Occupational Radiation Exposure at Commercial Nuclear Power Reactors

NUREG-0713
Vol. 26
Occupational Radiation
Exposure at Commercial
Nuclear Power Reactors
and Other Facilities
2004
Thirty-Seventh Annual Report
U.S. Nuclear Regulatory Commission
Office of Nuclear Regulatory Research
Washington, DC 20555-0001
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_______________________________________________________________
A.
NUREG-0713
Vol. 26
Occupational Radiation
Exposure at Commercial
Nuclear Power Reactors
and Other Facilities
2004
Thirty-Seventh Annual Report
Manuscript Completed: November 2005
Date Published: December 2005
Prepared by
Sheryl Burrows
D. A. Hagemeyer*
Division of Systems Analysis and Regulatory Effectiveness
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
*Oak Ridge Associated Universities
210 Badger Road
Oak Ridge, TN 37830
PREVIOUS REPORTS IN SERIES
WASH-1311
NUREG-751032
NUREG-0109
NUREG-0323
NUREG-0482
NUREG-0594
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
NUREG-0713
A Compilation of Occupational Radiation Exposure from Light Water Cooled Nuclear Power Plants, 1969-1973.
U.S. Atomic Energy Commission, May 1974.
Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969-1974, U.S. Nuclear Regulatory
Commission. June 1975.
Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969-1975, U.S. Nuclear Regulatory
Commission, August 1976.
Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969-1976. U.S. Nuclear Regulatory
Commission, March 1978.
Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1977, U.S. Nuclear Regulatory
Commission, May 1979.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1978, U.S. Nuclear Regulatory
Commission, November 1979.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors 1979, Vol. 1. U.S. Nuclear Regulatory
Commission, March 1981.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors 1980, Vol. 2, U.S. Nudear Regulatory
Commission, December 1981.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors 1981, Vol. 3, U.S. Nuclear Regulatory
Commission, November 1982.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors 1982, Vol. 4, U.S. Nuclear Regulatory
Commission, December 1983.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors 1983, Vol. 5, U.S. Nuclear Regulatory
Commission, March 1985.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1984, Vol. 6, U.S.
Nuclear Regulatory Commission, October 1988.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1985, Vol. 7, U.S.
Nuclear Regulatory Commission, April 1988.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1986. VoL 8, U.S.
Nuclear Regulatory Commission, August 1989.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1987, Vol. 9, U.S.
Nuclear Regulatory Commission, November 1990.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1988, Vol. 10, U.S.
Nuclear Regulatory Commission, July 1991.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1989, Vol. 11, U.S.
Nuclear Regulatory Commission, April 1992.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1990, Vol. 12, U.S.
Nuclear Regulatory Commission, January 1993.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1991, Vol. 13, U.S.
Nuclear Regulatory Commission, July 1993.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1992, Vol. 14, U.S.
Nuclear Regulatory Commission, December 1993.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1993, Vol. 15, U.S.
Nuclear Regulatory Commission, January 1995.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1994, Vol. 16, U.S.
Nuclear Regulatory Commission, January 1996.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1995, Vol. 17, U.S.
Nuclear Regulatory Commission, January 1997.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1996, Vol. 18, U.S.
Nuclear Regulatory Commission, February 1998.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1997, Vol. 19. U.S.
Nuclear Regulatory Commission, November 1998.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1998, Vol. 20, U.S.
Nuclear Regulatory Commission, November 1999.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1999, Vol. 21, U.S.
Nuclear Regulatory Commission, October 2000.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2000, Vol. 22, U.S.
Nuclear Regulatory Commission, September 2001.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2001, Vol. 23, U.S.
Nuclear Regulatory Commission, September 2002.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2002, Vol. 24, U.S.
Nuclear Regulatory Commission, October 2003.
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2003, Vol. 25, U.S.
Nuclear Regulatory Commission, October 2004.
Previous reports in the NUREG-0714 series which are now combined with NUREG-0713 are as follows:
WASH-1350-Rl First through Sixth Annual Reports of the Operation of the U.S. AEC's Centralized Ionizing Radiation Exposure
Records and Reporting System, U.S. Atomic Energy Commission.
through
WASH-11350-R6
NUREG-75/108 Seventh Annual Occupational Radiation Exposure Report for Certain NRC Licensees - 1974, U.S. Nuclear
Regulatory Commission, October 1975.
Eighth Annual Occupational Radiation Exposure Report for 1975, U.S. Nuclear Regulatory Commission, October 1976.
NUREG-0119
Ninth Annual Occupational Radiation Exposure Report for 1978, U.S. Nuclear Regulatory Commission, October 1977.
NUREG-0322
Tenth Annual Occupational Radiation Exposure Report for 1977, U.S. Nuclear Regulatory Commission, October 1978.
NUREG-0463
Eleventh Annual Occupational Radiation Exposure Report for 1978, U.S. Nuclear Regulatory Commission,
NUREG-0593
January 1981.
Twelfth Annual Occupational Radiation Exposure Report for 1979, Vol. 1, U.S. Nuclear Regulatory Commission,
NUREG-0714
August 1982.
Occupational Radiation Exposure, Thirteenth and Fourteenth Annual Reports, 1980 and 1981, Vols. 2 and 3, U.S.
NUREG-0714
Nuclear Regulatory Commission, October 1983.
Occupational Radiation Exposure, Fifteenth and Sixteenth Annual Reports, 1982 and 1983, Vols. 4 and 5, U.S.
NUREG-0714
Nuclear Regulatory Commission, October 1985.
NUREG-0713
ii
ABSTRACT
This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear
Regulatory Commission's (NRC's) Radiation Exposure Information and Reporting System
(REIRS). The bulk of the information contained in the report was compiled from the 2004 annual reports submitted by five of the seven categories' of NRC licensees subject to the reporting
requirements of 10 CFR 20.2206. The annual reports submitted by these licensees consist of
radiation exposure records for each monitored individual. These records are analyzed for trends
and presented in this report in terms of collective dose and the distribution of dose among the
monitored individuals. Because there are no geologic repositories for high-evel waste currently
licensed, and no low-evel waste disposal facilities in operation, only five categories will be considered in this report.
Annual reports for 2004 were received from a total of 227 NRC licensees, of which 104 were operators of nuclear power reactors in commercial operation. Compilations of the reports submitted
by the 227 licensees indicated that 123,332 individuals were monitored, 61,060 of whom received
a measurable dose (Table 3.1). The collective dose incurred by these individuals was 12,774
person-rem, which represents a 12% decrease from the 2003 value. The number of workers
receiving a measurable dose decreased, resulting in an average measurable dose of 0.21 rem for
2004. The average measurable dose is defined as the total collective dose (TEDE) divided by the
number of workers receiving a measurable dose.2 The figures for commercial reactors have been
adjusted to account for transient reactor workers.
In calendar year 2004, the annual collective dose per reactor for light water reactor (LWR) licensees was 100 person-rem. This represents a 13% decrease from the value reported for 2003
(115). The annual collective dose per reactor for boiling water reactors (BWRs) was 156 personrem, and, for pressurized water reactors (PWRs), it was 71 person-rem.
Analyses of transient worker data indicate that 24,251 individuals completed work assignments at
two or more licensees during the monitoring year. The dose distributions are adjusted each year
to account for the duplicate reporting of transient workers by multiple licensees. In 2004, the average measurable dose per worker for all licensees calculated from reported data was 0.16 rem.
The corrected dose distribution resulted in an average measurable dose per worker for all licensees of 0.21 rem.
Commercial nuclear power reactors; Industrial radiographers; fuel processors (including uranium enrichtment), fabricators, and
reprocessors; manufacturers and distributors of byproduct material; independent spent fuel storage installations; facilities for land
disposal of low-evel waste; and geologic repositories for high-level waste. There are currently no NRC licensees involved in
low-level waste disposal or geologic repositories for high-level waste.
2
The number of workers with measurable dose includes any individual with a dose greater than zero rem and does not include
doses reported as 'not detectable.
iii
Hii
NUREG-071 3
NURvEG-0713
EDITOR'S NOTE
Mr. Charles Hinson assisted in the preparation of this NUREG, serving as
the Office of Nuclear Reactor Regulation technical reviewer. The NRC
welcomes responses from readers.
Comments should be directed to:
Sheryl Burrows: (301) 415-6086
E-Mail Address: [email protected]
REIRS Project Manager
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555
NUREG-071 3
NUREG-0713
iv
iv
TABLE OF CONTENTS
Ii
PREVIOUS REPORTS IN SERIES ............................................................
ABSTRACT ............................................................
iii
EDITOR'S NOTE .i............................................................
iv
TABLE OF CONTENTS .............................................................
v
PREFACE ..............................................................
xi
FOREWORD .x............................................................
xiii
I INTRODUCTION ............................................................
1-1
1.1
1.2
Background ............................................................ 1-1
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 Definition of Terms and Sources of Data ....................................... ......................
3.1.1 Statistical Summary Reports ............................................................
...........................
3.1.2 Number of Monitored Workers .................................
3.1.3 Number of Workers with Measurable Dose .......................................................
3.1.4 Collective Dose ............................................................
3.1.5 Average Individual Dose ............................................................
3.1.6 Average Measurable Dose ............................................................
3.1.7 Number of Licensees Reporting............................................................
3.1.8 Collective TEDE Distribution by Dose Range ....................................................
3-1
3.2 Annual TEDE Dose Distributions ............................................................
3-1
3-1
3-1
3-1
3-1
3-2
3-2
3-2
3-2
3-4
........................3-7
3.3 Summary of Occupational Exposure Data by License Category .
.......... 3-7
3.3.1 Industrial Radiography Ucenses, Single and Multiple Locations ............
3.3.2 Manufacturing and Distribution Licenses, Type "A"Broad and Limited ............3-8
3-14
3.3.3 Low-Level Waste Disposal Licenses............................................................
3-14
.................
3.3.4 Independent Spent Fuel Storage Installation Licenses ..................
3-18
3.3.5 Fuel Cycle Ucenses............................................................
3.3.6 Light-Water-Cooled Power Reactor Licenses .................................................. 3-20
3.4 Summary of Intake Data by License Category ............................................................ 3-22
V~
v
~~
_UE-7
NURtEG-071 3
Occupational Radiation Exposure at NRC Licensed Facilities
7hirty-Seventh An nmd Rep ort, 2004
-
TABLE OF CONTENTS (Continued)
Page
4 COMMERCIAL LIGHT WATER REACTORS - FURTHER ANALYSIS .................................... 4-1
4-1
4.1 Introduction ............................................................
4.2 Definition of Terms and Sources of Data ................................ ............................ 4-1
4-1
4.2.1 Number of Reactors ............................................................
4-1
4.2.2 Electric Energy Generated ............................................................
4-5
4.2.3 Collective Dose per Megawatt-Year ............................................................
4.2.4 Average Maximum Dependable Capacity ............................................................ 4-5
4.2.5 Percent of Maximum Dependable Capacity Achieved ............................ ................. 4-5
4-6
4.3 Annual TEDE Distributions ............................................................
4.4 Average Annual TEDE Doses ............................................................ 4-8
4.5 Three-YearAverage Collective TEDE per Reactor .......................................................... 4-12
4.6 Graphical Representation of Dose Trends inAppendix D................................................ 4-17
5 TRANSIENT WORKERS AND CAREER DOSES AT NRC-LICENSED FACILITIES ............. 5-1
5-1
5.1 Termination Reports ............................................................
5-1
.................................................
5.2 Transient Workers at NRC Facilities
6 EXPOSURES TO PERSONNEL IN EXCESS OF REGULATORY LIMITS .............................. 6-1
6.1
6.2
6.3
6.4
Control Levels............................................................
Limitations of the Data ............................................................
Summary of Exposures in Excess of Regulatory Limits ....................................................
Maximum Exposures Below the NRC Limits ............................................................
7 REFERENCES ............................................................
6-1
6-2
6-3
6-6
7-1
APPENDIX A - ANNUAL TEDE FOR NON-REACTOR NRC LICENSEES, 2004 ........................ A-1
APPENDIX B -ANNUAL WHOLE BODY DOSES AT LICENSED NUCLEAR
POWER FACILITIES, 2004 ............................................................
B-1
APPENDIX C - PERSONNEL, DOSE, AND POWER GENERATION SUMMARY,
1969 -2004 ............................................................
C-1
APPENDIX D - DOSE PERFORMANCE INDICATORS BY REACTOR SITE,
1973 -2004 ............................................................
D-1
NUREG-071
NUREG-07133
vi
vi
7hirty-SeventhAnnudReport,2OL74
Thirty-Sevei#h AnnzwiRpori 2004
Occupational Radiation Exposure at NRC Ucensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
LIST OF FIGURES
Figure 3.1
Average Annual Values at Industrial Radiography Facilities, 1973 - 2004 ............... 3-9
Figure 3.2
Collective TEDE Distribution by Dose Range, Industrial Radiographer Single Location Licensees, 2000 - 2004 ..................................................
3-10
Collective TEDE Distribution by Dose Range, Industrial Radiographer Multiple Location Licensees, 2000 - 2004 ..................................................
3-10
Average Annual Values at Manufacturing and Distribution
Facilities, 1973 - 2004 ..................................................
3-12
Figure 3.3
Figure 3.4
Figure 3.5
Collective TEDE Distribution by Dose Range, Type WAD
Broad
Manufacturing and Distribution Licensees, 2000 - 2004 ......................................... 3-13
Figure 3.6
Collective TEDE Distribution by Dose Range, Limited
Manufacturing and Distribution Licensees, 2000 - 2004......................................... 3-13
Figure 3.7
Average Annual Values at Low-Level Waste Disposal
Facilities, 1982 - 199 ..................................................
3-15
Average Annual Values at Independent Spent Fuel Storage
Facilities, 1982 - 2004 ..................................................
3-16
Collective TEDE Distributon by Dose Range, Independent Spent
Fuel Storage Licensees, 2000 - 2004 ..................................................
3-17
Figure 3.8
Figure 3.9
Figure 3.10 Average Annual Values at Fuel Cycle Licensees, 1973 -2004 .............................. 3-19
Figure 3.11
Collective TEDE Distribution by Dose Range, Fuel Cycle
Licensees, 2000 - 2004 ..................................................
3-20
Figure 3.12 Collective TEDE Distribution by Dose Range, Reactor
Licensees, 2000 - 2004 .................................................. 3-21
Figure 4.1
Figure 4.2
Average Collective Dose and Number of Workers with Measurable Dose
per Reactor, 1973 - 2004 ..................................................
Number of Operating Reactors and Gross Electricity
Generated, 1973 -2004 ..................................................
vii..i
4-9
4-10
NUREG-071 3
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
7irlySeventh Agnnud Report, 2004
Thirty-Seventh Arnrnai Repori 2004
LIST OF FIGURES (Continued)
-age
Figure 4.3
Average Measurable Dose per Worker and Collective Dose per
Megawatt-Year, 1973 - 2004 ..............................................
4-11
Figure 4.4
Average, Median, and Extreme Values of the Collective
Dose per Reactor, 1973 - 1986 .............................................. 4-13
Figure 4.5
Average, Median, and Extreme Values of the Collective
Dose per Reactor, 1987 - 2004 .............................................. 4-14
LIST OF TABLES
Table 3.1
Average Annual Exposure Data for Certain Categories of
NRC Licensees, 1995 -2004 .............................................. 3-3
Table 3.2
Distribution of Annual Collective TEDE by License
Category, 2004 ..............................................
3-5
Table 3.3
Summary of Annual Dose Distributions for Certain NRC
Licensees, 1968 - 2004 .............................................. 3-6
Table 3.4
Annual Exposure Information for Industrial
Radiographers, 2002 - 2004 ..............................................
Table 3.5
Annual Exposure Information for Manufacturers and
Distributors, 2002 - 2004..............................................
3-7
3-11
Table 3.6
Annual Exposure Information for Fuel Cycle Licenses, 2002 - 2004 ..................... 3-18
Table 3.7
Intake by Licensee Type and Radionuclide
Mode of Intake - Ingestion and Other, 2004 ..............................................
Table 3.8
3-23
Intake by Licensee Type and Radionuclide
Mode of Intake - Inhalation, 2004 ..............................................
3-24
Table 3.9
Collective and Average CEDE by Licensee, 2004 ..............................................
3-26
Table 3.10
Internal Dose (CEDE) Distribution, 1994 - 2004 ..............................................
3-27
NUREG-0713
viii
...
7hiny-Seventh Annual Report,2004
Occupational Radiation Exposure at NRC Licensed Facilities
LIST OF TABLES (Continued)
Page
Table 4.1
Summary of Information Reported by Commercial
Boiling Water Reactors, 1973 - 2004 .................................................
Table 4.2
Summary of Information Reported by Commercial
Pressurized Water Reactors, 1973 - 2004 .......................
Table 4.3
Table 4.4
Table 4.5
......................... 4-3
Summary of Information Reported by Commercial
Light Water Reactors, 1973 - 2004 ................................................
4-4
Summary Distribution of Annual Whole Body Doses at
Commercial Light Water Reactors, 1977 - 2004 ................................................
4-7
Three-Year Totals and Averages Listed inAscending Order
of Collective TEDE per BWR, 2002 - 2004 .............................
Table 4.6
4-2
Three-Year Totals and Averages Listed inAscending Order
of Collective TEDE per PWR, 2002 - 2004 ...............................
................... 4-15
.................. -16
Table 5.1
Effects of Transient Workers on Annual Statistical Compilations, 2004 ................... 5-2
Table 6.1
Occupational Exposures in Excess of Regulatory Limits, 1994 - 2004 .................... 6-4
Table 6.2
Occupational Exposures in Excess of Regulatory Limits, 1985 - 1993 .................... 6-5
Table 6.3
Maximum Occupational Exposures for Each Exposure Category, 2004 ................. 6-6
ox
NUREG-0713
PREFACE
A number of NRC licensees have inquired as to how the occupational radiation exposure data that
are compiled from the individual exposure reports required by § 20.2206 are used by the NRC
staff. In combination with other sources of information, the principal uses of the data are to provide
facts regarding routine occupational exposures to radiation and radioactive material that occur in
connection with certain NRC licensed activities. These facts are used by the NRC staff as indicated
below:
1. The data permit evaluation of trends, both favorable and unfavorable, from the viewpoint
of the effectiveness of overall NRC/licensee radiation protection and as low as reasonably
achievable (ALARA) efforts by licensees.
2. The external dose data assist in the evaluation of the radiological risk associated with certain
categories of NRC licensed activities and are used for comparative analyses of radiation
protection performance: U.S./foreign, BWRs/PWRs, civilian/military, facilitytfacility, nuclear
industry/other industries, etc.
3.
The data are used as one of the metrics of the NRC's Reactor Oversight Program to evaluate
the effectiveness of the licensee's ALARA program and also for inspection planning purposes.
4.
The data provide for the monitoring of transient workers who may affect dose distribution
statistics through multiple counting.
5.
The data help provide facts for evaluating the adequacy of the current risk limitation system
(e.g., Are individual lifetime dose limits, worker population collective dose limits, and
requirements for optimization needed?).
6.
The data permit comparisons of occupational radiation risks with potential public risks when
action for additional protection of the public involves worker exposures.
7.
The data are used in the establishment of priorities for the utilization of NRC health physics
resources: research, standards development, and regulatory program development.
8. The data provide facts for answering Congressional and Administration inquiries and for
responding to questions raised by the public.
9. The data are used to provide radiation exposure histories to individuals who were exposed to
radiation at NRC licensed facilities.
10. The data provide information that may be used in the planning of epidemiological studies.
xi
NUREG-071 3
FOREWORD
Through this annual report, the U.S. Nuclear Regulatory Commission (NRC) supports openness
in our regulatory process by providing the public with accurate and timely information about
the safety performance of the agency's licensees. Toward that end, NUREG-0713, Volume
26, summarizes the 2004 occupational radiation exposure data maintained in NRC's Radiation
Exposure Information and Reporting System (REIRS) database. Seven categories of NRC
licensees are required to annually report individual exposure in accordance with Title 10,
Section 20.2206, of the Code of Federal Regulations (10 CFR 20.2206). Specifically, these
categories include commercial nuclear power plants; industrial radiographers; fuel processors
(including uranium enrichment facilities), fabricators, and reprocessors; manufacturers and
distributors of byproduct material; independent spent fuel storage installations; facilities for land
disposal of low-level waste; and geologic repositories for high-level waste. Because the NRC
has not yet licensed any geologic repositories for high-level waste, and no NRC-licensed lowlevel waste disposal facilities are currently in operation, this report considers only the first five
categories of NRC licensees. As such, this report reflects the occupational radiation exposure
data that the NRC received from 227 licensees, of which 104 were operators of nuclear power
reactors in commercial operation.
The data submitted by licensees consist of radiation exposure records for each monitored
individual. (In 2004, 123,332 individuals were monitored, and 61,060 received a measurable
dose.) This report analyzes and presents these records in terms of collective dose and the
distribution of dose among the monitored individuals. During 2004, these individuals incurred
a collective dose of 12,774 person-rem, which represents a 12% decrease from the 2003 value
of 14,567 person-rem. The average measurable dose was 0.21 rem which represents a 9%
decrease from the 2003 value of 0.23 rem. (The average measurable dose is the total collective
dose divided by the number of workers receiving a measurable dose.) This value can be
compared to the 0.30 rem that the average person in the United States receives annually from
natural background radiation. Worldwide annual exposures to natural radiation are generally
expected to be in the range of 0.1 rem to 1.0 rem, with 0.24 rem being the current average
worldwide value.
This annual report is useful in evaluating trends in occupational radiation exposure to assess
the effectiveness of licensees' radiation protection programs to maintain exposures as low
as reasonably achievable (ALARA). For example, the NRC staff uses the data presented in
this report as one of the metrics of the agency's Reactor Oversight Program to evaluate the
effectiveness of licensees'ALARA programs.
Carl J. per lb, Director
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
xiii
xiti
NUREG-071 3
NUREG-0713
Section 1
INTRODUCTION
system that was maintained at the Oak Ridge
National Laboratory Computer Technology
Center in Oak Ridge, Tennessee, until May
1990. At that time, the data were transferred
to a database management system and are
now maintained at the Oak Ridge Institute
for Science and Energy (ORISE), which is
managed by Oak Ridge Associated Universities
(ORAU). The computerization of these data
ensures that they are kept indefinitely and
facilitates their retrieval and analysis. The data
maintained in REIRS have been summarized
and published in a report every year since
1969. Annual reports for each of the years 1969
through 1973 presented the data reported by
both AEC licensees and contractors and were
published in six documents designated as
WASH-1 350-RI through WASH-1 350-R6.
1.1 BACKGROUND
One of the basic purposes of the Atomic Energy
Act and the implementing regulations in Title 10,
Code of Federal Regulations (CFR), Chapter I,
Part 20, is to protect the health and safety of the
public, including the employees of the licensees
conducting operations under those regulations.
Among the regulations designed to ensure that
the standards for protection against radiation
set out in 10 CFR 20 are met is a requirement
that licensees provide individuals likely to be
exposed to radiation with devices to monitor
their exposure. Each licensee is also required
to maintain indefinitely records of the results of
such monitoring. However, there was no initial
provision that these records or any summary of
them be transmitted to a central location where
the data could be retrieved and analyzed.
In January 1975, with the separation of the AEC
into the Energy Research and Development
Administration (ERDA) and the U.S. Nuclear
Regulatory Commission (NRC), each agency
assumed responsibility for collecting and
maintaining occupational radiation exposure
information reported by the facilities under
its jurisdiction. The annual reports published
by the NRC on occupational exposure for
calendar year 1974 and subsequent years
do not contain information pertaining to
ERDA facilities or contractors. Comparable
information for facilities and contractors under
ERDA, now the Department of Energy (DOE),
is collected and published by DOE's Office
of Corporate Performance Assessment, a
division of Environment, Safety and Health, in
Germantown, Maryland.
On November 4, 1968, the U.S. Atomic Energy
Commission (AEC) published an amendment
to 10 CFR 20 requiring the reporting of certain
occupational radiation exposure information to
a central repository at AEC Headquarters. This
information was required of the four categories3
of AEC licensees that were considered to
involve the greatest potential for significant
occupational doses and of AEC facilities and
contractors exempt from licensing. A procedure
was established whereby the appropriate
occupational exposure data were extracted
from these reports and entered into the
Commission's Radiation Exposure Information
and Reporting System (REIRS), a computer
3
commercial nuclear power reactors; industrial radiographers; fuel processors (induding uranium enrichment as of 1997).
fabricators, and reprocessors; manufacturers and distributors of specified quantities of byproduct material.
1-1
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
In 1982 and 1983, paragraph 20.408(a) of
Tide 10 of the Code of Federal Regulations
was amended to require three additional
categories of NRC licensees to submit annual
statistical exposure reports and individual
termination exposure reports. The categories
were (1) geologic repositories for high-level
radioactive waste, (2) independent spent
fuel storage installations, and (3)facilities
for the land disposal of low-level radioactive
waste. This document presents the exposure
information that was reported by NRC licensees
representing two of these categories, since
there are no geologic repositories for high-level
waste currently licensed.
This report and each of the predecessors
summarize information reported for both the
current year and for previous years. More
licensee-specific data for previous years,
such as the annual reports submitted by each
commercial power reactor pursuant to 10 CFR
20.407 and 20.2206 (after 1993) and their
technical specifications (prior to Volume 20 of
this report), may be found in those documents
listed on the inside of the front cover of this
report for the specific year desired. Additional
NUJREG-07131-
7hirty-SeventhAnnud Report,2004
operating data and statistics for each power
reactor for the years 1973 through 1982 may
be found in a series of reports, "Nuclear Power
Plant Operating Experience' [Refs. 1-9].
These documents are available for viewing at
all NRC public document rooms, as well as on
the NRC public web site (www.nrc.gov), or they
may be purchased from the National Technical
Information Service, as shown in the Reference
section.
In May of 1991, 10 CFR 20 "Standards for
Protection Against Radiation; Final Rule' was
revised. The revision redefined the radiation
monitoring and reporting requirements of NRC
licensees. Instead of submitting summary
annual reports (§20.407) and termination
reports (§ 20.408), licensees are now required
to submit an annual report of the dose received
by each monitored worker (§ 20.2206).
Licensees were required to implement the new
requirements no later than January 1994.
Recommendations for further analysis or
for different presentation of information are
welcome.
I1-2
Birty-Seventh Annual Report, 2004
Thirty-Seventh Annual Report; 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
1.2 RADIATION EXPOSURE
INFORMATION ON THE
INTERNET
In May 1995, the NRC began pursuing the
dissemination of radiation exposure information
via a web site on the Internet. This allows
interested parties with the appropriate
equipment to access the data electronically
rather than through the published NUREG0713 document. A web site was created for
radiation exposure and linked into the main
NRC web page. The web site contains upto-date information on radiation exposure, as
well as information and guidance on reporting
radiation exposure information to the NRC.
Interested parties may read the documents
online or download information to their systems
for further analysis. Software, such as the
Radiation Exposure Monitoring and Information
Transmittal (REMIT) System, a software
application designed to maintain licensee
exposure records, and REIRView, a software
package designed to validate a licensee's
annual data submittal, are also available for
downloading via the web site. There are also
links to other web sites dealing with the topics
of radiation and health physics. Individuals
and organizations may also submit requests for
dose records contained in REIRS on this web
site. Visit the site for more details. The NRC
intends to continue pursuing the dissemination
of radiation exposure information via the Web
and will focus more resources on the electronic
distribution of information rather than the
published hard-copy reports.
The main web URL address for the NRC is:
http://wwwinrc.gov
The NRC radiation exposure information web
URL address is:
himpdllwWw.reirs.com
Comments on this report or the NRC's radiation
exposure web page should be directed to:
REIRS Project Manager
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555
1-3
1-3
I
NUREG-071 3
NUREG-071 3
Section 2
LIMITATIONS OF THE DATA
In an effort to account for this, the number of
individuals reported as having uno measurable
exposure4 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).
All of the figures compiled in this report relating
to exposures and doses are based on the
results and interpretations of the readings of
various types of personnel monitoring devices
employed by each licensee. This information,
obtained from routine personnel monitoring
programs, is sufficient to characterize the
radiation exposure incident to individuals'
work and is used in evaluating the radiation
protection program.
The average dose per individual, as well as
the dose distributions shown for groups of
licensees, also can be affected by the multiple
reporting of individuals who were monitored
by two or more licensees during the year.
Licensees are only required to report the doses
received by individuals at their licensed facility.
A dose distribution for a single licensee does
not consider that some of the individuals may
have received doses at other facilities. When
the data are summed to determine the total
number of individuals monitored by a group of
licensees, individuals may be counted more
than once if they have worked at more than
one facility during the calendar year. This can
also affect the distribution of doses because
individuals may be counted multiple times in
the lower dose ranges rather than one time in
the higher range corresponding to the actual
accumulated dose for the year (the sum of the
individual's dose accrued at all facilities). This
source of error has the greatest potential impact
on the data reported by power reactor facilities
since they employ many short-term workers.
Section 5 contains an analysis that corrects for
individuals being counted more than once.
Monitoring requirements are specified in 10
CFR § 20.1502, which requires licensees to
monitor individuals who receive or are likely
to receive a dose in a year in excess of 10%
of the applicable limits. For most adults, the
annual limit for the whole body is 5 rem, so
0.5 rem per year is the level above which
monitoring is required. Separate dose limits
have been established for minors and declared
pregnant workers. Monitoring is required for any
individual entering a high or very high radiation
area. Depending on the administrative policy
of each licensee, persons such as visitors and
clerical workers may also be provided with
monitoring devices, although the probability of
their being exposed to measurable levels of
radiation is extremely small. Ucensees 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.
4
The number of workers with measurable dose includes any individual with a total effective dose equivalent greater than zero rem.
Workers reported with zero dose, or no detectable dose, are included in the number of workers with no measurable exposure.
2-1
2-1
NUREG-0713
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
Another fact that should be kept in mind when
examining the annual statistical data is that
all of the personnel included in the report may
not have been monitored throughout the entire
year. Many licensees, such as radiography
firms and nuclear power facilities, may monitor
numerous individuals for periods much less
than a year. The average doses calculated from
these data, therefore, are less than the average
dose that an individual involved in that activity
for the full year would receive.
Considerable attention should be paid when
referencing the collective totals presented
in this report. The differences between the
totals presented for all licensees that reported
versus only those licensees that are required to
report should be noted. Ukewise, one should
distinguish between the doses attributed
to the pressurized water reactors (PWRs)
and the doses attributed to boiling water
reactors (BWRs). The totals may be inclusive
or exclusive of those licensees that were in
commercial operation for less than one full year.
These parameters vary throughout the tables
and appendices of this report The apparent
discrepancies among the various tables are a
necessary side effect of this endeavor.
The data contained in this report are subject to
change as licensees may submit corrections
or additions to data for previous years. For
the 2004 report, data for prior years have
been updated to account for these corrections
and additions. Users should be alert to these
changes.
Dirty-SeventhAnnudReport, 2004
Thirty -Seventh Annu4Repori, 2004
It should again be pointed out that this report
contains information reported by NRC licensees
and some Agreement State5 licensees who
also have reported to the NRC. Since the
NRC licenses all commercial nuclear power
reactors, fuel processors and fabricators,
and independent spent fuel storage facilities,
information shown for these categories reflects
the total U.S. experience. This is not the
case, however, for the remaining categories
of industrial radiography, manufacturing
and distribution of specified quantities of
byproduct material, and low-level waste
disposal. Companies that conduct these
types of activities in Agreement States are
licensed by the state and are not required
to submit occupational exposure reports to
the NRC. More than three times as many
facilities are regulated by Agreement States
than are licensed by the NRC. In addition, this
report does not include compilations of nonoccupational exposure, such as exposure
due to medical X-rays, fluoroscopy, and
accelerators, received by patients.
All dose equivalent values in this report are
given in units of rem in accordance with
the general provisions for records, 10 CFR
20.2101 (a). In order to convert rem into the
International System of Units (SI) unit of sieverts
(Sv), divide the value in rem by 100. Therefore,
I rem = 0.01 Sv. In order to convert rem into
millisieverts (mSv), multiply the value in rem by
10. Therefore, 1 rem = 10 mSv.
States that have entered into an agreement with the NRC that allows each state to license organizations using radioactve materials
for certain purposes. As of March 2004, there are 33 Agreement States.
NUREG-0713
NUREG-0713
2-2
2-2
Section 3
ANNUAL PERSONNEL MONITORING
REPORTS - 10 CFR 20.2206
3.1 DEFINITION OF TERMS
AND SOURCES OF DATA
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. 101.
3.1.1 StatisticalSummaryRtports
The total effective dose equivalent (TEDE)
is summed per individual and tabulated into
the appropriate dose range to generate the
dose distribution for each licensee. The total
collective dose is more accurate using this
method because the licensee reported the dose
to each individual, and the total collective dose
was calculated from the sum of these doses
and not statistically derived from the distribution
(see Section 3.1.4). The TEDE includes the
dose contribution from the committed effective
dose equivalent (CEDE) for those workers
who had intakes that required monitoring and
reporting of internal dose.
3.1.4 CollectiveDose
The concept of collective dose is used inthis
report to denote the summation of the TEDE
received by all monitored workers and is reported
in units of person-rem. 10 CFR 20.2206 requires
that the TEDE be reported, so the collective
dose is calculated by summing the TEDE for
all monitored workers. The phrase Tcollective
dose" is used throughout this report to mean the
collective TEDE, unless otherwise specified.
3.1.2 Number ofMonitored Workers
The number of monitored workers refers to the
total number of workers that the NRC licensees
(who are covered by 10 CFR 20.1502) reported
as being monitored for exposure to external and
internal radiation during the year. This number
includes all workers for whom monitoring is
required and may include visitors, service
representatives, contract workers, clerical
workers, and any other workers for whom the
licensee determines that monitoring devices
should be provided.
It should be noted that prior to the implementation
of the revised dose reporting requirements of
10 CFR 20.2206 in 1994, the collective dose
was, in some cases, calculated from the dose
distributions by summing the products obtained
from multiplying the number of workers reported
in each of the dose ranges by the midpoint of the
corresponding dose range. This assumes that the
midpoint of the range is equal to the arithmetic
mean of the individual doses in the range.
Experience has shown that the actual mean
dose of workers reported in each dose range
is less than the midpoint of the range. For this
reason, the resultant calculated collective doses
shown inthis report for these licensees may be
about 10% higher than the sum of the actual
individual doses. Care should be taken when
For licensees submitting under 10 CFR
20.2206, the total number of workers was
determined from the number of unique personal
identification numbers submitted per licensee.
Uniqueness is defined by the combination of
identification number and identification type
[Ref. 10].
3-1
3-1
NUREG-071 3
NUREG-0713
7hirty-Seventh An nud Repo rt,2004
Claupational Radiation Esposure at NRC Licensed Facilities
Exosue a NR Liensd FailiiesThity-evenh Anua Reors200
OccuatinalRadatin
comparing the actual collective dose calculated
for 1994 to 2004 wihU the collective dose for
years prior to 1994 because of this change in
methodology. In addition, prior to 1994, doses
only included the external whole body dose.
Although the contribution of internal dose to the
TEDE is minimal for most licensees, it should be
considered when comparing collective doses for
1994 and later with the collective dose for years
prior to 1994. One noted exception is for fuel
fabrication licensees where the CEDE in some
cases contributes the majority of the TEDE
(see Section 3.3.5).
3.1.5 Average IndividualDose
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 Averape Measurable Dose
The average measurable dose is obtained by
dividing the collective TEDE by the number
of workers who received a measurable dose.
This is the average most commonly used
in this and other reports when examining
trends and comparing doses received by
workers in various segments of the nuclear
industry because it deletes those workers
receiving zero or no detectable dose, many
of whom were monitored for convenience or
identification purposes.
3.1.7 Number of Licensees Reporting
The number of licensees refers to the NRC
licenses issued to use radioactive material for
certain activities that would place the licensees
in one of the sevens categories that are required
to report pursuant to 10 CFR 20.2206. The
third column in Table 3.1 shows the number of
licensees that have filed such reports during
the last 10 years. All nuclear power plants, fuel
processors and fabricators, and independent
spent fuel storage facilities are required to
report occupational exposure to the NRC,
whether they are in an Agreement State or
not. But the other types of Agreement State
licensees are not required to submit exposure
reports to the NRC and are not included in this
report
3.1.8 Collective TEDE Distribution
by Dose Rang=
The United Nations Scientific Committee on
the Effects of Atomic Radiation's (UNSCEAR's)
2000 report entitied wReport of the Scientific
Committee on the Effects of Atomic Radiation"
[Ref. 11] recommends the calculation of a
parameter "SR7 (previously referred to as CR or
MR) to aid in the examination of the distribution
of radiation exposure among workers. SR is
defined as the ratio of the annual collective
dose incurred by workers whose annual doses
exceed a certain dose level to the total annual
collective dose. UNSCEAR uses a subscript to
denote the specific dose level in millisieverts.
Therefore, SRi5 is the notation for the annual
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 tow-level waste; and geologic repositories for high-level waste. There are currently no NRC licensees Involved In
low-level waste disposal or geologic repositories for high-level waste.
l_
_U_G_
NUREG-0713
3-2
_-
-
-
TABLE 3.1
Average Annual Exposure Data for Certain Categories of NRC Ucensees
1995-2004
a
S
C
I
*-.-*-*-
NuWussa.
Radiography
03310
03320
Manufacturing
and
Distribution
02500
03211
03212
03214
Low.Avei
Waste
Disposair
03231
Independent
Spent Fuel
Storage
23100
23200
Fuel
Cycle
Ucenses Fabrication
Processing and
Uranium Enrich.
21200
21210
Conmiercral
Ught Water
Reactors
dff
I
Al*l
t*
.
e
10.b
1996
1997
1998
1999
2000
2001
2002
2003
148
148
142
132
129
124
100
107
3.786
3.670
4,952
3,637
3.368
3,780
3,420
2.918
2004
an
3 102
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1995
1996
1997
1998
1999
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1995
1996
1997
1998
1999
2000
2001
2002
2003
36
38
33
31
39
39
36
29
31
21
2
2
2
1
0
1
1
1
1
2
2
2
2
2
1
8
a
10
10
9
9
9
8
8
2,666
2,631
1,154
1,986
2,181
2,461
1,662
1,437
2,146
2.251
212
165
185
27
2004
8
2.639
2,574
3,448
2.827
2,542
3,161
2.842
2,541
2 716
1,222
1,24t
665
654
836
1,188
1,211
1.052
1,668
1.580
56
67
50
13
S-
,
f
0.8
r
us
2,111
1,729
1.632
0.40
0.45
0.56
0.51
0.56
0.55
0.53
0.54
0.55
0.60
0.67
0.61
0.64
i 567
O040
0l 7
0.22
0.21
0.34
0.20
0.19
0.17
0.19
0.23
0.20
0.14
0.04
0.05
0.03
0.05
0.49
0.45
0.60
0.61
0.50
0.35
0.29
0.31
0.25
0.21
0.15
0.12
0.11
0.10
1,449
1 356
1,863
1,551
1,528
595
556
397
402
419
415
351
328
420
324
a
8
5
1
0.38
0.38
0.38
104
49
51
0.49
1.04
97
53
54
0.56
1.02
55
24
6
0.11
0.24
53
21
3
0.05
0.12
86
33
5
0.06
016
146
83
6
0.04
0.07
154
107
13
0.08
0.12
75
67
6
0.08
0.09
55
46
3
0.05
0.06
37
27
1
0.03
0.05
4,106
2,959
1,217
0.30
OA1
4,369
3,061
878
0.20
0.29
11.214
3,910
1,006
0.09
0.26
10,684
3,613
950
0.09
0.26
9,693
3,927
1,020
0.11
0.26
9,336
4,649
1,339
0.14
0.29
8,145
3,980
1,162
0.14
029
7,937
3,886
661
0.08
0.17
7,738
3.633
556
0.07
0.15
7,562
3,814
514
0.07
0.13
132,266
70,821
21,688
0.16
0.31
126,402
68,305
18,883
0.15
0.28
126,781
68,372
17,149
0.14
0.25
114,367
57,466
13,187
0.12
023
114,154
59,216
13.68
0.12
0.23
110,557
57,233
12,652
0.11
0.22
104,928
52,292
11,109
0.11
0.21
107,900
54.460
12,126
0.11
0.22
109,990
55,967
11,956
0.11
0.21
110.290
52.873
10.368
0.09
0.20
143,115
77,758
25,003
0.17
0.32
137,430
75,366
21,828
0.16
0.29
142,959
75,595
19,919
0.14
026
132,069
65,213
16,406
0.12
0.25
129,951
66,839
16,661
0.13
0.25
125,868
65,695
15.940
0.13
0.24
118,869
60,751
14,746
0.12
0.24
120,769
62,307
14,850
0.12
0.24
122,847
63,855
14,567
0.12
0.23
12332.06
12.774
0.10
021
Agreement State licensed organizations are not required to report occupational eposure data
1995
109
1996
109
1997
109
1998
105
41111
1999
104
2000
104
2001
104
2002
104
2003
104
2004
104
Grand Totals
1995
305
and Averages
1996
306
1997
303
1998
290
1999
286
2000
283
2001
275
2002
243
2003
252
___ _ 2004 227
I These categoIes consist only of NRC licensees.
to the NRC.
