0.35 0.4

1994 2,220.7 100.0 528 32 0.060.0

1995 1,686.9 79.1 1,914 455 0.24 0.3

19962,089.3 93.2 1,272 129 0.10 0.1

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

1991 810.4 75.9 699 92 0.13 0.1

1992 932.4 81.3 806147 0.18 0.2

1993 1,071.5 93.6110 60.05 0.0

1994 736.4 63.5 852 113 0.13 0.2

1995 995.5 87.5 800 102 0.13 0.1

19961,168.6 99.6 206 10 0.05 0.0

1997 907.0 79.8 1,571 1860.12 0.21

1998 957.684.5 559 19 0.03 0.02

1982 583.5 52.8 1,965 570 0.29 1.0

1983 1,663.7 75.1 1,772 491 0.28 0.3

1984 1,481.9 69.0 2,373 1,117 0.47 0.8

1985 1,151.3 51.3 1,854 1,071 0.58 0.9

19860.0 0.0 1,735 5260.30 ---

1987 0.0 0.0 2,080 420 0.20 ---

1988 490.8 31.8 2,439 678 0.28 1.4

1989 1,851.7 85.7 2,007 657 0.33 0.4

1990 1,662.6 77.2 2,934 1,678 0.57 1.0

1991 1,965.4 88.0 1,928 698 0.36 0.4

1992 1,849.0 85.4 1,714 465 0.27 0.3

1993 405.7 21.8 1,629 372 0.23 0.9

1994 1,418.7 66.3 1,657 292 0.18 0.2

1995 1,864.2 86.1 1,618 358 0.22 0.2

19962,009.4 87.9 1,404 265 0.19 0.1

1997 1,946.1 89.0 1,932 414 0.21 0.21

1998 2,135.3 95.3 1,440 255 0.18 0.12

11 San Onofre 1 was shut down 11/92 and is no longer in the count of commercial reactors.
C-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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

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

SURRY 1, 2

Docket 50-280, 50-281;

