ML20101B012
| ML20101B012 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 92-269, NUDOCS 9205050061 | |
| Download: ML20101B012 (123) | |
Text
..
V11tOINIA l$Ll:CTitIC AND l'OWEll COh!PANY
}{ ICil BLOND, V11tOINIA. 2 0 0 61 April 29, 1992 United States Nuclear Regulatory Commission Serial No.92-269 Attention: Document Control Desk NAPS /JHL Washington, D. C. 20555 Docket Nos.
50 338 50 339 License Nos. NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH - ANNA POWER STATION UNIT NOS.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 Unit Nos.1 and 2 for 1991.
If you have any questions or requi.e additionalinformation, please contact us.
Very truly yours, n,,g ib W. L. Stewart Senior Vice President - Nuclear cc:
U. S. Nuclear Regulatory Commission Region ll 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station c'
9205050061 911231
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Virginia Electric anct Potver Contpany Nortl) Anna Power Station 1
A Racifological Environntenf al Monitoring Progrant Jarmary 1,1991 to Decernber 31,1991 r
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Prepared by VIRGINIA ELECITUCMD 1M7!R COMI%VY and TEIJ! DYNE ISOIDPES 1
- _ _ _______._ y Annual Radiological Environsnental Opetriling Report North Anna PotverStation January 1,1991 to Decernber 31,1991 Prepared by Y}
- 7 James 11. Ilreeden, Supervisor Radiological Analysis E. /pu f j
Reviewed by:
l' Erich W. Dreyer l
Supervisor liealth Physics Technical Services l
l Approved by:
.-8 9 Y h c Alan 1I,/M. afford Superintendent Radiological Protection
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Table OfContents ni
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V Section Title Page Forward
............................................7 Executive Summay.
.. 8 1.
Introduction.........
.... 10 II.
Nuclear Power And The Environment: In Perspective...............12 III.
Sampling And Analysis Progmm....
........................25
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IV.
Program Exceptions........
.. 41 s
V.
Summary And Discussion Of W1 Analyticalitesults.
. 43 A. Airtome Exposure Pathway.,,,
.43
- 1. Air kxline/Paniculates ;
...... 43
- 2. Precipitation..
..........45
- 3. Soil..........
. 45 O
B. Waterbome Exposure Pathway.
.46
- 1. Grount'1 J! Water..
.46
- 2. River "' ater.
.46
- 3. Surface Water.
.46 C. Aquatic Exposure Pathway......
. 48
- 1. Sediment / Silt.
......48
- 2. Shoreline Soil.
.48 D. Ingestion Exposure Pathway
. 52
- 1. Milk.
.........52
- 2. Fish..
. 52
- 3. Food / Vegetation...
. 52 E. Direct Radiation Exposure Pathway...
. 54
- 1. TLD Dosimeters....
. 54 VI.
Conclusion
. 56 m
i s
V 3
Table ofContents (Continued) nv Section Title Page VII.
References.....
.59 Vill. Appendices.
. 60 Appendix A - Radiological Environmental Monitoring Program Annual Sununary Tables - 1991
.60 Appendix B - Data TF
. 65 Appendix C - Land Use Census - 1991..
. f,7 Appendix D - Synopsis of Analytical Procedures.
.88 Appendix E - EPA Interlaboratory Comparison Program.
.99 List ofTrending Graphs 1.
Gross Beta in Air Particulates.
.44 q
2.
Tritium in River Water.
.47 V
3.
Tritium in Surface Water.
.47 4.
Cobalt-58 in Sediment Silt..
. 50 5.
Cobalt 60 in Sediment Silt..
.50 6.
Cesium-134 in Sediment Silt.
. 51 7.
Cesium-137 in Sediment Silt.
.51 8.
Cesium-134 in Fish..
.53 9.
Cesium-137 in Fish..
.53 10.
Environmental Radiation - TIDs.
.55 li
Table ofContents (Continued) nV List Of Figures Figure Title Page 1.
Atomic Structure......
. 12 2.
Alpha Panicle..........
......... 14 3.
Beta Panicle.,...
.14 4.
Gamma Ray....................
...I 5.
The Penetrating Ability of Wrious Types of Radiation.
.15 6.
Unit Con,parison..................
.15 7.
The Curie, a Measurement of Activity..
........................16 8.
Average Annual Dose Equivalent to Persons in the U.S.
from Various Radiation Sources.
17 O
9.
estimmted ^ver28e oars or tire exeectaocv to~t oue to Various Health Risks..
.19 10.
Reactor V.ssel with Fuel Assemblies, Rods, and Fuel Pellets... 20 11.
Fissico: a Chzin React on...
. 21 i
12.
PWR System Diagram.
.........22 13 Containment Schematic.
.... 23 14.
Nonh Anna Radiological Monitoring Locations..................
32 l
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List Of Tables Table Page 1
Uranium isotopes...
. 13 2
Radiological Sampling Station Distance and Direction From Unit 1...
.26 3
Sample Analysis Program.
38 4
REMP Exceptions For Scheduled Sampling And Analysis During 1991.
- i2 Appendix B Tables B-1 lodine-131 Concentration in Filtered Air.
.65 lb2 Concentrations of Gross Beta in Air Particulates.
.67 Ib3 Gamnu Emitter, Strontium 89, and StronJum 90 Concentrations in Air Particulates.
.71 B-j Gross Beta, Tridum and Gamnu Emitter Concentrations in Precipitation.
. 7-1 B-5 Gamnu Emitter Concentration in Soil.
. 7<1 O
B-6 Ganuna Emitter, Strontium, and Tritium Concentrations in Ground and Well Water.
.75 B-7 Gamma Emitter, Strontium, and Tritium Concentrations in River Water..
.75 B-8 Gamma Emitter, Strontium, and Tritium Concentrations in Surfzce Water.
.76 B-9.
Gamma Emitter, Strontium, and Tritium Concentrations in Surface Water-State Split Samples.
77 B-10 Gamma Emitter Concentration in Sediment Silt.
.78 B-11 Gamma Emitter Concentration in Shoreline Soil
.78 B-12 Gamma Emitter Concentration in Milk.
.79 B-13 Gamma Emitter Concentration in Fish
.81 B-14 Gamma Emitter Concentration in Food / Vegetation..
.82 B-15 Direct Radiation Measurements -
Quarterly Annual TLD Results.
81 B-16 Direct Radiation Measurements -
Sector Quarterly TLD Results.
.85 6
Forwarri a)
%d This repon is submitted as required by Technical Specification 6.9.1.8, Annual Radiological Environmental Opemting Repon for Nonh Anna Power Stations, Units 1 and 2, Virginia Electric and Power Company Docket Nos, 50-338 and 50-339.
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7
MRWWWfMHEl$LPQf2WMVMM%mwnau Executive Summmy O
Tius document is a detailed repon on the 1991 Nonh Anna Nuclear Power Station Radiological Environmental Monitoring Progmm (RFMP).
Fadioactivity levels from January 1 through December 31,1991 in water, silt, shoreline sediment, milk, aquatic biota, food pn xlucts, vegetation, and direct exposure pathways have been analyzed, evaluated, and sumnurized. The REMP is designed to ensure tha; radiologic:d ef0uent releases are As Low As is Reasonably Achievable (ALARA), no undue envimnmental elTects occur, and the health and sa.fety of the public is protected. The program also detects any unexpected environmental processes which could allow radiation accumulations in the environment or food pathway chains.
Radiation and radioattivity in the environment is con-stantly raonitored within a 25 mile radius of the station.
s Virginia Power also collects samples within this area. A number of sampling locations for each medium were selected using available meteorological, land use, and water use data.
Two types of samples are obtained. The first type, control
, g +j d samples, are collected from areas that are beyond the measur-g '
y A3 Wd able in0uence of Nonh Anna Nuclear Power Station or any D other nuclear facility. These samples are used as reference 3-data. Nomul background radiation levels, or radiation present due to causes other than Nonh Anna Poiver Station, can thus
/
bq be compared to the environment surrounding the nuclear power station. Indicator samples are the second sample type obtained.
These samples show how much radiation is contributed to the environment by the plant. Indicator samples are taken from areas close to the station where any plant contribution will be at the highest concentration.
Prior to station operation, samples were collected and analyzed to detennine the amount of radioactivity present in the area.. The resulting values are used as a "premperational baseline."
An:dysis results from the indicator samples are compared to both current control sample values and the pre-operational baseline to detennine if changes in mdioactivity levels are attributable to station operations, other causes such as the Chemobyl accident, or natural variation.
Teledyne Isotopes provides, ample anaiyses for various radioisotopes as appropriate for each sample media. Participation in the Environmental Protection Agencys (EPA) Interlaboratory Comp _ ison Program provides an independent check of samp!e measurement precision and accuracy. Typically, radioactivity levels in the environment are so low that analysis 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 radiological environmental monitoring must be able to detect specified minimum Inwer Limits of Detection (11D). This ensures that analyses are as accurate as possible. Samples with extremely O
io-icvei of radi2 tion which cannet be detected are thererere reported as beina beiew the otD.
The NRC also mandates a " reporting level " Licensed nuclear facilities must repon any releases 8
..m equal to or greater than this reporting level. Environmental radiation levels are sometimes referred to as a percent of the reporung level.
O Analytical results are divided into five c-tegories based on exposure pathways: Airlsome, waterbome, aquatic, ingesdon, and direct radiation. Each of these pathways is described below:
The airbome exposure pathway indudes airbome iodine, airbome particulate, precipita-tion, and soil samples. The overall 1991 airbome results were very similar to previous years and to preoperational le vels. No increase was noted and there were no detections of fission products or other man-nude isotopes in the aict ome particulate media during 1991.
The waterbome 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 e
except for tridum. The average tridum activity in 1991 was 11 Iwo of the NHC reporting level.
This has increased from preoperatio;.al levels but has not increased from 1989 and 1990 levels.
The aquatic exposure pathway includes sediment / silt and shoreline samples. North Anna sediment contained some cobalt-60, cesium-134 and cesium-137. During the preopera-tional period, cesium-137 was detected. Additional nun-nude iscxopes appear to have accumulated since that time. Sediment contanination, however, does not provide a direct dose pathway to nun. Shoreline soil, which may provide a direct dose pathway, contained no cesium-134. Cesium-137 levels increased from 378 pCi/kg in 1989 to 502 pCi/kg in 1991.
The ingestion exposure pathway indudes milk, fish, and focxVvegetation samples. lodine-pd 131 was not detected in any 1991 milk samples Although cesium-137 has been detected in the past, it was not c'etected in 1991 milk samples. Strontium-90 was detected at levels comparable to 1989, and lower than preopemtional years. Both strondun>90 and cesium-137 are attributable to atmospheric nuclear weapons twung in the past. Naturally occurnng potassium-40 was detected at nomul environmental levels.
Fish samples during 1991 contained cesium-137 at a slightly higher activity than preoperational levels. Steam generator repairs and better liquid waste paressing, 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 thermoluminescent dosimeters (TI.Dsl TLD results have remained essentially the same since the preoperational period in 1977.
During 1991, as in previous years, operation of the North Anna Nuclear Power Station created no adverse emironmental affects or health hazards. The maximum radiation dose calculated for a hypothetical individual at the North Anna Power Station boundary due to liquid and gaseous effluents released from the site during 1991 was 1.016 millirem. For reference this dose may be compared to the 360 millirem average annual exposure to every persor in the United States from natural and man-made sources. Natural sources in the environment provide approxinutely 82%
of radiation exposure to man while Nuclear Power contnbutes less than 0.1% These results demonstrate not only compliance with federal and state regulations, but also demonstrate the Q
adequacy of radioactive effluent control at the North Anna Nuc! car Power Station.
9
Yhylnia E4ctric AnctPower Contpany
!O North Anna Power Statfan l
Raillologleal.Enchvnntental Operating Ptnyratn i
I. Introcluction i
j
'Ihe ogrrational Itadiological Erwironmental Monitoring Prognun (ItEMP) conducted for the i
l year 19')1 for North Anna Power Station is piovided in this teport. 'lhe results of me tsurements and analyses of data obtai ul from s;unples collected froripnuary 1,1991 through December 31, I
106)I are surninan7ed.
i A. 'lhe North Anna Power Station of Virginia Electric and Power Company is h>cated on I.ake j
i Anna in Mineral, Virginia, approximately 35 miles southwest of Fredericksburg, Virginia.
l 1he site corsists of two urits, each with pressurized water reactor (PWIO nuclear steam j
supply systems and turbine generators furnished by Westinghouse Eledric Corporation.
Each unit is designed with a gross eledrical output of 970 megawatts electric (MWe). Uni' 1 achieved commercial operation onJune 6,1978, and Umt 2 on December 14,1980.
l l
11 'the United States Nuclear Regulatory Commission (USNRC) tegulatiom (10 CFR 50.31a)
I amuire that nuclear power plants be designed, constmeted, and opemted to keep levels lioactis e material in ellluents to unrestricted areas As low As is Reasonably A hievaSle i
O a^). To cosure inese criieri> 2re met. ine oneretiaR ccuse ror sor1h ^no> rower ii l
Su in includes Technical Specifications which address the release of radioactive Mlluents.
l Inplant monitoring is used to ensure release limits are not exceeded. As a pre caution against j
unexpected or undefined environmental procvsses which might allow undue accumula-tion of radioactivity in the environment, a progmm for monitoriag the plant environs is also included in Virginia Power's Station Administrative Pn>cedure VPAP-2103, Offsite Dose Calculation Manual (ODCM).
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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 Q
submitting reports of radicarulyses. 'lhe results are used to determine if dunges in radioactivity levels could be attribeable to stauon operations. Menored values are compared to control levels, which vary with time due to such c:nemal events as cosmic my lx>mbardment, weapons test fallout, and seasonal variations of naturally occurring isotopes. D v a collmed prior to the plant operation is " sed to indicate the degree of natural 6
variation to be expected. 'this peoperadonal data is compared to data collected dudng the operational phase to assist in evaluating any radiological impact of plant operadons.
D. Occasionally samples of environmental media show the presence of nun made isotopes.
As a method of referendng the measured radionudide concentrations in the sample media to a dose consequence to nun, the data is conozred to the reponing kvel concentratfor.a listed in the USNRC Regulatory Guide 4.8 ano North Anna Power Stadon's OIX'M. '!hese concentrations are based upon the annual dose commitment recommended by 10 CFit 50, Appendix 1, to meet the criterion cf "As inw As is Iteasonably Achievable."
E. 'this repon documents the results of the Radiological Emironmental Monitoring Program for 1991 and satisfies the following objectives of the program-
- 1. Provides measurements of radiation and of radioactive nuterials in those e.yposure pathva.ys and for those radionudides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station O
- 2. Supplements the radiological effluent monitoring program by verifying diat radioactive effluents are within allowabb lita a.
- 3. Identifies radioactivity changes in the environment.
- 4. Verifies that the plant operations have no detrimental effect on the health and safety of the public.
O 11
i H. Nuclear Power Anti The Enuhunonent:
In Perspective Coal, oil. sutural gas, nuclear gxmvr, atal hphoix m es h.n e all Iven used to nin ilw iunon -
electric generating stations. Each methal. lum es er, lus its draw f ucks. Out fired xmei $un i
damage the erwironment during the mining pnicem, or by aid xime disclurges sta h as fly a4 urut chemicals which contribute to acid rein. Oil and tutural gis are costly because ofilwir liinitett supply. Few suitable sites for hpfro[xmrt exist, and building Ilka large d.tiits twri* eiary to pn sitice liydrolxmvr lus a significant imitn1 on the envinniment.
Nuclear energy pn n ides an alt etrute sou n e of erwrgy whici us ie.n hiv.n.ulal de 11 w og viar ion of nudear power statioits has a very snull impxt on the em ironment in fact. hinxiteth of acres adjoining Suny l'ower Station are a state waterfowl refuge. and take Annu. rw to Ntuth Antu l'ower Station, is a well kntm n fishing site with a state park on its slw >re in onter to more fully understand this ank ue energ) w nute. lut kgn unal utlinnutkin alon l
lusic radiation clunnieristics. risk aswssment n actor ojeration elliuent control. em innturntal monitoring and nidio.u1ive waste is pnwkled in this section j
Funtlansentals 1heA!om Eser) thing we encounter is trude of.utnns Atorns.ne the snulless gurts of an elenxin iltic still Inn e all the chemkul projwities of tlut element At the wnter of an aloin b a ntn-letis ^!1 a' nucleus tonsists of neutrons.inxi [~otons Elections six n e in an orbit arotitxt Ilw nucletas a*l. ire nepitively clurged. I'n gons and trut n nts are nearly klentical in size arxl weight, arxl each is ai m a n 2((X) times heavier tlun an chtron. Uw pn gon,1x mrver, Ius a posith e durge, while the nei. n in lus no clurge, it is elettricilly neutral Figure i presents a simple di.ignun of an atorn.
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O The number of protons in the atom of any specific element is always the same. Fc ex:unple.
all hydrogen atoms have one proton whereas all oxygen ator, a luve eight protons, Unlike prtexts, 12
1 the number of neutrons in the nucleus of an element rnay vary. Atoms with the same number of protons, but a different number of neutrons, are called isotopes. Table 1 lists the isotopes of O
Isoto Syrnhols Nundier Nundser ofProtons ofNeutrons Uranlun>235 50 92 143 Uranium 236 "U
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- U 92 148 Table 1. Uranluin Isotopes Radiation andRadioactivity Radiomwlldes Q
Normally, the pans 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 radioisotope, or radionuclide. 'the excess energy is usually(ue to an imbalance in the number of electrons, protons, and/or neutmns which nuke up the atont Radionuclides can be naturally occurring, such as uranium-238, thoriun>232 and potassium-40, or nun-nude, such as iodine-131, ceslunr137, and cobalt 60.
P Radioactive Decay Radioactive atoms attempt to reach a stable (non-radioactive) state through a process known as radioactive decaf. Radioactive decayis the release ofenergy from the atom through the emission of particulate and/or electronugnetic radiation. Particulate radiation nuy be in the form of 1
electrically charged particles such as alpha (2 protons plus 2 neutrons) or beta partides (1 electron),
or may be electrically neutral, such as neutrons. Part of the electmmagnetic spectrum consists of
- gamma rays and X-rays which are similar to light and microwaves, but have a much higher energy.
HalfLffe A radioactive half life is the amount of time required for a radioactive substance to lose half O
fits activity through the process of radioactive decay. Cobalt-60 has a half life of about > years.
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Several quantities.ind units are used to dest ni ne radio.a tiuts and its ellects in the folk m um sectiom two errm rem azul attisity. will be used to descnhe amounts of r;uliation.
l(em measures the potentiti effect of r.nluuon exposure on human (ells Snull doses.ue counted in millirem. En h Inillirem is equal to one thous.untth of a tem Federal statulants lunit exposure for an indh idual member of the public to 500 millisem annually. This annual limit th o not inclade the average NO millirem re( cis ed from natural sources and apptoximately 60 millitem from medical applications
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one 10 Tons of Thofium 232 i Geam c,f Hadiurn ya trillionth of a L,une. A Cune is a med-(radiation sou'ce)
(rad:ation source) surernent of I idioactis it),1101 a quall-One gram of rad'um 220 and 10 tons or thonum ?32 tity of mate!ial The amount of nuteri.il are both appronmate!y 1 Cune necessary to nuke one Cutie v.irieN Ir
[m p yI[r
^
p.
n - Q, o }r gI
~
exmnple. one gr.un of nidinne226 r
. m2 33 t
"^
one Curie of nidioat tis ity, but it would takc 9,1 0,(4) grams (aluut lu tons)of thorium 232 !() t dilaill ()ne Culle Satures Of Radiadon O
iksckgtvnenil Rastiation itidiation is not a nen (icata >n of 1ht not lear pou ti u ndusti). it is a natutal ot t urrence e o iln earth. Mankind lus alwap In ed with radunon and alwap w til IS ci) m und of our lis e os ci
9 0 atoms undergo radioactive decay in the lui) of the.n enige adult itidioactisity custs naturally in the soil. water, air and spat e All of Ihese tununon sources of rat'ution contohute i the natural background radiation tlut we.ne eqused to each day The canh is constantly show cred by a steady stre.un of high energy g.unnu rays. Thest ra p come from space and are known as cosmic nidiation Our atmosphere shields out most of this radiation but everyone still receises about 20 to 50 millirem each ye.u from this source. At high altitudes, the air is thinner and provides less protection from (osma radiation itecause of this people living at higher altitudes or esen thing in an airplane are exposed to more radiation ILidioactive atoms conunonly found in the atn iosphere as a result of cosmic my intemctions in< lude beryllium-7, carbon-1 i, tritium, and sodium-22 Other natural sources of radation include radionuclides natundly found in soil, water, food.
building materials and even people. People have alway 3 been radioactive, in pait because the carbon found in our lxAlies is a mixture of all carbon isotopes, both non-radioactive and radioactive. Approximately two-thirds of the whole lxxly dose from natural soort es is contributed eq hy Ibdon gas. About one-third of the naturally occuring external terrestrial and int emal whoic luly radiation dose is attributable to a naturally radioactive isotope of potassium. potassium-i0 v
16
Man-Matte O
io "aaiti"o io >mtorsiir -co"io:t r"ii>ti"u-ne"nie 2re sis" esr>'ea t" mao m.mie mamo-"
i ne largest sources of these exp>sures are from medical X mys. liuoroscopic examinations mdioactive dmgs, and tobacco, Small doses are receis ed from consumer m alucts sut h as Yery silla l dOscs lesult floill the pn A LK~tioll 4)f lith leal l
teleVINiof), silloke al.lnlis, and felillilefs p>wer.1:allout from innlear weapons tests is ano her source of inan nude exp nure. 1'.illout mdionuclides include strontium W, cesium-1.C, (arion-1-i and tritiuin i
Man Made Sources 1
I
- f melear Pov.et (01'.)
i
~
f.
ccano us (O P.)
)
Med: ai X rays (60 9 p
Occupational (14M onsumet Goods (16 6%)
nor Medica 4219N j
)
Man Made
{
Medical I
Natural And Man Made Sources Diagnostic X-Rays 39 00 !
Other Medical 14.00 l Consumer Products 5.00 to 13 00 I O
occenat'onai o oo !
Miscellaneous Environmental 0 06 4
Nuclear Power 0 05 h
c.n #
Natural Background Radon @5.6*')j o
-b -
Radon and Radon Daughters 200 00 Cosmic Rays 27 00 n Made 7.8 Cosmogenic Radiation 1.00 l e-
~ s Terrestrial Radiation 28 00 !
- 'n i'
Internal Radiation 40.00 l
m&
y.
W ya Total 360.00 MREM Per Year 4
l y
Db
~
' g?
Inte m 1.1
- p l
T.
l
, &. r J
Teriestna 7.8%
s as.8%)
NCRP Repovt No. G3 'kwurmg ReJapon Emosure o' the Popt.iakon vt the Lhted States.*.wNc 1967, Bethesda, MD Pue14 KC5t,3 M EE2?J W ?FS 17
Efects OfRadiation nG Studies lhe effects ofionizing 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 cor.ditions. It has proven dimcult, however, to relate the biological effects of irradiated laboratory aninuls to the potential health efTects on hununs.
llecause of this, human populations inadiated under various drcumstances have been studied in great depth.1 hew groups include:
Sunivors of the atomic bonh Persons undergoing medical radiation treatment.
