NUREG-0713, Vol.41, Occupation Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2019: Fifty-Second Annual Report

NUREG-0713, Vol.41, Occupation Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2019: Fifty-Second Annual Report

ML22111A013
Person / Time
Issue date:	04/30/2022
From:	Terry Brock, Hagemeyer D, Holcomb D, Minh-Thuy Nguyen Office of Nuclear Regulatory Research, Oak Ridge Associated Universities
To:
Malone Tina
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NUREG-0713 V41
Download: ML22111A013 (240)

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NUREG-0713 Volume 41 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2019 Fifty-Second Annual Report Office of Nuclear Regulatory Research

AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS NRC Reference Material Non-NRC Reference Material As of November 1999, you may electronically access Documents available from public and special technical NUREG-series publications and other NRC records at the libraries include all open literature items, such as books, NRCs Library at www.nrc.gov/reading-rm.html. Publicly journal articles, transactions, Federal Register notices, released records include, to name a few, NUREG-series Federal and State legislation, and congressional reports.

publications; Federal Register notices; applicant, licensee, Such documents as theses, dissertations, foreign reports and vendor documents and correspondence; NRC and translations, and non-NRC conference proceedings correspondence and internal memoranda; bulletins and may be purchased from their sponsoring organization.

information notices; inspection and investigative reports; licensee event reports; and Commission papers and their Copies of industry codes and standards used in a attachments. substantive manner in the NRC regulatory process are maintained at NRC publications in the NUREG series, NRC regulations, The NRC Technical Library and Title 10, Energy, in the Code of Federal Regulations Two White Flint North may also be purchased from one of these two sources: 11545 Rockville Pike Rockville, MD 20852-2738

1. The Superintendent of Documents U.S. Government Publishing Office These standards are available in the library for reference Washington, DC 20402-0001 use by the public. Codes and standards are usually Internet: www.bookstore.gpo.gov copyrighted and may be purchased from the originating Telephone: (202) 512-1800 organization or, if they are American National Standards, Fax: (202) 512-2104 from American National Standards Institute

2. The National Technical Information Service 11 West 42nd Street 5301 Shawnee Road New York, NY 10036-8002 Alexandria, VA 22312-0002 Internet: www.ansi.org Internet: www.ntis.gov (212) 642-4900 1-800-553-6847 or, locally, (703) 605-6000 Legally binding regulatory requirements are stated only in A single copy of each NRC draft report for comment is laws; NRC regulations; licenses, including technical available free, to the extent of supply, upon written specifications; or orders, not in NUREG-series publications.

The views expressed in contractor prepared publications in request as follows:

this series are not necessarily those of the NRC.

Address: U.S. Nuclear Regulatory Commission The NUREG series comprises (1) technical and Office of Administration administrative reports and books prepared by the staff (NUREG-XXXX) or agency contractors (NUREG/CR-XXXX),

Division of Resource Management & Analysis (2) proceedings of conferences (NUREG/CP-XXXX),

Washington, DC 20555-0001 (3) reports resulting from international agreements E-mail: distribution.resource@nrc.gov (NUREG/IA-XXXX),(4) brochures (NUREG/BR-XXXX), and Facsimile: (301) 415-2289 (5) compilations of legal decisions and orders of the Commission and the Atomic and Safety Licensing Boards and of Directors decisions under Section 2.206 of the NRCs regulations (NUREG-0750).

Some publications in the NUREG series that are posted at the NRCs Web site address www.nrc.gov/reading-rm/ DISCLAIMER: This report was prepared as an account doc-collections/nuregs are updated periodically and may of work sponsored by an agency of the U.S. Government.

differ from the last printed version. Although references to Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, material found on a Web site bear the date the material or assumes any legal liability or responsibility for any third was accessed, the material available on the date cited partys use, or the results of such use, of any information, may subsequently be removed from the site. apparatus, product, or process disclosed in this publication, or represents that its use by such third party would not infringe privately owned rights.

NUREG-0713 Volume 41 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2019 Fifty-Second Annual Report Manuscript Completed: June 2021 Date Published: April 2022 Prepared by T.A. Brock M.N. Nguyen D.A. Hagemeyer*

D.B Holcomb*

• ORAU 1299 Bethel Valley Road, SC-200, MS-21 Oak Ridge, TN 37830 M.N. Nguyen, NRC Project Manager Office of Nuclear Regulatory Research

PREVIOUS REPORTS IN THIS SERIES WASH-1311 A Compilation of Occupational Radiation Exposure from Light Water Cooled Nuclear Power Plants, 1969-1973, U.S. Atomic Energy Commission, May 1974.

NUREG-75/032 Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969-1974, U.S. Nuclear Regulatory Commission, June 1975.

NUREG-0109 Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969-1975, U.S. Nuclear Regulatory Commission, August 1976.

NUREG-0323 Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969-1976, U.S. Nuclear Regulatory Commission, March 1978.

NUREG-0482 Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1977, U.S. Nuclear Regulatory Commission, May 1979.

NUREG-0594 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1978, U.S. Nuclear Regulatory Commission, November 1979.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1979, Vol. 1, U.S. Nuclear Regulatory Commission, March 1981.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1980, Vol. 2, U.S. Nuclear Regulatory Commission, December 1981.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1981, Vol. 3, U.S. Nuclear Regulatory Commission, November 1982.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1982, Vol. 4, U.S. Nuclear Regulatory Commission, December 1983.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors, 1983, Vol. 5, U.S. Nuclear Regulatory Commission, March 1985.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1984, Vol. 6, U.S. Nuclear Regulatory Commission, October 1986.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1985, Vol. 7, U.S. Nuclear Regulatory Commission, April 1988.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1986, Vol. 8, U.S. Nuclear Regulatory Commission, August 1989.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1987, Vol. 9, U.S. Nuclear Regulatory Commission, November 1990.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1988, Vol. 10, U.S. Nuclear Regulatory Commission, July 1991.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1989, Vol. 11, U.S. Nuclear Regulatory Commission, April 1992.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1990, Vol. 12, U.S. Nuclear Regulatory Commission, January 1993.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1991, Vol. 13, U.S. Nuclear Regulatory Commission, July 1993.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1992, Vol. 14, U.S. Nuclear Regulatory Commission, December 1993.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1993, Vol. 15, U.S. Nuclear Regulatory Commission, January 1995.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1994, Vol. 16, U.S. Nuclear Regulatory Commission, January 1996.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1995, Vol. 17, U.S. Nuclear Regulatory Commission, January 1997.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1996, Vol. 18, U.S. Nuclear Regulatory Commission, February 1998.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1997, Vol. 19, U.S. Nuclear Regulatory Commission, November 1998.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1998, Vol. 20, U.S. Nuclear Regulatory Commission, November 1999.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 1999, Vol. 21, U.S. Nuclear Regulatory Commission, October 2000.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2000, Vol. 22, U.S. Nuclear Regulatory Commission, September 2001.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2001, Vol. 23, U.S. Nuclear Regulatory Commission, September 2002.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2002, Vol. 24, U.S. Nuclear Regulatory Commission, October 2003.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2003, Vol. 25, U.S. Nuclear Regulatory Commission, October 2004.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2004, Vol. 26, U.S. Nuclear Regulatory Commission, December 2005.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2005, Vol. 27, U.S. Nuclear Regulatory Commission, December 2006.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2006, Vol. 28, U.S. Nuclear Regulatory Commission, November 2007.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2007, Vol. 29, U.S. Nuclear Regulatory Commission, December 2008.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2008, Vol. 30, U.S. Nuclear Regulatory Commission, December 2009.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2009, Vol. 31, U.S. Nuclear Regulatory Commission, April 2011.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2010, Vol. 32, U.S. Nuclear Regulatory Commission, May 2012.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2011, Vol. 33, U.S. Nuclear Regulatory Commission, April 2013.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2012, Vol. 34, U.S. Nuclear Regulatory Commission, April 2014.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2013, Vol. 35, U.S. Nuclear Regulatory Commission, December 2015.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2014, Vol. 36, U.S. Nuclear Regulatory Commission, April 2016.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2015, Vol. 37, U.S. Nuclear Regulatory Commission, September 2017.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2016, Vol. 38, U.S. Nuclear Regulatory Commission, May 2018.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2017, Vol. 39, U.S. Nuclear Regulatory Commission, March 2019.

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities, 2018, Vol. 40, U.S. Nuclear Regulatory Commission, April 2020.

Previous reports in the NUREG-0714 series, which are now combined with NUREG-0713, are as follows:

WASH-1350-R1/ First through Sixth Annual Reports of the Operation of the U.S. AECs Centralized Ionizing Radiation Exposure Records and Reporting WASH-1350 R6 System, U.S. Atomic Energy Commission.

NUREG-75/108 Seventh Annual Occupational Radiation Exposure Report for Certain NRC Licensees, 1974, U.S. Nuclear Regulatory Commission, October 1975.

NUREG-0119 Eighth Annual Occupational Radiation Exposure Report for 1975, U.S. Nuclear Regulatory Commission, October 1976.

NUREG-0322 Ninth Annual Occupational Radiation Exposure Report for 1976, U.S. Nuclear Regulatory Commission, October 1977.

NUREG-0463 Tenth Annual Occupational Radiation Exposure Report for 1977, U.S. Nuclear Regulatory Commission, October 1978.

NUREG-0593 Eleventh Annual Occupational Radiation Exposure Report for 1978, U.S. Nuclear Regulatory Commission, January 1981.

NUREG-0714 Twelfth Annual Occupational Radiation Exposure Report for 1979, Vol. 1, U.S. Nuclear Regulatory Commission, August 1982.

NUREG-0714 Occupational Radiation Exposure, Thirteenth and Fourteenth Annual Reports, 1980 and 1981, Vols. 2 and 3, U.S. Nuclear Regulatory Commission, October 1983.

NUREG-0714 Occupational Radiation Exposure, Fifteenth and Sixteenth Annual Reports, 1982 and 1983, Vols. 4 and 5, U.S. Nuclear Regulatory Commission, October 1985.

ABSTRACT This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission (NRC) Radiation Exposure Information and Reporting System (REIRS) database. The bulk of the information contained in this report was compiled from the 2019 annual reports submitted by five of the seven categories 1 of NRC licensees subject to the reporting requirements of Title 10 of the Code of Federal Regulations (10 CFR) 20.2206, Reports of Individual Monitoring. Because there are no geologic repositories for high-level waste currently licensed and no NRC-licensed low-level waste disposal facilities currently in operation, only five categories are considered in this report. 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.

In the Fiscal Year 2022 Annual Evaluation Plan [Ref. 11] the NRC developed its Annual Evaluation Plan which included an evaluation of the Radiation Protection Program. The purpose of the Outcome Evaluation of the Radiation Protection Program is to measure the effectiveness NRCs Radiation Protection Program as it pertains to as low as is reasonably achievable (ALARA) regulations of 10 CFR 20.1101(b) for each of the NRC-licensee categories. The evaluation included trend analysis of radiation exposure to transient individuals (i.e., those who have been to two or more sites during the year) as well as radiation exposure histories to individuals who were exposed to radiation at NRC-licensed facilities. The evaluation conducted for the Radiation Protection Program analyzed the radiological risk associated with certain categories of NRC-licensed activities and performed comparative analyses of radiation protection performance.

Based upon the trend analysis of the occupational exposure data, for all NRC-licensee categories, the overall NRC/licensee radiation protection program is effective with respect to ALARA.

Annual reports for 2019 were received from a total of 181 NRC licensees from the five categories included in this report. The summation of reports submitted by the 181 licensees indicated that 144,243 individuals were monitored, 60,289 of whom received a measurable dose (dose that is reported as a positive value, see Table 3.1). When adjusted for transient individuals, there were actually 102,182 unique individuals that were monitored, 44,848 of whom received a measurable dose (see Section 5).

The collective dose incurred by these individuals was 7,150 person-rem (71,500 person-millisieverts [mSv]), which represents a 12 percent decrease from the 2018 value (see Table 3.1). The 2019 collective dose is 14 percent lower than the 5-year average of 8,348 person-rem (2014 - 2018), which is a statistically significant change.2 The decrease in collective dose in 2019 was due to decreases in two categories offsetting increases in the remaining three reporting categories. Two reporting categories reported decreases, namely, industrial radiography licensees (15 percent decrease) and commercial nuclear power reactor licensees (13 percent decrease).

Three reporting categories reported increases; spent fuel storage licensees (11 percent increase), fuel cycle licenses (9 percent increase) and manufacturing and distribution (M&D) licensees (8 percent increase). When compared to the 5-year average of collective dose for 1 Commercial nuclear power reactors and test reactor facilities; industrial radiographers; fuel processors (including uranium enrichment facilities), fabricators, and reprocessors; manufacturing and distribution of byproduct material; independent spent fuel storage installations; facilities for land disposal of low-level waste; and geologic repositories for high-level waste. There are currently no NRC licensees involved in low-level waste disposal or geologic repositories for high-level waste.

2 This report presents additional Statistical Comparisons in Section 2.2.

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each category, commercial nuclear power reactor licensees had a statistically significant decrease. The increases or decreases for the remaining three categories were not statistically significant.

The number of individuals receiving a measurable dose decreased by 11 percent from 2018, and was 15 percent below the 5-year average and statistically significant. When adjusted for transient individuals, the average measurable dose of 0.20 rem (2.0 mSv) was slightly higher in 2019, compared to 0.17 rem (1.7 mSv) in 2018, and is statistically significant when compared to the 5-year average. The average measurable dose is defined as the total effective dose equivalent (TEDE) divided by the number of individuals receiving a measurable dose.

In calendar year 2019, the average annual collective dose per reactor for light-water reactor (LWR) licensees was 53 person-rem (530 person-mSv). This is a 10 percent decrease from the value reported for 2018 (Table 4.3) and is statistically significant when compared to the 5-year average. The total outage hours at commercial nuclear power plants decreased 12 percent from 2018 to 2019 [Ref. 1]. The collective dose for the LWR licensee category decreased 748 person-rem (7,480 person-mSv) from 5,829 person-rem (58,290 person-mSv) in 2018 to 5,081 person-rem (50,810 person-mSv). The average annual collective dose per reactor was 105 person-rem (1,050 person-mSv) for the 32 boiling-water reactors (BWRs) and 27 person-rem (270 person-mSv) for 64 pressurized-water reactors (PWRs). The BWR 2019 value is 6 percent lower than the 5-year average annual collective dose per BWR reactor, but is not statistically significant. The 2019 value for PWR licensees is 32 percent below the 5-year average annual collective dose per PWR reactor and is statistically significant when compared to the 5-year average. The primary driver for the decrease in collective dose was the closure of Three Mile Island 1 (PWR) and Pilgrim 1 (BWR).

There were 23,196 individuals that were monitored at two or more licensees during the monitoring year. The assessment of the average measurable dose per individual is adjusted each year to account for the reporting of a measurable dose for transient individuals by multiple licensees. The adjustment to account for transient individuals has been specifically noted in footnotes in the figures and tables for commercial nuclear power reactors.

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FOREWORD Through this annual report, the U.S. Nuclear Regulatory Commission (NRC) supports openness in its regulatory process by providing the public with accurate and timely information about the radiation protection program of NRC licensees. Toward that end, NUREG-0713, Volume 41, summarizes the 2019 occupational radiation exposure data maintained in the NRC Radiation Exposure Information and Reporting System (REIRS) database.

Seven categories of NRC licensees are required to report annually on individual exposure in accordance with Title 10 of the Code of Federal Regulations (10 CFR 20.2206, Reports of Individual Monitoring). Specifically, these categories include commercial nuclear power reactors and test reactor facilities; industrial radiographers; fuel processors (including uranium enrichment facilities), fabricators, and reprocessors; manufacturing and distribution 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 licensed any geologic repositories for high-level waste and all low-level waste disposal facilities are regulated by Agreement States, 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 181 licensees.

The data submitted by licensees consist of radiation exposure records for each monitored individual. Adjusted for transient individuals who worked at two or more facilities during the year, 102,182 were monitored and 44,848 received a measurable dose in 2019. This report analyzes and presents these records in terms of collective dose and the distribution of dose among the monitored individuals.

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PREFACE A number of U.S. Nuclear Regulatory Commission (NRC) licensees have inquired as to how the occupational radiation exposure data that are compiled from the individual exposure reports required by Title 10 of the Code of Federal Regulations (10 CFR) 20.2206, Reports of Individual Monitoring, 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 for use in making decisions that impact public health and safety. The NRC staff uses this data for the following purposes:

1. The data is used to perform a trend analysis that may produce either favorable or unfavorable results. The trend analysis, in part, provides insights into the evaluation findings for the effectiveness of the NRC and licensee radiation protection and as low as is reasonably achievable (ALARA) efforts.

2. The data is analyzed to make evidence-based decisions regarding the radiological risks associated with certain categories of NRC-licensed activities. A comparative analysis using the radiological risks is then performed to determine radiation protection performance (e.g., U.S./foreign, boiling-water reactors/pressurized-water reactors

[BWRs/PWRs], civilian/military, facility/facility, nuclear industry/other industries).

3. The data are used within the NRC Reactor Oversight Process for inspection planning and in the Significance Determination Process.

4. The data is analyzed to make evidence-based decisions regarding the radiation exposure to transient individuals.

5. The data are used to establish priorities for the use of NRC health physics resources:

research, standards development, regulatory program development, and inspections conducted at NRC-licensed facilities.

6. The data are interpreted to provide insights that are evidence-based and will assist in answering Congressional and administrative inquiries as well as responding to questions raised by the public.

7. The data are used to determine radiation exposure histories to individuals who were exposed to radiation at NRC-licensed facilities.

8. The data can be used to conduct epidemiologic studies.

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TABLE OF CONTENTS ABSTRACT ..............................................................................................................................iii FOREWORD .............................................................................................................................v PREFACE................................................................................................................................vii TABLE OF CONTENTS ..........................................................................................................ix LIST OF FIGURES ..................................................................................................................xi LIST OF TABLES ..................................................................................................................xiii ABBREVIATIONS AND ACRONYMS ................................................................................. xv 1 INTRODUCTION .............................................................................................................. 1-1 1.1 Background ...........................................................................................................................1-1 1.2 Radiation Exposure Information on the Internet ..................................................................1-2 1.3 Evidence and Evaluation ......................................................................................................1-3 1.3.1 Annual Evaluation Plan ............................................................................................1-3 2 LIMITATIONS OF THE DATA ......................................................................................... 2-1 2.1 Limitations .............................................................................................................................2-1 2.2 Statistical Comparisons ........................................................................................................2-2 3 ANNUAL PERSONNEL MONITORING REPORTS - 10 CFR 20.2206...................... 3-1 3.1 Definition of Terms and Methodologies................................................................................3-1 3.1.1 Number of Licensees Reporting ..............................................................................3-1 3.1.2 Number of Monitored Individuals .............................................................................3-1 3.1.3 Number of Individuals with Measurable Dose ......................................................... 3-1 3.1.4 Collective Dose.........................................................................................................3-3 3.1.5 Average Individual Dose ..........................................................................................3-3 3.1.6 Average Measurable Dose ......................................................................................3-3 3.2 Annual TEDE Dose Distributions .........................................................................................3-3 3.3 Summary of Occupational Dose Data by Licensee Category ............................................. 3-5 3.3.1 Industrial Radiography Licensees - Fixed Location and Temporary Job Sites....... 3-5 3.3.2 Manufacturing and Distribution Licensees - Broad-Type A, Broad-Type B, Other, and Nuclear Pharmacies...............................................................................3-6 3.3.3 Low-Level Waste Disposal Licensees .....................................................................3-8 3.3.4 Independent Spent Fuel Storage Installation Licensees ......................................... 3-8 3.3.5 Fuel Cycle Licensees ...............................................................................................3-9 3.3.6 Light-Water Reactor Licensees..............................................................................3-11 3.3.7 Other Facilities Reporting to the NRC....................................................................3-11 3.4 Summary of Intake and Internal Dose Data by Licensee Category ..................................3-12 4 COMMERCIAL Power REACTORS ............................................................................... 4-1 4.1 Introduction ...........................................................................................................................4-1 ix

4.2 Definition of Terms and Sources of Data .............................................................................4-1 4.2.1 Number of Reactors .................................................................................................4-1 4.2.2 Electric Energy Generated .......................................................................................4-1 4.2.3 Collective Dose per Megawatt-Year ........................................................................4-2 4.2.4 Average Maximum Dependable Capacity ...............................................................4-2 4.2.5 Percent of Maximum Dependable Capacity Achieved ............................................ 4-2 4.3 Annual TEDE Distributions ...................................................................................................4-6 4.4 Average Annual TEDE Doses ..............................................................................................4-9 4.5 Three-Year Average Collective TEDE per Reactor ...........................................................4-15 4.6 International Occupational Radiation Exposure .................................................................4-20 4.7 Decontamination and Decommissioning of Commercial Nuclear Power Reactors ..........4-22 5 TRANSIENT INDIVIDUALS AT NRC-LICENSED FACILITIES .................................... 5-1 6 EXPOSURES TO PERSONNEL IN EXCESS OF REGULATORY LIMITS ................ 6-1 6.1 Reporting Categories ............................................................................................................6-1 6.2 Summary of Occupational Radiation Doses in Excess of NRC Regulatory Limits ............. 6-2 6.3 Summary of Annual Dose Distributions for Certain NRC Licensees................................... 6-2 6.4 Maximum Occupational Radiation Doses Below NRC Regulatory Limits........................... 6-2 7 RADIATION PROTECTION EVALUATION DISCUSSION ........................................... 7-1 7.1 Individual Licensee Category Results ..................................................................................7-1 7.1.1 Industrial Radiography Licensees ............................................................................7-1 7.1.2 Manufacturing and Distribution Licensees ...............................................................7-1 7.1.3 Independent Spent Fuel Storage Installation Licensees ......................................... 7-2 7.1.4 Fuel Cycle Licensees ...............................................................................................7-2 7.1.5 Commercial Power Reactor Licensees ...................................................................7-2 7.2 Collective Results .................................................................................................................7-3 7.3 Conclusions ..........................................................................................................................7-4 8 REFERENCES ................................................................................................................. 8-1 APPENDIX A ANNUAL TEDE FOR NONREACTOR NRC LICENSEES AND OTHER FACILITIES REPORTING TO THE NRC, 2019 ............................................... A-1 APPENDIX B ANNUAL DOSES AT LICENSED NUCLEAR POWER FACILITIES, 2019 .... B-1 APPENDIX C PERSONNEL, DOSE, AND POWER GENERATION

SUMMARY

1969-2019 ........................................................................................................C-1 APPENDIX D DOSE PERFORMANCE TRENDS BY REACTOR SITE, 1973-2019 ............. D-1 APPENDIX E PLANTS NO LONGER IN OPERATION, 2019 ................................................ E-1 APPENDIX F GLOSSARY, 2019 ............................................................................................ F-1 x

LIST OF FIGURES Figure 3.1 Individuals with Measurable TEDE, Collective TEDE, and Average Measurable TEDE for Industrial Radiography Licensees 1994-2019 .................. 3-6 Figure 3.2 Individuals with Measurable TEDE, Collective TEDE, and Average Measurable TEDE for Manufacturing and Distribution Licensees 1994-2019 ..... 3-7 Figure 3.3 Individuals with Measurable TEDE, Collective TEDE, and Average Measurable TEDE for Independent Spent Fuel Storage Installation Licensees 1994-2019 ... 3-9 Figure 3.4 Annual Exposure Information for Fuel Cycle Licensees 1994-2019 .................. 3-10 Figure 4.1 Average Collective Dose per Reactor and Average Number of Individuals with Measurable Dose per Reactor 1994-2019 ................................................. 4-10 Figure 4.2 Number of Operating Reactors and Electricity Generated 1994-2019 .............. 4-11 Figure 4.3 Average Measurable Dose per Individual and Collective Dose per Megawatt-Year 1994-2019 ................................................................................ 4-12 Figure 4.4a Average, Median, and Extreme Values of the Collective Dose per BWR Reactor 1994-2019 ............................................................................................ 4-13 Figure 4.4b Average, Median, and Extreme Values of the Collective Dose per PWR Reactor 1994-2019 ............................................................................................ 4-14 Figure 4.5 Average Collective Dose per PWR Reactor 1995-2019 .................................... 4-21 Figure 4.6 Average Collective Dose per BWR Reactor 1995-2019 .................................... 4-21 Figure 4.7 D&D Process Flowchart ..................................................................................... 4-24 xi

LIST OF TABLES Table 3.1 Average Annual Exposure Data for Certain Categories of NRC Licensees 2009-2019 ........................................................................................................... 3-2 Table 3.2 Distribution of Annual Collective TEDE by License Category 2019 ..................... 3-4 Table 3.3 Annual Exposure Information for Industrial Radiography Licensees 2017-2019 ........................................................................................................... 3-5 Table 3.4 Annual Exposure Information for Manufacturing and Distribution Licensees 2017-2019 ........................................................................................................... 3-7 Table 3.5 Annual Exposure Information for Fuel Cycle Licensees 2017-2019 .................. 3-11 Table 3.6 Intake by Licensee Category and Radionuclide Mode of IntakeIngestion and Other 2019................................................................................................... 3-12 Table 3.7 Intake by Licensee Category and Radionuclide Mode of IntakeInhalation 2019 ................................................................................................................... 3-13 Table 3.8 Collective and Average CEDE by Licensee Category 2019 ............................... 3-15 Table 3.9 Internal dose (CEDE) distribution 1994-2019 .................................................... 3-16 Table 4.1 Summary of Information Reported by Commercial Boiling-Water Reactors 1994-2019 ........................................................................................................... 4-3 Table 4.2 Summary of Information Reported by Commercial Pressurized-Water Reactors 1994-2019 ............................................................................................ 4-4 Table 4.3 Summary of Information Reported by Commercial Light-Water Reactors 1994-2019 ........................................................................................................... 4-5 Table 4.4a Summary of Distribution of Annual Doses at Commercial Light-Water Reactors 1994-2019 ............................................................................................ 4-7 Table 4.4b Summary of Distribution of Annual Doses at Commercial Light-Water Reactors, Adjusted for Transients 1994-2019 .................................................... 4-8 Table 4.5 Three-Year Totals and Averages Listed in Ascending Order of Collective TEDE per BWR 2017-2019 ............................................................................... 4-16 Table 4.6 Three-Year Totals and Averages Listed in Ascending Order of Collective TEDE per PWR 2017-2019 ............................................................................... 4-17 Table 4.7 Three-Year Collective TEDE per Reactor-Year for BWRs 2017-2019 .............. 4-18 Table 4.8 Three-Year Collective TEDE per Reactor-Year for PWRs 2017-2019 .............. 4-19 Table 4.9 Plants No Longer in Operation 2019 .................................................................. 4-26 Table 5.1 Effects of transient individuals on annual statistical compilations 2019 ................ 5-3 Table 6.1 Summary of Annual Dose Distributions for Certain NRC Licensees 2009-2019 ........................................................................................................... 6-3 Table 6.2 Maximum Occupational Doses for Each Exposure Category 2019 ..................... 6-3 xiii

ABBREVIATIONS AND ACRONYMS AEC U.S. Atomic Energy Commission ALARA as low as is reasonably achievable BWR boiling-water reactor CDE committed dose equivalent CEDE committed effective dose equivalent CFR Code of Federal Regulations D&D decontamination and decommissioning DDE deep dose equivalent DOE U.S. Department of Energy ERDA Energy Research and Development Administration EVESR ESADA Vallecitos Experimental Superheat Reactor FBR fast breeder reactor FSSR final status survey report IAEA International Atomic Energy Agency ICRP International Commission on Radiological Protection ISFSI independent spent fuel storage installation ISOE Information System on Occupational Exposure ISOEDAT Information System on Occupational Exposure Database LDE lens dose equivalent LTP license termination plan LWR light-water reactor M&D manufacturing and distribution mSv millisievert MW megawatts MWe megawatts electric MWt megawatts thermal MW-hr megawatt-hour MW-yr megawatt-year NEA Nuclear Energy Agency NMSS Office of Nuclear Material Safety and Safeguards NRC U.S. Nuclear Regulatory Commission NS Nuclear Ship OECD Organisation for Economic Co-operation and Development PSDAR post-shutdown decommissioning activities report PWR pressurized-water reactor REIRS Radiation Exposure Information and Reporting System xv

SDE-ME shallow dose equivalent maximally exposed extremity SDE-WB shallow dose equivalent whole body SI international system of units SG steam generator Sv sieverts TBD to be determined TEDE total effective dose equivalent TMI Three Mile Island TODE total organ dose equivalent UF6 uranium hexafluoride VBWR Vallecitos Boiling-Water Reactor xvi

1 INTRODUCTION

1.1 Background

One of the basic purposes of the Atomic Energy Act and the implementing regulations in Title 10 of the Code of Federal Regulations (10 CFR) Part 20, Standards for Protection Against Radiation, is to protect the health and safety of the public, including the employees of the licensees conducting operations under those regulations.

On November 4, 1968, the U.S. Atomic Energy Commission (AEC) published an amendment to 10 CFR Part 20 requiring the reporting of a statistical summary of occupational radiation exposure information (but not individual exposure records) to a central repository at AEC Headquarters. At that time, there were only four categories 1 of AEC licensees required to report. These facilities were considered to have the greatest potential for significant occupational doses. Licensees were required to report the total number of individuals who were monitored per dose range (§20.407) and provide cumulative radiation exposure reports for individuals no longer employed (§20.408).

Occupational exposure data were extracted from these reports and entered into the AEC Radiation Exposure Information and Reporting System (REIRS), a computer system that was maintained at the Oak Ridge National Laboratory Computer Technology Center in Oak Ridge, TN, 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 Education, which is managed by Oak Ridge Associated Universities. The computerization of these data facilitates their collection and analysis.

The data maintained in REIRS have been summarized and published in a report every year since 1969. Annual reports for each of the years 1969 through 1973 presented the data reported by both AEC licensees and contractors and were published in six documents designated as WASH-1350-R1 through WASH-1350-R6.

In January 1975, with the separation of 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 U.S. Department of Energy (DOE) is collected and published by the DOE Office of ES&H Reporting and Analysis within the Office of Environment, Health, Safety and Security in Germantown, MD.

In 1982 and 1983, 10 CFR 20.408(a) was amended to require three additional categories of NRC licensees to submit annual statistical exposure reports and individual termination exposure reports. The three additional NRC licensee categories were: (1) geologic repositories for high-level radioactive waste, (2) independent spent fuel storage installations (ISFSIs), 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 one of these additional categories 1 Commercial nuclear power reactors; industrial radiographers; fuel processors (including uranium enrichment facilities as of 1997), fabricators, and reprocessors; and manufacturing and distribution of specified quantities of byproduct material.

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(i.e., ISFSIs), since there are no geologic repositories for high-level waste currently licensed and there are no low-level waste land disposal facilities currently in operation that report to the NRC.

In May 1991, 10 CFR Part 20 was revised to redefine the radiation monitoring and reporting requirements of NRC licensees. Instead of submitting annual reports summarizing the total number of individuals who were monitored (§20.407) and termination reports (§20.408), licensees were required to submit an annual report of the dose received by each monitored individual

(§20.2206). Licensees were required to implement the new requirements no later than January 1994. The regulations in 10 CFR 20.1502 specify conditions that require individual monitoring of external and internal occupational dose. Each licensee is also required, under 10 CFR 20.2106, to maintain records of the results of such monitoring until the Commission terminates the license.

This report summarizes information reported for the current year and previous 10 years. More licensee-specific data for the previous 10 years, such as the annual reports submitted by each commercial nuclear power reactor pursuant to 10 CFR 20.407 and 20.2206 (after 1993) and their technical specifications (before Volume 20 of this report), may be found in the documents listed on the inside of the front cover of this report for the specific year desired. Additional operating data and statistics for each commercial nuclear power reactor for the years 1973 through 1982 may be found in a series of reports, Nuclear Power Plant Operating Experience [Refs. 2-10]. These documents are available for viewing at all NRC public document rooms, as well as on the NRC public Web site (https://www.nrc.gov), or they may be purchased from the National Technical Information Service, as shown in the References section.

1.2 Radiation Exposure Information on the Internet In May 1995, the NRC began disseminating radiation exposure information at a Web site on the Internet. This site allows interested parties to access the data electronically rather than through the published NUREG-0713 document. A Web site was created for radiation exposure and linked to the main NRC Web page. The Web site contains up-to-date information on radiation exposure, as well as information and guidance on reporting radiation exposure information to the NRC.

Interested parties may read the documents on line or download information for further analysis.

REIRView, a software package designed to validate a licensees annual data submittal, is available for downloading on the Web site. There are also links to other Web sites dealing with the topics of radiation and health physics. Individuals may submit requests for their dose records contained in REIRS on this Web site. In addition, organizations that have provided documentation to the NRC may submit requests for dose records contained in REIRS on this Web site.

The NRC intends to continue disseminating radiation exposure information on the Web and will focus more resources on the electronic distribution of information rather than on the publication of hard-copy reports.

The main Web address for the NRC is https://www.nrc.gov 1-2

The NRC radiation exposure information Web URL is https://www.reirs.com Comments on this report or on the NRCs radiation exposure Web page should be directed to Minh-Thuy Nguyen REIRS Project Manager Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555 Phone: 301-415-5163 E-mail Address: Minh-Thuy.Nguyen@nrc.gov 1.3 Evidence and Evaluation 1.3.1 Annual Evaluation Plan In the Fiscal Year 2022 Annual Evaluation Plan [Ref. 11] the NRC developed its Annual Evaluation Plan which included an evaluation of the Radiation Protection Program. Evaluations included in the annual evaluation plan, such as this evaluation of the Radiation Protection Program, are considered to be of significance to the agency. The purpose of the Outcome Evaluation of the Radiation Protection Program is to measure the effectiveness NRCs Radiation Protection Program as it pertains to NRCs as low as is reasonably achievable (ALARA) regulations of 10 CFR 20.1101(b) along 1 with the licensees implementation of this regulation for each of the NRC-licensee categories.

By analyzing the data pertaining to number of licensees reporting exposure, the number of individuals monitored, the collective dose, and exposure trends (i.e., average individual and measurable doses) across the five categories of licensees, 2 relative strengths or areas for improvement may be identified. The analyses and assessments will be used for this evaluation to identify potential improvements to NRC's regulatory programs (i.e., licensing, inspection and rule-making).

The NRC conducted evidence-building and evaluation activities to fulfill this projects objective by answering questions such as the following:

• How can the agency use radiation exposure data from NRC-licensed facilities to assess whether the NRCs radiation protection regulatory programs are achieving their intended outcomes?

2 The five categories include: commercial nuclear power reactors and test reactor facilities; industrial radiographers; fuel processors (including uranium enrichment facilities), fabricators, and reprocessors; manufacturing and distribution of byproduct material; independent spent fuel storage installations; facilities for land disposal of low-level waste; and geologic repositories for high-level waste. There are currently no NRC licensees involved in low-level waste disposal or geologic repositories for high-level waste.

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• What do the trends in radiation exposure data at NRC licensed facilities suggest about the radiation protection programs effectiveness over time?

• Does the data suggest differences in the effectiveness across the agencys radiation protection programs?

• Will increased data use provide insights into potential performance measures or process improvements relating to risk-informed regulation?

In order to complete the objective of this evaluation plan, the NRC performed an Outcome Evaluation to measure the effectiveness of the Agencys regulatory programs with respect to radiation protection. The Outcome Evaluation helps answer the question of the effectiveness of the Radiation Protection Program for the various NRC-licensee categories.

Section 2 of this report provides a discussion of the radiation exposure data including limitations and statistical comparisons of the data. The inferences and statements used to support the evaluation findings are based upon the data as reported by licensees, which does not include uncertainty values associated with the dosimetric calculations. All statistical inferences are made at the population level, i.e., aggregated doses for a licensee or group of licensees. Sections 3 and 4 of this report provides summaries of the data and trends for each of the licensee five categories.

Finally, Section 7 of this report provides a discussion of the radiation protection program evaluation and the effectiveness of the NRC regulatory programs to appropriately limit the occupational dose to nuclear workers.

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2 LIMITATIONS OF THE DATA 2.1 Limitations All of the figures compiled in this report relating to exposures and occupational doses are based on the results and interpretations of the readings of various types of personnel-monitoring devices employed by each licensee. This data, obtained from routine personnel-monitoring programs, assists in characterizing the radiation exposure incident to individuals work and is used in evaluating the radiation protection program.

Monitoring requirements are specified in 10 CFR 20.1502, which requires licensees to monitor individuals at levels sufficient to demonstrate compliance with occupational dose limits. As a minimum, monitoring must be provided for adults likely to receive, in 1 year from sources external to the body, a dose in excess of 10 percent of the applicable limits in 10 CFR 20.1201(a) and all individuals entering a high or very high radiation area. Separate dose limits have been established for minors, declared pregnant women, and members of the public. Depending on the administrative policy of each licensee, persons such as visitors and administrative individuals may also be provided with monitoring devices, even though the probability of their exposure to measurable levels of radiation is extremely small.

Pursuant to 10 CFR 20.2206(b), certain categories of licensees must submit an annual report of the results of individual monitoring carried out by the licensee for each individual for whom monitoring was required by 10 CFR 20.1502. In addition to this requirement, many licensees elect to report the doses for every individual for whom they provided monitoring. This practice increases the number of individuals that are monitored for radiation exposure. In an effort to account for this increase, the number of individuals reported as having no measurable dose 1 is subtracted from the total number of monitored individuals. This resulting number can then be used to calculate the average measurable dose per individual with a measurable dose, as well as the average dose per monitored individual (i.e., with or without a measurable dose).

This report can be obtained from the Web site, www.reirs.com. This report does not include compilations of non-occupational exposures, such as exposures received by medical patients from X-rays, fluoroscopy, or accelerators.

This report contains information reported by NRC licensees. Since NRC licenses all commercial nuclear power reactors, fuel processors and fabricators, and ISFSIs, information shown for these categories reflect all relevant activity in the United States. This is not the case, however, for the remaining categories of industrial radiography, manufacturing and distribution (M&D) of specified quantities of byproduct material, and low-level waste disposal. Many companies that conduct these types of activities are located in Agreement States. More than six times as many facilities are licensed and regulated by Agreement States than are licensed and regulated by the NRC.

Agreement States are not required to adopt the reporting requirements in 10 CFR 20.2206. As a result, Agreement State licensees are not required to submit occupational dose reports to the NRC.

Although some Agreement State licensees voluntarily submit occupational dose reports to the NRC, these results are not included in the analyses presented in Sections 3, 5, and 6 of this report. NUREG-2118, Occupational Radiation Exposure at Agreement State-Licensed Materials 1 The number of individuals with measurable dose includes any individual with a total effective dose equivalent (TEDE) greater than zero rem. Individuals reported with zero dose, or no detectable dose, are included in the number of individuals with no measurable exposure.

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Facilities, 1997-2010, provides information regarding occupational radiation exposures at Agreement State-licensed facilities [Ref. 12].

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 facilities. Section 5 contains an analysis that adjusts the data for transient individuals being counted more than once.

When examining the annual statistical data, it is important to note 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 commercial nuclear power reactors, may monitor numerous individuals for periods of much less than a year.

Considerable attention should be given when referencing the collective totals presented in this report. The differences between the totals presented for all licensees that reported versus only those licensees that are required to report should be noted. See Section 1.1 for the categories of licensees that are required to report to REIRS. A number of licensees are not required to report to REIRS, but voluntarily report for convenient recordkeeping or because they have reported in the past and have decided to continue this practice. These licensees are listed in Appendix A, Table A2 - Other Facilities Reporting to the NRC, 2019.

Although uncommon, the data contained in this report are subject to change because licensees may submit corrections or additions to data for previous years.

All dose equivalent values in this report are given in units of rem in accordance with the general provisions for records in 10 CFR 20.2101(a).

1 rem = 0.01 sievert (Sv) 1 rem = 10 millisievert (mSv) 1 Curie (Ci) = 3.7 X 1010 Becquerel (Bq) 2.2 Statistical Comparisons For statistical comparisons of averages, a two-sided one-sample t test with a 0.05 significance level (i.e., 95 percent confidence) is used to determine whether the difference between the two averages is significantly different. For values that are not averages, such as total collective dose, a 5-year average from the previous 5 years (not including the current year under consideration) is calculated with 95 percent confidence interval based on the normal distribution. If the value for the current year falls within the 5-year 95 percent confidence interval, then it is not significantly different; whereas, if the value falls outside (i.e., below the lower limit or above the upper limit),

there is an indication of a statistical significant change.

Two-sided one-sample t test formula:

=

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Where:

t = calculated t statistic

= sample mean

µ = population mean S = sample standard deviation n = sample number Example:

We wish to determine if the average measurable dose for a type of nuclear reactor differs from the previous 5 years. The 5-year mean for the average measurable dose is 0.080. The population mean is the current years average measurable dose, 0.060. The sample standard deviation is 0.01, and the sample number is 5. Using the formula, 0.0800.060

= 0.01 = 4.472 2.236 The two-tailed probability value (as obtained from a Students t distribution table) given a t-value of 4.472 is 0.006 which is statistically significant at a 0.05 significance level.

It should be noted that an analysis of the uncertainties associated with dosimetry and dose measurement is not included in this report as the information required for such an analysis is not required to be reported to the NRC. The inferences and statements represented in the report are based upon the data as reported by the licensees, which does not include uncertainty values associated with the dosimetric calculations. All statistical inferences are made at the population level, e.g., aggregated doses for a licensee or group of licensees.

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3 ANNUAL PERSONNEL MONITORING REPORTS - 10 CFR 20.2206 3.1 Definition of Terms and Methodologies 3.1.1 Number of Licensees Reporting The number of licensees in each category is provided in Table 3.1 for each of the seven 1 categories that are required to report pursuant to 10 CFR 20.2206. The first column denotes the NRC license category and the program code. The program code is a five-digit number assigned by NRC to each licensee to designate the major activity or principal use authorized in the license.

A full description and definition is referenced in Consolidated Guidance about Materials Licenses, NUREG-1556, Volume 20, Appendix G [Ref. 13]. The third column in Table 3.1 shows the number of licensees that have filed such reports during the past 11 years. All commercial nuclear power reactors, fuel processors and fabricators, and ISFSIs are required to report occupational exposures to the NRC, whether or not they are in an Agreement State.

Many companies that conduct industrial radiography and M&D activities are located in and regulated by Agreement States and are, therefore, not required to adopt the reporting requirements of 10 CFR 20.2206. However, industrial radiography and M&D licensees that are licensed and regulated by the NRC are required to report occupational exposure to the NRC.

Appendix A, Table A1 lists all nonreactor licensees that reported occupational data to the NRC in 2019.

3.1.2 Number of Monitored Individuals The number of monitored individuals refers to the total number of individuals that NRC licensees reported as being monitored for exposure to external or internal radiation during the year. This number includes both individuals for whom monitoring is required, as well as individuals for whom monitoring was voluntarily provided and reported (e.g., workers receiving a minimal dose below the monitoring threshold, visitors, service representatives, contract individuals, and administrative individuals).

The total number of individuals 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. 14].

3.1.3 Number of Individuals with Measurable Dose The number of individuals with a measurable dose includes any individual with a total effective dose equivalent (TEDE) that is reported as a positive value.

1 These categories are commercial nuclear power reactors and test reactor facilities; industrial radiographers; fuel processors (including uranium enrichment facilities), fabricators, and reprocessors; manufacturing and distribution of byproduct material; ISFSIs; facilities for land disposal of low-level waste; and geologic repositories for high-level waste. There are currently no NRC licensees involved in low-level waste disposal or geologic repositories for high-level waste.

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Table 3.1 Average Annual Exposure Data for Certain Categories of NRC Licensees 2009-2019 NRC License Number of Number of Number of Collective Average Measurable Category* and Calendar Licensees Monitored Individuals with TEDE Average TEDE per Individual Program Code Year Reporting Individuals Measurable TEDE (person-rem) TEDE (rem) (rem)

Industrial 2009 65 2,662 2,307 1,317.982 0.50 0.57 Radiography 2010 57 2,377 2,034 1,297.300 0.55 0.64 2011 64 2,545 2,210 1,608.821 0.63 0.73 03310 2012 67 2,670 2,275 1,508.792 0.57 0.66 03320 2013 60 2,925 2,506 1,547.351 0.53 0.62 2014 57 3,288 2,862 1,778.171 0.54 0.62 2015 69 3,426 2,908 1,695.040 0.49 0.58 2016 64 3,035 2,635 1,270.459 0.42 0.48 2017 62 3,389 2,912 1,709.858 0.50 0.59 2018 61 3,876 3,303 1,967.879 0.51 0.60 2019 60 3,732 3,152 1,668.408 0.45 0.53 Manufacturing 2009 17 1,939 1,388 179.539 0.09 0.13 and 2010 18 976 672 146.667 0.15 0.22 Distribution 2011 16 903 702 112.023 0.12 0.16 2012 22 1,057 713 118.709 0.11 0.17 02500 2013 20 994 627 114.550 0.12 0.18 03211 2014 19 962 656 138.631 0.14 0.21 03212 2015 21 949 634 155.688 0.16 0.25 03214 2016 21 905 606 142.958 0.16 0.24 2017 21 940 615 139.071 0.15 0.23 2018 14 1,086 718 136.505 0.13 0.19 2019 16 1,188 804 147.927 0.12 0.18 Independent 2009 2 72 34 1.465 0.02 0.04 Spent Fuel 2010 2 73 39 1.337 0.02 0.03 Storage 2011 2 54 25 1.449 0.03 0.06 2012 2 42 15 1.099 0.03 0.07 23100 2013 2 53 18 1.533 0.03 0.09 23200 2014 2 51 22 3.192 0.06 0.15 2015 2 57 20 1.102 0.02 0.06 2016 2 57 22 0.579 0.01 0.03 2017 2 67 20 0.631 0.01 0.03 2018 2 70 17 1.740 0.02 0.10 2019 2 79 28 1.939 0.02 0.07 Fuel Cycle Licenses - 2009 11 8,918 3,738 533.721 0.06 0.14 Fabrication, 2010 11 9,362 4,212 541.876 0.06 0.13 Processing, and 2011 11 9,535 4,361 607.202 0.06 0.14 Uranium Enrichment, 2012 9 7,388 3,541 438.729 0.06 0.12 and Uranium 2013 8 7,476 3,942 357.067 0.05 0.09 Hexafluoride (UF6) 2014 9 6,689 3,685 366.224 0.05 0.10 Production 2015 7 5,296 3,033 327.112 0.06 0.11 Plants 2016 7 5,413 2,999 277.687 0.05 0.09 11400 2017 7 5,058 2,930 254.997 0.05 0.09 21200 2018 7 4,737 2,783 229.530 0.05 0.08 21210 2019 7 4,347 2,690 250.522 0.06 0.09 Commercial 2009 104 176,381 81,754 10,024.804 0.06 0.12 Light-Water Reactors 2010 104 179,648 75,010 8,631.384 0.05 0.12 (LWRs) ** 2011 104 191,538 81,321 8,771.326 0.05 0.11 2012 104 193,977 79,549 8,035.393 0.04 0.10 41111 2013 100 174,614 67,236 6,759.547 0.04 0.10 2014 100 174,853 70,847 7,124.519 0.04 0.10 2015 99 176,886 70,798 7,019.088 0.04 0.10 2016 99 155,574 59,353 5,365.709 0.03 0.09 2017 99 157,072 64,761 6,416.548 0.04 0.10 2018 98 150,219 61,014 5,829.471 0.04 0.10 2019 96 134,897 53,615 5,080.795 0.04 0.09 Grand Totals and 2009 199 189,972 89,221 12,057.511 0.06 0.14 Averages 2010 192 192,436 81,967 10,618.564 0.06 0.13 2011 197 204,575 88,619 11,100.821 0.05 0.13 2012 204 205,134 86,093 10,102.722 0.05 0.12 2013 190 186,062 74,329 8,780.048 0.05 0.12 2014 187 185,843 78,072 9,410.737 0.05 0.12 2015 198 186,614 77,393 9,198.030 0.05 0.12 2016 193 164,984 65,615 7,057.392 0.04 0.11 2017 190 159,355 67,341 7,909.670 0.05 0.12 2018 182 159,988 67,835 8,165.125 0.05 0.12 2019 181 144,243 60,289 7,149.591 0.05 0.12 NOTE: The data shown in this table for all categories of licensees have not been adjusted to account for transient workers (see Section 5).

• These categories consist only of NRC licensees required to submit an annual report (see Section 2).

• • This category includes all LWRs in commercial operation for a full year for each of the years indicated.

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3.1.4 Collective Dose The concept of collective dose is used in this report to denote the summation of the TEDE received by all monitored individuals within a category and is reported in units of person-rem.

Since 10 CFR 20.2206 requires that the TEDE be reported, the collective dose is calculated by summing the TEDE for all monitored individuals in each category.

The phrase collective dose is used throughout this report to mean the collective TEDE, unless otherwise specified.

Before the implementation of the revised dose-reporting requirements of 10 CFR 20.2206 in 1994, the collective dose, in some cases, was calculated from the dose distributions by multiplying the number of individuals reported in each of the dose ranges by the midpoint of the corresponding dose range and then summing the products. This assumed that the midpoint of the range was equal to the arithmetic mean of the individual doses in the range. Experience has shown that the actual mean dose of individuals reported in each dose range is less than the midpoint of the range. For this reason, the resultant calculated collective doses shown in this report for these licensees may be approximately 10 percent higher than the sum of the actual individual doses.

Care should be taken when comparing the actual collective dose calculated for 1994 to 2019 with the collective dose for years before 1994 because of this change in methodology.

In addition, before 1994, doses only included the external whole-body dose with no internal dose contribution. 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 before 1994. One noted exception is for fuel fabrication licensees, where the committed effective dose equivalent (CEDE), in some cases, contributes the majority of the TEDE (see Section 3.3.5).

3.1.5 Average Individual Dose The average individual dose is obtained by dividing the collective dose by the total number of monitored individuals. This figure is usually less than the average measurable dose, because it includes the number of those individuals who received zero or less than measurable doses.

3.1.6 Average Measurable Dose The average measurable dose is obtained by dividing the collective TEDE by the number of individuals with a measurable dose. This is the average most commonly used in this and other reports when examining trends and comparing doses received by individuals in various segments of the nuclear industry.

3.2 Annual TEDE Dose Distributions Table 3.2 provides a statistical compilation of the occupational dose reports by 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 several licensee categories, a large number of individuals received doses that were less than measurable. Eighty-nine percent of the reported individuals with measurable doses (shown in Table 3.2) were monitored by commercial nuclear power reactors in 2019, where they received 71 percent of the total collective dose.

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Table 3.2 Distribution of Annual Collective TEDE by License Category 2019 Number of Individuals with TEDE in the Ranges (rem)

• License Category Total Number Total Collective (Number of sites No. Meas. 0.025- 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number with Meas. Dose (TEDE) reporting) Meas. <0.025 0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose (person-rem)

INDUSTRIAL RADIOGRAPHY Fixed Locations (2) 4 2 2 - 1 - - - - - 1 - - 10 6 4.695 Temporary Job Sites 576 355 462 535 614 396 243 442 77 20 2 - - 3,722 1,663.713 (58) 3,146 Total (60) 580 340 463 519 615 396 243 442 77 20 3 0 0 3,732 1,668.408 3,152 MANUFACTURING AND DISTRIBUTION Type "A" Broad (2) 124 81 60 39 47 18 16 30 2 - - - - 417 102.107 293 Type "B" Broad and Other (0) - -

Nuclear Pharmacies 260 229 178 70 22 6 1 1 3 1 - - - 771 45.820 (14) 511 3-4 Total (16) 384 261 211 112 69 24 17 31 5 1 0 0 0 1,188 147.927 804 INDEPENDENT SPENT FUEL STORAGE Total (2) 51 17 4 5 2 0 0 0 0 0 0 0 0 79 28 1.939 FUEL CYCLE**

Total (7) 1,241 654 473 249 67 4 2 0 0 0 0 0 4,347 250.522 1,657 2,690 COMMERCIAL POWER REACTORS***

Boiling Water (32) 26,370 9,271 10,314 5,643 2,666 803 262 140 1 - - - - 55,470 29,100 3,372.909 Pressurized Water (64) 54,912 9,045 10,438 3,869 970 139 38 16 - - - - - 79,427 24,515 1,707.886 Total (96) 81,282 18,316 20,752 9,512 3,636 942 300 156 1 0 0 0 0 134,897 53,615 5,080.795 GRAND TOTALS 83,954 20,175 22,084 10,621 4,571 1,429 564 631 83 21 3 0 0 144,243 60,289 7,149.591 NOTE: The data shown in this table for all categories of licensees have not been adjusted to account for transient workers (see Section 5).

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

• • This category includes fabrication, processing, and uranium enrichment plants (see Section 3.3.5).

• • • This category includes all reactors in commercial operation for a full year during 2019.

3.3 Summary of Occupational Dose Data by Licensee Category 3.3.1 Industrial Radiography Licensees - Fixed Location and Temporary Job Sites Industrial radiography licenses are issued to allow the use of sealed radioactive materials, usually in exposure devices or cameras that primarily emit gamma rays for nondestructive testing of pipeline weld joints, steel structures, boilers, aircraft and ship parts, and other high-stress alloy parts. Some firms are licensed to conduct such activities in one location, usually in a permanent facility designed and shielded for radiography; others perform radiography at temporary job sites in the field. The radioisotopes most commonly used are cobalt-60 and iridium-192. As shown in Table 3.1, annual reports were received for 60 radiography licensees in 2019. Table 3.3 summarizes the reported data for the two types of industrial radiography licensees for 2017, 2018, and 2019 for comparison purposes.

Table 3.3 Annual Exposure Information for Industrial Radiography Licensees 2017-2019 Number of Collective Average Number of Monitored Individuals with Dose Measurable Year Type of License Licensees Individuals Measurable Dose (person-rem) Dose (rem)

Fixed Location 2 12 7 0.325 0.05 2017 Temporary Job Sites 60 3,377 2,905 1,709.533 0.59 Total 62 3,389 2,912 1,709.858 0.59 Fixed Location 2 11 6 0.944 0.16 2018 Temporary Job Sites 59 3,865 3,297 1,966.935 0.60 Total 61 3,876 3,303 1,967.879 0.60 Fixed Location 2 10 6 4.695 0.78 2019 Temporary Job Sites 58 3,722 3,146 1,663.713 0.53 Total 60 3,732 3,152 1,668.408 0.53 The average measurable dose for individuals performing radiography at fixed locations historically over the last 5 years is about 10 percent of the average at temporary job sites. In 2019, one individual (of the 6 individuals with measurable dose) received a total effective dose of 4.255 rem.

The resulting collective dose for fixed location radiography increased to 4.695 person-rem for 2019 with an average measurable dose of 0.78 rem. This is the first time the fixed location average measurable dose was above the value for temporary job site radiographers.

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 reducing exposure. A relatively small number of exposed individuals involved in radiographer licensee activities usually receive average measurable doses that are higher than those received by other license categories.

Figure 3.1 shows the number of individuals with a measurable dose, the total collective dose, and the average measurable dose per individual for both types of industrial radiography licensees from 1994 through 2019. From 2018 to 2019, there was a 5 percent decrease in the number of individuals with measurable TEDE and a 15 percent decrease in the collective TEDE. Compared to the 5-year average of 2,924, the number of individuals with measurable TEDE was not statistically higher in 2019. Compared to the 5-year average of 1,684 person-rem (16,840 person-mSv), the collective TEDE was not statistically higher in 2019. The average 3-5

measurable TEDE decreased to 0.53 rem (5.3 mSv) for 2019, but was not statistically different than the 5-year average of 0.57 rem (5.7 mSv).

Figure 3.1 Individuals with Measurable TEDE, Collective TEDE, and Average Measurable TEDE for Industrial Radiography Licensees 1994-2019 3.3.2 Manufacturing and Distribution Licensees - Broad-Type A, Broad-Type B, Other, and Nuclear Pharmacies M&D 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 organizations or companies specifically licensed by the NRC. Broad-Type A licenses are issued to larger organizations that may use many different radionuclides in many different ways and that have a comprehensive radiation protection program. Some Broad-Type A firms are medical suppliers that process, package, or distribute such products as diagnostic test kits, radioactive surgical implants, and tagged radiochemicals for use in medical research, diagnosis, and therapy. Broad-Type B licenses involve the processing, encapsulation, packaging, and distribution of the radionuclides that have been purchased in bulk quantities from production reactors and cyclotrons. Major products include gamma radiography sources, cobalt irradiation sources, well-logging sources, sealed sources for gauges and smoke detectors, and radiochemicals for nonmedical research. Note that no Broad-Type B licensees have reported to NRC since 2010. M&D Other licenses are usually issued to smaller organizations requiring a more restrictive license. These licenses are usually more specific in identifying each radionuclide, the chemical and physical form, and the authorized activities and users. Nuclear pharmacies are involved in the compounding and dispensing of radioactive materials for use in nuclear medicine procedures.

Table 3.4 presents the annual data that were reported by the three types of licensees for 2017, 2018, and 2019. As shown in the table below, the average measurable dose is generally higher for the Broad-Type A licensees, which includes only two licensees in the NRCs active licensee list.

Table 3.4 and Figure 3.2 show the number of individuals with measurable doses, the total collective dose, and the average measurable dose per individual for Broad-Type A, Broad-Type B 3-6

and Other, and Nuclear Pharmacy licensees. From 2018 to 2019 the number of individuals with a measurable dose increased by 12 percent and the collective TEDE increased by 8 percent. While the number of individuals with a measurable dose in 2019 was 24 percent more than the 5-year average of 646, the average measurable dose in 2019 (0.18 rem) was statistically lower than the 5-year average of 0.22 rem.

The values for Broad-Type A licensees are attributed to Curium US, LLC and International Isotopes Idaho, Inc., which accounted for 69 percent of the total collective dose in 2019.

Table 3.4 Annual Exposure Information for Manufacturing and Distribution Licensees 2017-2019 Number of Collective Average Number of Monitored Individuals with Dose Measurable Year Type of License Licensees Individuals Measurable Dose (person-rem) Dose (rem)

M & D - Type "A" Broad 2 315 205 99.578 0.49 M & D - Type "B" Broad and Other 1 1 1 0.010 0.01 2017 M & D - Nuclear Pharmacies 18 624 409 39.483 0.10 Total 21 940 615 139.071 0.23 M & D - Type "A" Broad 2 357 237 88.338 0.37 M & D - Type "B" Broad and Other 0 0 0 0.000 0.00 2018 M & D - Nuclear Pharmacies 12 729 481 48.167 0.10 Total 14 1,086 718 136.505 0.19 M & D - Type "A" Broad 2 417 293 102.107 0.35 M & D - Type "B" Broad and Other 0 0 0 0.000 0.00 2019 M & D - Nuclear Pharmacies 14 771 511 45.820 0.09 Total 16 1,188 804 147.927 0.18 Figure 3.2 Individuals with Measurable TEDE, Collective TEDE, and Average Measurable TEDE for Manufacturing and Distribution Licensees 1994-2019 3-7

3.3.3 Low-Level Waste Disposal Licensees 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 places such as hospitals and laboratories, store them for a short time, and dispose of them in a properly prepared burial ground. Since 1999, all licensees that have conducted these activities have been located in Agreement States, which have primary regulatory authority over the licensees activities; therefore, there are no NRC low-level waste licensees who report radiation exposure data to REIRS.

3.3.4 Independent Spent Fuel Storage Installation Licensees The NRC issues ISFSI licenses to allow the possession of commercial nuclear power reactor spent fuel and other associated radioactive materials for the purpose of storage. According to 10 CFR 72.3, Definitions [Ref. 15], spent fuel means fuel that has been withdrawn from a nuclear reactor following irradiation, has undergone at least 1 year of decay since being used as a source of energy in a power reactor, and has not been chemically separated into its constituent elements by reprocessing. Spent fuel includes the special nuclear material, byproduct material, source material, and other radioactive materials associated with fuel assemblies. The spent fuel that is removed from the reactor is initially stored in a spent fuel pool and usually cooled for at least 5 years in the pool before it is transferred to dry cask storage at an ISFSI. The NRC has authorized transfer as early as 3 years; however, the industry norm is approximately 10 years. An ISFSI provides interim storage of spent fuel and protection and safeguarding, pending its final disposal.

The majority of ISFSI facilities are located on site at commercial nuclear power reactors. The occupational dose information from ISFSI facilities is usually included with the dose information reported by the commercial nuclear power reactors and is not reported separately to the NRC.

Since 2005, two ISFSI licensees reported dose information to the NRC. One is the GE Morris facility located in Illinois and the second is the Trojan ISFSI located in Oregon. The GE Morris facility is the only spent fuel pool that is not located at an existing or former reactor site. The GE Morris ISFSI license has been renewed by the NRC until 2022. The Trojan commercial nuclear power reactor is no longer in commercial operation and has been decommissioned. However, the ISFSI facility at Trojan remains in operation and the occupational dose information is reported to the NRC under the ISFSI license. Appendix A, Table A1 summarizes the occupational dose information reported by these licensees.

Figure 3.3 shows the number of individuals with a measurable dose, the total collective dose, and the average measurable dose per individual for ISFSI facilities. Table 3.1 shows that the number of individuals with a measurable dose increased to 28 individuals in 2019 from 17 individuals in 2018.

Although the collective TEDE increased by 11 percent from 2018 to 2019, the dose increase was relatively small (1.740 person-rem in 2018 to 1.939 person-rem in 2019) and was statistically insignificant. The effect of a slight increase in the collective TEDE and the increase in number of individuals with a measurable dose resulted in a slight (but not significantly different) decrease in the average measurable TEDE per individual which decreased to 0.07 rem. The average measurable dose was not significantly different from the 5-year average.

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Figure 3.3 Individuals with Measurable TEDE, Collective TEDE, and Average Measurable TEDE for Independent Spent Fuel Storage Installation Licensees 1994-2019 3.3.5 Fuel Cycle Licensees The fuel cycle category addresses the use and handling of special nuclear material as described in 10 CFR Part 70, Domestic Licensing of Special Nuclear Material [Ref. 16]. While the bulk of exposure cited in this report addresses reactor fuel production, there are other uses of special nuclear material in education, research, and homeland security. The fuel cycle facilities are licensed by the NRC to process and handle special nuclear material, source material, or both.

These forms of nuclear material are highly regulated to ensure the safe use and enhanced security.

The majority of fuel cycle licenses are issued to allow the processing, enrichment, and fabrication of reactor fuels. Many of the fuel cycle facilities are different from each otherin purpose and technologyas they comprise the different stages of the Nuclear Fuel Cycle. The fuel cycle facilities that are currently operational fall into three different categories: uranium enrichment, uranium conversion, and fuel fabrication. Fuel fabrication facilities convert enriched uranium into fuel for nuclear reactors. Fabrication also can involve mixed oxide fuel, which is a combination of uranium and plutonium. Fuel cycle facilities make nuclear fuel for commercial nuclear reactors and for the U.S. Navy's nuclear fleet.

Figure 3.4 shows the number of individuals with a measurable dose, the total collective dose, and the average measurable dose per individual for fuel cycle licensees. The collective deep dose equivalent (DDE), the DDE average measurable dose, the collective CEDE, and the CEDE average measurable dose are also shown, because they make a significant contribution to the TEDE for fuel fabrication facilities.

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Figure 3.4 Annual Exposure Information for Fuel Cycle Licensees 1994-2019 Table 3.5 shows that there were seven licensed fuel cycle (fabrication processing, uranium enrichment, and UF6 production) facilities reporting in 2019. The collective TEDE and DDE increased in 2019 by 9 percent and 19 percent, respectively, and the collective CEDE decreased by 2 percent from 2018. When compared to the 5-year average, the increases in collective TEDE 3-10

and collective DDE were not statistically significant, whereas the decrease in collective CEDE was statistically significant.

Honeywell International, Inc. reported a decrease (26 percent) in collective TEDE in 2019. Since the 2011 Fukushima Daiichi event, demand for nuclear fuel has dropped while global supply overall has increased, resulting in decreased fuel production by this licensee. In addition, after a routine outage in October of 2017, Honeywell announced in November of that same year that they were suspending operations at the UF6 production plant which has remained in a ready-idle status since that time. The shift from production related activities to maintaining minimal operations is a major factor contributing to the reduction in collective TEDE in 2019.

