ML061310236

Annual Radiological Environmental Operating Report (AREOR) Report January Through December 2005

ML061310236
Person / Time
Site:	Browns Ferry
Issue date:	05/09/2006
From:	Crouch W Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML061310236 (96)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 May 9, 2006 10 CFR 50, APPENDIX I, Sections IV.B.2, IV.B.3, & IV.C U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) REPORT -

JANUARY THROUGH DECEMBER 2005 In accordance with the BFN Technical Specifications (TS)

Section 5.6.2 and 10 CFR 50, Appendix I, Section IV.B, TVA is submitting the AREOR report for BFN Units 1, 2, and 3. This report covers the period from January through December 2005.

TS Section 5.6.2 requires that the enclosed AREOR report contain summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. In addition, the BFN Offsite Dose Calculation Manual, Section 5.1, requires the AREOR include the following information:

• Results of land use censuses

• Summarized and tabulated results of the radiological environmental samples taken during the reporting period, in the format of Regulatory Guide 4.8, December 1975, and NUREG 1302, April 1991

• Summary description of the radiological environmental monitoring program 50

U.S. Nuclear Regulatory Commission Page 2 May 9, 2006

• A map of sampling locations keyed to a table giving distances and directions from one reactor

• Results of TVA's participation in the Interlaboratory Comparison Program The report concludes, that based upon the analyses of the environmental sampling results and trend data, the exposure to members of the public which may have been attributable to BFN operation is negligible.

There are no regulatory commitments contained in this letter.

If you have any questions, please contact me at (256) 729-2636.

Sincerely, William D. Crouch Manager of Site Licensing and Industry Affairs Enclosure cc: See page 3

U.S. Nuclear Regulatory Commission Page 3 May 9, 2006 Enclosure cc (Enclosure):

U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 Mr. Malcolm T. Widmann, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 Mr. Ronald Sanacore American Nuclear Insurers Town Center, Suite 300S 29 South Main Street West Hartford, Connecticut 06107-2430 Mr. Stanley Self West Morgan-East Lawrence Water Authority 6505 County Road 400 Hillsboro, Alabama 35643

U.S. Nuclear Regulatory Commission Page 4 May 9, 2006 WDC:DTL:JEW Enclosure cc (w/o Enclosure):

B. M. Aukland, POB 2C-BFN M. Bajestani, NAB 1A-BFN A. S. Bhatnagar, LP 6A-C J. C. Fornicola, LP 6A-C R. G. Jones, POB 2C-BFN R. F. Marks, PAB 1C-BFN G. W. Morris, BR 4X-C B. J. O'Grady, PAB 1E-BFN K. W. Singer, LP 6A-C E. J. Vigluicci, ET 1lA-K NSRB Support, LP 5M-C EDMS WT CA - K (with Enclosure) s: lic\SUBMIT\SUBS\areor2002 .do

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR),

JANUARY THROUGH DECEMBER 2005 (See Attached)

Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant 2005

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT BROWNS FERRY NUCLEAR PLANT 2005 TENNESSEE VALLEY AUTHORITY April 2006

TABLE OF CONTENTS Table of Contents ............................................. ii List of Tables ................................................. iv List of Figures ................................................ v Executive Summary ........................................... 1 Introduction ................................................. 2 Naturally Occurring and Background Radioactivity ................. 2 Electric Power Production ..................................... 4 Site/Plant Description .......................................... 6 Radiological Environmental Monitoring Program ......... . .......... 7 Direct Radiation Monitoring ..................................... 10 Measurement Techniques ...................................... 10 Results .................................................... 11 Atmospheric Monitoring ....................................... 13 Sample Collection and Analysis ................................. 13 Results.................................................... 14 Terrestrial Monitoring ......................................... 16 Sample Collection and Analysis ................................ 16 Results.................................................... 16 Liquid Pathway Monitoring ...................................... 18 Sample Collection and Analysis ................................ 18 Results..................................................... 19 Assessment and Evaluation ................. 21 Results ...................... 21 Conclusions ................................................ 22 References.............................. v.................... 23 Appendix A Radiological Environmental Monitoring Program and Sampling Locations ............................................ 27 Appendix B 2005 Program Modifications ........................... 38 Appendix C Program Deviations .................................. 40 Appendix D Analytical Procedures ................................ 43 Appendix E Nominal Lower Limits of Detection (LLD) ................ 46 Appendix F Quality Assurance/Quality Control Program ............... 51 Appendix G Land Use Survey .................................... 56 Appendix H Data Tables and Figures .............................. 61

-. ii-

LIST OF TABLES Table 1 Comparison of Program Lower Limits of Detection with Regulatory Limits for Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas and Reporting Levels ............. 24

-iv-

LIST OF FIGURES Figure 1 Tennessee Valley Region ................................. 25 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atmosphere and Lake .................................... 26

EXECUTIVE

SUMMARY

This report describes the radiological environmental monitoring program conducted by TVA in the vicinity of the Browns Ferry Nuclear Plant (BFN) in 2005. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Monitoring includes the sampling of air, water, soil, food crops, fish, shoreline sediment, and the measurement of direct radiation levels.

Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations.

The vast majority of the activity detected from environmental samples was the result of naturally occurring radioactive materials. Small amounts of Cs-137 were measured in a limited number of samples collected during 2005. The concentrations measured for Cs-137 were consistent with levels commonly found in the environment as a result of atmospheric nuclear weapons fallout.

The level of activity measured in these samples would result in no measurable increase over background in the dose to the general public.

INTRODUCTION This report describes and summarizes results of radioactivity measurements made in the vicinity of BFN and laboratory analyses of samples collected in the area. The measurements are made to comply with the requirements of 10 CFR 50, Appendix A, Criterion 64 and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of BFN Technical Specification 5.6.2 and Offsite Dose Calculation Manual (ODCM) Administrative Control 5.1.

The data presented in this report include results from the prescribed program and information to help correlate the significance of results measured by this monitoring program to the levels of environmental radiation resulting from naturally occurring radioactive materials.

Naturally Occurring and Background Radioactivity Most materials in our world today contain trace amounts of naturally occurring radioactivity.

Potassium-40 (K-40), with a half-life of 1.3 billion years, is one of the major types of radioactive materials found naturally in our environment. An individual weighing 150 pounds contains about 140 grams of potassium (Reference 1). This is equivalent to approximately 100,000 pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body.

Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212, 214, lead (Pb)-212, 214, thallium (Tl)-208, actinium (Ac)-228, uranium (U)-238, 235, thorium (Th)-234, radium (Ra)-226, radon (Rn)-222, carbon (C)-14, and hydrogen (H)-3 (generally called tritium). The radiation from these materials makes up a part of the low-level natural background radiation. The remainder of the natural background radiation comes in the form of cosmic ray radiation from outer space.

It is possible to get an idea of the relative hazard of different types of radiation sources by evaluating the amount of radiation the U.S. population receives from each general type of radiation source. The following information is primarily adapted from References 2 and 3.

U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source Millirem/Year Per Person Natural background dose equivalent Cosmic 27 Cosmogenic 1 Terrestrial 28 In the body 39 Radon-222 200 Total 295 Release of radioactive material in natural gas, mining, ore processing, etc. 5 Medical (effective dose equivalent) 53 Nuclear weapons fallout less than 1 Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately)

As can be seen from the table, the natural background radiation dose equivalent to the U.S.

population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and terrestrial radiation.

Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electrical generating plants. The basic process behind electrical power production in both types of plants is that fuel is used to heat water to produce steam which provides the force to turn turbines and generators. In a nuclear power plant, the fuel is uranium and heat is produced in the reactor through the fission of the uranium. Nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfunction.

The nuclear reactions produce radionuclides commonly referred to as fission and activation products. Very small amounts of these fission and activation products are released into the plant systems. This radioactive material can be transported throughout plant systems and some of it released to the environment.

The pathways through which radioactivity is released are monitored. Liquid and gaseous effluent monitors record the radiation levels for each release. These monitors also provide alarm mechanisms to prompt termination of any release above limits.

Releases are monitored at the onsite points of release and through the environmental monitoring program which measures the environmental radiation in areas around the plant. In this way, not only is the release of radioactive materials from the plant tightly controlled, but measurements are made in surrounding areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials.

The BFN ODCM, which is required by the plant Technical Specifications, prescribes limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents. The dose to a member of the general public from radioactive materials released to unrestricted areas, as given in NRC guidelines and in the ODCM, is limited as follows:

Liquid Effluents Total body <3 mrem./year Any organ <10 mrem/year Gaseous Effluents Noble gases:

Gamma radiation <10 mrad/year Beta radiation <20 mrad/year Particulates:

Any organ <15 mrem./year The Environmental Protection Agency (EPA) limits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are as follows:

Total body <25 mrem/year Thyroid <75 mrem/year Any other organ <25 mremlyear Appendix B to 10 CFR 20 presents the regulatory limits for the annual average concentrations of radioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted area. Table 1 of this report compares the nominal lower limits of detection for the BFN monitoring program with the regulatory limits for maximum annual average effluent concentrations released to unrestricted areas and levels requiring special reports to the NRC. The data presented in this report indicate compliance with the regulations.