Radium dial painters during World War 1 who ingested large amounts of radioactivity by " tipping" the paint brushes with their lips.
Uranium miners, who innaled large amounts of radioactive dust while mining pitchblende (uranium orel Early radiologists, who accumulated large doses of radiadon from early X-ray equipment while being unaware of the potential hazards.
O Analysis of these groups has increased our knowledge of health effects resulting from large tadiation doses. Icss is known about the effects oflow 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.1 hat is, if one dose of radiation causes an effea, then half the dose will cause half the effect. Radiation scientists agree that this assumption overestimates the risks asscxiated with low level radiation exposure. The effects predicted in this nunner have not been actually obsen ed in individuals exposed to low level radiation.
Health Risks Since the actual effects of exposure to low level radiation are difficult to measure, scientists often refer to the possible risk involved. The problem is one of evaluating altenutives, of comparing risks and weighing them against benefits. People make decisions invohing risks every day, such as deciding whether to wear seat belts or smoke cigarettes. Risks are a part of everyday life.1he question is to determine how great the risks are.
We accept the inevitability of automobile accidents. Building safer cars or wearing seat belts
- ill reduce the risk ofinjury. 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 automobiles to zero requires moving to a place where there are no automobiles.
O 18
While accepting the nuny daily risks of in ing. some p ople lecl ilui thcu denunds for energ3 O
should le met on an essentially risk-hee Imis Attention is focused on safegtunkng the publh developing a realistic assessment of the risks. and placing them in pensjvois e Ikvause you cannot see, feel, taste, hear. or smell radution. it is often a soon e of cont ca n \\\\ <
luse the s.une lack of sensory perception for things suc h as radio was es. c.uion monoxide. and snull corn entrations of numerous cancer causing substances Although these :isks are just as real as the risks associated with radution. they luse not genenned the same degice of coix em as nuliation Most risks are with us ihniughot t our in es, and their clie(ts un be added up os er a hietone to obtain a total effect on our life span. 'lhe t)pical hfe span for.m Amesi(.m nonun is nim 'h years, whereas men aserage il year > of age 1igure 9 sin m s a numire of ditlinent f.uiots ilui decreased our average life esp ctancy Days Activity 2500 J
- 1. Smoking i Pack of Cigarettes a Day 2000 -
~
2 Being 20% Overweight 3 Construction Agriculture 4
O e ^vo ^ ice"oi censemni'oo ner ee,sc,,
- 7. Home Accidents 8 Allindustry Hazards 500 -
9 Radiat;on Dose of G S Millirem per Year for 30 Years i
p NcRP Rswt No 95. *Rajakm Ewowe of the t %
1 0 '
/
r
--/
/sywlatm from consumer 14oducts aof uscessmus j s
s s
i i
s s
i sawcu Naumai coance on nas.ata ensaam we -
n 1
2 3
4 5
6 7
8 9
'*"*"'*"'5" ' " 8'**** D #"8 "
i KC W.
,1 The American Cancer Society estimates flut about 30 percent of all Americans will deselop cancer at some thne in their lives from all possible causes. So, in a group of 10,000 people it is expected tlut 3,000 of them will develop cmcer. If each person were to receive a radution exposure ofone rem in addition to rutural background radiation, then it is expeded tlut three mor e nuy develop cancer during their lifetime. This increases the risk from 30 percent to 30.03 per(ent Hence, the risks of radiation exposure are small when compan d to the risks of everyda; life These comparisons should give you some idea of the risk involved in adivities that you are familiar with. They give a basis for judging what smoking, eating, or dnving a car could mean to your health and safety. Everyone knows tlut life is full of risks. If you have the basis for judgment.
O voe caa aeeiae wimi to ao or wiui aot io ao 19
Nuclear Reactor Operation O
eice'r*<>'r io ine t'">'ea si"tesisi i"8 e" ~nmea "sion ioss>ii"ei. "> """ m ori.'tu"x " >>c' A fossil fueled x>wer station burns uul, oil or sutural gas in a luiler to pn s ! e enesgy. Nut Ic.u l
power stations use uranitun fuel and the heat pnxtured from the fission pn x ess to make energ)
In luth cases, they heat and luil water to pnxture steam lhe ste.un n used to drhe a tiubine which turns a genemtor and pn(luces ekctricity Nuck ar Essel Uranium (10 is the lusic ingredient in notlear fuel. consisting of i' 23;.ind I L238 atour Natural uranium (ontains less llun one percent I ' 235 w hen it is mined Conunen ial nucle.u lw m ei plants use fuel with a t L235 content of appn minutely tluce ivrrent 1he pn = m uwd te ini te.oc the Ib235 o>ocentration is known as enriclunent Reactor Operation After enridunent. the uranium fuel is t benutall) ch.inged to uranium dioxide, a dr) bl..< L powder. This powder is (ompressed into small cenunic pellets lin h fuel pellet is al uut 39 u n hes long and 3/8 itu hes in di.uneter The pellets an pl acd into 12 foot long metal tubes nude of 7irconium alloy to make a fuel rc xi Alout fh e pounds of pellets.uc used to fill c.n h n xi A toul of 20i fuel rods make a single fuel assemlih Virginii l'ower not le.u reattors contains IC f uel assemblies (Figure 10)
O Reactor Vessel l
DGpG Fuel Rod lL1 '.A 77 -
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x g
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- Walet levtti Jp
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Fission n
,v-t F
o -
Nuclear energ) is punlumi by a y ga 1
pn x ess calk d fission. Fission oaurs in 3y o
12 4
~~~*$::-f a reactor when uranium is split into
,,o-fmgments producing heat and releas-g o
.M' ing neutrons These neutrons strike v
other uranium atoms, causing them to
}0
-+ "o split (fission) and release more heat t
u ww.
and neutn>ns 1his is called a chain reaction (Figure 11) and is controlled
$ Hea y Atom o Free Neutron by the use of re.ictor control nxk Control ax.js are an eswntial pan of gNMg;ghjp{ }
the nuclear reactor Control nxis con-tain cadmium, indium, and siher inetals which absorb.unt control the amount of neutnins pnxluced in the reactor The control iods act to slow dow n or stop the chain reaction. A ch.un reaction cannot occur when the control nuls are insened completely into the core. When the contful nxts are withdrawn the chain reaction begins and heat is generated Hesign & Operallon Surry Power 5tation and Nonh Anna Power $tation use a Pressurized Water ite.utor (PM lu sy. stem to genemte elecificity There are two complete and independent P%1tsystems on site at both Surry and Nonh Anna Power Stations These are refened to as l' rut-l and l' nit-2.
The reactor core is inside a large sit el contamer called the iteatto: Pressm e Vessel. 'lhe teai tu core is always surrounded by water The fissioning of the uranium fuel makes the fuel nxis get hot.1he hot fuel nxis heat the water, w hich serves as a cook nt that can;es away heat.
In a pressurized water reactor, heat is mo; ed hum plat e to place by moving water, the reactor's coolant. The water flows in closed hops As (primary) water moves through the core it gets t cry hot (605'F), but because it is under such high pressure, 2235 pounds per squate inch (psi), it doesn't boil. The hot water then flows to the steam generator. The steam genemtor is a heat exchanger. Iteactor coolant passes through it but doesn't mix with the steam generatoi (secondary) water. Instead, heat from the primary water is transferred through thousands of tubes to the cooler secondary water. The water in the steam genemtor is under muc h less pressure, and the heat boils the secondary water to steam At Virginia Electric and Power stations, each unit has 3 steam genemtors.
The steam is piped to a steam turbine that tums an electric generator. The exhausted steam from the turbine is cooled and converted back to water in a condenser. The condenser is also a heat exchanger; in it heat passes from the steam to a third loop of water. In Surry's case theJames
-n River provides the third loop water. At North Anna Power Station third loop water is from lake U
Anna. The steam tums back to liquid and is pumped back to the steam generator. Figure 12 is a diagram of typic:d nuclear reactor systems.
21
lt in 1
- If.0P,';'73*JJ7#"'*" I it:,.';*:;Y'Wj'"" l Ce co ~
se.., r...
s-Reactor Contanment Building
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k Contairtrnent Nuclear 1xmer plants are designed to pres eni the esuipe of large quantities of mdi.ition.ual radioactive substances lwo principles are used. I trst. thic k, heavy walls are used as shieldinp to absorb radiation and prevent its escape Second, strong ainight walls called containment are used to prevent the escalm of radioactive nuterials lhe reactor pressure vessel and the contairunent building that houses a are enonnously strong (Figure 15). Strong enough, in fad, to withstand a direct hit from a 707 jetliner.1he reador core lies within a sealed pressure vessel. Like all boilers its walls must be very strong because the water inside must be kept under high pressure. The reactor pressure vessel in a nudear power plant is even heavier tha-a ordinary steam boiler because of the need to minimize the (hance of mpture and release of any 3adioactive materials. The reactor presst.re vessel is made from a stainless steel alloy 6 to 8 inches thick.
Around the reactor pressure vessel is a thick conaete wall. This wall ads as shielding.
protecting workers by absorbing radiation resulting from the nuclear chain reacion. Next an p
ainight 1/2 inch steel liner surrounds the entire interior of the containment. If the reactor pressure V
vessel or any of the primary piping should break, the escaping steam would be tmpped inside tbe liner.
22
~
l O
I'2 inch Steel hner
(
l 7
3 8 Inch Steel L ner l
I E
- s l
)
u u m-
,p, g g Gewators Pressutiier
~j
[,h MN 9'
,?
%n 185 Feet
, Id u.1
. 31 t'
m 122 Feel i
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l Linet 10 feet Thick Coretel6 I
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Fin. illy, the building s reinforced mncrete ource wall ts 1 1/2 feet thick tapering to 21/.! leet at the top of the dome. It is designed to act as shielding and is also intended to withstand natural and man-nude esents like eanhquakes and esen the direct impad from a large commercial ici aircraft.
l l
Operathig Ihe Reactor Safe (y Accklents l
The most serious accident that coula tuppen in a nuclear power plant involves overheating in the triclear reactor core. Such an accident would result from a lossof-cocAint accident or LOCA During a LOCA primary coolant would no longer circulate through the reador core to remove heat
]
Circulation could be lost if a combination of pipes burst, for example. Conceivably, a dry.
overheated reactor core could melt tivough the pressure vessel.
23
n c
'Ihe reactor itself is designed to respond autonutically to such an emergency. Operators are also trained to nuke corrections for any system failure. 'lhe autonutic and operator responses have O
tw g is: t prevent danuge t the re et r, and prevent the rek:ase of radiation. Shutting the reactor down is relatively easy. Control rods drop in and chemical to stop the nudear reaction are injected into tne coolant. Insing the coolant itself tends to stop the chain reaction because the coolant is needed to keep the nudear duin reaction going. Within 10 seconds of shutdown, the amount of heat is less than 5 percent of the amount produced at full power and within 15 minutes, less than 1 percent.
To carry heat away during an accident, all reactors have Emergency Core Cooling Systems (ECCS). The ECCS consists of prirnary and back-up pumps and reservoirs of coolant that operate separately from those tlut nemully circulate through 'he systent A nudtar reactor has nuny different back-up safety systems designed so that if one fails another ts always available.
j trorkers There are many different }obs at a nudear 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 Nudear Power Operations. The operators are tested and certified by the United 3
States Nudear Regulatory r nmission (NRC).
Sajkty Statistics Job safety is another measure of assurance that the station is lx ing properly operated. Surry Power Sat 5n attained 1,000,000 man hours without a lost time accident and is continuing that record into Icf)2, w hile North Anna reached 6,000,000 nun hours withat.t a lost time accident.
Sunnumy C
Nuclear energy provides an altemate source of energy which is readily available. The operation of a nudcar power station has a very small impact on the environment.
Radiation is not a new creat. ion of the nudear power industry; it is a natural occurrence on the canh. 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 acMition to naturally occurring radiation and radioactivity, people are also exposed to nun-made radiation. Very srnall doses result from the production of nudear power, Nudear power plants are designed to prevent the escape of radiation and radioactive substances.
(]
A nudear reactor has many different back-up safety systems designed so that if one fails another is a'.ailable.
24
III. Sampling AndAnalysisIw> gram O
A. Santpling Pmgram
- 1. Table 1 sumnurizes the sampling program for North Anna Power Station during 1991. 'lhe maps indicate the locations c,f the environmental monitoring stations.
- 2. For routine TLD measurements, two dcsimeters nude of CaSOjDy in a teflon card are deployed at e.ch sampling lcxmtion. Several TIDs are co-located with NitC and Commonwealth of Virginia direct radiation recording devices. 'Ihese are indicated as *ccw location" samples.
- 3. In addition to the ltadiological Environmental Monitoring Program required by Nonh Anna Technical Specifications, Virginia Electric and Power Cornpany (VEPCO) splits samples with the Commonwealth of Virginia. All samples listed in Tab!c 1 are collected by VEPCO personnel except for those labeled state split. All samples are shipped to Teledyne isotopes in Westwood, New Jersey.
- 4. All samples listed in Table 1 are taken at indicator locations except those labeled " control" O
l 25 1
1
Table 2 (Page 1 of5)
North Anna PowerStation 1991 RadiologicalSarnpilng Statton Distance And Dirvction Frorn Unit Na 1 IMstarre Campass O &cctbo Sample Media locadon
$tation Miles Dircrtbn Degrecs Frequcncy Remarks I
tuvironsnental N APS Sewage C1 0 20 NE
(?
Quanerty us ne, hr 5;ig Thermolumlnencent Trea: ment Plad
& Anrudy thwimetry (TID)
Prederx*s lla'l 02 3 30 55T 225' Quantdy hte Spa
& Arrudy Mncral, Va 03 7 10 T5T 24 3' Quanedy
& Anrudy Tares Cicraroth 04
$10 TNT 28
- Quanctly he spa
& Arymdy he 752 05 4 20 NNE
??
Quanerfy a A'un.dy
$tegnars Creek OSA 3 20 N
11' Quartedy Marria
& Artua3y levy, VA 06 4 70 LSE 115' Quanaiy kate $p4 Cdxatxt.
& ArumaDy Bampa.5,VA 07 730 SSE 16 '
Quar'erly he$ps
& Annudy Erd ci hie (A$
21 1 00 ThT 30!'
Quanedy f.xdwun IbunJry
& Arawdy km Spit, Colotauon hte 700 22 1 00 UT 24 7 Quandy Laduson ikwrxtry
& Annually karSpa
' Aspen Hils' 23 0 93
$50 15r Quancsfy Ladusm ikwndry
& Arymdy State Spid, Colocatum Orange, \\ A 24 22 (0 hT 325' Quaneriy C(vitral
& Anrually
!kant.g Cocling towr N-1/33 0 06 N
10*
Quanerty Oivste Stargeon s Crec1 NT34 3 20 N
11' Quaneriy Mant.4 Patrg ia V NNE-3'35 0 25 NNE 3r Quaneriy On&te (on4ae)
Gotd flore Ourch SNF4'36 4 96 NNE 25' Quancriy he Spit Parkrg Lcx T NE-5/37 0 20 NE 4?
Quancty Or>Ste lake Anna Manna NE4'36 149 NE 34*.
Quanedy Tea:hcr Tower Fence LNE-7/39 0 36 ENE 74*
Quanedy On-Ste Route 69 ENET40 243 ENE 65*
Quanrity Near Trarung E&41 0 33 E
91' Quanerly On-ste Faddy O
26
~
. - ~
Table 2 (Page 2 of5)
Q North Anna Pou'er Station 1991 Radiok>gicalSarnpling Stations Distance And Direction Frorn Unit Na i tx.tm, r..p..
Cona an Sample Medh location station Miks IXtectbn Degras, Frequmcy Remarks Irnirunmental hung Gkry !!QF B.10/42 2 95 E
97 Quanciy Thermoluminenant tbalmcuy (MD) hiand Dat f5L11/43 0 12 13E 10 7 Quaneiy On Ltc Rouie C2 13E 12'44 4 70 ISE 115' Quandy VIKO Bdyy lab SLil'45 0 75 SE 13r Quanety (wkte kmie 701 Gkm fatraxe)
St.14'46 5 88 SE 13 7 Quanely
'A$ fen ill!s'
$5L1V47 0 93 Ssf 15r Quandy fadem ikwr. dry Ek Creek SE16/48 2 33 55E 165' Quavriy Tan: hour Ccrgound Cate $17/49 0 22 5
17 7 Quanety OnSte 12k Creek Churdi 51g'50 1 55 5
17F Quanety NAPS Arres Road SST 1W51 0 36 MW 197 Quancty On Sue kuute 618
$5T-2752 5 30 SST 20$'
Qua teriy AM'S Accru kaad
$7 21/53 0 30 ST 21r Quancriy On 5:e Acute 730 ST-21'54 4 36 ST 23 ?
Quaneiy 500 kv iceer T57-23/55 0%
T57 23F Vuandy Onkte kaute 700 T5T2456 1 00 WST 24 ?
Quancriy fadusa ikun:iary Gadur,m boundry)
NAPS Ra6o Tower T-2V57 0 31 T
27 7 Quandy Onke koute 665 T 2958 1 55 W
274*
Quartetty Fnd cl Route 665 TNT 2759 1 00 TNT 30l*
Quanaly fadamn Iburday 11 Purcch Prnte kd TNT 2WO 1 52 TNT 30 7 Quaneriy Ccdocaton End d el/#2 intake NT-2W61 0 15 NT 321' Qaaner!y Orr k:e lake Anna Camppound NT 3Q/C 2 54 NT 31 7 Quancrty
- 1/82 Intake NNT-31/63 0 07 NNT 34 7 Quanely On-kic Route 208 NNT 32/64 343 NNT 344' Quanedy Dunyas Pm OfIce C-1/2 7 30 SSE 1 67*
Quanctly Caed Orange, VA C 5/4 22 00 hv 325' Quaneriy Ceard Meeral, V A C4/6 7 10 T57 24r Quaneiy Con:rd lousa,VA C,.7/8 1154 T5T 25 ?
Quanerly Caed O
27
Table 2 (Page3 of5)
North Anna Power Station - 1991 RadiokrgicalSarnp!htg Stations Distance Arul Direction Frorn Unit Na 1 l
l Istarre Compus CoDeobn Sample Mulla la a m Station Wiks Directbn IMnce frequeixy RemarLa l
AWrne Particulate HAM seware 01 0 20 NE 4r 4 ccAly On54c,5;arspa ard Radlukdine 7teaurert Plant Frederda Hall 02 5 50 55w 205*
s eekly Macal, V A 03 7.10 43T 24 5'
- nkly Vares Caturoada 04 510 4%T 28 7 TeeUy Raute 752 05 4 20 NNE 20' TetUy sturgeons Creek Marina 05A 3 20 N
11*
S cruy tryi, VA 06 4 70 E5E 115' 4 erk!y llum;am, VA 07 7 30 SSE 16 ?
Terily Int ellixte (25 21 1 00 Tsv 301' s eekly fadan tkurdary Route 700 22 1 00 T5T 24F WeeUy fadusxe Iturdary O
'As;tn lilla*
23 0 93 55f 15r Vecky ladusam ikwdary Orangt, VA 24 22 00 hT 3.T Yecuy Contrd surfue Taler Tawe heat 08 1 10 SSE 14r Mrddy sur Spa Tresunent hd!gy T
(Setmd Cooing lagwr0
- lake Anna (upenearr) 09 2 20 NT 3F MwMy Cordrul,5: ale Spa (Route 206 Ekx!ge)
' lake Anna (u;*rearr0 09A 12 90 TN"E 295*
MontNy Getrd (Rouw 669 Brdge)
River Water Ncrth Anna Racr 11 5 60 SE 12r MardJy W
(dcarcam)
Grund 4 ster 11dgy lab 01A 0 75 SE 13r Quarterty
'une 5pd f4 ell Ta:ct)
W Precipkatbn lid >gy lab 01A 0 75 SE 13r M 4dy T
Aquatic Sedimers Enie licat 09 110 SSE 14r Semi-Annuaty Sia:e Spa Treatment hdry (Seccrd Codog Lagwr0 l
Lake Anna (upwrean0 09 2 20 ST 3P SnAnnua!!y Qvurd,SurSpa l
Nd Anna Rntr 11 5 80 SSE 12r Semi-Annally (Dwratrean0
- In ocrater 1991 the surface Taw simpe lura, at sanan 09 wu trawed io on 28 L
Table 2 (Page 4 of5)
Q North Anna Power Station 1991 llatifologicalSarnpling Stations Distance Arul Direction Frorn Unit Na 1 Distatus Compass Colkstbn
$ampic EdLa tecstnen Statbn klke Direttk a Ikgms Trequeruy Remarks Shortline Sall lake anru (urstreartQ 09 2 20 hT 32 7 5cm ArnuaDy Sur 5;dd
$5 (Route 236 !!rdge)
Soll NAPS Sessge 01 0.20 NE 4P (xst') yean (wsite Trea:meru Piarg Frederks llall C2
$30 56T 205*
Orxe/3 yem Mmeral. VA 03 7 10 T5T 24 3*
O<st/3 yem intes Crmrtei 04 5 10 TNT P
Orre/3 yem houw 752 05 4 20 NNE
??
Orwe/3 yem siurge<ms Creek Marra 05A 3 20 N
11' rnve/3 yeen levy, VA 06 4 70 Est 115' Ormt'3 yean Burniss, V A 07 7)?
SSE 16 ?
Ona/3 yem End d Route (e5 21 1 00 Evt M1' Once/3 years 123.r.no Iburdary Rouw 700 22 1 00 TST 24 7 Ona/3yem Erdusun Iknrdan f
O
'Aspm lits
- 23 0 93 SsE 151P Once/3 yem ladusum Dourdary Orange, VA 24 22 00 NT 325' Orrt/3 years Ccotred Milk Haliaday Dury 12
& 30 NT Sir Methly 5 tar Spit A
(RC Goodwr)
Terrejh Dany 13
$ 60 55 4 20 9 Mcmthly ble $pla (Fredernis litD nah" 4 aste list 06 1 10 SSE 148' 5emi-Annually Sa:e 5%a Treatment Faday I
(Sectrd Cordrig Lagxr0 Lake Anna (upurrand 09 2 20 NT 327 SrmeAnnually $a:e Spa (Rouw 208 Bndge) take Orange '
25 16 5 NT 31P Scru-Annually Ccoral Fami Products Rate 713 14 1 20 NE 43' Anthly i arallatne (firtadeaf or at harvest Yege:aluQ Route 614 15" 17XI33 SE 133' Monthly li svadatie or at harvest
- Alted as resalt of 1%0 Qua!ay Assurarxe A4t
" locauan danged as a result cl1991 land lac Casa L garden at 137 truim Cktute 1991.