Table 3.5 Annual Exposure Information for Fuel Cycle Licensees 2017-2019 Collective Average Collective Average Collective Average Number Number of Individuals TEDE Meas. Individuals DDE Meas. Individuals CEDE Meas.

Type of of Monitored with Meas. (person- TEDE with Meas. (person- DDE with Meas. (person- CEDE Year License Licensees Individuals TEDE rem) (rem) DDE rem) (rem) CEDE rem) (rem) 2017 Fuel Cycle 7 5,058 2,930 254.997 0.09 1,879 127.017 0.07 2,220 127.980 0.06 2018 Fuel Cycle 7 4,737 2,783 229.530 0.08 1,764 117.856 0.07 1,913 111.674 0.06 2019 Fuel Cycle 7 4,347 2,690 250.522 0.09 1,779 140.757 0.08 1,838 109.765 0.06 3.3.6 Light-Water Reactor Licensees 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, pressurized-water reactors (PWRs) and boiling-water reactors (BWRs), each of which uses water as the primary coolant.

Table 3.1 shows the number of licensees, number of monitored individuals, number of individuals with a measurable dose, total collective dose, average collective dose and average measurable dose per individual for reactor facilities that were in commercial operation for at least 1 full year for each of the years 2009 through 2019. The values do not include reactors that have been permanently shut down, or reactors that have been in commercial operation less than 1 full year.

The figures for reactors have not been adjusted for the multiple counting of transient individuals (see Section 5).

Appendix B presents the reported dose distribution of individuals monitored at each plant site for the year 2019 in alphabetical order by plant name. Sections 4 and 5 contain more detailed presentations and analyses of the annual dose information reported by commercial nuclear power reactors.

3.3.7 Other Facilities Reporting to the NRC Appendix A, Table A2 contains data for additional facilities that provided occupational radiation dose reports to the NRC in 2019. These facilities are not among the seven categories of licensees required to report under 10 CFR 20.2206 and are not included in the analyses presented in this report. However, these facilities may be of interest to researchers and are included in this report for completeness.

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3.4 Summary of Intake and Internal Dose Data by Licensee Category All internal dose estimates are based on the amount of the intake as the basis for the calculation.

The intake is the total amount of radioactive material that enters the human body, and internal dose (as defined in 10 CFR 20.1003) means that portion of the dose equivalent received from radioactive material taken into the body. For each intake recorded, licensees are required to list the radionuclide that was taken into the body, pulmonary clearance class, intake mode, and amount of the intake. An NRC Form 5, its equivalent paper document, or an electronic format containing this information is required to be completed and submitted to the NRC under 10 CFR 20.2206.

Tables 3.6 and 3.7 summarize the intake data reported to the NRC during 2019. The data are categorized by licensee type and are listed in order of radionuclide and pulmonary clearance class or pulmonary solubility type. Table 3.6 lists the intakes where the mode of intake into the body was recorded as ingestion or other, such as absorption through the skin or injection through a puncture or wound.

Table 3.6 Intake by Licensee Category and Radionuclide Mode of IntakeIngestion and Other 2019 Collective Intake in Number of Microcuries Mode Licensee Category Program Code Radionuclide Intake Records (sci. notation)

Ingestion Nuclear Power Reactor 41111 Am-241 1 3.30E-07 Nuclear Power Reactor 41111 Ce-144 1 5.19E-04 Nuclear Power Reactor 41111 Cm-242 1 1.07E-06 Nuclear Power Reactor 41111 Co-58 2 9.91E-02 Nuclear Power Reactor 41111 Co-60 7 3.73E-01 Nuclear Power Reactor 41111 Cr-51 1 1.56E-01 Nuclear Power Reactor 41111 Fe-55 1 1.58E-02 Nuclear Power Reactor 41111 Fe-59 1 3.08E-03 Nuclear Power Reactor 41111 Mn-54 2 1.13E-02 Nuclear Power Reactor 41111 Nb-95 2 2.00E-01 Nuclear Power Reactor 41111 Ni-63 2 6.27E-03 Nuclear Power Reactor 41111 Sb-124 2 9.41E-04 Nuclear Power Reactor 41111 Sb-125 1 1.04E-03 Nuclear Power Reactor 41111 Sn-113 2 7.30E-04 Nuclear Power Reactor 41111 Zn-65 2 3.29E-03 Nuclear Power Reactor 41111 Zr-95 1 5.41E-02 Table 3.7 lists the intakes where the mode of intake was inhalation from ambient airborne radioactive material in the workplace. The pulmonary clearance class or pulmonary solubility type is recorded as D, W, Y (days, weeks, years) or F, M, S (fast, medium, slow), respectively, corresponding to the clearance half-time from the pulmonary region of the lung into the blood and gastrointestinal tract. The pulmonary clearance class designation depends on whether the licensee is using the nomenclature in International Commission on Radiological Protection (ICRP)

Publication 30 (D, W, Y) [Ref. 17], which is described in 10 CFR Part 20, or ICRP Publication 68 (F, M, S) [Ref. 18]. Licensees that use the methodology described in ICRP Publication 30 use D, W, and Y pulmonary clearance classes to determine the dose. Licensees that use the methodology described in ICRP Publication 68 use F, M, and S pulmonary solubility types to determine the dose.

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The amount of material taken into the body is given in microcuries, a unit of measure of the quantity of radioactive material. For each licensee category, the maximum number of intake records and the maximum intake are highlighted in the table in bold and boxed for ease of reference.

Table 3.7 Intake by Licensee Category and Radionuclide Mode of IntakeInhalation 2019 Pulmonary Number of Collective Intake Clearance Class Intake in Microcuries Licensee Category Program Code Radionuclide or Solubility Type Records * (sci. notation)

Nuclear Pharmacies 02500 I-123 W 8 6.91E-02 02500 I-131 D 6 5.34E-01 02500 I-131 W 89 3.08E+00 Manufacturing and 03211 Cs-137 D 7 9.26E+00 Distribution Type A Broad 03211 I-131 D 7 7.40E-01 Uranium Hexafluoride (UF6) 11400 Ac-227 D 1 1.00E-06 Production Plants 11400 Ac-227 W 88 1.33E-04 11400 Pa-231 D 1 1.00E-06 11400 Pa-231 W 88 1.33E-04 11400 Pb-210 D 79 1.06E-04 11400 Po-210 D 1 1.00E-06 11400 Po-210 W 71 8.80E-05 11400 Ra-226 D 1 2.00E-06 11400 Ra-226 W 112 3.17E-04 11400 Ra-228 D 1 1.00E-06 11400 Ra-228 W 64 7.80E-05 11400 Th-228 D 1 1.00E-06 11400 Th-228 W 64 7.80E-05 11400 Th-230 D 1 2.20E-05 11400 Th-230 W 128 3.20E-03 11400 Th-232 D 1 1.00E-06 11400 Th-232 W 64 7.80E-05 11400 U-234 D 1 2.06E-03 11400 U-234 W 130 2.95E-01 11400 U-235 D 1 9.60E-05 11400 U-235 W 130 1.38E-02 11400 U-238 D 1 1.72E-03 11400 U-238 W 130 2.46E-01 Uranium Fuel Processing Plants 21210 Am-241 M 26 1.03E-04 21210 Pu-239 M 53 4.22E-04 21210 Sr-90 S 249 3.81E-01 21210 Th-232 M 9 1.36E-07 21210 Th-232 S 14 1.52E-04 21210 U-232 D 2 8.80E-07 21210 U-232 W 1 1.00E-08 21210 U-232 Y 111 1.98E-04 21210 U-234 D 182 1.51E-01 21210 U-234 F 720 4.94E-02 NOTE: The data values shown bolded and in boxes represent the highest value in each category.

• An intake event may involve multiple nuclides; 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.

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Table 3.7 Intake by Licensee Category and Radionuclide Mode of IntakeInhalation 2019 (continued)

Pulmonary Number of Collective Intake Clearance Class Intake in Microcuries Licensee Category Program Code Radionuclide or Solubility Type Records * (sci. notation)

Uranium Fuel Processing Plants 21210 U-234 M 648 6.39E-03 (continued) 21210 U-234 S 1,702 1.96E+00 21210 U-234 W 65 5.37E-02 21210 U-234 Y 624 1.60E+00 21210 U-235 D 130 2.99E-03 21210 U-235 S 317 5.63E-02 21210 U-235 W 65 2.00E-03 21210 U-235 Y 241 3.34E-02 21210 U-236 D 130 1.55E-04 21210 U-236 F 645 9.59E-04 21210 U-236 S 50 3.85E-04 21210 U-236 W 65 8.58E-05 21210 U-236 Y 241 7.53E-03 21210 U-238 D 182 2.26E-02 21210 U-238 M 538 3.98E-04 21210 U-238 S 326 1.98E-01 21210 U-238 W 65 7.29E-03 21210 U-238 Y 624 2.36E-01 Nuclear Power Reactor 41111 Am-241 W 1 1.80E-07 41111 Ce-144 Y 1 2.76E-04 41111 Cm-242 W 1 5.60E-07 41111 Co-58 W 1 1.70E-02 41111 Co-58 Y 8 2.50E-01 41111 Co-60 W 3 1.05E-01 41111 Co-60 Y 8 1.80E-01 41111 Cr-51 Y 3 8.28E-02 41111 Fe-55 W 1 8.39E-03 41111 Fe-59 W 1 1.63E-03 41111 I-131 D 84 7.50E+00 41111 I-132 D 2 2.78E-01 41111 I-133 D 80 4.90E+01 41111 I-135 D 64 3.00E+01 41111 Mn-54 W 3 2.83E-03 41111 Nb-95 Y 5 1.10E-01 41111 Ni-63 W 1 7.14E-04 41111 Sb-124 W 1 4.04E-04 41111 Sb-125 W 1 5.53E-04 41111 Sn-113 W 1 2.55E-04 41111 Zn-65 Y 1 1.30E-03 41111 Zr-95 D 1 1.70E-01 41111 Zr-95 W 2 7.05E-02 41111 Zr-95 Y 2 1.10E-08 NOTE: The data values shown bolded and in boxes represent the highest value in each category.

• An intake event may involve multiple nuclides, and individuals may incur multiple intakes during the year. The number of intake records given here indicates the number of separate intake reports that were submitted on NRC Form 5 reports under 10 CFR 20.2206.

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Table 3.8 lists the number of individuals with a measurable CEDE, the collective CEDE, and the average measurable CEDE per individual for each licensee category. The number of individuals with a measurable CEDE was significantly lower than the 5-year average. Fuel fabrication facilities combined with the UF6 production facility had the majority of internal doses (98.7 percent of total collective CEDE) in 2019. The UF6 production facility had a collective dose of 4.249 person-rem. Although not statistically significant, the average CEDE for fuel fabrication facilities decreased to 0.062 rem in 2019 which was below the 5-year average of 0.066 rem. The fuel fabrication licensee with the highest collective dose reported 41.905 person-rem and an average of 0.133 rem per individual. This is due to the exposure of individuals to uranium during the processing and fabrication of the uranium fuel.

Table 3.8 Collective and Average CEDE by Licensee Category 2019 Number Collective Average Meas.

Licensee with Meas. CEDE CEDE Category Licensee Name License Number CEDE (person-rem) (rem)

MANUFACTURING AND DISTRIBUTION 02500 CARDINAL HEALTH 34-29200-01MD 27 0.085 0.003 02500 CARDINAL HEALTH 34-31473-02MD 2 0.003 0.002 02500 GE HEALTHCARE - KENTWOOD 21-26707-01MD 3 0.011 0.004 02500 GE HEALTHCARE - ST. LOUIS/OVERLAND 24-32462-01MD 1 0.002 0.002 03211 CURIUM US, LLC 24-04206-01 1 0.213 0.213 03211 INTERNATIONAL ISOTOPES IDAHO, INC. 11-27680-01 11 0.319 0.029 Totals and Averages 45 0.633 0.014 UF6 PRODUCTION HONEYWELL PERFORMANCE MATERIALS AND 11400 SUB-0526 130 4.249 0.033 TECHNOLOGY Totals and Averages 130 4.249 0.033 FUEL FABRICATION 21210 BWX TECHNOLOGIES, INC. SNM-0042 224 10.500 0.047 21210 FRAMATOME, INC. SNM-1227 241 27.594 0.114 21210 GLOBAL NUCLEAR FUEL - AMERICAS, LLC SNM-1097 383 22.995 0.060 21210 NUCLEAR FUEL SERVICES, INC. SNM-0124 544 2.522 0.005 21210 WESTINGHOUSE ELECTRIC COMPANY, LLC SNM-1107 316 41.905 0.133 Totals and Averages 1,708 105.516 0.062 COMMERCIAL LIGHT-WATER REACTORS 41111 RIVER BEND NPF-47 90 0.630 0.007 41111 SOUTH TEXAS NPF-76 1 0.003 0.003 41111 SUMMER NPF-12 8 0.117 0.015 41111 SEQUOYAH DPR-77 2 0.030 0.015 41111 POINT BEACH DPR-24 7 0.009 0.001 Totals and Averages 108 0.789 0.007 Grand Totals and Averages 1,991 111.187 0.056 NOTE: The data values shown bolded and in boxes represent the highest value in each category.

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Table 3.9 shows the distribution of internal doses (CEDE) from 1994 to 2019 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 were received by individuals working at fuel fabrication facilities. In 2019, the collective CEDE decreased by 1 percent from 2018 while the number of individuals with a measurable CEDE decreased by 3 percent. The collective CEDE was significantly lower from the 5-year average of 141.0 person-rem, as was the number of individuals with a measurable CEDE in 2019 (1,991) from the 5-year average of 2,357. The collective CEDE of 112.004 person-rem in all facilities in 2018 decreased to 111.187 person-rem. Although there was a decrease in the number of individuals reported with CEDE dose and a decrease in the collective CEDE, the average measurable CEDE increased by 2 percent to 0.056 rem for 2019. However, the average measurable CEDE in 2019 was not statistically different from the 5-year average.

Table 3.9 Internal dose (CEDE) distribution 1994-2019 Number of Individuals with CEDE in the Ranges (rem)

• Collective Average Indiv. with CEDE Meas.

Meas. 0.020- 0.100- 0.250- 0.500- 0.750- 1.0- 2.0- 3.0- 4.0- Meas. (person- CEDE Year 0.020 0.100 0.250 0.500 0.750 1.0 2.0 3.0 4.0 5.0 CEDE rem) (rem) 1994 3,425 577 287 683 237 141 293 69 2 - 5,714 1,170.453 0.205 1995 2,869 691 338 730 254 147 290 49 2 - 5,370 1,167.105 0.217 1996 3,096 598 305 584 324 138 187 22 2 2 5,258 931.799 0.177 1997 3,835 869 381 827 267 148 169 30 - - 6,526 998.406 0.153 1998 3,310 932 426 746 246 140 153 21 2 - 5,976 922.935 0.154 1999 3,423 752 466 438 206 117 173 29 - - 5,604 813.605 0.145 2000 3,275 1001 570 383 216 98 224 58 7 1 5,833 988.640 0.169 2001 1,774 827 716 364 128 53 146 82 15 1 4,106 884.134 0.215 2002 1,760 746 647 531 144 33 23 3 - - 3,887 494.821 0.127 2003 2,208 778 726 388 116 17 5 - - - 4,238 395.573 0.093 2004 1,989 838 657 381 105 17 3 - - - 3,990 375.021 0.094 2005 1,205 706 685 341 98 33 2 - - - 3,070 365.258 0.119 2006 1,302 726 686 346 96 18 3 - - - 3,177 346.918 0.109 2007 1,480 805 646 310 52 5 3 - - - 3,301 300.863 0.091 2008 1,008 761 526 303 41 8 4 - - - 2,651 267.415 0.101 2009 1,115 711 597 229 80 21 7 - - - 2,760 293.251 0.106 2010 1,216 884 669 210 67 30 6 - - - 3,082 308.332 0.100 2011 1,243 916 628 270 72 19 14 1 - - 3,163 322.615 0.102 2012 1,158 933 554 155 52 6 3 - - - 2,861 232.462 0.081 2013 1,632 758 353 149 20 1 - - - - 2,913 164.799 0.057 2014 1,175 829 417 86 24 1 - - - - 2,532 157.191 0.062 2015 1,036 838 442 103 16 - - - - - 2,435 162.670 0.067 2016 1,100 920 407 69 7 - - - - - 2,503 144.627 0.058 2017 1,073 766 324 99 6 - - - - - 2,268 128.373 0.057 2018 1,159 489 297 99 1 - - - - - 2,045 112.004 0.055 2019 1,096 482 318 91 3 1 - - - - 1,991 111.187 0.056

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

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4 COMMERCIAL POWER REACTORS 4.1 Introduction General trends in occupational radiation exposure at commercial nuclear power reactors are best analyzed within the context of other pertinent information. In this section, some of the tables and appendices that summarize dose data also show the type, capacity, amount of electricity generated, and age of the reactor. Dose data are then presented as a function of these data.

4.2 Definition of Terms and Sources of Data 4.2.1 Number of Reactors The number of reactors shown in Tables 4.1, 4.2, and 4.3 are the number of BWRs, PWRs, and LWRs that were in commercial operation during the year listed. This is the number of reactors that the average number of individuals with a measurable dose and the average collective dose per reactor are based. Excluded are reactors that have not yet completed a first full year of commercial operation and those reactors that have been permanently defueled. The date that each reactor was declared to be in commercial operation was taken from licensed operating reactors, Monthly Operating Report Data [Ref. 1].

In May 2019, Pilgrim 1 ceased operation, dropping the number of active BWRs from 33 to 32.

Three Mile Island (TMI) Unit 1 permanently shut down in September 2019, dropping the number of active PWRs from 65 to 64. The dose information for these operational reactors and for others that are no longer in commercial operation is listed at the end of Appendix B and the current status of plants no longer in operation can be found in Appendix E. Watts Bar Unit 2 began commercial power operation on November 21, 2016, and reported its dose information with Watts Bar Unit 1 beginning in 2017.

4.2.2 Electric Energy Generated The electric energy generated in megawatt-years (MW-yr) each year by each reactor is graphically represented in Appendix D. This number was obtained by dividing the megawatt-hours (MW-hr) of electricity annually produced by each facility by 8,760, the number of hours in the year, except for leap years, when the number was 8,784 hours0.00907 days <br />0.218 hours <br />0.0013 weeks <br />2.98312e-4 months <br />. The number of MW-hr of electricity produced each year was obtained from licensed operating reactors, Monthly Operating Report Data [Ref. 1].

For the years 1973 to 1996, the electricity generated is the gross electricity output of the reactor.

For 1997 to 2019, the number reflects the net electricity produced, which is the gross electricity minus the amount the plant used for operations. This change is the result of a change in NRC power generation reporting requirements. The electricity generated in MW-yr 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.

As shown in Table 4.3, in 2019, the net electricity generated at LWRs was nearly equivalent to 2018 and not significantly different from the 5-year trend. Twenty-three reactor sites had decreased power production and 34 reactor sites had increased power production from 2018 to 2019. Waterford 3 had the largest percentage of decreased power production (26 percent), while 4-1

Perry and Callaway 1 experienced a 14 and 13 percent decrease in power production, respectively. Waterford 3 was shut down 72.8 days due to refueling and 20.1 days for equipment failure for a total of 92.9 days off line. Perry and Callaway 1 were shut down 41.5 and 48.2 total outage days, respectively. From 2018 to 2019, Grand Gulf had the largest increase in power production (59 percent).

4.2.3 Collective Dose per Megawatt-Year The number of MW-yr of electricity generated was used in determining the ratio of the average value of the annual collective dose (TEDE) to the number of MW-yr of electricity generated. The ratio was calculated by dividing the total collective dose in person-rem by the electric energy generated in MW-yr and is a measure of the dose incurred by individuals at commercial nuclear power reactors 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 2019, the number reflects the net electricity produced. The ratio of collective dose to the number of MW-yr is calculated by year for BWRs, PWRs, and LWRs, and the ratios are presented in Tables 4.1, 4.2, and 4.3. This ratio is also calculated for each reactor site (see Appendix C). The average collective dose per MW-yr for LWRs remained at 0.06 rem/MW-yr in 2019. This value is not statistically different from the 5-year average of 0.07 rem/MW-yr.

4.2.4 Average Maximum Dependable Capacity The average maximum dependable capacity, as shown in Tables 4.1, 4.2, and 4.3, is calculated by dividing the sum of the net maximum dependable capacities of the reactors in megawatts (net megawatts electric [MWe]) by the number of reactors included each year. The net maximum dependable capacity is defined as the gross electrical output as measured at the output terminals of the turbine generator during the most restrictive seasonal conditions less the normal station service loads. The capacity of each plant was found in Monthly Operating Report Data [Ref. 1]. As shown in Table 4.3 for 2019, the value for the average electricity generated per reactor was the highest reported since 1994 (955 MW-yr).

4.2.5 Percent of Maximum Dependable Capacity Achieved The percent of maximum dependable capacity achieved is shown for all LWRs in Table 4.3. This parameter gives an indication of the overall power generation performance of LWRs as compared with the maximum dependable capacity that could have been 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.

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Table 4.1 Summary of Information Reported by Commercial Boiling-Water Reactors 1994-2019 Average No. Average No. of Average Average Individuals Collective Average Average Individuals Annual Measurable Collective with Dose per Electricity Maximum Maximum Number of with Collective Dose per Dose per Measurable Electricity MW-yr Generated Dependable Dependable Reactors Measurable Dose Individual Reactor Doses per Generated*** (person-rem/ per Reactor Capacity Net Capacity Year Included* Dose** (person-rem) (rem)** (person-rem) Reactor** (MW-yr) MW-yr) (MW-yr) (MWe) Achieved 1994 37 39,171 12,098 0.31 327 1,059 22,139.0 0.55 598 801 75%

1995 37 35,686 9,471 0.27 256 964 24,737.0 0.38 669 835 80%

1996 37 37,792 9,466 0.25 256 1,021 24,322.2 0.39 657 838 78%

1997 37 34,021 7,603 0.22 205 919 22,866.1 0.33 618 845 73%

1998 36 32,899 6,829.296 0.21 190 914 23,781.2 0.29 661 874 76%

1999 35 31,482 6,434.430 0.20 184 899 26,962.6 0.24 770 885 87%

2000 35 31,186 6,089.676 0.20 174 891 28,476.9 0.21 814 893 91%

2001 35 28,797 4,835.397 0.17 138 823 28,730.4 0.17 821 895 92%

2002 35 30,978 6,107.767 0.20 175 885 29,460.0 0.21 842 907 93%

2003 35 30,759 5,659.434 0.18 162 879 29,094.4 0.19 831 912 91%

2004 35 33,948 5,450.982 0.16 156 970 29,424.8 0.19 841 893 94%

2005 35 33,544 5,995.975 0.18 171 958 29,386.8 0.20 840 946 89%

4-3 2006 35 34,159 4,989.761 0.15 143 976 30,238.4 0.17 864 954 91%

2007 35 37,515 5,388.416 0.14 154 1,072 30,189.3 0.18 863 955 90%

2008 35 34,642 4,522.413 0.13 129 990 31,248.3 0.14 893 957 93%

2009 35 36,207 5,282.869 0.15 151 1,034 30,762.7 0.17 879 959 92%

2010 35 37,214 4,807.656 0.13 137 1,063 31,274.6 0.15 894 961 93%

2011 35 38,202 4,976.503 0.13 142 1,091 30,549.7 0.16 873 937 93%

2012 35 38,164 4,200.281 0.11 120 1,090 30,485.4 0.14 871 968 90%

2013 35 36,513 4,459.270 0.12 127 1,043 31,221.1 0.14 892 967 92%

2014 35 33,706 3,798.108 0.11 109 963 31,904.2 0.12 912 976 93%

2015 34 35,346 4,155.273 0.12 122 1,040 31,720.1 0.13 933 992 94%

2016 34 31,299 3,339.055 0.11 98 921 31,464.8 0.11 925 995 93%

2017 34 32,234 4,007.342 0.12 118 948 31,820.0 0.13 936 995 94%

2018 33 31,169 3,659.588 0.12 111 945 30,722.7 0.12 931 1,008 92%

2019 32 29,100 3,372.909 0.12 105 909 31,237.4 0.11 976 1,018 96%

• Includes only those reactors that had been in commercial operation for at least 1 full year as of December 31 of each of the indicated years.

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

• • • Beginning in 1997, the electricity reflects the net electricity generated.

Table 4.2 Summary of Information Reported by Commercial Pressurized-Water Reactors 1994-2019 Average No. Average No. of Average Average Individuals Collective Average Average Individuals Annual Measurable Collective with Dose per Electricity Maximum Maximum Number of with Collective Dose per Dose per Measurable Electricity MW-yr Generated Dependable Dependable Reactors Measurable Dose Individual Reactor Doses per Generated*** (person-rem/ per Reactor Capacity Net Capacity Year Included* Dose** (person-rem) (rem)** (person-rem) Reactor** (MW-yr) MW-yr) (MW-yr) (MWe) Achieved 1994 70 44,283 9,574 0.22 137 633 52,397.6 0.18 749 928 81%

1995 70 49,985 11,762 0.24 168 714 54,138.2 0.22 773 929 83%

1996 72 46,852 9,417 0.20 131 651 55,337.8 0.17 769 935 82%

1997 72 50,690 9,546 0.19 133 704 48,985.3 0.19 680 943 72%

1998 69 38,586 6,358.096 0.16 92 559 53,288.7 0.12 772 942 82%

1999 69 43,938 7,231.281 0.16 105 637 56,235.0 0.13 815 942 87%

2000 69 42,922 6,562.006 0.15 95 622 57,529.9 0.11 834 943 88%

2001 69 38,773 6,273.155 0.16 91 562 58,822.4 0.11 852 946 90%

2002 69 42,264 6,018.423 0.14 87 613 59,369.7 0.10 860 947 91%

2003 69 44,054 6,296.136 0.14 91 638 57,920.6 0.11 839 949 88%

2004 69 35,901 4,916.915 0.14 71 520 60,398.7 0.08 875 943 93%

2005 69 44,583 5,459.832 0.12 79 646 59,790.9 0.09 867 955 91%

4-4 2006 69 46,106 6,031.425 0.13 87 668 59,751.3 0.10 866 960 90%

2007 69 42,015 4,731.597 0.11 69 609 61,955.6 0.08 898 961 93%

2008 69 44,808 4,673.527 0.10 68 649 60,586.0 0.08 878 964 91%

2009 69 45,547 4,741.935 0.10 69 660 60,467.9 0.08 876 966 91%

2010 69 37,796 3,823.728 0.10 55 548 60,859.4 0.06 882 967 91%

2011 69 43,119 3,795.601 0.09 55 625 59,682.5 0.06 865 937 92%

2012 69 41,385 3,835.112 0.09 56 600 57,272.5 0.07 830 974 85%

2013 65 30,723 2,300.277 0.07 35 473 58,785.5 0.04 904 987 92%

2014 65 37,141 3,326.411 0.09 51 571 59,262.2 0.06 912 989 92%

2015 65 35,452 2,863.815 0.08 44 545 59,377.2 0.05 913 990 92%

2016 65 28,054 2,026.654 0.07 31 432 60,052.5 0.03 924 1,001 92%

2017 65 32,527 2,409.206 0.07 37 500 60,148.9 0.04 925 1,001 92%

2018 65 29,845 2,169.883 0.07 34 459 61,113.7 0.04 940 1,002 94%

2019 64 24,515 1,707.886 0.07 27 383 60,400.6 0.03 944 1,008 94%

• Includes only those reactors that had been in commercial operation for at least 1 full year as of December 31 of each of the indicated years.

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

• • • Beginning in 1997, the electricity reflects the net electricity generated.

Table 4.3 Summary of Information Reported by Commercial Light-Water Reactors 1994-2019 Average No. Average No. of Average Average Individuals Collective Average Average Individuals Annual Measurable Collective with Dose per Electricity Maximum Maximum Number of with Collective Dose per Dose per Measurable Electricity MW-yr Generated Dependable Dependable Reactors Measurable Dose Individual Reactor Doses per Generated*** (person-rem/ per Reactor Capacity Net Capacity Year Included* Dose** (person-rem) (rem)** (person-rem) Reactor** (MW-yr) MW-yr) (MW-yr) (MWe) Achieved 1994 107 83,454 21,672 0.26 203 780 74,536.6 0.29 697 884 79%

1995 107 85,671 21,233 0.25 198 801 78,875.2 0.27 737 896 82%

1996 109 84,644 18,883 0.22 173 777 79,660.0 0.24 731 902 81%

1997 109 84,711 17,149 0.20 157 777 71,851.4 0.24 659 910 72%

1998 105 71,485 13,187.392 0.18 126 681 77,069.9 0.17 734 918 80%

1999 104 75,420 13,665.711 0.18 131 725 83,197.6 0.16 800 923 87%

2000 104 74,108 12,651.682 0.17 122 713 86,006.8 0.15 827 926 89%

2001 104 67,570 11,108.552 0.16 107 650 87,552.8 0.13 842 929 91%

2002 104 73,242 12,126.190 0.17 117 704 88,829.7 0.14 854 934 91%

2003 104 74,813 11,955.570 0.16 115 719 87,015.0 0.14 837 936 89%

2004 104 69,849 10,367.897 0.15 100 672 89,823.5 0.12 864 926 93%

2005 104 78,127 11,455.807 0.15 110 751 89,177.7 0.13 857 952 90%

4-5 2006 104 80,265 11,021.186 0.14 106 772 89,989.7 0.12 865 958 90%

2007 104 79,530 10,120.013 0.13 97 765 92,144.9 0.11 886 959 92%

2008 104 79,450 9,195.940 0.12 88 764 91,834.3 0.10 883 961 92%

2009 104 81,754 10,024.804 0.12 96 786 91,230.6 0.11 877 964 91%

2010 104 75,010 8,631.384 0.12 83 721 92,134.0 0.09 886 965 92%

2011 104 81,321 8,771.326 0.11 84 782 90,232.2 0.10 868 967 90%

2012 104 79,549 8,035.393 0.10 77 765 87,757.9 0.09 844 972 87%

2013 100 67,236 6,759.547 0.10 68 672 90,006.6 0.08 900 980 92%

2014 100 70,847 7,124.519 0.10 71 708 91,166.4 0.08 912 985 93%

2015 99 70,798 7,019.088 0.10 71 715 91,097.3 0.08 920 991 93%

2016 99 59,353 5,365.709 0.09 54 600 91,517.3 0.06 924 999 93%

2017 99 64,761 6,416.548 0.10 65 654 91,968.8 0.07 929 999 93%

2018 98 61,014 5,829.471 0.10 59 623 91,836.4 0.06 937 1,004 93%

2019 96 53,615 5,080.795 0.09 53 558 91,638.0 0.06 955 1,011 94%

• Includes only those reactors that had been in commercial operation for at least 1 full year as of December 31 of each of the indicated years.

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

• • • Beginning in 1997, the electricity reflects the net electricity generated.

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. At 94 percent in 2019, the percent of maximum dependable capacity for LWRs was the highest value reported since 1994.

4.3 Annual TEDE Distributions Table 4.4a summarizes the distribution of the annual TEDE doses received by individuals (unadjusted for transient workers) at all commercial LWRs during each of the years 1994 through 2019. This distribution is the sum of the annual dose distributions reported by each licensed LWR each year. As previously noted, Appendix B shows the distribution reported by each LWR site for 2019. Table 4.4a includes only those reactors that have been in operation for at least a full year.

In 2019, the total collective dose decreased by 13 percent to a value of 5,081 person-rem.

Each year, this report identifies the reactors with the largest increases and decreases in collective dose from the previous year and identifies the main reasons for these changes. The changes generally are driven by whether the sites had an increase or decrease in outages from one year to the next. During an outage, more work is performed by individuals working in radiation areas, thereby resulting in increased collective doses. This is particularly true during a refueling outage, which entails the opening of the reactor vessel by removing the vessel head and transferring spent fuel to the spent fuel pool. In addition, the sites usually schedule maintenance and inspections during a refueling outage, which tend to increase the collective dose. If a site does not have a refueling outage during a year, the collective dose for that site is normally much lower. For example, in 2019 Waterford 3 was the PWR with the largest percentage increase in collective dose which increased from 1.130 person-rem in 2018, to 69.780 person-rem in 2019. PWR collective dose decreased by 21 percent which coincided with a decrease in refueling outage days in 2019, decreasing from a total of 1,766 days in 2018 to 1,665 days in 2019. Outage days for PWRs ranged from 0 to 124 days during 2019. Seabrook had the largest percentage decrease in collective dose (33.418 to 1.084 person-rem) along with the fewest number of total outage days (0) in 2019.

For BWRs from 2018 to 2019, Perry had the highest percent increase in collective dose. In 2018, Perry had 0 total outage days and reported a collective dose of 29.848 person-rem, while in 2019, Perry had over 41 total outage days (refueling and equipment outages) and reported a collective dose of 301.067 person-rem. In 2019, Fitzpatrick had a 90 percent decrease in collective dose. In 2018, Fitzpatrick had 27.6 total outage days and reported a dose of 231.548 person-rem, while in 2019, Fitzpatrick had 0 total outage days and reported a collective dose of 24.160 person-rem.

Combined, the refueling outage hours declined by 15 percent from 2018 to 2019 (15 percent decrease for BWRs and 15 percent decrease for PWRs) which was a factor in the decreased collective dose.

Table 4.4b summarizes the distribution of the annual TEDE doses received by unique individuals (adjusted for transient workers) at all commercial LWRs during each of the years 1994 through 2019. The values do not include reactors that have been permanently shut down or reactors that have not been in commercial operation for 1 full year. See Section 5 for a detailed analysis of the impact of transient individuals on the distribution of annual doses in 2019.

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Table 4.4a Summary of Distribution of Annual Doses* at Commercial Light-Water Reactors** 1994-2019 Number of Individuals with Annual Doses* in the Ranges (rem) *** Average Note: Numbers of individuals shown have not been adjusted for the multiple reporting of transient individuals (see Section 5). Number Measurable with Collective Dose No. Measurable Measurable 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Total Number Measurable Dose (person- (person-Year Exposure <0.1 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Exposure rem) rem) 1994 85,145 36,528 18,633 14,246 6,800 3,502 3,323 215 6 - - - 168,398 83,253 21,534.000 0.259 1995 81,032 38,575 20,245 15,279 6,884 3,336 3,077 125 5 - - - 168,558 87,526 21,674.000 0.248 1996 78,197 39,426 19,955 14,201 5,809 2,648 2,342 68 - - - - 162,646 84,449 18,874.000 0.223 1997 80,163 41,759 19,951 13,396 5,394 2,240 1,671 59 3 - - - 164,636 84,473 17,136.000 0.203 1998 77,080 37,039 17,189 10,467 3,930 1,562 1,129 35 - - - - 148,431 71,351 13,169.366 0.185 1999 74,867 39,663 18,063 10,964 3,994 1,569 1,141 24 2 - - - 150,287 75,420 13,665.711 0.181 2000 73,793 40,301 17,598 10,310 3,525 1,375 976 23 - - - - 147,901 74,108 12,651.682 0.171 2001 73,206 37,461 16,078 9,231 2,930 1,060 747 63 - - - - 140,776 67,570 11,108.552 0.164 2002 76,270 41,588 16,752 9,426 3,121 1,245 1,003 105 2 - - - 149,512 73,242 12,126.190 0.166 2003 77,889 42,720 17,231 9,589 3,139 1,233 864 37 - - - - 152,702 74,813 11,955.570 0.160 2004 80,473 41,583 15,626 8,245 2,733 978 668 16 - - - - 150,322 69,849 10,367.897 0.148 2005 82,574 46,444 17,754 9,191 2,934 1,104 683 17 - - - - 160,701 78,127 11,455.807 0.147 2006 84,558 48,571 18,269 9,312 2,675 904 532 2 - - - - 164,823 80,265 11,021.186 0.137 4-7 2007 84,551 49,998 17,672 8,294 2,329 824 402 11 - - - - 164,081 79,530 10,120.013 0.127 2008 89,875 51,831 17,337 7,578 1,847 583 269 5 - - - - 169,325 79,450 9,195.940 0.116 2009 94,627 52,670 17,417 8,352 2,161 741 413 - - - - - 176,381 81,754 10,024.804 0.123 2010 104,638 49,571 16,042 6,656 1,801 602 333 5 - - - - 179,648 75,010 8,631.384 0.115 2011 110,217 55,407 16,651 6,753 1,675 559 276 - - - - - 191,538 81,321 8,771.326 0.108 2012 114,428 55,735 15,593 6,072 1,509 385 242 13 - - - - 193,977 79,549 8,035.393 0.101 2013 107,378 47,190 13,158 5,088 1,227 380 191 2 - - - - 174,614 67,236 6,759.547 0.101 2014 104,006 50,110 13,650 5,231 1,167 421 235 33 - - - - 174,853 70,847 7,124.519 0.101 2015 106,088 50,067 13,856 4,980 1,230 421 242 2 - - - - 176,886 70,798 7,019.088 0.099 2016 96,221 43,386 10,938 3,829 865 243 92 - - - - - 155,574 59,353 5,365.709 0.090 2017 92,311 45,920 12,376 4,745 1,184 382 154 - - - - - 157,072 64,761 6,416.548 0.099 2018 89,205 44,206 11,030 4,207 1,086 316 168 1 - - - - 150,219 61,014 5,829.471 0.096 2019 81,282 39,068 9,512 3,636 942 300 156 1 - - - - 134,897 53,615 5,080.795 0.095

• These doses are annual TEDE doses.

• • Summary of reports submitted in accordance with 10 CFR 20.2206 by BWRs and PWRs that had been in commercial operation for at least 1 full year as of December 31 of each of the indicated years. Figures shown have not been adjusted for the multiple reporting of transient individuals (see Table 4.4b and Section 5).

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

Table 4.4b Summary of Distribution of Annual Doses* at Commercial Light-Water Reactors**, Adjusted for Transients 1994-2019 Number of Individuals with Annual Doses* in the Ranges (rem) *** Average Note: Numbers of individuals shown have been adjusted for the multiple reporting of transient individuals (see Section 5). Number Measurable with Collective Dose No. Measurable Measurable 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Total Number Measurable Dose (person- (person-Year Exposure <0.1 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Exposure rem) rem) 1994 67,700 29,847 14,841 11,716 6,124 3,586 4,222 508 40 - - - 138,584 70,884 21,534.000 0.304 1995 61,505 29,588 15,097 12,020 6,121 3,300 3,906 595 133 2 - - 132,267 70,762 21,674.000 0.306 1996 58,292 30,021 14,831 11,340 5,418 2,831 3,194 408 67 - - - 126,402 68,110 18,874.000 0.277 1997 58,647 31,751 14,881 10,902 5,228 2,447 2,598 286 41 - - - 126,781 68,134 17,136.000 0.252 1998 57,041 27,905 12,829 8,802 3,930 1,839 1,829 182 15 1 - - 114,373 57,332 13,169.366 0.230 1999 55,121 29,271 13,278 9,017 3,806 1,908 1,898 245 18 - - - 114,562 59,441 13,665.711 0.230 2000 53,324 28,480 12,921 8,679 3,571 1,644 1,734 186 18 - - - 110,557 57,233 12,651.682 0.221 2001 52,636 27,246 11,491 7,659 2,907 1,323 1,392 221 53 - - - 104,928 52,292 11,108.552 0.212 2002 53,440 28,523 11,610 7,668 3,004 1,479 1,820 320 35 1 - - 107,900 54,460 12,126.190 0.223 2003 54,028 29,161 11,971 8,190 3,253 1,527 1,651 184 18 - - - 109,983 55,955 11,955.570 0.214 2004 57,420 28,863 11,178 7,335 2,873 1,233 1,190 188 13 - - - 110,293 52,873 10,367.897 0.196 2005 56,709 31,035 12,422 7,813 3,106 1,537 1,490 147 3 - - - 114,262 57,553 11,455.807 0.199 4-8 2006 57,546 32,439 12,687 7,802 2,971 1,415 1,407 82 2 - - - 116,351 58,805 11,021.186 0.187 2007 57,314 32,706 11,961 7,396 2,714 1,284 1,100 97 9 - - - 114,581 57,267 10,120.013 0.177 2008 61,336 33,832 12,322 6,786 2,430 1,026 922 38 - - - - 118,692 57,356 9,195.940 0.160 2009 66,310 35,877 12,318 7,317 2,562 1,174 1,144 68 4 - - - 126,774 60,464 10,024.804 0.166 2010 74,218 33,873 11,670 6,356 2,231 946 832 42 3 - - - 130,171 55,953 8,631.384 0.154 2011 78,090 36,745 12,119 6,307 2,226 1,008 837 23 - - - - 137,355 59,265 8,771.326 0.148 2012 79,222 36,990 11,943 5,904 1,962 774 672 37 - - - - 137,504 58,282 8,035.393 0.138 2013 76,261 32,326 10,166 5,231 1,680 674 430 18 - - - - 126,786 50,525 6,759.547 0.134 2014 73,390 32,917 10,285 5,212 1,685 695 589 58 - - - - 124,831 51,441 7,124.519 0.138 2015 71,980 31,806 10,208 5,034 1,686 708 647 27 3 - - - 122,099 50,119 7,019.088 0.140 2016 67,685 29,063 8,736 4,196 1,236 429 332 16 1 - - - 111,694 44,009 5,365.709 0.122 2017 62,882 29,448 9,210 4,695 1,666 671 532 11 - - - - 109,115 46,233 6,416.548 0.139 2018 59,356 28,012 8,146 4,205 1,488 663 462 20 2 - - - 102,354 42,998 5,829.471 0.136 2019 55,718 25,322 7,167 3,798 1,272 554 402 4 - - - - 94,237 38,519 5,080.795 0.132

• These doses are annual TEDE doses.

• • Summary of reports submitted in accordance with 10 CFR 20.2206 by BWRs and PWRs that had been in commercial operation for at least 1 full year as of December 31 of each of the indicated years.

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

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 individuals per BWR have been higher than those for PWRs for all years depicted. BWRs generally have higher collective doses because the steam produced directly from the reactor is used to drive turbines to produce electricity, which results in radioactivity being present in both the reactor and turbine systems. PWR systems are designed to keep the radioactivity within the reactor vessel and primary system and not in the turbine systems.

In 2019, the average collective dose per reactor for BWRs was 105 person-rem and the average collective dose per reactor for PWRs was 27 person-rem. In comparison with the 2018 values, the average collective dose per reactor for BWRs decreased by 5 percent and the average collective dose per reactor for PWRs decreased by 20 percent which was significantly different from the 5-year average. The average collective dose per reactor for LWRs decreased by 11 percent from 2018 which was significantly different from the 5-year trend. This is the tenth year in a row that the average collective dose per reactor for LWRs has been below 90 person-rem. The overall decreasing trend in average reactor collective doses since 1994 indicates that licensees are continuing to successfully implement as low as is reasonably achievable (ALARA) dose reduction processes at their facilities. Further impacting this decreasing trend, in 2019, eleven LWRs reported substantial decreases (> 75 percent) in collective dose due to fewer outages. In 2019, the number of individuals with a measurable dose per reactor decreased to 909 for BWRs and decreased to 383 for PWRs. The decrease in PWR was significantly different from the 5-year average.

Figures 4.2 and 4.3 are plots of most of the other information that is presented in Tables 4.1, 4.2, and 4.3. Table 4.3 shows that the net electricity generated at LWRs decreased slightly from 91,836 MW-yr in 2018 to 91,638 MW-yr in 2019, while the number of operating reactors decreased to 96 in 2019. The net electricity generated in 2019 was not significantly different than the 5-year trend. Table 4.3 also shows that the value for the total collective dose for all LWRs decreased by 13 percent to 5,081 person-rem in 2019 from 5,829 person-rem in 2018, and was a statistically significant decrease from the 5-year trend. Table 4.3 shows that the average measurable dose per individual decreased slightly to 0.09 rem (not adjusted for transient individuals). The average collective dose for all LWRs per MW-yr was not significantly lower than the 5-year average.

The decrease seen in dose trends since 1994 may be attributed to several factors. For example, utilities have completed the tasks initiated as a result of the lessons learned from the 1979 TMI accident, and they are increasing efforts to avoid and reduce exposure. 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 exposure control processes, techniques, and procedures.

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Average Collective Dose per Reactor 400 BWR PWR Collective Dose per Reactor (person-rem) 350 LWR 300 250 200 150 100 50 0

Year Average Number of Individuals with Measurable Dose per Reactor 1,600 BWR PWR 1,400 LWR 1,200 Individuals per Reactor 1,000 800 600 400 200 0

Year Figure 4.1 Average Collective Dose per Reactor and Average Number of Individuals with Measurable Dose per Reactor 1994-2019 4-10

Number of Operating Reactors 130 BWR 120 PWR 110 Number of Operating Reactors 100 96 90 80 32 70 60 50 40 30 64 20 10 0

Year Electricity Generated*

110 BWR 100 PWR LWR 90 Megawatt-Years (Thousands) 80 70 60 50 40 30 20 10 0

Year

• Gross electricity is shown for 1994-1996, net electricity is shown for 1997-2019.

Figure 4.2 Number of Operating Reactors and Electricity Generated 1994-2019 4-11

Average Measurable Dose per Individual*

0.5 BWR PWR LWR 0.4 Average Measurable Dose (rem) 0.3 0.2 0.1 0.0 Year Collective Dose per Megawatt-Year**

0.7 BWR PWR Collective Dose (person-rem) per MW-yr 0.6 LWR 0.5 0.4 0.3 0.2 0.1 0.0 Year

• Not adjusted for transient workers. See Section 5.

• • Gross electricity is shown for 1994-1996, net electricity is shown for 1997-2019.

Figure 4.3 Average Measurable Dose per Individual and Collective Dose per Megawatt-Year 1994-2019 4-12

To further assist in the identification of any trends that might exist, Figures 4.4a and 4.4b display the average and median values of the collective dose per reactor for BWRs and for PWRs for the years 1994 through 2019. The median values are included here for statistical completeness and are not used in other sections of this report. 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.

Figure 4.4a Average, Median, and Extreme Values of the Collective Dose per BWR Reactor 1994-2019 4-13

Figure 4.4b Average, Median, and Extreme Values of the Collective Dose per PWR Reactor 1994-2019 The rectangles indicate the range of values of the collective dose exhibited by those plants ranked in the 25th through the 75th percentiles. Figure 4.4a shows that the median collective dose for BWRs increased from 89 person-rem in 2018 to 101 person-rem in 2019, but this change was not significant. The median collective dose for PWRs decreased to 27 person-rem in 2019 and was not significantly lower than the 5-year median of 30 person-rem. Figure 4.4a and Figure 4.4b show that, in 2019, 50 percent of the BWRs reported collective doses between 71 and 4-14

121 person-rem, while 50 percent of the PWRs reported collective doses between 18 and 37 person-rem. The middle 50 percent of BWRs and PWRs in Figures 4.4a and 4.4b are the reactors between the 25 percent and 75 percent dose ranges. These values are based on annual collective dose values, not the 3-year rolling average that is presented in Section 4.5. Nearly every year, the median collective dose is less than the average, which indicates that more of the reactors tend to be at lower collective doses than is reflected by the average. This is a result of the wide difference between the maximum and minimum annual collective doses at power plants and the fact that some plants accrue higher collective doses during refueling outages. The plants that have outages during the year (and thus higher collective doses) increase the value of the average collective dose, while the median (or middle-point of the doses) remains lower.

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 Process for inspection planning and in the Significance Determination Process.

Tables 4.5 and 4.6 list the sites that had been in commercial operation for at least 3 years as of December 31, 2019, and show the values of several parameters for each of the sites. These tables also give averages for the two types of reactors.

Based on the 96 reactor-years of operation accumulated over a 3-year period by the 32 BWRs listed, the average 3-year collective TEDE per reactor was found to be 113 person-rem, the average measurable TEDE per individual was 0.120 rem, and the average collective TEDE per MW-yr was 0.12 rem. For BWRs, only the average measurable TEDE per individual was statistically significant when compared to the 5-year average.

Based on the 192 reactor-years of operation accumulated over a 3-year period at the 64 PWRs listed, the average annual collective TEDE per reactor, average measurable TEDE per individual, and average collective TEDE per MW-yr were found to be 32 person-rem, 0.072 rem, and 0.03 rem, respectively. All three values were significantly lower in 2019 when compared to the 5-year trend.

In addition to the listings provided in Tables 4.5 and 4.6, the quartile ranking is used by the NRC as a factor in planning the number of inspection hours assigned per site. For this reason, Tables 4.7 and 4.8 are included in the 2019 annual report for BWRs and PWRs, respectively.

These tables show the plant name, 3-year collective TEDE per reactor year, the percent change in the 3-year average from the previous 3-year period, and the quartile ranking from the previous period if the ranking has changed.

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Table 4.5 Three-Year Totals and Averages Listed in Ascending Order of Collective TEDE per BWR 2017-2019 Three-year Collective Number of TEDE per Three-year Workers Average Average Reactor Year Collective with TEDE per TEDE per Reactor 2017-2019 TEDE per Site Measurable Worker Total MW-Yr Plant Name* Years (person-rem) (person-rem) TEDE (rem) MW-Yrs (rem)

DUANE ARNOLD 3 36.963 110.889 1,114 0.100 1,751.7 0.06 HATCH 1,2 6 55.816 334.894 3,577 0.094 4,891.7 0.07 COOPER STATION 3 59.213 177.640 1,681 0.106 2,225.6 0.08 DRESDEN 2,3 6 75.161 450.963 5,966 0.076 5,261.9 0.09 SUSQUEHANNA 1,2 6 75.646 453.873 4,036 0.112 7,113.1 0.06 LIMERICK 1,2 6 77.043 462.260 5,390 0.086 6,551.1 0.07 GRAND GULF 3 80.766 242.298 2,787 0.087 2,902.8 0.08 QUAD CITIES 1,2 6 90.049 540.296 5,462 0.099 5,288.6 0.10 PEACH BOTTOM 2,3 6 90.372 542.234 5,308 0.102 7,501.2 0.07 MONTICELLO 3 91.159 273.477 2,143 0.128 1,797.0 0.15 BRUNSWICK 1,2 6 103.671 622.023 4,964 0.125 5,104.3 0.12 NINE MILE POINT 1,2 6 113.060 678.360 4,644 0.146 5,363.4 0.13 HOPE CREEK 1 3 117.061 351.183 3,362 0.104 3,311.5 0.11 CLINTON 3 130.408 391.224 3,850 0.102 2,870.4 0.14 BROWNS FERRY 1,2,3 9 134.634 1,211.709 8,825 0.137 9,491.1 0.13 COLUMBIA GENERATING 3 138.009 414.027 3,607 0.115 3,048.4 0.14 FITZPATRICK 3 139.301 417.904 2,976 0.140 2,290.5 0.18 RIVER BEND 1 3 199.501 598.502 3,520 0.170 2,359.3 0.25 LASALLE 1,2 6 204.798 1,228.786 8,042 0.153 6,591.8 0.19 PERRY 3 219.544 658.632 2,888 0.228 3,390.9 0.19 FERMI 2 3 219.793 659.379 6,015 0.110 2,970.8 0.22 Totals and Averages 96 - 10,820.553 90,157 0.120 92,077.1 0.12 Average per Reactor-Year - 112.714 - 939 - 959.1 -

• Sites where not all reactors had completed 3 full years of commercial operations as of December 31, 2019, are not included.

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Table 4.6 Three-Year Totals and Averages Listed in Ascending Order of Collective TEDE per PWR 2017-2019 Three-year Collective TEDE Three-year Number of Average Average per Reactor Year Collective Workers with TEDE per TEDE per Reactor 2017-2019 TEDE per Site Measurable Worker Total MW-Yr Plant Name* Years (person-rem) (person-rem) TEDE (rem) MW-Yrs (rem)

OCONEE 1,2,3 9 13.960 125.639 2,822 0.045 7,417.5 0.02 PALO VERDE 1,2,3 9 15.139 136.253 3,150 0.043 10,886.6 0.01 PRAIRIE ISLAND 1,2 6 16.108 96.646 1,534 0.063 3,067.2 0.03 SEABROOK 3 21.231 63.693 1,055 0.060 3,533.9 0.02 DAVIS-BESSE 1 3 21.343 64.029 986 0.065 2,636.5 0.02 CALLAWAY 1 3 21.518 64.554 1,027 0.063 3,221.9 0.02 FARLEY 1,2 6 21.838 131.026 2,063 0.064 4,909.4 0.03 DIABLO CANYON 1,2 6 21.843 131.058 2,292 0.057 5,991.5 0.02 HARRIS 1 3 23.059 69.176 1,234 0.056 2,672.1 0.03 BYRON 1,2 6 24.887 149.323 2,588 0.058 6,771.9 0.02 GINNA 3 25.376 76.127 1,133 0.067 1,642.8 0.05 BEAVER VALLEY 1,2 6 25.654 153.924 2,222 0.069 5,185.1 0.03 WATTS BAR 1,2 6 26.268 157.609 2,685 0.059 5,686.7 0.03 BRAIDWOOD 1,2 6 26.554 159.321 2,510 0.063 6,794.5 0.02 CALVERT CLIFFS 1,2 6 27.504 165.023 2,398 0.069 5,149.8 0.03 VOGTLE 1,2 6 29.680 178.079 2,204 0.081 6,722.4 0.03 COOK 1,2 6 30.233 181.398 2,748 0.066 5,863.3 0.03 SOUTH TEXAS 1,2 6 30.327 181.962 1,999 0.091 7,350.1 0.02 CATAWBA 1,2 6 31.318 187.908 2,739 0.069 6,630.1 0.03 NORTH ANNA 1,2 6 32.836 197.017 2,311 0.085 5,416.5 0.04 POINT BEACH 1,2 6 34.199 205.192 1,804 0.114 3,404.0 0.06 SUMMER 1 3 34.705 104.116 1,750 0.059 2,571.7 0.04 COMANCHE PEAK 1,2 6 36.787 220.724 2,397 0.092 6,512.6 0.03 MILLSTONE 2,3 6 37.730 226.381 2,610 0.087 5,734.6 0.04 SURRY 1,2 6 37.992 227.950 2,665 0.086 4,773.9 0.05 ST. LUCIE 1,2 6 39.563 237.378 2,981 0.080 5,361.9 0.04 MCGUIRE 1,2 6 40.304 241.824 3,346 0.072 6,649.1 0.04 INDIAN POINT 2,3 6 40.393 242.360 5,132 0.047 5,510.2 0.04 WOLF CREEK 1 3 40.501 121.502 2,211 0.055 3,319.6 0.04 TURKEY POINT 3,4 6 40.650 243.898 2,674 0.091 4,636.5 0.05 SEQUOYAH 1,2 6 40.785 244.711 3,044 0.080 6,163.9 0.04 ROBINSON 2 3 40.802 122.405 1,889 0.065 2,007.3 0.06 WATERFORD 3 3 43.879 131.638 1,923 0.068 3,003.7 0.04 SALEM 1,2 6 47.399 284.393 3,068 0.093 6,279.2 0.05 ARKANSAS 1,2 6 51.161 306.963 5,186 0.059 4,462.0 0.07 PALISADES 3 123.492 370.477 1,924 0.193 2,102.5 0.18 Totals and Averages 192 - 6,201.677 86,304 0.072 180,042.5 0.03 Average per Reactor-Year - 32.300 - 450 - 937.7 -

• Sites where not all reactors had completed 3 full years of commercial operation as of December 31, 2019, are not included.

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Table 4.7 Three-Year Collective TEDE per Reactor-Year for BWRs 2017-2019 Three-Year Coll. TEDE per Percent 2016-2018 Reactor Year Change From Quartile Plant Name 2017-2019 2016-2018 (if changed)

DUANE ARNOLD 36.963 -46% -

HATCH 1,2 55.816 -28% -

1st Quartile COOPER STATION 59.213 -50% 3 DRESDEN 2,3 75.161 16% -

SUSQUEHANNA 1,2 75.646 -17% 2 LIMERICK 1,2 77.043 7% -

GRAND GULF 80.766 -40% 4 2nd Quartile QUAD CITIES 1,2 90.049 13% 1 PEACH BOTTOM 2,3 90.372 -6% 3 MONTICELLO 91.159 58% 1 BRUNSWICK 1,2 103.671 10% -

< Average 112.714 NINE MILE POINT 1,2 113.060 -13% -

3rd Quartile HOPE CREEK 1 117.061 9% -

CLINTON 130.408 47% 2 BROWNS FERRY 1,2,3 134.634 -3% 4 COLUMBIA GENERATING 138.009 66% 2 FITZPATRICK 139.301 -1% -

4th Quartile RIVER BEND 1 199.501 45% -

LASALLE 1,2 204.798 -2% -

PERRY 219.544 67% 3 FERMI 2 219.793 2% -

Average per Reactor-Year 112.714 3% -

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Table 4.8 Three-Year Collective TEDE per Reactor-Year for PWRs 2017-2019 Three-Year Percent 2016-2018 Coll. TEDE per Change Quartile Reactor Year From (if Plant Name 2017-2019 2016-2018 changed)

OCONEE 1,2,3 13.960 -15% -

PALO VERDE 1,2,3 15.139 -15% -

PRAIRIE ISLAND 1,2 16.108 -20% -

1st Quartile SEABROOK 21.231 -1% -

DAVIS-BESSE 1 21.343 -63% 4 CALLAWAY 1 21.518 -12% -

FARLEY 1,2 21.838 3% -

DIABLO CANYON 1,2 21.843 11% -

HARRIS 1 23.059 -9% -

BYRON 1,2 24.887 -11% -

GINNA 25.376 0% -

BEAVER VALLEY 1,2 25.654 -11% -

2nd Quartile WATTS BAR 1,2 26.268 12% 1 BRAIDWOOD 1,2 26.554 -11% -

CALVERT CLIFFS 1,2 27.504 -14% -

VOGTLE 1,2 29.680 -4% -

COOK 1,2 30.233 -6% -

SOUTH TEXAS 1,2 30.327 15% -

CATAWBA 1,2 31.318 -4% -

< Average 32.300 NORTH ANNA 1,2 32.836 -11% -

POINT BEACH 1,2 34.199 9% 2 3rd Quartile SUMMER 1 34.705 2% -

COMANCHE PEAK 1,2 36.787 11% -

MILLSTONE 2,3 37.730 -7% -

SURRY 1,2 37.992 3% -

ST. LUCIE 1,2 39.563 -9% 4 MCGUIRE 1,2 40.304 -5% 4 INDIAN POINT 2,3 40.393 -8% -

WOLF CREEK 1 40.501 -27% -

TURKEY POINT 3,4 40.650 4% 3 4th Quartile SEQUOYAH 1,2 40.785 -11% -

ROBINSON 2 40.802 -2% 3 WATERFORD 3 43.879 102% 1 SALEM 1,2 47.399 2% -

ARKANSAS 1,2 51.161 -8% -

PALISADES 123.492 1% -

Average per Reactor-Year 32.300 -42%

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4.6 International Occupational Radiation Exposure In 1992, the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (NEA/OECD), with sponsorship from the International Atomic Energy Agency (IAEA), created the Information System on Occupational Exposure (ISOE) Program as an international forum for representatives from nuclear electric utilities and regulatory agencies to share dose reduction information, operational experience, and information to improve the optimization of radiological protection at commercial nuclear power plants. The ISOE database, ISOEDAT, includes occupational exposure information for 400 operating units and 80 units in cold-shutdown or some stage of decommissioning in 29 countries, covering about 90 percent of the world's operating commercial nuclear power reactors. One of the purposes of ISOEDAT is to allow a comparison of radiation protection effectiveness and trends among the participating countries and among the various types of commercial nuclear power reactors.

As part of the agencys international cooperative research program initiatives, the NRC joined the ISOE Program as a regulatory member in December 1994. The NRCs REIRS database is the U.S. system comparable with ISOEDAT on the global scale. Since joining the ISOE Program, the NRC has leveraged experience in data management and analysis of the REIRS database, as well as provided input to NEA/OECD and IAEA for streamlining certain ISOEDAT methods for capturing, maintaining, and displaying data.

Figures 4.5 and 4.6 show the average collective dose per reactor for both PWRs and BWRs for the United States and participating reactors from ISOEDAT. For PWRs, the international average collective dose per unit increased from 49 to 54 person-rem per reactor in 2019, while the U.S.

average decreased from 34 to 27 person-rem per reactor. The international average for BWRs remained the same at 26 person-rem per reactor in 2019, which is approximately 25 percent of the average for U.S. BWRs (105 person-rem per reactor).

It should be noted that the information from reactor sites in Japan has been affected by the Fukushima Daiichi event that occurred in 2011. Following the earthquake and tsunami at the Fukushima Daiichi and Daini reactor sites, all Japanese reactors were shut down to assess safety concerns. While these plants ceased power production, they were still officially counted as operational reactors. The collective dose at these sites decreased significantly as most operational activities were not required when the reactors were not producing power. Similarly, the collective dose data for German reactors in the ISOE database includes reactors that were shut down in 2011 by the German government following the Fukushima event. This resulted in a significant reduction in the average collective dose per reactor as operational activities ceased.

The decrease in the average collective dose per reactor from these two countries decreased the overall international averages for both types of reactors since 2011. Since the Japan data represent a large percent (30 percent of the total BWRs), the decrease in the average collective dose per BWR in Japan is the primary factor in the decrease for international BWRs since 2011 as can be seen in Figure 4.6.

The data were compiled from the ISOEDAT online database. The NEA publishes an annual report entitled Occupational Exposures at Nuclear Power Plants that is available on the ISOE Web site at www.isoe-network.net [Ref. 19].

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180 USA 160 International Average collective dose per PWR reactor 140 120 100 (person-rem) 80 60 40 20 0

Year Figure 4.5 Average Collective Dose per PWR Reactor 1995-2019 300 USA International Average collective dose per BWR reactor 250 200 (person-rem) 150 100 50 0

Year Figure 4.6 Average Collective Dose per BWR Reactor 1995-2019 4-21

4.7 Decontamination and Decommissioning of Commercial Nuclear Power Reactors The NRC regulates the decontamination and decommissioning (D&D) of commercial nuclear power reactors. The purpose of the NRC Decommissioning Program is to ensure that NRC-licensed sites are decommissioned in a safe, timely, and effective manner so that they can be returned to beneficial use and to ensure that stakeholders are informed and involved in the process, as appropriate.

The NRC Office of Nuclear Material Safety and Safeguards (NMSS) has project management responsibilities for decommissioning commercial nuclear power reactors. The NRCs commercial nuclear power reactor decommissioning activities include project management, technical review of licensee submittals in support of decommissioning, licensing amendments and exemptions in support of the progressive stages of decommissioning, inspections of decommissioning activities, support for the development of rulemaking guidance, public outreach efforts, international activities, and participation in industry conferences and workshops. The NMSS staff regularly coordinates with other offices on issues affecting all commercial nuclear power reactors, both operating and decommissioning, and specifically in regard to the ISFSIs at reactor sites undergoing decommissioning [Ref. 20].

Decommissioning Process The decommissioning process begins when a licensee decides to permanently cease operations.

The major steps that comprise the commercial nuclear power reactor decommissioning process are notification of cessation of operations; submittal and review of the post-shutdown decommissioning activities report (PSDAR); submittal, review, and approval of the license termination plan (LTP); implementation of the LTP; and completion of decommissioning. The flowchart in Figure 4.7 illustrates the D&D process.

Notification When a licensee has decided to permanently cease operations, it is required to submit a written notification to the NRC. In addition, the licensee is required to notify the NRC in writing once fuel has been permanently removed from the reactor vessel.

Post-Shutdown Decommissioning Activities Report Within 2 years of cessation of operations, the licensee must submit a PSDAR to the NRC and a copy to the affected State(s). The PSDAR must include a description and schedule for the planned decommissioning activities, an estimate of the expected costs, and a discussion of the means for concluding that the environmental impacts associated with site-specific decommissioning activities will be bounded by appropriate, previously issued environmental impact statements. The NRC will provide notice of receipt of the PSDAR in the Federal Register and make the PSDAR available for public comment. In addition, the NRC will hold a public meeting in the vicinity of the licensees facility to discuss the PSDAR.

