ML20108C528
| ML20108C528 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1995 |
| From: | Bowling M, Breeden J, Dreyer E VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 96-185, NUDOCS 9605070010 | |
| Download: ML20108C528 (136) | |
Text
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o VIHOINIA ELECTRIC AND power Coxiwxy Ricunowx),V norwrA 2r5201 l
April 22,1996 1
l United States Nuclear Regulatory Commission Serial No.96-185 Attention: Document Control Desk NURPC Washington, D. C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 l
NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Pursuant to Technical Specification 6.9.1.8, enclosed is the Annual Radiological Environmental Operating Report for North Anna Power Station Units 1 and 2 for 1995.
If you have any questions or require additional information, please contact us.
Very truly yours, M. L. Bowling, ianager Nuclear Licensing and Operations Support Attachment cc:
U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 l
l Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station
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VIRGINIA ELECTRIC AND POWER COMPANY l
NORTH ANNA POWER STATION
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Radiological Environmental Monitoring Program January 1,1995 to December 31, 1995 l
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1 Prepared by l
VIRGINIA ELECTRIC AND POWER COMPANY and 1
TELEDYNE BROWN ENGINEERING
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O Annual Radiological Environmental Operating Report North Anna Power Station January 1,1995 to December 31, 1995 Yb Prepared by:
Y James B. Breeden, Supervisor Radiological Analysis Reviewed by:
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erich w. oreyer Supervisor Health Physics Technical Services Approved by:
8 dn H. Stafford Superintendent Radiological Protection i
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l Table Of Contents n
i-I Seetion Title Pare Preface.......................................................................................7 Executi ve S u mmary.......................................................................... 8 q
l I.
In trod uc tion................................................................
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II.
Nuclear Power And The Environment: In Perspective................................. 12 l
III.
S a m plin g A n d A n alysis Program.......................................................... 25 IV.
Program Exceptions.........................................................................41 V.
Summary And Discussion Of 1995 Analytical Results................................ 42 A.
Airborne Exposure Path way........................................................ 42 1.
Air Iodine /Particulates.....................................................
l 2.
Pmcipitation................................................
Soil............................................................................44 l
3.
....................45 O
B.
Waterborne Ex posure Pathway.................................................... 45 1.
Grou n d/Well Water........................................................
2.
Rive r Wate r..............................................................
3.
S urface Water.........................................................
l C.
Aquatic Exposure Pathway........................................................ 48 I
i 1.
Sedimen t/S il t.............................................................
2.
S hore line S oil............................................................
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i D.
Inge sticn Exposure Pathway...................................................... 51 1.
Mi1L.
Fish..........................................................................51 2.
Fo o d / V e g e t a t i o n.......................................
3.
. 52 E.
Direct Radiation Exposure Pathway............................................... 54 1.
TLD D o s i m e t e r s........................................................
i VI.
Co n e.l u sio n......................................................................
r ks 3
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Table Of Contents (Continued)
Sectlon Title P_ age VII.
R e fe r e n c e s.................................................................................. 5 8 VIII.
Appendices................................................................................59 Appendix A - Radiological Environmental Monitoring............................... 59 Program Annual Summary Tables - 1995 Appendix B - Data Tables............................................................... 66 Appendix C - Land Use Census - 199 5................................................. 8 9 Appendix D - Synopsis of Analytical Procedures..................................... 92 Appendix E - EPA Interlaboratory Comparison Program........................... 103 List of Trendine Graohs 1.
Gross Beta in Air Particulates............................................................. 4 3 2.
Triti um in River Water...................................................................... 4 3 3.
Tritium in Surface Water...............................................................47 4.
Cobalt-58 in Sediment Silt..............................................................47 5.
Coba1t-60 in Sediment Silt...................
....................................49 6.
Cesiu m-134 in Sediment Silt.......................................................... 49 7.
Cesium-137 in Sediment Silt...............
..........................................50 8.
Ce s iu m-13 4 i n Fi s h................................................................. 5 0 9.
Cesium-137 in Fish................
....................................................53 10.
Environmental Radiation - TLDs....................................................... 53 4
. List of Firures Figure Title Ease 1.
Atomic Structure............................................................................. 12 2.
Alpha Partic le................................................................................ 14 3.
Beta Particle.................................................................................. 1 4 4.
GammaRay..................................................................................14 5.
The Penetrating Ability of Various Types of Radiation................................. 15 6.
Uni t Compari son............................................................................ 15 l
i 7.
The Curie, a Measurement of Activity................................................... 16 8.
Average Annual Dose Equivalent to Persons in the U.S.
from Various Radiation Sources.......................................................... 17 9.
Estimated Average Days of Life Expectancy Lost Due to Q
Various Hea1th Risks........................................................................19 10.
Reactor Vessel with Fuel Assemblies, Rods, and Fuel Pellets......................... 20
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11.
Fission: a Chain Reaction.................................................................. 21 12.
PWR Syste m Diagram...................................................................... 2 2 13.
Containment Sc hematic..................................................................... 23 14.-
North Anna Radiological Monitoring Locations......................................... 32 i
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1
s List of Tables Table Page 1.
Uran i u m I sotopes......................................................................... 13 2.
Radiological Sampling Station Distance and Direction from Unit 1..............................................................................26 3.
- North Anna Power Station Sample Analysis Program............................... 38 4.
REMP Exceptions for Scheduled Sampling and Analysis During 1995...................................................................41 Appendix B Tables B-1 Iodine-131 Concentration in Filtered Air............................................... 66 B-2 Concentrations of Gross Beta in Air Particulates..................................... 68 B-3 Gamma Emitter, Strontium 89, and Strontium 90 Concentrations in Air Particulates...................................................... 72 B-4 Gamma Emitter and Tritium Concentration in River Water........................... 75 B-5 Gamma Emitter Co n c e n t ration in S 0i1............................................... 76 O
V B-6 Gamma Emitter, Strontium, and Tritium Concentrations in Ground and Well Water............................................................77 B-7 Gamma Emitter, Strontium, and Tritium Concentrations in Ri ve r W at e r.............................................................................. 7 7 B-8 Gamma Emitter, Strontium, and Tritium Concentrations i n S u rface Wate r....................................................................... 78 B-9 Gamma Emitter, Strontium, and Tritium Concentrations in Surface Water State-Split Samples................................................. 79 B-10 Gamma Emitter Concentrations in Sediment Silt................................... 80 B-11 Gamma Emitter Concentrations in Shoreline So11..................................... 80 B-12 Gamma Emitter Concentrations in Milk................................................ 81 B-13 Gamma Emitter Concentrations in Fish.......
...................................83 B-14 Gamma Emitter Concentrations in Food / Vegetation.................................. 84 B-15 Direct Radiation Measurements Quarter 1y A nn ua1 TLD ResuIts.................................................... 86 O
B-16 Din et Radiation Measurements d
Sector Quarierly TLD Resu1ts............
...............................87 6
Preface 1
This report is submitted as required by Technical Specification 6.9.1.8, Annual Radiological Environmental Operating Report for North Anna Power Stations, Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-338 and 50-339.
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Executive Sttmmary i
- O This document is a detailed report on the 1995 Nonh Anna Nuclear Power Station Radiological Environmental Monitoring Program (REMP). Radioactivity levels fromJanuary 1 through December 31,1995 in water, silt, shoreline sediment, milk, aquatic biota, food products, vegetation, and direct
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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 i
undue environmental effects occur, and the health and safety of the public is protected. The l
program also detects any unexpected environmental processes which could allow radiation l
accumulations in the emironment or food pathway chains.
i Radiation and radioactivity in the environment is con-j stantly monitored within a 25 mile radius of the station.
Virginia Power also collects samples within this area. A j
number of sampling locations for each medium were selected
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using available meteorological, land use, and water use data.
l Two types of samples are obtained. The first type, control j
samples, are collected from areas that are beyond the measur-g o
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able influence of North Anna Nuclear Power Station or any
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other nuclear facility. These samples are used as reference l
data. Normal background radiation levels, or radiation present I due to causes other than North Anna Power Station, can thus
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be c mp red to the environment surrounding the nuclear j
power station. Indicator samples are the second sample type J
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obtained.
These samples show how much radiation is ij j
contributed to the emironment by the plant.
Indicator i~@7 j
samples are taken from areas close to the station where any
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j plant contribution will be at the highest concentration.
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Prior to station operation, samples were collected and analyzed to determine the amount of radioactivity present in the area. The resulting values are used as a " pre-operational baseline."
l Analysis results from the indicator samples are compared to both current control sample values and l
the pre-operational baseline to determine if changes in radioactivity levels are attributable to station j
operations, other causes such as the Chemobyl accident, or natural variation.
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Teledyne Brown Engineering provides sample analyses for various radioisotopes as appropri-l ate for each sample media. Participation in the Environmental Protection Agency's (EPA)
Interlaboratory Comparison Program provides an independent check of sample measurement j
precision and accuracy. Typically, radioactivity levels in the emironment are so low that analysis j
values frequently fall below the minimum detection limits of state-of-the-art measurement methods.
Because of this, the Nuclear Regulatory Commission (NRC) requires that equipment used for
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radiological environmental monitoring must be able to detect specifled minimum Lower Limits of l
Detection (LLD). This ensures that analyses are as accurate as possible. Samples with extremely l
n low levels of radiation which cannot be detected are therefore reported as being below the LLD.
V The NRC also mandates a " reporting level." Licensed nuclear facilities must report any releases i
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equal to or greater than this reporting level. Environmental radiation levels are sometimes (G]
referred to as a percent of the reporting level.
Analytical results are divided into five categories based on exposure pathways: Airborne, waterbome, aquatic, ingestion, and direct radiation. Each of these pathways is described below:
The airborne exposure pathway includes airborne iodine, airborne particulate, precipi-tation, and soil samples. The overall 1995 airborne results were very similar to previous years and to preoperational levels. No increase was noted and there were no detections of fission products or other man-made isotopes in the aidx>rne particulate media during 1995.
The waterborne exposure pathway includes ground /well water, river water, and surface water samples. No nun-made or natural isotopes were detected in Lake Anna surface water except for tritium. The average tritium activity in 1995 was 14% of the NRC reporting level. This has essentially renuined unchanged from 1994 levels.
The aquatic exposure pathway includes sediment / silt and shoreline samples. North Anna sediment contained some cesium-137. During the preoperational period, cesium-137 was detected. Sediment contamination, however, does not provide a direct dose pathway to nun. In shoreline soil, which nuy provide a direct dose pathway, only cesium-137 was detected. Cesium-137 levels were 341 pCi/kg in 1995.
7(O The ingestion exposure pathway includes milk, fish, and food / vegetation samples.
Iodine-131 was not detected in any 1995 milk samples. Although cesium-137 has been detected in the past, it was not detected in 1995 milk samples. Strontium-90 was detected at levels comparable to 1989, 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 nornul environmental levels.
Fish samples during 1995 contained cesium-137 at a slightly higher activity than preoperational levels. Steam generator repairs and better liquid waste processing, however, have reduced these activity levels from previous years. Vegetation samples were statistically similar to both control and preoperational levels.
The direct radiation exposure pathway measures environmental radiation doses by use of themioluminescent dosimeters (TLDs). TLD results have renuined essentially the same since the preoperational period in 1977.
During 1995, as in previous years, operation of the North Anna Nuclear Power Station created no adverse environmental affects or health hazards. The maximum radiation dose calculated for a hypotheticalindividual at the North Anna Power Station site boundary due to liquid and gaseous effluents released from the site during 1995 was 0.30 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-nude sources. Natural sources in the environment provide approximately 82%
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of radiation exposure to nun while Nuclear Power contributes less than 0.1%. These results
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denmnstrate not only compliance with federal and state regulations, but also demonstrate the adequacy of radioactive effluent control at the North Anna Nuclear Power Station.
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Virginia Electric And Power Company O,
North Anna Power Station l
Radiological Environsnental Operating Prograrn L Introduction The operational Radiological Environmental Monitoring Progmm (REMP) conducted for the year 1995 for North Anna Power Station is provided in this repon. The results of measurements and analyses of data obtained from samples collected from January 1,1995 through December 31,1995 are summarized.
j A. The Nonh Anna Power Station of Virginia Electric and Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles southwest of Fredericksburg, Virginia. The site consists of two units, each with pressurized water reactor (PWIU nuclear steam supply systems and turbine generators fumished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 970 megawatts electric (MWe). Unit 1 achieved commercial operation onjune 6,1978, and Unit 2 on December 14,1980.
IL The United States Nuclear Regulatory Commission (USNRC) regulations (10 CFR
/N 50.34a) require that nuclear power plants be designed, constructed, and operated to b
keep levels of radioactive material in effluents to unrestricted areas As Low As is Reasonably Achievable (ALARA). To ensure these criteria are met, the operating license for North Anna Power Station includes Technical Specifications which address the release of radioactive effluents. Inplant monitoring is used to ensure 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 Virginia Power's Station Administrative Procedure VPAP-2103, Offsite Dose Calculation Manual (ODCM).
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 repons of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared to control levels, which vary with time due to such extemal events as cosmic ray bombardment, weapons test fallout, and seasonal 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 to data collected during the operational phase to assist in evaluating any radiological impact of plant opemtions.
p D. Occasionally samples of environmental media show the presence of man-made V
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 10
l level concentrations listed in the USNRC Regulatory Guide 4.8 and Nonh Anna Power p
Station's ODCM. These concentrations are based upon the annual dose commitment recommended by 10 CFR 50, 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 1991 and satisfies the following objectives of the program:
- 1. Provides 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. Supplements the mdiological effluent monitoring program by verifying that radioactive effluents are within allowable limits.
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- 3. Identifies radioactivity changes in the environment.
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- 4. Verifies that the plant operations have no detrimental effect on the health and safety of the public.
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II. Nuclear Power And The Environsnent:
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In Perspective Coal, oil, n,ttural gas nuclear power, and 11ydropower ha\\ e all heen used to run the nation's electric generating stations. Each method, however, has its drawbacks. Coal-fired power can damage the environment during the mining process, or by airborne discharges such as fly-ashand chemicals which contribute to acid rain.. Oil and natural gas are costly because of their limited supply. Few suitable sites for hydropower exist. and building the large dams necessary to i
produce liydropower has a significant impact on the environment.
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, hundreds of acres adjoining Suny Power Station are a state waterfowl refuge, and Lake Anna, next to North
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Anna Power Station, is a well-known fishing site with a state park on its shore.
In order to more fully understand this unique energy source, hackground information about basic radiation characteristics, risk assessment, reactor operation, efDuent control, environmental monitoring, and radioactive waste is provided in this section.
Fundamentals The Atom j
0V 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. The proton, however. has a positive charge, while the neutron has no charge, it i.s electrically neutral. Figure 1 presents a simple diagram of an atom.
/' Protons g
/
Electron /y
/
Positive Charge Negative Charge Nucleus Neutrons g
Neutral Charge l
l Isotopes p
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The number of protons in the atom of any specific element is always the same. For example, all hydrogen atoms has e one proton whereas all oxygen atoms has e eight protons. I'nlike protons.
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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 lists the isotopes
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of uranium.
Isotopes Symbols Number Number ofProtons ofNeutrons i
Uranium-235 2"U 92 143 i
Uranium-236 2*U 92 144 Uranium-237 2rU 92 145 Uranium-238 2*U 92 146 Uninium-239 2wU 92 147 Uranium-240 2*U 92 148 Table 1. Uranium Isotopes Radiation and Radioactivity Radionncildes bb Normally, the parts of an atom are in a balanced or stable state. A small percentage of atoms naturally contain excess energy and therefore are not stable atoms. If the nucleus of an atom contains excess energy, it may be called a radioactive atom, a mdioisotope, 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 umnium-238, thorium-232 and potassium-40, or man-made, such as iodine-131, cesium-137, and cobalt-60.
Radioactive Decay Itadioactive atoms attempt to reach a stable (non-radioactive) state through a process known as radioactive decay. Itadioactive decay is the release ofenergy from the atom through j
the emission of paniculate and/or electromagnetic radiation. Paniculate radiation may be in the form of electrically charged panicles such as alpha (2 protons plus 2 neutrons) or beta panicles (1 electron), or may be electrically neutral, such as neutrons.
Pan of the electromagnetic spectrum consists of gamma rays and X-rays which are similar to light and microwaves, but have a much higher energy.
Ha(fLife 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.
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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.
During the decay process, several daughter products may be funned which eventually transfonn j
into stable atoms. Naturally occurring radium-226, for example, has 10 successive daughter products (including radon) resulting finally with lead 206 as a stable form.
1 Types OfRadiation Tu o types of radiation are considered in the nuclear industry, particulate and electromagnetic. Particulateradiation may come from the nucleus of an atom in the form of an ejected alpha particle. As shown in Figure 2, alpha particles con-i sists of two protons together with two O
neutrons.
':g 2 Protrons
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, 2 Neutrons Alpha particles have a very limited xcses ability to penetrate matter. A piece of paper will stop all alpha radiation. For this reason, alpha radiation from sources out-side the body are not considered to be a radiation hazard.
Figure 3 shows how the beta particle is like an electron that has been ejected r<
3 from the nucleus of an atom. Skin or a thin g
piece of aluminum will stop beta radia-N g,'
y tion. Exposure to beta radiation can be a hazard to the skin or lens of the eye.
4
>1 Neutron transforms to 1 Electron (ejected beta)+
llecause of their limited ability to pen-1 Protron (in nucleus) s etrate the body, beta and alpha xes 7 radiation are a health concern primarily gM if alpha 01 beta emitters are swallowed or inhaled where they might cause internal radiation exposure.
Gamma rays are like X-rays. except that they come from the nutleus of an atom w hile E rays ( ome from the electron j
rings ( Fi,gure a N..
f N
Gamma rays can penetrate deeI) into Electrornagnetic the body and thus give a "whole-body'.
r radiation indistinguishabie radiation dose. Several inches of concrete from x-rays l
7 ead will stop both gamma and X-rays.
,c, hgure, show s the approximate penetrat-9
- 4. Gamma Ray ing ability of various types of radiation.
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u = Alpha F
[1 = Beta L.
y = Gamma N
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E g-usW l;
52052" y Il e,gA R
,gan pygrant pd
,pe 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 aluminum, and gamma radiation by severalinches of concrete or lead.
ga ure 5. The Penetr ~ ig Ab l of Various Types of Ra-Quantities And Units OfRadioactive Measurement Several quantities and units are used to describe nidioactivity and its effects. In the following sections two tenus, rem and activity, will be used to describe amounts of mdiation.
Item measures the potential effect of mdiation exposure on human cells. Small doses are counted in millirem. lhich millirem is equal to one thousandth of a tem (Figure 6). Federal sandards limit exposure for an individual member of the public to 100 millirem annually, compared with the average 300 millirem received fann natural sources and approximately 60 millirem from medical applications.
Il 1 milkmeter 1 milkrem L" A " A " "# ".=" " "=m" "
"l "l "#
~~" :A'"A" ::~:::::::A"
_p.u.onja aim;un,u uju,,nuj,u,u7oun7: no nunmjac,w L" A,," :. A," : : : : : : : : : : A,,," : : '"
100 200 300 00 500 600 700 Boo 900 7
",,~2.",,.,"." :. ",.
7,,
.=,
- =,,.,.,.,,".
"a.
vc< w ne snoe te sca e T :::::::::::::::::"Za Just as 1000 milimeters
?::::::::::::::::::::a
- - = = = = = = = = = = = = - - = = - = = = - - - = =
equals 1 meter 1000 millirem equals 1 rem KC561A 2 '
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u = Alpha
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ly p = Beta
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y = Gamma Radioactive Material Paper Aluminum Concrete
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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 aluminum, and gamma radkttion by severalinches of concrete or lead.
Ma ure 5. The. Penetrating Abi of Various Types of Ra.
Quantities And Units OfRadioactive Measurement Several quantities and units are used to describe radioactivity and its effects. In the following sections two tenus, rem and activity, will be used to describe amounts of radiation.
Rem measures the potential elTect of mdiation exposure on humaticells. Small d(>ses are counted in millirem. Each millirem is equal to one thousandth of a rem (Figure 6). Federal standards limit exposure for an individual member of the public to 100 millirem annually, compared with the average 300 millirem received from natural sources and approximately 60 millirem from medical applications.
Il 1 millimeter 1 milbrem L"::::: :* M :" :M.~.9
- : : : M :.* M : : : : : : : : : a".%
" " l1._" M_ _ : : M,,,: : : : : : ~ a,".1,
,.uiou ma mpma7.uuup;.mopo, 7 m o.,op,m o ap o o.og u.u 100 200 390 400 500 600 700 800 900 7."
7 * " "
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".".".I mc w e uo sca.
_,.,,_g.,_,,,,,,,,.,,.,.,.,,.
7 :::::::::::::::::::
7 :::::::::::.* ::::::aa T::::::::::::::::::
= = = ===. - = = = = = = = = - = = =:=:=a Just as 1000 milimeters
=
equals 1 meter 1000 millirem equals 1 rem KC8A1 A
'It Comparison 15
s Activity is the number of nuclei in a 1 cune sample that disintegrate (decay) every J
second. Each time a nucleus disinte-grates, radiation is emitted. As depicted
_ d-x___=___-_-_=_-___ _-__
in Figure 7, the unit of_ activity is the s s s p-33i32--0 I;::
curie. A Curie (Ci) is the amount of radioactive material which decays at a
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rate of 37 billion atoms per second.
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Smaller units of the Curie are ollen j :::::[: !
1 Curie used. Two common units are the j ::]:',:-
j microcurie (uCi), one millionth of a 7::
l Curie, and the picocurie (pCi), one CD J
trillionth of a Curie. A Curie is a mea.