" Fah sampe no langer chaned at s:ataan, a3 0
1 l
29
Table 2 (Page$ of5)
North Anna Power Station - 1991 RadiologicalSanspling Stations Distance Arul Direction Frvin Unit Na 1 Distamt Catopans (mikulun Esmpic Media location Station Miks Dim 1&on Drgrea frequcm:y Remarks Fm4 Pnduas kate 6N322 16 12 to NT 3W Uddy i avaSaue (Broadleaf or at tarvcs Vegetation)
)
Dd d kuule (65 21 1.00 TNT 30l*
Mmthly I avadatde 1
cv at twvest i
Aspn tus n
o p3 sst 1w wwdyIansaue cr ni twves
- A4kd as result d IM Qu.!dy Anuratur Auit O
O 30
Legerul For The North Anna Power Station Ern'irortrner:lai3fonitoring Stations Overview Alaps O
l Map Envirofunental Station Map Environinental Stadon Designation Identification Designation identification 1
N 1/33 24 WSW 24/56,22 2
N-2/.M,05A 25 W-25/57 3
NNE-3/35 26 W-26K/58 4
NNEst/36 27 WNW-27/59,21 5
NE-5/37,01 28 WNW-28/60 6
NR-6/38,14 29 NE-29/61 7
ENE-7/39 30 NW-30/62,09 8
ENE-8/40 31 NNW-31/63 9
E-9/41 32 NNW-32/61 10 E-10/42 33 03, C-5&6 11 ESE-11/43
.M 04 12 ESE-12/44,06 35 05 13 SE-13/45,01 A 36 07, C-1&2 14 SE-14/46 37 05 15 SSE-15/47,23 38 11 16 SSE-16'48 39 12 17 S-1 7-19 40 13 18 S-18-50 41 15 19 SSW-19/51 42 16 20 SSW-20/52,02 43' 24, C-3&4 21 SW-21/53 44 C-7&S 22 SW-22/54 45' 25 23 WSW-23/55 46 09A
' Stations 24 and 25 are located in lake Orange and are not shown on the following nups 31 1.
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2 Tab'c 2 sumamszes tse mmairsis prosram <emauctco sy rcica mc isotogcs re,so,1s imma r
Power Station during 1991.
CJ O
Table 3 (Page 1 of3)
North Anna 1%u'erStation Sarnple Anah' sis Prograrn Sample Media Fruluency Analysis 1.tD' Report Units TherrnoNadnescent Ontnerly Ganima Dose 2mRt2mR rnWstd. month Dostrnetty (TID)
(&1 Routine Station 'IID's) 12 Station TID's Annidly Gamma Dme nR mWstd. rnonth Altborne Weekiy 1131 0.07 pCVm$
Radlakdine Altborne Weekly Gross Beta 0.01 pCVm' Particulate Quarterly (1)
Gamma Isotopic pCVm$
Cs-1}i 0.05 Cs-137 0.06 Annually St-89 0.005 pCVm$
(2nd Quarter Sr-90 0.0002 Conposite)
Surface Water Monthly I-131 1
pCVI Gamma Isotopic pCVI Mn-54 15 Fe-59 30 00-58, 60 15 Zn45 30 Zr-Nb-95 15 Cs-131 15 Cs-137 18 Bada 140 15 Quanerly (1)
Tritium 013) 2000 pG1 2nd Quarterly Sr-89 5
pCi/l Composite St-90 1
(1) Quarterly Composites of each locatic,n's samples will be used for the required analysis.
11D's indicate those levels that the environmental samples should be analyzed to, in accordance widi the Nonb Anna Rad clogical E ironmental Program. Actual analysis of the samples by Teledyne Isototr.s may te. lower than thce listed.
O 38 m.
m t
1 % !c 3 (Page 2 of3)
Nortb Artna PowerSta:lon Sarnple Anodysis Prograrn Sample Media Frequency Analysis U D' Repo e Units River Water Monthly 1131 1
pCi1 Gamma isotopic pCV)
Mn-54 15 Fe-59 30 Co-58,60 15 Zn45 30 Zr-Nt>95 15 Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly Tritium (11-3) 2000 pCi'l 2nd Quaner Sr-8()
5 pCi1 Sample Sr-90 1
Ground Water Quanerly Gamma Isotopic pCi,1 (Well Water)
Mn-54 15 Fe-5?
30 Co-5890 15 Zn-65 30 Zr-Nt>95 15 I-131 1
Cs-131 15 Cs-137 18 Ba la-140 15 Tritium (11-3) 2000 l
2nd Quaner St-89 5
pCiq t-Composite Sr-90 1
Aquatic Send-Annually Gamma Isotopic pCVkg (dry)
Sedhnent Cs-134 150 1
Cs-137 180 l
Annually St89 200 pCVkg (dry) l 3r 90 40 l
Shoreline soll Semi-Annual Gamma Isotopic pCVkg (dry) l Cs-134 150 Cs-137 180 Annually Sr-89 200 pCVkg (dry)
Sr-90 40
' Illys indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna itadiological Environmental Program. Acual analysis of the samples by Teledyne isotopes may be lower than those listed.
O 39
--.---.- - -.-.- ~.-.--.-..-
Table 3
. North ta Station Sample Anah' sis Program Sample Media Frequency An:dpls 11D' Report Units Soll Once per 3 yrs..
Oamma Isotopic pCVkg (dry)
Cs 134 150 Cs-137 180 Once per 3 ym.
St-89 200 pTkg(dry)
Sr90 40 k
Monthly 1131 1
pC i Monthly Gamma Isotopic pCi/l Cs-134 15 Cs-137 18 Ba-la-140 15 Quarterly Sr89 5
pCVI Sr-90 1
Fish Semi-Annual Gamma Isotopic pCVkg (wr0 Mn-54 130 Fe-59 260 Cc>58, do 130 Zn45 260 Cs-134 -
130 Cs-137 150
- Food Products Monthly if Gamma Isotopic pCVkg (we0
- (Broadicaf available ct Cs-134 60 Vegetation) at harvest Cs-137 80
' I-131-60 Note:
This table is not a complete listing of nudides which can te deteced and reponed. Other peaks that are measurable and
- identifiable, together with the above nuclides, shall also be identified and reported.
- L!.D's indicate those levels that the environmental samples should te analyzed to, in accordance with the Nonh Anna Radiological Environmental Progrant Actdal analysis of the samples by Teledyne isotopes may be lower than those listed.
4 40
IV ProgramExceptions The IEMP progmm exceptions for 1991 are provided in this section. These program exceptions
' pertain to the samples not obtained and 11Ds not met during 1991. The IEMP deviations are provided in the data tables.
by 1
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41
Table 4 REMPExceptions ForScheduled O
Sampfhg And Anab* sis During 1.991 - North Anna O._
Locadon Descripdon Date of Sampling Heason(s) for loss / Exception W-26 Direct Radiation /
14rst Quaner TLD could not be found at collection
- i1.D Sta-23 Vegetation 03/21/91 Only 48g ofvegetation could belcnded into a 1 liter Marinelli, the largest calibrated sample container in use.at Teledyne Isotopes. The sample was counted for 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />, more than two time the normal count time. The LLD for Cs-134 was not met.
Sta-06 Air Paniculate /
02/27/91 - 03A>6/91 Air sampler malfunctioned, but timer Air Radiciodine functioned for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />. Unable to estimate samplevolume to determine if LLD could be rnet..
O d
O 42
. ~..
V Surninmy AndDiscussion Of1991 AnalyticalResults O
Data from the mdiological analyses of environmental media collected during the report period are tabulated and discussed below. The procedures and specifimtions followed in the laix>mtory l
for these analyses are as required in the TeleJ/ne isotopes Quality Assurance Manual and are l
explained in the Teledyne Isotopes Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Appendix D. In addition to intemal quality control measures performed by Teledyne, the labomtory also panicipates in the Environmental Protection Agency's Interlahomtory Comparison Program. Panicipation in this program ensures that 7I
.e1 independent checks on the precision and accuracy
.:I
- 3 of the measurements of radioactive material in
~ ~ ~ '
environmental samples are perfonned. The results
$ {j of the EPA Interialx>mtory Comparison are prc>-
l vided in Appendix E.
Radiological analyses of environmental media characteristically approach and frequently fall l
below the detection liniits of state-of-the-an measurement methods. The "less than" values in the data tables were calculated for each specific analysis and are dependent on saniple size, detector efficiency, length of counting time, chemical yield, when appropriate, and the mdioactive decav factor from time of counting to time of collection. Teledyne Isotopes analyti~il methcxis meet the n
Inwer Limit of Detection (LLD) requirements given in Table 2 of the USNI 9 ranch Technical l
V Position of Radiological Monitoring (November 1979, Revision 1) and the ODCM.
l l
l The following is a discussion and summaiy of the results of the environmental measurements l
taken during the 1991 reponing pericxi.
A. Airborne Exposure Pathtray
- 1. Air kxiine/Particulates l
Charcoal cartridges used to collect airbome icxline were collected weekly and analyzed by a radiochemical separation procedure for iodine-131. The results are presented in Table Ibl. All results were below the required lower limit of detection. Gross beta activity was observed in fifty-one of fifty-two control samples with an average concentration of 0.019 pCi/m and a mnge of 0.009 to 0.035 pCi/m. The avemge measurement for the indicator 5
5 i
locations was 0.021 pCi/m with a mnge of 0.003 to 0.041 pCi/m. The results of the gross 5
5 l
beta activities are presented in Table Ib2. The gross beta activities for 1991 were comparable to levels measured in the 1982-1990 period. Prior to that period the gross beta activities were higher due to atmospheric nuclear weapons testing by other countries.
During the preoperational period ofJuly 1,1974 through March 31,1978 gross beta activities i
ranged from a low of 0.005 pCi/m to a high of 0.75 pCi/m'.
]
5 h
Air paniculate filters were compo.ited by h> cations on a quarte basis and were analyzed by gamma my spectroscopy. The results are listed in Table Ib3. Ilesyllium-7, which is i
43 I
l 1
.-.. -.. ~ -.
. -. ~ ~....
1-0 01;6....<.........................................................e..
............................. 4 o
[
p
\\f
,b.
sQ"
}'
0 01 s
t-,-..--.-,-..--
=. _..
.a 0.001 1988 1987 1988 1989 1990 1991 1992
-e Control
- *- Indicator
.e-Avg LLD t Avg Pre-op Trending Graph - 1: Gross Beta in Air Particulates 0-
-1
-)
.,f......3 Oi.
E I,y
-z 0.01 -
A -- -
~~-r-~--------------u-~~-=-
-i 0.001 i
i i.
i i
i 1977.
1978 1979 1980 1981 1982 1983 1964 1965 1986
-*- Gross Beta
-k" Avg LLD t vg Pre-op
- .O i
Trending Graph - 1: Gross Beta in Air Particulates
praluced continuously in the upper atmosphere
'[
h by cosmic radiation, was measured in all 48 j
+
c ;g %s.c e j O
m m eo ite m m nie. w e ave m se m ea ere ment for the control location was 0.093 pCi/m' with a
(
..y G
.en~ ',
Qt' 1 -
range of 0.069 to 0.169 pCi/m'. The indicator lj ~,
n e
i.
locations had an average concentration of 0.113 4
4 q
5 pCi/m' and a range of G063 to 0.186 pCL/m.
During the preoperational period, luyllium-7 was 3';.,
measured at comparable levels, as would be i
i cxpected. Naturally occurring potassium-10 was detected in one indicator sample with an activity
[A of 0.022 pCi/m3. All other gamma emitters were below the detection limits. During the preopera-o tional period gamma ray spectroscopy measured
[
several hssion products in numerous air particu-
.L j:
Ei
- i late filters. Ali isotopes were attributed to atmo-C,.,
spheric nuclear weapons testing conducted be-k ;*:
- 1. -
2
'((
s fore the preoperational period. Among the iso-j,
' y.
' J--
topes measured were zirconium-95, mthenium-dM 103, mthenium-106, cesium-137, cerium-141 and..[ ( % '
w j[$
cerium-144.
The second quarter composites of air particulate filters from all twelve stations were Q
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 stations.
2.
Precipitation A sample of rain water was collected monthly at station 01 A, on-site,0.75 miles,138 degrees SE and analyzed for gross beta activity. The results are presented in Table Ib4. The average gross beta activity for 1991 in eleven of the twelve samples was 11.6 pCi/ liter with a range from 1.6 to 35 pCi/ liter. Semi-annual con posites were prepared and analyzed for gamma emitting isotopes and t ritium. All 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 1990. 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 1991 period. Tritium was measured in over half of the few quarterly composites made. The tritium activity ranged from 100 to 330 pCi/ liter.
- 3. Soil Soil samples are collected and analyzed every three years from tw elve stations. Since the samples were collected in 1989 they were not collected during 1991.
O 45
. _. ~,.
~.......
B Waterbome Exposurv Pathway h
- 1. Ground /Well Water Water was sampled quanerly from the on-site well at the biology laboratory. These samples were analyzed for gamma radiation and for tritium. %e results are presented in Table B-
- 6. No gamma emitting isotopes or tritium were detected. The second quaner sample was analyzed for strontium-89 and strontium-90. There were no detections of these isotopes alx)ve the detection level. No gamma emitting isotopes were detected during the preopemtional period Tritium was measured in most of the samples during that period with concentrations between 80 and 370 pCi/ liter.
- 2. River Water A sample of water from the North Anna River was ~
'y W collected monthly at station 11,5.8 miles down.
stmam from the discharge lagoon,128 degrees SSE. The results are presented in Table B-7. The samples were analyzed by gamnu spectroscopy, and for tritium. The second quarter samples were analyzed in addition for strontium-89 and stron-
..... M
- N tium-90.
x 3. _.
wp
+
^
Q All gamnu emitters were below the detection level. No detections of strontium-89 or stron-tium-90 occurred. Tritium was measured m od eleven of the twelve samples with an average n
level of 3645 pCi/ liter and a range of 3100 to 4400 cu
,7 w pCi/ liter. This compares favorably with the
.MW^ ""~~
%~
avemge tritium activity for 1989 of 3749 pCi/ liter 7'g-L.
and 1988 was 3925 pCi/ liter. No river water ap.t m_
samples were collected in the preoperational
- Ei --
pericxi.
- 3. Surface Water Samples of surface water were collected monthly from two stations. Station 08 is at the discharge lagoon,1.1 miles,14S degrees SSE on Lake Anna. Station 09 is 2.2 miles upstream on Lake Anna,320 degrees NW. In October of 1991, Station 09 was replaced with Station 09A, which is 12.9 miles WNW. The samples were analyzed for iodine-131 by mdiochemical separation. No iodine was detected in the 24 samples analyzed. The results are presented in Table B-8. The sampks were also analyzed by gamma my spectrometry.
Potassium-40, a naturally occurring radionuclide was measured at 82A pCi/ liter in one sample from station 09A. All gamma emitters were below their detection levels at both stations.
46
10000 l
\\'
E 1000 E
A 1
100 1985 1986 1987 1988 1989 1990 1991
-m-Tritium
+ Average LLD During pre-operational period tritium in river water was not measured, Trending Graph 2 : Tritium in River Water - Station 11 A
l
\\
\\
10000
+
f" Nl
'g f OW".
t
.ng
\\t c
E A2
=
n h
1000 R
d,'
s ha u.
3 i
h 100 r_
1/77 10/79 7/82 4/85 1/88 10/90 e-Tntium
-A-Average LLD
,g Unit 1 critical on 06/06/78.15
[
}
Unit 2 cntcal on 12/14/80.
\\_/
Trending Graph 3 : Tritium in Surface Water - Sta 08 47
o ____
A quanerly composite from each station was prepared and analyzed for tritium.
B
. fM "
O The aium a + ity at mii- 08 for the
~
quarterly composites was at an avemge 4
1
\\:4 level of 4025 pCVliter with a range of 3600 y
is p' gt [
to 4500 pCi/ liter. The tritium level had Q.
+
m been increasing since the middle of 1978 A
when the average level was below 300
>< ^
g 3p-pCi/ liter. Ilowever, during 1991 the re-Q
~g7 y;j sults were within the same range as those fE.
< @ $j?:
measured in 1986 thm 1990. During the W'M
'/
preopemtional period tritium was mea-IU he sured in several samples with concentra-tiom between 90 and 250 pCVliter.
The tritium activity from station 09 was at an average level of 2933 pCi/ liter with a range of 2200 to 3300 pCi/ liter. The level of tritium for 1991 for station 09 is also within the same range as those measured in 1986 thru 1990.
Samples of surface water were collected by the Commonwealth of Virginia from two station <. Station W-33 is located at the discharge lagoon while station W-27 is loc;ued on the North Anna River at the Rt. 208 Ilridge, which is upstream of the site. Twenty-four samples were collected and analyzed by gamma ray spectroscopy and for tritium. The Q
results are presented in Table 11-9. All other gamma emitters were below their detection levels.
Since the tritium level had been increasing during the last several years, four samples from each station were analyzed for tritium during 1991. The average activity at station W-33 in all four samples was 3550 pCi/ liter with a range of 3200 to 3800 pCVliter. This is slightly higher than the 3200 pCi/ liter measured during 1990 at this station. Tritium was measured
~
in two of the four samples at station W-27 with an average activity of 2250 pCVliter and a range of 1800 to 2700 pCVliter. This is also higher than the average of 1098 pCi/ liter measured at station W-27 during 1990.
C Acptatic Exposure Pathway y
- -,=
y (o'....
~
.-?lp g
1.
Sediment / Silt
-o
, - '% F,a *.y/"
Sediment s;unples were collected during
.f
- .:rch and September from each of three
.--Nv A
locations and were analyzed by gamma J,.-
A x1.
- ?-
i
[% j$@Ndh$$ M.u T e M,
spectrometry. The results are presented in 3-W di $$P.
Table 11-10. A number of man-made and kdM hhhh naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in two samp!cs with an average activity of 153 pCi/kg (dry weight) and a range 48
m'TRFilWE!EMt3LTEMNKUNYEWG95WN2iLUMiEN%"WEEEEEME2Gf from 112 to 191 pCVkg -(dry weigh 0. The highest reading for cesium-137 was obtained from station 08 located 1.10 miles downstream in the second cooling lagoon,148 SSF.
(]
k Naturally occurring potassium-40 was observed in all six samples with an average activity of 10955 pCVkg (dry weigh 0 and a range from 6580 to 16800 pCi/kg (dry weigh 0. Radium-226 was measured in five samples with an average concentration of 1638 pCi/kg (dry weigh 0 and a range of 1040 to 2090 pCi/kg (dry weigh 0. Cobalt-60 was measured in one indicator sample from station 08 with an activity of 61.2pCi/kg(dry weigh 0. Also naturally occurnng, thorium-228 was observed in all six samples with an average concentration of 1069 pCi/kg (dry weigh 0 and a range of 575 to 1750 pCi/kg (dry weigh 0. The September samples were analyzed for strontium-89 and strontium-90. There were no detections of strontium-89 in aquatic sediment / silt. Strontium-90 was measured in two samples with an average concentration of 175 pCVkg (dry weigh 0 and a range of 160 to 190 pCi/kg (dry weigh 0.
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 weigh 0. Strontium-90 was measured in most of the samples with concentrations between 60 and 540 pCVkg (dry weigh 0. Strontium-89 was not measured. Potassium-10, radium-226, and thorium 228, all naturally occurring, were measured at background levels.
2.
Shoreline Soil A sample of shoreline sediment was collet.ed in March and September from stauon 09, 2.2 miles upstream of the North Anna Power Station. The samples were analyzed by gamma ray spectiometry. The results are presented in Table B-11. The naturally occurring nuclide potassium-10 was measured in both samples with an average activity 'f 5305 pCi/kg (dry weigh 0 and a range of 4160 to 6150 pCi/kg (dry weigh 0. Thorium-228 was measured in lx)th samples at an average of 839 pCi/kg (dry weigh 0 and a range of 799 to 879 pCi/kg (dry weigh 0. Radium-226 was measured in both samples with an average activity of 1435 pCi/kg (dry weigh 0 and a range of 1170 pCi/kg (dry weigh 0 to 1700 pCi/kg (dry weigh 0.
Cesium-137, a fission product, was monitored in one sample with an activity of 502 pCi/
kg (dry weigh 0.
The September sample was analyzed for strontiurn and there were no detections of strontium-89 or strontium-90.
O 49
i i
1000.
!')
s 100:
k
\\
4i"\\
3.
j e
g
- i
_. p -/- e o
& 7cq\\
.P-
-3 M-f g
r.
p
.-y o
/l g
10:
j
~/ f g
i h
l
\\
\\
l
\\ /
\\/
)
__ _ E a
03'85 09/85 03'86 OW86 04/87 09/07 03/88 09/38 04/89 09H9 0390 0990 0391 0991
- - Staton-8 4-Statm09 d Staten 11 No cobalt 58 measured dunng pre operational perod Trending Graph - 4 : Cobalt-58 in Sediment Sitt C'
G 1000.
?
E 100 -
'A
{
,A,
~
\\
.e r
.n
. h..
is'~h
^~<a a-
..,~d en
/
s gg 10 1
03/85 09/85 '03'86 OG'86 04/87 09/87 03?8 09/B8 04/89 09/89 03TO OS90 0391 0391
- - Statico-8 4-Statm09 4 Staton-11 f))
l No cobalt 60 measured during pre-operatonal period Trending Graph 5 : Cobalt-60 in Sediment Sitt 50
r 1000; y,
L.
f
\\
y
/
l4 1
\\
,e 100'.
E
?.
A~
n' l
Q
/
~s e
Y '.,
a5 10-
'd 1
03'85 09/85 03'86 09 86 04/87 09'87 03/88 09'88 04'89 09'89 03SO 09'90 03'91 09'91
-a-Stat!on-8
+ Stat:on 09
-A-Station-11 No cesium 134 measured dunng pre-operational penod Trending Graph 6 : Cesium-t34 in Sediment Silt r\\
t 10000 c
+
1000
/~
?
L. _
,A i
.s
\\
y
/
p................ K.............qy
...\\....
4
,..Y
\\
A l
S 100 A
tr
_Q,$
w,
?
\\
4; N
n
+
l 3
C l
O l
s 10 :
1 1985 25 1985.75 1980 25 1C86 75 198725 1987.75 t988 251988 75 1989 3 1%9 75 1990 25 1990.75 199125 199175 l
1 a-Station-8 4-Station-09
- 4. ' Station-11 4 Avg. Pre-Op No cobott-58 rneasured during pre-operational period a
Trending Graph - 7 : Ceslum 137 in Sediment Sitt 51
D. Ingestion Exposure Pathway h
- 1. Milk The results of the iodine-131 analysis ofmilk samples are presented in Table 412. A sample was collected monthly from two stations. A total of 24 samples were analyzed during 1991.
There were no measurements of iodine-131 alx>ve the detection limits.
The milk samples were also analyzed by gamma ray spectroscopy and the results are also presented in Table B-12. A total of 24 samples were analyzed. Naturally occurring potassium-40 was measured in all of th, uples with an average of 1291 pCi/ liter and a
}
range of 1010 to 1480 pCi/lher. The fission protct cesium-137 has been detc1ed sporadically in recent years and the activity has been attributed to global fallout from p1st atmospheric weapms testing. However, cesium-137 was not detected at levels above 11D in any mtlk samples in 1991. All other gamma emitters v ere below their detection levels.