License Termination Plan Each commercial nuclear power reactor licensee must submit an application for termination of its license. An LTP must be submitted at least 2 years before the license termination date. The NRC and licensee hold pre-submittal meetings to agree on the format and content of the LTP. These 4-22

meetings are intended to improve the efficiency of the LTP development and review process. The LTP must include the following: a site characterization; the identification of remaining dismantlement activities; plans for site remediation; detailed plans for the final radiation survey; a description of the end use of the site, if restricted; an updated site-specific estimate of remaining decommissioning costs; and a supplement to the environmental report describing any new information or significant environmental change associated with the licensees proposed termination activities. In addition, the licensee must demonstrate that it will meet the applicable requirements of the License Termination Rule in 10 CFR Part 20, Subpart E, Radiological Criteria for License Termination.

The NRC will provide notice of receipt of the LTP in the Federal Register and make the LTP available for public comment. In addition, the NRC will hold a public meeting in the vicinity of the licensees facility to discuss the LTP and the LTP review process.

Implementation of the License Termination Plan After approval of the LTP, the licensee or responsible party must complete decommissioning in accordance with the approved LTP. The NRC staff will periodically inspect the decommissioning activities at the site to ensure compliance with the LTP. These inspections will normally include in-process and confirmatory radiological surveys.

Decommissioning must be completed within 60 years of permanent cessation of operations, unless otherwise approved by the NRC.

Completion of Decommissioning At the conclusion of decommissioning activities, the licensee will submit a final status survey report (FSSR), which identifies the final radiological conditions of the site and requests that the NRC either (1) terminate the 10 CFR Part 50 license, or (2) reduce the 10 CFR Part 50 license boundary to the footprint of the ISFSI. For decommissioning commercial nuclear power reactors with no ISFSI or an ISFSI holding a specific license under 10 CFR Part 72, completion of reactor decommissioning will result in the termination of the 10 CFR Part 50 license. The NRC will approve the FSSR and the licensees request if it determines that the licensee has met both of the following conditions: the remaining dismantlement has been performed in accordance with the approved LTP, and the final radiation survey and associated documentation demonstrate that the facility and site are suitable for release in accordance with the License Termination Rule.

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4-24 Figure 4.7 D&D Process Flowchart

Status of Decommissioning Activities at Commercial Nuclear Power Reactors While 96 commercial nuclear power reactors are currently in operation, several shutdown power reactors have undergone the D&D process. As more commercial nuclear power reactors permanently shut down, either because they have reached the end of their operating license or shut down for other reasons, there will be a commensurate increase in activities involving radiation exposure related to D&D. For this reason, there is an increased need to provide further information on plants undergoing D&D.

Appendix B contains a list of the plants that are no longer in commercial operation, along with the dose distribution and collective dose for these plants. It should be noted that these plants may be in different stages of D&D, so that a comparison of the dose at one plant versus another would not be meaningful. In addition, Appendix B lists the plant units that are no longer in commercial operation but report along with other units at the site. Under the licensing conditions and reporting requirements, it is permissible to report this information together in one report. Table 4.9 lists the plants that have ceased operation and have changed operational status as of the date shown

[Ref. 21]. In addition, Appendix E provides descriptions of the decommissioning activities currently underway at these commercial nuclear power reactors, as well as the total collective TEDE for each plant, based on available data through 2019.

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Table 4.9 Plants No Longer in Operation 2019 Date of First License Commercial Ceased Termination Plan PSDAR Completion of Plant Name Operation Operations Approved by NRC Submitted Plant Status Decommissioning CRYSTAL RIVER 3 12/1/1976 2/2013 TBD 12/2013 SAFSTOR 2074 DRESDEN 1 8/1/1960 10/1978 TBD 6/1998 SAFSTOR 2036 FERMI 1 5/10/1963 9/1972 TBD 4/1998 SAFSTOR 2032 FORT CALHOUN 6/20/1974 10/2016 TBD 3/2017 SAFSTOR 2065 HUMBOLDT BAY 3 8/1/1963 7/1976 2012 2/1998 DECON 2020 INDIAN POINT 1 3/26/1962 10/1974 TBD 1/1996 SAFSTOR 2034 KEWAUNEE 12/1/1973 5/2013 TBD 2/2013 SAFSTOR 2073 LACROSSE 11/1/1969 4/1987 TBD 5/1991 DECON 2020 MILLSTONE 1 12/28/1970 7/1998 TBD 6/1999 SAFSTOR 2056 OYSTER CREEK 12/1/1969 9/2018 TBD 5/2018 DECON 2035 PEACH BOTTOM 1 6/1/1967 10/1974 TBD 6/1998 SAFSTOR 2034 PILGRIM 1 12/1/1972 5/2019 TBD 11/2018 SAFSTOR 2080 SAN ONOFRE 1 1/1/1968 11/1992 TBD 12/1998 SAFSTOR 2032 SAN ONOFRE 2 1/1/1983 6/2013 TBD 9/2014 DECON 2032 SAN ONOFRE 3 1/1/1984 6/2013 TBD 9/2014 DECON 2032 THREE MILE ISLAND 1 9/2/1974 9/2019 TBD 4/2019 SAFSTOR 2079 THREE MILE ISLAND 2 12/30/1978 3/1979 TBD TBD SAFSTOR 2053 VERMONT YANKEE 11/30/1972 12/2014 TBD 12/2014 DECON 2030 ZION 1 12/31/1973 2/1997 TBD 2/2000 DECON 2020 ZION 2 9/17/1974 9/1996 TBD 2/2000 DECON 2020 DECOMMISSIONING COMPLETED BIG ROCK POINT 3/29/1963 8/1997 TBD 9/1997 ISFSI only 2007 HADDAM NECK 12/27/1974 12/1996 TBD 8/1997 ISFSI only 2007 MAINE YANKEE 6/29/1973 8/1997 TBD 8/1997 ISFSI only 2005 RANCHO SECO 4/17/1975 6/1989 TBD 3/1997 ISFSI only 2009 TROJAN 5/20/1976 11/1992 2/2001 8/1995 ISFSI only 2004 YANKEE ROWE 12/24/1963 10/1991 TBD - ISFSI only 2007 NOTE: Information regarding the latest decommissioning status of plants listed in this table can be found in Status of the Decommissioning Program: 2019 Annual Report from the NRCs public library under ADAMS Accession No. ML19282A393. Rows displayed in gray represent plants that have completed decommissioning [Refs. 21-21].

TBD = To Be Determined.

SAFSTOR = (often considered delayed DECON): a nuclear facility that is maintained and monitored in a condition that allows the radioactivity to decay; afterwards, it is dismantled.

DECON = (immediate dismantlement): soon after the nuclear facility closes, equipment, structures, and portions of the facility containing radioactive contaminants are removed or decontaminated to a level that permits release of the property and termination of the NRC license.

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5 TRANSIENT INDIVIDUALS AT NRC-LICENSED FACILITIES The following analysis examines the individuals who had more than one Form 5 dose record at more than one NRC-licensed facility during the monitoring year. These individuals are defined as transient because they worked at more than one facility during the monitoring year.

The term monitoring year is used here in accordance with the definition given in 10 CFR 20.1003, which defines a year as the period of time beginning in January used to determine compliance with the provisions of 10 CFR Part 20. 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.

Examination of the data reported for individuals 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 transients and the individual doses received by them can be determined from examining these data.

Additionally, the distribution of the doses received by transient individuals 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 commercial nuclear power reactors and all NRC licensees combined (one of the issues mentioned in Section 2).

Table 5.1 shows the actual distribution of transient individual doses as determined from the NRC Form 5 termination reports and compares it with the reported distribution of the doses of these individuals as they would have appeared in a summation of the annual reports submitted by each of the licensees.

In 2019, over 98 percent of the transient individuals were reported by commercial nuclear power reactors. For this reason, these data are shown separately in Table 5.1.

Table 5.1 illustrates the impact that the multiple reporting of these transient individuals had on the summation of the dose reports for 2019. Each licensee reports the radiation dose received by individuals monitored at its facility. Many of these individuals are monitored at more than one facility during the year. When these dose records are summed for all licensees, they appear to be separate individuals reported by each facility. If an individual visited five facilities during a year, this individual would appear in the summation to be five different people, with one dose record for each of the five facilities. When these dose records are summed per individual, these records appear as one person, with a total annual dose that accurately represents the dose received for the entire monitoring year. Thus, while the total collective dose would remain the same, the number of individuals, their dose distributions, and average doses would be affected by this multiple reporting.

For example, in 2019, Table 5.1 shows that the initial summation (see line [2] Transients, As Reported) of the Form 5 reports for reactor licensees indicated that no individuals received a dose greater than 2.0 rem. After accounting for those individuals who were reported more than once, the corrected distribution indicated that there were 3 transient individuals who received doses between 2.0 and 3.0 rem. One individual that was not transient received a dose above 2 rem bringing the total to 4. Correcting for the multiple counting of individuals also had a significant effect (see line [3] Transients, Actual) on the average measurable dose for these individuals. The corrected average measurable dose for transient individuals is twice as high as the value calculated by the summation of the Form 5 records. For all reporting licensees, the transient individuals represent 35 percent of the workforce that received a measurable dose. The correction 5-1

for the transient individuals increased the average measurable dose from 0.10 rem to 0.20 rem for the transient workforce for all licensees. It should be noted that the analysis of transient individuals does not include individuals who may have been exposed at facilities that are not required to report to the NRC (see Section 1), such as Agreement State licensees and DOE facilities.

One purpose of the REIRS database, which tracks occupational radiation exposures at NRC-licensed facilities, is to identify individuals who may have exceeded the occupational radiation dose limits because of multiple exposures at different facilities throughout the year. The REIRS database stores the radiation dose information for an individual by his/her unique identification number and identification type [Ref. 14, Section 1.5] and sums the dose for all facilities during the monitoring year. An individual exceeding the 5 rem per year regulatory limit (TEDE) would be identified in Table 5.1 in one of the dose ranges greater than 5 rem. In 2019, there were 83 unique individuals receiving doses between 2 to 3 rem, 21 individuals receiving between 3 to 4 rem, and 3 individuals receiving between 4 to 5 rem, as reported by NRC licensees to the REIRS database.

See Section 6 for more information on individuals who received exposures in excess of the NRC regulatory limits.

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Table 5.1 Effects of Transient Individuals on Annual Statistical Compilations 2019 Number of Individuals with TEDE in the Ranges (rem)*

Number Average No Total with Collective Meas.

Measurable Measurable 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Measurable TEDE TEDE License Category Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored TEDE (person-rem) (rem)

COMMERCIAL LIGHT-WATER REACTORS (1) Form 5 Summation 81,282 39,068 9,512 3,636 942 300 156 1 - - - - 134,897 53,615 5,080.795 0.09 (2) Transients, As Reported 32700 21472 5924 2272 581 178 90 - - - - - 63,217 30,517 3,630.988 0.12 (3) Transients, Actual 7,136 7,726 3,579 2,434 911 432 336 3 - - - - 22,557 15,421 3,630.988 0.24 5-3 Corrected Distribution 55,718 25,322 7,167 3,798 1,272 554 402 4 - - - - 94,237 38,519 5,080.795 0.13 (1-[2-3]) **

ALL LICENSEES (1) Form 5 Summation 83,954 42,353 10,634 4,571 1,429 564 631 83 21 3 - - 144,243 60,289 7,149.591 0.12 (2) Transients, As Reported 34,011 22,013 6,045 2,310 598 178 102 - - - - - 65,257 31,246 3,174.410 0.10 (3) Transients, Actual 7,391 7,932 3,669 2,477 938 433 353 3 - - - - 23,196 15,805 3,174.410 0.20 Corrected Distribution 57,334 28,272 8,258 4,738 1,769 819 882 86 21 3 - - 102,182 44,848 7,149.591 0.18 (1-[2-3]) **

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

• • The corrected distribution only applies to the number of individuals.

6 EXPOSURES TO PERSONNEL IN EXCESS OF REGULATORY LIMITS 6.1 Reporting Categories Doses in excess of regulatory limits are sometimes referred to as overexposures. The phrase doses in excess of regulatory limits is preferred to overexposures because the latter suggests that an individual has been subjected to an unacceptable biological risk, which may or may not be the case.

Regulations in 10 CFR 20.2202 and 10 CFR 20.2203 require that all licensees submit reports of all incidents involving personnel radiation doses that exceed certain levels, thus providing for investigations and corrective actions as necessary. Based on the magnitude of the dose, the occurrence may be placed into one of three categories as follows:

1. Category A 10 CFR 20.2202(a)(1) a TEDE to any individual of 25 rem or more, a lens 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 and the U.S.

Congress is notified annually through the U.S. NRC Abnormal Occurrence Report.

2. Category B 10 CFR 20.2202(b)(1) in a 24-hour period, the Commission must be notified of the following events: a TEDE to any individual exceeding 5 rem, a lens dose equivalent exceeding 15 rem, or a shallow dose equivalent to the skin or extremities exceeding 50 rem.

3. Category C 10 CFR 20.2203 in addition to the notification required by 10 CFR 20.2202 (Category A or B events), each licensee must submit a written report within 30 days after learning of any of the following occurrences:

a. any incident for which notification is required by 10 CFR 20.2202; or

b. doses that exceed the limits in §20.1201, §20.1207, §20.1208, or §20.1301 (for adults, minors, the embryo/fetus of a declared pregnant woman, and the public, respectively) or any applicable limit in the license; or

c. 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 10 CFR Part 20 or in the license (whether or not involving a dose of any individual in excess of the limits in §20.1301); or

d. for licensees subject to the provisions of the U.S. Environmental Protection Agencys generally applicable environmental radiation standards in 40 CFR Part 190, levels of radiation or releases of radioactive material in excess of those standards or license conditions related to those standards.

Doses in excess of regulatory limits that are reported as either Category A, B, or C typically undergo a review and evaluation process by the licensee, NRC inspectors, and NRC Headquarters staff. Preliminary dose estimates submitted by licensees are often conservatively high and do not represent the final (legal) dose of record assigned for the event. It is, therefore, 6-1

not uncommon for a dose in excess of a regulatory limit event to be reassessed and the final assigned dose to be categorized as not having been in excess of a regulatory limit. In other cases, the exposure event may not be identified until a later date, such as during the next scheduled audit or inspection of the licensees event records.

6.2 Summary of Occupational Radiation Doses in Excess of NRC Regulatory Limits The exposure events summary presented here is for events that occurred in 2019. An event that has been reassessed and determined not to be a dose in excess of a regulatory limit 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.

It is important to note that this summary of events includes:

• occupational radiation doses in excess of the annual 5 rem regulatory limit;

• events at NRC-licensed facilities; and

• the dose of record assigned to an individual.

It does not include:

• medical events as defined in 10 CFR Part 35;

• doses in excess of the regulatory limits to the general public;

• Agreement State-licensed activities or DOE facilities; or

• 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 licensee.

In 2019, there were no Category A occurrences, Category B, or Category C occurrences reported under the licensed activities included in this report.

6.3 Summary of Annual Dose Distributions for Certain NRC Licensees Table 6.1 gives a summary of the annual occupational dose records reported to the NRC, as required by 10 CFR 20.2206, by certain categories of NRC licensees. Table 6.1 shows that for the past 11 years, the percentage of individuals with less than 2 rem has been greater than 99 percent.

6.4 Maximum Occupational Radiation Doses Below NRC Regulatory Limits Certain researchers have expressed an interest in a listing of the maximum doses received at NRC licensees that do not exceed the regulatory limits. This information allows for an examination of these doses and could possibly provide insights into where certain improvements could be made in the licensees radiation protection program. Table 6.2 shows the maximum doses for each dose category required to be reported to the NRC. In addition, the number of doses in certain dose ranges is shown to reflect the number of doses that approach NRC regulatory limits.

As shown in Table 6.2, 52 individuals exceed half of the TEDE dose limit, 5 individuals exceeded 6-2

75 percent of the TEDE dose limit, and 0 individuals exceeded 95 percent of the TEDE dose limit.

The other dose categories where individuals exceeded 50 percent of the dose limit were the shallow dose equivalent to the maximally exposed extremity (SDE-ME).

Table 6.1 Summary of Annual Dose Distributions for Certain* NRC Licensees 2009-2019 Total Number of Individuals with Dose (TEDE) ***

Monitored Individuals < 2 rem > 2 rem < 5 rem > 5 rem Year Reported Number Corrected Number **  % Number  % Number 2009 189,972 139,381 99.9% 181 100% -

2010 192,436 142,523 99.9% 185 100% -

2011 204,575 149,971 99.9% 199 100% -

2012 205,134 148,316 99.9% 207 100% -

2013 186,062 138,233 99.8% 142 100% -

2014 185,843 135,817 99.8% 224 100% -

2015 186,614 131,827 99.9% 133 99.9% 2 2016 164,984 121,129 99.9% 81 100% -

2017 166,526 118,715 99.9% 164 99.9% 2 2018 159,988 110,861 99.8% 188 99.9% 1 2019 144,243 102,182 99.9% 110 100.0% -

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

• • This column lists the actual number of persons who may have been counted more than once because they worked at more than one facility during the calendar year (see Section 5).

• • • Data for 2009-2019 are based on the distribution of individual doses after adjusting for the multiple counting of transient individuals (see Section 5).

Table 6.2 Maximum Occupational Doses for Each Exposure Category* 2019 Maximum Number of Number of Number of Number of Number of Annual Dose Max Dose Individuals with Individuals Individuals Individuals Individuals Number of Dose Dose Limit Reported Percent of Measurable >25% of the >50% of the >75% of the >95% of the Individuals >

Category** 10CFR20*** (rem) the Limit Dose Limit Limit Limit Limit Limit SDE-ME 50 rem 40.826 82% 45,891 54 8 1 - -

SDE-WB 50 rem 4.389 9% 50,974 - - - - -

LDE 15 rem 4.268 28% 50,027 6 - - - -

CEDE 0.905 2,046 CDE 7.567 2,051 DDE 4.255 50,721 TEDE 5 rem 4.255 85% 51,734 554 52 5 - -

TODE 50 rem 7.692 15% 51,743 - - - - -

• Only records reported by licensees required to report under 10 CFR 20.2206 are included. Numbers have been adjusted for the multiple reporting of transient individuals.

• • SDE-ME = shallow dose equivalent to the maximally exposed extremity SDE-WB= shallow dose equivalent to the whole body LDE = lens dose equivalent to the lens of the eye CEDE = committed effective dose equivalent CDE = committed dose equivalent DDE = deep dose equivalent TEDE = total effective dose equivalent TODE = total organ dose equivalent

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

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7 RADIATION PROTECTION EVALUATION DISCUSSION The purpose of the outcome evaluation of the Radiation Protection Program is to measure the effectiveness NRCs Radiation Protection Program as it pertains to as low is reasonably achievable (ALARA) regulations of 10 CFR 20.1101(b) for each of the five NRC-licensee categories. 1 The outcome evaluation was limited in scope in that the evaluation solely evaluated the radiation protection programs based upon the data pertaining to number of licensees reporting exposure, the number of individuals monitored, the collective dose, and exposure trends (i.e., average individual and measurable doses) across the five categories of licensees. The evaluation does not take into consideration other factors related to ALARA practices but solely relies on exposure data to make conclusions.

This section describes the evidence to assess the effectiveness of the NRCs ALARA regulations in 10 CFR Part 20, and the licensees implementation of ALARA regulations for each licensee category (10 CFR Parts 30, 31, 32, 33, 34, 36, 40, 50, 72, 73, 74 and 76).

7.1 Individual Licensee Category Results Sections 3 and 4 of the report provides the definition of data terms and methodologies used to evaluate the radiation exposure data reported for the five categories of licensees. Some of these terms used in the evaluation include, for each licensee category, the number of individuals monitored, the collective dose, and a discussion of the trends in that data.

7.1.1 Industrial Radiography Licensees As noted in Section 3.3.1, the industrial radiography licensee group data was broken into fixed location and temporary job sites subsets; however, the analyses were done for the overall licensee group. The data in Section 3.3.1 indicate that even though the number of individuals with measurable TEDE and collective TEDE were higher than the 5-year average these results were not statistically significant 2 in 2019. Additionally, the average measurable TEDE decreased to 0.53 rem (5.3 mSv) for 2019 but was not statistically different than the 5-year average of 0.57 rem (5.7 mSv). The results of the 2019 exposure data for industrial radiography licensees were statistically significant and validate the effectiveness of the NRCs ALARA regulations in 10 CFR Parts 20 and 34 and the licensees implementation of this regulation for this licensee category.

7.1.2 Manufacturing and Distribution Licensees As stated in Section 3.3.2, the manufacturing and distribution licensees include Broad-Type A ,

Broad-Type B, Other and nuclear pharmacies. For the manufacturing and distribution licensees, the number of individuals with a measurable dose increased by 12 percent and the collective.

TEDE increased by 8 percent. While the number of individuals with a measurable dose in 2019 was 24 percent more than the 5-year average of 646, the average measurable dose in 2019 (0.18 rem) was statistically lower than the 5year average of 0.22 rem. While the results of the 1 Commercial nuclear power reactors and test reactor facilities; industrial radiographers; fuel processors (including uranium enrichment facilities), fabricators, and reprocessors; manufacturing and distribution of byproduct material; independent spent fuel storage installations; facilities for land disposal of low-level waste; and geologic repositories for high-level waste. There are currently no NRC licensees involved in low-level waste disposal or geologic repositories for high-level waste.

2 See Section 2.2 for a discussion about statistical significance.

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2019 exposure data for manufacturing and distribution licensees were not statistically significant, the decrease in the average measurable dose is a strong indicator of the effectiveness of manufacturing and distribution licensee ALARA programs. The number of individuals monitored, and the measurable doses reported by manufacturing and distribution licenses increased in 2019 while keeping average measurable doses lower. This indicates that while production at these manufacturing and distribution licensee facilities appear to be rising these licensees are continuing to successfully implement ALARA dose reduction processes at their facilities.

7.1.3 Independent Spent Fuel Storage Installation Licensees As stated in Section 3.3.4, the majority of ISFSI facilities are located on site at commercial nuclear power reactors and the occupational dose information from these facilities are usually included with the dose information reported by the commercial nuclear power reactors and is not reported separately to the NRC. Since 2005, two ISFSI licensees reported dose information to the NRC. The ISFSI facilities saw the collective TEDE increase by 11 percent from 2018 to 2019, but it should be noted that the dose increase was relatively small (less than 0.2 person-rem) and was statistically insignificant. The effect of a slight increase in the collective TEDE and the increase in number of individuals with a measurable dose resulted in a slight (but not significantly different) decrease in the average measurable TEDE per individual which decreased to 0.07 rem. The average measurable dose was not significantly different from the 5-year average. This indicates that the ISFSI licensees are continuing to successfully implement ALARA dose reduction processes at their facilities.

7.1.4 Fuel Cycle Licensees As stated in Section 3.3.5, the fuel cycle facilities that are currently operational fall into three different categories: uranium enrichment, uranium conversion, and fuel fabrication. Fuel cycle licensees collective TEDE and DDE increased in 2019 by 9 percent and 19 percent, respectively, and the collective CEDE decreased by 2 percent from 2018. When compared to the 5-year average, the increases in collective TEDE and collective DDE were not statistically significant, whereas the decrease in collective CEDE was statistically significant. Since the 2011 Fukushima Daiichi event, demand for nuclear fuel has dropped while global supply overall has increased, resulting in decreased fuel production by one licensee. In addition, this same licensee suspended operations at the UF6 production plant in November 2017 which has remained in a ready-idle status since that time. The shift from production related activities to maintaining minimal operations is a major factor contributing to the reduction in collective TEDE in 2019. This indicates that while production at these fuel cycle licensee facilities is at lower rates these licensees are continuing to successfully implement ALARA dose reduction processes at their facilities.

7.1.5 Commercial Power Reactor Licensees As noted in Section 4, the average annual collective doses for both the PWR and BWR licensees decreased in 2019 and were lower than the 5-year average annual collective dose by 32 percent and 6 percent, respectively. While both the average annual collective doses per PWR and BWR are lower when compared to the 5-year average annual collective dose only the PWR value is statistically significant. The primary driver for the decrease in collective dose was the closure of Three Mile Island 1 (PWR) and Pilgrim 1 (BWR). Additionally, the overall decreasing trend in average reactor collective doses since 1994 indicates that licensees are continuing to successfully implement ALARA dose reduction processes at their facilities.

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The decrease seen in dose trends since 1994 may be attributed to several factors. For example, utilities have completed the tasks initiated as a result of the lessons learned from the 1979 TMI accident, and they are increasing efforts to avoid and reduce exposure. 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 exposure control processes, techniques, and procedures.

Finally, based on the 192 reactor-years of operation accumulated over a 3-year period at the 64 PWRs listed, the average annual collective TEDE per reactor, average measurable TEDE per individual, and average collective TEDE per MW-yr were found to be 32 person-rem, 0.072 rem, and 0.03 rem, respectively. All three values were significantly lower in 2019 when compared to the 5-year trend. The results of the 2019 exposure data for PWR licensees were statistically significant and validate the effectiveness of the NRCs ALARA regulations in 10 CFR Parts 20 and 50 and the licensees implementation of those regulations for this licensee category.

7.2 Collective Results As noted in Table 3.2, annual reports for 2019 were received from a total of 181 NRC licensees from the five categories included in this report. The summation of reports submitted by the 181 licensees indicated that 144,243 individuals were monitored, 60,289 of whom received a measurable dose. When adjusted for transient individuals, there were actually 102,182 unique individuals that were monitored, 44,848 (44 percent) of whom received a measurable dose (see Section 5). These doses are all below the annual occupational dose limit for adults of 5 rem and commensurate with the ALARA regulations of 10 CFR 20.1101(b).

As noted in Table 3.1, the collective dose incurred by these individuals was 7,150 person-rem (71,500 person-millisieverts [mSv]), which represents a 12 percent decrease from the 2018 value. Additionally, the 2019 collective dose is 14 percent lower than the 5-year average of 8,348 person-rem (2014 - 2018), which is a statistically significant change. 3 The decrease in collective dose in 2019 was due to decreases in two categories offsetting increases in the remaining three reporting categories as discussed in Sections 7.1.1 and 7.1.5. The increases or decreases for the remaining three categories were not statistically significant as noted in Sections 7.1.2 through 7.1.4.

Finally, one of the purposes of the REIRS database is to identify individuals who may have exceeded the occupational radiation dose limits because of multiple exposures at different facilities throughout the year. The REIRS database stores the radiation dose information for an individual by his/her unique identification number and identification type [Ref. 14] and sums the dose for all facilities during the monitoring year. An individual exceeding the 5 rem per year regulatory limit (TEDE) would be identified in Table 5.1 in one of the dose ranges greater than 5 rem. In 2019, there were 882 individuals (8E-03 percent) receiving dose between 1 to 2 rem, 86 individuals (8E-04 percent) receiving doses between 2 to 3 rem, 21 individuals (2E-04 percent) receiving between 3 to 4 rem, and 3 individuals (3E-05 percent) receiving between 4 to 5 rem, as reported by NRC licensees to the REIRS database. These low percentages when accompanied with the 57,334 individuals (56 percent) of whom received no measurable dose support the strong measure of effectiveness of the NRCs ALARA regulations and the licensees ALARA programs.

3 This report presents additional Statistical Comparisons in Section 2.2.

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7.3 Conclusions As noted in Section 1.3.2, the objective of the NRC Radiation Protection Program Outcome Evaluation was to assess the effectiveness NRCs as low as is reasonably achievable (ALARA) regulations of 10 CFR 20.1101(b) along with the licensees implementation of this regulation by reviewing the trends in of the occupational exposure data for each of the NRC-licensee categories.

The outcome evaluation fulfilled this objective by answering questions such as the following:

• How can the agency use radiation exposure data from NRC-licensed facilities to assess whether the NRCs radiation protection regulatory programs are achieving their intended outcomes?

• What do the trends in radiation exposure data at NRC licensed facilities suggest about the radiation protection programs effectiveness over time?

• Does the data suggest differences in the effectiveness across the agencys radiation protection programs?

• Will increased data use provide insights into potential performance measures or process improvements relating to risk-informed regulation?

With respect to the first question the occupational exposure data from the REIRS database can be used to glean insights with respect to the ALARA programs across each of the licensee categories and overall. The trends of the occupational exposure overall indicate that the 2019 collective occupational exposures are 14 percent lower than the 5-year average (2014 - 2018),

which is a statistically significant change validating the effectiveness of the Agencys regulatory programs and the licensees implementation for radiation protection. Additionally, the evaluation of the radiation exposure data for the various NRC-licensee categories validates that the radiation protection program meets the intended outcome of minimizing risk from occupational exposure to radiation for all licensee categories.

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8 REFERENCES

1. Monthly Operating Report Data, provided by the Institute of Nuclear Power Operations (INPO) and compiled by Idaho National Laboratorys Risk Assessment and Management Services Department under contract to the NRC.

2. U.S. Atomic Energy Commission, Nuclear Power Plant Operating Experience During 1973, USAEC Report 00EES004, December 1974.

3. U.S. Nuclear Regulatory Commission, Nuclear Power Plant Operating Experience 1974-1975, USNRC Report NUREG0227, April 1977.*

4. U.S. Nuclear Regulatory Commission, Nuclear Power Plant Operating Experience 1976, USNRC Report NUREG0366, December 1977.*

5. M. R. Beebe, Nuclear Power Plant Operating Experience1977, USNRC Report NUREG 0483, February 1979.*

6. U.S. Nuclear Regulatory Commission, Nuclear Power Plant Operating Experience 1978, USNRC Report NUREG0618, December 1979.*

7. U.S. Nuclear Regulatory Commission, Nuclear Power Plant Operating Experience 1979, USNRC Report NUREG/CR1496, May 1981.*

8. U.S. Nuclear Regulatory Commission, Nuclear Power Plant Operating Experience 1980, USNRC Report NUREG/CR2378, ORNL/NSIC191, October 1982.*

9. U.S. Nuclear Regulatory Commission, Nuclear Power Plant Operating Experience 1981, USNRC Report NUREG/CR3430, ORNL/NSIC215, Vol. 1, December 1983.*

10. U.S. Nuclear Regulatory Commission, Nuclear Power Plant Operating Experience 1982, USNRC Report NUREG/CR3430, ORNL/NSIC215, Vol. 2, January 1985.*

11. U.S. Nuclear Regulatory Commission, Foundations for Evidence-Based Policymaking Act of 2018: Interim Learning Agenda, Interim Capacity Assessment, and Annual Evaluation Plan, SECY-20-0067, July 27,2020. Available at Agencywide Documents Access and Management System (ADAMS) Accession No. ML20182A285.

12. U.S. Nuclear Regulatory Commission, Occupational Radiation Exposure at Agreement State-Licensed Materials Facilities, 1997-2010, USNRC Report NUREG-2118, Vol. 1, July 2012.

13. U.S. Nuclear Regulatory Commission, Consolidated Guidance about Materials Licenses, USNRC Report NUREG1556, Vol. 20, December 2000. *

• Report is available for purchase from the National Technical Information Service, Springfield, VA, 22161, and/or the Superintendent of Documents, U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328.

• Report is available for purchase from the National Technical Information Service, Springfield, VA, 22161, and/or the Superintendent of Documents, U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328.

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14. U.S. Nuclear Regulatory Commission, Instructions for Recording and Reporting Occupational Radiation Exposure Data, USNRC Regulatory Guide 8.7, Rev. 4, May 2018.

15. 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste.

July 18, 1990.

16. 10 CFR Part 70, Domestic Licensing of Special Nuclear Material, title 10, sec. 70. 2015.

17. International Commission on Radiological Protection Publication 30, Limits for Intakes of Radionuclides by Workers, Annals of the ICRP Volume 2 No 3/4, 1972.

18. International Commission on Radiological Protection Publication 68, Dose Coefficients for Intakes of Radionuclides by Workers, Annals of the ICRP Volume 24/4, December 1994.

19. ISOE Annual Report - 2018, Occupational Exposures at Nuclear Power Plants. Twenty-eighth Annual Report of the ISOE Programme, 2018. http://www.isoe-network.net/publications/pub-resources/pub-annual-reports.html

20. U.S. Nuclear Regulatory Commission, 2019-2020 Information Digest, USNRC Report NUREG-1350, Volume 30, August 2019, ADAMS Accession No. ML19242D326.

21. U.S. Nuclear Regulatory Commission, Division of Decommissioning, Uranium Recovery, and Waste Programs, Office of Nuclear Material Safety and Safeguards, Status of the Decommissioning Program, 2019 Annual Report, ADAMS Accession No. ML19282A393.

22. U.S. Nuclear Regulatory Commission, Locations of Power Reactor Sites Undergoing Decommissioning. Available at: https://www.nrc.gov/info-finder/decommissioning/power-reactor/- last reviewed/updated May 4, 2020.

23. https://www.nrc.gov/reading-rm/basic-ref/glossary.html - last reviewed/updated May 2020.

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APPENDIX A ANNUAL TEDE FOR NONREACTOR NRC LICENSEES AND OTHER FACILITIES REPORTING TO THE NRC 2019

ANNUAL TEDE FOR NONREACTOR NRC LICENSEES AND OTHER FACILITIES REPORTING TO THE NRC Table A1 Annual TEDE for Nonreactor NRC Licensees Number of Individuals with Whole Body Doses in the Ranges (rem)* Total Number Collective Average No Total with TEDE Meas.

PROGRAM CODE - Meas. Meas. 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Meas. (person- TEDE LICENSEE NAME LICENSE # Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose rem) (rem)

INDUSTRIAL RADIOGRAPHY FIXED LOCATION 03310 HARRISON STEEL CASTINGS CO. 13-02141-01 4 1 - - - - - - - - - - 5 1 0.050 0.050 METALTEK INTERNATIONAL 24-26136-01 - 3 - 1 - - - - - 1 - - 5 5 4.645 0.929 Total 2 4 4 0 1 0 0 0 0 0 1 0 0 10 6 4.695 0.783 INDUSTRIAL RADIOGRAPHY TEMPORARY JOB SITE 03320 ABB, INC. 04-24888-01 4 4 1 2 1 - - - - - - - 12 8 1.545 0.193 ACUREN INSPECTION, INC. 22-27593-01 31 27 13 40 33 19 19 - - - - - 182 151 80.170 0.531 ADVANCED CORROSION TECH & TRAINING 42-35135-02 1 1 3 2 2 1 - - - - - - 10 9 3.092 0.344 ADVEX CORPORATION 45-16452-01 2 4 - - - - - - - - - 6 4 0.187 0.047 ALASKA INDUSTRIAL X-RAY 50-16084-01 2 2 1 1 2 - 2 - - - - - 10 8 4.537 0.567 ALONSO & CARUS IRON WORKS, INC. 52-21350-01 1 3 - - - - - - - - - 4 3 0.136 0.045 A-1 AMERICAN ENGINEERING TESTING, INC. 22-20271-02 - 2 1 5 1 - - - - - - - 9 9 3.151 0.350 AMERICAN PIPING INSPECTION 35-35011-01 12 10 12 28 10 8 21 4 3 - - - 108 96 76.741 0.799 APPLUS RTD USA WEST 04-29076-02 29 45 13 18 19 14 44 2 - - - - 184 155 101.218 0.653 CALUMET TESTING SERVICES, INC. 13-16347-01 2 3 - - 1 6 - - - - - 12 10 8.312 0.831 CENTURY INSPECTION INC. 42-08456-02 17 9 7 10 5 - 2 1 - - - - 51 34 13.649 0.401 CONCRETE IMAGING, INC. 47-31316-01 - 1 2 1 1 - 1 - - - - - 6 6 3.006 0.501 CONSUMERS ENERGY LAB. SERVICES 21-08606-03 14 9 12 6 1 - - - - - - - 42 28 4.557 0.163 DBI, INC 15-29301-02 2 23 17 18 15 12 46 15 6 - - - 154 152 151.530 0.997 DIAMOND TECHNICAL SERVICES, INC. 37-31259-01 5 1 5 4 3 1 6 - - - - - 25 20 12.328 0.616 DOMINION NDT SERVICES, INC. 45-35118-01 - 2 1 1 3 1 3 - - - - - 11 11 7.948 0.723 ELECTRIC BOAT CORPORATION 06-01781-08 8 35 1 - - - - - - - - - 44 36 0.888 0.025 ENGINEERING & INSPECTIONS - HAWAII 53-27731-01 3 3 - 3 4 1 8 - - - - - 22 19 16.634 0.875 GENERAL TESTING & INSPECTION CO. 47-32191-01 - - 2 - - - - - - - - - 2 2 0.290 0.145 H & H X-RAY SERVICES, INC 17-19236-01 26 28 22 30 19 19 50 11 2 - - - 207 181 142.819 0.789 HIGH COUNTRY FABRICATION 49-29300-01 - 1 1 1 2 - - - - - - - 5 5 1.832 0.366 HIGH MOUNTAIN INSPECTION SERVICES 49-26808-02 1 10 8 14 12 8 28 9 5 1 - - 96 95 104.918 1.104 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5).

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

Table A1 Annual TEDE for Nonreactor NRC Licensees (continued)

Number of Individuals with Whole Body Doses in the Ranges (rem)* Total Number Collective Average No Total with TEDE Meas.

PROGRAM CODE - Meas. Meas. 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Meas. (person- TEDE LICENSEE NAME LICENSE # Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose rem) (rem)

INDUSTRIAL RADIOGRAPHY TEMPORARY JOB SITE 03320 (Continued)

HUNTINGTON INGALLS, INC. 45-09428-02 13 23 5 - - - - - - - - - 41 28 1.713 0.061 INTEGRITY TESTLAB 07-30791-01 4 13 8 7 3 5 5 1 - - - - 46 42 19.110 0.455 INTERTEK 17-29308-01 3 42 8 13 7 7 6 1 - 1 - - 88 85 31.452 0.370 J CORE DRILLING, INC. 45-30846-01 2 3 - - - - - - - - - 5 3 0.094 0.031 JAN X-RAY SERVICES, INC. 21-16560-01 98 53 79 96 61 31 40 3 - - - - 461 363 173.263 0.477 KAKIVIK ASSET MANAGEMENT 50-27667-01 56 98 40 68 40 27 22 - - - - - 351 295 110.350 0.374 LEHIGH TESTING LABORATORIES, INC. 07-01173-03 1 1 - - - - - - - - - - 2 1 0.002 0.002 LKS INSPECTION SERVICES, LLC 53-27795-01 1 2 - 1 - - - - - - - - 4 3 0.398 0.133 MAGNUM NIS 37-35141-01 - 8 4 4 2 3 6 1 - - - - 28 28 16.225 0.579 MARYLAND Q.C. LABORATORIES, INC. 19-28683-01 5 8 1 2 - - - - - - - - 16 11 1.205 0.110 MATERIALS INTEGRITY, INC. 50-27722-01 3 2 - - - - - - - - - - 5 2 0.070 0.035 METALS TESTING SERVICES, INC. 37-29406-02 4 8 8 6 9 3 11 2 - - - - 51 47 34.010 0.724 MID AMERICAN INSPECTION SERVICES 21-26060-01 - - 4 8 6 1 1 - - - - - 20 20 9.565 0.478 A-2 MISTRAS GROUP, INC. 12-16559-02 16 28 17 5 4 3 - - - - - - 73 57 10.294 0.181 NATIONAL INSPECTION SERVICE 17-35438-01 - - 1 3 1 5 15 6 1 - - - 32 32 47.135 1.473 NONDESTRUCTIVE & VISUAL INSPECTION 17-29410-01 - 3 10 7 5 11 18 9 2 - - - 65 65 69.849 1.075 PREMIER TECHNOLOGY, INC. 11-27746-01 4 - - - - - - - - - - - 4 - - -

PRIME NDT SERVICES, INC. 37-23370-01 25 50 55 36 28 4 9 1 - - - - 208 183 61.952 0.339 QCI TESTING LAB 11-29245-01 2 2 3 - 1 - - - - - - 8 6 2.035 0.339 QUALITY INSPECTION & TESTING 17-35492-01 - 7 8 8 8 8 7 - - - - - 46 46 25.368 0.551 QUALITY INSPECTION & TESTING 50-29038-01 - 1 2 1 - - 2 - - - - - 6 6 3.010 0.502 QUALITY TESTING SERVICES, INC. 24-32292-01 10 16 6 4 3 - - - - - - - 39 29 4.902 0.169 SCIENTIFIC TECHNICAL, INC. 45-24882-01 3 3 - - - - - - - - - - 6 3 0.054 0.018 SHAW PIPELINE SERVICES, INC. 35-23193-03 43 83 59 49 17 7 5 - - - - - 263 220 53.675 0.244 SOUTHERN SERVICES, INC. - AK 50-35494-01 3 4 3 - 1 - - - - - - - 11 8 1.167 0.146 ST. LOUIS TESTING LABORATORIES, INC 24-00188-02 4 2 7 3 2 4 2 2 - - - - 26 22 15.119 0.687 STANLEY PIPELINE INSPECTION LLC 35-35301-01 70 45 40 48 37 22 38 5 - - - - 305 235 132.748 0.565 SYSTEM ONE HOLDINGS, LLC. 37-27891-02 17 11 6 4 3 1 2 - - - - - 44 27 7.689 0.285 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5).

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

Table A1 Annual TEDE for Nonreactor NRC Licensees (continued)

Number of Individuals with Whole Body Doses in the Ranges (rem)* Total Number Collective Average No Total with TEDE Meas.

PROGRAM CODE - Meas. Meas. 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Meas. (person- TEDE LICENSEE NAME LICENSE # Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose rem) (rem)

INDUSTRIAL RADIOGRAPHY TEMPORARY JOB SITE 03320 (Continued)

TEAM INDUSTRIAL SERVICES, INC. 42-32219-01 18 62 29 50 19 13 10 2 - - - - 203 185 65.902 0.356 TECH CORR USA, LLC 42-29261-01 - 4 3 1 2 - 3 2 1 - - - 16 16 14.008 0.876 TERRACON CONSULTANTS 24-35241-01 - - 1 - 1 - - - - - - - 2 2 0.706 0.353 TESTING TECHNOLOGIES, INC. 45-25007-01 1 6 2 3 3 2 1 - - - - - 18 17 6.210 0.365 THERMAL ENGINEERING INTERNATIONAL 24-19500-01 3 1 - - - - - - - - - - 4 1 0.039 0.039 TUV RHEINLAND 37-32340-02 1 - 1 - 1 - 2 - - - - - 5 4 2.995 0.749 TVA ADMIN PROGRAM 41-06832-06 6 5 4 - - - - - - - - - 15 9 0.797 0.089 XCEL NDT LLC 15-35544-01 - - 2 - - - 1 - - - - - 3 3 1.114 0.371 Total 58 576 817 535 614 396 243 442 77 20 2 0 0 3722 3146 1,663.713 0.529 MANUFACTURING AND DISTRIBUTION - NUCLEAR PHARMACIES - 02500 ADVANCED ISOTOPES OF IDAHO 11-29216-01MD - 1 - 1 - - - - - - - - 2 2 0.383 0.192 CARDINAL HEALTH 34-29200-01MD 137 313 52 15 5 1 1 3 1 - - - 528 391 37.516 0.096 CARDINAL HEALTH 34-31473-02MD 1 11 1 - - - - - - - - - 13 12 0.613 0.051 A-3 GE HEALTHCARE - KENTWOOD 21-26707-01MD 12 7 1 - - - - - - - - - 20 8 0.337 0.042 GE HEALTHCARE - LIVONIA 21-24828-01MD 10 7 1 - - - - - - - - - 18 8 0.466 0.058 GE HEALTHCARE - ST. LOUIS/OVERLAND 24-32462-01MD 5 5 - - - - - - - - - - 10 5 0.089 0.018 JUBILANT RADIOPHARMA - ST. LOUIS 09-32781-01MD - 9 3 - - - - - - - - - 12 12 0.758 0.063 MID-AMERICA ISOTOPES, INC. 24-26241-01MD 28 - 2 2 - - - - - - - - 32 4 0.914 0.229 PHARMALOGIC MT, INC. 09-29398-01MD 4 19 1 - - - - - - - - - 24 20 0.449 0.022 PHARMALOGIC WY, INC. 49-27629-01MD 14 4 - - - - - - - - - - 18 4 0.063 0.016 RADIOPHARMACY OF INDIANAPOLIS 13-32637-01MD 21 - 3 2 1 - - - - - - - 27 6 1.886 0.314 RADIOPHARMACY, INC. 13-26246-01MD 26 4 2 2 - - - - - - - - 34 8 1.059 0.132 TRIAD ISOTOPES - MI 09-32781-02MD 2 15 4 - - - - - - - - - 21 19 1.015 0.053 TRIAD ISOTOPES 09-32781-04MD - 12 - - - - - - - - - - 12 12 0.272 0.023 Total 14 260 407 70 22 6 1 1 3 1 0 0 0 771 511 45.820 0.090 MANUFACTURING AND DISTRIBUTION - TYPE "A" BROAD - 03211 INTERNATIONAL ISOTOPES IDAHO, INC. 11-27680-01 1 17 2 6 2 1 9 2 - - - - 40 39 24.519 0.629 CURIUM US, LLC 24-04206-01 123 124 37 41 16 15 21 - - - - - 377 254 77.588 0.305 Total 2 124 141 39 47 18 16 30 2 0 0 0 0 417 293 102.107 0.348 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5).

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

APPENDIX A Table A1 Annual TEDE for Nonreactor NRC Licensees (continued)

Number of Individuals with Whole Body Doses in the Ranges (rem)* Total Number Collective Average No Total with TEDE Meas.

PROGRAM CODE - Meas. Meas. 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Meas. (person- TEDE LICENSEE NAME LICENSE # Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose rem) (rem)

INDEPENDENT SPENT FUEL STORAGE INSTALLATION - 23200 GENERAL ELECTRIC - MORRIS ISFSI SNM-2500 2 21 5 2 - - - - - - - - 30 28 1.939 0.069 PORTLAND GENERAL ELECTRIC CO. SNM-2509 49 - - - - - - - - - - - 49 - - -

Total 2 51 21 5 2 0 0 0 0 0 0 0 0 79 28 1.939 0.069 URANIUM HEXAFLUORIDE (UF6 ) PRODUCTION PLANTS - 11400 HONEYWELL INTERNATIONAL, INC. SUB-0526 31 122 8 5 - - - - - - - - 166 135 6.362 0.047 Total 1 31 122 8 5 0 0 0 0 0 0 0 0 166 135 6.362 0.047 A-4 FUEL CYCLE URANIUM ENRICHMENT PLANTS - 21200 LOUISIANA ENERGY SERVICES, INC. SNM-2010 54 24 24 3 - - - - - - - - 105 51 5.841 0.115 Total 1 54 24 24 3 0 0 0 0 0 0 0 0 105 51 5.841 0.115 FUEL CYCLE FUEL FABRICATION FACILITIES - 21210 BWXT NUCLEAR OPERATIONS GROUP, INC SNM-0042 43 216 39 7 3 - 1 - - - - - 309 266 17.149 0.064 FRAMATOME INC. SNM-1227 419 509 82 68 6 - - - - - - - 1,084 665 48.118 0.072 GLOBAL NUCLEAR FUEL - AMERICAS, LLC SNM-1097 210 332 134 46 1 1 - - - - - - 724 514 49.220 0.096 NUCLEAR FUEL SERVICES, INC. SNM-0124 714 515 32 - - - - - - - - - 1,261 547 9.869 0.018 WESTINGHOUSE ELECTRIC COMPANY SNM-1107 186 177 154 120 57 3 1 - - - - - 698 512 113.963 0.223 Total 5 1,572 1,749 441 241 67 4 2 0 0 0 0 0 4,076 2,504 238.319 0.095 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5).

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

APPENDIX A Table A2 Other Facilities Reporting to the NRC Number of Individuals with Whole Body Doses in the Ranges (rem)* Total Number Collective Average No Total with TEDE Meas.

PROGRAM CODE - Meas. Meas. 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Meas. (person- TEDE LICENSEE NAME LICENSE # Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose rem) (rem)

OTHER SERVICES - 03225 VEGA AMERICAS, INC. 34-00639-04 10 20 4 - 1 1 1 - - - - - 37 27 3.866 0.143 Total 1 10 20 4 0 1 1 1 0 0 0 0 0 37 27 3.866 0.143 MASTER MATERIALS - ISSUED TO GOVERNMENT AGENCIES - 03614 NAVY, DEPARTMENT OF THE 45-23645-01NP 74 139 4 2 - - - - - - - - 219 145 2.757 0.019 Total 1 74 139 4 2 0 0 0 0 0 0 0 0 219 145 2.757 0.019 RESEARCH AND DEVELOPMENT, OTHER - 03620 APS TECHNOLOGY 06-35157-01 5 2 - - - - - - - - - - 7 2 0.100 0.050 HEALTH & HUMAN SERVICES, DEPT. OF 19-07538-05 4 - - - - - - - - - - - 4 - - -

Total 1 9 2 0 0 0 0 0 0 0 0 0 0 11 2 0.000 0.000 A-5 PROGRAM CODE - 02120 MADISON MEMORIAL HOSPITAL 11-27358-01 - - 5 - - - - - - - - - 5 5 0.787 0.157 Total 1 0 0 5 0 0 0 0 0 0 0 0 0 5 5 0.787 -

WASTE DISPOSAL SERVICE PROCESSING AND/OR REPACKAGING - 03234 ENERGYSOLUTIONS 39-35044-01 30 23 3 - - - - - - - - - 56 26 1.114 0.043 Total 1 30 23 3 0 0 0 0 0 0 0 0 0 56 26 1.114 0.043 TEST REACTOR FACILITIES - 42140**

NAT'L INSTITUTE OF STANDARDS & TECH TR-5 23 119 19 3 1 - - - - - - - 165 142 8.669 0.061 Total 1 23 119 19 3 1 0 0 0 0 0 0 0 165 142 8.669 0.061 PROGRAM CODE - 42150 AEROTEST OPERATIONS, INC. R-98 7 - - - - - - - - - - - 7 - - -

Total 1 7 0 0 0 0 0 0 0 0 0 0 0 7 0 0.000 -

NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5).

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

• • Test reactor facilities are required to report to the NRC, but only two facilities report under this category and one of the facilities is in decommissioning.

APPENDIX A Table A2 Other Facilities Reporting to the NRC 2018 (continued)

Number of Individuals with Whole Body Doses in the Ranges (rem)* Total Number Collective Average No Total with TEDE Meas.

PROGRAM CODE - Meas. Meas. 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Meas. (person- TEDE LICENSEE NAME LICENSE # Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose rem) (rem)

LEAK TEST SERVICE ONLY - 03220 NATIONAL INSPECTION SERVICE 17-35438-01 - - - - 1 - 6 2 2 - - - 11 11 21.148 1.923 QUALITY INSPECTION & TESTING 17-35492-01 - 5 4 2 2 7 7 5 - - - - 32 32 32.855 1.027 Total 2 0 5 4 2 3 7 13 7 2 0 0 0 43 43 54 1.256 WASTE DISPOSAL SERVICE PROCESSING AND/OR REPACKAGING - 03234 A-6 ENERGYSOLUTIONS 39-35044-01 31 12 - - - - - - - - - - 43 12 0.212 0.018 Total 1 31 12 0 0 0 0 0 0 0 0 0 0 43 12 0.212 0.018 TEST REACTOR FACILITIES - 42140**

NAT'L INSTITUTE OF STANDARDS & TECH TR-5 27 121 17 7 2 - - - - - - - 174 147 11.284 0.077 Total 1 25 111 21 5 0 0 0 0 0 0 0 0 174 147 11.284 0.077 PROGRAM CODE - 42150 AEROTEST OPERATIONS, INC. R-98 5 3 - - - - - - - - - - 8 3 0.044 0.015 Total 1 5 3 0 0 0 0 0 0 0 0 0 0 8 3 0.044 0.015 NOTE: The data values shown bolded and in boxes represent the highest value in each category. These values have not been adjusted for the multiple counting of transient workers (see section 5).

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

• • Test reactor facilities are required to report to the NRC, but only two facilities report under this category and one of the facilities is in decommissioning.

APPENDIX B ANNUAL DOSES AT LICENSED NUCLEAR POWER FACILITIES 2019

ANNUAL DOSES AT LICENSED NUCLEAR POWER FACILITIES APPENDIX B Annual Doses* at Licensed Nuclear Power Facilities Number of Individuals with Annual Doses* in the Ranges (rem)** Total Number Collective No Total with TEDE Meas. Meas. 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Meas. per Site PLANT NAME TYPE Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose (person-rem)

ARKANSAS 1, 2 PWR 1,297 1,183 240 35 1 - - - - - - - 2,756 1,459 84.085 BEAVER VALLEY 1, 2 PWR 1,709 399 47 13 2 - - - - - - - 2,170 461 25.416 BRAIDWOOD 1, 2 PWR 2,058 500 31 1 - - - - - - - - 2,590 532 19.553 BROWNS FERRY 1, 2, 3 BWR 1,382 1,638 516 323 105 20 15 - - - - - 3,999 2,617 362.997 BRUNSWICK 1, 2 BWR 1,737 1,057 343 181 69 14 9 - - - - - 3,410 1,673 222.735 BYRON 1, 2 PWR 1,925 597 84 12 - - - - - - - - 2,618 693 36.322 CALLAWAY 1 PWR 1,246 348 51 24 7 5 1 - - - - - 1,682 436 37.630 CALVERT CLIFFS 1, 2 PWR 1,378 640 173 24 - - - - - - - - 2,215 837 59.246 CATAWBA 1, 2 PWR 1,687 671 164 47 4 - - - - - - - 2,573 886 68.370 CLINTON BWR 1,802 891 317 113 35 14 2 - - - - - 3,174 1,372 158.832 COLUMBIA GENERATING BWR 1,066 874 270 154 62 21 8 - - - - - 2,455 1,389 190.694 COMANCHE PEAK 1, 2 PWR 1,383 620 130 36 4 - - - - - - - 2,173 790 58.051 COOK 1, 2 PWR 2,352 809 206 49 7 - - - - - - - 3,423 1,071 82.888 COOPER STATION BWR 666 240 45 1 - - - - - - - - 952 286 14.463 B-1 DAVIS-BESSE 1 PWR 830 139 29 7 - - - - - - - - 1,005 175 11.405 DIABLO CANYON 1, 2 PWR 1,655 629 119 22 4 - - - - - - - 2,429 774 51.135 DRESDEN 2, 3 BWR 1,367 1,582 387 135 34 7 10 - - - - - 3,522 2,155 202.866 DUANE ARNOLD BWR 587 137 38 12 - - - - - - - - 774 187 15.569 FARLEY 1, 2 PWR 1,576 721 140 33 2 - - - - - - - 2,472 896 63.320 FERMI 2 BWR 550 1,219 141 49 7 1 - - - - - - 1,967 1,417 65.282 FITZPATRICK BWR 599 302 67 12 - - - - - - - - 980 381 24.160 GINNA PWR 777 54 3 - - - - - - - - - 834 57 2.023 GRAND GULF BWR 1,217 848 78 16 6 - - - - - - - 2,165 948 35.139 HARRIS 1 PWR 1,498 502 118 6 - - - - - - - - 2,124 626 37.223 HATCH 1, 2 BWR 1,944 878 198 69 8 1 - - - - - - 3,098 1,154 94.104 HOPE CREEK 1 BWR 1,198 902 231 156 40 16 11 - - - - - 2,554 1,356 169.220 INDIAN POINT 2, 3 PWR 856 1,414 117 20 1 - - - - - - - 2,408 1,552 51.414 LASALLE 1, 2 BWR 1,174 1,445 469 240 88 39 14 - - - - - 3,469 2,295 309.129 LIMERICK 1, 2 BWR 1,356 1,447 315 115 20 8 1 - - - - - 3,262 1,906 157.471 MCGUIRE 1, 2 PWR 1,696 707 130 18 3 - - - - - - - 2,554 858 54.230 MILLSTONE 2, 3 PWR 1,969 555 136 23 1 - - - - - - - 2,684 715 47.673 MONTICELLO BWR 942 704 200 94 40 7 9 1 - - - - 1,997 1,055 128.425 NINE MILE POINT 1, 2 BWR 1,497 898 267 127 32 10 4 - - - - - 2,835 1,338 151.719 NORTH ANNA 1, 2 PWR 2,598 587 152 64 21 7 6 - - - - - 3,435 837 95.288 NOTE: The data values shown bolded and in boxes represent the highest value in each category. Totals corrected for transients on page B-2.

• These doses are annual TEDE doses.

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

APPENDIX B Annual Doses* at Licensed Nuclear Power Facilities (continued)

Number of Individuals with Annual Doses* in the Ranges (rem)** Total Number Collective No Total with TEDE Meas. Meas. 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Meas. per Site PLANT NAME TYPE Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose (person-rem)

OCONEE 1, 2, 3 PWR 2,500 641 72 2 - - - - - - - - 3,215 715 31.137 PALISADES PWR 784 136 18 7 - - - - - - - - 945 161 10.051 PALO VERDE 1, 2, 3 PWR 2,973 833 88 15 1 - - - - - - - 3,910 937 41.262 PEACH BOTTOM 2, 3 BWR 1,372 1,254 350 139 21 3 - - - - - - 3,139 1,767 167.083 PERRY BWR 1,276 509 296 223 105 55 34 - - - - - 2,498 1,222 301.067 POINT BEACH 1, 2 PWR 760 290 154 69 16 4 - - - - - - 1,293 533 74.485 PRAIRIE ISLAND 1, 2 PWR 1,205 343 68 5 1 - - - - - - - 1,622 417 24.593 QUAD CITIES 1, 2 BWR 1,379 1,172 516 194 14 - - - - - - - 3,275 1,896 204.958 RIVER BEND 1 BWR 1,387 802 299 198 87 40 21 - - - - - 2,834 1,447 255.918 ROBINSON 2 PWR 1,020 46 2 - - - - - - - - - 1,068 48 1.668 SALEM 1, 2 PWR 708 534 137 93 24 9 6 - - - - - 1,511 803 100.110 B-2 SEABROOK PWR 847 69 - - - - - - - - - - 916 69 1.084 SEQUOYAH 1, 2 PWR 1,769 667 109 41 18 8 3 - - - - - 2,615 846 76.085 SOUTH TEXAS 1, 2 PWR 1,621 484 144 45 3 - - - - - - - 2,297 676 56.887 ST LUCIE 1, 2 PWR 1,354 576 111 40 2 - - - - - - - 2,083 729 53.336 SUMMER 1 PWR 1,097 124 9 2 - - - - - - - - 1,232 135 4.557 SURRY 1, 2 PWR 2,738 540 139 31 2 2 - - - - - - 3,452 714 52.101 SUSQUEHANNA 1, 2 BWR 1,872 786 300 115 30 6 2 - - - - - 3,111 1,239 141.078 TURKEY POINT 3, 4 PWR 1,240 605 231 60 7 2 - - - - - - 2,145 905 84.610 VOGTLE 1, 2 PWR 1,641 448 141 35 1 - - - - - - - 2,266 625 50.668 WATERFORD 3 PWR 1,438 735 129 59 7 1 - - - - - - 2,369 931 69.780 WATTS BAR 1, 2 PWR 1,942 686 139 7 - - - - - - - - 2,774 832 45.017 WOLF CREEK 1 PWR 785 651 108 25 - - - - - - - - 1,569 784 45.183 Totals BWRs (32 Units) BWR 26,370 19,585 5,643 2,666 803 262 140 1 0 0 0 0 55,470 29,100 3,372.909 Totals PWRs (64 Units) PWR 54,912 19,483 3,869 970 139 38 16 0 0 0 0 0 79,427 24,515 1,707.886 Total LWRs (96 Units) LWRs 81,282 39,068 9,512 3,636 942 300 156 1 0 0 0 0 134,897 53,615 5,080.795 Corrected for Transients LWRs 55,718 25,322 7,167 3,798 1,272 554 402 4 0 0 0 0 94,237 38,519 5,080.795

• These doses are annual TEDE doses.

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

Totals corrected for transients and include all LWRs in commercial operation for a full year.

APPENDIX B Annual Doses* at Licensed Nuclear Power Facilities (continued)

Number of Individuals with Annual Doses* in the Ranges (rem)** Total Number Collective No Total with TEDE Meas. Meas. 0.10- 0.25- 0.50- 0.75- 1.0- 2.0- 3.0- 4.0- 5.0- Number Meas. per Site PLANT NAME TYPE Exposure <0.10 0.25 0.50 0.75 1.0 2.0 3.0 4.0 5.0 6.0 >6.0 Monitored Dose (person-rem)

REACTORS NO LONGER IN COMMERCIAL OPERATION CRYSTAL RIVER 3 PWR 125 2 - - - - - - - - - - 127 2 0.022 FERMI 1 FBR 51 - - - - - - - - - - - 51 - -

FT CALHOUN PWR 471 86 12 8 1 3 - - - - - - 581 110 11.120 GE VALLECITOS VBWR 113 55 12 1 5 - - - - - - - 186 73 6.113 GE ESADA VALLECITOS EVESR No longer required to report.

HUMBOLDT BAY 3 BWR No longer required to report.

KEWAUNEE PWR 55 2 - - - - - - - - - - 57 2 0.021 LACROSSE BWR 85 - - - - - - - - - - - 85 - -

OYSTER CREEK BWR 383 82 18 9 2 5 7 - - - - - 506 123 21.886 PEACH BOTTOM 1 HTGR No longer required to report.

PILGRIM 1 BWR 557 314 50 3 - - - - - - - - 924 367 18.041 SAN ONOFRE 1, 2, 3 PWR 612 30 30 11 5 - - - - - - - 688 76 12.774 SAVANNAH, NUCLEAR SHIP NS No longer required to report.

B-3 THREE MILE ISLAND 1 PWR 723 177 11 1 - - - - - - - - 912 189 7.252 VERMONT YANKEE BWR 35 115 18 21 5 4 11 5 - - - - 214 179 45.432 ZION 1, 2 PWR 209 4 - - - - - - - - - - 213 4 0.123 Total Reporting*** 12 3,419 867 151 54 18 12 18 5 0 0 0 0 4,544 1,125 122.784 REACTORS NO LONGER IN COMMERCIAL OPERATION, REPORTED WITH OTHER UNITS DRESDEN 1 BWR Reported with Dresden 2, 3.

INDIAN POINT 1 PWR Reported with Indian Point 2, 3.

MILLSTONE 1 BWR Reported with Millstone 2, 3.

THREE MILE ISLAND 2 PWR Reported with Three Mile Island 1.

REACTORS NO LONGER IN COMMERCIAL OPERATION, DECOMMISSIONED BIG ROCK POINT BWR 27 - - - - - - - - - - - 27 - -

HADDAM NECK PWR No longer required to report.

MAINE YANKEE PWR 25 14 - - - - - - - - - - 25 14 0.188 TROJAN PWR Reported as ISFSI (See Appendix A, Portland General Electric Company).

YANKEE-ROWE PWR 31 7 - - - - - - - - - - 31 7 0.113 Total Reporting*** 3 83 21 0 0 0 0 0 0 0 0 0 0 83 21 0.301 NOTE: Totals corrected for transients on page B-2.

• These doses are annual TEDE doses.

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

• • • These numbers are for the reactors no longer in commercial operation that report their doses separately (i.e., do not report their doses with other units).

APPENDIX C PERSONNEL, DOSE, AND POWER GENERATION

SUMMARY

1969-2019 A discussion of the methods used to collect and calculate the information contained in this appendix is given in Sections 3.1 and 4.2.