10 Tons of Thorium-232 1 Gram of Radium 226 (radiation source)
(radiation source) surement 01 radioactivity, not a quan-a tity of material. The amount of material 0"* 9'"* $,Yfh approximateY1 curie o
necessary to make one Curie varies. For example, one gram of radium-226 is
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one Curie of radioactivity, but it would take 9,170,000 grams (about 10 tons) of thorium-232 to obtain one Curie.
Sources OfRadiation 4
e ne average annual dose equivalent to persons in the United States from background and man-5 made sources is shown in Figure 8.
Backgmund Radiation Radiation is not a new creation of the nuclear power industry; it is a natural occurrence on the canh. 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 conunon sources of radiation contribute to the natural background radiation that we are exposed to each day.
The canh is constantly showered by a steady stream of high energy ganuna rays. These rays come from space and are 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. At high ahitudes. the air is thinner and provides less protection from cosmic radiation. Itecause of this, people living at higher altitudes or es en thing in an airplane are exposed to more radiation.
Radioactive atoms commonly found in the atmosphere as a result of cosmic ray interactions include iner\\ llium
( atik >n-l 1, If iliunt, and M)dium-22.
Other natural sources of radiation include radionuclides naturally found in soil, water, food, building materials and even people. People have always been radioactise, in part because the car hon found in our bodie.s is a mixture of all carbon isotopes, both non-radioactive and radioactive.
Approximately two-thirds of the whole body dose from natural sources is contributed by Radon gas. About one-third of the naturally occuring external terrestrial and internal w hole body radiation s
dose is attributable to a naturally radioactise isotope of potassium, potassiuman.
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Man Made i
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>""<'i>""i" ">'"<"iir"ce"<<i"x<>a>>ti"".ne"nie"<e"is"exn"'eut" m"" -"ae<"at"'<"#-
The largest sources of these exposures are from medical X-rays, fluoroscopic examinations, j
radioactive drugs, and tobacco. Small doses are received from consumer aroducts such as television, smoke alarms, and fenilizers. Very small doses result from the prot uction of nuclear i
I power. Fallout from nuclear weapons tests is another source of man-made exposure. Fallout i
radionuclides include strontium-90, cesium-137, carbon-14, and tritium.
ij Man-Made Sources
)
Nuclear Power (0.1%)
edical X-rays (60 9%
sceHaneous (0.1*,'o)
Occupational (1.4%)
)
nsumer Goods (15.6%)
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1 f
her Medical (21.9%)
Man-Made 4
Medical i
Natural And Man-Made Sources Diagnostic X-Rays 39.00 1
Other Medical 14.00 i
Consumer Products 5.00 to 13.00 i
Occupational 0.90 Miscellaneous Environmental 0.06 l
Nuclear Power 0.05 adon
.6%)
atural Background I
Radon and Radon Daughters 200.00 Cosmic Rays 27.00 an-Ma 7.8 Cosmogenic Radiation 1.00 Terrestnal Radiation 28.00 j
internal Radiation 40.00 l
i j
Y, Total 360.00 MREM Per Year
[,j.[f]h Internal (11.1%
1 i
Terrestnai (7.8 c.
osmic a s (7.8%)
??$0"&tateY $$2r"eY$bOI5SY s
4 O m=EiFM 17
Effects OfRadiation 1
O Studies i
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 oflaboratory animals that were exposed to radiation under controlled conditions. It has proven difficult, however, to relate the biological effects ofirradiated laboratory animals to the potential health effects on humans. Because of this, human populations irradiated under various circum-J stances have been studied in great depth. These groups include:
Suivivors of the atomic bomb.
Persons undergoing medical radiation treatment.
Radium dial painters during World War I who ingested large amounts i
of mdioactivity by " tipping" the paint brushes with their lips.
Umnium miners, who inhaled large amounts of radioactive dust while mining i
pitchblende (uranium orel Early radiologists, who accumulated large doses of radiation from early X-ray equipment while being unaware of the potential hazards.
i Analysis of these groups has increased our knowledge of health effects resulting from large j
radiation doses. 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 l
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 i
Since the actual effects of exposure to low level radiation are difficult to measure, scientists ohen refer to the possible risk involved. The problem is one of evaluating alternatives, of d
comparing risks and weighing them against benefits. People make decisions involving risks every day, such as deciding whether to wear seat belts or smoke cigarettes. Risks are a pan of everyday life. The question is to determine how great the risks are.
We accept the inevitability of automobile accidents. lluilding safer cars or wearing seat belts will reduce the risk of injury. You could choose to not drive to be even safer, but pedestrians and bicyclists are also injured by cars. Reducing the risk of injury from
- A automobiles to zero requires moving to a place where there are no automobiles.
,! U 18
t While accepting the many daily risks of living, some people feel that their demands for O
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.
liccause you cannot see, feel, taste, hear, or smell radiation, it is often 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 witb 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 9 shows a number of different factors that decreased our average life expectancy.
Days Activity 2500 -
- 1. Smoking 1 Pack of Cigarettes a Day
- 2. Being 20% Overweight
- 3. Coristruction
---~--
- 4. Agriculture 1500 -
- 5. Auto Accidents
- 6. Avg Alcohol Consumption per Person 1000 -
- 7. Home Accidents
- 8. AllIndustry Hazards 500 -
- 9. Radiation Dose of 6.5 Millirem per Year for 30 Years NCRPReport No 95, *Radate Esposure of he U S.
0-Pmulata from Conswner Prod > cts and Miscellaneous I
Sources.* Nabonal Counct on Radabon Protection and n
1 2
3 4
5 6
7 8
9 Measurenwnts. O Dec t987. Bemesda. MO 2m KC562 The American Cancer Society estimates 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 ofIhem will develop cancer. If each person were to receive a radiation exposure ofone rem in addition to natural background radiation, then it is expected flut tbree mot e may des clop cant er during iheir lifetime. This increases t he risk from 30 percent Io 3n 03 percent. llence, the iisks of radiation exposure are snull when compared to the risks of es eryday 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 l
for judgment, you can decide what to do or what not to do.
19
4 Nuclear Reactor Operation O
Eleuricit y in the United States is being pn >duced using fossil fuel, uraniu o 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 hssion 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.
Nuclear Fuel Uranium (l D is the basic ingredient in nuclear fuel, consisting of U-235 and U-238 atoms.
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 1
to increase the U-235 concentration is known as enriclunent.
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/
7 1 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 10).
1 Reactor Vessel
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Fission O
o V
Nuclear energy is pnxtured by a process called fission. Fission occurs g
a 9
p in a reactor w hen uranium is split into Y-f ragments producing heat and teleas-
'.we ing neutrons. These neutrons strike d
of het uranium atoms, causing them to do split (fission) and release more heat tg ~
and neutrons. This is called a chain teaction ( Figure 11 ) and is controlled
$ Heavy Atom o Free Neutron by the use of reactor control rods.
9 Fission Fragment w Heat Control rods are an essential part of the nuclear reactor. Control rods i
contain cadmium, indium, and silver metals w hich 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 insened completely into the core. When the control rods are withdrawn, the chain reaction begins and heat is generated.
Design & Operation i
Surry Power Station and North Anna Power Station use a Pressurized Water lleactor (PWR) l system to generate electricity. There are two complete and independent PWil systems on-site at both Surry and North Anna Power Stations. These are referred to as Unit-1 and Unit-2.
The reactor core is inside a large steel container called the lleactor 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 (609F), but because it is under such high pressure,2235 pounds per square inch ( psi), it doesn't boil. The hot waterihen flows io the steam generator. The steam generator is a heat exchanger. Iteactor 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 tl.e steam generator is under much less pressure. and the heat boils the secondary water to steam. At Virginia Electric and Power stations. c.u h unit has.4 steam generators.
The steam is piped to a steam turbine that tums an electric generator. The exhausted sicam from the tmbine is cooled and com crted 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 Suny's case the
, lames !tiver panides 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.
Figure 12 is a diagram of typical nuclear reactor systems.
21
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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 i
shielding to absorb radiation and prevent its escape. Second, strong, ainight walls called containment, are used to prevent the escape of radioactive materials.
The reactor pressure vessel and the containment building that houses it are enonnously strong (Figure 13). Strong enough, in fact, to withstand a direct hit from a jet airliner. The reactor core lies within a sealed pressure vessel.1.ike all boilers its walls must be very strong because the water inside must be kept under ligh pressure. The reactor pressure sessel in a notlear pow er plant is es en heas ier than :.n ordinary stean, boiler because of the need to minimize the chant e of rupture and relene of any radioactis e mateiials. The reactor pressure cessel is made from a stainless steel alloy 6 to 8 inches thick Around the reactor pressure vessel is a thick concrete w ll. This wall acts as shielding, protecting workers by absorbing radiation resulting from the nuclear chain reaction. Next an
]
airtight 1/2 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.
22
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i Finally, the building's reinforced concrete outer wall is el 1/2 feet thick tapering to 21/2 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 eanhquakes and even the direct impact from a large
]
commercial jet aircraft.
Operating the Reactor Safely Accittents The most serious accident that could happen in a nuclear power plant invoh es 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 O
reactor core to remove heat. Circulation could be lost if a combination of pipes burst, for example. Conceivably, a dry, overheated reactor core iuuld melt through the pressure vessel.
23
The reactor itself is designed to respond automatically to such an emergency. Operators f]
are also trained to make corrections for any system failure. The automatic and operator U
responses have twn goals: to prevent damage to the reactor, and prevent the release of radiation. Shutting the reactor down is relatively easy. Control rods are inserted in the core and chemicals are injected into the coolant to stop the nuclear reaction. Losing the ccx>lant itself tends to stop the chain reaction beca use 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 (ECCSL The ECCS consists of prinury and back-up 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 certified by the United States Nuclear Regulatory Commission (NRCL (v
Safety Statistics Job safety is another measure of assurance that the station is being properly operated. Surry Power Station attaiwd 6,000,000 man hours without a lost time accident and is continuing that record into 1996. North Anna Power Station has attained over 4,000,000 man hours without a lost time accident.
Sumanary 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.
Radution 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 ere 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.
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A nuclear reactor has many different back-up safety systems designed so that if one fails another is available.
24
III.
SAMPLING AND ANALYSIS PROGRAM O
A.
Sampling Program 1.
Table 2 summarizes the sampling program for North Anna Power Stadon during 1995. Figure 1 indicates the locadons of the environmental monitoring stations.
2.
For roudne TLD measumments, two dosimeters made of CaSO4:Dy in a teflon card am deployed at each sampling location. Seseral TLDs am co-located with hTC and Commonwealth of Virginia direct radiadon mcording devices. These are indicated as "co-locadon" samples.
3.
In addidon to the Radiological Environmental Monitoring Program required by North Anna Technical Specifications, Virginia Electric and Power Company (VEPCO) 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 Brown Engineedng located in Westwood, New Jersey.
4.
All samples listed in Table 2 are taken at indicator locanons except those labeled
" control".
O 25
O O
O TABLE 2 (Page I of 5)
North Anna Power Station - 1995 RADIOLOGICAL SAMPilNG STAlIONS DISTANCE AND DIRECTION FROM UNIT NO. I
~
Distance Compass Collection Semple Media Location Station Miles Direction Desrees Frequenev Remarks Eavironmental NAPS Sewage 01 0.20 NE 42*
Quarterly On-site, State Split TI ermolumineseent Treatment Plant
& Annually Dosimetry (TLD)
Fredericks IIall 02 5.30 SSW 225*
Quaterly State Split
& Annually Mineral,Va 03 7.10 WSW 243' Quarterly
& Annually Wares Crossroads G4 5.10 WNW 287*
Quarterly State Split
& Annually Route 752 05 4.20 NNE 2[F Quarterly
& Annually Sturgeon's Creek 05A 3.20 N
11' Quarterly Marina
& Annually levy, VA 06 4.70 ESE I15' Quarterly State Split, Co-location
& Annually Bumpass, VA 07 7.30 SSE 167' Quarterly State Split
& Annually End of Route 685 21 1.00 WNW 301' Quarterly Exclusion Boundary
& Annually State Split.Co-imcation y
Route 700 22 1.00 WSW 242' Quarterly Exclusion Boundary
& Annually State Split
" Aspen Ilills' 23 0.93 SSE 158' Quarterly Exclusion Boundary
& Annually State Split Co-Ircation Orange, VA 24 22.00 NW 325' Quaterly Control
& Annually Bearing Cooling Tower N-1/33 0.06 N
10' Quarterly On-Site Sturgeon's Creek N-2/34 3.20 N
11' Quarterly Marina Parking lot "C" NNE-3/35 0.25 NNE 32' Quaterly On-Site (on-site)
Good llope Church NNE-4/36 4.96 NNE 25' Quaterly State Split Parking lot "B" NE-5/37 0.20 NE 42' Quarterly On-Site IAe AnnaMarina NE-6/38 1.49 NE 34*
Quarterly WeatherTower Fence ENE-7/39 0.36 ENE 74' Quarterly On-Site Route 689 ENE-8/40 2.43 ENE 65' Quarterly Near Training E-9/41 0.30 E
91*
Quarterly On-Site Facility
t V) h O
I V
V TABLE 2 l
(Page 2 of 5)
North Anna Ibwer Station - 1995 RADIOLOGICAL 5AMPLING STATIONS DISTANCE AND DIRECTION FROM UNfr NO. I Distance Compass CoIIection Srmple Media Location Station Miles Direction Degrees Frequency Remaeks Environmental "Moming Glory llill" E-10/42 2.85 E
93*
Quarterly Thermoluminescent Island Dike ESE-11/43 0.12 ESE 103*
Quarterly On-Site Dosimetry (TLD)
Route 622 ESE-12/44 4.70 ESE 115' Quarterly VEPCO Biok>gy 12b SE-13/45 0.75 SE 138' Quarterly On-Site Route 701 (Dam Entrance)
SE-14/46 5.88 SE 137*
Quarterly
" Aspen flills' SSE-15/47 0.93 SSE 158*
Quanerly Exclusion Boundary Elk Creek SSE-16/48 2.33 SSE 165*
Quarterly Warehouse Compound S-17/49 0.22 S
173*
Quarterly On-Site Elk Creek Church S-18/50 1.55 S
178*
Quarterly 500 Kv Tower SSW-19/51 0.36 SSW 197*
Quarterly On-Site Route 618 SSW-20/52 5.30 SSW 205*
Quarterly NAPS Access Road SW-21/53 0.30 SW 218' Quarterly On-Site Route 700 SW-22/54 4.36 SW 232*
Quarterly m
NAPS Radio Tower WSW-23/55 0.3I WSW 237*
Quarterly On-Site Route 700 WSW-24/56 1.00 WSW 242*
Quarterly Exclusion Boundary f
(Exclusion Boundary)
[
South Gate Construction Switchyard W-25/57 0.25 W
279*
Quarterly On-Site Route 685 W-26/58 1.55 W
274*
Quarterly End of Route 685 WNW-27/59 1.00 WNW 30l*
Quarterly Exclusion Boundary
- 11. Purceirs Private Rd.
WNW-28/60
'l.52 WNW 303*
Quarterly Co4mcation North Gate Construction Side NW-29/61 0.44 NW 321*
Quarterly On-Site 12ydown Area Lake AnnaCampground NW-30/62 2.54 NW 319' Quarterly
- 1/#2 intake NNW-31/63 0.07 NNW 349' Quarterly On-Site Route 208 NNW-32/64 3.43 NNW 344*
Quarterly Bumpass Post Office C-1/2 7.30 SSE 1.67*
Quarterly Control Orange, VA C-3/4 22.00 NW 325' Quarterly Control Mineral,VA C-5/6 7.10 WSW 243' Quarterly Control Louisa. VA C-7/8 11.54 WSW 257*
Quarterly Control
O O
O TABLE 2 (Page 3 of 5)
North Anna Power Station - 1995 RADIOt.OGICAL SAMPilNG STAllONS DISTANCE AND DIREC110N FROM UNTT NO. I Distance Compass Collection Sample Media Location Station Miles Direction Degrees Frequency Remarks Airborne Particulate NAPS Sewage 01 0.20 NE 42' Weekly On-Site. State Split c6d Radiolodine Treatment Plant Fredericks Itall 02 5.30 SSW 205' Weekly Mineral.VA 03 7.10 WSW 243' Weekly Wares Crossroads 04 5.10 WNW 287' Weekly Route 752 05 4.20 NNE 2(P Weekly Sturgeon's Creek Marina 05A 3.20 N
11' Weekly levy. VA 06 4.70 ESE I15' Weekly Bumpass, VA 07 7.30 SSE 167*
Weekly End of Route 685 21 1.00 WNW 301' Weekly Exclusion Boundary Route 700 22 1.00 WSW 242' Weekly Exclusion Boundary State Split
" Aspen Ilills' 23 0.93 SSE 158' Weekly Exclusion Boundary Orange. VA 24 22.00 NW 325' Weekly Control Sxrface Water Waste IIcat 08 1.10 SSE 148' Monthly State Split Treatment Facility (Second Cooling Lagoon)
- Lake Anna (upstream) 09 2.20 NW 32tP Monthly Control, State Split (Route 208 Bridge)
- Lake Anna (upstream) 09A 12.90 WNW 295' Monthly Control (Route 669 Bridge)
River Water North Anna River 11 5.80 SE 128' Monthly (downstream)
Ground Water Biology lab OIA 0.75 SE 138' Quarterly State Split (Well Water)
Precipitation Biology Lab OIA 0.75 SE 123*
Monthly Aquatic Sediment Waste IIcat 08 1.10 SSE 148*
Semi-Annually State Split Treatment Facility (Second Cooling Lagoon) 1 Lake Anna (upstream) 09 2.20 NW 320*
Semi-Annually Control. State Split North Anna River 11 5.80 SSE 128' Semi-Annually (Downstream) 3 In October 1991 the Surface Water Sample location at station 09 was moved to 09A.
O O
O TABLE 2 (Page 4 of 5)
North Anna Power Station - 1995 RADIOI.OGICAL SAMPLING STA110NS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Compass Collection Srmple Media Location Station Miles Direction Degrees Frequency Remarks Shorelinr Soil I.ake Anna (upstream) 09 2.20 NW 320' Semi-Annually State Split (Route 208 Bridge)
Soil NAPS Sewage 01 0.20 NE 42' Once/3 years On-Site Treatment Plant Fredericks 11a11 02 5.30 SSW 205*
Once/3 years Mineral.VA 03 7.10 WSW 243' Once/3 years Wares Crossroads 04 5.10 WNW 287*
Once/3 years Route 752 05 4.20 NNE 2(F Once/3 years Sturgeon's Creek Marina 05A 3.20 N
11' On:c/3 years Irvy, VA 06 4.70 ESE I15' Once/3 years Dumpass. VA 07 7.30 SSE 167*
Once/3 years End of Route 685 21 1.00 WNW 30l*
Once/3 years
' Exclusion Boundary Route 700 22 1.00 WSW 242*
Once/3 years Exclusion Boundary (Exclusion Boundary)
- Aspen Ilills" 23 0.93 SSE 158' Once/3 years Exclusion Boundary r
Orange. VA 24 22.00 NW 325' Once/3 years Control Milk IIolladay Dairy 12 8.30 NW 310*
Monthly State Split (R.C. Goodwin)
Terretrs Dairy 13 5.60 SSW 205*
Monthly State Split (Fredericks Itall)
Fish * *
- Waste llent 08 1.10 SSE 148' Semi-Annually State Split Treatment Facility (Second Cooling Lagoon)
Lake Anna (upstream) 09 2.20 NW 320*
Semi-Annually State Split (Route 208 Bridge)
Lake Orange
- 25 16.5 NW 312*
Semi-Annually Control Food Products Route 713 14 1.20 NE 43*
Monthlyif available (Broadleaf or at harvest Vegetation)
Route 614 15 "
1.70(1.37)
SE 133' MontNyif available or at harvest Added as result of 1990 Quality Assurance Audit.
Imcation changed as a result of 1991 Land Use Census to garden at 137 miles October 1991.
Fish sample no longer obtamed at station #09.
O O
O TAELE 2 (Page 5 of 5)
North Anna Ibwer Station - 1995 RADIOLOGICAL SAMILING STAllONS DISTANCE AND DIRECTION IROM UNIT NO. I Distance Compass Collection Srmple Media Location Station Miles Direction Degrees Frequency Remarks -
Food Products Route 629/522 16 12.60 NW 314' Monthlyif available (Broadleaf or at harvest Vegetation) -
End of Route 685 21 1.00 WNW 301' Monthly if available or at harvest Aspen Itills 23 0.93 SSE 158' Monthlyif availaNe or at harvest c
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Environmental Monitoring Stations Overview Maps Map Environmental Sta Map Environmental Sta Designation identification Designation identification 1
(a) 01,NE-5/37 7/8 C-7&8 1A Ol A.SE-13/45 1/33 N-1/33 2
(a) 02,SSW-20/52 31/63 NNW-31/63 3
(a) 03,C-5/16 29/61 NW-29/61 4
(a) 04 3/35 NNE-3/35 5
(a) 5 7/39 ENE-7/39 5A (a) 05A,N-2/34 9/41 E-9/41 6
(a) 6,ESE-12/44 11/93 ESE-11/43 7
(a) 07,C-l&2 17/49 S-17/49 8
8-Water, Fish Sediment 19/51 SSW-19/51 9
09-Shoreline Soil Stations 21/53 SW-21/53 NW-30/62 9A 09A-Water sample, sediment 23/55 WSW-23/55 O
it 12-aiver water sedimeat 25/57 w-25/57 12 12-Milk 16/48 SSE-16/48 13 13-Milk 18/50 S-18/50 14 14-Vegetation, NE-6/38 14/46 SE-14/46 15 Vegetation 22/54 SW-22/54 16 Vegetation 26/58 W-26/58 21 (a) 21,WNN-27/59 28/60 WNW-28/60 22 (a) 22,WSW-24/56 32/64 NNW-32/64 23 (a) 23-SSE-15/47 8/40 ENE-8/40 24 (aXb) 24,C-3&4 4/36 NNE-40/36 25 (c) 25-Fish 10/42 E-10/42 (a) Indicates air sample station, annual and quanerly TLD, Triennial soil (b) inOrange
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B.