A quanerly composite was prepared from each of the two collection stations and analyzed for strontium-89 and strontium-90. Strontium-89 was not detected at levels above LID in any of the samples monitored. Strontium-90 was detected in seven of the eight samples monitored with an average level of 0.91 pCi/ liter and a range of 0.55 to 1.4 pCi/ liter. This is similar to activities detennined in previous years and lower than the preoperational levels of 2.2 to 5.4 pCi/ liter.
2.
Fish h
m.
Q'~4
.I -
Aquatic biota can be sensitive indicators of radio-
% N[J'd.
nuclide accumulation in the environment because 4-D of their ability to concentrate certain chemical W,
elements which have radioactive isotopes. The I?
' -h lU
,.i' 3
.. & g ;
results are presented inTable B-13. Ten samples of 4
r fish were collected during 1991. These samples ?:
- C.
- f g f" -
s'
~ ', [ I jjjj 4
were analyzed by gamma ray spectroscopy and the J
e-t. ' 'Q{,
naturally occw : 'ng isotope potassium-40 was found
?
g
{~
in all samples at an average of 1409 pCi/kg (wet
, /.'.,
weigh 0 with a range of 831 to 2160 pCi/kg (wet ?4
'/"
. g"jO.
weigh 0.
The fission product cesium-137 was measured in three samples at an average of 76.7 pCi/kg (wet weigh 0 a nd a range of 57.9 to 99.4 pCi/
?,# "* #
kg (wet weigh 0 During the preoperational period cesium-137 was measured in one-fourth of the fish samples collected with concentrations between 31 and 66 pCi/kg (wet weigh 0.
- 3. Food /Vegctation Forty food samples were collected from five k> cations and analyzed by gamma spectrom-g euy. The results are presented in Table R14. Naturally occurring potassium-40 was monitored in all of the samples with an average activity level of 8969 pCi/kg (wet weigh 0 52
1
}
4 l
1000.--
I E.
,c
.E 100
\\
,a-*-
y c
E M
(h A a N
-MA N
3,.
\\ JE 4
W
,5,
~as N
10 3
4/B0 4S2 4S4 4/85 4/86 12/86 8/87 12/87 6/88 12/88 6/89 1G'89 10/90 10/91 Station 08
--+--- Station-09
-A-Staton-25 During the pre operational penod cesium-134 was not measured Trending Graph 8 : Cesium 134 Iri Fish O
10000 1000 :
- M - w,.
.k YY
- 88 ~8
/
s v
~
z 100. g-m_
,a.
w
.................................................................................... 3.,,
f e a4 M
10.
g l
1 5/80 5/82 4/84 4/85 4/86 10/86 7/87 12/87 7/88 12/88 7/89 12/89 10/90 5/91
-*- Station-08
- Sta* ion-09 Station-25
.. +.. Average Pre-op Trending Graph - 9 : Cesium-137 in Fish 53 M
~. _ _ _. _ _ _ __ _ _. _ _ _ _. _ _ _ _ _ _ _ -
^*
and a range of 383 to 30500 pCi/kg (wet weigh 0. Cos-t0. g 'g %
. y mogenic beryllium-7 was detected in 32 of the 40 samples
,;[$ ;;9 f' C
' ;.g
,- ( r.
with an avemge concentmtion of1400 pCi/kg(wet weigh 0 dy f( ;h,; and a range of 252.o 7710 pCVkg (wet weig
- c' 6 Q \\ r.
y - 7 terrestrial nuclide thorium-228 was detected in nine of the
' 1( y, e 1
samples at an avemge activity of 370 pCi/kg (wet weigh 0 7 ^
b/j,',
K and a range of 29.5 to 844 pCi/kg (wet weigh 0.
f
'. Q
t2 h,. J ne fission product cesium-134 was not detected at g
i?.
- ~5 ~
levels above LLD during 1991. Cesium-137 was detected in
- 'gt,
founeen of the fony samples with an avemge activity of 168
/sp LM.t pCi/kg (wet weigh 0 and a range of 23.5 to 448 pCi/kg (wet k
(l
- 4. [,
~
'I in previous years. Cesium-137 was measured in broadleaf weigh 0. These results are consistent with (1 ose measured
[jP f'
p
/y gaiden vegetation during the preopemtional period with Fk
^ -
concentmtions between 53 and 98 pCi/kg (wet weigh 0.
/
$.. b E Dhect Radiation Exposure Pathway
- 1. TLD Dosimeters Thermoluminescent dosimeters (TLDs) detennine environmental radiation doses and the results are Q
presenteci in Table Ibl5. Individual measure-I ments of extemal radiation levels in the environs
~,
I of the Nonh Anna site had an average dose of 5.6 g
. s ',,
mIVstandard month with a range of 4.1 to 9.1 mIV xe standard month. The control station, No 24 had an D
S average reading of 3.8 mIVstandard month with a hM range of 3.4 to 4A mIVstandard month.
Sector 'ILDs are deployed quarterly at thirty-two locations in the environs of the Nonh Anna site.
Two badges are placed at each location. The results are presented in Table Ibl6. %e avemge level of the 32 locations (two badges at each location) was 6.2mIVstandard month with a range l
of 3.1 to 10.6 mIVstandard month. The thirty-two control TLDs from eight locations showed an -
average reading of 5.1 mIVstandard month with a range of 3.4 to 7.4 mIVstandard month. One of the badges from the first quaner was missing.
~
i Although a thorough search s s made of the area the TLD could not be located. During the part (starting in 1977) of the preoperational period that the calculation of the TLD dose included a correction fbr the in transit dose, the doses were measured between 4.3 and 8.8 mIVstandard month.
54
100 b
T I
- i E
10
. %(._.,. _. _=.%,=*e4,wwww_.._.
E 1
1/86 7/86 1/87 7/87 1/88 7/88 1/89 7/89 1/90 7/90 1/91 7/9 '
- a-- Environmente! TLDs
+- Sector TLDs 4
Average Pre op l
Trending Graph 10 : Environmental Radiation - TLDs l
i i
55
VL Conclusions l O The msults of the 1991 Radiological Environmental
)'
Monitoring Program for the North Anna Nuclear Power j
t y%
Station have been presented. The following sections
,2 discuss each pathway individually followed by a prognun am nx
- summary, umt s W AM>orne Exposurv Pathway I
Air paniculate gross beta concentrations of all the indicator locations for 1991 fallowed the gross beta concentrations at the control location. The gross beta concentnuions were comparable to levels observed since 1982 except for a five week period in 1986 which was l
influenced by the Chernobyl accident. G ross beta concen-l tmtions in the preoperational period were highly variable, mnging from 0.0043 to o.75 pci/ cum. This variation is due tooccasionalatmosphericnuclearweapons tests. Gamma isotopic analysis of the particulate samples identified natumi isotopes (beryllium-7 and potassium-40). There were no detections above the 11D for fission products nor other man-made isotopes in the paniculate media during 1991. Iodine-131 was not detected in the 624 charcoal filters analyzed O
during 1991.
A precipitation sample was collected monthly during 1991 and analyzed for gross beta activity.
All gross beta activities were comparable to those measured in previous years. During the l
preopemtional period the avemge gross beta activity was 0.92 pCi/ liter. Semi-annual composites were analyzed for gamma emitting isotopes and tritium. All gamma emitters were below detection limits. Tritium was not observed above the 11D during '1991. During the preoperational period, the avemge tritium activity was 165 pCi/ liter.
Waterborne Exposure Pathway No man-made or natural isotopes were monitored in Lake Anna surface water except for tritium. The average tritium activity in 1991 at the waste heat treatment facility was 4025 pCi/ liter, or 20.1% of the water sample reporting level. In 1990 the tritium level was 3900 pCi/ liter. The preoperational level of 150 pCi/ liter has been rising since 1977. The tritium level upstream of the site was 2933 pCi/ liter as compared with 3200 pCi/ liter in 1990.
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 3117 as compared to 2230 pCi/
liter for 1990. The upstream location had an activity of 2250 pCi/ liter as compared to 1098 pCi/
liter for 1990. No gamma emitting isotopes were detected.
i 56
}.l %$WW &$?3MQ&WW%R@5N?WNWMTMM$$hMkW River water collected from the Nonh Anna River,5.8 miles downstream of the site, had an average tritium level of 3645 pCi/ liter. The average tritium in 1990 had been 3783 pCi/ liter. No O
samma emitier8 were detected.
Ground water from the environmental well on-site contained no gamma emitters. 'Ihere were also no detections of tritium in ground /well water during 1991.
Acpeatic Pathway Sediment / silt samples provide a sen.ive indicator of discharges from nuclear power stations, e
although they do not provide a direct dose pathway to man. %e sediment from Nonh Anns erwironmental samples indicated that two man-made isotopes were present. Cesium-137 was detected in two samples at two locations. During the preoperational pericxt, cesium-137 was also measured in samples of aquatic sediment. Cobalt-60 was measured in one sample.
The samples of shoreline soil monitored downstream of the site contained no cesium 134.
Cesium-137 was measured in one sample at 502 pCi/kg. This is higher than the 1990 average of 74.6 pCi/kg.
\\
=i y hogestion Pathstvsy N
Iodine-131 was not detected in any of the twenty-four milk samples using the Q
\\
g radiochemicdseparationmethod. Ahhough cesium-137 has lxxn detected occasion-ally in previous years and attributed to past
...f,79W N
atmospheric nuclear weapons testing, there Ob[%g milk samples. The values were lower than
,2 were no detecions during 1991. Stron-
' k' g
.t tium-90 was measured in seven of the eight 1
4
&'. A* *4 ;oL~ t the levels detected in 1990 and during i
'g
+
preoperational years. Strontium-90 from those years is attributed to past atmo-spheric nuclear weapons testing. No strontium-89 w.s detected in any of the milk samples.
Naturally occuning potassium-40 was measured in all the milk samples at nomul environmental levels.
Radioactivity in fish, vegetatiot., and milk does present a direct dose pnhway to man. Fish samples in 1991 showed the presence of one man-nude isotope, cesium-137. This isotope was at an activity level somewhat higher than preoperational levels but statistically similar to levels in 1987 through 1990. Only cesium-137 was measured in preoperational environmental fish samples.
Due to primary and secondary steam generator problems experienced at North Anna during 1984/
1985, a build up in activity levels txath in efnuents and fish did occur. Repairs to the steam generators and better liquid waste processing have reduced these activity levels in efDuents and thus decreased O
"" tivi'Y '"" t' "'e " " " i"8 "*"r""d i" '"" ft'" '"" """'""" '"""' ' ""itv '" '99 ' ' '"' t " * ~
137 was 3.8% of the reponing level.
57
Vegetation samples contained the man-made isotope cesium-137. The cesium-137 activity levels in 1990 and in preoperational samples were statistically *imilar to the 1991 level.
O Dirret Radiation Exposurv Pathway The direct exposure pathway as measured in the environment of the Nonh Anna site by thermoluminescent dosimetry has remained essentially the same since the 1977 preoperational period at 6 milliroentgens per month or 0.2 milliroentgens per day. The average dose levels monitored have shown a normal fluctuation about these levels, and are less than the estimated whole body dose due to natural terrestrial and cosmic radiation and the intemal dosage from natural radionuclides.
Prograrn Conclusions The results were as expected for normal environmental samples. Naturally occurring activity was observed in sample media in the expected activity ranges. Occasional samples of nearly all media showed the presence of man-made isotopes. These have been discussed indisidually 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 Reponing level Concentrations listed in the Offsite Dose Calculation Manual. These concentrations are based upon 25% of the annual dose Os commitment recommended by 10CFR50, Appendix I, 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 observed in the environs of the Nonh Anna Nuclear Power Station in 1991.
O 58
~
VII. References (o)
- 1. Virginia Electric and Power Company, Nonh Anna power Station Technical Specifiations, Units 1 and 2.
- 2. Virginia Electric and Power Company, Station Admir t.mrive Prowdure, VPAP-2103, "Offsite Dose Calculation Manual," Rev. 2, September,1 1991.
- 3. Title 10 Code of Federal Regulation, Part 50 (10CFR50), " Domestic Licensing of Production and Utilization Facilities."
- 4. United States Nudear Regulatory Commission Regulatory Guide 1.109, Rev.1, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," October,1977.
- 5. United States Nuclear Regulatory Commission, Regulatory Guide 4.8, " Environmental Technical Specifications for Nudear Power Plants," December,1975.
- 6. USNRC Branch Tedmical Position, " Acceptable Radiological Environmental Monitoring Program," Rev.1, November 1979,
- 7. NUREG G172, " Radiological Effluent Technical Specifications for PWRS," Rev. 3, Mardi, 1982.
- 8. National Council on Radiation Protection and Measurements, Repon no. 39, " Basic n
Radiation Protection Criteria," Washington, D.C., January 1971.
q)
- 9. National Council on Radiation Protection and Measurements, Report No. 45, " Natural Background Radiation in the United States," Washington, D.C., November,1975.
- 10. National Council on Radiation Protection and Measurements, Repon No 93, "lonizing Radiation Exposure of the Population of the United States," Washington, D.L., December, 1987.
- 11. National Council on Radiation Protection and Measurements, Repon No. 95, " Radiation Exposure of the U.S. Population from Consumer Products and Miscellaneous Sources,"
Washington, D.C., December 1987.
- 12. DOE /NE-0072, "Nudear Energy and Electricity, The Hamessed Atom," US Dept. of Energy, 1986.
- 13. Eichholz, G., "Em'ironment Aspects of Nudear Power," Lewis Publishers, Inc.,1985.
- 14. Eisenbud, M., " Environmental Radioactivity," Academy Press, Inc., Orlando, F1,1987.
- 15. Fitzgibbon, W., " Energy Skill Builders, Nudear Reactor," Enterprise for Education, Inc.,
1987.
- 16. Glasstone, S., andJord;n, W., "Nudear Power and its Environmental Effects," American
()
Nudear Society,1982.
59
E@
@ M E1[3ff$$$IE N1(( BEE 9E E E E7 171 7E M RADIOLOGIGtL ENVIRONMENTAL MON 11DRING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 1991 Docket No. 50-338/339 january 1 to December 31,1991 Page 1 of 5 All indicalor Control Non-Medium or Analysis Locations Location with Highest Mpyn Location routine Pathway LLD1 R0 Ported Sampled Total Mean Name Distance Mean Dean Measure-(Un:t)
Type No.
Range Direction Range Range m onts Air lodine 1-131 624 0.04
-(0/572)
NA NA
-(0/52) 0 3
(pCi/m )
Airborne Gross 624 5
20.7(570-572) 05 4.20 mi.
22.4(52/52) 19.4(51/52)
O Particulates Beta (2.8-41)
NNE (13-35)
(8.9 35) 3 (1E 03 pCi/m )
Gamma 48 Be-7 48 10 113(44/44) 05 4.20 mi.
143(4/4) 93.2(4/4) 0 (62.7-186)
NNE (107-186)
(68.7 169)
K-40 48 10 21.8(1/44) 05A 3.20 mi.
21.8(1/4)
-(0/4) 0 N
St-89 12 3
-(0/11)
NA NA
-(0/1) 0 Sr90 12 0.4
-(0/11)
NA NA
-(O'1) 0 Ground Gamma 4
Well Water K-40 4
60
-(G'4)
N/A N/A NONE O
(pCi/ liter)
Tritium 4 2000
-(0/4)
N/A N/A NONE O
~
River Gamma 12 Water (pCi/ liter)
K 40 12 200
-(0/12)
N/A N/A NONE O
Tritium 12 2000 3645(11/12) 11 5.8 mi.
3645(11/12)
NONE O
(3100-4400)
SSE (3100-4400)
O I
60
EdFSIs3!!!i%tiSEsD!i 20 W amW99 m Momm l
ILtDIOLOGIGtL ENVIRONMENTAL MON 110 RING PROGRAM SilafMARY l n North Anna Nuclear Power Station, Louisa County, Virginia - 1991 v
Docket No %33&/339 January 1 to Decemler 31,1991 Page 2 of 5 All Indicator Control Non-Modium or Ane!ysis Locations Location with Highest Mean Location routine Pathway LLD1 Reported Samplod Total Mean Name Distanco Mean Mean Measure-(Unit)
Type No.
Range Olroction Rango Range monts Precipitation Monthly (pCVhter)
Gross 12 4
11.6(11/12) 01 A 0.2 mi.
11.0(11/12)
NONE O
Beta (1.6-35)
NE (1.6-35)
Gamma 2
(Semi-Annually)
Be-7 2
70
-(0/2)
N/A N/A NONE O
Tritium 2 2000
-(0/2)
N/A N/A NONE O
Surface 1-131 24 0.5
-(0/12)
N/A N/A
-(0/12) 0 Water (pCVliter)
Regular Gamma 24 O
x-40 24 200
-<o/12) oe 82.4(i/i2) 82.4 <, /i 2) 0 Tritium 8 2000 4025(4/4) 8 1.1 rr.i.
4025(4/4) 2933(3/4) 0 (3600-4500)
SSE (3600-4500)
(2200-3300)
Surface Sr-89 1
2000
-(0/1)
N/A N/A
-(0/1) 0 Water (pCVliter)
Regular Sr90 1
2000 0.73(1/1) 8 1.1 mi.
0.73(1/1)
-(0/1) 0 Monthlies SSE Surface Gamma 24 Water (pCi/ liter)
K-40 24 200
-(0/24)
N/A N'A NONE O
State Splits Tritium 14 2000 3117(6/8)
W33 3550(4/4)
NONE O
(1800-3800)
(3200-3800)
O 61
WOSMf785fV#"iFit!P5 Gig @TDM17sp3jyMNFq!LTggp RADIOLOGICAL ENVIRON 31ENIAI. 310NI1DRING PROGRA31 SU31.tfARY North Anna Nuclear Power Station, louisa County, Virginia - 1991 Docket No. 50 338/3y)
January 1 to Dewmber 31,1991 Page 3 of 5 All indicator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLD1 Reported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)
Type No.
Range Direction Range Range monts Sediment Gamma 6
Silt (pCi/kg K-40 6
200 11328(4/4) 11 5.8 mi 16000(2/2) 10210(2/2) 0 (dry))
(6580-16800)
SSE (15200-16800) (6620-13800)
Co-60 6
150 64.2(1/4) 8 1.1 mi SSE 64.2(1/2)
-(0/2) 0 Cs-137 6
194 194(1/4) 8 1.1 mi SSE 194(1/2) 112(1/2) 0 Ra 226 6
100 1843(3/4) 11 5.8 mi SSE 1925(2/2) 1330(2/2) 0 (1680 2090)
(1760-2090)
(1040-1620)
Th-228 6
30 1207(4/4) 11 5.8 mi.
1475(2/2) 793(2/2) 0 (816-1750)
SSE (1200-1750)
(575-1010)
Sr-89 3
4.0
-(0/2)
N/A N/A
-(0/1) 0 (Annually)
Sr 90 3
0.8 190(1/2) 11 5.8 mi.
190(1/2) 160(1/1) 0 SSE (Annually)
Shoreline Gamma 2
Soll (pCi/kg K-40 2
200 5305(2/2) 9 2.2 mi.
5305(2/2)
NONE O
(dry))
(4160-6450)
NW (4160-6450)
Cs-137 2
40 502(1/2) 9 2.2 mi.
502(1/2)
NONE O
NW Ra-226 2
100 1435(2/2) 9 2.2 mi.
1435(2/2)
NONE O
(1170-1700)
NW (1170 1700)
Th-228 2
30 839(2/2) 9 2.2 mi.
839(2/2)
NONE O
(799-879)
NW (799-879)
Sr-89 1
4.0
-(O'2)
NA NA NONE O
(Annually)
Sr-90 1
0.8
-(O'2)
NA NA NONE O
(Annually)
O 62
RADIOLOGICAL EN1'IRONMEN7ML MONITORING PROGRAM
SUMMARY
l North Anna Nuclear Power Station, Louisa County, Virginia - 1991 Docket No. 50-338/339
- January 1 to December 31,1W1 Page i of 5 All Indicator Control Non-M6dium or Analysis Locations Location with Highest Mean Location routine Pathway LLD1 R* Ported Sampled Total Mean Name Distance Mean Mean Measure-(Unit)
Type No.
Range Direction Range Range ments Milk 1-131 24 0.5
-(0/24)
N/A N/A NONE O
(pCViiter) l Gamma 24 K-40 24 100 1291(24/24) 12 8.3 mi.
1303(12/12)
NONE O
(1010-1480 NW (1010-1480)
Sr-89 8
5
-(0/8)
N/A N/A NONE O
l (Quarterly) i Sr90 8
0.8 0.91(7/8) 12 8.3 mi.
0.92(3/4)
NONE O
(Quarterly)
NW (0.55-1.4)
(0.71 1.1)
Fish Gamma 10 pCi/kg (wet)
K-40 10 200 1395(6/6 25 16.5 mi.
1430(4/4) 1430(4/4) 0 (831-2160)
NW (1100-2050)
(1100-2050)
Cs-137 10 40 76.7(3/6) 08 1.10 mi.
76.7(3/4)
-(0/4) 0 (57.9-99.4)
SSE (57.9-99.4)
Food Gamma 40 Vegetation Dose 1400(32/40) 25 0.93 mi.
2564(5/8)
NONE O
(pCi/kg Be-7 40 (wet))
(252-3600)
8969(40/40) 23 0.93 mi.
11095(8/8)
NONE--
0 (383-30500)
SSE (383-29100)
Cs-137 40 80 168(14/40) 15 1.37 mi.
243(2/8)
NONE O
(23.5-448)
SE (37.0-448)
Ra 226 40 80 580(3/40) 16 12.60 mi.
1070(1/8)
NONE O
(233-1070)
NW 370(9/40) 15 1.37 mi.
844(1/8)
NONE O
Th-228 40 (29.5-844)
SE Direct Gamma 48 0.2 5.74(44/44) 01 0.2 mi.
7.48(4/4) 3.78(4/4) 0 Radiation Dose (4.1-9.1)
NE (6.5-9.1)
(3.4-4.4)
(mR/std. month)
(Regular TLDs)
O 63
RADIOLOGICAL ENVIRONMENTAL MONI1DRING PROGRAM
SUMMARY
North Anna Nuclear Power Station, Louisa County, Virginia - 1991 Docket No. 50-338/339 January 1 to Demmber 31,1991 Page 5 of 5 All It"ilcator Control Non-Medium or Analysis Locations Location with Highest Mean Location routine Pathway LLo1 Reported Sampled Total Mean Name Distance Mean Mean Nieasure-(Unit)
Type No.