- As of 1999, there are no longer any NRC lcensees Involved Inthis activity. All low-levei waste disposal facilities are now located InAgreement
States and no longer report to the NRC.
-Includes all LWRs Incommercial Operation for a full year for each of the years Indicated. Reactor data have been corrected to account for the
multiple counting of transient reactor workcers (see Section 5).
3-3
NUREG-071 3
NUREG-0713
MrrpSeventhAnnudReport,2004
Occupational Radiation Fxposure at NRC Ucensed Facilities
nulRp~20
Ti--eet
R iesdFclteLdato Exouea
Occupational~~~~~~~~~~~~~~~~
collective dose above 1.5 rem divided by the
total annual collective dose. The UNSCEAR
2000 report notes that the 1.5 rem dose level
may not be useful where doses are consistently
lower than this level, and they recommend
that research organizations report SR values
lower than 1.5 rem where appropriate. For
this reason, the NRC has adopted the policy
of calculating and tracking the collective TEDE
distribution by dose range at dose levels of 0.10
rem, 0.25 rem, 0.50 rem, 1.0 rem, and 2.0 rem.
The collective TEDE distribution by dose range
values in this report was calculated by summing
the TEDE to each individual who received a
TEDE greater than or equal to the specified
dose range divided by the total collective TEDE.
In addition, the distribution is presented as a
percentage rather than a decimal fraction.
Figures 3.2, 3.3, 3.5, 3.6, 3.9, 3.11, and 3.12
show the collective TEDE distribution by dose
range calculated in terms of percentages of the
collective dose delivered above the specified
dose levels for each of the categories of NRC
licensee. Two properties of these graphs help
to further reveal the nature of the distribution
of dose and dose trends at NRC licensees.
The first is that the percentage of dose in the
higher dose ranges (above 0.50 rem) should be
relatively small. This would indicate that fewer
workers are exposed at these higher levels
of individual risk. The second property is the
ability to track the shift in dose over time. For a
given dose level, a reduction in the percentage
from one year to the next indicates that less
dose is being received by workers above this
level. Therefore, these graphs can be useful in
qualifying the dose received in a given year and
the trend in doses from year to year.
NUREG-0713
3.2 ANNUAL TEDE DOSE
DISTRIBUTIONS
Table 3.2 provides a statistical compilation
of the exposure reports submitted by six
categories of licensees (see Section 3.3 for a
description of each licensee category). The
dose distributions are generated by summing
the TEDE for each individual and counting
the number of individuals in each dose range.
In nearly every category, a large number of
workers receive doses that are less than
measurable, and very few doses exceed 4 or
5 rem. Ninety percent of the reported workers
with measurable doses were monitored by
nuclear power facilities in 2004, where they
received 81% of the total collective dose.
Under the regulatory limits of 10 CFR
20.1201, annual TEDE in excess of 5 rem for
occupationally exposed adults is, by definition,
an exposure in excess of regulatory limits (see
Section 6).
Table 3.3 gives a summary of the annual
exposures reported to the Commission by
certain categories of NRC licensees as
required by 10 CFR 20.2206. Table 3.3 shows
that approximately 95% of the exposures
consistently remained <2 rem between
1968 and 1984. For the past 14 years, the
percentage of workers with <2 rem has been
greater than 99%. The number of workers
receiving an annual exposure in excess of
5 rem has been <0.01% since 1985. No
individual received a dose above the 5 rem
annual TEDE limit in 2004 (see Section 6).
3-4
34
TABLE 3.2
Distribution of Annual Coilective TEDE by License Category
2004
- ..
EEEEEEEEEqamlflfi M~ I
INDUSTRIAL RADIOGRAPHY
Single Location (12)
Multiple Location (81)
Total (93)
101
325
426
751
785
MANUFACTURING AND
DISTRIBUTION
-A! - Broad (3)
Limited (18)
Total (21)
109
562
671
117
885
1,002
59
215
274
63
77
140
10
22
4
1
3,748
2,493
716
324
149
91
41
COMMERCIAL POWER REACTORS3
Boiling Water (35)
Pressurized Vater (69)
Total (104)
26,043 19,678 7,101
8,525
54,430 21,905
80,473 41,583 15,626
4,546
3,699
8,245
1,690
1,043
2,733
572
406
978
353
315
668
8
8
16
GRAND TOTALS
85,328 45,885
17,077
9,168
3,256
1,329
11,145
134
34
7
-EE
450 1 5
3,046
3,192
45
2,721
2,786
3.145
1,564.355
1,567.500
448
1,803
2,251
339
1,241
1,580
157.680
166.193
323.873
37
27
1.257
7,562
3,814
513.725
59,991
90,331
150,322
33,948
35,901
69,849
5,450.982
4,916.915
10,367.897
163,364
78.036
12,774.252
146
4
319
319
32
23
55
2351
235
377I
377
98
98
17
8
25
37
22
59
14
6
20
30
30
7
0
7
0
4
4
1
1
LOW4LEVEL WASTE DISPOSAL
Total (0)*
INDEPENDENT SPENT FUEL
STORAGE
Total (1)
FUEL CYCLE UCENSES*
Total (8)
z
-
0
34
8
* Dose values exactly equal to the values separating ranges are reported In the next higher range.
Afciltles ae now located In Agreement States.
There are no NRC licensees currently involved In this acvity. All
Indudes fabrication, processIng and uranium enrichment plants (see Section 3.3.5).
Incdudes all reactors In commercial operation for a full year during 2004. These values have not been adjusted for the multiple counting of transient reactor workers (see Section 5).
TABLE 3.3
Summary of Annual Dose Distributions for Certan NRC licensees
1968-2004
S.
1968
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
-
36,836
31,176
36,164
36,311
44,690
67,862
85,097
78,713
92,773
98,212
105,893
131,027
159,177
157,874
162,456
172,927
181,627
212,217
225,582
243,562
231,234
229,353
227,777
218,519
220,717
208,784
178,987
179,406
173,674
180,814
166,127
166,084
163,073
154,717
162,381
164,993
163.364
S
S
*
93,438
100,818
125,316
150,675
149,314
154,117
164,239
168,899
201,339
213,017
227,997
215,662
212,474
208,513
202,731
202,998
189,109
149,173
143,115
137,430
142,959
132,069
129,117
125,026
118,150
119,694
121,265
122.322
97.2%
96.5%
96.1%
96.3%
95.7%
95.0%
96.4%
94.8%
95.0%
93.8%
94.6%
95.2%
94.6%
94.6%
94.9%
94.6%
95.1%
97.6% (4,734)
98.0% (4,076)
98.8% (2,738)
98.6% (2,980)
99.1% (2,018)
98.9% (2,150)
99.4% (1,174)
99.6% (897)
99.5% (719)
99.5% (818)
99.3% (1,049)
99.5% (730)
99.5% (666)
99.6% (489)
99.6%
(534)
99.5%
(573)
(734)
99.4%
99.5% (582)
(414)
99.7%
99.7% (366)
99.5%
99.5%
99.4%
99.3%
99.5%
99.5%
99.7%
99.5%
99.6%
99.6%
99.8%
99.8%
99.7%
99.8%
99.9%
99.9%
99.9%
>99.99% (15)
>99.99% (8)
>99.99% (4)
>99.99% (8)
>99.99% (7)
>99.99% (3)
>99.99% (2)
>99.99% (1)
>99.99% (2)
>99.99% (1)
>99.99% (1)
>99.99% (1)
100%
(0)
>99.99% (6)
>99.99% (1)
>99.99% (3)
>99.99% (1)
>99.99% (1)
>99.99% (1)
100%
(0)
Licensees required to submit radiation exposure reports to the NRC under 10 CFR 20.2206.
This column lists Ihe actual number of persons who may have been counted more than once because they worked at more than one facility
during the calendar year (see Section 5)
Data for 1977-2004 are based on the distribution of individual doses after adjusting for the multiple counting of transient reactor workers (see
Section 5). The numbers of people exceeding both 2 and 5 rem are shown In parentheses from 1985-2004.
NUREG-0713
3-6
Diny-Seventh Annual Report,2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
Thirty-Seventh Annual Report; 2004
The average measurable dose for workers
performing radiography at a single location
ranged from 10% to 12% of the average
measurable dose of workers at multiple location
facilities over the past 3 years. This is because
it is more difficult for workers to avoid exposure
to radiation in the field, where conditions are
not optimal and may change daily. To view the
contribution that each radiography licensee
made to the total collective dose, see Appendix
A, which presents a summary of the information
reported by each of these licensees in 2004.
3.3 SUMMARY OF
OCCUPATIONAL EXPOSURE
DATA BY LICENSE CATEGORY
3.3.1 IndustrialRadiographyLicenses.
Single andMukibpe Locations
Industrial Radiography licenses are issued to
allow the use of sealed radioactive materials,
usually in exposure devices or cameras,0 that
primarily emit gamma rays for nondestructive
testing of pipeline weld joints, steel structures,
boilers, aircraft and ship parts, and other highstress alloy parts. Some firms are licensed to
conduct such activities in one location, usually
in a permanent facility designed and shielded
for radiography; others perform radiography
at multiple temporary sites in the field. The
radioisotopes most commonly used are
cobalt-60 and iridium-1 92. As shown in
Table 3.1, annual reports were received for
93 radiography licensees in 2004. Table 3.4
summarizes the reported data for the two types
of radiography licenses for 2004 and for the
previous 2 years for comparison purposes.
High exposures in radiography can be directly
attributable to the type and location of the
radiography field work. For example, locations
such as oil drilling platforms and aerial tanks
offer the radiographer little available shielding.
In these situations, there may not be an
opportunity to use distance as a means of
minimizing exposure and achieving doses
as low as reasonably achievable (ALARA).
TABLE 3.4
Annual Exposure Information for Industrial Radiographers
2002-2004
2002
Single Location
Multiple Locations
Total
15
85
100
112
3,308
3,420
55
2,787
2,842
4
1,725
1,729
0.08
0.62
0.61
2003
Single Location
Multiple Locations
Total
12
95
107
97
2,821
2,918
45
2,496
2,541
4
1,725
1,729
0.07
0.65
0.64
2004
Single Location
Multiple Locations
Total
12
81
93
146
3,046
3,192
45
2,721
2,766
3
1,564
1,567
0.07
0.57
0.57
3-7
NUREG-07l3
NUREG-0713
7Urty-SeventhAnnudRepor4 2004
Occupational Radiation Fxposure at NRC Licensed Facilities
Ri
=ua 200
A
Epour asNR lcese FciitesThrt-Seet
OccpaioalRaiaio
Although these licensed activities usually result
in average measurable doses that are higher
than other licensees, they involve a relatively
small number of exposed workers.
3.3.2 Manufacturing andDistribution
Licenses. Type A BroadandLimited
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.
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
Broad licenses are issued to larger
Type WAW
of Industrial Radiography facilities from 1973
organizations that may use many different
through 2004. The number of workers with
radionuclides in many different ways and that
measurable TEDE per licensee increased from
have a comprehensive radiation protection
2003 to 2004, and the average measurable
program. Some Type "A Broad license firms
TEDE decreased by 10% from 0.64 rem in
are medical suppliers that process, package,
2003 to 0.57 rem in 2004. Figures 3.2 and 3.3
or distribute such products as diagnostic test
show the collective dose distribution by dose
kits; radioactive surgical implants; and tagged
range (see Section 3.1.8) for single location and radiochemicals for use in medical research,
multiple location radiography licensees. These
diagnoses, and therapy. The Limited licenses
graphs demonstrate that multiple location
are usually issued to smaller firms requiring
licensees consistently have individuals receiving a more restrictive license. Umited firms are
doses in the higher dose ranges and routinely
suppliers of industrial radionuclides and are
have 25% to 40% of the collective dose
involved in the processing, encapsulation,
delivered to individuals above 2 rem. From
packaging, and distribution of the radionuclides
2000 to 2001, for these licensees, there were
that they have purchased in bulk quantities
increases in the percentage of dose for each
from production reactors and cyclotrons.
the
for
However,
rem.
0.50
above
range
dose
Major products include gamma radiography
past 3 years, the percentage of the collective
sources, cobalt irradiation sources, well-logging
dose delivered in each dose range above 0.50
sources, sealed sources for gauges and smoke
rem was less than the value in 2001. For single detectors, and radio-chemicals for nonmedical
location licensees, the percentage of individuals research.
in all dose ranges decreased for the second
year in a row from the 2002 values.
NUREG-0713
NUREG-0713
3-8
3-8
30
0--
-
_
1_________
1 __
°°
No. of Workers wI Measurable Dose per Ucensee,
090
Collective TEDE per Ucensee (person-mrm)
|
Average Meass. TEDE per Worker (rem)
o
30.0
0.
~0.70
Cr
-0.60
073-……40
'we
AA
Ne0.30~
N.
9
00
.d002
J,
7 U.
@0
0
0
0.10
00
0
Year
z
FIGURE 3.1. Average Annual Values at Industrial Radiography Facilities
1973-2004
U9
jg7G013
OcOP~tO~ iadatln
.1posi1E
ed
at NRC Uicens
~ac~li~
7i~qtsvexfh
A.sflU
I
80%-
70% 70%
I
I.
2000
2001
200
FIG
RE .2.colectveTEDE
IndsWE2000
2003
2004
Distfibut'OIn
-2004
by Dos"
100%
'30%
20%
A fetO
2000
2001
2002
2003
2004
FIGUE
3.. Cll~c"'
6
Industrial
TFD DIstributiofl
Radloc.
by Dose
2We u
Ranlge
PL0e
3-10
Ras g
4
Rport4 2004
7hirt-&entAnnualRe~port,2004
Thirsy-&ven:h Annwd Report, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
Table 3.5 presents the annual data that were
reported by the two types of licensees for
2004 and the previous 2 years. Looking at
the information shown separately for the Type
A Broad and Limited licensees, one can see
that the values of collective and average
measurable dose generally remain higher for
the Broad licensees. However, to examine
trends in the data presented for this category of
licensees, it should be noted that the types and
quantities of radionuclides may fluctuate from
year to year, and even during the year. For this
reason, some licensees may report dose data
one year and not the next and may be included
as a Broad licensee one year and a Limited
licensee at other times. Because the number
of reporting licensees is quite small, these
fluctuations may have a significant impact on
the values of the parameters. The number of
Type A Broad licensees remained at 3 in 2004,
the same as in 2002 and 2003.
Figure 3.4 shows the number of workers
with measurable dose per licensee, the total
collective dose per licensee, and the average
measurable dose per worker for both Type
A Broad and Umited Manufacturing and
Distribution facilities. Although the number of
workers with measurable dose per licensee
has been steadily increasing since 1999, the
collective TEDE per licensee has remained
relatively level during this same time period.
The figures for Type A Broad licensees are
primarily attributed to Mallinckrodt Medical,
Inc., which accounted for 97% of the collective
dose for this category of licensee in 2004.
Figures 3.5 and 3.6 show the collective dose
distribution by dose range (see Section 3.1.8)
for Type A Broad and Umited Manufacturing
and Distribution licensees. These graphs
clearly show that the Type A Broad licensees
consistently have individuals receiving dose in
the higher dose ranges. In 2000, 55% of the
collective dose was received by individuals
above 2 rem. In 2004, this percentage
TABLE 3.5
Annual Exposure Information for Manufacturers and Distributors
2002-2004
2002
M&D-A'-Broad
M & D-ULmited
Total
3
26
29
334
1,103
1,437
247
805
1,052
197
131
328
0.80
0.16
0.31
2003
M&D A'-WBroad
M & D-Umited
Total
3
28
31
438
1,708
2,146
349
1,319
1,668
229
191
420
0.66
0.14
0.25
2004
M & D -W - Broad
M & D-Limited
Total
3
18
21
448
1,803
2,251
339
1,241
1,580
158
166
324
0.47
0.13
0.21
3-11
3-11
NUREG-071 3
NUREG-0713
I
z
120-
.
I
of Worke0rs wi Measurable Dose per Licensee9
~No.
: Collective TEDE per Licensee (person-rem)
Average Meas TEDE per Worker (rem)
>
0
:
0.90
g.
100-
o
1.00
o
0.80
Ye0.70
*
0
60-
-0.50
----
30
40-
003
P
-U.4
0
10-00
cr20
7.0
0.0
zj
m
a-,A
D
iZ-0
z
0.60
00o0
…
-
W
O
2i.
~Si2
0(0
a0
CD
-(0ho
(0
(01
S
(0(0
00I
Ye ar
FIGURE 3.4. Average Annual Values at Manufacturing and Distribution Facilities
1973-2004
7kh-ty-Seventh Annud Report, 2004
ThrySeet AnulRprj20
Occupational Radiation Fxposure at NRC Ucensed FwAtics
tNCLcne altc
cuainlRdainEpsr
40%
12010%
0%
'-0.8000
000
1.3
2 200
20040
FIGURE 3.5. Collective TEDE Distribution by Dose Range
Type 'AW Broad Manufacturing and Distribution Licensees
2000 - 2004
90%
i60%
20%,
0%
oo
2000
i
FIGURE 3.6. Collective TEDE Distribution by Dose Range
Limited Manufacturing and Distribution Licensees
2000 - 2004
3-13
NUREG-0713
NUREG-0713
Occupational Radiation Exposure at NRC Ilcensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
decreased for the fifth consecutive year to 22%.
Limited licensees exhibit a distribution of the
collective dose where individuals below 0.50
rem receive over 50% of the collective dose.
Appendix A lists the contribution that each of
these licensees made toward the total values
of the number of workers monitored, number of
workers, and collective dose for 2004.
3.3.3 Low-Level Waste DisposalLicenses
Low-Level Waste Disposal licenses are
issued to allow the receipt, possession, and
disposal of low-level radioactive wastes at a
land disposal facility. The licensee has the
appropriate facilities to receive wastes from
such places as hospitals and laboratories,
store them for a short time, and dispose of
them in a properly prepared burial ground. The
licensees in this category are located in and
licensed by Agreement States, which have
primary regulatory authority over the licensees'
activities. Since 1999, all licensees that have
conducted these activities have been located
in Agreement States; therefore, there are no
licensees reporting radiation exposure data
to REIRS. Figure 3.7 shows the number of
workers with measurable dose per licensee,
the total collective dose per licensee, and
the average measurable dose per worker for
Low-Level Waste Disposal facilities from 1982
through 1998.
NUREG-0713
NUREG071
7hirtj-SeventbAnnud Report, 2004
Thirty-Seventh Annual Reporl, 2004
3.3.4 Independent Sent FuelStorage
InstallationLicenses
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 ina power reactor, is provided
interim storage, protection, and safeguarding for
a limited time, pending its ultimate disposal.
Thirty-four licenses were authorized to conduct
these activities during 2004. Nine of these
licenses are for activities involving cask
design and storage systems. Twenty-three
are located at nuclear power plants allowing
on-site temporary storage of fuel. These
twenty-three licensees report the dose from
fuel storage activities along with the dose from
reactor operations at these sites. The two
remaining licenses are located at facilities that
are independent of a reactor site. One is the
GE Morris facility located in Illinois. The second
site was included for the first time in 1999 and is
a site in Idaho operated by DOE for the storage
of fuel from Three Mile Island Unit 2. Only the
GE Morris facility reported and is included in
the 2004 data for this licensee category in this
report. Appendix A summarizes the exposure
information reported by this licensee.
3-1
3-14
_
400-
t
350 -
/
a.
-
_
No. of Workers w/ Measurable Doss per Licensee
_
Collective TEDE per Licensee (person-rem)
Average Meas. TEDE per Worler (rem)
-…-
° za
£f2 30090a
-0.70
-
\
0
-0.60
>
M
-
_0.50
250-…-…
2
-0.40
EYea 200-=0
-0.30
150a-
100
--
---
-
0.20
0*
)
505
0-………………
CD
co
………………
co
co
Q3
C
co
co CD CD
0)
0)0)
CD
CD
0
CD
CD
CO
0.00
to
to
CO
co
to
to
CDb
Cn
CD
C4
CO
CD
2
2
..
CA
z
Year
FIGURE 3.7. Average Annual Values at Low-Level Waste Disposal Facilities
1982-1998
z
O Note: As of 1999, there are
o
no longer any NRCIlconsem
InvolvedIn thIs activIty. All low-level wastedisposal facilfties aemnow locaftedInAgreement Staftes nd nolonger report to theNRC.
ft
10
10090 -
0-
I
No. of Worikrsw/ Measirable Doss per Licensee II
Collective TEDE per Licensee (persn-rem)
_
_
IT
I --I TI.
1I
I I
_,
-2.00
i
-
i
-
+
-
-i
-
-
A
.
.
.
.
.
.
.
I..---..- .- I\
F
-1.6C
I
80-
Average Mea. TEDE per Worker (rem)
_._
-I
-1.20
60--
ow
1a
an
*I .IJI
.-_
-
50
_
--
-
0
-
r
30
to
co
CD
CD
co
co
CD
w
I
C D
I
c o
I
I
w
I
I
I
C D C D
-
- _ _-
I
I
I
-
-
-
_ __- __
I
I
I
I
I
I
I
I
I
I
_0.20
n-
I0.
.40
----
--
…-
0.80
--- 04.0
-
-
,
10-- --
-
-
---
30-
co
co
I;
*1
20-
IL
1.00
-
-
0
I
D CDto
Year
FIGURE 3.8. Average Annual Values at Independent Spent Fuel Storage Facilities
1982-2004
w
w.
.
.
-n n n
I
I
I
O
1P
7hirty-&venthAnnudReport,2004
Thirty-Seventh Annual Report 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure a: NRC licensed Facilities
Figure 3.8 shows the number of workers
with measurable dose per licensee, the total
collective dose per licensee, and the average
measurable dose per worker for ISFSI
facilities. The large increase in the collective
dose per licensee and number of workers per
licensee in 1994 was mainly because only
one licensee reported separately for 1994
through 1998, rather than the two licensees
that reported in prior years. All parameters
decreased significantly from 1996 to 1999,
but increased from 2000 to 2001, and have
decreased from 2001 to 2004. The number
of workers with measurable dose per licensee
Increase in 2004 since only one licensee
reported. Figure 3.9 shows the collective
dose distribution by dose range (see Section
3.1.8) for ISFSI licensees from 2000 to 2004.
The percentages for each dose range have
fluctuated from year to year since 1998 due to
the small number of licensees involved. No
individual has received a dose above I rem at
these facilities for the past 5 years.
90%
80%
F
I
70%
60%
50%
I
40%
30%
10%
0%
FIGURE 3.9. Collective TEDE Distribution by Dose Range
Independent Spent Fuel Storage Licensees
2000 - 2004
3-17
3-17
UREG07l
NUREG-0713
7biriy-SeventhAnnualRepom 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
3.3.5 Fuel Cylk Licenses
Fuel Cycle licenses are issued to allow the
processing, enrichment, and fabrication of
reactor fuels. In most uranium facilities where
light water reactor (LWR) fuels are fabricated,
enriched uranium hexafluoride is converted to
solid uranium dioxide pellets and inserted into
zirconium alloy tubes. The tubes are fabricated
into fuel assemblies that are shipped to nuclear
power plants. Some facilities also perform
chemical operations to recover the uranium
from scrap and other off-specification materials
prior to disposal of these materials. For 1997
to 2004, this category also includes the two
uranium enrichment facilities at Portsmouth,
Ohio, and Paducah, Kentucky. The regulatory
oversight for these facilities was transferred
from DOE to the NRC in 1997.
Figure 3.10 shows the number of workers
with measurable dose per licensee, the total
collective dose per licensee, and the average
measurable dose per worker for Fuel Cycle
licensees. Inaddition to the TEDE collective
and average measurable dose, the Deep
Dose Equivalent (DDE) collective dose and
DDE average measurable dose are shown.
Thirty-Seventh Annual Rep on; 2004
Both doses are shown since the CEDE is a
significant contribution to the TEDE for Fuel
Fabrication facilities. Figure 3.11 shows the
collective dose distribution by dose range
(see Section 3.1.8) for Fuel Cycle licensees
from 2000 to 2004. The percentage of the
collective dose above each dose range
increased in almost every dose range from
2000 to 2001. However, from 2001 to 2004,
there was a decrease in the percentage of
the collective dose above each dose range.
Most of the decrease is due to reductions in
the collective dose reported by Westinghouse
Electric Co. at the Commercial Nuclear Fuel
Division in South Carolina. As shown in Table
3.6, the collective DDE remained the same
between 2003 and 2004, while the collective
CEDE decreased by 14%.
Appendix A lists each of the licensees reporting
in 2004, with the number of workers monitored,
the number of workers receiving measurable
external doses, and the collective dose for
each licensee. Table 3.6 shows that there
were 8 licensed Fuel Cycle (Fabrication and
Enrichment) facilities reporting in 2004.
TABLE 3.6
Annual Exposure Information for Fuel Cycle Licenses
2002-2004
2002 Fuel Cycle
8
7,937
3,886
661
0.17
3,021
296
0.10
2,404
365
0.15
2003 Fud Cycle
a
7,738
3,633
556
0.15
2,815
258
0.09
2,255
298
0.13
2004 Fud Cycle
8
7,562
3,814
514
0.13
2,933
258
0.09
2327
256
0.11
NUREG-071 3
NUREG-0713
3-18
3-18
650___
-
No. of Worlersw/ Measurable Dose per Licensee
Collective DDE per Licensee (person-rem)
---
> 600
O
Collective TEDE per Licensee (person-rem)
-
=
55co-n
a
500
5r
-
_
_ _…-0.60
-*-Average Meas DDE perWorler(rem)
Average Meas. TEDE per Worler (rem)
-----
0.50
450--O
CDro
*0
v
a
I
-
wco
a1
__XvLI
I__________
I I
A I_
.0
1300
1
k
40.
300
40
-
-
-
200- 350
t4
-
J0
0
SQ1C
nc
c
-
0s
D
1973-2004
-.
40
-s
0-4
;4 Poe U10
0S
1e
-
t
e
DE
1X
0E
<
-- 0.20
4b5
"s
0O
03
- 'o
F
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
Mr7 eventhnnual
etport 200
Thiry-& venthAnrn4 Report, 2004
40%
2004~2OO
2003
FIGURE 3.11. Collective TEDE Distribution by Dose Range
Fuel Cycle Licensees
2000 - 2004
3,3.6 Light-Water-CoodPow
Rtactor ins
LWR licenses are issued to utilities to allow
them to use special nuclear material in a reactor
that produces heat to generate electricity to
be sold to consumers. There are two major
types of commercial LWRs in the United States
- PWRs and BWRs, each of which uses water
as the primary coolant
Table 3.1 shows the number of licensees, total
number of monitored workers, the number
of workers with measurable dose, the total
collective dose, and average dose per worker
for reactor facilities that were in commercial
operation for a full year for each of the years
1995 through 2004. The values do not include
reactors that have been permanently shut down
or reactors that have not been in commercial
operation for a full year. The figures for reactors
NUREG-0713
have been adjusted for the multiple counting of
transient workers (see Section 5).
The reported dose distribution of workers
monitored at each plant site for the year 2004 is
presented in alphabetical order by site name in
Appendix B.
Figure 3.12 shows the collective dose
distribution by dose range (see Section 3.1.8)
for reactor licensees from 2000 to 2004. The
distribution of collective dose has been fairly
constant over the past 5 years, with a slight
decrease noted from 2002 to 2004 in each dose
range.
More detailed presentations and analyses of
the annual exposure information reported by
nuclear power facilities can be found in Sections
4 and 5.
3-20
3-20
B&V-SevexthAnnudReport, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
50%
40%
FIGURE 3.12. Collectie TEDE Distribution by Dose Range
Reactor Licensees
2000-2004
3-21
3-21
NUREG-0713
NUJREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
3.4 SUMMARY OF INTAKE DATA
BY LICENSE CATEGORY
10 CFR 20 requires licensees to report
additional data to the NRC concerning intakes
of radioactive material. Ucensees are required
to list for each intake the radionuclide that was
taken into the body, the pulmonary clearance
class, intake mode, and amount of the intake in
microcuries. An NRC Form 5 report containing
this information is required to be completed and
submitted to the NRC under 10 CFR 20.2206.
Tables 3.7 and 3.8 summarize the intake data
reported to the NRC during 2004. The data are
categorized by licensee type and are listed in
order of radionuclide and pulmonary clearance
class. Table 3.7 lists the intakes where the
mode of intake into the body was recorded as
ingestion or other mode. Table 3.8 lists the
intakes where the mode of intake was inhalation
from ambient airborne radioactive material in
the workplace. The pulmonary clearance class
is recorded as D, W, or Y corresponding to its
clearance half-time in the order of days, weeks,
or years from the pulmonary region of the lung
NUREG-071 3
NUREG-0713
7hirty-SeventhAnnudReport,2004
into the blood and gastrointestinal tract. The
amount of material taken into the body is given
in microcuries, a unit of measure of the quantity
of radioactive material. For each category
of licensee, the maximum number of intake
records and the maximum intake is highlighted
in the table in bold for ease of reference.
Table 3.9 lists the number of individuals with
measurable CEDE, the collective CEDE, and
the average measurable CEDE per individual
for each licensee category. Fuel fabrication
facilities have the majority of internal dose
(93%) in 2004 and the highest average CEDE
per individual. This is due to the worker's
exposure to uranium during the processing and
fabrication of the uranium fuel.
Table 3.10 shows the distribution of internal
dose (CEDE) from 1994 to 2004 for licensees
required to report under 10 CFR 20.2206. For
the purposes of this table, the definition of a
"measurable CEDE" is any reported value
greater than zero. As noted above, the vast
majority of the internal doses is received by
individuals working at fuel fabrication facilities.
3-22
3-22
Occupational Radiation Exposure at NRC Licensed Facilities
iesdFclte
R
cuainlRdanExouea
7hirty-Seventl,Annual Report, 2004
Tiy-Seet Anua Reo-20
TABLE 3.7
Mode of Intake - Ingestion and Other
Radionuclide
and
Type
Licensee
by
Intake
2004
_ 0_G
Ingestion
Power Reactors
41111
41111
41111
41111
41111
41111
41111
41111
41111
AM-241
CM-242
CM-243
CO-58
CO-60
CS-137
PU-238
PU-239
PU-241
5
5
5
4
6
4
5
5
5
0.000
0.000
0.000
0.119
0.778
0.011
0.000
0.000
0.003
3.28E-04
1.26E-06
1.13E-04
1.19E-01
7.78E-01
1.12E-02
2.29E-04
7.79E-05
3.4E-03
NOTE: The data values shown bolded and In boxes represent the highest value In each category.
* An intake event may involve multiple nudides, and Indviduals may incur multiple Intakes during the year. The number of Intake
records given here Indicates the number of separate intake reports that were submitted on NRC Form 5 reports under
10 CFR 20.2206.
A microcurie Is one millionth of a Curie.
3-23
NUREG-071 3
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
7hirty-Seventh Annud Report, 2004
Thiny-Swenth Annual Repors 2004
TABLE 3.8
Intake by Licensee Type and Radionuclide Mode of Intake - Inhalation
2004
Radlophannaceutical
Uranium Enrichment
Fuel Fabrication
-1E
02500
02500
03211
21200
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
21210
21210
21210
21210
I -
I.'to
1-131
NP-237
TC-99
TH-230
U-234
AM-241
CO-58
CO-60
PU-239
RA-224
RN-220
TH-228
TH-228
TH-232
U-232
U-232
U-232
U-234
U-234
U-234
U-234
U-234
U-234
U-235
U-235
U-235
U-235
U-235
U-235
U-236
U-238
U-236
U-238
U-236
U-23f
U-238
U-238
U-238
U-238
U-238
U-238
-- -
3
130
D
W
D
W
D
W
D
1-131
1-131
.A
-
0.077
47.811
0.000
0.000
2.140
0.000
0.042
j
4
I
2
1
9
41
16B
2
48
175
168
112
192
54
166
55
71
273
229
243
305
1,561
80
1.042
191
55
32
932
80
328
191
55
32
304
80
328
229
98
240
818
80
1042
7.70E-02
4.78E+01
1.77E-OR
0.000
0.248
0.2B8
0.001
0.001
2,340.972
0.001
0.000
0.001
0.000
0.000
-
0.000
0.217
0.129
0.058
4.801
0.053
3.686
0.005
0.000
0.000
0.157
0.002
0.068
0.000
0.004
0.001
0.018
0.000
0.022
0.032
0.000
0.002
OA90
0.007
0.553
_
_
2.11E-05
14E-00
8.13E-05
4.20E-02
1.29E-04
2.46E-01
2.68E-01
5.19E-04
6.50E-04
2.34E403
7.88E-04
2.115E-04
9.75E-04
9.02E-05
2.80E-04
3.76E-04
2.17E-01
1.29E+01
5.80E-02
4.80E+00
5.32E-02
3.69E+00
5.24E-03
2.59E-04
5.52E-05
1.57E-01
2.OOE-03
B.80E-02
2.17E-04
3.88E-03
6.90E-04
1.65E-02
8.30E-05
2.19E-02
3.23E-02
9.66E-05
2.32E-03
4.90E-01
7.32E-03
5.53E-01
NOTE: The data values shown bolded and in boxes represent the highest value In each category.
I An intake event may involve multiple nuclides. and individuals may incur multiple intakes during the year. The number of Intake
records given here Indicates the number of separate Intake reports that were submitted on NRC Form 5 reports under 10 CFR 20.2206.
A mirocurie Is one millionth of a Curie.
NUREG-0713
3-24
3-24
Zbirty-Seventh Annud Arport,2004
Occupational Radiation Exposure at NRC Licensed Facilities
TABLE 3.8 (continued)
Intake by Licensce Type and Radionudide Mode of Intake - Inhalation
2004
_
I
n-.-.
M-
ruvwuI Fneau'4a
_.
.
I
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
AM-241
AM-241
BA-140
CM-242
CM-243
CO-58
CO-58
CO-60
CO-60
CO-60
CS-134
CS-137
CS-137
CS-137
FE-55
FE-55
FE-59
FE-59
H-3
H-3
1-130
1-131
1-132
1-133
MN-54
MN-54
NB-95
NB-95
NI-63
NP-237
NP-239
PU-238
PU-238
PU-239
PU-239
PU-240
PU-240
PU-241
PU-241
SR-90
ZN-65
ZR-95
W
Y
D
W
W
Y
Y
Y
W
Y
D
D
Y
D
D
W
D
W
D
V
D
D
D
D
W
Y
W
Y
W
W
W
W
Y
W
Y
W
Y
W
Y
D
Y
W
_.
92
1
1
79
83
51
5
82
1
13
2
47
4
1
7
2
1
1
22
3
1
106
1
2
22
2
1
1
2
1
1
12
71
9
69
1
2
8
14
3
6
2
0.001
0.461
0.270
0.000
0.001
695A13
0.387
710.072
0.078
1.035
0.186
4.632
0.117
0.008
5.306
0.661
0.110
0.220
29.880
347.002
0.021
5.074
0.222
0.634
1.158
912.000
0.044
0.011
0.627
0.000
0.000
0.000
0.001
0.000
0.000
0.000
0.000
0.002
0.003
0.000
0.638
0.143
9.68E-04
4.61E-01
2.70E-01
2.86E-04
6.86E-04
6.95E+02
3.87E-01
7.10E+02
7.80E-02
1.03E+00
1.86E-01
4.63E+00
1.17E-01
8.00E-03
5.31E+00
6.61E-01
1.1OE-01
2.20E-01
2.99E+01
3.47E+02
2.13E-02
5.07E+00
2.22E-01
6.34E-01
1.16E+00
9.12E+02
4.36E-02
1.11E-02
6.27E-01
2.02E-08
4.20E-09
2.28E-04
1.04E-03
5.83E405
4.27E.04
1.40E-04
4.21E-06
2.27E-03
3.50E-03
1.43E-04
6.38E-01
1A3E-O1
IOTE: The data values shown bolded and In boxes represent the highest value in each category.
I An Intake event may Involve multiple nudides, 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 S reports under 10 CFR 20.2206.
A microcurle Is one millionth of a Curie.
3-25
3-25
NUREG-0713
NUREG-0713
I
Thirty-SeventhAnnual Report, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
TABLE 3.9
Collective and Average CEDE by Licensee
2004
Radlopharmaceuticalb
02500
03211
Industrial Radiography
03320
Uranium Enrichment
21200
EASTERN ISOTOPES, INC.
MALUNCKRODT INC.
CARDINAL HEALTH, INC.
CARDINAL HEALTH, INC.
CARDINAL HEALTH, INC.
CARDINAL HEALTH. INC.
INTERNATIONAL ISOTOPES IDAHO INC.
CLEARWATER ENVIRONMENTAL, INC.
U. S. ENRICHMENT CORP. - PADUCAH
U. S. ENRICHMENT CORP. - PORTSMOUTH
10
4
1
2
3
79
5
104
1
1
22
9
45-25221-OlMD
24-04206-1OMO
47-25322-01 MD
13-2B3B7-01MD
13-32053-01MD
04-26507-01MD
11-27680-01
Total
11-27746-01
Total
GDP-1
GDP-2
Total
Fuel Fabrication
21210
BWX TECHNOLOGIES, INC.
FRAMATOME ANP, INC.
FRAMATOME ANP, INC.
GLOBAL NUCLEAR FUEL - AMERICAS, LLC
NUCLEAR FUEL SERVICES, INC.
WESTINGHOUSE ELECTRIC COMPANY LLC
Power Reacton;
41111
BEAVER VALLEY
BIG ROCK POINT
BRAIDWOOD
BROWNS FERRY
BRUNSWICK
CALLAWAY
CALVERT CLIFFS
CLINTON
COLUMBIA GENERATING
DIABLO CANYON
DRESDEN
FITZPATRICK
GINNA
HADDAM NECK
HUMBOLDT BAY
LASALLE
LIMERICK
MAINE YANKEE
MILLSTONE 1
NINE MILE POINT
OCONEE
OYSTER CREEK
PALISADES
PALO VERDE
PEACH BOTTOM
QUAD CITIES
RIVER BEND
ROBINSON
SAN ONOFRE
SEQUOYAH
ST. LUCIE
SURRY
SUSQUEHANNA
VERMONT YANKEE
VOGTLE
WATTS BAR
SNM-0042
SNM-1168
SNM-1227
SNM-1097
SNM-0124
SNM-1107
Total
DPR-66
DPR-06
NPF-72
DPR-33
OPR-62
NPF-30
DPR-53
DPF-62
NPF-21
DPR-80
DPR-19
DPR-59
DPR-18
DPR-61
DPR-07
NPF-11
NPF-39
DPR-3B
DPR-21
OPR-63
DPR-38
DPR-16
DPR-20
NPF-41
DPR44
DPR-29
NPF-47
DPR-23
DPR-13
DPR-77
DPR-87
DPR-32
NPF-14
DPR-28
NPF-68
NPF-90
Total
I
Grand Totals
NUREG-0713
3-26
0.049
1.358
0.045
0.045
0.107
0.047
0.002
0.030
0.006
0.011
0.004
0.014
0.010
0.013
0.045
0.045
0.005
0.005
0.019
0.121
0.006
0.021
0.011
1
.1.131
31
0.1U4
0.005
252
82
261
592
725
384
24.603
6.121
54.763
57.840
13.194
99.148
0.098
0.075
0.210
0.098
0.018
0.258
2,296
255.669
0.111
3
1
2
593
1
49
4
7
1
4
7
2
2
13
3
1
3
2
3
7
65
2
1
4
1
2
8
1
28
56
14
1
3
23
2
173
1,092
0.032
0.016
0.022
13.367
0.015
0.130
0.074
0.159
0.007
0.069
0.091
0.040
0.081
0.439
0.035
0.011
0.012
0.005
0.153
0.114
1.094
0.037
0.023
0.040
0.014
0.024
0.118
0.022
0.0131
0.093
0.090
0.011
0.026
0.178
0.022
0.585
17.380
0.011
0.016
0.011
0.023
0.015
0.003
0.019
0.023
0.007
0.017
0.013
0.020
0.041
0.034
0.012
0.011
0.004
0.003
0.0S1
0.016
0.017
0.019
0.023
0.010
0.014
0.012
0.015
0.022
0.005
0.002
0.006
0.011
0.009
0.008
0.011
0.003
0.016
3,524
274.606
0.078
Occupational Radiation Exposure at NRC Licensed Facilities
7hirty-Seventh Annud Report, 2004
TABLE 3.10
(CEDE) Distribution
Dose
Internal
1994-2004
..
