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#REDIRECT [[NUREG/CR-2907 Volume 16, Radioactive Effluents from Nuclear Power Plants - Annual Report 2010]]
| number = ML18151A529
| issue date = 05/31/2018
| title = NUREG/CR-2907, Vol. 16, Radioactive Effluents from Nuclear Power Plants - Annual Report 2010
| author name = Davis J, Garry S M, Smith M
| author affiliation = NRC/NRR, Oak Ridge Associated Universities
| addressee name =
| addressee affiliation =
| docket =
| license number =
| contact person = Meyd, Donald
| document report number = NUREG/CR-2907 V16
| document type = NUREG
| page count = 101
}}
 
=Text=
{{#Wiki_filter:NUREG/CR-2907, V ol. 16 Radioactive Effluents from Nuclear Power Plants Annual Report 2010 Office of Nuclear Reactor Regulation
 
NRC Reference Material  As of November 1999, you may electronically access NUREG-series publications and other NRC records at the http://www.nrc.gov/reading-rm.html. Publicly released records include, to name a few, NUREG-series publications; Federal Register notices; applicant, licensee, and vendor documents and correspondence; NRC correspondence and internal memoranda; bulletins and information notices; inspection and investigative reports; licensee event reports; and Commission papers and their attachments. NRC publications in the NUREG series, NRC regulations, and Title 10, Energy,Code of Federal Regulations may also be purchased from one of these two sources. 1. The Superintendent of Documents U.S. Government Publishing Office Washington, DC  20402-0001 Internet: http://bookstore.gpo.gov Telephone: 1-866-512-1800 Fax: (202) 512-2104  2. The National Technical Information Service 5301 Shawnee Road Alexandria, VA  22161-0002 http://www.ntis.gov 1-800-553-6847 or, locally, (703) 605-6000  A single copy of each NRC draft report for comment is available free, to the extent of supply, upon written request as follows:  U.S. Nuclear Regulatory Commission Office of Administration Multimedia, Graphics and Storage & Distribution Branch Washington, DC  20555-0001 E-mail: distribution.resource@nrc.gov Facsimile: (301) 415-2289  Some publications in the NUREG series that are posted at the http://www.nrc.gov/reading-rm/doc-collections/nuregs are updated periodically and may differ from the last printed version. Although references to material found on a Web site bear the date the material was accessed, the material available on the date cited may subsequently be removed from the site. Non-NRC Reference Material Documents available from public and special technical libraries include all open literature items, such as books, journal articles, transactions, Federal Register notices, Federal and State legislation, and congressional reports. Such documents as theses, dissertations, foreign reports and translations, and non-NRC conference proceedings may be purchased from their sponsoring organization. Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at The NRC Technical Library Two White Flint North 11545 Rockville Pike Rockville, MD  20852-2738  These standards are available in the library for reference use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from  American National Standards Institute 11 West 42nd Street New York, NY  10036-8002 http://www.ansi.org (212) 642-4900    AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS Legally binding regulatory requirements are stated only in laws; NRC regulations; licenses, including technical specifications; or orders, not in NUREG-series publications. The views expressed in contractor-prepared publications in this series are not necessarily those of the NRC. The NUREG series comprises (1) technical and administrative reports and books prepared by the staff (NUREG-XXXX) or agency contractors (NUREG/CR-XXXX), (2) proceedings of conferences (NUREG/CP-XXXX), (3) reports resulting from international agreements (NUREG/IA-XXXX), (4) brochures (NUREG/BR-XXXX), and (5) compilations of legal decisions and orders of the Commission and (NUREG-0750). DISCLAIMER: This report was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any information, apparatus, product, or process disclosed in this publication, or represents that its use by such third party would not infringe privately owned rights. SR-CR 10/2017 NUREG/CR-2907, V ol. 16 Office of Nuclear Reactor Regulation Radioacti ve Effluents from Nuclear Power Plants Annual Report 2010 M anuscript C ompleted: F ebruary 2017 Date Published:
2 018 Prepared by
: J.DavisOak R idge Associate d Universities 1299 Bethel Valley R oad, S C-200, M S-21 Oak R idge, TN 37830 Steven Garry and Micheal Smith, NRC Project Manager s 
 
iii ABSTRACT There are 104 commercial nuclear power plants (NPPs) licensed to operate on 65 sites in the United States (U.S.) regulated by the Nuclear Regulatory Commission (NRC). Each year, each power reactor sends a report to the NRC that identifies the radioactive liquid and gaseous effluents discharged from the facility. In 2010, these effluent reports comprised about 10,000 pages of information, which described the radioactive materials discharged, as well as the resulting radiation doses to the general public. This report summarizes that information and presents the information in a format intended for both nuclear professionals and the general public.
The reader can use this report to quickly characterize the radioactive discharges from any U.S. NPP in 2010. The radioactive effluents from one reactor can be compared with other reactors. The results can also be compared with typical (or median) effluents for the industry, including short
-term trends and long
-term trends.
Reference information is included so the reader can compare the doses from NPP effluents with the doses the general public receives from other sources of radiation, such as medical procedures, industrial devices, and natural materials in the environment.
Although all NPPs released some radioactive materials in 2010, all effluents discharged were within the NRC's public dose limits, and NRC ALARA criteria. Additionally, the doses from radioactive effluents were much less than the doses from other sources of natural radiation that are commonly considered safe. This indicates radioactive effluents from NPPs in 2010 had no significant impact on the health and safety of the public or the environment.
 
v TABLE OF CONTENTS ABSTRACT ...............................................................................................................................
iii LIST OF FIGURES
................................................................................................................... v ii LIST OF TABLES
......................................................................................................................
ix ABBREVIATIONS AND ACRONYMS
.......................................................................................
xi 1 INTRODUCTION
.................................................................................................................... 1 1.1 Purpose ...........................................................................................................................
1 1.2 Scope .............................................................................................................................. 1 1.3  Source of Data
................................................................................................................ 5 1.4  Limitations of Data
........................................................................................................... 5 2 DESCRIPTION OF THE DATA ..............................................................................................
7 2.1  Introduction
..................................................................................................................... 7 2.2  Measuring Radioactivity in Radioactive Effluents
............................................................. 7 2.3  Dose Units and Limits
...................................................................................................... 9 2.4  Radiation Dose to the Public
.........................................................................................
10 2.5  Other Sources of Radiation Dose to the U.S. Population
...............................................
11 3 EFFLUENT DATA
................................................................................................................
13 3.1  Radioactive Materials in Liquid and Gaseous Effluents
.................................................
13 3.2  Short-Term Trend in Gaseous Effluents
........................................................................
51 3.3  Long-Term Trend in Gaseous Effluents
.........................................................................
55 3.4  Short-Term Trend in Liquid Effluents
.............................................................................
56 3.5  Long-Term Trend in Liquid Effluents
..............................................................................
60 3.6  Radiation Doses from Gaseous and Liquid Effluents
.....................................................
61 4
 
==SUMMARY==
...........................................................................................................................
75 5 REFERENCES
.....................................................................................................................
77 6 GLOSSARY .........................................................................................................................
79 
 
vii LIST OF FIGURES Figure 2.1 Sources of Radiation Exposure to the U.S. Population
................................
......12 Figure 3.1 BWR Gaseous Releases
- Fission and Activation Gases
................................
32 Figure 3.2 BWR Gaseous Releases
- Iodine ................................
....................................33 Figure 3.3 BWR Gaseous Releases
- Particulates
................................
...........................
34 Figure 3.4 BWR Gaseous Releases
- Tritium ................................
................................
...35 Figure 3.5 BWR Gaseous Releases
- Carbon-14 ................................
.............................
36 Figure 3.6 PWR Gaseous Releases
- Fission and Activation Gases
................................
37 Figure 3.7 PWR Gaseous Releases
- Iodine ................................
....................................39 Figure 3.8 PWR Gaseous Releases
- Particulates
................................
...........................
40 Figure 3.9 PWR Gaseous Releases
- Tritium ................................
...................................41 Figure 3.10 PWR Gaseous Releases
- Carbon-14 ................................
.............................
43 Figure 3.11 BWR Liquid Releases
- Fission and Activation Products
................................
.45 Figure 3.12 BWR Liquid Releases
- Tritium ................................
........................................46 Figure 3.13 PWR Liquid Releases
- Fission and Activation Products
................................
.47 Figure 3.14 PWR Liquid Releases
- Tritium ................................
........................................49 Figure 3.15 Long-Term Trend in Noble Gases in Gaseous Effluents
................................
....55 Figure 3.16 Long-Term Trend in MFAPs in Liquid Effluents ................................
..................
60 Figure 3.17 BWR Gaseous Effluents
- Maximum Annual Organ Dose
................................
68 Figure 3.18 PWR Gaseous Effluents
- Maximum Annual Organ Dose
................................
69 Figure 3.19 BWR Liquid Effluents
- Maximum Annual Total Body and Organ Dose
............
71 Figure 3.20 PWR Liquid Effluents
- Maximum Annual Total Body and Organ Dose
............
72 Figure 3.21 Median Maximum Annual Organ Dose, Gaseous Effluents  4
-Year Trend,  2007-2010................................
................................................................
..........
74 Figure 3.22 Median Maximum Annual Dose, Liquid Effluents 4
-Year Trend,  2007-2010................................
................................................................
..........
74   
 
ix LIST OF TABLES Table 1.1 Nuclear Power Plants, 2010
................................
................................................
2 Table 1.2 Reactors for Which the NRC Has Normalized Data on a Unit
-Specific Basis ................................
................................................................
...................
6 Table 2.1 Radionuclides in Gaseous Effluents
................................
.................................... 8 Table 2.2 Radionuclides in Liquid Effluents
........................................................................ 9 Table 3.1 BWR Gaseous Releases
- Fission and Activation Gases, 2010
.......................
15 Table 3.2 BWR Gaseous Releases
- Iodine, 2010
................................
..........................
16 Table 3.3 BWR Gaseous Releases
- Particulates, 2010
................................
..................
17 Table 3.4 BWR Gaseous Releases
- Tritium, 2 010 ................................
.........................
18 Table 3.5 BWR Gaseous Releases
- Carbon-14, 2010 ................................
...................
19 Table 3.6 PWR Gaseous Releases
- Fission and Activation Gases, 2010
.......................
20 Table 3.7 PWR Gaseous Releases
- Iodine, 2010
................................
..........................
22 Table 3.8 PWR Gaseous Releases
- Particulates, 2010
................................
..................
23 Table 3.9 PWR Gaseous Releases
- Tritium, 2010
................................
.........................
25 Table 3.10 PWR Gaseous Releases
- Carbon-14, 20 10 ................................
...................
26 Table 3.11 BWR Liquid Releases
- Fission and Activation Products, 2010
........................
27 Table 3.12 BWR Liquid Releases
- Tritium, 2010
................................
..............................
28 Table 3.13 PWR Liquid Releases
- Fission and Activation Products, 2010
........................
29 Table 3.14 PWR Liquid Releases
- Tritium, 2010
................................
..............................
31 Table 3.15 Short-Term Trend in Noble Gases in Gaseous Effluents, BWRs, Curies (Ci) ................................
................................................................
.....................
52 Table 3.16 Short-Term Trend in Noble Gases in Gaseous Effluents, PWRs, Curies (Ci) ................................
................................................................
.....................
53 Table 3.17 Short-Term Trend in Mixed Fission and Activation Products in Liquid Effluents, BWRs, millicuries (mCi)
................................
......................................57 Table 3.18 Short-Term Trend in Mixed Fission and Activation Products in Liquid Effluents, PWRs, millicuries (mCi)
................................
......................................58 Table 3.19 BWR Gaseous Effluents
- Maximum Annual Organ Dose, 2010
......................
64 Table 3.20 PWR Gaseous Effluents
- Maximum Annual Organ Dose, 2010
......................
65 Table 3.21 BWR Liquid Effluents
- Maximum Annual Total Body and Organ Dose, 2010
................................
................................................................
........66 Table 3.22 PWR Liquid Effluents - Maximum Annual Total Body and Organ Dose, 2010
................................
................................................................
........67   
 
xi ABBREVIATIONS AND ACRONYMS ALARA as low as is reasonably achievable ARERR Annual Radioactive Effluent Release Report Bq becquerel BWR boiling-water reactor C-14 carbon-14 CFR Code of Federal Regulations Ci curie DOE Department of Energy GBq gigabecquerels H-3 tritium mCi millicurie MFAP mixed fission and activation products mrem millirem mSv millisievert NCRP National Council on Radiation Protection and Measurements NPP nuclear power plant ODCM Offsite Dose Calculation Manual PWR pressurized
-water reactor RG Regulatory Guide SI International System of Units (abbreviation is from the French:  Le Systme International d'Unités)  Sv sievert USGS United States Geological Survey U.S. NRC United States Nuclear Regulatory Commission
 
1 1    INTRODUCTION
 
===1.1 Purpose===
This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the U.S. during calendar year 2010. It is based on an extensive amount of information submitted to the Nuclear Regulatory Commission (NRC) by all U.S. NPP licensees.
The original information was submitted by the NPPs in their Annual Radioactive Effluent Release Reports (ARERRs) and comprises several thousand pages of data. The ARERRs may be viewed in their entirety on the NRC Web site at:  http://www.nrc.gov/reactors/operating/ops
-experience/tritium/plant
-info.html. For the years between 1972 and 1993, this type of annual information was condensed into a tabular format and published as a large volume of tabulated data (Refs. [1
-22] ). An evaluation of the practice of generating tabular annual reports revealed the need for a more concise summary report that presented the information in a more intuitive, graphic format (Ref. [23] ). As a result, this style of improved reports was created. This report joins a series of previous reports on radioactive effluents presented in the revised graphic format (Refs. [24
-26] ). The purpose of this report is to condense an extremely large volume of technical information into a few tables and figures from which the reader can quickly, if broadly, characterize the effluents from any operating U.S. NPP. These tables and figures are designed to provide easily understandable information for the public at large, while also providing experienced professionals with enough information to evaluate trends in industry performance and to identify potential performance issues for individual power plants. Those users wanting more extensive and detailed information are encouraged to retrieve the original ARERRs from the NRC Web site. 1.2  Scope This report summarizes data from all NPPs in commercial operation between January 1, 2010 and December 31, 2010. The list of NPPs included in this report is provided in Table 1.1. The NPP type-boiling-water reactor (BWR) or pressurized
-water reactor (PWR)
-is indicated in the table. Some of the shutdown reactors were totally dismantled during the decommissioning process. As a result, for some shutdown reactors, no visible structures or facilities may be present at the locations listed in Table 1.1.
 
2 Table 1.1 Nuclear Power Plants, 2010 Plant Name Type Full Plant Name Location Arkansas 1, 2 PWR Arkansas Nuclear One (ANO), Units 1, 2 Russellville, AR Beaver Valley 1, 2 PWR Beaver Valley, Units 1, 2 Shippingport, PA Braidwood 1, 2 PWR Braidwood Generating Station, Units 1, 2 Braceville, IL Browns Ferry 1, 2, 3 BWR Browns Ferry Nuclear Plant, Units 1, 2, 3 Decatur, AL Brunswick 1, 2 BWR Brunswick Steam Electric Plant, Units 1, 2 Southport, NC Byron 1, 2 PWR Byron Generating Station, Units 1, 2 Byron, IL Callaway  PWR Callaway Plant, Unit 1 Callaway, MO Calvert Cliffs 1, 2 PWR Calvert Cliffs Nuclear Power Plant, Units 1, 2 Lusby, MD Catawba 1, 2 PWR Catawba Nuclear Station, Units 1, 2 York, SC Clinton BWR Clinton Power Station Clinton, IL Columbia  BWR Columbia Station Richland, WA Comanche Peak 1, 2 PWR Comanche Peak Steam Electric Station, Units 1, 2 Glen Rose, TX Cook 1, 2 PWR Donald C. Cook Nuclear Plant, Units 1, 2 Bridgman, MI Cooper BWR Cooper Nuclear Station Brownville, NE Crystal River 3 PWR Crystal River, Unit 3 Crystal River, FL Davis-Besse PWR Davis-Besse Nuclear Power Station, Unit 1 Oak Harbor, OH Diablo Canyon 1, 2 PWR Diablo Canyon, Units 1, 2 Avila Beach, CA Dresden 2, 3 BWR Dresden Generating Station, Units 2, 3 Morris, IL Duane Arnold BWR Duane Arnold Energy Center Palo, IA Farley 1, 2 PWR Joseph M. Farley Nuclear Plant, Units 1, 2 Ashford, AL Fermi 2 BWR Fermi 2 Nuclear Power Plant Newport, MI FitzPatrick BWR James A. FitzPatrick Nuclear Power Plant Lycoming, NY Ft. Calhoun PWR Ft. Calhoun Station, Unit 1 Ft. Calhoun, NE Ginna PWR R.E. Ginna Nuclear Power Plant, Unit 1Ontario, NY Grand Gulf BWR Grand Gulf Nuclear Station, Unit 1 Port Gibson, MS Harris PWR Shearon Harris Nuclear Power Plant, Unit 1 New Hill, NC Hatch 1, 2 BWR Edwin I. Hatch Nuclear Plant, Units 1, 2 Baxley, GA Hope Creek BWR Hope Creek Generating Station, Unit 1 Hancocks Bridge, NJ Indian Point 2, 3 PWR Indian Point Energy Center, Units 2, 3 Buchanan, NY Kewaunee PWR Kewaunee Power Station Kewaunee, WI LaSalle 1, 2 BWR LaSalle County Generating Station, Units 1, 2 Marseilles, IL Limerick 1, 2 BWR Limerick Generating Station, Units 1, 2 Saratoga, PA
 
3 Table 1.1 Nuclear Power Plants, 2010 (continued)
Plant Name Type Full Plant Name Location McGuire 1, 2 PWR McGuire Nuclear Station, Units 1, 2 Huntersville, NC Millstone 2, 3 PWR Millstone Power Station, Units 2, 3 Waterford, CT Monticello BWR Monticello Nuclear Generating Plant Monticello, MN Nine Mile Point 1, 2 BWR Nine Mile Point Nuclear Station, Units 1, 2 Lycoming, NY North Anna 1, 2 PWR North Anna Power Station, Units 1, 2 Mineral, VA Oconee 1, 2, 3 PWR Oconee Nuclear Station, Units 1, 2, 3 Seneca, SC Oyster Creek BWR Oyster Creek Nuclear Generating Station Forked River, NJ Palisades PWR Palisades Nuclear Plant Covert, MI Palo Verde 1, 2, 3 PWR Palo Verde Nuclear Generating Station,  Units 1, 2, 3 Phoenix, AZ Peach Bottom 2, 3 BWR Peach Bottom Atomic Power Station, Units 2, 3 Delta, PA Perry BWR Perry Nuclear Power Plant, Unit 1 Perry, OH Pilgrim  BWR Pilgrim Nuclear Power Station, Unit 1 Plymouth, MA Point Beach 1, 2 PWR Point Beach Nuclear Plant, Units 1, 2 Two Rivers, WI Prairie Island 1, 2 PWR Prairie Island Nuclear Generating Plant,  Units 1, 2 Welch, MN Quad Cities 1, 2 BWR Quad Cities Generating Station, Units 1, 2 Cordova, IL River Bend BWR River Bend Station, Unit 1 St. Francisville, LA Robinson 2 PWR H. B. Robinson Steam Electric Plant, Unit 2 Hartsville, SC Salem 1, 2 PWR Salem Nuclear Generating Station, Units 1, 2 Hancocks Bridge, NJ San Onofre 2, 3 PWR San Onofre Nuclear Generating Station,  Units 2, 3 San Clemente, CA Seabrook PWR Seabrook Station, Unit 1 Seabrook, NH Sequoyah 1, 2 PWR Sequoyah Nuclear Plant, Units 1, 2 Soddy-Daisy, TN South Texas 1, 2 PWR South Texas Project Electric Generating Station, Units 1, 2 Wadsworth, TX St. Lucie 1, 2 PWR St. Lucie Nuclear Plant, Units 1, 2 Ft. Pierce, FL Summer  PWR Virgil C. Summer Nuclear Station, Unit 1 Jenkinsville, SC Surry 1, 2 PWR Surry Power Station, Units 1, 2 Surry, VA Susquehanna 1, 2 BWR Susquehanna Steam Electric Station, Units 1, 2 Berwick, PA Three Mile Island 1 PWR Three Mile Island Generating Station, Unit 1 Harrisburg, PA Turkey Point 3, 4 PWR Turkey Point Nuclear Plant, Units 3, 4 Princeton, FL Vermont Yankee BWR Vermont Yankee Nuclear Plant, Unit 1 Vernon, VT Vogtle 1, 2 PWR Vogtle Electric Generating Plant, Units 1, 2 Waynesboro, GA
 