Range Direction Range Range ments Direct Gamma 12 0.2 5.28(11/11) 01 0.2 mi 6.8(1/1) 3.4(1/l) 0 Radtation Dose (3.9-6.8)
NE (mR/std. Month) -
(Annual TLDs)
Direct Gamma 287 0.2 6.20(255/255)21/53 0.30 mi 8.99(8/8) 5.12(32/32) 0 Radiation Dose (3.1 10.6)
SW (7.9-10.6)
(3.4-7.4)
(mR/std. Month)
(Sector TLDs) 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, o
u t
O 64 r,-
E &T39W#E31( M N & R M EELggg7jggf2Z32s2Gfit TAIRE B-1: JODINE-131 CONCENTRATION IN FILTERED AIR I
North Anna Power Station, l.ouisa County, Virginia - 1991 pCUm3 12 Sigma January 1 to December 31,1991 Page 1 of 2 Collection STATIONS Dato 01 02 03 04 05 05A 06 07 21 22 23 24 JANUARY 01/02-01/09 <.008
<.009
<.009
<.01
<.01
<.01
<.009
<.009
<.01
<.009
<.01
<.009 01/09-01/16 <.03
<.03
<.03
<.01
<.03
<.06
<.03
<.03
<.05
<.02
<.02
<.02 01/16-01/23 <.05
<.06
<.03
<.07a
<.03
<.06
<.02
<.02
< 01
<.01
<.02
<.02 01/23-01/30 <.009
<.009
<.009
<.02
<.02
<.02
<.02
<.02
<.02
<.02
<.02
<.02 FEBRUARY 01/30-02/06 <.009
<.009
<.009
<.009
<.009
<.01
<.01
<.008
<.009
<.01
<.01
<.01 02/06-02/13 <.008
<.01
<.009
<.01
<.009
<.009
<.01
<.01
<.01
<.01
<.01
<.009 02/13-02/20 <.02
<.01
<.01
<.01
<.009
<.01
<.01
<.01
<.01 c.0 i
<.01 c.005 02/20-02/27 <.007
<.006
<.006
<.006
<.007
<.006
<.007
<.006
<.006a <.007
<.006
<.006 MARCH 02/27-03/06 <.008
<.007
<.008
<.008
<.007
<.007
<.2 b
<.01
<.008
.006
<.008
<.007 03/06-03/13 <.01
<.02
<.01
<.01
<.01
<.01
<.009
<.01
<.008
<.01
<.02
<.01
^'3/13-03/21 <.006
<.005
<.005
<.005
<.005
<.005
<.01
<.006
.005
<.003
<.004
<.003 L3/21-03/27 <.01
<.0 *
<.01
<.01
<.009
<.01
<.05
<.06
<.01
<.01
<.01
<.01 03/27 04/03 <.008
<.008
<.02
<.02
<.01
<.02
<.01
<.01
<.02
<.008
<.006
<.007 APRIL 04/0310/91 <.02
<.32
<.01
<.02
<.02
<.01
<.02
<.01
<.02
<.02
<.02
<.02 r^
04/10-17/91 <.01
<.02
<.01
<.02
<.02
<.02
<.02
<.008
<.008
<.008
<.008
<.008
(
04/17 25/91 <.003
<.003
<.003
<.005
<.005
<.003
<.005
<.003
<.005
<.009
<.006
<.007 04/25-01/91 <.008
<.009
<.01
<.01
<.006
<.007
<.008
<.009
<.009
<.008
<.007
<.008 MAY 05/01-08/91 <.006c <.007
<.007
<.006C <.007
<.007
<.006
<.006
<.008
<.008
<.007 05/08-16/91 <.005
<.007
<.004d y,oo4d <.004
<.004
<.004
<.003
<.003
<.003
<.003
'o
<.006d <.007
<.006
<.006
<.007
<.005
<.007
<.003 05/16-22/91 <.005
<.007
<.06I
'3
<.003
<.003
<.003
<.003
<.003
<.0039 <.002
<.002 05/22-30/91 <.004
<.004
<.004 JE 05/30-05/91 <.006
<.005
<.005
<.005
<.005
<.01
<.003
<.005
<.005
<.006
<.007
<.009 06/05-12/91 <.007
<.007
<.007
<.007
<.005
<.005
<.006
<.005
<.005
<.005
<.005
<.004 06/12 19/91 <.005
<.004
<.004h <.003
<.004
<.004
<.003
<.004
<.004
<.004
<.002
<.002 06/19-26/91 <.004
<.005
<.004d <.004
<.004
<.005
<.004
<.004
<.004
<.004
<.008
<.007 06/26-03/91 <.008
<.007
<.006
<.007
<.007
<.007
<.006
<.007
<.007
<.007
<.004
<.005 JULY I <.04J
<.004
<.004
<.002
<.004
<.004
<.005
<.004
<.002
<.006
<.006 07/03-10/91 <.004 07/10-17/91 <.002
<.002
<.002
<.005
<.005
<.005
<.002
<.005
<.005
<.002
<.005
<.02 07/17-24/91 <.006
<.01
<.01
<.006
<.005
<.004
<.004
<.004
<.004
<.01
<.004
<.004 07/24 31/91 <.01
<.01
<.01
<.01
<.02
<.02
<.01
<.01
<.02
<.01
<.02
<.01 AUGUST 07/31-07/91 <.03
<.03
<.03
<.03
<.02
<.01
<.03
<.04
<.03
<.03
<.01
<.04 08/07-14/91 <.02
<.02
<.02
<.02
<.01
<.01
<.01
<.01
<.01
<.01
<.01
<.01 08/14 21/91 <.02
<.02
<.01
<.02
<.02
<.02
<.02
<.01
<.006
<.009
<.008
<.007 08/21-28/91 <.01
<.02
<.02
<.02
<.02
<.02
<.02
<.02
<.02
<.02
<.02
<.02 g
08/28-04/91 <.008
<.008
<.009
<.009
<.009
<.01
<.008
<.008
<.01
<.009
<.009
<.008 65 1
.o 1ABLE B 1: IODINE 131 CONCENIRA110N IN FILTERED AIR North Anna Power Station, Louisa County, Virginia - 1991 pCi/m3 12 Sigma january 1 to Dewmber 31,1991 Page 2 of 2 Collection,
STATIONS Date 01 02 03 04 05 05A 06 07 21 22 23 24 SEPTEfaBEB 09/0411/91 <.005
<.007
<.006k <.006
<.006
<.005
<.005
<.005
<.007
<.006
<.000
<.008 09/11 T91 <.005
<.004
<.004
<.004
<.02
<.006
<.004
<.005
<.005
<.005
<.02
<.02 09/18 25/91 <.Cf
<.004
<.003
<.002
<.002
<.003
<.003
<.003
<.003
<.0s2
<.003
<.003 09/25 02/91 <.004
<.006
<.005
<,006
<.005
<.008
<.006
<.006
<.006
<.006
<.006
<.006 9C.10Bf3 10/02-00/91 e.007
<.007
<.007
<.007
<.008
<.009
<.007
<.039
<.009
<.009
<.01
<.01 10'09 7N91 <.007
<.006
<.006
<.006
<.005
<.006
<.007
<.006
< 004
<.003
<.006
<.005 10/16 23/91 <.01
<.009
<.02
<.008
<.009
<.01
<.008
<.01
<.009
<.01
<.01
<.01 105 30/91 <.005
<.01
<.01
<.01
<.01
<.01
<.01
<.01
<.01
<.01
<.01
<.01 ROVEMBER 10/30-0W91 <.03
<.02
<.03
<.02
<.02
<.02
<.01
<.01
<.01
<.01
<.01
<.02 11/06 13/91 <.03
<.02
<.02
<.02 s.02
<.02
<.02
<.03
<.02
<.02
<.03
<.03 11/13 2G'91 <.02
<.01
<.01
<.01
<.01
<.02
<.01
<.01
<.02
<.02
<.01
<.02 11/20 27/91 <.02
<.02
<.02
<.02
<.02
<.03
<.02
<.02
<.02
<.02
<.02
<.02 DECEMDEB 11/2'F.04/91 <.03
<.03
<.03
<.02
<.02
<.04
<.03
<.04
<.02
<.02
<.02
<.01 1Lt+12/91 <.006
<.005
<.009
<.01
<.009
<.005
<.004
<.004
<.004
<.004
<.004
<.C05 12/12 M/91 <.02
<.01
<.01
<.01
<.01
<.02
<.01
<.02
<.02
<.01
<.01
<.01 J
O 12/18-26/91 <.01
<.01
<.01
<.01
<.0 t
<.01
<.01
<.01
<.01
<.01
<.01
<.01 12/26-1/2/92 <.02
<.02
<.02
<.02
<.02
<.02
<.02
<.02
<.02
<.01
<.02
<.02 a
Sampler mehunction cauung low volume.
b Pump malfunction; results in total pCi e
Samplers not running on arrival although pumps were hot Volumes estimated d
Timer malfunctioned; estimated volumes using starthtop times e
Volumes low due to decrease flow rate.
f Voiume low due to malfunction of pump.
g Pump not mnning on arrival.. Volumes determined by timer.
h Timer malfunction; sampler operating propedy and volume satisfactory, i
Pump not runnir.g on arrival, estimated volume.
J Pump vanes broke resulting in low volume.
5 k
Timer malfunction; volume estimated by start stop times.
/
O 66 m___m.____--
____m
3-j;
\\
.. e n
l l
i r
j TABLE B-2 I
(PeseIat4)
{
NORTH N4NA - 1991
}
s t
j CONGNTRAllONS OF GROSS BETA IN AIR PARTICULATES f
I.0E43 rG/m3 12 %gma i
COLLECIlON 1991 1
AVERAGE DATE ol 42 93 64 05 45A 96 87 21 22 23
- 2 s.d.
JANUARY i
I 01M241/d9 2113 26.5 221 3 171 3 3115 351 5 2413 2213 261 5 3215 2113 241 3 25 1.
10 01M9 01/16 -
121 3 131 3 181 3 101 3 211 3 171 3 16 t 3 1113 1413 1813 1413 141 3
- 4 1 7
}
$1/16-01/23 2313 201 3 201 3 4118 (e) 261 5 241 5 2013 171 3 181 3 2515 181 3 231 3 23 1 I)
)
01/23 41/30 221 5 2315 2815 3015 3515 291 5 2515 2113 121 3 3115 3015 2515 26 1 12 j.
j FEBRUARY l
Ol/3642M6 2113 231 3.
201 3 201 3 3115 cd 21 t 3 1813 1613 2815 3115 281 5 24 t to f
l 022642/13 181 3' 161 3' 2315 231 5 2915 fi ? -
,:15 1413 2115 ist3 241 6 2115 2It 8 02/13 42/20 1413 201 5 211 3 211 3 2315 2: e t c13 131 3 1513 1713 1713 2515 19 8
]
02/20 02/27 1713 1713 171 3 1813 2215 17 1 691 3 141 3
< 5 (a) 2113 1813 2115 18 1 5 MARCH
\\
02/274326 141 3 1713
'61 3 1513 2t i 3 161 3 2.810.7 (b) 1512 111 3 201 3 1713 181 3 151 9
}
03M643/13 2515 2515' 2415 18 1 _*
261 5 3115 1413 1813 141 3 301 5 301 5 2615 23 1 12 i:
03/13 43/21 221 3 1413 151 3 14 1 's 201 3 151 3 1516 101 3 1313 161 3 1413 171 3 151 6 6
}
03/21 43/27 2615 2415 2215 201 5 251 5 2615 161 5 131 3 2115 231 5 181 5 2515 22 1 s i
j 03/2744S3 1615 1413 161 5 1715 211 5 1715 9.313.7 1715 141 3 1815 131 3 1513 161 6 t
faverage 19 i 9 26 i 9 2419 26 i 16 251 le 23 i 13.16112 1617 le 19 23 i 11 2ei13 2219 30 1 6 I
i 7 s d.
{
6 k-I 1
i h
67 (a) Sampler malfunctam Owse came oiT) causing low volume.
j j
(b) 5%mp malfunctam causing km volume; resulu in antal gCs.
t i
O O
O TABLE B-2 0' age 2 ct 4)
NORTII ANNA - 1996 CONCINIRAEONS OFGROSS BETA IN AIR PARTICULATES
~
tCE43 Gm32 2 Lgua i
3 COIJ ECTION 1991 AVERAGE LATE 01 02 33 e4 95 45A 96 97 21 22 23 24 i 2 s.d.
APRIL 000344/10 221 5 2815 201 5 22^ 5 2615 301 5 181 5 301 5 221 5 2815 211 5 1413 23 1 10 04/104t/17 1713 1413 141 3 131 3 1713 1613 141 3 1713 2113 161 3 151 3 131 3 161 5 04/17 44/25 1413 161 3 1413 131 3 151 6 161 3 121 3 1413 171 3 1813 15 1 *,
1513 15 1 3 04f2545A)!
241 5 201 5 231 5 20 1 ?
301 6 321 6 201 5 221 5 241 5 231 5 20 1 ',
171 5 231 9 1
i MAY 05All45/08 1814 (a) 1914 1613 201 4 171 A(a) 171 4 181 4 1413 1613 1814 93130 161 3 171 6 05/08 45/16 101 3 22i 4 2214 (b) 1215 (c) 1813 (b) 241 4 221 4 201 3 2214 2012 1113 1813 Ib i 10 J
05/1645/22 241 4 221 4 125150(d) 1614 1614 (b) 1614 1714 1214 1814 161 4 131 4 1714 171 7 05/22 45/30 121 3 181 3 171 3 161 3 201 3 201 3 171 3 211 3 231 4 1313(c) 1513 161 3 171 7 JUNE 2
05/300M)5
) i
- 231 4 221 4 201 4 18 i 4 221 4 161 4 221 4 201 4 191 4 211 4 191 4 201 4 OM)5&V12 1713 191 3 201 4 1813 22 4 161 3 1713 211 3 271 4 191 3 191 3 2114 201 6 L
i Ordl2&J19 11i 3 151 3 1714 (f) 1113 131 3 181 4 171 4 151 3 171 4 1714 1413 9.1 1 3.0 151 6 I
OU19-W/26 9.2 i 2.7 141 3 1613(b) 9312.8 14i 3 14 t 3 181 3 1713 141 3 14 i 3 121 3 161 3 14 i 6 092647/03 9.012.9 6.412.7 191 4 181 3 1813 1413 1613 151 3 161 3 161 3 141 3 121 3 151 8 t
Average 16 111 18 i11 18 1. 6 16 i E 19 i10 29 i 12 1715 18 i 18 20 i 8-18 i 8 15 i 8 16 i 6 1813 1 2 s.d.
l l
(s) Samplers ra running ca arrival althnogh pamps were hot. Volumes estimated.
i (b) Timer malfunctioned, estimated volumes using stst/stm times.
g (c) Wilumes km due to decrease flow rate.
(d) Volume km due to malfunction of punp. Result nd used in averages _
l (e) Pump nad running on amval. Volumes determined by timer.
3 (f) Tuwr malfuncton. samples operating preperiv and volume s.arisfact<vy.
i
m N
Om O
TABLE B-2 0%e 3 es4)
NORT11 ANNA-1991 CONCDCRATIONS OFGROSS BETA IN AIR PARTICULATES 1 CE01 pCur=3 2 siyne t
COLLECTION 1991 AVERAGE DATE 01 02 03 94 05 05A 06 07 28 22 23 24 1 2 sd.
.1111 1 07/0347n0 1313 (a)
< 9 (b) 261'4 191 4 23i 4 221 4 2114 271 4 181 4 221 4 231 4 261 4 221 8 07/10 47/17 241 4 25 1 4 241 4 1713 231 4 201 4 2014 221 4 2514 241 4 221 4 23 2 4 221 5 07/17 47/24 281 4 21.1 4 231 4 171 3 241 4 231 4 261 4 2914 311 4 301 4 331 4 24 1 4 261 9 l-07/24 47/31 261 4 14 1 3 1814 11 t 3 131 3 1513 2014 151 3 201 4 1914 161 3 18 1 4 171 8 A l'G US T 07/3148M7 2: 14 251 4 321 4 261 4 241 4 2514 221 4 261 4 271 4 201 4 261 4 251 4 251 6 C9748/14 191 4 15 1 3 201 4 151 3 181 3 201 4 1914 231 4 191 4 20 i 4 192 4 19 1 4 19 1 4 08/14 08/21 271 4 251 4 301 4 1513 3114 261 4 291 4 331 4 3414 321 4 291 4 331 4 201 11 l
08/21 48/28 261 4 21 1 3 221 4 221 4 241 4 211 3 2814 241 4 271 4 261 4 241 4 291 4
- 1 08/284N94 131 3 131 3 131 3 1113 151 3 191 4 1413 181 3 1814 161 3 161 3 181 3 151 3 SEPTEMB ER 099449A 1 25i 4 251 4 26 i d (c) 131 3 2914 2514 301.4 2914 301 4 2714 301 4
<3 26 1 10 09/18 49/18 271 4 25 1 4 211 4 241 4 341 4 281 4 331 4 2914 261 4 291 4 261 4 331 4 28 1 8 09/18 49/25 191 4 201 4 151 3 8.6 1 2.9 1714 161 3 251 4 231 4 314 261 4 161 3 22 1 4 191 10 09/25-10/02 191 4 201. 4 231 4 171 3 241 4 191 3 281 4 261 4 23 4 241 4 241 4 291 4 231 7 i
Average 22 1 le 2119 23 i II 17 i le 23112 21 i 8 22 11 25 i IS 24 11 2419 23 i I I 25 i 11 21 i 14
[
t 2 s.d.
M MM,
M 04 I%mp nr.ars bette woukeg m low vedame.
69 (c)
Terre malfunctnt; vehme essmased by mart /any taw.
i
O O
TABLE B-2 j
&ase 4 c(4)
}
NORill ANNA - 1991 CONGNTRA110NS OFGROSS BETA IN AIR PARTICUlATES
[
3 t 0E43 r< van t 2 s.gma COLLECTION 1991 AVERAGE DATE 01 02 93 04 85 SSA e6 07 21 22 23 24 i 2 a.d.
OCTOBER 1002 1009 181 4 201 4 201 4 221 1 261 4 231 4 1814 221 4 23i 4 1214 1814 241 4 211 6 10m9-10/16 171 3 261 4 (e) 271 4 36i 4 351 4 351 4 221 4 261 4 2914 261 4 291 4 211 3 271 12 10/16-10f23 201 4 30 1 4 251 4 261 4 271 4 241 4 241 4 231 4 271 4 151 3 241 4 18 1 3 211 8 10/23-10/10 161 4 24 i 4 1714 261 4 291 4 271 4 191 4 191 4 291 4 221 4 201 4 171 4 22 1 10 1
NOVEMBER 10/30-11 2 6 381 5 351 4 271 4 351 4 311 4 3214 291 4 31 4 271 4 2814 231 4 20 1 4 30 1 10 11/06-11/13 271 4 33 1 4 20 1 -4 221 4 2914 331 4 191 4 3014 251 4 321 4 151 3 20 1 4 25 1 12
+
ll/13-I tc0 171 3 24 i 4 15 i 3 23 4 2114 28 i 4 251 4 21.1 4 181 3 2114 211 4 10 1 3 201 10 11/20-11/27 14i 3 15 1 3 1413 1413 1413 1313 1713 171 3 Ist 4 161 3 211 4 8.9 2.9 151 6 DECEMBER i
II/27-12M4 121 3 18 1 3 14 i 3 141 3 11 3 1813 151 3 181 3 181 3 191 3 201 3 13 1 3 16t 6 12S4-12/12 2514 291 4 191 3 14i 3 19t 3 2514 24i 4 221 4 231 4 291 4 241 4 121 3 22 1 11 i
12/12-12/18 221 4 20 1 4 2114 321 5 2114 271 5 251 4 231.4 231 4 231 4 251 4 11 i 3 23 1 10 i
12/18-12/26 181 3 20 1 3 151 3 181 3 191 3 201 3 2113 191 3 1613 1813 201 3 131 3 18 1 5 12/264)l/02 2114 201 4 121 3 261 4 271 4 321 4 1814 241 4 171 4 231 4 2314 17 1 #
22 1 11 e
Qtr Averste 20113 24 i 12 19 le 24 i 15 24 i 14 26 113 21 i 8 23 i 9 23 i 9 22 i l e 2217 16 i le 22 1 12 1 2 s.d.
Ann Average 29 112 21 1 11 29 ile 19 i 14 23 i 1 2 22 i 12 29 111 28 i !!
21 111 22111 29 111 19 1 12 21 1 15 1 2 s.d.
~
i i
(a) Timer malfuncta m. wlome estunated.
70 b
s
TAllt.E B-3: GA3f3tA E3fl17 Eld, S11 TON 11U3189, AND S11t0N11U3190 CONCEN11tA110NS IN Allt l' Alt 11CULATES North Anna Power Stat. ion, Inuisa County, Virginia 1991 1.0 e43 lGm3 t 2 Sigrna January 1 to Decemter 31,1W1 Page 1 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station Nuclide 01/02-04/03 04/03-07/03 07/03-10/02 10/02 1/02 12 s.d.
STA 01 St 89 (a)
< 0.9 (a)
(a)
St90 (a)
< 0.1 (a)
(a)
Bo-7 116 17 80.3 17.6 104117 80.1111.5 95.1135.8 K 40
< 12
< 30
< 30
< 10 Co-60
<1
< 0.8
< 0.9
< 0.7 Ru 103
<2
<3
<2
<1 Cs 134
< 0.8
<1
< 0.9
< 0.6 Cs 137
< 0.9
< 0.9
< 0.9
< 0.7 Th 228
<1
<1
<1
<1 STA-02 Sr89 (a)
<1 (a)
(a)
St90 (a)
< 0.2 (a)
(a)
Be 7 162 21 126 19 102116 112 1 12 126152 K 40
< 12
< 10
< 10
< 20 Co-60
<1
< 0.8
< 0.8
< 0.0 Ru 103
<2
<2
<2
<2 Cs 134
< 0.8
< 0.7
< 0.8
< 0.7 Cs 137
< 0.8
< 0.7
<1
< 0.6 Th 228
<1
<1
<1
< 0.9 O
STA-03 Sr89 (a)
<1 (a)
(a)
St90 (a)
< 0.2 (a)
(a)
Be-7 1121 22 145123 103 18 83 8 i 13.2 111151 K 40
< 23
< 40
< 30
< 20 Co-60
<1
<1
<1
< 0.7 Ru-103
<3
<4
<3
<2 Cs 134
<1
<1
<1
< 0.7 Cs-137
<1
<1
<1
< 0.6 Th-228
<2
<2
<2
<1 STA-04 St89 (a)
< 0.9 (a)
(a)
St90 (a)
< 0.1 (a)
(a)
Be-7 121 1 20 101 116 68.2115.5 103112 98.3144.0 K 40
< 35
< 10
< 30
< 10 Co-60
< 0.9
< 0.8
<1
< 0.5 Ru-103
<3
<2
<2
<2 Cs-134
< 0.9
< 0.6
<1
< 0.5 Cs 137
< 0.9
< 0.6
<1
< 0.5 Th-228
<1
<1
< 11
<1 STA-05 Sr89 (a)
<1 (a)
(a)
Sr-90 (a)
< 0.1 (a)
(a)
Be-7 186 21 145 1 27 134 18 107114 143 66 K 40
<12
< 20
< 10
< 20 Co-60
< 0.8
<1
< 0.0
< 0.6 Ru-103
<2
<3
<2
<2 Cs-134
< 0.7
< 0.9
< 0.7
< 0.7 O
c >a7
<o7
<o8
<o7
<o7 Th-228
<1
<2
<1
<1 71
TABLE B 3: GAhthfA E3tlT11!RI, STROATIUht 89, AND S1ROATIUAl 90
\\
O-.