S
S
S
tit"
mm=g~.
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
3,425
2,868
3,096
3,835
3,310
3,399
3,248
1,767
1,759
2,208
1,987
577
691
598
869
932
630
891
766
739
727
738
287
338
305
381
426
402
514
572
555
572
440
351
362
317
366
355
425
373
277
370
271
252
196
216
190
242
230
206
214
109
95
98
90
138
145
121
148
140
117
98
51
20
13
14
293
288
185
169
153
173
224
146
23
4
3
69
49
22
30
21
29
58
82
3
3-27
2
2
2
-
2
-
-
2
-
-
-
7
15
1
1
-
-
-
-
-
-
-
-
5,338
4,959
4,838
6,040
5,569
5,381
5.628
3,786
3,564
3,893
3,524
1.033.688
1,019.045
741.373
826.280
779.148
792.586
969.792
810.128
377.016
311.641
274.606
0.194
0.205
0.153
0.137
0.140
0.147
0.172
0.214
0.106
0.080
0.078
NUREG-071 3
NUREG-0713
Section 4
COMMERCIAL LIGHT WATER
REACTORS -FURTHER ANALYSIS
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 inTables 4.1,
4.2, and 4.3 is the number of BWRs, PWRs,
and LWRs, respectively, that had been in
commercial operation for at least 1 full year as
of December 31 of each of the indicated years.
This is the number of reactors on which the
average number of workers with measurable
dose and average collective dose per reactor is
based. Excluded are reactors that have been in
commercial operation for less than 12 months
during the first year and reactors that have been
permanently defueled. This yields conservative
values for many of the averages shown in the
tables. The date that each reactor was declared
to be incommercial operation was taken from
Ref. 12.
Three Mile Island (TMI) 2 was included in the
compilation of data for commercially operating
reactors through 1988, even though the reactor
was shut down following the 1979 accident,
since TMI 2 was in the process of defueling and
decommissioning during those years. TMI 2
has not been included in the data analysis since
1988. Data for this reactor, however, will be listed
in Appendix B for reference purposes. The dose
data presented in Appendix D for TMI include the
dose data for Unit 2 priorto 1986.
There were no changes to the count of
operating reactors in 2004. The number of
operating BWRs remains the same as in 2003
at 35 and the number of operating PWRs
remains the same at 69. The dose information
for these reactors and others that are no longer
in commercial operation is listed at the end of
Appendix B.
4.2.2 Electrk Ener=y Generated
The electric energy generated in megawatt
years (MW-yr) each year by each reactor is
graphically represented in Appendix D. This
number was obtained by dividing the megawatt
hours of electricity annually produced by each
facility by 8,760, the number of hours in the
year, except for leap years, when the number
is 8,784 hours. For the years 1973 to 1996,
the electricity generated is the gross electricity
output of the reactor. For 1997 to 2004, the
number reflects the net electricity produced,
4-1
4-1
NUREG-071 3
NUREG-0713
0
TABLE 4.1
Summary of Information Reported by Commercial Boiling Water Reactors
1973-2004
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1988
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
12
14
18
22
23
25
25
26
26
26
26
27
29
4,564
7,095
12,633
12.298
19,054
15,257
18,251
29,472
25,490
24,447
27,487
27,111
20,578
5,340
8,769
17,350
16,927
21,515
20,381
25,425
34,220
34,873
32,318
33,581
41,315
38,338
3,393.9
4,060.2
5,788.4
8,137.9
9,102.5
11,858.0
11,671.0
10,868.2
10,899.2
10,614.6
9,730.1
10,019.2
12,284.0
0.86
0.81
0.73
0.73
0.89
0.75
0.72
0.88
0.73
0.76
0.82
0.68
0.54
380
507
702
559
828
610
730
1,134
980
940
1,058
1,004
710
445
628
964
769
935
815
1,017
1,316
1,341
1,243
1,292
1,530
1,322
1.35
1.75
2.18
1.51
2.09
1.29
1.58
2.71
2.34
2.30
2.82
2.71
1.68
283
290
321
370
396
474
487
418
419
408
374
371
424
438
485
595
630
637
680
660
883
683
683
683
754
775
65%
60%
54%
59%
62%
72%z
71%
63%
63%
62%
56%
49%
55%
32
34
38
37
37
37
37
37
37
37
37
38
35
35
35
35
35
35
16,722
17,988
15,550
15,781
12,007
13,312
12,221
12,098
9,471
9,486
7,603
6,829
6,434
6,090
4,835
6,108
5,659
5,451
41,806
40,371
44,384
41,585
38,508
42,107
39,352
39,171
35,686
37,792
34,021
32,899
31,482
31,188
28,797
30,978
30,759
33,948
15,109.0
16,685.4
17,543.5
21,338.1
21,505.8
20,592.2
21,995.6
22,139.0
24,737.0
24,322.2
22,888.1
23,781.2
26,962.6
28,476.9
28,730.4
29,480.0
29,094.4
29,424.8
0.40
0.45
0.35
0.38
0.31
0.32
0.31
0.31
0.27
0.25
0.22
0.21
0.20
0.20
0.17
0.20
0.18
0.16
523
529
432
427
325
380
330
327
258
256
205
190
184
174
138
175
162
156
1,306
1,187
1,233
1,124
1,041
1,138
1,064
1,059
964
1,021
919
914
899
891
823
885
879
970
1.11
1.08
0.89
0.74
0.58
0.5
0.56
0.5
0.38
0.39
0.33
0.29
0.24
0.21
0.17
0.21
0.19
0.19
472
490
487
577
581
557
594
598
689
657
618
681
770
814
821
842
831
841
832
845
857
882
880
859
798
801
835
838
845
874
885
893
895
907
912
893
57%
58%
57%
87%
68%
65%
74%
75%
80%
78%
73%
76%
87%
91%
92%
93%
91%
68%
30
19,353
37,999
12,102.1
0.51
645
1,267
1.60
least one fu year as of Decenber 31 of each of the indicated years.
includes only ftho reactos ftht had been incommnercial operation for at (se0
Sec3ion 5).
of tansient individuals
19F2ures are not adjus2edfor the muilerepo
gross eSIcM y germae for tbe yea 1via -1 i . weginning In i i, it rets me net eodeicily generaed.
r ienbad reflects hMe
ecWcCty
-
403
788
51%
'
I
a
TABLE 4.2
Summary of Information Reported by Commercial Pressurized Water Reactors
1973-2004
__
5
_f
'1,.***._
_
_~~~~.
i
S.
.T
__
a
a
l
l
s
rph11.Anaa,,.JX19:m111,IJfl,,_
z
0:
-.
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
12
19
26
30
34
39
42
42
44
48
49
51
53
60
64
68
71
73
74
73
69
70
70
72
72
69
69
69
69
69
69
69
9,398
6,555
8,268
13,807
13,467
16,528
21,657
24,267
28,673
27,754
29,017
28,140
22,470
23,033
23,684
22,786
20,381
20,821
16,512
15,985
13,376
9,574
11,762
9,417
9,546
6,358
7,231
6,562
6,273
6,018
6,296
4,917
.
L.
9,440
9,370
10,884
17,588
20,878
25,700
38,828
46,237
47,351
52,149
52,170
56,994
54,632
62,998
62,597
62,923
63,894
67,082
60,274
61,048
54,397
44,283
49,985
46,852
50,690
38,586
43,938
42,922
38,773
42,264
44,054
35,901
3,770.2
6,530.7
11,982.5
13,325.0
17,345.8
19,840.5
18,255.0
18,289.3
20,553.7
22,140.6
23,195.5
26,478.4
29,470.7
33,593.0
37,007.3
42,929.7
44,679.5
46,955.6
51,942.6
J.
53,419.8
48,709.3
52,397.6
54,138.2
55,337.8
48,985.3
53,288.7
56,235.0
57,529.9
58,822.4
59,369.7
57,920.6
60,398.7
L
1.00
0.70
0.76
0.79
0.65
0.64
0.56
0.53
0.61
0.53
0.56
0.49
0.41
0.37
0.38
0.38
0.32
0.31
0.27
0.26
0.25
0.22
0.24
0.20
0.19
0.17
0.17
0.15
0.16
0.14
0.14
0.14
J
783
345
318
460
398
424
518
578
652
578
592
552
424
384
370
335
287
285
223
219
194
137
168
131
133
92
105
95
91
87
91
71
787
493
419
586
614
659
924
1,101
1,076
1,086
1,065
1,118
1,031
1,050
978
925
900
919
815
836
788
633
714
651
704
559
637
622
562
613
638
520
J.
2.49
1.00
0.69
1.04
0.78
0.83
1.19
1.33
1.40
1.25
1.25
1.06
0.76
0.69
0.64
0.53
0.46
0.44
0.32
0.30
0.28
0.18
0.22
0.17
0.20
0.12
0.13
0.11
0.11
0.10
0.11
0.08
* Incds onl those reactors that had been in commercial oeratin for at lat one h year as of December 31 of each of the Indicated years.
-Figures are not adjusted for te mulpe report
d transbent indtsduals (see Secton 5).
-Ekectity
~
a~
...
I
;.._
Generated reflects th gross elecricity generated for the years 1973.- 1996. Beginning In 19g7, I renlects the net electricity generted.
314
344
461
444
510
509
435
435
467
461
473
519
556
560
578
631
629
643
702
732
706
749
773
769
680
772
815
834
852
860
839
875
x
l
l
*1,.uJ,,ra.Ia-,-
-l
544
591
647
701
688
706
746
746
752
m
785
809
820
878
900
885
897
907
913
923
941
928
929
935
943
942
942
943
946
947
949
943
i
h
;_.
l
_I.}8l
:X
58%
58%
71%
63%
74%
72%
58%
58%
62%
59%
60%
64%
68%
64%
64%
71%
70%
71%
77%
79%
75%
81%
83%
82%
72%
82%
86%
88%
90%
91%
88%
93%
t
0
k
a
U
SI
0
MI-
I
2a.
I.
p
z
E
v
_______________
t
I
0
TABLE 4.3
Summary of Infornation Reported by Commercial Light Water Reactors
1973-2004
EEME__E__hhhh__.:
_
I,
F
09
N
*___
0
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
24
33
44
52
57
64
67
68
70
74
75
78
82
90
96
102
107
110
111
110
106
107
107
109
109
105
104
104
104
104
104
104
13,962
13,650
20,901
26,105
32,521
31,785
39,908
53,739
54,163
52,201
56,484
55,251
43,048
42,386
40,406
40,772
35,931
36,602
28,519
29,297
25,597
21,672
21,233
18,883
17,149
13,187
13,666
12,652
11,109
12,126
11,956
10,368
14,780
18,139
28,234
34,515
42,393
46,081
64,253
80,457
82,224
84,467
85,751
98,309
92,968
100,997
104,403
103,294
108,278
108,667
98,782
103,155
93,749
83,454
85,671
84,644
84,711
71,485
75,420
74,108
67,570
73,242
74,813
69,849
7,164.1
10,590.9
17,768.9
21,462.9
26,448.3
31,696.5
29,926.0
29,157.5
31,452.9
32,755.2
32,925.6
36,497.6
41,754.7
45,695.1
52,116.3
59,595.1
62,223.0
68,291.7
73,448.4
74,012.0
70,704.9
74,536.6
78,875.2
79,660.0
71,851.4
77,069.9
83,197.6
86,006.8
87,552.8
88,829.7
87,015.0
89,823.5
0.95
0.75
0.74
0.76
0.77
0.69
0.62
0.67
0.66
0.62
0.66
0.56
0.46
0.42
0.39
0.40
0.33
0.34
0.29
0.28
0.27
0.26
0.25
0.22
0.20
0.18
0.18
0.17
0.16
0.17
0.16
0.15
582
414
475
502
571
497
596
790
774
705
753
708
525
471
421
400
336
333
257
266
241
203
198
173
157
126
131
122
107
117
115
100
616
550
642
664
744
720
959
1,183
1,175
1,141
1,143
1,260
1,134
1,122
1,088
1,013
1,012
988
890
938
884
780
801
777
777
681
725
713
650
704
719
672
1.95
1.29
1.18
1.22
1.23
1.00
1.33
1.84
1.72
1.59
1.72
1.51
1.03
0.93
0.78
0.68
0.58
0.54
0.39
0.40
0.36
0.29
0.27
0.24
0.24
0.17
0.16
0.15
0.13
0.14
0.14
0.12
Includes onl those reactors that had been incommercial operation for at east one fullyearas of December 31 of each of the indicatd years.
Ir
the rnultipb repotting o transient dividuals (see Section 5).
Figures are not adjusted
generted.
Electricity Generated relcsthe gross electricity generated for the yearn 1973- 1996. Beginning In 1997, it reflects the neteectricity
299
321
404
413
464
495
447
429
449
443
439
468
509
508
543
584
582
621
662
673
667
697
737
731
659
734
800
827
842
854
837
864
491
546
626
671
667
688
714
714
719
737
743
790
804
847
877
871
883
892
895
901
891
884
896
902
910
918
923
926
929
934
936
926
61%
59%
65%
62%
70%
72%
63%
60%
63%
60%
59%
59%
63%
60%
62%
67%
66%
70%
74%
75%
75%
79%
82%
81%
72%
80%
87%
89%h
91%
91%
89%
93%
o
N
zP(0N
I
a
P.
z
In
h
7hirty-Seventh Annud Report, 2004
Thirty-&venth Annual Report; 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
which is the gross electricity minus the amount
the plant uses for operations. This change is
the result of a change in NRC power generation
reporting requirements. The electricity
generated (in MW-yrs) that is presented in
Tables 4.1, 4.2, and 4.3 is the summation of
electricity generated by the number of reactors
included in each year. These sums are divided
by the number of operating reactors included
in each year to yield the average amount of
electric energy generated per reactor, which
is also shown in Tables 4.1, 4.2, and 4.3.
The number of megawatt hours of electricity
produced each year was obtained from Ref. 12.
As shown in Table 4.3, there was a 3% increase
in the net electricity generated at LWRs in 2004.
Contributors to this increase included Davis
Besse (restarted), South Texas, Surry, and
Cook for PWRs and Cooper Station and Duane
Arnold for BWRs. These plants had increases
of over 20% in power production from 2003 to
2004.
4.2.3 Collective Dose per-Megawatt-Year
The number of MW-yrs of electricity generated
was used in determining the ratio of the average
value of the annual collective dose (TEDE) to
the number of MW-yrs of electricity generated.
The ratio was calculated by dividing the total
collective dose in person-rem by the electric
energy generated in MW-yrs and is a measure
of the dose incurred by workers at power plants
in relation to the electric energy produced.
For the years 1973 to 1996, the electricity
generated is the gross electricity output of
the reactor. For 1997 to 2004, the number
reflects the net electricity produced. This ratio,
calculated by year for BWRs, PWRs, and
LWRs, is presented in Tables 4.1, 4.2, and 4.3.
This ratio was also calculated for each reactor
site (see Appendix C). The average collective
dose per MW-yr for LWRs decreased to a value
of 0.12 rem/MW-yr in 2004 from a value of 0.14
rem/MW-yr in 2003 due to a combination of the
reduction in the collective dose and an increase
in power production.
4.2.4 Average Maximum Depnb
Average maximum dependable capacity as
shown in Tables 4.1, 4.2, and 4.3 was found
by dividing the sum of the net maximum
dependable capacities of the reactors in
megawatts (net MWe) by the number of
reactors included each year. The net maximum
dependable capacity is defined as the gross
electrical output as measured at the outputterminals of the turbine generator during the
most restrictive seasonal conditions less the
normal station service loads. This "capacity" of
each plant was found in Ref. 12.
4.2.5 Percent ofMaximurm Dependabk
Capacity Achieved
The percent of maximum dependable capacity
achieved is shown for all LWRs in Table 4.3.
This parameter gives an indication of the
overall power generation performance of LWRs
as compared to the maximum dependable
capacity that could be obtained in a given year.
It is calculated by dividing the average electricity
generated per reactor by the average maximum
dependable capacity for each year.
4-5
4-5
UREG071
NUnREG-0713
-
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Raicliation Exposure at NRC Licensed Facilities
From 1973 to 1978 this indicator exhibited
an increasing trend as a number of new
reactors began producing power at higher
efficiencies. Following the accident at TMI,
reactor operations personnel concentrated on
improving safety systems and complying with
the new regulations for these systems. During
this time period, from 1979 to 1987, the percent
of maximum dependable capacity remained
around 61%. Following the completion of most
of these mandated repairs, reactors increased
the percent of maximum dependable capacity
from 62% in 1987 to 81% in 1996, a gain of
nearly 20% in 10 years. The decrease in
maximum dependable capacity from 1996 to
1997 was due to the change from measuring
the gross electricity generated to the net
electricity generated. The percent of maximum
dependable capacity has continued to increase
since 1997 to an all-time high of 93% in 2004.
NUREG-0713
NUREG-0713
7hirty-SeventhAnnud Report, 2004
Thirty-Seventh Annual Repori. 2004
4.3 ANNUAL TEDE
DISTRIBUTIONS
Table 4.4 summarizes the distribution of the
annual TEDE doses received by workers at
all commercial LWRs during each of the years
1977 through 2004. This distribution is the sum
of the annual dose distributions reported by
each licensed LWR each year. As previously
noted, the distribution reported by each LWR
site for 2004 is shown in Appendix B. Table 4A
shows the reported dose distributions corrected
for the number of transient workers that were
reported by more than one site (see Section 5).
Table 4.4 includes only those reactors in
operation for a full year for each year presented
in the table. The total collective dose decreased
by 13% to a value of 10,368 person-rem in
2004. The PWRs with the largest decreases
in the collective dose were Sequoyah, Davis
Besse, and Surry. San Onofre experienced
the highest increase in collective dose among
PWRs. The BWRs with the largest decreases
in the collective dose were Perry and Pilgrim.
Clinton experienced the highest increase in
collective dose among BWRs.
4-6
4-6
4
TABLE 4.4
Summary Distribution ofAnnual Whole Body Doses at Commercial Light Water Reactors*
1977-2004
*
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
22,688
26.360
40.535
44,716
39,258
41,704
47,027
54,637
59,625
67,677
85,170
87,281
83,954
83,875
87,247
87,717
83,068
67.777
61,445
58,097
58.409
56,901
54,885
53,324
52,636
53,440
54.023
57,417
12,436
15,165
22,642
26,990
26,916
29,278
29,200
36,488
36,920
41,536
41,283
40,290
45,302
42,612
42,603
41,943
37,332
30.185
29,631
30,204
31,955
27,998
29,048
28.480
27,246
28,523
29,164
28s863
15,010
15,096
14,831
14,890
12,849
13,184
12,921
11,491
11,610
11,978
11,179
h
U-
9
6,056
6,349
9,012
10,697
11,241
11,734
11,200
13,438
13,015
14,574
15,842
15,915
17,270
17,526
16,770
17,821
17,235
a
4,538 2,905
5,010 3,094
7,485 4,795
8,913 5,573
9,338 6,051
9,907 6,235
9,345 5.854
10,277 6,338
11,044 6,626
11,842 7,017
12,838 7,586
13,152 7,905
13,778 7,944
14,199 8,226
13,182 7,188
14,779 8,135
13,734 7,562
11,823 6,185
12,023 6,125
11,343 5,423
10,913 5,233
8,816 3,940
8,949 3,793
8,679 3,571
7,659 2,907
7,668 3,004
8,199 3,249
7,334 2,873
2,230
2,255
3,262
4,139
4.501
4,422
4,279
4,804
4,545
4,893
5,333
5,461
5,138
5,261
4,192
4,521
4,289
3,620
3,304
2,833
2,455
1,841
1,900
1,644
1,323
1,479
1,524
1,233
t
5,660 2,858
5,984 3,050
7,574 3,401
10,672 4.607
11,174 4,809
10,220 4,716
11,342 5,334
11,284 5,208
10,042 3,574
10,241 3,062
10,611 2,192
10,310 2,442
8,633 1,615
8,594 1,791
938
5,977
6,076
808
5,322
638
4,242
508
3,912
595
3,196
408
2,599
286
1,827
179
1,894
245
1,734
188
1,392
221
1,820
320
1,651
184
1,190
188
1,290
1,194
1,403
1,816
1,999
2,068
2.270
2,122
1.002
868
477
511
370
337
219
85
76
40
133
67
41
15
18
18
53
35
18
13
661
517
545
831
533
596
716
487
157
146
69
26
34
21
17
89
37
42
119
93
31
38
22
186
110
117
235
103
97
121
52
47
23
9
17
29
9
5
3
7
3
8
2
I
I
4
5
2
1
I
61,673
69,137
100,834
119,345
116,030
121,013
126,736
145,157
146.551
161,656
181,401
183,294
184,038
182,442
178,333
181,889
189,259
139,390
132,266
126,402
126,781
114,367
113,916
110,557
104,928
107,900
109,990
110,290
42,777
60,299
74,629
76,772
79,309
79,709
90,520
86,926
93,979
96,231
96,013
100,084
98,567
91,086
94,172
86,193
71,613
70,821
.
. for. at least. I full.yeras of December31
* Summary of reports submitted In accordance with 10 CFR 20.407 or 20.2206 by BWRs and PWRs that had been In commercial operation
.
.
.
l
32,521
31,785
39,908
53,739
54,163
52,201
56.484
55,251
43,048
42,386
40,406
40,772
35,931
36,602
28,519
29,297
26,384
21,704
21,688
18,883
17,149
13,187
13,599
12,652
11,109
12,126
11,956
10,368
38,985
68,305
68,372
57,466
59,031
57,233
52,292
54,460
55,967
52,873
.
.
0
k
0
z
F
1:I
I
i
P.
z
9
V
E
of each of the indicoted
yem. Figure. shown hae 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 desacibed In Section 3.1.4.
a-
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
4.4 AVERAGE ANNUAL
TEDE DOSES
Some of the data presented in Tables 4.1, 4.2,
and 4.3 are graphically displayed in Figure 4.1,
where it can be seen that the average collective
dose and average number of workers per BWR
have been higher than those for PWRs since
1974 and that the values of both parameters,
in general, continued to rise at both types
of facilities until 1983. Between 1983 and
2004, the average collective dose per LWR
dropped by 87%. Between 2003 and 2004, the
collective dose per reactor for PWRs decreased
by 22% to 71 person-rem. The collective dose
per reactor for BWRs decreased by 4% to 156
person-rem from 2003 to 2004. The overall
collective dose per reactor for LWRs decreased
by 13% to 100 person-rem in 2004. This is
the lowest average LWR dose per reactor
ever recorded. The number of workers with
measurable dose per reactor increased to 970
for BWRs and decreased to 520 for PWRs in
2004. The overall decreasing trend in average
reactor collective doses since 1983 indicates
that licensees are continuing to successfully
implement ALARA dose reduction features at
their facilities.
NUREG-0713
NUREG40713
Mrly-SeventhAnnudReport,2004
Thirty-Seventh Annual Repori 2004
Figures 4.2 and 4.3 are plots of most of the
other information that is given in Tables 4.1,
4.2, and 4.3. Figure 4.2 shows that in 2004
the net electricity generated increased to
89,824 MW-yr while the number of operating
reactors has remained constant for the past 6
years. The value for the total collective dose
for all LWRs decreased by 13% from a value of
11,956 person-rem in 2003 to 10,368 personrem in 2004. Together with the decrease in
the number of workers with measurable dose,
this resulted in the average measurable dose
per worker decreasing from 0.16 rem in 2003
to 0.15 rem in 2004 (when not adjusted for
transient workers).
The fluctuations in the parameters for the
years following the accident at the TMI plant in
1979 may reflect some of the impact that this
incident had on the nuclear power industry. The
decrease seen in dose trends since 1983 may
be attributable to several factors. Utilities have
completed most of the tasks initiated as a result
of the lessons learned from the TMI accident,
and they are increasing efforts to avoid and
reduce exposure. The importance of exposure
control and the concept of keeping exposures
to ALARA levels is continually being stressed,
and most utilities have established programs to
collect and share information relative to tasks,
techniques, and exposures.
4-8
4-8
7hirty-Seventh Annud Report, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Average Annual Collective Dose
1200
I
0
0
Im
U
mg a:
E:9
SiiiI: 9 8 9 I I« I I 9 I I I $ g I Af I I g I I I - I I A
-
r-
-
-
--
-
-
-
-
-
-
-
-
-
Year
Average Annual Number of Workers with Measurable Dose
I.
0
L
U!
9 a9I
S I 9 1 8- 9 I I I I 9 I I I § I I fI I I k I I ICJ ('- I I A
-
----
-
-
-
-
-
-
14
Year
FIGURE 4.1. Average Collective Dose and Number of Workers
with Measurable Dose per Reactor
1973-2004
4-9
NUREG-0713
Mbrty-SeventhAnnul Report, 2004
Thirsy-SeventbAnnuaiAepors 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
Number of Operating Reactors
n
0!
5
2
PWR1g
90
1
SI::
2
ne
o30i
r
Is
r-
Year
Electrfcit Generated*
sa
9
9
I2
i N
I9 I
Ia I I
§ §
a i
I
I
t I I I A
Year
IGrsso
ecbtidty 1973-196
w escb fo 1W-20.
FIGURE4.2. Number of Operating Reactors and Gross Electricity Generated
1973-2004
NUREG-0713
4-10
4-10
7hirty-Seventh Annual Report,2004
Thiray-Seventh Annual Repon 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
Average Measurable Dose per Worker
1.0
E-09
- 0.8
I 0.7
0
9 0.7
.0
110.5
U
E 0.3
0.4
0C0.3
1!
_ 9 9
S 9 I IR i I I IE I} I 9 IE I I § I I
I I I k I I I
I I AY
Year
Collective Dose per Megawatt-Year*
2.8-……-
WR
2.6-…-
1.2.42.26m_
……
-
…-
PWl
LWR
2.0
.
.
.
0
a
I
I
.5
0
_ U
Year
Goss uledrldcay 1973-1996, nel ecdty for 19-2004.
FIGURE 4.3. Average Measurable Dose per Worker and Collective Dose per Megawatt-Year
1973-2004
4-11
4-11
NUREG-071 3
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
xosr tNCliesdFcliisTi~-See
OcuainlRaito
To further assist in the identification of any
trends that might exist, Figures 4.4 and 4.5
together display the average and median7
values of the collective dose per reactor for
BWRs and for PWRs for the years 1973
through 2004. The ranges of the values
reported each year are shown by the vertical
lines with a small bar at each end marking
the two extreme values. The rectangles
indicate the range of values of the collective
dose exhibited by those plants ranked in the
25th through the 75th percentiles. Because
the median values usually are not as greatly
affected by the extreme values of the collective
doses, they do not normally fluctuate as
much from year to year as do the average
values. The median collective dose for PWRs
decreased to 65 person-rem in 2004. At BWRs,
the median fluctuates more from year to year.
The median collective dose decreased from
169 person-rem in 2003 to 158 person-rem in
2004. Figure 4.5 also shows that, in 2004, 50%
of the PWRs reported collective doses between
47 and 78 person-rem, while 50% of the BWRs
reported collective doses between 90 and 224
person-rem. Nearly every year the median
collective dose is less than the average, which
indicates that the collective dose for most plants
is less than the average collective dose per
reactor (the value that is widely quoted).
T
Mrty-SeventbAnnud Report,2004
AnulRpot,20
4.5 THREE-YEAR AVERAGE
COLLECTIVE TEDE PER
REACTOR
The 3-year average collective dose per reactor
is one of the metrics that the NRC uses in the
Reactor Oversight Program to evaluate the
effectiveness of the licensee's ALARA program.
Tables 4.5 and 4.6 list the sites that had been
in commercial operation for at least 3 years as
of December 31, 2004, and show the values
of several parameters for each of the sites.
They also give averages for the two types of
reactors. Based on the 105 reactor-years of
operation accumulated by the 35 BWRs listed,
the average 3-year collective TEDE per reactor
was found to be 164 person-rem, the average
measurable TEDE per worker was 0.18 rem,
and the average collective TEDE per MW-yr
was 0.21 person-rem per MW-yr. The average
3-year collective TEDE per reactor and the
average collective TEDE per MW-yr increased
from 2003 to 2004, while the average
measurable TEDE per worker remained the
same.
Based on the 207 reactor-years of operation
at the 69 PWRs listed, the average annual
collective TEDE per reactor, average
measurable TEDE per worker, and average
collective TEDE per MW-yr were found to be
83 person-rem, 0.14 rem, and 0.10 personrem per MW-yr, respectively. All three values
decreased from the previous 3-year period.
The value at which 50% of the reactors reported greater collective doses and the other 50% reported smaller collective doses.
NUREG-0713
NUREG-0713
4-12
4-12
Occupational Radiation Exposure at NRC Licensed Facilities
7birty-Seventh Annual Report,2004
-4000
0
3500
300
23000
100
10.
2500
Mn
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
Year
FIGURE 4.4. Average, Median, and Extreme Values of the Collective Dose per Reactor
1973- 1986
4-13
4-13~~
_UE-7 3
NUREG-0713
7Urty-Seventh An nud Rep ort,2004
Thir*y-Seventh Annual RIpors 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
low
* Middl 50% d BWRs
Cl MonesoofPWR
1400T
[S Average Cofleclive Dose
@ Median Collecflve Dose
1200
I
I
-
--- T
1uuu
800
T
X 4TT
I
600
I
!U
400
l
,.. fee
|
200
0
198 ff
1988
1989
1990
1991
199
199
1994 1995
1996
1997
1998
1999
20XO
2001
200
2003
2004
Year
FIGURE 4.5. Average, Median, and Extreme Values of the Collective Dose per Reactor
1987-2004
NUREG-0713
NUREG-0713
4-14
4-14
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
7birty-Seventh Annud Report,2004
7hirty-&venth Arnusal Report 2004
TABLE 4.5
Three-Year Totals and Averages Listed in Ascending Order of Collective TEDE per BWR
2002-2004
DUANE ARNOLD
3
59
178
1,368
0.13
2,473.5
0.07
COOPER STATION
3
74
221
1,725
0.13
2,062.1
0.11
LIMERICK 1,2
6
76
457
3,811
0.12
4,410A
0.10
MONTICELLO
3
81
244
1,536
0.16
2645.7
0.09
HATCH 1,2
6
94
563
3,803
0.15
3,894.4
0.14
COLUMBIA GENERATING
3
106
318
2,981
0.11
4,058.9
0.08
PILGRIM
3
110
330
2,327
0.14
2,135.7
0.15
FERMI 2
3
117
351
2,972
0.12
2,719.4
0.13
GRAND GULF
3
122
366
2,593
0.14
2,386.4
0.15
BRUNSWICK 1,2
6
128
769
5,677
0.14
4,935.8
0.16
SUSQUEHANNA 1,2
6
130
782
5,968
0.13
4,852.0
0.16
HOPE CREEK 1
3
135
405
4,257
0.10
1,833.3
0.22
VERMONTYANKEE
3
139
416
2,684
0.16
3,157.7
0.13
FITZPATRICK
3
156
468
2,623
0.18
2,007.3
0.23
0.18
PEACH BOTTOM 2,3
6
159
954
4,978
0.19
5,341.2
RIVER BEND 1
3
163
488
3,047
0.16
2,489.5
0.20
OYSTER CREEK
3
179
536
3,230
0.17
1,779.8
0.30
7,827
0.21
6,187.9
0.26
6,961
0.16
3,664.0
0.30
BROWNS FERRY 1,2,3**
9
181
1,633
DRESDEN 2,3
6
182
1,093
CLINTON
3
183
548
3,412
0.16
2,773.1
0.20
LASALLE 1,2
6
212
1,273
6,631
0.19
6.359.5
0.20
NINE MILE POINT 1,2
6
223
1,340
5,312
0.25
4,787.8
0.28
PERRY
3
250
751
2,812
0.27
2,785.4
0.27
QUAD CITIES 1,2
6
456
2,735
7,150
0.38
2,965.8
0.92
*105
1
1 82,706_.6
0.21
Totals and Averages
Averages per Reactor-Yr
164
71
,r218
1
I
I
95,685
1
0.18
oil
I
0
787.7
* Sites where not all reactors had completed 3 full years of commercial operation as of 12131/04 are not included.
Browns Ferry I remains in the count of operating reactors, but was placed on Administrative Hold in June of 1985.
4-15
NUREG-0713
NUREG-0713
irty-Seent Annual Report, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
TABLE 4.8
Three-Year Totals and Averages Listed in Ascending Order of Collective TEDE per PWR
2002-2004
_=_
INDIAN POINT 3
HARRIS
CRYSTAL RIVER 3
SUMMER 1
SEABROOK
FARLEY 1.2
GINNA
THREE MILE ISLAND 1
PRAIRIE ISLAND 1,2
KEWAUNEE
PALO VERDE 1,2,3
BYRON 1.2
POINT BEACH 1,2
WOLF CREEK 1
VOGTLE 1,2
WATERFORD 3
CATAWBA 1,2
COMANCHE PEAK 1,2
BRAIDWOOD 1,2
TURKEY POINT 3,4
MCGUIRE 1,2
CALLAWAY 1
ST. LUCIE 1,2
NORTH ANNA 1,2
ROBINSON 2
ARKANSAS 1,2
BEAVER VALLEY 1,2
WATTS BAR 1
SURRY 1,2
DIABLO CANYON 1,2
OCONEE 1,2,3
SALEM 1,2
SOUTH TEXAS 1,2
SEQUOYAH 1,2
COOK 1,2
CALVERT CLIFFS 1,2
SAN ONOFRE 2,3
MILLSTONE 2,3
FORT CALHOUN
INDIAN POINT 2
PALISADES
DAVIS-BESSE
Totals and Averages
Averages per Reactor-Yr
3
3
3
3
3
6
3
3
6
3
9
6
6
3
6
3
6
6
6
6
6
3
6
6
3
6
6
3
6
6
9
6
6
6
6
6
6
6
3
3
3
3
207
107
132
136
141
143
315
162
165
333
169
550
371
375
192
409
207
415
427
431
438
448
225
457
460
234
471
524
265
533
539
838
565
592
625
644
654
707
752
398
456
598
629
17,231
36
44
45
47
48
52
54
55
55
56
61
62
63
64
68
69
69
71
72
73
75
75
76
77
78
78
87
88
89
90
93
94
99
104
107
109
118
125
133
152
199
210
j
_
83
1_
j
1,292
1,678
1,220
1,630
2,387
2,701
1,156
1.507
2,749
1,106
4,610
3,017
2,199
1,729
2.723
1,581
3,416
2,609
3,533
3,324
3,124
2,359
3,088
2,920
1,891
3,781
3,941
2,521
3,455
3,250
6,198
5,257
3,261
4,902
4,047
4,458
4,176
3,625
1,871
2,738
2,020
3,191
122,219
590
0.08
0.08
0.11
0.09
0.06
0.12
0.14
0.11
0.12
0.15
0.12
0.12
0.17
0.11
0.15
0.13
0.12
0.18
0.12
0.13
0.14
0.10
0.15
0.16
0.12
0.12
0.13
0.11
0.15
0.17
0.14
0.11
0.18
0.13
0.16
0.15
0.17
0.21
0.21
0.17
0.30
0.20
0.14
[
___
2,267.2
3.357.2
2,237.9
3,215.0
4,249.1
4,112.9
2,043.1
1539.0
3,436.8
982.2
8,916.6
6,775.8
2,766.1
3,196.3
5,144.3
3,074A
6,340.7
5,817.2
6,841.6
3,066.4
4,207.0
2,951.9
4,098.1
5,251.0
3,221.5
5,094.1
4,577.7
3,129.0
4,871.3
5,235.7
5,084.2
3,891.2
5,461.3
3,882.0
4,016.6
4,592.5
5,298.8
4,110.4
833.2
2,809.1
4,627.6
1,842.1
1 168,465.1
813.8 1
I Sites where not all reactors had completed 3 full years of commercial operation as of 12/31)04 are not included.
NUREG-0713
4-16
4-16
0.11
0.17
0.18
0.15
0.12
0.21
0.33
0.20
0.35
0.38
0.17
0.16
0.41
0.17
0.19
0.19
0.20
0.20
0.19
0.36
0.22
0.25
0.31
0.27
0.36
0.27
0.33
0.24
0.35
0.31
0.39
0.31
0.24
0.29
0.34
0.40
0A1
0.40
0.86
0.53
0.98
0.96
0.10
7hirty-Seventh AnnualReport, 2001
Occupational Radiation Exposure at NRC Licensed Facilities
The average 3-year collective TEDE per
BWR for 2002 to 2004 is 4% more than the
average for 2001 to 2003. The average 3-year
collective TEDE per PWR for 2002 to 2004 is
8% less than the average for 2001 to 2003.
4.6 GRAPHICAL
REPRESENTATION OF DOSE
TRENDS IN APPENDIX D
Each page of Appendix D presents a graph
of selected dose performance indicators from
1973 through 2004. The dose and performance
indicators illustrate the history of the collective
dose per reactor for the site, the rolling 3-year
average collective dose per reactor, and the
electricity generated at the site. These data are
plotted, beginning with the plant's first full year
of commercial operation and continuing through
2004. Data for years when the plant was not in
commercial operation have been included when
available. However, any data reported prior
to 1973 are not induded. The 3-year average
collective dose per reactor data are included
because they provide an overall indication of
the plants general trend in collective dose. The
3-year average collective dose per reactor is
also one of the metrics used by the NRC in the
Reactor Oversight Program to evaluate a plant's
ALARA program. This average is determined
by summing the collective dose for the current
year and the previous 2 years and then dividing
this sum by the number of reactors reporting
during those years. Depicting dose trends
using a 3-year average reduces the sporadic
effects on annual doses of refueling operations
(usually an 18- to 24-month cycle) and
occasional high dose maintenance activities
and gives a better idea of collective dose trends
over the life of the plant. The annual average
collective dose per reactor for all reactors of the
same type is also shown on the graph.
4-17
NUREG-0713
NUREG-0713
Section 5
TRANSIENT WORKERS AND CAREER
DOSES AT NRC-LICENSED FACILITIES
5.1 TERMINATION REPORTS
Under 10 CFR 20, licensees are required to
submit NRC Form 5's to the Commission for
each individual who is required to be monitored
at the end of the monitoring year or upon the
individual's termination of employment at the
facility. The 'termination reports' submitted
in accordance with the old § 20.408, listing
the individual's complete dose history during
employment at the facility, are no longer
required.
However, the Form 5's submitted to the NRC
upon an individual's termination of employment
serve the same function as the previous
requirements with regard to the analysis of
transient workers at NRC-licensed facilities.
