ML18151A341
| ML18151A341 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1990 |
| From: | Blount P, Noce D, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-243, NUDOCS 9105030302 | |
| Download: ML18151A341 (156) | |
Text
{{#Wiki_filter:* I C I I ~,
.1 _..
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 28, 1991 United States Nuclear Regulatory Commission Serial No. 91-243 Attention: Document Control Desk NL&P/RBP Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Attached is the 1990 Radiological Environmental Monitoring Program Report for Surry Power Station which fulfills the requirement for the Annual Radiological Environmental Operating Report per Technical Specification 6.6.B.2. Very truly yours, cQL~ W. L. Stewart Senior Vice President - Nuclear Attachment cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219 ( I 91050]0::::02 *~1 012::::1. 1 F'DR A:OOCK 05000280 I i ': R PDR
- l ATTACHMENT
' *::.: ; ~. ;~ OUT THR'OOGff liHE'MAllD REMOVAL . ** .; * * * .
. ***~F" 1~£ll~E~i~i~t%~~~~~f~i~ i
,FQR',REPRODlile:m@NnMwsr,:BE%RE;;;({,, ;'
FE~a~~J~IIJll ~"if~~11
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR 1990 Prepared by VIRGINIAELECIRICANDPOWERCOMPANY and 1ELEDYNEIS0TOPES
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SURRY POWER STATION JANUARY 1, 1990 to DECEMBER 31, 1990 Peter F. Blount Supervisor Radiological Analysis Reviewed by: d_~,£ -4,.,,,,L._ Barry A. Garber Supervisor Technical Services Health Physics Approvedby:JJ,,.ec;,__ f. ~ Dean L. Erickson Superintendent Radiological Protection
TABLE OF CONTENTS SECTION TITLE PAGE FORWARD .............................................................................. , ...... i EXECUTIVE
SUMMARY
.................................................................. ii I. IN1RODUCI10N ........................................................................... 1 II. NUCLEAR POWER AND 1HE ENVIRONMENT IN PERSPECTIVE ............. 3 III. SAMPLING AND ANALYSIS PROORAM ............................................ 18 IV. PROGRAM EXCEP'TIONS ............................................................... 29 V.
SUMMARY
AND DISCUSSION OF 1990 ANALYTICAL RESULTS ........... .31 A. AIRBORNE EXPOSURE PATHWAY ........................................... 32
- 1. Air Iodine/Air Particulates .................................................... 32 B. WATERBORNE EXPOSURE PATHWAY ..................................... .35
- 1. RiverWater ..................................................................... 35
- 2. Well Water ...............................-....................................... 39 C. AQUATIC EXPOSURE PATHWAY ............................................ .39
- 1. Silt .....................-.......................................................... 39
- 2. Shoreline Sedhnent ............................................................ 45 D. INGESTIONEXPOSUREPATHWAY ......................................... .46
- 1. Milk .............................................................................. 46
- 2.
- Aquatic Biota ................................................................... 47
- 3. Food Products .................................................................. 50 E. DIRECT RADIATION EXPOSURE PATIIWAY ............................... 51
- 1. TLD Dosimeters ................................................................ 51
- VI. CONCLUSION ............................................................................. 57 i
TABLE OF CONTENTS (Cont) SECTION TI1LE PAGE VIl. REFERENCES .............................................._................................ 61 VIll. APPENDICES ................................. *................ ~ ............................. 63 APPENDIX A - Radiological Environmental Monitoring .............................. 63 Program Annual Summary Tables - 1990 APPENDIX B - Data Tables ............................................................... 71 APPENDIX C-Land Use Census-1990 ............................................. 102 APPENDIX D - Synopsis of Analytical Procedures .................................. 107 APPENDIX E - EPA Interlaboratory Comparison Program ......................... 119 LIST OF FIGURES
- 1. Land Based Environmental Sampling Locations ........................................... 23
- 2. River Based Environmental Sampling Locations ..........................................24
- 3. Site Boundary TLD Locations ...............................................................25
- 4. Land Use Census Map ...................................................................... 104 LIST OF TRENDING GRAPHS
- 1. Gross Beta in Air Particulates ............................................................ -.... 34
- 2. Tritium in River Water ........................................................................ 36
- 3. Tritium in Well Water ......................................................................... 40
- 4. Cobalt-58 in Silt ............................................................................... 41
- 5. Cobalt-6() in Silt ........................................ ~.*.................... _................. 42
- 6. Cesium-134 1n Silt .............................................................................43
- 7. Cesium-137 in Silt ............-. ................................................................ 44
- 8.
- Cobalt-58 in Clams ............................................................................ 47
- 9. Cobalt-6() in Clams ............................................................................ 48
- 10. Cesium-137 in Clams ......................................................................... 49
- 11. Direct Radiation Measurements-1LD Results .............................................. 52
- 12. US EPA* Cross Check Program ............................................................ 123 ii
LIST OF TABLES TABLE PAGE B-1 Concentrations of Iodine-131 in Filtered Air .....................................................72 B-2 Concentrations of Gross Beta in Air Particulates ................................................7 6 B-3 Concentrations of Gamma Emitters in Quarterly Air Particulates.............................. 80 B-4 Concentrations of Gamma Emitters and Tritium in River Water............................... 82 B-5 Concentrations of Gamma Emitters and Tritium in State Split River Water .................. 85 B-6 Concentrations of Gamma Emitters and Tritium in Well Water................................ 86 B-7 Concentrations of Gamma Emitters in Silt ....................................................... 87 B-8 Concentrations of Gamma Emitters in Shoreline Sediment .................................... 89 B-9
- Concentrations of Strontium 89/90 and Gamma Emitters in Milk .............................90 B-10 Concentrations of Gamma Emitters in Clams ....................................................93 B-11 Concentrations of Gamma Emitters in Oysters ..................................................94 B-12 Concentrations of Gamma Emitters in Crabs ................*.................................... 95 B-13 Concentrations of Gamma Emitters in Fish ......................................................96 B-14 Concentrations of Gamma Emitters in Vegetation ............................................... 97 B-15 Direct Radiation Measurements - Quarterly 1LD Results Set 1................................ 98 B-16 Direct Radiation Measurements - Quarterly 1LD Results Set 2 .............................. 100
FORWARD This report is submitted as required by Technical Specification 6.6.B.2, Annual Radiological Environmental Operating Report for Surry, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-280 and 50-281. iv
EXECUTIVE
SUMMARY
This document is a detailed report on the 1990 Surry Nuclear Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels from January 1 through December 31, 1990 in air, water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct exposure pathways have been analyzed, evaluated and summarized. The REMP is designed to ensure that radiological effluent releases are As Low As is Reasonably Achievable (ALARA), no undue environmental effects occur, and the health and safety of the public is protected. The program also detects any unexpected environmental processes which could allow radiation accumulations in the environment or food pathway chains. Radiation and radioactivity in the environment is constantly monitored within a 25 mile radius of the station. Samples are also collected by Virginia Power within this area. A number of sampling locations for each medium were selected using available meteorological, land and water use data: Control samples are collected from areas that are beyond measurable influence of Surry Nuclear Power Station or any other nuclear facility for use as reference data. Normal background radiation levels or radiation present due to causes other than Surry Power Station can thus be compared to the environment surrounding the nuclear power station. Indicator samples showing how much radiation is contributed by the plant are taken from areas close to the station where any plant contribution will be at the highest concentration. Measured values are compared with both current control samples and the pre-operational baseline -- radioactive concentrations present in the environment before Surry became operational -- to determine if changes in radioactivity levels are attributable to station operations, to other causes such as the Chernobyl accident, or to natural variation. Teledyne Isotopes provides sample analyses for various radioisotopes as appropriate for each sample media. Participation in the Environmental Protection Agency's (EPA) Interlaboratory Comparison Program provides an independent check on the precision and accuracy of sample measurements. Radioactivity in the environment is typically so minimal that radiological analyses frequently fall below the detection limits of state-of-the-art measurement methods. The Nuclear Regulatory Commission (NRC) sets forth minimum Lower Limits of Detection (LLD) to ensure that analyses are as accurate as possible. Samples with extremely low levels of radiation which cannot be detected are therefore reported as being below the LLD. The NRC also mandates a "reporting level." Licensed nuclear facilities must report any releases equal to or greater than this reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporting level. V
Analytical results are divided into five categories based on exposure pathways: Airborne, waterborne, aquatic, ingestion, and direct radiation.
- The airborne exposure pathway includes airborne iodine and airborne particulates. The 1990 airborne results were very similar to previous years and to preoperational levels. No increase was noted and there were no detections for fission products or other man-made isotopes in the airborne particulate media during 1990.
- The waterborne exposure pathway includes well water and river water. No man-made or natural isotopes were detected in the James River with the exception of naturally occurring potassium-40 and tritium. The average tritium activity in 1990 was 1.06% of the NRC reporting level. This has decreased from preoperational levels and is less than the average for the previous five years. No man-made or naturally occurring isotopes were detected in well water. This trend is consistent throughout the operational monitoring program.
- The aquatic exposure pathway includes silt and shoreline sediment samples. Silt contained some cesium-137, cesium-134 and cobalt-60. During the preoperational period, there were no man-made isotopes detected for this pathway, however, man-made isotopes have accumulated. The concentrations of the gamma-emitting isotopes in 1990 indicate a decreasing trend compared to the previous five year period. Shoreline sediment, which may provide a direct exposure pathway, contained no man-made isotopes. Naturally occurring isotopes detected in 1990 sediment samples revealed a steady trend over the recent past.
- The ingestion exposure pathway includes milk, aquatic biota, and food product samples.
Iodine-131 was not detected in any 1990 milk samples and has not been detected in milk prior to and since the 1986 Chernobyl accident. Although cesium-137 has been detected in the past, it was not detected in 1990 samples. Strontium-90 was detected at levels less than the previous two years and lower than preoperational years. Both strontium-90 and cesium-137 are attributable to atmospheric nuclear weapons testing in the past. Naturally occurring potassium-40 was detected at normal environmental levels. 1990 aquatic biota sample results revealed gamma-emitting isotopes with the exception of one fish sample in which cesium-137 was detected at a concentration less than the average for the previous five years and lower than both the LLD and reporting level concentration. This is consistent with preoperational data. Naturally occurring vi
potassium-40 was detected in each of the aquatic biota samples with a decreasing trend compared to the previous five years. Vegetation samples revealed naturally occurring potassium-40 and beryllium-? at levels which were statistically similar to both control and preoperational levels. Cesium-137 was detected in two soybean samples at concentrations less than the average for the previous five years and lower than the LLD and reporting levels.
- The direct exposure pathway measures environmental radiation doses by use of thermoluminescent dosimeters (TLDs). TLD results have remained statistically the same since the preoperational period. 1990 results are slightly less than the previous five years.
During 1990, as in previous years, operation of the Surry Nuclear Power Station created no adverse environmental affects or health hazards. The maximum dose calculated for the hypothetical individual at the Surry Power Station site boundary due to liquid and gaseous effluents released from the site during 1990 was 0.663 millirem. For reference this dose may be compared to the 360 millirem average annual exposure to every person in the United States from natural and man-made sources. Natural sources in the environment provide approximately 82% of radiation exposure to man while Nuclear Power contributes less than 0.1 %. These results demonstrate not only compliance with federal and state regulations, but also demonstrate the adequacy of radioactive effluent control at the Surry Nuclear Power Station. Vll
e VIRGINIA ELECTRIC ANI) POWER COMPANY. e SURRY POWER STATION . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I. INTRODUCTION The operational Radiological Environmental Monitoring Program (REMP) conducted for the year 1990 for the Surry Power Station is provided in this report. The results of measurements and analyses of data obtained from samples collected from January l, 1990 through December 31, 1990 are summariz.ed. A. The Surry Power Station of Virginia Electric and Power Company is located on the Gravel Neck peninsula adjacent to the James River, approximately 25 miles upstream of the Chesapeake Bay. The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply system and turbine generator furnished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 822.6 megawatts electric (MWe). Unit 1 achieved commercial operation on December 22, 1972, and Unit 2 on May l, 1973. B. The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria are met, the operating license for Surry Power Station includes Technical Specifications which address the release of radioactive effluents. Inplant monitoring is used to ensure that these release limits are not exceeded. As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in Surry Power Station Technical Specifications. C. Virginia Electric and Power Company is responsible for collecting the various indicator and control environmental samples. Teledyne Isotopes is responsible for sample analysis and submitting reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared with control levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal 1
variations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected. This preoperational data is compared with data collected during the operational phase to assist in evaluating any radiological impact of the plant operation. D. Occasional samples of environmental media show the presence of man-made isotopes. As a method of referencing the measured radionuclide concentrations in the sample media to a dose consequence to man, the data is compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and Table 4.9-4 of Surry Power Station's Technical Specifications. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is Reasonably Achievable". E. This report documents the results of the Radiological Environmental Monitoring Program for 1990 and satisfies the following objectives of the program:
- 1. To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station operation.
- 2. To supplement the radiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.
- 3. To identify changes of radioactivity in the environment
- 4. To verify that the plant operations have no detrimental effect on the health and safety of the public.
2
Nuclear Power And The Environment In Perspective IT. NUCLEAR POWER AND THE ENVIRONMENT: IN PERSPECTIVE Coal, *oil, natural gas, and hydropower have been used to run the nation's electric generating stations; however, each method has its drawbacks. Coal-fired power can affect the environment through mining, acid rain, and airborne discharges. Oil and natural gas are in limited supply and are therefore costly. Hydropower is limited-due to the impact of damming our waterways and the scarcity of suitable sites in our country. Nuclear energy provides an alternate source of energy which is readily available. The operation of nuclear power stations has a very small impact on the environment. In fact, the hundreds of acres adjoining Surry Power Station is state waterfowl refuge, while at North Anna Power Station Lake Anna is a well-known fishing site and has a state park on its shore. In order to more fully understand this unique source of energy, background information on basic radiation characteristics, risk assessment, reactor operation, effluent control, and environmental monitoring is provided in this section. FUNDAMENTALS The Atom Everything we encounter is made of atoms. Atoms are the smallest parts of an element that still have all the chemical properties of that element. At the center of an atom is a nucleus. The nucleus consists of neutrons and protons. Electrons move in an orbit around the nucleus and are negatively charged. Protons and neutrons are nearly identical in size and weight, and each is about 2000 times heavier than an electron. However, the proton has a positive charge and the neutron has no charge, it is electrically neutral. Figure 1-1 presents a simple diagram of an atom. Isotopes The number of protons in the atom of any single element is always the same. For example, all hydrogen atoms have one proton and all oxygen atoms have eight protons. However, the number of neutrons in the nucleus of an element may vary. Atoms with the same number of protons, but a different number of neutrons, are called isotopes. Table. 1-1 lists the isotopes of uranium. 3
ATOMIC STRUCTURE Figure 1-1: Diagram of an Atom Table 1-1: Isotopes of Uranium Number Number Isotopes Symbols of Protons of Neutrons Uranium-235 235u 92 143 Uranium-236 236u 92 144 Uranium-237 237u 92 145 Uranium-238 238u 92 146 Uranium-239 I 239u I 92 I 147 I Uranium-240 240u 92 148 RADIATION AND RADIOACTIVITY Radionuclides Normally, the parts of an atom are in a balanced or stable state. If the nucleus of an atom contains excess energy, it may be called a radioactive atom, a radioisotope, or radionuclide. The excess energy is usually due to an imbalance in the number of electrons, protons, and/or neutrons which make up the atom.*
Radionuclides can be naturally occurring, such as uranium-238, thorium-232 and potassium-40, or man-made, such as iodine-131, cesium-137, and cobalt-60. Radioactive Decay Radioactive atoms attempt to reach a stable (non-radioactive) state through a process known as radioactive decay. Radioactive decay is the release of energy from the atom through the emission of particulate and/or electromagnetic radiation. Particulate radiation may be in the form of electrically charged particles such as alpha (2 protons plus 2 neutrons) or beta particles (1 electron), or may be electrically neutral, such as neutrons. Part of the electromagnetic spectrum consists of gamma rays and X-rays which are similar to light and microwaves, but have a much higher energy. Half-Life A radioactive half-life is the amount of time required for a radioactive substance to lose half of its activity through the process of radioactive decay. Cobalt-60 has a half-life of about 5 years, so after 5 years 50% of its radioactivity is gone and after 10 years 75% has decayed away. Radioactive half-lives vary from millionths of a second to millions of years. Radioactive atoms may decay directly to a stable state or may undergo a series of decay stages and produce several daughter products which eventually lead to a stable atom. Naturally occurring radium-226, for example, has 10 successive daughter products (including radon) and has lead-206 as a final stable form. TYPES OF RADIATION Two types of radiation are considered in the nuclear industry, particulate and electromagnetic. Particulate radiation may come from the nucleus of an atom in the form of an ejected alpha particle. Alpha particles consists of two ALPHA protons together with two neutrons. Particle Alpha particles have a very limited ability to penetrate matter. A piece of paper will stop all alpha radiation. For this reason, alpha radiation from sources outside the body are not considered to be a radiation hazard. A beta particle is like an electron 5
that has been ejected from the nucleus of an atom. The outer layers of skin or a BET A Particle thin piece _of plastic will stop beta
~~.~~} ~ ~~::: ~:;:!':"::!~ +
radiation. Exposure to beta radiation can be a hazard to the skin or lens of the 1 Proton ( in nucleus) eye. Because of their limited ability to penetrate the body, beta and alpha radiation are a health concern primarily if swallowed or
* . inhaled where they_ might cause internal GAMMA Ray radiation exposure. Gamma rays are like X-rays except that they come from the
* ;:::,.,.,.. } Electromagnetic nucleus of an atom and X-rays come
... radiation indistin-
. guisable from X-rays from the electron rings. Gamma rays may pass through the entire body and thus give a "whole-body" radiation dose. Several inches of concrete or lead will stop gamma and X-rays. Figure 1-2 shows the approximate penetrating ability of various types of radiation.
a = Alpha b = Beta g = gamma e Radioactive Material Paper Aluminum Concrete As radiation travels, it collides with other atoms and loses energy. Alpha particles can be stopped by a sheet of paper, beta particles by a thin sheet of alum mum, and gamma radiation by several inches of concrete or lead. Figure 1-2: The Penetrating Ability of Various Types of Radiation QUANTITIES AND UNITS OF RADIOACTIVE MEASUREMENT There are several quantities and units used to describe radioactivity and its effects. In the following sections two terms, rem and activity, will be used to describe amounts of radiation. 6
Rem measures the potential effect of radiation exposure on hum*an cells. Small doses are counted in millirem which are equal to one thousandth of a rem. Federal standards limit n c:, one inch one millirem Just as twelve inches equals one foot 1000 millirem equals 1 rem Figure 1-3: Unit Comparison exposure for an individual member of the public to 500 millirem annually, not counting about 300 millirem received from na.tural sources and appro:x:imately 60 millirem from medical applications. Activity is the number of nuclei in a sample that disintegrate (decay) every second.. Each time a nucleus disintegrates, radiation is emitted. . 1 Curie
~
The unit of activity is the curie. A curie (Ci) is the amount of radioactive material which decays at a rate of 37 billion atoms per second. Smaller ..E~ units of the curie are often used. Two common ... ~ units are the microcurie (uCi), one millionth of a ~-~---~~
~
~
... ~ 1 Curie*
curie, and the picocurie (pCi), one trillionth of a .,, ... ~ curie. A curie is a measurement of radioactivity, ~"~
-~
~"~ ~
not a quantity* of materiaL The amount of "~"~~" material to make one curie varies. For example, 1O Tons of Thorium-232 1 Gram of Radium-226 one gram of radium-226 is one curie of* (radiation source) (radiation source) radioactivity, but it would take 9,170,000 grams One gram of radlum-226 and 10 tons of (about 10 tons) of thorium-232 to obtain one. thorlum-232 are both approximately 1 Curie. curie. 7
SOURCES OF RADIATION Background Radiation Radiation is not a new creation of the nuclear power industry; it is a natural occurrence on the earth. Mankind has always lived with radiation and always will. Every second of our lives, over 7,000 atoms undergo radioactive decay in the body of the average adult. Radioactivity exists naturally in the soil, water, air and space. All of these common sources of radiation contribute to the natural background radiation that we are exposed to each day. Table 1-2: Sources of Background Radiation
'NATURAL BACKGROUND Radon and Radon Daughters ................ 200.00 Cosmic Rays ....... :.................................... 27.00 Cosmogenic Radiation .............................. 1.00 Terrestrial Radiation ............................... 28.00 Internal Radiation ..................................... 40.0 MAN MADE Nuclear Power .......................................... 0.05 Miscellaneous Environmental.. ................ 0.06 Medical Diagnostic X-rays ........ .-..................... 39.00 Other Medical. .................................... 14.00 Occupational .................. :.......................... 0.90 Consumer Products ................... 5.00 to 13.00 MREM
- TOT AL 360.00 PER YEAR The earth is constantly showered by a steady stream of high energy gamma rays that come from space, known as cosmic radiation. Our atmosphere shields out most of this radiation, but everyone still receives about 20 to 50 millirem each year from this source. The thinner air at higher altitudes provides less protection from cosmic radiation. So, people living at higher altitudes or even flying in an airplane are exposed to more radiation. Radioactive atoms commonly found in the -atmosphere as a result of cosmic ray interaction include beryllium-7, carbon-14, tritium, and sodium-22.
8
Other natural sources of radiation include the radiqnuclides naturally found in soil, water, food, building materials and even people. People have always been radioactive, in part because the carbon found in our bodies is a mixture of all carbon isotopes, both non-radioactive and radioactive. About one-third of the external terrestrial and internal whole body radiation dose from natural sources is attributable to a natural radioactive isotope of potassium, potassium-40. Man-Made In addition to naturally occurring radiation people are also exposed to man-made radiation. The largest sources of these exposures are from medical X-rays, fluoroscopic examinations, radioactive drugs and tobacco. Small doses are received from consumer products such as television, smoke alarms, and fertilizers. Very small doses result from the production of nuclear power. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout radionuclides include strontium-90, cesium-137, carbon-14, and tritium. EFFECTS OF RADIATION Studies The effects of ionizing radiation on human health have been under study for more than eighty years. Scientists have obtained valuable knowledge through the study of laboratory animals that were exposed to radiation under controlled conditions. It has proven difficult, however, to relate the biological effects of irradiated laboratory animals to the potential health effects on humans. Because of this human populations irradiated under various circumstances have been studied in great depth. These groups include:
- Survivors of the atomic bomb.
- Persons undergoing medical radiation treatment.
- Radium dial painters during World War I who ingested large amounts of radioactivity by "tipping" the paint brushes with their lips.
- Uranium miners, who inhaled large amounts of radioactive dust while mining pitchblende (uranium ore).
- Early radiologists, who accumulated large doses of radiation from early X-ray equipment while being unaware of the potential hazards.