4 Table 1.1 Nuclear Power Plants, 2010 (continued)
Plant Name Type Full Plant Name Location Waterford 3 PWR Waterford Steam Electric Station, Unit 3 Killona, LA Watts Bar 1 PWR Watts Bar Nuclear Plant, Unit 1 Spring City, TN Wolf Creek PWR Wolf Creek Generating Station, Unit 1 Burlington, KS Reactors No Longer In Commercial Operation in 2010 Big Rock Point BWR Big Rock Point Restoration Project Charlevoix, MI Dresden 1 BWR Dresden Generating Station, Unit 1 Morris, IL Haddam Neck PWR Haddam Neck Nuclear Plant Site Haddam Neck, CT Humboldt Bay BWR Humboldt Bay Power Plant, Unit 3 Eureka, CA Indian Point 1 PWR Indian Point Energy Center, Unit 1 Buchanan, NY La Crosse BWR La Crosse Boiling-Water Reactor Genoa, WI Maine Yankee PWR Maine Yankee Bath, ME Millstone 1 PWR Millstone Power Station, Unit 1 Waterford, CT Rancho Seco PWR Rancho Seco, Unit 1 Herald, CA San Onofre 1 PWR San Onofre Nuclear Generating Station, Unit 1 San Clemente, CA Three Mile Island 2 PWR Three Mile Island Nuclear Station, Unit 2 Middletown, PA Trojan PWR Trojan Nuclear Plant, Unit 1 Portland, OR Yankee-Rowe PWR Yankee Nuclear Power Station Franklin Co., MA Zion 1, 2 PWR Zion Generating Station, Units 1, 2 Warrenville, IL The NRC uses the information on radioactive releases, along with other information collected during routine inspections of each facility, to ensure NPPs are operated within regulatory requirements. One of those requirements includes maintaining radiation doses from radioactive effluents as low as is reasonably achievable (ALARA). For this summary report, only information submitted with regard to NRC reporting requirements and guidance is included. Information not related to the NRC requirements for radioactive effluents or the NRC guidance on radioactive effluents is not included in this summary report. Additionally, information on solid radioactive waste is not included in this report.
Some reactors are no longer operating. For the 2010 data shown in the tables and figures of this report, those reactors are treated as follows. The Big Rock Point, Haddam Neck, Humboldt Bay, La Crosse, Maine Yankee, Rancho Seco, Trojan, Yankee
-Rowe, Zion Unit 1, and Zion Unit 2 reactor sites are shut down and are not collocated with an operating reactor. The data from these shutdown reactors are not included in this report. The Millstone Unit 1 and Three Mile Island Unit 2 reactors are shut down and are collocated with one or more operating reactors. For these shutdown reactors, the licensee reports data for the shutdown unit separately from the operating units, and the results from these shutdown reactors are not included in this report on operating reactors. For the Dresden Unit 1, Indian Point Unit 1, and San Onofre Unit 1 reactors, which are shut down and collocated beside two operating units, the licensee reports the sum of the effluents from the shutdown unit with one or both of the operating units.
 
5 For these shutdown reactors, the effluent data are included with (and attributed to) one or more of the operating units in this report.
The historical data from all reactors, including the reactors that are no longer operating, are included in Figures 3.15 and 3.16, which depict the long
-term trend of radioactive effluents.
 
===1.3 Source===
of Data Each commercial nuclear power plant in the United States is authorized by the NRC to release small amounts of radioactive materials to the environment as specified in the licensing documents for the plant. NRC regulations require each NPP to establish and maintain a program for monitoring radioactive effluents (per Title 10 of the Code of Federal Regulations
[CFR] Part 50.36a and 10 CFR Part 50, Appendix I, Section IV.B) and to report these effluents in an Annual Radioactive Effluent Release Report (ARERR) (per 10 CFR 50.36a) (Ref. [27] ). In accordance with the regulatory framework, licensees submit their reports to the NRC in a format outlined by Regulatory Guide (RG) 1.21 (Ref. [28] ) or an equivalent format.
The information included in this document was obtained from the licensees' ARERRs. Individual licensee reports are available through the NRC Public Document Room, One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland 20852, phone 1
-800-397-4209 or 301-415-4737, and directly from the NRC's public Web site at:  http://www.nrc.gov/reactors/operating/ops
-experience/tritium/plant
-info.html. The data from these reports are also entered into a database that is maintained by the NRC. The public may access this database through an NRC Web site (http://www.reirs.com/effluent/). The data are entered into the database as they are reported by each site.
 
===1.4 Limitations===
of Data Some NPPs have more than one reactor unit located at a site. If the licensee reports data separately for each reactor unit, those data are reflected in this report as reported by the licensee. Because some licensees are allowed to operate multi
-unit sites with a common radioactive waste processing system, the NRC allows these licensees to report total effluents from the site instead of reporting the totals from each reactor unit. This complicates the task of presenting the effluent information in a manner that allows both (1) a direct comparison of one reactor unit with another, and (2) a direct comparison of each reactor unit with NRC limits and regulations.
For purposes of presentation in this report, the data are normalized on a per
-unit basis. For mult i-unit sites where the effluents are from a common radioactive waste system, the effluents are divided equally between the units in operation during that year. For example, Calvert Cliffs has two units (1 and 2) with a common radioactive waste processing system. For this report, the total effluents for Calvert Cliffs were split equally between Unit 1 and Unit 2. For other multi
-unit sites, the effluent activity is not divided equally between the units. For example, in the case of Beaver Valley, the licensee reports gaseous effluents from four sources:  Unit 1, Unit 2, a common plant vent, and a common building vent. In this case, the releases from the common vents are split equally between Unit 1 and Unit 2, and the totals for each unit then are calculated. This method of splitting the data has been applied to radionuclide activity data and radiation dose data at some multi
-unit sites. The affected NPPs and the type of data affected are listed in Table 1.2.
 
6 Although there are other methods of normalizing effluent data (e.g., on the basis of thermal or electrical power generation), the unit
-based method selected for this report (1) is most intuitive, (2)is most directly comparable with the NRC required design objectives and limiting conditionsfor operation (i.e., referred to as ALARA criteria in this report), and (3) is easily derived from t he effluent data supplied by the licensee. This approach satisfies a primary objective for this reportwhich is to allow the reader to quickly formulate reasonable comparisons between reactors and the regulatory limits. It should be noted, however, that for some multi
-unit sites, the actualcontributions from each unit might be different than the equal distributions calculated with this approach, such as when a plant is undergoing a major or extended outage.
Care has been taken to assure the information contained in this report accurately reflects the information provided by the licensees. The report may include licensees' corrections submitted to the NRC up to the time of publication. If a licensee submits amended data in accordance with NRC regulatory guidance, the NRC reserves the right to update the data in future reports. For the most current data, the reader should use the NPPs' ARERRs which are available on the NRC Web site. Table 1.2 Reactors for Which the NRC Has Normalized Data on a Unit
-Specific Basis Boiling-Water Reactors (BWRs) R D Pressurized
-Water Reactors (PWRs)
R D Browns Ferry 1, 2, 3 Beaver Valley 1, 2 Brunswick 1, 2 Calvert Cliffs 1, 2 Dresden 1, 2, 3 Catawba 1, 2 LaSalle 1, 2 Comanche Peak 1, 2 Limerick 1, 2 Cook 1, 2 Nine Mile Point 1, 2 Diablo Canyon 1, 2 Peach Bottom 2, 3 Indian Point 1, 2 Quad Cities 1, 2 McGuire 1, 2 Susquehanna 1, 2 North Anna 1, 2 Oconee 1, 2, 3 Point Beach 1, 2 Prairie Island 1, 2 San Onofre 1, 2, 3 Sequoyah 1, 2 Surry 1, 2 Notes:  R = Radionuclide Data, D = Dose Data
 
7 2    DESCRIPTION OF THE DATA 2.1  Introduction Radioactive materials may be disposed of in one of three forms:  solid, liquid, or gas. This report summarizes the disposal of radioactive materials in liquid and gaseous effluents from commercial nuclear power plants. Note:  Data on solid radioactive waste shipped from a nuclear power plant site is provided in each licensee's ARERR, and data on solid waste disposed in licensed waste disposal facilities is available from the Department of Energy Manifest Information Management System (MIMS) database at URL
:  http://mims.doe.gov/
. As described in Section 1.3, owners and operators of NPPs are required to report the radioactive effluents from their facilities to the NRC. The two basic characteristics most often used to describe radioactive effluents are the amount of radioactivity (curies or millicuries) and radiation dose (mrem). Radioactivity will be referred to as "activity" and radiation dose will simply be referred to in this document as "dose."
For this report, activity can be thought of as the amount of radioactive material present in radioactive effluents. The units for measuring activity are further described in Section 2.2. The activities of various radionuclides in radioactive effluents from NPPs are presented in Sections 3.1 through 3.5.
Although the amount of activity is an important, inherent characteristic that helps to describe radioactive effluents, it is not
-by itself-a good indicator of the potential health effects from exposure to the radiation. Health effects are dependent on many factors, such as the radionuclide, the activity of the radionuclide, the type of radiation emitted by the radionuclide, the energy of the radiation, the uptake of the radionuclide into the human body, and the metabolism of the radionuclide by the human body. To properly describe the potential health effects from exposure to radioactive materials, a combined measure of risk (i.e., dose) that accounts for all of these differences is needed.
The units for measuring dose (mrem) are described in more detail in Section 2.3. The methods and models for calculating dose from radioactive effluents are discussed in Section 2.4. The actual dose values due to radioactive effluents from NPPs are presented in Section 3.6.
Radiation is around us all of the time. The human body
-each of us
-contains some natural radioactive materials such as radioactive carbon and radioactive potassium. Natural radioactive materials are also in rocks, in soil, in the air we breathe, and in the food we eat. As a result, humans have been exposed to radiation since the dawn of man. Over the last 100 years, man has developed new radioactive materials and new machines that create additional sources of radiation. These new sources include radioactive materials used in medicine, research, industry, and nuclear power plants. Section 2.5 contains basic information on the doses received by the average member of the U.S. population each year from all sources of radiation, including commercial NPPs.
 
===2.2 Measuring===
Radioactivity in Radioactive Effluents In order to present the liquid and airborne (gaseous) effluent data in a manner that is both useful and concise, only significant radionuclides are included in the tables and figures in this report.
8 Using the guidance in Revision 2 of RG 1.21 (Ref. [28] ), licensees evaluate radionuclides that have either a significant activity or a significant dose contribution in NPP effluents. The radionuclides chosen for inclusion in this report are shown in Tables 2.1 and 2.2.
Activity is a measure of the number of atoms that transform (historically referred to as decay) in a given period of time and is reported in various units, normally either curies (Ci) or becquerels (Bq). In the United States, the traditional unit for reporting activity is the Ci. One Ci is equal to 37,000,000,000 (37 billion) radioactive atoms transforming in one second. In this document, activity will be reported as curies and millicuries (mCi). A curie is equal to one thousand millicuries. In countries that have adopted the International System of Units (or SI units), activity is reported in units of becquerels (Bq). One Bq is one atomic disintegration (transformation) or decay per second. One curie equals 37,000,000,000 becquerels, which may be expressed in scientific notation as 3.7E+10 becquerels or 3.7 x 10 10 becquerels. One curie is sometimes expressed as 37 gigabecquerels or simply 37 GBq.
One curie of cobalt
-60 and one curie of hydrogen
-3 have the same activity; however, when an atom of cobalt
-60 transforms, the atomic transformations typically produce one moderately energetic beta particle and two highly energetic gamma rays. By contrast, when an atom of hydrogen-3 (tritium) transforms, it emits a single, low
-energy beta particle. Sensitive instruments can detect and measure the transformation products that are unique to each radionuclide.
Cobalt and hydrogen are just two examples of elements that can be radioactive. Other examples are shown in Tables 2.1 and 2.2.
The reporting of radionuclides in liquid and gaseous wastes is commonly grouped into categories (Ref. [28] ). These categories are described in Tables 2.1 and 2.2 as noble gases, iodines, particulates, tritium, carbon, and gross alpha activity. Each category contains one or more radionuclides. Beginning with the 2010 annual effluent summary report, a new radionuclide category has been added for carbon
-14 (C-14) in gaseous effluents.
Table 2.1 Radionuclides in Gaseous Effluents Gaseous Effluent Category Common Radionuclides Significant Radionuclides Fission and Activation Gases (sometimes referred to as Noble Gases)
Krypton (85, 85m, 87, 88)
Xenon (131, 131m, 133, 133m, 135, 135m)
Argon (41)
Kr-85 Xe-133 Xe-135 All (Sections 3.2, 3.3, and 3.6)
Iodines Iodine (131, 132, 133, 134, 135)
I-131All (Section 3.6)Particulates Cobalt (58, 60)
Cesium (134, 137)
Chromium (51)
Manganese (54)
Niobium (95)
Co-58 Co-60 Cs-134 Cs-137 All (Section 3.6)
Tritium Hydrogen (3)
H-3Carbon Carbon (14)
C-14Gross Alpha Total alpha activity Not Presented in this Report The radionuclides listed in this report are the most significant radionuclides discharged from a site. For example, although Table 2.1 lists 11 radionuclides in the category called "fission and 9 activation gases," only the 3 most significant radionuclides (Kr-85, Xe-133, and Xe
-135) were selected for inclusion in Table 3.1 and Figure 3.1 for noble gas radionuclides. These three were chosen because these radionuclides are representative of the overall effluent releases, and because as their activities increase, the activities of other fission and activation gases typically increase as well. Conversely, if the activities of these three radionuclides are very low, the activities of other fission and activation gases tend to be low also. All noble gas radionuclides are included in Sections 3.2 Short
-Term Trend in Gaseous Effluents, 3.3 Long
-Term Trend in Gaseous Effluents, and 3.6 Radiation Doses from Gaseous and Liquid Effluents.
Table 2.2 Radionuclides in Liquid Effluents  Liquid Effluent Category Common Radionuclides Significant Radionuclides Mixed Fission and Activation Products Iron (55) Cobalt (58, 60)
Cesium (134, 137)
Chromium (51)
Manganese (54)
Zirconium (95)
Niobium (95)
Iodine (131, 133, 135)
Fe-55 Co-58 Co-60 Cs-134 Cs-137 I-131 All (Sections 3.4, 3.5 and 3.6)
Tritium Hydrogen (3)
H-3 Dissolved and Entrained Noble Gases Krypton (85, 85m, 87, 88)
Xenon (131, 133, 133m, 135, 135m)
Not Presented in this Report Gross Alpha Total alpha activity Not Presented in this Report Much information about the operation of plant systems can be obtained from the radionuclides present in radioactive effluents. Additionally, the ratios of the activities of radionuclides can provide insights into fuel integrity, radioactive waste system operation, and general radioactive waste handling practices at a site. The reader who is interested in seeing the activities of all radionuclides released from any particular NPP is encouraged to review the detailed, site
-specific ARERRs provided on the NRC Web site.
Laboratory instruments can identify which radionuclides are present in radioactive effluents. The instruments can also measure the activities (curies or becquerels) of the radionuclides. As a result, many discussions about radioactive effluents focus on the curies (or becquerels) released. Although activity measures the rate of atomic transformations, it does not provide a direct measure of the potential health effects from exposure to radionuclides. When discussing potential health effects, the concept of dose is used. Radiation dose is discussed in more detail in the following paragraphs.
2.3  Dose Units and Limits The traditional unit for reporting radiation dose in the United States is the rem. Small exposures are often reported as millirem (mrem) or as fractions of a mrem. One thousand mrem equals one rem. Other countries report radiation dose in units of sieverts (Sv). One sievert equals 100 rem. One millirem equals 0.00001 sievert or 0.01 millisievert (mSv). The number 0.00001 can be represented in scientific notation as 1 x 10
-5 or 1E-05.
10 Radioactive effluents discharged from NPPs are controlled by regulations. NRC regulations (10 CFR 20.1301) specify that the annual dose to individual members of the public does not exceed 100 mrem (1 millisievert) (Ref. [29] ). In addition, the Environmental Protection Agency has established environmental radiation protection standards for nuclear power operations that the annual dose to any member of the public does not exceed 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.
Typically, the median dose from radioactive effluents to members of the public is so low (usually less than 1 mrem in a year) that the radionuclides and the dose in the environment cannot be measured directly. As a result, hypothetical doses are typically calculated based on the measurements at the point of release from the plant.
 
===2.4 Radiation===
Dose to the Public Licensees are required by 10 CFR 50.36a to establish Technical Specifications which require that operating procedures for the control of effluents be established and followed, and that the radioactive waste system be maintained and used to keep average annual effluent releases at small percentages of the public dose limits (Ref. [29] ). The Technical Specifications establish the licensee's Radioactive Effluent Controls Program, which is used to ensure plant operations keep radioactive effluent releases ALARA and meet the ALARA criteria in 10 CFR Part 50, Appendix I (Ref. [27] ). The ALARA criteria are established as a small fraction (typically about 3 percent) of the NRC safety limits for dose to members of the public.
The licensee is required to keep levels of radioactive material in effluents ALARA, even under unusual operating conditions. The ALARA criteria are design objectives and limiting conditions for operation, not safety limits. If releases ever exceed design objectives, the licensee is required to take corrective actions to ensure the plant systems are functioning as designed and to report this information to the NRC.
The Radioactive Effluent Controls Program requires licensees to determine the public dose from the release of radioactive effluents. The methods of determining dose are described in the licensee's Offsite Dose Calculation Manual (ODCM). The ODCMs are available through the NRC Public Document Room. Any changes to the ODCM are reported to the NRC and are provided in the licensee's ARERR.
The ODCM contains both the offsite dose calculation methodologies and a radiological environmental monitoring program. Those dose calculations are based on:
actual measurements of the radioactive materials discharged to the unrestricted area;models of how radionuclides are dispersed and diluted in the environment;models of how radionuclides are incorporated into animals, plants, and soil; andbiokinetic models of human uptake and metabolism of radioactive materials.The dose calculation models are designed to calculate the dose either to a real individual closest to the NPP or conservatively to a hypothetical individual exposed to the highest concentrations of radioactive materials from radioactive effluents. This person is often referred to as the maximum exposed individual (or maximum exposed hypothetical individual). The parameters and assumptions used in these dose calculations typically include conservative assumptions that tend to overestimate the dose. As a result, the actual doses received by real 11 individuals are often much less than those calculated. Guidance for these calculations is provided in NRC RG 1.109 (Ref. [30] ). The calculated annual organ doses and annual total body doses are included in Section 3.6. Note that there are other types of doses calculated by each facility. All the doses calculated by a licensee are reported in the NPPs' ARERRs. Summaries of the calculated doses are provided in Tables 3.19 through 3.22, and are shown graphically in Figures 3.17 through 3.22.
 