The following analysis examines the workers
who had more than one Form 5 dose record at
more than one NRC-licensed facility during the
monitoring year. These workers are defined as
Ntransient' because they worked at more than
one facility during the monitoring year.
The term rmonitoring year is used here in
accordance with the definition of a year given
in § 20.1003, which defines a year as Othe
period of time beginning in January used to
determine compliance with the provisions of
this part. The licensee may change the start
date of the monitoring year used to determine
compliance provided that the change is made
at the beginning of the monitoring/calendar
year and that no day is omitted or duplicated in
consecutive years."
5.2 TRANSIENT WORKERS AT
NRC FACILITIES
Examination of the data reported for workers
who began and terminated two or more periods
of employment with two or more different
facilities within one monitoring year is useful
in many ways. For example, the number of
and individual dose received by these 'annual
transients' can be determined from examining
these data.
Additionally, the distribution of the doses
received by transient workers can be useful
in determining the impact that the inclusion
of these individuals in each of two or more
licensees' annual reports has on the annual
summary (as reported in Appendix B) for all
nuclear power facilities and all NRC licensees
combined (one of the problems mentioned
in Section 2). Table 5.1 shows the "actual
distributions of transient worker doses as
determined from the NRC Form 5 termination
reports and compares it with the 'reported
distribution' of the doses of these workers as
they would have appeared in a summation of
the annual reports submitted by each of the
licensees.
In 2004, over 99% of the transient individuals
were reported by nuclear power facilities. For
this reason, these data are shown separately in
Table 5.1.
5-1
NUREG-071 3
0
z
0
-in
0
TABLE 5.1
Effects of Transient Workers on Annual Statistical Compilations
U
2004
IL
0
POWER REACTORS
le,
U
1) Form 5 Summation
80.473_,._
41.583
_.___
---
15.626
__
2) Transients -As Reported
29,785
19,152
8,432
3) Transients -Actual
Corrected Distribution (1-[2-3])
8.245
1 2.733
_,
._
_, __
978
_. _I
4,348
528
409
781
931
1,452
3,435 1,592
I
688
___
1
16
,
.
4
31-
1
6,729
6,432
3,985
57,417
28,863
11,179
7,3341 2,873 11,233 11,190 188
85,328
45,885
17,077
9,168 3,256
_
13
150.322
69,849
10,368
0.15
64,10
34,321
5,513
0.16
24,074j
17,345
5,513
0.32
110,290
52,873
10,368
0.20
163,384
78,038
12,774
0.16
65,293
35,019
5,659
0.16
24,251
17,580
5,659
0.32
122,322
60,697
1 2,774
0.21
.I.
ALL LICENSEES
1) Form 5 Summation
2) Transients -As Reported
3) Transients
-Actual
Corrected Distribution (1-[2-3J)
1.329
1,145
134
34
30,274
19,545
8,588
4,432 1,490
548
431
6
1
6,671
6,469
4,029
3,483 1,650
804
968 182
15
61,726
32,809
12,540
8,199 3,416
1,585 1,682
310
48
8
_
8
Nyirty-SeventhAnnudReport, 2004
Thiny-Sevciah Annual Report 2004
Occupational Radiation Exposurc at NRC Liccnscd Facilitics
Occupational Radiation Exposure at NRC Licensed Facilities
Table 5.1 illustrates the impact that the multiple
reporting of these transient individuals had on
the summation of the exposure reports for 2004.
Because each licensee reports the doses
received by workers while monitored by the
particular licensee during the year, it is expected
that a summation of these reports would result
in individuals being counted several times in
dose ranges lower than the range in which
their total accumulated dose (the sum of the
personnel monitoring results incurred at each
facility during the year) would actually place
them. Thus, while the total collective dose
would remain the same, the number of workers,
their dose distribution, and average dose would
be affected by this multiple reporting. This
was found to be true because too few workers
were reported in the higher dose ranges.
For example, in 2004, Table 5.1 shows that
the summation of annual reports for reactor
licensees indicated that 16 individuals received
doses greater than 2 rem. After accounting for
those individuals who were reported more than
once, the corrected distribution indicated that
there were really 201 transient workers who
received doses greater than 2 rem. Correcting
for the multiple counting of individuals also has
a significant effect on the average measurable
dose for these workers. The corrected average
measurable dose for transient workers is
twice as high as the value calculated by the
summation of licensee records. The transient
workers represent 29% of the workforce that
receives measurable dose. The correction for
the transient workers increases the average
measurable dose by a factor of 2 from 0.16 rem
to 0.32 rem for the transient workforce for all
licensees. It should be noted that this analysis
of transient workers does not include workers
who may have been exposed at facilities that
are not required to report to the NRC REIRS
database (see Section 1), such as Agreement
State licensees or DOE facilities.
One purpose of the REIRS database, which
tracks occupational radiation exposures at
NRC4icensed facilities, is to identify individuals
who may have exceeded the occupational
radiation exposure limits because of multiple
exposures at different facilities throughout the
year. The REIRS database stores the radiation
exposure information for an individual by his/her
unique identification number and identification
type [Ref. 10, Section 1.5] and sums the
exposure for all facilities during the monitoring
year. An individual exceeding the TEDE 5 rem
per year regulatory limit would be identified in
Table 5.1 in one of the dose ranges >5 rem. In
2004, there were no individuals that exceeded
the 5 rem annual TEDE limit.
5-3
NUREG-071 3
NUREG-0713
Section 6
EXPOSURES TO PERSONNEL IN EXCESS
OF REGULATORY LIMITS
6.1 CONTROL LEVELS
Exposures in excess of regulatory limits are
sometimes referred to as moverexposures."
The phrase 'exposures in excess of regulatory
limits' is preferred to moverexposures" because
the latter suggests that a worker has been
subjected to an unacceptable biological risk,
which may or may not be the case.
10 CFR 20.2202 and 10 CFR 20.2203
require that all licensees submit reports of
all occurrences involving personnel radiation
exposures that exceed certain control levels,
thus providing for investigations and correcfive
actions as necessary. Based on the magnitude
of the exposure, the occurrence may be placed
into one of three categories:
(1)
The implementation date for the revised
10CFR 20 was January 1, 1994. 10 CFR 20
includes requirements for summing internal
and external dose equivalents to yield TEDE
and to implement a similar limitation system
for organs and tissues (such as the gonads,
red bone marrow, bone surfaces, lung, thyroid,
and breast). 10 CFR 20.1201 limits the TEDE
of workers to ionizing radiation from licensed
material and other sources of radiation within
the licensee's control. 10 CFR 20 no longer
contains quarterly exposure limits but has
reporting requirements for planned special
exposures (PSEs) 8. The annual TEDE limit for
adult workers is 5 rem.
I
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.
See 10 CFR 20.1206, 20.2204, and Regulatory Guide 8.35 for more information on PSEs and their reporting requirements.
6-1
6-i
NUREG-071 3
NUREG-071 3
Occupational Radiation Exposure at NRC Licensed Facilities
icnedFciiie
OcuatoalRditonEpoue tNR
(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
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 overexposur& events; therefore,
the distinctions should be noted.
(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.
NUREG-0713
NUREG-0713
7hirty-Seventh Annud Report, 2004
hit-Seet Ana Reot;20
6-2
6-2
Dirty-Seventh Annual Report, 2004
Thiry-Sevcnh Annual Report; 2004
Occupational Radiation Exposurc at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
The analysis and summary of incidents
presented here involving exposures in excess
of regulatory limits represent the status of
events as of the publication of this report.
Exposure events of this type typically undergo
a long review and evaluation process by the
licensee, the NRC inspector for the regional
office, and NRC Headquarters. Preliminary
dose estimates submitted by licensees are often
conservatively high and do not represent the
final (record) dose assigned for the event. It is,
therefore, not uncommon for an "overexposure"
event to be reassessed and the final assigned
dose to be categorized as not having been in
excess of the regulatory limits. In other cases,
the exposure may not be identified until a later
date, such as during the next scheduled audit or
inspection of the licensee's exposure records.
For these reasons, an attempt is made to keep
the exposure events summary presented here
current. An event that has been reassessed
and determined not to be an exposure in
excess of the limits is not included in this report.
In addition, events that occurred in prior years
are added to the summary in the appropriate
year of occurrence. The reader should note
that the summary presented here represents
a 'snapshot' of the status of events as of the
publication date of this report. Previous or
future reports may not correlate in the exact
number of events because of the review cycle
and reassessment of the events.
6.3 SUMMARY OF EXPOSURES
IN EXCESS OF REGULATORY
LIMITS
Table 6.1 summarizes the occupational
exposures in excess of regulatory limits as
reported by Commission licensees pursuant
to 10 CFR 20.2202 and 10 CFR 20.2203
from 1994 to 2004. Table 6.2 shows the data
reported under 10 CFR 20.403 and
10 CFR 20.405 for the period 1985 to 1993.
Note that the categorization criteria changed
effective with the revision of 10 CFR 20 in 1994.
For the period 1990 to 1993, Table 6.2 shows
the number of individuals who exceeded various
limits while employed by one of several types
of licensees. For the period 1985 to 1989, only
the exposures in excess of regulatory limits
reported by licensed industrial radiography firms
are shown separately. Most of the occurrences
included in the 'All Other" category come from
research facilities, universities, and measuring
and well-logging activities.
In 2004, there were no Category A, B, or C
occurrences. No individuals were reported to
have exceeded the annual extremity, skin dose,
or organ dose limits.
6-3
6-3
NUREG-071 3
NUREG-0713
TABLE 6.1
Occupational Exposures in Excess of Regulatory Limits
1994-2004
*a*.
2004
2003
2002
INDUSTRIAL
RADIOGRAPHY
POWER
REACTORS
MEDICAL
FACILITIES
MARKETING &
MANUFACT.
OTHER
INDUSTRIAL
RADIOGRAPHY
POWER
REACTORS
MEDICAL
FACLmES
MARKETING &
NANUFACT.
OTHER
INDUSTRIAL
RADIOGRAPHY
POWER
REACTORS
MEDICAL
FACLITIES
MARKETING &
MANUFACT.
OTHER
INDUSTRIAL
RADIOGRAPHY
POWER
REACTORS
2001201MEDICAL
FACLITIES
MARKETING &
MANUFACT.
OTHER
INDUSTRIAL
2000
1999
RADIOGRAPHY
OTHER
INDUSTRIAL
RADIOGRAPHY
OTHER
8
INDUSTRIAL
RADIOGRAPHY
OTHER
1997
INDUSTRIAL
RADIOGRAPHY
OTHER
199
1996
1995
1994
INDUSTRIAL
RADIOGRAPHY
OTHER
INDUSTRIAL
RADIOGRAPHY
OTHER
INDUSTRIAL
RADIOGRAPHY
OTHER
a One of tese
lvdualsa *o
NO. OF PERSONS
SUM OF DSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES_
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
-I-&
l5oS
15.678
15.667
1
5.880
1
5.608
so
NO.
OFOF
PERSONS
DOSES________
SUM
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
2
NO. OF PERSONS
SUM OF DOSES
NO.OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO.OF PERSONS
SUM OF DOSES
NO.OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO.OFPERSONS
SUM OF DOSES
NO.OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO.OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
NO.OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
received tOh exbrgrnty exposure -
11_373
2
10.636
1
3
2,677
5.67
52
568
4'
34.8
10o0
50-200
5
675
ID
51.1
1,115
-
'
431
-3
1,199
1
83
7r
810.8
T
5.1
*r-
f
782
255
2
12.2
16
18O
s5.
b fla exposure was tom a hot Parin to a oafted aa of the side.
c ehisexposaa, wa*from a bot pacie to aiocied armof the sik
dfmmexpomssn(Z egunrd34 rnwVw.dewsraLdf ht pue.
d i9oo
NUREG-0713
3
1260
1
127
6-4
6-4
* ibis exposure wa, from a hot pwide to a localized war of UI sn.
nOtoexbwnltp
I Them eposu han been added dutoareasses
dose frorn the direct handing of vista containing Indium a a
lIcensee,
mwnufacturlng
radiophanaceutical
9 These exposures were received by the same Individual.
R
TABLE 6.2
Occupational Exposures in Excess of Regulatory Limits
1985-1993
S~~.
1993
INDUSTRIAL
RADIOGRAPHY
NO. OF PERSONS _
SUM OF DOSES
POWER
REACTORS
NO. OF PERSONS
SUM OF DOSES
MEDICAL
FACIMES
NO. OF PERSONS
SUM OF DOSES
1
1.3
MARKETING &
NO. OF PERSONS
SUM OF DOSES
5
10.6
OTHER
NO. OF PERSONS
SUM OF DOSES
2
4.0
MANUFACT
1992
1991
1990
1989
1987.
1986
985
L
:
..
.
::
.. S.S
-
6
31
167.3
1
5.4
1
275
I
INDUSTRIAL
RADIOGRAPHY
NO. OF PERSONS
SUM OF DOSES
POWER
REACTORS
NO. OF PERSONS
SUM OF DOSES
MEDICAL
FACILITIES
NO. OF PERSONS
SUM OF DOSES
MARKETING *
MANUFACT.
NO. OF PERSONS
SUM OF DOSES
OTHER
NO. OFPERSONS
SUM OF DOSES
jb
1.9
INDUSTRIAL
RADIOGRAPHY
NO. OF PERSONS
SUM OF DOSES
2
5.6
POWER
REACTORS
NO. OF PERSONS
SUM OF DOSES
MEDICAL
FACILITIES
NO. OFPERSONS
SUM OF DOSES
MARKETING &
MANUFACT.
NO. OF PERSONS
SUM OF DOSES
OTHER
NO. OF PERSONS
SUM OF DOSES
2.4
INDUSTRIAL
RADIOGRAPHY
NO. OF PERSONS
SUM OF DOSES
3
7.2
POWER
REACTORS
NO. OF PERSONS
SUM OF DOSES
MEDICAL
FACILITIES
NO. OF PERSONS
SUM OF DOSES
MARKETING &
MANUFACT.
NO. OF PERSONS
SUM OF DOSES
OTHER
NO. OF PERSONS
SUM OF DOSES
1
2.3
INDUSTRIAL
NO. OF PERSONS
3
1
1
RADIOGRAPHY
ALL OTHER
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
8.1
93
72
2
105
INDUSTRIAL
RADIOGRAPHY
ALL OTHER
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
3
7
19.34
INDUSTRIAL
RADIOGRAPHY
NO. OF PERSONS
SUM OF DOSES
1
3.1
ALL OTHER
NO. OF PERSONS
SUM OF DOSES
2
2.8
INDUSTRIAL
RADIOGRAPHY
ALL OTHER
NO. OF PERSONS
SUM OF DOSES
NO. OF PERSONS
SUM OF DOSES
2
44
4
3
9.6
INDUSTRIAL
RADIOGRAPHY
NO. OF PERSONS
SUM OF DOSES
6
16.7
ALL OTHER
NO. OF PERSONS
SUM OF DOSES
7
11.8
300-1000
4
57.7
1
1.9
4
143.6
1
272
1
40.5
I
24.1
2
3.8
1
22.3
1
I
i11
C
6000
3c, d
49.9
2d
3962
I
48.8
3e
1.9
4
6.6
8.1
1
9.2
178
1
1
6.1
118
1
61
4
66.8
1
278
1
58
1
127
1
180
..
1
41.2
3
32.6
1
650
3
72.0
5
128.4
1
7.5
1
115
2
930
1
288
1
27.0
3
60.2
1
93
etese Individuals Aceived a rem whole-body dose In addition to a
d One of
1070 rem extremity dose.
One of linee Individuals exceeded the quarterty whole-body dose limits Ehree
times in oe calendar yer.
f An additional 1353 exposurews spored I 1SS4
* Same Individual exceeded 1.25 fmmlqr lmit twice during 193
This 1352 exposure was reported In 193
ON
*This Individual received awhole-ody dose of24 rem in add~ition to a__
dose.
r
155
6-5
UREG071
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Mity-Seventh Annual Report, 2004
eos20
iene aiiisTia-SeenhAna
OcuainlRdain
xouea R
As shown in Table 6.3, few exposures exceed
half of the NRC occupational annual limits. In
2004, only 8 individuals exceeded 75% of the
TEDE dose limit. No individual exceeded the 5
rem TEDE annual limit.
6.4 MAXIMUM EXPOSURES
BELOW THE NRC LIMITS
Because few exposures exceed the NRC
occupational exposure limits, certain
researchers have expressed an interest in a
listing of the maximum exposures received at
NRC licensees that do not exceed the limits.
This would allow an examination of exposures
that approach, but do not exceed, the limits.
Table 6.3 shows the maximum exposures for
each dose category required to be reported to
the NRC. In addition, the number of exposures
in certain dose ranges is shown to reflect the
number of exposures that approaches the NRC
limits.
TABLE 6.3
Maximum Occupational Exposures for Each Exposure Category*
2004
SDE-ME
5srem
455.3
SDE-WB
50 rem
.913
LDE
83%
1%
n o trans.408
it 5 d
CEDE
_
CDmE
_10.244
DE d
I
54,020
197
59,950
1.235
3,513
al
2,910
4.392
46
61,962
0
0
a
0
7
61,011
TEDE
|
5rm
4.392
88%
62,032
TODE
l
0rm
010.605
21%
55,122
1,275
158
1
- I
-0
20=80 are included. Numbers hane been adjusteforthe muli~ph
*Only recrseported by lMensae requird to report under 10 CFR
reporting oftrOanshent indIvIduals
SDE-MIE ssh lbw dose *qulvalbnt -maxlmaty exposed *xtremitt
SDE-WI a shallow dose equivalent - whole body
LDE a qap dose equivalent to the Ions of the ey,
CEDE =commited effndv dose equivalent
CDE : committd dose equivalent
DOE deep dose equhivlnt
TEDE :total effective dose equivalent
TOD! =total organ dose equivalent
Shaded boxes represent dose categories Ot do not have specific dose limite defined In 10 CFR 20.
NUREG-0713
-
4
6-6
Section 7
REFERENCES
1.
U.S. Atomic Energy Commission, Nuclear Power Plant Operating Experience During 1973,
USAEC Report OOE-ES-004, December 1974.*
2.
U.S. Nuclear Regulatory Commission, NuclearPowerPlant 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 NUREGICR-1496,
May 1981.*
7.
NuclearPowerPlant Operating Experience - 1980, USNRC Report NUREG/CR-2378,
ORNLJNSIC-191, October 1982.*
8.
Nuclear Power Plant Operating Experence - 1981, USNRC Report NUREG/CR-3430,
ORNLINSIC-215, Vol. 1, December 1983.*
9.
Nuclear Power Plant Operating Experience - 1982, USNRC Report NUREGICR-3430,
ORNL/NSIC-215, Vol. 2, January 1985.*
10. Instructions for Recording and Reporting Occupational Radiation Exposure Data, USNRC
Regulatory Guide 8.7, Rev. 1, June 1992.
11.
United Nations, Sources and Effects of Ionizing Radiation, United Nations Scientific
Committee on the Effects ofAtomic Radiation UNSCEAR 2000 Report to the General
Assembly, with scientific annexes, Volume 1,General Assembly of Official Records, United
Nations, New York, 2000.
12. Licensed Operating Reactors, Status Summary Report, compiled from reactor monthly
operating reports submitted to the NRC. Data provided electronically from the Idaho National
Engineering and Environmental Laboratory (INEEL) Risk, Reliability and Regulatory Support
Department under contract to the NRC in support of the NRC's Performance Indicator Project.
*
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.
7-1
7-1
NUREG-071 3
NUREG-0713
Appendix A
ANNUAL TEDE FOR NON-REACTOR
NRC LICENSEES
2004
A-l
NUREG-0713
z
0
APPENDIX A
Annual TEDE for Non-Reactor NRC Licensees
CY 2004
0
-I
I.
0I
INDUSTRIAL RADIOGRAPHY - SINGLE LOCATION - 03310
t.
AMERICAN CASTINGS, LLC
ARMY, DEPARTMENT OF THE
ARMY, DEPARTMENT OF THE (CRANE)
ARROW TANK &ENGINEERING CO.
CHART INDUSTRIES, INC.
35-18099-01
2
23
22-13253-01
22-24393-01
-
DURALOY TECHNOLOGIES. INC.
HARRISON STEEL CASTINGS CO.
37-02279-02
-
13-02141-01
5
HUTCHINSON TECHNICAL COLLEGE
INTERMET-ARCHER CREEK
22-15554-01
61
NILES STEEL TANK CO.
TESTWELL LABORATORIES, INC.
WAUKESHA FOUNDRY. INC.
21-04741-01
31-30653-02
Total
I
12
2
0.008
0.004
3
1
0.004
0.004
28
3
0.058
0.019
6
S
-
5
5
0.192
0.038
-
4
4
0.599
0.150
5
-
-
-
75
1 14
0.478
0.034
C.,
5
5
0.155
0.031
2.
3
1
0.015
0.015
a
4
0.610
0.153
3
-
-
3
4 1
-
3
3
1
13
-
-
.
*
-.
I.
-
m
-
-
-
-
:
-
3
1
- 0.i-0
*4
1
2
1
.-
4
4
2
1
101
2
-
1
45-1744-01
48-13776-01
-
2
29-00047-06
13-18236-01
.
-
.:-:
|.
.
.
0
.
.
,
.:.
.
.,t
.:
-
-
-
.
-
.
-
:
-
^
.-
1
-
-
f
-
-
-;;
-
-:
-:
-:
1.026
[
1
.-
;
34
7
:
4
NOTE: The data values shown bolded and in boxes represent the highest value in each category.
.
I
14
48
3.14
|
I.,
z
0.171
4
0.070
APPENDIX A
Annual TEDE for Non-Reactor NRC Licensees
CY 2004 (continued)
__0,_
____________
INDUSTRIAL RADIOGRAPHY- MULTIPLE LOCATION - 03320
z
C]
0
-4
ALASKA INDUSTRIAL X-RAY, INC.
50-1e084-01
4
1
ALLIED INSPECTION SERVICES, INC.
21-18428-01
*
*-
ALONSO & CARUS IRON WORKS, INC.
52.21350-01
AMERICAN ENGINEERING TESTING, INC.
22.20271-02
*
7
ANVIL CORPORATION
46-23236-03
3
23
APPLIED TECHNICAL SERVICES, INC.
45-25477-01
2
11
BILL MILLER, INC.
35-19048-01
I
BRANCH RADIOGRAPHIC LABS,, INC.
29-03405-02
a
BRAUN INTERTEC CORPORATION
22-16537-02
CALUMET TESTING SERVICES. INC.
13-10347-017
CANSPEC (USA), INC.
42-32443-01
CAPITAL X-RAY SERVICES, INC.
35-1111401
CENTURY INSPECTION, INC.
42-08458-02
le
13
4
CERTIFIED TESTING LABS, INC.
29-14150-01
2
16
4
COLBY & THIELMEIER TESTING CO.
24-13737-01
1
1
COMO TECH INSPECTION
15-26978-01
-
*-
1
3
1
CONAM INSPECTION
12-16559-02
23
118
85
85
60
44
CONSUMERS ENERGY LAB. SERVICES
21-806-03
7
4
t
5
8
2
-
COOPER HEAT-MOS
42-32219-01
7
43
19
23
13
12
9
CTL - ASTROTECH DMSION
37-09928-01
13
14
2
-
*
-
CURTISS-WRIGHT ELECTRO-MECH. CORR 37-05809-02
-
5
*
*.
*
-
,-
ELITE INSPECTION, INC.
13-26712-01
2
4
79
5
1
6
5
ENGINEERING & INSPECTIONS, HAWAII
53-27731-01
-
-
6
4
FINLAY TESTING LABORATORIES
53-27718-02
3
2
3
2
FROEHUNG & ROBERTSON. INC.
45-08890-01
10
2
1
-
G E. INSPECTION SERVICES, INC.
39-24888-01
1
11
4
1
GENERAL TESTING & INSPECTION CO.
47-32191-01
1
1
3
1
1
3
1
1
1
1
-
:
1
-
1
2
2
3
-
12
12
6
2
2
3
17'
5
4
5
4
1
1
1
1
4
7
8
2
1
3
3
3
2
4
4 :1
4
3
1
-
1
3
1
13
171
4
.12
5
1
1
1
3
4
2
1
-
10
7
3
10
1
2
-
1
4
2
8
9
9
5.727
0.636
5
5
2.558
0.512
3
3
0.824
0.275
2
2
-
27
27
26.472
0.980
-
-
-
75
72
22.896
0.318
24
22
5.072
0.231
18
17
7.619
0.448
26
20
5.821
0.291
0.506
..
-
-I
-
1
20
20
17
8.600
13
9.617
0.740
63
62
20.983
0.338
24
24
19.278
0.803
66
50
35.521
0.710
II
-
-
-
-
23
21
1.766
0.064
1
1
4
-
-
10
10
8.674
0.667
0.703
i-
1
-
NOTE: The data values shown bolded and inboxes represent the highest value In each category.
1
-
70o
13
1
-
. S
1
1
-
-
6
4.216
478
25.22
0.555
0.396
-
-
24
17
-
-
127
120
6.720
44.668
29
16
0.743
0.046
5
5
0.035
0.007
36
34
29.300
0.862
-
5
6
-
3
0
PC.
I.
A,0
I
0.372
12
12
7.482
0.824
-
2
13
10
5.060
0.506
-
-
13
3
0.240
0.060
-
0
1
e8
17
2.266
0.133
-
6
5
0.954
o.1gi
z
o
Z
a
0
z
APPENDIX A
Annual TEDE for Non-Reactor NRC Licensees
CY 2004 (continued)
9
0
-
I.
a
L
:,
g
0
INDUSTRIAL RADIOGRAPHY- MULTPLE LOCAnON - 03320 Contnud
3
3
a
8
6
1'
-
4
6
1
60
6
7
GLOBE X-RAY SERVICES, INC.
H & G INSPECTION COMPANY, INC.
H & HX-RAY SERVICES, INC.
HIGH MOUNTAIN INSPECTION SERVICES
35-15194-01
42-26838-01
49-26808-02
6
-
31
7
26
15
HUDSON GLOBAL RESOURCES, INC.
HUNTINGTON TESTING &TECHNOLOGY
INSPECTION SERVICES ORGANIZATION
37-27891-01
2
6
1
47-23076-01
1
9
10
41-06832-06
10
3
2
INTEGRITY TESTLAB
07-30791-01
1
1
2
IN'L RADIOGRAPHY & INSPEC. SERVICES
JAN X-RAY SERVICES, INC
KAKIVIKASSET MANAGEMENT
LONGVIEW INSPECTION, INC.
35-30246-01
2
15
9
7:
10
4
10
21-165680-01
50-27687-01
42-27593-01
31-30821-01
77
10
12
-
30
21
19
3
34
16
10
1
46
23
1I
7
2
18
5
1
23
15
_
.
LUCIUS PITKIN, INC.
MARTIN INDUSTRIAL TESTING, INC.
MARYLAND OC. LABORATORIES, INC.
MASSACHUSETTS MATERIALS RESEARCH
17-19236-01
45-25452-01
19-28683-01
2
10
311
10
3
I1
-
13
1
3
2
3
44
43-27382-01
7
5
-
MIDWEST INDUSTRIAL X-RAY, INC.
NEWPORT NEWS SHIP BUDG & DRY DOCK CO.
NON-DESTRUCTIVE TESTING GROUP
NOVA DATA TESTING LABS, INC.
33-27427-01
45-09428-02
1
2
-
1
21-32340401
2
10
2
45-24872-01
-
4
1
PACIFIC TESTING, INC.
PRECISION CALIBRATION & TESTING CO.
PRECISION CUSTOM COMPONENTS, LLC.
53-29118-01 ,
37-30546-01
37-16280-01
PRECISION TESTING & INSPECTION
45-25475-01
-
31
9
-
4
6
4
13
7
-
-
45
23
2
4
2
3
10
12
*
2
2
2
3
0.759
1.085
0.467
34
12.645
0.372
5
0.423
0.085
15
12.555
0.837
70
68
255
66.023
94.671
37.146
0.971
0.531
0.437
29.301
0.255
0.575
0.064
1.729
3.807
0.576
0.200
0.252
0.396
6.024
0.084
0.079
0.548
91
-
-
-
2
6
4
35
0
15
-
1
,
-
2
2
2.
-
- -.
5
14
178
65
51
4
3
19
3
5
11
*.
-
2
-
-
-
15
8
2.705
0.338
4
1
3,
3
22
21
45
16
6
42212
4.067
3.793
0.594
2900
47
9
4
1.187
0.048
0.132
0.012
8
0.302
0.038
6
5.973
0.996
9
3
1
I9
2
.1
-
0-
*
-
95
-
63
I
.¶
-
4
3
.-
21
.
-
1
1.
4
.
6
1
-
63
1
2
1
j-
18
.*
-
-.
6
9
.
8
-
-)
21
-
-
.
*
.: 3
-
145.656
97.196
7.478
. *
.-
2
192
91
16
198
.-
2
0.775
0.611
-
1
2
1
-
23
14
2
21.696
25.674
42
-
*
<1
-
07-01173-03
50-27722-01
25-21479-01
MATERIALS INTEGRITY, INC.
MATTINGLY TESTING SERVICES, INC.
MET-CHEM TESTING LASS OF UTAH. INC.
6
26
*
4
3
51
28
42
29
- -
2-
t
1
-
NOTE: The data values shown boldd and in boxes represent the highest value in each category.
-
3:
-'
6
-
0.090
0.237
0.099
p
z
a
R
2
is
I
APPENDIX A
Annual TEDE for Non-Reactor NRC Licensees
CY 2004 (continued)
i;
Mmmmxv aS
N~
M
.
~I
# II
INDUSTRIAL RADIOGRAPHY. MULTIPLE LOCATION - 03320 Contlnued
PRIME NOT SERVICES, INC.
37-23370-01
6
1
3
1
PROFESSIONAL NDE & WELDING SERVICES
52-25538-01
-
5
-
5
1
PROFESSIONAL SERVICE INDUSTRIES
12-18941-03
1
2
1
1
-
O.C. LABORATORIES, INC.
09-11579-03
QUALITY INSPECTION SERVICES, INC.
31-30187-01
SCHNABEL ENGINEERING ASSOCIATES, INC4S-19703-O1
z
C)
0
-4
SCIENTIFIC TECHNICAL, INC.
45-24882-01
SHAW PIPELINE SERVICES, INC.
35-23193-01
:
e
4
1
2
2
1
2
4
1
3
1
1
1
2
4
4
5*i
13
1.
1*
18
12
32-25137-01
-.
2
3
1
SOUTHWEST X-RAY CORPORATION
49-27434-01
-:
1
1
ST. LOUIS TESTING LABS, INC.
24-00188-02
1:
1l
1
2
:1
2
-
1
2
-
6;
STORK TWIN CrTY TESTING CORP
22-01376-02
1
T & K INSPECTION, INC.
33-27678-01
-
-
TEI ANALYTICAL SERVICES, INC.
37-28004-01
2
17
TESTING INSTITUTE OF ALASKA, INC.
50-17446-01
8.
1
TESTING TECHNOLOGIES, INC.
45-25007-01
-
8
6.
TESTMASTER INSPECTION CO.
34-24872-02
THERMAL ENGINEERING INTL
24-19500-01
THREE RIVERS GAMMA
37-28367-01
TULSA GAMMA RAY, INC.
3
-
I
-
I
7
.7
2
-
..*-
2
3
I
-
2
5
4.
4
4
1
1
6
4
3
2
1
1
1
3
1
-
35-17178-01
2
8
48-23476-01
4
6
10
2
5
2
7I
TWIN PORTS TESTINQ INC.
11
1
U.S. INSPECTION SERVICES
34-00943.02
11
55
04-29078-01
14
16
24
9
13
, 13
21
VALLEY INDUSTRIAL X-RAY
VALLEY INSPECTION SERVICE, INC.
WASHINGTON GROUP INERNATIONAL
WESTERN X-RAY COMPANY
28
6
13
I
11
35-19993-01
2
10
-
..
.
.
.
.
-
20.465
0.890
11
2.482
0.226
5
1.506
0.302
13
2.387
0.164
6
2.821
0.437
-
::
7
10
2.435
0.244
.
*
10
6
0.473
0.079
42
69
37.161
0.539
6
0.911
0.152
3.923
0.654
7.173
0.512
0.132
-
:
-
.
.-
13
23
9
-
-
-
15
-
;
.
421
-
14
1
.
*
.*
-
.
.
.-
*
.
-.
-
-*
1.054
11
20.954
1.905
8
40
14.912
0.373
12
8
1.484
0.244
21
21
9.450
0.450
a
5.490
0.666
0.065
0.065
1.257
2
-
-
a
8
;
.
1
1
.
.
1
17
. i3I
*
*<
*
*
5
1
-9
-
3
8
8
;
4
-
1
I
I
--
1*
29-27761-01
...
.
~
-
-
4
;
-
-
4
-
-
37-28385-01
23
-
-*,-
:
:
-
I
2
WOS TESTING COMPANY. INC.
2
-
S.K. MCBRYDE, INC.
1
6
5
9
I,
-
10
1
*
167
-
-
-
-
:
9
4
1
2
4
5
-:
5
48-26385n-0 _
.I
2 ..
5
1
Total
11
328
751
450 454 319 235
NUTE: The data values Shown bolded and In boxes represent the highest value in each category.
-
11
-
-
1.287
11
3.690
0.335
156
68.617
0.440
es
37.585
0.569
a
6.820
0.853
-
-
125
24
3.284
0.137
-
*
-
28
28
23.560
0.841
1 051
0.150
30
73046 3045
IM
355
1664355
0.675
.67
7
-
m377
2.513
110.254
-
1.1
9
2
87
3o :: 7
2721
2721
0
-0
C
If
z
Cn
Ph
0
z
APPENDIX A
Non-Reactor NRC Licensees
for
TEDE
Annual
CY 2004 (continued)
-
A)
zMANUFACTURING AND DISTRIBUTION - LIMITED
NUCLEAR PHARMACIES - 02500
CAPITAL PHARMACY, INC.
CARDINAL HEALTH, INC.
EASTERN ISOTOPES, INC.
MALLNCKRODT, INC.
MALLINCKRODT, INC.
MALLINCKRODT MEDICAL, INC.
MALLINCKRODT MEDICAL, INC.
MALLINCKRODT MEDICAL, INC.
MALLINCKRODT MEDICAL, INC.
MALLINCKRODT MEDICAL, INC.
MALLINCKRODT MEDICAL, INC.
MID-AMERICA ISOTOPES, INC.
NUCLEAR DIAGNOSTICS PRODUCTS
PSI, INC.
I- UIU - l1M^4T. INU.
Total
21-26597-OIMD
04-28507-O1MD
45-25221-0IMD
24-04200-OOMD
24-04206-22MD
24-04206-OIMD
PR
7
1
394
5 ,
624 132
42
12
5
2
25
114
17
9
7
3
7
6
1
-
16
2
1
-
:13
:7
24-04206-IOMD
12
24-04206-14MD
9
24-04206-iSMD
7
24-04206-19MD
24-17450-42MD
24-26241-OIMD
1.
18
5
29-30500-1OMD
11-27705-01MD
8
32
l*XB=lMU
e:
18
4
.9
7
8
*
U5
3
-'
-I
18
IA
8U1
4
3
210
204
4
1
81*
10
0.077
1 63.1
179 |
72.7T3
0.112
-
19
3
0.253
0.084
-
20
7
0.283
0.040
-
23
11
0.780
0.071
-
28
19
1.728
0.091
2
18
10
1.118
0.112
38
20
3.748
0.187
1
17
9
1.035
0.115
-
28
10
1.588
0.159
85
57
9.470
0.166
8
8
3.321
0.415
28
22
1 712
0.078
1,748
1,203
163.136
0.135
..
1
1
1
1
.
-
3
74
2i
NOTE: The data values shown bolded and In boxes represent the highest value In each category.
*
-
22
-
*.
.
-
'-
4
1
'
*
a.
040
1.563
.14 9.1
5
6
19
1 t,2U
0.037
14
a6
5
.
0.074
17
.
7
.10
18
25
3
ti
h
f
;1
APPENDIX A
Annual TEDE for Non-Reactor NRC Licensees
CY 2004 (continued)
m
I
-
-
-
- '
i
-.
MI
MANUFACTURING AND DISTRIBUT7ON - TYPE A BROAD - 03211
CANBERRA DOVER, INC.
29-04236-01
INTERNATIONAL ISOTOPES IDAHO, INC. 11-27680-01
MALLINCKRODT, INC.
24-04206-01
Total
3
MANUFACTURING AND DISTRIBUTION - LIMITED
TYPE O BROAD- 03212
OHMARTNEGACORP.
34-00639-04
Total
I
4
14
6
26
3
2
2
2
89
109
88
57
61
30
17
117
69
63
32
17
-
-
^-
-
40
16
1
36S 14
37
14
392
448
26
10
|30
339
0.341
0.013
3.953
0.395
153.386
0.50r
157.030
0.465
0
04
A
17
117
27
27
3
3
1
3
3
I
-
-
el
34
2JJ33
0.077
e1
34
2.633
0.077
US
PS
MANUFACTURING AND DISTRIBUTION - LIMITED
OTHER- 03214
BMS-MEDICAL IMAGING
20-00320-19
1
1
2
2
0.232_|0.116
MDS NORDION, INC.
54-28275-01
1
1
2
2
0.192
Total
2
2
2
4
4
0.424
-
-
-
-
0.096
0.10S
NOTE: The data values shown bolded and In boxes represent the highest value In each category.
;J1
z
C
-4
0
z
APPENDIX A
Annual TEDE for Non-Reactor NRC Liccensees
CY 2004 (continued)
ig
C0
9
C
1JJ
_
-
E=
P*
s
____c^_
3
_
0
IM
IE__
M;R;
v
sr
1-
=R.O
_Z
=mM"
E~I
INDEPENDENT SPENT FUEL STORAGE INSTALLATION - 23200
GENERAL ELECTRIC COMPANY
SNM-2500
10
22
4
1
Total
1
10
22
4
1
*
3
37
*
-
-
37
37
1.27
0.047
0.047
IM
FUEL CYCLE
URANILIM ENRICHMENT PLANTS .21200
USECPADUCAH
GDP-1
USEC-PORTSMOUTH
GDP-N
12278
Total
2
3
3
2
2,923.
0
185
?
4C9
41 -13
33
179
89
20
358 60;
1
2
13
38
1 *
19
|
-
75
43208
13285.
4
*
S,36
C13
8.81B
0.042
1389
5
0.304
12.376
0.044
FUEL CYCLE
FUEL FABRICATION FACILITES - 21210
BWXTECHNOLOGIES, INC. (NPD)
SNM-0042
FRAMATOAE ANP, INC.
SNM-1168
FRAMATOME ANP, INC.
SNM-1227
59
185
62'
GLOBAL NUCLEAR FUEL-WILMINGTON, NC
SNM-1097
284
387
188
87
NUCLEAR FUEL SERVICES. INC.
SNM40124
112
712
136
15
WESTINGHOUSE ELECTRIC COMPANY
SNM-1107
18
TOWl
6
214 i151
2,033 675
3
525
22
1
1
-
17
2
I
4
19
6
83
;38,
-
.-
-
-
-
-
-
.
-
-
-
-
107
18
70
311
149
91
NOTE: The data values shown bolded and In boxes represent the highest value In each category.
32
41
-
r
325
292
30.220
Q.104
750
^-
430-
; 27.574
0.064
431
- ^
372
---
*-85.538
0.230
946
662
2
7.070
0.106
42.003
0.049
682
3,300
23.140
491.164
0.149
|
700
4.126
0
9:
z
WI
1.,
Appendix B
ANNUAL WHOLE BODY DOSES AT LICENSED
NUCLEAR POWER FACILITIES
2004
B-i
B-i
NUREG-071 3
NUREG-0713
zC
APPENDIX B
0
Annual Whole Body Doses at Licensed Nudear Power Facilities
CY 2004
p.