CONCENTRATIONS IN AIR 1*AR17CUL4TES North Anna Power Station, louisa County, Virginia - 1991 1.0 e-03 [Ci/m3 12 Sigma January 1 to Demmler 31,1991 Page 2 of 3 First Socord Third Fourth Quarter Quarter Quarter Quarter Average Statbn Nuclide 01/0? 04/03 04/03-07/03 07/03-10/02 10/02 1/02 1 2 s.d.
STA-05A Sr 89 (a)
< 0.8 (a)
(a)
St90 (a)
< 0.1 (a)
(a)
Be 7 154123 97.1110.0 95.2114.8 132 1 15 120157 K 40 4 35 21I i 8.4
< 30
< 10 21.8 f 8.4 Co40
<1
<1
<1
< 0.7 Ru 103
<3
<3
<2
<2
+
Cs 134
<1
<1
< 0.9
< 0.5 Cs137
<1
< 0.9
< 0.9
< 0.7 Th 228
<2
<1
<1
<1 STA 06 Sr89 (a)
< 0.8 (a)
(a)
St 90 (a)
< 0.09 (a)
(a)
Be 7 110125 114117 110 1 16 85.0110.9 105 1 27 K-40
< 12
< 10
< 10
< 10 Co-60
< 0.8
< 0.9
< 0.9
< 0.6 Ru 103
<2
<2
<2
<1 Cs 134
< 0.9
< 0.0
< 0.6
< 0.5 Cs 13/
< 0.8
<1
< 0.7
< 0.4 Th 228
<1
<1
<1
< 0.8 STA-07 Sr 89 (a)
<1 (a)
(a)
St90 (a)
< 0.1 (a)
(a)
Be 7 101116 139119 102116 114 1 15 114135 K 40
< 12
< 20
< 10
< 10 Co-60
< 0.8
< 0.9
< 0.8
< 0.7 Ru 103
..<2
<3
<2
<2 Cs 134
< 0.6
<1
< 0.7
< 0.6 Cs 137
< 0.6
<1
< 0.9
< 0.7 Th-228
<1
<2
<1
<1 STA 21 Sr 89 (a)
<2 (a)
(a)
Sr90 (a)
< 0.1 (a)
(a)
Be 7 62.71169 131 i 22 120 1 14 109114 106160 K 40
< 12
< 30
< 20
< 20 Co-60
< 0.7
<1
< 9.9
< 0.8 Ru-103
<2
<3
<2
<2 Cs 134
< 0.7
<1
< 18
< 0.7 Cs 137
< 0.7
<1
< 0.8
< 0.7
- Th 228
<1
<2
<1
<1
- STA 22 Sr 89 -
(a)
<2 (a)-
(a)
Sr (a)
< 0.2 (a)
-(a)
Be-7 151120 83.3120.9 96.7116.5 110 1 13 110159 K 40
< 23
< 30
< 30
< 10 Co-60
< 0.9
<1
<1
< 0.8 Ru-103
<2
<3
<2
<2 Cs 134
<1
<1
< 0.9
< 0.6 O
c -'37
< o.a
< o.9
< o.a Th-228
<1
<1
<1
<1 72
l I
GAMMA EM11*DiR, STRONTIUM 89, AND STRONTIUM 90 TAllLE B3:
CONCENTRAllONS IN AIR IMR11CULATES North Anna Power Station, louisa County, Viry, inia - 1991 1.0 e 03 pCl/m3 12 Sigma January 1 to Decemler 31,1991 Page 3 of 3 First Second Third Fourth Quarter Quarter Quarter Quarter Average Station U '-tido 01/02-04/03 04/03 07/03 07/03 10/02 10/02 1/02 12 s.d.
STA 23 St89 (a)
<2 (a)
(a)
St90 (a)
< 0.2 (a)
(a)
Be 7 132120 105i18 105i16 119 1 14 115 1 20 K 40
< 12
< 10
< 10
< 10 Co-60
< 0.9
< 0.8
< 0.7
< 0.6 F',u 103
<2
<2 t2
<2 Cs 134
< 0.8
<7
< 0.8
$ 0.7 l
Os-137
<1
< 0.9
< 0.a
< 0.8 Th 228
<1
<1
< 0.9 STA 24 Sr 89 (a)
<3 (a)
(a)
St90 (a)
< 0.2 (a)
(a)
Bo 7 109 1 21 28.11163 107119 G8.71130 93 1 120 K 40
< 23
< 10
< 40
< 30 Co-60
< 0.9
< 0.8
<1
< 0. 8 Ru 103
<3
<3
<3
<2 Cs 134
< 0.9
< 0.7
<1
< 0.9 Cs 137
<1
< 0.0
<1
< 0,9 Th 228
<1
<1
<2
<1 0
1 All gamma emitters other than those listed were <l.l.D.
(a) Strontium-89/90 analyses perfonned annually.
0 73
TAllLE B-4: GROSS BETA, TRITIU31, AND GAbiatA E3fl1TERI CONCENTRATIONS IN PREC)PITAT)ON Station O!A -- (On Site)
North Anna Power Station, Louisa County, Virginia - 1991
- G112 Sigma january 1 *.o Dewmler 31, IW1 Page 1 of I COI.LECTION DATES GitOSS 11 ETA ItAINFAIL (Inches) 12/31/90-01/30/91 1.61 0.0 3.26 01/30/91 02/27/91 12 1 2 0.93 02/27/91 03'27/91 3.4 1 21 2.3 03/27/91 04/25/91 5.1 i 2.4 2.52 04/25/91 05/30/91 35 1 3 (a) 1.21 05/30/910G/2G/91 0.9 i 1.0 A.95 OG/26/9107/31/91 3.1 0.7 E15 07/31/91 08/28/91
<4 4.28 08/2&'91 09/25/91 14 i 1 1.8 09/25/91 10/33'91 3.3 i 0.7 1.93 10/30/91 11/27/91 18 1 2 0.78 11/27/91 12/2G/91 26 i 7 4.22 Avorage 2 s.d.
12122 O
SE3ff-ANNilAL PRECIP)(ATION COSIPOSITES 12/31No 06/24/91 06/26/91 12/26/91 De-7 = < 60 lle-7 = < 40 11-3 = < 2(X) 11-3 = < 2(X) 1 All gamma emitters other than those listed were <LLD.
(a) Recounted to con 0rm result.
TABLE B-5 SOIL Soil samnles are collected every three years from twelve stations. Since the samples were collected in 1989, Table D-5 will not be included in the 1991 report.
O 74
I TABLE B-Ce GAMMA EMITIER, STRONTIUM, AND TRITIUM CONCENTRATIONS i
IN GROUND AND W* ELL WATER O'
Nonh Anna Power Station, louisa County, Virginia - 1991 pCi/li 2 Sigma January 1 to Decemler 31,299'.
Page 1 of 1 Collection Date H3 St 89 St 90 Be-7 K-40 113t Da 140 Th 228 STATION 0.1A ON27
< 200 (a)
(a)
< 40
< 100
< 0.2
<9
<7 OG/26
< 200
<3
< 0.8
< 30
< 60
< 0.2
<8
<7 1NO4
< 200 (a)
(a)
< 40
< 200
< 0.2
<9
<9 12/26
< 200 (a)
(a)
< 30
< 60
< 0.2
<7
<6 3
All gamma cmitters other than time listed were <LLD.
(a) Strontium 49/90 analyses performed only on wcond quarter sample.
I GAMMA EMITIER, STRONTIUM, AND TRITIU)
- ONCENTRATIONS TABLE B-7
IN RIVER WATER North Anna Power Station, louisa County, Virginia - 1991 pCi/l i 2 Sigma January 1 to Decernier 31,1991 Page 1 of 1 Collection Dates Sr-89 Sr 90 H-3 Be-7 K-40 1131 Cs 137 Ba 140 Fla 226 Th-220 STATION - 11 01/22 (a)
(a) 3900 1 100
< 30
< 50
< 0.2
<4
<6
< 80
<7 02/21 35001100
< 30
<40
< 0.3
<4
<7
< 60
<6 03/25 35001 30
< 30
< 50
< 0.2
<3
<6
< 70
<6 04/26
< 200
< 40
< 100
< 0.3
<5
<8
< 00
<8 05/28
<2
< 0.6 32001300
< 50
< 100
< 0.2
<5
< 10
< 90
<8 06/17
<2
< 0.5 3600 200
< 30
< 40
< 0.2
<4
< 10
< 60
<5 07/24 31001200
< 40
< 100
< 0.1
<4
< 10
< 70
<6 OW21 36001 200
< 30
< 50
< 0,1
<4
<9
< 60
<6 09/16 39001200
< 40
< 90
< 0.1
<4
<8
< 80
<8 10/21 30001200
< 20
< 50
< 0.5
<3
<6
< 70
<5 11/13 3800 200
< 30
< 50
< 0.5
<4
<5
< 60
<5 12/17 44001200
< 30
< 60
< 0.2
<3
<8
< 70
<7 Avorage 12 s.d, 3645z712 1
All gamma emitters other thar! those listed werc <LLD.
(a) Tr-89/90 analyses performed on second quarter samples.
LO 75
I GA313fA E3fl117?R, S7RONTIU31, AND TRITIU31 CONCEN1 RATIONS TAlls.E B 8:
JY SURFACil WATER pU Nonh Anna Power Station, Inuisa County, Virginia - 1991 pCD112 Sigma
.lanuary 1 to December 31,1991 Page 1 of 1 Collection Datos H-3 1-1312 Sr-83 Sr 90 Be7 K-40 Cs 137 Ba 140 Ra-226 Th-228 STATION - QA 01/22 (a)
< 0.2 (b)
(b)
< 40
< 100
<5
<6
< 90
<8 02/21
< 0.3
< 30
< 40
<3
<7
< 70
<6 03'25 4500 200 < 0.1
< 30
< 50
<3
<6 4 60
<6 04/26
< 0.2
< 50
< B0
<5
< 10
< 100
< 10 05/28
< 0.2
< 40
< 100
<5
< 10
< 90
<8 06/17 3900 1 200 < 0.2
< 3 0.73 i 0.40 < 30
< 50
<3
< 10
< 80
<7 OW24
< 0.1
< 30
< 40
<3
<9
< 50
<5 O &21
< 0.2
< 40
< 100
<4
<9
< 80
<7 09/16 3600 1 200 < 0.2
< 30
< 60
<3
<9
< 80
<6 10/21
< 0.5
< 30
< 50
<3
<5
< 60
<6 11/13
< 0.2
< 30
< 60
<4
<6
< 90
<7 12/17 4100 1 200 < 0.2
< 30
< 80
<3
<8
< 50
<5 Avg.
4025 755 0.73 i 0.40
- 2. s.d.
O STATION - 02 01/22 (a)
< 0.1 (b)
(b)
< 40
< 100
<5
<7
< 90
<8 02/21
< 0.3
< 30
< 60
<3
<8
< 90
<7 03/25 2200 i 200 < 0.1
< 30
< 40
<3
<6
< 60
<5 04/26
< 0.3
< 40
< 100
<5
<8
< 100
<9 05/28
< 0.1
< 40
< 100
<5
<9
< 100
<9 06/17 3300 1 200 < 0.2
<3
< 0.6
< 40
< 80
<3
< 10
< 70
<6 07/24
< 0.1
< 40
< 100
<4
< 10
< 80
<7 OW21
< 0.1
< 50
< 100
<5
< 10
< 90
<8 09/17 3300 1 200 < 0.1
< 30
< 50
<3
<9
< 70
<6 10/21
< 0.1
< 30
< 40
<3
<6
< 50
<5 11/13
< 0.4
< 30
< 90
<4
<6
< 70
<6 12/17
< 200
< 0.2
< 40 82.4128,4 <4
<7
< 80
<8 Avg. 2933 1270 82.4 28.4 1 2 s.d.
1 All gamma emitters other than '. hose listed were <ll.D.
2 1-131 by radiochemistry (a) Analysis perfonned quanerly.
(b) Analysis performed only with second quaner.
O 76
I GAMMA EM1171?R, S7RONTIU.11, AND 11UTIUM CONCENTRATIONS TABI.E B-9:
IN SURFACE WATER O
State Split Samples North Anna Power Station, louisa County, Virginia - 1991 pCUl12 Sigma January 1 to December 31,1991 Page 1 of 1 Collection Datos H-3 Be-7 K-40 1-131 Cs-137 Ba 140 Ra-226 Th-228 STATION W 27 01/?1
< 200
< 40
< 50
< 0.5
<3
< 10
< 70
<6 02/28
<40
< 80
< 30 (a)
<4
< 10
< 80
<7 03/31
< 50
< 80
< 0.6
<5
< 10
< 100
< 10 04/30
< 200
< 30
< 40
< 0.3
<4
<15
< 60
<5 05/31
< 30
< 50
< 30 (a)
<3
< 10
< 70
<5 0630
< 30
< 40
< 0.4
<3
< 10
< 60
<6 07/31 1800 100
< 30
< 40
< 20 (a)
<3
<9
< 60
<5 08/31
< 30
< 50
< 0.3 3
< 10
< 70
<5 09/30
<40
< 50
< 0.2
<4
< 10
< 70
<6 10/: -
2700 1 200 < 30
< 50
< 0.7
<3
<10
< 70
<6 11/30
< 40
< 60
< 0.5
<3
< 10
< 80
<6 1W31
< 40
< 100
<1
<4
< 10
< 80
<7 STATION - W-33 01/31 3600 300 < 30
< 40
< 0.6
<3
< 10
< 60
<5 02/28
< 30
< 40
< 20 (a)
<3
< 10
< 60
<5 03/31
< 30
< 50
< 0.6
<4
< 10
< 60
<5 04/30 3200 200
< 50
< 100
< 0.3
<4
< 15
< 80
<7 05/31
< 30
< 40
< 30 (a)
<3
< 10
< 50
<5 06/30
< 40
< 100
< 0.5
<4
< 15
< 80
<7 07/31 38001 100 < 30
< 50
< 20 (a)
<3
<10
< 80
<7 08/31
< 30
< 40
< 0.3
<3
< 10
< 50
<5 09/30
< 30
< 40
< 0.3
<3
< 10
< 50
<5 10/31 36001200 < 30
< 40
< 0.5
<3
< 10
< 60
<5 11/30
< 30
< 40
< 0.5
<3
< 10
< 50
<5 12/31
<40
< 40
< 0.6
<4
< 10
< 60
<6 Avg.
311711500 2 s.d.
I All gamma emitters othen than those listed were <!l.fL (a) LLD could not be saet due to delay in neceipt o" sample from the State of Virginia.
O 77
n TABLE B-10: GAMMA EMITI1?RI CONCESTRATION IN SEDIMENT Sil.T
- r' " ^ "" "
- e' st"'i " '""i"
""'v "ai"'" - ' 99 2 O
pCi/kg i 2 Sigma January 1 to Decemoer 31, IrM1 Page 1 oi 1 STA-06 STA 09 STA 11 STA-08 STA-09 STA-11 Average Nuclide 03/25 03/25 03/25 09/16 09/17 09/16 12 Sigma St89 (a)
(a)
(a)
< 300
< 70
< 90 Sr90 (a)
(a)
(a)
< 30 1601 30 190140 1751 42 Be-7
< 400
< 300
< 400
< 500
< 600
< 700 K-40 65801 660 66201660 15200 1 1500 6730 1 670 13800 i 1400 16800 1 1700 10955i 9636 Mn-54
< 30
< 30
< 40
< 40
< 40
< 50 Co-58
< 40
< 30
< 40
< 40
< 50
< 60 Co-60 64.2 i 33.3
< 30
< 40
< 50
< 50
< 50 64.2133.3 Cs-134
< 40
< 40
< 50
< 40
< 50
< 60 Cs 137
< 50 112134
< 40 1941 42
< 50
< 50 153i116 Ra 226 16801530 16201650 1760t 600
< 700 10401600 20901 800 16381761 Th 228 10601110 10101100 12001120 816182 575i58 17501170 1069i796 1
All gamnia emitters other than tnose listed were <l.1.D.
(a) Strontium 89/90 analyses perfonned annually.
TABI.E B-11: GAMMA EMirfliRI CONCENTRATION IN SilOREI.INE SOIL Q
North Anna Power Station, l.ouisa County, Virginia - 1991 pCiAg i 2 Sigma January 1 to December 31,1991 Page 1 of 1 f
Station 09 Station 09 Average l
Nuclide ON21 09/16 i 2 Sigma l
Sr-89 (a)
< 400 Sr-90 (a)
< 30 Be-7
< 400
< 600 K-40 6450 640 4160 660 5305 3239 Mn-54
< 40
< 40 Co-58
< 40 s 30 Co-60
< 40
< 40 Cs-134
< 40
< 40 Cs 137 502152
< 50 502 1 52 Ra 226 1700 670 11701570 1435 750 Th-228 879 88 799 80 8391 113 1
All gamma emitters other than those listed were <l.l.D.
(a) Strontium 89/90 analyses performed annually.
O 78
~.. -. -. -. _. -.
TABili 1512: GAMMA EM11TERI CONCI!NTRATION IN MILK North Anna Power Station, Inuisa County, Virginia - 1991 pCVI i 2 Sigma January 1 to Decemixt 31,1991 Page 1 of 2 MONTII NUCLIDE STATION.12 STATION.13 l
JANUARY Sr89
<3
<3 St90 0,7110.13 1 0 1 0.2 K 40 14201 140 12201120 Cs 137
<4
<4 l131
< 0.2
< 0.1 FEBRUARY Sr-89 (a)
(a)
St90 (a)
(a)
K 40 14301140 13401130 Cs 137 -
<4
<4 l131
< 0.4
< 0.5 MARCH Sr 89 (a)
(a)
)
Sr90 (a)
(a)
K 40 13601140 12601130 Cs 137
< 10
<5 l131
< 0.3
< 0.3 i
APRIL Sr89
<3
<5 r O Sr 90
<04 4.4 1 0.7 K 40 13401130 1260i 130 Cs 137
<4
<4 r
1131
< 0.2
< 0.4 MAY
-Sr89 (a)
(a)
Sr90 (a)
(a)
K 40 1220 1 120 1240 1 120 Cs 137
<4
<4 1-131
< 0.2
< 0.2 JUNE
_ Sr-89 (a)
(a)
St-90
'(a)
(a)
K-40 1390x140 14301140 Cs 137
<4
<4 l131
< 0.2
< 0.2 JULY St89
<1
<1 Sr 90 1.1 0.1 0.6310.12 K-40 1150z150 1200 1 120 Cs 137
<6
<5 l131
< 0.2
< 0.1 0-79
..,~
TABLE B-12: GA313fA E311TTERI CONCENTRATION IN StiLK
]
North Anna Power Station, louisa County, Virginia - 1991 pCD112 Sigma january 1 to Decemter 31,1991 Page 2 of 2 MONTil NUCLIDE STATION.12 ST..rlON.13 AUGUST Sr-89 (a)
(a)
Sr-90 (a)
(a)
K-40 14801 150 1280i130 Cs 137
<4
<4 l131
< 0.1
< 0.2 SEPTEMBER Sr89 (a)
(a)
St90 (a)
(c)
K 40 13401130 1310t 130 Cs 137
<4
<5 l131
< 0.3
< 0.1 OCTOBER Sr 89
<2
<1 Sr-90 0.9610.16 0.5510.13 K-40 12501120 1200 120 Cs 137
<4
<5 l131
< 0.1
< 0.1 NOVEMBER St 89 (a)
(a)
O Sr 90
<e)
<e)
K 40 12401120 1320i130 Cs 137
<4
<5 l131
< 0.3
< 0.3 DECEMBER Sr-89 (a)
(a)
Sr90 (a)
(a)
K-40 1010 100 13001 130 Cs-137
<S
<5 l131
< 0.4
< 0.2 1
All gamma emitters other than those listed were <lill (a) Strontium 89/90 analyses performed quanerly.
O 80
TABLE B-13: GA3tMA E3fl11ERI CONCENTRATION IN FISil O
N "" ^"a" " "e' S'" " '"""" c ""tv vi's'"'" - ' 99 '
pCi/kg i 2 Sigma Janur:y 1 to Dece; ter 31,1991 Page 1 of 1 vui.,etion S'ation Sample K 40 Co-58 Cs-134 Cs-137 Date Type 04/11/91 08 Sport Species 1240iS30
< 50
< 30 57.9131.5 05/08/91 08 Catfish 831 1329
< 40
< 40 99.4135.0 10/23/91 08
. Catfish 2100 1380
< 30
< 30 72.8129.6 10/25/91 08 Game Fish 1400 1400
< 50
< 50
< 60 04/09/91 09 Sport Species 1GG01430
< 40
< 30
< 40 04/09/91 09 Catfish 1080 1340
< 40
< 30
< 50 04/08/91 25 Sport Species 1100 1410
< 50
< 40
< 40 05/08/91 25 Catfish 1200 1340
< 40
< 30
< 40 10/23/91 25 Catfish 1370 1380
< 20
< 30
< 30 10/24/91 25 Game Fish 2050 1480
< 40
< 40
< 40 Average i 2 s.d.
14091856 76.7142.0 1
All gamma eminers other than those listed were <LLD.