Analysis' Program O
1.
Table 3 summarizes the analysis program conducted by Teledyne Brown Engineering for North Anna Power Station during 1995.
i I
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!O 37
TABLE 3 (Page 1 of 3) gC NOR'III ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY AN A LYSIS LLD*
REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2mRi2mR mR/std. month Dosimetry (TLD)
(84 Routine Station TLD's) 12 Station TLD's Annually Gamma Dose 2mRi2mR mR/std. month 3
l Airborne Weekly I-131 0.07 pCi/m Radiolodine 3
Airborne Weekly Gross Beta 0.01 pCi/m Particulate 3
Quarterly (a)
Gamma Isotopic pCi/m Cs-134 0.05 Cs-137 0.06 Annually Sr-89 (c) pCi/m3 (2nd Quarter Sr-90 (c)
Composite) nU Surface Water Monthly I-131 1(b) pCill Gamma Isotopic pCi/l Mn-54 15 Fe-59 30 l
Co-58 15 i
Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly (a)
Tritium (H-3) 2000 pCi/l 2nd Quarterly Sr-89 (c) pCi/l Composite Sr-90 (c) i LLD's indicate those levels that the environmental samples should te analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed.
O (a)
Quarterly Composites of each location's samples are used for the required analysis.
(b)
LLD for non-drinking water is 10 pCi/ liter.
(c)
'Dere are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.
38
l TABLE 3 l
(Page 2 of 3)
O noarninnt eowea Sririos SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY AN A LYSIS LLD*
REPORT UNITS l
River Water Monthly I-131 1(b) pCi/l i
Gamma Isotopic pCi/l Mn-54 15 Fe-59 30 Co-58/Co-60 15 Zn-65 30 Zr-95 30 Nb-95 15 Cs-134 15 Cs-137 18 Ba-140 60 La-140 15 Quarterly (a)
Tritium (H-3) 2000 pCi/l 2nd Quaner Sr-89 (c) pCi/l Sample Sr-90 (c)
Ground Water Quarterly (a)
Gamma Isotopic pCi/l (Well Water) 2nd Quaner Mn-54 15 p
Composite Fe-59 30 O
Co-58/Co-60 15 1
Zn-65 30 Zr-95 30 Nb-95 15 I-131 1(b)
Cs-134 15 Cs-137 18 j
Ba-140 60 La-140 15 Quarterly (a)
Tritium (H-3) 2000 pCi/l 2nd Quarter Sr-89 (c) i Composite Sr-90 (c)
Aquatic Semi-Annually Gamma Isotopic pCi/kg (dry)
Sediment Cs-134 150 Cs-137 180 l
Annually Sr-89 (c) pCi/kg (dry)
Sr-90 (c)
Precipitation Monthly Gross Beta pCi/l l
Semi-Annual Gamma Isotopic pCi/l l
Composite LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Pmgram. Actual analysis of the samples by Teledyne Brown Engineering may be lower than those listed.
(a)
Quarterly Composites of each location's samples are used for the required analysis.
(b)
LLD for non-drinking water is 10 pCi/ liter.
(c)
Dere are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.
39
TABLE 3 (Page 3 of 3)
AU NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY A N ALYSIS LLD*
REPORT UNITS Shoreline Soil Semi-Annual Gamma Isotopic pCi/kg (dry)
Cs-134 150 Cs-137 180 Annually Sr-89 (a)
Sr-90 (a)
Soil Once per 3 yrs.
Gamma Isotopic pCi/kg (dry)
Cs-134 150 Cs-137 180 Once per 3 yrs.
Sr-89 (a) pCi/kg (dry)
Sr-90 (a)
Milk Monthly I-131 1
pCi/l Monthly Gamma Isotopic pCi/l Cs-134 15 f-~
Cs-137 18 d
Ba-140 60 La-140 15 Quarterly Sr-89 (a) pCi/l Sr-90 (a)
Fish Semi-Annual Gamma Isotopic pCi/kg (wet)
Mn-54 130 Fe-59 260 Co-58 130 Co-60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Monthly if Gamma Isotopic pCi/kg (wet)
(Broadleaf available or Vegetation) at harvest Cs-134 60 Cs-137 80 I-131 60 pCi/kg (wet)
Note:
' Itis table is not a complete listing of nuclides which can be detected and reported. Other 1xaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
! p)
LLIYs indicate those levels that the environmental samples should be analyzed to, in accordance with the North l
Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Brown Engineering may I
be lower than those listed.
(a)
'Ihere are no required LLD's for strontium-89/90. LLD's are those achieved by Teledyne Brown Engineering.
40
I 1
Appendix B REMP Exceptions For Scheduled 0
Sampling And Analysis During 1995 - North Anna Location Description Date of Sampling Reason (s) for Loss / Exception J
ENE-8 Direct Radiation /
03/29/95 TLD was missing from sampling location.
4 TLD ENE-40 TLD was missing from sampling location.
W-27 Surface Water 11/30/95 LLD for I-131 not met due to late receipt of sample at laboratory.
i O
41
i l
V.
Summary And Discussion of 1995 Analytical Results O
Data from the radiological analyses of environmental media collected during 1995 are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne Brown Engineering Quality Assurance Manual and are explained in the Teledyne Brown Engineering Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Appendix D. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program. Participation in this program ensures that independeat checks on the precision and accuracy of the measurements of radioactive material in environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Appendix E.
Radiological analyses of environmental medit characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods. The "less than" values in the data tables were calculated for each specific analysis and are dependent on sample size, detector efficiency, length of counting time, chemical yield, when appropriate, and the radioactive decay factor from time of counting to time of collection. Teledyne Brown Engineering's analytical methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position, Radiological Monitoring Exceptable Program (November 1979, Revision 1) and the ODCM.
The following is a discussion and summary of the results of the environmental measuremen's taken during the 1995 reporting period.
A.
Airborne Exposure Pathway 1.
Air Iodine /Particulates Charcoal cartridges used to collect airbome iodine were collected weekly and analyzed by gamma spectrometry for iodine-131. The results are presented in Table B-1. All results were below the required lower limit of detection. For air particulates, gross beta activity was observed in all fifty-three control samples with an average concentration of 0.020 pCi/m3 and a range of 0.009 to 0.033 pCi/m3. The average measurement for the indicator locations was 0.019 pCi/m3 with a range of 0.004 to 0.031 pCi/m3. The results of the gross beta activities are presented in Table B-2. The gross beta activities for 1995 were comparable to levels measured in the 1982-1994 period. hior to that period the gross beta O
activitie were higher due to atmospheric nuclear weapons testing performed in other 42
(
TRENDlHG GRAPH-1: GROSS BETA IN AIR PARTICULATES i
O.1.
4 I
l E 0.01+ - - - - - - - - - - - - - - - - - - - - - -
I--
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On t
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,,nnnnnoin,unnnnoinnno,nnou,,nnnnnnn,nnn,nnn,nnnon,n,n n,nnn,,n n,
1986 1987 1988 1989 1990 1991 1992 1993 1994 1995
--m-Control-Sta-24
--o-Indicator
-A Average Pre op
-+
Required LLD's O
TRENDING GR APH 2: TRITIUM IN AlVER WATER-STATION 11 10000.
=
=
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.4 1000 g
kIz 100-k B
- i 10
Oa 1
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i 2
1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 d Tritium
- + - Required LLD's O
During the preoperatonal period, tritum was not detected in the samples analyzed j
43
countries. During the preoperational period of July 1,1974 through March 31,1978 gross O
beta activities r nged from a low of 0.005 pCi/m to a high of 0.75 pCi/m3, 3
Air particulate Elters were composited by locations on a quanerly basis and were analyzed by gamma ray spectroscopy. The results are listed in Table B-3. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation, was measured in all 48 composite samples. The average measurement for the control location was 0.071 pCi/m3 with a range of 0.050 to 0.079 pCi/m3. The indicator locations had an average concentration of 0.070 pCi/m3 and a range of 0.048 to 0.088 pCi/m3. During the preoperational period, beryllium-7 was measured at comparable levels, as would be expected. Naturally occurring potassium-40 was detected in two control samples with an average concentration of 0.005 pCi/m3 and a range of 0.004 to 0.006 pCi/m3. Potassium-40 was detected in eleven indicator samples with an average concentration of 0.011 pCi/m3 and a range of 0.003 to 0.030 pCi/m3. All other gamma emitters were below the detection limits. During the preoperational period gamma ray spectroscopy measured several fission products in numerous air particulate filters. All isotopes were attributed to atmospheric nuclear weapons testing conducted before the preoperational period. Among the isotopes measured were zirconium-95, ruthenium-103, ruthenium-106, cesium-137, cerium-141 q
and cerium-144.
v The second quarter composites of air particulate filters from all twelve stations were analyzed for strontium-89 and 90. There was no detection of these fission products at any
]
of the eleven indicator stations nor at the control station.
i 2.
Precipitation A sample of rain water was collected monthly at station Ol A, on site,0.75 miles,138 degrees SE and analyzed for gross beta activity. The results are presented in Table B-4.
The average gross beta activity for 1995 in the twelve samples was 4.34 pCi/ liter with a range from 0.86 to 13 pCi/ liter. Semi-annual composites were prepared and analyzed for gamma emitting isotopes and tritium. Beryllium-7 was measured in one sample with a concentration of 61.5 pCi/ liter. All other gamma emitters were below their detection limits.
Tritium was not detected in the semi-annual composite samples. These results were comparable to or lower than those measured in 1986 thru 1994. During the preoperational period gross beta activity in rain water was expressed in nCi per square meter of the collector surface, thus a direct comparison can not be made to the 1995 period. During the n
44
preoperational period, tritium was measured in over half of the few quarterly composites O-made. The tritium activity ranged from 100 to 330 pCi/ liter.
l 3.
Soil Soil samples which are collected every three years from twelve stations, were collected in July and analyzed by gamma ray spectroscopy. The results are presented in Table B-5.
Naturally occurring potassium-40 was detected in all twelve samples with an average activity of 11588 pCi/kg (dry weight) and a range of 3820 to 23100 pCi&g (dry weight).
Beryllium-7 was measured in one sample with an activity of 1090 pCi/kg (dry weight).
The terrestrial nuclide radium-226 was monitored in ten samples with an average activity of 2083 pCi/kg (dry weight) and a range of 798 to 2900 pCi/kg (dry weight). Thorium-228 also naturally occurring was detected in all samples with an average activity of 1233 pCi/kg (dry weight) and a range of 335 to 2020 pCi/kg (dry weight). The fission product cesium-137 was detected in nine of the twelve samples at an average activity of 342 pCi/kg (dry weight) and a range of 58.5 to 767 pCi/kg (dry weight). The cesium-137 is attributed to past atmospheric nuclear weapons testing. Cesium-137 was not detected in the sample from station 24, the control station.
O The twelve soil samples were analyzed for strontium-89 and strontium-90. There were no detections of strontium-89. Strontium-90 was detected in five of the twelve samples with an average activity of 105 pCi/kg (dry weight) and a range of 68 to 170 pCi/kg (dry weight). These fission products occurred in previous years and are believed to be from j
atmospheric nuclear weapons testing in previous years.
B.
Waterborne Exposure Pathway 1.
Ground /Well Water Water was sampled quarterly from the on site well at the metrology laboratory. These samples were analyzed for gamma radiation and for tritium. The results are presented in Table B-6. No gamma emitting isotopes or tritium were detected during 1995. The second quarter sample was analyzed for strontium-89 and strontium-90. There were no detections of these isotopes above the detection level. No gamma emitting isotopes were detected l
during the preoperational period. Tritium was measured in most of the samples during that period with concentrations between 80 and 370 pCi/ liter.
l
!O i
45
1 l
2.
River Water lO A sample of water from the North Anna River was collected monthly at station 11,5.8 miles downstream from the discharge lagoon,128 degrees SSE. The results are presented in Table B-7. The samples were analyzed by gamma spectroscopy monthly. The samples were analyzed for tritium quanerly on a composite sample. The second quarter samples were analyzed in addition for strontium-89 and strontium-90.
Potassium-40 was not measured during 1995 and all other gamma emitters were below the detection level. No detections of strontium-89 or strontium-90 occurred. Tritium was measured in all four samples with an average level of 2825 pCiAiter and a range of 2100 to 3600 pCiAiter. This is slightly higher than the average level measured in 1994 of 2400 pCiniter and a range of 1800 to 3100 pCiniter. No river water samples were collected during the preoperational period.
I 3.
Surface Water Samples of surface water were collected monthly from two stations. Station 08 is at the discharge lagoon,1.1 miles,148 degrees SSE on Lake Anna. Station 09A is located 12.9 C
miles WNW. The samples were analyzed for iodine-131 by radiochemical separation. No iodine was detected in the 24 samples analyzed. The results are presented in Table B-8.
The samples were also analyzed by gamma ray spectrometry. No gamma emitters were below their detection levels at both station.
A quarterly composite from each station was prepared and analyzed for tritium. The tritium activity at station 08 for the quarterly composites was at an average level of 2775 pCiAiter with a range of 2100 to 3300 pCiditer. The tritium level had been increasing since the middle of 1978 when the average level was below 300 pCiAiter. However, during 1995 the results were within the same range as those measured in 1986 thru 1994. During the preoperational period tritium was measured in several samples with concentrations between 90 and 250 pCihiter. Tritium was not detected at station 09A.
Samples of surface water were collected by the Commonwealth of Virginia from two stations. Station W-33 is located at the discharge lagoon while station W-27 is located on the North Anna River at the RT. 208 Bridge, which is upstream of the site. Twenty-four samples were collected and analyzed by gamma ray spectroscopy. The results are presented in Table B-9. All gamma emitters were below their detection levels.
i 46 l
l TREND!NG GR APH - 3: TRITIUM IN SURFACE W ATER - ST A 08 r
10000
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_________A 100 1/77 1/78 1/79 1/80 1/81 1/82 1/83 1/84 1/85 1/86 1/87 168 1S9 160 161 1S2 163 164 165
--G-Tntum
-4 Required LLD's
--A Average Pre-op Unit 1 cdtical on 06K)6/78. Unit 2 critical on 12/14/80.
AU TRENDING GRAPH -4: COB ALT-58 IN SEDIMENT SILT 1000 E
100 -
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i 03/85 03S6 04S7 03/88 04/89 03SO 03S1 03S2 03S3 10S3 08S4 865 0) 1 b
l During the preoperational period, cobalt-58 was not detected in the samples analyzed.
. Staton-8
-+-- Station-09 Control Sta-09A
-+- Station-11 47
Four samples from each station were analyzed for tritium during 1995. The average O
activity at station W-33 in all samples was 3075 pCi/ liter with a range of 2200 to 4200 pCi/ liter. This is slightly higher than the 2600 pCi/ liter measured during 1994 at this station. Tritium was measured in three samples at station W-27 with an average activity of 1033 pCi/ liter and a range of 300 to 1500 pCi/ liter. This is lower than the average of 1510 pCi/ liter measured at station W-27 during 1994.
C.
Aquatic Exposure Pathway 1.
Sediment / Silt Sediment samples were collected during March and Augus' lom each of three locations and were analyzed by gamma spectrometry. The results are presented in Table B-10. One man-made and a number of naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in two samples with an average activity of 148 pCi/kg (dry weight) and a range from 66.2 to 229 pCi/kg (dry weight). The highest reading for cesium 137 va.s obtained from station 11 located 5.80 miles SSE.
Naturally occurring potassium-40 was observed in all six samples with an average activity of 13520 pCi/kg (dry weight) and a range from 2160 to 23700 pCi/kg (dry weight).
O Radium-226 was mea ured in five samples with an average concentration of 1113 pCi/kg (dry weight) and a range of 795 to 1590 pCi/kg (dry weight). Also naturally occurring, thorium-228 was observed in all six samples with an average concentration of 661 pCi/kg (dry weight) and a range of 348 to 1080 pCi/kg (dry weight). Cesium-137 was measured in one sample with a concentration of 66.2 pCi/kg (dry weight). The August samples were analyzed for strontium-89 and strontium-90. There were no detections of strontium-89 or strontium-90 in aquatic sediment / silt.
During the preoperational period sediment samples were analyzed by gamma ray spectroscopy. Cesium-137 was measured in most of the samples with concentrations between 33 and 1210 pCi/kg (dry weight). Strontium-90 was measured in most of the samples with concentrations between 60 and 540 pCi/kg (dry weight). Strontium-89 was not measured. Potassium-40, radium-226, and thorium-228, all naturally occurring, were measured at background levels.
O 48
i i
TRENDING GR APH - 5: COB ALT-60 IN SEDIMENT SILT I
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t; O
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03/85 03/86 03/87 0328 04/89 0300 03Si 03S2 03G3 10S3 08S4 0865 Station-8
-*- Station-09
+
Control-Sta-09A
-+- Station-11 During the preoperational period, cobalt-60 was not detected in the sarnples analyzed.
/s TRENDING GR AFH - 6: CES!UM-134 IN SEDIMENT SILT (J
1000 _
~ k A
- p 100m.
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i 03/85 03/86 03/87 03/88 0469 03S0 03G1 03S2 0363 1063 08S4 08S5 l Staton 6--
Staton-09 Control-Sta49A + Staton-11 -+- Required LLD's During the preoperational period, cesium-134 was not detected in the samples analyzed.
49 l
l TRENDING GRAPH - 7: CESIUM-137 IN SEDIMENT SILT l
10000 0
1000 j
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_ _ q E
4-E 100:
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325 326 3/87 3/88 3/89 3SO 3S1 3S2 3S3 10/93 8S4 08S5
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Station-8 Control-Sta-09A
--A Average Pte-Op
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-+
Required LLD's TRENDING GR APH - 8: CESIUti-134 IN FISH 1000_:
M 4
__________________4 E
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i i i i i i i i i i e i e i e i i i i i i i i i i i i i i i i i i i 4/80 4/82 4/84 4/85 4/8612/86 8/8712/87 6/8812/88 68910/891060106110G21063 8S4 08SS During the preoperational period, c ssium-134 was not detected in the samples analyzed.
Staton 25 replaced station 09.
-- 5 _- Stabon-08
--+-- Staton-09
- Control Sta-25
-+
Required LLD's 50
r 2.
Shoreline Soil O
A sample of shoreline sediment was collected in February and August from station 09,2.2 miles upstream of the North Anna Power Station. The samples were analyzed by gamma ray spectrometry. The n:sults are presented in Table B-11. The naturally occurring nuclide potassium-40 was measured in both samples with an average activity of 4190 pCi/kg (dry weight) and a range of 2200 to 6180 pCi/kg (dry weight). Cosmogenic beryllium-7 was measured m one sample with an activity of 466 pCi/kg (dry weight). Thorium-228 was measured in both samples at an average of 1056 pCi/kg (dry weight) and a range of 461 to 1650 pCi/kg (dry weight). Radium-226 was measured in both samples with an average activity of 1935 pCi/kg (dry weight) and a range of 1330 to 2540 pCi/kg (dry weight).
Cesium-137, a fission product, was monitored in both samples with an average level of 341 pCi/kg (dry weight) and a range of I89 to 493 pCi/kg (dry weight).
The August sample was analyzed for strontium and there were no detections of strontium-89 or strontium-90.
D.
Ingestion Exposure Pathway lO The results of the iodine-131 analysis of milk samples are presented in Table B-12. A sample was collected monthly from two stations. A total of 24 samples were analyzed during 1995. There were no measurements ofiodine-131 above the detection limits.
l l -
i The milk samples were also analyzed by gamma ray spectroscopy and the results are also l
presented in Table B-12. A total of 24 samples were analyzed. Naturally occurring i
potassium-40 was measured in all samples with an average of 1364 pCi/ liter and a range of j
1170 to 1640 pCi/ liter. The fission product cesium-137 has been detected sporadically in recent years and the tctivity has been attributed to global fallout from past atmospheric weapons testing. However, cesium-137 was not detected at levels above LLD in any milk samples during 1995. All other gar ma emitters were below their detection levels. A quarterly composite was prepared from each of the two collection stations and analyzed for strontium-89 and strontium-90. Strontiam-89 was not detected at levels above LLD in any of the samples monitored. Strontium-90 was detected in the eight samples monitored with i
an average level of 1.39 pCi/ liter aM a range of 0.96 to 2.1 pCi/ liter. This is similar to i
activities determined in previous years and lower than the preoperational levels of 2.2 to
! Q 5.4 pCi/ liter.
51 i
f
O 2.
vish Aquatic biota can be sensitive indicators of radionuclide accumulation in the environment because of their ability to concentrate certain chemical elements which have radioactive isotopes. The results are presented in Table B-13. Eight samples of fish were collected during 1995. These samples were analyzed by gamma ray spectroscopy and the naturally l
occurring isotope potassium-40 was found in all samples at an average of 1475 pCi&g (wet -
weight) with a range of 1200 to 2110 pCi&g (wet weight). The fission product cesium-137 was measured in three samples at an average of 37.2 pCi/kg (wet weight) and a range of 26.2 to 49.9 pCi&g (wet weight). During the preoperational period cesium-137 was measured in one-fourth of the fish samples collected with concentrations between 31 and 66 pCi&g (wet weight). All other gamma emitters were below their detection levels.
3.