9
The analysis of these groups have increased our knowledge of the health effects from large doses of radiation. However, less is known about the effects of low doses of radiation. To be on the conservative side, we assume that health effects occur proportionally to those observed following a large dose of radiation. That is, if one dose of radiation causes an effect, then half the dose will cause half the effect. Radiation scientists agree that this assumption overestimates the risks associated with low level radiation exposure. The effects predicted in this manner have not been actually observed in individuals exposed to low level radiation. Health Risks Since the actual effects of exposure to low level radiation are difficult to measure, scientists often refer to the risk involved. The problem is one of evaluating alternatives, of comparing risks and weighing them against benefits. People make decisions involving risks every day such as whether to wear seat belts or smoke cigarettes. Risks are a part of everyday life. The question is one of determining how great the risks are. We accept the inevitability of automobile accidents. Building safer cars or wearing seat belts will reduce the .risk of injury. You could choose to not drive but even pedestrians and bicyclists are injured by cars. Reducing the risk of injury from automobiles to zero requires moving to a place where there are no automobiles.
- While accepting the many daily risks.of living, some people feel that their demands for energy should be met on an essentially risk-free basis. Attention is focused on safeguarding the public, developing a realistic assessment of the risks, and placing them in perspective.
Because you cannot see, feel, taste, hear, or smell radiation, it is a source of concern. We have the same lack of sensory perception for things such as radio waves, carbon monoxide, and small concentrations of numerous cancer causing substances. Although these risks are just as real as the risks associated with radiation, they have not generated the same degree of concern as radiation. Most risks are with us throughout our lives, and their effects can be added up over a lifetime to obtain a total effect on our life span. The typical life span for an American woman is now 76 years, whereas men average 71 years of age. Figure 1-4 shows a number of different factors that decreased our average life expectancy. 10
EST I MATED AVERAGE DAYS OF LI FE EXPECTANCY LOST DUE TO VARIOUS HEALTH RISKS 10000 ACTIVITY 9000 8000 en 7000 ( 1) Co ricer
- ,)
G:J 6000 (2) Cigorette smoking: 2 pocks/day C (3) Cigorette smoking: 1 pock/day 5000 (4) Heart diseases 4000 (5) Male rother thon female (6) City liYing (not rural) 3000 (7) 0Yerweight by 30% 2000 (B) 125 operating nuclear power stotior 1000 0 2 3 4 5 6 7 8 Figure 1-4: Loss of Life From Various Health Risks The American Cancer Society estimat~s that about 30 percent of all Americans will develop cancer at some time in their lives from all possible causes. So, in a group of 10,000 people it is expected that 3,000 of them will develop cancer. If each person were to receive a radiation exposure of one rem in addition to natural background radiation, then it is expected that three more may develop cancer during their lifetime. This increases the risk from 30 percent to 30.03 percent. Hence, the risks of radiation exposure are small when compared to the risks of everyday life. These comparisons should give you some idea of the risk involved in activities that you are familiar with. They give a basis for judging what smoking, eating, or driving a car could mean to your health and safety. Everyone knows that life is full of risks. If you have the basis for judgment, you can decide what to do or what not to do. NUCLEAR REACTOR OPERATION Electricity in the United States is being produced using fossil fuel, uranium, or falling water. A fossil-fueled power station burns coal, oil or natural gas in a boiler to produce energy. Nuclear power stations use uranium fuel and the heat produced from the fission process to make energy. In both cases, they heat and boil water -to produce steam. The steam is used to drive a turbine which turns a generator and produces electricity. 11
Nuclear Fuel Uranium (U) is the basic ingredient in nuclear fuel, consisting of atoms of U-235 and U-238. Natural uranium contains less than one percent U-235 when it is mined. Commercial nuclear power plants use fuel with a U-235 content of approximately three percent. The process used to increase the concentration ofU-235 is known as enrichment. Reactor Operation After enrichment, the uranium fuel is chemically changed to uranium dioxide, a dry black powder. This powder is compressed into small ceramic pellets. Each fuel pellet is about 3/4 inches long and 3/8 inches in diameter. The pellets are placed into 12 foot long metal tubes made of zirconium alloy, to make a fuel rod. About five pounds of pellets are used to fill each rod. A total of 204 fuel rods make a single fuel assembly. Virginia Power nuclear reactors contains 157 fuel assemblies (Figure 1-5). Reactor Vessel Fuel Rod Control Rods Coolant Outlet Nozzle Coolant Inlet MT424 Nozzle Fuel Rod Assembly Fuel Rod Assemblies Thermal Shield Cora Support Reactor Vessel With Fuel Assemblies, Rods, and Fuel Pellets Figure 1-5: Reactor Core Design 12
Fission Nuclear energy is produced by a process called fission. Fission occurs in a reactor when uranium is split into fragments producing heat and releasing neutrons. These ~ neutrons strike other uranium atoms, causing them to split (fission) and release more heat and neutrons. This is called a chain reaction (Figure 1-6) and is controlled by the use of reactor control rods. e HeavyAtom o Free Neutron
@ Fission Fragment Wv> Heat Control rods are an essential part of the nuclear reactor. Control rods contain Fission: A Chain Reaction cadmium, indium, and silver metals which absorb and control the amount of neutrons produced in the reactor. The control rods act to slow down or stop the chain reaction. A chain reaction cannot occur when the control rods are inserted completely into the core. When the control rods are withdrawn, the chain reaction begins and heat is generated.
Design & Operation The Surry Power Station and North Anna Power Station use a Pressurized Water Reactor (PWR) system to generate electricity. There are two complete and independent PWR systems on site at both Surry and North Anna Power Stations. These are called U_nit-1 and Unit-2. The reactor core is inside a large steel container called the Reactor Pressure Vessel. The reactor core is always surrounded by water. The fissioning of the uranium fuel makes the fuel rods get hot. The hot fuel rods heat the water, which serves as a coolant that carries away heat. In a pressurized water reactor, heat is moved from place to place by moving water, the reactor's coolant. The water flows in closed loops. As (primary) water moves through the core it gets very hot (605°F), but because it is under such high pressure, 2235 pounds per square inch (psi), it doesn't boil. The hot water then flows to the steam generator. The steam generator is a heat exchanger. Reactor coolant passes through it but doesn't mix with the steam generator (secondary) water. Instead, heat from the primary water is transferred through thousands of tubes to the cooler secondary water. The water in the steam generator is under much less 13
pressure, and the heat boils the secondary water to steam. At Virginia Electric and Power* stations, each unit has 3 steam generators. The steam is piped to a steam turbine that turns an electric generator. The exhausted steam from the turbine is cooled and convened back to water in a condenser. The condenser is also a heat exchanger; in it heat passes from the steam to a third loop of water. In Surry's case the James River provides the third loop water. At Nonh Anna Power Station third loop water is from Lake Anna. The steam turns back to liquid and is pumped back to the steam generator. Containment Nuclear power plants are designed to prevent the escape of large quantities of radiation and radioactive substances. Two principles are used. First, thick, heavy walls are used as shielding to absorb radiation and prevent its escape. Second, strong, airtight walls called containment, are used to prevent the escape of radioactive materials. The reactor pressure vessel and the containment building that houses it is enormously strong (Figue 1-7). Strong enough, in fact, to withstand a direct hit from a large jetliner. The reactor core lies within a sealed pressure vessel. Like all boilers its walls must be very strong because the water inside must be kept under high pressure. The reactor pressure vessel in a nuclear power plant is even heavier than an ordinary steam boiler because of the need to minimize the chance of rupture and release of any radioactive materials. The reactor pressure vessel is made from a stainless steel 6 to 8 inches thick. Around the reactor pressure vessel is a thick concrete wall. This wall acts as shielding, protecting workers by absorbing radiation resulting from the nuclear chain reaction. Next an airtight lfi inch steel liner surrounds the entire interior of the containment. If the reactor pressure vessel or any of the primary piping should break, the escaping steam would be trapped inside the liner. Finally, the building's reinforced concrete outer wall is 411z feet thick tapering to 2112 feet at the top of the dome. It is designed to act as shielding and is also intended to withstand natural and man-made events like earthquakes and even the direct impact from a large commercial jet aircraft. 14
HIGH PRESSURE SAFETY INJECTION SYSTEM (EM ERG. CORE COOLING) LOW PRESSURE SAFETI' JNJ ECTION SYSTEM (EMERG. CORE COOLING) CONTAINMENT SPRAY SYSTEM REACTOR CONTAINMENT BUILDING i£WWWILlll&IIIM MAJN ~TEAM SY~TEM REACTOR COOLING SYSTEM (PRIMARY COOLJNG SYSTEM)
~~ CONDENSER COOLING SYSTEM MAIN fEEDWATER SYSTEM AUXJLIARY FEED WATER SYSTEM CONTAINMENT SPRAY NOZZLES TURBINE BUILDING VENTILATION RELEASE STACK t
RADIATION !IIONJTOR
/
AUXILIARY BUILDING
-~=--l_il_.E-C_TRICAL POWER TO
' CHARCOAL FILTER TRANSMISSION SYSTEM
"-. CONTAINMENT SPRAY PUMP
,Rq~1 LAKE OR RIVER VOLUME CONTROL TANK -l'EEDPUMP SAFETY INJECTION PUMP EMERGENCY CONDENSATE TANK REACTOR COOLANT PUMP CONTAINMENT SUMP
- PWR SYSTEM DIAGRAM -
2 1/2 Feet Thick Concrete 1/2 Inch Steel Liner 3/8 Inch Steel Liner 4 1/2 Feet Thick Concrete Steam 185 Feet 122 Feet 1----f:
* *-,:*<<**0 tfif'.d.',** Liner 1o Feet Thick Concrete
,.. 126 Feet ..,
Containment Schematic I Figure 1-7: Containment Dimensions Operating the Reactor Safely Accidents The most serious accident that could happen in a nuclear power plant involves overheating in the nuclear reactor core. Such an accident would result from a loss-of-coolant accident or LOCA. During a LOCA primary coolant would no longer circulate through the reactor core to remove heat. Circulation could be lost if a combination of pipes burst, for example. Conceivably, a dry, overheated reactor core could melt through the pressure vessel. 15
The reactor itself is designed to respond automatically to such an emergency. Operators are also trained to make corrections for any system failure. The automatic and operator responses have two goals: to prevent damage to the reactor, and prevent the release of radiation. Shutting the reactor down is relatively easy. Control rods drop in and chemicals to stop the nuclear reaction are injected into the coolant. Losing the coolant itself tends to stop the chain reaction because the coolant is needed to keep the nuclear chain reaction going. Within 10 seconds of shutdown, the amount of heat is less than 5 percent of the amount produced at full power and within 15 minutes, less than 1 percent. To carry heat away during an accident, all reactors have Emergency Core Cooling Systems (ECCS). The ECCS consists of primary and backup pumps and reservoirs of coolant that operate separately from those that normally circulate through the system. A nuclear reactor has many different back-up safety systems designed so that if one fails another is always available. Workers There are many different jobs at a nuclear power plant and they are filled by people with diverse backgrounds. All employees are initially trained and then retrained annually by the company. Virginia Power's Training centers are fully accredited by the National Academy for Nuclear Training and the Institute for Nuclear Power Operations. The operators are tested and c_ertified by the United States Nuclear Regulatory Commission (NRC). Safety Statistics Job safety is another measure of assurance that the station is being properly operated. Surry Power Station was awarded the Virginia Power Presidential Safety A ward for attaining 1,349,415 man hours without a lost time accident and we are continuing that record into 1991, while North Anna reached 5,000,000 man hours without a lost time accident in March 1991. 16
SUMMARY
- Nuclear energy provides an alternate source of energy which is readily available. The operation of a nuclear power station has a very small impact on the environment.
- Radiation is not a new creation of the nuclear power industry; it is a natural occurrence on the earth. Mankind has always lived with radiation and always will. Radioactivity exists naturally in the soil, water, air and space. All these common sources of radiation contribute to the natural background radiation to which we are exposed.
- In addition to naturally occurring radiation and radioactivity, people are also exposed to man-made radiation. Very small doses result from the production of nuclear power.
- Nuclear power plants are designed to prevent the escape of radiation and radioactive substances.
- A nuclear reactor has many different back-up safety systems designed so that if one fails another is available.
17
- C * -* ,- - 'i III. SAMPLING AND ANALYSIS PROGRAM A. Samplina Pco&cam
- 1. Table 1 summarizes the sampling program for Surry Power Station during 1990.
The symbols on this table refer to the sample locations shown on Figures 1 through
- 3. Figure 1 indicates the locations of the land based samples while Figure 2 shows the locations of the river based samples. The small triangles in Figure 3 designate the position of environmental thermoluminescent dosimeters (1LDs) at the site boundary.
- 2. For routine TLD measurements, two dosimeters made of CaS04:Dy in a teflon card are deployed at each sampling location. Several 'ILDs are co-located with NRC and Commonwealth of Virginia direct radiation recording devices. These are indicted as "co-location" samples.
- 3. In addition to the Radiological Environmental Monitoring Program required by Surry Technical Specifications, Virginia Electric and Power Company splits samples with the Commonwealth of Virginia. All samples listed in Table 1 are collected by Vepco personnel except for those labeled state split. All samples are shipped to Teledyne Isotopes in Westwood, New Jersey.
- 4. All samples listed in Table 1 are taken at indicator locations except those labeled "control".
B. Analysis Pco&cam
- 1. Table 2 summarizes the analysis program conducted by Teledyne Isotopes for Surry Power Station during 1990.
18
- e TABLE 1 (Page 1 of 4)
SURRY-1990 RADIOLOOICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental Control (00) Quarterly Onsite* (TLD's) West North West (02) 0.17 WNW mo Quarterly Site Bowidary Surry Station Discharge (03) 0.6 NW 3()1)" . Quarterly Site Bowidary 1l North North West (04) 0.4 NNW 330" Quarterly Site Bowidary North (05) 0.33 N 357° Quarterly Site Boundary North North East (06) 0.28 NNE ZZ' Quarterly Site Bowidary North East (07) 0.31 NE 45° Quarterly Site Boundary East North East (08) 0.43 ENE fi8" Quarterly Site Boundary East (Exclusion) (09) 0.31 E W' Quarterly Onsite West (10) 0.40 w ZlO" Quarterly Site Boundary West South West (11) 0.45 WSW 250" Quarterly Site Boundary South West (12) 0.30 SW 2250 Quarterly Site Boundary South South West (13) 0.43 SSW 2()3<> Quarterly Site Boundary South (14) 0.48 s 180° Quarterly Site Boundary South South East (15) 0.74 SSE 157° Quarterly Site Boundary ...... South East (16) 1.00 SE 135° Quarterly Site Boundary I.O East (17) 0.57 E !X)" Quarterly Site Boundary Station Intake (18) 1.23 ESE 113° Quarterly Site Boundary Hog Island Reserve (19) 1.94 NNE 'lf,O Quarterly Near Resident, co-location Bacons Castle (20) 4.45 SSW 'lJ.J1!' Quarterly Apx. 5 mile TLD co-location Route633 (21) 3.5 SW 2240 Quarterly Apx. 5 mile TLD Allim:.e (22) 5.1 WSW 2480 Quarterly Apx. 5 mile TLD co-location Surry (23) 8.0 WSW 250" ' Quarterly Population Center Route 636 and 637 (24) 4.0 w ZlO" Quarterly Apx. 5 mile TLD Scotland Wharf (25) 5.0 WNW 2850 Quarterly Apx. 5 mile TLD co-location Jamestown (26) 6.3 NW 310" Quarterly Apx. 5 mile TLD co-location Colonial Parkway (27) 3.7 NNW 330" Quarterly Apx. 5 mile TLD Route 617 and 618 (28) 5.2. NNW 340" Quarterly Apx. 5 mile TLD Kingsmill (29) 4.8 N 'P Quarterly Apx. 5 mile TLD Williamsburg (30) 7.8 N O' Quarterly Population Center co-location Kingsmill North (31) 5.6 NNE 14° Quarterly Apx. 5 mile TLD Budweiser (32) 5.7 NNE z,o Quarterly Population Center
- TLD ston:d in a lead shield in environmental building
e TABLE 1 (Page2of4) SURRY-1990 RADIOLOOICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Environmental Watte Plant (33) 4.8 NE 41° Quarterly Apx. 5 mile TLD TLD's(Cont.) Dow (34) 5.1 ENE 1CJ' Quarterly Apx. 5 mile TLD Lee Hall (35) 7.1 ENE 73° Quarterly Population Center co-location 11 Goose Island (36) 5.0 E 88° Quarterly Apx. 5 mile TLD Fort Eustis (37) 4.8 ESE 107° Quarterly Apx. 5 mile TLD co-location Newport News (38) 16.5 ESE 102° Quarterly Population Center James River Bridge (39) 14.8 SSE 147° Quarterly Control Location Benn's Church (40) 14.5 s 175° Quarterly Control Location Smithfield (41) 11.5 s 176° Quarterly Population Center Rushmere (42) 5.2 SSE 156° Quarterly Apx. 5 mile TLD RL628 (43) 5.0 s 177° Quarterly Apx. 5 mile TLD co-location Afr Charcoal Suny Station (SS) .37 NNE 150 Weekly Site boundaiy location with and Partlcul11te HighestD/Q Hog Island Reserve (HIR) 2.0 NNE 260 Weekly Co-location t.> 0 D Bacons Castle (BC) 4.5 SSW '}ffZ' Weekly Allim:e (ALL) 5.1 WSW 2480 Weekly Co-location Colonial Parkway (CP) 3.7 NNW 330" Weekly Dow Chemical (DOW) 5.1 ENE 1CJ' Weekly Fort Eustis (FE) 4.8 ESE 107° Weekly Newport News (NN) 16.5 ESE 122° Weekly Control Location River Water Suny Discharge 0.17 NW 3250 Monthly State Split Scotland Wharf 5.0 WNW 2850 Monthly Control Location/State Split w Suny Station Intake 1.9 ESE ,77° Bi-monthly Hog Island Point 2.4 NE 5'1:' Bi-monthly Newport News 12.0 SE 140° Bi-monthly Chickahominy River 11.2 WNW 300° Bi-monthly Control Location Surry Station Discharge 0.17 NW 3250 Monthly Scotland Wharf 5.0 WNW 2850 Monthly
e TABLE 1 (Page 3 of 4) SURRY-1990 RADIOLOOICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Miles Direction Degrees Frequency Remarks Well Water Surry Station Quarterly Onsite* Hog Island Reserve 2.0 NNE z,o Quarterly w Bacons Castle 4.5 SSW 203° Quarterly Jamestown 6.3 NW 300" Quarterly Shoreline Hog Island Reserve 0.8 N 5' Semi-Annually Sediment Burwell's Bay 7.76 SSE 167° Semi-Annually SD Silt Chickahominy River 11.2 WNW 300" Semi-Annually Control Location Surry Station Intake 1.9 ESE Tf' Semi-Annually s Hog Island Point 2.4 NE 5'1:' Semi-Annually Point of Shoals 6.4 SSE 157° Semi-Annually Newport News 12.0 SE 140" Semi-Annually N ,_. Suny Station Discharge 0.5 NNW 341° Semi-Annually MIik
. Lee Hall Epps Colonial Parkway Judkins Williams 7.1 4.8 3.7 6.2 22.5 ENE SSW NNW SSW s
640 201° 3'5'1° 211° 18'1:' Monthly Monthly Monthly Monthly Monthly State Split State Split Control Location Oysters Deep Water Shoals 3.9 ESE 105° Bi-Monthly Point of Shoals 6.4 SSE 157° Bi-Monthly 0 Horsehead Shoals 4.2 ESE 137° Bi-Monthly State Split Rock Landing Shoals 7.8 SE 140" Bi-Monthly Newport News 12.0 SE 140" Bi-Monthly Clams Chickahominy River 11.2 WNW 300" Bi-Monthly Control Location Suny Station Discharge 1.3 NNW 341° Bi-Monthly State Split C Hog Island Point 2.4 NE 5'1:' Bi-Monthly Jamestown 5.1 WNW 300" Bi-Monthly Lawnes Creek 2.4 SE 131° Bi-Monthly
*Well water sample taken onsite at Suny Environmental Building
e TABLE 1 (Page 4 of 4) SURRY-1990 RADIOLOOICAL SAMPLING STATION DISTANCE AND DIRECTION FROM UNIT NO. 1 Distance Collection Sample Media Location Miles Direction Degrees Frequency Remarks Crabs Swry Station Discharge 0.6 NW 312" Annually CR Fish Swry Station Discharge 0.6 NW 312° Semi-Annually F Crops Brock's Fann 3.8 s 188° Annually State Split (Com,Peanuts) Slade's Fann 2.4 s 171° Annually State Split Soybeans) (Cabbage,Kale) Pool's Garden 2.3 s 182° Annually State Split Carter's Grove Garden 4.8 NE 560 Annually State Split Ryan's Garden Annually State Split/Control Loe. (Chester, Va.) Stone's Garden Annually State Split N N
1 LAND BASED SAMPLES 23
j FIGURE 2 RIVER BASED SAMPLES
\
24
HOG ISLAND RESERVE N.