O l
t l
1
' O 81
TABill B-14: GAMMA EM11TERI CONCEN1RA110N IN FOOD / VEGETATION g
North Anna Power Station, Inuisa County, Virginia - 1991 pCIAg i 2 Sigma January 1 to December 31,1991 Page 1 of 2 Collection Date Be 7 K-40 1-131 Ru-103 Cs-134 Cs-137 Ra-226 Th 228 STATION 14 03/21 3600 360 2820 280
< 10
< 20
< 10
< 10
< 20')
75.1 126.7 04/26 327i64 55101 550
<5
<9
<7
<8
< 100
< 10 05/22
< 90 7420 i 740
<7
< 10
<8
<8
< 100
< 10 06/19 8071 237 80801 810
< 10
< 40
< 30
< 20
< 500
< 40 07/24 252 1 131 5370i S40
< 10
< 20
< 10 23.5 i 12.0
< 300
< 20 08/21 515i156 4490 1 450
< 20
< 20
< 10 e 10
< 200
< 20 09/18
< 500 42401420
< 10
< 60
< 30
< 30
< 500
< 60 i
10/16 2250 230 45001 450
<9
< 30
< 20
< 20
< 400
< 40 STATldtit5 03/21 1100 t 140 36001 370
< 30
< 20
< 10 37.0112.2
< 200
< 20 04/26 9901 99-7790 780
<6
< 10
< 10
<9
< 200
< 20 05,22 490 1 234 10400 1 1000
< 10
< 40
< 30
< 30
< 600
< 50 -
06/19 1540f 660 1020011000
< 10
< 80 e 50 448 i 51
< 900 844i84 07/24
< 5s C 7450 750
< 20
< 70
< 40
< 40
< 900
< 80 08/21 7481 99 13000 1300
< 50
< 10
<9
<9 233 1 102
< 10 09/18 1010 1 370 30500 1 3100
<9
< 70
< 40
< 40
< 600
< 60 0
10/1e 33701 340 50001 500
< 20
< 30
< 20
< 20
< 400
< 30 STATION 16 03/21 1820 i 180 33501 340
< 10
< 10
<9
< 10
< 200 29.5 i 14.0 04/20 1160 1 120 15300 1500
<5
< 10
<9
<9
< 100
< 10 05/22---360 1 131 6410 i 640
<8-
< 20
< 10
< 20
< 300
< 20 OG/19 7451 227 162001 1600
< 30
- < 40
< 30 161121 1070 1 320 641 i 64 07/24
< 200 7250 720
< 30
< 30
< 20
< 20
< 300
< 30 08/21 1100 1 350 33801 340
< 10
< 60
< 30
< 30
< 700
< 60 09/18 5671246 10400 1000
<8
< 40
< 20
< 20
< 500
< 40 10/16 6921143 48101 480
< 10
< 20
< 10
< 10
< 300
< 30 STATION 21 03/21 974-1225 3210 320
< 20
< 30
< 20 256 i 26
< 500 154119 04/26 1250 150 10400i1000
<7
< 20
< 20 3551 36 437 252 191119 05/22 3211111 101001 1000
< 10
< 20
< 10 71.71 1.3
< 200
< 20 OG/19. 3140i 810 1750011800
- < 30
< 100
< 30 389i66
< 1000 723 116
- 07/24 456 207-68101 680-
< 10
< 40
< 20
- 51.3 i 20.1
< 400
- < 40 08/21 9811200 97001 980
< 10
< 30
< 20 165 i 18
< 300
< 30 09/18
< 700 10000 1000
< 20
< 90
< 40 -
230 1 46
< 900
< 90 10/16 1420 150 47001 470
< 10
< 20
< 10
< 20
< 200
< 20 O
l 82 l
.-....,,.-.n
TABLE B 14: GAMMA EM111ERI CONCEN1RA110N IN FOOD /VEGETA110N North Anna Power Station, louisa County, Virginia - 1991 gCiag i 2 Signu January 1 to Decemler 31,1W1 Page 2 of 2 Collection Dato Bo-7 K-40 i131 Ru 103 Cs 134 Cs-137 Ra-226 Th-228 S.IAIlQtt22 03/21a 77101770 2000012000
< 10
< 100
< 80
< 80
< 1000 6171105 04/26 1240 1 120 64601 650
<8
< 10
<9 77.018.0
< 200 53.4111.6 05/22 404i 116 59301 590
<8
< 10
< 10 48.5 i 10.2
< 200
< 20 06/19
< 70 3831 52
< 20
<9
<6
<6
< 100
< 10 07/24
< 700 29100 1 2900
< 10
< 90
< 50
< 50
< 800
< 80 08/21 406 147 6530 650
< 10
< 20
< 10
< 10
< 200
< 20 09/18
< 600 12700 1 1300
<8
< 80
< 40
< 40
< 600
< 60 10/16 3060 310 7660 770
< 30
< 30
< 20 35.4118.2
< 400
< 40 Avg.110012958 8969112873 1681 291 5801873 370 658 2 s.d.
1 All gamma emitters other than those listed were <l.l.D.
a Only 48 gm. could le packed into a marinelli, sample counted for 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
O O
83
TABLE B-15: DIRECT RADIATlON MEASUREMEN15 -- QUARTERLY AND ANNUAL 11.D RESUL15 North Anna Power Station, Inuisa County, Virginia - 1991 mR/Std. Month (30.4 days) i 2 Sigma january 1 to Dewmler 31,1W1 l' age 1 of 1 Station First Otr Second Otr Third Otr Fourth qtr Quarterly Annual TLD Number 12/27/90 03/27/91 06/26/91 09/27/91 Average 06/27/90 03/27/91 06/2G/91 09/27/91 12/28/91 07/03/91 01 9.1 0.6 7.4 1 0.4 6.5 1 1.2 6.9 1 0.3 7.5 1 2.3 6.8 t 0.3 02 5.1 0.2 5.2 1 0.5 4.110,1 4.4 0.2 4.7 1 1.1 4.310.2 03 5.1 1 0.2 4.9 0.7 4.5 1 0.6 4.4 1 0.3 4.7 1 0.7 3.9 1 0.2 04 5.0 1 0.1 4.2 i 0.2 4.2 1 0.1 4.9 1 0.4 4.6 i 0.9 4.6 1 0.2 05 6.3 1 0.2 5.2 1 0.3 5.4 1 0.2 5.6 1 0.3 5.6 1 1.0 5.4 1 0.3 05A 6.2 1 0.2 4.7 1 0.2 5.1 1 0.4 5.5 1 0.2 5.4 1 1.3 5.0 1 0.3 06 8.3 1 0.7 6.3 1 0.4 6.5 1 0.7 6.9 1 0.4 7.0 1 1.8 5.810.1 07 5.7 0.1 4.0 i 0.3 5.1 0.2 4.3 i 0.3 5.0 1 1.2 5.010.6 21 5.6 1 0.2 4.8 1 0.2 5.0 i 0.2 5.4 1 0.3 5.2 1 0.7 5.2 1 0.3 22 6.9 1 0.6 6.3 0.5 6.8 0,3 0.3 1 1.0 0.6 1 0.6 5.7 1 0.2 23 7.4 1 0.6 6.7 0.3 6.6 0.5 7.0 1 1.7 6.9 1 0.7 6 4 i 0.3 24 4.4 1 0.8 3.4 1 0 2 3.5 0.2 3 8 1 0.4 3.8 0.9 3410.1 Avorage 6.3 2.9 5.3 2.3 5.3 1 2.2 5.3 1 2.2 5.6 1 0.9 5.1 1 2.0 2 s.d.
O O
u.1. y e c. T m J w a a m.. V,s G Y M 2B R E E R N M 3 HE T R W N 4 0 R M 1 M Ig rd E M B E R.-
TAHl.E 1116: DIRE!Cl* RADIA110N MEASUREMl!N15 ~
SECIDR QLMRil!RLY 11.D RESULIS North Anna Power Station, louisa County, Virginia - 1991 mR/Shi W1onth (30.4 days)12 Sigma january 1 to Ikcerniv;r 31,1W1 l' age 1 of 2 statkm First Otr Second Otr Third Otr Fourth qtr Aserage Numtwr 12/27-0V27 (a)
DV23-(W27 OM27 09/27 09/2712/2M i 2 S.d.
N1 7.0 1 0.3 6.8 i 0.4 5.6 1 0.5 6.5 1 0.1 6.5 i 1.2 N2 6.4 0.3 4.4 0.2 4.4 0.3 5.5 1 0.2 5.2 i 1.9 NNE 3 7.2 1 0.2 6.7 0.2 0.5 1 0.0 6.5 1 0.2 6.7 1 0.7 NNE-4 6.2 0.4 5.1 1 0.3 5.8 0.7 4.7 1 0.1 5.5 1 1.4 NE 5 8.8 1 0.4 6.9 1 0.3 9.0 1 1.1 7.811.4 8.1 1 1.9 NE-6 4.6 1 0.2 3.9 0.3 3.7 1 0.2 3.9 0.3 4.0 1 0.8 ENE 7 7.1 1 0.6 5.7 1 0.2 0.0 i 0.7 6.5 1.1 6.3 1 1.2 ENE 8 5.4 1 0.8 3.8 0.3 4.4 0.1 4.6 1 0.5 4.6 1.3 E9 7.3 i 0.4 6.7 1 0.7 7.7 1 0.6 7.0 1 0.4 7.2 1 0.9 E 10 6.0 i 0.3 5.9 i 0.5 5.0 1 0.3 4.7 1 0.4 5.4 i 1.3 ESE-11 6.1 0.3 6.1 0.1 5.5 0.2 6.7 1 0.2 6.111.0 ESE 12 7.7 0.3 6.8 0.4 6.3 0.6 6.1 0.4 6.7 1 1.4 SE 13 6.7 0.1 6.1 0.1 6.6 1 0.2 5.9 0.4 6.3 1 0.8 SE 14 8.6 0.5 8.9 1 0.7 7.8 1 0.2 8 7 1 1.3 8.5 1 1.0 SSE 15 7.2 0.2 6.6 1 0.5 6.2 1 0.7 6.4 1 0.1 6.6 0.9 SSE 16 5.8 1 0.3 5.5 i 0.4 5.3 1.5 4.2 0.2 5.211.4 S-17 8.1 1 0.3 7.6 0.4 8.0 i 0.2 7.7 0.3 7.9 1 0.5 S 18 5.0 1 0.5 3.3 0.1 38 0.3 3.5 1 0.4 3.9 1 1.5 SSW 19 8.6 0.4 8.6 1 0.5 8.1 0.3 8 0 1 0.1 8.3 1 0.C SSW 20 4.8 0.3 4.4 t 0.2 4.4 0.2 4.0 1 0.6 4.4 i 0.7 SW 21 9.9 1 0.3 8.8 0.8 8.4 0,4 7.9 1 0.3 8.9 1 1.7 O
SW 22 6.6104 7.4 1 1.2 5.6 0.3 5.6 1 0.2 6.3 1 1.7 W 23 6.2 0.2 5.6 1 0.4 5.6 0.7 4.0 1 0.3 5.5 i 1.3 W 24 7.2 1 0.3 5.9 0.1 6.0 1 0.2 5.9 1 0.3 0.3 i 1.3 W 25 82 0.5 6.5 0.4 7.4 0.9 6.5 i 0.5 7.2 1 1.6 W 26 (b) 4.4 1 0.1 4.5 0.3 4.2 0,2 4.4 1 0.3 WNW-27 6.5 0.2 4.7 0.1 4.7 1 0.5 4.7 1 0.2 5.2 1.8 WNW-28 58 0.1 5.1 0.3 5.7 1 0.5 4.6 1 0.3 5.3 1 1.1 NW 29 8.2 0.2 7.0 0.2 7.5 0.2 6.8 i 0.3 7.4 1 1.2 NW-30 5.9 0.4 4.3 0.2 5.3 0.5 4.1 1 0.1 4.9 1 1.7 NNW-31 7.4 1 0.2 5.010.2 6.1 0.5 4.5 0.3 5.8 i 2.6 NNW 32 6.2 1 0.1 4.9 0.2 5.5 1 0.8 4.5 1 0.3 5.3 1 1.5 N 33 6.6 1 0.1 6.5 0.6 6.5 1 0.5 5.4 1 0.3 6.3 1 1.1 N 34 6.7 1.0 4.8 0.5 5.9 0.3 4.5 1 0.4 5.5 1 2.0 NNE 35 7.1 0.3 6.1 0.4 7.2 i 0 3 6.1 1 0.1 6,6 i 1.2 NNE-36 6.3 1 0.1 6.1 i 1.0 5.1 0.1 4.9 1 0.3 5.6 1 1.4 NE-37 8.6 0.9 7.4 0.2 7.8 0.8 7.4 0.4 7.8 1 1.1 NE-38 3.9 0.1 4.0103 4.2 0.2 3.1 0.1 3.8 1 1.0 ENE 39 7.7 0.4 5.9 1 0.2 6.7 1 0.5 6.010.2 6.6 1.7 ENE 40 5.7 0.3 3.9 1 0.3 4.5 1 0.1 4.8 0.4 4.7 1 1.5 E 41 7.0 1 0.7 6.2 0.3 7.3 1 0.5 7.4 1 0.5 7.0 1.1 E-42 6.5 1.8 5.0 0.2 5.0 0.4 5.7 0.2 5.6 1 1.4 ESE-43 6.6 1 0.1 5.6 0.3 7.3 1 0.5 6.4 1 0.6 6.5 1 1.4 ESE-44 7.5 0.4 6.4 0.1 7.8 0.4 6.4 0.8 7.0 1.5 SE-45 7.3 0.1 7.2 1 0.1 6.5 1 0.2 7.4 0.4 7.1 i 0.8 SE-46 8.8 0.1 8.0 1 0.3 9.0 0.5 8.9 2.8 8.7 i O.9 SSE-47 8.0 0.1 6.4 0.3 7.1 0.6 6.1 0.5 6.9 1 1.7 SSE-48 6.3 0.3 4.9 0.1 5.2 1 0.2 5.5 1 0.4 5.5 i 1.2 S-49 9.4 0.2 7.4 0.2 7.6 0.7 7.1 1 0.3 7.9 1 2.1 O
s-so s41o' a81oa 4., 1 0,3 a.s 1 o.4 4.41,.4 SSW 51 9.2 0.4 8.8 1 0.4 9.3 1 0.4 9.7 0.7 9.3 0.7 85
TABLE B-1(>: DIRECI' RADIATION btEASURE3 FEN *IS --
SECIDR QUARTERLY TI.D RESUL1S Nonh Anna Power Station, Inuisa County, Virginia - 1991 mlUStd. Month CW.4 days)12 Sigma January 1 to Decemler 31.1991 Page 2 of 2 Stathm First Otr Second Otr Third Otr Fourth qtr Aserage Numier 12/27 0.V27 (a) 0.V28-06/27 06,7 09/27 09/2712/2H i 2 S.d.
SSW 52 4.8 0.5 3 9 i 0.1 4.5 1 0 2 3.6 1 0.2 4.2 1 1.1 SW 53 9.8 0.5 8.6 1 0.4 10.610.3 7.9 1 0.4 9.2 1 2.4 SW 54 7.1 0.6 6.3 1 0.4 6.2 1 0 6 5.5 1 0.2 6.3 1 1.3 WSW-55 5.6 1 0.1 4.9 1 0.1 5.5 1 0.2 4.510.3 5.1 1 1.0 WSW 56 0.0 1 0.2 6.0 i 0.2 5.7 1 0.3 4.6 0.2 5.6 1 1.3 W-57 8.3 1.1 7.1 1 0.2 7.9 1 0.6 6.5 1 0.9 7.5 i 1.6 W 58 5.8 0.2(c) 5.9 1 0.5 5.9 1 1.6 4.6 1 0.2 5.6 1 1.3 WNW 59 5.I 1 0.3 5.4 1 0.2 5.6 1 0.2 4.3 1 0.1 5.211.2 WNW-60 5.0 1 0.5 5.1 0.3 0.210.1 4.8 1 0.4 5.4 1 1.2 NW-01 8.3 1 0.6 8.3 1 0.8 8.811.1 8.1 1 0.3 8.4 1 0.6 NW 62 5.5 0.1 4.5 0.2 4.9 i 0.7 4.9 1 0.4 5.0 1 0.8 NNW-63 7.3 1 0.3 5.3 1 0.3 5.4 1 0.4 4.9 i 0.4 5.7 i 2.1 NNW-64 5.8 0.4 5.4 1 0.4 6.4 1 0.2 5.6 1 0.2 5.8 1 0.9 C1 5.010.1 5.7 1 0.7 5.4 1 0.2 5.4 1 0.5 5.5 1 0.3 C-2 6.0 t 0.8 5.5 0.4 5.6 i 0.7 4.9 1 0.3 5.5 1 0.9 C-3 5.4 1 0.8 4.5 1 0.6 4.2 1 0.2 3.4 i 0.2 4.4 1 1.7 C4 4.9 1 0.2 4.1 1 0.4 4.5.0.3 3.5 1 0.2 4 3 1 1.2 C5 4.3 1 0.1 4.6 0.3 5.1 1 1.1 3.9 1 0.2 4.511.0 C-6 5.2 0.1 4.5 1 0.3 4.9 1 0.2 3.9 0.4 4.6 1 1.1 C7 6.6- 0 2 5.9 i 0.8 5.8 i 0.4 5.8 1 0.4 0.0 1 0.8 C8 7.4 1 0.7 5.9 0.3 5.5 1 0.6 5.8 1 0.7 6.211.7 Average 6.7 2.7 5.9 1 2.7 6.1 1 2.9 5.6 1 3.0 6.1 1 2.9 i 2 s.d.
(a) Several stations had collection dates of 12/27/90 to 03/2W91.
GO T1.D not found.
(c) TLD found on ground with damaged casing 86
LAND USE CENSUSI North Anna Power Station, Louisa County, Virginia KM = Kilometer January 1 to Decemler 31,1991 Page 1 of 1 Nearest Nearest Nearest Nearest Veg Sector Direction Resident Site Boundary Meat Animali Garden 500 ft.2 KM (Mile)
KM (Mile)
KM (Mile)
KM (Mile)
A N
2.17 (1.35) 1.40 (0.87) 3.23 (2.01) 3.07 (1.91)
B NNE 2.17 (1.35) 1.36 (0.85) 4.22 (2.62) 2.17 (1.35)
C NE 1.90(1.18) 1.32 (0.82) 2.51 (1.56) 2.51 (1.56) 1 D
ENE 3.17 (1.97) 1.31 (0.81) 4.12 (2.56) 3.17 (1.97)
E E
2.03 (1.26) 1.33 (0.83)
NONE 2.53 (1.57) l F
ESE 2.60 (1.62) 1.37 (0.85) 7.74 (4.81) 5.63 (3.50) i G
SE 2.20 ()1.37 1.41 (0.88) 2.20 (1.37) 2.20 (1.37)
H SSE 1,47 (0.91) 1.47 (0.91) 8.83 (2.38) 1.47 (0.91)
J S
1.67 (1.04) 1.52 (0.94) 2.32 (1.44) 1.67 (1.04)
K SSW 2.30(1.43) 1.62 (1.01) 5.92 (3.68) 2.30 (1.43)
L SW 4.83 (3.00) 1.70 (1.06)
NONE 4.83 (3.00)
M WSW 2.86 (1.78) 1.75 (1.09) 2.86 (1.78) 2.86 (1.78)
N W
2.46 (1.53) 1.71 (1.06)
NONE 6.58 (4.09)
P WNW 2.20 (1.37) 1.64 (1.02) 7.13 (4.43) 4.09 (2.54)
O NW 1.63 (1.01) 1.56 (0.97)
NONE 1,77 (1.10)
R NNW 1.72 (1.07) 1.45 (0.90) 3.57 (2.22) 1.91 (1.19)
T 1
No milk cows or goats within a five mile r.edius of North Anna Power Station COMPARISON OF TifE 19.91 70 1990 LAND USE CENSUS
(
1.
Changes in nearest resident as compared to previous year.
a.
NW Sector:
1.90 Km (1990) to 1.63 Km (1991)
- b. NNW Sector:
1.91 Km (1990) to 1.72 Km (1991)
II.
No changes were observed in the nearest site boundaries distances.
Ill.
No changes were observed in the nearest milk cow status.
IV.
Changes in nearest ; vegetable garden as compared to previous year, a.
ENE Sector:
4.04 Km (1990) to 3.17 Km (1991) b.
ESE Sector:
6.93 Km (1990) to 5.63 Km (1991)
- c. S Sector:
1.96 Km (1990) to 1.67 Km (1991)
- d. W Sector:
3.91 Km (1990) to 6.58 Km (1991) e.
WNW Sector: 4.92 Km (1990) to 4.09 (1991)
- f. NW Sector:
1.90 Km (1990) to 1.77 Km (1991)
V.
No changes were observed in the nearest milk goat status.
l VI.
Changes in nearest meat animal as compared to previous year.
a.
SSector:
3.20 Km (1990) to 2.32 Km (1991)
- b. WSW Sector: NONE (1990) to 2.86 Krn (1991)
~
c.
W Sector:
7.13 Km (1990) to NONE (1991)
Land Use Census Data Shawn on Maps, Section 3, Pages 33-37 87 l -
ANALY17GtL PROCEDURES SYNOPSIS h
ANAIXTICAL PitOGDUllES SYNOPSIS Appendix D is a synopsis of the analytical procedures performed ori samples collected for the North Anna Power Station's 1(adiclogical Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne isotopes and include those recommended by the USSRC 15 ranch Technical Position, llev.1, November 1979.
ANAIXSIS TITIE PAGl?
Gross lieta Analysis of Samples...
. 89 Airborne Particulates...
.. 90 Analysis of Samples for Tritium...
. 91 Water.
. 91 Analysis of Samples for Strontium-89 and -90.
.92 Total Water..
. 92 Milk.
.92 Soil and Sediment.
.. 92 O
organic Solids.
. 93 Air Particulates.
.93 Analysis of Samples for lodine-131.
.95 Milk or Water.
.95 Gamma Spectrometry of Samples..
. 96 Milk and Water..
... 96 Dried Solids other than Soils and Sediment.
. 96 Fish.
. 96 Soils and Sediments.
..... 96 Charcoal Cartridges (Air lodine).
. 96 Airborne Pamculates.
.96 Environmental Dosimetry
.98 0
88
l l
DETEh NATION OF GROSS BEIA ACTIVITY Q
IN WATER SAMPLES Intnxinction 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 filterert through No. 54 filter paper before evaporation, removing panicles greater than 30 microns in size.
After evaporating to a small volume in a beaker, the sample is rinsed into a 2 inch diameter stainless steel planchette which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps.
Itesidue mass is determined by weighing the planchette before and alter mounting the sample. The planchette is counted for beta activity on an automatic proportional counter.
Itesults are calculated using empirical self absorption curves which allow for the change m effective counting efficiency caused by the residue mass.
Detection Capability Detection capability depends upon the sample volume actually represented on the planchette, the background and the efficiency of the counting instrument, and upon self-absorption of beta particles by the mounted sample.11ecause the radioactive species are not O
identified, no decay corrections are made and the reported activity refers to the counting time.
The minimum detectable level (MDI.) 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 signu level), assuming that 1 1
liter of sample is used and that 7 gram of sample residue is mounted on the planchette.
These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively.
The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 signu MDL for gross beta is 0.9 picoCuries per liter. These values reflect a beta counting efficiency of 0.38.
O 89
GROSS BETA ANALYSIS OF SAMPLES O
rir varticuiaies After a delay of five or more days, allowing for the radon 222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air paniculate filter, supplied by the customer, is counted as the blank.
Calculations of the results, the two sigma enor and the lower limit of detection (1. ldh RESULT (pCl/m3)
((S/T) - (B/t))/(2.22 V E)
=
2((S/r2) + (B/t ))1/2 (2.22 V E)
TWO SIGMA ERROR (pC!/m3) 2
/
=
4.66 (B1/2)/(2.22 V E t)
LLD (pC1/m3)
=
where:
S Gross counts of sample including blank
=
Counts of blank B
=
E a
Counting officiency Number of minutes sample was counted T
=
Number of minutes blank was counted t
=
Sample aliquot s:ze (cubic meters)
V
=
- O l
O 90
ANALYSIS OF SAMPLES FOR TRITIUM O
watec Approxinutely 2 ml of water are converted to hydrogen by passing the water, heated to its vapor state, over a granular zine conversion column heated to 40(T C. 'lhe hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure.