Food / Vegetation Thirty-five food samples were collected from five locations and analyzed by gamma spectrometry. The results are presented in Table B-14. Naturally occurring potassium-40 was monitored in all 35 samples with an average activity level of 14981 pCi/kg (wet i
O weis t) and a ranse or45io to 334oo gCi/ks cwet weis t). Ce mo8enic berviiium-7 was a
n detected in 34 of the 35 samples with an average concentration of 1542 pCi&g (wet weight) and a range of 318 to 5730 pCi/kg (wet weight). Radium was measured in four samples with an average activity of 805 (wet weight) and a range of 440 to 1250 pCi/kg (wet l
weight). The terrestrial nuclide thorium-228 was detected in nine samples at an average activity of 149 pCi/kg (wet weight) and a range of 41.3 to 260 pCi/kg (wet weight).
t The fission product cesium-134 was not detected at levels above LLD during 1995.
l Cesium-137 was detected in seven samples with an average concentration of 56.2 pCi/kg (wet weight) and a range of 13.9 to 159 pCi/kg (wet weight). These results are consistent with those measured in previous years. Cesium-137 was measured in broadleaf garden vegetation during the preoperational period with concentrations between 53 and 98 pCi/kg (wet weight).
8 i
- O 52
i TRENDING GRAPH - 9: CESIUM-137 IN FISH 10000 l
- 1000, m
E y
~
_ _ _ _ _ _ _ b7 - _
t 100:
y
~
_A f
~t;
/i
,9 f/
\\/
4.
CD s /
a5 10
.. l-l l
l l
1 5/B0 5/83 4/85 8/86 7/87 4/88 12/88 10/89 10/90 10S1 4/93 8/94
--S-Staton-08
---*-- Staton-09 Staton-25
--A Average Pre-op
-+
Required LLD
~-
l Station 25 replaced station 09.
TRENDING GRAPH - 10: ENVIRONMENT AL R ADI ATON - TLD's 10
?
1 e
-A-k
^^:.
t l
2 I
l b
d.
G 82 2
0 6
tt E
l 1
i,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
1/86 1086 7/87 4/88 1/89 10/89 760 461 162 10S2 763 464 165 1065
, Environmental TLD's
--+- Sector TLD's
--A Average Pre-op O
i 53
E.
Direct Radiation Exposure Pathway
!O l
1.
TLD Dosimeters l
l Thermoluminescent dosimeters (TLDs) determine environmental radiation doses and the results are presented in Table B 14. Individual measurements of external radiation levels in l
the environs of the North Anna site had an average dose of 5.5 mR/ standard month with a range of 3.9 to 8.3 mR/ standard month. This is comparable to the preoperational range.
The control station, No. 24, had an average reading of 5.2 mR/ standard month with a range of 4.9 to 5.3 mR/ standard month.
Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location. The results are presented in Table B-
- 15. The average level of the 32 locations (two badges at each location) was 6.2 mR/ standard month with a range of 3.7 to 9.4 mR/ standard month. The eight control TLDs, collected quarterly from four locations, showed an average reading of 5.1 mR/ standard month with a range of 3.9 to 6.8 mR/ standard month. During the preoperational period (starting in 1977), when the calculation of the TLD dose included a l
correction for the in-transit dose, the doses were measured between 4.3 and 8.8
,O mR/ standard month.
l
.O 54
1 I
VI.
Conclusions The results of the 1995 Radiological Environmental Monitoring Program for the North Anna Nuclear Power Station have been presented. The following sections discuss each pathway I
individually followed by a program summary.
Airborne Exposure Pathway Air particulate gross beta concentrations of all the indicator locations for 1995 followed the gross beta concentrations at the control location. The gross beta concentrations were comparable to levels observed since 1982 except for a five week period in 1986 which was influenced by the Chernobyl accident. Gross beta concentrations in the preoperational period were highly variable, ranging from 0.0043 to 0.75 pCi/ cum, due to occasional atmospheric nuclear weapons tests.
Gamma isotopic analysis of the particulate samples identified the gamma emitting isotopes as natural products (beryllium-7 and potassium-40). There were no detections above the LLD for fission products nor other man-made isotopes in the particulate media during the first three quarters of 1995. Iodine-131 was not detected in the chamoal filters analyzed during the first three quarters of 1995.
i A precipitation sample was collected monthly during 1995 and analyzed for gross beta activity. All the gross beta activities were comparable to those measured in previous years. During the preoperational period the average gross beta activity was 0.92 pCi/ liter. Semi-annual composites were analyzed for gamma emitting isotopes and tritium. All gamma emitters were below their detection limits. Tritium was not observed above the LLD during this reporting period f
in 1995. During the preoperational period the average tritium activity was 165 pCi/ liter.
Waterborne Exposure Pathway No man-made or natural isotopes were monitored in the surface water of Lake Anna except tritium. The average tritium activity during 1995 at the waste heat treatment facility was 2775 pCi/ liter which is 14.0% of the reporting level for a water sample. In 1994 the tritium level was t
2850 pCi/ liter. The preoperational level was 150 pCi/ liter and has been rising since 1977. Tritium was not measured upstream of the site, at station 09A.
The samples of surface water collected by the Commonwealth of Virginia at the waste heat treatment facility had similar tritium results with a measurement of 2200 pCi/ liter as compared to
[
55
2237 pCi/ liter for 1994. The upstream location had three measurements at an average activity of
(]
1033 pCi/ liter as compared to 1510 pCi/ liter for 1994. No gamma emitting isotopes were detected.
River water collected from the North Anna River,5.8 miles downstream of the site had an average tritium level of 2825 pCi/ liter. The average tritium in 1994 had been 2400 pCi/ liter. No gamma emitters were detected.
Ground water from the environmental well on site contained no gamma emitters. There were also no detections of tritium in ground /well water during 1993.
Aquatic Pathway Sediment / silt samples provide a sensitive indicator of discharges from nuclear power stations. The sediment from North Anna environmental samples indicated that one man-made isotopes was present. Cesium-137 was detected in two samples at two locations. During the preoperational period, cesium-137 was measured in samples of aquatic sediment. Sediment contamination does not provide a direct dose pathway to man.
The samples of shoreline soil monitored downstream of the site contained no measurement of cesium-134. Cesium-137 was measured in both samples at an average level of 341 pCi/kg which was higher than the average of 134 pCi/kg detected in 1994.
Ingestion Pathway Iodine-131 was not detected in any of the twenty-four milk samples using the radiochemical separation method. Although cesium-137 has been detected occasionally in previous years and attributed to past atmospheric nuclear weapons testing there were no detections during 1995. Strontium-90 was measured in all eight milk samples. Strontium-90 is attributed to past atmospheric nuclear weapons testing. No strontium-89 was detected in any of the milk samples.
Naturally occurring potassium-40 was measured in all the milk samples at normal environmental levels.
Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples during 1995 showed the presence of one man-made isotope, cesium-137.
This isotope was at an activity level somewhat higher than preoperational levels but statistically similar to levels in 1987 through 1994. Only cesium-137 was measured in preoperational l
environmental fish samples. Due to primary and secondary steam generator problems experienced
(}
at North Anna during 1984/1985, a build up in ac.ivity levels both in effluents and fish did occur.
l 56
Repairs to the steam generators and better liquid waste processing have reduced these activity O
levels in effluents and thus decreased activity levels are now being observed in the fish. The average level of activity during 1995 of cesium-137 was 3.4.% of the reporting level.
Vegetation samples did not contained the man-made isotope cesium-137 during 1995.
Cesium-137 was measured during 1993 and in preoperational samples.
Direct Exposure Pathway The direct exposure pathway as measured in the environment of the North Anna site by thermoluminescent dosimetry has remained essentially the same since the preoperational period in 1977 at 6 milliroentgens per month or 0.2 milliroentgens per day. The average dose levels monitored have shown a normal fluctuation about these levels which are less than the estimated whole body dose due to natural terrestrial and cosmic radiation and the internal dose from natural radionuclides.
Program Conclusions The results were as expected for normal environmental samples. Naturally occurring i
C activity was observed in sample media in the expected activity ranges. Occasional samples of l
nearly all media showed the presence of man-made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had 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 Concentrations listed in the Offsite Dose Calculation Manual. These concentrations are based upon 25% of the annual dose i
commitment recommended by 10CFR50, Appendix 1, to meet the criterion "As Low as is Reasonably Achievable." Based upon the evidence of the environmental monitoring program the
)
station is operating within regulatory limits. Thus, no unusual radiological characteristics were 1
l observed in the environs of the North Anna Nuclear Power Station during 1995.
l l
l l
57
t VII. References O
1.
Virginia Electric and Power Company, Nonh Anna Power Station Technical Specifications, Units 1 and 2.
2.
Virginia Electric and Power Company, Station Administrative Procedum, VPAP-2103, "Offsite Duse Calculation Manual.
3.
Title 10 Code of Federal Regulation, Part 50 (10CFR50), " Domestic Licensing of l
Production and Utilization Facilities."
l 4.
United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev.1, -
l
" Calculation of Annual Doses to Man from Roudne 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.
l 7.
NUREG 0472, " Radiological Effluent Technical Specifications for PWRs," Rev. 3, l
March 1982.
l 8.
National Council on Radiation Protection and Measurements, Report No. 39, " Basic Radiation Protection Criteria," Washington, D.C., January 1971.
O.
9.
' National Council on Radiation Protection and Measumments, Report No. 45, " Natural Background Radiation in the United States," Washington, D.C., November 1975.
10.
National Council on Radiation Protection and Measurements, Report No. 93, " Radiation Exposure of the Population of the United States, Washington, D.C., December,1987.
I 1.
National Council on Radiation Protection and Measurements, Report No. 95, " Radiation Exposure of the U.S. Population from Consumer Products and Miscellaneous Soumes,"
Washington, D.C., December 1987.
12.
DOE /NE-0072, " Nuclear Energy and Electricity The Harnessed Atom," US Dept. of Energy,1986.
13.
Eichholz, G., "F.nvironmental Aspects of Nuclear Power," lewis Publishers, Inc.,1985.
14.
Eisenbud, M., " Environmental Radioactivity," Academy Press, Inc., Orlando, F1,1987.
l 15.
Fitzgibbon, W., " Energy Skill Builders, Nuclear Reactor," Enterprise for Education, Inc.,
1987.
l 16.
Glasstone, S., and Jordan, W., " Nuclear Power and its Environmental Effects," American l
Nuclear Society,1982.
- O 58
a u.,,5
)
i lO
)
l l
l 1
l C
APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
ANNUAL
SUMMARY
TABLES - 1995 l
l i
i l
l 1
i i
i lO l
l l
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1995 Docket No. 50-338/339 Page 1 of 7 AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*
Reported Sampled Total Mean Name Distance Mean Mean Nieasure-(Unit)
Type No.
Range Direction Range Range m ents Air lodine 1-131 636 0.04 -(0/583)
N/A N/A
-(0/53) 0 3
(pCi/m )
Airborne Gross 636 5
18.6(583-583) 24 22.0 mi NW 20.3(53/53) 20.3(53/53) 0 Particulates Beta (3.8-31)
(9.3-33)
(9.3-33) 3 (1E-03 pCi/m )
Gamma 48 Be-7 48 10 70.1(44/44) 02 5.130mi 74.5(4/4) 70.5(4/4) 0 (47.9-87.9)
WSW (59.9-83.0)
(49.5-78.8)
K-40 48 10 10.6(11/44) 22 1.0 mi 25.3(1/4) 4.88(2/4) 0 (2.68-29.9)
WSW (4.18-5.58)
Sr-89 12 3
-(0/11)
N/A N/A
-(0/1) 0 Sr-90 12 0.4
-(0/11l N/A N/A
-(0/1) 0 Ground Gamma 4
Well Water K-40 4
60
-(0/4)
N/A N/A
-(0/0) 0 (pCi/ liter)
Tritium 4 2000 -(0/4)
N/A N/A
-(0/0) 0 Sr 89 1
3
-(0/1)
N/A N/A
-(0/0) 0 Sr-90 1
0.4
-(0/1)
N/A N/A
-(0/0) 0 i
O 1
LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
59
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O, North Anna Nuclear Power Station, Louisa County, Virginia - 1995 Docket No. 50-338/339 Page 2 of 7 AllIndicator Controf Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*
Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)
Type No.
Range Direction Range Range ments River Gamma 12 Water (pCi/ liter)
K-40 12 200
-(0/12)
N/A N/A
-(0/0) 0 Tritium 4 2000 2825(4/4) 11 5.8 mi.SSE 2825(4/4)
-(0/0) 0 (2100-3600)
(2100-3600)
Sr-89 1
3
-(0/1)
N/A N/A
-(0/0) 0 Sr-90 1
0.4
-(0/1)
N/A N/A
-(0/0) 0 l O Precipitation Monthly (oCi/ liter)
Gross 12 4
4.3412/12) 01 A 0.2 mi.
4.34(12/12)
-(0/0) 0 Beta (0.86-13)
NE (0.86-13)
Gamma 2
(Semi-Annually)
Be-7 2
70 61.5(1/2) 01 A 0.2 mi 61.5(1/2)
-(0/0) 0 NE Tritium 2 2000 -(0/2)
N/A N/A
-(0/0) 0 Surface 1-131 24 0.5
-(0/12)
N/A N/A
-(0/12) 0 Water l
(pCi/Mer) l Regular Gamma 24 I
Monthlies K-40 24 200
-(0/12)
N/A N/A
-(0/12) 0 Tritium 8 2000 2775(4/4) 08 1.10 mi 2775(4/4)
-(0/4) 0 (2100-3300)
SSE (2100-3300) lO 1
LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
60
(
1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
'O North Anna Nuclear Power Station, Louisa County, Virginia - 1995 Docket No. 50-338/339 Page 3 of 7 AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine l
Pathway LLD*
Reported l
Sampled Total Mean Name Distance Mean Mean Wieasure-l (Unit)
Type No.
Range Direction Range Range ments Surface Sr-89 1
-(0/1)
N/A N/A
-(0/1) 0 Water (pCi/ liter)
Regular Sr-90 1
-(0/1)
N/A N/A
-(0/1) 0 Monthlies Surface Gamma 24 Water (pCi/ liter)
K-40 24 200
-(0/24)
N/A N/A
-(0/0) 0 l
State Splits Tritium 8 2000 2200(7/8)
W33 3075(4/4)
-(0/0) 0 l 0
<300-4200>
(2200-4200) l Sediment Gamma 6
l Sitt (pCi/kg K-40 6
200 12530(4/4) 11 5.8 mi 21300(2/2) 15500(2/2) 0 (dry))
(2160-23700)
SSE (18900-23700)
(12000-19000) i l
Cs 137 6
194 148(2/4) 11 5.8 mi 229(1/2)
-(0/2) 0 i
(66.2-229)
SSE l
Ra-226 6
100 1315(3/4) 11 5.8 mi 1575(2/2) 810(2/2) 0 (795-1590)
SSE (1560-1590)
(800-819)
Th-228 6
30 774(4/4) 11 5.8 mi.
1012(2/2) 435(2/2) 0 (348-1080)
SSE (943-1080)
(354-515)
Sr-89 3
4.0
-(0/2)
N/A N/A
-(0/1) 0 (Annually) l Sr-90 3
0.8
-(0/2)
NA N/A
-(0/1) 0 (Annually) 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
61 l
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 1995 Docket No. 50-338/339 Page 4 of 7 AllIndicator Control Non-Medium or AN/Alysis Locations Location with Highest Mean Location routine Pathway LLD*
Reported Sampled Total Mean Name Distance Mean Mean Measure-l (Unit)
Type No.
Range Direction Range Range ments Soil Gamma 12 (pCi/kg (dry))
Be-7 12 1090(1/11) 05A 3.20 mi N 1090(1/1)
-(0/1) 0 K-40 12 12295(11/11) 23 0.93 mi SSE 23100(1/1) 3820(1/1) 0 (4300-23100)
J Cs 134 12 100
-(0/11)
N/A N/A
-(0/1) 0 Cs-137 12 180 342(9/11) 21 1.00 mi 767(1/1)
-(0/1) 0 (58.5-767)
WNW O
Re-22e 12 100 2075(9/11) oe.2.2 mi. " w 2900(i/1) 2150(1/1) o (798-2900)
Th-228 12 30 1189(11/11) 06 2.2 mi. NW 2020(1/1) 1720(1/1) 0 4
(335-2020)
Sr-89 12 200
-(0/11)
N/A N/A
-(0/1) 0 (Annually)
Sr-90 12 40 105(5/11) 05 4.20 mi 170(1/1)
-(0/1) 0 (Annually)
(68-170)
NNE 0
1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
62 1
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1995 l
Docket No. 50-338/339 Page 5 of 7 AllIndicator Control Non-Medium or AN/Alysis Locations Location with Highest Mean Location routine Pathway LLD*
Reported Sampled Total Mean Name Distance Mean Mean Measure.
l (Unit)
Type No.
Range Direction Range Range ments Shoreline Gamma 2
Soil j
(pCl/kg Be-7 2
466(1/2) 9 2.2 mi. NW 466(1/2)
-(0/0) 0 j
(dry))
K-40 2
200 4190(2/2) 9 2.2 mi. NW 4190(2/2)
-(0/0) 0 (2200-6180)
(2200-6180)
Cs-137 2
40 341(2/2) 9 2.2 mi. NW 341(2/2)
-(0/0) 0 (189-493)
(189-493)
Ra-226 2
100 1935(2/2) 9 2.2 mi. NW 1935(1/2)
-(0/0) 0 (1330-2540)
(1330-2540)
Th-228 2
30 1056(2/2) 9 2.2 mi. NW 1056(2/2)
-(0/0) 0 (461-1650)
(461-1650) 1 I
Sr-89 1
4.0
-(0/1)
N/A N/A
-(0/0) 0 (Annually)
Sr-90 1
0.8
-(0/1)
N/A N/A
-(0/0) 0 (Annually)
Milk l-131 24 0.5
-(0/24)
N/A N/A
-(0/0) 0 (pCi/ liter)
Gamma 24 K-40 24 100 1364(24/24) 12 8.3 mi. NW 1423(12/12)
-(0/0) 0 (1170-1640 (1320-1640)
Sr 89 8
5
-(0/8)
N/A N/A
-(0/0) 0 (Ouarterly)
Sr-90 8
0.8 1.39(8/8) 13 5.60 mi. SSW 1.60(4/4)
-(0/0) 0 (Quarterly)
(0.96-2.1)
(1.2-2.1) l I
1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
l l
63 l
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1995 Docket No. 50-338/339 Page 6 of 7 AllIndicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*
Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)
Type No.
Range Direction Range Range ments Fish Gamma 8
pCi/kg (wet)
K-40 8
200 1460(4/4) 25 16.5 mi. NW 1490(4/4) 1490(4/4) 0 (1200-1650)
(1220-2110)
(1220-2110)
Cs-137 8
40 37.2(3/4) 08 1.10 mi. SSE 37.2(3/4)
-(0/4) 0 (26.2-49.9)
(26.2-49.9)
Food Gamma 35 Vegetation Dose (pCi/kg Be-7 35 1542(34/35) 16 12.6 mi 1988(7/7)
-(0/0) 0 (wet))
(318-5730)
NW (318-5730)
K-40 35 14981(35/35) 15 1.37 mi.
17547(7/7)
-(0/0) 0 (4510-33400)
SE (9730-33400)
Cs-137 35 80 56.2(7/35) 16 12.6 mi.
86.5(2/7)
-(0/0) 0 (13.9-159)
NW (13.9-159)
Ra-226 35 805(4/35) 15 1.37 mi.
1250(1/7)
-(0/0) 0 (440-1250)
SE Th-228 35 149(9/35) 21 1.00 mi 224(2/7)
-(0/0) 0 (41.3-260)
WNW (187-260) i 1
LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
64
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
O North Anna Nuclear Power Station, Louisa County, Virginia - 1995 Docket No. 50-338/339 Page 7 of 7 All Indicator Control Non-Msdium or Analysis Locations Location with Highest Mean Location routine Pathway LLD*
Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)
Type No.
Range Direction Range Range ments Direct Gamma 48 0.2 5.60(44/44) 01 0.2 ml. NE 7.76(4/4) 5.18(4/4) 0 Radiation Dose (3.9-8.3)
(7.4-8.3, (4.9-5.3)
)
(mR/std. month)
(Regular TLDs)
Direct Gamma 12 02 5.57(11/11) 01 0.2 mi. NE 7.7(1/1) 5.2(1/1) 0 Radiation Dose (4.3-7.7)
(mR/std. Month)
(AnnualTLDs)
Direct Gamma 286 0.2 6.23(254/254) 21/53 0.30 mi.
8.59(8/8) 5.08(32/32) 0 Radiation Dose (3.7-9.4)
SW (8.1-9.4)
(3.9-6.8)
O (mR/std. Month)
(Sector TLDs) l l
O 1 LLD is the Lower Limit of Detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program, Revision 1, November 1979.