}
I SPOILS POND
" - - - -YE.Io
£-----~ ==-=-=-------_:__----,
TABLE 2 SURRY POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FRE2UENCY ANALYSIS LLD!ll REPORT UNITS Thermoluminescent Quarterly Gamma Dose 1.5 mR/month Dosimetry (TLD) Air Iodine Weekly 1-131 0.07 pCi/m3 Air Particulate Weekly Gross Beta 0.01 pCi/m3 Quarterly (2) Gamma Isotopic pCi/m3 Cs-134 0.05 Cs-137 0.06 River Water Quarterly Tritium 2000 pCi/1 composite of monthly sample Monthly and 1-131 10 pCi/1 Bi-monthly Gamma Isotopic Mn-54 15 Fe-59
- 30 Co-58, 60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Well Water Quarterly Tritium 2000 pCi/1 1-131 1 Gamma Isotopic Mn-54 15 Fe-59 30 Co-58, 60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15
- Footnotes located at end of table. 26
TABLE 2 (Cont.) SURRY POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD(l) REPORT UNITS Shoreline Sediment Semi-Annual Gamma Isotopic pCi/kg-dry Cs-134 150 Cs-137 180 Silt Semi-Annual Gamma Isotopic pCi/kg-dry Cs-134 150 Cs-137 180 Milk Monthly I-131 1 pCi/1 Gamma Isotopic Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Oyster Bi-Monthly Gamma Isotopic pCi/kg-wet - Mn-54 Fe-59 Co-58, 60 Zn-65 Cs-134 Cs-137 130 260 130 260 130 150 Clams Bi-Monthly Gamma Isotopic pCi/kg-wet Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150 Crabs Annually Gamma Isotopic pCi/kg-wet Mn-54 130 Fe-59 260 Co-58, 60 130 Zn-65 260 Cs-134 130 Cs-137 150 - Footnotes located at end of table. 27
TABLE 2 (Cont.) SURRY POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD(l) REPORT UNITS Fish Semi-Annual Gamma Isotopic. pCi/k:g-wet Mn-54 130 Fe-59 2(,() Co-58, f>O 130 Zn-65 2(,() Cs-134 130 Cs-137 150 Crops Annually Gamma Isotopic pCi/kg-wet 1-131 f,() Cs-134 f,() Cs-137 80 Footnotes: This table is not a complete listing of nuclides which can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported. (1) ILDs indic:ate those levels that the environmental samples should be analyzed to, in accordance . with the Surry Radiological Environmental Program. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed. - (2) Quarterly composites of each location's weekly air particulate samples are analyzed for gamma emitters. 28
Program Exceptions
\
- h
<V
~J.~
e
IV. PROGRAM EXCEPTIONS REMP deviations for 1990 are listed in this chapter. Thermoluminescent Dosimeters (1LD) were discovered missing from 1LD stations No. 5 and No. 12 during the June routine monthly 1LD check. For.1LD station No. 5, the Company property sign on which the TLDs were attached had been removed without notification to the power station. The cause for the missing TLDs at station No. 12 could not be determined. 1LD data from adjacent monitoring locations was reviewed and no unusual data was evident. Three TLDs for the third quarter, two from station No. 17 and one form station No. 43, were inadvertently mixed in with the fourth quarter 1LDs during field replacement. As a result,* these three third quarter 1LDs were mistakenly reinstalled in the field and the three corresponding fourth quarter TLDs were returned for analysis instead; This was rectified and the three third quarter TLDs were returned to the analytical laboratory on November 2, 1990 for analysis. Discussions were held with technicians responsible for quarterly 1LD replacement, emphasizing the importance of accurate TLD replacement During a calendar year, 3361LD are located in the field as part of the REMP. This year, four of the 336 TLDs were found missing. This represents only 1.2% of the total number of TLDs. The four missing TLDs are not indicative of a programmatic weakness of the REMP. The TLDs are not under constant surveillance, are located up to 16 miles from the power station, and due to the nature of the assay are subjected to nature's elements. Due to a microorganism infestation in the lower James River (MSX/Dermo), oyster shell stock has been virtually depleted at the Newport News (Naseway Shoal) sample location. Sampling terminated at this location in 1988 and will recommence when the oyster beds revitalize as determined by the Commonwealth of Virginia. An alternative sampling location at Rock Landing Shoals was selected. The Commonwealth of Virginia also added Horsehead Shoals to the State Split sampling program for oysters. Horsehead Shoals is located between Deep Water Shoals and Rock Landing Shoals downstream of the power station. These samples will continue until the Newport News location is approved for sampling again. 29
REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1990
- SURRY Date of Location Description Sampling Reason(s) for Loss/Exception STA-05 Direct Radiation Second Quarter 'ILDmissing 1ID Sets 1/2 STA-12 Direct Radiation Second Quarter 'ILDmissing 1ID Sets 1/2 STA-17 Direct Radiation Third Quarter Fourth quarter 11.D returned instead of 1ID Sets 1/2 third quarter TLD.
STA-43 Direct Radiation Second Quarter Fourth quarter 1LD returned instead of 1ID Set 1 third quarter TLD. e 30
, 14 ., * * ,
- V.
SUMMARY
AND DISCUSSION - 1990 ANALYTICAL RESULTS DEFINITIONS Below are listed definitions of words and phrases for some of the common terms used in the following sections. AVERAGE ACTIVITY The arithmetic mean of detected radioactivity for all samples within a sampled parameter. IMPACT Defines the influence on people. ISOTOPE The radioactive element identified in a sampled pathway. LOWER LIMIT OF DETECTION (LLD)
. The LLD is used,to describe the smallest amount of radioactivity that can be detected by analysis instrumentation and is statistically significant above background level.
- The NRC provides Surry Power Station with LLD's that we must achieve using our analysis equipment.* Many times the results of an analysis is reported as below LLD and this may sound like a contradiction. However, the LLD being referred to is the Technical Specification (NRC provided) LLD and not the actual instrument LLD. The technology in the analytical field is advancing rapidly and the LLD's achieved by current state-of-the-art equipment is in many cases less than those provided by the NRC.
PATHWAY This is the route by which people may become exposed to man made and naturally occurring radioactivity. In this report, VEPCO and the State of Virginia sample and analyze components of many pathways; for example: air samples are obtained to analyze the exposure through the inhalation pathway and fish and other marine species are analyzed for exposure through the ingestion pathway. 31
- PERCENT TECHNICAL SPECIFICATION(% TS) REPORTING LEVEL This is the average level of radioactivity detected in a sample that must be reported to the NRC. VEPCO reports any activity detected in all samples. TREND Steady, rising or falling based on the same sampled parameter from preoperational data and previous years. V.
SUMMARY
A brief summary of the REMP radiological analyses is provided in this section.
- Based on the results of the 1990 Radiological Environmental Monitoring Program (REMP)
*. report, Surry Power Station is operated within regulatory limits.
- All samples analyzed were either below the Technical Specifications reporting limits or below the lower limits of detection. *
- Overall, the results were as expected for normal environmental samples. Naturally occurring radioactivity was observed in sample med.fa and was within the expected activity ranges.
- Occasional samples revealed the presence of man made isotopes. The concentration of isotopes attributable to station effluents are very low and of no significant dose consequence.
AIRBORNE EXPOSURE PATHWAY Airborne Radioiodine Charcoal cartridges are used to collect airborne radioiodine. Once a week, the samples are collected and analyzed. The results are presented in Table B-1. All results are below the lower limit of detection with no positive activity detected. These results are similar to preoperational data and the results of samples taken prior to and after the 1986 accident in the Soviet Union at Chernobyl. 32
Airborne Grog Beta Results of the weekly gross beta analysis are presented in Table B-2. A review of Table B-2 indicates that results from the station indicator compare favorably to the control location in Newport News; briefly summarized below: Quarterly Average Quarterly Average Calendar Ouarter All Locations Control Station 1st 15pCi/m3 15 pCi/m3 2nd 14pCi/m3 14pCi/m3 3rd. 15 pCi!m3 l6pCi/m3 4th 19pCi/m3 19pCi/m3 Quarterly averages are consistent with background radioactivity levels. The gross beta concentrations observed indicate a steady trend compared to levels found during the previous 5 years. Gross beta activity found during the preoperational and early operating period of Surry
- were higher because of nuclear weapons testing. During the past two decades nearly 740 nuclear weapons have been tested worldwide. In 1985 weapons testing ceased, and with the exception of the Chernobyl accident, airborne gross beta results have trended at stable levels.
Airborne Gamma Isotopic Air particulate filters are analyzed for isotopes that are gamma emitters. The results of the composite analysis are listed in Table B-3. No gamma emitting radioactivity attributable to the power station was detected. However, natural background radioactivity was detected in many of the samples. The two isotopes that were identified are beryllium-7 and potassium-40. Beryllium-7 is continuously produced in the upper atmosphere by cosmic radiation. Potassium-40 is naturally present in foods, building materials and soil.
- 33
I e TRENDING GRAPH - 1 GROSS BETA IN AIR PARTICULATES A-----------------------------------------------------------------------------------------------------------A
- J en 0
u a. GI v,l C"I
~
0 a. 3 10- -+--------.-------....-.-----,----------,*.-------.------"T",-----------------..-------,----------,,,---------------.--......------t 1984 1985 1986 1987 1988 1989 1990 1991
......"'9....... Indicator ----A--- Preoperational Average (A) Chernobyl ................. Control -- Lower Limit of Detection - Average
WATERBORNE EXPOSURE PATHWAY River Water The analysis results for the James River water sampling program are presented in Table B-
- 4. Samples of James River water are collected as monthly grab samples at both Surry Discharge and Scotland Wharf and bi-monthly grab samples at Hog Island Point, Newport News, Chickahominy River and Surry Intake. All samples are analyzed by gamma spectroscopy and for iodine-131 by a radiochemical procedure. These samples are also composited and analyzed for tritium and on a quarterly basis.
Naturally occurring potassium-40 was measured in 11 samples with an average concentration of 100.8 pCi/liter. All samples were analyzed for gamma emitting radioisotopes. With the exception of naturally occurring potassium-40, no other gamma emitters were detected. In particular, no iodine-131 was detected. This trend is consistent with previous years. Tritium was measured in 12 of 24 quarterly composite samples. The average tritium concentration was 319 pCi/liter. Preoperational data for tritium indicated levels of activity considerably higher than current levels due, in part, to atmospheric weapons testing. This years' level is less than the average for the past 5 years. The State of Virginia samples water from the station discharge and a control site located up stream of the station Scotland Wharf. These samples are taken as part of the State Split Sample Program and analyzed independently. The results are presented in Table B-5. River water from the station discharge and control location identified tritium concentration of 835 pCi/liter and 475 pCi/liter respectively. Scotland Wharf is taken as a weekly grab sample. Station discharge is sampled by a composite sampler and collected weekly. Monthly composite samples are prepared for gamma and iodine-131 analysis and quarterly composites are prepared for tritium analysis. In addition to the VEPCO monthly grab sample and the State Split composite sample, a VEPCO station discharge composite sampler was placed in service in May of 1989. A tritium composite from this sampler was analyzed monthly and then composited for quarterly analysis. The average tritium concentration for 1990 was 462 pCi/liter. The attached trend graphs provide a comparison of tritium concentration measured in the downstream sample (Surry Station Discharge) and in the upstream control location (Scotland Wharf). Also, provided for comparison is the average concentration of tritium in plant effluent 35
TRENDING GRAPH - 2 TRITIUM IN RIVER WATER a.. a..
- , 10000
,n 0
u v,l C. Cl) 0\
> R
*s G) 1000
\\ -d ~ .(\
0
/. *, o-ef~
C.
.X****1C* *** .-.
*v 11111
* -... . . . . . * .._ *9'
.. *** .". *** .,... .. 0
*u* *. ..~ "*
A )C.- ** '\
)c 1004-------...---.---i.-,--t,--.,-----.----.----.--..----,,---,.----.----.--.....---.,---,,-~
68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 Year ---o-- Surry Discharge Unit 1 critical on 12/22/72.
** ***** ** Scotland Wharf Unit 2 critical on 05/01/73.
Average LLD
TRENDING GRAPH - 2 (Cont.) TRITIUM VEPCO VS. STATION DISCHARGE UJ 0 0 --*-*-..*-------------* *~~~~~~~-~~~----------------------0 () a. t,.J CD -.J > 1000
. o*-*-*- ........a.
............ -o... .i::::a CD s=
0 a. [J' ...
' ' ,_.,. ...... ~ ~...-..:***-*
o*-*
'd
;; \
.,,.~.-*
o' .. ,
\ 0.
\
....0-----n
,.VO~... ;
[] r- \
\
\
\r..."*<'
"" ; \
\
......*o*,*' ', "d><*,. \'
'*' . .. ......a
'*o*-*-
100 - .......-----..-----~--.-----r----.,.----r----r----r-----r-----.---~- 1 /90 2/90 3/90 4/90 5/90 6/90 7 /90 8/90 9/90 10/90 11 /90 12/90
-*-*-O*-* Monthly Composite
- - -o- - Effluent
- 0 - Average LLD
e TRENDING GRAPH 2 (Cont.) RIVER WATER TRITIUM VEPCO VS STATION EFFLUENT
- , JI, u, ,' \ _______ o I\
V -------*--,----..!--\,-----------,---............ ' ' 0 C, ' Q. vl G)
> 1000 ' ' '
00
' \ ... ----k
+--- --..~,
G) 0 Q.
. ~ - - - - -
**=-*-*r._-*-*-***-*-Q*-.
-Ir I
I
.J--
** ... ._..,....-- _...o
------'\ \
\
\ \...
', ....--<>*..*-*--..,---**-**-***o
,~_._...-
---...... + ,
-o....~,......, ..._, _ _
--.... ........--- ... --- ---- ----- ~
o-- ',,._.~/ ****A*-.... ----------------- ......_ '"O
---.....--.._........., .......... _.......6. '
.,,..-A*-*-*-* ........ ***-**A 100 - - - - - - - - - - - - - - - - - -.......-------------'*-n-*"'----------------
flit,..... 6/89 9/89 12/89 3/90 6/90 9/90 12/90
-o--- Station Effluent -*-*-6-*-* Scotland Wharf Grab
----*--- Station Discharge Grab --+ - Station Discharge Composite
-o- Average LLD
. samples obtained prior to release from the station. As expected, the Surry discharge samples
./. indicated higher levels of tritium than the control location. Sampling methodology (grab sample versus composite) and frequency may cause problems in comparing results. The Station discharge composite sample taken by VEPCO personnel, however, does compare well with the station effluents. The trend follows the projected activity from samples taken prior to release. The comparison of these two data points is due to the increased frequency of sampling (hourly for the VEPCO samples versus once per six hours for the State sampler). The water in the discharge canal is further diluted by the river water beyond the discharge structure. The average tritium concentration in grab samples taken downstream of the station indicate good comparison to the State Split control concentration. Well Water Well water is not considered to be affected by station operations because there are no discharges made to this pathway. However, Surry does monitor well water and analyzes water samples from four indicator locations. The results of these sample analysis are presented in Table B-6. These samples were analyzed by gamma spectroscopy and indicated that there were no e man-made or naturally occurring radioisotopes present. Preoperational samples were only analyzed for gross alpha and gross beta. Gamma emitting isotopes have not been detected within the recent past and this trend is consistent throughout the operational monitoring program. All well water samples were analyzed for tritium. No tritium was detected in any of the control or indicator samples. Preoperational samples were not analyzed for tritium however, this years results indicate a decrease from previous operating data AQUATIC EXPOSURE PATHWAY Silt
. Silt samples were taken to evaluate any buildup of radionuclides in the environment due to the operation of the power station. The radioactivity in silt is a result of.precipitation of radionuclides in the waste discharges and the subsequent dispersion of the material by the river cUITent Sampling this pathway provides a good indication of the dispersion effects of effluents to the river. Buildup of radionuclides in silt could indirectly lead to increasing radioactivity levels in - clams, oysters and fish.
39
TRENDING GRAPH - 3 TRITIUM IN WELL WATER 10000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , 1000-:
. , ,ll.\
ll. , \ 0 mI . ,'
, \
\ ,
,Jj. \
\ I A.\
,-,--ll.
f-1' \ C It \ ' \ I D / [J\
/i ) \\
.i:,. 0 0 cu __ ... .---u
~-*-*-*-o ...
\
* \~
\
/ \
I ,-P.)\o,, I .1 ,
.x~ ,..,.*.*j'.X~D.:t::.*~---,°',
.*~*.
1
"* U' I **
I I ,*' \ \
,:..- , \
/**-***~~ ./~
en 100 - 0~
-~"*--*=lr~ -~---lil-----n --u
~..t:f
* ""** \
~~
..... '* \ I .,*
..,*~*1 **
a J.\
.... \
'.1
--1'---ft-- .rllL
--u--J .
104---.----.---......--..,.,---,.--....---,.---,.,---,.--..,.--.....--,--,--.,..---T-"--T-"--T1---....---,,.--,----, 1986 1987 1988 1989 1990 1991
-*O-* Station-Bacons Castle -*-*O*-* Station-Jamestown
*****>t-*** Station-Hog Island Reserve ---tr- Station-Surry Station
- Average of LLD
TRENDING GRAPH - 4 COBALT-58 IN SILT 10000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- l rn 1000 0
0 a. Cl) +'> I-' a
--a. .!I:
0 100 10 ..._______.._________________________________....----------..-------......... 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year
- Hog Island During the preoperational period cobalt-58 was not measured. - - ~- Station Intake Unit 1 critical on 12/22/72. ,..,....a,- Station Discharge Unit 2 critical on 05/01/73.
TRENDING GRAPH - 5 COBALT-60 IN SILT 10000
- I U)
~
A I \ 0 u C. a, 1000 I, 3 I\
\
\
I I ~ pl
/ ,P I * ,
a ~
.:r,:
- I I
I
'0 N
u I C. I 100
O... .,
., .,6
'O 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year
- Hog Island During the preoperational period cobalt-60 was not measured.
- - - Station Intake Unit 1 critical on 12/22/72. "Nl""0"'* Station Discharge Unit 2 critical on 05/01/73.
e TRENDING GRAPH - 6 CESIUM-134 IN SILT m Hog Island ****O*** Station Dis.
- - - Station Intake ta Average LLD
- I 1000 en
~-..**o-....q._
0 *.*. () a. CD +:> > CJ.I
- C,
.:i,c
- 100 ua.
10-1---........--......--...,..--~----...----.----,.......---..----.----...---......--........--....---...,..--~----...----.-------t 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year During the preoperational period cesium-134 was not measured.
TRENDING GRAPH - 7 CESIUM-137 IN SILT 0 0 () Cl. 1000 .i,. CD .i,. > CJ)
.:.r:
0 Cl. 100 _ __,,,_____......- - - - . - - . . - - - - . . . - - - - - - - - - - - - - - - - . . - - . . . - - - - - - - - - - - 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year m Hog Island During the preoperational period cesium-137 was not measured. - - - Station Intake Unit 1 critical on 12/22/72. Unit 2 critical on 05/01/73. ---*-O*** Station Discharge A Average LLD
Silt samples are collected from six locations both up stream and down stream of the power station. These samples are analyzed for gamma emitting radioisotopes. The results of these analyses are presented in Table B-7. The NRC does not assign reporting levels to radioisotopes measured in this pathway.' Surry's Technical Specifications require that the concentrations of man-made and naturally occurring gamma emitters be monitored and trended. Preoperational analyses indicates that there were no man-made radioisotopes present in this pathway. Cobalt-6(), cesium-137 and cesium-134 average levels indicate a decrease in concentration when compared to the previous 5 year trend During 1990 an increase in the average concentration was observed compared to 1989 and this is attributable to the continuous operation of both units at Surry Power Station. The concentration of manmade radioisotopes in silt is not projected to continu~ to increase. Surry Power Station currently has under construction a Radioactive Waste Treatment Facility which will employ state of the art technologies to reduce the volume and activity of liquid effluents and reduce the impact on the environment. This facility is scheduled to go into operation in late . 1991. Shoreline Sediment Unlike river bottom silt, shoreline sediment may provide a direct dose to humans. Buildup of radioisotopes along the shoreline may provide a source of direct exposure for those using the area for commercial and recreational uses. Samples were taken in February and August at Hog Island Point and at Burwell's Bay. The samples were analyzed by gamma spectroscopy and the results are presented in Table B-8. This exposure pathway was not selected for analysis during the preoperational years. Nevertheless, samples analyzed over the past 5 years from this release pathway indicate a decreasing trend in the detection of gamma radioisotopes. This years analysis along with last years results indicates that no radioisotopes attributable to the operation of the power station have been detected. Naturally occurring radioisotopes were measured in several of the samples. Potassium-40, thorium-228 and radium-226 show a steady trend over the recent past. 45
INGESTION EXPOSURE PATHWAY Milk Mille samples are an important indicator for measuring the affect of radioactive iodine, and* other radioisotopes in airborne releases. The dose consequence to man is from both a direct and indirect exposure pathway. The direct exposure pathway is from the inhalation of radioactive material. The indirect exposure pathway is from the grass-cow-milk pathway. In this pathway radioactive material is deposited on the plants consumed by the dairy animals. The radioactive material is in turn passed on to man via the millc. The results of iodine-131 and other gamma analysis of milk are presented in Table B-9. Iodine-131 has not been detected in milk prior to and since the 1986 accident at Chernobyl in the Soviet Union. The lower limit of detection was 0.5 pCi/liter for all samples. Preoperational data shows that cesium-137 was detected in this pathway. The average activity over the past five years is consistent with the preoperational data. This year shows a significant decline in cesium-137 as none was detected in the(,() samples analyzed. Naturally occurring potassium-40 was detected in all samples analyzed. There is a slight decrease in the average concentration of this raioisotope when compared to the previous two years and is less than the average for the past five years. The preoperational monitoring program did not analyze for this radioisotope. Strontium-90 was detected in all of the samples collected in participation with the State Split Program. Preoperational data shows levels 5 to 6 times higher than present values. This years analysis show a decrease when compared to the previous two years and is less than the average for the past 5 years. Strontium-90 is not a part of station effluents but rather a product of weapons fallout Aquatic Biota All plants and animals have the ability to concentrate certain chemicals. Radioisotopes display the same chemical properties as their non..:radioactive counter part. VEPCO samples various aquatic biota to determine the accumulation of radioisotopes in the environment. The results of the sampling program for this pathway are detailed below. Clams were analyzed from 5 different locations. The results of the analysis is presented in Table B-10. As expected, naturally occurring potassium-40 was detected in all 18 samples. Based 46
TRENDING GRAPH - 8 COBALT-58 IN CLAMS 1000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - El Chickahominy ***
- 0 * *
- Hog Island
- - Surry Discharge /!J Average LLD en 0
u
- a. 100 CD
\
\
\ ,' ',
, ..0 o---a ti ******D*****'CJ 10 -t----..--......----..--......----..--......----..---......-----.---......-----.---"'9'--......--"'T--......-----1 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year During the preoperational period cobalt-58 was not measured.
TRENDING GRAPH - 9 COBALT-60 IN CLAMS 1000 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - a Chickahominy - -
- Hog Island
----,o--- Surry Discharge ts Average LLD
(/) 0 C.
.* I
~ 100 .* I
.i::. 00
> -d I I
Cl
.:ac ' 'a I I
--***O-*****0---***v
------0.-. ** 0
- __ -a - - -a *--'Q 0
C.
'a .,. .,. .,a '\ *.',
\
\ .