The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional shielding from cosmic i _.ys.
Calculation of the results, the two signu error and the lower limit detection (Lt.D) in pCi/h 2(3.234) T V (Co - B)/(C V )
RESULT
=
u u n
2(3.234)T V (E)1/2/(C V )
TWO SIGMA ERROR
=
u u u
3.3 (3.234)T V (E)1/2/(C V )
=
u u u s tritium units of the standard where:
Tu
=
conversion factor changing tritium units to pCl/l 3.234
=
volume of the standard used to calibrate the efficiency of Vn
=
the detector in psia volume of the sample loaded into the detector in psia V
=
3 the net cpm of the standard of volume VN Cu
=
the gross cpm of the sample of volume VS C
=
o the background of the detector in cpm B
=
counting time for the sample
~
At
=
Sfr2 + B/t2 E
=
O 91
.a m:v4cm nmW wwmi! Item ANALYSIS OF SAMPLES 9
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 3
an iron (ferric hydroxide) scavenge are performed followed by addition of stable vttrium carrier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and ir counted in a low lev:1 beta counter to infer Sr 90 activity. Strontium-3 rom the sample after yttrium separation.
f 89 activity is determined by precipitating SrCO Thh precipitate is mounted on a 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 mufne furnace.
The arh is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrNO3 using fuming (90%)
nitric acid. A barium chronute scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchette and is counted in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by 4 rom the sample after yttrium separation. This precipitate is mounted on f
precipitating SrC0 O
a nvion nl2nchette and i covered with an 80 ma'cm2 aiuminum as orber for iow icvei beta Counting.
Soll and Sedlinent The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrachloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as 4
Sr(NO )2 using fuming (90& nitric acid. A barium chromate scavenge and an iron (ferric 3
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-3 rom the sample after yttrium separation.
f 89 activity is determined by precipitating SrC0 This precipitate is mounted on a nylon planchette and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.
Organic Solids A wei portion of the sample is dried and then ashed in a mufne furnace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO ) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, 3
followed by addition of stable yttrium carrier and a minimum of 5 d sys period for yttrium ingtowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate.
O The viirium oxaiate i mounted on a nvion niancheite and i counied in a iow icvei beta 92
counter to infer strontium-90 activity. Strontium-89 activity is detennined by precipitating 3 rom the sample after yttrium separation. This precipitate is mounted on a nylon f
SrC0 O
piancheite and is co cred with an 80 ms cm2 aiuminum ab orber for iow icvei beia count ng.
Air Particulates Stable strontium carrier is added to the sample and it is leached in titric acid to bring deposits into solution. The mixture is then filtered and the filtrate is redaced in volume 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 performed, followed by addition of stable yttrium carrier and a 7 to 10 dy period 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 strontium 90 activity. Strontium-89 activity is determined by precipitating 3 rom the sample after yttrium separation. This precipitate is mounted on a nylon f
SrC0 2
planchette and is covered with 80 mg/cm aluminum absorber for low level beta counting.
Calculations of the results, two sigma errors and lower limits of detection (1.1.lM are expressed in activity of pCi/ volume or pCi/nuss:
= (N/Dt B 'O )/(2.22 V Yg DFSR 89 ESR 89)
RESULT Sr 89 C A TWO SIGMA ERROR Sr 89
= 2((N/Dt+B 4B )/At)1 /(2.22 V YS DFSR-89 SR 89)
E C
A
= 4.66((B +B )/At)1/2 (2.22 V YS DFSFr89 ESR 89)
Q C
A
/
LLD Sr 89 RESULT Sr 90
= (N/At B)/(2.22 V Yj Y DF IF E) 2
= 2((N/At+B)/At)1/2 (2.22 V Yj Y DF E IF))
TWO SIGMA ERROR Sr-90
/
2
= 4.66(B/At)1/2(2.22 V Yj Y IF DF E)
LLD Sr 90
/
2 WHERE:
N total counts from sample (counts)
=
counting time for sample (min)
At
=
background rate of counter (cpm) using absorber configuration Bc
=
dpm/pCl 2.22
=
volume or weight of sample analyzed V
=
A background addition from St 90 and ingrawth of Y-90 B
=
0.016 (K) + (K) EY/ abs) (IGy.90)
B
=
A chemical yield of strontium Y
=
s sR 89 decay factor from the mid collection date to the counting DF
=
date for SR-89 efficiency of the counter for SR 89 with the 80 mg/cm.sq.
EsR-89
=
aluminum absorber (Nat - B )Y-90 (Ey.go IFy.go DFy.90 1)
C
/
Y K
=
the decay factor for Y-90 from the ' milk" time to the mid DF.go)
=
y count time g
efficiency of the counter for Y 90 v
Ey.93
=
93 1
~ ~.
IF.,o.
= L ingrowth factor for Y 90 from scavenga tima to milking tima -
y lG.go
=. the ingrowth factor for Y.90 into the strontium mount from
~
1L.O-y ine mr ume ioine mid =unt ume the efficiency of measuring SR 90 through a No,' 6 absorber
'O016
=:
- EYje,
- = :.the efficiency of counting Y-90 through a No. 6 absorber -
background rate of counter (cpm) i B-
=
chemical yleid of yttrium -
.Y.
=
3 chemicalyield of strontium Y2
=
-DF-
=
decay factor of yttrium from the radiochemical milking time to
. the mid count time.
'E
= - efficiency of the counter for Y 90 ingrowth factor for Y-90 from scavenge time to the radio-IF
.=
chemical milking time f
I i
e l
l' I,
l 1'
O l
94 l
l
- +
ANALYSIS OF SAMPLES FOR IODINE-131 O
Milk or Water a
Two liters of sample are first equilibrated with stable iodide carrier. A bach 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 prec' n ted as palladium iodide. The precipitate is a
weighed for chemical yield and is me um
,n a nylon planchette for low level beta counting. The chemical yield is correcti.t b easuring the stable iodide content of the milk or the water with a specifa 'w
-ctrode.
Calculations of results, two sigma ercor and the lower limit of detection (11D) in pCi/l:
(N/At B)/(2.22 E V Y F)
RESULT
=
2((N/At+B)/At)1/2 (2.22 E V Y DF)
/
TWO SIGMA ERROR
=
= 4.66(B/At)1/2 (2.22 E V Y DF)
/
=
total counts from sample (counts) where:
N
=
counting time for sample (min)
At
=
background rate of counter (cpm)
B
=
bes dpm/pCl 2.22
=
volume or weight of sample analyzed V
=
chemical yield of the mount or sample counted Y
=
decay factor from the collection to the counting date DF
=
efficiency of the counter for 1-131, corrected for self E
i
=
absorption effects by the formula E (exp-0.0061M)/(exp-0.0061M )
~
E
=
s s
efficiency of the counter deten-ad from an 1-131 E
=
s standard mount mass of Pd12 on the ;tandard mount, mg Ms
=
mass of PDl2 on the sample mount, mg M
=
O 95
m GAMMA SPECTROMETRY OF SAMPLES O
Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) dctector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
Dried Solids Other Than Solls and Sediments A large quantity of the sample is dried at a low temperature, less than 100 C. As much as possible (up to the total sample) is loaded into a tared 1-liter Marinelli and weighed.
The sample is then counted for a-oximately 1000 minutes with a shielded Ge(la detector coupled to a mini-computer-baseo data acquisition system which per orms pulse height r
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.
Solls 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 O
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. lach Ge(Li) detector is calibrated for both positions. The detection iimit for 1-131 of each charcoal cartridge can be determined (assuming no positise 1-131) uniquely from the volume of air which passed through it. In the event 1-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detecior.
Air Particidate The thirteen airborne particulate filters for a quarterly composite ior each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume of pCi/ mass:
(S-B)/(2.22 t E V F DF)
RESULT
=
O Two siam ennos 2(S+B),,2,(2.221 s v s os)
=
96
4.66(B)1/2 (2.22 t E V F DF)
/
=
Area, in counts, of sample peak and background where:
S
=
g-d (region of spectrum of interest)
Background area, in counts under sample peak, B
=
determined by a linear interpolation of the representative backgrounds on either side of the peak length of time in minutes the sample was counted t
=
dpm/pCi 2.22
=
detector efficie
.y for energy of interest E
=
and geometry of sample V
sample aliquot size ' liters, cubic meters, kilograms,
=
or grams) fractional gamma abundanco (specific for each F
=
emitted gamma) decay factor from the mid-collection date to the DF
=
counting date O
O 97
ENVIRONMENTAL DOSIMETRY O
Teledyne isotopes uses a CaSO :Dy thermolununescent dosimeter (TI.D) which the 4
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 features) satisfies NitC lleg. Guide 4.13 Transit doses are accounted for by use of separate T1.Ds.
Following the field exposure period the T1.Ds are placed in a Teledyne isotopes Model 8300. One fourth of the rectangular TI.D is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner.
Calculations of results and the two signu error in net millilloentgen (mIO:
RESULT D = (D +D +D +D )/4
=
3 2
3 4
2((D -D)2+(D -D)2+(D -D)2+(o4.D)2)/3)1/2 TWO SIGMA ERROR
=
3 2
3 1
the net mR of area 1 of the TLD, and similarly for D, D, and WHERE:
D 2
3
=
D4 1 K/R - A D1 1
3 11 the instrument reading of the field dose in area 1
=
K the known exposure by the Cs-137 source
=
p R1 the instrument reading due to the Cs 137 dose on area 1
=
'd A
average dose in mR, calculated in similar manner as above,
=
of the transit control TLDs the average net mR of all 4 areas of the TLD.
D
=
O 98 j
EPA Interlaboratory Contparison Progrant O
Teiedyne i otones participete in the uS Eri interiaboratory comparison erogram 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 trending graphs (since 1981) and the 1991 data sumnury tables are presented for isotopes in the various sample media applicable to the Surry cower Station's Radiological Environmental Monitoring erogram. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence.
5>
t O
O 99
O OT O
i WPCO ~ NOR77f ANNA POWER STA770N US EPA INTERLADOMATORY COMPARISON PROGRAM 1991 (Page 1 <I3) 1 l
EPA Date TI Mailed Date EPA EPA TI Norm Dev.
- Warning. '
l Preparation Results Issued Results Media Nuclide '
Rer.sts(a)
Results(b)
(Known)-
"* Action 01/11/91 03/07/91 04/15/91 Water Sr-89 5.01 5.0 5.00 1 0.00 0.00 Sr-90 5.0 1 5.0 5.00 1 0.00 0.00 1
01/25/91 02/21/91 03/18/91 Water Gross Alpha 5.3i 5.0 9.00 1 1.00 1.39 Gross Beta 5.01 5.0 7.00 1 0.00 0.69'
-l 02/08/91 03'22/91 0//10'0' Water Co-60
. 40.0 i 5.0 39.33 3.06
-0.23 i
Zrt-65 149.0 i 15.0 147.00 i 1.00
-023 Ru-106 186.0 1 19.0.
176.67 i 17.56
-0.85
)
Cs-134 8.0 a 5.0 7.33 0.58
-0.23 i
Cs-137 8.0 t '
5.0 7.67 i 3.21
-0.12 Ba-133 75.0 1 8.0 75.67 i 5.51 0.14 02/15/91 03/18/91 05/03/91 Water 1-131 75.0 i FM 80.00 t 5.29 1.08 02/22/91 03/22/91 04/15/91 Water H-3 4418.0 1 442.0 4500 1 173.21 0 32 03/08/91 05/06/91 05/31/91 Water Ra-226 31.8 i 4.8 28.33 4.73
-1.25 Ra-228 21.1 1 5.3 16.67 ' 2.00
-1.45 03/29/91 06/06/91 07/02/91
- Air Filter Gross A!pha 25.0 1 6.0 42.67.1 0.58 5.10
- "(c)
Gross Beta 124.0 i
' 6.0 126.67 i 57,7 0.77 Sr-90 40.0 1 5.0 37.00 1 1.00
-1.04 Cs-137 40.0 1 5.0 43.00 1 5.29 1.04 04/16/91 07/25/91 Water Gross Alpha -
54.0 1 14.0 59.67 1 4.04 0.70-Gross Beta 115.0 1 17.0 110.00 i OMO
-0.51 i
Sr-89 28.0 1 5.0 31.00 1 1.00 1.04
'l St-90 26.0 t 5.0 21.00 1 0.00
-1.73 Cs-134 24.0 i 5.0 25.00 1-1.00 0.35 Cs-137 25.0 1 5.0 24.00 i 1.73
. -0.35 04/26/91 06/28/91 07/31/91
' Milk St-89 32.0 i 5.0 24.00 1 3.00
-2.77
"(d)
St-90 32.0 1 5.0 26.33 1 2.08
-1.96 l-131 60.0 i 6.0 '
53.33 i 2 31
-1.92 Cs-137 49.0 1 5.0 52.C71 1.53 1.27 K
1650.0 1 83.0 1690.00 1 81.85
-1.25 ma
O O
0:
VEPCO - NORTH ANNA POWER STA770N r
i US EPA INTERLABORATORY COMPARISON PROGRAM 1991 (Page 2 cf 3) -
i EPA Date TI Mailed Date EPA EPA TI Norin Dev.
- Warning '
Preparation Results Issued Results Media NucBde Results(n)
Resultsib)
(Known)
- Action
.r 05/10/911 05/06/91
- 05/10/91 Water Sr-89 39.0 1 5.0 38.67 1 4.51
-0.12 l
24.0 i 5.0 22.00 i 1.73
-0.69 -
05/17/91 06/13/91 07/08/91
. Water
' Gross A!pha 24.0 1 6.0 2423 1 2.52 0.10 I
Gross Beta 46.0 1 5.0 50 33 i 1.53 1.50 i
06/07/91 07/I8/91 08/19191 Water Co-60 10.0 1 5.0
' 10.3" z 0.58 0.12 Zn-65 108.0 i 11.0 106.0": 1 2.65
-031 Ru-106 149.0 1 15.0 136.67 i-3.79
-1 A2 Cs-134 15.0 1 5.0 13.67 1 1.53
-0 16 Cs-137 14.0 i 5.0 13.67 1 1.53
-c M Be-133 62.0 6.0 56.33 1 1.53
-1.64 06/21/91 07/18/91
' 08/12/91 Water H-3 12480.i 1248.0 12833.33 i 115.50 0.49 07/12/91 10/08/91 09/06/91 Water Ra-226 15.9 1 2.4 15.0 1 1.00
-0.65 Ra-228 16.7 i 4.2 14331 2.31
-0.98 08/09/91 10/08/91 09/04/91 Water 1-131 20.0 t 6.0 19331 0.58
-0.19 08/?0/91 10/25/91 12/04/P1 Air Filter Gr-Alpha 25.0 1 6.0 27.00 1 2.00 0.58 i
GT-Beta 92.0 1 10.0 100.00 1 0.00 139 St-90 30.0 1 5.0 27.67 1 2.89
-0.81
't Cs-137 30.0 1 5.0 33331 3.21 1.15 t
09/13/91 10/25/91 12/12/91 Water St-89 49.0 1 5.0 50.67 1 2.89 0.58
't St-90 25.0 1 5.0 26.00 1 1.00 035 09/20/71 10/17/91 11/04/91 Water Gr-Alpha 10.0 1 5.0 11.67 1 0.58 0.58 1
Gr-Beta 20.0 1 5.0 21.00 i 0.00 0.35 i
09/27 /91 12/06/91 12/23/91 Me Sr-89 25.0 1 5.0 21.00 1 2.65
-1.39 Sr-90 25.0 1 5.0 19.00 1 0.00
-2.08
"(d) 1-131 1080 i 11.0 11333i 5.77 0.83 Cs-137 30.0 1 5.0 29.00 3.61
-035 i
K 1740.0 87.0 1503 33 i.75.06
-4.71
-"(e).
i 101 e
b
?
p f.
k.
1 ITPCO - NOR77i ANNA PO15TR STA770N US ETA INTERLABORATORY COMPARISON PROGRAM 1991 (Page 3 of 3)
EPA Date TI 31 sited Date EPA EPA TI Norm Dev.
- Werning Preparation Results Issued Resulta 3tedia Nuclide Nesultsf-;
Result Ab)
(Known)
- Action 10/04/91 11/15/91 12/12/91 Water Co-60 29.0 1 5.0 30.33 1 2.08 0.46 Zn-65 73.0 1 7.0 72.67 i 7.09
-0.08 Ru-106 199.0 1 20.0 147.67 1 7.51
-0.12 Cs-134 10.0 5.0 10.33 i 3.58 Oci2 Cs-137 10.0 1 5.0 11.33 1 0.58 0.46 Ba-133 98.0 10.0 97.00 i 8.72
-0.17 10/18/91 11/15/91 12/04/91 Water H-3 2454.0 1 353.0 23 3.33 t 57.74
-0.59 l
10/22/91 01/02/9'2 01/2'/92 Water Gross Alpha 82.0 21.0 55.00 1 4.36
-2 23
- "(f)
Ra-226 22.0 1 3.3 21.00
- 2.65
-0.52 Ra-228 22.2 !
5.G 18.00 1 1.00
-1 30 Gross Beta 65.0 1 10.0 56.00 i 1.00
-1.56
.0 10.67 2.08 0.23 5
St-89 10.0 St-90 10.0 1 5.0 9.33 i 0.58
-0.23 Co-60 20.0 1 5.0 19.67 i 0.58
-0.12 Cs-134 10.0 1 5.0 10.33 1 2.08 0.12 Cs-137 11.0 5.0 13.67 i 0.58 0.92 l
11/08/91 01/02/92 01/21/?2 Water Ra-226 6.5 i io 5.37 i O.32
-1.96 Ra-228 8.1 i
.:.0 7.90 i
- 20
-0.17 (a) Average i expenmental sigma.
(b) Expected latx>ratory prenwm (I sigma,1 determinatsm)The EPA depsits actJvey in a l'4 tru h diameter orde, ren a plastic disk apywximately l'32 inc h stuc k.
A special calkraron (c) The sample presents a ddferern cunning geometry.
fw EPA Alters wall te performei lhe laboratory has chamed blank fikers from the las Vegas farahty. araf will semulate Itur depsas i
I 1he raue for the deviaten is behewd to te cemecmly h:gh str mrium yields, probaNy cauwd Lp incomplete separatxe c4 catchim. The latmarcwy has swegated carr er concer:tratrens I
(d) and pipeting techniques, and haw fouwt tiem to be cormt. Fonhet aspects of anahw irchru<raes are terng tested The laboratory has rernved a new wmenrum extrw1xm matenal wa implemersed (m 2/1/42 dewir> ped at Argonne Newmal laboratory. Expro:nents wah this method to achcw tcuer separatxm of ca mm wew completed and proce bre PRO 432105 nere a w, apprent caow for the low K-40 resuks. Two cater wwopen syked a de sampic were in gm.d agreerners wrth ITA vakes Urut eteverwes were mi ami (c) fwrk] to te correctly apphed PcmebM backgrrend enors in geometr r were irwongated and fcend so haw an inspufkant effect.
(f) Probabk failure to trarsier all sampk residuc e> tre cournmg planchet Analysts are bring tesco using irvixxise eruf nher EPA spkrs 102
O O
O US EPA CROSS CHECK PROGRAM STRONTIUM-90 IN WATER 80 60 -
g 40 -
g i
t i
2 e
j a.
ti ii i
q 20 -
i I I
i f d<' '
fd I I [
I 4 hh 1
a.
0-981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 o Tii 3 sigma l
- EPA 13 sigma
~
O O
O US EPA CROSS CHECK PROGRAM STRONTIUM-89 IN WATER 100 t
80 -
7 j
80 -
m ii
=
2 3
40 -
l i l si,i
'o
^
7 20 -,
j o
l I,
I 0-
-20
=
~
1981 1982 1983 19g4 1985 o Tl23s$ma o EPA 23s' ma g
O O
O US EPA CROSS CHECK PROGRAM
'IltlTIUM IN WATER tconu 18000 14000 -
,f 12000 -
l 10000 -
O:
t d
(
qg B
[
j j
"{
~
r og "O
{
[
g 4
"a 4
m-0 1985 1986 1987 1988 1989 1940 1991 1992 o Tl i 3 S
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O O
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I US EPA CROSS CHECK PROGRAM l
TRITIUM IN WATER i
5000 l
4000 -
L1 l
41 ti
]
f
}
.(
u l
2 3000 -
1, g
A i '
u
<lf en c%.
11
,,p ll
'I' a
i,,
O 1000 -
0 1981 1982 1983 1984 1985 o T113 sgma EPA 13 sigma o
.(
R./
US EPA CROSS CHECK PROGRAI5 GROSS BETA IN WATER (cont.)
140 7
120 -
< i a
100 -
e 80 -
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l i ' si o
4
}
40 t
[
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US EPA CROSS CHECK PROGRAM TRITIUM IN WNIER (cont.)
18000 14000 -
12000.
10000 -
8000-
'I 1
a l
i f
[
{
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I i
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1985 1986 1987 1988 1989 1990 1991 1992 o Ti t 3 S
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.p-g, 7-y US EPA CROSS CHECK' PROGRAM GROSS BETAIN WATER 180 100 -
< i 140 -
120-g 100 -
o oa 80 -
60 -
40 -
l E
20 -
k b
p g
g l
P E
< g
< g g
.c O-20 1984 1985 1986 1987 G Tl 13 ssjma
- EPA 2 3 sigma
[
O O
O US EPA CROSS CHECK PROGRAM GROSS BETAIN WXIER 220 200 -
180 -
1l 180 -
I j40 4l m-l 120-I 2
< \\
o o
8L 100 -
80 -
i l g
40 -
T il l b
k h
k
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US EPA CROSS CHECK PROGRAM GROSS ALPHA IN WATER i
l 22o I
l 180 -
H 140 -
e=
C Ua 100 -
i l
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<$1 60 -
i,
I i
i ii 20 -
l g'
I g
g g
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D 20 1982 1983 Io Tl 13 -jgma le EPA 13 signa u
US EPA CROSS CHECK PROGRAM GROSS ALPHAIN WATER 120 100 -
,i lI 5
C 60 -
i, LL
't II 40 -
4 b,
jh
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20 --
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- O US EPA CROSS CHECK PROGRAM IODINE-131 IN WATER 140 129-1 6 100 -
80 -
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l
(:
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O O
O US EPA CROSS CHECK PROGRAM STRONTIUM-90 IN MILK 100 I
80 -
80 -
81
'T' E
Y n
40 -
1
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P T lll 3{,
, ll i
c i
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20 1981 1982 1983 1984 1925 1966 1987 1988 1989 1990 1991 1992 o Tl13sgma EPA 13 sigma o
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US EPA C$ TOSS CHECK PROGRAM STRONTIUM-89 IN MHJC 100 g
80 -
i 4,
n n r 80 -
E ci 94 40 -
4 e
i '
ai g
=n
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=,
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-20 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 o Tl13sgma o EPA 13 sigma
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O
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'US EPA CROSS CHECK PROGRA POTASSIUM-40 IN wir.K 1
2eoo 2200-i b*
1800 -
'y.
=
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i
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1000 -
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