65
a m O
l l
O APPENDIX B DATA TABLES 0
l TABLE B-1: IODINE-131 CONCENTRATIONS IN FILTERED AIR G
lV North Anna Power Station, Louisa County, Virginia - 1995 3
pCl/m 12 Sigma Page 1 of 2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 l
i i
JANUARY 12/28-01/05(a) <.01
<.01
<.02
<.02
<.01
<.02
<.02
<.01
<.01
<.006
<.02
<.02 01/05-01/11m) <.02
<.02
<.02
<.01
<.03
<.02
<.02
<.02
<.02
<.009
<.02
<.01 l
01/11-01/18
<.01
<.01
<.01
<.01
<.007
<.01
<.01
<.01
<.01
<.009
<.02
<.02 01/18-01/25
<.01
<.01
<.01
<.01
<.009
<.02
<.02
<.02
<.02
<.01
<.01
<.01 01/25-02/01
<.02
<.02
<.02
<.02
<.007
<.01
<.01
<.01
<.01
<.009
<.02
<.02 FEBRUARY 02/01-02/08
<.02
<.02
<.02
<.02
<.007
<.02
<.02
<.02
<.02
<.009
<.02
<.02 i
02/08-02/15
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.01
<.01 02/15-02/22
<.01
<.01
<.01
<.01
<.008
<.01
<.01
<.01
<.01
<.008
<.02
<.01 02/22-03/01
<.01
<.01
<.01
<.01
< 009
<.02
<.02
<.02
<.02
<.01
<.02
<.008 MARCH 03/01-03/08
<.01
<.01
<.01
<.01
<.008
<.02
<.02
<.02
<.02
<.01
<.01
<.02 03/08-03/15
<.01
<.01
<.01
<.01
<.009
<.01
<.01
<.01
<.01
<.007
<.02
<.02 i
03/15-03/22
<.01
<.01
<.01
<.01
<.007
<.02
<.02
<.02
<.02
<.01
<.009
<.009 w
l 03/22-03/29
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.01
<.01 APRIL 03/29-04/05
<.01
<.01
<.01
<.01
<.009
<.02
<.02
<.02
<.02
<.01
<.01
<.01 04/05-04/12
<.01
<.01
<.01
<.01
<.006
<.01
<.01
<.01
<.01
<.008
<.02
<.02 04/12-04/19
<.01
<.01
<.01
<.01
<.009
<.02
<.02
<.02
<.02
<.01
<.009
<.009 04/19-04/26
<.01
<.01
<.01
<.01
<.009
<.01
<.01
<.01
<.01
<.01
<.02
<.01 l
04/26-05/03
<.01
<.01
<.01
<.03
<.008
<.02
<.02
<.02
<.02
<.01
<.01
<.01 MAY 05/03-05/10
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.01
<.01 i
05/10-05/17
<.01
<.01
<.01
<.01
<.009
<.02
<.02
<.02
<.02
<.01
<.02
<.02 i
05/17-05/24
<.01
<.01
<.01
<.01
<.01
<.02
<.02
<.02
<.02
<.01
<.02
<.02 05/24-05/31
<.02
<.02
<.02
<.02
<.01
<.01
<.01
<.01
<.01
<.009
<.01
<.01 JUNE 05/31-06/07
<.02
<.02
<.02
<.02
<.01
<.01
<.01
<.01
<.01
<.008
<.01
<.01 06/07-06/14
<.01
<.01
<.01
<.01
<.008
<.02
<.02
<.02
<.02
<.01
<.01
<.01 06/14-06/21
<.01
<.01
<.01
<.01
<.008
<.02
<.02
<.02
<.02
<.01
<.008
<.01 06/21-06/28
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.01
<.01 t
]-
(a) Several stations had a stop date of 01/04/95.
(b) Several stations had a start date of 01/04/95.
66
TABLE B-1: IODINE-131 CONCENTRATION IN FILTERED AIR O
North Anna Power Station, Louisa County, Virginia - 1995 pCi/m3 i 2 Sigma Page 2 of 2 Collection STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 JULY 06/28-07/05
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.02
<.01 07/05-07/12
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.02
<.01 07/12-07/19
<.02
<.02
<.02
<.02
<.01
<.01
<.01
<.01
<.01
<.009
<.01
<.01 07/19-07/27
<.01
<.01
<.01
<.01
<.007
<.01
<.01
<.01
<.01
<.01
<.008
<.008 07/27-08/02
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.009
<.02
<.02 AUGUST 08/02-08/09
<.01
<.01
<.01
<.01
<.009
<.02
<.02
<.02
<.02
<.01
<.01
<.01 08/09-08/17
<.02
<.02
<.02
<.02
<.01
<.01
<.01
<.01
<.01
<.008
<.01
<.009 08/17-08/23
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.02
<.02 08/23-08/30
<.01
<.01
<.01
<.01
<.009
<.01
<.01
<.01
<.01
<.009
<.02
<.02 SEPTEMBER 08/30-09/06
<.01
<.01
<.01
<.01
<.008
<.02
<.02
<.02
<.02
<.01
<.02
<.01 09/06-09/13
<.02
<.02
<.02
<.02
<.01
<.01
<.01
<.01
<.01
<.009
<.02
<.02 09/13-09/20
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.01
<.01 3
09/20-09/27
<.02
<.02
<.02
<.02
<.01
<.01
<.01
<.01
<.01
<.008
<.05
<.05 09/27-10/04
<.01
<.01
<.01
<.01
<.009
<.02
<.02
<.02
<.02
<.01
<.01
<.01 OCTOBER 10/04-10/11
<.01
<.01
<.01
<.01
<.008
<.009
<.009
<.009
<.009
<.007
<.01
<.01 10/11-10/18
<.02
<.02
<.02
<.02
<.01
<.009
<.009
<.009
<.009
<.007
<.01
<.01 10/18-10/25
<.01
<.01
<.01
<.01
<.008
<.009
<.009
<.009
<.009
<.006
<.01
<.01 10/25-11/01
<.01
<.01
<.01
<.01
<.008
<.01
<.01
<.01
<.01
<.009
<.01
<.01 NOVEMBER 11/01 11/09
<.01
<.01
<.01
<.01
<.008
<.01
<.01
<.01
<.01
<.008
<.008
<.007 11/09-11/16
<.01
<.01
<.01
<.01
<.008
<.01
<.01
<.01
<.01
<.006
<.02
<.007 11/16-11/22
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.02
<.02 11/22-11/29
<.01
<.01
<.01
<.01
<.008
<.01
<.01
<.01
<.01
<.008
<.01
<.01 DECEMBEB 11/29-12/06
<.01
<.01
<.01
<.01
<.008
<.01
<.01
<.01
<.01
<.009
<.01
<.01 12/06-12/13
<.01
<.01
<.01
<.01
<.009
<.009
<.009
<.009
<.009
<.007
<.01
<.01 12/13-12/20
<.02
<.03
<.03
<.03
<.02
<.02
<.02
<.02
<.02
<.01
<.03
<.03 12/20-12/27
<.02
<.02
<.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.02
<.007 12/27-01/03
<.01
<.009
<.01
<.01
<.007
<.02
<.02
<.02
<.02
<.02
<.01
<.01 3J l
67
O O
O TABLE B-2 (Page I of 4)
NORTII ANNA - 1995 CONCENTRATIONS OFGROSS BETA IN AIR PARTICULATES 1.0E-03 pCi/m3 i 2 Sigma COLI.ECTION AVERAGE DATE 01 02 03 04 05 OSA 06 07 21 22 23 24 i 2 s.d.
l
.IANUARY 12/28-01/05 (a) 2112 2112 20 2 2512 16 i 2 22i 2 21 181 2 201 2 201 2 18i 2 2112 201 5 Ol/05-01/I I (b) 271 2 241 2 26i 2 281 2 2114 271 2 2412 261 2 2512 261 2 271 2 291 2 261 4 01/11-01/18 181 2 17i 2 191 2 181 2 1712 1612 12 2 1312 161 2 12 i 2 14 2 171 2 161 5 01/18-01/25 12 2 131 2 121 2 14i2 1112 loi 1 1212 121 2 Ili 2 1112 13i2 121 2.
121 2 01/254)2/01 181 2 19 2 19 i 2 1712 171 2 151 2 16i2 161 2 191 2 181 2 171 2 181 2 171 3 FEBRUARY 02/01-02/08 2112 241 2 261 2 231 2 241 2 231 2 231 2 221 2 21 i 2 251 2 221 2 2512 23 1 3 02A)8-02/15 2412 221 2 22 2 22i 2 171 2 201 2 221 2 2112 201 2 181 2 20i 2 241 2 211 4 02/15-02/22 221 2 21 2 181 2 1912 181 2 2ii 2 181 2 1712 171 2 181 2 191 2 2112 19 1 4 02/22-03/01 161 2 141 2 151 2 171 2 14i 2 1112 1712 121 2 121 2 131 2 1612 181 2 15 1 5 MARCH 03/01-03/08 201 2 181 2 201 2 21 2 181 2 171 2 161 2 191 2 17 2 161 2 171 2 161 2 181 4 03/08-03/15 281 2 251 2 241 2 261 2 27 i 2 261 2 201 2 231 2 201 2 221 2 261 2 261 2 24 i 5 03/15-03/22 191 2 2112 191 2 201 2 191 2 221 2 191 2 191 2 181 2 17 i 2 181 2 181 2 19 i 3 03/22-03/29 171 2 181 2 1412 171 2 15 i 2 151 2 151 2 15i 2 151 2 15 2 161 2 181 2 16 i 3 Quarter Avg. 2019 2017 2019 2118 18 8
19 i 11 18 i 8 1819 18i8 1819 19 8
2019 20 i 9 i 2 s.d.
(a) Several stations had a stop date of 01/M/95.
(b) Several stations had a start date of Ol/M/95.
O Q
O TAHLE II.2
[
(Page 2 of 4)
NORTil ANNA - 1995 CONCENTRATIONS OF GROSS BLTA IN AIR PARTICULATES 1.0E-03 pCi/m3 i. 2 Sigma COLLECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 i 2 s.d.
i Af_R[L 03/294M/05 201 2 2112 18 i 2 1812 211 2 20 i 2 151 2 201 2 171 2 21 i 2 2312 2212 20 1 5 m/054M/12 18 i 2 191 2 2112 261 2 221 2 2412 2112 2112 21 i 2 22i 2 22i 2 26 i 2 221 5 M/124M/19 2112 191 2 18 i 2 181 2 171 2 16 i 2 161 2 171 2 161 2 181 2 161 2 191 2 181 3 i
M/194M/26 161 2 151 2 16 2 13 2 1312 1512 151 2 131 2 1312 1412 131 2 16i 2 14 1 3 m/26-05/03 13 i 2 14 i 2 1312 191 3 1312 13i2 131 2 13 i 2 1312 131 2 1412 1612 141 4 MAX 05/03-05/10 17 2 171 2 171 2 181 2 161 2 16i 2 1612 1512 1512 1512 18i2 181 2 17 1 2 05/10-05/17 1412 131 2 11 i I 131 2 3.8 1 1.l (a) 131 2 13 i 2 121 2 121 2 13i 2 131 2 11 i 1 121 5 m
05/17-05/24 221 2 191 2 201 2 201 2 181 2 181 2 201 2 181 2 191 2 191 2 171 2 191 2 19 1 3 05/24-05/31 151 2 131 2 12i2 14 i 2 121 2 141 2 1212 121 2 121 2 141 2 121 2 15 i 2 13 1 2 JUNE f
05/31-06/07 9.6 i 1.5 131 2 13i 2 14i2 131 2 121 2 131 2 121 2 131 2 11 i 2 1412 121 2 12 1 2 06M7-06/14 1612 14i2 141 2 17i 2 131 2 1412 161 2 151 2 141 2 1312 151 2 14i2 15 1 2 6
06/14-06/21 17i 2 171 2 161 2 17i2 141 2 181 2 I412 131 2 14i 2 1612 151 2 191 2 161 4 06/21-06/28 12 2 8.5 i 1.3 9.3 1.4 1011 8.7 i 1.4 9.8 i 1.4 7.9 i 1.3 8.3 i 1.3 11 i 1 1011 11 i 1 9.3 i 1.1 101 2 Quarter Avg. 1617 16i7 15 1 7 17 i 8 14 i10 16 i 7 1517 15 i 7 15 i 6 15 i 7 16 i 7 17 i 9 15 i 7 i 2 s.d.
r (a) Results confirmed by recalculation.
J
. -. -. - ~,,
O O
O TABLE H-2 (Page 3 of 4)
NORTil ANNA - 1995 i
CONCENTRATIONS OF GROSS HETA IN AIR PARTICULATES 1.0E-03 pCi/m3 i 2 Sigma COLLECTION AVERAGE I
DATE 01 02 03 04 05 OSA 06 07 21 22 23 24 i 2 s.d.
t JUL) 06/28-07m3 15 i 2 1412 121 2 13 i 2 131 2 12 i 2 7212 121 2 12 i 2 14 2 141 2 1512 13 1 2 07A)5-07/12 19 2 15 i 2 151 2 16 2 15 2 171 2 1812 15i 2 16 i 2 18 2 181 2 171 2 171 3 L
07/12-07/19 291 2 28 i 2 271 2 2512 271 2 261 2 29 i 2 27 i 2 26i 2 301 2 28i 2 271 2 27 1 3 s
07/19-07/27 2112 2112 221 2 201 2 2112 20 i 2 191 2 181 2 22 i 2 201 2 2112 21 i 2 21i 2 07/27-08A)2 22 i 2 22i 2 181 2 21 i 2 20 i 2 201 2 1812 21 i 2 17 i 2 19 2 221 2 23 i 2 20 4 AUGUST 08/02-08/09 1512 12i2 1011 12i 2 12 i 2 12 i 2 11 i i 12 i 2 131 2 Ili i 131 2 121 2 12 i 2 08A)9-08/I7 21 i 2 181 2 181 2 1812 161 2 231 2 17 i 2 151 2 17i 2 211 2 201 2 2112 19 1 5 08/17-08/23 27i 2 26i 2 22 i 2 2512 24i 2 24 2 25 i 2 201 2 201 2 231 2 23 i 2 2512 24 i 4 i.
08/23-08/30 18 2 201 2 18i 2 20i 2 18i 2 18 i 2 181 2 16 2 161 2 201 2 17i 2 191 2 18 i 3 w
+
SEPTEMBER i
l 08/30-09A)6 301 2 27 i 2 261 2 27i 2 271 2 26 2 22 i 2 231 2 24 i 2 26i 2 26i 2 291 2 261 5 09/06-09/13 26i 2 27 i 2 27i 2 25 i 2 25 i 2 26i 2 28i 2 241 2 231 2 271 2 2512 301 2 26 i 4
[
09/13-09/20 2112 19 i 2 171 2 18i 2 17 i 2 19i 2 17i 2 161 2 1512 1512 1612 181 2 17 i 4 09/20-09/27 191 2 18 i 2 1512 151 2 16i 2 16i 2 151 2 131 2 131 2 14i 2 1612 17 i 2 16 i 4
+
09/27-10 01 311 2 3112 28 2 25 i 2 301 2 27 2 24i 2 221 2 1412 291 2 291 2 33i 2 28 1 7 i
Quarter Avg. 22 i 11 21 i 12 20 12 20 i 10 20 i 11 20i10 20 i l1 18 10 18 i 9 21 i 12 21 i 10 22 i12 22 i.I1 i 2 s.d.
t h
i f
O O
O TABLE B-2 (Page d of 4)
NORTil ANNA - 1995 CONCENTR ATIONS OF GROSS 11 ETA IN AIR PARTICULATES 1.0E-03 pCi/m3 i 2 Sigma COI I.ECTION AVERAGE DATE 01 02 03 04 05 05A 06 07 21 22 23 24 i 2 s.d.
OCTOBE_R.
10A410/II 201 2 17 2 14 i 2 171 2 15 i 2 151 2 14i2 151 2 Ili i 16 2 15 i 2 191 2 161 5 10/11-10/18 271 2 23 i 2 22i 2 2212 2112 21 2 2112 2112 221 2 26 i 2 241 2 2712 23 1 5 10/18-10/25 201 2 20 2 20 2 21 i 2 181 2 181 2 1912 191 2 2ii 2 221 2 201 2 221 2 201 3 10/25-11/01 18 i 2 19 i 2 16 i 2 16 i 2 16 2 171 2 1412 161 2 141 2 16 i 2 16i 2 201 2 171 4 NOVEMILFR I I/01-I I A)9 201 2 1812 17 2 191 2 171 2 191 2 181 2 17 i 2 17 i 2 201 2 201 2 201 2 191 3 II A)9-I I/16 181 2 171 2 161 2 15 i 2 15 i 2 15 2 141 2 1612 181 2 I5 i 2 17 i 2 17 2 16 i 3 11/16-11/22 2512 221 2 22 i 2 2412 181 2 22 2 22 i 2 191 2 23 i 2 221 2 22 i 2 231 2 22 1 4 11/22-11/29 28i 2 271 2 25 2 25 i 2 26 2 25 i 2 271 2 221 2 2512 271 2 26 i 2 2712 26 i 3 DECEMBER 11/29-12/06 22 2 201 2 23 i 2 2412 201 2 2112 24i 2 2l i 2 22 i 2 2112 271 2 271 2 23 1 5 12M>-12/13 241 2 25 i 2 241 2 271 2 221 2 25 2 25 i 2 2112 241 2 231 2 261 2 2512 24 1 3 12/13-12/20 29 i 2 281 2 281 2 28 i 2 281 2 291 2 271 2 25i 2 221 2 29 i 2 301 2 2912 281 4 12/20-12/27 171 2 13 i 2 121 2 141 2 131 2 15 2 131 2 121 2 1412 141 2 151 2 15 i 2 14 i 3 12/27-01/03 171 2 16 2 171 2 191 2 181 2 17 2 171 2 16i2 191 2 191 2 17i 2 181 2 181 2 Quarter Avg. 22 i 9 2019 20 i 10 21 9
1919 2019 20 i 10 1917 19 9
2119 21 i 10 2219 20 i 9 2 s.d.
Annual Avg. 20 i 10 19 10 19 i 10 20i9 18 i 10 19 10 18 i 10 17 i 9 1819 19 i 10 19 i 10 20 i11 19 i 10 1 2 s.d.
m
_.,__m
I TABLE B-3: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES O
North Anna Power Station, Louisa County, Virginia - 1995 3
1.0 E-03 pCi/m 2 Sigma Page 1 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/298 03/29 03/29-06/28 06/28-09/27 09/27-01/03 2 s.d.
STA-01 Sr-89 (a)
< 0.6 (a)
(a)
Sr-90 (a)
< 0.1 (a)
(a)
Be-7 76.1 7.6 81.6 i 82 81.5 8.1 55.6 5.6 73.7 i 24.7 K-40
<5 4.56 i 1.86
<5 11.7 i 2.3 8.13 10.1 Co-60
< 0.3
< 0.3
< 0.2
< 0.2 Ru-103
< 0.3
< 0.3
< 0.3
< 0.2 Cs-134
< 0.3
< 0.2
< 0.2
< 0.2 Cs-137
< 0.3
< 0.3
< 0.2
< 0.2 Th-228
< 0.5
< 0.4
< 0.4
< 0.3 STA-02 Sr-89 (a)
< 0.8 (a)
(a)
Sr-90 (a)
< 0.1 (a)
(a)
Be-7 81.2 8.1 74.0 7.4 83.0 i 8.3 59.9 i 6.0 74.5 21.0 K-40
<5 8.01 2.30
<6
<5 8.01 i 23.0 l
< 0.3
< 0.3
< 0.2
< 0.2 Ru-103
< 0.3
< 0.3
< 0.3
< 0.3 Cs-134
< 0.2
< 0.3
< 0.3
< 0.2 Cs-137
< 0.3
< 0.2
< 0.3
< 0.2 q
!Q Th-228
< 0.5
< 0.3
< 0.6
< 0.4 i
i STA-03 Sr-89 (a)
< 0.7 (a)
(a)
I Sr-90 (a)
< 0.2 (a)
(a) l Be-7 70.5 7.0 70.2 7.0 65.7 6.6 57.7 5.8 66.01 11.9 K-40
<7
< 10
<9
<5 Co-60
< 0.3
< 0.3
< 0.3
< 0.2 Ru-103
< 0.3
< 0.3
< 0.3
< 0.2 Cs-134
< 0.2
< 0.3
< 0.3
< 0.2 i
Cs 137
< 0.3
< 0.3
< 0.3
< 0.2 Th-228
< 0.3
< 0.4
< 0.4
< 0.4 STA-04 Sr-89 (a)
<1 (a)
(a)
Sr-90 (a)
< 0.2 (a)
(a)
Be-7 73.4 7.3 83.0 8.3 75.1 i 7.5 58.1 5.8 72.4120.8 l
< 10
<4
<4
<6 Co-60
< 0.3
< 0.2
< 0.2
< 0.3 l
Ru-103
< 0.3
< 0.3
< 0.3
< 0.3 l
Cs-134
< 0.3
< 0.2
< 0.2
< 0.3 Cs-137
< 0.3
< 0.2
< 0.3
< 0.3 Th-228
< 0.4
< 0.4
< 0.4
< 0.6 l
All gamma emitters other than those listed were <LLD.
(a) Strontium-89/90 analyses performed only on second quarter samples.
l l
72 i
TABLE B-3: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES O
North Anna Power Station, Louisa County, Virginia - 1995 1.0 E-03 pCl/m3 2 Sigma Page 2 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/28-03/29 03/29-06/28 06/28-09/27 09/27-01/03 2 s.d.