DPR-32, -37

1st commercial operation

12/72, 5/73

Type - PWRs

Capacity - 801, 801 MWe

1989 769.3 65.6 989 161 0.16 0.2

1990 1,504.1 65.9 1,136 206 0.18 0.1

1991 1,741.5 72.4 1,144 257 0.22 0.1

1992 2,096.0 83.8 923 147 0.16 0.1

1993 163.1 8.3 1,138 251 0.22 1.5

1994 1,700.2 70.6661 47 0.07 0.0

1995 2,294.2 89.9 1,485 291 0.20 0.1

19962,465.9 95.0 1,145 137 0.12 0.1

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

1977 649.1 84.7 445 152 0.34 0.2

1978 606.4 76.5 797 337 0.42 0.6

1979 592.0 74.0 907 438 0.48 0.7

1980 627.9 77.5 1,074 532 0.50 0.8

1981 599.1 72.7 1,473 929 0.63 1.6

1982 816.8 94.0 1,045 272 0.26 0.3

1983 290.3 15.4 2,211 1,204 0.54 4.1

1984 1,183.0 69.6 2,090 1,263 0.60 1.1

1985 1,445.8 82.5 1,971 1,344 0.68 0.9

19861,588.6 89.1 1,279 491 0.38 0.3

1987 1,407.9 81.9 2,012 951 0.47 0.7

1988 1,639.7 93.0 1,448 611 0.42 0.4

1989 1,493.1 85.1 1,414 495 0.35 0.3

1990 1,188.4 70.0 1,876777 0.41 0.7

1991 1,592.8 90.8 1,282 479 0.37 0.3

1992 1,511.9 87.3 1,251 264 0.21 0.2

1993 1,227.677.7 1,462 492 0.34 0.4

1994 1,424.8 85.0 1,896505 0.27 0.4

1995 1,306.6 76.0 1,498 413 0.28 0.3

19961,473.4 86.5 1,433 385 0.27 0.3

1997 1,394.683.6 2,314 646 0.28 0.46

1998 1,572.5 94.2 1,170 134 0.11 0.09

1984 504.661.1 1,120 295 0.26 0.6

1985 627.7 71.6 1,201 379 0.32 0.6

1986853.7 95.3 392 23 0.06 0.0

1987 618.7 71.0 1,075 560 0.52 0.9

1988 605.3 69.1 1,127 511 0.45 0.8

1989 652.4 83.1 374 52 0.14 0.1

1990 730.0 83.9 1,090 3760.34 0.5

1991 642.5 82.9 984 291 0.30 0.5

1992 892.697.4 249 27 0.11 0.0

1993 728.3 84.0 1,121 297 0.260.4

1994 536.7 69.5 1,549 374 0.24 0.7

1995 899.8 97.2 257 13 0.05 0.0

1996850.4 90.3 701 97 0.14 0.1

1997 829.7 89.8 820 163 0.20 0.20

1998 934.8 98.8 285 14 0.05 0.01

1973 420.6936152 0.160.4

1974 717.4 49.8 1,715 884 0.52 1.2

1975 1,079.0 70.8 1,948 1,649 0.85 1.5

1976930.7 60.4 2,753 3,165 1.15 3.4

1977 1,139.0 72.2 1,860 2,307 1.24 2.0

1978 1,210.677.2 2,203 1,837 0.83 1.5

1979 343.0 42.3 5,065 3,584 0.71 10.4

1980 568.2 40.3 5,317 3,836 0.72 6.8

1981 907.659.3 3,753 4,244 1.13 4.7

1982 1,323.3 88.5 1,878 1,490 0.79 1.1

1983 916.2 61.3 2,754 3,220 1.17 3.5
C-25

Thirty-First Annual Report, 1998 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

SURRY 1, 2

(continued)

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

THREE MILE ISLAND 1, 2

Docket 50-289, -320;