===2.5 Other===
Sources of Radiation Dose to the U.S. Population Doses from NPP effluents were discussed in the previous sections. This section discusses the doses that the average American typically receives each year from naturally occurring background radiation and all other sources of radiation. With the information presented in this section, the reader can compare the doses received from NPP effluents with the doses received from natural, medical, and other sources of radiation. This comparison provides some context to the concept of radiation dose effects.
In March 2009, the National Council on Radiation Protection and Measurements (NCRP) published Report No. 160 as an update to the 1987 NCRP Report No. 93, "Ionizing Radiation Exposure of the Population of the United States" (Refs. [32] , [33] ). Report No. 160 describes the doses to the U.S. population from all sources of ionizing radiation for 2006, the most recent data available at the time the NCRP report was written. The NCRP report also includes information on the variability of those doses from one individual to another. The NCRP estimated that the average person in the United States receives about 620 mrem of radiation dose each year from all sources; i.e., both
-natural background radiation and man
-made radiation sources. NCRP Report No. 160 describes each of the sources of radiation that contribute to this dose, including:
naturally occurring sources (natural background) such as cosmic radiation from space, terrestrial radiation from radioactive materials in the earth, and naturally occurring radioactive materials in the food people eat and in the air people breathe; medical sources from diagnosis and treatment of health disorders using radioactive pharmaceuticals and radiatio n-producing equipment; consumer products (such as household smoke detectors);
industrial processes, security devices, educational tools, and research activities; and exposures of workers that result from their occupations.
Figure 2.1 is a pie chart showing the relative contributions of these sources of radiation to the dose received by the average American person. Larger contributors to dose are represented by proportionally larger slices of the pie. Doses to the public from NPPs are included in the industrial category; while doses to workers from nuclear power generation are included in the category of occupational dose.
Doses to the public due to effluents from NPPs are less than 0.1 percent (one
-tenth of one percent) of what the average person receives each year from all sources of radiation. Doses to workers from occupational exposures, including those received from work at NPPs, also are less than 0.1 percent of the dose to members of the public from all sources.
 
12 Figure 2.1 Sources of Radiation Exposure to the U.S. Population The chart above shows the contribution of various sources of exposure to the total collective dose and the total dose per individual in the U.S. population for 2006. Values have been rounded to the nearest 1%, except for those <1% [less than 1%]. Credit:  Modification to image courtesy of National Council on Radiation Protection and Measurements.
 
13 3    EFFLUENT DATA
 
===3.1 Radioactive===
Materials in Liquid and Gaseous Effluents The activity of the most significant radionuclides discharged in liquid and gaseous effluents for 2010 are shown in Tables 3.1 through 3.14. The data from these tables are illustrated graphically in Figures 3.1 through 3.14. The tables and figures are organized by the two types of reactors used in the United States:  boiling
-water reactors (BWRs) and pressurized
-water reactors (PWRs). The tables and figures are further subdivided into liquid and gaseous effluents. Finally, the data are subdivided into the radionuclide categories (common radionuclides and significant radionuclides) as listed in Tables 2.1 and 2.2. These tables and figures allow a detailed comparison of each reactor's effluents with other reactors of the same type. As described in Section 2.2, only the most significant radionuclides are included in the tables and graphs in Section 3.1. However, the total radiation dose from all radionuclides discharged from the reactors is included in Section 3.6, Radiation Doses from Liquid and Gaseous Effluents.
For comparison between plants, median values are included in some tables and figures. The median is the midpoint of the data such that half of the power plants will have greater activity and dose values than the median plant and half of the power plants will have values equal to or lower than the median plant. The median is a method of estimating a central or typical value while avoiding bias caused by extremely high or low values in the data set. All operating nuclear plant units are included when calculating the medians, even those sites for which no measurable release of a particular radionuclide is reported.
All licensees are required to have and use sensitive radioactive effluent measurement capabilities.
Many times, radioactive effluent releases are so low in concentration that a release cannot be detected. If no value is listed for a particular radionuclide in a table, it is because the licensee reported that the radionuclide was not detected at that NPP. Blanks in data fields are generally used instead of zeros in order to make it easier for the reader to quickly identify the positive values. On the following pages, the tables are presented first. In general, the information in each table is organized in descending order of activity. The facilities discharging the most activity are shown near the top of each table, while the facilities discharging the least activity are shown toward the bottom of each table. The median is shown in the middle of each data set. Tables with information on more than one radionuclide are listed by the total activity per plant, in descending order. The figures are shown following the tables. In general, the information is organized in each figure in descending order of activity. The facilities discharging the most activity of the selected radionuclides are shown near the top of the figure, while the facilities discharging the least activity of the radionuclides are shown toward the bottom of each figure. The median is shown in the middle of each data set.
Figures with information on more than one radionuclide are listed by the total activity per plant, in descending order of activity. Figures with information on more than one radionuclide are shown in multi
-colored graphs. For example, Figure 3.1 is a multi
-colored graph. In figures with 14 multi-colored graphs, the total activity of the selected radionuclides is shown on the right side of the graph, while the relative contribution of each radionuclide to the total activity is shown on the left side of the graph. The relative contributions of each nuclide are shown
-in multiple colors
-as a percent of the total activity. A multi
-colored graph allows the reader to compare not only the activity but also the relative amounts of significant radionuclides released by the various facilities. Multi
-colored graphs contain two separate scales of measurement. The total activity is shown on a logarithmic scale, while the radionuclide percentages of the total activity are shown on a linear scale.
15 Table 3.1 BWR Gaseous Releases
- Fission and Activation Gases, 2010 Shown in Descending Order of Total Activity BWR Facility Kr-85 (Ci) Xe-133 (Ci) Xe-135 (Ci) Total (Ci) Monticello 3.66E+02 8.46E+01 4.50E+02 Grand Gulf 1.40E+02 1.24E+02 2.65E+02 Oyster Creek 1.09E+00 2.19E+02 2.20E+02 LaSalle 1  1.74E+02 1.12E+00 1.75E+02 LaSalle 2  1.74E+02 1.12E+00 1.75E+02 Nine Mile Point 2 4.87E-01 8.62E+01 2.08E+01 1.07E+02 River Bend 5.18E+00 6.03E+01 6.55E+01 FitzPatrick 4.60E+01 6.68E-01 4.66E+01 Brunswick 1 5.55E+00 3.33E+01 3.89E+01 Brunswick 2 5.55E+00 3.33E+01 3.89E+01 Peach Bottom 2 7.95E+00 2.21E+01 3.00E+01 Peach Bottom 3 7.95E+00 2.21E+01 3.00E+01 Hatch 2  5.37E+00 1.20E+01 1.73E+01 Hope Creek 5.81E+00 1.07E+01 1.65E+01 Limerick 1 8.98E-01 5.64E+00 6.18E+00 1.27E+01 Limerick 2 8.98E-01 5.64E+00 6.18E+00 1.27E+01 Hatch 1  2.97E+00 9.20E+00 1.22E+01 BWR Median Release 2.97E+00 1.59E+00 1.14E+01 Quad Cities 1 1.97E+00 9.41E+00 1.14E+01 Quad Cities 2 1.97E+00 9.41E+00 1.14E+01 Dresden 2  4.78E+00 1.56E+00 6.34E+00 Dresden 3  4.78E+00 1.56E+00 6.34E+00 Pilgrim  2.82E+00 1.93E+00 4.75E+00 Duane Arnold 1.59E+00 1.59E+00 Clinton  1.11E+00 1.11E+00 Perry  6.05E-03 3.76E-01 3.82E-01 Fermi 2  1.57E-01 1.20E-01 2.77E-01 Cooper  1.03E-01 1.03E-01 Susquehanna 1 4.89E-04 4.89E-04 Susquehanna 2 4.89E-04 4.89E-04 Nine Mile Point 1 3.09E-05 3.09E-05 Browns Ferry 1 Browns Ferry 2 Browns Ferry 3 Columbia    Vermont Yankee
 
16 Table 3.2 BWR Gaseous Releases - Iodine, 2010 Shown in Descending Order of Activity BWR Facility I-131 (Ci)BWR Facility I-131 (Ci)Brunswick 1 1.95E-02 BWR Median Release 9.80E-04 Brunswick 2 1.95E-02 Peach Bottom 2 9.80E-04 LaSalle 1 1.56E-02 Peach Bottom 3 9.80E-04 LaSalle 2 1.56E-02 Hatch 1 8.48E-04 Monticello 1.53E-02 Hatch 2 8.28E-04 Oyster Creek 8.60E-03 Nine Mile Point 1 5.73E-04 River Bend 5.77E-03 Dresden 2 4.86E-04 Nine Mile Point 2 4.98E-03 Dresden 3 4.86E-04 Hope Creek 4.59E-03 FitzPatrick 3.46E-04 Quad Cities 1 3.94E-03 Perry 2.12E-04 Quad Cities 2 3.94E-03 Columbia 1.47E-04 Grand Gulf 2.86E-03 Cooper 9.07E-05 Browns Ferry 1 2.51E-03 Vermont Yankee 6.41E-05 Browns Ferry 2 2.51E-03 Clinton 2.00E-05 Browns Ferry 3 2.51E-03 Duane Arnold 1.97E-05 Pilgrim 1.94E-03 Limerick 1 Fermi 2 1.75E-03 Limerick 2 Susquehanna 1 Susquehanna 2
 
17 Table 3.3 BWR Gaseous Releases
- Particulates, 2010 Shown in Descending Order of Total Activity BWR Facility Co-58 (Ci)  Co-60 (Ci)  Cs-134 (Ci)  Cs-137 (Ci)  Total (Ci)
Oyster Creek 1.62E-03 4.81E-03  1.67E-04 6.60E-03 Peach Bottom 2 3.29E-07 2.48E-03  9.14E-05 2.57E-03 Peach Bottom 3 3.29E-07 2.48E-03  9.14E-05 2.57E-03 Nine Mile Point 2 1.79E-04 1.84E-03  2.02E-03 Nine Mile Point 1 2.39E-05 1.48E-03  3.92E-06 1.51E-03 LaSalle 1 6.55E-05 6.09E-04  2.31E-09 6.75E-04 LaSalle 2 6.55E-05 6.09E-04  2.31E-09 6.75E-04 Monticello 3.65E-04  1.81E-04 5.46E-04 Fermi 2 2.44E-04 2.54E-04  4.99E-04 Quad Cities 1  3.64E-04  1.15E-05 3.75E-04 Quad Cities 2 3.64E-04  1.15E-05 3.75E-04 Brunswick 1 7.73E-05 2.72E-04  4.38E-06 3.53E-04 Brunswick 2 7.73E-05 2.72E-04  4.38E-06 3.53E-04 River Bend 3.20E-04  3.20E-04 Dresden 2 1.17E-05 2.25E-04  9.80E-07 2.38E-04 Dresden 3 1.17E-05 2.25E-04  9.80E-07 2.38E-04 Duane Arnold 2.64E-05 1.40E-04  3.02E-05 1.96E-04 BWR Median Release 3.29E-07 1.40E-04  8.04E-07 1.62E-04 Cooper 7.05E-07 1.60E-04  8.04E-07 1.62E-04 Columbia  9.06E-05  9.06E-05 Browns Ferry 1 1.21E-05 6.41E-05  8.54E-07 7.71E-05 Browns Ferry 2 1.21E-05 6.41E-05  8.54E-07 7.71E-05 Browns Ferry 3 1.21E-05 6.41E-05  8.54E-07 7.71E-05 Vermont Yankee 2.87E-05 5.92E-08 1.80E-06 3.06E-05 Clinton  2.11E-05  2.11E-05 Susquehanna 1 2.10E-06 1.00E-05  1.21E-05 Susquehanna 2 2.10E-06 1.00E-05  1.21E-05 Hope Creek 1.11E-05  1.11E-05 Grand Gulf 3.09E-08 5.07E-06  9.03E-07 6.01E-06 FitzPatrick 5.07E-06  5.07E-06 Hatch 1 2.51E-08 2.06E-06  7.57E-07 2.84E-06 Limerick 1 1.77E-06  1.77E-06 Limerick 2 1.77E-06  1.77E-06 Hatch 2 2.51E-08 2.02E-07  8.03E-07 1.03E-06 Perry      Pilgrim 18 Table 3.4 BWR Gaseous Releases - Tritium, 2010 Shown in Descending Order of Activity BWR Facility H-3 (Ci)BWR Facility H-3 (Ci)Hatch 1 1.91E+02 BWR Median Release 2.70E+01 Fermi 2 1.18E+02 Duane Arnold 2.70E+01 Browns Ferry 1 1.04E+02 Hatch 2 2.45E+01 Browns Ferry 2 1.04E+02 Grand Gulf 2.34E+01 Browns Ferry 3 1.04E+02 LaSalle 1 2.19E+01 Brunswick 1 9.87E+01 LaSalle 2 2.19E+01 Brunswick 2 9.87E+01 Limerick 1 2.15E+01 Nine Mile Point 2 8.79E+01 Limerick 2 2.15E+01 Hope Creek 7.32E+01 Monticello 2.02E+01 Oyster Creek 6.33E+01 Peach Bottom 2 1.96E+01 Pilgrim 4.34E+01 Peach Bottom 3 1.96E+01 Quad Cities 1 3.97E+01 River Bend 1.89E+01 Quad Cities 2 3.97E+01 Clinton 1.87E+01 FitzPatrick 3.62E+01 Susquehanna 1 1.55E+01 Nine Mile Point 1 3.58E+01 Susquehanna 2 1.55E+01 Columbia 3.28E+01 Perry 8.30E+00 Cooper 2.74E+01 Dresden 2 6.68E+00 Dresden 3 6.68E+00 Vermont Yankee 2.16E+00 19 Table 3.5 BWR Gaseous Releases
- Carbon-14, 2010 Shown in Descending Order of Activity BWR Facility C-14 (Ci)  BWR Facility C-14 (Ci) Columbia 1.78E+01  BWR Median Release 1.17E+01 Peach Bottom 2 1.78E+01  Browns Ferry 1 1.17E+01 Peach Bottom 3 1.78E+01  Browns Ferry 2 1.17E+01 Perry 1.71E+01  Browns Ferry 3 1.17E+01 Nine Mile Point 2 1.57E+01  Cooper 1.16E+01 Clinton 1.48E+01  River Bend 1.10E+01 Fermi 2 1.42E+01  Hope Creek 1.08E+01 Hatch 1 1.42E+01  Brunswick 1 1.06E+01 Hatch 2 1.42E+01  Brunswick 2 1.06E+01 Quad Cities 1 1.40E+01  Oyster Creek 1.00E+01 Quad Cities 2 1.40E+01  Grand Gulf 9.49E+00 Dresden 2 1.39E+01  Limerick 1 9.40E+00 Dresden 3 1.39E+01  Limerick 2 9.40E+00 Susquehanna 1 1.23E+01  FitzPatrick 9.28E+00 Susquehanna 2 1.23E+01  LaSalle 1 9.19E+00    LaSalle 2 9.19E+00    Nine Mile Point 1 9.16E+00    Pilgrim 8.55E+00    Duane Arnold 8.17E+00    Monticello 6.50E+00    Vermont Yankee 6.00E+00 20 Table 3.6 PWR Gaseous Releases - Fission and Activation Gases, 2010 Shown in Descending Order of Total Activity PWR Facility Kr-85 (Ci) Xe-133 (Ci) Xe-135 (Ci) Total (Ci)
Vogtle 2 5.43E-01 2.02E+02 4.41E+00 2.07E+02 Callaway 1.74E+00 1.58E+02 1.85E+00 1.62E+02 Davis-Besse 5.01E+01 7.44E+01 8.94E-02 1.25E+02 Calvert Cliffs 1 6.40E+01 3.65E+01 5.75E-01 1.01E+02 Calvert Cliffs 2 6.40E+01 3.65E+01 5.75E-01 1.01E+02 San Onofre 2 2.68E+00 5.80E+01 1.16E-01 6.08E+01 San Onofre 3 2.68E+00 5.80E+01 1.16E-01 6.08E+01 North Anna 1 2.85E+00 4.05E+01 2.42E-01 4.36E+01 North Anna 2 2.85E+00 4.05E+01 2.42E-01 4.36E+01 Palisades 1.90E+00 3.02E+01 1.01E+01 4.21E+01 Millstone 3 2.16E+00 2.50E+01 9.02E-01 2.80E+01 South Texas 2 1.96E-03 2.70E+01 2.70E+01 Oconee 1 3.11E+00 1.25E+01 7.71E-02 1.57E+01 Oconee 2 3.11E+00 1.25E+01 7.71E-02 1.57E+01 Oconee 3 3.11E+00 1.25E+01 7.71E-02 1.57E+01 St. Lucie 2 1.04E+01 1.38E+00 2.09E-01 1.19E+01 Arkansas 2 5.09E+00 0.00E+00 2.91E+00 8.00E+00 Three Mile Island 1 2.60E+00 3.25E+00 2.50E-03 5.86E+00 Farley 1 1.90E+00 3.81E+00 5.71E+00 Watts Bar 1 3.75E-06 2.69E+00 1.08E+00 3.76E+00 Cook 1 1.71E+00 8.60E-01 8.04E-03 2.58E+00 Cook 2 1.71E+00 8.60E-01 8.04E-03 2.58E+00 Millstone 2 2.11E+00 2.50E-02 2.24E-03 2.14E+00 South Texas 1 1.78E+00 1.78E+00 Comanche Peak 1 1.73E+00 1.08E-02 1.34E-03 1.74E+00 Comanche Peak 2 1.73E+00 1.08E-02 1.34E-03 1.74E+00 Indian Point 2 1.47E+00 6.10E-02 1.53E+00 Ft. Calhoun 3.28E-04 1.07E+00 5.06E-02 1.12E+00 St. Lucie 1 6.50E-01 2.72E-01 9.22E-01 Ginna 8.60E-01 1.29E-02 8.72E-01 Turkey Point 3 1.40E-01 5.27E-01 4.86E-02 7.16E-01 Turkey Point 4 1.40E-01 4.63E-01 4.86E-02 6.52E-01 Sequoyah 1 8.80E-03 4.94E-01 5.36E-02 5.56E-01 Sequoyah 2 8.80E-03 4.94E-01 5.36E-02 5.56E-01 21 Table 3.6 PWR Gaseous Releases
- Fission and Activation Gases , 2010 (continued)
Shown in Descending Order of Total Activity PWR Facility Kr-85 (Ci) Xe-133 (Ci) Xe-135 (Ci) Total (Ci)
PWR Median Release 2.67E-03 4.19E-01 8.04E-03 5.15E-01 Braidwood 1 5.02E-01 1.25E-02 5.15E-01 Palo Verde 1 4.89E-01 1.07E-03 4.90E-01 Braidwood 2 4.69E-01 1.25E-02 4.81E-01 Robinson 2 1.08E-01 3.25E-01 1.47E-04 4.33E-01 Catawba 1 2.43E-03 4.01E-01 2.44E-02 4.27E-01 Catawba 2 2.43E-03 4.01E-01 2.44E-02 4.27E-01 Beaver Valley 1 4.19E-01 4.43E-03 4.23E-01 Beaver Valley 2 4.19E-01 4.43E-03 4.23E-01 Byron 2  3.71E-01 1.36E-03 3.72E-01 Byron 1  3.55E-01 1.37E-03 3.56E-01 Surry 1  2.29E-01 3.50E-02 2.64E-01 Surry 2  2.29E-01 3.50E-02 2.64E-01 Palo Verde 2 2.22E-01 6.94E-03 2.29E-01 Harris  1.75E-01  1.75E-01 Point Beach 1 1.41E-01 3.07E-02 1.72E-01 Point Beach 2 1.41E-01 3.07E-02 1.72E-01 Prairie Island 1 1.38E-01 8.05E-05 8.25E-06 1.38E-01 Prairie Island 2 1.38E-01 8.05E-05 8.25E-06 1.38E-01 Salem 1  1.26E-01 6.48E-03 1.32E-01 Diablo Canyon 1 2.93E-02 7.97E-02  1.09E-01 Diablo Canyon 2 2.93E-02 7.97E-02  1.09E-01 Wolf Creek 5.67E-04 9.87E-02  9.93E-02 Arkansas 1 6.92E-02 2.49E-04  6.94E-02 McGuire 1 2.67E-03 5.33E-02 6.26E-03 6.22E-02 McGuire 2 2.67E-03 5.33E-02 6.26E-03 6.22E-02 Salem 2  4.57E-02 1.87E-03 4.76E-02 Farley 2  3.37E-02 5.27E-05 3.37E-02 Indian Point 3 9.70E-03 2.16E-02 3.15E-06 3.13E-02 Vogtle 1  6.76E-03  6.76E-03 Palo Verde 3 3.79E-03  3.79E-03 Seabrook  6.57E-04 2.11E-03 2.77E-03 Crystal River 3 Kewaunee    Summer    Waterford 3
 