STA-05 Sr-89 (a)
< 0.7 (a)
(a)
Sr-90 (a)
< 0.2 (a)
(a) i Be 7 75.5 7.5 64.9 6.5 66.5 6.6 50.815.1 64.4 20.4 K 40
<4
<6
<4
<7 Co-60
< 0.3
< 0.2
< 0.2
< 0.2 Ru-103
< 0.3
< 0.2
< 0.3
< 0.3 Cs-134
< 0.2
< 0.2
< 0.2
< 0.3 Cs-137
< 0.3
< 0.2
< 0.3
< 0.3 Th-228
< 0.4
< 0.3
< 0.3
< 0.4 STA-05A Sr-89 (a)
< 0.9 (a)
(a)
Sr-90 (a)
< 0.2 (a)
(a)
Be-7 70.0 7.0 87.9 8.8 79.8 8.0 50.31 5.0 72.0 i 32.4 K-40 19.3 2.9
<5
< 10 3.121 1.75 11.2 i 22.9 Co-60
< 0.3
< 0.3
< 0.4
< 0.2 Ru-103
< 0.3
< 0.3
< 0.4
< 0.3 Cs-134
< 0.2
< 0.3
< 0.4
< 0.2 Cs-137
< 0.3
< 0.2
< 0.3
< 0.3 Th-228
< 0.4
< 0.5
< 0.5
< 0.4 STA-06 Sr-89 (a)
< 0.5 (a)
(a)
Sr-90 (a)
< 0.09 (a)
(a)
Be-7 83.4 8.3 72.7 7.3 77.4 7.7 50.4 i 5.0 71.01 28.8 K-40
<5
<4
<5 2.68 1.38 2.68 i 1.38 Co-60
< 0.3
< 0.2
< 0.3
< 0.2 Ru-103
< 0.3
< 0.3
< 0.3
< 0.2 Cs 134
< 0.3
< 0.2
< 0.2
< 0.2 Cs-137
< 0.3
< 0.2
< 0.3
< 0.3 Th-228
< 0.5
< 0.4
< 0.4 s 0.3 STA-07 Sr-89 (a)
< 0.9 (a)
(a)
Sr90 (a)
< 0.2 (a)
(a)
Be-7 77.7 7.8 76.1 7.6 63.8 6.4 47.9 4.8 66.4 i 27.6 K-40 3.20 1.84
<6 29.9 3.7
<9 16.6 37.8 Co-60
< 0.3
< 0.3
< 0.3
< 0.3 Ru-103
< 0.3
< 0.3
< 0.3
< 0.4 Cs-134
< 0.2
< 0.3
< 0.3
< 0.3 Cs-137
< 0.2
< 0.3
< 0.3
< 0.3 Th-228
< 0.4
< 0.6
< 0.4
< 0.5 All gamma emitters other than those listed were <LLD.
(a) Strontium-89/90 analyses performed only on second quarter samples.
73
TABLE B-3: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN AIR PARTICULATES pC North Anna Power Station, Louisa County, Virginia - 1995 1.0 E-03 pCl/m3 2 Sigma Page 3 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 12/28-03/29 03/29 46/28 06/28-09/27 09/27-01/03 i 2 s.d.
STA-21 Sr-89 (a)
< 0.7 (a)
(a)
Sr-90 (a)
< 0.1 (a)
(a)
Be-7 85.6 8.6 68.7 6.9 79.0 7.9 58.0 5.8 72.8124.2 K-40
<6
<9
<4
<4 Co-60
< 0.3
< 0.3
< 0.3
< 0.3 Ru-103
< 0.4
< 0.3
< 0.3
< 0.3 Cs-134
< 0.3
< 0.3
< 0.2
< 0.2 Cs-137
< 0.4
< 0.3
< 0.3
< 0.2 Th-228
< 0.7
< 0.4
< 0.5
< 0.4 STA-22 Sr-89 (a)
<1 (a)
(a)
Sr-90 (a)
< 0.2 (a)
(a)
Be-7 70.0 7.0 73.2 7.3 65.7 6.6 50.6 5.1 64.9 20.0 K 40
<8
<5
<5 25.3 3.2 25.3 3.2 Co-60
< 0.3
< 0.3
< 0.3
< 0.3 Ru-103
< 0.3
< 0.3
< 0.3
< 0.3 Cs-134
< 0.3
< 0.2
< 0.2
< 0.3 n
< 0.3
< 0.3
< 0.2
< 0.3
()
< 0.4
< 0.4
< 0.4
< 0.3 STA-23 Sr-89 (a)
<1 (a)
(a)
Sr-90 (a)
< 0.2 (a)
(a)
Be-7 72.9 7.3 73.1 7.3 71.117.1 73.3 7.3 72.6 2.0 K-40
<4 3.29 1.50
<4
<5 3.29 1.50 Co-60
< 0.2
< 0.2
< 0.2
< 0.3 Ru-103
< 0.2
< 0.2
< 0.3
< 0.3 Cs-134
< 0.2
< 0.2
< 0.2
< 0.2 Cs-137
< 0.3
< 0.3
< 0.2
< 0.2 Th-228
< 0.4
< 0.3
< 0.3
< 0.4 4
STA-24 Sr-89 (a)
<1 (a)
(a)
Sr-90 (a)
< 0.2 (a)
(a)
Be-7 78.8 7.9 77.2 7.7 76 3 7.6 49.5 4.9 70.5 28.0 K 40 4.18 1.75 5.58 2.47
<4
<4 4.88 1.98 Co-60
< 0.2
< 0.4
< 0.2
< 0.3 Ru-103
< 0.2
< 0.4
< 0.2
< 0.3 Cs-134
< 0.2
< 0.4
< 0.2
< 0.2 Cs-137
< 0.2
< 0.3
< 0.2
< 0.2 Th-228
< 0.3
< 0.5
< 0.3
< 0.4 O
All gamma emitters otl er than those listed were <LLD.
(a) Strontium-89/90 analys0s performed only on second quarter samples.
74
l TABLE B-4: GROSS BETA, TRITIUM AND GAMMA EMITTER
- CONCENTRATIONS IN PRECIPITATION Station 01A -(On Site)
North Anna Power Station, Louisa County, Virginia - 1995 pCl/li 2 Sigma Page 1 of 1 Collection Dates Gross Beta Rainfall (inches) 12/28/94-01/25/9E 13 i 1 6.52 01/25/95-03/01/95 3.110.7 1.61 l
03/01/95 03/30/95 1.6 i 0.6 2.37 1
03/30/95-04/26/95 3.2 i 0.7 1.73 04/26/95-05/31/95 2.31 0.6 2.96 05/31/95-06/28/95 3.41 0.7 3.78 06/28/95-07/27/95 3.8 i 0.8 3.07 07/27/95-08/30/95 131 2 0.76 I
08/3C/95-09/27/95 1.8 i 0.6 2.58 09/27/95-10/25/95 0.86 i 0.49 6.62 10/25/95-11/29/95 3.0 0.7 4.80 11/29/95-12/27/95 3.0 0.7 2.15 Average 2 s.d.
4.3 8.3 l
SEMI-ANNUAL PRECIPITATION COMPOSITES 12/28/94-06/28/95 06/28/95-12/28/95 Be-7 = < 40 Be-7 61.5 i 30.1
=
< 200
=
All gamma emitters other than those listed were <LLD.
75
O O
O TABLE R-5 NORIll ANNA-1995 CONCFNIRATIONS OF GAMM A EM1TERS* IN SOIL pCi/kgi 2 Sigma COLL STATION DATES Sr-89 Sr-90 Re-7 K-40 Cs-134 Cs-137 Ra-226 Th-228 01 07/05 S 5
< 200
< 80
< 600 18700i 1900
< 50
< 50 22401 790 1300 i I30 02 07/05 S 5
< 100
< 30
< 300 6460i 650
< 20 128i 25
< 400 335 i 34 03 07/05 S 5
< 200
< 70
< 500 10100 i 1000
< 50 1M i 34
< 800 752 i 75 M
07/05 S 5
< 100
< 40
< 700 4300i 590
< 50 592i 61 1410 i 670 816 i 82 05 07/05SS
< 200 170i 50
< 500 13200i 1300
< 40 707 i 71 23701 570 1560i 160 05A 07/05 S 5
< 300
< 100 1090i 370 13000i 1300
< 40 585 1 28.4 1590 i 600 11101 110 06 07/05 S 5
< 200 68i 33
< 700 11000i 1100
< 60 231 i 35 2900i 660 20201 200 g
07 07/05 S 5
< 200
< 60
< 500 55801 590
< 50
< 50 28301 730 1810 i 180 21 07/05 S 5
< 100 87 31
< 400 11300i 1100
< 30 767 i 77 798i 449 614 i 61 22 07/05 S 5
< 200 72i 43
< 600 18500 i 1800
< 60 234 1 45 2260i 730 1180 t 120 23 07/05 S 5
< 200 130i 50
< 700 23100 i 2300
< 60 255 i 41 2280i 790 1580 i 160 24 07/0585
< 100
< 50
< 500 3820 i 470
< 40
< 40 2150i 610 17201 170 Average 105 i 87 1990 i 379 11588 1 12269 342 i 543 2083 i 1292 1233 i 1958 i 2 s.d.
Allother gamma emitters were < LLD.
TABLE B-6: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS p
IN GROUND AND WELL WATER North Anna Power Station, Louisa County, Virginia - 1995 pCi/l 2 Sigma Page 1 of 1 Collection Dates Sr-89 Sr-90 H-3 Be-7 K-40
!?1 Ba-140 Th-228 STATION 01 A 03/29/95 (a)
(a)
< 200
< 30
< 50
< 0.2
<5
<7 06/30/95
< 0.9
< 0.2
< 200
< 30
< 70
< 0.5
<9
<6 09/28/95 (a)
(a)
< 200
< 30
< 50
< 0.2
<5
<8 j
12/21/95 (a)
(a)
< 100
< 40
< 100
< 0.3
<9
<6 All gamma emitters other than those listed were <LLD.
(a) Stront um-89/90 analyses performed only on second quarter sample.
TABLE B-7: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS Q
IN RIVER WATER North Anna Power Station, Louisa County, Virginia - 1995 pCill 2 Sigma Page 1 of 1 Collection Dates Sr-89 Sr-90 H-3 Be-7 K-40 1-131 Cs-137 Ba-140 Ra-226 Th-228 STATION - 11 01/18/95 (a)
(a) 3300 1 200
< 100
< 0.3
<5
<5
< 90
<8 02/13/95 (a)
(a)
(b)
< 40
< 100
< 0.2
<4
<6
< 70
<6 03/23/95 (a)
(a)
(b)
< 30
< 100
< 0.2
<4
<5
< 70
<7 04/18/95
<4
< 0.7 3600 200
< 40
< 70
< 0.2
<4
<7
< 100
<9 05/23/95 (a)
(a)
(b)
< 30
< 60
< 0.2
<4
<6
< 90
<7 06/20/95 (a)
(a)
(b)
< 40
< 100
< 0.2
<4
<8
< 70
<7 07/17/95 (a)
(a) 2100 200
< 40
< 100
< 0.2
<4
<7
< 70
<7 08/23/95 (a)
(a)
(b)
< 30
< 50
< 0.2
<4
<5
< 60
<5 09/20/95 (a)
(a)
(b)
< 30
< 50
< 0.3
<4
<7
< 70
<6 10/16/95 (a)
(a) 23001200
< 40
< 100
< 0.4
<4
<7
< 80
<7 11/22/95 (a)
(a)
(b)
< 30
< 100
< 0.2
<4
<5
< 70
<6 12/20/95 (a)
(a)
(b)
< 40
< 100
< 0.4
<4
<7
< 70
-7 Average 2 s.d.
2825 1473 All gamma emitters other than those listed were <LLD.
l (a)
Sr-89/90 analyses performed only on second quarter samples.
(b)
Tritium analysis performed on quarterly composite.
77
1 TABLE B-8: GAMMA EMITTER *, STRONTIUM AND TRITIUM CONCENTRATIONS IN n
SURFACE WATER U
North Anna Power Station, Louisa County, Virginia - 1995 pCi/li 2 Sigma Page 1 of 1 Collection i
Dates Sr-89 Sr-90 H-3 Be-7 K-40 1-131 "
Cs-137 Ba-140 Ra-226 Th-228 STATION - 08 01/18 (a)
(a) 33001200
< 30
< 60
< 0.2
<4
<5
< 70
<6 02/13 (a)
(a)
(b)
< 30
< 50
< 0.2
<3
<6
< 60
<6 03/23 (a)
(a)
(b)
< 30
< 60
< 0.2
<4
<5
< 90
<7 04/18
<4
< 0.7 33001200
< 30
< 90
< 0.2
<4
<5
< 70
<7 05/23 (a)
(a)
(b)
< 30
< 50
< 0.2
<4
<5
< 80
<7 j
06/20 (a)
(a)
(b)
< 30
< 50 s 0.2
<4
<7
< 80
<7 07/17 (a)
(a) 21001200
< 30
< 60
< 0.2
<3
<7
< 90
<7 08/23 (a)
(a)
(b)
< 30
< 100
< 0.2
<4
<6
< 70
<7 09/20 (a)
(a)
(b)
< 30
< 70
< 0.3
<4
<8
< 100
<8 10/16 (a)
(a) 2400 i 200
< 30
< 60
< 0.4
<3
<8
< 70
<6 11/22 (a)
(a)
(b)
< 30
< 70
< 12
<4
<6
< 90
<8 12/20 (a)
(a)
(b)
< 30
< 60
<L3
<4
<7
< 90
<7
(]
Avg.
2775 i 1237 l
- 2. s.d.
STATION - 09A 01/18 (a)
(a)
< 200
< 40
< 100
< 0.2
<4
<5
< 80
<6 02/13 (a)
(a)
(b)
< 30
< 50
< 0.2
<3
<5
< 60
<6 03/23 (a)
(a)
(b)
< 40
< 70
< 0.2
<4
<6
< 100
<9 04/18
<3
< 0.6
< 200
< 30
< 60
< 0.1
<4
<6
< 90
<7 05/23 (a)
(a)
(b)
< 40
< 100
< 0.2
<4
<6
< 70
<7 06/20 (a)
(a)
(b)
< 40
< 60
< 0.2
<4
<8
< 100
<8 07/17 (a)
(a)
< 200
< 30
< 70
< 0.2
<4
<6
< 100
<8 08/23 (a)
(a)
(b)
< 30
< 50
< 0.2
<4
<5
< 70
<6 l
09/20 (a)
(a)
(b)
< 40
< 100
< 0.3
<4
<8
< 70
<6 l
10/16 (a)
(a)
< 200
< 40
< 70
< 0.4
<4
<6
< 100
< 10 l
11/22 (a)
(a)
(b)
< 30
< 90
< 0.2
<4
<5
< 70
<6 12/20 (a)
(a)
(b)
< 30
< 70
< 0.3
<4
<7
< 70
<6 O
All gamma emitters other than those listed were <LLD.
D l-131 by radiochemistry s
(a) Analysis pedormed only with second quarter.
i 1
(b) Analysis performed quarterly.
78
1 i
TABLE B-9: GAMMA EMITTER
- AND TRITIUM CONCENTRATIONS l'
IN SURFACE WATER State-Spilt Samples North Anna Power Station, Louisa County, Virginia - 1995 pCi/li 2 Sigma Page 1 of 1 Collection Dates H-3 Be-7 K-40 1-131 Cs-137 Ba-140 Ra-226 Th-228 STATION - W-27 1
01/31 3001110
< 30
< 50
< 0.3
<4
<6
< 60
<5 02/28 (a)
< 30
< 50
< 0.6
<4
< 10
< 70
<6 03/31 (a)
< 30
< 40
< 0.8
<3
<10
< 60
<5 04/30
< 300
< 40
< 90
< 0.7
<4
< 10
< 90
<8 05/31 (a)
< 40
< 50
< 0.7
<4
< 20
< 70
<6 06/30 (a)
< 50
< 50
< 0.5
<3
< 30
< 60
<5 07/31 13001200
< 30
< 60
< 0.4
<3
<6
< 70
<6 08/30 (a)
< 30
< 50
< 0.6
<3
<9
< 60
<6 09/30 (a)
< 30
< 50
< 0.5
<4
<9
< 70
<6 10/31 1500 200
< 30
< 60
< 0.4
<4
<9
< 90
< 10 11/30 (a)
< 30
< 30
< 2 (b)
<3
< 10
< 50
<4 12/31 (a)
< 40
< 60
<1
<3
< 10
< 70
<7 Avg.
103311286 2 s.d.
STATION - W-33 01/31 4200 200
< 50
< 100
< 0.3
<5
<9
< 90
<8 02/28 (a)
< 30
< 50
< 0.7
<4
<10
< 60
<5 03/31 (a)
< 30
< 50
< 0.9
<3
< 10
< 70
<G 04/30 3600 300
< 50
< 80
< 0.8
<5
<10
< 100
<9 05/31 (a)
< 40
< 40
<1
<4
< 20
< 60
<6 06/30 (a)
< 40
< 40
< 0.6
<3
< 10
< 70
<7 07/31 2300 200
< 30
< 70
< 0.3
<3
<5
< 60
<6 08/30 (a)
< 40
< 60
< 0.7
<3
<10
< 70
<6 09/30 (a)
< 30
< 70
< 0.5
<3
<8
< 60
<6 10/31 22001200
< 40
< 70
< 0.3
<4
<8
< 100
<8 11/30 (a)
< 20
< 30
< 2 (b)
<3
< 10
< 40
<3 12/31 (a)
< 30
< 70
< 0.9
<3
< 10
< 60
<5 Avg.
3075 1969 2 s.d.
All gamma emitters other than those listed were <LLD.
(a) Tritium analysis performed on the first monthly composite of each quarter.
(b) LLD was not met due to the late arrival (29 days) from time of collection to receipt at laboratory.
79
i TABLE B-10: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN SEDIMENT SILT North Anna Power Station, Louisa County, Virginia - 1995 pCi/kgi 2 Sigma Page 1 of 1 STA-06 STA-09A STA-11 STA-08 STA-09A STA-11 Average l
Nuclide 03/10 03/10 03/10 08/23 08/23 08/23 i2 Sigma l
Sr-89 (a)
(a)
(a)
< 500
< 400
< 500 l
Sr-90 (a)
(a)
(a)
< 40
< 30
< 30 Be-7
< 300
< 400
< 300
< 300
< 200
< 400 l
K-40 21601 350 12000 i 1200 18900 1 1900 53601 540 19000 1 1900 23700 i 2400 13520 1 16984 Mn-54
< 30
< 40
< 30
< 30
< 20
< 40 Co-58
< 30
< 40
< 30
< 30
< 20
< 40 Co-60
< 40
< 30
< 30
< 30
< 20
< 40 Cs-134
< 30
< 40
< 40
< 40
< 20
< 40 Cs-137 66.2123.8
< 40
< 40
< 40
< 30 229i42 148 i 230 Ra-226
< 800 8001 467 1560i 500 795 i 431 819 i 303 15901 600 1113 1 844 Th-228 348 i 41 515 1 52 10801 110 725 i 72 3541 35 943 i 94 661 i 615 i
1 All gamma emitters other than those listed were <LLD.
(a) Strontium 89/90 analyses performed annually.
lO TABLE B-11: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN SHORELINE SOIL North Anna Power Station, Louisa County, Virginia - 1995 l
pCl/kg i 2 Sigma Page 1 of 1 Station-09 Station-09 Average Nuclide 02/13 08/17 i2 Sigma l
l Sr-89 (a)
< 400 Sr40 (a)
< 80 Be-7
< 500 466i P.24 466 i 224 K-40 6180 650 2200 MO 4190 1 5629 Mn-54
< 50
< 30 Co-58
< 50
< 30 Co-60
< 50
< 30 Cs-134
< 60
< 40 1
Cs-137 493 57 189 27 341 430 Ra-226 2540 780 1330 1 420 1935 i 1711 Th-228 1650 170 461 46 1056 i 1682 All gamma emitters other than those listed were <LLD.
(a) Strontium 89/90 analyses performed annually.
80
TABLE B-12: GAMMA EMITTER
- AND STRONTIUM CONCENTRATIONS IN MILK i O North Anna Power Station, Louisa County, Virginia - 1995 pCi/li 2 Sigma Page 1 of 2 MONTH NUCLIDE STATION-12 STATION-13 JANUARY Sr-89
<2
<2 Sr-90 1.4 i 0.3 1.9 i 0.3 K-40 16401 160 1390 i 140 Cs-137
<5
<4 1-131
< 0.5
< 0.5 FEBRUARY Sr-89 (a)
(a)
Sr-90 (a)
(a)
K-40 15001 150 1330 i 130 Cs-137
<4
<4 l-131
< 0.3
< 0.3 MARCH Sr-89 (a)
(a)
Sr-90 (a)
(a)
K-40 1510 i 150 13301 130 Cs-137
<4
<5 l-131
< 0.2
< 0.3
('
APRIL Sr-89
<2
<2
\\
Sr-90 0.96 i 0.24 1.2 i 0.2 K-40 1410 i 140 1330 i 130 Cs 137
<5
<4 l-131
< 0.2
< 0.2 MAY St-89 (a)
(a)
Sr-90 (a)
(a)
K-40 14201 140 13401 130 Cs-137
<5
<4 l-131
< 0.3
< 0.2 JUNE Sr-89 (a)
(a)
Sr-90 (a)
(a)
K-40 1490 150 1290 i 130 Cs-137
<4
<4 l-131
< 0.2
< 0.2 i
i i
All gamma emitters other than those listed were <LLD.
(a) Strontium 89/90 analyses performed on the last monthly sample of each quarter.
81
i TABLE B-12: GAMMA EM!~TER* AND STRONTIUM CONCENTRATIONS IN MILK O
North Anna Power Station, Louisa County, Virginia - 1995 pCl/li 2 Sigma Page 2 of 2 l
MONTH NUCLlDE STATION-12 STATION-13 l
JULY Sr-89
< 0.7
< 0.8 l
Sr-90 1.4 i 0.2 1.21 0.2 l
K-40 1360 140 13201 130 i
<4
<5 1-131
< 0.5
< 0.4 l'
AUGUST Sr-89 (a)
(a)
Sr-90 (a)
(a)
<4
<4 l131
< 0.2
< 0.2 SEPTEMBER Sr89 (a)
(a)
Sr-90 (a)
(a)
K 40 1360 i 140 1240 120 Cs-137
<4
<4 l-131
< 0.2
< 0.3 o
OCTOBER Sr-89
< 0.9
< 0.9
()
Sr-90 0.98 i 0.16 2.110.2 K 40 1320 i 130 1320 t 130 Cs-137
<4
<3 1-131
< 0.2
< 0.5 NOVEMBER Sr-89 (a)
(a)
Sr-90 (a)
(a)
K-40 1330 i 130 1340 i 130 Cs-137
<4
<4 l131
< 0.2
< 0.2 DECEMBER Sr-89 (a)
(a)
Sr-90 (a)
(a)
K-40 1390 i 140 1270 1 130 Cs-137
<4
<4 1-1 31
< 0.3
< 0.3 l
l J
All gamma emitters other than those listed were <LLD.