DPR-50, -73

1st commercial operation 9/74,

12/78

Type - PWRs

Capacity - 786, 880 MWe

THREE MILE ISLAND 112

Docket 50-289; DPR-50

1st commercial operation 9/74

Type - PWR

Capacity - 786 MWe

1984 1,026.7 71.0 3,198 2,247 0.70 2.2

1985 1,166.4 78.2 3,206 1,815 0.57 1.6

1986 1,080.5 69.0 3,763 2,356 0.63 2.2

1987 1,132.7 72.7 2,675 712 0.27 0.6

1988 750.4 50.0 3,184 1,542 0.48 2.1

1989 489.3 33.0 3,100 8360.27 1.7

1990 1,276.4 83.9 1,947 575 0.30 0.5

1991 1,271.9 84.5 1,547 510 0.33 0.4

1992 1,396.3 88.9 1,660 539 0.32 0.4

1993 1,283.1 84.61,402 383 0.27 0.3

1994 1,320.9 85.2 1,530 378 0.25 0.3

1995 1,333.0 84.2 1,883 4060.22 0.3

19961,562.9 93.1 983 209 0.21 0.1

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

1984 719.9 72.62,827 308 0.11 0.4

1985 1,452.2 76.4 3,669 1,106 0.30 0.8

19861,344.8 67.0 2,996 828 0.28 0.6

1987 1,749.5 85.3 2,548 621 0.24 0.4

1988 1,691.0 83.5 1,904 516 0.27 0.3

1989 1,572.5 77.1 2,063 704 0.34 0.4

1990 1,746.9 85.4 1,691 440 0.26 0.3

1991 1,878.0 89.8 1,844 507 0.27 0.3

1992 1,604.2 79.7 1,885 724 0.38 0.5

1993 1,602.1 77.3 1,488 335 0.23 0.2

1994 1,814.4 85.4 1,580 442 0.28 0.2

1995 1,850.8 85.3 1,773 4760.27 0.3

19961,998.7 90.7 1,430 289 0.20 0.1

1997 1,918.9 89.61,646433 0.260.23

1998 1,879.688.3 1,575 361 0.23 0.19

1975 675.9 82.2 131 73 0.56 0.1

1976530.0 65.4 819 286 0.35 0.5

1977 664.5 80.9 1,122 360 0.32 0.5

1978 690.0 85.1 1,929 504 0.26 0.7

1979 266.0 21.9 3,975 1,392 0.35 5.2

1980 0.0 0.0 2,328 394 0.17 ---

1981 0.0 0.0 2,103 3760.18 ---

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

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

1984 0.0 0.0 1,079 688 0.64 ---

1985 103.610.6 1,890 857 0.45 8.3

1986585.2 70.9 1,360 213 0.16 0.4

1987 610.7 73.6 1,259 149 0.12 0.2

1988 661.0 77.8 1,012 210 0.21 0.3

1989 871.3 100.0 670 54 0.08 0.1

1990 645.5 84.6 1,319 264 0.20 0.4

1991 688.7 86.4 1,542 198 0.13 0.3

1992 836.8 100.0 558 34 0.06 0.0

1993 722.0 88.5 1,835 2060.11 0.3

1994 798.7 95.5 434 40 0.09 0.1

1995 772.9 90.8 1,220 213 0.17 0.3

1996857.4 100.0 267 16 0.06 0.0

1997 675.7 84.3 1,049 204 0.19 0.30

1998 805.8 100.0 280 17 0.060.02

12 Three Mile Island 1 resumed commercial power generation 10/85 after being under regulatory restraint since 1979.
C-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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 213