0
I
la
BEAVER VALLEY 1. 2
BRAIDWOOD 1. 2
PWR
PW
PWR
BROWNS FERRY 1,2,3
BRUNSWICK 1, 2
BWR
BWR
BYRON 1,2
PWR
PWR
PWR
PWR
ARKANSAS 1,2
CALLAWIAY I
CALVERT CLIFFS 1,2
CATAWBA 1, 2
CLINTON
COLUMBIA GENERATING
COMANCHE PEAK 1, 2
COOK 1, 2
COOPER STATION
CRYSTAL RIVER 3
DAVIS-BESSE
DIABLO CANYON 1,2
DRESDEN 2, 3
BWR
BWR
PMR
PWR
BWR
PWR
PWR
PWR
BWR
DUANE ARNOLD
FARLEY 1,2
FERMI 2
BWR
FITZPATRICK
BWR
PWR
FORT CALHOUN
GINNA
GRAND GULF
HARRIS
HATCH 1,2
HOPE CREEK 1
INDIAN POINT 2
INDIAN POINT 3
KEWAUNEE
LASALLE 1,2
LIMERICK 1, 2
MCGUIRE 1, 2
PWR
BWR
PWR
BWR
PWR
BWR
BWR
PWR
PWR
PWR
BWR
BWR
MILLSTONE 2, 3
PWR
PWR
MONTICELLO
NINE MILE POINT 1, 2
NORTH ANNA 1, 2
BWR
BWR
PWR
1,204
1,662
1,444
2,501
1,287
1,352
1,325
1,152
.1,717
1,173
: 49
1.310
1,643
1,042
690
1,033
1,438
1,094
808
987
1,450.
826
754
84
881
1,012
1,000
386
1,580
1,550
670
1,358
1,617
1,283
1,388
734
1,062
2,441
857
773
663
1,537
1,480
612
745
824
703
852
523
498
572
322
126
160
550
1,064
147
768
835
581
147
88
764
552
653
1,649
60
223
305
1,432
802
623
428
168
294
301
239
691
387
229
259
200
N315
389
115
230
250
107
5
10
348
458
62
291
292
257
48
20
288
184
313
288
287
10
.132,.
484
300
292
198
63
490 . 304
278
562
72
163
78
596
188
53
93
113
78
243
61
87
129
48
4
30
6
318
87
10
20
49
24
96
.13
20
35
5
1
-
208
314
11
73
150
166
17
81
144
2
1
-
42
1
43
86
52
10
14
25
22
138
30
182
191
185
1
93
314
123
109
128
43
251
83
-
9
26
60
3
.
-
3
92
21
1
7
15
3
25
4
9
20
1
9 ^
0
-
4.
17 ,
.20
-
-
24
34
-
16
3
-
*1.
a.
.
40
21
92
29
4.
1
-
211
6.
-
1,784
-
26
:31
39
37
6
5
36
3
24
9
1
140
28
69
8
99
2,491
2,932
2,430
5,743
3,427
2,258
2,449
2,357
2,840
2,795
1,565
2,174
2,658
1,523
821
1,194
2,668
3,138
1,028
2,128
2,752
1,917
989
995
2,124
1,769
2,209
2,826
2,688
20
-
103 :
6
5
1
1,235
3,724
2,882
2,399
2,191
1,013
2,424
3,406
1,227
1,270
988
3,242
2,140
906
1,124
1,205
1,123
1,622
718
884
1,015
481
131
161
1,230
2,044
220
1,141
1,302
1,091
215
111
1,243
747
1,209
2,440
1,136
234
565
2,366
1,265
1,118
803
279
1,362
965
106.172
158.509
94.942
672.714
244.577
89.147
120.621
143.944
122.831
282.833
66.130
135.388
158.213
47.064
4.044
6.594
254.367
381.054
18.993
107.227
145.090
186.055
21.574
7.488
158.112
57.103
180.129
239.540
196.830
4.232
91.168
359.470
149.433
196.193
138.459
35.081
448.509
129.688
L
gi.
o
C3
APPENDIX B
f
Annual Whole Body Doses at Licensed Nuclear Power Facilities
CY 2004 (continued)
I
b
OCONEE 1, 2,3
OYSTER CREEK
PALISADES
PWR
2,221
BWR
1,160
PAR
765
PALO VERDE 1, 2,3
PEACH BOTTOM 2,3
PMW
BWR
BWR
PERRY
PILGRIM
POINT BEACH 1, 2
PRAIRIE ISLAND 1, 2
QUAD CmES 1, 2
RIVER BEND I
ROBINSON 2
SALEM 1,2
1,695
1,508
.861
BWR
PWR
PM
BWR
BWR
PWR
PWR
PWR
475
836
g919
9"1
881
995
PWR
PWR
238
2,379
830
1,663
1,237
1,547
902
2,482
BWR
PWR
1,244
1,071
TURKEY POINT 3,4
PWR
VERMONT YANKEE
VOGTLE 1,2
WATERFORD 3
WATTS BAR I
WOLF CREEK 1
BWR
PWR
PWR
PWR
1,779
86s
TOTALS
TOTALS
TOTALS
BWRS
SAN ONOFRE 2, 3
SEABROOK
SEQUOYAH 1, 2
SOUTH TEXAS 1,2
ST. LUCIE 1, 2
SUMMER I
SURRY 1, 2
SUSQUEHANNA 1, 2
THREE MILE ISLAND I
PWR
PWR
PWR
PWR
PWR
PWRS
LWRS
1,092
754
296
853
759.
256
282
301
674
1,155
725
535.
1,138
895.
278
907
406
618
733
275
215.
246
318
133
`10
168
364
480
328
282
178
307
12
199
200
348
171
65o
1,433
339
217
198
123
214
88
33
112
133
373
228
121
117
213
1
47
93
152
104
63
103
26
3
250
391
288
286
202
90
203
105
175
56
4
18
2-
8
-
19,678
7,101
6,826
41,883 '18,626
4,854
1,690,
21,906
3,6919
1,043
8,245
2,733
101
687
1,160
817
499
1,023
1,218
921
202
85
26,043
.4,43
80,473
56
4
49
83
16
2
37
13
184
e1
11
40
114
*
7
31
29
26
29
75
19
25
3
1
4,518
2,496
1,739
3,019
2,930
1,357
902
1,463
2,105
3,325
2,259
1,947
1,734
4,140
1121
2,824
2,079
2,704
1,102
3,510
3,388
1,176
2,686
2,244
1,925
1,083
1,438
1,014
*
79
34
20
-
-
-
6
3
-
7
2
92
19
3
16
64
2
s
-
44
17
-
*-
-
7
78..
-
1
20
12
2
-
-
*.
20
89
6
28
-
3
20
-
-
9
67
1
-
-
-
25
0
2
-
6
-
-
-
.
672
406
978
:*
-
353
26
sea
8
*
e
*
1a
-
.
..
.
.
-90
: ,
-
89,991
3031
150,322
2,295
1,346
974
1,324
1,422
496
427
627
1,186
2,334
1,378
952
1,496
1,781
291
1,161
842
1,157
200
1,028
2,144
105
1,089
1,379
765
60
220
93
387.89t
226.880
370.895
199.018
264.727
73.481
41.109
109.515
143.806
510.521
235.749
118.159
148.894
407.083
5.858
85.941
119.834
159.436
10.085
119.854
272.202
3.573
117.404
211.529
80.763
2.517
5.893
3.388
33,946
5,40.982
35,901
4,916.916
69,849 10,367.897
0
C
o9Y.
tL
I
0
I.
*PI
z
(0
C.,
I4
z0
APPENDIX B
:2
b
Annual Whole Body Doses at Licensed Nuclear Power Facilities
CY 2004 (continued)
90
REACTORS NOT YET INCOMMERCIAL OPERATION
WATTS BAR 2
PWu Reported with Witt Bar 1
REACTORS NO LONGER INCOMMERCIAL OPERATION
161
135
HADDAM NECK
HUMBOLDT BAY
INDIAN POINT I
LACROSSE
MAINEYANKEE
MILLSTONE I
RANCHO SECO
SAN ONOFRE I
BWR
PWR
BWR
PWR
BWR
PWR
BWR
PWR
PWR
658
107
1,50
12
252
255
142
1454
TROJAN
PWR
216
YANKEE-ROWE
PWR
360
ZION 1 2
PWR
87
306
11
149
58
132
78
88
117
6
54
6
BIG ROCK POINT
t
17
13
18
13
388
227
153
72
16
9
8
2
5
1
8
7~ 2
6
3
2
1
1222
118
1706
68
442
402
264
1623
584
11
158
56
190
147
122
169
331
-
-
38
36
17
39
11
23
8
13
-
-
.
7
8
1
-
-
.
-
-
.
57.599
918981
0.54
2.916
0.918
21.313
11.152
14.890
14.899
220
5
0.079
430
0.502
93
70
6
6,976
1,723
222.870
0.167
REACTORS NO LONGER INCOMMERCIAL OPERATION, REPORTED WITH OTHER UNITS
BROWNS FERRY 1
DRESDEN 1
THREE MILE ISLAND 2
BWR
BWR
PWR
Total Reporltng
12
Reported with Browns Feny 2, 3
Reported with Dresden 2,3
Reported with Three Mile Island 1; estimated dose from Unit 2 s0.216 person-rem.
62U3
1,137
323-
157
46
36
24
-
*
units).
These numbers are for the reactors no longer In commercial operation that report their doses separalely p e., do not report their doses with other
*Browns Fe"y I remains in the count of operating reactors but was placed on Administrative Hold In June 1985.
|
EL
Appendix C*
PERSONNEL, DOSE, AND POWER GENERATION
SUMMARY
1969-2004
*
A discussion of the methods used to collect and calculate the information contained in this Appendix is given in Section 3.1.
C-l
c-i
UREG071_
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
X
ro+SenthAnnual Report, 2004
MUI
w"I;
ARKANSAS 1,2
Docket 50-313, 50-368;
DPR-51; NPF-8
1st commercial operation
12/74, 3180
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 - 821, 831 MWe
NUREG-0713
NURUEG-0713
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
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
588.0
464.6
610.3
627.2
397.0
452.8
1,104.7
905.4
915.0
1,289.1
1,192.3
1,070.3
1,366.1
1,070.3
1,066.3
1,351.9
1,515.8
1,352.1
1,606.0
1,662.8
1,397.0
1,596.0
1,621.9
1,494.6
1,477.3
1,329.2
1,684.0
1,659.0
1,675.8
1759.5
355.6
304.2
221.0
39.8
573.4
326.7
561.2
576.7
717.7
581.3
684.1
1,386.1
1,017.4
1,271.0
1,267.5
1,441.9
1,157.9
1,514.6
1,389.2
1,269.0
1,159.3
523.1
1,353.7
1,378.7
1,500.8
1,548.0
1,437.0
1,593.1
10"4.
76.5
56.6
76.8
77.5
55.3
63.7
68.3
58.6
54.7
77.4
73.6
66.9
88.9
69.4
72.0
84.2
88.4
77.4
91.3
93.6
82.7
89.5
95.9
88.1
86.9
79.5
95.8
91.8
93.1
95.0
57.0
40.8
40.0
6.8
73.6
41.6
68.2
71.8
91.9
70.7
83.8
87.4
69.6
85.3
78.6
89.1
73.1
88.6
83.1
76.5
72.1
33.5
85.9
87.3
92.3
95.4
88.4
96.3
C-2
C-2
D'I.
]w
147
476
601
722
1,321
1,233
2,225
1,608
2,109
1,742
1,262
2,135
1,123
2,421
2,063
2,493
2,064
3,114
1,981
1,361
2,259
1,441
1,195
1,249
1,463
1,977
1,082
1,581
973
_,227
331
646
704
1,817
1,237
1,755
1,485
1,393
619
1,575
1,282
1,764
2,349
1,675
1,689
1,414
2,087
487
1,536
1,688
1,391
700
841
1,730
1,202
1,048
1,623
1,270
.~
21
289
256
189
369
342
1,102
803
1,397
806
286
1,141
382
1,387
711
762
351
876
268
172
386
203
119
167
184
242
106
265
99
106
878
190
132
553
229
599
772
504
60
627
210
530
1,378
348
495
289
621
44
453
449
306
59
99
338
184
90
277
157
0.14
0.61
0.43
0.26
0.28
0.28
0.50
0.50
0.66
0.46
0.23
0.53
0.34
0.57
0.34
0.31
0.17
0.28
0.14
0.13
0.17
0.14
0.04
0.62
0.42
0.30
0.93
0.76
0.10
0.07
0.11
0.12
0.18
0.06
0.16
0.06
0.06
2.47
0.62
0.60
13.89
0.40
1.83
1.38
0.87
0.08
1.08
0.31
0.38
1.35
0.27
0.39
0.20
0.54
0.03
0.33
0.35
0.26
0.11
0.07
0.24
0.12
0.06
0.19
0.10
0.13
0.13
0.12
0.10
0.17
0.10
0.09
0.26
0.29
0.19
0.30
0.19
0.34
0.52
0.36
0.10
0.40
0.16
0.30
0.59
0.21
0.29
0.20
0.30
0.09
0.29
0.27
0.22
0.08
0.12
0.20
0.15
0.09
0.17
0.12
1.00
0.89
1.53
0.63
0.24
1.07
0.28
1.30
0.67
0.56
0.23
0.65
0.17
0.10
0.28
0.13
Occupational Radiation Exposurm at NRC Licensed Facilities
7birty-SeventhAnnud Report, 2004
!,,2
BIG ROCK POINr
Docket 50-155; DPR-6
1st commercial operation 3/63
Type - BWR
Capacity - (67) MWe
BRAIDWOOD 1, 2
Docket 50-456, 5-457;
NPF-72, NPF-77
1st commercial operation
7/88,10/88
Type - PWRs
Capacity - 1161, 1129 MWe
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
1997
1998
1999
2000
2001
2002
2003
2004
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
48.1
43.5
44.4
43.5
50.9
40.7
35.1
29.5
43.6
48.5
13.0
48.9
56.9
43.6
42.3
50.3
43.8
61.0
45.3
46.1
50.2
51.3
59.1
32.7
51.2
49.5
62.2
22.4
0.0
0.0
0.0
0.0
0.0
0.0
0.0
1,381.8
1,740.2
1,377.2
1,885.9
1,899.3
1,666.1
1,914.7
1,854.9
1,863.3
1,979.1
2,161.6
2,142.8
2,186.4
2,284.0
2,279.9
2,277.8
.|iJi
70.3
59.8
50.1
73.4
77.9
23.5
79.0
90.6
70.8
71.0
78.6
73.5
95.5
71.0
72.8
79.0
77.2
85.2
54.5
79.4
75.3
95.0
54.1
0.0
0.0
0.0
0.0
0.0
0.0
0.0
75.4
84.1
68.9
89.0
86.9
77.2
85.4
82.1
85.4
88.9
95.8
94.9
95.8
96.8
95.6
97.3
.,
165
290
260
195
241
281
300
488
465
285
623
599
479
521
493
297
435
202
251
303
418
351
435
496
419
310
205
258
432
285
226
167
170
336
227
1,460
1,081
1,641
1,059
1.043
1,237
1,134
1,356
1,693
1,869
1,153
1,562
881
975
1,572
986
.
.
136
194
184
181
285
276
180
289
334
175
455
354
160
328
263
155
291
84
222
170
177
232
226
277
152
119
54
55
104
87
89
48
44
121
58
296
186
550
228
273
298
236
334
321
259
146
194
101
91
245
95
0.82
0.67
0.71
0.93
1.18
0.98
0.60
0.59
0.72
0.61
0.73
0.59
0.33
0.63
0.53
0.52
0.67
0.42
0.88
0.56
0.42
0.66
0.52
0.56
0.36
0.38
0.26
0.21
0.24
0.31
0.40
0.28
0.26
0.36
0.25
0.20
0.17
0.34
0.22
0.26
0.24
0.21
0.25
0.19
0.14
0.13
0.12
0.11
0.09
0.16
0.10
3..'
2.83
4.46
4.14
4.16
5.60
6.78
5.13
9.80
7.66
3.61
35.00
7.24
2.81
7.52
6.22
3.08
6.64
1.38
4.90
3.69
3.53
4.52
3.82
8.47
2.97
2.40
0.87
2.46
-
0.21
0.11
0.40
0.12
0.14
0.18
0.12
0.18
0.17
0.13
0.07
0.09
0.05
0.04
0.11
0.04
Big Rock Point was shut down in 9/97 and is no longer included in the count of operating reactors. Parentheses indicate plant
capacity when plant was operational.
C-3
NUREG-071 3
NUREG-071 3
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
7hirty-Seventh AnnualReport,2004
Thiny-Severnh Annual Report; 2004
.,.
-.
BROWNS FERRY 12,2,3
Docket 50-259, 50-260,
50-296
DPR - 33, - 52, - 68
1st commercial operation
8/74, 375, 3177
Type - BWRs
Capacity-(1065), 1118.
1118 MWe
BRUNSWICK 1, 2
Docket 50-324, 50-325;
DPR-62, -71
1st commercial operation
3/77, 11/75
Type - BWRs
Capacity - 872, 900 MWe
2
.
_
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
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
_
161.7
337.6
1,327.5
1,992.1
2,393.0
2,182.1
2,132.9
2,025.4
1,641.0
1,431.9
368.2
0.0
0.0
0.0
0.0
0.0
445.0
979.9
675.1
860.2
1,165.8
1,972.8
1,928.8
1,961.9
2,091.0
2,143.8
2,074.0
2,069.0
2,014.5
2,104.7
297.2
291.1
1,173.1
810.0
687.2
925.2
540.3
636.7
761.3
822.2
1,051.3
1,152.4
990.8
990.9
991.6
952.8
375.9
470.0
1,268.4
1,411.7
1,261.1
1,474.0
1,521.0
1,494.7
1,571.2
1,576.0
1,568.0
1,676.9
1,690.6
,
.
I.
*
a.
a..
2,743
2,530
1,985
2,479
2,869
347
232
876
3.
-
_
17.8
26.9
73.7
73.5
79.1
73.6
69.5
67.6
54.3
54.2
11.9
0.0
0.0
0.0
0.0
0.0
17.7
32.2
66.8
83.4
98.6
93.0
90.2
87.7
85.1
97.1
90.7
95.4
93.6
95.5
56.0
55.7
83.7
60.1
52.2
56.9
50.3
44.3
51.5
58.4
69.1
80.6
70.1
65.8
67.8
64.5
27.9
33.8
83.0
92.9
85.9
94.1
94.3
92.8
95.6
95.8
94.5
95.6
94.5
2,838
3,497
3,360
3,410
3,172
2,854
3,074
3,184
3,390
2,707
2,725
1,831
2,670
3,594
3,362
2,567
1,904
2,268
1,612
1,741
1,657
1,525
1,977
2,608
3,242
1,265
1,512
1,458
2,891
3,788
3,854
4,957
5,602
5,046
4,057
3,370
3,052
2,648
3,844
3,182
2,586
2,690
2,921
3,049
2,657
2,784
2,212
2,005
1,818
1,648
1,623
1,743
1,794
2,140
1,776
1,593
1,768
2,398
2,230
3,375
1,954
1,164
1,054
1,186
1,158
657
1,311
356
519
870
861
413
389
522
368
447
333
294
358
603
673
326
1,120
1,004
2,602
3,870
2,638
3,792
3,475
3,260
2,804
1,909
1,419
1,747
1,786
1,548
778
623
872
999
683
716
411
396
418
322
303
276
249
245
0.13
0.09
0.44
0.72
0.56
0.62
0.69
0.66
0.99
0.62
0.41
0.34
0.37
0.34
0.24
0.48
0.19
0.19
0.24
0.26
0.16
0.20
0.23
0.23
0.26
0.20
0.19
0.18
0.23
0.21
0.26
0.74
0.69
0.90
1.02
0.68
0.76
0.62
0.65
0.69
0.57
0.46
0.66
0.46
0.49
0.30
0.23
0.30
0.70
0.26
0.26
0.19
0.20
0.23
0.20
0.19
0.16
0.14
0.11
2.15
0.69
0.66
0.89
0.67
0.81
1.12
1.10
2.06
1.36
3.16
0.80
0.53
1.29
1.00
0.35
0.20
0.27
0.19
0.21
0.16
0.14
0.17
0.30
0.32
1.10
3.85
0.86
3.21
5.63
2.85
7.02
5.46
4.28
3.41
1.82
1.23
1.76
1.80
1.56
0.82
1.66
1.86
0.79
0.48
0.57
0.28
0.26
0.28
0.20
0.19
0.18
0.15
0.14
Browns Ferry 1 remains in the count of operatng reactors but was placed on Administrative Hold in June of 1985. Parentheses
indicate plant capacity when plant was operational.
NUREG-0713
CA
C-4
7birtySeventh Annual Reort,2004
Occupational Radiation Exposure at NRC Licensed Facilities
VW .
i1 ;'. I9
BYRON 1,2
Docket 50-454, 50-455;
NPF-37, NPF-66
1st commercial operation
9/85,8/87
Type- PWRs
Capacity- 1152,1125 Me
CALLAWAY 1
Docket 50-483; NPF-30
1st commercial operation 12184
Type - PWR
Capacity- 1125 MWe
CALVERT CLIFFS 1, 2
Docket 50-317, 50-318;
DPR-53, -69
1st commercial operation
5175, 4/77
Type - PWRs
Capacity - 870, 858 MWe
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
894.5
650.9
1,534.7
1,812.6
1,567.3
1,816.3
1,888.4
1,785.6
1,953.3
1,900.6
1,758.4
1,856.7
1,869.8
2,064.2
2,196.9
2,301.5
2,205.0
2,294.8
2,277.4
967.4
865.2
759.0
1,069.2
1,000.3
960.7
1,193.1
967.5
1,002.9
1,196.4
989.6
1,066.0
1,022.2
972.2
981.3
1,137.5
954.5
955.0
1,104.3
892.8
753.4
583.0
1,188.5
1,161.0
1,309.9
1,379.7
1,238.3
1,397.2
1,389.4
1,189.8
1,530.0
1,207.3
1,397.7
333.6
161.1
1,085.0
1,271.2
1,462.1
1,342.1
1,542.8
88.6
70.9
86.3
90.2
78.8
89.9
90.1
83.5
90.7
85.5
79.3
86.6
85.9
92.3
97.4
97.8
93.8
97.2
97.7
90.0
81.3
71.1
93.4
85.4
84.1
99.7
83.0
86.4
100.0
84.7
90.5
100.0
91.3
88.7
99.8
86.7
86.2
96.2
78.9
95.2
72.1
75.8
74.0
84.1
83.1
73.7
81.6
79.3
68.4
87.2
71.8
81.0
20.1
11.0
64.7
73.9
83.9
79.4
89.9
C-5
C-5
1,081
1,826
1,222
1,109
1,396
1,077
1,021
1,370
962
1,107
1,610
1,546
1,809
1,478
959
719
1,287
824
906
964
1,052
1,082
353
1,055
1,134
280
1,133
1,126
191
1,062
980
248
929
1,098
244
873
983
252
1,124
507
2,265
1,391
1,428
1,496
1,555
1,805
1,915
1,369
1,598
1,296
1,384
1,296
1,786
2,019
1,974
1,979
1,462
1,482
1,203
3.
76
769
459
172
434
268
199
432
280
306
455
241
275
239
194
59
195
87
89
36
225
393
27
283
442
21
336
225
14
187
248
12
201
321
16
107
96
8
121
74
547
500
805
677
607
1,057
668
479
694
347
412
291
346
304
132
330
405
454
235
-
1.!
0.07
0.42
0.38
0.16
0.31
0.25
0.08
1.18
0.30
0.19
0.11
0.32
0.29
0.28
0.28
0.16
0.15
0.16
0.20
0.08
0.15
0.24
0.14
0.16
0.26
0.13
0.15
0.12
0.11
0.10
0.04
0.04
0.04
0.26
0.52
0.03
0.28
0.46
0.02
0.35
0.22
0.04
0.21
0.36
0.08
0.27
0.39
0.07
0.30
0.20
0.07
0.18
0.25
0.05
0.22
0.29
0.07
0.12
0.10
0.03
0.09
0.28
0.15
0.09
0.03
0.09
0.01
0.19
0.23
0.01
0.21
0.33
0.01
0.11
0.10
0.01
0.11
0.14
0.15
0.24
0.36
0.56
0.45
0.39
0.59
0.35
0.35
0.43
0.27
0.30
0.22
0.10
0.19
0.15
0.07
0.17
0.28
0.31
0.20
0.94
0.42
0.69
0.52
0.44
0.85
0.48
0.34
0.58
0.23
0.34
0.21
1.04
1.89
0.12
0.26
0.28
0.34
0.15
NIJREG-071 3
NURtEG-0713
1Xhirty-Seenth Annual Reort, 20024
Occupational Radiation Exposmre at NRC Licensed Facilities
Occupational Radiation Ezposure a: NRC licensed Facilities
Thiny-Seventh Annual Repori 2004
SreL
;
,j,..
;s
,5S
1998
1997
1998
1999
2000
2001
2002
2003
2004
1986
CATAWBA 1, 2
1987
Docket 50-413, 50-414;
1988
NPF-35, NPF-52
1989
1st commercial operation
1990
6185, 8186
1991
Type- PWRs
1992
Capacity- 1129,1129 MWe
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1988
CLINTON
1989
Docket 50-461; NPF-62
1st commercial operation 11187 1990
1991
Type- BWR
1992
Capacity- 1022 MWe
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
3
1985
COLUMBIA GENERATING
1986
Docket 50-397; NPF-21
1st commercial operation 12184 1987
1988
Type - BWR
1989
Capacity- 1107 MWe
1990
1991
1992
1993
1994
1995
1996
1997
1998
CALVERT CUFFS 1. 2
(continued)
i
.
1,438.5
1,499.6
1,523.1
1,521.4
1,575.7
1,554.7
1,380.0
1,558.4
1,653.7
638.9
1,651.2
1,675.2
1,733.6
1,618.3
1,691.5
1,962.8
1,898.1
2,105.2
2,011.9
1,879.1
2,028.2
2,006.4
2,046.7
2,038.3
2,119.9
2,238.0
1,991.8
2,111.4
701.3
348.3
435.8
722.7
589.7
701.5
883.3
731.1
634.7
0.0
0.0
537.0
784.2
896.8
872.0
990.5
910.8
616.0
616.0
639.0
707.7
727.2
684.7
508.5
682.3
849.6
803.8
824.7
662.9
697.0
789.5
!
82.4
89.1
89.3
90.1
92.7
91.7
81.7
90.9
95.7
49.9
75.9
77.2
79.5
70.8
74.6
83.9
81.5
90.2
85.3
80.5
89.3
89.6
90.2
90.3
92.9
97.2
89.2
93.0
84.2
48.5
55.1
80.8
68.6
79.6
94.8
83.0
66.7
0.0
0.0
63.5
87.8
98.5
90.5
99.1
92.6
87.6
74.4
70.8
71.8
78.3
67.5
50.3
65.6
79.5
75.2
83.8
82.2
72.7
75.3
S.
1,167
1.091
1,042
1,134
912
895
1,582
1,671
1,205
1,724
1,865
2,009
1,6B0
2.174
1,871
1,515
1,564
1,268
1,892
1,588
1,561
1,123
1,024
1,185
960
884
1,409
1,123
769
1,198
1,390
1,010
1,195
1,253
409
1,182
1,154
738
866
637
1,248
329
1,418
372
1,622
755
1,013
1,201
1,050
1,299
1,348
1,088
1,489
1,385
1,870
1,694
1,453
1,218
1,220
i
5
.5
*.
.5
i
S
239
229
187
192
135
167
245
265
144
286
449
556
334
809
462
414
396
207
462
302
266
162
119
187
116
81
211
123
130
372
553
233
431
498
63
316
350
172
177
87
253
34
208
57
283
119
222
406
353
492
536
387
612
469
866
456
373
251
286
3 Energy Northwest has changed the name of Washington Nuclear 2 to Columbia Generating Station.
NUREG-0713
C-6
i
S.
-
3.
, _E
0.20
0.21
0.18
0.17
0.15
0.19
0.16
0.16
0.12
0.17
0.24
0.28
0.20
0.37
0.25
0.27
0.25
0.16
0.24
0.19
0.17
0.14
0.12
0.18
0.12
0.09
0.15
0.11
0.17
0.31
0.40
0.23
0.36
0.40
0.15
0.27
0.30
0.23
0.17
0.14
0.20
0.10
0.15
0.15
0.17
0.16
0.22
0.34
0.34
0.38
0.40
0.36
0.41
0.34
0.46
0.27
0.26
0.21
0.23
0.17
0.15
0.12
0.13
0.09
0.11
0.18
0.17
0.09
0.45
0.27
0.33
0.19
0.50
0.27
0.21
0.21
0.10
0.23
0.16
0.13
0.08
0.06
0.09
0.06
0.04
0.11
0.06
0.19
1.07
1.27
0.32
0.73
0.71
0.07
0.43
0.55
0.16
0.32
0.04
0.24
0.06
0.31
0.19
0.36
0.64
0.50
0.68
0.78
0.76
0.90
0.55
1.08
0.55
0.56
0.38
0.36
Occupational Radiation Exposure at NRC Licensed Facilities
7hirty-Seventh Annud Report, 2004
F:fI
;.L:1a
COLUMBIAGENERATING'
(continued)
COMANCHE PEAK 1, 2
Docket 50-445, 50-446;
NPF-87,89
1st commercial operation
8/90, 8/93
Type - PWR
Capacity- 1150, 1150 MWe
COOK 1,2
Docket 50-315; DPR-58, -74
1st commercial operation
8/75,7/78
Type - PWRs
Capacity- 1000, 1060 MWe
COOPER STATION
Docket 50-298; DPR-46
1st commercial operation 7/74
Type - BWR
Capacity - 764 MWe
3
1999
2000
2001
2002
2003
2004
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
694.7
979.6
939.3
1,023.0
866.9
1,022.5
644.4
830.8
853.8
1,750.0
2,022.6
1,804.8
2,002.4
2,037.8
1,981.5
2,104.7
2,085.9
1,887.0
2,020.6
2,169.5
807.4
573.0
744.8
1,373.0
1,552.4
1,557.3
1,461.6
1,456.5
1,526.0
925.4
1,307.1
1,199.5
1,160.4
1,433.1
1,318.5
1,837.4
760.9
1,927.7
1,105.2
1,656.0
1,938.9
1,189.7
0.0
0.0
560.1
1,794.3
1,756.0
1,557.6
1,909.2
456.4
433.3
538.2
576.0
591.0
448.3
457.1
622.3
396.6
411.9
70.0
96.3
88.1
97.5
81.8
94.6
82.2
84.0
81.2
93.7
92.5
81.4
93.4
94.9
90.9
95.3
94.7
86.9
91.6
95.1
83.1
76.1
73.6
65.3
74.1
73.4
69.8
71.2
75.3
47.6
73.4
70.2
63.5
72.8
67.9
90.2
50.8
98.5
65.2
82.1
92.7
59.7
0.0
0.0
28.1
89.2
87.3
75.7
91.4
83.6
75.5
86.2
91.0
87.6
71.2
71.2
84.6
63.3
67.2
1,022
706
1,515
647
1,618
716
985
1,128
945
970
951
1,462
870
967
1,316
759
853
1,106
639
864
395
802
778
1,445
1,345
1,341
1,527
1,418
1,559
1,984
1,774
1,696
2,266
1,575
1,851
815
1,954
587
1,748
1,310
1,114
1,884
1,155
1,662
2,506
423
1,624
1,408
1,015
579
763
315
297
426
785
935
743
1,383
1,598
.
155
53
227
47
205
66
148
188
109
90
179
288
146
232
251
78
115
225
66
135
116
300
336
718
493
656
699
658
762
945
745
666
867
493
580
69
492
44
479
203
214
550
105
171
338
27
278
210
156
117
350
198
158
221
859
579
542
1,293
799
Energy Northwest has changed the name of Washington Nuclear 2 to Columbia Generating Station.
CC-7
-
ja.
0.15
0.08
0.15
0.07
0.13
0.09
0.15
0.17
0.12
0.09
0.19
0.20
0.17
0.24
0.19
0.10
0.13
0.20
0.10
0.16
0.29
0.37
0.43
0.50
0.37
0.49
0.46
0.46
0.49
0.48
0.42
0.39
0.38
0.31
0.31
0.08
0.25
0.07
0.27
0.15
0.19
0.30
0.09
0.10
0.14
0.06
0.17
0.15
0.15
0.20
0.46
0.63
0.53
0.52
1.09
0.62
0.73
0.93
0.50
0.22
0.05
0.24
0.05
0.24
0.06
0.23
0.23
0.13
0.05
0.09
0.16
0.07
0.11
0.13
0.04
0.06
0.12
0.03
0.06
0.14
. 0.52
0.45
0.52
0.32
0.42
0.48
0.45
0.50
1.02
0.57
0.56
0.75
0.34
0.44
0.04
0.65
0.02
0.43
0.12
0.11
0.46
0.60
0.02
0.16
0.13
0.08
0.26
0.81
0.37
0.27
0.37
1.92
1.27
0.87
3.26
1.94
UE-7
NUREG-0713
Mrty-SeventhAnnudReport, 2004
nulRpr;20
Occupational Radiation Exposure at NRC licensed Facilities
iesdFcliisTiySvn
Raito
R
Ocuptina xouea
9
COOPER STATION
(continued)
CRYSTAL RIVER 3
Docket 50-302; DPR-72
1st commercal operation 3/77
Type - PWR
Capacity - 838 MWe
DAVIS-BESSE 1
Docket 50-346; NPF-3
1st commercial operation 7/78
Type - PWR
Capacity- 882 MWe
NUREG-0713
..
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
,!li
i.*.
127.3
480.0
652.3
493.4
564.3
602.0
566.3
731.0
436.1
262.2
486.5
742.1
622.8
555.9
743.2
539.2
592.7
719.0
511.4
702.6
311.5
453.0
404.1
490.4
589.8
452.1
774.2
344.2
319.5
436.0
690.2
352.8
497.8
654.6
632.1
722.4
711.9
866.3
290.8
0.0
739.9
727.5
819.4
741.6
831.0
749.0
831.4
326.4
381.0
256.4
531.4
390.8
592.1
518.5
238.3
3.3
618.0
144.1
.
9:
21.5
74.7
96.2
67.9
76.2
79.4
78.8
96.4
58.8
35.1
66.8
97.9
84.4
75.9
98.1
74.2
80.9
98.6
74.1
94.7
41.4
58.9
53.2
62.2
76.0
58.8
94.5
47.6
41.8
60.9
84.0
48.8
63.8
82.0
76.1
85.0
84.3
100.0
37.7
0.0
90.3
87.8
97.6
89.2
99.4
90.8
98.1
48.7
67.0
36.2
67.4
51.5
73.0
62.5
31.2
1.3
89.6
27.1
C-8
C-8
L.
1,980
895
549
942
1,202
1,174
1,099
463
1,130
333
1,095
468
1,125
977
318
963
1,309
362
882
481
643
1,150
1,053
1,120
780
1,720
549
1,976
1,057
1,384
569
880
1,441
821
1,403
683
1,079
209
1,192
973
313
1,324
257
902
128
961
131
421
304
1,283
578
1,350
718
1,088
718
981
625
1,183
a
.
1,333
320
103
251
343
379
405
84
391
79
228
48
174
182
48
200
169
39
135
47
321
495
625
408
177
552
49
689
472
488
64
234
476
116
424
60
228
8
353
179
19
251
15
148
5
127
4
48
30
154
58
164
80
177
71
124
47
307
0.67
0.36
0.19
0.27
0.29
0.32
0.37
0.18
0.35
0.24
0.21
0.10
0.16
0.19
0.15
0.21
0.13
0.11
0.15
0.10
0.50
0.43
0.59
0.36
0.23
0.32
0.09
0.35
0.45
0.35
0.11
0.27
0.33
0.14
0.30
0.09
0.21
0.04
0.30
0.18
0.06
0.19
0.06
0.16
0.04
0.13
0.03
0.11
0.10
0.12
0.10
0.12
0.11
0.16
0.10
0.13
0.08
0.26
10.47
0.67
0.16
0.51
0.61
0.63
0.72
0.11
0.90
0.30
0.47
0.06
0.28
0.33
0.06
0.37
0.28
0.05
0.26
0.07
1.03
1.09
1.55
0.83
0.30
1.22
0.06
2.00
1.48
1.12
0.09
0.66
0.96
0.18
0.67
0.08
0.32
0.01
1.21
0.03
0.35
0.02
0.20
0.01
0.17
0.15
0.08
0.60
0.11
0.42
0.14
0.34
0.30
37.58
0.08
2.13
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
775iny-SeventhAnnud Report,2004
Thiray-SeventA AnnuidRepori. 2004
.I
I~
DAVIS-BESSE 1
(continued)
DIABLO CANYON 1, 2
Docket 50-275, 50-323;
DPR-80, DPR-82
1st commercial operation
5t85, 3186
Type - PWRs
Capacity - 1087, 1087 MWe
DRESDEN 1', 2,3
Docket 50-010, 50-237, 50-249;
DPR-2, -19, -25
1st commercial operation 7t60,
'
6n70, 1171
Type- BWRs
Capacity - (197), 850, 850 Mte
4
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1969
1970
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
880.0
500.0
703.6
915.2
729.5
768.4
920.4
775.8
820.0
699.8
841.3
770.8
875.6
106.0
0.0
657.8
641.5
1,688.6
1,386.1
1,899.0
1,952.6
1,809.6
1,995.7
2,008.6
1,832.6
1,950.3
2,003.6
1,948.7
1,955.1
1,902.8
1,940.1
2,067.7
1,860.0
1,970.7
1,736.3
99.7
163.1
394.5
1,243.7
1,112.2
842.5
708.1
1,127.2
1,132.9
1,242.2
1,013.0
1,074.4
1,035.7
1,085.3
913.6
789.8
903.0
740.5
933.9
1,014.7
1,184.2
1,107.8
675.2
_..I*
C
98.6
56.7
81.8
100.0
83.4
88.0
100.0
85.3
94.0
83.2
95.6
87.3
100.0
12.6
0.0
77.6
80.6
83.0
67.6
87.5
91.0
83.8
90.9
91.4
83.3
90.0
90.7
92.7
92.8
90.1
92.0
96.4
88.4
91.6
83.5
404
1,377
1,000
287
1,244
861
256
949
213
980
397
1,109
119
1,983
1,047
161
1,260
1,170
1,826
1,646
1,441
2.040
1.850
1.508
2,317
1,615
1,462
1,331
1,313
1,566
1,057
1,074
1,016
1,004
1,230
54.9
54.6
80.8
77.0
79.5
74.7
55.0
51.5
77.9
65.6
55.3
64.5
52.6
74.0
75.8
83.1
76.6
60.7
1,341
1,594
2,310
1,746
1,862
1,946
2,407
2,717
2,331
2,572
2,854
2,261
2,817
3,111
2,052
2,414
2,259
2,235
2,044
3.
38
489
216
19
348
144
7
167
10
155
28
168
6
403
220
7
304
336
877
465
323
546
459
281
590
286
176
219
173
449
181
118
149
135
254
286
143
715
728
939
1,662
3,423
1,680
1,694
1,529
1,800
2,105
2,802
2,923
3,582
1,774
1,686
2,668
1,145
1,409
1,131
1,400
1,005
~_
0.09
0.36
0.22
0.07
0.28
0.17
0.03
0.18
0.05
0.16
0.07
0.15
0.05
0.20
0.21
0.04
0.24
0.29
0.48
0.28
0.22
0.27
0.25
0.19
0.26
0.18
0.12
0.17
0.13
0.29
0.17
0.11
0.15
0.13
0.21
0.70
1.04
1.48
0.96
0.91
0.79
0.75
0.77
1.20
1.14
1.26
0.78
0.60
0.86
0.56
0.58
0.50
0.63
OA9
0.04
0.98
0.31
0.02
0.48
0.19
0.01
0.22
0.01
0.22
0.03
0.22
0.01
3.81
0.01
0.47
0.20
0.63
0.24
0.17
0.30
0.23
0.14
0.32
0.15
0.09
0.11
0.09
0.24
0.09
0.06
0.08
0.07
0.15
2.87
0.88
1.81
0.59
0.84
1.97
4.83
1.49
1.50
1.23
1.78
1.96
2.71
2.69
3.92
2.25
1.87
3.60
1.23
1.39
0.96
1.26
1.49
Dresden 1 has been shut down since 1978, and In 1985 it was decided that it would not be put in commercial operation again.