SITE/PLANT DESCRIPTION Browns Ferry Nuclear Plant (BFN) is located on the north shore of Wheeler Reservoir at Tennessee River Mile 294 in Limestone County in north Alabama (Figure 1). Wheeler Reservoir averages 1 to 1-1/2 miles in width in the vicinity of the plant. The site, containing approximately 840 acres, is approximately 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama. The dominant character of land use is small, scattered villages and homes in an agricultural area. A number of relatively large farming operations occupy much of the land on the north side of the river immediately surrounding the plant. The principal crop grown in the area is cotton.

Approximately 2500 people live within a 5-mile radius of the plant. The town of Athens has a population of about 17,000, while approximately 49,000 people live in the city of Decatur. The largest city in the area with approximately 160,000 people is Huntsville, Alabama, located about 24 miles east of the site.

Area recreation facilities are developed along the Tennessee River. The nearest facilities are public use areas located 2 to 3 miles from the site. The city of Decatur has developed a large municipal recreation area, Point Mallard Park, approximately 15 miles upstream of the site. The Tennessee River is also a popular sport fishing area.

BFN consists of three boiling water reactors. Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in March 1977.

All three units were out of service from March 1985 to May 1991. Unit 2 was restarted May 24, 1991 and Unit 3 restarted on November 19, 1995. Recovery work for Unit 1 is ongoing.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor itself or one of the other plant systems. Plant effluent monitors are designed to detect the small amounts released to the environment. Environmental monitoring is a final verification that the systems are performing as planned. The monitoring program is designed to sample the pathways between the plant and the people in the immediate vicinity of the plant. Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized. The radiological environmental monitoring program is outlined in Appendix A.

There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see Figure 2). The air pathway can be separated into two components:

the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples collected in this program are designed to monitor these pathways A number of factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use. Terrestrial sampling stations were selected after reviewing such things as the locations of dairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment. Table A-2 (Appendix A, Table 2: This method of notation is used for all tables and figures given in the appendices.) lists the sampling stations and the types of samples collected from each.

Modifications made to the REMP program are described in Appendix B. While there were no modifications made in 2005, Appendix B is included in this report as a place keeper. Deviations in the sampling and analysis schedule are discussed in Appendix C.

To determine the amount of radioactivity in the environment prior to the operation of BFN, a preoperational radiological environmental monitoring program was initiated in 1968 and operated until the plant began operation in 1973. Sampling and analyses conducted during the preoperational phase has provided data that can be used to establish normal background levels for various radionuclides in the environment.

The preoperational monitoring program is a very important part of the overall program. During the 1950s, 60s, and 70s, atmospheric nuclear weapons testing released radioactive material to .the environment causing fluctuations in background radiation levels. This radioactive material is the same type as that produced in the BFN reactors. Preoperational knowledge of radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of whether the operation of BFN is impacting the environment and thus the surrounding population.

The evaluation of the impact of plant operations also utilizes data from control stations that have been established in the monitoring program. Results of environmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to establish the extent of BFN influence.

Sample analyses are performed by TVA's Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory (WARL) in Muscle Shoals, Alabama. The analyses are conducted in accordance with written and approved procedures and are based on accepted methods. A summary of the analysis techniques and methodology is presented in Appendix D. Data tables summarizing the sample analysis results are presented in Appendix H.

The radiation detection devices and analysis methods used to determine the radionuclide content of samples collected in the environment are very sensitive to small amounts of radioactivity. The sensitivity of the measurement process is defined in terms of the lower limit of detection (LLD). A description of the nominal LLDs for the Radioanalytical Laboratory is presented in Appendix E.

The ERM&I Laboratory applies a comprehensive quality assurance/quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected. This program includes instrument checks to ensure that the radiation detection instruments are working properly and the analysis of quality control samples. To provide for interlaboratory comparison program cross checks, the laboratory participated in a blind sample program administrated by Analytics, Incorporated. In addition, samples are split with the EPA National Air and Radiation Environmental Laboratory and the State of Alabama. A complete description of the quality control program is presented in Appendix F.

DIRECT RAD[ATION MONITORING Direct radiation levels are measured at a number of stations around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and radioactivity that may be present as a result of plant operations. Because of the relative large variations in background radiation as compared to the small levels from the plant, contributions from the plant are difficult to distinguish.

Radiation levels measured in the area around the BFN site in 2005 were consistent with levels from previous years and with levels measured at other locations in the region.

Measurement Techniques Direct radiation measurements are made with thermoluminescent dosimeters (TLDs).

TVA uses the Panasonic Model LTD-814 dosimeter for measurement of the environmental radiation levels. This dosimeter contains four elements consisting of one lithium borate and three calcium sulfate phosphors. The calcium sulfate phosphors are shielded by approximately 1000 mg/cm2 plastic and lead to compensate for the over-response of the detector to low energy radiation.

TLDs are placed approximately 1 meter above the ground, with two or more TLDs at each monitoring location. Monitoring points for TLDs are located in each of the sixteen compass sectors surrounding the site. One monitoring point is located in each sector near the site boundary and a second monitoring point is located at a distance of approximately five miles in each sector. Nine additional locations are distributed through the sectors out to a distance of approximately 32 miles. The TLDs are exchanged every 3 months and read with a Panasonic Model UD-710A automatic reader interfaced-with a computer system for analysis of the data.

Since the calcium sulfate phosphor is much more sensitive than the lithium borate, the measured exposure is taken as the median of the results obtained from the calcium sulfate phosphors in all detectors from the monitoring location. The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element.

The system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental applications of TLDs.

Results All results are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). The monitoring locations are grouped according to the distance from the plant. The first group consists of all locations within 1 mile of the plant. The second group lies between 1 and 2 miles, the third group between 2 and 4 miles, the fourth between 4 and 6 miles, and the fifth group is made up of all locations more than 6 miles from the plant. Past data have shown that the results from all monitoring points greater than 2 miles from the plant are essentially the same. Therefore, for purposes of this report, all locations 2 miles or less from the plant are identified as "onsite" stations and all others are considered "offsite."

The quarterly gamma radiation levels determined from the TLDs deployed around BFN in 2005 are summarized in Table H-1. The results from all measurements at individual locations are presented in Table H-2. The exposures are measured in milliroentgens. For purposes of this report, one milliroentgen (mR), one millirem (mrem), and one millirad are assumed to be numerically equivalent. The rounded average annual exposures are shown below.

Annual Average Direct Radiation Levels mR/Year BFN 2005 Onsite Stations 68 Offsite Stations 59 The data in Table H-1 indicate that the average quarterly radiation levels at the BFN onsite locations are approximately 2.3 mR/quarter higher than levels at the offsite locations. This difference is consistent with levels measured for preoperation and construction phases of TVA nuclear plant sites where the average radiation levels on site were generally 2-6 mR/quarter higher than the levels offsite. The causes of these differences have not been isolated; however, it is postulated that the differences are probably attributable to combinations of influences such as natural variations in environmental radiation levels, earth-moving activities onsite, and the mass of concrete employed in the construction of the plant. Other undetermined influences may also play a part.

Figure H-1 compares plots of the environmental gamma radiation levels from the onsite or site boundary locations with those from the offsite locations over the period from 1976 through 2005.

All results reported in 2005 are consistent with direct radiation levels identified at locations which are not influenced by the operation of BFN. There is no indication that BFN activities increased the background direct radiation levels normally observed in the areas surrounding the plant.

ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote. In the current program, five local air monitoring stations are located on or adjacent to the plant site in the general direction of greatest wind frequency. Three of these stations (LM-1, LM-2, and LM-3) are located on the plant side of the Tennessee River and two stations (LM-6 and LM-7) are located immediately across the river from the plant site. One additional station (station LM-4) is located at the point of maximum predicted offsite concentration of radionuclides based on meteorological data. Three perimeter air monitoring stations are located in communities out to about 13 miles from the plant, and two monitors used as controls are located out to 32 miles. The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A.

Results from the analysis of samples in the atmospheric pathway are presented in Tables H-3 and H-4. Radioactivity levels identified in this reporting period are consistent with background radioactivity levels.

Sample Collection and Analysis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch glass fiber filter. The sampling system consists of a pump, a magnehelic gauge for measuring the drop in pressure across the system, and a dry gas meter. This allows an accurate determination of the volume of air passing through the filter. The sampling system is housed in a metal building. The filter is contained in a sampling head mounted on the outside of the monitor building. The filter is replaced weekly. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks, composites of the filters from each location are analyzed by gamma spectroscopy.

Gaseous radioiodine is collected using a commercially available cartridge containing TEDA-impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air. Each cartridge is analyzed for I-131 by gamma spectroscopy analysis.

Rainwater is sampled by use of a collection tray attached to the monitor building. As water drains from the tray, it is collected in one of two 5-gallon jugs inside the monitor building.

A 1-gallon sample, or the total volume available if less than one gallon, is removed from the container every 4 weeks. Any excess water is discarded. Rainwater samples are analyzed only if the air particulate samples indicate the presence of elevated activity levels or if fallout is expected. No rainwater samples from the vicinity of BFN were required to be analyzed in 2005.

Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 2005 was consistent with levels reported in previous years. The average gross beta concentrations in samples collected at both indicator and control locations was 0.021 pCi/m 3 .

The annual averages of the gross beta activity in air particulate filters at these stations for the years 1968-2005 are presented in Figure H-2. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981.

Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986.

These patterns are consistent with data from monitoring programs conducted by TVA at other nuclear power plant sites during construction and preoperational stages.