Docket 50-320; DPR-73

1st commercial operation 12/78

Type - PWR

Capacity - 880 MWe

TROJAN14

Docket 50-344; NPF-1

1st commercial operation 5/76

Type - PWR

Capacity - 1095 MWe

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

19860.0 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 1360.28 ---

1991 0.0 0.0 153 37 0.24 ---

1992 0.0 0.0 315 157 0.50 ---

1993 0.0 0.0 167 33 0.20 ---

1994 0.0 0.0 259 7 0.03 ---

1995 0.0 0.0 191 2 0.01 ---

19960.0 0.0 122 2 0.02 ---

1997 0.0 0.0 232 1 0.00 ---

1998 0.0 0.0 184 10 0.05 ---

1977 792.0 92.6591 174 0.29 0.2

1978 205.5 20.6711 319 0.45 1.6

1979 631.0 58.1 736 258 0.35 0.4

1980 727.5 72.5 1,159 421 0.360.6

1981 775.674.1 1,311 609 0.46 0.8

1982 579.5 60.8 977 419 0.43 0.7

1983 494.2 62.4 969 307 0.32 0.6

1984 567.0 54.4 1,042 433 0.42 0.8

1985 829.1 76.7 852 363 0.43 0.4

1986852.4 79.7 1,321 381 0.29 0.4

1987 525.5 54.0 1,209 363 0.30 0.7

1988 758.667.5 1,408 401 0.28 0.5

1989 666.8 61.9 1,360 421 0.31 0.6

1990 732.4 66.3 1,169 258 0.22 0.4

1991 181.616.1 1,496567 0.38 3.1

1992 553.9 68.4 567 84 0.15 0.2

1993 0.0 68.4 54 21 0.39 ---

1994 0.0 0.0 51 9 0.18 ---

1995 0.0 0.0 141 44 0.31 ---

19960.0 0.0 112 41 0.37 ---

1997 0.0 0.0 227 41 0.18 ---

1998 0.0 0.0 24612 0.05 ---

1973 401.9 444 78 0.18 0.2

1974 953.6794 454 0.57 0.5

1975 1,003.7 74.9 1,176876 0.74 0.9

1976974.2 71.2 1,647 1,184 0.72 1.2

1977 979.5 72.1 1,319 1,0360.79 1.1

1978 1,000.2 78.8 1,3361,032 0.77 1.0

1979 811.0 62.4 2,002 1,680 0.84 2.1

1980 990.673.6 1,803 1,651 0.92 1.7

1981 654.0 46.8 2,932 2,251 0.77 3.4

1982 915.7 65.2 2,956 2,119 0.72 2.3

1983 878.4 62.8 2,930 2,681 0.92 3.1

1984 946.7 68.5 2,010 1,255 0.62 1.3

1985 1,034.9 74.7 1,905 1,253 0.66 1.2

1986754.1 54.9 1,808 946 0.52 1.3

1987 431.3 36.6 1,980 1,371 0.69 3.2

1988 809.8 59.5 1,841 738 0.40 0.9

1989 689.9 56.8 1,625 433 0.27 0.6

1990 933.1 69.0 2,099 730 0.35 0.8

13 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 docontaminate the unit during this time period.

14 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

commercial reactors.
C-27

Thirty-First Annual Report, 1998 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