Therefore, it is no longer included in the count of operating reactors. Parentheses Indicate plant capacity when plant was
operational.
C9
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
7birtySeventhAnnualReport,2004
S
Thirty-Seventh Annual Rtpors, 20(Xi
-W]1.
..
.
S
DRESDEN 14, 2, 3
(continued)
DUANE ARNOLD
Docket 50-331; DPR-49
1st commercial operation 2/75
Type - BWR
Capacity-56BMWo
FARLEY 1,2
Docket 50-348, 50-364;
NPF-2, -8
1st commercial operation
12/77, 7/81
Type- PWRs
Capacity - 851, 849 MWe
4
.
.
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
872.4
960.1
690.2
643.1
812.6
1,096.2
1,354.7
1,410.9
1,506.4
1,427.4
1,547.0
1,555.9
1,405.5
305.2
353.6
149.2
352.0
339.1
277.7
278.5
283.0
329.4
236.2
365.5
308.4
386.5
388.5
367.4
503.7
416.5
393.4
498.6
452.5
476.8
474.4
438.3
416.6
507.3
439.5
522.0
455.2
561.2
713.8
211.0
557.3
310.2
1,271.5
1,356.5
1,447.0
1,368.2
1,409.4
1,369.7
1,567.7
1,402.9
1,464.0
1,464.0
1,331.7
*
.
IJ.
be
b
. ..
*
75.4
68.5
51.7
49.8
47.7
79.5
90.6
92.5
97.3
94.5
95.7
93.5
84.8
78.0
78.9
33.2
78.0
73.3
69.8
74.7
62.9
72.9
53.8
82.0
64.7
75.2
79.0
75.8
94.5
81.9
79.5
94.0
83.8
90.7
94.4
86.6
84.3
98.4
86.8
94.4
84.8
98.3
86.5
28.6
69.3
41.4
79.2
83.0
86.6
81.1
83.8
84.7
92.3
84.6
86.7
88.1
81.8
1,812
2,751
2,338
2,482
1,788
2,747
2,311
3,243
2,341
2,769
2,819
2,098
2,044
350
538
1,112
757
1,108
1,286
524
1,468
611
1,414
476
1,094
1,136
425
1,460
336
1,043
1,043
493
1,129
1,093
352
1,019
834
317
898
319
829
220
527
1,227
1,330
1,331
1,453
1,938
2,046
2,551
2,314
1,871
1,840
2,206
1,700
1,645
2,018
0.34
0.60
0.36
0.35
0.26
0.17
0.18
0.18
0.11
0.14
0.13
0.17
0.19
0.30
0.58
0.88
0.36
0.61
0.61
0.44
0.77
0.31
0.79
0.39
0.61
0.54
0.46
0.59
0.60
0.48
0.39
0.24
0.32
0.25
0.18
0.23
0.24
0.14
0.15
0.11
0.15
0.09
0.20
0.52
0.33
0.38
0.33
0.53
0.44
0.31
0.37
0.32
0.30
0.34
0.27
0.39
0.40
619
1,655
833
875
456
467
427
591
262
401
355
357
381
105
299
974
275
671
790
229
1,135
189
1,112
187
667
614
194
861
202
502
407
120
357
270
63
237
201
44
138
35
124
19
108
643
435
512
484
1,021
902
799
858
598
552
749
457
648
805
0.71
1.72
1.21
1.36
0.74
0.43
0.32
0.42
0.17
0.28
0.23
0.23
0.27
0.34
0.85
6.53
0.78
1.98
2.84
0.82
4.01
0.57
4.71
0.51
2.16
1.59
0.50
2.34
0.40
1.21
1.03
0.24
0.79
0.57
0.13
0.54
0.48
0.09
0.31
0.07
0.27
0.03
0.15
3.05
0.78
1.65
0.38
0.75
0.62
0.58
0.61
0.44
0.35
0.53
0.31
0.44
0.60
Dresden 1 has been shut down since 1978, and in 1985 it was decided that i would not be put in commercial operation again.
Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was
operational
NUREG-0713
0
C-10
_UE-7
_ _-
Ahirty-venthl Annuls Report, 2004
Thirty-&vendh Arni u4 Report;. 2004
FARLEY 1,2
(continued)
FERMI 2
Docket 50-341; NPF-43
1st commercial operation 1/88
Type - BWR
Capacity- 1089 MWe
FITZPATRICK
Docket 50-333; DPR-59
1st commercial operation 7/75
Type - BWR
Capacity - 813 MNWe
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
Occupational Ra~diton Exposumc at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
1,455.5
1,587.2
1,311.2
1,549.2
1,449.7
1,313.9
1,436.0
1,430.1
1,384.3
1,558.0
1,592.6
1,496.8
624.0
848.2
739.0
874.3
984.3
0.0
618.3
577.5
637.0
815.8
1,082.7
939.6
975.0
1,059.0
925.3
962.3
489.0
460.5
497.0
349.0
509.5
562.9
583.6
546.2
576.2
492.3
711.2
496.2
514.0
727.5
543.8
399.7
0.0
559.6
588.4
569.8
623.3
756.2
562.8
749.7
685.9
807.2
751.0
793.0
735.0
88.3
93.0
83.8
90.9
89.0
80.9
91.4
88.6
84.4
93.5
95.3
89.4
68.5
84.7
77.0
81.3
92.9
2.2
86.9
69.1
66.6
79.9
99.5
87.6
90.9
98.7
86.9
90.0
71.6
68.4
72.1
50.8
70.3
74.7
75.0
70.6
76.8
63.7
90.6
70.3
69.0
92.3
72.6
53.4
0.0
81.7
83.2
74.5
83.1
95.9
78.0
95.5
88.4
98.9
93.3
97.9
92.1
c-il
C-ll
1,284
1,035
1,574
1.150
1,105
1,380
1,102
1,683
1,810
772
788
1,141
1,270
462
1,223
1,213
360
1,130
390
1,402
623
1,362
461
1,266
1,202
463
1,207
1,302
600
1,380
904
850
2,056
2,490
2,322
1,715
1,610
1,845
1,185
1,578
1,553
1,027
1,536
1,269
2,374
1,427
1,595
1,249
1,384
662
1,781
558
1267
665
1,234
298
1,091
333
250
460
232
278
432
190
360
321
96
111
107
255
83
228
245
35
213
28
157
49
208
36
146
169
38
168
145
202
1,080
909
859
2,040
1.425
1,190
1,090
971
1,051
411
940
786
377
884
333
674
232
322
327
357
91
358
68
301
63
231
51
186
0.26
0.24
0.29
0.20
0.25
0.31
0.17
0.21
0.18
0.13
0.14
0.09
0.20
0.18
0.19
0.20
0.10
0.19
0.07
0.11
0.08
0.15
0.08
0.12
0.14
0.08
0.14
0.11
0.34
0.78
1.01
1.01
0.99
0.57
0.51
0.64
0.60
0.57
0.35
0.60
0.51
0.37
0.58
0.26
0.28
0.16
0.20
0.26
0.26
0.14
0.20
0.12
0.24
0.10
0.19
0.17
0.17
0.23
0.16
0.35
0.15
0.19
0.33
0.13
0.25
0.23
0.06
0.07
0.07
0.41
0.10
0.31
0.28
0.04
0.05
0.27
0.08
0.25
0.03
0.15
0.17
0.04
0.18
0.15
0.41
2.35
1.83
2.46
4.00
2.53
2.04
2.00
1.69
2.13
0.58
1.89
1.53
0.52
1.63
0.83
0.41
0.55
0.57
0.57
0.12
0.64
0.09
0.44
0.08
0.31
0.06
0.25
NUREG-071 3
NUREG-071 3
7birty-SeventhAnnudReport, 2004
Thirty-Seventh Annual Report 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
.. *.
.
C.
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
NUREG-0713 NUREG-71 3
..
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
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
5.
L
252.3
265.9
351.8
342.3
440.0
242.3
260.9
418.0
330.4
279.2
367.0
431.8
366.0
315.5
395.7
290.0
391.1
303.4
369.7
492.8
402.8
374.9
435.9
387.7
409.2
443.8
401.2
434.0
399.6
463.5
327.8
293.6
409.5
253.7
365.2
248.8
365.6
386.5
355.0
370.5
399.0
289.0
365.0
378.1
436.7
433.3
459.0
423.1
369.2
414.3
418.6
417.6
419.6
405.3
437.0
347.9
444.6
67.4
69.5
79.4
75.1
95.7
60.4
72.3
89.7
73.1
59.9
73.7
94.3
75.4
74.1
89.2
64.2
91.7
65.9
80.8
99.6
83.2
79.5
93.6
82.5
89.2
93.5
88.3
92.3
87.0
97.0
62.4
76.7
58.2
85.5
80.6
72.8
76.0
82.1
58.8
74.6
77.2
87.9
87.4
91.5
87.4
75.9
84.4
86.7
86.9
86.3
83.2
89.6
71.1
91.8
012
C-12
469
516
535
596
451
891
822
604
860
913
982
756
1,247
1,594
1,210
760
284
802
713
211
627
740
258
788
676
249
770
742
914
215
340
677
319
884
685
758
530
657
878
1,073
925
1,117
969
713
845
901
773
897
1,254
991
947
832
856
679
738
976
533
294
313
297
410
126
668
458
217
433
563
373
75
388
272
93
290
57
272
157
23
139
226
41
224
159
35
226
164
212
22
430
1,032
224
1,225
538
636
401
450
592
708
655
1,140
855
395
426
357
344
295
605
347
328
261
193
138
136
168
81
0.63
0.61
0.56
0.69
0.28
0.75
0.56
0.36
0.50
0.62
0.38
0.10
0.31
0.17
0.08
0.38
0.20
0.34
0.22
0.11
0.22
0.31
0.16
0.28
0.24
0.14
0.29
0.22
0.23
0.10
1.26
1.52
0.70
1.39
0.79
0.84
0.76
0.68
0.67
0.66
0.71
1.02
0.88
0.55
0.50
0.40
0.45
0.33
0.48
0.35
0.35
0.31
0.23
0.20
0.18
0.17
0.15
1.17
1.18
0.84
1.20
0.29
2.76
1.76
0.52
1.31
2.02
1.02
0.17
1.06
0.86
0.24
1.00
0.15
0.90
0.42
0.05
0.35
0.60
0.09
0.58
0.39
0.08
0.56
0.38
0.53
0.05
1.31
3.51
0.55
4.83
1.47
2.56
1.10
1.16
1.67
1.91
1.64
3.94
2.34
1.04
0.98
0.82
0.75
0.70
1.64
0.84
0.78
0.63
0.46
0.34
0.31
0.48
0.18
7hirty-Seventh Annual Arport,2004
,iiySvetAlua Reot 204Ocptoa
GINNA
(continued)
GRAND GULF
Docket 50-416; NPF-29
1st commercial operation 7/85
Type - BWR
Capacity- 1207 MWe
HADDAM NECK 5
Docket 50-213; DPR-61
1st commercial operation 1/68
Type- PWR
Capacity - (560) MWe
1998
1999
2000
2001
2002
2003
2004
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
491.8
403.4
434.2
488.0
438.0
440.4
490.5
494.7
920.7
1,136.6
932.6
883.5
1,085.2
969.0
936.4
1,143.2
952.9
1,096.2
1,234.9
1,049.2
962.1
1,217.5
1,129.8
1,145.0
1,241.2
1,165.2
438.5
424.7
502.2
515.6
293.1
521.4
494.3
482.9
480.7
563.4
493.0
426.8
487.5
543.9
453.7
404.0
556.1
294.8
304.6
397.4
356.4
142.7
444.4
465.2
448.6
455.6
439.4
331.8
-1.3
0.0
0.0
Occupational Radiation Exposure at NRC Licensed Facilities
aiainEps
tNC iesdFclte
100.0
85.6
91.6
100.0
91.3
91.1
99.5
60.9
82.2
96.7
80.0
78.9
94.0
83.7
81.5
96.6
80.4
88.7
100.0
88.9
81.3
99.4
93.0
93.6
98.6
92.2
91.2
89.9
82.5
83.9
98.6
87.5
75.0
84.3
93.4
77.8
71.7
98.4
53.6
54.0
70.3
67.2
32.2
76.4
80.1
81.6
77.7
77.7
55.7
0.0
0.0
0.0
161
641
429
140
535
510
111
1,486
1,358
692
1,972
1,765
699
2,032
1,807
455
1,589
1,564
514
1,410
1,180
289
1,109
1,060
290
1.243
138
734
289
355
951
550
795
644
894
216
1,226
1,860
1,554
559
1,645
1,430
384
1,945
1,763
735
1,455
979
1,168
797
1,004
463
1,006
673
219
423
545
15
175
76
10
80
75
7
436
420
147
498
482
94
484
332
56
342
357
105
304
226
35
185
176
31
158
106
689
342
325
697
201
703
449
641
117
1,162
1,353
1,036
126
1,384
1,216
101
1,567
750
237
596
421
590
202
408
135
442
175
11
94
109
0.09
0.27
0.18
0.07
0.15
0.15
0.07
0.29
0.31
0.21
0.25
0.27
0.13
0.24
0.18
0.12
0.22
0.23
0.20
0.22
0.19
0.12
0.17
0.17
0.11
0.13
0.77
0.94
1.18
0.91
0.73
0.37
0.88
0.70
0.72
0.54
0.95
0.73
0.67
0.23
0.84
0.85
0.26
0.81
0.43
0.32
0.41
0.43
0.51
0.25
0.41
0.29
0.44
0.26
0.05
0.22
0.20
0.03
0.43
0.18
0.02
0.18
0.17
0.02
0.88
0.46
0.13
0.53
0.55
0.09
0.50
0.35
0.05
0.36
0.33
0.09
0.29
0.23
0.03
0.16
0.15
0.03
0.14
0.24
1.62
0.68
0.63
2.38
0.39
1.42
0.93
1.33
0.21
2.36
3.17
2.13
0.23
3.05
3.01
0.18
5.32
2.46
0.60
1.67
2.95
1.33
0.43
0.91
0.30
1.01
0.53
-
5Haddam
Neck (also known as Connecticut Yankee) was shut down 12/4/96 and is no longer inthe count of operating reactors.
Parentheses indicate plant capacity when plant was operational.
C-13
C-13
NUREG-071 3
NUREG-071 3
7birV-&venth Annuai Report,2004
Occupational Radiation Exposure at NRC Licensed Facilities
.
*.:
....
:S
uJ
.
2000
2001
2002
2003
2004
1988
HARRIS 1
1989
Docket 50-400; NPF-63
1990
1st commercial operation 5187
1991
Type- PWR
1992
Capacity - 900 MWe
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1976
HATCH 1, 2
1977
Docket 50-321, 50-366;
1978
DPR-57; NPF-05
1979
1st commercial operation
1980
12/75, 9179
1981
Type - BWRs
1982
Capacity - 869, 883 MWe
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1987
HOPE CREEK 1
1988
Docket 50-354; NPF-57
1st commercial operation 12/86 1989
1990
Type-BWR
1991
Capacity - 1049 MWe
1992
1993
HADDAM NECK'
(continued)
L!
0.0
0.0
0.0
0.0
0.0
652.9
690.6
776.4
724.8
661.8
913.0
740.8
731.1
860.6
673.6
766.2
827.0
783.0
611.2
892.0
823.9
797.9
496.3
446.8
513.0
401.0
1,008.7
870.9
768.0
934.7
658.6
1,211.0
872.0
1,295.4
1,001.4
1,271.1
1,268.0
1,152.4
1,293.8
1,189.6
1,289.0
1,376.3
1,519.6
1,374.7
1,458.4
1,487.4
1,515.0
1,603.0
1,600.0
1,606.3
1,641.3
869.2
832.7
791.1
966.4
882.5
841.9
1,049.2
.:;
.
0.0
0.0
0.0
0.0
0.0
75.0
79.5
89.6
81.5
74.9
99.7
82.7
83.8
95.4
80.4
90.4
97.9
92.5
72.4
99.4
93.2
88.2
83.8
66.3
72.8
54.6
70.9
64.3
56.6
68.6
47.3
79.6
64.8
89.7
70.4
87.1
83.5
77.4
88.6
85.5
87.1
90.6
94.0
88.1
91.7
90.0
88.7
93.5
94.0
94.5
95.3
86.4
80.7
77.8
91.6
84.2
80.8
97.8
3.....
555
361
258
400
564
721
929
453
872
930
327
1,089
1,068
444
1,131
931
247
888
1,586
145
786
747
630
1,303
1,304
2,131
1,930
2,899
3,418
3,428
4,110
2,841
3,486
2,202
2,509
1,350
2,902
2,508
1,615
1,733
2,243
1,458
1,495
1,945
1,610
1,866
1,913
1,407
1,299
1,295
1,209
589
1,734
1,873
1,394
1,700
1,694
688
'
:.i!
262
95
52
82
92
169
156
85
226
213
31
222
174
17
149
133
16
101
252
7
68
57
134
465
248
582
449
1,337
1,460
1,299
2,218
818
1,497
816
1,401
556
1,455
1,161
550
669
884
488
441
722
320
329
402
230
214
168
180
117
287
465
196
373
436
98
0.47
0.26
0.20
0.21
0.16
0.23
0.17
0.19
0.28
0.23
0.09
0.20
0.16
0.04
0.13
0.14
0.06
0.11
0.16
0.05
0.09
0.08
0.21
0.36
0.19
0.27
0.23
0.46
0.43
0.38
0.54
0.29
0.43
0.37
0.56
0.41
0.50
0.46
0.34
0.39
0.39
0.33
0.29
0.37
0.20
0.18
0.21
0.16
0.17
0.13
0.15
0.20
0.17
0.25
0.14
0.22
0.26
0.14
-
0.26
0.23
0.11
0.31
0.32
0.03
0.30
0.24
0.02
0.22
0.17
0.02
0.13
0.41
0.01
0.08
0.07
0.27
1.04
0.48
1.45
0.45
1.54
1.90
1.39
3.37
0.68
1.72
0.63
1.40
0.44
1.15
1.01
0.43
0.56
0.67
0.35
0.29
0.53
0.22
0.22
0.26
0.14
0.13
0.10
0.11
0.13
0.34
0.59
0.20
0.42
0.52
0.09
' Haddam Neck (also known as Connecticut Yankee) was shut down 1214/96 and is no longer inthe count of operating reactors.
Parentheses indicate plant capacity when plant was operational.
NUREG-0713
C-14
7arty-Sevnnal Annulta Rport, 2004
Occupational Radiation Exposure at NRC Incensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
Thirty-Seventh Annual Report, 2004
9
*
**i9
HOPE CREEK I
(continued)
HUMBOLDT BAYr
Docket 50-133; DPR-7
1st commercial operation 8163
Type - BWR
Capacity - (63) MWe
INDIAN POINT 1, 2,3'
Docket 50-3, 50-247, 50-286;
DPR-5,-26, -64
1st commercial operation
10/62, 8/74, 8/76
Type - PWRs
Capacity - (265), 956, 979 MWe
.
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1969
1970
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1969
1970
1971
1972
1973
1974
1975
1976
1977
1978
.
852.0
844.5
806.9
731.8
993.2
879.1
827.8
918.2
1,007.0
826.6
688.6
44.6
49.3
39.6
43.1
50.1
43.4
45.3
23.5
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
206.2
43.3
154.0
142.3
0.0
556.1
584.4
273.9
1,278.3
1,172.3
.
;
s.*
9
-
I.1
.
i9
81.2
79.8
77.4
77.8
98.0
86.7
87.9
91.1
99.2
84.6
71.3
83.8
83.9
46.4
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
59.4
74.8
34.8
75.3
67.8
-
1,779
1,571
1,069
1,747
620
1,111
1,236
1,532
220
1,597
2,440
125
115
140
127
210
296
265
523
1,063
320
135
142
75
71
84
24
21
42
66
105
38
28
20
10
18
14
11
2,998
1,019
891
1,590
1,391
1,909
326
196
158
350
55
279
188
156
26
139
240
164
209
292
253
266
318
339
683
1,905
335
31
22
9
19
17
1
1
2
5
16
1
1
I
0
2
0
0
298
1,639
768
967
5,262
910
705
1,950
1,070
2,006
0.18
0.12
0.15
0.20
0.09
0.25
0.15
0.10
0.12
0.09
0.10
1.31
1.82
2.09
1.99
1.27
1.07
1.28
1.31
1.79
1.05
0.23
0.15
0.12
0.27
0.20
0.04
0.05
0.05
0.08
0.15
0.03
0.04
0.05
0.04
0.08
0.03
0.04
0.38
0.23
0.20
0.48
0.06
0.32
0.23
0.17
0.03
0.17
0.35
3.68
4.24
7.37
5.87
5.31
7.33
7.48
29.06
1.45
37.85
4.99
6.80
1.76
0.89
0.79
1.23
0.77
1.05
1.64
1.21
7.12
0.84
1.71
' Humboldt Bay had been shut down since 1976, and in 1984 it was decided that it would not be placed in operation again.
Therefore, It is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was
operational.
7 Indian Point 1was defueled in 1975, and in 1984 it was decided that it would not be placed in operation again. Therefore,
it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.
' Indian Point 3 was purchased by a different utility in 1979 and subsequently reported its dose separately. Although Indian
Point 1, 2, and 3 have been owned by the same utlity since 2001, Indian Point 3 still reports separately.
c-i
C-155
NUREG-071 3
NUREG-0713
7hirty-Seventh Annud Report, 2004
hrySvnhAna e r,20
Occupational Radiation Exposure at NRC Licensed Facilities
iesdFclte
xoueaRaitoR
Occuptiona
*
*9.
.
9
INDIAN POINT 1T, 2
Docket 50-3,50-247; DPR-05,-26
1st commercial operation
10162, 874
Type - PWRs
Capacity - (265), 956 MWe
INDIAN POINT 17
Docket 50-3; DPR-05
1st commercial operation 10/62
Type - PWR
Capacity - (265) MWe
INDIAN POINT 2
Docket 50-247; DPR-26
1st commercial operation 8/74
Type - PWR
Capacity - 956 MWe
INDIAN POINT 3'
Docket 50-286; DPR-64
1st commercial operation 8/76
Type- PWR
Capacity - 979 MWe
.
.
9
B.
.
9.
I..
B..
2.23
1.90
3.07
0.69
6.35
0.24
2.73
1.99
0.33
2.70
0.98
3.18
0.10
0.96
0.05
0.94
0.08
1.02
1.03
0.05
4.90
0.02
0.29
0.01
B.
1979
1980
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
574.0
510.8
532.4
702.6
416.7
791.4
457.5
611.4
719.3
532.5
618.0
461.2
930.9
702.1
903.8
582.4
927.8
360.6
282.8
831.8
115.4
887.2
860.0
953.0
0
71.4
64.8
65.4
84.0
51.9
95.7
56.2
73.4
86.9
64.6
66.6
55.7
99.1
75.7
100.0
70.8
94.8
45.1
31.5
88.2
13.0
97.2
91.3
98.9
0
1,349
1,577
2,144
1,057
2,919
708
1,926
1.980
890
2,093
1,061
1,810
489
1,514
381
1,690
388
1,340
1,154
350
2,003
399
1,361
241
156
1,279
971
1,635
486
2,644
192
1,250
1,217
235
1,436
608
1,468
97
675
48
548
54
367
290
41
567
22
248
3
0.95
0.62
0.76
0.46
0.91
0.27
0.65
0.61
0.26
0.69
0.57
0.81
0.20
0.45
0.13
0.32
0.14
0.27
0.25
0.12
0.28
0.06
0.18
0.05
0.02
2004
855.3
91.0
1,136
196
0.17
0.23
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
574.0
367.3
367.5
171.5
7.8
714.4
566.5
655.3
574.6
792.5
587.8
595.3
862.8
561.7
140.5
0.0
174.8
695.3
495.1
874.0
829.8
66.5
53.2
59.8
22.5
2.6
76.3
66.0
73.4
62.7
83.3
61.1
62.9
87.5
61.4
14.9
0.0
21.4
74.8
54.9
95.3
88.3
808
977
677
1,477
941
658
1,093
588
1,308
451
1,800
1,066
299
1,003
478
529
638
289
1,608
213
893
636
308
364
1,226
607
230
570
202
500
93
876
358
40
212
60
58
67
22
234
15
117
0.79
0.32
0.54
0.83
0.65
0.35
0.52
0.34
0.38
0.21
0.49
0.34
0.13
0.21
0.13
0.11
0.11
0.08
0.15
0.07
0.13
1.11
0.84
0.99
7.15
77.82
0.32
1.01
0.31
0.87
0.12
1.49
0.60
0.05
0.38
0.43
0.38
0.03
0.47
0.02
0.14
12
-
-
Point I was defueled in 1975, and in 1984 it was decided that it would not be placed in operation again. Therefore,
it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.
Indian Point 3 was purchased by a different utility in 1979 and subsequently reported its dose separately. Although Indian
Point 1, 2, and 3 have been owned by the same utlity since 2001, Indian Point 3 still reports separately.
7Indian
'
.9*
-.
.9
*'99
NUREG-0713
C-16
Mrty-&venth Annud Report, 2004
INDIAN POINT 3'
(continued)
KEWAUNEE
Docket 50-305; DPR-43
1st commercial operation 6f74
Type - PWR
Capacity - 556 MWe
LACROSSE'
Docket 50-409; DPR-45
1st commercial operation 11/69
Type - BWR
Capacity- (48) MWe
2000
2001
2002
2003
2004
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
1970
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1993
1994
Occupational Radiation Exposure at NRC Licensed Facilities
960.0
903.9
960.0
866.2
995.8
401.9
405.9
425.0
466.6
412.0
433.8
451.8
458.4
444.1
455.3
443.1
461.7
480.0
467.5
449.1
468.8
441.8
471.4
457.1
475.6
455.6
380.4
269.8
423.0
505.1
432.6
394.1
509.0
473.5
441.0
15.3
323.1
29.2
24.4
37.9
32.0
21.2
11.3
21.6
24.0
26.4
29.6
17.2
24.8
38.5
39.2
19.6
0.0
0.0
0.0
99.3
93.1
98.5
89.8
100.0
88.2
78.9
79.9
89.5
79.0
82.1
86.7
87.6
83.7
85.7
82.4
85.8
89.7
88.3
84.9
87.9
83.4
88.0
86.8
88.8
87.8
71.8
56.0
87.2
100.0
88.8
80.8
97.4
90.5
81.0
143
1,014
156
902
234
104
381
312
335
343
401
383
353
445
482
519
502
755
705
570
490
495
450
436
364
415
474
278
284
103
394
1,110
102
439
565
218
81.0
69.6
47.6
33.7
62.0
71.8
68.5
76.0
44.6
59.7
80.5
86.7
46.1
0.0
0.0
0.0
115
165
118
141
182
153
124
187
148
160
288
373
260
127
48
65
9
118
7
96
4
28
270
140
154
127
165
141
101
165
139
176
169
226
210
239
145
221
122
106
72
109
126
56
88
5
100
200
4
73
91
l11
158
151
157
139
234
110
225
164
186
218
123
205
313
252
173
290
68
8
8
0.06
0.12
0.04
0.11
0.02
0.27
0.71
0.45
0.46
0.37
0.41
0.37
0.29
0.37
0.29
0.34
0.34
0.30
0.30
0.42
0.30
0.45
0.27
0.24
0.20
0.26
0.27
0.20
0.23
0.05
0.25
0.18
0.04
0.17
0.16
0.72
1.14
1.41
1.21
1.42
0.93
1.60
0.90
1.22
1.76
0.66
1.39
1.96
0.88
0.46
1.12
0.54
0.17
0.12
0.01
0.13
0.01
0.11
0.07
0.67
0.33
0.33
0.31
0.38
0.31
0.22
0.37
0.31
0.40
0.37
0.47
0.45
0.53
0.31
0.50
0.26
0.23
0.15
0.24
0.33
0.21
0.21
0.01
0.23
0.51
0.01
0.15
0.21
7.25
0.49
5.17
6.43
3.67
7.31
5.19
19.91
7.59
7.75
8.26
4.16
11.92
12.62
6.55
4.41
14.80
-
' Indian Point 3 was purchased by a different utility in 1979 and subsequently reported its dose separately. Although Indian
Point 1,2, and 3 have been owned by the same utlity since 2001, Indian Point 3 still reports separately.
' LaCrosse ended commercial operation in 1987 and will not be put incommercial operation again. Therefore, it is no longer
included inthe count of operating reactors. Parentheses indicate plant capacity when plant was operational.
C-17
C-17
NLJREG-071 3
NUREG-0713
7hirtySeventhAnnudReport, 2009
Thirty-Se :kAnrnwl Repon; 2004
Occupational Radiation Exposure at NRC Uncensed Facilities
Occupational Radiation Fiposure at NRC Licensed Facilities
- -;.
I5
*S
i
*.
LACROSSE"
(continued)
LASALLE 1, 2
Docket 50-373,-374;
NPF-11, -18
1st commercial operation
1/84,6184
Type- BWRs
Capacity - 1111, 1111 MWe
LIMERICK 1, 2
Docket 50-352, 50-353;
NPF-39,-85
1st commercial operation
2186, 1/90
Type- BWRs
Capacity- 1134,1134 MWe
MAINE YANKEE"
Docket 50-309; DPR-36
1st commercial operation 12172
Type - PWR
Capacity - (860) MWe
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1973
1974
1975
1976
1977
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
677.8
987.9
929.5
1,030.0
1,317.6
1,503.5
1,754.3
1,837.0
1,447.4
1,542.0
1,580.0
1,696.6
1,053.8
0.0
380.9
1,671.9
2,138.6
2,223.8
2,040.0
2,100.2
2,162.1
636.1
794.9
628.4
1,527.7
1,810.9
1,741.4
1,913.2
1,944.4
1,957.1
2,026.2
2,001.7
1,907.2
2,089.6
2,154.9
2,205.9
2,197.0
2.213.6
2,218.9
408.7
432.6
542.9
712.2
617.6
.,
S
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
77.8
53.0
50.6
59.3
71.6
73.1
84.6
86.7
72.0
76.0
77.6
82.1
54.3
0.0
19.3
81.8
97.1
98.9
92.1
94.8
96.0
70.2
96.5
66.0
78.2
86.8
84.8
91.6
94.9
93.0
93.3
95.8
89.5
94.2
95.8
97.3
97.1
97.2
97.6
68.7
79.9
95.0
82.2
i ,.
: P.*
l
CL
31
25
23
27
66
37
45
47
65
56
1,245
1,635
1,614
1,744
2,737
2,475
1,830
1.985
2,418
1,701
1,812
1,623
2,782
1,661
2,099
2,689
1,831
535
2,012
2,253
2,366
2,156
950
1,818
1,422
1,151
1,559
1,287
1,543
1,581
1,654
1,463
1,854
1,800
1,279
1,127
1,248
1,298
1,265
782
619
440
244
508
3
3
4
2
2
4
4
3
2
2
1
252
685
898
1,396
2,471
1,386
948
806
1,167
854
726
512
819
318
422
576
260
83
450
464
359
174
52
266
175
106
330
217
275
260
234
234
357
272
261
210
160
147
149
117
420
319
85
245
:
,. -
.
0.10
0.15
0.09
0.07
0.06
0.10
0.06
0.05
0.03
0.02
0.20
0.42
0.56
0.80
0.90
0.56
0.52
0.41
0.48
0.50
0.40
0.32
0.29
0.19
0.20
0.21
0.14
0.15
0.22
0.21
0.15
0.08
0.05
0.15
0.12
0.09
0.21
0.17
0.18
0.16
0.14
0.16
0.19
0.15
0.20
0.19
0.13
0.11
0.12
0.15
0.68
0.72
0.35
0.48
~
-
0.37
0.69
0.97
1.36
1.88
0.92
0.54
0.44
0.81
0.55
0.46
0.30
0.78
1.11
0.34
0.12
0.04
0.22
0.22
0.17
0.27
0.07
0.42
0.11
0.06
0.19
0.11
0.14
0.13
0.12
0.12
0.19
0.13
0.12
0.10
0.07
0.07
0.07
0.29
0.97
0.59
0.12
0.40
LaCrosse ended commercial operation in 1987 and will not be put in commercial operation again. Therefore, it is no longer
included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.
10
Maine Yankee was shut down in 8/97 and is no longer included inthe count of operating reactors. Parentheses indicate plant
capacity when plant was operational.
'
NUREG-0713
C-I 8
C-1 8
Occupational Radiation Exposure at NRC Licensed Facilities
7birty-crSevnAnnzudReport 2004
9
]~~~~
..
l9
MAINE YANKEE'0
(continued)
MCGUIRE 1,2
Docket 50-369, -370;
NPF-9,-17
1st commercial operation
12/81, 3184
Type - PWRs
Capacity- 1100, 1100 MWe
MILLSTONE UNIT 1"
Docket 50-245; DPR-21
1st commercial operation 3/71
Type - BWR
Capacity - (641) MWe
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
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1972
1973
1974
1975
1976
642.7
537.0
527.0
624.2
542.5
677.1
605.7
635.4
737.6
478.1
591.9
819.2
573.0
738.1
631.7
674.8
782.8
23.6
602.9
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
524.9
558.3
764.1
808.4
1,360.0
1,774.7
1,830.7
1,810.2
1,340.3
1,945.1
1,696.8
1,470.4
1,848.0
2,132.3
1,881.8
1,558.2
2,139.8
1,961.7
2,100.1
2,113.3
2,051.0
2,156.2
2,075.7
377.6
225.1
430.3
465.4
449.8
5
.
.9*
;.
84.1
68A
72.2
78.2
69.1
83.6
74.4
79.2
87.8
65.3
79.1
93.7
71.0
86.6
79.1
79.8
90.9
3.7
78.1
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
80.4
55.4
68.5
77.0
60.1
79.2
80.2
80.8
61.3
85.0
74.4
66.2
80.2
92.9
82.8
73.0
95.1
88.9
94.2
93.9
91.7
96.0
91.8
79.1
75.6
76.1
638
393
735
868
1,295
592
1,262
1,009
495
1,100
1.058
375
1.359
426
1,189
1,016
297
1,167
408
991
438
365
490
412
452
342
190
1,560
1,751
1,663
2,217
2,326
2,865
2,808
1,994
2,289
1,723
1,619
1,685
1,637
1,259
1,622
2,193
1,045
1,274
940
963
1,167
841
1,116
612
1,184
2,477
2,587
1,387
2 !
;.i
.
.
420
154
462
424
619
165
884
700
100
722
725
99
682
105
461
377
84
653
56
153
163
135
121
68
66
44
21
169
521
507
771
1,015
1,043
1,104
620
727
361
418
463
397
138
238
492
142
257
133
137
181
71
196
596
663
1,430
2,022
1,194
U.
0.66
0.39
0.63
0.49
0.48
0.28
0.70
0.69
0.20
0.66
0.69
0.26
0.50
0.25
0.39
0.37
0.28
0.56
0.14
0.15
0.37
0.37
0.25
0.17
0.15
0.13
0.11
0.11
0.30
0.30
0.35
0.44
0.36
0.39
0.31
0.32
0.21
0.26
0.27
0.24
0.11
0.15
0.22
0.14
0.20
0.14
0.14
0.16
0.08
0.18
0.97
0.56
0.58
0.78
0.86
0.65
0.29
0.88
0.68
1.14
0.24
1.46
1.10
0.14
1.51
1.22
0.12
1.19
0.14
0.73
0.56
0.11
27.67
0.09
0.32
0.93
0.66
0.95
0.75
0.59
0.60
0.34
0.54
0.19
0.25
0.31
0.21
0.06
0.13
0.32
0.07
0.13
0.06
0.06
0.09
0.03
0.09
1.58
2.95
3.32
4.34
2.65
'°Maine Yankee was shut down in 8/97 and is no longer included in the count of operating reactors. Parentheses indicate plant
capacity when plant was operational.
"Millstone Unit I was shut down 6/30/98 and is no longer included in the count of operating reactors. Parentheses indicate plant
capacity when plant was operational.
9
c-iC-19
NUREG-071 3
NLUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
RaidnEpsr aiie
Occupationzl- :NCLcne
-
MILLSTONE UNIT 1"
(continued)
MILLSTONE UNIT 2,3
Docket 50-336, 50423;
DPR-65, NPF-49
1st commercial operation
12/75,4/86
Type - PWRs
Capacity - 878, 1148 MWe
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
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
575.7
556.6
505.0
405.8
304.3
490.2
640.1
516.1
548.5
626.8
523.4
658.8
554.6
608.3
213.1
431.8
627.9
394.0
520.6
0.0
-2.9
-2.7
0.0
0.0
0.0
0.0
0.0
0.0
545.7
518.7
536.6
520.0
579.3
722.4
595.9
294.0
782.7
417.8
1,313.8
1,624.5
1,594.8
1,428.3
1,614.9
819.5
1,115.1
1,525.2
1,556.6
1,278.1
418.1
0.0
374.9
1,446.3
1,865.8
1,759.3
1,703.0
1,834.6
1,887.5
89.6
87.6
77.3
69.0
51.6
79.9
95.6
78.8
83.6
95.4
79.6
98.6
84.2
91.6
35.4
681
96.8
63.6
80.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
78.7
65.7
67.3
62.8
69.2
82.6
70.6
34.2
93.5
49.4
80.4
84.1
83.2
72.9
87.1
69.7
59.9
79.7
73.1
60.5
19.3
0.0
20.9
73.3
92.4
92.0
87.5
91.0
95.0
.
7birty-Seventh Annud Report, 2004
hrySvnhAna eot O4
.
..
1,075
1,391
2,001
3,024
2,506
1,370
309
1,992
732
389
1,588
327
852
365
1,154
348
305
1,321
910
747
1,053
347
397
478
414
185
195
147
620
667
1,420
525
893
890
2,083
2,383
285
1,905
2,393
1,441
1,827
1,984
1,652
1,084
3,190
2,064
1,249
1,691
983
1,435
1,179
1,688
1,385
1,327
1,548
1,274
803
0MCI3.
394
1,416
1,795
2,157
1,496
929
244
836
608
150
684
144
462
131
409
99
81
391
620
431
195
13
10
60
15
4
11
11
168
242
1,444
471
637
531
1,413
1,881
120
1,581
993
505
804
1,079
593
381
1,280
557
188
416
126
253
113
252
143
174
292
323
136
0.37
1.02
0.90
0.71
0.60
0.68
0.79
0.42
0.83
0.39
0.43
0.44
0.54
0.36
0.35
0.28
0.27
0.30
0.68
0.58
0.19
0.04
0.02
0.13
0.04
0.02
0.05
0.08
0.27
0.36
1.02
0.90
0.71
0.60
0.68
0.79
0.42
0.83
0.41
0.35
0.44
0.54
0.36
0.35
0.40
0.27
0.15
0.25
0.13
0.18
0.10
0.15
0.10
0.13
0.19
0.25
0.17
0.68
2.54
3.55
5.32
4.92
1.90
0.38
1.62
1.11
0.24
1.31
0.22
0.83
0.22
1.92
0.23
0.13
0.99
1.19
0.31
0.47
2.69
0.91
1.10
0.74
2.37
6.40
0.15
3.78
0.76
0.31
0.50
0.76
0.37
0.46
1.15
0.37
0.12
0.33
0.30
0.30
0.17
0.08
0.10
0.17
0.18
0.07
"iMillstone Unit I was shut down 6130198 and is no longer included in the count of operating reactors. Parentheses indicate plant
capacity when plant was operational.
NUREG-0713
C-20
C-20
Occupational Radiation Exposure at NRC Licensed Facilities
7birty-Seventh Annual Report,2004
..
e I v^
==
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 -BWRs
Capacity-565, 1120 MWe
424.4
389.5
349.3
344.8
476.4
425.6
459.4
522.0
411.8
389.3
291.1
494.6
33.7
509.8
402.7
422.5
542.5
318.2
536.0
429.4
528.3
458.1
471.3
564.7
461.6
417.4
470.2
530.7
483.2
441.3
571.0
522.8
573.2
227.0
346.5
381.8
411.0
385.9
359.0
484.6
347.4
527.7
354.0
533.9
385.2
133.5
329.8
426.8
580.9
371.0
542.6
0.0
527.5
656.2
1,250.8
965.9
1,380.2
1,589.6
1,382.2
1,598.6
,
L] . .