Only naturally occurring radionuclides were identified by the monthly gamma spectral analysis of the air particulate samples.

There was no I-131 detected in any charcoal cartridge samples collected during 2005. The results for the analysis of charcoal cartridges are reported in Table H-4.

TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples of environmental media that may transport radioactive material from the atmosphere to humans. Samples of soil and food crops are collected and analyzed to determine the potential impacts from exposure to this pathway.

The results from the analysis of these samples are shown in Tables H-5 through H-ll.

A land use survey is conducted annually to locate milk producing animals and gardens within a 5-mile radius of the plant. No milk-producing animals have been identified within 5 miles of the plant. The results of the 2005 land use survey are presented in Appendix G.

Sample Collection and Analysis Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cutter" or an auger type sampler. After drying and grinding, the sample is analyzed by gamma spectroscopy. When the gamma analysis is complete, the sample is ashed and analyzed for Sr-89, 90.

Samples representative of food crops raised in the area near the plant are obtained from individual gardens, corner markets, or cooperatives. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. In 2005, samples of apples, cabbage, corn, green beans, potatoes, and tomatoes were collected from local gardens. The edible portion of each sample is analyzed by gamma spectroscopy.

Results The only fission or activation product identified in soil samples was Cs-i 37. The average concentration measured in samples from indicator locations was 0. 18 pCi/g. The average concentration for control locations was 0.07 pCi/g. These concentrations are consistent with levels previously reported from fallout. All other radionuclides reported were naturally occurring isotopes. The results of the analysis of soil samples are reported in Table H-5. A plot of the annual average Cs-137 concentrations in soil is presented in Figure H-3. The concentration of Cs-137 in soil is steadily decreasing as a result of the cessation of weapons testing in the atmosphere, the 30-year half-life of Cs-137 and transport through the environment.

Only naturally occurring radioactivity was identified in food crops. The predominant natural radionuclide detected in samples of food crops was K-40. Analyses of these samples indicated no contribution from plant activities. The results are reported in Tables H-6 through H-1i.

LIOUID PATHWAY MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of fish, and from direct radiation exposure to radioactive materials deposited in the river shoreline sediment.

The liquid pathway monitoring program conducted during 2005 included the collection of samples of surface (river/reservoir) water, groundwater, drinking water supplies, fish, and shoreline sediment. Samples from the reservoir are collected both upstream and downstream from the plant.

Results from the analysis of aquatic samples are presented in Tables H-12 through H-17.

Radioactivity levels in water and shoreline sediment were consistent with background levels previously reported. Trace levels of Cs-137 were identified in fish.

Sample Collection and Analysis Samples of surface water are collected from the Tennessee River using automatic sampling systems from one downstream station and one upstream station. The upstream sample is collected from the raw water intake at the Decatur, Alabama water plant and is utilized as control sampling location for both surface and drinking water. A timer turns on the system at least once every two hours. The line is flushed and a sample collected into a collection container. A 1-gallon sample is removed from the container every 4 weeks and the remaining water in the jug is discarded. The 4-week composite sample is analyzed by gamma spectroscopy and for gross beta activity. A quarterly composite sample is analyzed for tritium.

Samples are also collected by an automatic sampling system at the first downstream drinking water intake. This sample is collected at the intake for the water plant and is raw untreated water. These samples are collected in the same manner as the surface water samples.

These monthly samples are analyzed by gamma spectroscopy and for gross beta activity. A quarterly composite is analyzed for tritium.

At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. A quarterly composite sample from each station is analyzed for tritium.

A groundwater well onsite is equipped with an automatic water sampler. Water is also collected from a private well in an area unaffected by BFN. Samples from the wells are collected every 4 weeks and analyzed by gamma spectroscopy. A quarterly composite sample is analyzed for tritium.

Samples of commercial and game fish species are collected semiannually from each of two reservoirs: the reservoir on which the plant is located (Wheeler Reservoir) and the upstream reservoir (Guntersville Reservoir). The samples are collected using a combination of netting techniques and electrofishing. To sample edible portions of the fish, the fish are filleted. After drying and grinding, the samples are analyzed by gamma spectroscopy.

Shoreline sediment was collected from two downstream recreational use areas and one upstream location. The samples were collected at the normal water level shoreline and analyzed by gamma spectroscopy.

Results All radioactivity in surface water samples was below the detection limits except the gross beta activity and naturally occurring isotopes identified by gamma spectral analysis. These results are consistent with previously reported levels. A trend plot of the gross beta activity in surface. water samples from 1968 through 2005 is presented in Figure H-4. A summary table of the results for this reporting period is shown in Table H-12.

For drinking water (public water), gross beta activity averaged 2.5 pCi/liter at the downstream stations and 2.8 pCi/liter at control stations. These results are consistent with previous monitoring results. The results are shown in Table H-13 and a trend plot of the gross beta activity from 1968 to 2005 is presented in Figure H-5.

No fission or activation products were detected in groundwater samples from BFN REMP monitoring locations. Only naturally occurring radon decay products (Pb-214 and Bi-214) were identified in these samples. Results from the analysis of groundwater samples are presented in Table H-14.

Additional on site ground water monitoring locations were sampled during the year. These locations were not part of BFN REMP. The purpose of these shallow wells was to monitor for potential leaks from plant equipment such as storage tanks and discharge lines. Trace levels of tritium were detected in two of these monitoring locations. Investigations are ongoing to identify the source of the tritium.

Trace levels of Cs-137 were identified in three fish samples. These concentrations were consistent with data from previous monitoring years. The only other isotopes found in fish were naturally occurring radionuclides. The results are summarized in Tables H-15 and H-16. Plots of the annual average Cs-137 concentrations in game fish are presented in Figure H-6.

Only naturally occurring radionuclides were identified by the gamma spectral analyses of samples of shoreline sediment. The results from the analysis of shoreline sediment are provided in Table H-17.

ASSESSMENT AND EVALUATION Potential doses to the public are estimated from measured effluents using computer models.

These models were developed by TVA and are based on methodology provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of a nuclear power plant. The results of the effluent dose calculations are reported in the Annual Radioactive Effluent Release Report. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum expected values which will tend to overestimate the dose to this "hypothetical" person. The calculated maximum dose due to plant effluents are small fractions of the applicable regulatory limits. In reality, the expected dose to actual individuals is significantly lower.

Based on the very low concentrations of radionuclides actually present in the plant effluents, radioactivity levels measured in the environment as a result of plant operations are expected to be negligible. The results for the radiological environmental monitoring conducted for the BFN 2005 operations confirm this expectation.

Results As stated earlier in the report, the estimated increase in radiation dose equivalent to the general public resulting from the operation of BFN is negligible when compared to the dose from natural background radiation. The results from each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences from the plant. During this report period, Cs-137 was identified in soil and fish samples. The distribution of Cs-137 in fish is consistent with fallout levels identified in samples during the preoperational phase of the monitoring program. The Cs-137 detected in soil was consistent with levels generally found in the environment as the result of past nuclear weapons testing.

Conclusions It is concluded from the above analysis of the environmental sampling results and from the trend plots presented in Appendix H that the exposure to members of the general public which may have been attributable to BFN is negligible. The radioactivity reported herein is primarily the results of fallout or natural background radiation. Any activity which may be present as a result of plant operations does not represent a significant contribution to the exposure of Members of the Public.

REFERENCES

1. Merril Eisenbud, Environmental Radioactivity. Academic Press, Inc., New York, NY, 1987.

2. National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposure of the Population of the United States," September 1987.

3. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instruction Concerning Risks from Occupational Radiation Exposure," July 1981.

S.

Table 1 COMPARISON OF PROGRAM LOWER LIMITS OF DETECTION WITH THE REGULATORY LIMITS FOR MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS AND REPORTING LEVELS Concentrations in Water. pCi/Liter Concentrations in Air. pCilCubic Meter Effluent Reporting Lower limit Effluent Reporting Lower limit Concentration' Level 2 of Detection 3 Concentration' Level2 of Detection 3 H-3 1,000,000 20,000 300 100,000 Cr-51 500,000 45 30,000 0.02 Mn-54 30,000 1,000 5 1,000 0.005 Co-58 20,000 1,000 5 1,000 0.005 Co-60 3,000 300 5 50 0.005 Zn-65 5,000 300 10 400 0.005 Sr-89 8,000 5 1,000 0.0011 Sr-90 500 2 6 0.0004 Nb-95 30,000 400 2,000 0.005 Zr-95 20,000 400 10 400 0.005 Ru-103 30,000 5 900 0.005 Ru-106 3,000 40 20 0.02 I-131 1,000 2 0.4 200 0.9 0.03 Cs-134 900 30 200 10 0.005 Cs-137 1,000 50 5 200 20 0.005 Ce-144 3,000 30 40 0.01 Ba-140 8,000 200 25 2,000 0.015 La-140 9,000 200 10 2,000 0.01 Note: 1pCi = 3.7 x10-2 Bq.

Note: For those reporting levels that are blank, no value is given in the reference.

1 Source: Table 2 of Appendix B to 10 CFR 20.

2 Source: BFN Offsite Dose Calculation Manual, Table 2.3-3.

3 Source: Table E-1 of this report.

Ill tAj Yl ID,

Figure 2 ENVIRONMENTAL EXPOSURE PATHWAYS OF MAN DUE TO RELEASES OF RADIOACTIVE MATERIAL TO THE ATMOSPHERE AND LAKE.