' \ .,. .,.a' \
b
'If 10+--...---------..-----------------....---------------------------------------1 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 Year During the preoperational period cobalt-60 was not measured.
e e TRENDING GRAPH - 10 CESIUM-137 IN CLAMS a Chickahominy --O-- Hog Island
****O*** Surry Discharge ~ Average LLD ti) .,.a, 0
(,) _.,,. a. '-0 Cl) 100 a
.:.I:
0 a. 10 ......---.---------...----,.----..----...---~---.-----------------------.....---------------.1 74 75 76 77 78 79 80 81 82 83 84 . 85 86 87 88 89 90 Year During the preoperational period cesium-137 was not measured.
on the previous 5 years, the trend of potassium-40 in clams is decreasing. Potassium-40 is a naturally occurring radioisotope and is not a component of station effluent. No gamma emitting radioisotopes were detected in any of the samples. This is consistent with preoperational data. The trend of gamma emitting radioisotopes in clams over the recent past continues to decrease and is well below the lower limits of detection. This marked decrease coincides with the extensive steam generator replacement project completed in 1982. Oysters were analyzed from 5 different locations. The results of the analysis is presented in Table B-11. As expected, naturally occurring potassium-40 was detected in 21 of 24 samples. Based on the previous 5 years, the trend of potassium-40 in oysters is decreasing. The current level of potassium-40 is less than the preoperational average. No gamma emitting radioisotopes were detected in any samples. This is consistent with preoperational data and data collected since the 1986 accident at Chernobyl in the Soviet Union. Crab samples were collected in June from the discharge canal of the station and analyzed by gamma spectroscopy. The results of this analysis is presented in Table B-12. As expected naturally occurring potassium-40 was detected. Based on the previous 5 years, the trend of potassium-40 in crabs ls steady. Potassium-40 is a naturally occurring radioisotope and is not a component of station effluent. No other gamma emitting radioisotopes were detected in this sample. This is consistent with preoperational data and data collected during the past 5 years. Four fish samples were collected in April and October from the station discharge canal and analyzed by gamma spectroscopy. The results of this analysis is presented in Table B-13. As expected naturally occurring potassium-40 was detected in all samples. Based on the previous 5 years, the trend of potassium-40 in fish is decreasing. Cesium-137 was observed in one of the fish samples with an activity of 18.7 pCi/kg. This is lower than the average of the past 5 years and indicates a decreasing trend over this time period. However, this sample is less than the lower limits of detection (150 pCi/kg) and considerably below the Technical Specification reporting level of 2,000 pCi/kg. Food Products and Vegetation Food products and vegetation samples were collected from four different locations and analyzed by gamma spectroscopy. The results of this analysis is presented in Table B-14. As expected naturally occurring potassium-40 was detected in all samples. Based on the previous 5 years, the trend of potassium-40 in food products and vegetation is increasing. Potassium-40 is a so
naturally occurring radioisotope and is not a component of station effluent. Naturally occurring
- e beryllium-7 was detected in one of the three samples. Based on the previous 5 years, the trend of beryllium-7 is steady. Cesium-137 was measured in two soybean samples with an average activity of 11.3 pCi/kg. This measurement is less than the average concentration over the past 5 years and indicates a slight decreasing trend. This sample is less than the lower limits of detection (80 pCi/kg) and is considerably less than the Technical Specification reporting limits of 2,000 pCi/kg.
DIRECT RADIATION EXPOSURE PATHWAY A thermoluminescent dosimeter (TLD) is an inorganic crystal used to detect ambient radiation. TLDs are placed in two concentric rings around the station at the site boundary and at approximately 5 miles. TLDs are also placed in special interest areas such as population areas and nearby residents. Several TLDs also serve as controls. These 1LDs measure ambient radiation from naturally occurring radioisotopes in the air and soil, radiation from cosmic origin, fallout from nuclear weapons testing, station effluents and direct radiation from the station. The results of this analysis is presented in Table B-15 and B-16. Control and indicator averages indicate a decreasing trend in ambient radiation levels. This years levels are slightly less than the previous five years. 51
e TRENDING GRAPH*- 11 DIRECT RADIATION MEASUREMENTS-TLD RESULTS 100
- J en 0
u Q. Cl) u, N
.c C
0
- i 10
'C ca C
ca en a: E 1 I
- I *
- I *
- I *
- I
- I I
- I I
- I 80 81 82 83 84 85 86 87 88 89 90 . 91 Year .... 0... Site Boundary
****,tr*** 5 Mile Boundary
SUMMARY
OF RESULTS - SURRY REMP PROGRAM
- Isotope Average Actlvlty TS Limit Trend % TS Reporting Level Impact Airborne Exposure Pathway Beryllium 7 0.087 pCi/m3 Not Applicable Steady Not applicable. Naturally occurring isotopes do not have assigned None; this is a naJUrally occurring reporting levels because they are considered to contribute to natural radioisotope.
background radiation levels. Potassiwn 40 0.004 pCi/m3 Not Applicable Decreasing Not applicable. This is a naturally occurring radioisotope. None; this is a naJUrally occurring radioisotope. Waterborne Exposure Pathway River Water Potassiwn 40 101.0pCi/l Not Applicable Steady Not applicable. This is a naturally occmring isotope. None; this is a naJUrally occurring radioisotope. Tritium 319pCi/l 30,000 pCi/l Decreasing 1.06% None; James River water is not used for a Average for drinking water supply or crop inigation. Indicator Locations u, Tritiwn 0.0 pCi/1 30,000 pCi/1 Steady 0.0% None vi Average for Caurol Locations Well Water Gross gamma No gamma emitters Not Applicable Steady 0.0% None mutters natural or man-made were detected Tritium 0.0pCi/l Not Applicable Decreasing . 0.0% None Aquatic Exposure Pathway Slit Cesiwn 134 181 pCi/kg Not Applicable Decreasing Not Applicable The NRC does not assign reporting levels for radioisotopes measured in this pathway. However these radioisotopes may indirectly effect the concentration of radioactivity found in the ingestion pathway.
e
SUMMARY
OF RESULTS - SURRY REMP PROGRAM Isotope Average Activity TS Limit Trend % TS Reporting Level Impact Aquatic Exposure Pathway (Cont.) Cesiwn 137 771 pCi/kg Not Applicable Decreasing Not Applicable The NRC does not assign reporting levels for radioisotopes measured in this pathway. However these radioisotopes may indirectly effect the concentration of radioactivity found in the ingestion pathway. Cobalt 60 688 pCi/kg Not Applicable Decreasing Not Applicable The NRC does not assign reporting levels for radioisotopes measured in this pathway. However, these radioisotopes may indirectly effect the concentration of radioactivity found in the ingestion pathway. Cobalt58 0.0 pCi/kg Not Applicable Decreasing Not Applicable The NRC does not assign reporting levels for radioisotopes measured in this pathway. However, these radioisotopes may indirectly effect the concentration of radioactivity found in the ingestion pathway. Shoreline Sediment Potassiwn 40 4850 pCi/kg Not Applicable Steady Not Applicable This is a naturally occurring isotope. None; this is a naturally occurring radio-isotope. Radiwn 226 442 pCi/kg Not Applicable Steady Not Applicable. This is a naturally occurring isotope. None; this is a naturally occurring radio-isotope. Thoriwn 228 121 pCi/kg Not Applicable Steady Not Applicable. This is a naturally occurring isotope. None; this is a naturally occurring radio-isotope. Ingestion Exposure Pathway Milk Potassium 40 1300pCi/l Not Applicable Decreasing Not Applicable. This is a naturally occurring isotope. None; this is a naturally occurring radio-isotope. Iodine 131 0.0 pCi/1 3.0 pCi/1 Steady 0.0% None
e
SUMMARY
OF RESULTS - SURRY REMP PROGRAM Isotope Average Activity TS Limit Trend % TS Reporting Level Impact Ingestion Exposure Pathway (Cont.) Aquatic Biota Clam Potassium 40 469 pCi/kg Not Applicable Decreasing Not Applicable. This is a naturally occurring isotope. None, this is a naturally occurring radio-isotope. Oyster Potassium 40 595 pCi/kg Not Applicable Decreasing Not Applicable. This is a naturally occurring isotope. None, this is a naturally occurring radio-isotope. Crab Potassium 40 2430pCi/kg Not Applicable Steady Not Applicable. This is a naturally occurring isotope. None, this is a naturally occurring radio-isotope. Fish (Jl Potassium 40 1511 pCi/kg Not Applicable Decreasing Not Applicable. This is a naturally occurring isotope. None, this is a naturally occurring radio-(Jl During 1990 isotope. Ccsiwn-137 18.7 pCi/kg 2,000 pCi/kg Decreasing Less than 1.0% None; the concentration of radioactivity fmmd in one sample this year is comp-arable to last year. The percent Technical Specification Reporting Level indicate an insignificant ingestion dose consequen, Food Products & Vegetation Potassium 40 8736 pCi/kg Not Applicable Increasing Not Applicable. This is a naturally occurring isotope. None; this is a naturally occurring radio-isotope. Beryllium 7 220pCi/kg Not Applicable Steady Not Applicable. This is a naturally occurring isotope. None; this is a naturally occurring radio-isotope. Cesium-137 11.3 pCi/kg 2,000 pCi/kg Decreasing Less than 1.0% None; the concentration of radioactivity found in samples this year is comparable to last year and may be attributable to worldwide fallout. The percent Technical Specification Reporting Level indicate an insignificant ingestion dose consequence.
e
SUMMARY
OF RESULTS - SURRY REMP PROGRAM Isotope Average Activity TS Limit Trend 'I, TS Reporting Level Impact Direct Radiation Exposure Pathway Tbermolumlnescent Dosimeter Gross Gamma for 5.2 mR/std mth. Decreasing This is the radiation level at the cmtrol site; Control Stations this is "background radiation." This number should be subtracted from the average activity for the gross gamma at indicator stations to give a true ambient radiation level. Gross Gamma for 6.3 mR/std mth. Decreasing When background (5.0 mR/standard month) Surry Site area is subtracted from this indicator location, the 1LDaverage remaining Till average 1.1 is the result of station operations. Gross Gamma for 5.8 mR/std mth. Decreasing When background (5.2 mR/standard month) indicator stations is subtracted from this indicator location, excluding the SWiy .* the remaining 6 tenths of 1.0 mR is not Site area 1LDs significant when compared to the U.S. average background radiation levels of 300 mRem/year.
Conclusion VI. CONCLUSIONS The results of the 1990 Radiological Environmental Monitoring Program for Surry Nuclear Power Station have been presented. Based on the results of the REMP, Surry Power Station is operating within regulatory limits. All samples analyzed were either below the Technical Specifications reporting limits or below the lower limits of detection. Overall, the results were as expected for normal environmental samples. Naturally occurring radioactivity was observed in sample media and was within the expected activity ranges. Occasional samples revealed the presence of man made isotopes. The concentration of isotopes attributable to station effluents are very low and of no significant dose consequence. As a method of referencing the measured radionuclide concentrations in sample media to the dose consequence, the data may be compared to the Reporting Level Concentratioris listed in the NRC Regulatory Guide* 4.8. These concentrations are based upon 25% of the annual dose commitment recommended by 10CFR50, Appendix I, to meet the criterion "As Low as is Reasonably Achievable." A,irborne
- Exposure Air particulate gross beta concentrations of all the indicator locations for 1990 trend well with the control location. The gross beta concentrations indicate a steady trend when compared to the levels found during the previous 5 years. Gamma isotopic analysis of the particulate samples identified natural background radioactivity. No radioactivity attributable to the operation of the power station were identified.
River Water All river water samples were analyzed for gamma emitting radioisotopes. With the exception of naturally occurring potassium-40, no other gamma emitters were detected. In particular, no iodine-131 was detected. Tritium activity was measured in several samples with an average concentration of 319 pCi/liter. This value is less than the average for the past five years. The percent of Technical
.Specification Peporting Level is 1.06% of the VEPCO Reporting L?vel Concentration. Because
there is no supply of drinking water or water used for.crop inrrigation, there is an insignificant dose consequence to the public from this pathway. Research of the preoperational data for tritium indicates levels of activity considerably higher than current levels due to atmospheric weapons testing. Well Water Well water samples were analyzed and indicated that there were no man made or naturally occurring radioisotopes present. Silt The NRC does not assign reporting levels to radioisotopes measured in this pathway. The average levels of man made radioisotopes in silt indicate a decrease in concentration when compared to the previous 5 year trend. During 1990 an increase in the average concentration was observed compared to 1989 and this is attributable to the continuous operation of both units at Surry Power Station. Shoreline Sediment Only naturally occurring radioisotopes were detected at concentrations equivalent to normal background activities. There were no radioisotopes attributable to the operation of the power station found in any sample. Milk Milk samples are an important indicator for measuring the affect of radioactive iodine and radioisotopes in airborne releases. Iodine-131 was not measured in any of the 60 milk samples. Naturally occurring potassium-40 was detected at a slight decrease in average concentration when compared to the previous two years. The concentration of strontium-90 in this years analysis shows a decrease when compared to the previous two years. Strontium-90 is not a part of station effluent, but rather a product of weapons fallout. 58
Aquatic Biota Clams, Oysters and Crabs As expected, naturally occurring potassium-40 was detected in all samples. Based on the previous 5 years, the trend of potassium in clams and oysters is decreasing (in crabs the trend is steady). No gamma emitting radioisotopes were detected in any of the samples. This trend is consistent with preoperational data.
. Fish As expected, naturally occurring potassium-40 was detected in all samples. Based on the previous 5 years, the trend of potassium-40 in fish is decreasing.
Cesium-137 was observed in one of the fish samples. The concentration in this one sample is lower than the average of the past 5 years and indicates a decreasing trend. Further, this sample is less than the lower limits of detection for the instrumentation and is considerably below the Technical Specification Reporting Limits. The percent of Technical Specification Reporting Level 9 for this sample is calculated to be less than 1 % and indicates an insignificant ingestion dose consequence. Food Products and Vegetation As expected, naturally occurring potassium-40 and beryllium-7 (one sample) was detected in samples collected and analyzed. Cesium-137 was observed in two soybean samples. The concentration of radioactivity found in samples this year is comparable to last year and may be attributable to world wide fallout. The percent Technical Specification Reporting Level for this sample is calculated to be less than 1% and indicates an insignificant ingestion dose consequence. Direct Radiation Exposure Pathway
- Control and indicator averages indicate a decreasing trend in ambient radiation levels. This
. years levels are slightly less than the previous five years.
59
The direct radiation exposure that may be attributed to the station operation is 1.1 mR/standard month (0.036 mR/day). This exposure is not significant when compared to the United States average background radiation levels of 360 mRem/year (0.98 mRem/day). 60
e
- I
VII. REFERENCES,
- 1. Virginia Electric and Power Company, Surry Power Station Technical Specifications, Units 1 and 2.
- 2. Virginia Electric and Power Company, Station Administrative Procedure, VPAP-2103, "Offsite Dose Calculation Manual," Rev. 0, May 31, 1990.
- 3. Title 10 Code of Federal Regulation, Part 50 (10CFR50), "Domestic Licensing of Production and Utilization Facilities."
- 4. United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," October, 1977.
- 5. United States Nuclear Regulatory Commission, Regulatory Guide 4.8 "Environmental Technical Specifications for Nuclear Power Plants," December, 1975.
- 6. USNRC Branch Technical Position, "Acceptable Radiological Environmental Monitoring Program," Rev. 1, November 1979.
- 7. NUREG 0472, "Radiological Effluent Technical Specifications for PWRs," Rev. 3, March 1982.
- 8. National Council on Radiation Protection and Measurements, Report No. 39, "Basic Radiation Protection Criteria," Washington, D.C., January 1971.
- 9. National Council on Radiation Protection and Measurements, Report No. 45, "Natural Background Radiation in the United States,11 Washington, D.C., November 1975.
- 10. National Council on Radiation Protection and Measurements, Report No. 95, "Radiation Exposure of the U.S. Population from Consumer Products and Miscellaneous Sources," Washington, D.C., December 1987.
- 11. DOE/NE-0072, "Nuclear Energy and Electricity, The Harnessed Atom," US Dept.
of Energy, 1986. 61
- 12. Eichholz, G., "Environmental Aspects of Nuclear Power," Lewis Publishers, Inc.,
1985.
- 13. Eisenbud, M., "Environmental Radioactivity," Academy Press, Inc., Orlando, Fl, 1987.
- 14. Fitzgibbon, W., "Energy Skill Builders, Nuclear Reactor," Enterprise for Education, Inc., 1987.
- 15. Glasstone, S., and Jordan, W., "Nuclear Power and its Environmental Effects,"
American Nuclear Society, 1982. 62
Appendices APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
TABLES - 1990 63
e RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1990 ANALYSIS AND LOWER LIMIT NUMBER.OF MEDIUM OR PAnIWAY TOTAL NUMBFR. CF ALL INDICATOR LOCATIONS LOCATION wrrn IIlGHEST MEAN OONI'ROL.LOCATION NONROUllNE SAMIU.D OF ANALYSES DE1EC1l0N MEAN NAME MF.AN MEAN REPORTED (UNIT OF MBASUREMENT) PFRR>RMED (LLD) (1) RANGE DISTANCE AND DIRECI10N RANGE RANGE MEASUREMENTS Air Iodine 1-131 416 0.07 -(01364) NIA NIA -(0152) 0 (pCi/m3) Airborne Gross Beta 416 10 15.9(364/364) AIL 5.1 mi WSW 16.8(52152) 15.8(52152) *O Particulates (6.2-39) (7.3-38) (6.6-32) (lE-03 pCi/m3) Gamma 32 Be-7 32 86.7(28/28) NN 16.5 mi ESE 96.2(414) 96.2(414) 0 (46.6-130) (58.0-122) (58.0-122) °'.,. K-40 32 130 3.91(3/28) DOW 5.1 mi ENE 5.12(114) -{0/0) 0 (3.31-5.12) (1) LLD is lower limit of detection as defmed and required in USNRC Branch Technical Position on an Acceptable Radiological Envirorunental Monitoring Program, Revision l, November 1979.
- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 toDECEMBER31, 1990 ANALYSIS AND WWERLIMIT NUMBEROF MIIDIUMORPAlHWAY TOTAL NUMBER <F ALL INDICATOR LOCATIONS LOCATIONWDJI IIlGHEST MEAN OONl'ROLLOCATION NONROUTINE SAMPLED OF ANALYSF.s DE'IF..C110N MEAN NAME MF.AN MEAN REPOR'IED (UNIT OF MEASUREMENT) PERR>RMED (LLD) (1) . RANGE DISTANCE AND DIRECl10N RANGE RANGE MEASUREMENTS River Water (a) Gamma 48 (pCi/liter) K-40 48 101(11142) SI 12.0mi SE 189(116) -(016) 0 (43.6-189) Tritium 24 2000 319(12/20) IIlP 2.4mi NE 500(314) -(014) 0 (Quarterly) . (140-950) (260-950) River Water (b) Gamma 24 °' u, (pCi/liter - State Split) K-40 24 0 71.7(3/12) . SD 0.17mi NW 71.7(3/12) 61.6(1/12) 0 (61.7-79.4) (61.7-79.4) Tritium 24 2000 835(414) SD 0.17mi NW 835(414) 475(2/4) 0 (Quarterly) (270-1500) (270-1500) (350-600) Well Water Gamma 16 (pCi/liter) K-40 16 -(0116) NIA NIA NONE 0 Tritium 16 2000 . -(0116) NIA NIA NONE 0 (Quarterly) (I) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGJNIA JANUARY 1 to DECEMBER 31, 1990 ANALYSIS AND LOWERLIMIT NUMBERCF MEDIUM OR PATIIWAY TOTAL NUMBFR. CF ALL INDICAIQR LOCA))Q~S LOCA))QNWITII IIlGHESI MEAN OONfROL LOCATION NONROUTINE SAMPUID OFANALYSES DE'IBCllON MFAN NAME MFAN MEAN REPORIBD (UNIT OF MEASUREMEN1) PFRR>RMED (LLD)(l) RANGE DISTANCE AND DIRECflON RANGE RANGE MEASUREMENTS Silt Gamma 12 pCi/kg (dry) Be-7 12 9')3(2/10) SI 1.9mi ESE 1270(1/2) -(0/l.) . 0 (715-1270) K-40 12 15678(9/10) SI 1.9miESE 19100(2/2) 16950(2/2 0 (11800-20800) (17400-20800) (16100-17800) Co-60 12 688(9/10) SD 0.5miNNW 1911(2/2) 249(1/2) 0 (66.9-3610) (212-3610) a, Cs-134 12 150 181(3/10) SD 0.5miNNW 231(1/2) -(0/l.) 0 a, (156-231) Cs-137 12 180 771(10/10) SI 1.9mi ESE 1262(2/2) 615(2/2) 0 (173-1730) (954-1570) (562-667) Ra-226 12 2164(10/10) CHIC 11.2miWNW 3305(2/2) 3305(2/2) 0 (1540-2770) (3160-3450) (3160-3450) Th-228 12 1275(10/10) CHIC 11.2miWNW 1550(2/2) 1550(2(1.) 0 (860-1680) (1540-1560) (1540-1560) (1) 11..D is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1990 ANALYSIS AND LOWER LIMIT NUMBEROF MEDIUM ORPATIIWA Y TOTAL NUMBER CF ALL INDICAIQR LOCATIONS LOCAIIOti WITII HIGHESI MEAN CONfROL LOCATION NONROUTINE SAMPLED OF ANALYSF.S DE'IF..CTION MF.AN NAME MFAN MEAN RFPORTED (UNIT OF MEASUREMENI) PERFORMED (ll.D) (1) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Shoreline Sediment Gamma Spec 4 (pCi/kg dry) K-40 4 4850(4/4) HIR 0.8miN 6570(2/2) NONE 0 (2910-6930) (6210-6930) Ra-226 4 442(2/4) HIR 0.8miN 450(1/2) NONE 0 (434-450) Th-228 4 121(2/4) HIR 0.8miN 121(2/2) NONE 0 °' ---l (105-137) (105-137) (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Envirorunental Monitoring Program, Revision 1, November 1979.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DOCKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1990 ANALYSIS AND LOWER LIMIT NUMBEROF MEDIUMORPATIIWAY TOTALNUMBFR CF ALL INDICATOR LOCATIONS LOCATION WfDJ lilGHIID MEAN OONIROL LOCATION NONROlITINE SAMruID OF ANALYSF.S DB'JF.CI10N MFAN NAME MFAN MF.AN REPORTED (UNITOFMEASUREMENT) PERR>RMED (ll.D)(l) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Milk Gamma 60 (pCi/lita) K-40 60 1300(48148) CP 3.7mi NNW 1338(12112) 1265(12/12) 0 (1130-1480) (1220-1440) (1150-1360) 1-131 60 1 -(0148) NIA NIA -(0/12) 0 Cs-137 60 10 -(0148) NIA NIA -(0112) 0 CJ\ 00 Sr-89 12 -(0112) NIA NIA -(0/0) 0 Sr-90 12 1.62(12/12) CP 3.7mi NNW 3.40(3.3) -(0/0) 0 (0.50-3.7) (3.2-3.7) (1) lLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision I. November 1979.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION DCX:KET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 to DECEMBER 31, 1990 ANALYSIS AND LOWER LIMIT NUMBEROF MEDIUMOR.PATIIWAY TOTAL NUMBER <F AIL INDICATOR LOCATIONS LOCATION WIDJ lllGHEST MEAN
- CONIROL LOCATION NONROUI1NE SAMPUID OF ANALYSF.S DE'IECTION MF.AN NAME MFAN MFAN REPORIBD (UNIT OF MF.ASUREMEN'I) PERR>RMED (LLD) (1) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS Clams GammaSpec 30 (pCi/kg wet)
K-40 469(21/24) CHIC 11.2 mi WNW 560(6/6) 560(6/6) 0 (321-585) (192-1190) (192-1190) Oysters GammaSpec 24 (pCi/kg wet) K-40 595(21/24) RLS 7.8 mi SE 663(6/6) NONE 0 (370-900) (520-900) °'
- .o Crabs Gamma Spec (pCi/kg wet)
K-40 2430(1/1) SD 0.6miNW 2430(1/1) NONE 0 Fish Gamma Spec 4 (pCi/kg wet) K-40 1511(4/4) SD 0.6miNW 1511(4/4) NONE 0 (942-2010) (942-2010) Cs-137 150 18.7(1/4) SD 0.6miNW 18.7(1/4) NONE. 0 (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SURRY NUCLEAR POWER STATION IX>CKET NO. 5-280-281 SURRY COUNTY, VIRGINIA JANUARY 1 toDECEMBER31, 1990 ANALYSIS AND LOWER LIMIT NUMBEROF MEDIUMORPATIIWAY TOTALNUMBFR CF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CON'IROL LOCATION NONROUTINE SAMPIED OF ANALYSF.S DE1ECTION MEAN NAME MEAN MEAN RFPOR'IED (UNIT OF MF.ASURBMEN'I) PERR>RMED (ILD) (1) RANGE DISTANCE AND DIRF..CfION RANGE RANGE MEASUREMENTS Direct Radiation Ganuna 332 2 6.0(316/316) 38 16.5 mi ESE 7.9(8/8) 5.2(16/16) 0 TLDs (1.1-9.0) (7.1-9.0) (4.2-6.3) (mR/std. month) Vegetation Gamma 5 (pCi/k:g wet) K-40 5 8736(5/5) Brock's Garden 15200(1/1) NONE 0 (4300-15200) Be-7 5 220(1/5) Turner's Garden 220(1/1) NONE 0 Cs-137 5 11.3(2/5) Slade's Garden 12.4(1/1) NONE 0 (10.2-12.4) (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979. .