(a) Strontium 89/90 analyses performed on the last monthly sample of each quarter.
82
1 I
l TABLE B-13: GAMMA EMITTER
- CONCENTRATIONSIN FISH O
North Anna Power Station, Louisa County, Virginia - 1995 pCl/kgi2 Sigma Page 1 of 1 Collection Sample Date Station Type K-40 Co-58 Cs-134 Cs-137 02/13 08 Fish (a) 16201170
< 20
< 20 35.5 i 14.5 03/13 25 Fish (a) 1250 190
< 20
< 20
< 20 02/28 08 Catfish (b) 13701140
< 20
< 10 49.9113.2 03/01 25 Catfish (b) 1220 i 130
< 20
< 20
< 20 08/09 08 Fish (a) 1200 270
< 20
< 30
< 30 08/10 25 Fish (a) 2110 250
< 20
< 20
< 20 08/09 08 Catfish (b) 1650 190
< 20
< 20 26.2 12.9 08/10 25 Catfish 1380 190
< 20
< 20
< 20 t
t v
Avg.
1475 617 37.2123.9 2 s.d.
l l
All gamma emitters other than those listed were <LLD.
(a) Non-bottom dwelling species of gamefish.
(b) Bottom dwelling species of fish.
83
TABLE B-14: GAMMA EMITTER
- CONCENTRATIONSIN FOODNEGETATION O
North Anna Power Station, Louisa County, Virginia - 1995 pCl/kg i 2 Sigma Page 1 of 2 l
Collection l
Date Be-7 K-40 1-131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228 f
STATION 14 There were no food / vegetation samples for all stations during the first quarter, November and December i
l 1995, due to seasonal unavailability.
04/19 1710 170 19200i 1000
< 20
< 20
< 10
< 10
< 200
< 20 05/24 912 i 404 9930 990
< 40
< 70
< 60
< 60
< 900
< 90 06421 1770 i 430 145001 1500
< 30
< 60
< 50
< 50
< 700
< 70 07/19 1870 i 280 250001 2500
< 10
< 40
< 40
< 40
< 600 112i29 08/23 6981 120 7480 i 750
< 10
< 20
< 10
< 10
< 300
< 30 09/20 2640 350 6210 620
< 50
< 50
< 40
< 40
< 700
< 70 10/18 2370 350 4510 i 450
< 10
< 50
< 40
< 40
< 700
< 60 STATION 15 04/19 18801 190 189001 1900
< 40
< 20
< 20
< 20
< 300
< 30 05/24 1130 140 13500 i 1400
< 40
< 20
< 20
< 20
< 400 95.3 i 19.1 06/21 1090 310 9730 970
< 30
< 40
< 30
< 40
< 600 195 1 48 07/19 1310 180 11900 1200
< 10
< 30
< 30
< 20
< 400
< 40 08 23 1170 310 33400 1 3300
<9
< 50
< 40
< 40
< 600
< 60 09/20 1940 290 19000 i 1903
< 30
< 40
< 40
< 40 1250i500
< 70 10/18 994 99 16400 1600
<9
< 10
< 10
< 10
< 200
< 20 STATION 16 04/19 330 i 44 7390 740
< 10
<7
<7
<6
< 100
< 10 05/24 318 1 52 10600 1100
< 50
<9
<9
<9
< 200
< 10 06/21 1310 i 200 10300 1000
< 20
< 30
< 20
< 20
- 00
< 30 07/19 57301 570 27600 2800
< 10
< 50
< 50
< 50
.800 157 40 08/23 720 289 169001 1700
< 20
< 40
< 40 159 i 35
< 700 121 33 09/20 346 79 128001 1300
< 20
< 10
< 10 13.9 7.6
< 200 41.3 i 13.9 10/18 5160 1 520 14200 i 1400
< 10
< 30
< 30
< 30
< 400
< 40 l
1 i
O All gamma emitters other than those listed were <LLD.
84
l t
l l
TABLE B-14: GAMMA EMITTEW CONCENTRATION IN FOODNEGETATION O
'd North Anna Power Station, Louisa County, Virginia - 1995 pCl/kg i 2 Sigma Page 2 of 2 Collection Date Be-7 K-40 1-131 Ru-103 Cs-134 Cs-137 Ra-226 Th-228
!LTATION 21 04/19 2170 220 14400 1400
<7
< 20
< 20 51.2113.4 767 i 255 260126 05/24 1060 360 8070 i 810
< 50
< 60
< 50 57.3 i 32.8
< 700
< 70 06/21 1490 210 13000 i 1300
< 30
< 30
< 30 29.1 14.2 440 i 237 187 22 07/19 2380 240 20800 1 2100
< 10
< 30
< 40 36.9 i 20.1 7631356
< 50 08/23 367 i 138 25600 2600
< 10
< 20
< 20
< 20
< 300
< 30 09/20 2020 200 15000 1500
< 30
< 20
< 20
< 20
< 400
< 40 10/18 639 130 21400 i 2100
<9
< 20
< 20
< 20
< 300
< 30 STATION 23 04/19 1810 180 17300 1700
< 10
< 20
< 20
< 20
< 400
< 40 05/24 502 206 6120 1 610
< 40
< 40
< 40
< 40
< 600 168 30 O
08/21 854*,ss 8830* 880
< 30
< 30
< 20
< 20
< 300
< 30 07/19 1530 390 18400 i 1800
< 10
< 70
< 60
< 60
< 1000
< 100 08/23
< 400 20800 2100
< 10
< 40
< 40
< 40
< 600
< 60 09/20 804 97 18800 i 1900
< 20
< 10
< 10 46.2 i 11.6 < 200
< 20 10/18
?390 350 6350 1 640
< 10
< 60
< 50
< 50
< 900
< 80 Average 1542 2362 14981 13556 56.2 i 95.2 805i668 149 128 2 s.d.
j l
l l
All gamma emitters other than those hsted were <LLD.
85 l
I l
TABLE B-15: DIRECT RADIATION MEASUREMENTS - QUARTERLY AND ANNUAL Q
TLD RESULTS l
North Anna Power Station, Louisa County, Virginia - 1995 mR/Std. Month (30.4 days) 2 Sigma Page 1 of 1 Station First Otr Second Qtr Third Otr Fourth Qtr Quarterly Annual TLD Number 01/05/95 03/29/95 06/28/95 09/27/95 Average 06/2W94 03/29/95 06/28/95 09/27/95 12/28/95 06/28/95 01 7.8 1 0.5 7.5 0.1 7.4 0.2 8.3 1 0.2 7.8 1 0.8 7.7 0.3 02 4.5 0.3 4.2 0.1 4.0 0.1 3.9 i 2.5 4.2 0.5 4.3 1 0.0 03 4.3 0.1 5.2 0.5 3.9 0.2 4.1 1 0.2 4.4 1.1 4.4 i 0.1 04 4.5 0.3 4.410.1 4.3 0.1 4.6 1 0.2 4.5 1 0.3 4.5 1 0.1 05 6.6 0.1 5.3 0.3 5.0 1 0.1 5.3 0.9 5.6 1.4 5.3 1 0.2 05A 5.5 1 0.2 5.2 0.2 5.0 0.1 5.2 0.1 5.2 0.4 5.3 0.2 06 6.7 0.1 6.6 0.2 6.8 0.3 6.8 0.3 6.7 0.2 6.5 0.2 07 5.3 1 0.5 5.1 1 0.2 4.7 0.1 5.2 i 0.2 5.1 0.5 5.1 0.1 21 5.2 0.2 6.0 1 0.3 4.8 0.1 5.4 0.3 5.4 1.0 5.1 i 0.1 22 6.3 0.3 6.6 0.8 6.0 0.2 6.2 0.1 6.3 0.5 6.0 0.1 23 7.0 0.3 6.4 0.2 6.3 0.2 7.0 0.1 6.7 i 0.8 7.1 0.4 24 5.2 0.2 5.3 0.2 4.9 0.1 5.3 0.3 5.2 1 0.4 5.2 0.1 Average 5.7 2.2 5.7 1 2.0 5.3 2.2 5.0 1 2.5 5.6 2.5 5.5 i 2.2 i
i 2 s.d.
l 86
}
TABLE B-16: DIRECT RADIATION MEASUREMENTS-Q SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1995 mR/Std. Month (30.4 days) 2 Sigma Page 1 of 2 Station First Qtr.
Second Qtr.
Third Qtr.
Foruth Otr.
Average Number 01/05 03/29 03/29-06/28 06/28-09/27 09/27-12/28 i 2 s.d.
N-1 6.1 1 0.3 6.0 i 0.3 5.7 i 0.2 6.510.1 6.1 1 0.7 N-2 5.6 i 0.4 4.7 0.1 4.8 i 0.1 5.3 1 0.2 5.1 0.8 NNE-3 8.2 0.8 8.3 0.1 8.010.1 9.4 i 1.0 8.5 1.3 NNE4 5.2 0.3 6.1 0.2 5.0 1 0.2 5.5 i 0.4 5.5 1.0 NE-5 7.9 0.5 8.2 0.2 7.0 0.1 8.0 0.1 7.8 i 1.1 NE-6 5.41 0.3 5.2 0.2 4.9 0.4 5.6 i 0.7 5.3 0.6 ENE-7 6.6 0.3 8.4 0.5 6.2 1 0.2 6.6 0.2 7.n i 2.0 ENE-8 (a) 4.3 1 0.2 4.2 0.3 4.6 1 0.3 4.4 i 0.4 E-9 6.9 0.2 6.6 0.1 6.5 i 0.2 7.1 1 0.3 6.8 0.6 E-10 6.2 0.0 6.8 0.6 5.510.1 6.1 i 0.3 6.2 1 1.1 ESE-11 5.91 0.1 5.6 0.1 5.8 i 0.9 6.5 1 0.8 6.0 0.8 ESE-12 6.8 1.1 6.5 0.4 6.6 i 0.4 6.8 0.2 6.7 0.3 SE 13 6.4 0.2 5.8 i 0.1 5.7 0.1 5.8 i 0.8 5.9 1 0.6 SE-14 8.9 1 0.5 8.5 i 0.7 8.3 0.2 8.5 i 0.2 8.6 i 0.5 SSE-15 5.9 0.3 7.2 1 0.6 6.6 1 0.2 6.7 0.1 6.6 1.1 SSE-16 5.3 0.3 5.1 0.3 4.9 0.2 5.3 i 0.2 5.2 i 0.4 S-17 8.3 0.1 7.7 0.8 7.9 0.2 8.4 1 0.8 8.1 1 0.7 S-18 4.5 0.7 4.0 0.3 4.1 0.1 4.4 i 0.3 4.3 1 0.5 O
SSW-,9 7.8 i o.7 e.2
- 0.8 7.0 1 0.4 7.5 i o.4 7.e *,.e SSW-20 4.2 0.2 3.9 0.1 4.0 0.0 4.3 0.4 4.1 0.4 SW-21 5.5 0.2 5.0 0.2 5.1 0.1 5.4 0.5 5.3 1 0.5 SW-22 6.4 0.4 6.3 0.2 6.0 0.4 6.6 0.2 6.3 0.5 WSW-23 7.6 0.2 7.7 1.3 7.4 i 0.3 7.9 0.4 7.7 i 0.4 WSW-24 6.31 0.3 6.2 0.1 6.2 0.1 6.6 1 0.2 6.3 0.4 W-25 8.5 0.3 8.2 0.8 7.7 0.1 8.3 0.2 8.2 1 0.7 W-26 4.51 0.4 4.6 0.1 4.6 0.1 5.1 0.0 4.7 0.5 WNW-27 5.1 0.1 5.2 0.2 4.9 0.2 5.2 i 0.2 5.1 i 0.3 WNW-28 5.5 1.6 4.7 0.1 4.5 0.1 5.0 1 0.1 4.9 1 0.9 NW-29 E.9 0.1 6.7 0.1 7.3 0.2 7.8 i 0.5 7.2 i 1.0 NW-30 5.1 0.2 6.2 0.2 4.7 0.1 5.3 i 0.1 5.3 1.3 NNW-31 6.0 0.3 6.3 0.5 4.8 0.2 5.7 1 0.5 5.7 i 1.3 NNW-32 5.8 0.1 6.7 0.3 5.2 0.2 5.7 0.3 5.9 1 1.2 N-33 6.6 0.2 6.3 0.8 5.9 0.1 6.5 i 0.2 6.3 0.6 N-34 5.2 0.2 4.7 0.3 4.5 0.2 4.2 1.6 4.7 i 0.8 NNE-35 8.8 i 0.4 8.3 0.3 7.9 0.1 8.9 0.3 8.5 1 0.9 NNE-36 5.7 0.1 5.4 0.1 5.4 0.4 5.7 i 0.2 5.6 1 0.3 NE-37 8.1 0.2 7.8 0.6 7.0 0.2 7.9 1 0.2 7.7 i 1.0 NE-38 5.6 0.2 5.1 0.1 4.9 0.2 5.7 0.6 5.3 1 0.8 ENE-39 6.9 0.1 6.9 1.4 6.5 0.2 7.6 0.8 7.0 0.9 l
ENE-40 (a) 4.2 0.1 4.2 0.1 4.9 0.8 4.4 i 0.8 j
E-41 7.2 0.2 7.7 0.5 6.5 0.2 7.7 0.1 7.3 1.1 E-42 6.2 0.2 6.5 0.1 5.7 0.1 6.8 1 0.2 6.3 0.9 ESE-43 6.1 0.1 6.5 0.2 5.4 0.1 6.410.1 6.1 1 1.0 ESE-44 6.8 i 0.1 6.6 0.9 6.1 0.2 7.8 1.3 6.8 1.4 SE-45 6.5 0.2 5.7 0.2 5.9 0.0 6.8 0.9 6.2 1.0 O
(a) TLD missing.
87 l
l
l TABLE B-16: DIRECT RADIATION MEASUREMENTS 0
SECTOR QUARTERLY TLD RESULTS North Anna Power Station, Louisa County, Virginia - 1995 mR5/Std. Month (30.4 days)i 2 Sigma Page 2 of 2 Station First Otr Second Qtr Third Qtr Fourth Qtr Average l
Number 01/05-03/29 03/29-06/28 06/28-09/27 09/27-12/28 2 S.d.
I SE-46 8.61 0.3 8.4 0.2 8.1 1 0.2 9.4 i 1.0 8.6 i 1.1 SSE-47 6.8 0.2 6.6 0.3 6.0 i 0.2 6.8 0.3 6.6 i 0.8 l
SSE-48 5.71 0.1 5.3 0.5 4.7 0.1 5.7 i 0.2 5.4 0.9 S-49 8.61 0.1 8.4 0.6 7.9 0.3 9.0 1 0.9 8.5 i 0.9 l
S-50 4.6 0.1 5.2 0.3 3.7 0.1 5.0 0.4 4.6 i 1.3 SSW-51 8.4 0.3 9.0 0.5 7.0 1 0.2 8.3 1 0.1 8.2 1 1.7 i
SSW-52 4.7 0.1 4.2 0.1 4.010.1 5.0 0.1 4.5 1 0.9 SW-53 5.5 1 0.1 5.1 0.8 5.010.1 5.7 0.3 5.3 i 0.7 l
SW-54 6.5 0.1 6.7 0.1 6.3 1 0.2 6.7 i 0.3 6.6 1 0.4 WSW-55 7.4 0.1 7.0 0.5 7.1 0.1 8.3 0.3 7.5 1.2 WSW-56 6.0 0.3 5.3 0.6 6.1 i 0.1 6.7 0.7 6.0 1 1.1 W-57 8.6 0.2 7.3 1.2 7.4 0.3 8.4 0.4 7.9 i 1.3 W-58 4.61 0.1 5.2 0.9 4.5 1 0.1 5.3 0.3 4.9 1 0.8 l
WNW-59 5.2 0.2 4.7 1 0.1 4.8 1 0.1 5.4 i 0.2 5.0 1 0.7 l
WNW-60 5.6 0.4 4.6 0.1 4.710.1 5.2 i 0.2 5.0 1 0.9 NW-61 6.8 0.3 6.1 0.3 7.2 0.1 8.1 1 0.2 7.1 1 1.7 NW-62 5.0 0.1 5.2 0.2 4.6 1 0.1 5.3 0.3 5.0 1 0.6 l
NNW-63 5.7 0.4 5.2 0.1 5.2 i 0.1 6.1 0.7 5.6 0.9 i
i (s)
NNW-64 5.8 0.1 5.7 0.5 5.3i0.2 6.1 0.7 5.7 i 0.7 C-1 5.11 0.1 5.1 0.1 4.8 1 0.2 5.4 04 5.1 0.5 C-2 5.2 0.2 5.1 0.2 4.8 0.1 5.1 1 0.2 5.1 1 0.3 C-3 4.9 0.3 5.1 0.3 5.010.1 4.3 1 2.8 4.8 0.7 C-4 5.0 0.1 5.3 0.4 4.8 0.1 5.4 0.1 5.1 0.6 C-5 4.2 0.1 4.0 0.1 3.9 0.2 4.4 0.1 4.1 0.4 C-6 4.2 0.4 3.9 0.1 4.0 0.2 4.5 i 0.1 4.2 1 0.5 C-7 6.2 0.4 6.8 0.6 5.7 0.1 6.5 0.2 6.3 1 0.9 C-8 6.2 0.2 5.9 0.2 5.7 1 0.2 6.2-10.3 6.0 1 0.5 Average 6.2 2.5 6.1 2.7 5.7 2.4
- 6. 4 2.7 6.2 5.5 l
88
A_
m-aa_
..-~ _ _-ma-d--r w---
- -h-m.
mA.A- -.
4 AwaM
-s--A a + *. +
w e-4-&--
m 4-A--
a m
a w
a m-----
O J
O Areenoix c LAND USE CENSUS - 1995 O
1
1 VIRGINIA POWER l
NORTH ANNA POWER STATION O
A i R aioionic i savire -e t i t a use ce s s o t ror 1995 l
July (1-31) i l
Nearest Nearest Site Milk
- Meat Milk
- Veg. Garden Sector Resident Boundary Cow Animal Goat 500 Sq Ft.
N 2.14 1.40 3.23 2.98 NNE 1.51 1.36 4.22 1.87 NE 1.57 1.32 2.51 1.80 ENE 3.17 1.31 4.12 3.17 E
1.95 1.33 1.95 l
ESE 2.53 1.37 7.74 5.63 SE 2.20 1.41 2.20 2.20 SSE 1.47 1.47 3.83 1.55 S
1.67 1.52 2.32 1.67 i
SSW 2.30 1.62 6.61 2.20 SW 4.83 1.70 4.83 WSW 2.86 1.75 2.86 2.86 W
2.60 1.71 3.20 WNW 1.61 1.64 6.13 4.28 NW 1.57 1.56 1.77 NNW 1.72 1.45 3.57 1.80 i
l
- Note:
No milk cow or goats within a five mile radius of North Anna Power Station l
KM = Kilometer 89 l
VIRGINIA POWER NORTH ANNA POWER STATION O
A i R aioionie i E viron-e t i t a use ce s s a t ror 1995 l
July (1-31) l Nearest Nearest Site Milk
- Meat Milk
- Veg. Garden Sector Resident Boundary Cow Animal Goat 500 Sq Ft.
M M
M M
M M
N 1.33 0.87 2.01 1.85 NNE 0.94 0.85 2.62 1.16 NE 0.98 0.82 1.56 1.12 ENE 1.97 0.81 2.56 1.97 1
l E
1.21 0.83 1.21 l
ESE 1.57 0.85 4.81 3.50 SE 1.37 0.88 1.37 1.37 l
l SSE 0.91 0.91 2.38 0.96
'%/U S
1.04 0.94 1.44 1.04 SSW 1.43 1.01 4.11 1.37 l
l SW 3.00 1.06 3.00 i
WSW 1.78 1.09 1.78 1.78 l
W l.61 1.06 1.99 WNW 1.00 1.02 3.83 2.66 i
NW 0.98 0.97 1.10 l
NNW 1.07 0.90 2.22 1.12 i
i O
- Note:
No milk cow or goats within a five mile radius of North Anna Power Station M = Mile 9C
VIRGINIA POWER NORTH ANNA POWER STATION n
COMPARISON OF THE 1995 TO 1994 LAND USE CENSUS I.
Changes in the nearest resident status as compared to previous year are as follows:
a.
E Sector:
2.03 Km (1994) to 1.95 Km (1995) b.
ESE Sector:
2.60 Km (1994) to 2.53 Km (1995)
II.
No changes were observed in the nearest site boundary distances.
III.
No changes were observed in the nearest milk cow / goat status.
IV.
Changes in nearest vegetable garden as compared to previous year are as
- follows, a.
E Sector:
2.53 Km (1994) to 1.95 Km (1995)
V.
No changes were observed in the nearest meat animal status.
O i
)
91
1 lO i
4 i
O APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES O
ANALYTICAL PROCEDURES SYNOPSIS i
'- O Appendix D is a synopsis of the analytical procedures performed on samples collected for the North Anna Power Station's Radiological Environmental Monitoring Program. All analyses l
have been mutually agreed upon by VEPCO and Teledyne Brown Engineering and include those recommended by the USNRC Branch Technical Position, Rev.1, November 1979.