22 Table 3.7 PWR Gaseous Releases - Iodine, 2010 Shown in Descending Order of Activity PWR Facility I-131 (Ci)PWR Facility I-131 (Ci)Palisades 5.22E-03PWR Median Release 1.57E-06Millstone 3 2.38E-03 Ginna 1.57E-06 Calvert Cliffs 1 2.24E-03 Robinson 2 1.35E-06 Calvert Cliffs 2 2.24E-03 Salem 2 9.46E-07 Davis-Besse 9.93E-04 St. Lucie 1 8.52E-07 Cook 1 4.93E-04 Watts Bar 1 5.45E-07 Cook 2 4.93E-04 Harris 4.66E-07 Vogtle 2 4.41E-04 Farley 2 3.39E-08 North Anna 1 4.07E-04 South Texas 1 8.03E-09 North Anna 2 4.07E-04 Arkansas 1 South Texas 2 1.96E-04 Arkansas 2 San Onofre 2 1.73E-04 Beaver Valley 1 San Onofre 3 1.73E-04 Beaver Valley 2 Oconee 1 1.50E-04 Catawba 1 Oconee 2 1.50E-04 Catawba 2 Oconee 3 1.50E-04 Comanche Peak 1 Farley 1 1.49E-04 Comanche Peak 2 Point Beach 1 7.70E-05 Crystal River 3 Point Beach 2 7.70E-05 Diablo Canyon 1 Millstone 2 7.22E-05 Diablo Canyon 2 Callaway 7.08E-05 Ft. Calhoun St. Lucie 2 5.88E-05 Indian Point 2 Braidwood 2 3.34E-05 Indian Point 3 Braidwood 1 3.23E-05 Kewaunee Palo Verde 1 1.69E-05 Palo Verde 2 Palo Verde 3 1.36E-05 Prairie Island 1 Vogtle 1 7.13E-06 Prairie Island 2 Waterford 3 5.81E-06 Salem 1 Turkey Point 3 4.55E-06 Seabrook Byron 1 4.42E-06 Sequoyah 1 Turkey Point 4 3.89E-06 Sequoyah 2 Byron 2 2.56E-06 Summer McGuire 1 1.76E-06 Surry 1 McGuire 2 1.76E-06 Surry 2 Three Mile Island 1 Wolf Creek
 
23 Table 3.8 PWR Gaseous Releases
- Particulates, 2010 Shown in Descending Order of Total Activity PWR Facility Co-58 (Ci)  Co-60 (Ci)  Cs-134 (Ci)
Cs-137 (Ci)
Total (Ci)
South Texas 2 3.73E-04 6.86E-05  4.42E-04 Palo Verde 3 2.90E-04 1.64E-05  1.20E-07 3.07E-04 San Onofre 2 1.51E-04 8.00E-05  3.24E-06 2.34E-04 San Onofre 3 1.51E-04 8.00E-05  3.24E-06 2.34E-04 Beaver Valley 1 1.52E-04 1.74E-05  2.74E-05 1.97E-04 Palo Verde 1 1.77E-04 4.67E-06  8.10E-07 1.82E-04 Millstone 3 9.52E-05 6.18E-06 8.35E-06 4.71E-06 1.14E-04 Salem 1 7.42E-05  2.24E-06 7.64E-05 Byron 2 3.04E-07 5.56E-05  5.59E-05 Harris 2.34E-05 8.39E-06  3.18E-05 North Anna 1 1.39E-06 1.96E-05  5.89E-06 2.69E-05 North Anna 2 1.39E-06 1.96E-05  5.89E-06 2.69E-05 Byron 1  2.27E-05  2.27E-05 Callaway  1.91E-05  1.91E-05 Catawba 1  1.47E-05  1.47E-05 Catawba 2  1.47E-05  1.47E-05 Beaver Valley 2 3.66E-06 2.34E-06  7.95E-06 1.39E-05 Waterford 3 1.33E-06 4.13E-07 5.43E-06 6.70E-06 1.39E-05 Watts Bar 1 1.36E-05    1.36E-05 McGuire 1 9.81E-06 2.25E-06  1.21E-05 McGuire 2 9.81E-06 2.25E-06  1.21E-05 St. Lucie 2 2.51E-06  1.53E-08 9.57E-06 1.21E-05 Surry 1 1.00E-05    1.00E-05 Surry 2 1.00E-05    1.00E-05 Prairie Island 1 3.06E-06  5.60E-06 8.66E-06 Prairie Island 2 3.06E-06  5.60E-06 8.66E-06 Cook 1  8.15E-06  8.15E-06 Cook 2  8.15E-06  8.15E-06 St. Lucie 1 3.38E-06 1.78E-06  2.44E-06 7.61E-06 Calvert Cliffs 1 5.81E-06    5.81E-06 Calvert Cliffs 2 5.81E-06    5.81E-06 Diablo Canyon 1 5.35E-06    5.35E-06 Diablo Canyon 2 5.35E-06    5.35E-06 Indian Point 2 3.59E-06 3.59E-06 24 Table 3.8 PWR Gaseous Releases
- Selected Particulates, 2010 (continued)
Shown in Descending Order of Total Activity PWR Facility Co-58 (Ci) Co-60 (Ci) Cs-134 (Ci) Cs-137 (Ci) Total (Ci)
PWR Median Release 1.12E-07 1.63E-06 Palisades 1.53E-06 8.61E-08 1.09E-08 1.63E-06 Farley 1 1.02E-06 4.82E-07 4.27E-08 1.54E-06 South Texas 1 1.52E-06 4.32E-09 1.52E-06 Point Beach 1 1.50E-06 9.60E-09 1.51E-06 Point Beach 2 1.50E-06 9.60E-09 1.51E-06 Kewaunee 9.70E-07 1.10E-07 3.90E-07 1.47E-06 Palo Verde 2 1.23E-06 1.23E-06 Three Mile Island 1 1.00E-06 1.00E-06 Turkey Point 3 6.41E-07 1.57E-08 6.57E-07 Oconee 1 5.77E-07 5.77E-07 Oconee 2 5.77E-07 5.77E-07 Oconee 3 5.77E-07 5.77E-07 Crystal River 3 1.08E-07 3.51E-07 4.59E-07 Farley 2 1.12E-07 1.08E-07 2.20E-07 Robinson 2 6.70E-08 1.97E-08 1.06E-08 9.73E-08 Arkansas 1 1.07E-08 1.07E-08 Arkansas 2 Braidwood 1 Braidwood 2 Comanche Peak 1 Comanche Peak 2 Davis-Besse Ft. Calhoun Ginna Indian Point 3 Millstone 2 Salem 2 Seabrook Sequoyah 1 Sequoyah 2 Summer Turkey Point 4 Vogtle 1 Vogtle 2 Wolf Creek
 
25 Table 3.9 PWR Gaseous Releases
- Tritium, 2010 Shown in Descending Order of Activity PWR Facility H-3 (Ci)  PWR Facility H-3 (Ci) Palo Verde 3 1.19E+03  PWR Median Release 3.17E+01 Palo Verde 1 8.79E+02  Point Beach 1 3.17E+01 Palo Verde 2 4.74E+02  Point Beach 2 3.17E+01 Salem 1 3.84E+02  Watts Bar 1 2.53E+01 Harris 2.75E+02  Arkansas 1 2.45E+01 Braidwood 1 2.58E+02  Surry 1 2.31E+01 Catawba 1 1.36E+02  Surry 2 2.31E+01 Catawba 2 1.36E+02  Palisades 2.30E+01 Three Mile Island 1 1.32E+02  Oconee 1 2.24E+01 Salem 2 1.05E+02  Oconee 2 2.24E+01 Davis-Besse 9.73E+01  Oconee 3 2.24E+01 Cook 1 9.30E+01  Comanche Peak 1 2.16E+01 Cook 2 9.30E+01  Comanche Peak 2 2.16E+01 Braidwood 2 8.55E+01  Byron 1 1.99E+01 Diablo Canyon 1 7.66E+01  Indian Point 3 1.98E+01 Diablo Canyon 2 7.66E+01  Vogtle 1 1.93E+01 Seabrook 7.37E+01  Arkansas 2 1.76E+01 Farley 1 6.68E+01  Kewaunee 1.67E+01 McGuire 1 6.21E+01  Vogtle 2 1.64E+01 McGuire 2 6.21E+01  Indian Point 2 1.43E+01 Waterford 3 5.96E+01  Millstone 2 1.17E+01 Ginna 5.65E+01  St. Lucie 1 1.14E+01 Wolf Creek 5.36E+01  Prairie Island 1 1.01E+01 Millstone 3 5.10E+01  Prairie Island 2 1.01E+01 Farley 2 4.47E+01  Crystal River 3 9.68E+00 Sequoyah 1 4.44E+01  Beaver Valley 1 8.30E+00 Sequoyah 2 4.44E+01  Robinson 2 5.85E+00 Byron 2 4.17E+01  Calvert Cliffs 1 2.81E+00 San Onofre 2 4.13E+01  Calvert Cliffs 2 2.81E+00 San Onofre 3 4.13E+01  Ft. Calhoun 2.50E+00 South Texas 2 3.98E+01  North Anna 1 2.39E+00 South Texas 1 3.36E+01  North Anna 2 2.39E+00 Callaway 3.19E+01  Beaver Valley 2 2.33E+00    Turkey Point 3 2.20E+00    St. Lucie 2 6.63E-01    Turkey Point 4 4.87E-01    Summer 6.32E-04 26 Table 3.10 PWR Gaseous Releases - Carbon-14, 2010 Shown in Descending Order of Activity PWR Facility C-14 (Ci)PWR Facility C-14 (Ci)Comanche Peak 1 1.27E+01PWR Median Release 8.76E+00Comanche Peak 2 1.27E+01 Arkansas 1 8.76E+00 Millstone 3 1.22E+01 Cook 1 8.70E+00 Seabrook 1.21E+01 Cook 2 8.70E+00 Vogtle 1 1.21E+01 North Anna 1 8.49E+00 Vogtle 2 1.21E+01 North Anna 2 8.49E+00 Diablo Canyon 2 1.18E+01 Three Mile Island 1 8.40E+00 Salem 2 1.14E+01 St. Lucie 1 8.04E+00 Callaway 1.11E+01 Harris 8.00E+00 Indian Point 3 1.11E+01 Palisades 7.70E+00 Beaver Valley 1 1.10E+01 Oconee 1 7.49E+00 Beaver Valley 2 1.10E+01 Oconee 2 7.49E+00 San Onofre 2 1.10E+01 Oconee 3 7.49E+00 San Onofre 3 1.10E+01 Calvert Cliffs 2 7.40E+00 Arkansas 2 1.09E+01 Davis-Besse 7.32E+00 Millstone 2 1.09E+01 South Texas 1 7.29E+00 Sequoyah 1 1.09E+01 Turkey Point 4 7.28E+00 Sequoyah 2 1.09E+01 South Texas 2 7.27E+00 Wolf Creek 1.07E+01 Calvert Cliffs 1 6.80E+00 Watts Bar 1 1.06E+01 Ginna 6.80E+00 Diablo Canyon 1 1.05E+01 Turkey Point 3 6.57E+00 Catawba 1 1.02E+01 Kewaunee 6.12E+00 Catawba 2 1.02E+01 Prairie Island 1 5.37E+00 McGuire 1 1.01E+01 Prairie Island 2 5.37E+00 McGuire 2 1.01E+01 Point Beach 1 5.24E+00 Salem 1 1.01E+01 Point Beach 2 5.24E+00 St. Lucie 2 1.01E+01 Robinson 2 5.03E+00 Waterford 3 1.01E+01 Braidwood 1 4.45E+00 Summer 1.00E+01 Braidwood 2 4.45E+00 Farley 1 9.28E+00 Byron 1 4.45E+00 Farley 2 9.28E+00 Byron 2 4.45E+00 Indian Point 2 9.20E+00 Palo Verde 1 2.72E+00 Surry 1 9.14E+00 Palo Verde 2 2.72E+00 Surry 2 9.14E+00 Palo Verde 3 2.72E+00 Ft. Calhoun 2.36E+00 Crystal River 3 Note: During the entire year of 2010, Crystal River Unit 3 was in a cold shutdown mode.
 
27 Table 3.11 BWR Liquid Releases
- Fission and Activation Products, 2010 Shown in Descending Order of Total Activity BWR Facility Co-58  (Ci) Co-60  (Ci) Cs-134 (CI) Cs-137 (Ci) Fe-55  (Ci) I-131  (Ci) Total    (Ci) Hope Creek 1.19E-03 3.84E-02 2.30E-06 2.53E-06  3.25E-08 3.96E-02 Susquehanna 1 8.92E-03 2.53E-02  3.28E-04  3.45E-02 Susquehanna 2 8.92E-03 2.53E-02  3.28E-04  3.45E-02 Peach Bottom 2 8.56E-03 5.72E-03 8.92E-07 2.51E-05 1.86E-02  3.29E-02 Peach Bottom 3 8.56E-03 5.72E-03 8.92E-07 2.51E-05 1.86E-02  3.29E-02 Pilgrim 2.37E-04 8.06E-03  7.07E-05 5.93E-03  1.43E-02 Perry 7.71E-05 8.12E-03    8.20E-03 Grand Gulf 2.92E-04 2.81E-03  8.24E-05 2.22E-03 3.60E-06 5.40E-03 Cooper  1.59E-03 1.02E-04 1.69E-03 1.70E-04  3.55E-03 Brunswick 1 1.56E-05 8.59E-04 6.43E-06 2.05E-04  3.76E-04 1.46E-03 Brunswick 2 1.56E-05 8.59E-04 6.43E-06 2.05E-04  3.76E-04 1.46E-03 Browns Ferry 1 9.26E-05 6.39E-04 2.03E-05 4.10E-04 2.95E-05  1.19E-03 Browns Ferry 2 9.26E-05 6.39E-04 2.03E-05 4.10E-04 2.95E-05  1.19E-03 Browns Ferry 3 9.26E-05 6.39E-04 2.03E-05 4.10E-04 2.95E-05  1.19E-03 Hatch 1 1.29E-05 2.42E-04  6.56E-04 1.35E-04 3.47E-07 1.05E-03 Limerick 1 2.07E-05 3.88E-04  2.01E-05 4.08E-04 4.52E-07 8.37E-04 Limerick 2 2.07E-05 3.88E-04  2.01E-05 4.08E-04 4.52E-07 8.37E-04 BWR Median Release  2.42E-04    5.14E-04 River Bend 5.14E-04    5.14E-04 Hatch 2 2.23E-05 1.01E-04  2.48E-05 9.85E-05 2.96E-05 2.77E-04 Nine Mile Point 2 1.71E-04    1.71E-04 Dresden 2  2.17E-05    2.17E-05 Dresden 3  2.17E-05    2.17E-05 Nine Mile Point 1 5.66E-07    5.66E-07 Clinton        Columbia        Duane Arnold Fermi 2        FitzPatrick LaSalle 1        LaSalle 2        Monticello Oyster Creek Quad Cities 1 Quad Cities 2 Vermont Yankee
 
28 Table 3.12 BWR Liquid Releases - Tritium, 2010 Shown in Descending Order of Activity BWR Facility H-3 (Ci)BWR Facility H-3 (Ci)Brunswick 1 1.50E+02 BWR Median Release 3.91E+00 Brunswick 2 1.50E+02 Limerick 1 3.91E+00 Grand Gulf 5.70E+01 Limerick 2 3.91E+00 Peach Bottom 2 5.58E+01 Vermont Yankee 3.84E+00 Peach Bottom 3 5.58E+01 Browns Ferry 1 3.63E+00 River Bend 4.36E+01 Browns Ferry 2 3.63E+00 Hope Creek 3.95E+01 Browns Ferry 3 3.63E+00 Susquehanna 1 2.87E+01 Pilgrim 2.48E+00 Susquehanna 2 2.87E+01 Oyster Creek 2.66E-01 Hatch 1 2.11E+01 FitzPatrick 1.99E-01 Perry 1.78E+01 Nine Mile Point 1 1.32E-02 Quad Cities 1 9.06E+00 Dresden 2 2.60E-03 Quad Cities 2 9.06E+00 Dresden 3 2.60E-03 Hatch 2 5.70E+00 Duane Arnold 8.55E-04 Nine Mile Point 2 4.82E+00 Clinton Cooper 4.01E+00 Columbia Fermi 2 LaSalle 1 LaSalle 2 Monticello
 