Airborne Releases 7 Plume Exposure Liquid Releases Diluted By Lake IJL MAN Animals Man 1S (Milk,Meat) Shoreline Exposure Consumed By Animals 8

] Drinking Water

]I Fish U Vegetation Uptake From Soil APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

1. AIRBORNE

a. Particulates Six samples from locations (in Continuous sampler operation with Analyze for gross beta radioactivity different sectors) at or near the site sample collection as required by dust greater than or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> boundary (LM-1, LM-2, LM-3, LM-4, loading but at least once per 7 days. following filter change. Perform LM-6, and LM-7). gamma isotopic analysis on each sample when gross beta activity is Two samples from control locations greater than 10 times the average of greater than 10 miles from the plant control samples. Perform gamma (RM-1 and RM-6). isotopic analysis on composite (by location) sample at least once per 31 o

l. Three samples from locations in days.

communities approximately 10 miles from the plant (PM-1, PM-2, and PM-3).

b. Radioiodine Same locations as air particulates. Continuous sampler operation with I-131 by gamma scan on each sample.

charcoal canister collection at least once per 7 days.

c. Rainwater Same locations as air particulates. Composite sample at least once per 31 Analyzed for gamma nuclides only if days. radioactivity in other media indicates the presence of increased levels of fallout

Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

d. Soil Samples from same locations as air Once every year. Gamma scan, Sr-89, Sr-90 once per particulates. year.

e. Direct Two or more dosimeters placed at At least once per 92 days. Gamma dose once per 92 days.

locations (in different sectors) at or near the site boundary in each of the 16 sectors.

Two or more dosimeters placed at At least once per 92 days. Gamma dose once per 92 days.

stations located approximately 5 I miles from the plant in each of the 16 sectors.

Two or more dosimeters in at least 9 additional locations of special interest.

2. WATERBORNE

a. Surface Water One sample upstream (TRM 306.0). Collected by automatic sequential- Gross beta and gamma scan on 4-One sample immediately downstream type sampler with composite sample week composite. Composite for of discharge (TRM 293.5). taken at least once per 31 daysc. tritium at least once per 92 days.

b. Drinking water One sample at the first potable Collected by automatic sequential- Gross beta and gamma scan on 4-surface water supply downstream type sampler with composite sample week composite. Composite for from the plant (TRM 286.5). taken at least once per 31 days'. tritium analysis at least once per 92 days.

Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM' Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

c. Drinking Water Four additional samples of potable Grab sample taken from water supply Gross beta and gamma scan on 4-(Continued) surface water downstream from the at a facility using water from the week composite. Composite for plant (TRM 282.6, TRM 274.9, public supply being monitored. tritium analysis at least once per 92 TRM 259.8 and TRM 259.6). Sample collected at least once per days.

31 days.

One sample at a control locationd Collected by automatic sequential- Same as downstream location.

(TRM 306). type sampler with composite sample taken at least once per 31 days'.

d. Groundwater One sample adjacent to the plant Collected by automatic sequential- Gamma scan on each composite.

I (Well No. 6). type sampler with composite sample Composite for tritium analysis at taken at least once per 31 days. least once per 92 days.

One sample at a control location Grab sample taken at least once per Gamma scan on each sample.

up gradient from the plant. 31 days. Composite for tritium analysis at least once per 92 days.

e. Shoreline Sediment One sample upstream from a At least once per 184 days. Gamma scan of each sample.

recreational area (TRM 305).

Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

e. Shoreline Sediment One sample from each of at least two At least once per 184 days. Gamma scan of each sample.

(Continued) downstream locations with recreational use (TRM 293 and 279.5).

4. INGESTION

a. Fish Two samples reprcsenting At least once per 184 days. Gam.ma scan at least once per 184 commercial and game species in days on edible portions.

I, Guntersville Reservoir above the plant.

Two samples representing commercial and game species in Wheeler Reservoir near the plant.

Table A-I BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

b. Fruits and Samples of food crops such as greens, At least once per year at time of Gamma scan on edible portion.

Vegetables corn, green beans, tomatoes, and harvest.

potatoes grown at private gardens and/or farms in the immediate vicinity of the plant.

One sample of each of the same foods grown at greater than 10 miles distance from the plant.

N.)

a. The sampling program outlined in this table is the program conducted during 2005.

b. Sample locations, sector and distance from plant, are described in Table A-2 and A-3 and shown in Figures A-l, A-2, and A-3.

c. Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

d. The sample location at the Decatur City Water Plant serves as a control sample for both surface water and drinking water.

Table A-2 BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (I)

Location Distance or Samples Number' Station Sector (Miles) Control (C) Collectedb 1 PM- I NW 13.8 I AP,CF,R,S 2 PM-2 NE 10.9 AP,CF,R,S.

3 PM-3 SSE 7.5 I AP,CF,R,S 4 LM-7 W 2.1 I AP,CF,R,S 5 RM-I W 31.0 I AP,CF,R,S 6 RM-6 E 23.4 C AP,CF,R,S 7 LM- I NNW 1.0 I AP,CF,R,S 8 LM-2 NNE 0.9 I AP,CF,R,S 9 LM-3 ENE 0.9 I AP,CF,R,S 10 LM-4 NNW 1.7 I AP,CF,R,S I

11 LM-6 SSW 3.0 AP,CF,R,S I

12 Farm B NNW 6.8 W I

22 Well No.6 NW 0.02 W I

23 TRMG282.6 1.4 d PW 24 TRM 306.0 - 12. od C PW, SW 25 TRM 259.6 - 34.4 d I PW 26 TRM 274.9 19.1d I PW 28 TRM 293.5 - 0 ,5 d I SW 70 TRM 259.8 - 34,2d I PW 71 TRM 286.5 - 7.5d I PW 72 TRM 305 - C SS 1.0d 73 TRM 293 I SS 74 TRM 279.5 145 d I SS Wheeler Reservoir (TRM 275-349) I F Guntersville Reservoir (TRM 349-424) C F

a. See Figures A-i, A-2, and A-3

b. Sample codes:

AP = Air particulate filter CF = Charcoal filter (Iodine) PW = Public drinking water F = Fish S = Soil SS = Shoreline sediment R = Rainwater W = Well water SW= Surface Water

c. TRM = Tennessee River Mile.

d. Miles from plant discharge at (TRM 294).

Table A-3 BROWNS FERRY NUCLEAR PLANT THERMOLUMINESCENT DOSIMETER (TLD) LOCATIONS Map Approximate Onsite (On Location Distance or Numbera Station Sector (miles) Offsite (Off)

I NW-3 NW 13.8 Off 2 NE-3 NE 10.9 Off 3 SSE-2 SSE 7.5 Off 5 W-3 W 31.0 Off 6 E-3 E 23.1 Off 7 N-i NNW 1.0 On 8 NNE-I NNE 0.9 On 9 ENE-i ENE 0.9 On 10 NNW-2 NNW 1.7 On 38 N-2 N 5.0 Off 39 NNE-2 NNE 0.7 On 40 NNE-3 NNE 5.2 Off 41 NE-I NE 0.8 On 42 NE-2 NE 5.0 Off 43 ENE-2 ENE 6.2 Off 44 E-I E 0.8 On 45 E-2 E 5.2 Off 46 ESE-I ESE 0.9 On 47 ESE-2 ESE 3.0 Off 48 SE-I SE 0.5 On 49 SE-2 SE 5.4 Off 50 SSE-I SSE 5.1 Off 51 S-i S 3.1 Off 52 S-2 S 4.8 Off 53 SSW-I SSW 3.0 Off 54 SSW-2 SSW 4.4 Off 55 SW-I SW 1.9 On 56 SW-2 SW 4.7 Off 57 SW-3 SW 6.0 Off 58 WSW-1 *WSW 2.7 Off 59 WSW-2 WSW 5.1 Off 60 WSW-3 WSW 10.5 Off 61 W-- W 1.9 On 62 W-2 W 4.7 Off 63 W-4 W 31.7 Off 64 WNW-I WNW 3.3 Off 65 WNW-2 WNW 4.4 Off 66 NW-I NW 2.2 Off 67 NW-2 NW 5.3 Off 68 NNW-I NNW 1.0 On 69 NNW-3 NNW 5.2 Off 75 N-IA N 1.0 On

a. See Figures A-i, A-2, and A-3.

b. TLDs designated "onsite" are those located 2 miles or less from the plant.

TLDS designated "offsite" are those located more than 2 miles from the plant.

Figure A-1 Radiological Environmental Monitoring Locations Within 1 Mile of Plant 5

348.75 N 112 326.2 7 - 33.75 8 NE ESE

/BOWNS FERR5; ,101.25

/

V4<t NCLEAR PLA N i-S SSE Scale Io Mile 1 Figure A-2 Radiological Environmental Monitoring Locations From 1 to 5 Miles from the Plant Figure A-3 Radiological Environmental Monitoring Locations Greater than 5 miles from the Plant APPENDIX B 2005 PROGRAM MODIFICATIONS APPENDIX B Radiological Environmental Monitoring Program Modifications There were no modifications to the BFN REMP during 2005.

APPENDIX C PROGRAM DEVIATIONS APPENDIX C Program Deviations During 2005, problems with sampling equipment resulted in sample unavailability or inadequate sample volumes for three sets of air particulate filter and charcoal cartridge samples. Table C-1 provides additional details on these program deviations.