APPENDIX B DATA TABLES 71
e e e TABLE B-1 (Page 1 of 4) SURRY -1990 CONCENTRATIONS OF IODINE-131 IN FIL1ERED AIR pCi/m3 +/- 2 Sigma STATIONS COILECTION DA1E ss HIR BC ALL CP DOW FE NN
,JANUARY 0 l/02/90-01/()()/90 < .03 .< .03 < .03 < .03 <.03 < .03 < .03 < .03 Ol/()()/90-01/16/90 <.02 < .02 <.02 < .02 < .01 < .02 < .01 <.02 01/16/90-01/23/90 <.02 < .02 < .02 < .02 < .02 <.02 < .02 < .02 01/23/90-01/29/90 < .02 < .02 < .02 < .02 < .008 < .008 < .008 < .008 FEBRUARY 01/29/90-02/05/90 < .02 <.02 <.02 < .02 <.02 < .02 < .02 <.02 02/05/90-02/13/90 < .01 < .01 <.01 < .01 < .01 < .01 < .01 < .01
-.._J 02/13/90-02/20/90 < .02 < .02 < .02 < .02 < .01 < .01 < .01 < .01 N 02/20/90-02/27/90 < .01 < .01 <.01 < .01 <.02 <.02 < .02 < .02 MARCH 02/27/90-03/06/90 < .02 <.02 < .02 < .02 < .02 <.02 <.02 < .02 03/06/90-03/13/90 < .02 < .02 < .02 < .02 < .02 < .02 < .02 < .02 03/13/90-03/20/90 < .02 <.02 < .01 < .02 < .01 < .01 < .01 < .02 03/20/90-03/28/90 < .01 < .01 < .01 < .01 < .02 < .02 < .02 < .02 03/28/90-04/03/90 < .02 <.02 < .02 < .02 < .03 < .03 < .03 < .03
e - TABLE .B-1 e (Page 2 of4) SURRY-1990 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS COU..ECfION DATE ss HIR BC ALL CP DOW FE NN Al!lUL 04/03,90-04/lOf.)() <.01 < .01 < .01 < .01 < .02 < .02 < .02 <.02 04/10,90-04/17f.)() < .01 < .01 < .01 < .01 <.01 < .01 < .01 < .01 04/l 7,90-04/24f.)() < .02 < .02 < .02 < .02 < .02 < .02 < .02 < .02 04/24,90-05/0lf.)() < .02 * < .02 < .02 <.02 < .02 < .02 < .02 < .02 Mil 05/0l,90-05/08f.)() < .01 <.01 < .01 < .01 <.02 < .02 < .02 < .02 05/08,90-05/15f.)() < .02 < .02 < .02 < .02 < .02 < .02 < .02 < .02 '-I 05/15,90-05/22f.)() < .02 < .02 < .01 < .02 ~
< .01 < .01 < .01 < .01 05/22,90-05/29f.)() < .01 < .01 < .01 < .01 <.02 < .02 < .02 < .02 .I.llliE 05/29,90-06/0Sf.)() < .02 < .02 < .02 <.02 < .02 <.02 <.02 <.02 06/05,90-06/12f.)(} < .01 < .01 < .01 < .01 <.02 < .02 < .02 < .02 06/12,90-06/19f.)() <.02 <.02 < .02 < .02 < .02 < .02 < .02 < .02 06/l 9,90-06/26f.)() < .02 < .02 < .02 < .02 <.02 <.02 < .02 < .01 06/l6,90-07/03f.)() < .01 < .02 < .01 < .01 . < .03 * < .02. <.03 < .02 _
e e e TABLE B-1 (Page 3 of 4) SURRY-1990 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS COU..ECTION DA1E ss HIR ec* ALL CP DOW FE NN
.I.llLX 07/03/90-'1l/10/90 < .02 < .02 < .02 < .02 <.02 < .02 < .02 <.02 07/10/90-'1l/17/90 <.02 .< .02 < .02 < .02 < .01 < .02 < .02 < .02 07/17/90-'1lf]A/90 < .01 < .01 < .01 < .01 <.02 < .02 < .02 <.02 07/l4/90-'1l/31/90 < .01 < .01 < .01 < .01 < .02 < .02 < .02 <.02 AUGUST 07/31/90-08/(17/90 < .02 < .02 < .02 < .01 < .02 < .02 <.02 <.02 08/07/90-08/14/90 < .02 < .02 < .02 < .02 < .02 < .02 < .02 <.02
--.a 08/14/90-08/21,4)(} < .02 < .01 < .01 < .01 < .02 < .02 <.02 < .02 .... 08/21 fJ0-08/28/90 < .01 < .01 < .01 < .01 < .01 < .01. < .01 < .01 SEPTEMBER 08/l8/90-(1)/05/90 <.01 < .01 <.01 < .01 < .02 < .02 <.02 < .02 00/05/90-(1)/11/90 < .02 < .02 <.02 <.02 < .01 * < .01 < .01 < .01 00/11/90-00/18/90 < .01 < .01 < .01 < .01 <.02 < .02 <.02 < .02 00/18/90-00/25/90 < .02 < .02 < .02 < .02 <.02 <.02 < .02. < .02 OO/l5/90-I0/02/90 <.02 <.02 <.02 < .02 < .02 < .02 < .02 < .02
e e e TABLE B-1 (Page4 of4) SURRY-1990 CONCENTRATIONS OF IODINE-131 IN FILTERED AIR pCi/m3 +/- 2 Sigma STATIONS COLLECTION DATE ss HIR BC ALL CP DOW FE NN OCTOBER 10,U2/90-10/()l),9() <.02 <.02 <.02 < .02 <.02 <.02 < .02 < .02 10/09/90-10/16,90 <.02 < .02 < .02 < .02 < .02 < .02 <.02 < .02 10/16/90-10/23,90. <.02 < .02 <.02 < .02 < .01 < .01 < .01 < .01 10/23/90-10/30,90 < .02 <.02 < .02 < .02 < .02 <.02 < .02 <.02 NOVEMBER 10/30/90-11/06,90 <.02 < .02 <.02 < .02 < .01 < .01 <.02 < .01
- -...J ll,U6/90-ll/12,90 < .02 < .01 <.02 < .02 <.02 <.02 < .02 < .02 tr, l l /12,90-11 /20/90 <.02 < .04 <.02 < .02 < .02 < .02 < .02 < .02 11 n.0/90-11/27,90 < .02 < .02 <.02 < .02 < .01 < .01 < .01 < .01 DECEMBER 11/27/90-12/05,90 < .02 < .02 < .02 < .02 <.02 <.02 < .02 < .02 12iU5/90-12/ll,90 <.03 < .02 <.02 < .02 < .03 < .04 (a) <.03 < .03 12/11/90-12/18,90 < .02 <.02 <.02 < .02 < .02 <.02 < .02 <.02 l 2/18/90-12/26,90 <.02 <.02 <.02 < .02 <.03 <.02 < .03 < .02 12/26/90-01/02,90 < .02 < .02 <.02 < .02 <.02 <.02 < .02 < .02 (a) The timer on the air sampler only indicated 96.6 hours. No reason could be detected for the short nm time.
e TABLE B-2 (Page 1 of 4) SURRY-1990 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATIONS Average COLLECTION DATE ss HIR BC ALL . CP DOW FE NN +/- 2 s.d . JANUARY 01/02/90-01/0'J/90 17+/- 2 18+/- 2 19+/- 2 17+/- 2 19+/- 2 19+/- 2 18 +/- 2 18+/- 2 18+/-2 Ol/09/90-01/16/90 15 +/- 2 18 +/- 2 17 +/- 2 15+/- 2 15 +/- 2 17+/- 2 16+/- 2 14+/- 2 16+/-3 01/16/90-01/23/90 18+/- 2 19+/- 2 20+/- 2 21 +/- 2 16+/- 2 19+/- 2 22+/- 2 19+/- 2 19+/-4 01/23/90-01/29/90 19+/- 2 17+/- 2 19+/- 2 18+/- 2 16+/- 2 16+/- 2 18+/- 2 18+/- 2 18+/-2 FEBRUARY 01/29/90-02/05/90 12+/- 1 11 +/- 1 14+/- 2 11 +/- 1 12+/- 1 10+/- 1 12+/- 1 14+/- 2 12+/-3 02/05/90-02/13/90 14 +/- 2 16 +/- 2 16+/- 2 15 +/- 2 15+/- 2 15 +/- 2 15 +/- 2 13+/- 2 15+/-2 ~ (]\ 02/l 3/9fJ-02/20/90 15 +/- 2 19+/- 2 15 +/- 2 15+/- 2 12+/- 1 11 +/- 1 15 +/- 2 15+/- 2 15+/-5 02n.0/90-02/27/90 14 +/- 2 13 +/- 2 8.1 +/- 1.3 13+/- 2 11 +/- 1 12+/- 2 11 +/- 1 12+/- 2 12+/-4 MARCH 02/27 /90-03/06/90 18 +/- 2 19+/- 2 19+/- 2 22+/- 2 20+/- 2 19+/- 2 18 +/- 2 15 +/- 2 .19+/-4 03/06/90-03/13/90 19+/- 2 18+/- 2 17+/- 2 20+/- 2 16+/- 2 19+/- 2 18+/- 2 18+/- 2 18 +/-3 03/13/90-03/20/90 14+/- 2 14+/- 2 14+/- 2 16+/- 2 13+/- 2 13+/- 2 15+/- 2 15+/- 2 14+/-2 03/20/90-03/28/90 18 +/- 2 17+/- 2 13 +/- 1 17+/- 2 13+/- 1 16+/- 2 16+/- 2 14+/- 2 16+/-4 03/28/90-04/03/90 6.2+/- 1.3 8.5 +/- 1.5 6.7 +/- 1.5 7.3 +/- 1.4 8.0+/- 1.5 7.3 +/- 1.4 9.5 +/- 1.6 6.6 +/- 1.4 8+/-2 Quarter Average 15 +/- 7 16 +/- 7 15 +/- 8 16 +/- 8 14 +/- 7 15 +/- 8 16 +/- 7 15 +/- 7 15 +/-1
+/- 2 s.d.
TABLE B-2 (Page 2 of4) SURRY-1990 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATIONS Average COLLECTION DA1E ss HIR BC ALL CP DOW FE NN +/- 2 s.d. ilBlL 04/03/90-04/10/90 15+/- 2 13+/- 2 15 +/- 2 14+/- 2 14+/- 2 13+/- 2 14+/- 2 14+/- 2 14+/- 2 04/10/90-04/17/90 15+/- 2 14+/- 2 15 +/- 2 16+/- 2 15 +/- 2 14+/- 2 15 +/- 2 12+/- 2 15 +/- 2 04/17/90-04/'lA/90 17+/- 2 16+/- 2 18 +/- 2 20+/- 2 16+/- 2 18 +/- 2 21 +/- 2 14+/- 2 18 +/- 5 04(1.4/90-05/01/!X) 19+/- 2 18+/- 2 19+/- 2 22+/- 2 18+/- 2 22+/- 2 20+/- 2 20+/- 2 20+/- 3 Mil 05/01/90-05/08/90 16+/- 2 . 15 +/- 2 17+/- 2 18+/- 2 15 +/- 2 16+/- 2 16+/- 2 19+/- 2 17 +/- 3 05/08/90-05/15/90 11 +/- 2 8.8 +/- 1.4 13 +/- 2 14+/- 2 13+/- 2 13 +/- 2 . 13+/- 2 11 +/- 2 12+/- 3 05/15/90-05/22/90 17+/- 2 14+/- 2 17+/- 2 19+/- 2 12+/- 2 17 +/- 2 16+/- 2 17+/- 2 16+/- 4 '-l '-l 05/22/90-05/29/90 7.1 +/- 1.2 7.4 +/- 1.3 8.4 +/- 1.3 10+/- 1 9.3 +/- 1.4 7.0 +/- 1.2 7.6+/- 1.3 9.5 +/- 1.4 8+/- 2 JJlN.E 05/29/90-06/05/90 11 +/- 2 11 +/- 2 10+/- 1 11 +/- 2 9.2 +/- 1.4 12+/- 2 12+/- 2 11 +/- 2 11 +/- 2 06/05/90-06/12/!X) 13+/- 2 12+/- 2 13+/- 2 13+/- 2 13+/- 2 11 +/- 2 13+/- 2 14+/- 2 13 +/- 2 06/12/90-06/19/90 10+/- 2 9.8 +/- 1.5 11 +/- 2 10+/- 2 11 +/- 2 10+/- 2 9.8 +/- 1.5 8.2+/- 1.5 10+/- 2 06/19/90-06/26/90 12+/- 2 11 +/- 1 11 +/- 1 13+/- 2 13+/- 2 13 +/- 2 11+/- 1 13+/- 2 12+/- 2 06(1.6/90-07/03/90 16+/- 2 17+/- 2 16+/- 2 16+/- 2 19+/- 2 15 +/- 2 15+/- 2 16+/- 2 16+/- 3 Quarter Average 14 +/- 7 13 +/- 6 14 +/- 7 15 +/- 8 14 +/- 6 14 +/- 8 14 +/- 7 14 +/- 7 14 +/- 1
+/- 2s.d.
e ,, TABLE B-2 (Page 3 of4) SURRY-1990 CONCEN1RATIONS OF GROSS BETA IN AIR PARTICULATES 10-3 pCi/m3 +/- 2 Sigma STATIONS Average COLLECTION DATE ss HIR BC ALL CP DOW FE NN +/- 2 s.d.
.IllLl'.:
07/03/90-07/10/90 13+/- 2 10+/- 2 17 +/- 2 17+/- 2 13+/- 2 14+/- 2 12+/- 2 15 +/- 2 14+/- 5 07/10/90-fYl/17/90 11 +/- 2 13+/- 2 14+/- 2 14+/- 2 13+/- 2 14+/- 2 14+/- 2 14+/- 2 13+/- 2 07/17/90-07/')A/90 14+/- 2 11 +/- 2 13+/- 2 .12+/- 2 13+/- 2 12+/- 2 15+/- 2 15 +/- 2 13 +/- 3 07/l4/90-(Y//31/90 7.9+/- 1.3 8.5 +/- 1.4 9.2 +/- 1.4 9.1 +/- 1.4 10+/- 1 8.7 +/- 1.4 9.7 +/- 1.5 10+/- 1 9+/- 2 AUGUST 07/31/90-08/(Y//90 11 +/- 2 12+/- 2 12+/- 2 14+/- 2 16+/- 2 14+/- 2 14+/- 2 14+/- 2 13+/- 3 08/07/90-08/14/90 14+/- 2 16+/- 2 16+/- 2 15+/- 2 12+/- 2 17 +/- 2 17+/- 2 17+/- 2 16+/- 4 -..J 08/14/90-08/21/90 19+/- 2 16 +/- 2 17+/- 2 15+/- 2 16+/- 2 15 +/- 2 16+/- 2. 16 +/- 2 16+/- 3 00 12+/- 2 2 2 9.8 +/- 1.5 11 +/- 2 11 +/- 2 13+/- 2 10+/- 2 11 +/- 2 08/21/90-08/28/90 10+/- 11 +/- 5E£IEMUEB 08/l8/90-fl)/05/90 23+/- 2 22+/- 2 21 +/- 2 20+/- 2 20+/- 2 20+/- 2 22+/- 2 20+/- 2 21 +/- 2 09/05/90-fl)/l l/90 21 +/- 2 19+/- 2 21 +/- 2 22+/- 2 19+/- 2 20+/- 2 21 +/- 2 20+/- 2 20+/- 2 09/11/90-fl)/18/90 16+/- 2 16+/- 2 18+/- 2 16+/- 2 16+/- 2 18 +/- 2 16+/- 2 17 +/- 2 17+/- 2 09/18/90-fl)/25/90 12+/- 2 14+/- 2 14+/- 2 15 +/- 2 14+/- 2 14+/- 2 15 +/- 2 14+/- 2 14+/- 2 fl)fl5/90- l0/crl./90 21+/- 2 19+/- 2 21 +/- 2 23+/- 2 19+/- 2 18 +/- 2 23+/- 2 23+/- 2 21 +/- 4 Quarterly Average 15 +/- 9 14 +/- 8 16 +/- 8 16 +/- 8 15 +/- 6 15 +/- 7 16 +/- 8 16 +/- 7 15 +/- 1
+/- 2 s.d.
TABLE B-2 (Page4 of 4) SURRY-1990 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATES lQ.3 pCi/m3 +/- 2 Sigma STATIONS Average COLLECTION DATE ss HIR .BC. ALL CP DOW FE NN +/- 2 s.d. OCTOBER 10/02/90-10/()()/90 15 +/- 2 18 +/- 2 25+/- 2 19+/- 2 16 +/- 2 15 +/- 2 19+/- 2 17+/- 2 18 +/- 7 10/09/90-10/16/90 13 +/- 2 14+/- 2 15 +/- 2 15 +/- 2 13+/- 2 15 +/- 2 13 +/- 2 14+/- 2 14+/- 2 10/16/90-10/23/90 13 +/- 2 17+/- 2 14+/- 2 14+/- 2 15 +/- 2 15 +/- 2 16+/- 2 16+/- 2 15 +/- 3 10/23/90-10/30/90 14+/- 2 16+/- 2 16+/- 2 16+/- 2 13+/- 2 11 +/- 1 16+/- 2 13 +/- 2 14+/- 4 NOYEMBER 10/30/90-11/06/90 33+/- 2 33+/- 2 35+/- 2 38+/- 3 30+/- 2 29+/- 2 39+/- 3 32+/- 2 34+/- 7 11/06/90-11 /12/90 14+/- 2 16+/-. 2 13 +/- 2 16+/- 2 15 +/- 2 13+/- 2 17+/- 2 15 +/- 2 15 +/- 3 ll/12/90-11/20/90 19+/- 2 22+/- 2 23+/- 2 23+/- 2 22+/- 2 20+/- 2 19+/- 2 23+/- 2 21 +/- 4 '-I 11 /20f}f)- ll/27/90 20*+/- 2 24+/- 2 22+/- 2 26+/- 2 24+/- 2 23+/- 2 24+/- 2 23+/- 2 23+/- 4 ID DECEMBER ll/27/90-12/05/90 17+/- 2 21 +/- 2 24+/- 2* 19+/- 2 18.+/- 2 17+/- 2 21 +/- 2 21 +/- 2 20+/- 5 12/05/90-12/11/90 23+/- 2 20+/- 2 23+/- 2 25+/- 2 21 +/- 2 32+/- 3 (a) 24+/- 2 23+/- 2 24+/- 7 12/11/90-12/18/90 19+/- 2 22+/- 2 22+/- 2 20+/- 2 21 +/- 2 17+/- 2 23+/- 2 20+/- 2 21 +/- 4 12/18/90-12/26/90 15+/- 2 17 +/- 2 15 +/- 2 18+/- 2 15 +/- 2 17+/- 2 15+/- 2 16+/- 2 16+/- 2 12/26/90-01/02/C:)1 15 +/- 2 15 +/- 2 15 +/- 2 17+/- 2 13+/-2 15 +/- 2 17+/- 2 14+/- 2 15 +/- 3 Qtr Average 18 +/- 11 20 +/- 10 20 +/- 12 20 +/- 13 18 +/- 10 18 +/- 12 20 +/- 13 19 +/- 11 19 +/- 2
+/- 2 s.d.
Annual Average 15 +/- 9 16 +/- 9 16 +/- 10 17 +/- 10 15 +/- 8 16 +/- 9 17 +/- 10 16 +/- 9 16 +/- 2
+/- 2 s.d.
(a) Timer malfunction.
e e TABLE B-3 (Page 1 of2) SURRY-1990 CONCENTRATIONS OF GAMMA EMITIERS* IN QUARTERLY AIR PARTICULA1ES 10-3 pCiJm3 +/- 2 Sigma FIRST QUARTER .*SECOND QUARTER 1HIRD QUARTER FOUR1H QUARTER AVERAGE STATION NUCLIDE 01,1)2-04/03 04/03-07/03 07/03-10/02 10/02-01/02 +/- 2 s.d. STA-SS Be-7 98.4 +/- 9.8 46.6 +/-4.7 88.9+/- 8.9 91.8 +/- 9.2 81.4 +/- 47.1 K-40 <4 <4 3.31 +/- 1.82 <5 3.31 +/- 1.82 Co-60 < 0.2 < 0.1 < 0.3 < 0.3 Cs-134 < 0.2 < 0.2 < 0.2 < 0.3 Cs-137 < 0.2 < 0.2 < 0.2 <0.3 Th-228 < 0.4 < 0.3 < 0.4 < 0.5 STA-HIR Be-7 109+/- 11 56.3 +/- 5.6 92.8 +/- 9.3 89.9+/- 9.0 87.0 +/- 44.2 K-40 <6 < 10 <3 <6 Co-60 < 0.3 <0.4 < 0.2 < 0.4 Cs-134 . < 0.3 < 0.4 < 0.2 < 0.3 Cs-137 < 0.3 < 0.3 < 0.2 < 0.3 Th-228 < 0.6 < 0.6 < 0.3 < 0.5 00 0 STA-BC Be-7 94.8 +/- 9.5 55.8 +/- 5.6 79.9 +/- 8.0 91.0 +/- 9.1 80.4 +/- 35.1 K-40 < 10 <4 <6 <7 Co-60 < 0.3 < 0.2 < 0.3 < 0.3 Cs-134 < 0.3 < 0.2 < 0.3 < 0.3 Cs-137 < 0.3 < 0.2 < 0.2 < 0.3 Th-228 < 0.4 < 0.3 < 0.5 <().4 STA-ALL Be-7 130+/- 13 59.2 +/- 5.9 84.6 +/- 8.5 101 +/- 10 93.7 +/- 59.4 K-40 <5 3.31 +/- 1.32 <6 <4 3.31 +/- 1.32 Co-60 < 0.3 < 0.2 < 0.3 < 0.2 Cs-134 < 0.3 < 0.2 < 0.3 < 0.2 Cs-137 < 0.3 < 0.2 < 0.3 < 0.2 Th-228 < 0.5 < 0.3 < 0.4 <0.3
- All other ganuna emitters were < LLD.