PERSONNEL, DOSE, AND POWER GENERATION

SUMMARY

1969-2019 Total Collective Personnel Dose Average Total Collective Megawatt Unit with per Site Measurable Collective Personnel Dose Average Years Availability Measurable (person- Dose Dose/

Megawatt Unit with per Site Measurable Collective Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr ARKANSAS 1, 2 1975 588.0 76.5 147 21 0.14 0.04 Docket 50-313, 50-368; 1976 464.6 56.6 476 289 0.61 0.62 DPR-51; NPF-6 1977 610.3 76.8 601 256 0.43 0.42 1st com mercial operation 1978 627.2 77.5 722 189 0.26 0.30 12/74, 3/80 1979 397.0 55.3 1,321 369 0.28 0.93 Type - PWRs 1980 452.8 63.7 1,233 342 0.28 0.76 Capacity - 836, 988 MWe 1981 1,104.7 68.3 2,225 1,102 0.50 1.00 1982 905.4 58.6 1,608 803 0.50 0.89 1983 915.0 54.7 2,109 1,397 0.66 1.53 1984 1,289.1 77.4 1,742 806 0.46 0.63 1985 1,192.3 73.6 1,262 286 0.23 0.24 1986 1,070.3 66.9 2,135 1,141 0.53 1.07 1987 1,366.1 88.9 1,123 382 0.34 0.28 1988 1,070.3 69.4 2,421 1,387 0.57 1.30 1989 1,066.3 72.0 2,063 711 0.34 0.67 1990 1,351.9 84.2 2,493 762 0.31 0.56 1991 1,515.8 88.4 2,064 351 0.17 0.23 1992 1,352.1 77.4 3,114 876 0.28 0.65 1993 1,606.0 91.3 1,981 268 0.14 0.17 1994 1,662.8 93.6 1,361 172 0.13 0.10 1995 1,397.0 82.7 2,259 386 0.17 0.28 1996 1,596.0 89.5 1,441 203 0.14 0.13 1997 1,621.9 95.9 1,195 119 0.10 0.07 1998 1,494.6 88.1 1,249 166.599 0.13 0.11 1999 1,477.3 86.9 1,463 183.997 0.13 0.12 2000 1,329.2 79.5 1,977 242.326 0.12 0.18 2001 1,684.0 95.8 1,082 106.040 0.10 0.06 2002 1,659.0 91.8 1,581 265.337 0.17 0.16 2003 1,675.8 93.1 973 99.003 0.10 0.06 2004 1,759.5 95.0 1,227 106.172 0.09 0.06 2005 1,560.0 84.5 2,335 475.784 0.20 0.30 2006 1,739.8 95.0 1,184 143.296 0.12 0.08 2007 1,769.3 96.0 1,387 105.310 0.08 0.06 2008 1,614.8 89.7 1,791 196.047 0.11 0.12 2009 1,733.7 95.5 1,139 102.732 0.09 0.06 2010 1,716.6 93.7 1,388 99.376 0.07 0.06 2011 1,621.9 90.5 1,526 116.884 0.08 0.07 2012 1,764.5 96.2 931 43.908 0.05 0.02 2013 1,366.6 74.3 1,098 50.041 0.05 0.04 2014 1,654.6 92.3 1,372 71.561 0.05 0.04 2015 1,582.0 87.5 1,881 136.727 0.07 0.09 2016 1,535.7 84.0 1,674 111.105 0.07 0.07 2017 1,451.4 83.4 1,757 86.504 0.05 0.06 2018 1,456.8 81.8 1,970 136.374 0.07 0.09 2019 1,553.8 85.3 1,459 84.085 0.06 0.05 BEAVER VALLEY 1, 2 1977 355.6 57.0 331 87 0.26 0.24 Docket 50-334, 50-412; 1978 304.2 40.8 646 190 0.29 0.62 DPR-66; NPF-73 1979 221.0 40.0 704 132 0.19 0.60 1st commercial operation 1980 39.8 6.8 1,817 553 0.30 13.89 10/76, 11/87 1981 573.4 73.6 1,237 229 0.19 0.40 Type - PWRs 1982 326.7 41.6 1,755 599 0.34 1.83 Capacity - 908, 905 MWe 1983 561.2 68.2 1,485 772 0.52 1.38 1984 576.7 71.8 1,393 504 0.36 0.87 1985 717.7 91.9 619 60 0.10 0.08 1986 581.3 70.7 1,575 627 0.40 1.08 1987 684.1 83.8 1,282 210 0.16 0.31 1988 1,386.1 87.4 1,764 530 0.30 0.38 1989 1,017.4 69.6 2,349 1,378 0.59 1.35 1990 1,271.0 85.3 1,675 348 0.21 0.27 1991 1,267.5 78.6 1,689 495 0.29 0.39 1992 1,441.9 89.1 1,414 289 0.20 0.20 1993 1,157.9 73.1 2,087 621 0.30 0.54 1994 1,514.6 88.6 487 44 0.09 0.03 1995 1,389.2 83.1 1,536 453 0.29 0.33 C-1

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr BEAVER VALLEY 1, 2 1996 1,269.0 76.5 1,688 449 0.27 0.35 (continued) 1997 1,159.3 72.1 1,391 306 0.22 0.26 1998 523.1 33.5 700 59.311 0.08 0.11 1999 1,353.7 85.9 841 99.461 0.12 0.07 2000 1,378.7 87.3 1,730 337.867 0.20 0.25 2001 1,500.8 92.3 1,202 184.361 0.15 0.12 2002 1,548.0 95.4 1,048 90.479 0.09 0.06 2003 1,437.0 88.4 1,623 277.168 0.17 0.19 2004 1,593.1 96.3 1,270 156.509 0.12 0.10 2005 1,590.4 96.7 978 79.055 0.08 0.05 2006 1,385.6 84.0 2,174 370.146 0.17 0.27 2007 1,664.1 96.0 955 86.595 0.09 0.05 2008 1,670.2 94.4 991 83.394 0.08 0.05 2009 1,599.3 89.6 1,504 224.516 0.15 0.14 2010 1,714.2 95.6 750 49.983 0.07 0.03 2011 1,705.5 95.1 831 72.206 0.09 0.04 2012 1,622.6 90.4 1,272 125.166 0.10 0.08 2013 1,687.4 93.3 746 41.712 0.06 0.02 2014 1,684.6 92.5 907 62.951 0.07 0.04 2015 1,659.6 91.1 1,115 95.208 0.09 0.06 2016 1,737.4 94.8 687 44.146 0.06 0.03 2017 1,747.9 95.5 776 53.706 0.07 0.03 2018 1,672.8 93.0 985 74.802 0.08 0.04 2019 1,764.4 96.9 461 25.416 0.06 0.01 BIG ROCK POINT1 1969 48.1 --- 165 136 0.82 2.83 Docket 50-155; 1970 43.5 --- 290 194 0.67 4.46 DPR-6 1971 44.4 --- 260 184 0.71 4.14 1st commercial operation 3/63 1972 43.5 --- 195 181 0.93 4.16 Type - BWR 1973 50.9 --- 241 285 1.18 5.60 Capacity - (67) MWe 1974 40.7 70.3 281 276 0.98 6.78 1975 35.1 59.8 300 180 0.60 5.13 1976 29.5 50.1 488 289 0.59 9.80 1977 43.6 73.4 465 334 0.72 7.66 1978 48.5 77.9 285 175 0.61 3.61 1979 13.0 23.5 623 455 0.73 35.00 1980 48.9 79.0 599 354 0.59 7.24 1981 56.9 90.6 479 160 0.33 2.81 1982 43.6 70.8 521 328 0.63 7.52 1983 42.3 71.0 493 263 0.53 6.22 1984 50.3 78.6 297 155 0.52 3.08 1985 43.8 73.5 435 291 0.67 6.64 1986 61.0 95.5 202 84 0.42 1.38 1987 45.3 71.0 251 222 0.88 4.90 1988 46.1 72.8 303 170 0.56 3.69 1989 50.2 79.0 418 177 0.42 3.53 1990 51.3 77.2 351 232 0.66 4.52 1991 59.1 85.2 435 226 0.52 3.82 1992 32.7 54.5 496 277 0.56 8.47 1993 51.2 79.4 419 152 0.36 2.97 1994 49.5 75.3 310 119 0.38 2.40 1995 62.2 95.0 205 54 0.26 0.87 1996 41.5 76.5 1,688 449 0.27 0.35 1997 22.4 54.1 258 55 0.21 2.46 1998 0.0 0.0 432 104.130 0.24 ---

1999 0.0 0.0 285 86.577 0.30 ---

2000 0.0 0.0 226 89.271 0.40 ---

2001 0.0 0.0 167 47.556 0.28 ---

2002 0.0 0.0 170 43.538 0.26 ---

2003 0.0 0.0 336 121.045 0.36 ---

2004 0.0 0.0 227 57.599 0.25 ---

2005 0.0 0.0 223 20.227 0.09 ---

2006 0.0 0.0 27 0.382 0.01 ---

1 Big Rock Point ceased operations in August 1997 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-2

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr BIG ROCK POINT1 2007 0.0 0.0 0 0.000 --- ---

(continued) 2008 0.0 0.0 0 0.000 --- ---

2009 0.0 0.0 0 0.000 --- ---

BRAIDWOOD 1, 2 1989 1,381.8 75.4 1,460 296 0.20 0.21 Docket 50-456, 50-457; 1990 1,740.2 84.1 1,081 186 0.17 0.11 NPF-72, NPF-77 1991 1,377.2 68.9 1,641 550 0.34 0.40 1st commercial operation 1992 1,885.9 89.0 1,059 228 0.22 0.12 7/88, 10/88 1993 1,899.3 86.9 1,043 273 0.26 0.14 Type - PWRs 1994 1,666.1 77.2 1,237 298 0.24 0.18 Capacity - 1,166, 1,144 MWe 1995 1,914.7 85.4 1,134 236 0.21 0.12 1996 1,854.9 82.1 1,356 334 0.25 0.18 1997 1,863.3 85.4 1,693 321 0.19 0.17 1998 1,979.1 88.9 1,869 259.236 0.14 0.13 1999 2,161.6 95.8 1,153 145.976 0.13 0.07 2000 2,142.8 94.9 1,562 194.126 0.12 0.09 2001 2,186.4 95.8 881 100.570 0.11 0.05 2002 2,284.0 96.8 975 90.716 0.09 0.04 2003 2,279.9 95.6 1,572 244.860 0.16 0.11 2004 2,277.8 97.3 986 94.942 0.10 0.04 2005 2,253.7 96.6 926 88.084 0.10 0.04 2006 2,234.1 95.0 1,624 199.168 0.12 0.09 2007 2,244.0 96.0 1,258 98.040 0.08 0.04 2008 2,252.5 96.3 1,235 103.180 0.08 0.05 2009 2,195.0 93.8 1,397 142.066 0.10 0.06 2010 2,111.9 94.0 870 63.856 0.07 0.03 2011 2,257.5 96.8 1,071 70.165 0.07 0.03 2012 2,141.0 92.1 1,818 167.655 0.09 0.08 2013 2,244.2 96.2 633 31.847 0.05 0.01 2014 2,313.9 97.3 866 42.493 0.05 0.02 2015 2,250.0 94.9 986 52.468 0.05 0.02 2016 2,265.9 96.0 733 39.695 0.05 0.02 2017 2,281.4 96.4 1,052 78.668 0.07 0.03 2018 2,201.3 93.8 926 61.100 0.07 0.03 2019 2,311.8 97.9 532 19.553 0.04 0.01 BROWNS FERRY 12, 2, 3 1975 161.7 17.8 2,743 347 0.13 2.15 Docket 50-259, 50-260, 50-296; 1976 337.6 26.9 2,530 232 0.09 0.69 DPR-33, DPR-52, DPR-68 1977 1,327.5 73.7 1,985 876 0.44 0.66 1st commercial operation 1978 1,992.1 73.5 2,479 1,776 0.72 0.89 8/74, 3/75, 3/77 1979 2,393.0 79.1 2,869 1,593 0.56 0.67 Type - BWRs 1980 2,182.1 73.6 2,838 1,768 0.62 0.81 Capacity - 1,101, 1,104, 1981 2,132.9 69.5 3,497 2,398 0.69 1.12 1,105 MWe 1982 2,025.4 67.6 3,360 2,230 0.66 1.10 1983 1,641.0 54.3 3,410 3,375 0.99 2.06 1984 1,431.9 54.2 3,172 1,954 0.62 1.36 1985 368.2 11.9 2,854 1,164 0.41 3.16 1986 0.0 0.0 3,074 1,054 0.34 ---

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

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

1989 0.0 0.0 2,707 657 0.24 ---

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

1991 445.0 17.7 1,831 356 0.19 0.80 1992 979.9 32.2 2,670 519 0.19 0.53 1993 675.1 66.8 3,594 870 0.24 1.29 1994 860.2 83.4 3,362 861 0.26 1.00 1995 1,165.8 98.6 2,567 413 0.16 0.35 1996 1,972.8 93.0 1,904 389 0.20 0.20 1997 1,928.8 90.2 2,268 522 0.23 0.27 1998 1,961.9 87.7 1,612 367.716 0.23 0.19 1999 2,091.0 85.1 1,741 446.941 0.26 0.21 1

Big Rock Point ceased operations in August 1997 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

2 All three Browns Ferry units were placed on administrative hold in 1985. Units 2 and 3 were restarted in 1991 and 1995, respectively. Browns Ferry Unit 1 was restarted during 2007.

C-3

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr BROWNS FERRY 12, 2, 3 2000 2,143.8 97.1 1,657 333.215 0.20 0.16 (continued) 2001 2,074.0 90.7 1,525 293.879 0.19 0.14 2002 2,069.0 95.4 1,977 357.573 0.18 0.17 2003 2,014.5 93.6 2,608 602.535 0.23 0.30 2004 2,104.7 95.5 3,242 672.714 0.21 0.32 2005 2,044.2 94.3 3,743 636.282 0.17 0.31 2006 2,040.1 94.0 3,618 641.154 0.18 0.31 2007 2,420.2 90.0 3,027 554.314 0.18 0.23 2008 2,837.4 88.5 2,633 482.127 0.18 0.17 2009 2,933.1 91.2 2,188 348.257 0.16 0.12 2010 2,828.0 92.3 2,825 556.749 0.20 0.20 2011 2,845.8 87.9 2,079 296.642 0.14 0.10 2012 2,969.2 91.2 3,139 464.325 0.15 0.16 2013 3,050.0 93.5 2,543 382.609 0.15 0.13 2014 3,052.3 94.0 2,401 389.854 0.16 0.13 2015 3,158.6 96.4 2,282 288.063 0.13 0.09 2016 2,992.6 93.3 3,077 404.585 0.13 0.14 2017 3,179.0 96.9 2,819 350.062 0.12 0.11 2018 2,930.8 90.5 3,389 498.650 0.15 0.17 2019 3,381.3 93.8 2,617 362.997 0.14 0.11 BRUNSWICK 1, 2 1976 297.2 56.0 1,265 326 0.26 1.10 Docket 50-324, 50-325; 1977 291.1 55.7 1,512 1,120 0.74 3.85 DPR-62, DPR-71 1978 1,173.1 83.7 1,458 1,004 0.69 0.86 1st commercial operation 1979 810.0 60.1 2,891 2,602 0.90 3.21 3/77, 11/75 1980 687.2 52.2 3,788 3,870 1.02 5.63 Type - BWRs 1981 925.2 56.9 3,854 2,638 0.68 2.85 Capacity - 938, 932 MWe 1982 540.3 50.3 4,957 3,792 0.76 7.02 1983 636.7 44.3 5,602 3,475 0.62 5.46 1984 761.3 51.5 5,046 3,260 0.65 4.28 1985 822.2 58.4 4,057 2,804 0.69 3.41 1986 1,051.3 69.1 3,370 1,909 0.57 1.82 1987 1,152.4 80.6 3,052 1,419 0.46 1.23 1988 990.8 70.1 2,648 1,747 0.66 1.76 1989 990.9 65.8 3,844 1,786 0.46 1.80 1990 991.6 67.8 3,182 1,548 0.49 1.56 1991 952.8 64.5 2,586 778 0.30 0.82 1992 375.9 27.9 2,690 623 0.23 1.66 1993 470.0 33.8 2,921 872 0.30 1.86 1994 1,268.4 83.0 3,049 999 0.33 0.79 1995 1,411.7 92.9 2,657 683 0.26 0.48 1996 1,261.1 85.9 2,784 716 0.26 0.57 1997 1,474.0 94.1 2,212 411 0.19 0.28 1998 1,521.0 94.3 2,005 395.526 0.20 0.26 1999 1,494.7 92.8 1,818 418.417 0.23 0.28 2000 1,571.2 95.6 1,648 321.785 0.20 0.20 2001 1,576.0 95.8 1,623 302.812 0.19 0.19 2002 1,568.0 94.5 1,743 275.534 0.16 0.18 2003 1,676.9 95.6 1,794 248.622 0.14 0.15 2004 1,690.6 94.5 2,140 244.577 0.11 0.14 2005 1,654.9 92.2 1,944 305.978 0.16 0.18 2006 1,661.2 90.0 2,103 280.465 0.13 0.17 2007 1,714.9 92.0 2,186 290.093 0.13 0.17 2008 1,694.5 91.7 2,546 354.212 0.14 0.21 2009 1,647.9 89.6 2,683 350.347 0.13 0.21 2010 1,690.7 91.3 3,227 407.424 0.13 0.24 2011 1,662.7 90.5 2,778 381.057 0.14 0.23 2012 1,629.3 89.4 3,368 369.873 0.11 0.23 2013 1,650.6 89.9 3,978 361.148 0.09 0.22 2014 1,750.6 94.5 3,498 261.897 0.07 0.15 2015 1,745.6 93.7 2,660 230.570 0.09 0.13 2016 1,756.7 95.7 1,756 167.236 0.10 0.10 2

All three Browns Ferry units were placed on administrative hold in 1985. Units 2 and 3 were restarted in 1991 and 1995, respectively. Browns Ferry Unit 1 was restarted during 2007.

C-4

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr BRUNSWICK 1, 2 2017 1,754.6 96.0 1,748 216.013 0.12 0.12 (continued) 2018 1,669.7 93.2 1,543 183.275 0.12 0.11 2019 1,680.0 91.5 1,673 222.735 0.13 0.13 BYRON 1, 2 1986 894.5 88.6 1,081 76 0.07 0.08 Docket 50-454, 50-455; 1987 650.9 70.9 1,826 769 0.42 1.18 NPF-37, NPF-66 1988 1,534.7 86.3 1,222 459 0.38 0.30 1st commercial operation 1989 1,812.6 90.2 1,109 172 0.16 0.09 9/85, 8/87 1990 1,567.3 78.8 1,396 434 0.31 0.28 Type - PWRs 1991 1,816.3 89.9 1,077 268 0.25 0.15 Capacity - 1,157, 1,127 MWe 1992 1,888.4 90.1 1,021 199 0.19 0.11 1993 1,785.6 83.5 1,370 432 0.32 0.24 1994 1,953.3 90.7 962 280 0.29 0.14 1995 1,900.6 85.5 1,107 306 0.28 0.16 1996 1,758.4 79.3 1,610 455 0.28 0.26 1997 1,856.7 86.6 1,546 241 0.16 0.13 1998 1,869.8 85.9 1,809 275.221 0.15 0.15 1999 2,064.2 92.3 1,478 239.102 0.16 0.12 2000 2,196.9 97.4 959 193.871 0.20 0.09 2001 2,301.5 97.8 719 59.451 0.08 0.03 2002 2,205.0 93.8 1,287 195.013 0.15 0.09 2003 2,294.8 97.2 824 87.129 0.11 0.04 2004 2,277.4 97.7 906 89.147 0.10 0.04 2005 2,175.6 94.2 1,542 199.812 0.13 0.09 2006 2,223.3 95.0 1,163 134.497 0.12 0.06 2007 2,152.1 93.0 1,311 128.797 0.10 0.06 2008 2,203.7 94.6 1,483 140.809 0.09 0.06 2009 2,250.9 96.7 985 83.443 0.08 0.04 2010 2,266.6 97.4 922 56.425 0.06 0.02 2011 2,077.9 91.0 1,849 244.104 0.13 0.12 2012 2,085.4 94.6 924 50.973 0.06 0.02 2013 2,231.4 96.8 1,002 57.708 0.06 0.03 2014 2,197.8 94.2 1,184 80.774 0.07 0.04 2015 2,222.8 96.8 878 42.935 0.05 0.02 2016 2,237.5 96.0 884 54.012 0.06 0.02 2017 2,186.4 93.7 1,280 87.846 0.07 0.04 2018 2,288.9 97.9 615 25.155 0.04 0.01 2019 2,296.6 97.9 693 36.322 0.05 0.02 CALLAWAY 1 1985 967.4 90.0 964 36 0.04 0.04 Docket 50-483; 1986 865.2 81.3 1,052 225 0.21 0.26 NPF-30 1987 759.0 71.1 1,082 393 0.36 0.52 1st commercial operation 12/84 1988 1,069.2 93.4 353 27 0.08 0.03 Type - PWR 1989 1,000.3 85.4 1,055 283 0.27 0.28 Capacity - 1,190 MWe 1990 960.7 84.1 1,134 442 0.39 0.46 1991 1,193.1 99.7 280 21 0.08 0.02 1992 967.5 83.0 1,133 336 0.30 0.35 1993 1,002.9 86.4 1,126 225 0.20 0.22 1994 1,196.4 100.0 191 14 0.07 0.01 1995 989.6 84.7 1,062 187 0.18 0.19 1996 1,066.0 90.5 980 248 0.25 0.23 1997 1,022.2 100.0 248 12 0.05 0.01 1998 972.2 91.3 929 200.729 0.22 0.21 1999 981.3 88.7 1,098 320.554 0.29 0.33 2000 1,137.5 99.8 244 16.058 0.07 0.01 2001 954.5 86.7 873 106.782 0.12 0.11 2002 955.0 86.2 983 95.648 0.10 0.10 2003 1,104.3 96.2 252 8.297 0.03 0.01 2004 892.8 78.9 1,124 120.621 0.11 0.14 2005 913.2 80.7 1,600 222.629 0.14 0.24 2006 1,152.8 95.0 225 6.308 0.03 0.01 2007 1,069.7 89.0 1,079 73.236 0.07 0.07 2008 1,067.6 89.8 729 45.738 0.06 0.04 2009 1,170.3 97.6 164 4.821 0.03 0.00 2010 1,029.9 84.8 800 58.735 0.07 0.06 2011 1,071.7 88.9 838 80.215 0.10 0.07 C-5

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr CALLAWAY 1 2012 1,220.2 100.0 169 4.525 0.03 0.00 (continued) 2013 959.9 80.9 680 43.123 0.06 0.04 2014 1,061.3 88.0 649 37.173 0.06 0.04 2015 1,192.2 99.1 96 3.128 0.03 0.00 2016 1,078.3 89.8 641 46.770 0.07 0.04 2017 951.9 80.3 507 23.713 0.05 0.02 2018 1,216.6 100.0 84 3.211 0.04 0.00 2019 1,053.4 87.3 436 37.630 0.09 0.04 CALVERT CLIFFS 1, 2 1976 753.4 95.2 507 74 0.15 0.10 Docket 50-317, 50-318; 1977 583.0 72.1 2,265 547 0.24 0.94 DPR-53, DPR-69 1978 1,188.5 75.8 1,391 500 0.36 0.42 1st commercial operation 1979 1,161.0 74.0 1,428 805 0.56 0.69 5/75, 4/77 1980 1,309.9 84.1 1,496 677 0.45 0.52 Type - PWRs 1981 1,379.7 83.1 1,555 607 0.39 0.44 Capacity - 877, 855 MWe 1982 1,238.3 73.7 1,805 1,057 0.59 0.85 1983 1,397.2 81.6 1,915 668 0.35 0.48 1984 1,389.4 79.3 1,369 479 0.35 0.34 1985 1,189.8 68.4 1,598 694 0.43 0.58 1986 1,530.0 87.2 1,296 347 0.27 0.23 1987 1,207.3 71.8 1,384 412 0.30 0.34 1988 1,397.7 81.0 1,296 291 0.22 0.21 1989 333.6 20.1 1,786 346 0.19 1.04 1990 161.1 11.0 2,019 304 0.15 1.89 1991 1,085.0 64.7 1,974 132 0.07 0.12 1992 1,271.2 73.9 1,979 330 0.17 0.26 1993 1,462.1 83.9 1,462 405 0.28 0.28 1994 1,342.1 79.4 1,482 454 0.31 0.34 1995 1,542.8 89.9 1,203 235 0.20 0.15 1996 1,438.5 82.4 1,167 239 0.20 0.17 1997 1,499.6 89.1 1,091 229 0.21 0.15 1998 1,523.1 89.3 1,042 186.887 0.18 0.12 1999 1,521.4 90.1 1,134 191.778 0.17 0.13 2000 1,575.7 92.7 912 134.689 0.15 0.09 2001 1,554.7 91.7 895 166.864 0.19 0.11 2002 1,380.0 81.7 1,582 245.075 0.16 0.18 2003 1,558.4 90.9 1,671 265.164 0.16 0.17

2004 1,653.7 95.7 1,205 143.944 0.12 0.09 2005 1,678.1 97.2 942 168.390 0.18 0.10 2006 1,581.8 92.0 1,215 203.790 0.17 0.13 2007 1,641.6 95.0 1,191 153.335 0.13 0.09 2008 1,670.7 97.4 745 74.149 0.10 0.04 2009 1,660.9 96.6 891 95.756 0.11 0.06 2010 1,597.3 93.5 834 128.581 0.15 0.08 2011 1,635.9 95.7 703 95.233 0.14 0.06 2012 1,545.6 89.9 725 115.525 0.16 0.07 2013 1,632.6 94.0 580 61.079 0.11 0.04 2014 1,638.3 94.9 586 62.065 0.11 0.04 2015 1,672.4 95.6 583 45.624 0.08 0.03 2016 1,685.6 96.3 904 85.891 0.10 0.05 2017 1,725.0 97.2 686 49.283 0.07 0.03 2018 1,711.0 96.5 875 56.494 0.06 0.03 2019 1,713.8 96.5 837 59.246 0.07 0.03 CATAWBA 1, 2 1986 638.9 49.9 1,724 286 0.17 0.45 Docket 50-413, 50-414; 1987 1,651.2 75.9 1,865 449 0.24 0.27 NPF-35, NPF-52 1988 1,675.2 77.2 2,009 556 0.28 0.33 1st commercial operation 1989 1,733.6 79.5 1,660 334 0.20 0.19 6/85, 8/86 1990 1,616.3 70.8 2,174 809 0.37 0.50 Type - PWRs 1991 1,691.5 74.6 1,871 462 0.25 0.27 Capacity - 1,160, 1,150 MWe 1992 1,962.8 83.9 1,515 414 0.27 0.21 1993 1,896.1 81.5 1,564 396 0.25 0.21 1994 2,105.2 90.2 1,268 207 0.16 0.10 1995 2,011.9 85.3 1,892 462 0.24 0.23 1996 1,879.1 80.5 1,588 302 0.19 0.16 1997 2,028.2 89.3 1,561 266 0.17 0.13 C-6

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr CATAWBA 1, 2 1998 2,006.4 89.6 1,123 162.068 0.14 0.08 (continued) 1999 2,046.7 90.2 1,024 118.662 0.12 0.06 2000 2,038.3 90.3 1,185 186.532 0.16 0.09 2001 2,119.9 92.9 960 116.241 0.12 0.05 2002 2,238.0 97.2 884 81.325 0.09 0.04 2003 1,991.8 89.2 1,409 210.617 0.15 0.11 2004 2,111.4 93.0 1,123 122.831 0.11 0.06 2005 2,194.5 96.0 1,019 83.679 0.08 0.04 2006 1,928.6 85.0 1,792 212.570 0.12 0.11 2007 2,102.5 92.0 1,399 144.218 0.10 0.07 2008 2,160.3 93.5 1,110 85.080 0.08 0.04 2009 2,044.8 89.1 1,385 169.409 0.12 0.08 2010 2,164.8 94.8 1,045 97.010 0.09 0.04 2011 2,144.2 93.9 961 52.321 0.05 0.02 2012 2,029.7 88.8 1,157 94.734 0.08 0.05 2013 2,187.9 95.5 1,053 82.906 0.08 0.04 2014 2,136.0 93.3 996 50.777 0.05 0.02 2015 2,098.6 92.2 1,299 97.678 0.08 0.05 2016 2,232.7 96.1 1,000 77.097 0.08 0.03 2017 2,249.6 96.8 642 32.236 0.05 0.01 2018 2,143.8 93.0 1,211 87.302 0.07 0.04 2019 2,236.7 96.7 886 68.370 0.08 0.03 CLINTON 1988 701.3 84.2 769 130 0.17 0.19 Docket 50-461; 1989 348.3 48.5 1,196 372 0.31 1.07 NPF-62 1990 435.8 55.1 1,390 553 0.40 1.27 1st commercial operation 11/87 1991 722.7 80.8 1,010 233 0.23 0.32 Type - BWR 1992 589.7 68.6 1,195 431 0.36 0.73 Capacity - 1,022 MWe 1993 701.5 79.6 1,253 498 0.40 0.71 1994 883.3 94.8 409 63 0.15 0.07 1995 731.1 83.0 1,182 316 0.27 0.43 1996 634.7 66.7 1,154 350 0.30 0.55 1997 0.0 0.0 738 172 0.23 ---

1998 0.0 0.0 866 144.140 0.17 ---

1999 537.0 63.5 637 87.489 0.14 0.16 2000 784.2 87.8 1,248 253.382 0.20 0.32 2001 896.8 98.5 329 33.770 0.10 0.04 2002 872.0 90.5 1,418 208.094 0.15 0.24 2003 990.5 99.1 372 57.118 0.15 0.06 2004 910.8 92.6 1,622 282.833 0.17 0.31 2005 989.1 97.4 298 36.019 0.12 0.04 2006 939.9 92.0 1,649 295.720 0.18 0.32 2007 1,049.2 100.0 310 30.618 0.10 0.03 2008 973.0 93.3 1,381 205.086 0.15 0.21 2009 1,014.6 96.6 435 48.009 0.11 0.05 2010 983.1 93.5 1,540 219.954 0.14 0.22 2011 989.9 94.4 1,683 228.447 0.14 0.23 2012 1,067.1 100.0 215 14.250 0.07 0.01 2013 950.2 91.9 1,182 128.781 0.11 0.14 2014 1,038.6 98.8 186 17.866 0.10 0.02 2015 922.9 94.1 1,197 97.634 0.08 0.11 2016 1,017.8 97.2 480 33.218 0.07 0.03 2017 954.1 91.9 1,341 154.579 0.12 0.16 2018 958.7 92.3 1,137 77.813 0.07 0.08 2019 957.6 91.2 1,372 158.832 0.12 0.17 COLUMBIA GENERATING3 1985 616.0 87.6 755 119 0.16 0.19 Docket 50-397; 1986 616.0 74.4 1,013 222 0.22 0.36 NPF-21 1987 639.0 70.8 1,201 406 0.34 0.64 1st commercial operation 12/84 1988 707.7 71.8 1,050 353 0.34 0.50 Type - BWR 1989 727.2 78.3 1,299 492 0.38 0.68 Capacity - 1,131 MWe 1990 684.7 67.5 1,348 536 0.40 0.78 1991 508.5 50.3 1,088 387 0.36 0.76 1992 682.3 65.6 1,489 612 0.41 0.90 3

Energy Northwest changed the name of Washington Nuclear 2 to Columbia Generating Station in 2001.

C-7

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr COLUMBIA GENERATING3 1993 849.6 79.5 1,385 469 0.34 0.55 (continued) 1994 803.8 75.2 1,870 866 0.46 1.08 1995 824.7 83.8 1,694 456 0.27 0.55 1996 662.9 82.2 1,453 373 0.26 0.56 1997 697.0 72.7 1,218 251 0.21 0.36 1998 789.5 75.3 1,220 286.020 0.23 0.36 1999 694.7 70.0 1,022 155.109 0.15 0.22 2000 979.6 96.3 706 53.152 0.08 0.05 2001 939.3 88.1 1,515 226.675 0.15 0.24 2002 1,023.0 97.5 647 46.650 0.07 0.05 2003 866.9 81.8 1,618 205.225 0.13 0.24 2004 1,022.5 94.6 716 66.130 0.09 0.06 2005 938.3 87.3 1,718 325.025 0.19 0.35 2006 1,064.9 98.0 623 55.817 0.09 0.05 2007 925.6 87.0 2,147 306.443 0.14 0.33 2008 1,055.3 98.3 715 54.957 0.08 0.05 2009 757.2 76.3 1,958 305.163 0.16 0.40 2010 1,054.9 100.0 733 54.712 0.07 0.05 2011 548.7 54.4 2,309 335.657 0.15 0.61 2012 1,062.6 97.6 1,155 45.462 0.04 0.04 2013 965.9 88.4 1,787 223.809 0.13 0.23 2014 1,084.2 100.0 775 33.771 0.04 0.03 2015 931.6 87.0 2,088 289.135 0.14 0.31 2016 1,098.8 97.8 586 26.825 0.05 0.02 2017 927.9 87.7 1,724 180.255 0.10 0.19 2018 1,108.3 98.6 494 43.078 0.09 0.04 2019 1,012.2 89.7 1,389 190.694 0.14 0.19 COMANCHE PEAK 1, 2 1991 644.4 82.2 985 148 0.15 0.23 Docket 50-445, 50-446; 1992 830.8 84.0 1,128 188 0.17 0.23 NPF-87, NPF-89 1993 853.8 81.2 945 109 0.12 0.13 1st commercial operation 1994 1,750.0 93.7 970 90 0.09 0.05 8/90, 8/93 1995 2,022.6 92.5 951 179 0.19 0.09 Type - PWR 1996 1,804.8 81.4 1,462 288 0.20 0.16 Capacity - 1,205, 1,195 MWe 1997 2,002.4 93.4 870 146 0.17 0.07 1998 2,037.8 94.9 967 232.026 0.24 0.11 1999 1,981.5 90.9 1,316 251.276 0.19 0.13 2000 2,104.7 95.3 759 77.679 0.10 0.04 2001 2,085.9 94.7 853 114.968 0.13 0.06 2002 1,887.0 86.9 1,106 225.317 0.20 0.12 2003 2,020.6 91.6 639 66.313 0.10 0.03 2004 2,169.5 95.1 864 135.388 0.16 0.06 2005 2,099.6 91.5 1,365 242.481 0.18 0.12 2006 2,271.3 97.0 686 59.959 0.09 0.03 2007 2,151.3 93.0 1,616 219.799 0.14 0.10 2008 2,189.7 94.3 1,037 168.836 0.16 0.08 2009 2,299.3 96.7 938 51.420 0.05 0.02 2010 2,316.8 96.3 1,037 70.807 0.07 0.03 2011 2,216.8 92.6 1,580 154.716 0.10 0.07 2012 2,279.9 94.6 1,001 66.742 0.07 0.03 2013 2,353.5 96.8 745 45.237 0.06 0.02 2014 2,141.7 88.6 1,123 139.246 0.12 0.07 2015 2,294.6 94.7 641 42.889 0.07 0.02 2016 2,340.7 96.0 624 36.648 0.06 0.02 2017 1,947.3 81.5 1,052 120.996 0.12 0.06 2018 2,346.3 96.5 554 41.677 0.08 0.02 2019 2,219.0 93.0 790 58.051 0.07 0.03 COOK 1, 2 1976 807.4 83.1 395 116 0.29 0.14 Docket 50-315, 50-316; 1977 573.0 76.1 802 300 0.37 0.52 DPR-58, DPR-74 1978 744.8 73.6 778 336 0.43 0.45 1st commercial operation 1979 1,373.0 65.3 1,445 718 0.50 0.52 8/75, 7/78 1980 1,552.4 74.1 1,345 493 0.37 0.32 Type - PWRs 1981 1,557.3 73.4 1,341 656 0.49 0.42 Capacity - 1,030, 1,168 MWe 1982 1,461.6 69.8 1,527 699 0.46 0.48 3

Energy Northwest changed the name of Washington Nuclear 2 to Columbia Generating Station in 2001.

C-8

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr COOK 1, 2 1983 1,456.5 71.2 1,418 658 0.46 0.45 (continued) 1984 1,526.0 75.3 1,559 762 0.49 0.50 1985 925.4 47.6 1,984 945 0.48 1.02 1986 1,307.1 73.4 1,774 745 0.42 0.57 1987 1,199.5 70.2 1,696 666 0.39 0.56 1988 1,160.4 63.5 2,266 867 0.38 0.75 1989 1,433.1 72.8 1,575 493 0.31 0.34 1990 1,318.5 67.9 1,851 580 0.31 0.44 1991 1,837.4 90.2 815 69 0.08 0.04 1992 760.9 50.8 1,954 492 0.25 0.65 1993 1,927.7 98.5 587 44 0.07 0.02 1994 1,105.2 65.2 1,748 479 0.27 0.43 1995 1,656.0 82.1 1,310 203 0.15 0.12 1996 1,938.9 92.7 1,114 214 0.19 0.11 1997 1,189.7 59.7 1,864 550 0.30 0.46 1998 0.0 0.0 1,155 104.638 0.09 ---

1999 0.0 0.0 1,662 171.479 0.10 ---

2000 560.1 28.1 2,506 337.584 0.13 0.60 2001 1,794.3 89.2 423 27.290 0.06 0.02 2002 1,756.0 87.3 1,624 278.001 0.17 0.16 2003 1,557.6 75.7 1,408 209.526 0.15 0.13 2004 1,909.2 91.4 1,015 156.213 0.15 0.08 2005 1,989.0 95.0 852 91.192 0.11 0.05 2006 1,790.5 86.0 1,780 312.214 0.18 0.17 2007 1,983.7 93.0 1,310 238.829 0.18 0.12 2008 1,711.8 80.8 971 76.460 0.08 0.04 2009 950.5 45.3 693 40.007 0.06 0.04 2010 1,786.1 86.7 1,116 83.276 0.07 0.05 2011 1,981.5 94.2 842 57.169 0.07 0.03 2012 2,017.5 94.7 754 49.112 0.07 0.02 2013 1,858.5 87.1 1,187 103.772 0.09 0.06 2014 2,012.7 94.3 727 53.798 0.07 0.03 2015 1,885.7 87.4 626 29.827 0.05 0.02 2016 1,753.5 82.3 1,123 93.715 0.08 0.05 2017 2,008.2 89.7 830 57.999 0.07 0.03 2018 2,010.4 90.5 825 40.511 0.05 0.02 2019 1,844.7 84.4 1,071 82.888 0.08 0.04 COOPER STATION 1975 456.4 83.6 579 117 0.20 0.26 Docket 50-298; 1976 433.3 75.5 763 350 0.46 0.81 DPR-46 1977 538.2 86.2 315 198 0.63 0.37 1st commercial operation 7/74 1978 576.0 91.0 297 158 0.53 0.27 Type - BWR 1979 591.0 87.6 426 221 0.52 0.37 Capacity - 769 MWe 1980 448.3 71.2 785 859 1.09 1.92 1981 457.1 71.2 935 579 0.62 1.27 1982 622.3 84.6 743 542 0.73 0.87 1983 396.6 63.3 1,383 1,293 0.93 3.26 1984 411.9 67.2 1,598 799 0.50 1.94 1985 127.3 21.5 1,980 1,333 0.67 10.47 1986 480.0 74.7 895 320 0.36 0.67 1987 652.3 96.2 549 103 0.19 0.16 1988 493.4 67.9 942 251 0.27 0.51 1989 564.3 76.2 1,202 343 0.29 0.61 1990 602.0 79.4 1,174 379 0.32 0.63 1991 566.3 78.8 1,099 405 0.37 0.72 1992 731.0 96.4 463 84 0.18 0.11 1993 436.1 58.8 1,130 391 0.35 0.90 1994 262.2 35.1 333 79 0.24 0.30

1995 486.5 66.8 1,095 228 0.21 0.47 1996 742.1 97.9 468 48 0.10 0.06 1997 622.8 84.4 1,125 174 0.15 0.28 1998 555.9 75.9 977 181.858 0.19 0.33 1999 743.2 98.1 318 47.815 0.15 0.06 2000 539.2 74.2 963 199.589 0.21 0.37 2001 592.7 80.9 1,309 168.665 0.13 0.28 C-9

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr COOPER STATION 2002 719.0 98.6 362 38.739 0.11 0.05 (continued) 2003 511.4 74.1 882 135.249 0.15 0.26 2004 702.6 94.7 481 47.064 0.10 0.07 2005 670.8 89.4 1,266 275.652 0.22 0.41 2006 674.7 90.0 1,265 270.135 0.21 0.40 2007 761.6 99.0 730 49.902 0.07 0.07 2008 679.0 89.9 1,715 359.926 0.21 0.53 2009 654.6 86.6 1,638 254.032 0.16 0.39 2010 775.4 100.0 773 61.303 0.08 0.08 2011 658.5 84.8 1,737 349.247 0.20 0.53 2012 662.9 87.6 1,800 279.301 0.16 0.42 2013 776.5 100.0 548 35.870 0.07 0.05 2014 675.3 88.8 1,274 202.670 0.16 0.30 2015 776.1 99.4 408 27.634 0.07 0.04 2016 676.1 88.2 1,291 195.518 0.15 0.29 2017 789.1 100.0 394 30.193 0.08 0.04 2018 642.9 84.5 996 132.984 0.13 0.21 2019 793.6 100.0 286 14.463 0.05 0.02 CRYSTAL RIVER 34 1978 311.5 41.4 643 321 0.50 1.03 Docket 50-302; 1979 453.0 58.9 1,150 495 0.43 1.09 DPR-72 1980 404.1 53.2 1,053 625 0.59 1.55 1st commercial operation 3/77 1981 490.4 62.2 1,120 408 0.36 0.83 Type - PWR 1982 589.8 76.0 780 177 0.23 0.30 Capacity - (860) MWe 1983 452.1 58.8 1,720 552 0.32 1.22 1984 774.2 94.5 549 49 0.09 0.06 1985 344.2 47.6 1,976 689 0.35 2.00 1986 319.5 41.8 1,057 472 0.45 1.48 1987 436.0 60.9 1,384 488 0.35 1.12 1988 690.2 84.0 569 64 0.11 0.09 1989 352.8 48.8 880 234 0.27 0.66 1990 497.8 63.8 1,441 476 0.33 0.96 1991 654.6 82.0 821 116 0.14 0.18 1992 632.1 76.1 1,403 424 0.30 0.67 1993 722.4 85.0 683 60 0.09 0.08 1994 711.9 84.3 1,079 228 0.21 0.32 1995 866.3 100.0 209 8 0.04 0.01 1996 290.8 37.7 1,192 353 0.30 1.21 1997 0.0 0.0 973 179 0.18 ---

1998 739.9 90.3 313 19.298 0.06 0.03 1999 727.5 87.8 1,324 251.077 0.19 0.35 2000 819.4 97.6 257 14.649 0.06 0.02 2001 741.6 89.2 902 147.946 0.16 0.20 2002 831.0 99.4 128 5.039 0.04 0.01 2003 749.0 90.8 961 126.554 0.13 0.17 2004 831.4 98.1 131 4.044 0.03 0.00 2005 723.0 88.5 939 122.608 0.13 0.17 2006 793.8 95.0 138 4.474 0.03 0.01 2007 761.7 91.0 1,135 184.554 0.16 0.24 2008 796.9 93.7 282 16.110 0.06 0.02 2009 615.0 72.5 1,705 222.344 0.13 0.36 2010 0.0 0.0 666 31.922 0.05 ---

2011 0.0 0.0 251 8.292 0.03 ---

2012 0.0 0.0 94 1.876 0.02 ---

2013 0.0 0.0 40 0.794 0.02 ---

2014 0.0 0.0 26 0.696 0.03 ---

2015 0.0 0.0 20 0.700 0.04 ---

2016 0.0 0.0 95 14.746 0.16 ---

2017 0.0 0.0 68 4.133 0.06 ---

2018 0.0 0.0 25 1.215 0.05 ---

2019 0.0 0.0 2 0.022 0.01 ---

4 Crystal River ceased power generation in 2010 due to problems associated with containment building delamination. In June 2013, it was decided that it would not be put in commercial operation again and, therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-10

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr DAVIS-BESSE 1 1978 326.4 48.7 421 48 0.11 0.15 Docket 50-346; 1979 381.0 67.0 304 30 0.10 0.08 NPF-3 1980 256.4 36.2 1,283 154 0.12 0.60 1st commercial operation 7/78 1981 531.4 67.4 578 58 0.10 0.11 Type - PWR 1982 390.8 51.5 1,350 164 0.12 0.42 Capacity - 894 MWe 1983 592.1 73.0 718 80 0.11 0.14 1984 518.5 62.5 1,088 177 0.16 0.34 1985 238.3 31.2 718 71 0.10 0.30 1986 3.3 1.3 981 124 0.13 37.58 1987 618.0 89.6 625 47 0.08 0.08 1988 144.1 27.1 1,183 307 0.26 2.13 1989 880.0 98.6 404 38 0.09 0.04 1990 500.0 56.7 1,377 489 0.36 0.98 1991 703.6 81.8 1,000 216 0.22 0.31 1992 915.2 100.0 287 19 0.07 0.02 1993 729.5 83.4 1,244 348 0.28 0.48 1994 768.4 88.0 861 144 0.17 0.19 1995 920.4 100.0 256 7 0.03 0.01 1996 775.8 85.3 949 167 0.18 0.22 1997 820.0 94.0 213 10 0.05 0.01 1998 699.8 83.2 980 155.269 0.16 0.22 1999 841.3 95.6 397 27.951 0.07 0.03 2000 770.8 87.3 1,109 168.044 0.15 0.22 2001 875.6 100.0 119 5.505 0.05 0.01 2002 106.0 12.6 1,983 402.766 0.20 3.80 2003 0.0 0.0 1,047 219.696 0.21 ---

2004 657.8 77.6 161 6.594 0.04 0.01 2005 817.1 93.3 577 51.332 0.09 0.06 2006 727.8 84.0 1,331 204.201 0.15 0.28 2007 879.7 100.0 189 7.088 0.04 0.01 2008 777.5 89.4 985 106.603 0.11 0.14 2009 868.7 95.7 115 3.621 0.03 0.00 2010 598.0 67.1 1,649 464.095 0.28 0.78 2011 723.7 80.7 1,182 73.360 0.06 0.10 2012 808.5 90.0 659 43.071 0.07 0.05 2013 876.6 96.6 92 2.558 0.03 0.00 2014 681.8 74.1 2,029 200.466 0.10 0.29 2015 901.1 99.5 32 0.995 0.03 0.00 2016 730.0 84.7 996 118.472 0.12 0.16 2017 899.1 100.0 69 1.621 0.02 0.00 2018 842.5 93.7 742 51.003 0.07 0.06 2019 894.9 98.9 175 11.405 0.07 0.01 DIABLO CANYON 1, 2 1986 641.5 80.6 1,260 304 0.24 0.47 Docket 50-275, 50-323; 1987 1,688.6 83.0 1,170 336 0.29 0.20 DPR-80, DPR-82 1988 1,386.1 67.6 1,826 877 0.48 0.63 1st commercial operation 1989 1,899.0 87.5 1,646 465 0.28 0.24 5/85, 3/86 1990 1,952.6 91.0 1,441 323 0.22 0.17 Type - PWRs 1991 1,809.6 83.8 2,040 546 0.27 0.30 Capacity - 1,122, 1,118 MWe 1992 1,995.7 90.9 1,850 459 0.25 0.23 1993 2,008.6 91.4 1,508 281 0.19 0.14 1994 1,832.6 83.3 2,317 590 0.25 0.32 1995 1,950.3 90.0 1,615 286 0.18 0.15 1996 2,003.6 90.7 1,462 176 0.12 0.09 1997 1,948.7 92.7 1,331 219 0.16 0.11 1998 1,955.1 92.8 1,313 173.238 0.13 0.09 1999 1,902.8 90.1 1,566 448.634 0.29 0.24 2000 1,940.1 92.0 1,057 180.792 0.17 0.09 2001 2,067.7 96.4 1,074 117.804 0.11 0.06 2002 1,860.0 88.4 1,016 148.690 0.15 0.08 2003 1,970.7 91.6 1,004 135.482 0.13 0.07 2004 1,736.3 83.5 1,230 254.367 0.21 0.15 2005 2,022.4 94.8 955 124.469 0.13 0.06 2006 2,109.0 94.0 1,086 82.248 0.08 0.04 C-11

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr DIABLO CANYON 1, 2 2007 2,131.4 95.0 1,269 111.866 0.09 0.05 (continued) 2008 1,952.1 87.7 2,121 235.034 0.11 0.12 2009 1,873.0 85.3 2,534 337.831 0.13 0.18 2010 2,115.2 94.7 1,367 125.457 0.09 0.06 2011 2,131.1 94.6 747 31.625 0.04 0.01 2012 2,023.0 91.8 894 43.531 0.05 0.02 2013 2,064.1 92.4 760 28.767 0.04 0.01 2014 1,947.1 88.8 979 67.599 0.07 0.03 2015 2,116.8 94.9 807 57.244 0.07 0.03 2016 2,162.2 95.7 794 37.734 0.05 0.02 2017 2,051.4 92.0 787 47.910 0.06 0.02 2018 2,088.4 94.6 718 32.013 0.04 0.02 2019 1,851.7 84.1 774 51.135 0.07 0.03 DRESDEN 15, 2, 3 1969 99.7 --- --- 286 --- 2.87 Docket 50-010, 50-237, 50-249; 1970 163.1 --- --- 143 --- 0.88 DPR-2, DPR-19, DPR-25 1971 394.5 --- --- 715 --- 1.81 1st commercial operation 8/60, 1972 1,243.7 --- --- 728 --- 0.59 6/70, 11/71 1973 1,112.2 --- 1,341 939 0.70 0.84 Type - BWRs 1974 842.5 54.9 1,594 1,662 1.04 1.97 Capacity - (197), 870, 869 MWe 1975 708.1 54.6 2,310 3,423 1.48 4.83 1976 1,127.2 80.8 1,746 1,680 0.96 1.49 1977 1,132.9 77.0 1,862 1,694 0.91 1.50 1978 1,242.2 79.5 1,946 1,529 0.79 1.23 1979 1,013.0 74.7 2,407 1,800 0.75 1.78 1980 1,074.4 55.0 2,717 2,105 0.77 1.96 1981 1,035.7 51.5 2,331 2,802 1.20 2.71 1982 1,085.3 77.9 2,572 2,923 1.14 2.69 1983 913.6 65.6 2,854 3,582 1.26 3.92 1984 789.8 55.3 2,261 1,774 0.78 2.25 1985 903.0 64.5 2,817 1,686 0.60 1.87 1986 740.5 52.6 3,111 2,668 0.86 3.60 1987 933.9 74.0 2,052 1,145 0.56 1.23 1988 1,014.7 75.8 2,414 1,409 0.58 1.39 1989 1,184.2 83.1 2,259 1,131 0.50 0.96 1990 1,107.8 76.6 2,235 1,400 0.63 1.26 1991 675.2 60.7 2,044 1,005 0.49 1.49 1992 872.4 75.4 1,812 619 0.34 0.71 1993 960.1 68.5 2,751 1,655 0.60 1.72 1994 690.2 51.7 2,336 833 0.36 1.21 1995 643.1 49.8 2,482 875 0.35 1.36 1996 612.6 47.7 1,788 456 0.26 0.74 1997 1,096.2 79.5 2,747 467 0.17 0.43 1998 1,354.7 90.6 2,311 426.918 0.18 0.32 1999 1,410.9 92.5 3,243 591.443 0.18 0.42 2000 1,506.4 97.3 2,341 261.684 0.11 0.17 2001 1,427.4 94.5 2,769 400.702 0.14 0.28 2002 1,547.0 95.7 2,819 355.011 0.13 0.23 2003 1,555.9 93.5 2,098 356.572 0.17 0.23 2004 1,405.5 84.8 2,044 381.054 0.19 0.27 2005 1,550.8 92.0 2,006 258.799 0.13 0.17 2006 1,649.0 96.0 2,042 289.167 0.14 0.18 2007 1,658.8 97.0 2,310 275.697 0.12 0.17 2008 1,638.0 95.9 2,307 198.153 0.09 0.12 2009 1,628.7 95.4 1,932 231.688 0.12 0.14 2010 1,665.9 96.3 2,152 213.825 0.10 0.13 2011 1,679.7 96.7 2,382 236.427 0.10 0.14 2012 1,685.5 96.3 2,084 139.615 0.07 0.08 2013 1,759.9 96.8 1,823 136.942 0.08 0.08 2014 1,727.8 95.9 1,782 116.933 0.07 0.07 2015 1,734.4 95.8 1,900 138.864 0.07 0.08 2016 1,763.2 97.8 1,878 141.827 0.08 0.08 5

Dresden 1 ceased power generation in 1978, and in 1985, it was decided that it would not be put in commercial operation again. Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-12

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr DRESDEN 15, 2, 3 2017 1,763.3 97.5 1,928 129.266 0.07 0.07 (continued) 2018 1,776.9 98.1 1,883 118.831 0.06 0.07 2019 1,721.7 96.6 2,155 202.866 0.09 0.12 DUANE ARNOLD 1976 305.2 78.0 350 105 0.30 0.34 Docket 50-331; 1977 353.6 78.9 538 299 0.56 0.85 DPR-49 1978 149.2 33.2 1,112 974 0.88 6.53 1st commercial operation 2/75 1979 352.0 78.0 757 275 0.36 0.78 Type - BWR 1980 339.1 73.3 1,108 671 0.61 1.98 Capacity - 602 MWe 1981 277.7 69.8 1,286 790 0.61 2.84 1982 278.5 74.7 524 229 0.44 0.82 1983 283.0 62.9 1,468 1,135 0.77 4.01 1984 329.4 72.9 611 189 0.31 0.57 1985 236.2 53.8 1,414 1,112 0.79 4.71 1986 365.5 82.0 476 187 0.39 0.51 1987 308.4 64.7 1,094 667 0.61 2.16 1988 386.5 75.2 1,136 614 0.54 1.59 1989 388.5 79.0 425 194 0.46 0.50 1990 367.4 75.8 1,460 861 0.59 2.34 1991 503.7 94.5 336 202 0.60 0.40 1992 416.5 81.9 1,043 502 0.48 1.21 1993 393.4 79.5 1,043 407 0.39 1.03 1994 498.6 94.0 493 120 0.24 0.24 1995 452.5 83.8 1,129 357 0.32 0.79 1996 476.8 90.7 1,093 270 0.25 0.57 1997 474.4 94.4 352 63 0.18 0.13 1998 438.3 86.6 1,019 236.693 0.23 0.54 1999 416.6 84.3 834 201.196 0.24 0.48 2000 507.3 98.4 317 44.181 0.14 0.09 2001 439.5 86.8 898 137.564 0.15 0.31 2002 522.0 94.4 319 35.061 0.11 0.07

2003 455.2 84.8 829 124.402 0.15 0.27 2004 561.2 98.3 220 18.993 0.09 0.03 2005 517.4 90.5 879 139.622 0.16 0.27 2006 581.7 99.0 254 29.392 0.12 0.05 2007 515.8 88.0 1,062 183.609 0.17 0.36 2008 601.4 100.0 276 24.187 0.09 0.04 2009 534.1 91.3 960 140.206 0.15 0.26 2010 508.1 86.9 1,093 200.601 0.18 0.39 2011 595.3 98.6 400 29.663 0.07 0.05 2012 494.9 84.9 1,169 134.515 0.12 0.27 2013 598.6 100.0 262 16.414 0.06 0.03 2014 474.0 86.0 1,043 121.986 0.12 0.26 2015 598.6 100.0 391 20.441 0.05 0.03 2016 536.8 92.5 1,106 110.613 0.10 0.21 2017 595.2 99.3 228 17.336 0.08 0.03 2018 558.8 94.7 697 77.984 0.11 0.14 2019 597.7 99.6 187 15.569 0.08 0.03 FARLEY 1, 2 1978 713.8 86.5 527 108 0.20 0.15 Docket 50-348, 50-364; 1979 211.0 28.6 1,227 643 0.52 3.05 NPF-2, NPF-8 1980 557.3 69.3 1,330 435 0.33 0.78 1st commercial operation 1981 310.2 41.4 1,331 512 0.38 1.65 12/77, 7/81 1982 1,271.5 79.2 1,453 484 0.33 0.38 Type - PWRs 1983 1,356.5 83.0 1,938 1,021 0.53 0.75 Capacity - 874, 883 MWe 1984 1,447.0 86.6 2,046 902 0.44 0.62 1985 1,368.2 81.1 2,551 799 0.31 0.58 1986 1,409.4 83.8 2,314 858 0.37 0.61 1987 1,369.7 84.7 1,871 598 0.32 0.44 1988 1,567.7 92.3 1,840 552 0.30 0.35 1989 1,402.9 84.6 2,206 749 0.34 0.53 1990 1,464.0 86.7 1,700 457 0.27 0.31 1991 1,464.0 88.1 1,645 648 0.39 0.44 5

Dresden 1 ceased power generation in 1978, and in 1985, it was decided that it would not be put in commercial operation again. Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-13

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr FARLEY 1, 2 1992 1,331.7 81.8 2,018 805 0.40 0.60 (continued) 1993 1,455.5 88.3 1,284 333 0.26 0.23 1994 1,587.2 93.0 1,035 250 0.24 0.16 1995 1,311.2 83.8 1,574 460 0.29 0.35 1996 1,549.2 90.9 1,150 232 0.20 0.15 1997 1,449.7 89.0 1,105 278 0.25 0.19 1998 1,313.9 80.9 1,380 431.821 0.31 0.33 1999 1,436.0 91.4 1,102 190.463 0.17 0.13 2000 1,430.1 88.6 1,683 359.855 0.21 0.25 2001 1,384.3 84.4 1,810 320.509 0.18 0.23 2002 1,558.0 93.5 772 96.431 0.12 0.06

2003 1,592.6 95.3 788 111.016 0.14 0.07 2004 1,496.8 89.4 1,141 107.227 0.09 0.07 2005 1,564.2 93.3 810 67.826 0.08 0.04 2006 1,602.7 94.0 747 66.189 0.09 0.04 2007 1,495.8 88.0 1,226 139.716 0.11 0.09 2008 1,602.6 94.4 669 40.833 0.06 0.03 2009 1,595.2 94.1 657 41.851 0.06 0.03 2010 1,503.4 89.0 1,321 121.313 0.09 0.08 2011 1,647.4 95.1 723 37.510 0.05 0.02 2012 1,680.7 95.8 563 29.817 0.05 0.02 2013 1,609.4 92.8 775 53.212 0.07 0.03 2014 1,655.9 94.5 713 37.703 0.05 0.02 2015 1,631.0 93.6 888 55.942 0.06 0.03 2016 1,563.7 90.0 957 59.840 0.06 0.04 2017 1,690.0 96.1 575 31.351 0.05 0.02 2018 1,605.6 94.2 592 36.355 0.06 0.02 2019 1,613.8 92.3 896 63.320 0.07 0.04 FERMI 2 1989 624.0 68.5 1,270 255 0.20 0.41 Docket 50-341; 1990 848.2 84.7 462 83 0.18 0.10 NPF-43 1991 739.0 77.0 1,223 228 0.19 0.31 1st commercial operation 1/88 1992 874.3 81.3 1,213 245 0.20 0.28 Type - BWR 1993 984.3 92.9 360 35 0.10 0.04 Capacity - 1,096 MWe 1994 0.0 2.2 1,130 213 0.19 ---

1995 618.3 86.9 390 28 0.07 0.05 1996 577.5 69.1 1,402 157 0.11 0.27 1997 637.0 66.6 623 49 0.08 0.08 1998 815.8 79.9 1,362 207.593 0.15 0.25 1999 1,082.7 99.5 461 36.152 0.08 0.03 2000 939.6 87.6 1,266 145.964 0.12 0.16 2001 975.0 90.9 1,202 168.689 0.14 0.17 2002 1,059.0 98.7 463 38.235 0.08 0.04

2003 925.3 86.9 1,207 168.138 0.14 0.18 2004 962.3 90.0 1,302 145.090 0.11 0.15 2005 998.1 91.7 538 61.626 0.11 0.06 2006 855.9 83.0 1,430 181.300 0.13 0.21 2007 950.2 87.0 1,484 194.039 0.13 0.20 2008 1,094.5 99.5 460 35.186 0.08 0.03 2009 847.8 79.3 1,497 148.846 0.10 0.18 2010 885.0 86.4 1,625 146.490 0.09 0.17 2011 1,017.9 95.7 387 24.080 0.06 0.02 2012 589.3 65.2 1,420 144.973 0.10 0.25 2013 754.5 93.0 704 26.179 0.04 0.03 2014 891.5 85.9 1,806 199.698 0.11 0.22 2015 838.6 75.8 1,866 234.853 0.13 0.28 2016 1,045.0 96.2 779 54.761 0.07 0.05 2017 993.0 91.2 2,025 265.082 0.13 0.27 2018 849.2 78.3 2,451 329.015 0.13 0.39 2019 1,128.6 100.0 1,417 65.282 0.05 0.06 FITZPATRICK 1976 489.0 71.6 600 202 0.34 0.41 Docket 50-333; 1977 460.5 68.4 1,380 1,080 0.78 2.35 DPR-59 1978 497.0 72.1 904 909 1.01 1.83 1st commercial operation 7/75 1979 349.0 50.8 850 859 1.01 2.46 Type - BWR 1980 509.5 70.3 2,056 2,040 0.99 4.00 Capacity - 813 MWe 1981 562.9 74.7 2,490 1,425 0.57 2.53 C-14

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr FITZPATRICK 1982 583.6 75.0 2,322 1,190 0.51 2.04 (continued) 1983 546.2 70.6 1,715 1,090 0.64 2.00 1984 576.2 76.8 1,610 971 0.60 1.69 1985 492.3 63.7 1,845 1,051 0.57 2.13 1986 711.2 90.6 1,185 411 0.35 0.58 1987 496.2 70.3 1,578 940 0.60 1.89 1988 514.0 69.0 1,553 786 0.51 1.53 1989 727.5 92.3 1,027 377 0.37 0.52 1990 543.8 72.6 1,536 884 0.58 1.63 1991 399.7 53.4 1,269 333 0.26 0.83 1992 0.0 0.0 2,374 674 0.28 ---

1993 559.6 81.7 1,427 232 0.16 0.41 1994 588.4 83.2 1,595 322 0.20 0.55 1995 569.8 74.5 1,249 327 0.26 0.57 1996 623.3 83.1 1,384 357 0.26 0.57 1997 756.2 95.9 662 91 0.14 0.12 1998 562.8 78.0 1,781 357.826 0.20 0.64 1999 749.7 95.5 558 68.409 0.12 0.09 2000 685.9 88.4 1,267 300.997 0.24 0.44 2001 807.2 98.9 665 63.229 0.10 0.08 2002 751.0 93.3 1,234 230.523 0.19 0.31

2003 793.0 97.9 298 51.156 0.17 0.06 2004 735.0 92.1 1,091 186.055 0.17 0.25 2005 802.9 96.3 382 62.697 0.16 0.08 2006 771.5 93.0 1,527 234.425 0.15 0.30 2007 790.1 96.0 526 58.741 0.11 0.07 2008 761.7 92.9 1,430 184.772 0.13 0.24 2009 844.5 100.0 487 35.119 0.07 0.04 2010 726.2 91.3 1,429 219.887 0.15 0.30 2011 826.9 100.0 513 35.217 0.07 0.04 2012 691.1 87.2 1,546 169.886 0.11 0.25 2013 780.8 98.9 603 39.392 0.07 0.05 2014 665.4 87.8 1,674 135.890 0.08 0.20 2015 842.7 100.0 250 20.785 0.08 0.02 2016 668.7 95.4 362 28.304 0.08 0.04 2017 705.8 89.0 1,139 162.196 0.14 0.23 2018 745.2 92.6 1,456 231.548 0.16 0.31 2019 839.5 100.0 381 24.160 0.06 0.03 FORT CALHOUN6 1975 252.3 67.4 469 294 0.63 1.17 Docket 50-285; 1976 265.9 69.5 516 313 0.61 1.18 DPR-40 1977 351.8 79.4 535 297 0.56 0.84 1st commercial operation 6/74 1978 342.3 75.1 596 410 0.69 1.20 Type - PWR 1979 440.0 95.7 451 126 0.28 0.29 Capacity - (482) MWe 1980 242.3 60.4 891 668 0.75 2.76 1981 260.9 72.3 822 458 0.56 1.76 1982 418.0 89.7 604 217 0.36 0.52 1983 330.4 73.1 860 433 0.50 1.31 1984 279.2 59.9 913 563 0.62 2.02 1985 367.0 73.7 982 373 0.38 1.02 1986 431.8 94.3 756 75 0.10 0.17 1987 366.0 75.4 1,247 388 0.31 1.06 1988 315.5 74.1 1,594 272 0.17 0.86 1989 395.7 89.2 1,210 93 0.08 0.24 1990 290.0 64.2 760 290 0.38 1.00 1991 391.1 91.7 284 57 0.20 0.15 1992 303.4 65.9 802 272 0.34 0.90 1993 369.7 80.8 713 157 0.22 0.42 1994 492.8 99.6 211 23 0.11 0.05 1995 402.8 83.2 627 139 0.22 0.35 1996 374.9 79.5 740 226 0.31 0.60 1997 435.9 93.6 258 41 0.16 0.09 1998 387.7 82.5 788 223.847 0.28 0.58 1999 409.2 89.2 676 158.843 0.23 0.39 6