Table C-I Radiological Environmental Monitoring Program Deviations Date Station Location' Remarks 01/31/05 LM-7 2.1 miles W The total sample volume for air filter and charcoal cartridge samples was not adequate due to a problem with the sampling pump. The problem was a broken drive belt. The belt was replaced and the system returned to normal operation for the next sampling cycle. The missed samples were documented with PER 75851.

"S 05/02/05 LM-6 3.0 miles SSW The total sample volume for air filter and charcoal cartridge samples was not adequate due to a failure of the sampling pump. The pump was replaced and the sampler was restored to normal operation for the next sampling cycle. The missed samples were documented with PER 81888.

12/19/05 RM-1 31.0 miles W The total sample volume for the air filter and charcoal cartridge samples was not adequate due to a problem with the sampling system. The problem was a broken drive belt. The belt was replaced and the system was returned to normal operation for the next sampling cycle. The missed samples were documented with PER 94343.

APPENDIX D ANALYTICAL PROCEDURES Appendix D Analytical Procedures Analyses of environmental samples are performed by the radioanalytical laboratory located at the WARL facility in Muscle Shoals. All analysis procedures are based on accepted methods. A summary of the analysis techniques and methodology follows.

The gross beta measurements are made with an automatic low background counting system.

Normal counting times are 50 minutes. Water samples are prepared by evaporating 500 ml of samples to near dryness, transferring to a stainless steel planchet and completing the evaporation process. Air particulate filters are counted directly in a shallow planchet.

After a radiochemical separation, samples analyzed for Sr-89, 90 are counted on a low background beta counting system. The sample is counted a second time after a 7-day ingrowth period. From the two counts the Sr-89 and Sr-90 concentrations can be determined.

Water samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation. A commercially available scintillation cocktail is used.

Gamma analyses are performed in various counting geometries depending on the sample type and volume. Gamma counts are obtained with germanium detectors interfaced with a computer based multichannel analyzer system. Spectral data reduction is performed by the computer program HYPERMET.

The charcoal cartridges used to sample gaseous radioiodine were analyzed by gamma spectroscopy using a high resolution spectroscopy system with germanium detectors.

The necessary efficiency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system. A series of daily and periodic quality control checks are performed to monitor counting instrumentation. System logbooks and control charts are used to document the results of the quality control checks.

APPENDIX E NOMINAL LOWER LIMITS OF DETECTION (LLD)

Appendix E Nominal Lower Limits of Detection (LLD)

A number of factors influence the LLD for a specific analytical method, including sample size, count time, count efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the sample. The most probable values for these factors have been evaluated for the various analyses performed in the environmental monitoring program. The nominal LLDs are calculated from these values in accordance with the methodology prescribed in the ODCM. These nominal LLD values are presented in Table E-1. The maximum values for the lower limits of detection specified in the ODCM are shown in Table E-2. Milk samples are not currently collected and analyzed for the BFN REMP, but the nominal LLD values for the analysis of milk are included in the tables to maintain the historical record of the laboratory's measurement capabilities.

The nominal LLDs are also presented in the data tables. For analyses for which nominal LLDs have not been established, a LLD of zero is assumed in determining if a measured activity is greater than the nominal LLD.

TABLE E-l Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk Wet Vegetation and Soil (pCi/Of3 (pCi/U (pCi/Lh (pCi/Kg wet) (pCi/Q dry)

Gross Beta 0.002 1.9 Tritium 300 Iodine-131 0.4 0.4 6.0 Strontium-89 5.0 3.5 31.0 1.6 Strontium-90 2.0 2.0 12.0 0.4 II 0o

Table E-l Nominal LLD Values B. Gamma Analyses (GeLi)

Foods Air Charcoal Water Vegetation Wet Soil and Tomatoes Particulates Filter And Milk and Grain Vegetation Sediment Fish Clam Flesh Potatoes, etc.

pCi/m3_ pCi/mr3 pCi/L pCi/g. dry pCi/kg. wet pCi/g. dry pCi/g. dry pCi/g. dry pCi/kg. wet Ce-141 .005 .02 10 .07 35 .10 .07 .35 20 Ce-144 .01 .07 30 .15 115 .20 .15 .85 60 Cr-51 .02 0.15 45 .30 200 .35 .30 2.4 95 I-131 .005 0.03 10 .20 60 .25 .20 1.7 20 Ru-103 .005 0.02 5 .03 25 .03 .03 .25 25 Ru-106 .02 0.12 40 .15 190 .20 .15 1.25 90 Cs-134 .005 0.02 5 .03 30 .03 .03 .14 10 I .15 10 Cs-137 .005 0.02 5 .03 25 .03 .03 Zr-95 .005 0.03 10 .05 45 .05 .05 .45 45 Nb-95 .005 0.02 5 .25 30 .04 .25 .25 10 Co-58 .005 0.02 5 .03 20 .03 .03 .25 10 Mn-54 .005 0.02 5 .03 20 .03 .03 .20 10 Zn-65 .005 0.03 10 .05 45 .05 .05 .40 45 Co-60 .005 0.02 5 .03 20 .03 .03 .20 10 K-40 .04 0.30 100 .40 400 .75 .40 3.50 250 Ba-140 .015 0.07 25 .30 130 .30 .30 2.4 50 La-140 .01 0.04 10 .20 50 .20 .20 1.4 25 Fe-59 .005 0.04 10 .08 40 .05 .08 .45 25 Be-7 .02 0.15 45 .25 200 .25 .25 1.9 90 Pb-212 .005 0.03 15 .04 40 .10 .04 .30 40 Pb-214 .005 0.07 20 .50 80 .15 .50 .10 80 Bi-214 .005 0.05 20 .10 55 .15 .10 .50 40 Bi-212 .02 0.20 50 .25 250 .45 .25 2.0 130 TI-208 .002 0.02 10 .03 30 .06 .03 .25 30 Ra-224 .75 Ra-226 .15 Ac-228 .01 0.07 20 .10 70 .25 .10 .75 50

Table E-2 Maximum Values for the Lower Limits of Detection (LLD)

Specified by the BFN Offsite Dose Calculation Manual Airborne Particulate Food Water or Gases Fish Milk Products Sediment Analysis pCi/L p~/3 pCi/ku wet pCi/L pCi/kg. wet pCift, dry gross beta 4 1 x 10-2 N.A. N.A. N.A. N.A.

H-3 2000a N.A. N.A. N.A. N.A. N.A.

Mn-54 15 N.A. 130 N.A. N.A. N.A.

Fe-59 30 N.A. 260 N.A. N.A. N.A.

Co-58, 60 15 N.A. 130 N.A. N.A. N.A.

Zn-65 30 N.A. 260 N.A. N.A. N.A.

Zr-95 30 N.A. N.A. N.A. N.A. N.A.

Nb-95 15 N.A. N.A. N.A. N.A. N.A.

I-131 7 x 10 2 N.A. 1 60 N.A.

Cs-134 15 5 x1O2 130 15 60 150 Cs-137 18 6x 10-2 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A.

La-140 15 N.A. N.A. 15 N.A. N.A.

a. If no drinking water pathway exists, a value of 3000 pCi/liter may be used.

b. LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/liter. If levels greater than 15 pCi/liter are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/liter for I-131.

APPENDIX F QUALITY ASSURANCE/QUALITY CONTROL PROGRAM Appendix F Quality Assurance/Quality Control Program A thorough quality assurance program is employed by-the laboratory to ensure that the environmental monitoring data are reliable. This program includes the use of written, approved procedures in performing the work, provisions for staff training and certification, internal self assessments of program performance, audits by various external organizations, and a laboratory quality control program.

The quality control program employed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as intended. The program includes equipment checks and the analysis of quality control samples along with routine samples. Instrument quality control checks include background count rate and counts reproducibility. In addition to these two general checks, other quality control checks are performed on the variety of detectors used in the laboratory. The exact nature of these checks depends on the type of device and the method it uses to detect radiation or store the information obtained.

Quality control samples of a variety of types are used by the laboratory to verify the performance of different portions of the analytical process. These quality control samples include blanks, replicate samples, blind samples, or cross-checks.

Blanks are samples which contain no measurable radioactivity or no activity of the type being measured. Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured.

Duplicate samples are generated at random by the sample computer program which schedules the collection of the routine samples. For example, if the routine program calls for four public water samples every four weeks, on a random basis each location might provide an additional sample several times a year. These duplicate samples are analyzed along with other routine samples.

They provide information about the variability of radioactive content in the various sample media.

If enough sample is available for a particular analysis, the laboratory staff can split it into two portions. Such a sample provides information about the variability of the analytical process since two identical portions of material are analyzed side by side.

Analytical knowns are another category of quality control sample. A known amount of radioactivity is added to a sample medium. The lab staff knows the radioactive content of the sample. Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run. In this way, analytical knowns provide immediate data on the quality of the measurement process. A portion of these samples are also blanks.

Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples. The lab staff does not know the sample contains radioactivity. Since the bulk of the ordinary workload of the environmental laboratory contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or can be used to test the data review process. If an analysis routinely generates numerous zeroes for a particular isotope, the presence of the isotope is brought to the attention of the laboratory supervisor in the daily review process.