TABLE B-3 (Page2of2) SURRY -1990 CONCEN1RATIONS OF GAMMA EMITIERS* IN QUARTERLY AIR PARTICULATFS 10.3 pCi/m3 +/- 2 Sigma FIRST QUARTER SECOND QUARTER TIIlRD QUARTER FOUR'IH QUARTER AVERAGE STATION NUCLIDE 01/02-04/03 04/03-07/03 07/03-10/02 10/()2--01/02 +/- 2 s.d. STA-CP Be-7 92.6+/- 9.3 48.1 +/- 4.8 87.8 +/- 8.8 102 +/- 10 82.6 +/- 47.5 K-40 <7 <5 <4 < 10 Co-60 < 0.4 < 0.3 < 0.2 <0.4 Cs-134 < 0.4 < 0.2 < 0.2 < 0.4 Cs-137 < 0.3 < 0.2 <0.2 < 0.3 Th-228 < 0.5 < 0.5 < 0.3 < 0.6 STA-DOW Be-7 105+/- 10 57.4 +/- 5.7 99.7 +/- 10.0 92.8 +/- 9.3 88.7 +/- 42.9 K-40 <7 <5 5.12 +/- 2.57 <4 5.12 +/- 2.57 Co-60 < 0.3 < 0.3 <0.4 < 0.4 Cs-134 < 0.3 < 0.3 <0.3 <0.2 Cs-137 < 0.3 < 0.3 < 0.3 < 0.2 Th-228 < 0.5 < 0.5 < 0.6 < 0.3 00 ,_. STA-FE Be-7 121 +/- 12 57.5 +/- 5.7 99.1 +/- 9.9 94.5 +/- 9.4 93.0 +/- 52.7 K-40 <5 < 10 <5 <3 Co-60 < 0.3 < 0.4 < 0.3 <0.3 Cs-134 < 0.2 < 0.4 < 0.2 < 0.2 Cs-137 < 0.2 < 0.3 < 0.2 < 0.2 Th-228 < 0.4 < 0.5 < 0.4 < 0.3 STA-NN Be-7 110+/- 11 58.0 +/- 5.8 94.8 +/- 9.5 122+/- 12 96.2 +/- 55.6 K-40 <5 < 10 <4 <5 Co-60 < 0.3 < 0.3 < 0.2 < 0.2 Cs-134 < 0.3 < 0.3 < 0.2 < 0.2 Cs-137 < 0.2 < 0.3 < 0.2 < 0.2 Th-228 <0.4 <0.4 <0.4 < 0.4
- All other gamma emitters were < LLD.
~
- TABLE B-4 (Page. I of 3) e SURRY-1990 CONCENTRATIONS OF GAMMA EMITIERS* AND TRITIUM IN RIVER WATER pCi/1 +/- 2 Sigma STATION DATE Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3
,JANUARY CHIC 01/17/90 <30 <60 < 0.3 <4 < 10 <6 <7 HIP 01/16/90 <50 <*90 <0.4 <6 <20 <8 < 10 NN 01/16/90 <40 <90 < 0.4 <5 <20 <6 <8 SD 01/17/90 <30 <50 <0.5 <4 < 10 <5 <7 SI 01/16/90 * <30 <60 < 0.3 <4 < 10 <6 <7 SW 01/17/90 <30 <50 < 0.4 <4 < 10 <5 <6 FEBRUARY SD 02/20/90 <50 <90 < 0.4 <5 <20 <8 < 10 SW 02/20/90 <40 <90 < 0.3 <5 <20 <7 <8 00 N
MARCH CHIC 03/13/90 <30 <50 < 0.1 <3 < 10 <6 <6 < 100 HIP 03/12/90 <30 <50 < 0.2 <3 < 10 <6 <6 290+/- 110 NN 03/12/90 <50 <200 <0.2 <6 <20 < 10 < 10 <100 SD 03/12/90 <50 72.1 +/- 37.3 < 0.2 <6 <20 <9 < 10 330+/-80 SI 03/12/90 <30 <70 < 0.3 <3 < 10 <5 <7 < 100 SW 03/13/90 <40 <90 < 0.2 <5 <20 <7 <8 <200 illUL SD 04/17/90 <30 <60 < 0.3 <3 < 10 <5 <7 SW 04/17/90 <30 <60 < 0.2 <3 < 10 <5 <6
- All other gamma emitters were <LLD.
e e e TABLE B-4 (Page2 of 3) SURRY-1990 CONCENTRATIONS OF GAMMA EMITTERS* AND 1RITIUM IN RIVER WATER pCi/1 +/- 2 Sigma STATION DATE Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 MAI: CHIC 05/17/90 <30 <50 <0.2 <3 <20 <7 <6 < 100 HIP 05/17/90 <30 <40 < 0.2 <3 < 10 <6 <5 950+/- 90 (a) NN 05/17/90 <30 62.3 +/- 26.3 <0.2 <3 <20 <8 <5 340+/-90 SD 05/17/90 <50 <90 < 0.3 <6 <30 < 10 < 10 270+/-90 SI 05/17/90 <50 < 100 < 0.2 <5 <20 < 10 <8 300+/-90 SW 05/17/90 <40 <60 < 0.3 <4 <20 <9 <7 < 100 J.!lliE SD 06/19/90 <30 <50 < 0.1 <3 < 10 <5 <5 SW 06/19/90 <40 < 100 < 0.2 <4 <20 <6 <8 00 v-1 J..llLY CHIC 07/26/90 <30 <50 <0.2 <3 <20 <8 <6 HIP 07/26/90 <30 43.6 +/- 25.6 < 0.2 <3 <20 <7 <6 NN 07/26/90 <40 97.5 +/- 31.6 < 0.3 <4 <20 <8 <7 SD 07/26/90 <30 83.6 +/- 27.4 < 0.2 <3 <20 <8 <5 SI 07/26/90 <20 <50 < 0.2 <3 < 10 <7 <5 SW 07/26/90 <30 <50 < 0.2 <3 <20 <8 <6 A!..!~1!SI SD 08/21/90 <30 91.l +/- 43.6 < 0.2 <4 <20 <7 <8 SW 08/21/90 <40 < 100 < 0.2 <5 <20 <9 <7 (a) Result confirmed by a reanalysis.
- All other gamma emitters were <LLD.
e e e TABLE B-4 (Page 3 of 3) SURRY-1990 CONCENTRATIONS OF GAMMA EMITIERS* AND TRITIUM IN RIVER WATER pCi/1 +/- 2 Sigma STATION DATE Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3
~
SEl!IEMBEB CHIC 09/25/90 <40 <70 < 0.2 <4 <30 <8 <8 < 100 HIP 09/].4/90 <50 < 100 <0.2 <5 <30 < 10 <8 < 100 NN 09(}.4/90 <50 <200 < 0.2 <5 <40 < 10 <8 < 100 SD 09/l4/90 <40 141 +/- 33 < 0.2 <4 <30 < 10 <8 210+/-90 SI 09(}.4/90 <50 189+/- 38 < 0.2 <5 <40 < 10 <9 < 100 SW 09/25/90 <50 <90 < 0.1 <4 <30 < 10 <8 160+/- 80 Q~IQBEB SD 10/16/90 <30 92.4 +/- 31.9 < 0.2 <3 < 10 <6 <6 SW 10/16/90 <30 <60 < 0.2 <3 <20 <7 <7 00 .i:,. ISQYEMDEB CHIC 11/14/90 <30 <60 < 0.2 <5 <20 <9 <7 < 100 HIP 11/13/90 <30 <60 < 0.3 <3 <20 <9 <6 260+/- 120 NN 11/14/90 <40 137+/-40 < 0.2 <4 <20 <9 <7 <200 SD 11/14/90 <50 < 100 < 0.2 <5 <30 < 10 < 10 270+/- 110 SI 11/14/90 <40 < 100 < 0.2 <4 <30 <9 <8 310+/-70 SW 11/14/90 <40 <90 <0.2 <5 <20 <9 <8 140+/-80 I!E~EMBEB SD 12/18/90 <40 99.2 +/- 36.1 < 0.2 <5 < 10 <6 < 10 SW 12/18/90 <30 <80 <0.2 <4 < 10 <5 <6
- All other gamma emitters were <LLD.
e e TABLE B-5 SURRY-1990 CONCENTRATIONS OF GAMMA EMITrERS* AND TRITIUM IN RIVER WATER pCi/1 +/- 2 Sigma STATE SPLIT MONTH COLL.DATES Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 SCOTLAND WU, <SW) January 01/15/90 <50 <50 <2* <4 <80 (a) < 30 (a) <7 February 02/15/90 <60 < 100 <1 <5 <80 (a) < 30 (a) <8 March 03/15/90 <60 <90 <1 <5 <90 (a) < 30 (a) <8 600+/-90 April 04/30/90 <50 < 100 <0.4 <5 <40 < 15 <7 May 05/31/90 <50 <90 < 0.5 <5 <30 < 10 <8 June 06/30/90 <40 < 100 < 0.5 <4 <40 < 10 <7 350+/-90 July 07/31/90 <60 < 100 < 0.5 <5 <60 (a) < 30 (a) <8 August 08/31/90 <30 <50 < 0.5 <3 <20 < 10 <6 September 09/30/90 <30 61.6 +/- 25.0 <0.4 <3 <30 < 10 <5 < 100 October 10/31/90 <40 <60 < 0.9 <3 <50 (a) <20 <7 November 11/30/90 <40 <80 < 0.4 <4 <30 < 10 <7 December 12/31/90 <50 < 100 < 0.3 <5 <30 < 10 <8 <200 Average 61.6 +/- 25.0 475 +/- 354 00 u, +/- 2 s.d. SllBBl.: DJS, <SD) January 01/15/90 <50 61.7 +/- 34.7 <2 <4 <80 (a) <40 (a) <8 February 02/15/90 <50 <60 <1 <4 <60 < 30 (a) <9 March. 03/15/90 <70 <90 <1 <6 < 100 (a) < 50 (a) < 10 1100+/- 100
- April 04/30/90 <40 <80 < 0.5 <4 <40 < 10 <7 May 05/31/90 <40 <60 <0.5 <4 <30 < 10 <9 June 06/30/90 <40 < 100 < 0.5 <3 <30 < 10. <5 1500+/- 100 July 07/31/90 <50 <200 <0.5 <5 <50 <20 <9 August 08/31/90 <30 79.4 +/- 24.3 < 0.5 <3 <20 < 10 <6 September 09/30/90 <40 73.9+/- 33.6 < 0.3 <4 <40 < 10 <6 470+/- 100 October 10/31/90 <50 <70 <1 <4 < 60 (a) <20 <7 November 11/30/90 (b)
December 12/31/90 <30 <60 < 0.3 <3 <20 <8 <6 270+/- 140 Average 71.7 +/- 18.1 835 +/- 1134
+/- 2 s.d.
- All other gamma emitters were <11..D.
(a) 11..D not met because oflate receipt of sample from the State of Virginia. (b) Sample not received at analytical laboratory.
e e e TABLE B-6 SURRY-1990 CONCENTRATIONS OF GAMMA EMITIERS* AND TRITIUM IN WELL WATER pCi/1 +/- 2 Sigma DATE STATION Be-7 K-40 1-131 Cs-137 Ba-140 La-140 Th-228 H-3 FIRST QUARTER 03/20/90 BC <30 <50 < 0.2 <3 < 10 <5 <6 <200 03/20/90 HIR <40 < 100 < 0.2 <5 <20 <6 <7 <200 03/20/90 lMTN <50 <200 < 0.3 <6 <20 <9 < 10 < 100 03/20/90 ss <50 <90 < 0.2 <5 <20 <7 < 10 < 100 SE~QIS:ll QUABIEB 06/19/90 BC <50 <80 < 0.2 <5 <20 <9 < 10 < 100 06/19/90 HIR <30 <50 < 0.2 <3 < 10 <6 <6. < 100
- 06/19/90 JMTN <40 <80 < 0.1 <4 <20 <7 <7 < 100 00 06/19/90 ss <30 <60 < 0.1 <3 <20 <8 <7 < 100
(]\ IUIBll QL!~BIEB 09/18/90 BC <50 <80 < 0.2 <5 <20 <9 < 10 < 100 09/18/90 HIR <30 <60 < 0.2 <4 < 10 <7 <7 < 100
. 09/18/90 lMTN <30 <50 < 0.2 <3 < 10 <6 <6 < 100 09/18/90 ss <:30 <50 < 0.2 <4 < 10 <6 <6 < 100 FQURIH Ql!6BIEB 12/18/90 BC <30 <50 < 0.2 <3 < 10 <4 <6 <200 12/18/90 HIR <30 <60 < 0.2 <4 < 10 <4 <8 <200 12/18/90 JMfN <20 <40 <0.2 <3 <9 <4 <5 <100 12/18/90 ss <20 <40 < 0.2 <3 <9 <4 <5 < 100
- All other gamma emitters were <LLD.
e TABLE 8-7 (Page 1 of2) SURRY-1990 CONCENTRATIONS OF GAMMA EMITIERS* IN SILT pCi/kg (dry)+/- 2 Sigma STATION CHIC HIP NN POS SD SI COLLECTION DATE 03/12/90 03/12/90 03/12/90 03/12/90 03/12/90 03/12/90 Be-7 <800 <400 <400 715 +/- 480 <400 <2000 K-40 16100+/- 1600 11800+/- 1200 14800+/- 1500 <2000 18100 +/- 1800
- 20800 +/- 2100 Mn-54 <70 <40 <40 <50 <40 <80 Co-58 <80 <40 <40 <60 <40 <90 Co-60 < 100 387+/- 40 147 +/- 43 389+/- 53 3610+/- 360 702+/- 92 00 Cs-134 < 80 157 +/- 34 <40 < 60 231 +/- 39 156+/- 77
'-1 Cs-137 562+/- 73 859 +/- 86 421 +/- 42 929+/- 93 1730+/- 170 1570+/- 160 Ra-226 3450+/- 890 1900+/- 520 1610+/- 590 2320+/- 770 2530+/- 490 2770+/- 1150 Th-228 1540+/- 150 1300+/- 130 1200+/- 120 1370+/- 140 1450+/- 140 1680+/- 170
- All other ganuna emitters were <LLD.
TABLE B-7 (Page2of2) SURRY-1990 CONCENTRATIONS OF GAMMA EMITIERS* IN SILT pCi/kg (dry)+/- 2 Sigma STATION CHIC HIP NN POS SD SI Average COLLECTION DATE 09/25/90 09/24/90* 09/24/90 09/24/90 09/24/90 09/24/90 +/- 2 Sigma Be-7 < 1000 <500 <400 <500 <300 1270+/-610 993 +/- 785 K-40 17800+/- 1800 12200 +/- 1200 15900+/- 1600 15800+/- 1600 14300+/- 1400 17400+/- 1700 15909+/-5255 Mn-54 < 100 <40 <30 <40 <30 <70 Co-58 < 100 <50 <40 <50 <30 <70 Co-60 249+/- 93 280+/- 42 66.9+/- 31.4 <50 212+/- 27 402+/- 74 644+/- 2113 00 00 Cs-134 < 100 <50 <40 <50 <30 <70 181 +/- 86 Cs-137 667+/- 143 , 480+/- 48 293+/- 29 173+/- 38 297+/- 30 954+/- 95 745 +/- 989 Ra-226 3160+/- 1330 2260+/- 680 1540+/- 500 1970+/- 570 2090+/- 390 2650+/- 980 2354+/- 1174 Th-228 1560+/- 160 1240+/- 120 860+/- 86 1180+/- 120 1130+/- 110 1340+/- 130 1321 +/- 445
- All other gamma emitters were <LLD.
e TABLE B-8 SURRY -1990 CONCENTRATIONS OF GAMMA EMITIERS* IN SHORELINE SEDIMENT pCi/kg (dry)+/- 2 Sigma STATION HIR BURWELL'S HIR BURWELL'S AVERAGE COLLECTION DATE 02/27/90 02/27/90 08/28/90 08/28/90 +/- 2 s.d. Be-7 <200 < 100 < 100 <200 K-40 6210+/- 620 2910+/- 290 6930+/- 690 3350+/- 340 4850+/- 4031 Co-60 <20 < 10 < 10 <20 Cs-134 <20 < 10 < 10 <20 Cs-137 <20 <20 <20 <20 Ra-226 450+/- 236 434 +/- 201 <200 * <300 442+/- 23 Th-228 137 +/- 17 <30 105 +/- 19 <30 121 +/- 45 00 \0
- All other gamma emitters were <LLD.
TABLE B-9 (Page 1 of3) SURRY-1990 CONCENTRATIONS OF GAMMA EMIITERS** AND SlRONTIUM-89 AND-90 IN MILK pCi/liter +/- 2 Sigma MONTH NUCLIDE LEE HALL EPPS CP WMS JDKS JANUARY Sr-89 Sr-90 K-40 1370+/- 140 1270+/- 130 1290+/- 130 1280+/- 130 1200+/- 120 Cs-137 <4 <6 <4 <5 <4 1-131 < 0.2 < 0.3 < 0.4 < 0.2 <0.4 FEBRUARY Sr-89 Sr-90 K-40 1480+/- 150 1250+/- 130 1420+/- 140 1210+/- 120 1270+/- 130 Cs-137 <5 <4 <4 <4 <4 1-131 < 0.2 < 0.1 < 0.1 < 0.2 < 0.2 ID 0 MARCH Sr-89 <3 <2 <3 Sr-90 1.3 +/- 0.4 1.1 +/- 0.3 3.3 +/- 0.4 K-40 1380+/- 140 1170+/- 120 1380 +/- 140 1150+/- 120 1230+/- 120 Cs-137 <5 <4 <4 <6 <3 1-131 < 0.1 < 0.1 < 0.3 < 0.2 < 0.1 APRIL Sr-89 Sr-90 K-40 1160+/- 120 1200+/- 120 1440 +/- 140 1280+/- 130 1400+/- 140 Cs-137 <4 <4 <4 <4 <7 1-131 < 0.2 < 0.2 < 0.2 < 0.2 <0.2 (*) Strontium-89 and 90 sample analysis done on a quarterly composite of state split samples (Epps, Lee Hall) and Colonial Parkway(CP) sample at the request of the State of Virginia. (**) All other gamma emitters were <LLD.
TABLE B-9 (Page 2 of3) SURRY-1990 CONCENTRATIONS OF GAMMA EMITIERS** AND S1RONTIUM-89 AND-90 IN MILK pCi/liter +/- 2 Sigma MONTH NUCLIDE LEE HALL EPPS CP WMS JDKS MAY Sr-89 Sr-90 K-40 1290+/- 130 1260+/- 130 1320+/- 130 1200+/- 120 1190+/- 120 Cs-137 <4 <4 <4 <4 <5 1-131 < 0.2 < 0.3 < 0.2 < 0.2 <0.3 JUNE Sr-89 <3 <5 <l Sr-90 1.5 +/- 0.4 0.81 +/- 0.24 3.2 +/- 0.2 K-40 1360+/- 140 1330+/- 130 1420+/- 140 1300+/- 130 1220+/- 120 Cs-137 <5 <4 <4 <4 <4 1-131 < 0.2 < 0.2 < 0.1 < 0.1 < 0.2 <.O JULY Sr-89 Sr-90 K-40 1440+/- 140 1160+/- 120 1360 +/- 140 1240+/- 120 1470+/- 150 Cs-137 <3 <4 <4 <4 <6 1-131 < 0.3 < 0.4 < 0.2 <0.3 < 0.4 AUGUST Sr-89 Sr-90 K-40 1370+/- 140 1280+/- 130 1220+/- 120 1350+/- 130 1230 +/- 120 Cs-137 <4 <4 <4. <4 <4 1-131 < 0.3 < 0.4 < 0.2 < 0.2 < 0.2 (*) Strontiwn-89 and 90 sample analysis done on a quarterly composite of state split samples (Epps, Lee Hall) and Colonial Parkway(CP) sample at the request of the State of Virginia. (**) All other garruna emitters were <LLD.
TABLE B-9 (Page 3 of3) SURRY - 19'JO CONCENTRATIONS OF GAMMA EMITl'ERS** AND STRONTIUM-89 AND-90 IN*MILK pCi/liter +/- 2 Sigma MONTH NUCLIDE LEE HALL EPPS CP. WMS JDKS SEPTEMBER Sr-89 <4 <4 <5 Sr-90 0.76 +/- 0.55 0.70 +/- 0.24 3.7 +/- 0.4 K-40 1330+/- 130 1340+/- 130 1270+/- 130 1190+/- 120 1320+/- 130 Cs-137 <4 <4 <4 <4 <4 1-131 < 0.2 <0.2 < 0.2 < 0.2 < 0.3 OCTOBER Sr-89 Sr-90 K-40 1330+/- 130 1280+/- 130. 1400 +/- 140 1350+/- 140 1240+/- 120 Cs-137 <5 <4 <4 <5 <6 1-131 <0.2 < 0.2 < 0.2 < 0.2 < ~-2 w N NOVEMBER Sr-89 Sr-90 K-40 1250+/- 120 1320+/- 130 1280+/- 130 1270+/- 130 1370+/- 140 Cs-137 <4 <4 <4 <4 <4 1-131 < 0.1 < 0.1 < 0.2 < 0.2 <0.2 DECEMBER Sr-89 <4 <5 <4 (a) Sr-90 0.50 +/- 0.14 0.61 +/- 0.20 1.9 +/- 0.2
- K-40 .1130+/- 110 1280+/- 130 1260+/- 130 . 1360+/- 140 1190+/- 120 Cs-137 <5 < 10 <4 <4 <5 1-131 <0.4 < 0.4 < 0.2 <0.2 <0.2
(*) Strontiwn-89 and 90 sample analysis done on a quarterly composite of state split samples (Epps, Lee Hall) and Colonial Parkway(CP) samples at the request of the S~ of Virginia. (**) All other gamma emitters were <LLD. (a) Sample not received in original shipment Replacement received 12/l.0/90.
e e e TABLE B-10 SURRY -1990 CONCENTRATIONS OF GAMMA EMTITERS* IN CLAMS pCi/kg (wet) +/- 2 Sigma STATION DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228
~- 01/17/90 Clams < 100 359+/- 87 < 10 <9 <9 <200 <20 03/13/90 Clams < 100 1190+/- 120 < 10 < 10 < 10 <300 <20 05/17/90 Clams <300 595 +/- 197 <30 <20 <30 <500 <50 01{16/90 Clams <200 653+/- 129 <20 <20 <20 <300 <30 09{15/90 Clams < 100 372+/- 91 < 10 <9 < 10 <200 <20 11/14/90 Clams <200 192+/- 101 <20 < 10 < 10 <300 <30
.IM.IN 01/16/90 Clams < 100 321 +/- 100 < 10 < 10 <9 <200 <20 03/12/90 Clams < 100 425 +/- 98 < 10 < 10 < 10 <200 <20 05/17/90 Clams < 100 454+/- 90 < 10 < 10 < 10 <200 <20 07{16/90 Clams < 100 382+/- 94 < 10 < 10 < 10 <200 <20 09{15/90 Clams < 100 397+/- 88 < 10 < 10 <9 <200 <20 11/13/90 Clams <200 445+/- 111 <20 < 10 <20 <300 <30 SJ! 01/17/90** Clams <300 372+/- 180 <30 <30 <20 <400 <40 03/01/90** Clams < 100 431 +/- 82 < 10 <9 <8 <200 <20 05/03/90** Clams <200 529+/- 103 < 10 < 10 < 10 <300 <20
\D c.,.., 06{18/90** Clams <200 573+/- 150 <20 < 10 < 10 <200 <20 09/18/90** Clams <200 484 +/- 124 <20 <20 <20 <300 <30 11/02/90** Clams <300 <500 <20 <20 <20 <300 <30 lilt 01/16/90 Clams <200 435 +/- 117 <20 < 10 < 10 <300 <30 03/12/90 Clams <200 <600 <20 <20 <20 <300 <30 05/17/90 Clams <200 569+/- 125 <20 <20 <20 <300 <30 07{16/90 Clams <200 335 +/- 110 <20 <20 <20 <300 <30 09{14/90 Clams <200 <500 <20 <20 <20 <300 <30 11/13/90 Clams <200 573+/- 145 <20 <20 <20 <300 <30 LC 01/16/90 Clams <200 566+/- 112 <20 < 10 < 10 <300 <20 03/12/90 Clams <200 561 +/- 106 <20 <20 <20 <300 <30 05/17/90 Clams < 100 442+/- 120 <10 < 10 < 10 <300 <30 07{16/90 Clams < 100 502+/- 148 < 10 < 10 < 10 <300 <30 09{14/90 Clams < 100 585 +/- 97 < 10 < IO < 10 <200 <20 11/13/90 Clams <200 565+/- 158 <20 <20 <20 <300 <30 Average 493 +/- 350
+/- 2 s.d.