Fort Calhoun ceased power generation in October 2016 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-15

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr FORT CALHOUN6 2000 443.8 93.5 249 35.215 0.14 0.08 (continued) 2001 401.2 88.3 770 225.891 0.29 0.56 2002 434.0 92.3 742 163.806 0.22 0.38

2003 399.6 87.0 914 212.422 0.23 0.53 2004 463.5 97.0 215 21.574 0.10 0.05 2005 332.4 72.2 1,069 272.876 0.26 0.82 2006 353.9 75.0 1,591 289.100 0.18 0.82 2007 499.9 100.0 100 3.990 0.04 0.01 2008 400.4 82.2 839 96.155 0.11 0.24 2009 422.7 87.0 870 110.918 0.13 0.26 2010 486.5 98.5 171 9.763 0.06 0.02 2011 134.4 26.8 1,042 79.226 0.08 0.59 2012 0.0 0.0 494 39.377 0.08 ---

2013 10.9 3.6 678 63.853 0.09 5.86 2014 477.7 97.7 159 5.053 0.03 0.01 2015 402.5 81.5 747 75.987 0.10 0.19 2016 0.0 0.0 166 11.255 0.07 0.00 2017 0.0 0.0 72 2.770 0.04 ---

2018 0.0 0.0 74 6.939 0.09 ---

2019 0.0 0.0 110 11.120 0.10 ---

GINNA 1971 327.8 --- 340 430 1.26 1.31 Docket 50-244; 1972 293.6 --- 677 1,032 1.52 3.51 DPR-18 1973 409.5 --- 319 224 0.70 0.55 1st commercial operation 7/70 1974 253.7 62.4 884 1,225 1.39 4.83 Type - PWR 1975 365.2 76.7 685 538 0.79 1.47 Capacity - 560 MWe 1976 248.8 58.2 758 636 0.84 2.56 1977 365.6 85.5 530 401 0.76 1.10 1978 386.5 80.6 657 450 0.68 1.16 1979 355.0 72.8 878 592 0.67 1.67 1980 370.5 76.0 1,073 708 0.66 1.91 1981 399.0 82.1 925 655 0.71 1.64 1982 289.0 58.8 1,117 1,140 1.02 3.94 1983 365.0 74.6 969 855 0.88 2.34 1984 378.1 77.2 713 395 0.55 1.04 1985 436.7 87.9 845 426 0.50 0.98 1986 433.3 87.4 901 357 0.40 0.82 1987 459.0 91.5 773 344 0.45 0.75 1988 423.1 87.4 897 295 0.33 0.70 1989 369.2 75.9 1,254 605 0.48 1.64 1990 414.3 84.4 991 347 0.35 0.84 1991 418.6 86.7 947 328 0.35 0.78 1992 417.6 86.9 832 261 0.31 0.63 1993 419.6 86.3 856 193 0.23 0.46 1994 405.3 83.2 679 138 0.20 0.34 1995 437.0 89.6 738 136 0.18 0.31 1996 347.9 71.1 976 168 0.17 0.48 1997 444.6 91.8 533 81 0.15 0.18 1998 491.8 100.0 161 14.892 0.09 0.03 1999 403.4 85.6 641 175.173 0.27 0.43 2000 434.2 91.6 429 76.435 0.18 0.18 2001 488.0 100.0 140 10.156 0.07 0.02 2002 438.0 91.3 535 80.432 0.15 0.18

2003 440.4 91.1 510 74.533 0.15 0.17 2004 490.5 99.5 111 7.486 0.07 0.02 2005 455.0 93.9 564 72.841 0.13 0.16 2006 470.2 94.0 514 44.580 0.09 0.09 2007 564.4 99.0 111 4.412 0.04 0.01 2008 540.1 94.5 976 101.996 0.10 0.19 2009 529.2 94.3 633 41.809 0.07 0.08 2010 564.9 98.9 75 3.168 0.04 0.01 2011 492.1 86.4 931 100.711 0.11 0.20 2012 523.9 92.1 654 54.636 0.08 0.10 6

Fort Calhoun ceased power generation in October 2016 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-16

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr GINNA 2013 570.0 99.1 104 3.434 0.03 0.01 (continued) 2014 532.2 93.5 621 58.380 0.09 0.11 2015 544.5 95.1 415 24.163 0.06 0.04 2016 575.6 100.0 79 1.882 0.02 0.00 2017 536.3 94.5 614 46.173 0.08 0.09 2018 536.4 94.9 462 27.931 0.06 0.05 2019 570.1 99.5 57 2.023 0.04 0.00 GRAND GULF 1986 494.7 60.9 1,486 436 0.29 0.88 Docket 50-416; 1987 920.7 82.2 1,358 420 0.31 0.46 NPF-29 1988 1,136.6 96.7 692 147 0.21 0.13 1st commercial operation 7/85 1989 932.6 80.0 1,972 498 0.25 0.53 Type - BWR 1990 883.5 78.9 1,765 482 0.27 0.55 Capacity - 1,428 MWe 1991 1,085.2 94.0 699 94 0.13 0.09 1992 969.0 83.7 2,032 484 0.24 0.50 1993 936.4 81.5 1,807 332 0.18 0.35 1994 1,143.2 96.6 455 56 0.12 0.05 1995 952.9 80.4 1,589 342 0.22 0.36 1996 1,096.2 88.7 1,564 357 0.23 0.33 1997 1,234.9 100.0 514 105 0.20 0.09 1998 1,049.2 88.9 1,410 303.695 0.22 0.29 1999 962.1 81.3 1,180 226.277 0.19 0.23 2000 1,217.5 99.4 289 34.877 0.12 0.03 2001 1,129.8 93.0 1,109 185.214 0.17 0.16 2002 1,145.0 93.6 1,060 176.396 0.17 0.15

2003 1,241.2 98.6 290 31.250 0.11 0.03 2004 1,165.2 92.2 1,243 158.112 0.13 0.14 2005 1,147.3 91.9 1,326 167.914 0.13 0.15 2006 1,233.7 98.0 1,016 59.935 0.06 0.05 2007 1,070.5 88.0 1,750 177.884 0.10 0.17 2008 1,072.1 89.5 1,843 167.859 0.09 0.16 2009 1,255.5 100.0 521 30.721 0.06 0.02 2010 1,102.0 91.5 1,822 188.370 0.10 0.17 2011 1,180.0 100.0 530 21.084 0.04 0.02 2012 835.2 67.8 2,446 276.378 0.11 0.33 2013 1,231.1 92.2 396 35.449 0.09 0.03 2014 1,173.5 89.5 1,726 181.746 0.11 0.15 2015 1,337.8 98.2 587 25.241 0.04 0.02 2016 682.8 52.4 1,443 194.755 0.13 0.29 2017 849.1 75.4 538 40.251 0.07 0.05 2018 794.3 69.4 1,284 166.908 0.13 0.21 2019 1,259.4 93.8 948 35.139 0.04 0.03 HADDAM NECK7 1969 438.5 --- 138 106 0.77 0.24 Docket 50-213; 1970 424.7 --- 734 689 0.94 1.62 DPR-61 1971 502.2 --- 289 342 1.18 0.68 1st commercial operation 1/68 1972 515.6 --- 355 325 0.92 0.63 Type - PWR 1973 293.1 --- 951 697 0.73 2.38 Capacity - (560) MWe 1974 521.4 91.2 550 201 0.37 0.39 1975 494.3 89.9 795 703 0.88 1.42 1976 482.9 82.5 644 449 0.70 0.93 1977 480.7 83.9 894 641 0.72 1.33 1978 563.4 98.6 216 117 0.54 0.21 1979 493.0 87.5 1,226 1,162 0.95 2.36 1980 426.8 75.0 1,860 1,353 0.73 3.17 1981 487.5 84.3 1,554 1,036 0.67 2.13 1982 543.9 93.4 559 126 0.23 0.23 1983 453.7 77.8 1,645 1,384 0.84 3.05 1984 404.0 71.7 1,430 1,216 0.85 3.01 1985 556.1 98.4 384 101 0.26 0.18 1986 294.8 53.6 1,945 1,567 0.81 5.32 1987 304.6 54.0 1,763 750 0.43 2.46 1988 397.4 70.3 735 237 0.32 0.60 1989 356.4 67.2 1,455 596 0.41 1.67 7

Haddam Neck (also known as Connecticut Yankee) ceased operations on December 4, 1996, and is no longer in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-17

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr HADDAM NECK7 1990 142.7 32.2 979 421 0.43 2.95 (continued) 1991 444.4 76.4 1,168 590 0.51 1.33 1992 465.2 80.1 797 202 0.25 0.43 1993 448.6 81.6 1,004 408 0.41 0.91 1994 455.6 77.7 463 135 0.29 0.30 1995 439.4 77.7 1,006 442 0.44 1.01 1996 331.8 55.7 673 175 0.26 0.53 1997 -1.3 0.0 219 11 0.05 ---

1998 0.0 0.0 423 93.743 0.22 ---

1999 0.0 0.0 545 108.602 0.20 ---

2000 0.0 0.0 555 262.192 0.47 ---

2001 0.0 0.0 361 95.348 0.26 ---

2002 0.0 0.0 258 51.668 0.20 ---

2003 0.0 0.0 400 82.022 0.21 ---

2004 0.0 0.0 564 91.981 0.16 ---

2005 0.0 0.0 350 36.479 0.10 ---

2006 0.0 0.0 124 11.883 0.10 ---

2007 0.0 0.0 0 0.000 --- ---

2008 0.0 0.0 1 0.011 0.01 ---

2009 0.0 0.0 1 0.010 0.01 ---

2010 0.0 0.0 2 0.024 0.01 ---

2011 0.0 0.0 6 0.364 0.06 ---

2012 0.0 0.0 2 0.024 0.01 ---

2013 0.0 0.0 9 0.182 0.02 ---

2014 0.0 0.0 11 0.185 0.02 ---

2015 0.0 0.0 13 0.204 0.02 ---

2016 0.0 0.0 15 0.244 0.02 ---

2017 0.0 0.0 11 0.182 0.02 ---

2018 0.0 0.0 15 0.25 0.02 ---

2019 0.0 0.0 0 0 0.00 ---

HARRIS 1 1988 652.9 75.0 721 169 0.23 0.26 Docket 50-400; 1989 690.6 79.5 929 156 0.17 0.23 NPF-63 1990 776.4 89.6 453 85 0.19 0.11 1st commercial operation 5/87 1991 724.8 81.5 872 226 0.26 0.31 Type - PWR 1992 661.8 74.9 930 213 0.23 0.32 Capacity - 964 MWe 1993 913.0 99.7 327 31 0.09 0.03 1994 740.8 82.7 1,089 222 0.20 0.30 1995 731.1 83.8 1,068 174 0.16 0.24 1996 860.6 95.4 444 17 0.04 0.02 1997 673.6 80.4 1,131 149 0.13 0.22 1998 766.2 90.4 931 133.497 0.14 0.17 1999 827.0 97.9 247 15.538 0.06 0.02 2000 783.0 92.5 888 100.981 0.11 0.13

2001 611.2 72.4 1,586 252.241 0.16 0.41 2002 892.0 99.4 145 6.674 0.05 0.01

2003 823.9 93.2 786 68.463 0.09 0.08 2004 797.9 88.2 747 57.103 0.08 0.07 2005 902.9 99.5 164 8.483 0.05 0.01 2006 802.4 89.0 917 87.225 0.10 0.11 2007 845.1 94.0 870 64.808 0.07 0.08 2008 890.4 97.4 192 10.356 0.05 0.01 2009 845.1 92.7 742 41.401 0.06 0.05 2010 808.3 89.0 1,069 82.578 0.08 0.10 2011 926.0 100.0 157 4.724 0.03 0.01 2012 810.8 87.4 1,066 79.845 0.07 0.10 2013 786.3 85.4 861 54.874 0.06 0.07 2014 918.8 97.5 52 1.275 0.02 0.00 2015 830.2 88.4 875 57.978 0.07 0.07 2016 857.7 91.1 687 43.876 0.06 0.05 2017 937.1 99.7 12 0.217 0.02 0.00 2018 866.2 90.0 596 31.736 0.05 0.04 2019 868.8 90.0 626 37.223 0.06 0.04 7

Haddam Neck (also known as Connecticut Yankee) ceased operations on December 4, 1996, and is no longer in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-18

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr HATCH 1, 2 1976 496.3 83.8 630 134 0.21 0.27 Docket 50-321, 50-366; 1977 446.8 66.3 1,303 465 0.36 1.04 DPR-57; NPF-5 1978 513.0 72.8 1,304 248 0.19 0.48 1st commercial operation 1979 401.0 54.6 2,131 582 0.27 1.45 12/75, 9/79 1980 1,008.7 70.9 1,930 449 0.23 0.45 Type - BWRs 1981 870.9 64.3 2,899 1,337 0.46 1.54 Capacity - 876, 883 MWe 1982 768.0 56.6 3,418 1,460 0.43 1.90 1983 934.7 68.6 3,428 1,299 0.38 1.39 1984 658.6 47.3 4,110 2,218 0.54 3.37 1985 1,211.0 79.6 2,841 818 0.29 0.68 1986 872.0 64.8 3,486 1,497 0.43 1.72 1987 1,295.4 89.7 2,202 816 0.37 0.63 1988 1,001.4 70.4 2,509 1,401 0.56 1.40 1989 1,271.1 87.1 1,350 556 0.41 0.44 1990 1,268.0 83.5 2,902 1,455 0.50 1.15 1991 1,152.4 77.4 2,508 1,161 0.46 1.01 1992 1,293.8 88.6 1,615 550 0.34 0.43 1993 1,189.6 85.5 1,733 669 0.39 0.56 1994 1,289.0 87.1 2,243 864 0.39 0.67 1995 1,376.3 90.6 1,458 488 0.33 0.35 1996 1,519.6 94.0 1,495 441 0.29 0.29 1997 1,374.7 88.1 1,945 722 0.37 0.53 1998 1,458.4 91.7 1,610 320.469 0.20 0.22 1999 1,487.4 90.0 1,866 328.583 0.18 0.22 2000 1,515.0 88.7 1,913 401.891 0.21 0.27 2001 1,603.0 93.5 1,407 230.242 0.16 0.14 2002 1,600.0 94.0 1,299 214.441 0.17 0.13

2003 1,606.3 94.5 1,295 168.281 0.13 0.10 2004 1,641.3 95.3 1,209 180.129 0.15 0.11 2005 1,562.1 91.3 1,288 207.295 0.16 0.13 2006 1,604.9 94.0 1,405 259.313 0.18 0.16 2007 1,626.5 94.0 1,341 137.273 0.10 0.08 2008 1,584.0 92.7 1,397 189.433 0.14 0.12 2009 1,416.5 83.2 1,310 186.013 0.14 0.13 2010 1,586.9 93.0 1,734 245.797 0.14 0.15 2011 1,550.4 93.1 1,681 176.976 0.11 0.11 2012 1,637.5 94.5 1,592 191.189 0.12 0.12 2013 1,578.1 92.1 1,348 140.994 0.10 0.09 2014 1,656.4 95.6 1,608 189.428 0.12 0.11 2015 1,654.9 95.6 1,584 83.419 0.05 0.05 2016 1,672.1 95.8 1,669 222.865 0.13 0.13 2017 1,658.8 95.7 1,126 101.422 0.09 0.06 2018 1,644.2 95.9 1,297 139.368 0.11 0.08 2019 1,588.7 92.3 1,154 94.104 0.08 0.06 HOPE CREEK 1 1987 869.2 86.4 589 117 0.20 0.13 Docket 50-354; 1988 832.7 80.7 1,734 287 0.17 0.34 NPF-57 1989 791.1 77.8 1,873 465 0.25 0.59 1st commercial operation 12/86 1990 966.4 91.6 1,394 196 0.14 0.20 Type - BWR 1991 882.5 84.2 1,700 373 0.22 0.42 Capacity - 1,172 MWe 1992 841.9 80.8 1,694 436 0.26 0.52 1993 1,049.2 97.8 688 98 0.14 0.09 1994 852.0 81.2 1,779 326 0.18 0.38 1995 844.5 79.8 1,571 196 0.12 0.23 1996 806.9 77.4 1,069 158 0.15 0.20 1997 731.8 77.8 1,747 350 0.20 0.48 1998 993.2 98.0 620 54.816 0.09 0.06 1999 879.1 86.7 1,111 279.063 0.25 0.32 2000 827.8 87.9 1,236 188.295 0.15 0.23 2001 918.2 91.1 1,532 156.180 0.10 0.17 2002 1,007.0 99.2 220 25.922 0.12 0.03

2003 826.6 84.6 1,597 139.295 0.09 0.17 C-19

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr HOPE CREEK 1 2004 688.6 71.3 2,440 239.540 0.10 0.35 (continued) 2005 874.9 88.6 881 67.063 0.08 0.08 2006 983.8 93.0 2,135 133.570 0.06 0.14 2007 929.3 91.0 2,221 191.068 0.09 0.21 2008 1,139.1 100.0 999 34.510 0.03 0.03 2009 1,111.4 93.3 2,090 169.362 0.08 0.15 2010 1,082.0 92.1 1,985 160.910 0.08 0.15 2011 1,199.3 99.4 426 24.677 0.06 0.02 2012 1,091.3 93.4 2,207 153.866 0.07 0.14 2013 1,040.3 89.7 2,019 150.568 0.07 0.14 2014 1,187.9 98.8 853 36.543 0.04 0.03 2015 1,078.9 91.7 2,915 169.862 0.06 0.16 2016 1,100.4 92.8 1,661 139.883 0.08 0.13 2017 1,216.7 100.0 412 31.919 0.08 0.03 2018 1,094.0 92.6 1,593 150.044 0.09 0.14 2019 1,000.8 89.2 1,356 169.220 0.12 0.17 HUMBOLDT BAY8 1969 44.6 --- 125 164 1.31 3.68 Docket 50-133; 1970 49.3 --- 115 209 1.82 4.24 DPR-7 1971 39.6 --- 140 292 2.09 7.37 1st commercial operation 8/63 1972 43.1 --- 127 253 1.99 5.87 Type - BWR 1973 50.1 --- 210 266 1.27 5.31 Capacity - (63) MWe 1974 43.4 83.8 296 318 1.07 7.33 1975 45.3 83.9 265 339 1.28 7.48 1976 23.5 46.4 523 683 1.31 29.06 1977 0.0 0.0 1,063 1,905 1.79 ---

1978 0.0 0.0 320 335 1.05 ---

1979 0.0 0.0 135 31 0.23 ---

1980 0.0 0.0 142 22 0.15 ---

1981 0.0 0.0 75 9 0.12 ---

1982 0.0 0.0 71 19 0.27 ---

1983 0.0 0.0 84 17 0.20 ---

1984 "Data not available" 1985 0.0 0.0 178 51 0.29 ---

1986 0.0 0.0 115 50 0.43 ---

1987 "Data not available" 1988 0.0 0.0 10 1 0.10 ---

1989 0.0 0.0 0 0 0.00 ---

1990 0.0 0.0 0 0 0.00 ---

1991 0.0 0.0 0 0 0.00 ---

1992 0.0 0.0 8 0 0.00 ---

1993 0.0 0.0 24 1 0.04 ---

1994 0.0 0.0 21 1 0.05 ---

1995 0.0 0.0 42 2 0.05 ---

1996 0.0 0.0 66 5 0.08 ---

1997 0.0 0.0 105 16 0.15 ---

1998 0.0 0.0 38 0.929 0.02 ---

1999 0.0 0.0 28 0.720 0.03 ---

2000 0.0 0.0 20 0.911 0.05 ---

2001 0.0 0.0 10 0.360 0.04 ---

2002 0.0 0.0 18 1.504 0.08 ---

2003 0.0 0.0 14 0.351 0.03 ---

2004 0.0 0.0 11 0.454 0.04 ---

2005 0.0 0.0 11 0.547 0.05 ---

2006 0.0 0.0 40 4.086 0.10 ---

2007 0.0 0.0 45 3.271 0.07 ---

2008 0.0 0.0 56 2.051 0.04 ---

2009 0.0 0.0 30 0.631 0.02 ---

2010 0.0 0.0 136 7.691 0.06 ---

2011 0.0 0.0 158 6.709 0.04 ---

8 Humboldt Bay had been shut down since 1976, and in 1983, PG&E announced its intention to decommission the unit. Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-20

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr HUMBOLDT BAY8 2012 0.0 0.0 156 15.859 0.10 ---

(continued) 2013 0.0 0.0 172 24.121 0.14 ---

2014 0.0 0.0 125 12.381 0.10 ---

2015 0.0 0.0 54 4.391 0.08 ---

2016 0.0 0.0 0 0.000 --- ---

2017 0.0 0.0 0 0.000 --- ---

2018 0.0 0.0 0 0.000 --- ---

INDIAN POINT 19, 2, 310 1969 206.2 --- --- 298 --- 1.45 Docket 50-3, 50-247, 50-286; 1970 43.3 --- --- 1,639 --- 37.85 DPR-5, DPR-26, DPR-64 1971 154.0 --- --- 768 --- 4.99 1st commercial operation 1972 142.3 --- --- 967 --- 6.80 8/62, 8/74, 8/76 1973 0.0 --- 2,998 5,262 1.76 ---

Type - PWRs 1974 556.1 59.4 1,019 910 0.89 1.64 Capacity - (265), 998, 1,030 MWe 1975 584.4 74.8 891 705 0.79 1.21 1976 273.9 34.8 1,590 1,950 1.23 7.12 1977 1,278.3 75.3 1,391 1,070 0.77 0.84 1978 1,172.3 67.8 1,909 2,006 1.05 1.71 INDIAN POINT 19, 2 1979 574.0 71.4 1,349 1,279 0.95 2.23 Docket 50-3, 50-247; 1980 510.8 64.8 1,577 971 0.62 1.90 DPR-5, DPR-26 1981 367.5 46.0 2,595 2,731 1.05 7.43 1st commercial operation 1982 532.4 65.4 2,144 1,635 0.76 3.07 10/62, 8/74 1983 702.6 84.0 1,057 486 0.46 0.69 Type - PWRs 1984 416.7 51.9 2,919 2,644 0.91 6.35 Capacity - (265), 998 MWe 1985 791.4 95.7 708 192 0.27 0.24 1986 457.5 56.2 1,926 1,250 0.65 2.73 1987 611.4 73.4 1,980 1,217 0.61 1.99 1988 719.3 86.9 890 235 0.26 0.33 1989 532.5 64.6 2,093 1,436 0.69 2.70 1990 618.0 66.6 1,061 608 0.57 0.98 1991 461.2 55.7 1,810 1,468 0.81 3.18 1992 930.9 99.1 489 97 0.20 0.10 1993 702.1 75.7 1,514 675 0.45 0.96 1994 903.8 100.0 381 48 0.13 0.05 1995 582.4 70.8 1,690 548 0.32 0.94 1996 927.8 94.8 388 54 0.14 0.06 1997 360.6 45.1 1,340 367 0.27 1.02 1998 282.8 31.5 1,154 289.600 0.25 1.02 1999 831.8 88.2 350 40.931 0.12 0.05 2000 115.4 13.0 2,003 567.224 0.28 4.92 2001 887.2 97.2 399 22.067 0.06 0.02 2002 860.0 91.3 1,361 248.487 0.18 0.29

2003 953.0 98.9 241 11.778 0.05 0.01 2004 0.0 0.0 156 3 0.02 ---

INDIAN POINT 19 2005 0.0 0.0 151 6.692 0.04 ---

Docket 50-3; 2006 0.0 0.0 193 7.670 0.04 ---

DPR-05 2007 0.0 0.0 210 2.554 0.01 ---

1st commercial operation 10/62 2008 0.0 0.0 234 4.322 0.02 ---

Type - PWR 2009 0.0 0.0 140 0.404 0.00 ---

Capacity - (265) MWe 2010 0.0 0.0 157 0.833 0.01 ---

2011 0.0 0.0 103 0.262 0.00 ---

2012 0.0 0.0 106 0.343 0.00 ---

2013 0.0 0.0 3 0.283 0.09 ---

INDIAN POINT 310 1979 574.0 66.5 808 636 0.79 1.11 Docket 50-286; 1980 367.3 53.2 977 308 0.32 0.84 DPR-64 1981 367.5 59.8 677 364 0.54 0.99 1st commercial operation 8/76 1982 171.5 22.5 1,477 1,226 0.83 7.15 Type - PWR 1983 7.8 2.6 941 607 0.65 77.82 Capacity - 1,030 MWe 1984 714.4 76.3 658 230 0.35 0.32 9

Indian Point 1 was defueled in 1975, and in 1984, it was decided that it would not be placed in operation again. Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

10 Indian Point 3 was purchased by a different utility in 1979 and subsequently reported its dose separately. Indian Point 1, 2, and 3 have been owned by the same utility since 2001 and report together.

C-21

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr INDIAN POINT 310 1985 566.5 66.0 1,093 570 0.52 1.01 (continued) 1986 655.3 73.4 588 202 0.34 0.31 1987 574.6 62.7 1,308 500 0.38 0.87 1988 792.5 83.3 451 93 0.21 0.12 1989 587.8 61.1 1,800 876 0.49 1.49 1990 595.3 62.9 1,066 358 0.34 0.60 1991 862.8 87.5 299 40 0.13 0.05 1992 561.7 61.4 1,003 212 0.21 0.38 1993 140.5 14.9 478 60 0.13 0.43 1994 0.0 0.0 529 58 0.11 ---

1995 174.8 21.4 638 67 0.11 0.38 1996 695.3 74.8 289 22 0.08 0.03 1997 495.1 54.9 1,608 234 0.15 0.47 1998 874.0 95.3 213 14.774 0.07 0.02 1999 829.8 88.3 893 116.920 0.13 0.14 2000 960.0 99.3 143 8.693 0.06 0.01 2001 903.9 93.1 1,014 118.115 0.12 0.13 2002 960.0 98.5 156 6.797 0.04 0.01

2003 866.2 89.8 902 96.059 0.11 0.11 INDIAN POINT 2, 310 2004 1,851.1 191.0 1,370 199.862 0.15 0.11 Docket 50-247, 50-286; 2005 1,922.2 191.7 1,363 85.280 0.06 0.04 DPR-26, DPR-64 2006 1,936.0 191.0 1,634 289.701 0.18 0.15 1st commercial operation 2007 1,899.3 188.0 1,971 109.969 0.06 0.06 8/74, 8/76 2008 1,977.2 192.6 1,456 142.728 0.10 0.07 Type - PWRs 2009 1,884.2 187.5 1,853 79.090 0.04 0.04 Capacity - 998, 1,030 MWe 2010 1,859.2 183.6 1,962 200.382 0.10 0.11 2011 1,938.8 95.1 1,185 63.267 0.05 0.03 2012 1,921.0 94.7 1,289 109.807 0.09 0.06 2013 1,946.6 95.6 1,297 74.038 0.06 0.04 2014 1,973.1 96.5 1,313 142.195 0.11 0.07 2015 1,870.1 92.6 1,277 60.475 0.05 0.03 2016 1,723.7 85.9 958 72.915 0.08 0.04 2017 1,740.7 86.6 1,899 102.735 0.05 0.06 2018 1,863.6 92.0 1,624 88.211 0.05 0.05 2019 1,905.9 93.7 1,552 51.414 0.03 0.03 KEWAUNEE11 1975 401.9 88.2 104 28 0.27 0.07 Docket 50-305; 1976 405.9 78.9 381 270 0.71 0.67 DPR-43 1977 425.0 79.9 312 140 0.45 0.33 1st commercial operation 6/74 1978 466.6 89.5 335 154 0.46 0.33 Type - PWR 1979 412.0 79.0 343 127 0.37 0.31 Capacity - (556) MWe 1980 433.8 82.1 401 165 0.41 0.38 1981 451.8 86.7 383 141 0.37 0.31 1982 458.4 87.6 353 101 0.29 0.22 1983 444.1 83.7 445 165 0.37 0.37 1984 455.3 85.7 482 139 0.29 0.31 1985 443.1 82.4 519 176 0.34 0.40 1986 461.7 85.8 502 169 0.34 0.37 1987 480.0 89.7 755 226 0.30 0.47 1988 467.5 88.3 705 210 0.30 0.45 1989 449.1 84.9 570 239 0.42 0.53 1990 468.8 87.9 490 145 0.30 0.31 1991 441.8 83.4 495 221 0.45 0.50 1992 471.4 88.0 450 122 0.27 0.26 1993 457.1 86.8 436 106 0.24 0.23 1994 475.6 88.8 364 72 0.20 0.15 1995 455.6 87.8 415 109 0.26 0.24 1996 380.4 71.8 474 126 0.27 0.33 1997 269.8 56.0 278 56 0.20 0.21 1998 423.0 87.2 384 88.205 0.23 0.21 1999 505.1 100.0 103 5.055 0.05 0.01 10 Indian Point 3 was purchased by a different utility in 1979 and subsequently reported its dose separately. Indian Point 1, 2, and 3 have been owned by the same utility since 2001 and report together.

11 Kewaunee ceased operations in May 2013 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-22

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr KEWAUNEE11 2000 432.6 88.8 394 99.864 0.25 0.23 (continued) 2001 394.1 80.8 1,110 200.245 0.18 0.51 2002 509.0 97.4 102 4.449 0.04 0.01

2003 473.5 90.5 439 73.108 0.17 0.15 2004 441.0 81.0 565 91.168 0.16 0.21 2005 346.4 62.7 97 4.000 0.04 0.01 2006 419.4 77.0 539 74.734 0.14 0.18 2007 528.0 95.0 145 11.126 0.08 0.02 2008 499.5 88.9 598 92.951 0.16 0.19 2009 515.4 92.0 595 56.215 0.09 0.11 2010 569.7 100.0 135 4.690 0.03 0.01 2011 524.5 92.3 757 79.396 0.10 0.15 2012 514.1 90.9 585 39.093 0.07 0.08 2013 0.0 0.0 114 4.915 0.04 ---

2014 0.0 0.0 57 1.964 0.03 ---

2015 0.0 0.0 7 0.156 0.02 ---

2016 0.0 0.0 5 0.092 0.02 ---

2017 0.0 0.0 64 6.167 0.10 ---

2018 0.0 0.0 8 1.002 0.13 ---

2019 0.0 0.0 2 0.021 0.01 ---

LA CROSSE12 1970 15.3 --- --- 111 --- 7.25 Docket 50-409; 1971 33.1 --- 218 158 0.72 4.77 DPR-45 1972 29.2 --- 151 172 1.14 5.89 1st commercial operation 11/69 1973 24.4 --- 157 221 1.41 9.06 Type - BWR 1974 37.9 81.0 115 139 1.21 3.67 Capacity - (48) MWe 1975 32.0 69.6 165 234 1.42 7.31 1976 21.2 47.6 118 110 0.93 5.19 1977 11.3 33.7 141 225 1.60 19.91 1978 21.6 62.0 182 164 0.90 7.59 1979 24.0 71.8 153 186 1.22 7.75 1980 26.4 68.5 124 218 1.76 8.26 1981 29.6 76.0 187 123 0.66 4.16 1982 17.2 44.6 148 205 1.39 11.92 1983 24.8 59.7 160 313 1.96 12.62 1984 38.5 80.5 288 252 0.88 6.55 1985 39.2 86.7 373 173 0.46 4.41 1986 19.6 46.1 260 290 1.12 14.80 1987 0.0 0.0 127 68 0.54 ---

1988 0.0 0.0 49 31 0.63 ---

1989 0.0 0.0 60 15 0.25 ---

1990 0.0 0.0 51 9 0.18 ---

1991 0.0 0.0 42 8 0.19 ---

1992 0.0 0.0 28 6 0.21 ---

1993 0.0 0.0 48 8 0.17 ---

1994 0.0 0.0 65 8 0.12 ---

1995 0.0 0.0 31 3 0.10 ---

1996 0.0 0.0 25 4 0.16 ---

1997 0.0 0.0 23 2 0.09 ---

1998 0.0 0.0 27 1.530 0.06 ---

1999 0.0 0.0 66 3.725 0.06 ---

2000 0.0 0.0 37 3.548 0.10 ---

2001 0.0 0.0 45 2.782 0.06 ---

2002 0.0 0.0 47 2.314 0.05 ---

2003 0.0 0.0 65 1.836 0.03 ---

2004 0.0 0.0 56 0.918 0.02 ---

2005 0.0 0.0 51 8.139 0.16 ---

2006 0.0 0.0 0 0.000 --- ---

2007 0.0 0.0 86 37.092 0.43 ---

2008 0.0 0.0 40 1.759 0.04 ---

2009 0.0 0.0 48 1.307 0.03 ---

11 Kewaunee ceased operations in May 2013 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

12 La Crosse ceased operations in 1987 and will not be put in commercial operation again. Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-23

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr LA CROSSE12 2010 0.0 0.0 78 2.971 0.04 ---

(continued) 2011 0.0 0.0 110 5.296 0.05 ---

2012 0.0 0.0 100 7.652 0.08 ---

2013 0.0 0.0 51 3.411 0.07 ---

2014 0.0 0.0 59 5.499 0.09 ---

2015 0.0 0.0 22 1.587 0.07 ---

2016 0.0 0.0 34 3.904 0.11 ---

2017 0.0 0.0 58 6.356 0.11 ---

2018 0.0 0.0 21 0.633 0.03 ---

2019 0.0 0.0 0 0.000 0.00 ---

LASALLE 1, 2 1984 677.8 77.8 1,245 252 0.20 0.37 Docket 50-373, 50-374; 1985 987.9 53.0 1,635 685 0.42 0.69 NPF-11, NPF-18 1986 929.5 50.6 1,614 898 0.56 0.97 1st commercial operation 1987 1,030.0 59.3 1,744 1,396 0.80 1.36 1/84, 6/84 1988 1,317.6 71.6 2,737 2,471 0.90 1.88 Type - BWRs 1989 1,503.5 73.1 2,475 1,386 0.56 0.92 Capacity - 1,111, 1,111 MWe 1990 1,754.3 84.6 1,830 948 0.52 0.54 1991 1,837.0 86.7 1,985 806 0.41 0.44 1992 1,447.4 72.0 2,418 1,167 0.48 0.81 1993 1,542.0 76.0 1,701 854 0.50 0.55 1994 1,580.0 77.6 1,812 726 0.40 0.46 1995 1,696.6 82.1 1,623 512 0.32 0.30 1996 1,053.8 54.3 2,782 819 0.29 0.78 1997 0.0 0.0 1,661 316 0.19 ---

1998 380.9 19.3 2,099 422.249 0.20 1.11 1999 1,671.9 81.8 2,689 576.354 0.21 0.34 2000 2,138.6 97.1 1,831 260.320 0.14 0.12 2001 2,223.8 98.9 535 82.721 0.15 0.04 2002 2,040.0 92.1 2,012 449.587 0.22 0.22

2003 2,100.2 94.8 2,253 464.427 0.21 0.22 2004 2,162.1 96.0 2,366 359.470 0.15 0.17

2005 2,130.4 95.0 2,097 334.558 0.16 0.16 2006 2,181.3 97.0 2,006 248.454 0.12 0.11 2007 2,166.7 98.0 1,953 228.373 0.12 0.11 2008 2,145.8 96.4 2,402 217.567 0.09 0.10 2009 2,141.0 95.7 1,986 296.659 0.15 0.14 2010 2,184.1 96.5 2,386 384.434 0.16 0.18 2011 2,198.2 96.1 2,805 340.529 0.12 0.15 2012 2,230.8 96.9 1,973 224.711 0.11 0.10 2013 2,141.6 94.1 1,960 383.622 0.20 0.18 2014 2,141.0 94.0 2,151 366.524 0.17 0.17 2015 2,132.9 95.7 2,492 501.666 0.20 0.24 2016 2,185.5 96.0 2,653 338.985 0.13 0.16 2017 2,158.5 94.5 2,824 570.389 0.20 0.26 2018 2,214.7 96.3 2,923 349.268 0.12 0.16 2019 2,218.6 97.1 2,295 309.129 0.13 0.14 LIMERICK 1, 2 1987 636.1 70.2 2,156 174 0.08 0.27 Docket 50-352, 50-353; 1988 794.9 96.5 950 52 0.05 0.07 NPF-39, NPF-85 1989 628.4 66.0 1,818 266 0.15 0.42 1st commercial operation 1990 1,527.7 78.2 1,422 175 0.12 0.11 2/86, 1/90 1991 1,810.9 86.8 1,151 106 0.09 0.06 Type - BWRs 1992 1,741.4 84.8 1,559 330 0.21 0.19 Capacity - 1,099, 1,108 MWe 1993 1,913.2 91.6 1,287 217 0.17 0.11 1994 1,944.4 94.9 1,543 275 0.18 0.14 1995 1,957.1 93.0 1,581 260 0.16 0.13 1996 2,026.2 93.3 1,654 234 0.14 0.12 1997 2,001.7 95.8 1,463 234 0.16 0.12 1998 1,907.2 89.5 1,854 357.139 0.19 0.19 1999 2,089.6 94.2 1,800 271.547 0.15 0.13 2000 2,154.9 95.8 1,279 260.611 0.20 0.12 2001 2,205.9 97.3 1,127 210.336 0.19 0.10 2002 2,197.0 97.1 1,248 160.324 0.13 0.07

12 La Crosse ceased operations in 1987 and will not be put in commercial operation again. Therefore, it is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-24

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr LIMERICK 1, 2 2003 2,213.6 97.2 1,298 147.047 0.11 0.07 (continued) 2004 2,218.9 97.6 1,265 149.433 0.12 0.07 2005 2,168.9 96.3 1,460 187.609 0.13 0.09 2006 2,207.2 97.0 1,509 193.429 0.13 0.09 2007 2,185.8 96.0 1,570 197.104 0.13 0.09 2008 2,169.2 96.0 1,393 176.825 0.13 0.08 2009 2,211.4 97.2 1,606 234.742 0.15 0.11 2010 2,165.2 96.7 1,525 167.797 0.11 0.08 2011 2,112.7 94.5 2,007 184.415 0.09 0.09 2012 2,071.4 92.8 2,011 159.812 0.08 0.08 2013 2,235.7 96.8 1,663 133.531 0.08 0.06 2014 2,182.1 94.8 1,523 138.396 0.09 0.06 2015 2,165.6 95.9 1,516 124.787 0.08 0.06 2016 2,219.1 96.3 1,626 126.799 0.08 0.06 2017 2,123.1 93.4 1,808 183.736 0.10 0.09 2018 2,214.9 97.2 1,676 121.053 0.07 0.05 2019 2,213.1 97.2 1,906 157.471 0.08 0.07 MAINE YANKEE13 1973 408.7 --- 782 117 0.15 0.29 Docket 50-309; 1974 432.6 68.7 619 420 0.68 0.97 DPR-36 1975 542.9 79.9 440 319 0.73 0.59 1st commercial operation 12/72 1976 712.2 95.0 244 85 0.35 0.12 Type - PWR 1977 617.6 82.2 508 245 0.48 0.40 Capacity - (860) MWe 1978 642.7 84.1 638 420 0.66 0.65 1979 537.0 68.4 393 154 0.39 0.29 1980 527.0 72.2 735 462 0.63 0.88 1981 624.2 78.2 868 424 0.49 0.68 1982 542.5 69.1 1,295 619 0.48 1.14 1983 677.1 83.6 592 165 0.28 0.24 1984 605.7 74.4 1,262 884 0.70 1.46 1985 635.4 79.2 1,009 700 0.69 1.10 1986 737.6 87.8 495 100 0.20 0.14 1987 478.1 65.3 1,100 722 0.66 1.51 1988 591.9 79.1 1,058 725 0.69 1.22 1989 819.2 93.7 375 99 0.26 0.12 1990 573.0 71.0 1,359 682 0.50 1.19 1991 738.1 86.6 426 105 0.25 0.14 1992 631.7 79.1 1,189 461 0.39 0.73 1993 674.8 79.8 1,016 377 0.37 0.56 1994 782.8 90.9 297 84 0.28 0.11 1995 23.6 3.7 1,167 653 0.56 27.67 1996 602.9 78.1 408 56 0.14 0.09 1997 0.0 0.0 991 153 0.15 ---

1998 0.0 0.0 438 163.008 0.37 ---

1999 0.0 0.0 365 135.057 0.37 ---

2000 0.0 0.0 490 121.133 0.25 ---

2001 0.0 0.0 412 68.121 0.17 ---

2002 0.0 0.0 452 66.226 0.15 ---

2003 0.0 0.0 342 43.775 0.13 ---

2004 0.0 0.0 190 21.313 0.11 ---

2005 0.0 0.0 2 0.048 0.02 ---

2006 0.0 0.0 0 0.000 --- ---

2007 0.0 0.0 0 0.000 --- ---

2008 0.0 0.0 1 0.013 0.01 ---

2009 0.0 0.0 3 0.137 0.05 ---

2010 0.0 0.0 1 0.084 0.08 ---

2011 0.0 0.0 2 0.060 0.03 ---

2012 0.0 0.0 6 0.238 0.04 ---

2013 0.0 0.0 4 0.186 0.05 ---

2014 0.0 0.0 3 0.079 0.03 ---

2015 0.0 0.0 9 0.176 0.02 ---

2016 0.0 0.0 2 0.038 0.02 ---

13 Maine Yankee ceased operations in August 1997 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-25

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr MAINE YANKEE13 2017 0.0 0.0 3 0.054 0.02 ---

(continued) 2018 0.0 0.0 6 0.089 0.01 ---

2019 0.0 0.0 14 0.188 0.01 ---

MCGUIRE 1, 2 1982 524.9 80.4 1,560 169 0.11 0.32 Docket 50-369, 50-370; 1983 558.3 55.4 1,751 521 0.30 0.93 NPF-9, NPF-17 1984 764.1 68.5 1,663 507 0.30 0.66 1st commercial operation 1985 808.4 77.0 2,217 771 0.35 0.95 12/81, 3/84 1986 1,360.0 60.1 2,326 1,015 0.44 0.75 Type - PWRs 1987 1,774.7 79.2 2,865 1,043 0.36 0.59 Capacity - 1,158, 1,158 MWe 1988 1,830.7 80.2 2,808 1,104 0.39 0.60 1989 1,810.2 80.8 1,994 620 0.31 0.34 1990 1,340.3 61.3 2,289 727 0.32 0.54 1991 1,945.1 85.0 1,723 361 0.21 0.19 1992 1,696.8 74.4 1,619 418 0.26 0.25 1993 1,470.4 66.2 1,685 463 0.27 0.31 1994 1,848.0 80.2 1,637 397 0.24 0.21 1995 2,132.3 92.9 1,259 138 0.11 0.06 1996 1,881.8 82.8 1,622 238 0.15 0.13 1997 1,558.2 73.0 2,193 492 0.22 0.32 1998 2,139.8 95.1 1,045 142.245 0.14 0.07 1999 1,961.7 88.9 1,274 256.524 0.20 0.13 2000 2,100.1 94.2 940 132.513 0.14 0.06 2001 2,113.3 93.9 963 136.581 0.14 0.06 2002 2,051.0 91.7 1,167 180.618 0.15 0.09

2003 2,156.2 96.0 841 71.323 0.08 0.03 2004 2,075.7 91.8 1,116 196.193 0.18 0.09 2005 1,993.9 89.2 1,401 173.972 0.12 0.09 2006 2,100.2 93.0 1,218 108.285 0.09 0.05 2007 2,011.4 89.0 1,375 156.035 0.11 0.08 2008 1,943.3 86.2 1,613 165.767 0.10 0.09 2009 2,170.6 95.3 1,165 79.773 0.07 0.04 2010 2,151.9 94.8 1,225 81.321 0.07 0.04 2011 2,038.3 89.9 1,648 119.637 0.07 0.06 2012 2,045.6 90.4 1,222 62.690 0.05 0.03 2013 2,157.3 94.4 1,447 109.423 0.08 0.05 2014 2,008.0 87.0 1,760 138.257 0.08 0.07 2015 2,230.1 95.5 1,074 49.399 0.05 0.02 2016 2,269.9 96.1 1,201 67.654 0.06 0.03 2017 2,145.6 92.0 1,607 147.589 0.09 0.07 2018 2,267.4 96.2 881 40.005 0.05 0.02 2019 2,236.1 96.6 858 54.230 0.06 0.02 MILLSTONE 114 1972 377.6 --- 612 596 0.97 1.58 Docket 50-245; 1973 225.1 --- 1,184 663 0.56 2.95 DPR-21 1974 430.3 79.1 2,477 1,430 0.58 3.32 1st commercial operation 3/71 1975 465.4 75.6 2,587 2,022 0.78 4.34 Type - BWR 1976 449.8 76.1 1,387 1,194 0.86 2.65 Capacity - (641) MWe 1977 575.7 89.6 1,075 394 0.37 0.68 1978 556.6 87.6 1,391 1,416 1.02 2.54 1979 505.0 77.3 2,001 1,795 0.90 3.55 1980 405.8 69.0 3,024 2,157 0.71 5.32 1981 304.3 51.6 2,506 1,496 0.60 4.92 1982 490.2 79.9 1,370 929 0.68 1.90 1983 640.1 95.6 309 244 0.79 0.38 1984 516.1 78.8 1,992 836 0.42 1.62 1985 548.5 83.6 732 608 0.83 1.11 1986 626.8 95.4 389 150 0.39 0.24 1987 523.4 79.6 1,588 684 0.43 1.31 1988 658.8 98.6 327 144 0.44 0.22 13 Maine Yankee ceased operations in August 1997 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

14 Millstone 1 ceased operations in 1998 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational. From 2008-2014, Millstone 1 voluntarily provided an estimate of the collective dose for Unit 1, but not the number of individuals with measurable dose.

C-26

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr MILLSTONE 114 1989 554.6 84.2 852 462 0.54 0.83 (continued) 1990 608.3 91.6 365 131 0.36 0.22 1991 213.1 35.4 1,154 409 0.35 1.92 1992 431.8 68.1 348 99 0.28 0.23 1993 627.9 96.8 305 81 0.27 0.13 1994 394.0 63.6 1,321 391 0.30 0.99 1995 520.6 80.0 910 620 0.68 1.19 1996 0.0 0.0 747 431 0.58 ---

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

1998 -2.7 0.0 347 12.741 0.04 ---

1999 0.0 0.0 397 9.790 0.02 ---

2000 0.0 0.0 478 59.955 0.13 ---

2001 0.0 0.0 414 14.946 0.04 ---

2002 0.0 0.0 185 4.151 0.02 ---

2003 0.0 0.0 195 10.675 0.05 ---

2004 0.0 0.0 147 11.152 0.08 ---

2005 0.0 0.0 145 0.897 0.01 ---

2006 0.0 0.0 4 0.607 0.15 ---

2007 0.0 0.0 33 0.901 0.03 ---

2008 0.0 0.0 0 0.222 --- ---

2009 0.0 0.0 0 0.114 --- ---

2010 0.0 0.0 0 0.142 --- ---

2011 0.0 0.0 0 0.265 --- ---

2012 0.0 0.0 0 0.137 --- ---

2013 0.0 0.0 0 0.313 --- ---

2014 0.0 0.0 0 0.313 --- ---

2015 0.0 0.0 0 0.000 --- ---

2016 0.0 0.0 0 0.000 --- ---

2017 0.0 0.0 0 0.000 --- ---

MILLSTONE 2, 3 1976 545.7 78.7 620 168 0.27 0.31 Docket 50-336, 50-423; 1977 518.7 65.7 667 242 0.36 0.47 DPR-65; NPF-49 1978 536.6 67.3 1,420 1,444 1.02 2.69 1st commercial operation 1979 520.0 62.8 525 471 0.90 0.91 12/75, 4/86 1980 579.3 69.2 893 637 0.71 1.10 Type - PWRs 1981 722.4 82.6 890 531 0.60 0.74 Capacity - 870, 1,210 MWe 1982 595.9 70.6 2,083 1,413 0.68 2.37 1983 294.0 34.2 2,383 1,881 0.79 6.40 1984 782.7 93.5 285 120 0.42 0.15 1985 417.8 49.4 1,905 1,581 0.83 3.78 1986 1,313.8 80.4 2,393 993 0.41 0.76 1987 1,624.5 84.1 1,441 505 0.35 0.31 1988 1,594.8 83.2 1,827 804 0.44 0.50 1989 1,428.3 72.9 1,984 1,079 0.54 0.76 1990 1,614.9 87.1 1,652 593 0.36 0.37 1991 819.5 69.7 1,084 381 0.35 0.46 1992 1,115.1 59.9 3,190 1,280 0.40 1.15 1993 1,525.2 79.7 2,064 557 0.27 0.37 1994 1,556.6 73.1 1,249 188 0.15 0.12 1995 1,278.1 60.5 1,691 416 0.25 0.33 1996 418.1 19.3 983 126 0.13 0.30 1997 0.0 0.0 1,435 253 0.18 ---

1998 374.9 20.9 1,179 112.543 0.10 0.30 1999 1,446.3 73.3 1,688 252.138 0.15 0.17 2000 1,865.8 92.4 1,385 142.664 0.10 0.08 2001 1,759.3 92.0 1,327 174.238 0.13 0.10 2002 1,703.0 87.5 1,548 292.197 0.19 0.17 2003 1,834.6 91.0 1,274 322.923 0.25 0.18 2004 1,887.5 95.0 803 136.459 0.17 0.07 2005 1,777.1 88.8 1,329 202.490 0.15 0.11 2006 1,898.5 93.0 1,160 174.164 0.15 0.09 2007 1,875.1 94.0 1,150 163.780 0.14 0.09 2008 1,761.1 87.7 1,467 272.693 0.19 0.15 14 Millstone 1 ceased operations in 1998 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational. From 2008-2014, Millstone 1 voluntarily provided an estimate of the collective dose for Unit 1, but not the number of individuals with measurable dose.

C-27

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr MILLSTONE 2, 3 2009 1,906.1 89.6 983 159.203 0.16 0.08 (continued) 2010 1,916.8 93.1 718 81.589 0.11 0.04 2011 1,822.7 87.7 1,044 169.417 0.16 0.09 2012 1,948.9 92.2 726 73.270 0.10 0.04 2013 1,954.5 94.6 747 64.232 0.09 0.03 2014 1,812.7 87.5 1,250 160.502 0.13 0.09 2015 1,992.4 95.0 818 63.940 0.08 0.03 2016 1,896.1 93.1 856 64.125 0.07 0.03 2017 1,888.0 91.2 1,118 112.598 0.10 0.06 2018 1,931.7 91.5 777 66.110 0.09 0.03 2019 1,914.9 94.8 715 47.673 0.07 0.02 MONTICELLO 1972 424.4 --- 99 61 0.62 0.14 Docket 50-263; 1973 389.5 --- 401 176 0.44 0.45 DPR-22 1974 349.3 74.9 842 349 0.41 1.00 1st commercial operation 6/71 1975 344.8 72.2 1,353 1,353 1.00 3.92 Type - BWR 1976 476.4 91.5 325 263 0.81 0.55 Capacity - 628 MWe 1977 425.6 79.9 860 1,000 1.16 2.35 1978 459.4 87.2 679 375 0.55 0.82 1979 522.0 97.6 372 157 0.42 0.30 1980 411.8 78.2 1,114 531 0.48 1.29 1981 389.3 72.6 1,446 1,004 0.69 2.58 1982 291.1 63.3 1,307 993 0.76 3.41 1983 494.6 96.3 416 121 0.29 0.24 1984 33.7 9.2 1,872 2,462 1.32 73.06 1985 509.8 91.7 586 327 0.56 0.64 1986 402.7 79.1 895 596 0.67 1.48 1987 422.5 81.9 941 568 0.60 1.34 1988 542.5 99.8 375 110 0.29 0.20 1989 318.2 76.2 1,102 507 0.46 1.59 1990 536.0 96.9 336 94 0.28 0.18 1991 429.4 80.8 964 465 0.48 1.08 1992 528.3 97.5 454 114 0.25 0.22 1993 458.1 84.4 954 494 0.52 1.08 1994 471.3 87.0 788 395 0.50 0.84 1995 564.7 100.0 200 44 0.22 0.08 1996 461.6 86.9 757 240 0.32 0.52 1997 417.4 75.9 399 106 0.27 0.25 1998 470.2 88.1 674 209.137 0.31 0.44 1999 530.7 92.9 451 70.075 0.16 0.13 2000 483.2 84.2 792 216.136 0.27 0.45 2001 441.3 78.5 834 220.683 0.26 0.50 2002 571.0 99.0 399 40.030 0.10 0.07 2003 522.8 91.7 858 168.896 0.20 0.32 2004 573.2 99.2 279 35.081 0.13 0.06 2005 509.4 90.0 919 175.201 0.19 0.34 2006 579.1 100.0 273 33.416 0.12 0.06 2007 478.6 85.0 1,075 191.398 0.18 0.40 2008 555.3 95.8 351 43.777 0.12 0.08 2009 473.1 85.2 1,235 173.624 0.14 0.37 2010 536.0 98.5 534 56.116 0.11 0.10 2011 383.4 71.3 1,903 236.997 0.12 0.62 2012 556.7 98.6 528 38.786 0.07 0.07 2013 342.3 62.5 1,247 198.968 0.16 0.58 2014 493.6 95.0 282 35.306 0.13 0.07 2015 532.4 85.5 846 130.057 0.15 0.24 2016 639.0 100.0 313 28.547 0.09 0.04 2017 589.0 92.2 815 115.814 0.14 0.20 2018 641.3 100.0 273 29.238 0.11 0.05 2019 566.7 91.9 1,055 128.425 0.12 0.23 C-28

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr NINE MILE POINT 1, 2 1970 227.0 --- 821 44 0.05 0.19 Docket 50-220, 50-410; 1971 346.5 --- 1,006 195 0.19 0.56 DPR-63; NPF-69 1972 381.8 --- 735 285 0.39 0.75 1st commercial operation 1973 411.0 --- 550 567 1.03 1.38 12/69, 4/88 1974 385.9 70.5 740 824 1.11 2.14 Type - BWRs 1975 359.0 72.1 649 681 1.05 1.90 Capacity - 565, 1,277 MWe 1976 484.6 88.2 392 428 1.09 0.88 1977 347.4 59.2 1,093 1,383 1.27 3.98 1978 527.7 95.1 561 314 0.56 0.60 1979 354.0 66.1 1,326 1,497 1.13 4.23 1980 533.9 92.3 1,174 591 0.50 1.11 1981 385.2 66.0 2,029 1,592 0.78 4.13 1982 133.5 21.4 1,352 1,264 0.93 9.47 1983 329.8 56.2 1,405 860 0.61 2.61 1984 426.8 71.9 1,530 890 0.58 2.09 1985 580.9 96.4 1,007 265 0.26 0.46 1986 371.0 65.3 1,878 1,275 0.68 3.44 1987 542.6 93.3 1,190 141 0.12 0.26 1988 0.0 0.0 2,626 854 0.33 ---

1989 527.5 29.7 2,737 564 0.21 1.07 1990 656.2 46.6 2,405 699 0.29 1.07 1991 1,250.8 79.7 1,543 292 0.19 0.23 1992 965.9 61.8 1,800 563 0.31 0.58 1993 1,380.2 84.6 2,352 633 0.27 0.46 1994 1,589.6 95.9 800 149 0.19 0.09 1995 1,382.2 82.5 2,304 759 0.33 0.55 1996 1,598.6 91.6 1,596 290 0.18 0.18 1997 1,321.5 74.8 1,425 429 0.30 0.32 1998 1,387.3 87.0 1,744 378.484 0.22 0.27 1999 1,409.5 81.3 1,709 446.699 0.26 0.32 2000 1,443.9 88.1 1,783 282.838 0.16 0.20 2001 1,506.9 88.9 1,371 343.197 0.25 0.23 2002 1,517.0 90.4 2,449 516.663 0.21 0.34 2003 1,585.6 91.4 1,501 374.775 0.25 0.24 2004 1,551.9 92.0 1,362 448.509 0.33 0.29 2005 1,656.5 94.5 1,366 401.719 0.29 0.24 2006 1,647.1 96.0 1,130 229.551 0.20 0.14 2007 1,598.3 93.0 1,826 329.307 0.18 0.21 2008 1,642.1 95.8 1,391 301.824 0.22 0.18 2009 1,706.2 97.1 1,456 237.552 0.16 0.14 2010 1,627.1 95.2 1,703 375.424 0.22 0.23 2011 1,616.8 92.5 1,362 244.395 0.18 0.15 2012 1,504.6 87.3 1,764 407.900 0.23 0.27 2013 1,804.9 95.0 1,411 217.056 0.15 0.12 2014 1,737.8 94.7 1,483 263.710 0.18 0.15 2015 1,823.7 95.7 1,604 160.380 0.10 0.09 2016 1,765.5 95.1 1,679 256.794 0.15 0.15 2017 1,827.3 97.2 1,401 141.150 0.10 0.08 2018 1,758.9 95.8 1,905 385.491 0.20 0.22 2019 1,777.2 94.2 1,338 151.719 0.11 0.09 NORTH ANNA 1, 2 1979 507.0 61.7 2,025 449 0.22 0.89 Docket 50-338, 50-339; 1980 681.8 86.5 2,086 218 0.10 0.32 NPF-4, NPF-7 1981 1,241.9 71.5 2,416 680 0.28 0.55 1st commercial operation 1982 777.7 45.8 2,872 1,915 0.67 2.46 6/78, 12/80 1983 1,338.4 76.1 2,228 665 0.30 0.50 Type - PWRs 1984 1,021.3 58.8 3,062 1,945 0.64 1.90 Capacity - 948, 944 MWe 1985 1,516.9 86.1 2,436 838 0.34 0.55 1986 1,484.5 83.0 2,831 722 0.26 0.49 1987 1,112.6 67.8 2,624 1,521 0.58 1.37 1988 1,772.7 96.7 992 112 0.11 0.06 1989 1,226.8 72.5 2,861 1,471 0.51 1.20 1990 1,590.4 90.5 2,161 590 0.27 0.37 1991 1,597.5 88.6 2,085 629 0.30 0.39 C-29

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr NORTH ANNA 1, 2 1992 1,403.2 84.1 2,159 576 0.27 0.41 (continued) 1993 1,428.4 80.1 2,768 908 0.33 0.64 1994 1,717.1 95.9 1,036 193 0.19 0.11 1995 1,666.4 90.8 1,551 367 0.24 0.22 1996 1,569.6 89.1 1,203 291 0.24 0.19 1997 1,711.5 96.2 856 103 0.12 0.06 1998 1,632.8 92.7 1,201 265.922 0.22 0.16 1999 1,747.7 96.1 727 94.402 0.13 0.05 2000 1,734.1 95.8 730 65.405 0.09 0.04 2001 1,491.0 84.8 1,231 308.907 0.25 0.21 2002 1,557.0 84.3 914 143.312 0.16 0.09 2003 1,569.1 87.2 1,041 187.014 0.18 0.12 2004 1,685.6 92.0 965 129.686 0.13 0.08 2005 1,751.5 96.0 686 58.844 0.09 0.03 2006 1,723.0 95.0 749 82.069 0.11 0.05 2007 1,596.7 88.0 1,581 309.237 0.20 0.19 2008 1,643.1 91.2 795 61.003 0.08 0.04 2009 1,735.5 95.6 745 78.126 0.10 0.05 2010 1,529.6 84.9 1,032 182.289 0.18 0.12 2011 1,429.1 76.5 792 90.763 0.11 0.06 2012 1,745.6 91.4 762 106.518 0.14 0.06 2013 1,712.9 89.2 948 121.803 0.13 0.07 2014 1,813.8 94.1 753 71.914 0.10 0.04 2015 1,857.4 96.6 663 43.838 0.07 0.02 2016 1,726.2 90.0 1,109 119.339 0.11 0.07 2017 1,840.9 95.6 678 44.884 0.07 0.02 2018 1,826.2 95.1 796 56.845 0.07 0.03 2019 1,749.4 91.9 837 95.288 0.11 0.05 OCONEE 1, 2, 3 1974 650.6 60.1 844 517 0.61 0.79 Docket 50-269, 50-270, 50-287; 1975 1,838.3 75.5 829 497 0.60 0.27 DPR-38, DPR-47, DPR-55 1976 1,561.4 63.0 1,215 1,026 0.84 0.66 1st commercial operation 1977 1,566.4 65.9 1,595 1,329 0.83 0.85 7/73, 9/74, 12/74 1978 1,909.0 75.8 1,636 1,393 0.85 0.73 Type - PWRs 1979 1,708.0 67.7 2,100 1,001 0.48 0.59 Capacity - 847, 848, 859 MWe 1980 1,703.7 70.1 2,124 1,055 0.50 0.62 1981 1,661.5 66.8 2,445 1,211 0.50 0.73 1982 1,293.1 52.5 2,445 1,792 0.73 1.39 1983 2,141.5 82.2 1,902 1,207 0.63 0.56 1984 2,242.9 85.7 2,085 1,106 0.53 0.49 1985 2,036.3 80.5 2,729 1,304 0.48 0.64 1986 1,995.6 79.0 2,499 949 0.38 0.48 1987 1,962.6 82.4 2,672 1,142 0.43 0.58 1988 2,228.9 87.2 2,672 871 0.33 0.39 1989 2,188.6 85.4 2,205 684 0.31 0.31 1990 2,405.2 91.4 1,948 404 0.21 0.17 1991 2,275.0 86.7 1,966 551 0.28 0.24 1992 2,110.7 82.0 1,954 612 0.31 0.29 1993 2,399.2 91.3 1,499 237 0.16 0.10 1994 2,144.3 82.2 1,923 537 0.28 0.25 1995 2,366.1 89.5 1,586 304 0.19 0.13 1996 1,847.9 70.3 1,479 257 0.17 0.14 1997 1,563.7 67.7 1,379 223 0.16 0.14 1998 1,989.1 81.3 1,695 366.028 0.22 0.18 1999 2,264.5 90.3 1,568 202.025 0.13 0.09 2000 2,321.0 91.6 1,686 272.697 0.16 0.12 2001 2,167.6 86.8 2,002 579.209 0.29 0.27 2002 2,355.0 92.5 1,723 224.672 0.13 0.10 2003 2,177.7 86.3 2,180 245.349 0.11 0.11 2004 2,125.2 84.1 2,295 367.891 0.16 0.17 2005 2,349.5 92.3 1,516 148.694 0.10 0.06 2006 2,274.8 90.0 1,859 221.222 0.12 0.10 2007 2,347.8 92.0 1,915 252.936 0.13 0.11 2008 2,298.5 90.9 1,924 186.335 0.10 0.08 2009 2,385.7 92.6 1,830 180.868 0.10 0.08 C-30