Blind spikes test this process since the blind spikes contain radioactivity at levels high enough to be detected. Furthermore, the activity can be put into such samples at the extreme limit of detection (near the LLD) to determine whether or not the laboratory can find any unusual radioactivity whatsoever.

Another category of quality control samples is internal cross-checks. These samples have a known amount of radioactivity added and are presented to the lab staff labeled as cross-check samples. This means that the quality control staff knows the radioactive content or "right answer" but the lab personnel performing the analysis do not. Such samples test the best performance of the laboratory by determining if the lab can find the "right answer". These samples provide information about the accuracy of the measurement process. Further information is available about the variability of the process if multiple analyses are requested on the same sample. Like blind spikes or analytical knowns, these samples can also be spiked with low levels of activity to test detection limits. During 2005, all analysis results for internal cross-check samples were within agreement limits when compared to the known value.

To provide for an independent verification of the laboratory's ability to make accurate measurements, the laboratory participated in an environmental level cross-check program available through Analytics, Inc., during 2005. The results of TVA's participation in this cross-check program are presented in Table F-1.

The quality control data are routinely collected, examined and reported to laboratory supervisory personnel. They are checked for trends, problem areas, or other indications that a portion of the analytical process needs correction or improvement. The end result is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.

Table F-I Results For 2005 External Cross Checks Test Period Sample Type / Analysis Results 3 Sigma Range Known TVA First Quarter Water (pCi/L)

H-3 6040 6070 4228 7852 First Quarter Water (pCi/L)

Gross Beta 131 132 111 151 First Quarter Water (pCi/L) 131i 66 76 51 - 81 141 Ce 221 220 188 - 254 322 323 225 419 134Cs 134 125 114 154 58 125 129 106 144 Co 111 114 94 - 128 4

s Mn 154 165 131 177 59 65 Fe 107 104 91 - 123 Zn 191 195 134 - 248 60 co 139 145 118 - 160 First Quarter Milk (pCi/L) 131i 82 79 67 97 89 Sr 85 94 70 100 90 Sr 14 9 0 29 Third Quarter Sand (pCi/grarn) 141 Ce 0.340 0.335 0.289 - 0.391 5'Cr 34 0.493 0.452 0.345 - 0.641 1 cs 0.178 0.183 0.151 - 0.205 37

' Cs 0.284 0.279 0.241 - 0.327 0.092 0.090 0.073 - 0.111 54 Mn 0.134 0.147 0.114 - 0.154 9

5 65 Fe 0.089 0.086 0.070 - 0.108 Zn 0.126 60 0.180 0.190 - 0.234 Co 0.244 0.240 0.207 - 0.281 Third Quarter Air Filter (pCi/filter)

Gross Beta 140 133 119 161 Third Quarter Air Filter (pCi/filter) 141Ce 163 154 139 187 5'Cr 236 250 165 307

' 34 37 Cs 86 72 71 101 1 cS 136 135 116 156 58 Co 44 44 29 59 54 67 Mn 64 49 79 59 65 Fe 43 42 28 58 Zn 86 84 60 112 6oCO 117 115 99 135 Third Quarter Water (pCi/L)

H-3 4190 4360 2933 5447 APPENDIX G LAN) USE SURVEY Appendix G Land Use Survey A land use survey was conducted to identify the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant. The land use survey also identifies all gardens of greater than 500 square feet producing fresh leafy vegetables within a distance of 3 miles from the plant.

The land use survey was conducted between April 1 and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

In order to identify the locations around BFN which have the greatest relative potential for impact by the plant, radiation doses were projected for individuals living near BFN. These projections used the data obtained in the survey and historical meteorological data. The calculations also assumed that releases were equivalent to the design basis source terms. The dose projections are relative in nature and do not reflect actual exposures to individuals living near BFN.

Dose projections from air submersion were calculated for the nearest resident in each sector and dose projections from eating foods produced near the plant were calculated for the areas with gardens.

There were no changes in the distance for the location of the nearest resident in 2005 as compared to 2004. The location of the nearest garden as identified in the 2005 survey changed in a total of three sectors compared to the locations identified in 2004.

There were no locations identified within the five mile radius with milk production for human consumption.

Tables G-1 and G-2 show the comparative calculated doses for 2004 and 2005.

Table G-1 ROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within 8 Iom (5 Miles) of Plant mrern/year 2004 Survey 2005 Survey Approximate Approximate Distance Annual Distance Annual Sector Meters Dose Meters Dose N 2000 0.45 2000 0.45 NNE 2590 0.14 2590 0.14 NE 4096 0.12 4096 0.12 ENE 2458 0.17 2458 0.17 E 1290 0.47 1290 0.47 ESE 1860 0.22 1860 0.22 SE a a SSE a a S 4482 0.15 4482 0.15 SSW 4169 0.18 4169 0.18 SW 4458 0.10 4458 0.10 WSW 3976 0.08 3976 0.08 W 2530 0.19 2530 0.19 WNW 5470 0.10 5470 0.10 NW 3373 0.30 3373 0.30 NNW 1639 0.76 1639 0.76 Note a - There is no residence within the 8 km radius for this section Table G-2 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods mrem/year 2004 Survey 2005 Survey Approximate Approximate Number of Distance Annual Distance Annual Gardens Within Sector -Meters Dose Meters Dose 3 miles (2004)

N 4572 2.64 4572 2.64 1 NNE 5940 0.89 5940 0.89 1 NE 4313 1.27 4313 1.27 I ENE 4319 1.33 4319 1.33 1 E 4340 1.75 2286 4.03 ESE 2125 5.03 2125 5.03 2 as 01 a a 0 Co SE I 0 SSE a a S 4482 2.28 4482 2.28 1 SSW 4169 2.68 4959 2.09 1 SW 4458 1.15 4458 1.15 1 WSW 4578 0.56 4578 0.56 1 W 2977 1.15 2995 1.14 1 WNW a a 0 NW a a 0 NNW 1791 9.95 1791 9.95 2 note a - Garden not found within 8 km radius.

APPENDIX H DATA TABLES AND FIGURES Table H - 1 DIRECT RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from BROWNS FERRY Nuclear Plant for Each Quarter - 2005 mR / Quarter (a)

Distance per annum Miles Average External Gamma Radiation Levels (b) mR/yr 1st qtr 2nd qtr 3rd qtr

• 4 qtr 0-1 18.2+/-1.2 14.7 +/- 1.2 17.6 +/- 0.9 18.8 +/- 1.0 69 1 -2 1-7.0+/- 1.2 13.0 +/- 1.3 16.1 +/- 1.0 17.3 +/- 1.1 63 2-4 15.7 +/- 1.3 11.8 +/- 1.1 14.7 +/- 1.0 16.2 +/- 0.8 58 4-6 15.4+/- 1.0 11.8 +/- 0.8 14.9 +/- 0.9 16.6 +/- 0.7 59

>6 15.5+/-0.9 11.7 +/- 1.0 15.0 +/- 0.9 16.4 +/- 0.7 59

Average, 0 - 2 miles 17.9 +/- 1.3 14.3 +/- 1.5 17.3 +/- 1.1 18.5 +/- 1.2 68 (onsite)

Average,

> 2 miles 15.5 1.0 11.8 +/- 1.0 14.9 +/- 0.9 16.5 +/- 0.8 59 (offsite)

(a) Field periods normalized to one standard quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)

(b) Average of the individual measurements in the set +/- 1 standard deviation of the set

< , Co0N _ N co oO NON 0C0OCOtCOct nO C o N OsO rI L cNXNO 0O g' O Co oo 0 4 o - 0 N N MoN a N 0 CO C O N 0 0 o ' C OOI CD0r- r-C 0CD O CC OCO L O C 0 Nt i s - T' v_

CvL 7,

a. fi 0- co 0~ w0 co w 0 cs N Mco Mr c> N Mr- M co .s _ 0 C6 C6 t--4 6 6 6 6 C6 4 6 6 i t6 4 ui 6 6

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-J 6-c cll 1 _1 CC4 N w .22a)

) i n °) q oq °irlo.0 N OR o i q NIOR N C4 0 O.Lo qt Lo LO U7 ) CD vsZ, co M o M , L6 u6 t: v N zn ui c

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aC N MDC N. co00_

N ' DD

'- - '-0 M 00 xaj iDi.0 2:1 _ 6 C>w LllUj U >_Nn>

Qn z ZzzZUZj wi Un ts] M e ML CL.-

TABLE H - 2 continued DIRECT RADIATION LEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels mR / quarter Map TLD Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station Direction, Distance, Jan - Mar Apr - Jun Jul - Sep Oct - Dec Exposure Number Number degrees miles 2005 2005 2005 2005 mR/Year 52 S-2 182 4.8 14.0 10.2 13.4 15.3 52.8 53 SSW-1 203 3.0 13.8 10.4 13.6 15.2 53.1 54 SSW-2 199 4.4 15.1 11.2 15.0 17.1 58.4 55 SW-1 228 1.9 15.7 12.2 15.2 16.3 59.5

56. SW-2 219 4.7 15.6 11.7 15.2 16.4 58.9 57 SW-3 224 6.0 14.0 10.7 14.2 15.8 54.7 58 WSW-1 244 2.7 14.8 10.2 13.3 15.5 53.8 59 WSW-2 251 5.1 16.5 12.5 15.4 17.5 61.9 60 WSW-3 257 10.5 15.4 10.8 13.9 15.8 55.8 61 W-1 275 1.9 16.6 12.0 15.6 16.6 60.8 62 W-2 268 4.7 14.2 11.2 13.9 16.0 55.3 5 W-3 275 31.3 14.8 10.8 14.7 15.9 56.2 63 W-4 265 32.1 15.8 11.9 15.5 15.8 59.0 64 WNW-1 291 3.3 15.7 12.1 14.5 16.5 58.8 65 WNW-2 293 4.4 15.5 11.2 14.3 16.2 57.2 66 NW-1 326 2.2 18.1 13.3 16.3 (1) 63.5 67 NW-2 321 5.3 16.9 12.2 16.0 17.4 62.5 1 NW-3 310 13.8 14.4 10.3 13.4 15.5 ,53.6 68 NNW-1 331 1.0 17.4 13.6 16.8 18.0 65.8 10 NNW-2 331 1.7 18.7 14.8 17.6 18.8 69.9 69 NNW-3 339 5.2 17.2 12.4 15.6 17.6 62.7 Note: (1) Sum of available quarterly data normalized to 1 year for the annual exposure value.