- All other ganuna emitters were <LLD.
** State Split
e* e e TABLE B-11 SURRY-1990 CONCENTRATIONS OF GAMMA EMITI'ERS* IN OYSTERS
- pCi/kg (wet) +/- 2 Sigma STATION DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228
&La 01/16/90 Oysters <200 524+/- 103 <20 < 10 < 10 <200 <30 03/12/90 Oysters < 100 621 +/- 133 < 10 <20 < 10 <300 <30 05/17/90 Oysters < 100 520+/- 104 < 10 < 10 <10 <200 <20 07(1.6/90 Oysters < 100 900+/-149 < 10 < 10 < 10 <300 <30 09(1.4/90 Oysters < 100 851 +/- 125 < 10 < 10 < 10 <200 <20 11/13/90 Oysters <200 564+/- 116 <20 < 10 <20 <300 <30 12.lll 01/16/90 Oysters <200 405 +/- 117 <20 < 10 < 10 <300 <20 03/12/90 Oysters < 100 508+/- 132 < 10 .. < 10 < 10 <300 <20 05/17/90 Oysters <200 430+/- 142 <20 < 10 < 10 <300 <30 07(1.6/90 Oysters <200 557+/- 116 <20 < 10 <20 <300 <30 09(1.4/90 Oysters <300 <700 <30 <20 <20 <400 <40 11/13/90 Oysters <200 595 +/- 167 <20 <20 <20 <400 <40 I.D lfil 01/16/90 Oysters <200 836+/- 116 <20 < 10 < 10 <200 <20
+:,, 03/12/90 Oysters <200 <400 <20 <20 <20 <400 <50 05/02/90** Oysters < 100 409+/- 122 < 10 < 10 < 10 <300 <30 05/17/90 Oysters <200 370+/- 101 <20 < 10 < 10 < 300 <30 06(1.9,90** Oysters <200 740+/- 110 < 10 < 10 < 10 <200 <20 07(1.6/90 Oysters <200 558 +/- 131 <20 <20 <20 <400 . <30 09/13/90** Oysters < 100 849+/- 117 < 10 <9 <10 <200 <20 09(1.4/90 Oysters < 100 777+/- 109 < 10 <9 <10 <200 <20 11/01/90** Oysters <300 <500 <20 <20 <8 <300 <30 11/13/90 Oysters <200 636+/- 128 < 10 <10 < 10 < 300 <20 llfil 01/16,90** Oysters <100 436+/- 92 < 10 <10 <9 <200 <20 02(1.7,90** Oysters <100 418*+/- 113 < 10 < 10 < 10 <200 <20 Average 595 +/- 336
+/-.2 s.d.
- All other gamma emitters were <LLD.
** State Split
TABLE B-12 SURRY" 1990 CONCENTRATIONS OF GAMMA EMITIERS* IN CRABS pCi/kg (wet)+/- 2 Sigma STATION DATE TYPE Be-7 K-40 Co-58 Co-60 Cs-137 Ra-226 Th-228 06/07/90 Crabs <200 2430+/- 240 <20 <20 <20 <300 <30
- All other ganuna emitters were <LLD.
TABLE B-13 SURRY-1990 CONCEN'IRATIONS OF GAMMA EMITI'ERS* IN FISH pCiJkg (wet) +/- 2 Sigma COLL.DATE STATION SAMPLE TYPE K-40 Co-58 Cs-134 Cs-137 04,{)3/90 SD CATFISH 942+/- 111 <8 <8 < IO 04/04/90 SD WHITEPERCH 1140+/- 160 < IO < 10 < IO 10,{15/90 SD WHITEPERCH 2010+/- 240 <30 <30 18.7 +/- 1.04 10,{15/90 SD CATFISH 1950+/- 300 <20 <20 <20 Average 1511 +/- 1097 18.7 +/- 1.04
+/- 2 s.d.
- All other gamma emitters were below <LLD.
TABLE B-14 SURRY-1990 CONCEN1RATIONS OF GAMMA EMITIERS* IN VF.GETATION pCi/lcg (wet) +/- 2 Sigma SAMPLE COLLECTION STATION TYPE DATE Be-7 K-40 1-131 Cs-134 Cs-137 Poole's Garden** Kale 06/05/90 <200 5680+/- 570 <50 <20 <20 Ryan's Garden** Kale 06/05/90 <200 4900+/- 490 <50 <20 <20 Turner's Garden** Cabbage ffl/15/90 220+/- 82 4300+/- 430 <20 < 10 < 10 Brock"s Garden Soybeans 11/27/90 <60 15200+/- 1500 <30 <7 10.2 +/- 4.9 (a) Slade's Garden** Soybeans 12/06/90 <60 13600+/- 1400 < 10 <8 12.4 +/- 6.4 (a) Average +/- 2 s.d. 220 +/- 82 8736 +/- 10449 11.3 +/- 3.1 <.D -...i
- All other gamma emitten, were below <LLD
** State Split (a) Confirmed by reanalysis.
e e TABLE B-15 (Page 1 of2) SURRY-1990 DIRECT RADIATION MEASUREMENTS - QUARTERLY 1LD RESULTS mR/month +/- 2 Sigma - Set 1 - 098 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s.d. 02 7.1 +/- 0.6 7.7 +/- 0.8 6.6 +/- 0.3 8.0+/-0.6 7.4 +/- 1.2 03 7.0 +/- 0.4 8.0+/- 0.5 7.3 +/- 0.9 8.5 +/- 0.7 7.7 +/- 1.4 04 6.0+/-0.4 7.3 +/- 1.0 5.8 +/- 0.4 6.9 +/- 1.2 6.5 +/- 1.4 05 5.7 +/-0.2 (a) 4.9 +/- 0.2 6.6 +/- 0.2 5.1 +/- 1.7 06 6.1 +/- 0.3 6.9+/- 0.5 5.9+/-0.4 7.6+/- 0.5 6.6 +/- 1.6 07 5.1 +/-0.5 6.7 +/- 0.4 5.8 +/- 0.3 7.1 +/- 0.6 6.3 +/- 1.4 08 5.8 +/- 0.4 6.7 +/- 0.7 5.1 +/-0.4 7.0+/-0.6 6.3 +/- 1.3 09 5.4 +/- 1.0 6.8 +/- 1.1 5.8 +/- 0.3 6.9+/- 0.3 6.2 +/- 1.5 10 5.3 +/- 0,2 6.5 +/- 0.6 5.5 +/- 0.4 6.8 +/- 0.6 6.0 +/- 1.5 ID 11 5.8 +/- 0.3 6.5 +/- 0.8 5.7 +/- 0.7 6.8 +/-0.5 6.2 +/- 1.1 00 12 5.7 +/- 0.2 (a) 5.8 +/- Q.5 7.0 +/- 0.4 6.2 +/- 1.4 13 5.9 +/- 0.3 6.2 +/- 0.4 5.9 +/- 0.3 7.0 +/- 0.4 6.3 +/- 1.0 14 6.5 +/-0.4 7.0+/- 0.5 6.2 +/- 0.5 7.3 +/-0.6 6.8 +/- 1.0 15 . 5.3 +/- 0.3 6.1 +/- 0.6 5.4 +/- 0.3 6.2 +/- 0.3 5.8 +/- 0.9 16 5.7 +/- 0.4 5.6+/- 0.7 5.7 +/-0.3 6.5 +/- 0.7 5.9+/- 0.8 17 5.2 +/-0.5 5.1 +/- 0.4 4.6+/- 0.4 (b) 1.1 +/- 1.9 (c) 4.2+/-4.2 18 4.3+/-0.2 5.4+/- 0.7 . 4.3 +/- 0.3 5.3 +/- 0.3 4.8 +/- 1.2 19 4.9 +/-0.5 5.8 +/- 0.5 5.0 +/-0.2 6.1 +/- 0.2 5.5 +/- 1.2 20 4.8 +/-0.4 5.6 +/- 0.6 4.6+/- 0.3 5.8 +/- 0.3 5.2 +/- 1.2 21 5.0+/-0.2 5.7 +/- 0.5 5.2 +/- 0.4 6.4+/- 0.4 5.6 +/- 1.2 22 4.7 +/- 0.1 5.5 +/- 0.8 4.6+/-0.3 5.9+/- 0.2 5.2 +/- 1.3 (a) 1LD missing (b) Third quarter 1LD inadvertantly rehung when placing fourth quarter 1LD in field. Thinl quarter TLD received 11/02/90. (c) 11..D was apparently irridiated in transit to the vendor laboratory.
- e TABLE B-15 (Page2 of2)
SURRY-1990 DIRECT RADIATION MEASUREMENTS -QUAR1ERLY Till RFSULTS mR/month +/- 2 Sigma - Set 1 - 098 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s.d. 23 6.0+/- 0.3 6.7 +/- 0.6 5.6+/- 0.3 6.8 +/- 0.3 6.3 +/- 1.1 24 5.2 +/- 0.3 6.1 +/- 0.6 5.1 +/- 0.3 6.3 +/- 0.3 5.7 +/- 1.2 25 5.5 +/-0.2 5.7 +/- 0.6 5.5 +/- 0.3 6.4 +/- 0.1 5.8 +/- 0.9 26 5.1 +/- 0.2 6.0 +/- 0.1 5.3 +/- 0.4 7.0 +/- 0.4 5.9 +/- 1.7 27 4.7 +/-0.3 5.7 +/- 0.2 4.8 +/- 0.2 6.2 +/- 1.0 5.4 +/- 1.4 28 5.6 +/- 0.3 6.2 +/- 0.5 5.2+/- 0.3 6.8 +/- 0.7 6.0+/- 1.4 29 4.6+/- 0.3 5.7 +/- 0.4 4.6+/- 0.4 6.0 +/- 0.4 5.2 +/- 1.5 30 5.0 +/- 0.1 6.0 +/- 0.3 4.8 +/- 0.3 6.2 +/- 0.3 5.5 +/- 1.4 31 4.5 +/- 0.3 5.3 +/- 0.3 4.5 +/- 0.2 5.4 +/- 0.2 4.9 +/- 1.0 32 5.2 +/- 0.3 5.7 +/- 0.1 5.1 +/- 0.4 7.0 +/- 1.1
- 5.8 +/- 1.7
<.D <.D 33 5.7 +/- 0.2 6.9 +/- 0.7 5.4+/- 0.5 7.0 +/- 0.4 6.3 +/- 1.6 34 5.8 +/- 0.4 6.3 +/- 0.3 5.6+/- 0.3 6.9 +/- 0.3 6.2 +/- 1.2 35 6.3 +/- 0.4 7.2 +/- 0.4 6.0 +/- 0.4 7.2 +/- 0.5 6.7 +/- 1.2 36 6.3 +/- 0.4 7.4 +/- 0.9 6.1 +/- 0.5 7.0 +/- 0.4 6.7 +/- 1.2 37 5.6 +/- 0.3 6.4 +/- 0.7 5.3 +/- 0.5 6.9 +/- 0.3 6.1 +/- 1.5 38 7.5 +/- 0.5 7.7 +/- 0.7 7.1 +/- 0.5 9.0 +/- 0.8 7.8 +/- 1.6 39 5.3 +/-0.2 5.9+/- 0.2 5.3 +/- 0.3 6.2 +/- 0.3 5.1 +/- 0.9 40 4.3 +/- 0.1 4.8 +/- 0.3 4.3 +/- 0.1 5.4 +/- 0.3 4.7 +/- 1.0 41 6.0+/- 0.2 6.3 +/- 0.3 5.8 +/- 0.4 7.5 +/- 0.3 6.4 +/- 1.5 42 5.3 +/-0.2 5.1 +/- 0.4 5.3 +/- 0.4 6.7 +/- 0.7 5.8 +/- 1.3 43 5.4+/-0.4 5.4 +/- 0.1 4.6 +/- 0.3 (a) 4.4 +/- 3.6 (b) 5.0+/-U Average s.s +/- 1.4 6.3 +/- 1.5 5.4 +/- 1.4 6.6 +/- 2.4 6.0 +/- 1.2
+/- 2 s.d.
(a) Third quarter 1LD inadvertantly rehung when placing fourth quarter TLD in field. Third quarter Till received 11/02/90. (b) 1LD was apparently irridiated in transit to the vendor laboratory.
- e TABLE B-16 (Page 1 of2)
SURRY-1990 DIRECT RADIATION MEASUREMENTS -QUARTERLY 1LD RESULTS mR/month +/- 2 Sigma - Set 2 - 099 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s.d. 02 7.3 +/- 0.3 7.4+/- 0.6 7.1 +/- 0.4 8.1 +/- 0.5 1.5 +/- 0.9 03 7.6 +/- 0.5 7.3+/- 0.5 7.4 +/- 0.6 8.6+/- 0.7 7.7 +/- 1.2 04 6.1 +/- 0.3 6.1 +/- 0.9 5.8 +/- 0.3 7.4 +/- 0.4 6.4 +/- 1.4 05 5.1 +/- 0.1 (a) 5.2 +/- 0.2 6.8 +/- 0.2 5.9 +/- 1.6 06 6.4 +/- 0.3 7.0+/- 0.4 6.3 +/-0.4 7.4 +/- 0.4 6.8 +/- 1.0 07 5.1 +/- 0.2 5.7 +/- 0.5 5.7 +/- 0.3 7.0+/- 0.2 6.0 +/- 1.3 08 5.9 +/- 0.3 6.4 +/- 0.9 5.8 +/- 0.4 6.8 +/- 0.4 6.2+/- 0.9 09 6.2 +/- 0.2 6.0+/- 0.6 5.9 +/- 0.4 7.0 +/- 0.7 6.3 +/- 1.0 10 5.5 +/- 0.4 6.6+/- 0.6 5.6 +/- 0.2 7.1 +/- 0.6 6.2+/- 1.6 ...- II 5.8 +/- 0.3 6.0 +/- 0.7 5.9 +/- 0.2 7.0+/- 0.8 6.2 +/- 1.1 0 0 12 6.1 +/- 0.2 (a) 5.9 +/- 0.4 7.1 +/- 0.6 6.4 +/- 1.3 13 6.0 +/- 0.2 6.3 +/- 0.3 5.9 +/- 0.3 7.3 +/- 0.2 6.4 +/- 1.3 14 6.6 +/- 0.2 7.3 +/- 0.2 6.3 +/- 0.5 7.1 +/- 0.6 6.8 +/- 0.9 15 5.1 +/- 0.3 5.1 +/- 0.5 5.5 +/- 0.2 6.9 +/- 0.6 6.0 +/- 1.3 16 5.1 +/- 0.1 6.5 +/- 1.3 5.4+/- 0.5 6.7 +/- 0.4 6.1 +/- 1.2 17 5.4 +/- 0.3 6.0+/- 0.6 4.6+/- 0.4 (b) 2.2 +/- 2.5 (c) 4.6 +/- 3.3 18 4.7 +/- 0.2 5.2+/- 0.6 4.3.+/- 0.2 5.1 +/- 0.2 5.0 +/- 1.2 19 5.1 +/- 0.1 6.1 +/- 0.3 5.0 +/- 0.5 6.6 +/- 0.4 5.1 +/- 1.6 20 4.9+/- 0.2 5.1 +/- 0.3 4.7 +/- 0.2 6.3 +/-0.4 5.4 +/- 1.5 21 5.6 +/- 0.7 6.6 +/- 1.6 5.1 +/- 0.2 6.2 +/- 0.5 5.9 +/- 1.3 22 5.i +/- 0.1 5.5 +/- 0.5 4.6 +/- 0.3 5.8 +/- 0.3 5.3 +/- 1.0. (a) 1LD missing , (b) Third quaner 1LD inadvertantly rehung when placing fourth quarter TLD in field. Third quarter TLD received 11/02/90. (c) 1LD was apparently irridiated in transit to the vendor laboratory.
e TABLE B-16 (Page2 of2) SURRY-1990 DIRECT RADIATION MEASUREMENTS - QUARTERLY TlD RESULTS mR/month +/- 2 Sigma - Set 2 - 099 STATION AVERAGE NUMBER FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER +/- 2 s.d. 23 6.0+/- 0.2 6.7 +/- 0.6 5.6+/- 0.3 7.2 +/- 0.2 6.4 +/- 1.4 24 5.7 +/- 0.3 6.3 +/- 0.4 5.2+/- 0.2 6.2 +/- 0.6 5.9 +/- 1.0 25 5.8 +/-0.2 5.9+/- 0.3 5.2 +/- 0.3 6.1 +/- 0.2 5.8 +/- 0.8 26 5.2 +/- 0.2 5.9 +/- 0.7 5.3+/- 0.2 5.6 +/- 0.9 5.5 +/- 0.6 27 4.8 +/- 0.3 5.9 +/- 0.5 4.5 +/- 0.2 6.4 +/- 0.4 5.4 +/- 1.8 28 5.4+/- 0.0 6.4+/- 0.5 5.3 +/- 0.3 6.7 +/- 0.4 6.0 +/- 1.4 29 4.7 +/-0.2 5.3 +/- 0.4 4.6+/- 0.2 5.5 +/- 0.5 5.0 +/- 0.9 30 5.1 +/- 0.2 6.3 +/- 0.6 5.0 +/- 0.5 6.2 +/- 0.3 5.7 +/- 1.4 31 4.6 +/- 0.1 5.6 +/- 0.8 4.5 +/- 0.2 6.0+/- 0.7 5.2 +/- 1.5 ...... 32 5.2 +/- 0.2 6.1 +/- 0.4 5.0+/- 0.2 6.5 +/- 0.6 5.7 +/- 1.4 0 ...... 33 5.6 +/- 0.2 6.8 +/- 0.6 5.4 +/- 0.3 7.2 +/- 0.7 6.3 +/- 1.8 34 5.7 +/- 0.2 6.2 +/- 0.5 5.4+/- 0.4
- 7.2 +/- 1.0 6.1 +/- 1.6 35 5.8 +/-0.2 6.8 +/- 0.4 5.9 +/- 0.3 7.1 +/- 0.6 6.4 +/- 1.3 36 6.3 +/- 0.5 7.3 +/- 0.3 6.1 +/- 0.5 1.5 +/- 0.1 6.8 +/- 1.4 37 5.2+/- 0.4 6.3 +/- 0.6 5.2+/- 0.2 6.5 +/- 0.4 5.8 +/- 1.4 38 7.2 +/-0.4 8.4 +/- 1.4 7.2+/- 0.5 9.0 +/- 1.1 8.0 +/- 1.8 39 5.3 +/- 0.2 6.1 +/- 0.6 5.2+/- 0.5 6.3 +/- 0.5 5.1 +/- 1.1 40 4.2+/- 0.2 5.3 +/- 0.9 4.2+/- 0.2 5.7 +/- 0.6 4.9 +/- 1.5 41 5.7 +/- 0.4 6.4 +/- 0.4 5.9+/- 0.9 7.2 +/- 0.8 6.3 +/- 1.3 42 5.4 +/- 0.3 6.0+/- 0.6 5.6+/- 0.6 6.3 +/- 0.6 5.8 +/- 0.8 43 5.1 +/- 0.3 6.1 +/- 0.4 5.5 +/- 0.7 6.3 +/- 0.4 5.8 +/- 1.1 Average 5.7 +/- 1.4 6.3 +/- 1.3 5.5 +/- 1.4 6.7 +/- 1.4 6.1 +/- 1.1
+/- 2 s.d.
APPENDIX C LAND USE CENSUS - 1990 102
ANNUAL RADIOLOGICAL ENVIRONMENTAL LAND USE CENSUS FOR SURRY POWER STATION
- 1990 Nearest Nearest Nearest Nearest Sector Resident Garden Cow Goat A-(N) 4.72@ 357° * *
- B-(NNE) 1.90@ 34° 1.90@ 34° *
- C-(NE)
- 4.91@ 56° *
- D-(ENE) 4.73@ 63° 4.91@ 56° *
- E-(E) * * *
- F-(ESE) * * *
- G-(SE) * * *
- H-(SSE) 4.75@ 152°. * *
- J-(S) 1.82@ 182° 2.01@ 182° *
- K-(SSW) 1.87@ 193° 1.87@ 193° 4.84@ 201°
- L-(SW) 2.28@ 222° 3.65@ 224° *
- M-(WSW) . 2.82@ 243° 3.52@ 246° *
- N-(W) 3.15@ 260° 4.12@ 267° *
- P-(WNW) 4.79@ 281° * *
- Q-(NW) * * *
- R-(NNW) 3.73@ 339° 4.89@ 340° 3.65@ 337° *
- None All distances are in statute miles.