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr OCONEE 1, 2, 3 2010 2,391.1 93.3 1,953 193.088 0.10 0.08 (continued) 2011 2,321.6 90.7 2,142 182.261 0.09 0.08 2012 2,351.0 91.8 1,777 131.442 0.07 0.06 2013 2,400.1 93.1 1,549 106.414 0.07 0.04 2014 2,419.3 94.1 2,005 109.011 0.05 0.05 2015 2,504.5 97.4 1,339 69.050 0.05 0.03 2016 2,417.5 93.9 1,179 53.398 0.05 0.02 2017 2,488.4 96.7 966 37.301 0.04 0.01 2018 2,430.8 94.4 1,141 57.201 0.05 0.02 2019 2,498.3 97 715 31.137 0.04 0.01 OYSTER CREEK15 1970 413.6 --- 95 63 0.66 0.15 Docket 50-219; 1971 448.9 --- 249 240 0.96 0.53 DPR-16 1972 515.0 --- 339 582 1.72 1.13 1st commercial operation 12/69 1973 424.6 --- 782 1,236 1.58 2.91 Type - BWR 1974 434.5 70.4 935 984 1.05 2.26 Capacity - (619) MWe 1975 373.6 73.3 1,210 1,140 0.94 3.05 1976 456.5 79.3 1,582 1,078 0.68 2.36 1977 385.7 70.1 1,673 1,614 0.96 4.18 1978 431.8 74.3 1,411 1,279 0.91 2.96 1979 541.0 85.9 842 467 0.55 0.86 1980 232.9 41.4 1,966 1,733 0.88 7.44 1981 314.8 59.8 1,689 917 0.54 2.91 1982 242.7 62.5 1,270 865 0.68 3.56 1983 27.9 11.5 2,303 2,257 0.98 80.90 1984 37.1 9.6 2,369 2,054 0.87 55.36 1985 446.1 89.4 2,342 748 0.32 1.68 1986 157.3 31.5 3,740 2,436 0.65 15.49 1987 371.0 64.2 1,932 522 0.27 1.41 1988 419.6 65.9 2,875 1,504 0.52 3.58 1989 287.5 57.3 2,395 910 0.38 3.17 1990 511.8 89.1 1,941 310 0.16 0.61 1991 351.6 60.5 3,089 1,185 0.38 3.37 1992 536.3 85.9 2,771 657 0.24 1.23 1993 551.9 87.8 2,560 416 0.16 0.75 1994 431.7 70.8 2,382 844 0.35 1.96 1995 615.4 97.4 761 90 0.12 0.15 1996 515.0 82.6 1,833 449 0.24 0.87 1997 579.1 94.3 509 50 0.10 0.09 1998 490.8 82.4 1,408 308.323 0.22 0.63 1999 615.1 100.0 466 41.664 0.09 0.07 2000 444.9 83.3 2,044 614.379 0.30 1.38 2001 595.0 97.6 442 45.817 0.10 0.08 2002 573.0 94.0 1,468 265.810 0.18 0.46

2003 598.4 97.2 416 43.363 0.10 0.07 2004 551.8 91.6 1,346 226.880 0.17 0.41 2005 611.9 99.5 316 27.813 0.09 0.05 2006 530.2 90.0 1,443 189.950 0.13 0.36 2007 579.7 97.0 464 46.590 0.10 0.08 2008 531.0 91.0 1,511 211.932 0.14 0.40 2009 568.3 96.4 382 37.272 0.10 0.07 2010 525.7 89.9 1,655 206.284 0.12 0.39 2011 604.8 98.0 434 46.984 0.11 0.08 2012 537.1 88.5 1,359 165.164 0.12 0.31 2013 584.1 96.5 299 29.981 0.10 0.05 2014 551.8 91.2 1,160 145.487 0.13 0.26 2015 602.3 97.7 275 22.710 0.08 0.04 2016 523.4 87.5 1,286 133.603 0.10 0.26 2017 619.8 99.5 249 17.511 0.07 0.03 2018 0.0 0.0 357 37.887 0.11 ---

2019 0.0 0.0 123 21.886 0.18 ---

15 Oyster Creek ceased operations in September 2018 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-31

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr PALISADES 1972 216.8 --- --- 78 --- 0.36 Docket 50-255; 1973 286.8 --- 975 1,133 1.16 3.95 DPR-20 1974 10.7 5.5 774 627 0.81 58.60 1st commercial operation 12/71 1975 302.0 64.5 495 306 0.62 1.01 Type - PWR 1976 346.9 55.2 742 696 0.94 2.01 Capacity - 777 MWe 1977 616.6 91.4 332 100 0.30 0.16 1978 320.2 49.7 849 764 0.90 2.39 1979 415.0 59.9 1,599 854 0.53 2.06 1980 288.3 42.9 1,307 424 0.32 1.47 1981 418.2 57.2 2,151 902 0.42 2.16 1982 404.3 54.7 1,554 330 0.21 0.82 1983 454.4 60.3 2,167 977 0.45 2.15 1984 98.7 15.2 1,344 573 0.43 5.81 1985 639.2 83.8 1,355 507 0.37 0.79 1986 102.3 15.1 1,438 672 0.47 6.57 1987 319.2 48.2 1,122 456 0.41 1.43 1988 413.4 56.8 1,472 730 0.50 1.77 1989 442.8 69.1 1,026 314 0.31 0.71 1990 366.7 58.7 2,414 766 0.32 2.09 1991 587.0 78.1 1,315 211 0.16 0.36 1992 581.9 76.1 1,267 295 0.23 0.51 1993 424.4 53.7 908 289 0.32 0.68 1994 541.8 67.0 397 60 0.15 0.11 1995 583.5 75.8 1,230 462 0.38 0.79 1996 638.2 81.4 1,109 318 0.29 0.50 1997 662.5 89.9 338 48 0.14 0.07 1998 615.4 83.5 895 216.563 0.24 0.35 1999 585.4 80.2 939 218.451 0.23 0.37 2000 654.4 88.0 255 26.305 0.10 0.04 2001 268.2 36.3 1,032 362.723 0.35 1.35 2002 725.0 94.8 224 24.380 0.11 0.03

2003 701.1 90.7 822 202.571 0.25 0.29 2004 608.6 82.3 974 370.895 0.38 0.61 2005 756.6 98.0 156 10.459 0.07 0.01 2006 675.5 86.0 882 239.652 0.27 0.35 2007 665.6 85.0 1,065 256.632 0.24 0.39 2008 778.4 98.2 272 23.478 0.09 0.03 2009 698.5 89.0 975 267.295 0.27 0.38 2010 712.5 90.8 908 219.873 0.24 0.31 2011 758.1 96.5 340 21.654 0.06 0.03 2012 589.5 77.1 1,096 245.129 0.22 0.42 2013 689.7 86.7 339 15.830 0.05 0.02 2014 665.6 83.4 1,231 486.062 0.39 0.73 2015 721.3 90.9 940 230.687 0.25 0.32 2016 803.8 100.0 161 5.667 0.04 0.01 2017 696.1 91.3 794 154.142 0.19 0.22 2018 622.8 78.8 958 206.284 0.22 0.33 2019 783.6 98.2 161 10.051 0.06 0.01 PALO VERDE 1, 2, 3 1987 1,638.1 66.1 1,792 669 0.37 0.41 Docket 50-528, 50-529, 50-530; 1988 1,700.9 65.5 2,173 688 0.32 0.40 NPF-41, NPF-51, NPF-74 1989 965.3 26.5 2,615 720 0.28 0.75 1st commercial operation 1990 2,500.9 67.5 2,236 499 0.22 0.20 1/86, 9/86, 1/88 1991 3,043.9 78.9 2,242 605 0.27 0.20 Type - PWRs 1992 3,102.3 82.0 1,981 541 0.27 0.17 Capacity - 1,311, 1,314, 1993 2,677.1 74.3 2,124 592 0.28 0.22 1,312 MWe 1994 2,827.6 79.1 2,048 462 0.23 0.16 1995 3,265.2 85.6 1,875 482 0.26 0.15 1996 3,482.7 90.0 1,717 302 0.18 0.09 1997 3,369.2 92.2 1,585 246 0.16 0.07 1998 3,454.4 93.2 1,410 192.425 0.14 0.06 1999 3,471.2 93.2 1,275 146.328 0.11 0.04 2000 3,458.6 93.0 1,279 158.105 0.12 0.05 2001 3,280.2 88.6 1,361 182.043 0.13 0.06 C-32

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr PALO VERDE 1, 2, 3 2002 3,513.0 94.0 1,343 140.057 0.10 0.04

(continued) 2003 3,254.4 88.6 1,943 210.842 0.11 0.06 2004 3,201.4 86.3 1,324 199.016 0.15 0.06 2005 2,937.6 80.4 2,014 200.300 0.10 0.07 2006 2,741.1 79.0 1,585 151.516 0.10 0.06 2007 3,058.5 81.0 2,372 148.660 0.06 0.05 2008 3,330.0 86.1 1,706 159.913 0.09 0.05 2009 3,500.2 89.6 1,695 97.902 0.06 0.03 2010 3,561.6 90.9 1,655 112.612 0.07 0.03 2011 3,570.5 91.9 1,248 61.374 0.05 0.02 2012 3,635.5 93.6 1,126 59.593 0.05 0.02 2013 3,588.0 91.8 1,164 93.713 0.08 0.03 2014 3,689.9 94.1 1,085 60.002 0.06 0.02 2015 3,711.7 94.1 1,142 57.996 0.05 0.02 2016 3,680.7 93.6 1,177 64.796 0.06 0.02 2017 3,691.8 94.1 1,088 53.888 0.05 0.01 2018 3,551.0 91.5 1,036 41.103 0.04 0.01 2019 3,643.8 92.6 937 41.262 0.04 0.01 PEACH BOTTOM 2, 3 1975 1,234.3 80.9 971 228 0.23 0.18 Docket 50-277, 50-278; 1976 1,379.2 73.0 2,136 840 0.39 0.61 DPR-44, DPR-56 1977 1,052.4 58.7 2,827 2,036 0.72 1.93 1st commercial operation 1978 1,636.3 84.0 2,244 1,317 0.59 0.80 7/74, 12/74 1979 1,740.0 84.5 2,276 1,388 0.61 0.80 Type - BWRs 1980 1,374.2 66.3 2,774 2,302 0.83 1.68 Capacity - 1,232, 1,251 MWe 1981 1,161.8 58.0 2,857 2,506 0.88 2.16 1982 1,583.3 76.9 2,734 1,977 0.72 1.25 1983 824.7 41.0 3,107 2,963 0.95 3.59 1984 1,165.8 57.5 3,313 2,450 0.74 2.10 1985 682.7 37.5 4,209 3,354 0.80 4.91 1986 1,395.0 71.7 2,454 1,080 0.44 0.77 1987 365.7 20.3 4,363 2,195 0.50 6.00 1988 0.0 0.0 4,204 2,327 0.55 ---

1989 491.0 35.0 2,301 728 0.32 1.48 1990 1,684.0 85.7 1,585 377 0.24 0.22 1991 1,210.9 62.3 2,702 934 0.35 0.77 1992 1,516.6 78.7 1,911 502 0.26 0.33 1993 1,654.0 81.9 1,757 552 0.31 0.33 1994 1,927.4 93.8 2,133 579 0.27 0.30 1995 1,955.9 95.1 1,940 398 0.21 0.20 1996 2,012.4 96.9 1,657 282 0.17 0.14 1997 1,956.3 95.0 1,872 490 0.26 0.25 1998 1,881.2 93.2 1,903 366.040 0.19 0.19 1999 2,057.2 96.0 1,630 319.307 0.20 0.16 2000 2,058.3 96.7 1,729 330.928 0.19 0.16 2001 2,037.1 95.8 1,445 344.283 0.24 0.17 2002 2,105.0 96.7 1,915 333.056 0.17 0.16

2003 2,072.4 94.9 1,641 355.969 0.22 0.17 2004 2,148.8 96.4 1,422 264.727 0.19 0.12 2005 2,102.0 95.6 1,801 306.201 0.17 0.15 2006 2,169.1 97.0 1,513 247.676 0.16 0.11 2007 2,163.8 97.0 1,906 384.795 0.20 0.18 2008 2,115.3 95.1 1,816 212.741 0.12 0.10 2009 2,130.4 95.5 2,032 310.517 0.15 0.15 2010 2,145.3 96.2 1,716 219.372 0.13 0.10 2011 2,152.0 95.7 2,758 389.814 0.14 0.18 2012 2,142.5 94.8 2,460 305.431 0.12 0.14 2013 2,143.5 94.7 2,902 483.936 0.17 0.23 2014 2,142.3 94.2 3,053 430.941 0.14 0.20 2015 2,267.6 95.6 2,938 395.597 0.13 0.17 2016 2,498.1 97.7 2,052 202.221 0.10 0.08 2017 2,481.1 98.0 1,824 197.814 0.11 0.08 2018 2,474.9 96.6 1,717 177.337 0.10 0.07 2019 2,545.2 97.9 1,767 167.083 0.09 0.07 C-33

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr PERRY 1988 869.3 79.0 782 105 0.13 0.12 Docket 50-440; 1989 642.2 57.0 1,883 767 0.41 1.19 NPF-58 1990 792.7 67.1 1,537 638 0.42 0.80 1st commercial operation 11/87 1991 1,074.2 91.9 600 146 0.24 0.14 Type - BWR 1992 856.2 75.5 1,487 571 0.38 0.67 Capacity - 1,240 MWe 1993 479.2 48.2 1,235 278 0.23 0.58 1994 550.8 50.2 2,098 691 0.33 1.25 1995 1,090.9 95.6 587 64 0.11 0.06 1996 895.6 77.2 1,622 307 0.19 0.34 1997 930.6 84.7 1,524 272 0.18 0.29 1998 1,163.1 99.3 385 41.945 0.11 0.04 1999 1,041.7 89.9 1,758 326.014 0.19 0.31 2000 1,148.2 97.1 501 55.827 0.11 0.05 2001 885.9 79.6 1,392 258.268 0.19 0.29 2002 1,136.0 95.0 436 70.258 0.16 0.06

2003 973.7 83.8 1,880 607.384 0.32 0.62 2004 1,164.3 95.9 496 73.481 0.15 0.06 2005 872.9 73.8 1,734 416.608 0.24 0.48 2006 1,195.8 99.0 488 65.152 0.13 0.05 2007 919.7 79.0 1,650 505.121 0.31 0.55 2008 1,215.9 97.9 528 52.058 0.10 0.04 2009 869.2 73.3 1,818 614.959 0.34 0.71 2010 1,213.3 98.5 278 32.186 0.12 0.03 2011 978.2 82.4 1,640 307.866 0.19 0.31 2012 1,194.3 98.6 408 43.374 0.11 0.04 2013 964.5 82.1 1,630 373.747 0.23 0.39 2014 1,193.5 97.4 442 84.578 0.19 0.07 2015 1,082.5 87.5 1,644 386.778 0.24 0.36 2016 1,189.5 96.9 351 36.389 0.10 0.03 2017 1,120.1 92.2 1,449 327.717 0.23 0.29 2018 1,223.6 100.0 217 29.848 0.14 0.02 2019 1,047.2 91.0 1,222 301.067 0.25 0.29 PILGRIM 116 1973 484.0 --- 230 126 0.55 0.26 Docket 50-293; 1974 234.1 39.2 454 415 0.91 1.77 DPR-35 1975 308.1 71.3 473 798 1.69 2.59 1st commercial operation 12/72 1976 287.8 60.7 1,317 2,648 2.01 9.20 Type - BWR 1977 316.6 61.4 1,875 3,142 1.68 9.92 Capacity - (685) MWe 1978 519.5 83.1 1,667 1,327 0.80 2.55 1979 574.0 89.4 2,458 1,015 0.41 1.77 1980 360.3 56.2 3,549 3,626 1.02 10.06 1981 408.9 65.9 2,803 1,836 0.66 4.49 1982 389.9 63.9 2,854 1,539 0.54 3.95 1983 559.5 87.2 2,326 1,162 0.50 2.08 1984 1.4 0.4 4,542 4,082 0.90 2,915.71 1985 587.3 91.5 2,209 893 0.40 1.52 1986 121.9 18.8 2,635 874 0.33 7.17 1987 0.0 0.0 4,710 1,579 0.34 ---

1988 0.0 0.0 2,073 392 0.19 ---

1989 204.6 64.1 1,797 207 0.12 1.01 1990 503.5 82.1 1,898 225 0.12 0.45 1991 406.3 65.8 2,836 605 0.21 1.49 1992 561.0 85.4 1,332 281 0.21 0.50 1993 513.7 80.9 1,328 435 0.33 0.85 1994 453.6 71.4 758 200 0.26 0.44 1995 531.7 80.7 1,294 482 0.37 0.91 1996 631.3 95.4 517 116 0.22 0.18 1997 492.1 80.7 1,655 588 0.36 1.19 1998 650.5 100.0 530 71.446 0.13 0.11 1999 510.7 84.4 1,222 344.270 0.28 0.67 2000 627.5 98.3 422 50.797 0.12 0.08 2001 585.6 91.0 1,113 179.585 0.16 0.31 16 Pilgrim 1 ceased operations in June of 2019 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-34

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr PILGRIM 116 2002 657.0 100.0 463 38.280 0.08 0.06

(continued) 2003 566.6 87.5 1,437 250.192 0.17 0.44 2004 676.1 99.5 427 41.109 0.10 0.06 2005 623.2 93.7 1,212 206.089 0.17 0.33 2006 665.4 100.0 654 43.531 0.07 0.07 2007 584.5 90.0 1,407 240.526 0.17 0.41 2008 668.1 99.0 377 22.568 0.06 0.03 2009 616.0 91.7 1,301 264.215 0.20 0.43 2010 675.5 100.0 303 25.739 0.08 0.04 2011 580.5 89.0 1,179 241.402 0.20 0.42 2012 669.0 99.4 284 21.620 0.08 0.03 2013 493.9 80.4 1,188 176.012 0.15 0.36 2014 658.6 98.9 421 36.716 0.09 0.06 2015 570.0 86.9 1,392 218.609 0.16 0.38 2016 617.9 94.7 634 44.242 0.07 0.07 2017 576.1 88.2 1,614 162.998 0.10 0.28 2018 507.0 83.8 629 38.777 0.06 0.08 2019 0.0 0.0 367 18.041 0.05 ---

POINT BEACH 1, 2 1971 393.4 --- --- 164 --- 0.42 Docket 50-266, 50-301; 1972 378.3 --- --- 580 --- 1.53 DPR-24, DPR-27 1973 693.7 --- 501 588 1.17 0.85 1st commercial operation 1974 760.2 81.3 400 295 0.74 0.39 12/70, 10/72 1975 801.2 82.9 339 459 1.35 0.57 Type - PWRs 1976 857.3 86.7 313 370 1.18 0.43 Capacity - 576, 578 MWe 1977 873.9 87.3 417 430 1.03 0.49 1978 914.4 90.9 336 320 0.95 0.35 1979 808.0 80.8 610 644 1.06 0.80 1980 727.2 82.5 561 598 1.07 0.82 1981 760.4 83.6 773 596 0.77 0.78 1982 757.2 84.3 767 609 0.79 0.80 1983 648.2 72.7 1,702 1,403 0.82 2.16 1984 788.9 78.6 1,372 789 0.58 1.00 1985 831.3 82.5 671 482 0.72 0.58 1986 858.9 85.7 664 402 0.61 0.47 1987 857.5 85.5 720 554 0.77 0.65 1988 899.3 88.6 734 410 0.56 0.46 1989 847.8 85.5 736 504 0.68 0.59 1990 875.5 86.5 617 378 0.61 0.43 1991 874.8 87.1 724 265 0.37 0.30 1992 866.7 85.8 617 256 0.41 0.30 1993 911.0 90.0 559 186 0.33 0.20 1994 914.5 91.2 548 170 0.31 0.19 1995 858.4 86.1 548 190 0.35 0.22 1996 831.6 84.7 1,029 276 0.27 0.33 1997 186.8 21.8 670 92 0.14 0.49 1998 649.7 69.7 881 169.253 0.19 0.26 1999 806.0 83.1 962 194.489 0.20 0.24 2000 872.0 88.7 765 138.989 0.18 0.16 2001 915.9 93.4 740 131.667 0.18 0.14 2002 909.0 91.1 945 180.654 0.19 0.20

2003 917.2 92.1 627 84.965 0.14 0.09 2004 912.3 90.1 627 109.515 0.17 0.12 2005 782.5 78.1 851 128.646 0.15 0.16 2006 977.2 96.0 453 39.597 0.09 0.04 2007 958.5 94.0 535 52.023 0.10 0.05 2008 889.4 87.8 958 144.021 0.15 0.16 2009 902.3 92.9 766 93.270 0.12 0.10 2010 952.8 93.8 869 95.695 0.11 0.10 2011 796.2 75.8 1,027 159.684 0.16 0.20 2012 1,114.3 95.2 581 69.755 0.12 0.06 2013 1,135.3 95.9 547 63.146 0.12 0.06 16 Pilgrim 1 ceased operations in June of 2019 and is no longer included in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-35

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr POINT BEACH 1, 2 2014 1,079.4 91.4 759 127.523 0.17 0.12 (continued) 2015 1,142.9 95.8 446 47.473 0.11 0.04 2016 1,159.0 96.8 515 57.294 0.11 0.05 2017 1,102.0 93.1 755 87.479 0.12 0.08 2018 1,156.7 97.2 511 43.228 0.08 0.04 2019 1,145.3 96.4 533 74.485 0.14 0.07 PRAIRIE ISLAND 1, 2 1974 181.9 43.9 150 18 0.12 0.10 Docket 50-282, 50-306; 1975 836.0 83.3 477 123 0.26 0.15 DPR-42, DPR-60 1976 725.2 76.6 818 447 0.55 0.62 1st commercial operation 1977 922.9 87.2 718 300 0.42 0.33 12/73, 12/74 1978 941.1 92.2 546 221 0.40 0.23 Type - PWRs 1979 865.0 86.0 594 180 0.30 0.21 Capacity - 522, 519 MWe 1980 800.7 79.9 983 353 0.36 0.44 1981 844.9 80.5 836 329 0.39 0.39 1982 944.9 90.4 645 229 0.36 0.24 1983 921.1 86.8 654 233 0.36 0.25 1984 972.4 91.7 546 147 0.27 0.15 1985 882.6 84.0 1,082 416 0.38 0.47 1986 930.6 90.3 818 255 0.31 0.27 1987 969.6 91.6 593 135 0.23 0.14 1988 932.0 89.1 732 199 0.27 0.21 1989 1,001.8 94.7 476 99 0.21 0.10 1990 925.4 89.2 737 188 0.26 0.20 1991 1,023.3 95.6 586 98 0.17 0.10 1992 811.6 76.2 845 211 0.25 0.26 1993 978.3 90.7 532 106 0.20 0.11 1994 996.9 91.5 478 109 0.23 0.11 1995 1,023.2 93.9 499 107 0.21 0.10 1996 992.1 91.4 558 112 0.20 0.11 1997 817.6 81.4 753 174 0.23 0.21 1998 860.3 83.4 582 116.649 0.20 0.14 1999 989.3 93.8 542 72.496 0.13 0.07 2000 992.2 93.1 632 106.091 0.17 0.11 2001 900.8 85.8 691 124.708 0.18 0.14 2002 987.0 93.6 969 127.713 0.13 0.13 2003 1,006.1 96.4 594 61.137 0.10 0.06 2004 940.4 89.9 1,186 143.806 0.12 0.15 2005 952.5 90.8 782 84.337 0.11 0.09 2006 926.4 89.0 1,103 137.352 0.12 0.15 2007 1,014.8 98.0 130 6.276 0.05 0.01 2008 924.3 88.9 1,060 126.723 0.12 0.14 2009 942.2 89.9 560 53.590 0.10 0.06 2010 1,002.6 94.9 661 54.933 0.08 0.05 2011 982.4 92.0 678 58.029 0.09 0.06 2012 803.8 76.7 909 119.166 0.13 0.15 2013 881.8 86.0 1,383 129.989 0.09 0.15 2014 957.0 91.1 768 70.860 0.09 0.07 2015 842.2 81.2 802 62.441 0.08 0.07 2016 944.5 87.9 705 48.078 0.07 0.05 2017 998.3 95.0 558 34.322 0.06 0.03 2018 1,025.5 95.5 559 37.731 0.07 0.04 2019 1,043.4 96.9 417 24.593 0.06 0.02 QUAD CITIES 1, 2 1974 958.1 72.3 678 482 0.71 0.50 Docket 50-254, 50-265; 1975 833.6 68.4 1,083 1,618 1.49 1.94 DPR-29, DPR-30 1976 951.2 73.1 1,225 1,651 1.35 1.74 1st commercial operation 1977 970.1 84.0 907 1,031 1.14 1.06 2/73, 3/73 1978 1,124.5 88.6 1,207 1,618 1.34 1.44 Type - BWRs 1979 1,075.0 84.6 1,688 2,158 1.28 2.01 Capacity - 887, 888 MWe 1980 866.9 64.4 3,089 4,838 1.57 5.58 1981 1,156.9 81.1 2,246 3,146 1.40 2.72 1982 1,018.7 76.0 2,314 3,757 1.62 3.69 1983 1,088.5 79.2 1,802 2,491 1.38 2.29 1984 994.6 65.7 1,678 1,579 0.94 1.59 1985 1,268.0 82.7 1,184 990 0.84 0.78 C-36

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr QUAD CITIES 1, 2 1986 1,093.2 71.0 1,451 950 0.65 0.87 (continued) 1987 1,126.6 75.3 1,429 720 0.50 0.64 1988 1,173.7 84.1 1,486 827 0.56 0.70 1989 1,196.3 85.9 1,721 900 0.52 0.75 1990 1,148.9 77.8 2,186 1,028 0.47 0.89 1991 1,044.5 73.2 1,722 509 0.30 0.49 1992 960.8 68.0 2,413 1,157 0.48 1.20 1993 974.9 67.0 2,150 849 0.39 0.87 1994 681.5 48.7 2,163 1,128 0.52 1.66 1995 1,002.5 70.4 2,041 736 0.36 0.73 1996 876.6 60.1 2,248 1,025 0.46 1.17 1997 935.3 66.5 2,474 654 0.26 0.70 1998 794.8 55.1 2,177 760.596 0.35 0.96 1999 1,476.5 95.9 1,000 200.556 0.20 0.14 2000 1,410.4 93.9 2,840 893.766 0.31 0.63 2001 1,478.2 95.9 736 143.849 0.20 0.10 2002 1,396.0 89.0 3,818 1,786.021 0.47 1.28

2003 1,569.4 93.1 998 438.144 0.44 0.28 2004 1,443.8 95.5 2,334 510.521 0.22 0.35 2005 1,516.2 94.2 2,869 961.026 0.33 0.63 2006 1,524.9 93.0 2,329 559.362 0.24 0.37 2007 1,650.3 97.0 1,945 249.927 0.13 0.15 2008 1,619.4 95.2 2,065 274.444 0.13 0.17 2009 1,662.6 95.4 2,366 318.418 0.13 0.19 2010 1,688.9 95.0 2,267 241.444 0.11 0.14 2011 1,735.3 95.9 2,453 288.618 0.12 0.17 2012 1,765.3 95.9 2,173 194.311 0.09 0.11 2013 1,776.0 96.3 2,210 192.059 0.09 0.11 2014 1,756.7 95.2 2,068 156.168 0.08 0.09 2015 1,776.5 96.9 1,860 170.123 0.09 0.10 2016 1,787.1 97.6 1,875 142.607 0.08 0.08 2017 1,758.2 96.8 1,888 173.167 0.09 0.10 2018 1,766.7 97.1 1,678 162.171 0.10 0.09 2019 1,763.7 96.8 1,896 204.958 0.11 0.12 RANCHO SECO17 1976 268.1 30.4 297 58 0.20 0.22 Docket 50-312; 1977 706.4 77.1 515 391 0.76 0.55 DPR-54 1978 607.7 80.5 508 323 0.64 0.53 1st commercial operation 4/75 1979 687.0 91.1 287 126 0.44 0.18 Type - PWR 1980 530.9 60.4 890 412 0.46 0.78 Capacity - (873) MWe 1981 321.2 40.2 772 402 0.52 1.25 1982 409.5 53.3 766 337 0.44 0.82 1983 347.9 46.8 1,338 787 0.59 2.26 1984 460.0 58.3 802 222 0.28 0.48 1985 238.7 30.8 1,764 756 0.43 3.17 1986 0.0 0.0 1,513 402 0.27 ---

1987 0.0 0.0 1,533 300 0.20 ---

1988 355.8 63.1 693 78 0.11 0.22 1989 179.9 54.7 603 81 0.13 0.45 1990 0.0 0.0 111 13 0.12 ---

1991 0.0 0.0 101 9 0.09 ---

1992 0.0 0.0 70 7 0.10 ---

1993 0.0 0.0 35 4 0.11 ---

1994 0.0 0.0 18 1 0.06 ---

1995 0.0 0.0 16 1 0.06 ---

1996 0.0 0.0 16 1 0.06 ---

1997 0.0 0.0 16 0 0.00 ---

1998 0.0 0.0 61 2.661 0.04 ---

1999 0.0 0.0 302 11.191 0.04 ---

2000 0.0 0.0 219 25.795 0.12 ---

2001 0.0 0.0 210 18.432 0.09 ---

2002 0.0 0.0 193 27.346 0.14 ---

2003 0.0 0.0 121 18.300 0.15 ---

2004 0.0 0.0 122 14.890 0.12 ---

17 Rancho Seco ceased operations in June 1989 and is no longer in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-37

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr RANCHO SECO17 2005 0.0 0.0 157 33.444 0.21 ---

(continued) 2006 0.0 0.0 143 31.793 0.22 ---

2007 0.0 0.0 129 12.524 0.10 ---

2008 0.0 0.0 84 2.434 0.03 ---

RIVER BEND 1 1987 605.2 68.4 1,268 378 0.30 0.62 Docket 50-458; 1988 880.7 94.3 513 107 0.21 0.12 NPF-47 1989 584.5 69.1 1,566 558 0.36 0.95 1st commercial operation 6/86 1990 682.2 78.0 1,616 489 0.30 0.72 Type - BWR 1991 814.7 87.2 780 144 0.18 0.18 Capacity - 967 MWe 1992 336.1 39.7 2,022 710 0.35 2.11 1993 640.0 71.6 847 180 0.21 0.28 1994 595.7 64.9 2,209 519 0.23 0.87 1995 967.1 99.6 667 85 0.13 0.09 1996 836.1 85.3 2,093 473 0.23 0.57 1997 778.8 86.3 1,671 347 0.21 0.45 1998 894.2 96.2 466 57.749 0.12 0.06 1999 651.2 75.2 1,327 343.858 0.26 0.53 2000 837.1 89.7 1,104 216.053 0.20 0.26 2001 889.3 93.6 1,249 207.614 0.17 0.23 2002 965.0 98.5 373 35.145 0.09 0.04

2003 871.3 92.7 1,296 216.950 0.17 0.25 2004 845.6 90.1 1,378 235.749 0.17 0.28 2005 890.5 94.4 498 55.816 0.11 0.06 2006 853.7 92.0 1,494 214.409 0.14 0.25 2007 823.0 92.0 1,131 131.373 0.12 0.16 2008 724.8 78.7 1,809 311.697 0.17 0.43 2009 895.6 92.6 1,978 219.446 0.11 0.25 2010 955.1 98.9 888 40.356 0.05 0.04 2011 878.6 91.9 1,880 211.212 0.11 0.24 2012 890.2 94.5 648 34.178 0.05 0.04 2013 867.6 90.8 1,915 188.331 0.10 0.22 2014 935.8 98.1 343 16.138 0.05 0.02 2015 791.6 87.9 888 128.492 0.14 0.16 2016 811.5 86.6 532 71.142 0.13 0.09 2017 804.5 87.7 1,500 273.004 0.18 0.34 2018 804.3 88.6 573 69.580 0.12 0.09 2019 750.5 86.0 1,447 255.918 0.18 0.34 ROBINSON 2 1972 580.0 --- 245 215 0.88 0.37 Docket 50-261; 1973 455.1 --- 831 695 0.84 1.53 DPR-23 1974 578.1 83.3 853 672 0.79 1.16 1st commercial operation 3/71 1975 501.8 72.7 849 1,142 1.35 2.28 Type - PWR 1976 585.5 84.7 597 715 1.20 1.22 Capacity - 741 MWe 1977 511.5 85.2 634 455 0.72 0.89 1978 480.5 72.0 943 963 1.02 2.00 1979 482.0 70.8 1,454 1,188 0.82 2.46 1980 387.3 62.2 2,009 1,852 0.92 4.78 1981 426.6 73.0 1,462 733 0.50 1.72 1982 277.5 48.9 2,011 1,426 0.71 5.14 1983 409.8 75.5 2,244 923 0.41 2.25 1984 28.0 7.0 4,127 2,880 0.70 102.86 1985 629.5 87.9 1,378 311 0.23 0.49 1986 577.1 80.3 1,571 539 0.34 0.93 1987 510.1 72.5 1,379 499 0.36 0.98 1988 385.0 65.9 1,351 564 0.42 1.46 1989 336.6 48.7 1,098 195 0.18 0.58 1990 400.3 64.8 1,626 437 0.27 1.09 1991 575.1 81.4 885 193 0.22 0.34 1992 487.2 66.8 1,267 352 0.28 0.72 1993 502.7 70.7 1,221 337 0.28 0.67 1994 560.3 79.5 420 63 0.15 0.11 1995 618.7 84.7 1,058 215 0.20 0.35 1996 654.8 88.6 1,031 167 0.16 0.26 1997 707.5 99.0 304 13 0.04 0.02 17 Rancho Seco ceased operations in June 1989 and is no longer in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-38

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr ROBINSON 2 1998 628.5 88.9 978 170.476 0.17 0.27 (continued) 1999 648.9 91.8 807 123.952 0.15 0.19 2000 710.0 99.7 138 8.396 0.06 0.01 2001 627.9 90.6 827 124.750 0.15 0.20 2002 638.0 91.2 830 110.631 0.13 0.17

2003 733.1 100.0 109 4.838 0.04 0.01 2004 653.7 89.3 952 118.159 0.12 0.18 2005 656.9 89.7 791 64.662 0.08 0.10 2006 735.5 100.0 86 3.320 0.04 0.00 2007 655.0 90.0 890 80.752 0.09 0.12 2008 618.1 84.6 788 68.381 0.09 0.11 2009 738.9 99.3 126 6.643 0.05 0.01 2010 410.8 57.0 996 85.917 0.09 0.21 2011 726.5 99.3 137 3.630 0.03 0.00 2012 613.4 82.2 1,027 65.258 0.06 0.11 2013 650.3 85.3 1,116 80.595 0.07 0.12 2014 703.1 91.2 477 28.666 0.06 0.04 2015 653.4 84.9 957 56.373 0.06 0.09 2016 734.3 96.3 133 3.704 0.03 0.01 2017 676.9 89.1 883 58.739 0.07 0.09 2018 602.5 80.3 958 61.998 0.06 0.10 2019 727.9 93.8 48 1.668 0.03 0.00 SALEM 1, 2 1978 546.4 55.6 574 122 0.21 0.22 Docket 50-272, 50-311; 1979 250.0 25.5 1,488 584 0.39 2.34 DPR-70, DPR-75 1980 680.6 69.2 1,704 449 0.26 0.66 1st commercial operation 1981 743.0 78.1 1,652 254 0.15 0.34 6/77, 10/81 1982 1,440.4 72.6 3,228 1,203 0.37 0.84 Type - PWRs 1983 742.0 30.5 2,383 581 0.24 0.78 Capacity - 1,116, 1,134 MWe 1984 650.1 31.8 1,395 681 0.49 1.05 1985 1,657.7 75.8 1,112 204 0.18 0.12 1986 1,484.3 70.4 3,554 599 0.17 0.40 1987 1,478.2 73.3 2,543 600 0.24 0.41 1988 1,591.6 73.6 1,609 503 0.31 0.32 1989 1,675.4 79.5 2,944 338 0.11 0.20 1990 1,362.6 65.1 3,636 272 0.07 0.20 1991 1,726.4 79.3 4,201 458 0.11 0.27 1992 1,200.9 61.1 4,376 431 0.10 0.36 1993 1,366.3 65.4 3,559 408 0.11 0.30 1994 1,367.4 73.8 950 188 0.20 0.14 1995 558.1 29.3 1,195 218 0.18 0.39 1996 0.0 0.0 1,671 300 0.18 ---

1997 279.3 17.8 894 175 0.20 0.63 1998 1,629.3 79.1 408 41.100 0.10 0.03 1999 1,821.8 86.8 1,200 317.545 0.27 0.17 2000 1,973.4 93.0 1,191 198.068 0.17 0.10 2001 1,961.2 91.1 1,274 153.088 0.12 0.08 2002 1,934.0 89.4 2,460 292.692 0.12 0.15

2003 1,957.2 90.7 1,301 124.042 0.10 0.06 2004 1,850.2 85.8 1,496 148.694 0.10 0.08 2005 2,086.4 91.7 3,162 240.567 0.08 0.12 2006 2,211.8 97.0 1,446 90.541 0.06 0.04 2007 2,158.2 96.0 1,365 117.604 0.09 0.05 2008 1,998.6 87.8 3,362 328.761 0.10 0.16 2009 2,252.9 96.2 1,249 101.186 0.08 0.04 2010 2,147.3 93.9 964 77.828 0.08 0.04 2011 2,054.6 91.4 2,180 126.716 0.06 0.06 2012 2,123.8 93.4 674 47.003 0.07 0.02 2013 2,213.1 94.7 797 59.430 0.07 0.03 2014 1,870.1 81.7 2,558 109.633 0.04 0.06 2015 2,131.3 93.8 580 33.810 0.06 0.02 2016 1,800.9 84.2 1,108 93.255 0.08 0.05 2017 2,060.5 89.7 1,745 135.197 0.08 0.07 2018 2,165.1 95.2 521 49.086 0.09 0.02 2019 2,053.6 90.4 803 100.110 0.12 0.05 C-39

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr SAN ONOFRE 118, 2, 319 1969 314.1 --- 123 42 0.34 0.13 Docket 50-206, 50-361, 50-362; 1970 365.9 --- 251 155 0.62 0.42 DPR-13; NPF-10, NPF-15 1971 362.1 --- 121 50 0.41 0.14 1st commercial operation 1972 338.5 --- 326 256 0.79 0.76 1/68, 8/83, 4/84 1973 273.7 --- 570 353 0.62 1.29 Type - PWRs 1974 377.8 86.1 219 71 0.32 0.19 Capacity - (436), (1,070), 1975 389.0 87.4 424 292 0.69 0.75 (1,080) MWe 1976 297.9 70.2 1,330 880 0.66 2.95 1977 281.2 63.7 985 847 0.86 3.01 1978 323.2 80.2 764 401 0.52 1.24 1979 401.0 90.2 521 139 0.27 0.35 1980 97.3 22.3 3,063 2,386 0.78 24.52 1981 95.9 26.7 2,902 3,223 1.11 33.61 1982 61.6 15.7 3,055 832 0.27 13.51 1983 0.0 0.0 1,701 155 0.09 ---

1984 670.4 68.3 7,514 986 0.13 1.47 1985 1,381.8 132.9 5,742 722 0.13 0.52 1986 1,698.2 61.1 3,594 824 0.23 0.49 1987 1,983.0 78.8 2,138 696 0.33 0.35 1988 1,982.3 68.4 2,324 781 0.34 0.39 1989 1,840.8 64.9 2,237 567 0.25 0.31 1990 1,980.5 69.1 2,224 885 0.40 0.45 1991 1,987.6 75.3 1,814 412 0.23 0.21 1992 2,228.6 87.1 1,651 324 0.20 0.15 1993 1,771.3 79.9 2,193 767 0.35 0.43 1994 2,220.7 100.0 528 32 0.06 0.01 1995 1,686.9 79.1 1,914 455 0.24 0.27 1996 2,089.3 93.2 1,272 129 0.10 0.06 1997 1,533.9 72.9 1,652 341 0.21 0.22 1998 1,996.4 92.0 1,091 195.600 0.18 0.10 SAN ONOFRE 118 1999 0.0 0.0 241 15.863 0.07 ---

Docket 50-206; 2000 0.0 0.0 416 71.214 0.17 ---

DPR-13 2001 0.0 0.0 338 57.785 0.17 ---

1st commercial operation 1/68 2002 0.0 0.0 308 61.214 0.20 ---

Type - PWR 2003 0.0 0.0 226 35.596 0.16 ---

Capacity - (436) MWe 2004 0.0 0.0 169 14.899 0.09 ---

2005 0.0 0.0 198 20.624 0.10 ---

2006 0.0 0.0 183 22.490 0.12 ---

2007 0.0 0.0 20 0.417 0.02 ---

2008 0.0 0.0 2 0.043 0.02 ---

SAN ONOFRE 2, 319 1999 1,901.4 86.9 1,477 353.765 0.24 0.19 Docket 50-361, 50-362; 2000 2,067.2 94.7 1,073 115.499 0.11 0.06 NPF-10, NPF-15 2001 1,727.2 78.9 1,083 131.384 0.12 0.08 1st commercial operation 2002 2,056.0 93.4 1,140 136.443 0.12 0.07 8/83, 4/84 2003 2,084.3 94.0 1,275 163.804 0.13 0.08 Type - PWRs 2004 1,713.8 79.1 1,761 407.063 0.23 0.24 Capacity - (1,070), (1,080) MWe 2005 2,094.7 96.0 305 11.332 0.04 0.01 2006 1,552.2 73.0 1,632 315.087 0.19 0.20 2007 1,964.6 89.0 1,065 91.545 0.09 0.05 2008 1,753.0 82.7 1,014 125.320 0.12 0.07 SAN ONOFRE 118, 2, 319 2009 1,774.5 79.9 1,575 178.131 0.11 0.10 Docket 50-206, 50-361, 50-362; 2010 1,578.9 75.3 1,642 199.399 0.12 0.13 DPR-13; NPF-10, NPF-15 2011 2,067.1 93.0 641 29.658 0.05 0.01 1st commercial operation 2012 115.2 5.4 2,150 221.463 0.10 1.92 1/68, 8/83, 4/84 2013 0.0 0.0 210 5.701 0.03 ---

Type - PWRs 2014 0.0 0.0 68 1.369 0.02 ---

Capacity - (436), (1,070), 2015 0.0 0.0 136 1.202 0.01 ---

(1,080) MWe 2016 0.0 0.0 87 1.787 0.02 ---

SAN ONOFRE 117, 2, 318 2017 0.0 0.0 1 0.005 0.01 ---

(continued) 2018 0.0 0.0 127 24.574 0.19 ---

2019 0.0 0.0 76 12.774 0.17 ---

18 San Onofre 1 ceased operations in November 1992 and is no longer in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

19 San Onofre 2, 3 ceased power generation in January 2012, and in June 2013 it was decided that they would not be put back into commercial operation. Therefore, they are no longer included in the count of operating reactors. Parentheses indicate plant capacities when plants were operational.

C-40

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr SEABROOK 1991 810.4 75.9 699 92 0.13 0.11 Docket 50-443; 1992 932.4 81.3 806 147 0.18 0.16 NPF-86 1993 1,071.5 93.6 110 6 0.05 0.01 1st commercial operation 8/90 1994 736.4 63.5 852 113 0.13 0.15 Type - PWR 1995 995.5 87.5 800 102 0.13 0.10 Capacity - 1,246 MWe 1996 1,168.6 99.6 206 10 0.05 0.01 1997 907.0 79.8 1,571 186 0.12 0.21 1998 957.6 84.5 559 18.509 0.03 0.02 1999 991.5 87.5 1,339 105.723 0.08 0.11 2000 901.8 79.3 1,158 70.091 0.06 0.08 2001 989.6 89.1 423 8.672 0.02 0.01 2002 1,058.0 92.8 1,095 66.583 0.06 0.06 2003 1,055.9 93.6 981 70.953 0.07 0.07 2004 1,158.6 100.0 291 5.858 0.02 0.01 2005 1,076.4 91.5 1,034 52.216 0.05 0.05 2006 1,072.8 89.0 1,246 76.583 0.06 0.07 2007 1,228.7 100.0 349 4.332 0.01 0.00 2008 1,064.4 86.9 1,297 74.992 0.06 0.07 2009 1,006.4 86.5 1,233 87.372 0.07 0.09 2010 1,245.4 100.0 335 4.488 0.01 0.00 2011 954.5 80.5 1,156 65.593 0.06 0.07 2012 932.2 87.8 1,092 53.636 0.05 0.06 2013 1,247.3 100.0 291 2.442 0.01 0.00 2014 1,160.7 93.8 1,056 39.983 0.04 0.03 2015 1,082.6 88.3 1,219 96.053 0.08 0.09 2016 1,228.4 98.8 59 1.672 0.03 0.00 2017 1,140.4 92.0 519 29.191 0.06 0.03 2018 1,148.5 92.7 464 33.418 0.07 0.03 2019 1,245.0 100.0 69 1.084 0.02 0.00 SEQUOYAH 1, 2 1982 583.5 52.8 1,968 570 0.29 0.98 Docket 50-327, 50-328; 1983 1,663.7 75.1 1,769 491 0.28 0.30 DPR-77, DPR-79 1984 1,481.9 69.0 2,373 1,119 0.47 0.76 1st commercial operation 1985 1,151.3 51.3 1,853 1,072 0.58 0.93 7/81, 6/82 1986 0.0 0.0 1,738 527 0.30 ---

Type - PWR 1987 0.0 0.0 2,080 420 0.20 ---

Capacity - 1,152, 1,140 MWe 1988 490.8 31.8 2,441 678 0.28 1.38 1989 1,851.7 85.7 2,007 657 0.33 0.35 1990 1,662.6 77.2 2,935 1,687 0.57 1.01 1991 1,965.4 88.0 1,933 700 0.36 0.36 1992 1,849.0 85.4 1,714 465 0.27 0.25 1993 405.7 21.8 1,631 373 0.23 0.92 1994 1,418.7 66.3 1,702 295 0.17 0.21 1995 1,864.2 86.1 1,650 368 0.22 0.20 1996 2,003.9 87.9 1,444 269 0.19 0.13 1997 1,946.1 89.0 1,962 420 0.21 0.22 1998 2,135.3 95.3 1,530 265.980 0.17 0.12 1999 2,165.1 97.0 1,346 164.569 0.12 0.08 2000 1,910.0 86.8 2,039 357.220 0.18 0.19 2001 2,158.3 95.7 1,292 145.066 0.11 0.07 2002 2,106.0 94.1 1,257 108.252 0.09 0.05 2003 1,776.4 80.0 2,484 430.889 0.17 0.24 2004 2,135.2 93.9 1,161 85.941 0.07 0.04 2005 2,162.9 94.9 1,125 95.133 0.08 0.04 2006 2,054.9 91.0 1,752 242.016 0.14 0.12 2007 2,129.1 94.0 1,197 123.540 0.10 0.06 2008 2,153.6 94.3 960 83.730 0.09 0.04 2009 2,026.8 90.1 1,415 166.776 0.12 0.08 2010 2,054.9 92.2 828 56.956 0.07 0.03 2011 2,133.3 95.3 1,354 109.417 0.08 0.05 2012 1,888.2 84.6 2,555 290.840 0.11 0.15 2013 2,108.1 94.2 666 44.478 0.07 0.02 2014 2,156.7 95.5 842 77.569 0.09 0.04 2015 1,884.9 87.0 1,484 136.826 0.09 0.07 C-41

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr SEQUOYAH 1, 2 2016 1,971.4 88.8 1,133 105.764 0.09 0.05 (continued) 2017 2,080.7 94.0 831 47.200 0.06 0.02 2018 2,021.0 90.8 1,367 121.426 0.09 0.06 2019 2,062.2 93.1 846 76.085 0.09 0.04 SOUTH TEXAS 1, 2 1989 769.3 65.6 989 161 0.16 0.21 Docket 50-498, 50-499; 1990 1,504.1 65.9 1,136 206 0.18 0.14 NPF-76, NPF-80 1991 1,741.5 72.4 1,144 257 0.22 0.15 1st commercial operation 1992 2,096.0 83.8 923 147 0.16 0.07 8/88, 6/89 1993 163.1 8.3 1,138 251 0.22 1.54 Type - PWRs 1994 1,700.2 70.6 661 47 0.07 0.03 Capacity - 1,251, 1,251 MWe 1995 2,294.2 89.9 1,485 291 0.20 0.13 1996 2,465.9 95.0 1,145 137 0.12 0.06 1997 2,265.5 93.6 1,583 273 0.17 0.12 1998 2,379.4 96.9 1,171 183.977 0.16 0.08 1999 2,219.7 91.6 1,328 259.770 0.20 0.12 2000 2,180.0 89.7 1,372 231.634 0.17 0.11 2001 2,262.7 92.2 1,325 237.645 0.18 0.11 2002 2,173.0 87.5 1,510 329.091 0.22 0.15

2003 1,796.3 72.1 909 143.495 0.16 0.08 2004 2,437.1 96.0 842 119.834 0.14 0.05 2005 2,258.5 90.0 1,268 247.655 0.20 0.11 2006 2,439.6 95.0 1,078 150.323 0.14 0.06 2007 2,527.3 96.0 881 91.613 0.10 0.04 2008 2,452.1 92.3 1,181 187.295 0.16 0.08 2009 2,444.5 91.9 1,138 79.687 0.07 0.03 2010 2,418.7 91.5 867 79.159 0.09 0.03 2011 2,333.3 87.7 1,153 139.274 0.12 0.06 2012 2,122.4 79.8 611 49.104 0.08 0.02 2013 2,062.4 78.4 832 59.736 0.07 0.03 2014 2,363.4 90.0 422 34.576 0.08 0.01 2015 2,224.5 85.5 900 83.993 0.09 0.04 2016 2,481.9 94.9 426 32.837 0.08 0.01 2017 2,467.1 94.6 620 55.025 0.09 0.02 2018 2,367.7 91.0 703 70.050 0.10 0.03 2019 2,515.3 95.9 676 56.887 0.08 0.02 ST. LUCIE 1, 2 1977 649.1 84.7 445 152 0.34 0.23 Docket 50-335, 50-389; 1978 606.4 76.5 797 337 0.42 0.56 DPR-67; NPF-16 1979 592.0 74.0 907 438 0.48 0.74 1st commercial operation 1980 627.9 77.5 1,074 532 0.50 0.85 12/76, 8/83 1981 599.1 72.7 1,473 929 0.63 1.55 Type - PWRs 1982 816.8 94.0 1,045 272 0.26 0.33 Capacity - 981, 987 MWe 1983 290.3 15.4 2,211 1,204 0.54 4.15 1984 1,183.0 69.6 2,090 1,263 0.60 1.07 1985 1,445.8 82.5 1,971 1,344 0.68 0.93 1986 1,588.6 89.1 1,279 491 0.38 0.31 1987 1,407.9 81.9 2,012 951 0.47 0.68 1988 1,639.7 93.0 1,448 611 0.42 0.37 1989 1,493.1 85.1 1,414 495 0.35 0.33 1990 1,188.4 70.0 1,876 777 0.41 0.65 1991 1,592.8 90.8 1,282 479 0.37 0.30 1992 1,511.9 87.3 1,251 264 0.21 0.17 1993 1,227.6 77.7 1,462 492 0.34 0.40 1994 1,424.8 85.0 1,896 505 0.27 0.35 1995 1,306.6 76.0 1,498 413 0.28 0.32 1996 1,473.4 86.5 1,433 385 0.27 0.26 1997 1,394.6 83.6 2,314 646 0.28 0.46 1998 1,572.5 94.2 1,170 134.459 0.11 0.09 1999 1,569.1 93.8 1,107 176.878 0.16 0.11 2000 1,630.0 96.0 990 98.691 0.10 0.06 2001 1,527.5 91.6 1,375 228.071 0.17 0.15 2002 1,633.0 96.6 992 155.946 0.16 0.10

2003 1,524.7 91.5 937 141.734 0.15 0.09 2004 1,492.0 89.3 1,157 159.436 0.14 0.11 2005 1,408.4 85.1 2,262 406.171 0.18 0.29 C-42

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr ST. LUCIE 1, 2 2006 1,542.4 93.0 1,226 119.963 0.10 0.08 (continued) 2007 1,302.1 78.0 2,447 409.958 0.17 0.31 2008 1,566.5 92.7 1,127 112.234 0.10 0.07 2009 1,490.6 88.8 1,139 132.861 0.12 0.09 2010 1,440.2 88.4 1,357 197.359 0.15 0.14 2011 1,200.9 77.3 2,050 295.228 0.14 0.25 2012 1,139.5 70.6 1,750 185.426 0.11 0.16 2013 1,783.4 90.3 964 74.926 0.08 0.04 2014 1,805.7 90.9 1,068 121.092 0.11 0.07 2015 1,720.9 87.2 1,477 188.087 0.13 0.11 2016 1,779.5 89.8 920 76.628 0.08 0.04 2017 1,875.3 94.2 933 71.123 0.08 0.04 2018 1,777.1 89.9 1,107 112.919 0.10 0.06 2019 1,709.5 85.5 729 53.336 0.07 0.03 SUMMER 1 1984 504.6 61.1 1,120 295 0.26 0.58 Docket 50-395; 1985 627.7 71.6 1,201 379 0.32 0.60 NPF-12 1986 853.7 95.3 392 23 0.06 0.03 1st commercial operation 1/84 1987 618.7 71.0 1,075 560 0.52 0.91 Type - PWR 1988 605.3 69.1 1,127 511 0.45 0.84 Capacity - 966 MWe 1989 652.4 83.1 374 52 0.14 0.08 1990 730.0 83.9 1,090 376 0.34 0.52 1991 642.5 82.9 984 291 0.30 0.45 1992 892.6 97.4 249 27 0.11 0.03 1993 728.3 84.0 1,121 297 0.26 0.41 1994 536.7 69.5 1,549 374 0.24 0.70 1995 899.8 97.2 257 13 0.05 0.01 1996 850.4 90.3 701 97 0.14 0.11 1997 829.7 89.8 820 163 0.20 0.20 1998 934.8 98.8 285 13.513 0.05 0.01 1999 842.0 89.4 827 120.172 0.15 0.14 2000 723.9 76.6 933 166.561 0.18 0.23 2001 769.3 83.3 486 69.398 0.14 0.09 2002 840.0 87.9 685 59.644 0.09 0.07

2003 837.0 87.4 745 70.828 0.10 0.08 2004 938.4 96.8 200 10.085 0.05 0.01 2005 850.3 88.9 734 72.454 0.10 0.09 2006 858.6 90.0 676 61.333 0.09 0.07 2007 967.9 100.0 75 2.691 0.04 0.00 2008 817.2 84.8 623 49.091 0.08 0.06 2009 784.5 82.6 767 56.050 0.07 0.07 2010 968.8 99.4 104 2.129 0.02 0.00 2011 847.7 87.6 598 31.580 0.05 0.04 2012 829.0 85.3 766 82.261 0.11 0.10 2013 955.5 97.2 172 5.113 0.03 0.01 2014 789.4 82.6 934 110.929 0.12 0.14 2015 812.3 83.8 811 64.958 0.08 0.08 2016 988.4 100.0 137 2.862 0.02 0.00 2017 789.2 81.3 856 50.308 0.06 0.06 2018 840.9 86.4 718 49.251 0.07 0.06 2019 941.6 96.2 135 4.557 0.03 0.00 SURRY 1, 2 1973 420.6 --- 936 152 0.16 0.36 Docket 50-280, 50-281; 1974 717.4 49.8 1,715 884 0.52 1.23 DPR-32, DPR-37 1975 1,079.0 70.8 1,948 1,649 0.85 1.53 1st commercial operation 1976 930.7 60.4 2,753 3,165 1.15 3.40 12/72, 5/73 1977 1,139.0 72.2 1,860 2,307 1.24 2.03 Type - PWRs 1978 1,210.6 77.2 2,203 1,837 0.83 1.52 Capacity - 838, 838 MWe 1979 343.0 42.3 5,065 3,584 0.71 10.45 1980 568.2 40.3 5,317 3,836 0.72 6.75 1981 907.6 59.3 3,753 4,244 1.13 4.68 1982 1,323.3 88.5 1,878 1,490 0.79 1.13 1983 916.2 61.3 2,754 3,220 1.17 3.51 1984 1,026.7 71.0 3,198 2,247 0.70 2.19 1985 1,166.4 78.2 3,206 1,815 0.57 1.56 C-43

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr SURRY 1, 2 1986 1,080.5 69.0 3,763 2,356 0.63 2.18 (continued) 1987 1,132.7 72.7 2,675 712 0.27 0.63 1988 750.4 50.0 3,184 1,542 0.48 2.05 1989 489.3 33.0 3,100 836 0.27 1.71 1990 1,276.4 83.9 1,947 575 0.30 0.45 1991 1,271.9 84.5 1,547 510 0.33 0.40 1992 1,396.3 88.9 1,660 539 0.32 0.39 1993 1,283.1 84.6 1,402 383 0.27 0.30 1994 1,320.9 85.2 1,530 378 0.25 0.29 1995 1,333.0 84.2 1,883 406 0.22 0.30 1996 1,562.9 93.1 983 209 0.21 0.13 1997 1,380.3 87.1 1,335 320 0.24 0.23 1998 1,476.2 91.6 1,165 188.831 0.16 0.13 1999 1,483.0 93.5 995 137.891 0.14 0.09 2000 1,490.0 92.7 1,197 193.169 0.16 0.13 2001 1,441.5 89.5 1,243 328.650 0.26 0.23 2002 1,557.0 96.0 799 87.778 0.11 0.06

2003 1,255.9 79.7 1,628 325.729 0.20 0.26 2004 1,537.9 94.6 1,028 119.654 0.12 0.08 2005 1,506.7 94.2 877 87.717 0.10 0.06 2006 1,427.0 90.0 1,227 234.978 0.19 0.16 2007 1,516.2 94.0 1,111 207.130 0.19 0.14 2008 1,536.6 95.7 1,069 150.269 0.14 0.10 2009 1,485.1 93.1 1,241 193.703 0.16 0.13 2010 1,503.7 93.7 958 111.129 0.12 0.07 2011 1,487.4 88.1 1,121 113.718 0.10 0.08 2012 1,549.9 91.6 1,205 168.755 0.14 0.11 2013 1,644.4 95.7 770 67.528 0.09 0.04 2014 1,636.1 95.2 743 57.491 0.08 0.04 2015 1,345.9 80.1 1,275 182.980 0.14 0.14 2016 1,667.9 96.8 645 44.432 0.07 0.03 2017 1,647.0 96.0 781 58.012 0.07 0.04 2018 1,509.0 88.6 1,170 117.837 0.10 0.08 2019 1,617.9 94.4 714 52.101 0.07 0.03 SUSQUEHANNA 1, 2 1984 719.9 72.6 2,827 308 0.11 0.43 Docket 50-387, 50-388; 1985 1,452.2 76.4 3,669 1,106 0.30 0.76 NPF-14; NPF-22 1986 1,344.8 67.0 2,996 828 0.28 0.62 1st commercial operation 1987 1,749.5 85.3 2,548 621 0.24 0.35 6/83, 2/85 1988 1,691.0 83.5 1,904 516 0.27 0.31 Type - BWRs 1989 1,572.5 77.1 2,063 704 0.34 0.45 Capacity - 1,257, 1,257 MWe 1990 1,746.9 85.4 1,691 440 0.26 0.25 1991 1,878.0 89.8 1,844 507 0.27 0.27 1992 1,604.2 79.7 1,885 724 0.38 0.45 1993 1,602.1 77.3 1,488 335 0.23 0.21 1994 1,814.4 85.4 1,580 442 0.28 0.24 1995 1,850.8 85.3 1,773 476 0.27 0.26 1996 1,998.7 90.7 1,430 289 0.20 0.14 1997 1,918.9 89.6 1,646 433 0.26 0.23 1998 1,879.6 88.3 1,575 360.778 0.23 0.19 1999 1,896.0 89.6 1,787 431.397 0.24 0.23 2000 1,994.6 92.6 1,812 331.163 0.18 0.17 2001 2,027.6 94.2 1,807 288.413 0.16 0.14 2002 1,973.0 91.6 1,890 259.968 0.14 0.13

2003 2,050.8 93.4 1,934 250.096 0.13 0.12 2004 2,058.8 92.7 2,144 272.202 0.13 0.13 2005 2,086.6 93.5 1,898 181.360 0.10 0.09 2006 2,040.4 91.0 1,873 184.901 0.10 0.09 2007 2,089.2 93.0 2,303 263.021 0.11 0.13 2008 2,174.1 94.2 1,895 192.892 0.10 0.09 2009 2,231.1 94.7 1,956 266.597 0.14 0.12 2010 2,121.6 90.4 1,950 176.161 0.09 0.08 2011 1,992.0 82.2 1,847 168.968 0.09 0.08 2012 1,936.5 81.4 2,140 175.881 0.08 0.09 2013 2,166.2 88.6 1,861 233.532 0.13 0.11 C-44

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr SUSQUEHANNA 1, 2 2014 2,153.1 87.3 1,956 214.467 0.11 0.10 (continued) 2015 2,354.3 93.3 1,763 206.154 0.12 0.09 2016 2,217.2 89.4 2,210 237.336 0.11 0.11 2017 2,375.6 95.1 1,440 165.468 0.11 0.07 2018 2,343.4 95.2 1,357 147.327 0.11 0.06 2019 2,394.1 96.2 1,239 141.078 0.11 0.06 THREE MILE ISLAND 120, 221 1975 675.9 82.2 131 73 0.56 0.11 Docket 50-289, 50-320; 1976 530.0 65.4 819 286 0.35 0.54 DPR-50, DPR-73 1977 664.5 80.9 1,122 360 0.32 0.54 1st commercial operation 1978 690.0 85.1 1,929 504 0.26 0.73 9/74, 12/78 1979 266.0 21.9 3,975 1,392 0.35 5.23 Type - PWRs 1980 0.0 0.0 2,328 394 0.17 ---

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

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

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

1984 0.0 0.0 1,079 688 0.64 ---

1985 103.6 10.6 1,890 857 0.45 8.27 THREE MILE ISLAND 120 1986 585.2 70.9 1,360 213 0.16 0.36 Docket 50-289; 1987 610.7 73.6 1,259 149 0.12 0.24 DPR-50 1988 661.0 77.8 1,012 210 0.21 0.32 1st commercial operation 9/74 1989 871.3 100.0 670 54 0.08 0.06 Type - PWR 1990 645.5 84.6 1,319 264 0.20 0.41 Capacity - (802) MWe 1991 688.7 86.4 1,542 198 0.13 0.29 1992 836.8 100.0 558 34 0.06 0.04 1993 722.0 88.5 1,835 206 0.11 0.29 1994 798.7 95.5 434 40 0.09 0.05 1995 772.9 90.8 1,220 213 0.17 0.28 1996 857.4 100.0 267 16 0.06 0.02 1997 675.7 84.3 1,049 204 0.19 0.30 1998 805.8 100.0 280 16.722 0.06 0.02 1999 722.4 89.7 1,171 154.936 0.13 0.21 2000 813.4 100.0 183 8.689 0.05 0.01 2001 616.7 84.2 1,196 196.699 0.16 0.32 2002 833.0 100.0 172 6.533 0.04 0.01 2003 706.4 87.1 1,230 155.101 0.13 0.22 2004 828.0 100.0 105 3.573 0.03 0.00 2005 769.1 93.2 955 65.576 0.07 0.09 2006 825.0 99.0 125 5.155 0.04 0.01 2007 758.6 92.0 1,266 114.203 0.09 0.15 2008 838.5 100.0 64 2.219 0.03 0.00 2009 672.6 81.7 2,019 241.780 0.12 0.36 2010 757.3 93.1 790 38.994 0.05 0.05 2011 744.2 91.4 1,224 129.775 0.11 0.17 2012 820.7 96.3 280 13.073 0.05 0.02 2013 762.5 92.2 1,294 125.803 0.10 0.16 2014 834.3 100.0 204 12.518 0.06 0.02 2015 753.2 92.1 1,454 171.431 0.12 0.23 2016 808.5 97.0 309 16.843 0.05 0.02 2017 783.3 94.4 1,009 82.657 0.08 0.11 2018 837.4 100.0 78 2.641 0.03 0.00 2019 0.0 0.0 189 7.252 0.04 ---

THREE MILE ISLAND 221 1986 0.0 0.0 1,497 915 0.61 ---

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

DPR-73 1988 0.0 0.0 1,247 917 0.74 ---

1st commercial operation 12/78 1989 0.0 0.0 1,014 639 0.63 ---

Type - PWR 1990 0.0 0.0 484 136 0.28 ---

Capacity - (880) MWe 1991 0.0 0.0 153 37 0.24 ---

20 Three Mile Island 1 resumed commercial power generation in October 1985 after being under regulatory restraint since 1979.

Three Mile Island 1 ceased operations in September of 2019 and is no longer included in the count of operating reactors.

Parentheses indicate plant capacity when plant was operational.

21 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. From 2001-2015, TMI voluntarily provided an estimate of the collective dose for Unit 2, but not the number of individuals with measurable dose.