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY INAIR FILTER PCI/M3 - 0.037 BQ/M3 Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260.296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GROSS BETA 580 2.00E-03 2.11E-02 (475/475) LM2 BF NORTH 2.15E-02 (53 / 53) 2.09E-02 (105/105) 8.23E 4.09E-02 0.9 MILE NNE 9.81E 3.62E-02 9.87E-03 - 3.92E-02 GAMMA SCAN (GELI) 154 AC-228 11.00E-02 126 VALUES < LLD PM-3 BF DECATUR AL 14 VALUES < LLD 1.95E-02 (1 / 28) 8.2 MILES SSE 1.95E 1.95E-02 BE-7 2.00E-02 1.04E-01 (126/126) PM-1 ROGERSVILLE AL 1.07E-01 (14 / 14) 1.01E-01 (28 / 28) 7.43E 1.41E-01 13.8 MILES NW 8.75E 1.36E-01 7.58E 1.32E-01 H

Bl-214 5.OOE-03 1.11E-02 (73/126) LM-7BF LAKEVIEW 1.39E-02 (9/ 14) 1.39E-02 (17 / 28) M.

Ed 5.20E 5.32E-02 2.1 MILES WEST 5.60E 5.32E-02 5.50E 4.21E-02 t-4 VI K-40 4.OOE-02 4.87E-02 (2 / 126) LM4 BF TRAILER P 5.38E-02 (1/ 14) 1.14E-01 (1/ 28) 4.36E 5.38E-02 1.7 MILES NNW 5.38E 5.38E-02 1.14E-01 - 1.14E-01 I W

PB-214 5.OOE-03 1.13E-02 (75/126) LM-7BF LAKEVIEW 1.36E-02 (10 / 14) 1.44E-02 (16 / 28) 5.30E 5.57E-02 2.1 MILES WEST 5.80E 5.57E-02 5.50E 3.70E-02 TL-208 2.OOE-03 126 VALUES < LLD PM-3 BF DECATUR AL 14 VALUES < LLD 7.60E-03 (1 / 28) 8.2 MILES SSE 7.60E-03 - 7.60E-03 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN CHARCOAL FILTER PCI/M3 - 0.037 BQ/M3 Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 580 BI-214 5.OOE-02 6.89E-02 (11 / 475) LMI BF NORTHWEST 9.97E-02 (1 / 53) 5.67E-02 (1 1105) 5.07E 1.01E-01 1.0 MILE N 9.97E 9.97E.02 5.67E 5.67E-02 1-131 3.OOE-02 SEE NOTE 3 K-40 3.OOE-01 3.35E-01 (8 / 475) LM-6BF BAKER BOTTOM 3.47E-01 (2/52) 3.24E-01 (2 /105) 3.13E 3.52E-01 3.0 MILES SSW 3.43E 3.51E-01 3.20E 3.29E-01 PB-212 3.OOE-02 3.48E-02 (11 475) LM4 BF TRAILER P 3.48E-02 (I / 53) 105 VALUES < LLD 3.48E 3.48E-02 1.7 MILES NNW 3.48E 3.48E-02 PB-214 7.OOE-02 8.96E-02 (7 /475) LM2 BF NORTH 1.06E-01 (2 / 53) 105 VALUES < LLD 7.02E 1.39E-01 0.9 MILE NNE 7.24E 1.39E-01 TI Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location Is indicated in parentheses (F).

Note: 3. The analysis of Charcoal Filters was performed by Gamma Spectroscopy. No 1-131 was detected. The LLD for 1-131 by Gamma Spectroscopy was 0.03 pCi/cubic meter.

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN SOIL PCI/GM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 11 AC-228 2.50E-01 1.20E+00 (9 /9) LM4 BF TRAILER P 1.41E+00 (I 1) 8.72E-01 (2 /2) 7.1OE-01 1.41E+00 1.7 MILES NNW 1.41E+00 - 1.41E+00 6.26E-01 - 1.12E+00 BE-7 2.50E-01 9 VALUES < LLD PM-3 BF DECATUR AL 1 VALUES < LLD 2.80E-01 (1/ 2) 8.2 MILES SSE 2.80E 2.80E-01 BI-212 4.50E-01 1.31E+00 (9/9) LM4 BF TRAILER P 1.72E+00 (1/ 1) 9.93E-01 (2/2) 7.27E 1.72E+00 1.7 MILES NNW 1.72E+00 - 1.72E+00 7.19E-01 - 1.27E+00 BI-214 1.50E-01 9.91E-01 (9/9) LM4 BF TRAILER P 1.20E+00 (1/1) 1.16E+00 (2/2) 6.78E 1.20E+00 1.7 MILES NNW 1.20E+00 - 1.20E+00 6.87E-01 - 1.62E+00 3.OOE-02 1.76E-01 (9/9) PM-2 BF ATHENS AL 3.87E-01 (1 / 1) 6.86E-02 (2/2) H-1 I CS-137 cr 6.31E 3.87E-01 10.9 MILES NE 3.87E-01 - 3.87E-01 6.68E-02 - 7.03E-02 Itz1 K-40 7.50E-01 5.45E+00 (9/9) LM4 BF TRAILER P 7.44E+00 (1I 1) 4.58E+00 (2/2) 3.18E+00 - 7.44E+00 1.7 MILES NNW 7.44E+00 - 7.44E+00 2.92E+00 - 6.24E+00 Lu PB-212 1.OOE-01 1.19E+00 (9/9) PM-3 BF DECATUR AL 1.44E+00 (1 i) 9.08E-01 (2/2) 6.84E-01 - 1.44E+00 8.2 MILES SSE 1.44E+00 - 1.44E+00 6.28E-01 - 1.19E+00 PB-214 1.50E-01 1.06E+00 (9/ 9) LM4 BF TRAILER P 1.19E+00 (1 /1) 1.27E+00 (2 2) 7.79E-01 - 1.19E+00 1.7 MILES NNW 1.19E+00 - 1.19E+00 7.48E-01 - 1.79E+00 RA-224 7.50E-01 1.27E+00 (5/ 9) PM-3 BF DECATUR AL 1.43E+00 (1 / 1) 1.34E+00 (1/2) 9.37E-01 - 1.43E+00 8.2 MILES SSE 1.43E+00 - 1.43E+00 1.34E+00 - 1.34E+00 RA-226 1.50E-01 9.91E-01 (9/9) LM4 BF TRAILER P 1.20E+00 (1/1) 1.16E+00 (2 /2) 6.78E-01 - 1.20E+00 1.7 MILES NNW 1.20E+00 - 1.20E+00 6.87E-01 - 1.62E+00 TL-208 6.OOE-02 3.88E-01 (9/ 9) LM4 BF TRAILER P 4.78E-01 (1 / 1) 2.86E-01 (2 /2) 2.33E-01 - 4.78E-01 1.7 MILES NNW 4.78E 4.78E-01 2.09E-01 - 3.62E-01 SR 89 11 1.60E+00 9 VALUES <LLD 2 VALUES < LLD SR 90 11 4.OOE-01 9 VALUES <LLD 2 VALUES < LLD Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - I Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated In parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY INAPPLES PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259.260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 BI-214 4.OOE+01 6.18E+01 (I / 1) LM-6BF BAKER BOTTOM 6.18E+01 (1/ 1) 1 VALUES <LLD 6.18E+01 - 6.18E+01 3.0 MILES SSW 6.18E+01 - 6.18E+01 K-40 2.50E+02 9.26E+02 (1/ 1) LM-6BF BAKER BOTTOM 9.26E+02 (1 / 1) 8.38E+02 (1 / 1) 9.26E+02 - 9.26E+02 3.0 MILES SSW 9.26E+02 - 9.26E+02 8.38E+02 - 8.38E+02 H

a% t-1 oo M T

M Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - I Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated In parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN CABBAGE PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 BI-214 4.00E+01 1 VALUES < LLD LM-6BF BAKER BOTTOM 1 VALUES < LLD 6.91E+01 (1 1 1) 3.0 MILES SSW 6.91E+01 - 6.91E+01 K-40 2.50E+02 1.84E+03 (1 I 1) LM-6BF BAKER BOTTOM 1.84E+03 (11/1) 1.67E+03 (11/ 1) 1.84E+03 - 1.84E+03 3.0 MILES SSW 1.84E+03 - 1.84E+03 1.67E+03 - 1.67E+03 as o1

-11

-4 Note: 1. Nominal Lower Level of Detection (LLD) as described In Table E - I Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN CORN PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 K40 2.50E+02 2.13E+03 (1/1) LM-6BF BAKER BOTTOM 2.13Et03 (I/ 1) 2.16E+03 (I1 1) 2.13E+03 - 2.13E+03 3.0 MILES SSW 2.13Ei03 - 2.13E+03 2.16E+03 - 2.16E+03 H

L-1 cc Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location Is Indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN GREEN BEANS PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 K-40 2.50E+02 3.28E+03 (I I 1) LM-6BF BAKER BOTTOM 3.28E+03 (1 / 1) 1.63E+03 (1 / 1) 3.28E+03 - 3.28E+03 3.0 MILES SSW 3.28E+03 - 3.28E+03 1.63E+03 - 1.63E+03 H

t- 4, t frI W.

Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is Indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Westem Area Radiological Laboratory RADIOACTIVITY IN POTATOES PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Deteclion Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 K40 2.50E+02 2.29E+03 (1/1) LM4 BF TRAILER P 2.29E+03 (1I 1) 3.49E+03 (1I 1) 2.29E+03 - 2.29E+03 1.7 MILES NNW 2.29E+03 - 2.29E+03 3.49E+03 - 3.49E+03 I

-i N.)

I t-.

0 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is Indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN TOMATOES PCI/KG - 0.037 BQIKG (WET WT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 K40 2.50E+02 2.43E+03 (111) LM4 BF TRAILER P 2.43E+03 (I/ 1) 2.26E+03 (11 1) 2.43E+03 - 2.43E+03 1.7 MILES NNW 2.43E+03 - 2.43E+03 2.26E+03 - 2.26E+03 i-3 r-,

M W

I I.-

Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY INSURFACE WATER(Total)

EIII PCI/L - 0.037 BQ/L Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed

• See Note 1 See Note 2 See Note 2 See Note 2 Measurements GROSS BETA 26 1.90E+00 2.76E+00 (9/13) TRM 293.5 2.76E+00 (9/ 13) 2.79E+00 (7 / 13) 2.06E+00 - 3.88E+00 2.06E+00 - 3.88E+00 2.02E+00 - 3.50E+00 GAMMA SCAN (GELI) 26 Bl-214 2.OOE+01 13 VALUES < LLD TRM 293.5 13 VALUES < LLD 2.30E+01 (1 / 13) 2.30E+01 - 2.30E+01 TRITIUM 8 3.OOE+02 4 VALUES < LLD 4 VALUES < LLD I

tzl I'

Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - I Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN PUBLIC WATER(Total)

PCI/L - 0.037 BQIL Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine

• of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GROSS BETA 78 1.90E+00 2.52E+00 (37 / 65) W MOR-E LAWR WAT ATH 2.78E+00 (7/ 13) 2.79E+00 (7 / 13) 1.90E+00 - .4.40E+00 TRM 286.5 1.93E+00 - 4.40E+00 2.02E+00 - 3.50E+00 GAMMA SCAN (GELI) 78 Bl-214 2.OOE+01 2.40E+01 (3 / 65) WHEELER DAM, AL 2.44E+01 (2/13) 2.30E+01 (1/13) 2.09E+01 - 2.78E+01 TRM 274.9 2.09E+01 - 2.78E+01 2.30E+01 - 2.30E+01 PB-214 2.00E+01 2.09E+01 (1/ 65) WHEELER DAM, AL 2.09E+01 (1 / 13) 13 VALUES < LLD 2.09E+01 - 2.09E+01 TRM 274.9 2.09E+01 - 2.09E+01 TRITIUM 24 3.OOE+02 20 VALUES < LLD 4 VALUES < LLD tri I).

Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is Indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN WELL WATER(Total)

PCI/L - 0.037 BQ/L Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine f?

of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GEL) 26 BI-214 2.OOE+01 13 VALUES < LLD BFN WELL #6 13 VALUES < LLD 5.59E+01 (12/13) 0.02 MILES W 2.01E+01 - 1.42E+02 PB-214 - 2.OOE+01 13 VALUES < LLD BFN WELL #6 13 VALUES < LLD 5.46E+01 (12/13) 0.02 MILES W 2.24E+01 - 1.41E+02 TRITIUM 8 3.OOE+02 4 VALUES < LLD 4 VALUES < LLD I . t Ml M i If Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN COMMERCIAL FISH PCI/GM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 4 B1-214 1.OOE-01 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 1.01E-01 (1/2)

TRM 275-349 1.01E 1.01E-01 CS-137 3.OOE-02 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 6.37E-02 (1 / 2)

TRM 275-349 6.37E 6.37E-02 K-40 4.OOE-01 1.36E+01 (2 / 2) WHEELER RES 1.36E+01 (2 / 2) 1.53E+01 (2/2) 1.28E+01 - 1.44E+01 TRM 275-349 1.28E+01 - 1.44E+01 1.44E+01 - 1.62E+01

-14

~-4 tIT r~n I-.

Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN GAME FISH PCI/GM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Delection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 4 BI-214 1.OOE-01 2 VALUES < LLD WHEELER RES 2 VALUES < LLD 1.13E-01 (1/2)

TRM 275-349 1.13E 1.13E-01 CS-137 3.OOE-02 4.24E-02 (1 / 2) WHEELER RES 4.24E-02 (1 / 2) 3.75E-02 (1 / 2) 4.24E 4.24E-02 TRM 275-349 4.24E 4.24E-02 3.75E 3.75E-02 K-40 4.OOE-01 1.59E+01 (2 / 2) WHEELER RES 1.59E+01 (2 / 2) 1.53E+01 (2 / 2) 1.46E+01 - 1.73E+01 TRM 275-349 1.46E+01 - 1.73E+01 1.50E+01 - 1.55E+01

'-q Ii I-M~

Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is Indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY INSHORELINE SEDIMENT PCI/GM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: BROWNS FERRY NUCLEAR PLANT Docket Number: 50-259,260,296 Location of Facility: LIMESTONE ALABAMA Reporting Period: 2005 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 6 AC-228 2.50E-01 4 VALUES < LLD MALLARD CREEK REC AR 2 VALUES < LLD 5.91E-01 (2/ 2)

TRM 293.0 5.11E-01 - 6.71E-01 Bl-212 4.50E-01 4 VALUES < LLD MALLARD CREEK REC AR 2 VALUES < LLD 6.63E-01 (2/2)

TRM 293.0 5.23E-01 - 8.02E-01 B-214 1.50E-01 2.29E-01 (31 4) JOE WHEELER ST PARK 2.66E-01 (1/2) 4.91 E-01 (2 /2) 1.68E 2.66E-01 TRM 279.5 2.66E-01 - 2.66E-01 4.34E-01 - 5.48E-01 K-40 7.50E-01 4 VALUES < LLD MALLARD CREEK REC AR 2 VALUES < LLD 4.98E+00 (2/2)

TRM 293.0 4.11E+00 - 5.84E+00 H I PB-212 11.00E-01 1.33E-01 (4/4) MALLARD CREEK REC AR i.38E-01 (2 /2) 5.90E-01 (2/ 2)

-I' 1.01E-01 - 1.74E-01 TRM 293.0 1.01E-01 - 1.74E-01 5.15E-01 - 6.66E-01 tzI PB-214 1.50E-01 2.39E-01 (3 /4) JOE WHEELER ST PARK 3.OOE-01 (1/ 2) 5.26E-01 (2 /2) 1.67E-01 - 3.OOE-01 TRM 279.5 3.OOE-01 - 3.OOE-01 4.48E-01 - 6.03E-01

-. 4 RA-226 1;50E-01 2.29E-01 (3 /4) JOE WHEELER ST PARK 2.66E-01 (1/ 2) 4.91E-01 (2/2) 1.68E-01 - 2.66E-01 TRM 279.5 2.66E-01 - 2.66E-01 4.34E-01 - 5.48E-01 TL-208 6.OOE-02 6.31E-02 (1/ 4) JOE WHEELER ST PARK 6.31E-02 (1/2) 1.77E-01 (2/ 2) 6.31E-02 - 6.31E-02 TRM 279.5 6.31E-02 - 6.31E-02 1.60E-01 - 1.95E-01 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E- 1

-Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Direct Radiation Levels Browns Ferry Nuclear Plant

-Dd C H CO E

1975 10975

.1980 1

1985, 1

1990 1995 Calendar Year 2000 2005 2010

-*- On-Site -o-Off-Site

Annual Average Gross Beta Activity in Air Filters - BFNP 0.25 0.20 E

0.15 V

I- H la 0.10 I.-

4 0.05 r?

0.00 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year I

• Indicator o Control -- l

lzj I

No 'I In LI)

zj F-I Io 0 l0 R

y T--

Annual Average Gross Beta Activity in Drinking Water - BFNP 6 -

Initial plant operation in 4

Preoperational A'.erage H 00 '----------------------A-------------------_______________

0 1,

Un

<: 2 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year Il - dovnstream e upstreamI

Annual Average Cs-1 37 Activity in Fish Flesh Game Fish - BFNP 0.5 Initial plant operation in August, 1973 0.4

.3Preoperationial A'.erage z 0.

Ln 50.2 0.1 0.0*

1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year

-- -downstream o upstream l