103
~URRY POWER STATION
~
...IL' 1990 LAND USE CENSUS LOCATION MAP 1 = NEAREST RESIDENT 2 = HEAREST GARDEN 3 .. HEAKKST COW 4., NEAREST GOAT 104
e APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 105
ANALYTICAL PROCEDURES SYNOPSIS Appendix D is a synopsis of the analytical procedures perfonried on samples collected for the Surry Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne Isotopes and include those recommended by the USNRC Branch Technical Position, Rev. 1, November 1979. ANALYSIS TITLE PAGE Gross Beta Analysis of Samples ......................................................................... 107 Airborne Particulates .............................................................................. 107 Analysis of Samples for Tritium........................................................................... 110 Water ................................................................................................. 110 Analysis of Samples for Strontium-89 and -90 ......................................................... 111 Total Water ................................................... ." ..................................... 111 Milk ...........................................................*...................................... 111 Soil and.Sediment ................................................................................. 111 Organic Solids .......................................................*.............................. 112 Air Particulates ..................................................................................... 112 Analysis of Samples for Iodine-131 ..................................................................... 115 Milk or Water ...................................................................................... 115 Gamma Spectrolnetry of Samples ........................................................................ 116 Milk and Water ..................................................................................... 116 Dried Solids other than Soils and Sediment .................................................... 116 Fish ................................................................................................. 116 Soils and Sediments ............................................................................... 116 Charcoal Cartridges (Air Iodine) .............................. : ................................. 116 Airborne Particulates .............................................................................. 117 _Envirolllllental Doshnetry ............................................. : ................. :................. 118 106
DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES I *.O INTRODUCTION The procedures described in this section are used to measure the overaUradioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved. One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size. After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchet which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness talces place under .heat lamps. Residue mass is determined by weighing the planchet before and after mounting the sample. The planchet is counted for beta activity on an automatic proportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective counting efficiency caused by the residue mass. 107
2.0 DETECTION CAPABILITY Detection capability depends upon the sample volume actually represented on the planchet, the background and the efficiency of the counting instrument, and upon self-. absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay corrections are made and the reported activity refers to the counting time. The minimum detectable level (MDL) for water samples is nominally 1.6 picocuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/1 at the 2.83 sigma level), assuming that 1 k liter of sample is used and that gram of sample residue is mounted on the planchet. These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively. The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picocuries per liter. These values reflect a beta counting efficiency of 0.38. e 108
GROSS BETA ANALYSIS OF SAMPLES Air Particulates After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air particulate filter, supplied by Vepco, is counted as the blank. Calculations of the results, the two sigma error and the lower limit of detection (LLD): RESULT (pCi/m3) = ((S/f) - (B/t))/(2.22 VE) TWO SIGMA ERROR (pCi/m3) = 2((Str2) + (B/t2))lf2/(2.22 VE) Lill(pCi/m3) = 4.66 (Bl/2)/(2.22 VE t) where: s = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) 109
ANALYSIS OF SAMPLES FOR TRITIUM Approximately 2 ml of water are converted to hydrogen by passing the water, heated to its vapor state, over a granular zinc conversion column heated to 400° C. The hydrogen is loaded into a orie liter proportional detector and the volume is determined by recording the pressure. The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shielding from cosmic rays. Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/1: RESULT = 2(3.234) TN VN(CQ - B)/(CN Vs) TWO SIGMA ERROR = 2(3.234) TN VN(E)l/2/(CN Vs) UD = 3.3 (3.234)TN VN(E)l/2/(CN Vs) where: TN = tritium units of the standard 3.234 = conversion factor changing tritium units to pCi/1 VN = volume of the standard used to calibrate the efficiency of the detector in psia Vs = volume of the sample loaded into the detector in psia CN = the net cpm of the standard of volume VN CG = the gross cpm of the sample of volume Vs B = the background of the detector in cpni
& = counting time for the sample E = S/f'}. + B/t2 110
ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(N03)2 using nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Stable strontium carrier is added to I liter of sample and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrN03 using fuming (90%) nitric acid A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrachloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N03)2 usin~ fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating 111
SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an -80 mg/cm2 aluminum absorber for low level beta counting. Or~anic Solids A wet portion of the sample is dried and then ashed in a muffle furnace. Stable strontium . carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(N03) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Yttrium is then pre-cipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation; Strontium is precipitated as Sr(N03)2 using fuming (90%) nitric acid. A barium scavenge is used to remove some interfering species. An -iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is detennined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for low level beta counting. Calculations of the results, two sigma *errors and lower limits of detection (LLD) are expressed in activity of pCi/volume or pCi/mass: RESULT Sr-89 = (N/Dt-Bc-BA)/(2.22 Vys DFsR-89 EsR-89) TWO SIGMA ERROR Sr-89 = 2((N/Dt+Bc+BA)//lt) 1/2/(2.22 Vys DFsR-89 EsR-89) LLDSr-89 = 4.66((Bc+BA)l/lt)ll2/(2.22 V YS DFsR-89 EsR-89). 112
RESULT Sr-90 = (N/At - B)/(2.22 VY 1 Y2 DF IF E) TWO SIGMA ERROR Sr-90 = 2((N/At+B)/At)ll2/(2.22VY1 Y2DFEIF)) LLDSr-90 = 4.66(B/At)ll2/(2.22VY1 Y2IFDFE) 113
where: N = total counts from sample (counts) At = counting time for sample (min) Be = background rate of counter (cpm) using absorber configuration 2.22 = dpm/pCi V -* volume or weight of sample analyzed BA background addition from Sr-90 and ingrowth of Y-90 BA = 0.016 (K) + (K) EY/abs) (IGy_90) Ys = chemical yield of strontium DF SR-89 = decay factor from the mid collection date to the counting date for SR-89 EsR-89 = efficiency of the counter for SR-89 with the 80 mg/cm.sq. aluminum absorber K = (NAt- Bc)Y-9o/CEY-90 IFy_90 DFy_90Y 1) DFy_90) = the decay factor for Y-90 from the "milk" time to the mid count time Ey_90 = efficiency of the counter for Y-90 1Fy_90 = ingrowth factor for Y-90 from scavenge time to milking time IGy_90 = the ingrowth factor for Y-90 into the strontium mount from the "milk" time to the mid count time 0.016 = the efficiency of measuring SR-90 through a No. 6 absorber EY/abs = the efficiency of counting Y-90 through a No. 6 absorber B = background rate of counter (cpm) Y1 = chemical yield of yttrium Y2 = chemical yield of strontium DF = decay factor of yttrium from the radiochemical milking time to the mid count time E = efficiency of the counter for Y-90 IF = ingrowth factor for Y-90 from scavenge time to the radio-chemical milking time 114
ANALYSIS OF SAMPLES FOR IODINE-131 . Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch* treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, reduced with hydroxylamine hydrochloride and extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The sodium bisulfite solution is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode. Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/1: RESULT = (N/L\t-B)/(2.22 EVY DF) TWO SIGMA ERROR = 2((N/L\t+B)/L\t)l/2(2.22 EVY DF) LLD = =4.66(B/L\t)ll2/(2.22 EVY DF) where: N = total counts from sample (counts) M. = counting time for sample (min) B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed y = chemical yield of the mount or sample counted DF = decay factor from tbe collection to the counting date E = efficiency of the counter for I-131, corrected for self absorption effects by the formula E = Es(exp-0.0061 M)/(exp-0.006 lMs) Es = efficiency of the counter determined from an I-131 standard mount Ms = mass of Pd I 2 on the standard mount, mg . M = mass of PdI2 on the sample mount, mg 115
GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried at a low temperature, less than 100°C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. Soils and Sediments Soils and sediments are dried at a low temperature, less than 100°C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed The sample is then counted for approximately six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height and analysis. Charcoal Cartridges (Air Iodine) Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for I-131 of each charcoal cartridge can be determined (assuming no positive I-131) uniquely from the volume of air which passed through it. In the event I-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector. 116
Air Particulate The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/volume ofpCi/mass: RESULT = (S-B)/2.22 t EV F DF) TWO SIGMA ERROR = 2(S+B)l/2/(2.22 t EV F DF) LID = 4.66(B)lf2/(2.22 t EV F DF) where: s = Area, in counts, of sample peak and background (region of spectrum of interest) B = Background area, in counts, under sample peak, determined by a linear interpolation of the representative backgrounds on either side of the peak t = length of time in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams) F = fractional gamma abundance (specific for each emitted gamma) DF = decay factor from the mid-collection date to the counting date 117
-- ENVIRONMENTAL DOSIMETRY Teledyne Isotopes uses a CaS04 :Dy thermoluminescent dosimeter (TLD) which the - company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible s~lf dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate 1LDs. Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular 1LD is heated at a time and the measured light emission (luminescence) is recorded The TLD is then annealed and exposed to a known Cs-137 dose;-each area is then read again. This provides a calibration of each area of each 1LD after every field use. The transit controls are read in the same manner. Calculations of results and the two sigma error in net milliRoentgen (mR): RESULT = D = (D 1+D2+D3+D4)/4 TWO SIGMA ERROR = 2((D1-D)2+(D2-D)2+(D3-D)2+(D4-D)2)/3)1/2 WHERE: D1 = the net mR of area 1 of the 1LD, and similarly for D2, D3, and D4 Dl = 11 K/R1 -A I1 = the instrument reading of the field dose in area 1 K = the known exposure by the Cs-137 source R1 = the instrumentreading due to the Cs-137 dose on area 1 A = average dose in mR, calculated in similar manner as above, of the transit control TLDs D = the average net mR of all 4 areas of the TLD. 118
APPENDIX E EPA INTERLABORATORY COMPARISON PROGRAM 119
e SURRY - 1990 US EPA INTERLABORAIDRY COMPARISON PROORAM 19CJO (Page 1 of3) EPA Date TI Malled Date EPA EPA TI Norm Dev. **warning Preparation Results Issued Results Media Nuclide Results(a) Results(b) (Known) *uActlon Ol/12JIJO 03/21/1)() 04/09/IJO W811::r Sr-89 25.00 +/- 5.00 24.00 +/- 1.73 -0.35 Sr-90 20.00 +/- 1.50 19.67 +/- 2.52 -0.38 01/26/1)() 02/23/1)() 03/30/1)() W811::r Gr-Alpha 12.0+/- 5.0 10.00 +/- 1.73 -0.69 Gr-Beta 12.0 +/- 5.0 12.33 +/- 1.53 0.12 02/09/1)() 03/23/1)() 04/09/IJO WBIJ::r Co-60 15.00 +/- 5.00 15.00 +/- 3.46 0.00 Zn-65 139.00 +/- 14.00 131.33 +/- 9.07 -0.95 Ru-106 139.00 +/- 14.00 113.67 +/- 4.04 -3.13 ***(c) Cs-134 18.00 +/- 5.00 15.33 +/- 2.31 -0.92 Cs-137 18.00 +/- 5.00 19.33 +/- 3.21 0.46 Ba-133 74.00 +/- 7.00 66.00+/- 3.46 -1.98 02/23/1)() 03f22JIJ() 04/09/1)() WBIJ::r H-3 4976.00 +/- 498.00 4900.00 +/- 100.00 -0.26 03/09/1)() 05ft)3/IJ() 05/21/IJO W811::r Ra-226 4.9 +/- 0.7 4.73+/- 0.47 -0.41 Ra-228 12.7 +/- 1.9 13.00 +/- 1.00 0.27 f--' 03/30/1)() . 06/08/1)() 07ft}3/IJO Air Filter Gr-Alpha 5.0+/- 5.0 6.33 +/- 0.58 0.46 N C) Gr-Beta 31.0 +/- 5.0 31.67 +/- 0.58 0.23 Sr-90 10.0+/- 1.5 9.33+/- 0.58 -0.77 Cs-137 10.0+/- 5.0 10.67 +/- 1.15 0.23 04/17/1)() 07/20/1)() WBIJ::r Gr-Alpha 90.00 +/- 23.0 79.33 +/- 2.89 -0.80 Ra-226 5.0 +/- 0.8 5.67 +/- 0.15 1.44 Ra-228 10.2 +/- 1.5 9.37 +/- 1.44 -0.96 Gr-Beta 52.0+/- 5.0 53.33 +/- 1.53 0.46 Sr-89 10.0+/- 5.0 10.67 +/- 1.15 0.23 Sr-90 10.0+/- 1.5 9.67 +/- 0.58 -0.38 Cs-134 15.0 +/- 5.0 12.67 +/- 1.53 -0.81 Cs-137 15.0+/- 5.0 16.33 +/- 1.15 0.46 04/27/1)() 06/1.2/1)() 07/27/1)() Sr-89 23.0+/- 5.0 24.67 +/- 1.53 0.58 Sr-90 23.0+/- 5.0 24.00 +/- 0.00 0.35 1-131 99.0+/- 10.0 89.67 +/- 3.21 -1.62 Cs-137 24.0+/- 5.0 27.33 +/- 2.52 1.15 K 1550.0 +/- 78.0 1483.33 +/- 75.06 -1.48
- See footnotes at end of table.
e SURRY - 1990 US EPA INTERLAB0RA1URY COMPARISON PROGRAM 19'JO (Page 2of3) EPA Date TI Malled Date EPA EPA TI Norm Dev. **Warning Preparation Results Issued Results Media Nuclide Results(a) Results(b) (Known) ***Action 05,1)4/90 06fl2/90 07/31/90 Water Sr-89 7.0+/- 5.0 6.67 +/- 0.58 -0.12 Sr-90 7.0 +/- 5.0 6.67 +/- 0.58 -0.12 05/11/90 06/08/90 07/03/90 Water Gr-Alpha 22.0+/- 6.0 16.00 +/- 1.00 -1.73 Gr-Beta 15.0+/- 5.0 17.00 +/- 1.00 0.69 06/08/90 07/17/90 08/14/90 Water Co-60 24.0+/- 5.0 25.33 +/- 2.52 0.46 Zn-65 148.0 +/- 15.0 148.67 +/- 3.06 0.08 Ru-106 210.0 +/- 21.0 196.00 +/- 20.66 -1.15 Cs-134 24.0+/- 5.0 23.67 +/- 2.89 -0.12 Cs-137 25.0 +/- 5.0 24.67 +/- 2.08 -0.12 Ba-133 99.0+/- 10.0 93.00 +/- 6.08 -1.04 06fl2/90 07/19/90 08/14/90 Water H-3 2933.0 +/- 358.0 2900.+/- 100.00 -0.16 07/13/90 09/06/90 10/09/90 Water Ra-226 12.1 +/- 1.8 11.37 +/- 0.60 -0.71 Ra-228 5.1 +/- 1.3 4.20+/- 0.75 -1.20 I .J 08/IOM> 08/30f}O 10(2.6f)O Water 1-131 39.0 +/- 6.0 36.00+/- 3.00 -0.87 08/3lf}O l l/06f}O 11(2.9/90 Air Filter Gr-Alpha 10.0+/- 5.0 16.00 +/- 1.00 2.08 ** (d) Gr-Beta 62.0 +/- 5.0 63.33 +/- 1.53 0.46 Sr-90 20.0+/- 5.0 18.00 +/- 1.00 -0.69 Cs-137 20.0+/- 5.0 18.33 +/- 3.21 -0.58 09/14/90 ll/'}1)/90 12/11/90 Water Sr-89 10.0+/- 5.0 8.67 +/- 0.58 -0.46 Sr-90 9.0+/- 5.0 9.0+/- 1.00 0.00 09(2.1/90 10/17/90 11/05/90 Water Gr-Alpha 10.0+/- 5.0 11.00 +/- 1.00 0.35 Gr-Beta 10.0+/- 5.0 11.00 +/- 1.00 0.35 09(2.8/90 12/04/90 12/24/90 Mille Sr-89 16.0+/- 5.0 9.0+/- 2.65 -2.42 **(e) Sr-90 20.0+/- 5.0 15.33 +/- 0.58 -1.62 1-131 58.0+/- 6.0 54.67 +/- 1.53 -0.96 Cs-137 20.0+/- 5.0 23.00+/- 1.73 1.04 K 1700.0 +/- 85.0 1710.00 +/- 65.51 0.20
- See foomotes at end of table.
e SURRY - 1990 US EPA INTERLAB0RA10RY COMPARISON PROGRAM 1990 (Page 3 of3) EPA Date TI Malled Date EPA EPA TI Norm Dev. **warning Preparation Results Issued Results Media Nuclide Results(a) Results(b) (Known) ***Action 10/151!)() 11/161!)() 1211)41!)() . Water Co-60 20:0+/- 5.0 21.00 +/- 1.00 0.35 Zn-65 115.0 +/- 12.0 115.00 +/- 11.53 0.00 Ru-106 151.0 +/- 15.0 142.00 +/- 8.66 -1.04 Cs-134 12.0+/- 5.0 11.00 +/- 0.00 -0.35 Cs-137 12.0+/- 5.0 16.33 +/- 2.52 1.50 Ba-133 110.0 +/- 11.0 94.67 +/- 5.13 -2.41 ** (f) 10/191!)() 11/16/!)() 1211)41!)() Water H-3 7203.0 +/- 720.0 7133.33 +/- 251.66 -0.17 10/30/90 01/10/91 0211)4/91 Lab Perf. Gr-Alpha 62.00 +/- 16.00 51.00 +/- 1.00 -0.54 Sample A Ra-226 13.6+/- 2.0 12.67 +/- 1.27 -0.81 Ra-228 5.0 +/- 1.3 4.87 +/- 0.23 -0.18 SampleB Gr-Beta 53.0+/- 5.0 51.00 +/- 2.31 -0.12 Sr-89 20.0+/- 5.0 19.00 +/- 3.61 -0.35 Sr-90 15.0 +/- 5.0 14.33 +/- 0.58 -0.23 Cs-134 7.0 +/- 5.0 9.00 +/- 0.00 0.69 Cs-137 5.0 +/- 5.0 7.67 +/- l.15 0.92 1--' N N 11/09/90 01/04/91 01/29/91 Water Ra-226 7.4+/- 1.1 7.27 +/- 0.38 -0.21 Ra-228 7.7 +/- 1.9 1.51 +/- 0.32 -0.12 (a) Average+/- experimental sigma. (b) Expected laboratory precision (1 sigma, 1 detamination). (c) No apparmt cause for the low results were found. Three aliquots of the sample were counted on three separate detectors. The results of all three were similar. The calibration curve fit is good (0.997). Rutheniwn-106 was obtained from the EPA. Results of spikes were acceptable. Subsequent cross-checks from the EPA did not exceed two normalized standard deviation. No additional follow-up is necessary, but we will continue to monitor the results. New calibrations were completed March, 1991. (d) The EPA deposit occupies a smaller area than our calibration planchet and hence has a higher counting efficiency. No further corrective action is required, since our calibration standanl better represents an air particulate filter. (e) Incomplete removal of calciwn, lead to erroneously high strontiwn yields. More care is being taken in the strontiwn nitrate and strontiwn sulfate precipitation steps to ensure a final volume of at least 20 ml in the strontium sulfate step. Reanalysis of internal QC samples produced good results after implementing the corrective action. (t) There is no apparent reason for the deviation between the EPA and Teledyne Isotopes values. Other isotopes in the sample were measured accurately. The calculations were reviewed and activities calculated from other Ba-133 gamma rays. Results were reproduced as reported.
e TRENDING GRAPH - 12 US EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICUIATES 80 d 60 N V, --- 0 D. 40 20 O+--..---...----,------.-------""T"""-~-'T"'"--r----.---,---.----.------------~ 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991
- 08/25/89 EPA Test Invalid a Tl +/-3sigma o EPA+/- 3 sigma
US 'EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES 100...,.........-----------------------------------------------------------------------------------------------------------------------------------------------, c Tl +/-3 sigma o EPA+/- 3 sigma 80 60
. Cl)
-- I-'
'..."' 40
~
20 I I 0 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991
US EPA CROSS CHECK PROGRAM IODINE-131 IN MILK 120 100
...II =
I-' N u Q. 80 (J1 60 40 20 a I 0 ...--.0-......----~-~---.------...-.,....._._......,...__..,__....,..____________- - t 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 a Tf +/-3 sigma o EPA +/-3 sigma
e US EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK 2400 2000
- CII I-'
N 0\ 0 . ~ I n. 1J {! 1600 ~ 1t I I I~ 11 > ~ I I II I,~ I 1* I I I
.~
1200 * .. 8004----.......- -.......-=-....--J.-....-,--.-----,.-----.----.,,-...--,----,.,----,.----y,,----y,----y,,----,..---.----r----r----.----l 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 a Tl +/-3 sigma o EPA +/-3 sigma
us* EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK 80 60 l f--< N --.J
=
0 II A. 40 20 o~--------------..--...-....--..---,.-----..-----------~ 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 a Tl+/-3slgma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM STRONTIUM 89 IN MILK 100---------------------------------------. 80 60 ~..) 0 co ~ 40 a a I a ~ 20 0 -M>-----,-~-,c....,__ _ _ _ _ _--r--------.----..--...------------...---.......;;;;i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 a Tl +/-3 sigma o EPA +/-3 sigma
US EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK 80 I 60 CII N
=
I.O 0 a. 40 a~ 0 H 20 I i ff 0 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 o Tl +/-3 sigma
- EPA+/-3 sigma
US EPA CROSS CHECK PROGRAM IODINE-131 IN WATER 160 Q)
=
0 120 Q. ...... g vi 0 80 r 40 0----.....------------.-------.-----.---__._-.-_,....___,,..._____________,,...______ 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 c Tl +/- 3 sigma o EPA +/-3 sigma
e US EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. I)
. 80.
... 60 *
. I GI )
v,I ...... u C. II 40
)
~,, ~
J 20
)
I I I* I
)
I f. J. I JI 1!I 0 1981 I 1982 I 1983 I 1984 il 1985 c Tl+/-3sigma o EPA +/-3 sigma
e US EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 2) 80
. 60 f--"
vl 0 N 40 A.
~
20
; I 0
' l i ~
. -20+-----......-------...--------------------------4 1984 1985 1986 1987 1988 1989 1990 1991 a Tl+/-3 Sigma o EPA+/- 3 Sigma
US EPA CROSS CHECK PROGRAM STRONTIUM-90 IN WATER 80
*E 60 Q
ii
&") +I I-' 40 tN tN i=
20 0
+-------------------------..--,--------------f 1980 1981 1982 1983 198" 1985 1986 1987 1988 1989 1990 1991 a T1+/-3Sigma o EPA+/-3Sigma
US EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 1) 4000 GI f I 3000 0 c.. vl .I:,. 7 2000 1000 o---------------.,----..-------------------- 1981 1982 1983 1984 1985 a Tl +/-3 sigma o EPA +/-3 sigma
- e US EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2) 8000 6000
~
t,,l tn
~
f 0 4000 Q, 2000
;i O-t----..-----..----------,.--.._..----,-----r----.--------..------------1 1985 1986 1987 1988 1989 1990 1991 o Tl+/-3 S o EPA+/-3S}}