C-45

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr THREE MILE ISLAND 221 1992 0.0 0.0 315 157 0.50 ---

(continued) 1993 0.0 0.0 167 33 0.20 ---

1994 0.0 0.0 259 7 0.03 ---

1995 0.0 0.0 191 2 0.01 ---

1996 0.0 0.0 122 2 0.02 ---

1997 0.0 0.0 232 1 0.00 ---

1998 0.0 0.0 105 0.697 0.01 ---

1999 0.0 0.0 203 0.512 0.00 ---

2000 0.0 0.0 70 0.401 0.01 ---

2001 0.0 0.0 0 0.228 --- ---

2002 0.0 0.0 0 --- --- ---

2003 0.0 0.0 0 0.260 --- ---

2004 0.0 0.0 0 0.216 --- ---

2005 0.0 0.0 0 --- --- ---

2006 0.0 0.0 0 0.372 --- ---

2007 0.0 0.0 0 0.082 --- ---

2008 0.0 0.0 0 0.138 --- ---

2009 0.0 0.0 0 0.113 --- ---

2010 0.0 0.0 0 0.359 --- ---

2011 0.0 0.0 0 0.291 --- ---

2012 0.0 0.0 0 0.194 --- ---

2013 0.0 0.0 0 0.229 --- ---

2014 0.0 0.0 0 0.188 --- ---

2015 0.0 0.0 0 0.255 --- ---

TROJAN22 1977 792.0 92.6 591 174 0.29 0.22 Docket 50-344; 1978 205.5 20.6 711 319 0.45 1.55 NPF-1 1979 631.0 58.1 736 258 0.35 0.41 1st commercial operation 5/76 1980 727.5 72.5 1,159 421 0.36 0.58 Type - PWR 1981 775.6 74.1 1,311 609 0.46 0.79 Capacity - (1,080) MWe 1982 579.5 60.8 977 419 0.43 0.72 1983 494.2 62.4 969 307 0.32 0.62 1984 567.0 54.4 1,042 433 0.42 0.76 1985 829.1 76.7 852 363 0.43 0.44 1986 852.4 79.7 1,321 381 0.29 0.45 1987 525.5 54.0 1,209 363 0.30 0.69 1988 758.6 67.5 1,408 401 0.28 0.53 1989 666.8 61.9 1,360 421 0.31 0.63 1990 732.4 66.3 1,169 258 0.22 0.35 1991 181.6 16.1 1,496 567 0.38 3.12 1992 553.9 68.4 567 84 0.15 0.15 1993 0.0 68.4 54 21 0.39 ---

1994 0.0 0.0 51 9 0.18 ---

1995 0.0 0.0 141 44 0.31 ---

1996 0.0 0.0 112 41 0.37 ---

1997 0.0 0.0 227 41 0.18 ---

1998 0.0 0.0 283 46.417 0.16 ---

1999 0.0 0.0 274 51.504 0.19 ---

2000 0.0 0.0 127 17.631 0.14 ---

2001 0.0 0.0 14 1.091 0.08 ---

2002 0.0 0.0 13 0.536 0.04 ---

2003 0.0 0.0 105 23.996 0.23 ---

2004 0.0 0.0 5 0.079 0.02 ---

TURKEY POINT 3, 4 1973 401.9 --- 444 78 0.18 0.19 Docket 50-250, 50-251; 1974 953.6 --- 794 454 0.57 0.48 DPR-31, DPR-41 1975 1,003.7 74.9 1,176 876 0.74 0.87 1st commercial operation 1976 974.2 71.2 1,647 1,184 0.72 1.22 12/72, 9/73 1977 979.5 72.1 1,319 1,036 0.79 1.06 Type - PWRs 1978 1,000.2 78.8 1,336 1,032 0.77 1.03 Capacity - 837, 821 MWe 1979 811.0 62.4 2,002 1,680 0.84 2.07 21 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. From 2001-2015, TMI voluntarily provided an estimate of the collective dose for Unit 2, but not the number of individuals with measurable dose.

22 Trojan ceased operations in 1992 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. As of 2005, Trojan no longer reports under its reactor license, but does report under its ISFSI license (see Appendix A).

C-46

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr TURKEY POINT 3, 4 1980 990.6 73.6 1,803 1,651 0.92 1.67 (continued) 1981 654.0 46.8 2,932 2,251 0.77 3.44 1982 915.7 65.2 2,956 2,119 0.72 2.31 1983 878.4 62.8 2,930 2,681 0.92 3.05 1984 946.7 68.5 2,010 1,255 0.62 1.33 1985 1,034.9 74.7 1,905 1,253 0.66 1.21 1986 754.1 54.9 1,808 946 0.52 1.25 1987 431.3 36.6 1,980 1,371 0.69 3.18 1988 809.8 59.5 1,841 738 0.40 0.91 1989 689.9 56.8 1,625 433 0.27 0.63 1990 933.1 69.0 2,099 730 0.35 0.78 1991 258.2 21.0 2,087 939 0.45 3.64 1992 968.9 75.5 1,374 325 0.24 0.34 1993 1,244.8 91.0 1,271 275 0.22 0.22 1994 1,172.9 87.2 1,489 476 0.32 0.41 1995 1,320.3 94.6 1,142 215 0.19 0.16 1996 1,307.8 94.0 1,157 187 0.16 0.14 1997 1,220.9 88.6 1,581 414 0.26 0.34 1998 1,323.0 94.5 1,045 156.415 0.15 0.12 1999 1,352.5 96.5 919 127.567 0.14 0.09 2000 1,283.7 92.2 1,292 219.852 0.17 0.17 2001 1,324.1 95.0 827 101.575 0.12 0.08 2002 1,374.0 97.9 793 73.764 0.09 0.05 2003 1,253.2 91.6 1,442 247.053 0.17 0.20 2004 1,231.0 89.9 1,089 117.404 0.11 0.10 2005 1,143.0 84.9 1,136 109.996 0.10 0.10 2006 1,251.8 90.0 1,321 149.208 0.11 0.12 2007 1,281.5 91.0 1,085 107.601 0.10 0.08 2008 1,294.9 92.0 1,067 97.357 0.09 0.08 2009 1,219.7 87.6 1,359 166.217 0.12 0.14 2010 1,290.9 91.9 1,025 86.749 0.08 0.07 2011 1,245.7 89.6 921 62.326 0.07 0.05 2012 878.0 67.9 2,024 241.151 0.12 0.27 2013 1,245.9 82.7 882 82.215 0.09 0.07 2014 1,375.7 89.4 1,271 114.326 0.09 0.08 2015 1,489.7 92.7 933 79.124 0.08 0.05 2016 1,567.7 95.6 892 76.269 0.09 0.05 2017 1,451.9 88.8 1,104 108.200 0.10 0.07 2018 1,570.2 94.9 651 51.088 0.08 0.03 2019 1,614.4 95.8 905 84.610 0.09 0.05 VERMONT YANKEE23 1973 222.1 --- 244 85 0.35 0.38 Docket 50-271; 1974 303.5 --- 357 216 0.61 0.71 DPR-28 1975 429.0 87.8 282 153 0.54 0.36 1st commercial operation 11/72 1976 389.6 77.1 815 411 0.50 1.05 Type - BWR 1977 423.5 85.1 641 258 0.40 0.61 Capacity - (605) MWe 1978 387.5 75.9 934 339 0.36 0.87 1979 414.0 82.1 1,220 1,170 0.96 2.83 1980 357.8 71.5 1,443 1,338 0.93 3.74 1981 429.1 84.6 1,264 731 0.58 1.70 1982 501.0 96.0 481 205 0.43 0.41 1983 346.1 69.3 1,316 1,527 1.16 4.41 1984 398.1 79.0 954 626 0.66 1.57 1985 361.4 71.8 1,392 1,051 0.76 2.91 1986 248.1 48.9 1,389 1,188 0.86 4.79 1987 423.6 84.2 827 303 0.37 0.72 1988 492.1 95.7 379 124 0.33 0.25 1989 432.8 84.7 832 288 0.35 0.67 1990 433.1 85.9 849 307 0.36 0.71 1991 492.3 94.3 310 118 0.38 0.24 1992 446.8 88.1 921 381 0.41 0.85 1993 402.3 80.1 833 217 0.26 0.54 23 Vermont Yankee ceased operations in December 2014 and is no longer in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-47

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr VERMONT YANKEE22 1994 515.8 98.7 220 38 0.17 0.07 (continued) 1995 462.1 87.0 737 182 0.25 0.39 1996 452.7 85.2 951 231 0.24 0.51 1997 487.1 96.0 260 57 0.22 0.12 1998 383.4 77.9 944 199.399 0.21 0.52 1999 463.4 91.0 854 175.795 0.21 0.38 2000 517.8 99.6 198 37.846 0.19 0.07 2001 474.9 93.5 863 143.010 0.17 0.30 2002 451.0 91.7 946 150.446 0.16 0.33

2003 505.9 98.8 359 54.348 0.15 0.11 2004 439.2 87.2 1,379 211.529 0.15 0.48 2005 467.5 94.2 1,105 198.003 0.18 0.42 2006 582.9 100.0 380 49.537 0.13 0.08 2007 537.0 93.0 1,191 171.200 0.14 0.32 2008 557.3 94.1 1,402 213.680 0.15 0.38 2009 611.9 100.0 392 61.105 0.16 0.10 2010 548.6 91.2 1,071 206.321 0.19 0.38 2011 562.1 93.3 1,029 176.129 0.17 0.31 2013 555.5 92.9 1,034 170.340 0.16 0.31 2014 580.4 99.3 196 21.350 0.11 0.04 2015 0.0 0.0 413 49.557 0.12 ---

2016 0.0 0.0 128 12.513 0.10 ---

2017 0.0 0.0 128 13.698 0.11 ---

2018 0.0 0.0 185 17.807 0.10 ---

2019 0.0 0.0 179 45.432 0.25 ---

VOGTLE 1, 2 1988 820.4 77.7 1,108 138 0.12 0.17 Docket 50-424; 50-425; 1989 1,045.8 96.0 427 32 0.07 0.03 NPF-68, NPF-81 1990 1,710.9 82.7 1,602 466 0.29 0.27 1st commercial operation 1991 1,966.5 89.2 1,357 362 0.27 0.18 6/87, 5/89 1992 2,047.9 90.0 1,262 426 0.34 0.21 Type - PWRs 1993 2,060.4 88.3 1,338 367 0.27 0.18 Capacity - 1,150, 1,152 MWe 1994 2,170.1 91.3 1,048 217 0.21 0.10 1995 2,285.4 95.2 953 199 0.21 0.09 1996 2,056.8 86.5 1,395 452 0.32 0.22 1997 2,121.1 91.4 994 158 0.16 0.07 1998 2,123.9 92.3 994 162.210 0.16 0.08 1999 2,106.0 91.5 1,359 228.942 0.17 0.11 2000 2,223.9 95.6 899 121.312 0.14 0.05 2001 2,231.5 96.2 870 129.270 0.15 0.06 2002 1,942.0 85.3 1,152 243.957 0.21 0.13

2003 2,179.9 94.8 806 84.344 0.10 0.04 2004 2,200.7 95.7 765 80.763 0.11 0.04 2005 2,027.9 88.6 1,099 151.096 0.14 0.07 2006 2,048.8 89.0 892 115.509 0.13 0.06 2007 2,089.9 92.0 951 120.515 0.13 0.06 2008 2,023.9 89.3 1,185 137.620 0.12 0.07 2009 2,201.6 95.7 931 79.681 0.09 0.04 2010 2,238.6 95.8 924 89.182 0.10 0.04 2011 2,138.0 92.6 1,179 118.931 0.10 0.06 2012 2,226.6 95.7 776 59.317 0.08 0.03 2013 2,178.4 95.3 857 78.298 0.09 0.04 2014 2,065.8 91.6 1,404 156.744 0.11 0.08 2015 2,210.0 95.3 843 60.565 0.07 0.03 2016 2,267.1 97.0 778 58.472 0.08 0.03 2017 2,189.0 94.3 938 80.556 0.09 0.04 2018 2,278.4 97.1 641 46.855 0.07 0.02 2019 2,255.0 96.6 625 50.668 0.08 0.02 WATERFORD 3 1986 875.7 79.1 1,244 223 0.18 0.25 Docket 50-382; 1987 891.8 82.5 959 156 0.16 0.17 NPF-38 1988 784.3 75.4 1,246 259 0.21 0.33 1st commercial operation 9/85 1989 909.8 82.6 1,306 265 0.20 0.29 Type - PWR 1990 1,027.9 92.8 432 47 0.11 0.05 Capacity - 1,152 MWe 1991 870.6 79.8 1,301 364 0.28 0.42 1992 909.6 83.2 1,213 226 0.19 0.25 22 Vermont Yankee ceased operations in December 2014 and is no longer in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-48

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr WATERFORD 3 1993 1,088.3 99.4 195 15 0.08 0.01 (continued) 1994 949.1 87.0 1,167 191 0.16 0.20 1995 927.4 83.4 1,092 153 0.14 0.16 1996 1,064.8 94.2 342 27 0.08 0.03 1997 767.2 71.2 1,186 148 0.13 0.19 1998 984.1 91.9 282 24.032 0.09 0.02 1999 849.5 79.6 833 123.198 0.15 0.15 2000 965.1 88.8 825 131.701 0.16 0.14 2001 1,086.0 99.6 91 4.677 0.05 0.00 2002 1,007.0 93.2 811 109.439 0.13 0.11

2003 968.0 90.9 710 95.332 0.13 0.10 2004 1,099.1 100.0 60 2.517 0.04 0.00 2005 900.9 80.2 902 136.318 0.15 0.15 2006 1,059.3 92.0 1,190 109.682 0.09 0.10 2007 1,130.2 96.0 469 20.125 0.04 0.02 2008 1,030.7 88.0 1,268 134.221 0.11 0.13 2009 1,023.4 88.0 1,479 255.088 0.17 0.25 2010 1,173.1 100.0 216 4.913 0.02 0.00 2011 1,020.8 90.4 1,144 100.053 0.09 0.10 2012 897.1 78.0 1,919 260.202 0.14 0.29 2013 1,071.6 93.7 130 3.129 0.02 0.00 2014 1,046.4 91.5 965 69.462 0.07 0.07 2015 959.5 85.1 979 65.826 0.07 0.07 2016 1,152.5 98.4 248 3.392 0.01 0.00 2017 959.1 83.8 894 60.728 0.07 0.06 2018 1,175.6 100.0 98 1.130 0.01 0.00 2019 869.0 75.8 931 69.780 0.07 0.08 WATTS BAR 1, 2 1997 867.6 83.8 1,103 113 0.10 0.13 Docket 50-390, 50-391; 1998 1,105.1 99.1 96 3.106 0.03 0.00 NPF-90, NPF-96 1999 943.1 87.2 975 98.946 0.10 0.10 1st commercial operation 2000 1,033.3 92.8 1,053 122.453 0.12 0.12

5/96, 10/16 2001 1,095.9 96.5 197 5.912 0.03 0.01 Type - PWR 2002 1,034.0 92.1 909 93.598 0.10 0.09

Capacity - 1,157, 1,164 MWe 2003 973.3 86.7 1,392 165.741 0.12 0.17 2004 1,122.1 99.1 220 5.893 0.03 0.01 2005 1,003.7 90.0 1,244 143.506 0.12 0.14 2006 764.5 70.0 2,070 322.682 0.16 0.42 2007 1,150.6 100.0 128 4.414 0.03 0.00 2008 923.5 83.2 887 70.648 0.08 0.08 2009 1,051.1 92.1 853 63.846 0.07 0.06 2010 1,111.7 98.3 129 6.193 0.05 0.01 2011 939.6 85.4 900 51.021 0.06 0.05 2012 969.5 86.5 1,002 62.779 0.06 0.06 2013 1,137.9 99.5 85 2.616 0.03 0.00 2014 1,003.4 89.0 600 28.268 0.05 0.03 2015 964.5 87.5 976 64.320 0.07 0.07 2016 1,284.1 97.8 189 4.489 0.02 0.00 2017 1,558.2 69.6 1,074 75.672 0.07 0.05 2018 2,110.1 92.3 779 36.920 0.05 0.02 2019 2,018.4 88.8 832 45.017 0.05 0.02 WOLF CREEK 1 1986 832.8 73.3 682 143 0.21 0.17 Docket 50-482; 1987 778.8 71.1 675 138 0.20 0.18 NPF-42 1988 794.7 70.7 1,010 297 0.29 0.37 1st commercial operation 9/85 1989 1,108.4 99.5 186 18 0.10 0.02 Type - PWR 1990 940.2 81.0 798 195 0.24 0.21 Capacity - 1,164 MWe 1991 707.6 71.9 1,010 331 0.33 0.47 1992 1,010.8 86.7 446 78 0.17 0.08 1993 940.5 80.6 975 183 0.19 0.19 1994 1,017.2 86.8 1,082 235 0.22 0.23 1995 1,198.0 98.7 242 14 0.06 0.01 1996 980.6 81.2 986 171 0.17 0.17 1997 964.3 83.8 989 265 0.27 0.27 1998 1,187.3 100.0 184 10.382 0.06 0.01 C-49

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr WOLF CREEK 1 1999 1,045.3 90.1 812 147.704 0.18 0.14 (continued) 2000 1,032.7 89.5 861 143.417 0.17 0.14 2001 1,177.9 100.0 105 5.176 0.05 0.00 2002 1,029.0 88.7 816 99.987 0.12 0.10

2003 1,013.5 87.2 820 88.941 0.11 0.09 2004 1,153.5 98.8 93 3.388 0.04 0.00 2005 1,004.2 86.7 856 106.870 0.12 0.11 2006 1,067.4 91.0 789 96.788 0.12 0.09 2007 1,183.7 100.0 91 4.307 0.05 0.00 2008 968.3 83.1 911 94.997 0.10 0.10 2009 1,001.0 86.9 1,504 73.637 0.05 0.07 2010 1,090.8 94.2 463 10.516 0.02 0.01 2011 839.1 73.0 1,266 133.960 0.11 0.16 2012 944.4 80.0 306 7.888 0.03 0.01 2013 819.2 72.5 1,452 111.257 0.08 0.14 2014 978.2 81.9 709 27.500 0.04 0.03 2015 987.9 82.5 1,190 74.804 0.06 0.08 2016 942.0 78.5 1,267 90.631 0.07 0.10 2017 1,215.5 100.0 238 3.437 0.01 0.00 2018 1,047.5 86.9 1,153 72.882 0.06 0.07 2019 1,056.6 87.4 784 45.183 0.06 0.04 YANKEE ROWE24 1969 138.3 --- 193 215 1.11 1.55 Docket 50-29; 1970 146.1 --- 355 255 0.72 1.75 DPR-3 1971 173.5 --- 155 90 0.58 0.52 1st commercial operation 7/61 1972 78.7 --- 282 255 0.90 3.24 Type - PWR 1973 127.1 --- 133 99 0.74 0.78 Capacity - (175) MWe 1974 111.3 --- 243 205 0.84 1.84 1975 145.1 82.4 249 116 0.47 0.80 1976 152.2 89.8 152 59 0.39 0.39 1977 124.6 73.9 725 356 0.49 2.86 1978 145.0 81.0 565 282 0.50 1.94 1979 149.0 81.6 441 127 0.29 0.85 1980 35.6 22.0 502 213 0.42 5.98 1981 109.0 74.4 515 302 0.59 2.77 1982 108.6 73.4 814 474 0.58 4.36 1983 163.5 91.4 395 68 0.17 0.42 1984 124.8 71.4 654 348 0.53 2.79 1985 144.3 85.3 653 211 0.32 1.46 1986 169.7 95.0 384 45 0.12 0.27 1987 138.7 82.7 593 217 0.37 1.56 1988 136.4 85.2 738 227 0.31 1.66 1989 159.4 92.9 496 62 0.13 0.39 1990 101.1 61.5 702 246 0.35 2.43 1991 121.2 72.3 162 40 0.25 0.33 1992 0.0 0.0 324 94 0.29 ---

1993 0.0 0.0 313 163 0.52 ---

1994 0.0 0.0 222 156 0.70 ---

1995 0.0 0.0 191 78 0.41 ---

1996 0.0 0.0 239 95 0.40 ---

1997 0.0 0.0 323 65 0.20 ---

1998 0.0 0.0 125 4.603 0.04 ---

1999 0.0 0.0 83 2.291 0.02 ---

2000 0.0 0.0 38 2.406 0.06 ---

2001 0.0 0.0 48 3.969 0.08 ---

2002 0.0 0.0 128 20.024 0.16 ---

2003 0.0 0.0 136 30.934 0.23 ---

2004 0.0 0.0 70 6.502 0.09 ---

2005 0.0 0.0 63 1.456 0.02 ---

24 Yankee Rowe ceased operations as of October 1991 and will not be put in commercial operation again. It is no longer in the count of operating reactors. Parentheses indicate plant capacity when plant was operational.

C-50

Total Collective Personnel Dose Average Megawatt Unit with per Site Measurable Collective Years Availability Measurable (person- Dose Dose/

Reporting Organization Year (MW-yr) Factor Doses rem) (rem) MW-yr YANKEE ROWE24 2006 0.0 0.0 45 0.975 0.02 ---

(continued) 2007 0.0 0.0 0 0.000 --- ---

2008 0.0 0.0 1 0.019 0.02 ---

2009 0.0 0.0 5 0.114 0.02 ---

2010 0.0 0.0 3 0.083 0.03 ---

2011 0.0 0.0 8 0.113 0.01 ---

2012 0.0 0.0 1 0.013 0.01 ---

2013 0.0 0.0 2 0.043 0.02 ---

2014 0.0 0.0 10 0.145 0.01 ---

2015 0.0 0.0 25 0.463 0.02 ---

2016 0.0 0.0 5 0.073 0.01 ---

2017 0.0 0.0 7 0.112 0.02 ---

2018 0.0 0.0 4 0.045 0.01 ---

2019 0.0 0.0 7 0.113 0.02 ---

ZION 1, 225 1974 425.3 71.1 306 56 0.18 0.13 Docket 50-295; 50-304; 1975 1,181.5 74.9 436 127 0.29 0.11 DPR-39, DPR-48 1976 1,134.9 61.9 774 571 0.74 0.50 1st commercial operation 1977 1,358.6 75.0 784 1,003 1.28 0.74 12/73, 9/74 1978 1,613.5 80.2 1,104 1,017 0.92 0.63 Type - PWRs 1979 1,238.0 67.6 1,472 1,274 0.87 1.03 Capacity - (1,040), (1,040) MWe 1980 1,411.2 74.1 1,363 920 0.67 0.65 1981 1,366.9 72.3 1,754 1,720 0.98 1.26 1982 1,186.4 64.3 1,575 2,103 1.34 1.77 1983 1,222.3 69.4 1,285 1,311 1.02 1.07 1984 1,389.9 69.6 1,110 786 0.71 0.57 1985 1,187.9 62.9 1,498 1,166 0.78 0.98 1986 1,462.0 73.2 967 474 0.49 0.32 1987 1,337.0 71.0 1,046 653 0.62 0.49 1988 1,549.1 78.3 1,926 1,260 0.65 0.81 1989 1,514.1 77.6 1,282 624 0.49 0.41 1990 860.4 46.9 1,385 696 0.50 0.81 1991 1,125.7 58.2 902 173 0.19 0.15 1992 1,128.8 59.0 1,732 1,043 0.60 0.92 1993 1,458.2 70.9 1,772 643 0.36 0.44 1994 1,224.9 59.9 1,176 306 0.26 0.25 1995 1,471.6 72.4 1,807 797 0.44 0.54 1996 1,538.4 75.8 1,567 437 0.28 0.28 1997 123.2 7.1 924 119 0.13 0.97 1998 0.0 0.0 246 12.417 0.05 ---

1999 0.0 0.0 67 4.194 0.06 ---

2000 0.0 0.0 26 3.015 0.12 ---

2001 0.0 0.0 6 0.274 0.05 ---

2002 0.0 0.0 12 0.276 0.02 ---

2003 0.0 0.0 2 0.049 0.02 ---

2004 0.0 0.0 6 0.167 0.03 ---

2005 0.0 0.0 5 0.109 0.02 ---

2006 0.0 0.0 7 0.109 0.02 ---

2007 0.0 0.0 8 0.224 0.03 ---

2008 0.0 0.0 7 0.147 0.02 ---

2009 0.0 0.0 0 0.000 --- ---

2010 0.0 0.0 17 0.562 0.03 ---

2011 0.0 0.0 128 28.794 0.22 ---

2012 0.0 0.0 183 75.801 0.41 ---

2013 0.0 0.0 218 44.689 0.20 ---

2014 0.0 0.0 358 78.730 0.22 ---

2015 0.0 0.0 340 142.605 0.42 ---

2016 0.0 0.0 194 45.788 0.24 ---

2017 0.0 0.0 75 4.542 0.06 ---

2018 0.0 0.0 7 0.085 0.01 ---

2019 0.0 0.0 4 0.123 0.03 ---

24 Yankee Rowe ceased operations as of October 1991 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.

25 Zion 1, 2 ceased operations in 1997 and 1996, respectively, and are no longer included in the count of operating reactors.

Parentheses indicate plant capacity when plant was operational.

C-51

APPENDIX D DOSE PERFORMANCE TRENDS BY REACTOR SITE 1973- 2019 Appendix D only contains data on plants still operating in 2019.

DOSE PERFORMANCE TRENDS BY REACTOR SITE 1973- 2019 GRAPHICAL REPRESENTATION OF DOSE TRENDS IN APPENDIX D Each page of Appendix D presents a graph of selected dose performance trends from 1973 through 2019. The graphs 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 each plants first full year of commercial operation and continuing through 2019. Data for years when a plant was not in commercial operation have been included when available; however, any data reported before 1973 are not included. The 3-year average collective dose per reactor data are included because the data provide an overall indication of each 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 licensees as low as is reasonably achievable program. This average is determined by summing the collective dose per reactor for the current year and the previous 2 years and then dividing this sum by 3, which is the number of years considered. Depicting dose trends by 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 provides a more representative depiction of collective dose trends over the life of a plant. The annual average collective dose per reactor for all reactors of the same type is also shown on the graph.

D-1

ARKANSAS 1, 2 ARKANSAS 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 2,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 MW-Yr 1,800 800 1,600 700 1,400 DOSE (Person-rem) DOSE (Person-rem) 600 1,200 500 1,000 MW-Yr 400 800 300 600 200 400 100 200 0 0 Year Year 10-Year Dose Performance Trends 200 2,000 3-Year Average 1,800 Collective Collective 175 Dose per Dose per 1,600 Year Reactor Reactor MW-Yr 150 2010 66.351 50.000 1,716.6 1,400 DOSE (Person-rem) 2011 53.165 58.000 1,621.9 125 1,200 2012 43.361 22.000 1,764.5 2013 35.139 25.000 1,366.6 100 1,000 MW-Yr 2014 27.585 36.000 1,654.6 800 75 2015 43.055 68.000 1,582.0 600 2016 53.232 55.553 1,535.7 50 2017 55.723 43.250 1,451.4 400 2018 55.664 68.187 1,456.8 25 200 2019 51.161 42.043 1,553.8 0 0 Year D-2

BEAVER VALLEY 1, 2 BEAVER VALLEY 1,2 Historical Dose Performance Trends Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 1,800 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 MW-Yr 1,600 800 1,400 700 1,200 DOSE (Person-rem) DOSE (Person-rem) 600 1,000 500 MW-Yr 800 400 600 300 400 200 100 200 0 0 Year Year 10-Year Dose Performance Trends 200 1,800 3-Year Average Collective Collective 175 1,600 Dose per Dose per Year Reactor Reactor MW-Yr 1,400 150 2010 59.650 25.000 1,714.2 1,200 2011 57.784 36.000 1,705.5 DOSE (Person-rem) 125 2012 41.226 62.000 1,622.6 1,000 2013 39.847 21.000 1,687.4 100 MW-Yr 800 2014 38.305 32.000 1,684.6 75 2015 33.312 47.604 1,659.6 600 2016 33.718 22.073 1,737.4 50 2017 32.177 26.853 1,747.9 400 2018 28.776 37.401 1,672.8 25 200 2019 25.654 12.708 1,764.4 0 0 Year D-3

BRAIDWOOD 1, 2 BRAIDWOOD 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 500 3-Year Average Collective Dose per Reactor 3,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor 450 MW-Yr 2,500 400 350 2,000 DOSE (Person-rem) DOSE (Person-rem) 300 250 1,500 MW-Yr 200 1,000 150 100 500 50 0 0 Year Year 10-Year Dose Performance Trends 150 3,000 3-Year Average Collective Collective Dose per Dose per 125 2,500 Year Reactor Reactor MW-Yr 2010 51.520 32.000 2,111.9 100 2,000 2011 46.014 35.000 2,257.5 DOSE (Person-rem) 2012 50.279 84.000 2,141.0 2013 44.944 16.000 2,244.2 75 1,500 MW-Yr 2014 40.333 21.000 2,313.9 2015 21.135 26.234 2,250.0 50 1,000 2016 22.443 19.848 2,265.9 2017 28.472 39.334 2,281.4 2018 29.911 30.550 2,201.3 25 500 2019 26.554 9.777 2,311.8 0 0 Year D-4

BROWNS FERRY 1, 2, 3*BROWNS FERRY 1, 2, 3 Historical Dose Performance Trends Dose Performance Trends BWR 1,400 3-Year Average Collective Dose per Reactor 3,500 Collective Dose per Reactor BWR Average Collective Dose per Reactor MW-Yr 1,200 3,000 1,000 2,500 DOSE (Person-rem) DOSE (Person-rem) 800 2,000 MW-Yr 600 1,500 400 1,000 200 500 0 0 YearYear 10-Year Dose Performance Trends 400 3,500 3-Year Average Collective Collective 350 3,000 Dose per Dose per Year Reactor Reactor MW-Yr 300 2,500 2010 154.123 186.000 2,828.0 DOSE (Person-rem) 2011 133.516 99.000 2,845.8 250 2,000 2012 146.413 155.000 2,969.2 2013 127.064 128.000 3,050.0 200 MW-Yr 2014 137.421 130.000 3,052.3 1,500 150 2015 117.836 96.021 3,158.6 2016 120.278 134.862 2,992.6 1,000 100 2017 115.857 116.687 3,179.0 2018 139.255 166.217 2,930.8 50 500 2019 134.634 120.999 3,381.3 0 0 Year

• Browns Ferry Unit 1 resumed power generation in 2007.

D-5

BRUNSWICK 1, 2 BRUNSWICK 1, 2 Historical Dose Performance Trends Dose Performance Trends BWR 3,000 3-Year Average Collective Dose per Reactor 2,000 Collective Dose per Reactor BWR Average Collective Dose per Reactor MW-Yr 1,800 2,500 1,600 1,400 2,000 DOSE (Person-rem) DOSE (Person-rem) 1,200 1,500 1,000 MW-Yr 800 1,000 600 400 500 200 0 0 10-Year Year Year Dose Performance Trends 300 2,000 3-Year Average 1,800 Collective Collective Dose per Dose per 250 1,600 Year Reactor Reactor MW-Yr 2010 185.329 204.000 1,690.7 1,400 200 DOSE (Person-rem) 2011 189.805 190.000 1,662.7 1,200 2012 193.059 185.000 1,629.3 2013 185.346 180.000 1,650.6 150 1,000 MW-Yr 2014 165.487 130.952 1,750.6 800 2015 142.270 115.285 1,745.6 100 600 2016 109.952 83.618 1,756.7 2017 102.303 108.007 1,754.6 400 50 2018 94.421 91.638 1,669.7 200 2019 103.671 111.368 1,680.0 0 0 Year D-6

BYRON 1, 2 BYRON 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 2,500 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 MW-Yr 800 2,000 700 DOSE (Person-rem) DOSE (Person-rem) 600 1,500 500 MW-Yr 400 1,000 300 200 500 100 0 0 10-Year Year Year Dose Performance Trends 200 2,500 3-Year Average Collective Collective 175 Dose per Dose per 2,000 Year Reactor Reactor MW-Yr 150 2010 46.778 28.000 2,266.6 DOSE (Person-rem) 2011 63.996 122.000 2,077.9 125 1,500 2012 58.584 26.000 2,085.4 2013 58.798 29.000 2,231.4 100 MW-Yr 2014 31.567 40.000 2,197.8 1,000 75 2015 30.236 21.468 2,222.8 2016 29.620 27.006 2,237.5 50 2017 30.799 43.923 2,186.4 500 2018 27.836 12.578 2,288.9 25 2019 24.887 18.161 2,296.6 0 0 Year D-7

CALLAWAY 1 CALLAWAY 1 Dose Performance Trends Historical Dose Performance Trends PWR 800 3-Year Average Collective Dose per Reactor 1,600 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 700 1,400 600 1,200 500 1,000 DOSE (Person-rem) DOSE (Person-rem) 400 800 MW-Yr 300 600 200 400 100 200 0 0 10-Year Year Dose Performance Trends Year 200 1,600 3-Year Average Collective Collective 175 1,400 Dose per Dose per Year Reactor Reactor MW-Yr 150 1,200 2010 36.419 59.000 1,029.9 DOSE (Person-rem) 2011 47.927 80.000 1,071.7 125 1,000 2012 47.829 5.000 1,220.2 MW-Yr 2013 42.621 43.000 959.9 100 800 2014 28.274 37.000 1,061.3 75 600 2015 27.808 3.128 1,192.2 2016 29.024 46.770 1,078.3 50 400 2017 24.537 23.713 951.9 2018 24.565 3.211 1,216.6 25 200 2019 21.518 37.630 1,053.4 0 0 Year D-8

CALVERT CLIFFS 1, 2 CALVERT CLIFFS 1, 2 Dose Performance Trends Historical Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 2,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 MW-Yr 1,800 800 1,600 700 1,400 DOSE (Person-rem) DOSE (Person-rem) 600 1,200 500 1,000 MW-Yr 400 800 300 600 200 400 100 200 0 0 10-Year Year Dose Performance Trends Year 150 2,000 3-Year Average 1,800 Collective Collective 125 Dose per Dose per 1,600 Year Reactor Reactor MW-Yr 2010 49.756 64.000 1,597.3 1,400 100 DOSE (Person-rem) 2011 53.262 48.000 1,635.9 1,200 2012 56.557 58.000 1,545.6 2013 45.306 30.000 1,632.6 75 1,000 MW-Yr 2014 39.778 31.000 1,638.3 800 2015 28.128 22.812 1,672.4 50 2016 32.263 42.946 1,685.6 600 2017 30.133 24.642 1,725.0 400 25 2018 31.945 28.247 1,711.0 200 2019 27.504 29.623 1,713.8 0 0 Year D-9

CATAWBA 1, 2 CATAWBA 1, 2 Dose Performance Trends Historical Dose Performance Trends PWR 600 3-Year Average Collective Dose per Reactor 3,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 500 2,500 400 2,000 DOSE (Person-rem) DOSE (Person-rem) 300 1,500 MW-Yr 200 1,000 100 500 0 0 10-Year Dose Performance Trends Year Year 200 3,000 3-Year Average Collective Collective 175 2,500 Dose per Dose per Year Reactor Reactor MW-Yr 150 2010 58.570 48.000 2,164.8 2,000 DOSE (Person-rem) 2011 53.124 26.000 2,144.2 125 2012 40.678 48.000 2,029.7 2013 38.327 42.000 2,187.9 100 1,500 MW-Yr 2014 38.070 26.000 2,136.0 75 2015 38.560 48.839 2,098.6 1,000 2016 37.592 38.549 2,232.7 50 2017 34.502 16.118 2,249.6 500 2018 32.773 43.651 2,143.8 25 2019 31.318 34.185 2,236.7 0 0 Year D-10

CLINTON CLINTON Dose Performance Trends Historical Dose Performance Trends BWR 1,000 3-Year Average Collective Dose per Reactor 1,200 Collective Dose per Reactor BWR Average Collective Dose per Reactor 900 MW-Yr 1,000 800 700 800 DOSE (Person-rem) DOSE (Person-rem) 600 500 600 MW-Yr 400 400 300 200 200 100 0 0 10-Year Dose Performance Trends Year Year 400 1,200 3-Year Average Collective Collective 350 1,000 Dose per Dose per Year Reactor Reactor MW-Yr 300 2010 157.688 220.000 983.1 800 2011 165.470 228.000 989.9 250 DOSE (Person-rem) 2012 154.217 14.000 1,067.1 MW-Yr 2013 123.826 129.000 950.2 200 600 2014 53.632 18.000 1,038.6 150 2015 81.427 97.634 922.9 400 2016 49.573 33.218 1,017.8 100 2017 95.144 154.579 954.1 200 2018 88.537 77.813 958.7 50 2019 130.408 158.832 957.6 0 0 Year D-11

COLUMBIA GENERATING COLUMBIA GENERATING Historical Dose Performance Trends Dose Performance Trends BWR 1,200 3-Year Average Collective Dose per Reactor 1,200 Collective Dose per Reactor BWR Average Collective Dose per Reactor MW-Yr 1,000 1,000 800 800 DOSE (Person-rem) DOSE (Person-rem) 600 600 MW-Yr 400 400 200 200 0 0 10-Year Year Year Dose Performance Trends 800 1,200 3-Year Average Collective Collective 1,000 Dose per Dose per Year Reactor Reactor MW-Yr 600 2010 138.292 55.000 1,054.9 800 DOSE (Person-rem) 2011 231.844 336.000 548.7 2012 145.277 45.000 1,062.6 MW-Yr 400 600 2013 201.662 224.000 965.9 2014 101.033 34.000 1,084.2 2015 182.257 289.135 931.6 400 2016 116.577 26.825 1,098.8 200 2017 165.405 180.255 927.9 200 2018 83.386 43.078 1,108.3 2019 138.009 190.694 1,012.2 0 0 Year D-12

COMANCHE PEAK 1, 2 COMANCHE PEAK 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 400 3-Year Average Collective Dose per Reactor 2,500 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 350 2,000 300 250 DOSE (Person-rem) DOSE (Person-rem) 1,500 200 MW-Yr 1,000 150 100 500 50 0 0 10-Year Year Year Dose Performance Trends 150 2,500 3-Year Average Collective Collective 125 Dose per Dose per 2,000 Year Reactor Reactor MW-Yr 2010 48.505 36.000 2,316.8 100 DOSE (Person-rem) 2011 46.157 78.000 2,216.8 1,500 2012 48.711 34.000 2,279.9 2013 44.449 22.000 2,353.5 75 MW-Yr 2014 41.871 70.000 2,141.7 1,000 2015 37.895 21.445 2,294.6 50 2016 36.464 18.324 2,340.7 2017 33.422 60.498 1,947.3 500 25 2018 33.220 20.839 2,346.3 2019 36.787 29.026 2,219.0 0 0 Year D-13

COOK 1, 2 COOK 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 2,500 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 MW-Yr 800 2,000 700 DOSE (Person-rem) DOSE (Person-rem) 600 1,500 500 MW-Yr 400 1,000 300 200 500 100 0 0 10-Year Year Year Dose Performance Trends 300 2,500 3-Year Average Collective Collective Dose per Dose per 250 2,000 Year Reactor Reactor MW-Yr 2010 33.281 42.000 1,786.1 200 DOSE (Person-rem) 2011 30.075 28.000 1,981.5 1,500 2012 31.593 24.000 2,017.5 2013 35.009 52.000 1,858.5 150 MW-Yr 2014 34.447 27.000 2,012.7 1,000 2015 31.233 14.914 1,885.7 100 2016 29.557 46.858 1,753.5 2017 30.257 29.000 2,008.2 500 50 2018 32.038 20.256 2,010.4 2019 30.233 41.444 1,844.7 0 0 Year D-14

COOPER STATION COOPER STATION Historical Dose Performance Trends Dose Performance Trends BWR 2,000 3-Year Average Collective Dose per Reactor 1,000 Collective Dose per Reactor BWR Average Collective Dose per Reactor 1,800 MW-Yr 900 1,600 800 1,400 700 DOSE (Person-rem) DOSE (Person-rem) 1,200 600 1,000 500 MW-Yr 800 400 600 300 400 200 200 100 0 0 10-Year Year Dose Performance Trends Year 600 1,000 3-Year Average 900 Collective Collective 500 Dose per Dose per 800 Year Reactor Reactor MW-Yr 2010 225.078 61.000 775.4 700 400 DOSE (Person-rem) 2011 221.527 349.000 658.5 600 2012 229.950 279.000 662.9 2013 221.473 36.000 776.5 300 500 MW-Yr 2014 172.614 203.000 675.3 400 2015 88.725 27.634 776.1 200 300 2016 141.941 195.518 676.1 2017 84.448 30.193 789.1 200 100 2018 119.565 132.984 642.9 100 2019 59.213 14.463 793.6 0 0 Year D-15

DAVIS-BESSE 1 DAVIS-BESSE 1 Historical Dose Performance Trends Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 1,200 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 MW-Yr 1,000 800 700 800 DOSE (Person-rem) DOSE (Person-rem) 600 500 600 MW-Yr 400 400 300 200 200 100 0 0 10-Year Year Dose Performance Trends Year 1,000 1,200 3-Year Average 900 Collective Collective 1,000 Dose per Dose per 800 Year Reactor Reactor MW-Yr 2010 191.439 464.000 598.0 700 800 DOSE (Person-rem) 2011 180.359 73.000 723.7 600 2012 193.509 43.000 808.5 2013 39.663 3.000 876.6 500 600 MW-Yr 2014 82.032 200.000 681.8 400 2015 68.006 0.995 901.1 400 300 2016 106.644 118.472 730.0 2017 40.363 1.621 899.1 200 200 2018 57.032 51.003 842.5 100 2019 21.343 11.405 894.9 0 0 Year D-16

DIABLO CANYON 1, 2 DIABLO CANYON 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 700 3-Year Average Collective Dose per Reactor 2,500 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 600 2,000 500 DOSE (Person-rem) DOSE (Person-rem) 1,500 400 MW-Yr 300 1,000 200 500 100 0 0 10-Year Dose Performance Trends Year Year 300 2,500 3-Year Average Collective Collective Dose per Dose per 250 2,000 Year Reactor Reactor MW-Yr 2010 116.382 62.000 2,115.2 200 DOSE (Person-rem) 2011 82.486 16.000 2,131.1 1,500 2012 33.436 22.000 2,023.0 2013 17.321 14.000 2,064.1 150 MW-Yr 2014 23.316 34.000 1,947.1 1,000 2015 25.602 28.622 2,116.8 100 2016 27.096 18.867 2,162.2 2017 23.815 23.955 2,051.4 500 2018 19.610 16.007 2,088.4 50 2019 21.843 25.568 1,851.7 0 0 Year D-17

DRESDEN 2, 3 DRESDEN 2, 3 Dose Performance Trends Historical Dose Performance Trends BWR 1,800 3-Year Average Collective Dose per Reactor 1,800 Collective Dose per Reactor BWR Average Collective Dose per Reactor 1,600 MW-Yr 1,600 1,400 1,400 1,200 1,200 DOSE (Person-rem) DOSE (Person-rem) 1,000 1,000 MW-Yr 800 800 600 600 400 400 200 200 0 0 10-Year Year Dose Performance Trends Year 200 1,800 3-Year Average 1,600 Collective Collective 175 Dose per Dose per Year Reactor Reactor MW-Yr 1,400 150 2010 107.286 107.000 1,665.9 1,200 DOSE (Person-rem) 2011 113.657 118.000 1,679.7 125 2012 98.311 70.000 1,685.5 1,000 2013 85.497 68.000 1,759.9 100 MW-Yr 800 2014 65.582 58.000 1,727.8 75 2015 65.457 69.432 1,734.4 600 2016 66.271 70.914 1,763.2 50 400 2017 68.326 64.633 1,763.3 2018 64.987 59.416 1,776.9 25 200 2019 75.161 101.433 1,721.7 0 0 Year D-18

DUANE ARNOLD DUANE ARNOLD Dose Performance Trends Historical Dose Performance Trends BWR 2,000 3-Year Average Collective Dose per Reactor 700 Collective Dose per Reactor BWR Average Collective Dose per Reactor 1,800 MW-Yr 600 1,600 1,400 500 DOSE (Person-rem) DOSE (Person-rem) 1,200 400 1,000 MW-Yr 300 800 600 200 400 100 200 0 0 10-Year Year Dose Performance Trends Year 500 700 3-Year Average Collective Collective 600 Dose per Dose per 400 Year Reactor Reactor MW-Yr 500 2010 121.669 201.000 508.1 DOSE (Person-rem) 2011 123.460 30.000 595.3 300 400 2012 121.593 135.000 494.9 2013 60.197 16.000 607.4 MW-Yr 300 2014 90.972 122.000 474.0 200 2015 52.947 20.441 598.6 2016 84.347 110.613 536.8 200 2017 49.463 17.336 595.2 100 2018 68.644 77.984 558.8 100 2019 36.963 15.569 597.7 0 0 Year D-19

FARLEY 1, 2 FARLEY 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 2,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 MW-Yr 1,800 800 1,600 700 1,400 DOSE (Person-rem) DOSE (Person-rem) 600 1,200 500 1,000 MW-Yr 400 800 300 600 200 400 100 200 0 0 10-Year Year Year Dose Performance Trends 200 2,000 3-Year Average 1,800 Collective Collective 175 Dose per Dose per 1,600 Year Reactor Reactor MW-Yr 150 2010 33.994 60.000 1,503.4 1,400 2011 33.446 19.000 1,647.4 DOSE (Person-rem) 125 1,200 2012 31.440 15.000 1,680.7 MW-Yr 2013 20.090 26.000 1,609.4 100 1,000 2014 20.122 19.000 1,655.9 800 2015 24.476 27.971 1,631.0 75 2016 25.581 29.920 1,563.7 600 2017 24.522 15.676 1,690.0 50 400 2018 21.258 18.178 1,605.6 25 2019 21.837 31.660 1,613.8 200 0 0 Year D-20

FERMI 2 FERMI 2 Dose Performance Trends Historical Dose Performance Trends BWR 800 3-Year Average Collective Dose per Reactor 1,500 Collective Dose per Reactor BWR Average Collective Dose per Reactor MW-Yr 1,350 700 1,200 600 1,050 500 DOSE (Person-rem) DOSE (Person-rem) 900 400 750 MW-Yr 600 300 450 200 300 100 150 0 0 10-Year Year Year Dose Performance Trends 500 1,500 3-Year Average 1,350 Collective Collective Dose per Dose per 400 1,200 Year Reactor Reactor MW-Yr 2010 110.179 146.000 885.0 1,050 DOSE (Person-rem) 2011 106.472 24.000 1,017.9 300 900 2012 105.181 145.000 589.3 2013 65.077 26.000 754.5 750 MW-Yr 2014 123.617 200.000 891.5 200 600 2015 153.577 234.853 838.6 450 2016 163.104 54.761 1,045.0 2017 184.899 265.082 993.0 100 300 2018 216.286 329.015 849.2 150 2019 219.793 65.282 1,128.6 0 0 Year D-21

FITZPATRICK FITZPATRICK Dose Performance Trends Historical Dose Performance Trends BWR 2,500 3-Year Average Collective Dose per Reactor 1,000 Collective Dose per Reactor BWR Average Collective Dose per Reactor MW-Yr 900 2,000 800 700 DOSE (Person-rem) DOSE (Person-rem) 1,500 600 500 MW-Yr 1,000 400 300 500 200 100 0 0 10-Year Year Dose Performance Trends Year 350 1,000 3-Year Average 900 Collective Collective 300 Dose per Dose per 800 Year Reactor Reactor MW-Yr 2010 146.602 220.000 726.2 250 700 DOSE (Person-rem) 2011 96.741 35.000 826.9 600 2012 141.663 170.000 691.1 200 2013 81.498 39.000 780.8 500 MW-Yr 2014 115.056 136.000 665.4 150 400 2015 65.356 20.785 842.7 2016 61.660 28.304 668.7 100 300 2017 70.428 162.196 705.8 200 2018 140.683 231.548 745.2 50 2019 139.301 24.160 839.5 100 0 0 Year D-22

GINNA GINNA Historical Dose Performance Trends Dose Performance Trends PWR 2,000 3-Year Average Collective Dose per Reactor 600 Collective Dose per Reactor PWR Average Collective Dose per Reactor 1,800 MW-Yr 500 1,600 1,400 400 DOSE (Person-rem) DOSE (Person-rem) 1,200 1,000 300 MW-Yr 800 200 600 400 100 200 0 0 10-Year Year Year Dose Performance Trends 200 600 3-Year Average Collective Collective 175 500 Dose per Dose per Year Reactor Reactor MW-Yr 150 2010 48.992 3.000 564.9 400 DOSE (Person-rem) 2011 48.563 101.000 492.1 125 2012 52.838 55.000 523.9 MW-Yr 2013 52.927 3.000 570.0 100 300 2014 38.817 58.000 532.2 75 2015 28.659 24.163 544.5 200 2016 28.142 1.882 575.6 50 2017 24.073 46.173 536.3 100 2018 25.329 27.931 536.4 25 2019 25.376 2.023 570.1 0 0 Year D-23

GRAND GULF GRAND GULF Dose Performance Trends Historical Dose Performance Trends BWR 1,000 3-Year Average Collective Dose per Reactor 1,600 Collective Dose per Reactor BWR Average Collective Dose per Reactor 900 MW-Yr 1,400 800 1,200 700 1,000 DOSE (Person-rem) DOSE (Person-rem) 600 500 800 MW-Yr 400 600 300 400 200 200 100 0 0 Year 10-Year Year Dose Performance Trends 600 1,600 3-Year Average Collective Collective 1,400 Dose per Dose per 500 Year Reactor Reactor MW-Yr 1,200 2010 128.997 188.000 1,102.0 400 DOSE (Person-rem) 2011 80.058 21.000 1,180.0 1,000 2012 161.944 276.000 835.2 2013 110.970 35.000 1,231.1 300 800 MW-Yr 2014 164.524 182.000 1,173.5 600 2015 80.812 25.241 1,337.8 200 2016 133.914 194.755 682.8 400 2017 86.749 40.251 849.1 100 2018 133.971 166.908 794.3 200 2019 80.766 35.139 1,259.4 0 0 Year D-24

HARRIS 1 HARRIS 1 Historical Dose Performance Trends Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 1,200 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 1,100 MW-Yr 1,000 800 900 700 800 DOSE (Person-rem) DOSE (Person-rem) 600 700 500 600 MW-Yr 400 500 400 300 300 200 200 100 100 0 0 10-Year Year Year Dose Performance Trends 200 1,200 3-Year Average 1,100 Collective Collective 175 1,000 Dose per Dose per Year Reactor Reactor MW-Yr 150 900 2010 44.793 83.000 808.3 800 DOSE (Person-rem) 2011 42.901 5.000 926.0 125 700 2012 55.716 80.000 810.8 2013 46.481 55.000 786.3 100 600 MW-Yr 2014 45.336 1.289 918.8 500 75 2015 38.047 57.978 830.2 400 2016 34.381 43.876 857.7 50 300 2017 34.024 0.217 937.1 200 2018 25.276 31.736 866.2 25 2019 23.059 37.223 868.8 100 0 0 Year D-25

HATCH 1, 2 HATCH 1, 2 Historical Dose Performance Trends Dose Performance Trends BWR 2,000 3-Year Average Collective Dose per Reactor 1,800 Collective Dose per Reactor BWR Average Collective Dose per Reactor 1,800 MW-Yr 1,600 1,600 1,400 1,400 1,200 DOSE (Person-rem) DOSE (Person-rem) 1,200 1,000 1,000 MW-Yr 800 800 600 600 400 400 200 200 0 0 10-Year Year Dose Performance Trends Year 300 1,800 3-Year Average 1,600 Collective Collective 250 Dose per Dose per 1,400 Year Reactor Reactor MW-Yr 2010 103.535 123.000 1,586.9 200 1,200 DOSE (Person-rem) 2011 101.464 88.000 1,550.4 2012 102.327 96.000 1,637.5 1,000 2013 84.860 70.000 1,578.1 150 MW-Yr 800 2014 86.935 94.000 1,656.4 2015 82.877 83.500 1,654.9 100 600 2016 96.522 111.433 1,672.1 400 2017 81.854 50.711 1,658.8 50 2018 77.276 69.684 1,644.2 200 2019 55.816 47.052 1,588.7 0 0 Year D-26

HOPE CREEK 1 HOPE CREEK 1 Dose Performance Trends Historical Dose Performance Trends BWR 1,000 3-Year Average Collective Dose per Reactor 1,400 Collective Dose per Reactor BWR Average Collective Dose per Reactor 900 MW-Yr 1,200 800 700 1,000 DOSE (Person-rem) DOSE (Person-rem) 600 800 500 MW-Yr 600 400 300 400 200 200 100 0 0 10-Year Year Year Dose Performance Trends 500 1,400 3-Year Average Collective Collective 1,200 Dose per Dose per 400 Year Reactor Reactor MW-Yr 2010 121.591 160.910 1,082.0 1,000 DOSE (Person-rem) 2011 118.316 24.677 1,199.3 300 2012 113.151 153.866 1,091.3 800 2013 109.704 150.568 1,040.3 MW-Yr 2014 113.659 36.543 1,187.9 600 200 2015 118.991 169.862 1,078.9 2016 115.429 139.883 1,100.4 400 2017 113.888 31.919 1,216.7 100 2018 107.282 150.044 1,094.0 200 2019 117.061 169.220 1,000.8 0 0 Year D-27

INDIAN POINT 2,3 INDIAN POINT 2, 3 Dose Performance Trends Historical Dose Performance Trends 5,262 person-rem PWR 2,000 3-Year Average Collective Dose per Reactor 3,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor 1,800 MW-Yr 2,500 1,600 1,400 2,000 DOSE (Person-rem) DOSE (Person-rem) 1,200 1,000 1,500 MW-Yr 800 1,000 600 400 500 200 0 0 10-Year Year Year Dose Performance Trends 200 3,000 3-Year Average 175 Collective Collective 2,500 Dose per Dose per Year Reactor Reactor MW-Yr 150 2010 70.361 100.000 1,859.2 2,000 DOSE (Person-rem) 2011 57.326 32.000 1,938.8 125 2012 62.379 55.000 1,921.0 2013 41.230 37.000 1,946.6 100 1,500 MW-Yr 2014 54.387 71.000 1,973.1 75 2015 46.165 30.238 1,870.1 1,000 2016 45.931 36.458 1,723.7 50 2017 39.354 51.368 1,740.7 500 2018 43.977 44.106 1,863.6 25 2019 40.393 25.707 1,905.9 0 0 Year D-28

LASALLE 1, 2 LASALLE 1, 2 Dose Performance Trends Historical Dose Performance Trends BWR 1,600 3-Year Average Collective Dose per Reactor 2,500 Collective Dose per Reactor BWR Average Collective Dose per Reactor MW-Yr 1,400 2,000 1,200 1,000 DOSE (Person-rem) DOSE (Person-rem) 1,500 800 MW-Yr 1,000 600 400 500 200 0 0 10-Year Year Dose Performance Trends Year 500 2,500 3-Year Average Collective Collective Dose per Dose per 400 2,000 Year Reactor Reactor MW-Yr 2010 149.782 192.000 2,184.1 DOSE (Person-rem) 2011 170.270 170.000 2,198.2 300 1,500 2012 158.279 112.000 2,230.8 2013 158.144 192.000 2,141.6 MW-Yr 2014 162.476 184.000 2,141.0 200 1,000 2015 208.635 250.833 2,132.9 2016 201.196 169.493 2,185.5 2017 235.173 285.195 2,158.5 100 500 2018 209.774 174.634 2,214.7 2019 204.798 154.565 2,218.6 0 0 Year D-29

LIMERICK 1, 2 LIMERICK 1, 2 Dose Performance Trends Historical Dose Performance Trends BWR 1,000 3-Year Average Collective Dose per Reactor 3,000 Collective Dose per Reactor BWR Average Collective Dose per Reactor 900 MW-Yr 2,500 800 700 2,000 DOSE (Person-rem) DOSE (Person-rem) 600 500 1,500 MW-Yr 400 1,000 300 200 500 100 0 0 10-Year Year Dose Performance Trends Year 200 3,000 3-Year Average Collective Collective 175 2,500 Dose per Dose per Year Reactor Reactor MW-Yr 150 2010 96.557 84.000 2,165.2 2,000 DOSE (Person-rem) 2011 97.826 92.000 2,112.7 125 2012 85.337 80.000 2,071.4 MW-Yr 100 1,500 2013 79.626 67.000 2,235.7 2014 71.957 69.000 2,182.1 75 2015 66.119 62.394 2,165.6 1,000 2016 64.997 63.400 2,219.1 50 2017 72.554 91.868 2,123.1 500 2018 71.931 60.527 2,214.9 25 2019 77.043 78.736 2,213.1 0 0 Year D-30

MCGUIRE 1, 2 MCGUIRE 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 3,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 MW-Yr 2,500 800 700 2,000 DOSE (Person-rem) DOSE (Person-rem) 600 500 1,500 MW-Yr 400 1,000 300 200 500 100 0 0 10-Year Dose Performance Trends Year Year 300 3,000 3-Year Average Collective Collective 250 2,500 Dose per Dose per Year Reactor Reactor MW-Yr 2010 54.483 40.000 2,151.9 200 2,000 DOSE (Person-rem) 2011 46.789 60.000 2,038.3 2012 43.941 32.000 2,045.6 2013 48.625 54.000 2,157.3 150 1,500 MW-Yr 2014 51.728 69.000 2,008.0 2015 49.513 24.700 2,230.1 100 1,000 2016 42.552 33.827 2,269.9 2017 44.107 73.795 2,145.6 50 500 2018 42.541 20.003 2,267.4 2019 40.304 27.115 2,236.1 0 0 Year D-31

MILLSTONE 2, 3 MILLSTONE 2, 3 Dose Performance Trends Historical Dose Performance Trends PWR 3,000 3-Year Average Collective Dose per Reactor 2,200 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 2,000 2,500 1,800 1,600 2,000 1,400 DOSE (Person-rem) DOSE (Person-rem) 1,200 1,500 MW-Yr 1,000 800 1,000 600 500 400 200 0 0 10-Year Year Year Dose Performance Trends 400 2,200 3-Year Average 2,000 Collective Collective 350 Dose per Dose per 1,800 Year Reactor Reactor MW-Yr 300 1,600 2010 85.599 41.000 1,916.8 1,400 DOSE (Person-rem) 2011 68.368 84.000 1,822.7 250 2012 54.046 36.000 1,948.9 1,200 2013 51.153 32.000 1,954.5 200 MW-Yr 1,000 2014 49.667 80.000 1,812.7 150 800 2015 48.112 31.970 1,992.4 2016 48.095 32.063 1,896.1 600 100 2017 40.111 56.299 1,888.0 400 2018 40.472 33.055 1,931.7 50 200 2019 37.730 23.837 1,914.9 0 0 Year D-32

MONTICELLO MONTICELLO Dose Performance Trends Historical Dose Performance Trends BWR 3,000 3-Year Average Collective Dose per Reactor 800 Collective Dose per Reactor BWR Average Collective Dose per Reactor MW-Yr 700 2,500 600 2,000 500 DOSE (Person-rem) DOSE (Person-rem) 1,500 400 MW-Yr 300 1,000 200 500 100 0 0 10-Year Year Year Dose Performance Trends 400 800 3-Year Average Collective Collective 350 700 Dose per Dose per Year Reactor Reactor MW-Yr 300 600 2010 91.180 56.000 536.0 2011 155.579 237.000 383.4 250 500 DOSE (Person-rem) 2012 110.633 39.000 556.7 MW-Yr 2013 158.250 199.000 342.3 200 400 2014 91.020 35.000 493.6 150 300 2015 121.444 130.057 532.4 2016 64.637 28.547 639.0 100 200 2017 91.473 115.814 589.0 2018 57.866 29.238 641.3 50 100 2019 91.159 128.425 566.7 0 0 Year D-33

NINE MILE POINT 1, 2 NINE MILE POINT 1, 2 Historical Dose Performance Trends Dose Performance Trends BWR 2,000 3-Year Average Collective Dose per Reactor 2,000 Collective Dose per Reactor BWR Average Collective Dose per Reactor 1,800 MW-Yr 1,800 1,600 1,600 1,400 1,400 DOSE (Person-rem) DOSE (Person-rem) 1,200 1,200 1,000 1,000 MW-Yr 800 800 600 600 400 400 200 200 0 0 Year 10-Year Year Dose Performance Trends 400 2,000 3-Year Average 1,800 Collective Collective 350 Dose per Dose per 1,600 Year Reactor Reactor MW-Yr 300 2010 152.463 188.000 1,627.1 1,400 DOSE (Person-rem) 2011 142.895 122.000 1,616.8 250 1,200 2012 171.287 204.000 1,504.6 2013 144.892 108.000 1,804.9 200 1,000 MW-Yr 2014 148.111 132.000 1,737.8 800 150 2015 106.858 80.190 1,823.7 600 2016 113.481 128.397 1,765.5 100 2017 93.054 70.575 1,827.3 400 2018 130.573 192.746 1,758.9 50 200 2019 113.060 75.860 1,777.2 0 0 Year D-34

NORTH ANNA 1, 2 NORTH ANNA 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 1,500 3-Year Average Collective Dose per Reactor 2,400 Collective Dose per Reactor 1,400 PWR Average Collective Dose per Reactor 2,200 MW-Yr 1,300 2,000 1,200 1,100 1,800 1,000 1,600 DOSE (Person-rem)

DOSE (Person-rem) 900 1,400 800 1,200 MW-Yr 700 600 1,000 500 800 400 600 300 400 200 100 200 0 0 Year 10-Year Year Dose Performance Trends 300 2,400 3-Year Average 2,200 Collective Collective 250 2,000 Dose per Dose per Year Reactor Reactor MW-Yr 1,800 2010 52.569 91.000 1,529.6 200 1,600 DOSE (Person-rem) 2011 57.530 46.000 1,429.1 1,400 2012 63.262 54.000 1,745.6 2013 53.181 61.000 1,712.9 150 1,200 MW-Yr 2014 50.039 36.000 1,813.8 1,000 2015 39.593 21.919 1,857.4 100 800 2016 39.182 59.670 1,726.2 600 2017 34.677 22.442 1,840.9 50 400 2018 36.845 28.423 1,826.2 200 2019 32.836 47.644 1,749.4 0 0 Year D-35

OCONEE 1, 2, 3 OCONEE 1, 2, 3 Historical Dose Performance Trends Dose Performance Trends PWR 1,500 3-Year Average Collective Dose per Reactor 2,800 Collective Dose per Reactor 1,400 PWR Average Collective Dose per Reactor 2,600 MW-Yr 1,300 2,400 1,200 2,200 1,100 2,000 1,000 1,800 DOSE (Person-rem) DOSE (Person-rem) 900 1,600 800 1,400 MW-Yr 700 1,200 600 1,000 500 800 400 300 600 200 400 100 200 0 0 10-Year Year Year Dose Performance Trends 200 2,800 3-Year 2,600 Average 175 2,400 Collective Collective Dose per Dose per 2,200 Year Reactor Reactor MW-Yr 150 2,000 2010 74.979 64.000 2,391.1 1,800 DOSE (Person-rem) 2011 61.667 61.000 2,321.6 125 1,600 2012 56.310 44.000 2,351.0 2013 46.680 35.000 2,400.1 100 1,400 MW-Yr 2014 38.541 36.000 2,419.3 1,200 75 1,000 2015 31.608 23.017 2,504.5 2016 25.718 17.799 2,417.5 800 50 2017 17.750 12.434 2,488.4 600 2018 16.433 19.067 2,430.8 25 400 2019 13.960 10.379 2,498.3 200 0 0 Year D-36

PALISADES PALISADES Historical Dose Performance Trends Dose Performance Trends PWR 1,500 3-Year Average Collective Dose per Reactor 900 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 800 1,250 700 1,000 600 DOSE (Person-rem)

DOSE (Person-rem) 500 MW-Yr 750 400 500 300 200 250 100 0 0 10-Year Year Year Dose Performance Trends 600 900 3-Year Average 800 Collective Collective Dose per Dose per 500 Year Reactor Reactor MW-Yr 700 2010 170.223 220.000 712.5 400 600 DOSE (Person-rem) 2011 169.607 22.000 758.1 2012 162.219 245.000 589.5 500 2013 94.204 16.000 689.7 300 MW-Yr 400 2014 249.007 486.000 665.6 2015 244.193 230.687 721.3 200 300 2016 240.805 5.667 803.8 2017 130.165 154.142 696.1 200 100 2018 122.031 206.284 622.8 100 2019 123.492 10.051 783.6 0 0 Year D-37