;
as
L
. .1.!
1lr.F
:
.
}_WPM
K
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
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
.L
74.9
72.2
91.5
79.9
87.2
97.6
78.2
72.6
63.3
96.3
9.2
91.7
79.1
81.9
99.8
76.2
96.9
80.8
97.5
84.4
87.0
100.0
86.9
75.9
88.1
92.9
84.2
78.5
99.0
91.7
99.2
70.5
72.1
88.2
59.2
95.1
66.1
92.3
66.0
21.4
56.2
71.9
96.4
65.3
93.3
0.0
29.7
46.6
79.7
61.8
84.6
95.9
82.5
91.6
C-21
99
401
842
1,353
325
860
679
372
1,114
1,446
1,307
416
1,872
586
895
941
375
1,102
336
964
454
954
788
200
757
399
674
451
792
834
399
858
279
821
1,006
735
550
740
649
392
1,093
561
1,326
1,174
2,029
1,352
1,405
1,530
1,007
1,878
1.190
2.626
2,737
2,405
1,543
1,800
2.352
800
2,304
1,596
61
176
349
1,353
263
1,000
375
157
531
1,004
993
121
2,462
327
596
568
110
507
94
465
114
494
395
44
240
106
209
70
216
221
40
169
35
44
195
285
567
824
681
428
1,383
314
1,497
591
1,592
1,264
860
890
265
1,275
141
854
564
699
292
563
633
149
759
290
0.62
0.44
0.41
0.14
0.45
1.00
3.92
0.55
2.35
0.82
0.30
1.29
2.58
3.41
0.24
73.06
0.64
1.48
1.34
0.20
1.59
0.18
1.08
0.22
1.08
0.84
0.08
0.52
0.25
0.44
0.13
0.45
0.50
0.07
0.32
0.06
0.81
1.16
0.55
0.42
0.48
0.69
0.76
0.29
1.32
0.56
0.67
0.60
0.29
0.46
0.28
0.48
0.25
0.52
0.50
0.22
0.32
0.27
0.31
0.16
0.27
0.26
0.10
0.20
0.13
0.05
1.00
0.19
1.11
0.56
0.75
1.38
2.14
1.05
1.90
1.09
0.88
3.98
0.60
4.23
0.19
0.39
1.03
1.27
0.56
1.13
0.50
0.78
0.93
0.61
0.58
0.26
0.68
0.12
0.33
0.21
0.29
1.11
4.13
9.47
2.61
2.09
0.46
3.44
0.26
0.31
0.27
1.07
1.07
0.23
0.58
0.46
0.19
0.09
0.33
0.18
0.55
0.18
0.19
NUREG-071 3
NJUREG-0713
7birty-Seventh An n udRep ort, 2004
Thirty-Seventh Anmeal Report;. 2004
Occupational Radiation Fxposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
Hi
*9*~
*.
.*
NINE MILE POINT 1, 2
(continued)
NORTH ANNA 1,2
Docket 50-338; NPF-04, -09
1st commercial operation
6878, 12180
Type-PWRs
Capacity - 925, 917 MWe
OCONEE 1, 2,3
Docket 50-269, 50-270,
50-287;
DPR-38, -47, -55
1st commercial operation
7173, 9/74, 12/74
Type - PWRs
Capacity - 846, 846, 846 MWe
NUREG-0713
NUREG-0713
!
.l!.E
i
.
.9.:,
a.
!:
I.
..
1997
1998
1999
2000
2001
2002
2003
2004
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
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
1,321.5
1,387.3
1,409.5
1,443.9
1,508.9
1,517.0
1,585.6
1,551.9
507.0
681.8
1,241.9
777.7
1,338.4
1,021.3
1,516.9
1,484.5
1,112.6
1,772.7
1,228.8
1,590.4
1,597.5
1,403.2
1,428.4
1,717.1
1,666.4
1,569.6
1,711.5
1,632.8
1,747.7
1,734.1
1,491.0
1,557.0
1,569.1
1,685.6
650.6
1,838.3
1,561.4
1,566.4
1,909.0
1,708.0
1,703.7
1,661.5
1,293.1
2,141.5
2,242.9
2,036.3
1,995.6
1,962.6
2,228.9
2,188.6
2,405.2
2,275.0
2,110.7
2,399.2
2,144.3
2,366.1
1,847.9
1,563.7
1,989.1
2,264.5
74.8
87.0
81.3
88.1
88.9
90.4
91.4
92.0
61.7
86.5
71.5
45.8
76.1
58.8
86.1
83.0
67.8
96.7
72.5
90.5
88.6
84.1
80.1
95.9
90.8
89.1
96.2
92.7
96.1
95.8
84.8
84.3
87.2
92.0
60.1
75.5
63.0
65.9
75.8
67.7
70.1
66.8
52.5
82.2
85.7
80.5
79.0
82.4
87.2
85.4
91.4
86.7
82.0
91.3
82.2
89.5
70.3
67.7
81.3
90.3
C-22
C-22
1,425
1,744
1,709
1.783
1,371
2,449
1.501
1,362
2.025
2,086
2,416
2,872
2,228
3,062
2,436
2,831
2,624
992
2,861
2,161
2,085
2,159
2,768
1,038
1,551
1,203
856
1,201
727
730
1,231
914
1,041
965
844
829
1,215
1,595
1,636
2,100
2,124
2,445
2,445
1,902
2,085
2,729
2,499
2,672
2,672
2,205
1,948
1,966
1,954
1,499
1,923
1,586
1,479
1,379
1,695
1,568
429
378
447
283
343
517
375
449
449
218
680
1,915
665
1,945
838
722
1,521
112
1.471
590
629
576
908
193
367
291
103
266
94
65
309
143
187
130
517
497
1,026
1,329
1,393
1,001
1,055
1,211
1,792
1,207
1,106
1,304
949
1,142
871
684
404
551
612
237
537
304
257
223
366
202
0.30
0.22
0.28
0.16
0.25
0.21
0.25
0.33
0.22
0.10
0.28
0.67
0.30
0.64
0.34
0.26
0.58
0.11
0.51
0.27
0.30
0.27
0.33
0.19
0.24
0.24
0.12
0.22
0.13
0.09
0.25
0.16
0.18
0.13
0.61
0.60
0.84
0.83
0.85
0.48
0.50
0.50
0.73
0.63
0.53
0.48
0.38
0.43
0.33
0.31
0.21
0.28
0.31
0.16
0.28
0.19
0.17
0.16
0.22
0.13
0.32
0.27
0.32
0.20
0.23
0.34
0.24
0.29
0.89
0.32
0.55
2.46
0.50
1.90
0.55
0.49
1.37
0.06
1.20
0.37
0.39
0.41
0.64
0.11
0.22
0.19
0.06
0.16
0.05
0.04
0.21
0.09
0.12
0.08
0.79
0.27
0.68
0.85
0.73
0.59
0.62
0.73
1.39
0.56
0.49
0.64
0.48
0.58
0.39
0.31
0.17
0.24
0.29
0.10
0.25
0.13
0.14
0.14
0.18
0.09
Occupational Radiation Exposure at NRC Licensed Facilities
hrly-SeventhAnnuilReport, 20/04
7/ny-S
Occupational Radiation Exposure at NRC Licensed Facilities
nthAnnualRepon; 2004
OCONEE 1,2,3
(continued)
OYSTER CREEK
Docket 50-219; DPR-16
1st commercial operation 12169
Type - BWR
Capacity - 619 MWe
PALISADES
Docket 50-255; DPR-20
1st commercial operation 12171
Type - PWR
Capacity -730 MWe
2000
2001
2002
2003
2004
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
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
2,321.0
2,167.6
2,355.0
2,177.7
2,125.2
413.6
448.9
515.0
424.6
434.5
373.6
456.5
385.7
431.8
541.0
232.9
314.8
242.7
27.9
37.1
446.1
157.3
371.0
419.6
287.5
511.8
351.6
536.3
551.9
431.7
615.4
515.0
579.1
490.8
615.1
444.9
595.0
573.0
598.4
551.8
216.8
286.8
10.7
302.0
346.9
616.6
320.2
415.0
288.3
418.2
404.3
454.4
98.7
639.2
102.3
319.2
413.4
442.8
366.7
587.0
70.4
73.3
79.3
70.1
74.3
85.9
41.4
59.8
62.5
11.5
9.6
89.4
31.5
64.2
65.9
57.3
89.1
60.5
85.9
87.8
70.8
97.4
82.6
94.3
82.4
100.0
83.3
97.6
94.0
97.2
91.6
1,686
2,002
1,723
2,180
2,295
95
249
339
782
935
1,210
1,582
1,673
1,411
842
1,966
1,689
1,270
2,303
2,369
2,342
3,740
1,932
2,875
2,395
1,941
3,089
2,771
2,560
2,382
761
1,833
509
1,408
466
2,044
442
1,468
416
1,346
5.5
64.5
55.2
91.4
49.7
59.9
42.9
57.2
54.7
60.3
15.2
83.8
15.1
48.2
56.8
69.1
58.7
78.1
975
774
495
742
332
849
1,599
1,307
2,151
1,554
2,167
1,344
1,355
1,438
1,122
1,472
1,026
2,414
1,315
91.6
86.8
92.5
86.3
84.1
C-23
C-23
273
579
225
245
368
63
240
582
1,236
984
1,140
1,078
1,614
1,279
467
1,733
917
865
2,257
2,054
748
2,436
522
1,504
910
310
1,185
657
416
844
90
449
50
308
42
614
46
266
43
227
78
1,133
627
306
696
100
764
854
424
902
330
977
573
507
672
456
730
314
766
211
0.16
0.29
0.13
0.11
0.16
0.66
0.96
1.72
1.58
1.05
0.94
0.68
0.96
0.91
0.55
0.88
0.54
0.68
0.98
0.87
0.32
0.65
0.27
0.52
0.38
0.16
0.38
0.24
0.16
0.35
0.12
0.24
0.10
0.22
0.09
0.30
0.10
0.18
0.10
0.17
1.16
0.81
0.62
0.94
0.30
0.90
0.53
0.32
0.42
0.21
0.45
0.43
0.37
0.47
0.41
0.50
0.31
0.32
0.16
0.12
0.27
0.10
0.11
0.17
0.15
0.53
1.13
2.91
2.26
3.05
2.36
4.18
2.96
0.86
7.44
2.91
3.56
80.90
55.36
1.68
15.49
1.41
3.58
3.17
0.61
3.37
1.23
0.75
1.96
0.15
0.87
0.09
0.63
0.07
1.38
0.08
0.46
0.07
0.41
0.36
3.95
58.60
1.01
2.01
0.16
2.39
2.06
1.47
2.16
0.82
2.15
5.81
0.79
6.57
1.43
1.77
0.71
2.09
0.36
NUREG-0713
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
St
*0**.
.
S
PAUSADES
(continued)
PALO VERDE 1, 2,3
Docket 50-528, 50-529; 50-530
NPF-41, NPF-51, NPF-74
1st commercial operation
1/86,9/86,1I88
Type- PWRs
Capacity - 1243,1335,
1247 MW.
PEACH BOTTOM 2, 3
Docket 50-277, 50-278;
DPR-44, -56
1st commercial operation
7/74, 12174
Type - BWRs
Capacity- 1112,1112 MWe
NUREG-0713
7hirty-Seventh Annud Report,2004
Thirty-Seventh Annual Report; 2004
.s
Sn
So
295
289
60
462
318
48
217
218
26
363
24
203
371
669
688
720
499
605
541
592
462
482
302
246
192
146
158
182
140
211
199
228
840
2,036
1,317
1,388
2,302
2,506
1,977
2,963
2,450
3,354
1,080
2,195
2,327
728
377
934
502
552
579
398
282
490
366
319
331
344
333
356
265
0.23
0.32
0.15
0.38
0.29
0.14
0.24
0.23
0.10
0.35
0.11
0.25
0.38
0.37
0.32
0.28
0.22
0.27
0.27
0.28
0.23
0.26
0.18
0.16
0.14
0.11
0.12
0.13
0.10
0.11
0.15
0.23
0.39
0.72
0.59
0.61
0.83
0.88
0.72
0.95
0.74
0.80
0.44
0.50
0.55
0.32
0.24
0.35
0.26
0.31
0.27
0.21
0.17
0.26
0.19
0.20
0.19
0.24
0.17
0.22
0.19
l
i:;S.
a
i.3
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
581.9
424.4
541.8
583.5
638.2
662.5
615.4
585.4
654.4
268.2
725.0
701.1
608.6
1,638.1
1,700.9
965.3
2,500.9
3,043.9
3,102.3
2,677.1
2,827.6
3,265.2
3,482.7
3,369.2
3,454.4
3,471.2
3,458.6
3,280.2
3,513.0
3,254.4
3,201.4
1,234.3
1,379.2
1,052.4
1,636.3
1,740.0
1,374.2
1,161.8
1,583.3
824.7
1,165.8
682.7
1,395.0
365.7
0.0
491.0
1,684.0
1,210.9
1,516.6
1,654.0
1,927.4
1,955.9
2,012.4
1,956.3
1,881.2
2,057.2
2,058.3
2,037.1
2,105.0
2,072.4
2,148.8
76.1
53.7
67.0
75.8
81.4
89.9
83.5
80.2
88.0
36.3
94.8
90.7
82.3
66.1
65.5
26.5
67.5
78.9
82.0
74.3
79.1
85.6
90.0
92.2
93.2
93.2
93.0
88.6
94.0
88.6
86.3
80.9
73.0
58.7
84.0
84.5
66.3
58.0
76.9
41.0
57.5
37.5
71.7
20.3
0.0
35.0
85.7
62.3
78.7
81.9
93.8
95.1
96.9
95.0
93.2
96.0
96.7
95.8
96.7
94.9
96.4
C-24
C-24
1,267
908
397
1,230
1,109
338
895
939
255
1,032
224
822
974
1,792
2,173
2,615
2,236
2,242
1,981
2,124
2,048
1,875
1,717
1,585
1,410
1,275
1,279
1,361
1,343
1,943
1,324
971
2,136
2,827
2,244
2,276
2,774
2,857
2,734
3,107
3,313
4,209
2,454
4,363
4.204
2,301
1,585
2,702
1,911
1,757
2,133
1,940
1,657
1,872
1,903
1,630
1,729
1,445
1,915
1,641
1,422
0.51
0.68
0.11
0.79
0.50
0.07
0.35
0.37
0.04
1.35
0.03
0.29
0.61
0.41
0.40
0.75
0.20
0.20
0.17
0.22
0.16
0.15
0.09
0.07
0.06
0.04
0.05
0.06
0.04
0.06
0.06
0.18
0.61
1.93
0.80
0.80
1.68
2.16
1.25
3.59
2.10
4.91
0.77
6.00
1.48
0.22
0.77
0.33
0.33
0.30
0.20
0.14
0.25
0.19
0.16
0.16
0.17
0.16
0.17
0.12
Ainy-SeventhAnnud Report,2004
Thirty-Sez'enfr Annual Report; 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Occupations! Radiation Exposure at NRC Licensed Facilities
no
PERRY
Docket 50-440; NPF-58
1st commercial operation 11187
Type - BWR
Capacity - 1235 MWe
PILGRIM 1
Docket 50-293; DPR-35
1st commercial operation 12/72
Type - BWR
Capacity - 685 MWe
POINT BEACH 1, 2
Docket 50-266, 50-301;
DPR-24. -27
1st commercial operation
12/70, 10/72
Type - PWRs
Capacity - 516. 518 MWe
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
1971
1972
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
79.0
57.0
67.1
91.9
75.5
48.2
50.2
95.6
77.2
84.7
99.3
89.9
97.1
79.6
95.0
83.8
95.9
869.3
642.2
792.7
1,074.2
856.2
479.2
550.8
1,090.9
895.6
930.6
1,163.1
1,041.7
1,148.2
885.9
1,136.0
973.7
1,164.3
484.0
234.1
308.1
287.8
316.6
519.5
574.0
360.3
408.9
389.9
559.5
1.4
587.3
121.9
0.0
0.0
204.6
503.5
406.3
561.0
513.7
453.6
531.7
631.3
492.1
650.5
510.7
627.5
585.6
657.0
566.6
676.1
39.2
71.3
60.7
61.4
83.1
89.4
56.2
65.9
63.9
87.2
0.4
91.5
18.8
0.0
0.0
64.1
82.1
65.8
85.4
80.9
71.4
80.7
95.4
80.7
100.0
84.4
98.3
91.0
100.0
87.5
99.5
393.4
378.3
693.7
760.2
801.2
857.3
873.9
914.4
808.0
727.2
760.4
757.2
81.3
82.9
86.7
87.3
90.9
80.8
82.5
83.6
84.3
C-25
782
1,883
1,537
600
1,487
1,235
2,098
587
1,622
1,524
385
1,758
501
1,392
436
1,880
496
230
454
473
1,317
1,875
18667
2,458
3,549
2,803
2, 854
2,326
4,542
2,209
2,635
4,710
2,073
1,797
1,898
2,836
1 332
1,328
758
1,294
517
1,655
530
1,222
422
1,113
463
1,437
427
501
400
339
313
417
336
610
561
773
767
El
105
767
638
146
571
278
691
64
307
272
42
326
56
258
0.13
0.41
0.42
0.24
0.38
0.23
0.33
70
0.16
0.32
607
73
126
415
798
2,648
3,142
1,327
1,015
3,626
1,836
1,539
1,162
4,082
893
874
1,579
392
207
225
605
281
435
200
482
116
588
71
344
51
180
38
250
41
164
580
588
295
459
370
430
320
644
598
596
609
0.11
0.19
0.18
0.11
0.19
0.11
0.19
0.15
0.55
0.91
1.69
2.01
1.68
0.80
0.41
1.02
0.66
0.54
0.50
0.90
0.40
0.33
0.34
0.12
1.19
0.80
0.14
0.67
0.58
1.25
0.06
0.34
0.29
0.04
0.31
0.05
0.29
0.06
0.62
0.06
0.26
1.77
2.59
9.20
9.92
2.55
1.77
10.06
4.49
3.95
2.08
2915.71
1.52
7.17
0.19
0.12
0.12
0.21
0.21
0.33
0.26
0.37
0.22
0.36
0.13
0.28
0.12
0.16
0.08
0.17
0.10
1.17
0.74
1.35
1.18
1.03
0.95
1.06
1.07
0.77
0.79
1.01
0.45
1.49
0.50
0.85
0.44
0.91
0.18
1.19
0.11
0.67
0.08
0.31
0.06
0.44
0.06
0.42
1.53
0.85
0.39
0.57
0.43
0.49
0.35
0.80
0.82
0.78
0.80
NUREG-0713
Mrty-SeventbAnnudReport, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
.9
POINT BEACH 1, 2
(continued)
PRAIRIE ISLAND 1, 2
Docket 50-282, 50-306;
DPR-42. -60
1st commercial operation
12173. 12174
Type - PWRs
Capacity - 522. 522 MWe
QUAD CmES 1, 2
Docket 50-254, 50-265;
DPR-29,-30
1st commercial operation
2173, 3/73
Type - BWRs
Capacity - 855, 855 MWe
NUREG-071 3
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
1974
1975
1976
1977
1978
1979
1980
648.2
788.9
831.3
858.9
857.5
899.3
847.8
875.5
874.8
866.7
911.0
914.5
858.4
831.6
186.8
649.7
806.0
872.0
915.9
909.0
917.2
912.3
181.9
836.0
725.2
922.9
941.1
865.0
800.7
844.9
944.9
921.1
972.4
882.6
930.6
969.6
932.0
1,001.8
925.4
1,023.3
811.6
978.3
996.9
1,023.2
992.1
817.6
860.3
989.3
992.2
900.8
987.0
1,006.1
940.4
958.1
833.6
951.2
970.1
1,124.5
1,075.0
866.9
72.7
78.6
82.5
85.7
85.5
88.6
85.5
86.5
87.1
85.8
90.0
91.2
86.1
84.7
21.8
69.7
83.1
88.7
93.4
91.1
92.1
90.1
43.9
83.3
76.6
87.2
92.2
86.0
79.9
80.5
90.4
86.8
91.7
84.0
90.3
91.6
89.1
94.7
89.2
95.6
76.2
90.7
91.5
93.9
91.4
81.4
83.4
93.8
93.1
85.8
93.6
96.4
89.9
72.3
68.4
73.1
84.0
88.6
84.6
64.4
C,26
.
.9*
1.702
1,372
671
664
720
734
736
617
724
617
559
548
548
1,029
670
881
962
765
740
945
627
627
150
477
818
718
546
594
983
836
645
654
546
1,082
818
593
732
476
737
586
845
532
478
499
558
753
582
542
632
691
969
594
1,8-6
678
1,083
1,225
907
1,207
1,688
3,089
.
9
1,403
789
482
402
554
410
504
378
265
256
186
170
190
276
92
169
194
139
132
181
85
110
18
123
447
300
221
180
353
329
229
233
147
416
255
135
.
0.82
0.58
0.72
0.61
0.77
0.56
0.68
0.61
0.37
0.41
0.33
0.31
0.35
0.27
0.14
0.19
188
98
211
106
0.20
0.18
0.18
0.19
0.14
0.17
0.12
0.26
0.55
0.42
0.40
0.30
0.36
0.39
0.36
0.36
0.27
0.38
0.31
0.23
0.27
0.21
0.26
0.17
0.25
0.20
109
0.10
199
99
107
112
174
117
72
106
125
128
61
144
482
1,618
1,651
1,031
1,618
2,158
4,838
0.21
0.20
0.23
0.20
0.13
0.17
0.18
0.13
0.10
0.12
0.71
1.49
1.35
1.14
1.34
1.28
1.57
2.16
1.00
0.58
0.47
0.65
0.46
0.59
0.43
0.30
0.30
0.20
0.19
0.22
0.33
0.49
0.26
0.24
0.16
0.14
0.20
0.09
0.12
0.10
0.15
0.62
0.33
0.23
0.21
0.44
0.39
0.24
0.25
0.15
0.47
0.27
0.14
0.21
0.10
0.20
0.10
0.26
0.11
0.11
0.10
0.11
0.21
0.14
0.07
0.11
0.14
0.13
0.06
0.15
0.50
1.94
1.74
1.06
1.44
2.01
5.58
Occupational Radiation Exposure at NRC Licensed Facilities
77jinY-Seventh Annual Report, 2W
u
*
QUAD CMES 1, 2
(continued)
RANCHO SECO'1
Docket 50-312; DPR-54
1st commercial operation 4/75
Type - PWR
Capacity - (873) MWe
12
.
1981
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
.. .
..
1,156.9
1,018.7
1,088.5
994.6
1,268.0
1,093.2
1,126.6
1,173.7
1,196.3
1,148.9
1,044.5
960.8
974.9
681.5
1,002.5
876.6
935.3
794.8
1,476.5
1,410.4
1,478.2
1,396.0
1,569.4
1,443.8
268.1
706.4
607.7
687.0
530.9
321.2
409.5
347.9
460.0
238.7
0.0
0.0
355.8
179.9
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
'
ii
L
-2.
...
,.
.
!
'
.
-
I..
a
. i.
81.1
76.0
79.2
65.7
82.7
71.0
75.3
84.1
85.9
77.8
73.2
68.0
67.0
48.7
70.4
60.1
66.5
55.1
95.9
93.9
95.9
89.0
93.1
95.5
30.4
77.1
80.5
91.1
60.4
40.2
53.3
46.8
58.3
30.8
0.0
0.0
63.1
54.7
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
2,246
2,314
1,802
1,678
1,184
1,451
1,429
1,486
1,721
2,186
1,722
2,413
2,150
2,163
2,041
2,248
2,474
2,177
1,000
2,840
736
3,818
998
2,334
297
515
508
287
890
772
766
1,338
802
1,764
1,513
1,533
693
603
111
101
70
35
18
16
16
16
61
302
219
210
193
121
122
3,146
3,757
2,491
1,579
990
950
720
827
900
1,028
509
1,157
849
1,128
736
1,025
654
761
201
894
144
1,786
438
511
58
391
323
126
412
402
337
787
222
756
402
300
78
81
13
9
7
4
1
1
1
0
3
11
26
18
27
18
15
1.40
1.62
1.38
0.94
0.84
0.65
0.50
0.56
0.52
0.47
0.30
0.48
0.39
0.52
0.36
0.46
0.26
0.35
0.20
0.32
0.20
0.47
0.44
0.22
0.20
0.76
0.64
0.44
0.46
0.52
0.44
0.59
0.28
0.43
0.27
0.20
0.11
0.13
0.12
0.09
0.10
0.11
0.06
0.06
0.04
0.00
0.05
0.04
0.12
0.09
0.14
0.15
0.12
2.72
3.69
2.29
1.59
0.78
0.87
0.64
0.70
0.75
0.89
0.49
1.20
0.87
1.66
0.73
1.17
0.70
0.96
0.14
0.63
0.10
1.28
0.28
0.35
0.22
0.55
0.53
0.18
0.78
1.25
0.82
2.26
0.48
3.17
0.22
0.45
-
Rancho Seco was shut down 6189 and is no longer in the count of operating reactors. Parentheses indicate plant capacity when
plant was operational.
C-27
NUREG-071 3
NUREG-071 3
Occupational Radiation Exposure at NRC licensed Facilities
Ocuatoa Raito EpsratNClcneFaiiisTit-eehAnu
7birty-Seventh Annud Report, 2004
Ron,20
-
RIVER BEND 1
Docket 50-458; NPF-47
1st commercial operation 6186
Type - BWR
Capacity - 966 MWe
ROBINSON 2
Docket 50-261; DPR-23
1st commercial operation 3171
Type- PWR
Capacity - 710 MWe
SALEM 1, 2
Docket 50-272, -311;
DPR-70, -75
1st commercial operation
6177. 10/81
Type - PWRs
Capacity - 1159.1116 MWe
NUREG-0713
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
1978
1979
1980
1981
1982
1983
1984
1985
1986
NUREG071
605.2
880.7
584.5
682.2
814.7
336.1
640.0
595.7
967.1
836.1
778.8
894.2
651.2
837.1
889.3
965.0
871.3
845.6
580.0
455.1
578.1
501.8
585.5
511.5
480.5
482.0
387.3
426.6
277.5
409.8
28.0
629.5
577.1
510.1
385.0
336.6
400.3
575.1
487.2
502.7
560.3
618.7
654.8
707.5
628.5
648.9
710.0
627.9
638.0
733.1
653.7
546.4
250.0
680.6
743.0
1,440.4
742.0
650.1
1,657.7
1,484.3
68.4
94.3
69.1
78.0
87.2
39.7
71.6
64.9
99.6
85.3
86.3
96.2
75.2
89.7
93.6
98.5
92.7
90.1
83.3
72.7
84.7
85.2
72.0
70.8
62.2
73.0
48.9
75.5
7.0
87.9
80.3
72.5
65.9
48.7
64.8
81.4
66.8
70.7
79.5
84.7
88.6
99.0
88.9
91.8
99.7
90.6
91.2
100.0
89.3
55.6
25.5
69.2
78.1
72.6
30.5
31.8
75.8
70.4
C-2
C-28
.
.
1,268
513
1,566
1,616
780
2,022
847
2,209
667
2,093
1,671
466
1,327
1.104
1,249
373
1,296
1,378
245
831
853
849
597
634
943
1,454
2,009
1,462
2,011
2,244
4,127
1,378
1,571
1,379
1,351
1,098
1,626
885
1,267
1,221
420
1,058
1,031
304
978
807
138
827
830
109
952
574
1,488
1,704
1,652
3,228
2,383
1,395
1,112
3,554
.
o
.
,
378
107
558
489
144
710
180
519
85
473
347
58
344
216
208
35
217
236
215
695
672
1,142
715
455
963
1,188
1,852
733
1,426
923
2,880
311
539
499
564
195
437
193
352
337
63
215
167
13
170
124
8
125
111
5
118
122
584
449
254
1,203
581
681
204
599
-u
m.
0.30
0.21
0.36
0.30
0.18
0.35
0.21
0.24
0.13
0.23
0.21
0.12
0.26
0.20
0.17
0.09
0.17
0.17
0.88
0.84
0.79
1.35
1.20
0.72
1.02
0.82
0.92
0.50
0.71
0.41
0.70
0.23
0.34
0.36
0.42
0.18
0.27
0.22
0.28
0.28
0.15
0.20
0.16
0.04
0.17
0.15
0.06
0.15
0.13
0.04
0.12
0.21
0.39
0.26
0.15
0.37
0.24
0.49
0.18
0.17
:..
0.62
0.12
0.95
0.72
0.18
2.11
0.28
0.87
0.09
0.57
0.45
0.06
0.53
0.26
0.23
0.04
0.25
0.28
0.37
1.53
1.16
2.28
1.22
0.89
2.00
2.46
4.78
1.72
5.14
2.25
102.86
0.49
0.93
0.98
1.46
0.58
1.09
0.34
0.72
0.67
0.11
0.35
0.26
0.02
0.27
0.19
0.01
0.20
0.17
0.01
0.18
0.22
2.34
0.66
0.34
0.84
0.78
1.05
0.12
0.40
7hirty-Seventh Annud Report,2004
10.A
:
...
.
;
Occupational Radiation Exposure at NRC Licensed Facilities
.
.
SALEM 1, 2
(continued)
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1,478.2
1,591.6
1,675.4
1,362.6
1,726.4
1,200.9
1,366.3
1,367.4
558.1
0.0
279.3
1,629.3
1,821.8
1,973.4
1,961.2
1,934.0
1,957.2
1,850.2
SAN ONOFRE I13, 2,3
1969
314.1
Docket 50-206, -361, -362;
DPR-13, NPF-10, NPF-15
1st commercial operation
1/68, 8/83,4/84
Type - PWRs
Capacity -(436), 1070,
1080 MWe
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
365.9
362.1
338.5
273.7
377.8
389.0
297.9
281.2
323.2
401.0
97.3
95.9
61.6
0.0
670.4
1,381.8
1,698.2
1,983.0
1,982.3
1,840.8
1,980.5
1,987.6
2,228.6
1,771.3
2,220.7
1,686.9
2,089.3
1,533.9
1,996.4
0.0
0.0
0.0
0.0
0.0
0.0
SAN ONOFRE 113
Docket 50-206;
DPR-13,
1st commercial operation 1/68
Type -PWR
Capacity - (436) MWe
i
:.
*
S:'a!.;
E
600
503
338
272
458
431
408
188
218
300
175
41
318
198
153
293
124
149
0.24
0.31
0.11
0.07
0.11
0.10
0.11
0.20
0.18
0.18
0.20
0.10
0.27
0.17
0.12
0.12
0.10
0.10
0.41
0.32
0.20
0.20
0.27
0.36
0.30
0.14
0.39
0.63
0.03
0.17
0.10
0.08
0.15
0.06
0.08
123
42
0.34
0.13
251
121
326
570
219
424
1,330
985
764
521
3,063
2,902
3,055
1,701
7,514
5,742
3,594
2,138
2,324
2,237
2,224
1,814
1,651
2,193
528
1,914
1,272
1,652
1.091
241
416
338
308
226
169
155
50
256
353
71
292
880
847
401
139
2,386
3,223
832
155
986
722
824
696
781
567
885
412
324
767
32
455
129
341
196
16
71
58
61
36
15
0.62
0.41
0.79
0.62
0.32
0.69
0.66
0.86
0.52
0.27
0.78
1.11
0.27
0.09
0.27
0.24
0.24
0.33
0.34
0.25
0.40
0.23
0.20
0.35
0.06
0.24
0.10
0.21
0.18
0.07
0.17
0.17
0.20
0.16
0.09
0.42
0.14
0.76
1.29
0.19
0.75
2.95
3.01
1.24
0.35
24.52
33.61
13.51
1.47
0.52
0.49
0.35
0.39
0.31
0.45
0.21
0.15
0.43
0.01
0.27
0.06
0.22
0.10
-
73.3
73.6
79.5
65.1
79.3
61.1
65.4
73.8
29.3
0.0
17.8
79.1
86.8
93.0
91.1
89.4
90.7
85.8
2,543
1,609
2,944
3,636
4,201
4,376
3,559
950
1,195
1,671
894
408
1,200
1,191
1,274
2,460
1,301
1,496
86.1
87.4
70.2
63.7
80.2
90.2
22.3
26.7
15.7
0.0
68.3
132.9
61.1
78.8
68.4
64.9
69.1
75.3
87.1
79.9
100.0
79.1
93.2
72.9
92.0
0.0
0.0
0.0
0.0
0.0
0.0
-
-
San Onofre I was shut down 11/92 and is no longer inthe count of operating reactors. Parentheses indicate plant capacity
when plant was operational.
13
C-29
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
7hirty-Seventh Annud Repom 2004
M
SAN ONOFRE 2, 3
Docket 50-361, -362;
NPF-10, NPF-15
1st commercial operation
8/83, 4/84
Type- PWRs
Capacity - 1070, 1080 MWe
SEABROOK
Docket 50-443; NPF-86
1st commercial operation 8190
Type - PWR
Capacity - 1155 Mwe
SEQUOYAH 1, 2
Docket 50-327, -328;
DPR-77,-79
1st commercial operation
7181, 6182
Type- PWR
Capacity - 1148,1124 MWe
SOUTH TEXAS 1, 2
Docket 50-498, 50-499;
NPF-76,-80
1st commercial operation
8188,6189
Type - PWRs
Capacity - 1251, 1251 MWe
NUREG-0713
1999
2000
2001
2002
2003
2004
1,901.4
2,067.2
1,727.2
2,056.0
2,084.3
1,713.8
86.9
94.7
78.9
93.4
94.0
79.1
1,477
1,073
1,083
1,140
1,275
1.761
354
115
131
136
164
407
0.24
0.11
0.12
0.12
0.13
0.23
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
810.4
932.4
1,071.5
736.4
995.5
1,168.6.
907.0
957.6
991.5
901.8
989.6
1,058.0
1,055.9
1,158.6
583.5
1,663.7
1,481.9
1,151.3
0.0
0.0
490.8
1,851.7
1,662.6
1,965.4
1,849.0
405.7
1,418.7
1,864.2
2,003.9
1,946.1
2,135.3
2,165.1
1,910.0
2,158.3
2,106.0
1,776.4
2,135.2
769.3
1,504.1
1,741.5
2,096.0
163.1
1,700.2
2,294.2
2,465.9
2,265.5
2,379.4
2,219.7
2,180.0
2,262.7
2,173.0
1,796.3
2,437.1
75.9
81.3
93.6
63.5
87.5
99.6
79.8
84.5
87.5
79.3
89.1
92.8
93.6
100.0
52.8
75.1
69.0
51.3
0.0
0.0
31.8
85.7
77.2
88.0
85.4
21.8
66.3
86.1
87.9
89.0
95.3
97.0
86.8
95.7
94.1
80.0
93.9
65.6
65.9
72.4
83.8
8.3
70.6
89.9
95.0
93.6
96.9
91.6
89.7
92.2
87.5
72.1
96.0
699
806
110
852
800
206
1,571
559
1,339
1,158
423
1,095
981
291
1,968
1,769
2,373
1,853
1,738
2,080
2,441
2,007
2,935
1,933
1,714
1,631
1,702
1,650
1,444
1,962
1,530
1,346
2,039
1,292
1,257
2,484
1i161
989
1,136
1,144
923
1,138
661
1,485
1,145
1,583
1,171
1,328
1,372
1,325
1,510
909
842
92
147
6
113
102
10
186
19
106
70
9
67
71
6
570
491
1,119
1,072
527
420
678
657
1,687
700
465
373
295
368
269
420
266
165
357
145
108
431
86
161
206
257
147
251
47
291
137
273
184
260
232
238
329
143
120
0.13
0.18
0.05
0.13
0.13
0.05
0.12
0.03
0.08
0.06
0.02
0.06
C-30
0.07
0.02
0.29
0.28
0.47
0.58
0.30
0.20
0.28
0.33
0.57
0.36
0.27
0.23
0.17
0.22
0.19
0.21
0.17
0.12
0.18
0.11
0.09
0.17
0.07
0.16
0.18
0.22
0.16
0.22
0.07
0.20
0.12
0.17
0.16
0.20
0.17
0.18
0.22
0.16
0.14
0.19
0.06
0.08
0.07
0.08
0.24
0.11
0.16
0.01
0.15
0.10
0.01
0.21
0.02
0.11
0.08
0.01
0.06
0.07
0.01
0.98
0.30
0.76
0.93
1.38
0.35
1.01
0.36
0.25
0.92
0.21
0.20
0.13
0.22
0.12
0.08
0.19
0.07
0.05
0.24
0.04
0.21
0.14
0.15
0.07
1.54
0.03
0.13
0.06
0.12
0.08
0.12
0.11
0.11
0.15
0.08
0.05
AMYU-SeVenthAnnudRepom 2W
Thra-&en AindRpr 04Ocptoa
lyl.!-.
Occupatiorial Radiation Exposum at NRC Liccnsed Facilities
iesdFclte
aito xouea R
~~..*
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 1184
Type - PWR
Capacity - 966 MWe
SURRY 1, 2
Docket 50-280,50-281;
DPR-32,-37
1st commercial operation
12172, 5/73
Type - PWRs
Capacity - 810, 815 MWe
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
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
649.1
606.4
592.0
627.9
599.1
816.8
290.3
1,183.0
1,445.8
1,588.6
1,407.9
1,639.7
1,493.1
1,188.4
1,592.8
1,511.9
1,227.6
1,424.8
1,306.6
1,473.4
1,394.6
1,572.5
1,569.1
1,630.0
1,527.5
1.633.0
1,524.7
1.492.0
504.6
627.7
853.7
618.7
605.3
652.4
730.0
642.5
892.6
728.3
536.7
899.8
850.4
829.7
934.8
842.0
723.9
769.3
840.0
837.0
938.4
420.6
717.4
1,079.0
930.7
1,139.0
1.210.6
343.0
568.2
907.6
1,323.3
84.7
76.5
74.0
77.5
72.7
94.0
15.4
69.6
82.5
89.1
81.9
93.0
85.1
70.0
90.8
87.3
77.7
85.0
76.0
86.5
83.6
94.2
93.8
96.0
91.6
96.6
91.5
89.3
61.1
71.6
95.3
71.0
69.1
83.1
83.9
82.9
97.4
84.0
69.5
97.2
90.3
89.8
98.8
89.4
76.6
83.3
87.9
87.4
96.8
49.8
70.8
60.4
72.2
77.2
42.3
40.3
59.3
88.5
C-3
C-31I
.