29 Table 3.13 PWR Liquid Releases
- Fission and Activation Products, 2010 Shown in Descending Order of Total Activity PWR Facility Co-58 (Ci) Co-60 (Ci) Cs-134 (Ci) Cs-137 (Ci) Fe-55 (Ci) I-131 (Ci) Total (Ci) Prairie Island 1 4.30E-02 4.39E-03  1.40E-05 7.35E-02 3.04E-06 1.21E-01 Prairie Island 2 4.30E-02 4.39E-03  1.40E-05 7.35E-02 3.04E-06 1.21E-01 Calvert Cliffs 1 3.77E-02 2.49E-03 1.47E-03 2.39E-03 1.31E-02 1.30E-04 5.73E-02 Calvert Cliffs 2 3.77E-02 2.49E-03 1.47E-03 2.39E-03 1.31E-02 1.30E-04 5.73E-02 Millstone 3 4.68E-03 1.17E-02 8.13E-03 5.50E-03 1.78E-02 1.81E-03 4.97E-02 Palisades 2.21E-02 1.38E-02  2.08E-04 1.13E-02 6.99E-04 4.81E-02 Watts Bar 1 5.47E-03 5.49E-03 5.45E-04 2.90E-03 2.18E-02 9.65E-03 4.58E-02 Beaver Valley 1 2.17E-02 4.23E-03 1.27E-05 1.89E-03 1.33E-02 3.90E-06 4.11E-02 Beaver Valley 2 2.17E-02 4.23E-03 1.27E-05 1.89E-03 1.33E-02 3.90E-06 4.11E-02 Salem 1 2.51E-02 4.14E-03 6.21E-04 1.01E-02  4.00E-02 Arkansas 1 2.23E-02 4.85E-03 3.86E-04 1.29E-03 7.22E-03 2.64E-04 3.63E-02 Davis-Besse 1.51E-02 5.52E-04 2.26E-04 3.59E-04 1.50E-02 1.06E-04 3.13E-02 Point Beach 1 2.14E-02 1.98E-03  5.84E-06 2.46E-03 6.05E-06 2.59E-02 Point Beach 2 2.14E-02 1.98E-03  5.84E-06 2.46E-03 6.05E-06 2.59E-02 Vogtle 1 5.02E-03 2.04E-03 6.05E-05 4.14E-04 1.47E-02 4.38E-04 2.27E-02 Indian Point 2 1.00E-02 6.50E-03  6.02E-03  2.25E-02 St. Lucie 1 3.52E-03 1.98E-03 6.14E-06 1.78E-04 1.43E-02 1.10E-05 2.00E-02 St. Lucie 2 3.52E-03 1.98E-03 6.14E-06 1.78E-04 1.43E-02 1.10E-05 2.00E-02 Salem 2 1.67E-02 1.17E-03 4.24E-06 8.19E-05  6.88E-06 1.79E-02 Farley 2 6.33E-03 7.24E-03  5.53E-04 3.04E-03  1.72E-02 McGuire 1 1.03E-02 4.49E-03 2.01E-04 1.63E-03  1.67E-02 McGuire 2 1.03E-02 4.49E-03 2.01E-04 1.63E-03  1.67E-02 Callaway 4.60E-03 2.77E-03 6.04E-04 3.27E-03  3.71E-03 1.50E-02 Catawba 1 5.33E-03 9.34E-03  3.09E-04  1.50E-02 Catawba 2 5.33E-03 9.34E-03  3.09E-04  1.50E-02 Robinson 2 9.95E-03 3.31E-03 2.01E-06 1.90E-05 4.33E-05  1.33E-02 Oconee 1 1.26E-02 2.23E-04 5.53E-05 1.81E-04  7.73E-06 1.31E-02 Oconee 2 1.26E-02 2.23E-04 5.53E-05 1.81E-04  7.73E-06 1.31E-02 Oconee 3 1.26E-02 2.23E-04 5.53E-05 1.81E-04  7.73E-06 1.31E-02 Seabrook 8.99E-03 9.38E-04  3.06E-05 3.01E-03  1.30E-02 Farley 1 7.13E-03 4.18E-03  7.82E-05 1.56E-03 1.62E-07 1.29E-02 Vogtle 2 1.71E-03 1.14E-03  1.03E-04 8.49E-03 1.53E-04 1.16E-02 Sequoyah 1 8.76E-03 1.75E-03 4.40E-08 2.98E-06 4.73E-04  1.10E-02 Sequoyah 2 8.76E-03 1.75E-03 4.40E-08 2.98E-06 4.73E-04  1.10E-02 30 Table 3.13 PWR Liquid Releases
- Fission and Activation Products, 2010 (continued)
Shown in Descending Order of Total Activity PWR Facility Co-58 (Ci) Co-60 (Ci) Cs-134 (Ci) Cs-137 (Ci) Fe-55 (Ci) I-131 (Ci) Total  (Ci) PWR Median Release 4.60E-03 1.98E-03 6.14E-06 1.81E-04 1.08E-03 1.03E-02 Summer 1.69E-03 3.84E-03 8.31E-05 3.76E-04 4.29E-03 1.03E-02 Diablo Canyon 1 2.51E-03 3.39E-03 6.96E-05 2.08E-04 3.50E-03 9.68E-03 Diablo Canyon 2 2.51E-03 3.39E-03 6.96E-05 2.08E-04 3.50E-03 9.68E-03 South Texas 2 2.47E-03 2.48E-03 1.09E-05 3.28E-05 4.02E-03 3.17E-04 9.33E-03 Millstone 2 1.24E-03 3.28E-03 9.85E-05 4.22E-04 3.55E-03 1.89E-05 8.61E-03 Kewaunee 5.24E-04 2.30E-03 5.65E-03 8.47E-03 Braidwood 1 3.71E-03 4.53E-03 2.58E-05 4.57E-05 8.31E-03 Braidwood 2 3.71E-03 4.53E-03 2.58E-05 4.57E-05 8.31E-03 Comanche Peak 1 7.07E-03 6.92E-04 1.02E-06 1.52E-04 7.91E-03 Comanche Peak 2 7.07E-03 6.92E-04 1.02E-06 1.52E-04 7.91E-03 Wolf Creek 5.93E-03 5.98E-04 1.01E-06 4.70E-05 1.17E-03 7.75E-03 South Texas 1 6.54E-04 3.35E-03 3.63E-04 3.37E-03 7.73E-03 Turkey Point 3 4.45E-03 1.06E-03 2.88E-04 5.24E-04 1.21E-03 4.10E-06 7.53E-03 Turkey Point 4 4.45E-03 1.06E-03 2.88E-04 5.24E-04 1.21E-03 4.10E-06 7.53E-03 Arkansas 2 5.54E-03 5.87E-04 6.78E-05 1.30E-04 1.19E-03 7.51E-03 Harris 3.11E-03 1.83E-03 2.05E-05 1.08E-03 6.03E-03 Waterford 3 4.94E-04 3.13E-04 1.08E-05 1.40E-05 5.07E-03 5.91E-03 Byron 1 3.48E-03 7.64E-04 4.25E-03 Byron 2 3.48E-03 7.64E-04 4.25E-03 Surry 1 6.33E-04 1.89E-03 1.15E-03 9.90E-06 3.68E-03 Surry 2 6.33E-04 1.89E-03 1.15E-03 9.90E-06 3.68E-03 North Anna 1 1.79E-03 1.59E-03 4.23E-05 1.74E-04 4.66E-05 3.64E-03 North Anna 2 1.79E-03 1.59E-03 4.23E-05 1.74E-04 4.66E-05 3.64E-03 San Onofre 2 8.60E-05 4.82E-04 2.87E-03 3.43E-03 San Onofre 3 8.60E-05 4.82E-04 2.87E-03 3.43E-03 Crystal River 3 2.52E-04 2.52E-03 1.53E-05 4.69E-04 3.25E-03 Indian Point 3 3.02E-04 8.94E-04 1.30E-04 9.52E-04 2.28E-03 Ft. Calhoun 1.25E-04 1.55E-04 4.52E-05 9.97E-04 5.92E-04 1.91E-03 Cook 1 3.57E-04 9.87E-04 6.15E-07 1.60E-05 1.36E-03 Cook 2 3.57E-04 9.87E-04 6.15E-07 1.60E-05 1.36E-03 Ginna 1.29E-03 1.94E-08 1.29E-03 Three Mile Island 1 3.19E-05 6.34E-05 5.46E-05 1.50E-04 Palo Verde 1 Palo Verde 2 Palo Verde 3
 
31 Table 3.14 PWR Liquid Releases
- Tritium, 2010 Shown in Descending Order of Activity PWR Facility H-3 (Ci)  PWR Facility H-3 (Ci) Watts Bar 1 1.70E+03  PWR Median Release 4.93E+02 South Texas 2 1.35E+03  Surry 1 4.93E+02 Callaway 1.16E+03  Surry 2 4.93E+02 Wolf Creek 1.11E+03  Davis-Besse 4.71E+02 Diablo Canyon 1 1.09E+03  Catawba 1 4.61E+02 Diablo Canyon 2 1.09E+03  Catawba 2 4.61E+02 Byron 1 1.02E+03  Robinson 2 4.37E+02 Byron 2 1.02E+03  Summer 4.37E+02 Cook 1 9.72E+02  San Onofre 2 4.34E+02 Cook 2 9.72E+02  San Onofre 3 4.34E+02 Salem 1 9.63E+02  Millstone 2 4.27E+02 Millstone 3 8.93E+02  Farley 2 4.21E+02 South Texas 1 8.26E+02  Arkansas 1 3.99E+02 Sequoyah 1 7.73E+02  Braidwood 1 3.95E+02 Sequoyah 2 7.73E+02  Braidwood 2 3.95E+02 Indian Point 2 7.32E+02  Seabrook 3.87E+02 Salem 2 7.31E+02  Harris 3.82E+02 Beaver Valley 1 6.91E+02  Oconee 1 3.65E+02 Beaver Valley 2 6.91E+02  Oconee 2 3.65E+02 Palisades 6.74E+02  Oconee 3 3.65E+02 Comanche Peak 1 6.67E+02  Prairie Island 1 2.89E+02 Comanche Peak 2 6.67E+02  Prairie Island 2 2.89E+02 Indian Point 3 6.58E+02  Point Beach 1 2.80E+02 North Anna 1 6.36E+02  Point Beach 2 2.80E+02 North Anna 2 6.36E+02  Vogtle 2 2.75E+02 Turkey Point 3 6.32E+02  Ginna 2.57E+02 Turkey Point 4 6.32E+02  Ft. Calhoun 1.78E+02 Vogtle 1 6.14E+02  Kewaunee 1.63E+02 Farley 1 6.05E+02  Waterford 3 1.43E+02 McGuire 1 6.04E+02  St. Lucie 1 1.36E+02 McGuire 2 6.04E+02  St. Lucie 2 1.36E+02 Calvert Cliffs 1 5.85E+02  Three Mile Island 1 1.29E+02 Calvert Cliffs 2 5.85E+02  Crystal River 3 2.12E+01 Arkansas 2 5.68E+02  Palo Verde 1    Palo Verde 2 Palo Verde 3
 