PALO VERDE 1, 2, 3 PALO VERDE 1, 2, 3 Historical Dose Performance Trends Dose Performance Trends PWR 800 3-Year Average Collective Dose per Reactor 5,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 4,500 700 4,000 600 3,500 500 DOSE (Person-rem) DOSE (Person-rem) 3,000 400 2,500 MW-Yr 2,000 300 1,500 200 1,000 100 500 0 0 10-Year Year Year Dose Performance Trends 300 5,000 3-Year Average 4,500 Collective Collective 250 Dose per Dose per 4,000 Year Reactor Reactor MW-Yr 2010 41.157 38.000 3,561.6 3,500 200 DOSE (Person-rem) 2011 30.210 20.000 3,570.5 3,000 2012 25.953 20.000 3,635.5 2013 23.583 31.000 3,588.0 150 2,500 MW-Yr 2014 23.701 20.000 3,689.9 2,000 2015 23.523 19.332 3,711.7 100 1,500 2016 20.310 21.599 3,680.7 2017 19.631 17.963 3,691.8 1,000 50 2018 17.754 13.701 3,551.0 500 2019 15.139 13.754 3,643.8 0 0 Year D-38

PEACH BOTTOM 2, 3 PEACH BOTTOM 2, 3 Dose Performance Trends Historical Dose Performance Trends BWR 2,600 3-Year Average Collective Dose per Reactor 2,600 Collective Dose per Reactor 2,400 BWR Average Collective Dose per Reactor 2,400 MW-Yr 2,200 2,200 2,000 2,000 1,800 1,800 1,600 1,600 DOSE (Person-rem)

DOSE (Person-rem) 1,400 1,400 MW-Yr 1,200 1,200 1,000 1,000 800 800 600 600 400 400 200 200 0 0 10-Year Year Year Dose Performance Trends 400 2,600 3-Year Average 2,400 350 Collective Collective 2,200 Dose per Dose per Year Reactor Reactor MW-Yr 300 2,000 2010 123.782 110.000 2,145.3 1,800 DOSE (Person-rem) 2011 153.284 195.000 2,152.0 250 1,600 2012 152.436 152.000 2,142.5 1,400 2013 196.530 242.000 2,143.5 200 1,200 MW-Yr 2014 203.385 216.000 2,142.3 1,000 150 2015 218.412 197.799 2,267.6 800 2016 171.460 101.111 2,498.1 100 600 2017 132.605 98.907 2,481.1 400 2018 96.229 88.669 2,474.9 50 200 2019 90.372 83.542 2,545.2 0 0 Year D-39

PERRY PERRY 1 Dose Performance Trends Historical Dose Performance Trends BWR 1,200 3-Year Average Collective Dose per Reactor 1,400 Collective Dose per Reactor BWR Average Collective Dose per Reactor MW-Yr 1,200 1,000 1,000 800 DOSE (Person-rem) DOSE (Person-rem) 800 600 MW-Yr 600 400 400 200 200 0 0 Year Year Dose Performance Trends 10-Year 900 1,400 3-Year Average 800 Collective Collective 1,200 Dose per Dose per Year Reactor Reactor MW-Yr 700 2010 233.082 32.000 1,213.3 1,000 600 DOSE (Person-rem) 2011 318.350 308.000 978.2 2012 127.822 43.000 1,194.3 500 800 2013 241.675 374.000 964.5 MW-Yr 400 600 2014 167.246 84.617 1,193.5 2015 281.714 386.778 1,082.5 300 2016 162.261 36.389 1,189.5 400 2017 250.295 327.717 1,120.1 200 2018 131.318 29.848 1,223.6 200 100 2019 219.544 301.067 1,047.2 0 0 Year D-40

POINT BEACH 1, 2 POINT BEACH 1, 2 Dose Performance Trends Historical Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 1,400 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 1,200 800 1,000 DOSE (Person-rem) DOSE (Person-rem) 600 800 MW-Yr 600 400 400 200 200 0 0 10-Year Year Year Dose Performance Trends 200 1,400 3-Year Average Collective Collective 175 1,200 Dose per Dose per Year Reactor Reactor MW-Yr 150 2010 55.494 48.000 952.8 1,000 DOSE (Person-rem) 2011 58.108 80.000 796.2 125 2012 54.189 35.000 1,114.3 800 2013 48.764 32.000 1,135.3 100 MW-Yr 2014 43.404 64.000 1,079.4 600 75 2015 39.690 23.737 1,142.9 2016 38.715 28.647 1,159.0 400 50 2017 32.041 43.740 1,102.0 2018 31.334 21.614 1,156.7 25 200 2019 34.199 37.243 1,145.3 0 0 Year D-41

PRAIRIE ISLAND 1, 2 PRAIRIE ISLAND 1, 2 Dose Performance Trends Historical Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 1,200 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 1,000 800 800 DOSE (Person-rem) DOSE (Person-rem) 600 600 MW-Yr 400 400 200 200 0 0 Year Year 10-Year Dose Performance Trends 200 1,200 3-Year Average Collective Collective 175 1,000 Dose per Dose per Year Reactor Reactor MW-Yr 150 2010 39.221 28.000 1,002.6 800 DOSE (Person-rem) 2011 27.759 29.000 982.4 125 2012 38.688 60.000 803.8 2013 51.197 65.000 881.8 100 600 MW-Yr 2014 53.336 36.000 957.0 75 2015 43.882 31.221 842.2 400 2016 30.230 24.039 944.5 50 2017 24.140 17.161 998.3 200 2018 20.022 18.866 1,025.5 25 2019 16.108 12.297 1,043.4 0 0 Year D-42

QUAD CITIES 1, 2 QUAD CITIES 1, 2 Dose Performance Trends Historical Dose Performance Trends BWR 3,000 3-Year Average Collective Dose per Reactor 2,000 Collective Dose per Reactor BWR Average Collective Dose per Reactor MW-Yr 1,800 2,500 1,600 1,400 2,000 DOSE (Person-rem)

DOSE (Person-rem) 1,200 1,500 1,000 MW-Yr 800 1,000 600 400 500 200 0 0 Year Year 10-Year Dose Performance Trends 400 2,000 3-Year Average 1,950 Collective Collective 350 Dose per Dose per 1,900 Year Reactor Reactor MW-Yr 300 2010 139.044 120.000 1,688.9 1,850 DOSE (Person-rem) 2011 141.413 144.000 1,735.3 250 1,800 2012 120.729 97.000 1,765.3 2013 112.498 96.000 1,776.0 200 1,750 MW-Yr 2014 90.423 78.000 1,756.7 1,700 150 2015 86.392 85.062 1,776.5 2016 78.150 71.304 1,787.1 1,650 100 2017 80.983 86.584 1,758.2 1,600 2018 79.658 81.086 1,766.7 50 1,550 2019 90.049 102.479 1,763.7 0 1,500 Year D-43

RIVER BEND 1 RIVER BEND 1 Dose Performance Trends Historical Dose Performance Trends BWR 1,000 3-Year Average Collective Dose per Reactor 1,200 Collective Dose per Reactor BWR Average Collective Dose per Reactor 900 MW-Yr 1,000 800 700 800 DOSE (Person-rem) DOSE (Person-rem) 600 500 600 MW-Yr 400 400 300 200 200 100 0 0 Year 10-Year Year Dose Performance Trends 500 1,200 3-Year Average Collective Collective Dose per Dose per 1,000 400 Year Reactor Reactor MW-Yr 2010 190.501 40.000 955.1 800 DOSE (Person-rem) 2011 157.005 211.000 878.6 300 2012 95.249 34.000 890.2 2013 144.574 188.000 867.6 600 MW-Yr 2014 79.549 16.000 935.8 200 2015 110.99 128.492 791.6 400 2016 71.924 71.142 811.5 2017 157.546 273.004 804.5 100 200 2018 137.909 69.580 804.3 2019 199.501 255.918 750.5 0 0 Year D-44

ROBINSON 2 ROBINSON 2 Dose Performance Trends Historical Dose Performance Trends PWR 3,500 3-Year Average Collective Dose per Reactor 800 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 3,000 700 600 2,500 500 DOSE (Person-rem) DOSE (Person-rem) 2,000 400 MW-Yr 1,500 300 1,000 200 500 100 0 0 Year 10-Year Year Dose Performance Trends 200 800 3-Year Average Collective Collective 175 Dose per Dose per Year Reactor Reactor MW-Yr 150 600 2010 53.653 86.000 410.8 DOSE (Person-rem) 2011 32.063 4.000 726.5 125 2012 51.602 65.000 613.4 2013 49.828 81.000 650.3 100 400 MW-Yr 2014 58.173 29.000 703.1 75 2015 55.211 56.373 653.4 2016 29.581 3.704 734.3 50 200 2017 39.605 58.739 676.9 2018 41.480 61.998 602.5 25 2019 40.802 1.668 727.9 0 0 Year D-45

SALEM 1, 2 SALEM 1, 2 Dose Performance Trends Historical Dose Performance Trends PWR 1,000 3-Year Average Collective Dose per Reactor 2,500 Collective Dose per Reactor PWR Average Collective Dose per Reactor 900 MW-Yr 800 2,000 700 DOSE (Person-rem) DOSE (Person-rem) 600 1,500 500 MW-Yr 400 1,000 300 200 500 100 0 0 10-Year Year Year Dose Performance Trends 300 2,500 3-Year Average Collective Collective Dose per Dose per 250 2,000 Year Reactor Reactor MW-Yr 2010 84.636 38.914 2,147.3 200 DOSE (Person-rem) 2011 50.955 63.358 2,054.6 1,500 2012 41.925 23.502 2,123.8 2013 38.858 29.715 2,213.1 150 MW-Yr 2014 36.011 54.817 1,870.1 1,000 2015 33.812 16.905 2,131.3 100 2016 39.450 46.628 1,800.9 2017 43.710 67.599 2,060.5 500 50 2018 46.256 24.543 2,165.1 2019 47.399 50.055 2,053.6 0 0 Year D-46

SEABROOK SEABROOK Dose Performance Trends Historical Dose Performance Trends PWR 500 3-Year Average Collective Dose per Reactor 1,600 Collective Dose per Reactor PWR Average Collective Dose per Reactor 450 MW-Yr 1,400 400 1,200 350 1,000 DOSE (Person-rem) DOSE (Person-rem) 300 250 800 MW-Yr 200 600 150 400 100 200 50 0 0 Year 10-Year Year Dose Performance Trends 200 1,600 3-Year Average Collective Collective 175 1,400 Dose per Dose per Year Reactor Reactor MW-Yr 150 1,200 2010 55.620 4.000 1,245.4 DOSE (Person-rem) 2011 52.484 66.000 954.5 125 1,000 2012 41.239 54.000 932.2 MW-Yr 2013 40.557 2.000 1,247.3 100 800 2014 32.020 40.000 1,160.7 75 600 2015 46.159 96.053 1,082.6 2016 45.903 1.672 1,228.4 50 400 2017 42.305 29.191 1,140.4 2018 21.427 33.418 1,148.5 25 200 2019 21.231 1.084 1,245.0 0 0 Year D-47

SEQUOYAH 1, 2 SEQUOYAH 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 1,100 3-Year Average Collective Dose per Reactor 2,500 Collective Dose per Reactor PWR Average Collective Dose per Reactor 1,000 MW-Yr 900 2,000 800 700 DOSE (Person-rem) DOSE (Person-rem) 1,500 600 MW-Yr 500 1,000 400 300 500 200 100 0 0 10-Year Year Year Dose Performance Trends 200 2,500 3-Year Average Collective Collective 175 Dose per Dose per 2,000 Year Reactor Reactor MW-Yr 150 2010 51.255 28.000 2,054.9 DOSE (Person-rem) 2011 55.525 54.000 2,133.3 125 1,500 2012 76.202 146.000 1,888.2 2013 74.123 22.000 2,108.1 100 MW-Yr 2014 68.817 39.000 2,156.7 1,000 75 2015 43.148 68.413 1,884.9 2016 53.360 52.882 1,971.4 50 2017 48.298 23.600 1,140.4 500 2018 45.732 60.713 2,021.0 25 2019 40.785 38.043 2,062.2 0 0 Year D-48

SOUTH TEXAS 1, 2 SOUTH TEXAS 1, 2 Dose Performance Trends Historical Dose Performance Trends PWR 500 3-Year Average Collective Dose per Reactor 3,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor 450 MW-Yr 2,500 400 350 2,000 DOSE (Person-rem) DOSE (Person-rem) 300 250 1,500 MW-Yr 200 1,000 150 100 500 50 0 0 10-Year Year Year Dose Performance Trends 200 3,000 3-Year Average Collective Collective 175 Dose per Dose per 2,500 Year Reactor Reactor MW-Yr 150 2010 57.675 40.000 2,418.7 2,000 DOSE (Person-rem) 2011 49.687 70.000 2,333.3 125 2012 44.590 24.000 2,122.4 2013 41.352 30.000 2,062.4 100 1,500 MW-Yr 2014 23.903 18.000 2,363.4 75 2015 29.718 41.997 2,224.5 1,000 2016 25.234 16.419 2,481.9 50 2017 28.643 27.513 2,467.1 500 2018 26.319 35.025 2,367.7 25 2019 30.327 28.444 2,515.3 0 0 Year D-49

ST. LUCIE 1, 2 ST. LUCIE 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 2,000 3-Year Average Collective Dose per Reactor 2,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor 1,800 MW-Yr 1,600 1,500 1,400 DOSE (Person-rem) DOSE (Person-rem) 1,200 1,000 1,000 MW-Yr 800 600 500 400 200 0 0 10-Year Year Year Dose Performance Trends 500 2,000 3-Year Average Collective Collective Dose per Dose per 400 Year Reactor Reactor MW-Yr 1,500 2010 73.737 98.000 1,440.2 DOSE (Person-rem) 2011 104.242 148.000 1,200.9 300 2012 113.002 92.000 1,139.5 2013 92.597 38.000 1,783.4 1,000 MW-Yr 2014 63.574 60.000 1,805.7 200 2015 64.018 94.044 1,720.9 2016 64.301 38.314 1,779.5 500 2017 55.973 35.562 1,875.3 100 2018 43.445 56.460 1,777.1 2019 39.563 26.668 1,709.5 0 0 Year D-50

SUMMER 1 SUMMER 1 Historical Dose Performance Trends Dose Performance Trends PWR 800 3-Year Average Collective Dose per Reactor 1,200 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 700 1,000 600 800 500 DOSE (Person-rem) DOSE (Person-rem) 400 600 MW-Yr 300 400 200 200 100 0 0 10-Year Year Year Dose Performance Trends 200 1,200 3-Year Average 175 Collective Collective 1,000 Dose per Dose per Year Reactor Reactor MW-Yr 150 2010 35.760 2.000 968.8 800 DOSE (Person-rem) 2011 29.920 32.000 847.7 125 2012 38.657 82.000 829.0 MW-Yr 100 600 2013 39.651 5.000 955.5 2014 66.101 111.000 789.4 75 2015 60.333 64.958 812.3 400 2016 59.583 2.862 988.4 50 2017 39.376 50.308 789.2 200 2018 34.140 49.251 840.9 25 2019 34.705 4.557 941.6 0 0 Year D-51

SURRY 1, 2 SURRY 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 3,000 3-Year Average Collective Dose per Reactor 2,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 1,800 2,500 1,600 1,400 2,000 DOSE (Person-rem)

DOSE (Person-rem) 1,200 1,500 1,000 MW-Yr 800 1,000 600 400 500 200 0 0 Year Year 10-Year Dose Performance Trends 200 2,000 3-Year Average 1,800 Collective Collective 175 Dose per Dose per 1,600 Year Reactor Reactor MW-Yr 150 2010 75.839 56.000 1,503.7 1,400 DOSE (Person-rem) 2011 69.759 57.000 1,487.4 125 1,200 2012 65.600 84.000 1,549.9 2013 58.334 34.000 1,644.4 100 1,000 MW-Yr 2014 48.962 28.000 1,636.1 800 75 2015 51.333 91.490 1,345.9 2016 47.484 22.216 1,667.9 600 50 2017 47.571 29.006 1,647.0 400 2018 36.714 58.919 1,509.0 25 200 2019 37.992 26.051 1,617.9 0 0 Year D-52

SUSQUEHANNA 1, 2 SUSQUEHANNA 1, 2 Dose Performance Trends Historical Dose Performance Trends BWR 1,500 3-Year Average Collective Dose per Reactor 2,500 Collective Dose per Reactor 1,400 BWR Average Collective Dose per Reactor MW-Yr 1,300 1,200 2,000 1,100 1,000 DOSE (Person-rem) DOSE (Person-rem) 900 1,500 800 MW-Yr 700 600 1,000 500 400 300 500 200 100 0 0 10-Year Year Year Dose Performance Trends 500 2,500 3-Year Average Collective Collective Dose per Dose per 400 2,000 Year Reactor Reactor MW-Yr 2010 105.927 88.000 2,121.6 DOSE (Person-rem) 2011 101.954 84.000 1,992.0 300 1,500 2012 86.835 88.000 1,936.5 2013 96.397 117.000 2,166.2 MW-Yr 2014 103.980 107.000 2,153.1 200 1,000 2015 109.026 103.077 2,354.3 2016 109.660 118.668 2,217.2 2017 101.493 82.734 2,375.6 100 500 2018 91.689 73.664 2,343.4 2019 75.646 70.539 2,394.1 0 0 Year D-53

TURKEY POINT 3, 4 TURKEY POINT 3, 4 Historical Dose Performance Trends Dose Performance Trends PWR 2,000 3-Year Average Collective Dose per Reactor 1,800 Collective Dose per Reactor PWR Average Collective Dose per Reactor 1,800 MW-Yr 1,600 1,600 1,400 1,400 1,200 DOSE (Person-rem) DOSE (Person-rem) 1,200 1,000 1,000 MW-Yr 800 800 600 600 400 400 200 200 0 0 Year Year 10-Year Dose Performance Trends 500 1,800 3-Year Average 450 1,600 Collective Collective Dose per Dose per 400 Year Reactor Reactor MW-Yr 1,400 2010 58.395 44.000 1,290.9 350 1,200 DOSE (Person-rem) 2011 52.549 31.000 1,245.7 300 2012 65.038 120.000 878.0 1,000 2013 64.282 41.000 1,245.9 250 MW-Yr 800 2014 72.949 57.000 1,375.7 200 2015 45.944 39.562 1,489.7 600 150 2016 44.953 38.135 1,567.7 2017 43.932 54.100 1,451.9 400 100 2018 39.260 25.544 1,570.2 50 200 2019 40.650 42.305 1,614.4 0 0 Year D-54

VOGTLE 1, 2 VOGTLE 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 400 3-Year Average Collective Dose per Reactor 3,000 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 350 2,500 300 2,000 250 DOSE (Person-rem) DOSE (Person-rem) 200 1,500 MW-Yr 150 1,000 100 500 50 0 0 Year Year 10-Year Dose Performance Trends 200 3,000 3-Year Average Collective Collective 2,500 Dose per Dose per Year Reactor Reactor MW-Yr 150 2010 51.077 44.000 2,238.6 2,000 DOSE (Person-rem) 2011 47.966 60.000 2,138.0 2012 44.572 30.000 2,226.6 2013 42.758 39.000 2,178.4 100 1,500 MW-Yr 2014 49.060 78.000 2,065.8 2015 49.268 30.283 2,210.0 1,000 2016 45.964 29.236 2,267.1 50 2017 33.266 40.278 2,189.0 500 2018 30.981 23.428 2,278.4 2019 29.680 25.334 2,255.0 0 0 Year D-55

WATERFORD 3 WATERFORD 3 Dose Performance Trends Historical Dose Performance Trends PWR 600 3-Year Average Collective Dose per Reactor 1,400 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 1,200 500 1,000 400 DOSE (Person-rem) DOSE (Person-rem) 800 300 MW-Yr 600 200 400 100 200 0 0 10-Year Year Year Dose Performance Trends 500 1,400 3-Year Average 450 Collective Collective 1,200 Dose per Dose per 400 Year Reactor Reactor MW-Yr 350 1,000 2010 131.400 5.000 1,173.1 DOSE (Person-rem) 2011 120.018 100.000 1,020.8 300 800 2012 121.723 260.000 897.1 2013 121.128 3.000 1,071.6 250 MW-Yr 600 2014 110.931 69.000 1,046.4 200 2015 46.330 66.399 959.5 150 400 2016 46.418 3.392 1,152.5 2017 43.506 60.728 959.1 100 2018 21.750 1.130 1,175.6 200 50 2019 43.879 69.780 869.0 0 0 Year D-56

WATTS BAR 1, 2 WATTS BAR 1, 2 Historical Dose Performance Trends Dose Performance Trends PWR 600 3-Year Average Collective Dose per Reactor 2,200 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 2,000 500 1,800 1,600 400 1,400 DOSE (Person-rem) DOSE (Person-rem) 1,200 300 MW-Yr 1,000 800 200 600 100 400 200 0 0 10-Year Dose Performance Trends Year 400 2,200 3-Year Average 2,000 Collective Collective 350 Dose per Dose per 1,800 Year Reactor Reactor MW-Yr 300 1,600 2010 46.880 6.000 1,111.7 1,400 DOSE (Person-rem) 2011 40.353 51.000 939.6 250 2012 39.998 63.000 969.5 1,200 2013 38.805 3.000 1,137.9 200 MW-Yr 1,000 2014 31.221 28.000 1,003.4 150 800 2015 31.735 64.320 964.5 2016 32.359 4.489 1,284.1 600 100 2017 36.120 37.836 1,558.2 400 2018 23.416 18.460 2,110.1 50 2019 26.268 22.509 2,018.4 200 0 0 Year D-57

WOLF CREEK 1 WOLF CREEK 1 Historical Dose Performance Trends Dose Performance Trends PWR 500 3-Year Average Collective Dose per Reactor 1,400 Collective Dose per Reactor PWR Average Collective Dose per Reactor MW-Yr 1,200 400 1,000 DOSE (Person-rem) DOSE (Person-rem) 300 800 MW-Yr 600 200 400 100 200 0 0 10-Year Year Year Dose Performance Trends 300 1,400 3-Year Average Collective Collective 1,200 Dose per Dose per Year Reactor Reactor MW-Yr 2010 59.718 11.000 1,090.8 1,000 200 DOSE (Person-rem) 2011 72.704 134.000 839.1 800 2012 50.788 8.000 944.4 2013 84.368 111.000 819.2 MW-Yr 600 2014 48.882 28.000 978.2 2015 71.187 74.804 987.9 100 400 2016 64.312 90.631 942.0 2017 56.291 3.437 1,215.5 200 2018 55.650 72.882 1,047.5 2019 40.501 45.183 1,056.6 0 0 Year D-58

APPENDIX E PLANTS NO LONGER IN OPERATION 2019 Information in this appendix was obtained from References 19, 20, and 21.

PLANTS NO LONGER IN OPERATION 2019 Big Rock Point Big Rock Point (BRP) was a boiling-water reactor rated at 75 megawatt (MW) electric (MWe),

designed by General Electric Company, and owned by Consumers Energy Company (CE). BRP was permanently shut down on August 29, 1997, and fuel was transferred to the spent fuel pool by September 20, 1997. The site completed decommissioning to a green field status. Big Rock Point will retain its 10 CFR Part 50 license until the fuel is removed from the ISFSI.

All fuel was transferred to the independent spent fuel storage installation (ISFSI) by March 2003.

After fuel is removed from the site to a U.S. Department of Energy (DOE) facility, the ISFSI will be decommissioned and the 10 CFR Part 50 license terminated.

Big Rock Point 1,000 800 Power Generation Collective Dose 600 (person-rem) 400 200 0

Year Crystal River 3 Crystal River Nuclear Generating Plant Unit 3 (CR-3) was a 2,609 MW thermal (MWt),

pressurized-water reactor that was licensed to operate from December 1976 to February 20, 2013, and is located on approximately 4,700 acres in Crystal River, FL. During a refueling outage that started on September 26, 2009, CR-3 replaced the steam generators (SGs),

requiring a large hole to be made in the containment building structure. When attempting to restore the containment structure following the SG replacement, damage to the containment structure was observed. The licensee attempted to repair the damage, but later decided to decommission the reactor.

Crystal River 3 700 600 Power Generation 500 Collective Dose 400 (person-rem) 300 200 100 0

Year E-1

The facility is currently in SAFSTOR condition although they are still considering beginning active decommissioning. The licensee submitted the CR-3 post-shutdown decommissioning activities report, including the site-specific cost estimate, on December 2, 2013. The plant began construction of an ISFSI in 2016, and begin loading fuel in summer 2017. Fuel transfer to the ISFSI was completed in January 2018.

Dresden Unit 1 Dresden Unit 1 (Dresden 1) produced power commercially from August 1, 1960, to October 31, 1978, and is now designated a Nuclear Historic Landmark by the American Nuclear Society.

Dresden 1 was shut down on October 31, 1978, and is currently in SAFSTOR. The NRC approved the Decommissioning Plan in September 1993.

During the SAFSTOR period, through 2027, the Dresden 1 facility will be subjected to periodic inspection and monitoring. The licensee plans that decontamination and dismantlement of Dresden 1 will take place from 2029 through 2031. A 4-year site restoration delay will follow the major decontamination and dismantlement of Dresden 1 to allow for the decontamination and dismantlement of Units 2 and 3, with completion of these activities tentatively planned for 2035. Site restoration will be conducted in 2035 and 2036, concluding with a final site survey in late 2036. The licensee will monitor the Dresden ISFSI complex with site security and periodic inspections until final transfer of the spent fuel to DOE.

Fermi Unit 1 The Enrico Fermi Atomic Power Plant Unit 1 (Fermi 1) was a fast breeder reactor power plant cooled by sodium and operated at essentially atmospheric pressure. The reactor plant was designed for a maximum capacity of 430 MW; however, the maximum reactor power was 200 MW. The primary system was filled with sodium in December 1960 and criticality was achieved in August 1963. The reactor was tested at low power in the first couple of years of operation.

Power ascension testing above 1 MW began in December 1965, immediately following receipt of the high-power operating license. In October 1966, during power ascension, a zirconium plate at the bottom of the reactor vessel became loose and blocked sodium coolant flow to some fuel subassemblies. Two subassemblies started to melt. Radiation monitors alarmed and the operators manually shut down the reactor. No abnormal releases to the environment occurred. Three years and nine months later, the cause had been determined, cleanup was completed, and fuel was replaced; Fermi 1 was restarted. In 1972, the core was approaching the burnup limit. In November 1972, the Power Reactor Development Company made the decision to decommission Fermi 1.

The fuel and blanket subassemblies were shipped off site in 1973. The nonradioactive secondary sodium system was drained and the sodium was sent to Fike Chemical Company.

The radioactive primary sodium was stored in storage tanks and in 55-gallon drums until the sodium was shipped off site in 1984. Decommissioning of the Fermi 1 plant was originally completed in December 1975. The license for Fermi 1 expires in 2025. The licensee submitted a revised license termination plan (LTP) in March 2010, and the NRC staff completed an expanded acceptance review of the revised LTP for Fermi Unit 1. The NRC LTP review was deferred at the request of the licensee in 2012.The license expires in 2025 and the estimated date for closure is 2032.

E-2

Fort Calhoun Fort Calhoun Station (FCS) was a 1,500 Mwt, pressurized-water reactor that began operation in 1973 and is owned by the Omaha Public Power District (OPPD). The reactor was permanently shut down on October 24, 2016. By letter dated November 13, 2016, OPPD certified that all fuel had been removed from the reactor.

OPPD submitted the FCS Post-Shutdown Decommissioning Activities Report (PSDAR) to the NRC on March 30, 2017. In the PSDAR, OPPD stated its intention to move all of the spent nuclear fuel into dry cask storage by the end of 2022 and put the plant into SAFSTOR until it is ready to fully decommission the facility starting in 2060. License termination is scheduled to take place by 2065.

Major regulatory activity to adapt the operating plant license to the needs of the post-shutdown functions of the facility has been completed. The activity focused on adapting the application of the regulations to post-shutdown requirements related to security, emergency planning, finance and insurance. As the licensee moves to place all spent fuel remaining in the spent fuel pool into onsite dry storage, licensing activities will begin for adapting the regulations to the dry storage only condition. In June 2018 the licensee requested to release a non-impacted part of their site from their 10 CFR Part 50 license for unrestricted use. The request was approved in April 2019.

Fort Crystal Calhoun River 3 700 600 Power Generation 500 Collective Dose 400 (person-rem) 300 200 100 0

Year GE Vallecitos Boiling-Water Reactor (VBWR)

The VBWR was shut down in 1963 and NRC issued a possession only license in 1965. The license was renewed in 1973 and the license has remained effective under the provisions of 10 CFR 50.51(b). The facility has been maintained in SAFSTOR condition with a limit of 60 years under 10 CFR 50.82(a)(3). The licensee has requested to maintain the facility in SAFSTOR past 60 years until other ongoing nuclear activities are terminated so that the entire site can be decommissioned in an integrated fashion. The spent fuel has been removed from the site.

In 2015, the licensee, GE Hitachi, began a licensing process to exempt the VBWR from the 60-year decommissioning schedule limit of 10 CFR 50.82(a)(3). The request is currently under NRC review and if the exemption request is approved, the estimated date for closure would be 2041.

E-3

GE ESADA Vallecitos Experimental Superheat Reactor (EVESR)

On April 15, 1970, NRC authorized the licensee to possess, but not operate the reactor. The license was renewed on June 11, 1976, and remains in effect under the provisions of 10 CFR 50.51(b). The facility has been maintained in SAFSTOR condition. The facility is next to the Vallecitos Boiling-Water Reactor which is also in SAFSTOR. The licensee plans to maintain the facility in SAFSTOR until other ongoing nuclear and radioactive activities are also to be decommissioned to provide an integrated site decommissioning. In 2015, the licensee began the process of requesting an exemption to the 60-year decommissioning schedule limit of 10 CFR 50.82(a)(3) so that the entire site can be decommissioned in an integrated fashion. If the exemption request is approved, the date for closure would move from 2025 to 2041.

Haddam Neck - Connecticut Yankee Haddam Neck was a 619 MWe (1,825 MWt) pressurized-water reactor that began commercial operation in January 1968, and ceased power operations in 1996. Decommissioning activities began in May 1998. Steam generators, reactor coolant pumps, the pressurizer, the reactor vessel, and shield wall blocks from the reactor building were disposed of off site and demolition of the administration and turbine buildings began in spring 2004. As of March 30, 2005, all spent fuel and greater-than-Class-C waste had been transferred to the ISFSI, which is currently operational.

Decommissioning at Haddam Neck was completed in 2007 and the applicable NRC reactor license under Title 10 of the Code of Federal Regulations (10 CFR) was terminated.

Crystal HaddamRiver Neck3 600 500 Power Generation Collective Dose 400 300 (person-rem) 200 100 0

Year Humboldt Bay Unit 3 Humboldt Bay Power Plant (HBPP) Unit 3 produced power commercially from August 1, 1963, to July 1976. In July 1976, Unit 3 was shut down for annual refueling and to conduct seismic modifications. In 1983, with the plant still shut down, Pacific Gas & Electric, the owner of the facility, determined that required seismic modifications and the requirements imposed as a result of the accident at Three Mile Island made continued operations no longer economically feasible and decided to decommission the plant. The NRC approved the licensees Decommissioning Plan in July 1988.

The licensee submitted a PSDAR in February 1998 and has begun incremental decommissioning activities. In December 2003, the licensee submitted an ISFSI application to the NRC. Humboldt Bay was to have unique dry cask storage because of the short length of its E-4

fuel assemblies. Moreover, the casks were to be stored below-grade to accommodate regional seismicity issues, security concerns, and site boundary dose limits. The NRC issued the ISFSI license on November 18, 2005, and the licensee began constructing the ISFSI in 2007.

Following fuel loading into the ISFSI in 2008, the licensee began constructing new combustion units in 2008 and 2009 to replace the old Humboldt Bay fossil Units 1 and 2. Decommissioning activities at the old fossil Units 1 and 2 were completed in 2013. During this period, decommissioning of Unit 3 commenced and HBPP successfully completed removal of the reactor vessel internals in September 2013. The Humboldt Bay Unit 3 decommissioning status is DECON. The only remaining activities are radiological final status surveys. It is estimated that all decommissioning activities will be completed by September 30, 2020. The ISFSI remains under a separate NRC license.

1,905 person-rem Big Humboldt Rock Point Bay 3 700 600 Power Generation 500 Collective Dose 400 (person-rem) 300 200 100 0

Year Indian Point Unit 1 Indian Point Unit 1 (IP-1) produced power commercially from August 1962 to October 1974. IP-1 was shut down on October 31, 1974, because the emergency core cooling system did not meet regulatory requirements. Some decommissioning work associated with spent fuel storage was performed from 1974 through 1978. By January 1976, all spent fuel had been removed from the reactor vessel. The NRC order approving SAFSTOR was issued in January 1996.

A PSDAR public meeting was held on January 20, 1999. The licensee plans to decommission IP-1 with Indian Point Unit 2 (IP-2), which is currently in operation. The licensee does not plan to begin active decontamination and decommissioning of IP-1 until IP-2 ceases operation.

Big Indian Rock Point Point 1

10 8

Collective Dose 6

(person-rem) 4 2

0 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 Year E-5

Kewaunee Kewaunee Power Station was a 1,772 MWt, pressurized-water reactor that was licensed to operate from December 1973 to May 2013. Kewaunee is located in Carlton, WI, on Lake Michigan about 35 miles southeast of Green Bay.

At present, the facility has transitioned to a SAFSTOR condition. Kewaunee submitted a PSDAR and conducted a public meeting near the site in April 2013. The facility retains its Part 50 license but is no longer authorized to operate or emplace fuel in the reactor vessel. The transfer of spent fuel from the spent fuel pool to the ISFSI was completed in June 2017. Major decommissioning and dismantlement activities are scheduled to begin in 2069 with license termination following in 2073.

Kewaunee Big Rock Point 300 250 Power Generation Collective Dose 200 150 (person-rem) 100 50 0

Year La Crosse The La Crosse Boiling-Water Reactor (LACBWR) produced power commercially starting on November 1, 1969. The plant was one of a series of demonstration plants funded, in part, by the U.S. Atomic Energy Commission (AEC). The nuclear steam supply system and its auxiliaries were funded by the AEC, and the balance-of-plant equipment was funded by the Allis-Chalmers Company. The AEC later sold the plant to Dairyland Power Cooperative (DPC) and provided it with a provisional operating license. LACBWR was shut down on April 30, 1987, and the NRC approved its Decommissioning Plan on August 7, 1991.

La Crosse 350 300 Power Generation 250 Collective Dose 200 (person-rem) 150 100 50 0

Year E-6

Because the NRC approved DPCs Decommissioning Plan (DP) before August 28, 1996 (the effective date of an NRC final rule concerning reactor decommissioning (61 FR 39278; July 29, 1996)), the DP is considered the Post Shutdown Decommissioning Activities Report (PSDAR) for LACBWR (see 10 CFR 50.82). The PSDAR public meeting was held on May 13, 1998, and subsequent updates to the LACBWR decommissioning report have combined the DP and PSDAR into the LACBWR Decommissioning Plan and Post-Shutdown Decommissioning Activities Report (D Plan/PSDAR). DPC constructed an onsite ISFSI and completed the movement of all 333 spent nuclear fuel elements from the Fuel Element Storage Well to dry cask storage at the ISFSI by September 19, 2012.

By order dated May 20, 2016, the NRC approved the direct transfer of Possession Only License No. DPR-45 for LACBWR from DPC to LaCrosse Solutions, LLC (LS), a wholly owned subsidiary of EnergySolutions, LLC. The order was published in the Federal Register on June 2, 2016 (81 FR 35383). The transfer assigns DPCs licensed possession, maintenance, and decommissioning authorities for LACBWR to LS in order to implement expedited decommissioning at the LACBWR site. On September 24, 2019, the NRC approved an order that allows the LACBWR license to be transferred back to DPC upon completion of decommissioning at the site and termination of the Part 50 license outside of the ISFSI. Final decommissioning activities at LACBWR are currently underway and are scheduled to be completed in 2020, with the license transfer to DPC to be executed soon after.

The license termination plan (LTP) for LACBWR was submitted on June 27, 2016. The staff issued the LTP amendment, safety evaluation, and environmental assessment on May 21, 2019.

Maine Yankee Maine Yankee was an 860 MWe pressurized-water reactor located on Bailey Point in Wiscasset, ME, that started commercial power operations in 1972. The Maine Yankee plant was shut down on December 6, 1996. Certification of permanent cessation of operations was submitted on August 7, 1997. The PSDAR was submitted on August 27, 1997, and the NRC approved the LTP on February 28, 2003.

Maine Yankee 800 600 Collective Dose Power Generation 400 (person-rem) 200 0

Year E-7

In 2003, the reactor pressure vessel was shipped to Barnwell, SC via barge. Spent nuclear fuel and greater-than-Class-C waste were transferred to the onsite ISFSI between August 2002 and February 2004. Decommissioning was completed in June 2005, and Maine Yankee will retain its 10 CFR Part 50 license until the fuel is removed from the ISFSI. The NRC LTP approval date is to be determined.

Millstone Unit 1 Millstone Unit 1 produced power commercially from December 28, 1970, to November 4, 1995. Millstone Unit 1 was a single-cycle, boiling-water reactor with a reactor thermal output of 2,011 MW and a net electrical output of 652.1 MW. The unit was shut down on November 4, 1995. On July 21, 1998, pursuant to 10 CFR 50.82(a)(1)(i) and 10 CFR 50.82(a)(1)(ii), the licensee certified to the NRC that, as of July 17, 1998, Millstone Unit 1 had permanently ceased operations and that fuel had been permanently removed from the reactor vessel. The owner of the facility submitted its PSDAR to the NRC on June 14, 1999, which included a combination of DECON and SAFSTOR options. After a formal assessment of spent fuel storage options in 2007, the licensee concluded that they would keep the Millstone Unit 1 fuel in the spent fuel pool, in a SAFSTOR status, until 2048 rather than move the fuel to an ISFSI.

Safety-related structures, systems, and components and those important to safety remaining at Millstone Unit 1 are associated with the spent fuel pool island where the spent fuel is stored.

Besides nonessential systems that support the balance-of-plant facilities, the remaining plant equipment has been de-energized, disabled, or removed from the unit and can no longer be used for power generation. Irradiated reactor vessel components have been removed. The reactor cavity and vessel have been drained, and a radiation shield has been installed to limit occupational radiation doses to workers. Currently, the licensee has estimated 2056 for completion of all decommissioning activities and the estimated closure date of this site.

Millstone 1 2,500 2,000 Power Generation Collective Dose 1,500 (person-rem) 1,000 500 0

Year Oyster Creek Oyster Creek produced power commercially from December 1969, to September 17, 2018.

Oyster Creek was a 1,930 MWt single-cycle, boiling-water reactor with a net electrical output of 619 MW. The unit was shut down on September 17, 2018. By letter dated September 25, 2018, Exelon Generation Company (Exelon), prior owner of the facility, certified that all fuel had been removed from the reactor. In the PSDAR that was submitted to the NRC on May 21, 2018, Exelon stated its intention to move all of the spent nuclear fuel into dry cask storage by the E-8

end of 2024 and put the plant into SAFSTOR until it is ready to fully decommission the facility starting in 2075. License termination is scheduled to take place by 2078 and site restoration by 2080.

On August 31, 2018, Exelon Generation and Holtec submitted a License Transfer Application (LTA) requesting NRC approval to transfer the Oyster Creek Renewed Facility Operating License and the General License for the Oyster Creek ISFSI to Oyster Creek Environmental Protection, LLC (OCEP), as the licensed owner and to Holtec Decommissioning International (HDI), as the licensed operator. The NRC staff is currently reviewing the revised PSDAR submitted by HDI on September 28, 2018, which includes a revised Site-Specific Decommissioning Cost Estimate and notifies the NRC of changes to accelerate the schedule for the prompt decommissioning of Oyster Creek. License termination would take place by 2035.

There are no major technical issues at this time.

Crystal Oyster Creek River 3 2,500 2,000 Power Generation Collective Dose 1,500 (person-rem) 1,000 500 0

Year Peach Bottom 1 Peach Bottom Atomic Power Station Unit 1 was a 200 MWt, high temperature, gas cooled reactor that was operated from June of 1967 to its final shutdown on October 31, 1974. All spent fuel has been removed from the site, and the spent fuel pool is drained and decontaminated.

The reactor vessel, primary system piping, and steam generators remain in place. The facility is currently in a SAFSTOR condition. Final decommissioning is not expected until 2034 when Units 2 and 3 are scheduled to shut down.

Pilgrim 1 Pilgrim Nuclear Power Station was a 670 MWe three-cycle, boiling-water reactor with a reactor thermal output of 2,028 MWt. The unit was shut down permanently by Entergy on May 31, 2019, after providing electricity safely to the region for more than 46 years. In August of 2019, Pilgrim Nuclear Power Station was purchased by Holtec International in a deal that allowed the site to enter immediate decommissioning. The deal enables decommissioning and site release for alternate uses decades sooner than previously anticipated. As Pilgrim enters into this new chapter, its commitment to safety, the community and the environment remains unchanged.

E-9

Pilgrim 1 1,000 4,000 Power Generation 800 Collective Dose 3,000 600 (person-rem) 2,000 400 1,000 200 0

Year Rancho Seco Rancho Seco Nuclear Generating Station was a 913 MW pressurized-water reactor owned by the Sacramento Municipal Utility District (SMUD). Rancho Seco permanently shut down in June 1989, after approximately 15 years of operation. The licensee was granted a site-specific 10 CFR Part 72 license for an onsite ISFSI on June 30, 2000. SMUD completed transfer of all the spent nuclear fuel to the Rancho Seco ISFSI in August 2002. Rancho Seco completed decommissioning of the former reactor site in 2009 and the site was released with the exception of a 6-acre ISFSI site and a class B and C waste storage building. The B/C waste building was decommissioned in 2017, and the 10 CFR Part 50 license was terminated on August 31, 2018.

The ISFSI is still in operation.

Rancho Seco 800 600 Collective Dose Power Generation 400 (person-rem) 200 0

Year San Onofre Unit 1 The San Onofre Nuclear Generating Station Unit 1 (SONGS-1), operated by Southern California Edison (SCE), produced power commercially from January 1, 1968, to November 30, 1992.

Unit 1 was a Westinghouse three-loop pressurized-water reactor with a reactor thermal output of 1,347 MW.

Defueling of SONGS-1 was completed on March 6, 1993, and the NRC approved the Permanently Defueled Technical Specifications on December 28, 1993. On November 3, 1994, SCE submitted a Proposed Decommissioning Plan to place SONGS-1 in SAFSTOR until the shutdown of SONGS-2 and SONGS-3. However, on December 15, 1998, SCE submitted the E-10

PSDAR for SONGS-1 to begin decontamination in 2000. Since that time, SCE has been actively decommissioning the facility, which has been almost entirely dismantled. SCE has removed and disposed of most of the structures and equipment. The SONGS-1 turbine building was removed and the licensee completed internal segmentation and cutup of the reactor pressure vessel. The licensee plans to store the reactor vessel on site for the foreseeable future, as long as licensed activities are ongoing. In addition, the licensee transferred SONGS-1 spent fuel to an onsite generally licensed ISFSI. Starting in 2015, the ISFSI began expanding into the area previously occupied by SONGS-1 to store the spent fuel from SONGS-2 and SONGS-3.

In February 2010, the NRC staff issued a license amendment to release offshore portions of the SONGS-1 cooling intake and outlet pipes for unrestricted use. It is estimated that all decommissioning activities for SONGS-1 will be completed in 2032.

San Onofre 1 80 60 Collective Dose 40 (person-rem) 20 0

1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 Year San Onofre Units 2 and 3 The San Onofre Nuclear Generating Station, Units 2 and 3 (SONGS), operated by the Southern California Edison Company (SCE) is located approximately 4 miles south of San Clemente, California. SONGS, Units 2 and 3, are Combustion Engineering 1,127 MWe pressurized-water reactors, which were granted Facility Operating Licenses NPF 10 on February 16, 1982, and NPF-15 on November 15, 1982, respectively. SONGS 2 and 3 generated power commercially from 1984 to 2012. In June 2013, pursuant to 10 CFR 50.82(a)(1)(i), the licensee certified to the NRC that as of June 7, 2013, operations had ceased at SONGS, Units 2 and 3. The licensee subsequently certified, pursuant to 10 CFR 50.82(a)(1)(ii), that all fuel had been removed from the reactor vessels of both units, and committed to maintaining the units in a permanently defueled status. Therefore, pursuant to 10 CFR 50.82(a)(2), SCEs 10 CFR Part 50 licenses no longer authorize operation of SONGS or emplacement or retention of fuel into the reactor vessels. The licensee is still authorized to possess and store irradiated nuclear fuel. Irradiated fuel is currently being stored onsite in spent fuel pools and in dry casks at an ISFSI.

The PSDAR for SONGS, Units 2 and 3, was submitted on September 23, 2014, and the associated public meeting was held on October 27, 2014, in Carlsbad, California. The NRC confirmed its review of the SONGS, Units 2 and 3, PSDAR and addressed public comments in a letter dated August 20, 2015. On July 17, 2015, the NRC approved the Permanently Defueled Technical Specifications for SONGS, Units 2 and 3. It is estimated that all decommissioning activities for SONGS, Units 2 and 3, will be completed in 2032. San Onofre Units 2 and 3 will retain its 10 CFR Part 50 license until the fuel is removed from the ISFSI.

E-11

San Onofre 2 and 3 500 400 Power Generation Collective Dose 300 (person-rem) 200 100 0

1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 Year Savannah, Nuclear Ship The Nuclear Ship (NS) Savannah was removed from service in 1970 and the fuel was removed from the ship in October 1971. The ship has been designated a national historic landmark by the American Nuclear Society. The Savannah is berthed in Baltimore, Maryland and is transitioning from SAFSTOR to DECON.

Three Mile Island Unit 1 Three Mile Island Generating Station Unit 1 (TMI Unit 1) was a 776 MWe three-loop pressurized-water reactor with a reactor thermal output of 2,568 MWt. TMI Unit 1 permanently shut down on September 20, 2019, leaving a 45-year legacy of safe, reliable, carbon-free electricity generation and service to the community. It now enters a new erathe safe decommissioning and dismantlement of its components, systems and buildings.

Three Mile Island 1 1,000 Power Generation 800 Collective Dose 600 (person-rem) 400 200 0

Year Three Mile Island Unit 2 Three Mile Island Unit 2 (TMI-2) produced power commercially from December 30, 1978, to March 28, 1979. On March 28, 1979, the unit experienced an accident that resulted in severe damage to the reactor core. TMI-2 has been in a non-operating status since that time. The licensee conducted a substantial program to defuel the reactor vessel and decontaminate the facility. The plant defueling was completed in April 1990. All spent fuel has been removed except for some debris in the reactor coolant system. The removed fuel is currently in storage at Idaho National Laboratory, and the DOE has taken title and possession of the fuel.

E-12

Three Mile Island 2 1,000 800 Collective Dose 600 (person-rem) 400 200 0

Year TMI-2 has been defueled and decontaminated to the extent the plant is in a safe, inherently stable condition suitable for long-term management. This long-term management condition is termed post-defueling monitored storage, which was approved in 1993. It is estimated that decommissioning activities for TMI-2 will be completed in 2036. The NRC LTP approval date is to be determined. There is no significant dismantlement underway. The plant shares equipment with the operating Three Mile Island Unit 1 (TMI-1). TMI-1 was sold to AmerGen (now Exelon) in 1999. GPU Nuclear retains the license for TMI-2 and is owned by FirstEnergy Corp. GPU Nuclear contracts with Exelon for maintenance and surveillance activities. The licensee plans to decommission TMI-2 independently of TMI-1, but may coordinate some TMI-2 decommissioning activities to support TMI-1 decommissioning. TMI-2 will retain its 10 CFR Part 50 license until the fuel is removed from the ISFSI.

Trojan The Trojan plant was shut down in November 1992, and the SGs and reactor vessel were shipped to the Hanford site. The licensee was granted a site-specific 10 CFR Part 72 license for an onsite ISFSI in March 1999 that is still in operation. The licensee began spent fuel transfer to the ISFSI in December 2002 and finished fuel transfer in August 2003.

In December 2004, the Trojan Nuclear Plant completed decommissioning activities. The NRC terminated Trojans 10 CFR Part 50 operating license on May 23, 2005.

Trojan 600 500 Power Generation Collective Dose 400 300 (person-rem) 200 100 0

Year E-13

Vermont Yankee Vermont Yankee Nuclear Power Station was a 1,912 Mwt, boiling-water reactor that began operation in 1972. The reactor was permanently shut down on December 29, 2014, and the fuel was removed from the reactor on January 12, 2015.

Entergy, which owns the facility, submitted the Vermont Yankee PSDAR to the NRC on Dec. 19, 2014. In the report, Entergy stated its intention to keep the plant in SAFSTOR until it is ready to fully decommission the facility in 2073. Entergy completed movement of the spent nuclear fuel to dry cask storage in August 2018.

On February 9, 2017, Entergy and NorthStar Group Services, Inc. (NorthStar) submitted a request to transfer the Vermont Yankee Nuclear Power Station license from Entergy to NorthStar. On October 12, 2018, NRC issued a first-of-a-kind order approving the permanent transfer of the Vermont Yankee Operating license and associated spent fuel in onsite storage from Entergy to Northstar for the purpose of decommissioning the reactor. With the completion of the transfer to Entergy on January 11, 2019, the new estimated date for closure is 2030.

Vermont Yankee 1,600 1,400 1,200 Power Generation Collective Dose 1,000 800 (person-rem) 600 400 200 0

Year Yankee Rowe The Yankee Rowe plant was permanently shut down on October 1, 1991, and the SGs were shipped to the Barnwell Low-Level Radioactive Waste Disposal Facility in North Carolina, in November 1993. The reactor vessel was shipped to Barnwell in April 1997.

Yankee Rowe 500 400 Power Generation Collective Dose 300 (person-rem) 200 100 0

Year E-14

The owner completed construction of an onsite ISFSI and all the fuel from the spent fuel pool was transferred to it.

Yankee Rowe completed decommissioning in 2007. The license for the site was reduced to the two acres surrounding the ISFSI, which is still in operation.

Zion Units 1 and 2 Zion Nuclear Power Station (ZNPS) received a construction permit in December 1968 to begin building two nuclear power reactors. Unit 1 produced power commercially from December 31, 1973, to February 21, 1997, and Unit 2 produced power commercially from September 17, 1974, to September 19, 1996. On April 27, 1997, all fuel from Unit 1 was removed and on February 25, 1998, all fuel from Unit 2 was removed and placed in the spent fuel pool. On January 14, 1998, the Unicom Corporation and ComEd Boards of Directors, the joint owners of the facility, authorized the permanent cessation of operations at ZNPS for economic reasons. ComEd certified, in a letter dated February 13, 1998, to the NRC that operations had ceased at ZNPS. On March 9, 1998, ComEd informed the NRC that all fuel had been removed from the ZNPS reactor vessels and committed to maintain them permanently defueled.

The NRC acknowledged the certification of permanent cessation of power operation and permanent removal of fuel from the reactor vessels in a letter dated May 4, 1998, and ZNPS was placed in SAFSTOR. The owner submitted the PSDAR, site-specific cost estimate, and fuel management plan on February 14, 2000. The SAFSTOR approach is the intended decommissioning method to be used for ZNPS, which involves removal of all radioactive material from the site following a period of dormancy. In 2010, the NRC staff finalized the transfer of the possession license for Zion Units 1 and 2 from Exelon Generating Company, LLC to Zion Solutions, LLC to facilitate decommissioning. At Zion Units 1 and 2, decommissioning planning activities for the removal of large components were performed during 2011. The NRC staff held a public meeting in April 2015 regarding the LTP for Zion Units 1 and 2, which was submitted in December 2014. All of the above-grade plant structures have been removed. Final site survey and license reduction to the ISFSI is currently planned for -2020. It is estimated that license termination will occur in September 2020.

Zion 1 and 2 2,500 2,000 Power Generation Collective Dose 1,500 (person-rem) 1,000 500 0

Year E-15

APPENDIX F GLOSSARY 2019 Information in this appendix was obtained from Reference 22.

GLOSSARY 2019 Agreement State: as defined in Title 10 of the Code of Federal Regulations (10 CFR) 30.4, means any State with which the Atomic Energy Commission or the U.S. Nuclear Regulatory Commission has entered into an effective agreement under subsection 274b. of the [Atomic Energy] Act [of 1954, including any amendments thereto]. To simplify subsection 274b., an Agreement State is a State that has signed an agreement with the NRC under which the State regulates the use of certain byproduct, source, and small quantities of special nuclear material in that State.

As low as is reasonably achievable (ALARA): as defined in 10 CFR 20.1003, means making every reasonable effort to maintain exposures to radiation as far below the dose limits in 10 CFR Part 20 as is practical, consistent with the purpose for which the licensed activity is undertaken, taking into account the state of technology, the economics of improvements in relation to the state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and licensed materials in the public interest.

Average measurable dose: the dose obtained by dividing the collective dose by the number of individuals 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, because it excludes those individuals receiving a less-than-measurable dose.

Boiling-water reactor (BWR): a reactor in which the water, used as both coolant and moderator, is allowed to boil in the core. The resulting steam can be used directly to drive a turbine and electrical generator, thereby producing electricity.

Byproduct material: as partially defined in 10 CFR 20.1003, means any radioactive material (except special nuclear material) yielded in, or made radioactive by, exposure to the radiation incident to the process of producing or using special nuclear material; and the tailings or wastes produced by the extraction or concentration of uranium or thorium from ore processed primarily for its source material content.

Breeder: a reactor that produces more nuclear fuel than it consumes. A fertile material, such as uranium-238, when bombarded by neutrons, is transformed into a fissile material, such as plutonium-239, which can be used as fuel. [Ref. 23]

Ceased operations: the date of plant shutdown notification to the NRC.

Ceased power generation: the date the plant ceased to generate electricity.

Class (or lung class or inhalation class): as defined in 10 CFR 20.1003, means a classification scheme for inhaled material according to its rate of clearance from the pulmonary region of the lung. Materials are classified as D, W, or Y, which applies to a range of clearance half-times: for Class D (Days) of less than 10 days, for Class W (Weeks) from 10 to 100 days, and for Y (Years) of greater than 100 days.

F-1

Collective dose: as defined in 10 CFR 20.1003, is the sum of the individual doses received in a given period of time by a specified population from exposure to a specified source of radiation.

Committed dose equivalent (HT,50 ): as defined in 10 CFR 20.1003, means the dose equivalent to organs or tissues of reference that will be received from an intake of radioactive material by an individual during the 50-year period following the intake (CDE [HT,50 ]). The acronym CDE is an NRC acronym used for this term.

Committed effective dose equivalent (HE,50 ): as defined in 10 CFR 20.1003, is the sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues (CEDE [HE,50 ] =

WTHT.50). The acronym CEDE is an NRC acronym used for this term.

Criticality: the normal operating condition of a reactor, in which nuclear fuel sustains a fission chain reaction. A reactor achieves criticality (and is said to be critical) when each fission event releases a sufficient number of neutrons to sustain an ongoing series of reactions. [Ref. 21]

DECON (immediate dismantlement): soon after the nuclear facility closes, equipment, structures, and portions of the facility containing radioactive contaminants are removed or decontaminated to a level that permits release of the property and termination of the NRC license.

Deep-dose equivalent (Hd ): as defined in 10 CFR 20.1003, which applies to external whole-body exposure, is the dose equivalent at a tissue depth of 1 cm (1000 mg/cm2). The acronym DDE is an NRC acronym used for this term.

Effective dose equivalent (HE ): as defined in 10 CFR 20.1003, is the sum of the products of the dose equivalent to the organ or tissue (HT) and the weighting factors (WT) applicable to each of the body organs or tissues that are irradiated (EDE [HE ] = WTHT). The acronym EDE is an NRC acronym used for this term.

ENTOMB: radioactive contaminants that are permanently encased on site in a structurally sound material such as concrete and appropriately maintained and monitored until the radioactivity decays to a level permitting restr icted release of the property.

Exposure: as defined in 10 CFR 20.1003, means being exposed to ionizing radiation or to radioactive material.

FBR: a fast breeder reactor is a nuclear reactor that generates more fissile material than it consumes. These devices achieve this because their neutron economy is high enough to breed more fissile fuel than they use from fertile material, such as uranium-238 or thorium-232.

Independent Spent Fuel Storage Installation (ISFSI): as defined in 10 CFR 72.3, means a complex designed and constructed for the interim storage of spent nuclear fuel, solid reactor-related greater-than-Class-C (GTCC) waste, and other radioactive materials associated with spent F-2

fuel and reactor-related GTCC waste storage. An ISFSI which is located on the site of another facility licensed under 10 CFR Part 72 or a facility licensed under 10 CFR Part 50 of [Title 10 of the Code of Federal Regulations] and which shares common utilities and services with that facility or is physically connected with that other facility may still be considered independent.

Lens dose equivalent (LDE): as defined in 10 CFR 20.1003, applies to the external exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeters (300 mg/cm2).

License: as defined in 10 CFR 20.1003, means a license issued under the regulations in 10 CFR Parts 30 through 36, 39, 40, 50, 60, 61, 63, 70, or 72 of [Title 10 of the Code of Federal Regulations].

Licensee: as defined in 10 CFR 20.1003, means the holder of the NRC license.

Licensed material: as defined in 10 CFR 20.1003, means source material, special nuclear material, or byproduct material received, possessed, used, transferred, or disposed of under a general or specific license issued by the [Nuclear Regulatory] Commission.

Light-water reactor (LWR): the term used in this report to describe commercial nuclear reactors that use ordinary water as a coolant and are operated for the purposes of generating electricity.

Light water reactors include boiling-water reactors (BWRs) and pressurized-water reactors (PWRs).

Measurable dose: a dose greater than zero rem (not including doses reported as not detectable).

Megawatt-year: unit of electric energy, equal to the energy from a power of 1,000,000 watts over a period of 1 year.

Mode of Intake: the manner of intake into the body: inhalation (H), absorption through the skin (B), oral ingestion (G), and injection (J).

Monitoring year: interval during which the radiation exposure monitoring was performed.

Nonreactor licensees: NRC licensees that are not commercial nuclear power reactors.

These licensees are industrial radiographers, fuel processors, fabricators, and reprocessors; manufacturers and distributors of byproduct material; ISFSIs; facilities for land disposal of low-level waste; and geologic repositories for high-level waste.

Number of individuals with measurable dose: the count of unique individuals who received a measurable dose during the monitoring year. In some instances in this report, the number of individuals with a measurable dose may include individuals who are counted more than once, F-3

since they may be monitored at more than one licensee during the year. (See Section 5 on the effect of transient individuals.) Tables that have been adjusted for transient workers are noted in the appropriate footnotes to the tables.

Occupational dose: as defined in 10 CFR 20.1003, means the dose received by an individual in the course of employment in which the individuals assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under [10 CFR] 35.75, from voluntary participation in medical research programs, or as a member of the public.

Pressurized-water reactor (PWR): a power reactor in which heat is transferred from the core to an exchanger by high-temperature water kept under high pressure in the primary system. Steam used to turn a turbine and electrical generator is generated in a secondary circuit. The majority of reactors producing electric power in the United States are pressurized-water reactors.

Radiation Safety Officer (RSO): as defined in 10 CFR 33, a person appointed who is qualified by training and experience in radiation protection, and who is available for advice and assistance on radiological safety matters.

Radionuclide: a radioisotope. A radioisotope is an unstable isotope that undergoes spontaneous transformation, emitting radiation. [Ref. 20]

REM: as defined in 10 CFR 20.1004, is the special unit of any of the quantities expressed as dose equivalent. The dose equivalent in rems is equal to the absorbed dose in rads multiplied by the quality factor (1 rem = 0.01 sievert).

SAFSTOR (often considered delayed DECON): a nuclear facility that is maintained and monitored in a condition that allows the radioactivity to decay; afterwards, it is dismantled.

Shallow-dose equivalent for both maximum extremity (SDE-ME) and whole body (SDE-WB):

the external exposure of an extremity, taken as the dose equivalent at a tissue depth of 0.007 centimeters.

Sievert: as defined in 10 CFR 20.1004, is the International System of Units (SI) of any of the quantities expressed as dose equivalent. The dose equivalent in sieverts is equal to the absorbed dose in grays multiplied by the quality factor (1 Sv = 100 rem).

Special nuclear material: as defined in 10 CFR 20.1003, means plutonium, uranium-233, uranium enriched in the isotope 233 or in the isotope 235, and any other material that the [Nuclear Regulatory] Commission, pursuant to the provisions of section 51 of the [Atomic Energy] Act

[of 1954, as amended], determines to be special nuclear material, but does not include source material, or any material artificially enriched by any of the foregoing.

F-4

Statistical comparisons: For statistical comparisons of averages, a two-sided one-sample t test with a 0.05 significance level (i.e., 95 percent confidence) is used to determine whether the difference between the two averages is significantly different. For values that are not averages, such as total collective dose, a 5-year average from the previous five years (not including the current year under consideration) is calculated with 95 percent confidence interval based on the normal distribution. If the value for the current year falls within the 5-year 95 percent confidence interval, then it is not significantly different; whereas, if the value falls outside (i.e., below the lower limit or above the upper limit), there is an indication of a statistical significant change.

Two-sided one-sample t test formula:

Where:

t = calculated t statistic

= sample mean

µ = population mean S = sample standard deviation n = sample number Example:

We wish to determine if the average measurable dose for a type of nuclear reactor differs from the previous five years. The five year mean for the average measurable dose is 0.080. The population mean is the current years average measurable dose, 0.060. The sample standard deviation is 0.01, and the sample number is 5. Using the formula, The two-tailed probability value (as obtained from a Students t distribution table) given a t-value of 4.472 is 0.006 which is statistically significant at a 0.05 significance level.

Total effective dose equivalent (TEDE): as defined in 10 CFR 20.1003, means the sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures) (TEDE = DDE + CEDE).

Total organ dose equivalent (TODE): as defined in the NRC Regulatory Guide 8.7, the sum of the deep dose equivalent and the committed dose equivalent to the organ receiving the highest dose as described in 10 CFR 20.2106(a)(6).

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Transient individual: one who is monitored at more than one licensed site during the calendar year.

Unit availability factor: the unit available hours (the total clock hours in the report period during which the unit operated on line or was capable of such operation) times 100 divided by the period hours.

Weighting factor (WT ): as defined in 10 CFR 20.1003, the weighting factor for an organ or tissue (T) is the proportion of the risk of stochastic effects resulting from irradiation of that organ or tissue to the total risk of stochastic effects when the whole body is irradiated uniformly.

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NUREG-0713 Volume 41 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2019 April 2022 Fifty-Second Annual Report T.A. Brock; M.N. Nguyen - NRC Technical D.A. Hagemeyer; D.B. Holcomb - ORAU January 2019 - December 2019 Oak Ridge Associated Universities 1299 Bethel Valley Road, SC-200, MS-21 Oak Ridge, TN 37830 Division of Systems Analysis Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission (NRC) Radiation Exposure Information and Reporting System (REIRS) database. The bulk of the information contained in this report was compiled from the 2019 annual reports submitted by five of the seven categories of NRC licensees subject to the reporting requirements of Title 10 of the Code of Federal Regulations (10 CFR) 20.2206, Reports of Individual Monitoring. Because there are no geologic repositories for high-level waste currently licensed and no NRC-licensed low-level waste disposal facilities currently in operation, only five categories are considered in this report. 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. Annual reports for 2019 were received from a total of 181 NRC licensees from the five categories included in this report. The summation of reports submitted by the 181 licensees indicated that 144,243 individuals were monitored, 60,289 of whom received a measurable dose.

occupational exposure nuclear power reactor fuel facility collective dose measurable dose

NUREG-0713 Occupational Radiation Exposure at Commercial Nuclear Power April 2022 Volume 41 Reactors and Other Facilities 2019