4 ANALYSIS TITLE PAGE G ross B eta Analysis of S amples...................................................................... 93 Airbome Particulates............................................................................ 93 Water.............................................................................................94 l
Analysis of Samples for Tritium (Liquid Scintillation).............................................. 95 i
Analysis of S amples for Strontium-89 and -90................................................... 96 Total Wate r...................................................................................... 9 6 Milk..........................................................................................96 S oil and Sediment................................
..........................................96 4
i A Org an ic S ol i d s.................................................................................. 97 V
2 Air Particu1ates.................................................................................99 1
1 Analysis o f S amples for lodine-131................................................................. 99 Milk or Water..............................................................................99 Gamma Spectrometry of S amples..................................................................... 100 M ilk and Water............................................................................ 100 Dried Solids other than Soils and Sediment................................................ 100 Fish......................................................................................100 i
Soils and Sediments...........
.......................................................100 Charcoal Cartridges (Air lodine)..
....................................................100 Airbome Particulates..
...........................................................100 Environmental Dosimetry......................
.......................................102 C
92
GROSS BETA ANALYSIS OF SAMPLES O-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 l
air particulate filter, supplied by the customer, is counted as the blank.
l Calculations of the msults, the two sigma error and the lower limit of detection (LLD):
RESULT (pCi/m3)
((S/r)- (B/t))/(2.22 V E) l
=
TWO SIGMA ERROR (pCi/m3) 2((S/T ) + (B/t ))l/2 (2.22 V E) 2 2
/
=
LLD (pCi/m3) 4.66 (BM)/(2.22 V E t)
=
I whem:
Gross counts of sample including blank S
=
Counts of blank B
=
Counting efficiency E
=
Number of minutes sample was counted T
=
O Number ormim - blank was counted t
=
Sample aliquot size (cubic meters)
V
=
1 o
O l
93
i l
DETERMINATION OF GROSS BETA ACTIVITY
'Q IN WATER SAMPLES Introduction The procedures described in this section are used to measure the overall radioactivity 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 ir.to a 2-inch diameter l
stainless steel planchette which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps.
l Residue mass is determined by weighing the planchette before and after mounting the l
sample. The planchette 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.
O.
Detection Capability Detection capability depends upon the sample volume actually mpresented on the planchette, the background and the efficiency of the counting instrument, and upon self-absorption of beta l
particles by the mounted sample. Because the radioactive species are not identified, no decay corrections am made and the reponed 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/l at the 2.83 sigma level), assuming that I liter of I
sample is used and that5 gram of sample residue is mounted on the planchette. These figures are based upon a counting time of 50 minutes and upon repmsentative values of counting efficiera 5 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.
]
i i
!O 1
94 i
l
l ANALYSIS OF SAMPLES FOR TRITIUM O
(Liquid Scintillation) s
.WalC[
Ten mi!!iliters of water are mixed with 10 ml of a liquid scintillation " cocktail" and then the mixture is counted in an automatic liquid scintillator, Calculation of the results, the two sigma error and the lower limit detection (11D) in pCi/l:
(N-B)/(2.22 V E)
RESULT
=
2((N + B)/At)1/2 (2.22 V E)
/
TWO SIGMA ERROR
=
l 4.66 (B/At)1/2 (2.22 V E )
/
=
the gross epm of the sample where:
N
=
the background of the detector in cpm B
=
conversion factor changing dpm to pCi 2.22
=
volume of the sample in ml V
=
efficiency of the detector E
=
counting time for the sample At
=
I 1
' O 95
ANALYSIS OF SAMPLES Q
FOR STRONTIUM-89 AND -90 Water Stable strontium carrier is added to 1 liter of sample and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO )2 using nitric acid. A barium scavenge and an 3
iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a l
minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, I'
dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrCO from the sample after yttrium separation. This precipitate is mounted on a 3
nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.
Milk Stable strontium carrier is added to 1 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 SrNO using fuming (90%) nitric acid. A barium chromate scavenge 3
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 planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC0 from the sample after yttrium separation. This precipitate 3
1 l
is mounted on a nylon planchette 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 l
precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO )2 using 3
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 l
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 planchette and is counted in a j
low level beta counter to infer Sr-90 activity. Strontium-89 activity is determined by precipitating SrC0 from the sample after yttrium separation. This precipitate is mounted on a nylon planchette 3
and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.
I 96
i I
i i
O o r s = =ic s aiid -
l A wet pordon of the sample is dried and then ashed in a muffle furnace. Stable strontium l
l 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(NO ) using 3
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 pm-l cipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer strontium-90 activity.
Strontium-89 activity is determined by precipitating SrC03 rom the sample after yttrium f
2 separation. This precipitate is mounted on a nylon planchette and is covered with an 80 mg/;m aluminum absorber for low level beta counting.
l e
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 volurne by evaporation. Strontium is precipitated as Sr(NO )2 using fuming (90%) nitric acid. A barium 3
scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is Q
performed, followed by addition of stable yttrium carrier and a 7 to 10 day period for yttrium j
ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-pmcipitated as oxalate. The
[
yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer i
strontium-90 activity. Strontium-89 activity is determined by precipitating SrC0 from the sample 3
j after yttrium separation. This precipitate is mounted on a nylon planchette and is covered with 80 2
mg/cm aluminum absorber for low level beta counting.
l Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/ volume or pCi/ mass:
= (N/Dt-B 'U )/(2.22 V Y DFSR-89 SR-89)
E RESULT Sr-89 C A 3
TWO SIGMA ERROR Sr-89
= 2((N/Dt+B +B )/At)l/2 (2.22 V Y DF E
SR-89 SR-89)
/
S C A t
= 4.66((B +B )/At)l/2 (2.22 V YS DFSR-89 ESR-89) l LLD Sr-89 C
A
/
RESULT Sr-90
= (N/At - B)/(2.22 V Y Y DF IF E) 1 2
= 2((N/At+B)/At)l/2 (2.22 V Y Y DF E IF))
/
1 2 TWO SIGMA ERROR Sr-90
= 4.66(B/At)l/2 (2.22 V Y Y IF DF E)
/
97
l l
totalcounts from sample (counts)
WHERE:
N
=
O co ti s ti-e r- -rie <-i >
ei background rate of counter (cpm) using absorber configuration B
=
C dpm/pCi 2.22
=
volume or weight of sample analyzed V
=
background addition from Sr-90 and ingrowth of Y-90 B
=
3 0.016 fK) + (K) EY/ abs)(IGy.90)
B
=
3 chemical yield of strontium Y
=
3 decay factor from the mid collection date to the counting DF
=
SR-89 date for SR-89 cfficiency of the counter for SR-89 with the 80 mg/cm.sq.
E
=
SR-89 aluminmn absorber (NAt - B )Y-90 (Ey.90IFy.90DFy.90 1)
C
/
Y K
=
the decay factor for Y-90 from the " milk" time to the mid DF.99)
=
y count time efficiency of the counter for Y-90 E 99
=
y ingrowth factor for Y-90 from scavenge time to milking time IF _99
=
y the ingrowth factor for Y-90 into the strontium mount from IG.99
=
y the " milk" time to the mid count time the efficiency of measuring SR-90 through a No. 6 absorber 0.016
=
the efficiency of counting Y-90 through a No. 6 absorber EY
=
fg, background rate of counter (cpm)
B
=
chemicalyield of yttrium Y
=
3 chemical yield of strontium Y2
=
decay factor of yttrium from the radiochemical milking time to DF
=
the mid count time efficiency of the counter for Y-90 E
=
ingrowth factor for Y-90 fnxn scavenge time to the radio-IF
=
chemical milking time O
98
~
l ANALYSIS OF SAMPLES FOR IODINE.131 O
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, is reduced with hydroxylamine hydrochloride and is 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 and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchette 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/l:
i (N/At-B)/(2.22 E V Y DF)
RESULT
=
2((N/At+B)/At)l/2 (2.22 E V Y DF)
/
TWO SIGMA ERROR
=
= 4.66(B/At)l/2 (2.22 E V Y DF)
/
A IlD
=
U total counts from sample (counts) where:
N
=
counting time for sample (min)
At
=
background rate of counter (cpm)
B
=
dpm/pCi 2.22
=
volume or weight of sample analyzed V
=
chemical yield of the mount or sample counted Y
=
l DF decay factor from the collection to the counting date
=
E cfficiency of the counter for I-131, coriected for self
=
l l
absorption effects by the formula E (exp-0.0061M)/(exp-0.0061M )
E
=
3 3
E efficiency of the counter determmed from an I-131
=
3 standard mount mass of Pdl on the standard mount, mg Ms
=
2 M
mass of PDI3 on the sample mount, mg
=
i
'O 99
GAMMA SPECTROMETRY OF SAMPLES O
Milk and Water A 1.0 liter Marinelli beakeris filled with a mpresentative aliquot of the sample. '1he sample is then counted for approximately 3000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition systere 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 tamd 1-liter Marinelli and weighed. The samph is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which perfonns pulse height analysis.
Fish 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.
G V
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 1-131 of each charcoal cartridge can be determined (assur.iing 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.
Air Particulate The thirteen airborne particulate filters for a quarterly composite for each field station are O
aiisned one in front of another and then counted for at ieast six hours with a shieided Ge(Li) 100
detector coupled to a mini-computer-based data acquisition system which performs pulse height Q
analysis.
A mini-computer software program defines peaks by certain changes in the slope of the spect:um. 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. 'Ihe calcuiation of msults, two sigma error and the lower limit of detection (LLD) in pCi/ volume of pCi/ mass:
1 (S-B)/(2.22 t E V F DF)
RESULT
=
2(S+B)l/2 (2.22 t E V F DF)
TWO SIGMA ERROR
/
=
4.66(B)l/2 (2.22 t E V F DF)
/
=
Area, in counts, of sample peak and background i
where:
S
=
(region of spectrum ofinterest)
B Background area, in counts, under sample peak,
=
determmed by a linear interpolation of the representative backgrounds on either i
side of the peak l
length of time in minutes the sample was counted
}
l t
=
dpm/pCi f
2.22
=
O oe'ecter erricie cx ter e e 8v eri 'erest e
and geometry of sample V
sample aliquot sLa (liters, cubic meters, kilograms,
=
l or gans) l fractional gamma abundance (specific for each F
=
emitted gamma) decay factor from the mid-collection date to the DF
=
I counting date I
l-l l
t f
I l
1 i O 101 l
ENVIRONMENTAL DOSIMETRY i O Teledyne Brown Engineering uses a CaSO :Dy thermoluminescent dosimeter (TLD) which 4
the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other l
features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.
l Following the field exposure period the TLDs are placed in a Teledyne Brown Engineering Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission l
(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 TLD after every field use.
The transit controls am read in the same manner.
Calculations of msults and the two sigma error in net milliroentgen (mR):
D = (D +D +D +D )/4 RESULT
=
j 2 3 4 2((D -D)2+(9 -D)2+(9 -D)2+(9 9)2)/3)1/2 TWO SIGMA ERROR
=
g 2
3 4
l i
the net mR of area 1 of the TLD, and similarly for D, D, and 04 WilERE:
D 2 3
=
I K/R - A Di l
j j
the instrument reading of the field dose in area 1 I
=
the known exposure by the Cs-137 source K
=
l 3
the instrument reading due to the Cs-137 dose on area 1 R
=
average dose in mR, calculated in similar manner as above, A
=
of the transit control TLDs the average net mR of all 4 areas of the TLD, D
=
4 h
N
- O 102
i i
4 4
lO 4
i 4
1 d
4 j
N i
]Q APPENDIX E EPA INTERLABORATORY COMPARISON PROGRAM 3
i i
N 4
i i
i
l EPA Interlaboratory Comparison Program
'O Teledyne Brown Engineering participates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. In this section the 1995 data summary tables are presented for isotopes in the various sample media applicable to the North Anna Power Station's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence.
l r
O l
l O
103 l
O O
O VEPCO - NORT". MNA EPA INTERIABORATORY CD.MPARISON PROGRAM 1995 (Pege I of 2)
EPA Date TI Malled Date EPA EPA TI Norm Dev.
- Warning Preparation Re sults Issued Results Media Nuclide Results(a)
Results(b)
(Known)(c)
- *
- Action 01/13/95 03/24/95 04/21/95 Water Sr-89 20.0 i 5.0 19.00 2.65
-0.35 Sr-90 15.0 5.0 14.00 0.00
-0.35 01/27/95 03/24/95 03/24/95 Water Gr-Alpha 5.0 i 5.0 5.00 i 1.00 0.00 Gr-Beta 5.0 1 5.0 6.00 i 1.00 0.35 02/03/95 03/20/95 04/21/95 Water 1-131 100.0 10.0 88.33 2.31
-2.02
- * (d) 02/10/95 04/07/95 05/23/95 Water Ra-226 19.1 i 2.9 20.67 i 0.58 0.94 Ra-228 20.0 1 5.0 18.67 i 0.58
-0.46 03/10/95 04/06/95 05/19/95 Water II-3 7435.0 i 744.0 7066.67 il15.47
-0.8G 03/17/95 05/12/95 06/05/95 Water Pu-239 11.1 1.1 10.33 1 0.58
-1.21 04/18/95 06/30/95 08/18/95 Water Gr-Beta 86.6 i 10.0 80.33 1 2.52
-1.09 Sr-89 20.0 1 5.0 20.67 i 1.15 0.23 yo Sr-90 15.0 1 5.0 14.67 1 0.58
-0.12 Co-60 29.0 1 5.0 31.67 i 2.08 0.92 l
Cs-134 20.0 i 5.0 19.67 i 1.73
-0.12 l
Cs-137 11.0 1 5.0 11.67 i 1.53 0.23 I
Gr-Alpha 47.5 t 11.9 39.67 i 2.52
-1.14
)
Ra-226 14.9 i 2.2 15.67 i 0.58 0.60 1
Ra-228 15.8 i 4.0 13.00 i 1.73
-1.21 06/09/95 08/09/95 02/26/96 Water Co-60 40.0 1 5.0 42.33 i 2.52 0.81 Zn-65 76.0 1 8.0 82.33 i 3.51 1.37 Cs-134 50.0 1 5.0 46.67 i 2.08
-1.15 Cs-137 35.0 1 5.0 37.67 i 1.15 0.92 Ba-133 79.0 i 8.0 74.33 1 2.08
-1.01 06/16/95 08/09/95 09/05/95 Water Ra-226 14.8 1 2.2 15.00 1 0.00 0.16 Ra-228 15.0 1 3.8 14.00 i 0.00
-0.46 07/14/95 08/09/95 09/05/95 Water Sr-89 20.0 i 5.0 18.33 i 1.53
-0.58 Sr-90 8.0 1 5.0 8.0 0.00 0.00 07/21/95 08/18/95 09/27/95 Water Gr-Alpha 27.5 1 6.9 18.33 i 1.53
-2.30
- * (c)
Gr-Beta 19.4 1 5.0 19.33 i 1.53
-0.02 08/04/95 09/01/95 09/29/95 Water 11-3 4872.0 1 487.0 4866.67 il52.75
-0.02 l
Footnotes at end of table.
O O
O VEPCO - NORTH ANNA EPA INTERIABORATORY COMPARISON PROGRAM 1995 (Page 2 of 2)
EPA Date TI Malled Date EPA EPA TI Norm Dev.
" Warning Preparation Re suits Issued Results Media Nuclide Results(a)
Results(b)
(Known)
"* Action 08/25/95 10/21/95 02/29/96 Air Filter Gr-Alpha 25.0 6.3 23.67 i 1.53
-0.37 Gr-Beta 86.6 i 10.0 84.67 i 1.53
-0.33 Sr-90 30.0 1 5.0 25.33 1 0.58
-1.62 Cn-137 25.0 1 5.0 27.00 i 1.00 0.69 09/15/95 11/10/95 02/26/96 Water h-226 24.8 i 3.7 27.33 i 1.15 1.19 Ra-228 20.0 1 5.0 14.67 i 0.58
-1.85 09/29/95 11/28/95 02/29/96 Milk Sr-89 20.0 i 5.0 23.33 3.06 1.15 Sr-90 15.00 1 5.0 16.33 i 0.58 0.46 1-131 99.0 10.0 103.33 i 5.77 0.75 Cs-137 50.0 i 5.0 54.67 i 2.52 1.62 Total K 1654.0 83.0 1683.33 il36.50 0.61 10/06/95 11/10/95 02/26/96 Water 1-131 148.0 i 15.0 150.00 1 0.00 0.23 E$
w 10/27/95 12/01/53 03/04/96 Water Gr-Alpha 51.2 i 12.8 37.00 1 3.00
-1.92 Gr-Beta 24.8 i 5.0 25.33 i 1.53 0.18 Footnotes:
(a) Average i experinnental sigma.
(b) Expected laboratory precision (1 sfgma. I determination)
(c) Normalized deviation from the known.
(d) The normaltzed deviation marginally exceeded the warning level and an apparent trend in the results appeared. The cause was a probable high bias in the beta counting emetency.
Check source control charts did not indimte any changes in the counting equipment, so the I-131 calibrauon was suspected. New I-131 calibrations were performed July 3 through 6.
1995 after receiving a new standard from the EPA. The Intercomparison sample data rheets were recalculated with the new emclencies and the average result was in excellent agreement with the EPA (96 pct /l versus the EPA value of 100 pCl/I). The discrepancy in the I.131 emetency between the current calibration and the previous one (aside from the uncertainty in the standard) appears to be an abnormally low yield in the preparation of the standard for the older calibration which created a high bias in the counter emclencies.
The bias was less than ten percent, therefore further corrective action or revision of previously reported data is deemed not necessary.
(e) The mineral salt content of the water used by the EPA to prepare the samples has been shown to vary substantially throughout the year. Absorption curves to account for mount weight may vary from the true absorption characteristics of a spectfle sample. Previous results do not indicate a trend toward "out of contror for gross alpha / beta analysis and the normalized deviation from the grand average is only -0.36. The normalized deviation from the known for TBE-ES does rot exceed three standard deviation and internal spikes have been in control. No mrrective action is planned at this Ume.
O O
O EPA CROSS CHECK PROGRAM GROSS ALPHA IN AIR PARTICULATES (pg.1 of 1) 80 60 -
40 -
o k
f T
o
[o 1
'j, 1
5 i
n m
L 5
,7 S
20 -
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i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o Tl 3 Sigma o EPA i 3 Sigma
O O
O EPA CROSS CHECK PROGRAM GROSS BETA IN AIR PARTICULATES (pg.1 of 1) 160 140 -
"o 120 -
100 -
D o
.-S 80 -
E i
I'
}'
's 60 -
H
,E'l
'b b
h f'
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Do 20 -
0 i
i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o TI 3 Sigma o EPA i 3 Sigma
O O
O EPA CROSS CHECK PROGRAM l
STRONTIUM-90 IN AIR PARTICULATES (pg.1 of 1) 80 70 -
60 -
50 -
40 -
o k
30 -
o o
10 -
II 0-,
981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o Tl 3 Sigma o EPA 3 Sigma
O O
O EPA CROSS CHECK PROGRAM CESIUM-137 IN AIR PARTICULATES (pg.1 of 1) 80 P
60 -
11 40 -
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O O
O.
1 EPA CROSS CHECK PROGRAM i
STRONTIUM-89 IN MILK (pg.1 of 1) 100
[
?
80 -
f t
i l
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(
l
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O O
O EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK (pg.1 of 1) 80 t
60 -
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i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o TIi 3 Sigma o EPA i 3 Sigma i
O O
O EPA CROSS CHECK PROGRAM POTASSIUM-40 IN MILK (pg.1 of 1) 2600 i
2400 -
2200 -
2000 -
1800 -
o
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1600 -
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I 1200 -
1000 -
800 -
600 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 o Tl 3 Sigma o EPA i 3 Sigma
O O
O EPA CROSS CHECK PROGRAM IODINE-131 IN MILK (pg.1 of 1) 160 140 -
Ip 120 -
o i1 100 -
,p
'l, f
il 80 -
e si
=
5 60 -
X" C
O 13 F
I
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O EPA CROSS CHECK PROGRAM CESIUM-137 IN MILK (pg.1 of 1) 100 80 -
il l>
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i 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 O Tl13 Sigma o EPA i3 Sigma
O O
O EPA CROSS CHECK PROGRAM l
GROSS ALPHA IN WATER (pg.1 of 1) 180 l
160 -
140 -
120 -
100 -
h b
80 -
E O-1 1
~
)
G S
60 -
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O O
O EPA CROSS CHECK PROGRAM l
l GROSS BETA IN WATER (pg.1 of 2) l 220 200 180 II 160 l
' s o
140 8
3
~
120 i,
100 80 4 I 60 40
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O EPA CROSS CHECK PROGRAM GROSS BETA IN WATER (pg. 2 of 2) 260 220 -
180 -
D 140 -
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EPA CROSS CHECK PROGRAM TR! TIUM IN WATER (pg.1 of 2) 5000 f
4000 il
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2000 r
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-1000 1981 1982 1983 1984 1985 O Tl13 sigma o EPA 13 sigma
I O
O O
EPA CROSS CHECK PROGRAM TRITIUM IN WATER (pg. 2 of 2) 16000 14000 -
12000 -
10000 -
og m*
ig 8000 -
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6000 -
- [
<g ef l
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O EPA CROSS CHECK PROGRAM IODINE-131 IN WATER (pg.1 of 1) 180 160 -
Do 140 -
120 -
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=
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O O
O EPA CROSS CllECK PROGRAM COBALT-60 IN WATER (pg 1 of 2) 100 80 l
i L
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COBALT-60 IN WATER (pg. 2 of 2) 100 i
80 -
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EPA CROSS CHECK PROGRAM CESIUM-134 IN WATER (pg.1 of 2) f i
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EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER (pg. 2 of 2) 80 70 -
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60 -
50 -
40 -
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