32 *BWR average radionuclide mix and median activity released.
Figure 3.1 BWR Gaseous Releases - Fission and Activation Gases 0%25%50%75%100%Vermont YankeeColumbiaBrowns Ferry 3Browns Ferry 2 Browns Ferry 1Nine Mile Point 1Susquehanna 2 Susquehanna 1CooperFermi 2PerryClintonDuane ArnoldPilgrimDresden 3 Dresden 2Quad Cities 2 Quad Cities 1BWR *Hatch 1Limerick 2 Limerick 1Hope CreekHatch 2Peach Bottom 3 Peach Bottom 2Brunswick 2 Brunswick 1FitzPatrickRiver BendNine Mile Point 2LaSalle 2 LaSalle 1Oyster CreekGrand GulfMonticelloRadionuclide Distribution1E-051E-041E-031E-021E-011E+001E+011E+021E+03Activity Released in 2010 (Ci)
Kr-85 Xe-133 Xe-135Total Activity Released Kr-85 Xe-133 Xe-135Total Activity Released 33  Figure 3.2 BWR Gaseous Releases
- Iodine  1E-71E-61E-51E-41E-31E-21E-1Susquehanna 2Susquehanna 1Limerick 2Limerick 1Duane ArnoldClintonVermont YankeeCooperColumbiaPerryFitzPatrickDresden 3Dresden 2Nine Mile Point 1Hatch 2Hatch 1Peach Bottom 3Peach Bottom 2 BWR Median ReleaseFermi 2PilgrimBrowns Ferry 3Browns Ferry 2Browns Ferry 1Grand GulfQuad Cities 2Quad Cities 1Hope CreekNine Mile Point 2River BendOyster CreekMonticelloLaSalle 2LaSalle 1Brunswick 2Brunswick 1Activity Released in 2010 (Ci)
I-131 34 *BWR average radionuclide mix and median activity released.
Figure 3.3 BWR Gaseous Releases - Particulates 0%25%50%75%100%PilgrimPerryHatch 2Limerick 2Limerick 1Hatch 1FitzPatrickGrand GulfHope CreekSusquehanna 2 Susquehanna 1ClintonVermont YankeeBrowns Ferry 3 Browns Ferry 2 Browns Ferry 1ColumbiaCooper BWR *Duane ArnoldDresden 3 Dresden 2River BendBrunswick 2 Brunswick 1Quad Cities 2 Quad Cities 1Fermi 2MonticelloLaSalle 2 LaSalle 1Nine Mile Point 1 Nine Mile Point 2Peach Bottom 3 Peach Bottom 2Oyster CreekRadionuclide Distribution1E-91E-81E-71E-61E-51E-41E-31E-21E-1Activity Released in 2010 (Ci)
Co-60 Co-58 Cs-134 Cs-137Total Activity Released 35  Figure 3.4 BWR Gaseous Releases
- Tritium  1 101001,000Vermont YankeeDresden 3Dresden 2PerrySusquehanna 2Susquehanna 1ClintonRiver BendPeach Bottom 3Peach Bottom 2MonticelloLimerick 2Limerick 1LaSalle 2LaSalle 1Grand GulfHatch 2Duane ArnoldBWR Median ReleaseCooperColumbiaNine Mile Point 1FitzPatrickQuad Cities 2Quad Cities 1PilgrimOyster CreekHope CreekNine Mile Point 2Brunswick 2Brunswick 1Browns Ferry 3Browns Ferry 2Browns Ferry 1Fermi 2Hatch 1Activity Released in 2010 (Ci)
H-3 36 Figure 3.5 BWR Gaseous Releases - Carbon-14 1 10100Vermont YankeeMonticelloDuane ArnoldPilgrimNine Mile Point 1LaSalle 2LaSalle 1FitzPatrickLimerick 2 Limerick 1Grand GulfOyster CreekBrunswick 2 Brunswick 1Hope CreekRiver BendCooperBrowns Ferry 3 Browns Ferry 2 Browns Ferry 1BWR Median ReleaseSusquehanna 2 Susquehanna 1Dresden 3 Dresden 2Quad Cities 2 Quad Cities 1Hatch 2 Hatch 1Fermi 2ClintonNine Mile Point 2PerryPeach Bottom 3 Peach Bottom 2ColumbiaActivity Released in 2010 (Ci)C-14 37
* PWR average radionuclide mix and median activity released.
Figure 3.6 PWR Gaseous Releases - Fission and Activation Gases 0%25%50%75%100%PWR *Sequoyah 2Sequoyah 1Turkey Point 4Turkey Point 3GinnaSt. Lucie 1Ft. CalhounIndian Point 2Comanche Peak 2Comanche Peak 1South Texas 1Millstone 2Cook 2Cook 1Watts Bar 1Farley 1Three Mile Island 1Arkansas 2St. Lucie 2Oconee 3Oconee 2Oconee 1South Texas 2Millstone 3PalisadesNorth Anna 2North Anna 1San Onofre 3San Onofre 2Calvert Cliffs 2Calvert Cliffs 1Davis-BesseCallawayVogtle 2Radionuclide Distribution1E-51E-41E-31E-21E-11E+01E+11E+21E+3Activity Released in 2010 (Ci)
Kr-85 Xe-133 Xe-135Total Activity Released 38 *PWR average radionuclide mix and median activity released.Figure 3.6 PWR Gaseous Releases
- Fission and Activation Gases (continued) 0%25%50%75%100%Waterford 3SummerKewauneeCrystal River 3SeabrookPalo Verde 3Vogtle 1Indian Point 3Farley 2Salem 2McGuire 2McGuire 1Arkansas 1Wolf CreekDiablo Canyon 2 Diablo Canyon 1Salem 1Prairie Island 2 Prairie Island 1Point Beach 2 Point Beach 1HarrisPalo Verde 2Surry 2 Surry 1Byron 1 Byron 2Beaver Valley 2 Beaver Valley 1Catawba 2 Catawba 1Robinson 2Braidwood 2Palo Verde 1Braidwood 1PWR *Radionuclide Distribution1E-51E-41E-31E-21E-11E+01E+11E+21E+3Activity Released in 2010 (Ci)
Kr-85 Xe-133 Xe-135Total Activity Released 39  Note:  See Table 3.7 for list of nuclear power plants with no releases of iodine reported.
Figure 3.7 PWR Gaseous Releases
- Iodine  1E-91E-81E-71E-61E-51E-41E-31E-21E-1South Texas 1Farley 2HarrisWatts Bar 1St. Lucie 1Salem 2Robinson 2Ginna PWR Median ReleaseMcGuire 2McGuire 1Byron 2Turkey Point 4Byron 1Turkey Point 3Waterford 3Vogtle 1Palo Verde 3Palo Verde 1Braidwood 1Braidwood 2St. Lucie 2CallawayMillstone 2Point Beach 2Point Beach 1Farley 1Oconee 3Oconee 2Oconee 1San Onofre 3San Onofre 2South Texas 2North Anna 2North Anna 1Vogtle 2Cook 2Cook 1Davis-BesseCalvert Cliffs 2Calvert Cliffs 1Millstone 3PalisadesActivity Released in 2010 (Ci)
I-131 40 Note:  See Table 3.8 for list of nuclear power plants with no releases of selected particulates reported.
*PWR average radionuclide mix and median activity released.Figure 3.8 PWR Gaseous Releases - Particulates 0%25%50%75%100%Arkansas 1Robinson 2Farley 2Crystal River 3Oconee 3Oconee 2 Oconee 1Turkey Point 3Three Mile Island 1Palo Verde 2KewauneePoint Beach 2 Point Beach 1South Texas 1Farley 1PalisadesPWR *Indian Point 2Diablo Canyon 2 Diablo Canyon 1Calvert Cliffs 2 Calvert Cliffs 1St. Lucie 1Cook 2 Cook 1Prairie Island 2 Prairie Island 1Surry 2 Surry 1McGuire 2 McGuire 1St. Lucie 2Watts Bar 1 Waterford 3Beaver Valley 2Catawba 2 Catawba 1CallawayByron 1North Anna 2 North Anna 1HarrisByron 2Salem 1Millstone 3Palo Verde 1Beaver Valley 1San Onofre 3 San Onofre 2Palo Verde 3South Texas 2Radionuclide Distribution1E-081E-071E-061E-051E-041E-03Activity Released in 2010 (Ci)
Co-60 Co-58 Cs-134 Cs-137Total Activity Released 41  Figure 3.9 PWR Gaseous Releases
- Tritium  1E-041E-031E-021E-011E+001E+011E+021E+031E+04PWR Median ReleaseCallawaySouth Texas 1South Texas 2San Onofre 3San Onofre 2Byron 2Sequoyah 2Sequoyah 1Farley 2Millstone 3Wolf CreekGinnaWaterford 3McGuire 2McGuire 1Farley 1SeabrookDiablo Canyon 2Diablo Canyon 1Braidwood 2Cook 2Cook 1Davis-BesseSalem 2Three Mile Island 1Catawba 2Catawba 1Braidwood 1HarrisSalem 1Palo Verde 2Palo Verde 1Palo Verde 3Activity Released in 2010 (Ci)
H-3 42 Figure 3.9 PWR Gaseous Releases
- Tritium (continued) 1E-041E-031E-021E-011E+001E+011E+021E+031E+04SummerTurkey Point 4St. Lucie 2Turkey Point 3Beaver Valley 2North Anna 2North Anna 1Ft. CalhounCalvert Cliffs 2 Calvert Cliffs 1Robinson 2Beaver Valley 1Crystal River 3Prairie Island 2 Prairie Island 1St. Lucie 1Millstone 2Indian Point 2Vogtle 2KewauneeArkansas 2Vogtle 1Indian Point 3Byron 1Comanche Peak 2 Comanche Peak 1Oconee 3 Oconee 2 Oconee 1 PalisadesSurry 2 Surry 1Arkansas 1Watts Bar 1Point Beach 2 Point Beach 1PWR Median ReleaseActivity Released in 2010 (Ci)H-3 43  Figure 3.10 PWR Gaseous Releases
- Carbon-14  1 10100 PWR Median ReleaseSurry 2Surry 1Indian Point 2Farley 2Farley 1SummerWaterford 3St. Lucie 2Salem 1McGuire 2McGuire 1Catawba 2Catawba 1Diablo Canyon 1Watts Bar 1Wolf CreekSequoyah 2Sequoyah 1Millstone 2Arkansas 2San Onofre 3San Onofre 2Beaver Valley 2Beaver Valley 1Indian Point 3CallawaySalem 2Diablo Canyon 2Vogtle 2Vogtle 1SeabrookMillstone 3Comanche Peak 2Comanche Peak 1Activity Released in 2010 (Ci)
C-14 44 Note: During the entire year of 2010, Crystal River Unit 3 was in a cold shutdown mode.
Figure 3.10 PWR Gaseous Releases
- Carbon-14 (continued) 1 10100Crystal River 3Ft. CalhounPalo Verde 3Palo Verde 2 Palo Verde 1Byron 2 Byron 1Braidwood 2 Braidwood 1Robinson 2Point Beach 2 Point Beach 1Prairie Island 2 Prairie Island 1KewauneeTurkey Point 3GinnaCalvert Cliffs 1South Texas 2Turkey Point 4South Texas 1Davis-BesseCalvert Cliffs 2Oconee 3 Oconee 2 Oconee 1 PalisadesHarrisSt. Lucie 1Three Mile Island 1North Anna 2 North Anna 1Cook 2 Cook 1Arkansas 1 PWR Median ReleaseActivity Released in 2010 (Ci)C-14 45
* BWR average radionuclide mix and median activity released.
Figure 3.11 BWR Liquid Releases
- Fission and Activation Products 0%25%50%75%100%Vermont YankeeQuad Cities 2Quad Cities 1Oyster CreekMonticelloLaSalle 2LaSalle 1FitzPatrickFermi 2Duane ArnoldColumbiaClintonNine Mile Point 1Dresden 3Dresden 2Nine Mile Point 2Hatch 2River BendBWR *Limerick 2Limerick 1Hatch 1Browns Ferry 3Browns Ferry 2Browns Ferry 1Brunswick 2Brunswick 1CooperGrand GulfPerryPilgrimPeach Bottom 3Peach Bottom 2Susquehanna 2Susquehanna 1Hope CreekRadionuclide Distribution1E-71E-61E-51E-41E-31E-21E-1Activity Released in 2010 (Ci)
Fe-55 Cs-137 Co-58 Co-60 Cs-134 I-131Total Activity Released 46 Figure 3.12 BWR Liquid Releases - Tritium 1E-51E-41E-31E-21E-11E+01E+11E+21E+31E+4MonticelloLaSalle 2LaSalle 1Fermi 2ColumbiaClintonDuane ArnoldDresden 3 Dresden 2Nine Mile Point 1FitzPatrickOyster CreekPilgrimBrowns Ferry 3 Browns Ferry 2 Browns Ferry 1Vermont YankeeLimerick 2 Limerick 1BWR Median ReleaseCooperNine Mile Point 2Hatch 2Quad Cities 2 Quad Cities 1PerryHatch 1Susquehanna 2 Susquehanna 1Hope CreekRiver BendPeach Bottom 3 Peach Bottom 2Grand GulfBrunswick 2 Brunswick 1Activity Released in 2010 (Ci)H-3 47
* PWR average radionuclide mix and median activity released.
Figure 3.13 PWR Liquid Releases
- Fission and Activation Products 0%25%50%75%100%PWR *Sequoyah 2Sequoyah 1Vogtle 2Farley 1SeabrookOconee 3Oconee 2Oconee 1Robinson 2Catawba 2Catawba 1CallawayMcGuire 2McGuire 1Farley 2Salem 2St. Lucie 2St. Lucie 1Indian Point 2Vogtle 1Point Beach 2Point Beach 1Davis-BesseArkansas 1Salem 1Beaver Valley 2Beaver Valley 1Watts Bar 1PalisadesMillstone 3Calvert Cliffs 2Calvert Cliffs 1Prairie Island 2Prairie Island 1Radionuclide Distribution1E-41E-31E-21E-11E+0Activity Released in 2010 (Ci)
Co-58 Co-60 Cs-134 Cs-137Fe-55 I-131Total Activity Released 48 *PWR average radionuclide mix and median activity released.Figure 3.13 PWR Liquid Releases
- Fission and Activation Products (continued) 0%25%50%75%100%Palo Verde 3Palo Verde 2 Palo Verde 1Three Mile Island 1GinnaCook 2 Cook 1Ft. CalhounIndian Point 3Crystal River 3San Onofre 3 San Onofre 2North Anna 2 North Anna 1Surry 2 Surry 1Byron 2 Byron 1Waterford 3HarrisArkansas 2Turkey Point 4 Turkey Point 3South Texas 1Wolf CreekComanche Peak 2 Comanche Peak 1Braidwood 2 Braidwood 1KewauneeMillstone 2South Texas 2Diablo Canyon 2 Diablo Canyon 1SummerPWR *Radionuclide Distribution1E-41E-31E-21E-11E+0Activity Released in 2010 (Ci)
Co-58 Co-60 Cs-134 Cs-137Fe-55I-131Total Activity Released 49  Figure 3.14 PWR Liquid Releases
- Tritium  101001,00010,000PWR Median ReleaseArkansas 2Calvert Cliffs 2Calvert Cliffs 1McGuire 2McGuire 1Farley 1Vogtle 1Turkey Point 4Turkey Point 3North Anna 2North Anna 1Indian Point 3Comanche Peak 2Comanche Peak 1PalisadesBeaver Valley 2Beaver Valley 1Salem 2Indian Point 2Sequoyah 2Sequoyah 1South Texas 1Millstone 3Salem 1Cook 2Cook 1Byron 2Byron 1Diablo Canyon 2Diablo Canyon 1Wolf CreekCallawaySouth Texas 2Watts Bar 1Activity Released in 2010 (Ci)
H-3 50 Figure 3.14 PWR Liquid Releases
- Tritium (continued) 101001,00010,000Palo Verde 3Palo Verde 2 Palo Verde 1Crystal River 3Three Mile Island 1St. Lucie 2 St. Lucie 1Waterford 3KewauneeFt. CalhounGinnaVogtle 2Point Beach 2 Point Beach 1Prairie Island 2 Prairie Island 1Oconee 3 Oconee 2 Oconee 1HarrisSeabrookBraidwood 2 Braidwood 1Arkansas 1Farley 2Millstone 2San Onofre 3 San Onofre 2SummerRobinson 2Catawba 2 Catawba 1Davis-BesseSurry 2 Surry 1PWR Median ReleaseActivity Released in 2010 (Ci)H-3 51 3.2  Short-Term Trend in Gaseous Effluents In the previous section, only the significant radionuclides from each of the categories in Table 2.1 were shown in the tables and figures. Although particular focus on the significant radionuclides yields useful information, many less
-significant radionuclides are typically present in radioactive gaseous effluents. This section provides the reader with information to gain a better understanding of the total releases of gaseous effluents from a facility.
A long-standing, historical measure of the licensee's ability to control gaseous effluents is based on the activities of noble gases discharged in gaseous effluents. This category of radionuclides
-noble gases
-is described in Table 2.1. The noble gases category includes all radionuclides in gaseous effluents except iodines, particulates, carbon
-14 (C-14), and tritium. Although the doses from noble gases are generally small, the activity and doses from other radionuclides (such as iodines and mixed fission and activation products) will generally only be elevated if the activity of noble gases is elevated. As a result, a plant's total noble gas release is sometimes used as a primary indicator of fuel integrity and the quality of a plant's gaseous radiological effluent control program. The amount of C
-14 released as a gaseous effluent is directly related to the amount of power produced rather than to the quality of a plant's effluent control program.
Tables 3.15 and 3.16 show the short
-term trend in the total activity of all noble gases in gaseous effluents for the last 4 years for BWRs and PWRs, respectively. The facilities are listed in alphabetical order for ease of reference when searching for a site. Table 3.15 shows that the discharges of noble gases from all BWRs in 2010 ranged from a low of 0 curies to a maximum of 1,484 curies, resulting in a median value of 41.1 curies. Table 3.16 shows that the discharge of noble gases from all PWRs in 2010 ranged from a low of 0 curies to a maximum of 216.6 curies, resulting in a median value of 1.2 curies.
Fluctuations in the short
-term data are within the range of expected values, based on power production and the increasing sensitivity of measurement techniques. For example, a plant that has an extremely sensitive measurement capability is capable of detecting extremely low concentrations of noble gas. Due to the amount of air discharged from the ventilation system, the plant is likely to report a certain amount of noble gas released. Meanwhile, a plant with a slightly less sensitive measurement capability may not be detecting the same extremely low concentration of noble gas and thus may report a low or zero amount of noble gas discharged. Overall, the nuclear power industry has steadily reduced the amount of radioactivity discharged into the environment (see Section 3.3 for the long
-term trend in gaseous effluents)
.
52 Table 3.15 Short-Term Trend in Noble Gases in Gaseous Effluents, BWRs, Curies (Ci)
Shown in Alphabetical Order Facility 2007 2008 2009 2010 Browns Ferry 1 0.0 0.0 0.0 0.0 Browns Ferry 2 0.0 0.0 0.0 0.0 Browns Ferry 3 0.0 0.0 0.0 0.0 Brunswick 1 743.5 846.0 348.5 224.5 Brunswick 2 743.5 846.0 348.5 224.5 Clinton 0.0 0.0 0.0 1.1 Columbia 60.3 91.4 90.0 186.3 Cooper 27.9 14.3 54.8 1.5 Dresden 2 157.0 82.1 30.7 25.3 Dresden 3 157.0 82.1 30.7 25.3 Duane Arnold 27.3 11.4 11.4 2.5 Fermi 2 0.0 15.4 14.4 17.5 FitzPatrick 623.2 188.9 53.0 101.8 Grand Gulf 622.4 443.3 182.0 518.9 Hatch 1 0.0 0.0 2.9 45.9 Hatch 2 0.0 0.0 2.9 75.2 Hope Creek 34.3 1.2 22.8 41.1 LaSalle 1 1,314.5 791.0 2,003.0 957.5 LaSalle 2 1,314.5 791.0 2,003.0 957.5 Limerick 1 24.3 36.7 14.1 27.1 Limerick 2 24.3 36.7 14.1 27.1 Monticello 198.6 1,059.0 1,503.0 1,484.0 Nine Mile Point 1 37.2 0.3 9.8 0.0 Nine Mile Point 2 412.6 359.4 447.7 406.3 Oyster Creek 13.4 7.6 15.4 398.9 Peach Bottom 2 269.0 303.5 511.0 386.5 Peach Bottom 3 269.0 303.5 511.0 386.5 Perry 27.4 2.4 1.2 2.6 Pilgrim 1,553.0 310.5 115.1 27.7 Quad Cities 1 73.0 85.6 85.8 200.8 Quad Cities 2 73.0 85.6 85.8 200.8 River Bend 343.4 204.2 99.2 120.5 Susquehanna 1 36.8 0.0 0.0 1.2 Susquehanna 2 36.8 0.0 0.0 1.2 Vermont Yankee 0.0 0.0 0.0 0.0 MEDIAN 37.2 36.7 30.7 41.1 53 Table 3.16 Short-Term Trend in Noble Gases in Gaseous Effluents, PWRs, Curies (Ci)
Shown in Alphabetical Order Facility 2007 2008 2009 2010 Arkansas 1 8.6 21.9 8.7 0.1 Arkansas 2 7.4 74.1 320.7 30.1 Beaver Valley 1 0.3 0.1 7.4 0.4 Beaver Valley 2 0.2 1.7 0.1 0.7 Braidwood 1 9.2 30.4 5.2 0.5 Braidwood 2 8.6 369.5 6.0 0.5 Byron 1 0.3 3.6 11.5 0.4 Byron 2 0.2 7.9 0.6 0.4 Callaway 19.8 110.6 209.6 165.6 Calvert Cliffs 1 314.9 331.5 134.4 101.7 Calvert Cliffs 2 314.9 331.5 134.4 101.7 Catawba 1 2.3 1.8 1.9 1.9 Catawba 2 2.3 1.8 1.9 1.9 Comanche Peak 1 7.0 498.5 2.5 1.9 Comanche Peak 2 7.0 498.5 2.5 1.9 Cook 1 4.9 18.5 2.7 3.2 Cook 2 4.9 18.5 2.7 3.2 Crystal River 3 4.4 3.3 0.1 0.0 Davis-Besse 31.6 27.0 178.3 112.2 Diablo Canyon 1 0.8 26.9 1.4 0.6 Diablo Canyon 2 0.8 26.9 1.4 0.6 Farley 1 22.4 27.2 17.8 42.3 Farley 2 3.1 5.9 16.4 8.6 Ft. Calhoun 2.8 3.8 3.5 2.0 Ginna 1.2 4.6 3.5 1.2 Harris 1.6 0.3 2.7 0.2 Indian Point 2 1.4 47.3 1.8 1.7 Indian Point 3 7.7 0.1 0.7 0.2 Kewaunee 0.1 0.1 0.1 0.0 McGuire 1 1.1 1.1 1.6 1.1 McGuire 2 1.1 1.1 1.6 1.1 Millstone 2 1.9 19.0 36.6 2.3 Millstone 3 46.0 61.8 9.4 28.2 North Anna 1 8.5 0.7 27.4 44.2 North Anna 2 8.5 0.7 27.4 44.2 54 Table 3.16 Short-Term Trend in Noble Gases in Gaseous Effluents, PWRs, Curies (Ci) (continued)
Shown in Alphabetical Order Facility 2007 2008 2009 2010 Oconee 1 112.9 5.9 6.9 15.8 Oconee 2 112.9 5.9 6.9 15.8 Oconee 3 112.9 5.9 6.9 15.8 Palisades 341.1 12.1 34.3 62.1 Palo Verde 1 0.6 0.9 9.9 0.8 Palo Verde 2 9.1 131.1 1.7 1.1 Palo Verde 3 2.2 0.3 23.5 0.7 Point Beach 1 0.3 0.6 0.5 0.7 Point Beach 2 0.3 0.6 0.5 0.7 Prairie Island 1 0.0 0.3 0.6 0.1 Prairie Island 2 0.0 0.3 0.6 0.1 Robinson 2 1.0 156.2 0.2 0.5 Salem 1 0.4 0.6 28.2 0.3 Salem 2 1.0 0.9 0.8 0.2 San Onofre 2 51.8 25.0 52.9 63.2 San Onofre 3 51.8 25.0 52.9 63.2 Seabrook 0.0 0.3 0.2 0.0 Sequoyah 1 16.5 4.7 2.4 2.5 Sequoyah 2 16.5 4.7 2.4 2.5 South Texas 1 1.5 15.4 3.9 2.7 South Texas 2 50.6 20.9 2.6 30.5 St. Lucie 1 6.0 7.9 1.7 22.3 St. Lucie 2 9.6 2.3 5.8 30.2 Summer 1.0 1.4 1.7 0.0 Surry 1  1.0 0.5 0.7 0.3 Surry 2 1.0 0.5 0.7 0.3 Three Mile Island 1 4.3 0.4 2.2 6.1 Turkey Point 3 6.1 60.0 162.2 0.7 Turkey Point 4 6.1 52.8 126.2 0.7 Vogtle 1 0.3 1.3 270.0 1.0 Vogtle 2 87.6 645.1 760.1 216.6 Waterford 3 40.8 525.6 3,560.2 0.0 Watts Bar 1 18.0 3.8 5.4 7.4 Wolf Creek 0.9 0.9 0.9 0.6 MEDIAN 4.4 5.9 3.5 1.2 55 3.3  Long-Term Trend in Gaseous Effluents This section discusses the long
-term trend of noble gases in gaseous effluents from nuclear power plants in the United States.
NRC regulations require radioactive effluents to be ALARA. As a result of improved radioactive effluent control programs, the amount of activity of radioactive effluents has steadily decreased over time. The trend in the median noble gas activity of gaseous effluents since 1975 is shown in Figure 3.15. All power reactors that have operated in the United States are included, some of which are now shut down.
Figure 3.15 Long-Term Trend in Noble Gases in Gaseous Effluents Figure 3.15 indicates a long
-term, downward trend in the amount of noble gases in gaseous effluents from both BWRs and PWRs. The magnitude of the reduction is significant. For example, in 1975, the median release for BWRs was greater than 40,000 curies; however, in 2010, the median was 41.
1 curies. That change corresponds to a 99.9 percent reduction in noble gas effluents over the last 35 years.
One of the primary contributors to the reduction in noble gas effluents is improved fuel integrity in both BWRs and PWRs. The use of advanced off
-gas systems in BWRs is also responsible for reductions in the BWR industry averages. Lastly, contributions from the operations, maintenance, chemistry, and health physics departments at the various facilities have improved the handling and processing of gaseous waste to further improve and optimize effluent performance. 0.010.10 1 101001,00010,000100,000Noble Gases(Ci)IndustryMedian, per ReactorBWRsPWRs 56 3.4  Short-Term Trend in Liquid Effluents In Section 3.1, only the significant radionuclides discharged in liquid and gaseous effluents were shown in the tables and figures. Although particular focus on the significant radionuclides yields useful information, many other radionuclides are typically present in radioactive liquid effluents. This section provides the reader with a tool to gain a better understanding of the total releases of liquid effluents from a facility.
An indicator of the licensee's ability to control liquid effluents is based on the activity of the mixed fission and activation products (MFAPs) discharged in liquid effluents. This category of radionuclides
-MFAPs-is described in Table 2.2. It includes all radionuclides in liquid effluents except tritium, C
-14, noble gases and gross alpha activity. MFAPs can be effectively reduced by liquid radioactive waste treatment systems installed in each NPP. As a result, MFAPs are sometimes used as a primary indicator of the overall control and handling of radioactive liquid effluents at a site.
Tables 3.17 and 3.18 show the short
-term trend in MFAPs in liquid effluents for BWRs and PWRs, respectively. In these tables, no MFAP radionuclides are left out. For each reactor unit, the activities of all MFAPs are added together. In this way, the yearly total of all MFAPs in liquid effluents from a reactor are represented by a single number. That number gives the total activity (as millicuries) of MFAPs discharged in liquid effluents at each reactor for each of the years listed. The facilities are listed in alphabetical order for ease of reference when searching for a site. Fluctuations in these short
-term data are within the range of expected values, based on power production and the increasing sensitivity of measurement techniques. Overall, the nuclear power industry has steadily reduced the amount of radioactivity discharged into the environment (see Section 3.5 for the long
-term trend in liquid effluents).
 
57 Table 3.17 Short-Term Trend in Mixed Fission and Activation Products in Liquid Effluents, BWRs, millicuries (mCi)
Shown in Alphabetical Order Facility 2007 2008 2009 2010 Browns Ferry 1 2,456.5 3.8 17.0 6.1 Browns Ferry 2 2,456.5 3.8 203.0 6.1 Browns Ferry 3 2,456.5 3.8 34,600.0 1 3,810.0 1 Brunswick 1 2.9 4.0 5.8 2.2 Brunswick 2 2.9 4.0 5.8 2.2 Clinton 0.0 0.0 0.0 0.0 Columbia 0.0 0.0 0.0 0.0 Cooper 0.0 4.7 0.4 3.6 Dresden 2 19.1 0.1 2.8 0.0 Dresden 3 19.1 0.1 2.8 0.0 Duane Arnold 0.0 0.0 0.0 0.0 Fermi 2 0.0 0.0 0.0 0.0 FitzPatrick 0.0 0.0 0.0 0.0 Grand Gulf 420.1 371.0 62.0 15.2 Hatch 1 5.6 23.9 2.8 1.4 Hatch 2 1.7 8.3 3.1 4.2 Hope Creek 44.9 16.6 57.5 70.3 LaSalle 1 0.0 0.0 0.0 0.0 LaSalle 2 0.0 0.0 0.0 0.0 Limerick 1 3.6 34.7 2.0 1.3 Limerick 2 3.6 34.7 2.0 1.3 Monticello 0.0 0.0 0.0 0.0 Nine Mile Point 1 0.0 0.0 0.4 0.0 Nine Mile Point 2 0.0 3.1 0.0 0.3 Oyster Creek 0.0 0.0 0.0 0.0 Peach Bottom 2 387.4 127.3 63.8 35.1 Peach Bottom 3 387.4 127.3 63.8 35.1 Perry 4.7 14.7 23.7 9.6 Pilgrim 0.1 0.0 1.4 36.9 Quad Cities 1 1.0 0.9 4.2 10.8 Quad Cities 2 1.0 0.9 4.2 10.8 River Bend 6.0 8.7 1.1 0.5 Susquehanna 1 0.2 1.2 4.4 55.8 Susquehanna 2 0.2 1.2 4.4 55.8 Vermont Yankee 0.0 0.0 0.0 0.0 MEDIAN 1.0 1.2 2.8 1.4                                                1 Browns Ferry had a condensate leak which resulted in a discharge of a short
-lived (less than 2 hours) radionuclide Fluorine-18, causing minor amounts of public dose.
 