445
797
907
1,074
1,473
1,045
2,211
2,090
1.971
1,279
2,012
1,448
1,414
1,876
1,282
1,251
1,462
1,896
1,498
1.433
2,314
1,170
1,107
990
1,375
992
937
1,157
1,120
1,201
392
1,075
1,127
374
1,090
984
249
1,121
1,549
257
701
820
285
827
933
486
685
745
200
936
1,715
1,948
2,753
1860
2,203
5,065
5,317
3,753
1,878
152
337
438
532
929
272
1,204
1,263
1,344
491
951
611
495
777
479
264
492
505
413
385
646
134
177
99
228
156
142
159
295
379
23
560
511
52
376
291
27
297
374
13
97
163
14
120
167
69
60
71
10
152
884
1,649
3,165
2,307
1,837
3,584
3,836
4,244
1,490
0.34
0.42
0.48
0.50
0.63
0.26
0.54
0.60
0.68
0.38
0.47
0.42
0.35
OA1
0.37
0.21
0.34
0.27
0.28
0.27
0.28
0.11
0.16
0.10
0.17
0.16
0.15
0.14
0.26
0.32
0.06
0.52
0.45
0.14
0.34
0.30
0.11
0.26
0.24
0.05
0.14
0.20
0.05
0.15
0.18
0.14
0.09
0.10
0.05
0.16
0.52
0.85
1.15
1.24
0.83
0.71
0.72
1.13
0.79
0.23
0.56
0.74
0.85
1.55
0.33
4.15
1.07
0.93
0.31
0.68
0.37
0.33
0.65
0.30
0.17
0.40
0.35
0.32
0.26
0.46
0.09
0.11
0.06
0.15
0.10
0.09
0.11
0.58
0.60
0.03
0.91
0.84
0.08
0.52
0.45
0.03
0.41
0.70
0.01
0.11
0.20
0.01
0.14
0.23
0.09
0.07
0.08
0.01
0.36
1.23
1.53
3.40
2.03
1.52
10.45
6.75
4.68
1.13
NUREG-071 3
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Raito
iesdFclte
Occupational~~~~~~~~~~~~~~~~
xouea R
;,
SURRY 1, 2
(continued)
SUSQUEHANNA 1, 2
Docket 50-387, 50-388;
NPF-14; NPF-22
1st commercial operation
6183, 2/85
Type - BWRs
Capacity - 1135, 1140 MWe
THREE MILE ISLAND 114, 21
Docket 50-289, -320;
DPR-50,-73
1st commercial operation
9/74,12/78
Type- PWRs
Capacity - 802, (880) MWe
1983
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1975
1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
916.2
1,026.7
1,166.4
1,080.5
1,132.7
750.4
489.3
1,276.4
1,271.9
1,396.3
1,283.1
1,320.9
1,333.0
1,562.9
1,380.3
1,476.2
1,483.0
1,490.0
1,441.5
1,557.0
1,255.9
1,537.9
719.9
1,452.2
1,344.8
1,749.5
1,691.0
1,572.5
1,746.9
1,878.0
1,604.2
1,602.1
1,814.4
1,850.8
1,998.7
1,918.9
1,879.6
1,896.0
1,994.6
2,027.6
1,973.0
2,050.8
2,058.8
675.9
530.0
664.5
690.0
266.0
0.0
0.0
0.0
0.0
0.0
103.6
i
.3.
61.3
71.0
78.2
69.0
72.7
50.0
33.0
83.9
84.5
88.9
84.6
85.2
84.2
93.1
87.1
91.6
93.5
92.7
89.5
96.0
79.7
94.6
72.6
76.4
67.0
85.3
83.5
77.1
85.4
89.8
79.7
77.3
85.4
85.3
90.7
89.6
88.3
89.6
92.6
94.2
91.6
93.4
92.7
82.2
65.4
80.9
85.1
21.9
0.0
0.0
0.0
0.0
0.0
10.6
Mrty4eventhAnnudReport, 2004
-rw~pr,20
hn-eet
J;ii.
2,754
3,198
3,206
3.763
2,675
3,184
3,100
1,947
1,547
1,660
1,402
1,530
1,883
983
1,335
1,165
995
1,197
1,243
799
1,628
1,028
2,827
3,669
2,996
2,548
1,904
2,063
1,691
1,844
1,885
1,488
1,580
1,773
1,430
1,646
1,575
1,787
1,812
1,807
1,890
1,934
2,144
131
819
1,122
1,929
3,975
2,328
2,103
2,123
1,592
1,079
1,890
.
3,220
2,247
1.815
2,356
712
1,542
836
575
510
539
383
378
406
209
320
189
138
193
329
88
326
120
308
1,106
828
621
516
704
440
507
724
335
442
476
289
433
361
431
331
288
260
250
272
73
286
360
504
1,392
394
376
1,004
1,159
688
857
5:i i'-
-
1.17
0.70
0.57
0.63
0.27
0.48
0.27
0.30
0.33
0.32
0.27
0.25
0.22
0.21
0.24
0.16
0.14
0.16
0.26
0.11
0.20
0.12
0.11
0.30
0.28
0.24
0.27
0.34
0.26
0.27
0.38
0.23
0.28
0.27
0.20
0.26
0.23
0.24
0.18
0.16
0.14
0.13
0.13
0.56
0.35
0.32
0.26
0.35
0.17
0.18
0.47
0.73
0.64
0.45
3.51
2.19
1.56
2.18
0.63
2.05
1.71
0.45
0.40
0.39
0.30
0.29
0.30
0.13
0.23
0.13
0.09
0.13
0.23
0.06
0.26
0.08
0.43
0.76
0.62
0.35
0.31
0.45
0.25
0.27
0.45
0.21
0.24
0.26
0.14
0.23
0.19
0.23
0.17
0.14
0.13
0.12
0.13
0.11
0.54
0.54
0.73
5.23
-
8.27
" Three Mile Island 1 resumed commercial power generation 10/85 after being under regulatory restraint since 1979.
" Three Mile Island 2 has been shut down since the 1979 accident but was still induded in the count of reactors through 1988 since
dose was still being accumulated to defuel and decontaminate the unit during this time period. Parentheses indicate plant capaoity when plant was operational. Since 2001 the dose breakdowns for Three Mile Island 2 have been reported with those for Unt 1.
NUREG-071
NUREG-07133
C-32
C-32
Occupational Radition Exposume at NRC Licensed Facilities
Occupational Radiation Exposure at NRC Licensed Facilities
Ahirty-SevntbnAnnuel~eport,2004
Thir*y-Seventli Annual Report; 2004
.
THREE MILE ISLAND 11'
Docket 50-289; DPR-50
1st commercial operation 9/74
Type - PWR
Capacity - 802 MWe
S.
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
THREE MILE ISLAND 211
Docket 50-320; DPR-73
1st commercial operation 12/78
Type - PWR
Capacity - (880) MWe
TROJAN"'
Docket 50-344; NPF-1
1st commercial operation 5/76
Type-PWR
Capacity - (1080) MWe
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2004
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
1989
1990
1991
:
585.2
610.7
661.0
871.3
645.5
688.7
836.8
722.0
798.7
772.9
857.4
675.7
805.8
722.4
813.4
616.7
833.0
706.4
828.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
792.0
205.5
631.0
727.5
775.6
579.5
494.2
567.0
829.1
852.4
525.5
758.6
666.8
732.4
181.6
.
70.9
73.6
77.8
100.0
84.6
86.4
100.0
88.5
95.5
90.8
100.0
84.3
100.0
89.7
100.0
84.2
100.0
87.1
100.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
92.6
20.6
58.1
72.5
74.1
60.8
62.4
54.4
76.7
79.7
54.0
67.5
61.9
66.3
16.1
S.S
1.360
1,259
1,012
670
1,319
1,542
558
1,835
434
1,220
267
1,049
280
1.171
183
1,196
172
1,230
1,497
1,378
1,247
1,014
484
153
315
167
259
191
122
232
105
203
70
0
105
591
711
736
1,159
1.311
977
969
1,042
852
1,321
1,209
1,408
1,360
1,169
1,496
213
149
210
54
264
198
34
206
40
213
16
204
17
155
9
197
7
155
915
977
917
639
136
37
157
33
7
2
2
1
1
1
0
0
4
174
319
258
421
609
419
307
433
363
381
363
401
421
258
567
0.16
0.12
0.21
0.08
0.20
0.13
0.06
0.11
0.09
0.17
0.06
0.19
0.06
0.13
0.05
0.16
0.04
0.13
0.36
0.24
0.32
0.06
0.41
0.29
0.04
0.29
0.05
0.28
0.02
0.30
0.02
0.21
0.01
0.32
0.01
0.22
0.00
0.00
0.61
0.71
0.74
0.63
0.28
0.24
0.50
0.20
0.03
0.01
0.02
0.00
0.01
0.00
0.01
0.03
0.29
0.45
0.35
0.36
0.46
0.43
0.32
OA2
0.43
0.29
0.30
0.28
0.31
0.22
0.38
-
0.22
1.55
0.41
0.58
0.79
0.72
0.62
0.76
0.44
0.45
0.69
0.53
0.63
0.35
3.12
Mile Island 1 resumed commercial power generation 10/85 after being under regulatory restraint since 1979.
" Three Mile Island 2 has been shut down since the 1979 accident but was still included in the count of reactors through 1988 since
dose was still being accumulated to defuel and decontaminate the unit during this time period. Parentheses indicate plant capacity when plant was operational. Since 2001 the dose breakdowns for Three Mile Island 2 have been reported with those for Unit 1.
" Trojan ended commercial operation as of 1/93 and will not be put in commercial operation again. It is no longer in the count of
operating reactors. Parentheses indicate plant capacity when plant was operational.
14 Three
C-33
NUREG-071 3
NUREG-0713
Occupational Radiation Exposure at NRC Ucensed Facilities
Occupational Radiation Exposure at NRC licensed Facilities
7hirty4eventhAnnudReport, 2004
Thirty-Seventh Annual Repor*. 2004
reSslF
L
*S
C
S
TROJAN"
(continued)
TURKEY POINT 3,4
Docket 50-250, 50-251;
DPR-31, -41
1st commercial operation
12172, 9/73
Type - PWRs
Capacity - 693, 693 MWe
VERMONT YANKEE
Docket 50-271; DPR-28
1st commercial operation 11/72
Type - BWR
Capacity - 510 MWe
'
.
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
1973
1974
1975
1976
1977
1978
1979
1980
1981
1982
1983
.
1.
553.9
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
401.9
953.6
1,003.7
974.2
979.5
1,000.2
811.0
990.6
654.0
915.7
878.4
946.7
1,034.9
754.1
431.3
809.8
689.9
933.1
258.2
968.9
1,244.8
1,172.9
1,320.3
1,307.8
1,220.9
1,323.0
1,352.5
1,283.7
1,324.1
1,374.0
1,253.2
1.231.0
222.1
303.5
429.0
389.6
423.5
387.5
414.0
357.8
429.1
501.0
346.1
S1
.*.
i.
.
S
IS
I ... . i! :
84
21
9
44
41
41
46
52
18
1
1
24
0
78
454
876
1,184
1,036
1,032
1,680
1,651
2,251
2,119
2,681
1,255
1,253
946
1,371
738
433
730
939
325
275
476
215
187
414
156
128
220
102
74
247
117
85
216
153
411
258
339
1,170
1,338
731
205
1,527
0.15
0.39
0.18
0.31
0.37
0.18
0.16
0.19
0.14
0.08
0.04
0.23
0.02
0.18
0.57
0.74
0.72
0.79
0.77
0.84
0.92
0.77
0.72
0.92
0.62
0.66
0.52
0.69
0.40
0.27
0.35
0.45
0.24
0.22
0.32
0.19
0.16
0.26
0.15
0.14
0.17
0.12
0.09
0.17
0.11
0.35
0.61
0.54
0.50
0.40
0.36
0.96
0.93
0.58
0.43
1.16
0.15
:
68.4
68.4
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
74.9
71.2
72.1
78.8
62.4
73.6
46.8
65.2
62.8
68.5
74.7
54.9
36.6
59.5
56.8
69.0
21.0
75.5
91.0
87.2
94.6
94.0
88.6
94.5
96.5
92.2
95.0
97.9
91.6
89.9
87.8
77.1
85.1
75.9
82.1
71.5
84.6
96.0
69.3
567
54
51
141
112
227
283
274
127
14
13
105
5
444
794
1,176
1,647
1,319
1,336
2,002
1,803
2,932
2,956
2,930
2,010
1,905
1,808
1,980
1,841
1,625
2,099
2,087
1,374
1,271
1,489
1,142
1,157
1,581
1,045
919
1,292
827
793
1,442
1.089
244
357
282
815
641
934
1,220
1,443
1,264
481
1,316
-
-
-
0.19
0.48
0.87
1.22
1.06
1.03
2.07
1.67
3.44
2.31
3.05
1.33
1.21
1.25
3.18
0.91
0.63
0.78
3.64
0.34
0.22
0.41
0.16
0.14
0.34
0.12
0.09
0.17
0.08
0.05
0.20
0.10
0.38
0.71
0.36
1.05
0.61
0.87
2.83
3.74
1.70
0.41
4.41
Trojan ended commercial operation as of 1193 and will not be put in commercial operation again. It isno longer inthe count of
operating reactors. Parentheses indicate plant capacity when plant was operational.
NUREG-0713
C-34
C-34
AinySeventb A/nnugl Report, 200N
Occupational Radiation Exposure at NRC licensed Facilities
:..^.s
.
VERMONT YANKEE
(continued)
VOGTLE 1, 2
Docket 50-424; 50-425;
NPF-68.-81
1st commercial operation
6/87, 5/89
Type - PWRs
Capacity -1152,1149 MWe
WATERFORD
Docket S0-382; NPF-38
1st commercial operation 9/85
Type - PWR
Capacity - 1075 MWe
AC
1984
1985
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
I.
398.1
361.4
248.1
423.6
492.1
432.8
433.1
492.3
446.8
402.3
515.8
462.1
452.7
487.1
383.4
463.4
517.8
474.9
451.0
505.9
439.2
820.4
1,045.8
1,710.9
1,966.5
2,047.9
2,060.4
2,170.1
2,285.4
2,056.8
2,121.1
2,123.9
2,106.0
2,223.9
2,231.5
1,942.0
2,179.9
2,200.7
875.7
891.8
784.3
909.8
1,027.9
870.6
909.6
1,088.3
949.1
927.4
1,064.8
767.2
984.1
849.5
965.1
1,086.0
1,007.0
968.0
1,099.1
.a.
;.
.
79.0
71.8
48.9
84.2
95.7
84.7
85.9
94.3
88.1
80.1
98.7
87.0
85.2
96.0
77.9
91.0
99.6
93.5
91.7
98.8
87.2
77.7
96.0
82.7
89.2
90.0
88.3
91.3
95.2
86.5
91.4
92.3
91.5
95.6
96.2
85.3
94.8
95.7
79.1
82.5
75.4
82.6
92.8
79.8
83.2
99.4
87.0
83.4
94.2
71.2
91.9
79.6
88.8
99.6
93.2
90.9
100.0
C-35
I:
...*!:C:
954
1,392
1,389
827
379
832
849
310
921
833
220
737
951
260
944
854
198
863
946
359
1,379
1,108
427
1,602
1.357
1.262
1.338
1,048
953
1,395
994
994
1.359
899
870
1,152
806
765
1,244
959
1,246
1,306
432
1,301
1,213
195
1,167
1,092
342
1,186
282
833
825
91
811
710
60
3.
3.:!.
s
626
1.051
1,188
303
124
288
307
118
381
217
38
182
231
57
199
176
38
143
150
54
212
138
32
466
362
426
367
217
199
452
158
162
229
121
129
244
84
81
223
156
259
265
47
364
226
15
191
153
27
148
24
123
132
5
109
95
3
0.66
0.76
0.86
0.37
0.33
0.35
0.36
0.38
0.41
0.26
0.17
0.25
0.24
0.22
0.21
0.21
0.19
0.17
0.16
0.15
0.15
0.12
0.07
0.29
0.27
0.34
0.27
0.21
0.21
0.32
0.16
0.16
0.17
0.14
0.15
0.21
0.10
0.11
0.18
0.16
0.21
0.20
0.11
0.28
0.19
0.08
0.16
0.14
0.08
0.13
0.09
0.15
0.16
0.05
0.14
0.13
0.04
!.
1.57
2.91
4.79
0.72
0.25
0.67
0.71
0.24
0.85
0.54
0.07
0.39
0.51
0.12
0.52
0.38
0.07
0.30
0.33
0.11
0.48
0.17
0.03
0.27
0.18
0.21
0.18
0.10
0.09
0.22
0.07
0.08
0.11
0.05
0.06
0.13
0.04
0.04
0.25
0.17
0.33
0.29
0.05
0.42
0.25
0.01
0.20
0.16
0.03
0.19
0.02
0.14
0.14
0.00
0.11
0.10
-
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Occupational Radiation Exposure a: NRC Licensed Facilities
**
S
WATTS BAR 1
Docket 50-390; NPF-90
1st commeraal operation 5196
Type - PWR
Capacity- 1121 MVe
WOLF CREEK 1
Docket 50-482; NPF-42
1st commercial operation 9/85
Type - PWR
Capacity- 1166MIe
YANKEE ROWE1 T
Docket 50-29; DPR-3
1st commercial operation 7/61
Type - PWR
Capacity - (175) MWe
.
.
1997
1998
1999
2000
2001
2002
2003
2004
1986
1987
1988
1989
1990
1991
1992
1993
1994
1995
1996
1997
1998
1999
2000
2001
2002
2003
2004
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
7hirty-SeventhAnnud Report,2004
Thirty-Seventh Annual Reporu 2004
867.6
1,105.1
943.1
1,033.3
1,095.9
1,034.0
973.3
1,122.1
832.8
778.8
794.7
1,108.4
940.2
707.6
1,010.8
940.5
1,017.2
1,198.0
980.6
964.3
1,187.3
1,045.3
1,032.7
1,177.9
1,029.0
1,013.5
1,153.5
138.3
146.1
173.5
78.7
127.1
111.3
145.1
152.2
124.6
145.0
149.0
35.6
109.0
108.6
163.5
124.8
144.3
169.7
138.7
136.4
159.4
101.1
121.2
0.0
0.0
0.0
0.0
0.0
83.8
99.1
87.2
92.8
96.5
92.1
86.7
99.1
73.3
71.1
70.7
99.5
81.0
71.9
86.7
80.6
86.8
98.7
81.2
83.8
100.0
90.1
89.5
100.0
88.7
87.2
98.8
82.4
89.8
73.9
81.0
81.6
22.0
74.4
73.4
91.4
71.4
85.3
95.0
82.7
85.2
92.9
61.5
72.3
0.0
0.0
0.0
0.0
0.0
1,103
96
975
1,053
197
909
1,392
220
682
675
1.010
186
798
1,010
446
975
1,082
242
986
989
184
812
861
105
816
820
93
193
355
155
282
133
243
249
152
725
565
441
502
515
814
395
654
653
384
593
738
496
702
162
324
313
222
191
239
S.
.
113
3
99
122
6
94
166
6
143
138
297
18
195
331
78
183
235
14
171
265
10
148
143
5
100
89
3
215
255
90
255
99
205
116
59
356
282
127
213
302
474
68
348
211
45
217
227
62
246
40
94
163
156
78
95
a
0.10
0.03
0.10
0.12
0.03
0.10
0.12
0.03
0.21
0.20
0.29
0.10
0.24
0.33
0.17
0.19
0.22
0.06
0.17
0.27
0.05
0.18
0.17
0.05
0.12
0.11
0.04
1.11
0.72
0.58
0.90
0.74
0.84
0.47
0.39
0.49
0.50
0.29
0.42
0.59
0.58
0.17
0.53
0.32
0.12
0.37
0.31
0.12
0.35
0.25
0.29
0.52
0.70
0.41
0.40
0.13
0.00
0.10
0.12
0.01
0.09
0.17
0.01
0.17
0.18
0.37
0.02
0.21
0.47
0.08
0.19
0.23
0.01
0.17
0.27
0.01
0.14
0.14
0.00
0.10
0.09
1.55
1.75
0.52
3.24
0.78
1.84
0.80
0.39
2.86
1.94
0.85
5.98
2.77
4.36
0.42
2.79
1.46
0.27
1.56
1.68
0.39
2.43
0.33
-
'7Yankee Rowe ended commercial operation as of 10/91 and will not be put in commercial operation again. It is no longer in the
count of operating reactors. Parentheses indicate plant capacity when plant was operational.
' Zion 1, 2 was shut down 12/97 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity
when plant was operational.
NUREG-0713
NUREG-0713
C-36
C-36
Occupational Radiation Exposure at NRC licensed Facilities
Aingy SeventbAnnud Report, 2004
rein
j~~~~~~~
YANKEE ROWE'T
(continued)
ZION 11, 21"
Dodet 50-295; 50-304;
DPR-39, -48
1st commercial operation
12/73, 9/74
Type - PWRs
Capacity - (1040), (1040) MWe
1997
1998
1999
2000
2001
2002
2003
2004
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
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
425.3
1,181.5
1.134.9
1,358.6
1,613.5
1,238.0
1,411.2
1,366.9
1,186.4
1,222.3
1,389.9
1,187.9
1,462.0
1,337.0
1,549.1
1,514.1
860.4
1,125.7
1,128.8
1,458.2
1,224.9
1,471.6
1,538.4
123.2
0.0
0.0
0.0
0.0
0.0
0.0
0.0
i.j1f!
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
71.1
74.9
61.9
75.0
80.2
67.6
74.1
72.3
64.3
69.4
69.6
62.9
73.2
71.0
78.3
77.6
46.9
58.2
59.0
70.9
59.9
72.4
75.8
7.1
0.0
0.0
0.0
0.0
0.0
0.0
0.0
.1
323
125
83
38
48
128
136
70
306
436
774
784
1,104
1,472
1.363
1.754
1,575
1,285
1,110
1,498
967
1,046
1,926
1,282
1,385
902
1,732
1,772
1,176
1,807
1,567
924
246
67
26
6
12
2
6
,1f
65
5
2
2
4
20
31
7
56
127
571
1,003
1,017
1,274
920
1,720
2,103
1,311
786
1,166
474
653
1,260
624
696
173
1,043
643
306
797
437
119
12
4
3
0
0
0
0
W.'!a2
0.20
0.04
0.02
0.06
0.08
0.16
0.23
0.09
0.18
0.29
0.74
1.28
0.92
0.87
0.67
0.98
1.34
1.02
0.71
0.78
0.49
0.62
0.65
0.49
0.50
0.19
0.60
0.36
0.26
0.44
0.28
0.13
0.05
0.06
0.12
0.05
0.02
0.02
0.03
-
0.13
0.11
0.50
0.74
0.63
1.03
0.65
1.26
1.77
1.07
0.57
0.98
0.32
0.49
0.81
0.41
0.81
0.15
0.92
0.44
0.25
0.54
0.28
0.97
-
to Yankee Rowe ended commercial operation as of 10/91 and will not be put in commercial operation again. It is no longer in the
count of operating reactors. Parentheses indicate plant capacity when plant was operational.
"Zion 1, 2 was shut down 12/97 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity
when plant was operational.
C-37
NUREG-071 3
NUREG-0713
Appendix D*
DOSE PERFORMANCE INDICATORS BY REACTOR SITE
1973-2004
* Appendix
D only contains data on plants in operation during 2004.
D-1
D-1
NUREG-0713
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
D1irty-SeventlwAnnud Report, 2004
ARKANSAS 1,2
Dose Performance Indicators
PWR
,2000
X.2
IU
is
Year
BEAVER VALLEY 1, 2
Dose Performance Indicators
I
.1
I
I
O 9
O 9
i
I
i I
Year
NUREG-0713
D-2
77irly-vnthAnnualRrport, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
BRAIDWOOD 1, 2
Dose Performance Indicators
PWR
I
I!
'I
4
Year
BROWNS FERRY 1, 2,3
Dose Performance Indicators
BWR
I
Ii
co
Year
D-3
NUREG-071 3
NUREG-071 3
MirtySeventhAnnud Report, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
BRUNSWICK 1, 2
Dose Performance Indicators
I
I
a.
1000 d
Year
BYRON 1, 2
Dose Performance Indicators
PWR
1200
1000
MWZ520
Average Coffective Dose Per Reactor
3
3Year
-*
Colecdv Dose Per Reactor
_
PWR Average Colective Dose Per Reactor
…-2000
Boo
II
o
4'
aoo
400
200
o
i
I
!Y
I
I
11
§
7I_500
§__
!
Year
NUREG-0713
- 000
I~F<o71
D-4
D4
!
I
i I I A
Occupational Radiation Exposure at NRC Licensed Facilities
Uhiny-ventlJAnnuReport,2004
CALLAWAY I
Dose Performance Indicators
PWR
800 - _
2C
* * * 3-Year Average Colecave Dose Per Reactor
-
-
MW-Years
Colective Dose Per Reactor
PWRAverage Colective Dose Per Reactor
600-
-
_
.
-
I~n
Year
CALVERT CLIFFS 1, 2
Dose Performance Indicators
PWR
'°°°--
a
*
_
_
___________
3-Year Average Cdoective Dose Per Reactr
11
Colective Dose Per Reactor
MW-Years
______________
_-25
-20
PWR Average Colective Dose Per Reactor
go -1:
1%0,
-
i
i:
i
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i
go I 9
I
I
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;
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_
_-
I I I i I I I A I I A
Year
D-5
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Mriy-SventhAnnugaleport,2004
CATAWBA 1, 2
Dose Performance Indicators
PWR
I
I
I
I I
i
I|
I
I
I
1 I I ai i I
I
I
i
I
I
I
i
,
I
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1 a I A I I IS
Year
CLINTON
Dose Performance Indicators
BWR
-
- 1200
-1000
I
4'
I
I7
_
a
Xa
i i I
i
I
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Year
NUREG-0713
D-6
D-6
a
I
I
I
I
IY Aea
7birty-Seventht Annual Report,2004
Occupational Radiation Exposure at NRC Licensed Facilities
I-
COLUMBIA GENERATING
Dose Performance Indicators
BWR
1400
,r-r1500
!I
I I
8
I I I i g
fI
fI I I i I I I E I I fI
Year
COMANCHE PEAK 1, 2
Dose Performance Indicators
PWR
I
Year
D-7
NUREG-0713
NUREG-0713
-
Mhrty-SeventhAnnudlReport, 2004
Occupational Raldiation Exposure at NRC Licensed Facilities
COOK 1, 2
Dose-Performance Indicators
PWR
T
I
Year
COOPER STATION
Dose-Performance Indicators
BWR
T
I
w
,1
I
I
I
I
II
I I
.
I
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I
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.
I
Year
NUREG-0713
D-8
I.
.
I
I
I
I
I
I
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.
.I
Occupational Radiation Exposure at NRC Licensed Facilities
Mnrry-&ent5AnnualReport,2004
CRYSTAL RIVER 3
Dose-Performance Indicators
PWR
7
*ooo - _7_I
m
]
S3-Year Average Collective Dose Per Reactor
"
__-2
.
-MW-Years
Collective Dose Per Reactor
-
-
1
|
PWR Average Collective Dose Per Ratr
-
804
6004
"40
600- _
-0
J
11fk.W
AL1i\
404
1L_
2t0
It~
I
0
-0
----- ---- - --- -- Year
DAVIS-BESSE
Dose-Performance Indicators
PWR
250
-
3-Year Average Collectve Dose Per Reactor
* ,
Colleetive Dose Per Reactor
8W
-
-
m
-
MW-rasm
PWR Average Colective Dose Per Reactor
j600
7!-
_=|
9
I
i
9
I
I
I
ON 9
8
I
I
§ I I I I I k I I A g I I A
Year
D-9
NUREG-0713
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
7hirtySeventhAnnual~eport,200N
DIABLO CANYON 1, 2
Dose Performance Indicators
PWR
-we%^
-I I I I I I I I I I
I
.
00-
500-
.-
I
I 4UU
a
.
3-Year Average Colective Dose Per Reactor
I
1
Colecie Dose Per Reactor
V-
-
Y
-
_
MW-Yesrs
-2500
I-
I~l
I I I
.. . . . .
PWR Average Collective Dose Per Reactor
I
--
I LI1.
I
-
-2000
W*"?ft%4w-W
-15W
Viz
~
I
200
.00
100
-I
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f%
II
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g
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a
I;
I
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I
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A
-
500
-
n
I11
I
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Year
DRESDEN 2, 3
Dose Performance Indicators
BWR
.
2000
,,
I
1500
IL
1000 X
500
I
i
I
I
I
I
I
r
I
T
a 0j;e i0 9 9 9aI
i
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I I3
I 1
Year
NUREG-071
NUREG-07133
D-1 0
D-10
i
§ §aa I i fI
I
|I
I
I
I 1
Ie A
1
II
r
B~irtySeventhAnnudaleport,2004
Occupational Radiation Exposure t NRC Licensed Facilities
DUANE ARNOLD
Dose Performance Indicators
BWR
0I
0
9 S s I I E 9 I I I I i I I Y g, I I fI I E f I I I - 1 I
Year
FARLEY 1, 2
Dose Performance Indicators
PWR
E
umu
ii S
h
o
aM O _ N! rM
a w
w o)a CD
~~~-
u
v
W
D r1
w
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aw
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u to
M
r9 N
o
N tNs
_
a
-
-
-
-
-
-
tN
N
cmN
N
Year
D-ll
D-11NURE-071
NUREG-0713
7birtySventiAnnual Report, 2004
Occupational Radiaton Exposure at NRC Licensed Facilitie
FERMI 2
Dose-Performance Indicators
BWR
-.- ,1500
I
I
Ir
>.
1000
I
500
I
aa
I
I
Year
FITZPATRICK
Dose-Performance Indicators
BWR
-
_
* *.
3-Year Average Colective Dose Per Reactor
WUu
I
WYears
=
_ _
Colecive Dose Per Reactor
2500 -
-
I
__
IIIIiI
I
30
PWR Average Codlective Dose Per Reactor
I
iO
15054
4i
I
-41DO
DO
I
I
_ _ _ _ _ _ _ _ _ _ _ _a' __I
§ Ri
fear
NUREG-0713
D-12
D-12
0I
T
I
- I
IR
II
Occupational Radiation Exposure at NRC Licensed Facilities
7birry-SeventhAnnuel Report, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Thirty-Seveizdi Annual Repors 2004
FORT CALHOUN
Dose-Performance Indicators
1000 -
I
__
__T
H
3-Year Average Colective Dose Per Reactor
*
Collective Dose Per Reactor
|
I I
_
PWR
-750
_ _
MW-Years
PWR Average Collective Dose Per Reactorr
750 - -
|
[500 S
ll;
|
1>LiF_
-M
As
>
500
/ls
/
Vow
Year
GINNA
Dose-Performance Indicators
PWR
2000- _ .
_
I
1 I
1 I
I1
I
1_ I
1
I1 I_
_ _-
_
-
-750
w as 3-YearAverageCollectveDosePerReactor
Collective Dose Per Reactor
-
1500
U'
I
mo,
AL
0-0op
-
……_
PWR Average Colective Dose Per Reactor
-
i
u
-
1500
4
-
I
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6
I
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Year
D-13
NUREG-0713
7birty-Seventh Annul Report, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
GRAND GULF
Dose-Performance Indicators
BWR
I
if
I
I
iI
I
r
a
I
a
I
I
§
i
I
a
I
I
I
I
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I Yi
I
a
I
a
I
I
I1
i
I
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Year
HARRIS
Dose-Performance Indicators
PWR
I
I
Year
NUREG-0713
D-14
D-14
Mhirty-Sevent5AnnualReport,2004
Occupational Radiation Exposure at NRC Licensed Facilities
HATCH 1, 2
Dose-Performance Indicators
BWR
I
I
d
ha.
I
Year
HOPE CREEK 1
Dose-Performance Indicators
BWR
I
i
I
I
8
Year
D-15
NUREG-0713
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
7bity-SeventhAnnual Piport,2004
INDIAN POINT 2
Dose-Performance Indicators
PWR
-,--
2000
I
I
a-
{:9 i rz j: aI i - -l
IE
3}I - Ia- I a-
-
I'--
- a
- I - Ia
- I a a AI
8§ 3 af
A
Year
INDIAN POINT 3
Dose-Performance Indicators
PWR
I
- I
_
I
I
: I
i
i I
I
i
iT
i
I
J
T
i I I a' I I I
I
i
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Year
NUREG-0713
D-16
I
I
I
I
i
i
I i I
I
T
I
T -
i I 1 1- 1 1 Ei X I RI A
Occupational Radiation Eposurm at NRC Licensed Faclities
Thirty-SevenxtArnnul Report, 2 94
KEWAUNEE
Dose-Performance Indicators
PWR
1o00
TT-17-rr-r-r-r-r-
,,
I.
I
j
g* 41
2t
§ I I fI I I i I I I i I I2
EiD: 9: 9 I -a 9 I I I I 9 I I
Year
E6
LASALLE 1,2
Dose-Performance Indicators
BWR
.
I
I
I
,
I
,
I
9
I
I
I
I
9
I
i
I
9
i
I
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i
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Year
I
k
I
I
I
D-17
i
I
A E
i
i
I
I
In
A
NUREG-071 3
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
7hirtySeenlthAnnud Report,200
LIMERICK 1, 2
Dose-Performance Indicators
BWR
*,--,3000
#4
i
0.
it
I1
Year
MCQUIRE 1, 2
Dose-Performance Indicators
PWR
- -
,- 3000
I
I
I
0.
gT
I
,
i
i
i
I
i
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j
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Year
NUREG-0713
D-18
D-18
i
II
,
i
I
i
,
I
I
i
I
I
Occupational Radiation Exposure at NRC Licensed Facilities
Dhirty4eventbAnnul Report, 2iW4
MILLSTONE UNIT 2, 3
Dose-Performance Indicators
PWR
I
I
I
I
iI
III
I
I
I
I
I
I
I
I
I ,
I
I
I
I
I O, 2W
a
Mi
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I
i
I
I
I
I
III
i
Year
MONTICELLO
Dose-Performance Indicators
BWR
I
II
IS
Year
D-19
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
7hirtySeventbAnanualeport,200
NINE MILE POINT 1, 2
Dose-Performance Indicators
BWR
I
i
d
I
99
_ me t g 9
5i aI
SC
i I I l IeIa1 1 § a i A I I iaY a I
I I
Year
NORTH ANNA 1, 2
Dose-Performance Indicators
PWR
I
I
a'
a.
.
r.
Year
NUREG-0713
D-20
D-20
.
. ...
.
I
Occupational Radiation Exposur at NRC Licensed Facilities
7birty-SeventhAnn alReport, 2004
OCONEE 1, 2, 3
lDose-Performance Indicators
PWR
---
LRu....
I
I
I
I
I
I
I
I
I
I
I
I
I
I
I
I
I
3-Year Average Cofective Dose Per Reactor
*,
Colective Dose Per Reactor
-
PWR Average Colective Dose Per Reactor
-
-
/
z0
K
l
A
(2
-
I I
-f_ - I_-
-
II
I-ID
I- -
JA
I9
.
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.
-2000
-1500
L
5%
._
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-1000
V
._
_ ._
. _
. _
.
.I
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I
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-
-
-
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MW-Years
-m
800-
VUU
3UU
.
.
I
I
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_
I
I
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Year
OYSTER CREEK
Dose-Performance Indicators
BWR
,,
..
1000
Iw
2:
!, Ye
- -. - -: - - -, -T
- - -, - -, -B - - -£||i - - - Year
D-21
NUREG-0713
Occupatoayaito
xouea
R Licensed Faciltie
Mhrsy-Seventb Annudz Report, 2004
PALISADES
Dose-Performance Indicators
PWR
,,
-1000
I
d
I
aif
Q
I;; 8;
; CP
t; I
Ii
Si
4 I
i
|I IN I § ai
i I a i 7a a A - SC I A
Year
PALO VERDE 1, 2, 3
Dose-Performance Indicators
PWR
I
I
GI
S
Year
NUREG-0713
D-22
D-22
Occupational Radiation Exposure at NRC Licensed Facilities
7hirty-SeventhAnnud Report,2004
PEACH BOTTOM 2, 3
IDose-Performance Indicators
PWR
I
I
Mi
I
I
I
I
I
I
II
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PERRY
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BWR- ..
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D-23
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NUREG-0713
NUREG-0713
Mn-SvntbAnnual Report,2004
Occupational Radiation Exposure at NRC Licensed Facilities
PILGRIM
Dose-Performance Indicators
BWR
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Occupational Radiation Exposure at NRC Licensed Facilities
PRAIRIE ISLAND 1, 2
Dose-Performance Indicators
PWR
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QUAD CITIES 1, 2
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D-25
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
7bbiySeventhb Annual Report,2004
Thiny-Seventh Anniwi Repor* 2004
Occupational Radiation Exposure at NRC Licensed Facilities
RIVER BEND I
Dose-Performance Indicators
BWR
1000-
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Occupational Radiation Exposure at NRC Licensed Fadilities
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D-27
NUREG-0713
7I4lySeventhAnnudlReport, 2004
Occupational Radiation Exposure at NRC Licensed F~acilities
SEABROOK
Dose-Performance Indicators
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Occupatifonal Radiation Exposure at NRC Licfensed 6Fadit
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2birty-evnthAnnuil Beort, 2004
Occupational Radiation Exposure at NRC Licensed Facilities
Thirty-Seventh Annual Report; 2004
Occupational Radiation Exposure at NRC Licensed Facilities
SUMMER I
Dose-Performance Indicators
PWR
1000-
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D-31
NTJREG-071 3
NUREG-0713
Thirty-SeventhAnnul Report; 2004
Occupational Radiation Exposure at NRC Licensed Facilities
-
TURKEY POINT 3, 4
Dose-Performance Indicators
PWR
20002000-_
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[
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D-32
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Occupational Radiation Exposure at NRC licensed Failities
VOGTLE 1, 2
Dose-Performance Indicators
PWR
I
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2
Year
WATERFORD 3
Dose-Performance Indicators
PWR
I
to
mu
Year
D-33
NUREG-0713
Occupational Radiation Exposure at NRC Licensed Facilities
Dip
ty-SeveunthAnnualRporms 2004
WATTS BAR I
Dose-Performance Indicators
PWR
500-
400
-
3-Year Average Colective Dose Per Reactor
Collective Dose Per Reactor
-
PWR Average Coleclive Dose Per Reactor
300
d
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100
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Year
WOLF CREEK I
Dose-Performance Indicators
600
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Collective Dose Per Reactor
400-
PWR Average Colledve Dose Per Reactor
I
Year
NUREG-0713
D-34
J
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PWR
NRC FORM 335
(9-2004)
NRCMD 3.7
U.S. NUCLEAR REGULATORY COMMISSION
1. REPORT NUMBER
(Assigned by NRCMAdd Vol., Supp., Reev.,
and Addendumn Numbers, It any.)
BIBLIOGRAPHIC DATA SHEET
Volers)Vume
26
(See kanuictins on th
Z TITLE AND SUBTITLE
3. DATE REPORT PUBLISHED
Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities
2004
YEA
December
Thirty-Seventh Annual Report
2005
4. FIN OR GRANT NUMBER
N6081
5. AUTHOR(S)
6. TYPE OF REPORT
S. A. Burrows
Final
D.A. Hagemeyer*
7. PERIOD COVERED
(lncustve Dates)
01/01/04 - 12/31/04
8. PERFORMING ORGANIZATION -NAME AND ADDRESS (iNRC.
pmvideso OfficorRgbn. U.S. NudearAe
,yComnuon.andmagaddess; ctrtor,
provft nme and mali addrs.)
Division of Systems Analysis and Regulatory Effectiveness
Office of Nuclear Regulatory Research
U. S. Nuclear Regulatory Commission
Washington, DC 20555-0001
*OakRidge Associated Universities
210 Badger Road
Oak Ridge, TN 37830
9. SPONSORING ORGANIZATION -NAME AND ADDRESS (#fNRC. tye Same as above';fcontrcor, ProvkVNRC~hosn,
Offic Ort/g,
U.S Nudzar~tegoltdWYCommisbon
and marft address.)
Same as 8. above
10. SUPPLEMENTARY NOTES
11. ABSTRACT (200 woids or las)
This report summarizes the 2004 occupational radiation exposure data that are maintained in the U.S. Nuclear Regulatory
Commission's (NRC's) Radiation Exposure Information and Reporting System (REIRS) database. The bulk of the information
contained in the report was compiled from the 2004 annual reports submitted by five of the seven categories of NRC licensees
subject to the reporting requirements of 10 CFR 20.2206. Annual reports of occupational radiation exposure for 2004 were
received from 227 NRC licesees, of which 104 were operators of nuclear power reactors in commercial operation.
12- KEY WORDS/DESCRIPTORS (List words or phrases that wil assist researchers in locart the report.)
occupational
radiation
13. AVAtNABLITY STATEMENT
unlimited
14. SECURITY CLASSIFICATION
exposure
(This page)
unclassified
dose
REIRS
Tis Report)
unclassified
15. NUMBER OF PAGES
16. PRICE
NR
FOR
(9204
NRC FORM 335 (9-2004)
..
_R
__YCE
E O_
P_..
PRINTED ON RECYCLED PAPER
Federal Recycling Program
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, DC 20555-0001
OFFICIAL BUSINESS