1991 258.2 21.0 2,087 939 0.45 3.6

1992 968.9 75.5 1,374 325 0.24 0.3

1993 1,244.8 91.0 1,271 275 0.22 0.2

1994 1,172.9 87.2 1,489 4760.32 0.4

1995 1,320.3 94.61,142 215 0.19 0.2

19961,307.8 94.0 1,157 187 0.16 0.1

1997 1,220.9 88.61,581 414 0.260.34

1998 1,323.0 94.5 1,045 1560.15 0.12

1973 222.1 244 85 0.35 0.4

1974 303.5 357 2160.61 0.7

1975 429.0 87.8 282 153 0.54 0.4

1976389.6 77.1 815 411 0.50 1.1

1977 423.5 85.1 641 258 0.40 0.6

1978 387.5 75.9 934 339 0.360.9

1979 414.0 82.1 1,220 1,170 0.962.8

1980 357.8 71.5 1,443 1,338 0.93 3.7

1981 429.1 84.61,264 731 0.58 1.7

1982 501.0 96.0 481 205 0.43 0.4

1983 346.1 69.3 1,316 1,527 1.16 4.4

1984 398.1 79.0 954 626 0.66 1.6

1985 361.4 71.8 1,392 1,051 0.76 2.9

1986248.1 48.9 1,389 1,188 0.86 4.8

1987 423.684.2 827 303 0.37 0.7

1988 492.1 95.7 379 124 0.33 0.3

1989 432.8 84.7 832 288 0.35 0.7

1990 433.1 85.9 849 307 0.360.7

1991 492.3 94.3 310 118 0.38 0.2

1992 446.8 88.1 921 381 0.41 0.9

1993 402.3 80.1 833 217 0.260.5

1994 515.8 98.7 220 38 0.17 0.1

1995 462.1 87.0 737 182 0.25 0.4

1996452.7 85.2 951 231 0.24 0.5

1997 487.1 96.0 260 57 0.22 0.1

1998 383.4 77.9 944 199 0.21 0.52

1988 820.4 77.7 1,108 138 0.12 0.2

1989 1,045.8 96.0 427 32 0.07 0.0

1990 1,710.9 82.7 1,602 466 0.29 0.3

1991 1,966.5 89.2 1,357 362 0.27 0.2

1992 2,047.9 90.0 1,262 426 0.34 0.2

1993 2,060.4 88.3 1,338 367 0.27 0.2

1994 2,170.1 91.3 1,048 217 0.21 0.1

1995 2,285.4 95.2 953 199 0.21 0.1

19962,056.8 86.5 1,395 452 0.32 0.2

1997 2,121.1 91.4 994 158 0.160.07

1998 2,123.9 92.3 994 162 0.16 0.08

1985 616.0 87.6 755 119 0.16 0.2

1986 616.0 74.4 1,013 222 0.22 0.4

1987 639.0 70.8 1,201 406 0.34 0.6

1988 707.7 71.8 1,050 353 0.34 0.5

1989 727.2 78.3 1,299 492 0.38 0.7

1990 684.7 67.5 1,348 536 0.40 0.8

1991 508.5 50.3 1,088 387 0.360.8

1992 682.3 65.6 1,489 612 0.41 0.9

1993 849.679.5 1,385 469 0.34 0.6

1994 803.8 75.2 1,870 866 0.46 1.1

1995 824.7 83.8 1,694 456 0.27 0.6

1996 662.9 82.2 1,453 373 0.26 0.6

1997 697.0 72.7 1,218 251 0.21 0.36

1998 789.5 75.3 1,220 2860.23 0.36

TURKEY POINT 3, 4

(continued)

VERMONT YANKEE

Docket 50-271; DPR-28

1st commercial operation 11/72

Type - BWR

Capacity - 510 MWe

VOGTLE 1, 2

Docket 50-424; 50-425;

NPF-68, -81

1st commercial operation

6/87, 5/89

Type - PWRs

Capacity - 1162, 1167 MWe

WASHINGTON NUCLEAR 2

Docket 50-397; NPF-21

1st commercial operation 12/84

Type - BWR

Capacity - 1107 MWe
C-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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

1986875.7 79.1 1,244 223 0.18 0.3

1987 891.8 82.5 959 1560.160.2

1988 784.3 75.4 1,246259 0.21 0.3

1989 909.8 82.61,306265 0.20 0.3

1990 1,027.9 92.8 432 47 0.11 0.0

1991 870.679.8 1,301 364 0.28 0.4

1992 909.683.2 1,213 226 0.19 0.2

1993 1,088.3 99.4 195 15 0.08 0.0

1994 949.1 87.0 1,167 191 0.16 0.2

1995 927.4 83.4 1,092 153 0.14 0.2

19961,064.8 94.2 342 27 0.08 0.0

1997 767.2 71.2 1,186 148 0.13 0.19

1998 984.1 91.9 282 24 0.09 0.02

1997 867.6 83.8 1,071 112 0.11 0.13

1998 1,105.1 99.1 80 3 0.04 0.00

1986832.8 73.3 682 143 0.21 0.2

1987 778.8 71.1 675 138 0.20 0.2

1988 794.7 70.7 1,010 297 0.29 0.4

1989 1,108.4 99.5 18618 0.10 0.0

1990 940.2 81.0 798 195 0.24 0.2

1991 707.671.9 1,010 331 0.33 0.5

1992 1,010.8 86.7 446 78 0.17 0.1

1993 940.5 80.6975 183 0.19 0.2

1994 1,017.2 86.8 1,082 235 0.22 0.2

1995 1,198.0 98.7 242 14 0.060.0

1996980.6 81.2 986 171 0.17 0.2

1997 964.3 83.8 989 265 0.27 0.27

1998 1,187.3 100.0 184 10 0.05 0.01

1969 138.3 193 215 1.11 1.6

1970 146.1 355 255 0.72 1.7

1971 173.5 155 90 0.58 0.5

1972 78.7 282 255 0.90 3.2

1973 127.1 133 99 0.74 0.8

1974 111.3 243 205 0.84 1.8

1975 145.1 82.4 249 1160.47 0.8

1976152.2 89.8 152 59 0.39 0.4

1977 124.673.9 725 356 0.49 2.9

1978 145.0 81.0 565 282 0.50 1.9

1979 149.0 81.6441 127 0.29 0.9

1980 35.622.0 502 213 0.42 6.0

1981 109.0 74.4 515 302 0.59 2.8

1982 108.673.4 814 474 0.58 4.4

1983 163.5 91.4 395 68 0.17 0.4

1984 124.8 71.4 654 348 0.53 2.8

1985 144.3 85.3 653 211 0.32 1.5

1986169.7 95.0 384 45 0.12 0.3

1987 138.7 82.7 593 217 0.37 1.6

1988 136.4 85.2 738 227 0.31 1.7

1989 159.4 92.9 49662 0.12 0.4

1990 101.1 61.5 702 246 0.35 2.4

1991 121.2 72.3 162 40 0.25 0.3

1992 0.0 0.0 324 94 0.29 ---

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

WOLF CREEK 1

Docket 50-482; NPF-42

1st commercial operation 9/85

Type - PWR

Capacity - 1163 MWe

YANKEE ROWE15

Docket 50-29; DPR-3

1st commercial operation 7/61

Type - PWR

Capacity - 167 MWe

15 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 commercial reactors.
C-29