58 Table 3.18 Short-Term Trend in Mixed Fission and Activation Products in Liquid Effluents, PWRs, millicuries (mCi)
Shown in Alphabetical Order Facility 2007 2008 2009 2010 Arkansas 1 46.2 43.0 21.2 60.4 Arkansas 2 25.1 47.2 50.2 13.1 Beaver Valley 1 85.9 198.9 110.2 57.5 Beaver Valley 2 85.9 198.9 110.2 57.5 Braidwood 1 1.7 51.6 136.0 13.5 Braidwood 2 1.7 51.6 136.0 13.5 Byron 1 13.1 9.9 11.1 5.5 Byron 2 13.1 9.9 11.1 5.5 Callaway 41.2 253.7 70.2 209.8 Calvert Cliffs 1 14.8 40.5 13.1 71.6 Calvert Cliffs 2 14.8 40.5 13.1 71.6 Catawba 1 27.2 22.2 34.4 19.6 Catawba 2 27.2 22.2 34.4 19.6 Comanche Peak 1 3.8 7.6 1.9 8.2 Comanche Peak 2 3.8 7.6 1.9 8.2 Cook 1 2.2 4.5 1.7 2.7 Cook 2 2.2 4.5 1.7 2.7 Crystal River 3 10.1 7.4 30.5 14.2 Davis-Besse 14.1 16.2 12.7 39.9 Diablo Canyon 1 28.2 14.5 21.6 24.3 Diablo Canyon 2 28.2 14.5 21.6 24.3 Farley 1 68.3 17.5 10.9 44.4 Farley 2 92.4 33.8 19.2 53.5 Ft. Calhoun 5.3 11.0 2.7 2.0 Ginna 22.0 5.1 4.7 1.3 Harris 34.3 19.8 15.7 12.9 Indian Point 2 42.4 54.6 37.3 56.2 Indian Point 3 11.5 14.3 25.3 10.6 Kewaunee 25.3 22.8 11.4 13.8 McGuire 1 30.6 57.5 17.4 22.4 McGuire 2 30.6 57.5 17.4 22.4 Millstone 2 25.0 112.8 84.2 17.3 Millstone 3 50.5 80.4 33.7 76.8 North Anna 1 128.0 61.3 12.2 3.7 North Anna 2 128.0 61.3 12.2 3.7 59 Table 3.1 8 Short-Term Trend in Mixed Fission and Activation Products in Liquid Effluents, PWRs, millicuries (mCi) (continued)
Shown in Alphabetical Order Facility 2007 2008 2009 2010 Oconee 1 6.5 7.0 8.5 15.1 Oconee 2 6.5 7.0 8.5 15.1 Oconee 3 6.5 7.0 8.5 15.1 Palisades 36.7 17.6 217.3 61.5 Palo Verde 1 0.0 0.0 0.0 0.0 Palo Verde 2 0.0 0.0 0.0 0.0 Palo Verde 3 0.0 0.0 0.0 0.0 Point Beach 1 40.2 60.1 48.3 38.9 Point Beach 2 40.2 60.1 48.3 38.9 Prairie Island 1 56.9 380.8 203.6 137.8 Prairie Island 2 56.9 380.8 203.6 137.8 Robinson 2 13.5 11.7 2.9 13.8 Salem 1 7.9 19.0 18.1 41.3 Salem 2 2.6 9.5 5.9 18.9 San Onofre 2 27.5 20.0 8.9 15.8 San Onofre 3 27.5 20.0 8.9 15.8 Seabrook 22.2 24.4 10.9 15.4 Sequoyah 1 61.5 40.8 10.2 12.8 Sequoyah 2 61.5 40.8 10.2 12.8 South Texas 1 12.3 9.6 14.8 11.9 South Texas 2 32.5 12.9 8.1 14.6 St. Lucie 1 20.7 14.3 66.9 67.6 St. Lucie 2 20.3 14.3 66.9 67.6 Summer 16.3 22.9 14.6 14.2 Surry 1 14.1 14.0 11.0 5.1 Surry 2 14.1 14.0 11.0 5.1 Three Mile Island 1 2.5 0.2 0.3 0.2 Turkey Point 3 29.5 58.8 82.0 32.2 Turkey Point 4 29.5 58.8 82.0 32.2 Vogtle 1 36.7 31.0 9.9 37.7 Vogtle 2 18.8 50.8 37.7 14.1 Waterford 3 174.0 23.8 32.3 6.6 Watts Bar 1 98.2 50.8 88.8 48.0 Wolf Creek 5.3 105.1 46.8 11.3 MEDIAN 25.0 22.2 14.8 15.1 60 3.5  Long-Term Trend in Liquid Effluents This section discusses the long
-term trend of MFAPs in liquid effluents from nuclear power plants in the United States. NRC regulations require radioactive effluents to be ALARA. As a result of improved radioactive effluent control programs, the amount of activity of radioactive effluents has steadily decreased over time. The trend in the median MFAP activity of liquid effluents since 1975 is shown in Figure 3.16. All power reactors that have operated in the United States are included, some of which are now shut down. Figure 3.16 Long-Term Trend in MFAPs in Liquid Effluents Figure 3.16 indicates a long
-term, downward trend in the amounts of MFAPs in liquid effluents from both BWRs and PWRs. The magnitude of the reduction is significant. For example, in 1975, the median activity of liquid effluents from BWRs was greater than 1100 millicuries; however, in 2010, the median was 1.4 millicuries. That corresponds to a 99.9 percent reduction in MFAPs in liquid effluents over the last 35 years.
One of the primary contributors to the reduction in liquid effluents is improved fuel integrity in both BWRs and PWRs. Additionally, many BWRs recycle (or reuse) some or all of the reactor water. The recycling of reactor water at BWRs is one reason why effluents from BWRs are generally lower than from PWRs. The PWR design requires the use of boron in the reactor water, which makes water re
-use impractical, whereas BWRs do not use boron in reactor water. The lack of boron in BWR reactor water allows the BWRs to recycle (or reuse) reactor water which contributes to lower liquid releases in BWRs, particularly for tritium. The use of advanced liquid radioactive waste processing systems has also significantly lowered liquid effluents. Lastly, improvements in the handling and processing of liquid waste made by the operations, maintenance, chemistry, and health physics departments at the various facilities have further reduced the amount of effluent releases and public dose.
0.010.10 1 101001,00010,000BWRsPWRsMFAPs (mCi)Industry Median, per Reactor 61 Figure 3.16 shows that from 2005 to 2009, there was a small increase in the median liquid effluents from BWRs. An analysis of this increase in median MFAP activity of liquid effluents from BWRs indicates a small change in the control of liquid effluents at some BWRs. For many decades, some BWRs have embraced a zero
-release strategy for radioactive liquid effluents. Such a strategy has cost advantages, because it is expensive to discharge very high
-quality water that could be reused in plant systems. Additionally, a zero
-release strategy conserves the natural resources and virtually eliminates radioactive liquid effluents in those BWRs that adopt this strategy. The zero-release strategy is partly responsible for the decreases in the median MFAP liquid activity releases during the 1980s, 1990s, and beyond 2000, which can be seen in Figure 3.16. This strategy can be very effective in reducing the amount of liquid activity. However, within the last 10 years, it was recognized that at some sites using a zero
-release strategy, releasing tritium as a gaseous release (rather than as a liquid effluent release) has the potential to increase doses to members of the public. This relative increase in public exposure, due to release of tritium as a gaseous release instead of as a liquid release, can be attributed to four factors:  Waste water in some plants has been recycled (instead of discharged as a liquid effluent).
As waste water is recycled, the tritium concentration in the water increases over time.
When all radioactive liquid releases are eliminated, tritium is released through the gaseous release points.
The dose due to tritium discharged from a gaseous release point can, depending on plant design and site characteristics, be higher than the dose from the same amount of tritium discharged from a liquid release point.
However, a plant that allows some liquid effluent releases can shift the release of tritium from a gaseous release point to a liquid release point, thereby lowering public doses. This strategy can cause a slight increase in the amount of activity of MFAPs in liquid effluents and a small decrease in total public dose.
 
===3.6 Radiation===
Doses from Gaseous and Liquid Effluents The maximum annual organ doses for 2010 from gaseous and liquid effluents are shown in Tables 3.19 through 3.22. The data from these tables are illustrated graphically in Figures 3.17 through 3.20. These tables and figures contain annual organ doses (for gaseous and liquid effluents) and annual total body doses (for liquid effluents).
In accordance with regulatory requirements and the calculation methodologies of RG 1.109 (Ref. [30] ), the doses are calculated for the individuals receiving the highest total body and organ doses. As a result, these doses are often referred to as the maximum total body and the maximum organ doses. Additionally, licensees are required to calculate the organ doses for six separate organs in the human body
:  bone, liver, thyroid, kidney, lung, and intestines. Only the highest of the organ doses is shown in this report. Because these doses are calculated for the individual receiving the highest dose from liquid and gaseous effluents, these individuals are typically located in close proximity to the facility. As a result, doses to other individuals, especially those located farther away from the facility, are expected to be significantly lower than those shown in this report.
 
62 The doses shown in the tables and graphs of this section include contributions from all radionuclides in the type of effluent shown (i.e., gaseous or liquid).
The NRC ALARA criteria, discussed in Section 2.4, are included in the tables and figures for purposes of comparison. Since many plants have more than one operating reactor, the ALARA criteria are shown on a per reactor basis.
If the licensee does not report a dose, a blank entry is used to indicate that either (1) no releases occurred (e.g., the NPP is a zero
-discharge plant) or (2) no exposure pathway exists. Also, blanks in data fields are generally used instead of zeros in order to make it easier for the reader to quickly identify the positive values.
Historically, C
-14 has not been considered a principal radionuclide, since the amount of activity in gaseous effluents was dominated by the xenon and krypton radionuclides. As a result, C
-14 has not been reported as a radioactive effluent. In addition, the release of C
-14 from NPPs has been insignificant compared to the natural production and world inventory of C
-14 (Ref. [31] ). Although the amount of C
-14 released from NPPs has not increased, steady improvements in nuclear power plant effluent management practices have resulted in a 99.9 percent decrease in the amount of activity from noble gas effluents released to the environment (see Figure 3.15, "Long-Term Trend in Noble Gases in Gaseous Effluents").
However, a recent NRC review of the significance o f C-14 releases on public dose has resulted in the NRC reclassifying C
-14 as a principal radionuclide. Releases of C
-14 have now been included beginning with this 2010 report.
For comparison purposes, median dose values are included in the tables and figures. The median is the midpoint of the data. Approximately half of the power plants will report doses greater than the median and approximately half will report doses lower than the median. The median is a method of estimating a central or typical value while avoiding bias caused by extremely high or low values in the data set. All sites are included when calculating the medians, even those sites for which no dose is reported.
For example, in Table 3.19, the BWR median annual organ dose due to gaseous effluents is highlighted in bold in the center of the table. In this case, the median dose is 0.215 mrem. This represents the typical annual organ dose, due to all gaseous effluents, from all BWRs operating in the United States in 2010. Figures 3.21 and 3.22 show the 4
-year trend in the median maximum annual organ doses in gaseous and liquid effluents, respectively. The sharp increase in the dose from gaseous effluents is the result of inclusion of C
-14 in the gaseous effluent data beginning in 2010. The median organ doses for liquid effluents from BWRs and PWRs have remained consistently low between 2007 and 2010 as seen in Figure 3.22.
A comparison between doses from gaseous effluents and liquid effluents can be made by examining Figures 3.21 and 3.22; and shows, in general, most of the dose from NPP effluents comes from the gaseous effluents. As a result, licensees wanting to lower doses may choose to focus additional efforts on reducing the radionuclides in gaseous effluents.
The evaluation of effluent data can be a key factor in understanding radioactive effluents. By gaining a better understanding of radioactive effluents, it is possible to exercise more control in reducing doses from such effluents. This helps to ensure radioactive effluents are ALARA.
63 The tables in this section indicate that the highest total body dose from all of the facilities was 0.226 mrem (Table 3.22), and the highest organ dose from all of the facilities was 5.96 mrem (Table 3.19). For purposes of comparison, 1 mrem is less than the radiation dose from any one of the following:
the dose received in 1 week from skiing in the Rocky Mountains; the dose received in 4 weeks from the natural potassium in each person's body; or the dose received in 8 weeks by a homeowner with a brick or stone house.
The basis for each of these three natural background dose values is based on information from the U.S. Geological Survey (USGS) (Ref. [34] ). Radiation exposure to cosmic rays at the high altitudes of Colorado would result in a dose of about 70 mrem per year. Additionally, the dose from rocks and soil in the mountains of Colorado would be about 40 mrem per year. The total of these two values is about 110 mrem per year for a person in the high elevations of Colorado. A person in Florida, who is typically at sea level and surrounded by the native Florida terrain, would receive about 40 mrem per year from rocks, soil, and cosmic radiation. As a result, people living at the high altitudes of Colorado receive about 70 mrem per year more radiation dose than a person living in Florida. People from Florida skiing in the Rocky Mountains for a week would be expected to receive an additional dose
-above what they might normally have received if they had stayed in Florida
-of about 1.3 mrem.
According to a DOE report prepared by the Pacific Northwest National Laboratory (Ref. [35] ), the average 150
-pound individual receives about 1.1 mrem per month or 14 mrem per year from the natural potassium
-40 that is incorporated into the human body.
NCRP Report No. 95 (Ref. [36] ) indicates that the radiation exposure from living in a brick, stone, adobe, or concrete home is about 7 mrem per year. At this annual dose rate, the exposure received in 8 weeks would be about 1.1 mrem.
NPPs in the United States discharge small but measurable amounts of radioactive materials in radioactive effluents. All of these radioactive releases must comply with NRC requirements. These requirements are in place to ensure (1) the radwaste processing systems at NPPs are operating properly, (2) the doses to members of the public are within the public dose limits, and (3) the doses to members of the public are ALARA. The information presented in this section indicates the maximum dose due to radioactive releases from NPPs was 5.96 mrem in 2010. The median dose was 0.273 mrem. Doses of these magnitudes are not expected to have a health impact on the public or the environment.
 
64 Table 3.19 BWR Gaseous Effluents
- Maximum Annual Organ Dose, 2010 Shown in Descending Order of Organ Dose BWR Facility Annual Organ Dose (mrem)
Grand Gulf 5.96E+00 River Bend 4.70E+00 Susquehanna 2 3.55E+00 Susquehanna 1 2.90E+00 Cooper 1.64E+00 Brunswick 1 1.18E+00 Brunswick 2 1.18E+00 Quad Cities 1 6.60E-01 Quad Cities 2 6.60E-01 Vermont Yankee 6.38E-01 Oyster Creek 4.71E-01 Dresden 2 3.31E-01 Dresden 3 3.31E-01 Peach Bottom 2 2.75E-01 Peach Bottom 3 2.75E-01 Fermi 2 2.35E-01 BWR Median Dose 2.15E-01 Nine Mile Point 1 2.15E-01 Nine Mile Point 2 2.15E-01 Perry 2.00E-01 LaSalle 1 1.87E-01 LaSalle 2 1.87E-01 Hatch 1 1.59E-01 Hatch 2 1.59E-01 FitzPatrick 1.37E-01 Monticello 1.15E-01 Pilgrim 1.09E-01 Limerick 1 1.03E-01 Limerick 2 1.03E-01 Duane Arnold 9.80E-02 Columbia 7.12E-02 Clinton 3.36E-02 Browns Ferry 1 2.93E-02 Browns Ferry 2 2.93E-02 Browns Ferry 3 2.93E-02 Hope Creek 4.61E-03 ALARA Criteria 15 65 Table 3.20 PWR Gaseous Effluents
- Maximum Annual Organ Dose, 2010 Shown in Descending Order of Organ Dose PWR Facility Annual Organ Dose (mrem)
PWR Facility Annual Organ Dose (mrem)
Waterford 3 3.86E+00  PWR Median Dose 2.73E-01 Watts Bar 1 3.75E+00  Surry 1 2.73E-01 Beaver Valley 2 2.96E+00  Surry 2 2.73E-01 Beaver Valley 1 2.67E+00  Turkey Point 4 2.63E-01 Catawba 1 2.39E+00  Robinson 2 2.60E-01 Catawba 2 2.39E+00  Arkansas 1 2.41E-01 Harris 1.46E+00  Turkey Point 3 2.38E-01 Cook 1 1.37E+00  Kewaunee 1.90E-01 Cook 2 1.37E+00  Diablo Canyon 1 1.83E-01 Wolf Creek 1.30E+00  Diablo Canyon 2 1.83E-01 Sequoyah 1 9.70E-01  Davis-Besse 1.70E-01 Sequoyah 2 9.70E-01  Seabrook 1.61E-01 Braidwood 2 9.36E-01  Three Mile Island 1 1.53E-01 Braidwood 1 9.35E-01  Comanche Peak 1 1.19E-01 Ft. Calhoun 9.20E-01  Comanche Peak 2 1.19E-01 Millstone 2 8.84E-01  Oconee 1 1.12E-01 Summer 8.00E-01  Oconee 2 1.12E-01 Millstone 3 6.13E-01  Oconee 3 1.12E-01 North Anna 1 5.80E-01  Point Beach 1 1.12E-01 North Anna 2 5.80E-01  Point Beach 2 1.12E-01 Palo Verde 1 5.77E-01  Palisades 1.05E-01 Palo Verde 2 5.77E-01  Vogtle 1 8.46E-02 Palo Verde 3 5.77E-01  Vogtle 2 8.46E-02 McGuire 1 4.59E-01  South Texas 1 6.56E-02 McGuire 2 4.59E-01  South Texas 2 6.56E-02 Farley 1 4.11E-01  Calvert Cliffs 1 6.50E-02 Farley 2 4.11E-01  Calvert Cliffs 2 6.50E-02 San Onofre 2 3.89E-01  Prairie Island 1 4.49E-02 San Onofre 3 3.89E-01  Prairie Island 2 4.49E-02 Byron 1 3.63E-01  Callaway 3.91E-02 Byron 2 3.62E-01  Salem 1 3.46E-02 Indian Point 3 3.38E-01  St. Lucie 1 3.42E-02 Arkansas 2 3.02E-01  St. Lucie 2 3.42E-02 Indian Point 2 2.84E-01  Ginna 1.94E-02    Salem 2 4.07E-03    Crystal River 3 2.34E-03    ALARA Criteria 15 66 Table 3.21 BWR Liquid Effluents
- Maximum Annual Total Body and Organ Dose, 2010 Shown in Descending Order of Organ Dose BWR Facility Total Body Dose (mrem) Organ Dose (mrem) Grand Gulf 2.92E-02 5.54E-02 Susquehanna 1 1.17E-02 2.06E-02 Susquehanna 2 1.17E-02 2.06E-02 Pilgrim 1.97E-03 9.97E-03 Quad Cities 1 2.86E-03 5.25E-03 Quad Cities 2 2.86E-03 5.25E-03 Hatch 1 2.32E-03 3.45E-03 Brunswick 1 1.67E-03 1.90E-03 Brunswick 2 1.67E-03 1.90E-03 Limerick 1 6.25E-04 7.00E-04 Limerick 2 6.25E-04 7.00E-04 Vermont Yankee 5.62E-04 5.62E-04 Hatch 2 1.59E-04 2.81E-04 Browns Ferry 1 1.86E-04 1.96E-04 Browns Ferry 2 1.86E-04 1.96E-04 Browns Ferry 3 1.86E-04 1.96E-04 Perry 1.53E-04 1.56E-04 BWR Median Dose 1.53E-04 6.44E-05 Hope Creek 1.86E-04 6.44E-05 FitzPatrick 2.66E-05 2.66E-05 River Bend 1.30E-05 1.90E-05 Peach Bottom 2 5.90E-06 9.25E-06 Peach Bottom 3 5.90E-06 9.25E-06 Oyster Creek 2.55E-06 2.55E-06 Duane Arnold 2.29E-06 2.29E-06 Dresden 3 2.67E-07 6.14E-07 Clinton Columbia Cooper Dresden 2 Fermi 2 LaSalle 1 LaSalle 2 Monticello Nine Mile Point 1 Nine Mile Point 2 ALARA Critera 3 10 67  Table 3.22 PWR Liquid Effluents
- Maximum Annual Total Body and Organ Dose, 2010 Shown in Descending Order of Organ Dose  PWR Facility Total Body Dose (mrem)
Organ Dose (mrem)  PWR Facility Total Body Dose  (mrem)
Organ Dose  (mrem) Wolf Creek 1.25E-01 2.37E-01  PWR Median Dose 6.75E-03 9.10E-03 North Anna 1 2.26E-01 2.30E-01  Point Beach 1 2.25E-03 9.10E-03 North Anna 2 2.26E-01 2.30E-01  Point Beach 2 2.25E-03 9.10E-03 Oconee 1 7.38E-02 2.19E-01  Millstone 2 2.76E-04 9.04E-03 Oconee 2 7.38E-02 2.19E-01  Calvert Cliffs 1 1.45E-03 6.85E-03 Oconee 3 7.38E-02 2.19E-01  Calvert Cliffs 2 1.45E-03 6.85E-03 St. Lucie 1 3.04E-02 1.22E-01  Sequoyah 1 6.75E-03 6.75E-03 St. Lucie 2 3.04E-02 1.22E-01  Sequoyah 2 6.75E-03 6.75E-03 Beaver Valley 1 6.82E-02 9.51E-02  South Texas 1 4.75E-03 4.79E-03 Beaver Valley 2 6.82E-02 9.51E-02  Millstone 3 9.66E-04 3.31E-03 McGuire 1 7.59E-02 8.00E-02  Ginna 2.79E-03 2.79E-03 McGuire 2 7.59E-02 8.00E-02  San Onofre 2 9.81E-04 2.29E-03 Byron 1 6.66E-02 7.97E-02  San Onofre 3 9.81E-04 2.29E-03 Byron 2 6.66E-02 7.97E-02  Arkansas 1 1.70E-02 2.10E-03 Comanche Peak 1 7.75E-02 7.75E-02  Prairie Island 1 8.90E-04 2.04E-03 Comanche Peak 2 7.75E-02 7.75E-02  Prairie Island 2 8.90E-04 2.04E-03 Farley 1 9.49E-03 6.09E-02  Summer 3.40E-03 1.95E-03 Catawba 1 4.42E-02 5.30E-02  Arkansas 2 1.00E-03 1.10E-03 Catawba 2 4.42E-02 5.30E-02  Indian Point 2 5.18E-04 1.09E-03 Vogtle 1 2.04E-02 4.56E-02  Indian Point 3 1.70E-04 9.73E-04 Farley 2 6.77E-03 4.48E-02  Kewaunee 6.44E-04 8.38E-04 Ft. Calhoun 2.27E-02 2.76E-02  Diablo Canyon 1 1.59E-04 5.45E-04 Cook 1 2.59E-02 2.17E-02  Diablo Canyon 2 1.59E-04 5.45E-04 Cook 2 2.59E-02 2.17E-02  Seabrook 1.31E-04 3.88E-04 Harris 8.81E-03 2.11E-02  Waterford 3 1.81E-04 2.11E-04 Callaway  1.39E-02 1.94E-02  Robinson 2 1.13E-04 1.67E-04 Watts Bar 1 1.51E-02 1.88E-02  Surry 1 1.13E-04 1.51E-04 Braidwood 1 1.30E-02 1.57E-02  Surry 2 1.13E-04 1.51E-04 Braidwood 2 1.30E-02 1.57E-02  Salem 1 5.77E-05 1.49E-04 Three Mile Island 1 1.43E-02 1.50E-02  Salem 2 4.13E-05 8.81E-05 Crystal River 3 1.10E-03 1.48E-02  Turkey Point 3 8.28E-05  Davis-Besse 1.04E-02 1.33E-02  Turkey Point 4 8.28E-05  Vogtle 2 7.61E-03 1.23E-02  Palo Verde 1 Palisades 6.95E-03 1.05E-02  Palo Verde 2 Palo Verde 3 South Texas 2 ALARA Criteria 3 10 68 Figure 3.17 BWR Gaseous Effluents - Maximum Annual Organ Dose 1E-61E-51E-41E-31E-21E-11E+01E+11E+2Hope CreekBrowns Ferry 3Browns Ferry 2 Browns Ferry 1ClintonColumbiaDuane ArnoldLimerick 2 Limerick 1PilgrimMonticelloFitzPatrickHatch 2 Hatch 1LaSalle 2 LaSalle 1PerryNine Mile Point 2 Nine Mile Point 1BWR Median DoseFermi 2Peach Bottom 3 Peach Bottom 2Dresden 3 Dresden 2Oyster CreekVermont YankeeQuad Cities 2 Quad Cities 1Brunswick 2Brunswick 1CooperSusquehanna 1 Susquehanna 2River BendGrand GulfALARA Criteria2010 Annual Organ Dose (mrem) 69  Figure 3.18 PWR Gaseous Effluents
- Maximum Annual Organ Dose 1E-61E-51E-41E-31E-21E-11E+01E+11E+2PWR Median DoseIndian Point 2Arkansas 2Indian Point 3Byron 2Byron 1San Onofre 3San Onofre 2Farley 2Farley 1McGuire 2McGuire 1Palo Verde 3Palo Verde 2Palo Verde 1North Anna 2North Anna 1Millstone 3SummerMillstone 2Ft. CalhounBraidwood 1Braidwood 2Sequoyah 2Sequoyah 1Wolf CreekCook 2Cook 1HarrisCatawba 2Catawba 1Beaver Valley 1Beaver Valley 2Watts Bar 1Waterford 3ALARA Criteria2010 Annual Organ Dose (mrem) 70 Figure 3.18 PWR Gaseous Effluents - Maximum Annual Organ Dose (continued) 1E-61E-51E-41E-31E-21E-11E+01E+11E+2Crystal River 3Salem 2GinnaSt. Lucie 2St. Lucie 1Salem 1CallawayPrairie Island 2 Prairie Island 1Calvert Cliffs 2 Calvert Cliffs 1South Texas 2 South Texas 1Vogtle 2 Vogtle 1PalisadesPoint Beach 2 Point Beach 1Oconee 3 Oconee 2 Oconee 1Comanche Peak 2 Comanche Peak 1Three Mile Island 1SeabrookDavis-BesseDiablo Canyon 2 Diablo Canyon 1KewauneeTurkey Point 3Arkansas 1Robinson 2Turkey Point 4Surry 2 Surry 1PWR Median DoseALARA Criteria2010 Annual Organ Dose (mrem) 71  Figure 3.19 BWR Liquid Effluents
- Maximum Annual Total Body and Organ Dose 1E-71E-61E-51E-41E-31E-21E-11E+01E+11E+2Nine Mile Point 2Nine Mile Point 1MonticelloLaSalle 2LaSalle 1Fermi 2Dresden 2CooperColumbiaClintonDresden 3Duane ArnoldOyster CreekPeach Bottom 3Peach Bottom 2River BendFitzPatrickHope CreekBWR Median DosePerryBrowns Ferry 3Browns Ferry 2Browns Ferry 1Hatch 2Vermont YankeeLimerick 2Limerick 1Brunswick 2Brunswick 1Hatch 1Quad Cities 2Quad Cities 1PilgrimSusquehanna 2Susquehanna 1Grand GulfALARA Criteria2010 Annual Dose (mrem)OrganTotal Body 72 Figure 3.20 PWR Liquid Effluents - Maximum Annual Total Body and Organ Dose 1E-61E-51E-41E-31E-21E-11E+01E+11E+2PWR Median DosePalisadesVogtle 2Davis-BesseCrystal River 3Three Mile Island 1Braidwood 2Braidwood 1Watts Bar 1CallawayHarrisCook 2 Cook 1Ft. CalhounFarley 2Vogtle 1Catawba 2 Catawba 1Farley 1Comanche Peak 2 Comanche Peak 1Byron 2 Byron 1McGuire 2 McGuire 1Beaver Valley 2 Beaver Valley 1St. Lucie 2 St. Lucie 1Oconee 3 Oconee 2 Oconee 1North Anna 2 North Anna 1Wolf CreekALARA Criteria2010 Annual Dose (mrem)OrganTotal Body 73  Figure 3.20 PWR Liquid Effluents
- Maximum Annual Total Body and Organ Dose (continued) 1E-61E-51E-41E-31E-21E-11E+01E+11E+2South Texas 2Palo Verde 3Palo Verde 2Palo Verde 1Turkey Point 4Turkey Point 3Salem 2Salem 1Surry 2Surry 1Robinson 2Waterford 3SeabrookDiablo Canyon 2Diablo Canyon 1KewauneeIndian Point 3Indian Point 2Arkansas 2SummerPrairie Island 2Prairie Island 1Arkansas 1San Onofre 3San Onofre 2GinnaMillstone 3South Texas 1Sequoyah 2Sequoyah 1Calvert Cliffs 2Calvert Cliffs 1Millstone 2Point Beach 2Point Beach 1PWR Median DoseALARA Criteria2010 Annual Dose (mrem)OrganTotal Body 74 Note:  The increase in reported organ dose from 2009 to 2010 is due largely to the addition of a radionuclide category for C
-14 in Table 2.1.
See text at the beginning of section 3.6 for more information on the addition of C
-14. Figure 3.21 Median Maximum Annual Organ Dose, Gaseous Effluents 4-Year Trend, 2007
-2010 Figure 3.22 Median Maximum Annual Dose, Liquid Effluents 4-Year Trend, 2007
-2010 0.0200.0180.0150.2150.0240.0130.0150.2730.0000.050 0.1000.1500.2000.2500.3002007200820092010BWRsPWRsDoses FromAll Gaseous Effluents (mrem)Noble gases, Iodines, Particulates, H
-3 and C-140.00070.00090.00040.00010.00860.00780.00820.00910.00030.00060.00040.00020.00490.00660.00610.00680.0000.002 0.004 0.006 0.008 0.010 0.012 0.0142007200820092010BWRsPWRsDoses From All Liquid Effluents (mrem)OrganTotalBody 75 4   
 
==SUMMARY==
The information contained in this report summarizes the liquid and gaseous effluents and public doses from all United States nuclear power plants (NPPs) in commercial operation for calendar year 2010. Although all NPPs released radioactive materials in 2010, none of the effluents from any NPP resulted in an exceedance of any NRC or EPA public dose limit, or any NRC ALARA criteria.
The radionuclides selected for inclusion in this report are either the most common radionuclides or the most significant radioactive effluents and are particularly useful indicators of overall releases. The radionuclides selected also provide additional information about operational practices at a site. Nuclear power plants have reduced their radioactive effluents by 99.9 percent in a long-term decreasing trend in radioactive effluents (i.e., mixed fission and activation products in liquid effluents and noble gases in gaseous effluents) since the mid
-1970s. For additional context, the median dose resulting from radioactive effluents are provided for comparison to the ALARA criteria, to the natural background sources of radiation, and other sources of radiation exposure to the U.S. population. Comparisons of the radioactive effluents between NPPs may indicate differences in fuel conditions, fuel cycle length, radioactive waste processing equipment, reactor types, reactor ages, electrical outputs, and operating conditions. Each of these factors can have an effect on radioactive effluents.
More complete and detailed information, including copies of the NPPs' ARERRs, is available to the public on the NRC Web site.
 
77 5    REFERENCES
[1]  "Report on Releases of Radioactivity in Effluents and Solid Wastes from Nuclear Power Plants for 1972," Directorate of Regulatory Operations, August 1973.
[2]  "Summary of Radioactivity Releases in Effluents from Nuclear Power Plants During 1973," NUREG-75/001, January 1975.
[3]  "Radioactive Materials Released from Nuclear Power Plants, 1974," NUREG
-0077,  June 1976.
[4]  "Radioactive Materials Released from Nuclear Power Plants, 1975," NUREG
-0218, March 1977. [5]  "Radioactive Materials Released from Nuclear Power Plants, 1976," NUREG
-0367, March 1978. [6]  "Radioactive Materials Released from Nuclear Power Plants, 1977," NUREG
-0521, January 1979. [7]  "Radioactive Materials Released from Nuclear Power Plants, 1978," NUREG/CR
-1497, BNL-NUREG-51192, March 1981.
[8]  "Radioactive Materials Released from Nuclear Power Plants, 1979," NUREG/CR
-2227, BNL-NUREG-51416, November 1981.
[9]  "Radioactive Materials Released from Nuclear Power Plants, 1980," NUREG/CR-2907, BNL-NUREG-51581, Vol. 1, January 1983.
[10]  "Radioactive Materials Released from Nuclear Power Plants, 1981," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 2, June 1984.
[11]  "Radioactive Materials Released from Nuclear Power Plants, 1982," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 3, February 1986.
[12]  "Radioactive Materials Released from Nuclear Power Plants, 1983," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 4, August 1986.
[13]  "Radioactive Materials Released from Nuclear Power Plants, 1984," NUREG/CR
-2907, BNL-NUREG-51581, Vol.
5, August 1987.
[14]  "Radioactive Materials Released from Nuclear Power Plants, 1985," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 6, January 1988.
[15]  "Radioactive Materials Released from Nuclear Power Plants, 1986," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 7, November 1988
. [16]  "Radioactive Materials Released from Nuclear Power Plants, 1987," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 8, October 1989.
[17]  "Radioactive Materials Released from Nuclear Power Plants, 1988," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 9, July 1991.
[18]  "Radioactive Materials Released from Nuclear Power Plants, 1989," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 10, September 1992.
[19]  "Radioactive Materials Released from Nuclear Power Plants, 1990," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 11, October 1993.
[20]  "Radioactive Materials Released from Nuclear Power Plants, 1991," NUREG/CR
-2907, BNL-NUREG-51581, Vol. 12, May 1994.
 
78 [21]"Radioactive Materials Released from Nuclear Power Plants, 1992," NUREG/CR
-2907,BNL-NUREG-51581, Vol. 13, August 1995.[22]"Radioactive Materials Released from Nuclear Power Plants, 1993," NUREG/CR
-2907,BNL-NUREG-51581, Vol. 14, August 1995.[23]SECY-06-0212, Preparation of Annual Reports on Radioactive Materials Released i n Gaseous and Liquid Effluents and in Solid Wastes Shipped for Disposal by CommercialNuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, DC,October 17, 2006.[24]"Radioactive Effluents From Nuclear Power Plants - Annual Report 2007," NRC Office ofNuclear Reactor Regulation, ADAMS Accession Number ML103620453, December 2010.[25]"Radioactive Effluents From Nuclear Power Plants
- Annual Report 2008," NRC Office ofNuclear Reactor Regulation, ADAMS Accession Number ML103620452, December 2010.[26]"Radioactive Effluents from Nuclear Power Plants, Annual Report 2009," NUREG/CR-2907,ADAMS Accession Number ML13218A300, Vol. 15, August 2013.[27]10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities,"
U.S. Nuclear Regulatory Commission, Washington, DC.[28]Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material i n L iquid and Gaseous Effluents and Solid Waste," Revision 2, U.S. Nuclear RegulatoryCommission, Washington, DC, June 2009.[29]10 CFR Part 20, "Standards for Protection Against Radiation," U.S. Nuclear Regulatory Commission, Washington, DC.[30]Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases ofReactor Effluents for the Purpose of Demonstrating Compliance with 10 CFR Part 50,Appendix I," U.S. Nuclear Regulatory Commission, Washington, DC, October 1977.[31]NCRP Report No. 81, "Carbon
-14 in the Environment, National Council of Radiati on Protection and Measurements," Bethesda, May 1985.[32]NCRP Report No. 160, "Ionizing Radiation Exposure of the Population of the United States,"
National Council on Radiation Protection and Measurements, Bethesda, MD, March 3, 2009.[33]NCRP Report No. 93, "Ionizing Radiation Exposure of the Population of the United States,"National Council on Radiation Protection and Measurements, Bethesda, MD, September
 
1987.[34]Duval, J.S., Carson, J.M., Holman, P.B., and Darnley, A.G., 2005, "Terrestrial Radioactivity and Gamma-ray Exposure in the United States and Canada:  U.S. Geological Survey Open
-File Report 2005
-1413." Available online only.[35]PNNL-18240, "Radiation Doses to Hanford Workers from Natural Potassium
-40," Strom, D.J., Lynch, T. P., and Weier, D. R., Pacific Northwest National Laboratory, February 2009.[36]NCRP Report No. 95, "Radiation Exposure of the U.S. Population from Consumer Products and Miscellaneous Sources," National Council on Radiation Protection and Measurements,Bethesda, MD, 1987.
79 6    GLOSSARY Activity or radioactivity
:  The rate of radioactive transformations of a radionuclide, measured in the traditional unit of the curie (Ci) or the international standard unit of the becquerel (Bq).
Background (radiation)
:  Radiation from cosmic sources; naturally occurring radioactive material, including radon (except as a decay product of source or special nuclear material); and global fallout as it exists in the environment from the testing of nuclear explosive devices and from past nuclear accidents such as Chernobyl that contribute to background radiation and are not under the control of the licensee. Background radiation does not include radiation from source, byproduct, or special nuclear materials regulated by the Nuclear Regulatory Commission.
Effluent discharge, radioactive discharge
:  The portion of an effluent release that reaches an unrestricted area.
Effluent release, radioactive release
:  The emission of an effluent from a plant structure into the site environment.
Exposure pathway
:  A mechanism by which radioactive material is transferred from the (local) environment to humans. There are three commonly recognized exposure pathways:  inhalation, ingestion, and direct radiation.
Fission and activation gases
:  The noble (chemically non
-reactive) gases formed from the splitting (fission) of the uranium
-235 isotope in a nuclear reactor or the creation of radioactive atoms from non
-radioactive atoms (activation) by the capture of neutrons or gamma rays that are released during the fission process.
Gaseous effluents
:  Airborne effluents.
Iodines:  The measured radioactive isotopes of iodine or of other non
-metal elements in group 17 of the Periodic Table of Elements. Licensees might report any combination of the iodine isotopes, I
-131, I-132, I-133, I-134, and I
-135. Maximum exposed individuals:  Individuals characterized as maximum with regard to food consumption, occupancy, and other usage of the region in the vicinity of the plant site. As such, they represent individuals with habits that are considered to be maximum reasonable deviations from the average for the population in general. Additionally, in physiological or metabolic respects, the maximum exposure individuals are assumed to have those characteristics that represent the averages for their corresponding age group in the general population.
Member of the public (10 CFR Part 20)
:  Any individual except when that individual is receiving an occupational dose.
Monitoring
:  The measurement of radiation levels, concentrations, surface area concentrations, or quantities of radioactive material and the use of results of these measurements to evaluate potential exposures and doses.
Noble gas:  One of six noble gases (helium, neon, argon, krypton, xenon, and radon) with an oxidation number of 0 that prevents it from forming compounds readily. All noble gases have the 80 maximum number of electrons possible in their outer shell (two for helium, eight for all others), making them unreactive.
Occupational dose
:  as defined in 10 CFR 20.1003, means the dose received by an individual in the course of employment in which the individual's 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.
NURE G:  A publication by or for the NRC containing non
-sensitive information related to NRC's mission that does not contain regulatory requirements and is published in a formal agency series to ensure the "-dissemination to the public of scientific and technical information related to atomic energy-" as mandated by the Atomic Energy Act of 1954, as amended. Each publication bears an agency designator (e.g., NUREG
-number-year). Particulates
:  Radioactive materials that are entrained in the gaseous effluents and are not included in any other effluent category.
Site boundary
:  That line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.
Tritium:  The radioactive isotope of hydrogen (H
-3) 
 
NUREG/CR-2907, Vol. 16 Jason Davis, PhD., CHP Health Physicist
- ORAU Oak Ridge Associated Universities 1299 Bethel Valley Road, SC
-200, MS-21 Oak Ridge, TN 37830 Division of Risk Assessment Office Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, CD 20555
-0001 There are 104 commercial nuclear power plants (NPPs) on 65 sites in the United States (U.S.) regulate d by the Nuclear Regulatory Commission (NRC). Each year, each power reactor sends a report to the NRC that identifies the radioactive liquid and gaseous effluents discharged from the facility. This report summarizes that information and presents it in a format intended for both nuclear professionals and the general public.
The reader can use this report to quickly characterize the radioactive discharges from any U.S. NPP in 2010. The radioactive effluents from one reactor can be compared with other reactors. The results can also be compared with typical (or median) effluents for the industry, including short
-term trends and long
-term trends.
Although all NPPs released some radioactive materials in 2010, all effluents discharged were within the NRC's public dose limits, and NRC ALARA criteria. Additionally, the doses from radioactive effluents were much less than the doses from other sources of natural radiation that are commonly considered safe. This indicates radioactive effluents from NPPs in 2010 had no significant impact on the health and safety of the public or the environment.
Effluents Radioactive materials ALARA Dose 2018  Technical January 2010 - December 2010 Radioactive Effluents from Nuclear Power Plants Annual Report 2010
 
NUREG/CR-2907, Vol. 16 Radioactive Effluents from Nuclear Power Plants 2018}}

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