Thirty-First Annual Report, 1998 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

1993 0.0 0.0 313 163 0.52 ---

1994 0.0 0.0 222 1560.70 ---

1995 0.0 0.0 191 78 0.41 ---

19960.0 0.0 239 95 0.40 ---

1997 0.0 0.0 323 65 0.20 ---

1998 0.0 0.0 283 460.16---

1974 425.3 71.1 306560.18 0.1

1975 1,181.5 74.9 436127 0.29 0.1

19761,134.9 61.9 774 571 0.74 0.5

1977 1,358.675.0 784 1,003 1.28 0.7

1978 1,613.5 80.2 1,104 1,017 0.92 0.6

1979 1,238.0 67.6 1,472 1,274 0.87 1.0

1980 1,411.2 74.1 1,363 920 0.67 0.7

1981 1,366.9 72.3 1,754 1,720 0.98 1.3

1982 1,186.4 64.3 1,575 2,103 1.34 1.8

1983 1,222.3 69.4 1,285 1,311 1.02 1.1

1984 1,389.9 69.6 1,110 786 0.71 0.6

1985 1,187.9 62.9 1,498 1,166 0.78 1.0

19861,462.0 73.2 967 474 0.49 0.3

1987 1,337.0 71.0 1,046653 0.62 0.5

1988 1,549.1 78.3 1,9261,260 0.65 0.8

1989 1,514.1 77.61,282 624 0.49 0.4

1990 860.4 46.9 1,385 696 0.50 0.8

1991 1,125.7 58.2 902 173 0.19 0.2

1992 1,128.8 59.0 1,732 1,043 0.60 0.9

1993 1,458.2 70.9 1,772 643 0.36 0.4

1994 1,224.9 59.9 1,176306 0.26 0.2

1995 1,471.672.4 1,807 797 0.44 0.5

19961,538.4 75.8 1,567 437 0.28 0.3

1997 123.2 7.1 924 119 0.13 0.97

1998 0.0 0.0 24612 0.05 ---

YANKEE ROWE

(continued)

ZION 1, 216

Docket 50-295; 50-304;

DPR-39, -48

1st commercial operation

12/73, 9/74

Type - PWRS

Capacity - 1040, 1040 MWe

16 Zion 1, 2 was shut down 12/97 and is no longer included in the count of commercial reactors.
C-30

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

NUREG-0713

Reporting Organization Year

Megawatt

Years

MW-YR

Unit

Availability

Factor

Collective

Dose

Average

Measurable

Dose

(rems)

Collective

Dose

MW-yr

Total

Personnel

with

Measurable

Doses

This page intentionally left blank.
D-1

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

NUREG-0713

DOSE PERFORMANCE INDICATORS BY REACTOR SITE

1973 - 1998

Appendix D

NOTE: Appendix D contains data on operating plants as well as plants which are no longer in commercial operation.
D-2

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-3

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-4

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-5

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-6

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-7

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-8

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-9

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-10

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-11

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-12

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-13

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-14

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-15

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-16

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-17

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-18

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-19

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-20

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-21

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-22

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-23

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-24

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-25

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-26

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-27

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-28

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-29

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-30

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-31

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-32

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-33

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-34

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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D-35

Thirty-First Annual Report, 1998 Occupational Radiation Exposure at NRC Licensed Facilities

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D-36

Occupational Radiation Exposure at NRC Licensed Facilities Thirty-First Annual Report, 1998

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