ML20209H877
| ML20209H877 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1986 |
| From: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| FVY-87-47, NUDOCS 8705040141 | |
| Download: ML20209H877 (77) | |
Text
l VERMONT YANKEE NUCLEAR POWER CORPORATION ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT January - December 1986 April 1987 Prepared By:
Yankee Atomic Electric Company Environmental Engineering Department 1671 Worcester Road Framingham, Massachusetts 01701 8705040141 861231 1 DR ADOCK 050
i TABLE OF CONTENTS Page LIST OF TABLES.................................................... iii LIST OF FIGURES................................................... iv 1
1.0 INTRODUCTION
2.0 ENVIRONMENTAL SURVEILLANCE PR0GRI.M................................ 2 3.0
SUMMARY
OF 1986 ENVIRONMENTAL DATA................................ 13 A. Air Particulate............................................... 15 B. Charcoal Filter............................................... 20 C. M11k.......................................................... 23 D. Mixed Vegetation.............................................. 29 E. Si1 age........................................................ 32 F. Groundwater................................................... 35 G. River Water................................................... 38 H. Sediment...................................................... 41 I. Finfish....................................................... 44 J. Direct Radiation.............................................. 47 4.0 ENVIRONMENTAL RADIOACTIVITY FROM THE CHERN0BYL ACCIDENT........... 52 64 5.0 QUALITY ASSURANCE PR0 GRAM.........................................
6.0 LAND USE CENSUS................................................... 68 7.0
SUMMARY
........................................................... 70
8.0 REFERENCES
........................................................ 71 2896R
LIST OF TABLES Title Page Number 2.1 Radiological Environmental Surveillance Program............. 3 2.2 Radiological Environmental Surveillance Locations........... 4 3.1 Summary of Direct Radiation Measurements - 1986............. 49 3.2 Ratio of Inner Ring to Outer Ring Exposure Rates............ 51 4.1 Chernobyl-Related Radioactivity in Precipitation............ 54 4.2 Iodine-131 In Precipitation, EPA ERAMS Network.............. 55 5.1 Intralaboratory and EPA Interlaboratory Results - 1986...... 66 6.1 1986 Land Use Census Results................................ 69
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LIST OF FIGURES Number Title Page 2.1 Environmental Radiological Monitoring Locations in Close Proximity to P1 ant.......................................... 7 2.2 Environmental Radiological Monitoring Locations Within 5 Kilometers of P1 ant....................................... 8 2.3 Environmental Radiological Monitoring Locations Greater Than 5 Kilometers from P1 ant................................ 9 2.4 TLD Locations in Close Proximity to Plant................... 10 2.5 TLD Locations Within 5 km of P1 ant . . . . . . . . . . . . . . . . . . . . . . . . . . 11 2.6 TLD Locations Greater than 5 km from Plant.................. 12 3.1 Gross-Beta Measurements of Air Particulate Filters.......... 17 3.2 Iodine-131 on Charcoal Filters.............................. 21 3.3 Cesium-134 in M11k.......................................... 24 3.4 Cesium-137 in M11k.......................................... 25 3.5 Iodine-131 in M11k.......................................... 26 4.1 Gross-Beta Measurements of Air Particulate Filters -
Meaa of All Stations........................................ 56 4.2 Cesium-134 on Air Particulate Filters - New England Controls............................................ 57 4.3 Cesium-137 on Air Particulate Filters - New England Controls............................................ 58 4.4 Ruthenium-103 on Air Particulate Filters - New England Controls............................................ 59 4.5 Iodine-131 on Charcoal Filters - Mean of All Stations....... 60 4.6 Cesium-134 in Milk - New England Controls................... 61 4.7 Cesium-137 in Milk - New England Controls................... 62 4.8 Iodine-131 in Milk - New England Controls................... 63
-iv-2896R
1.0 INTRODUCTION
The radiological environmental surveillance program at Vermont Yankee has been designed and carried out with specific objectives in mind. They are as follows:
- To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation of the nuclear power station.
- To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.
To verify the adequacy and proper functioning of station effluent controls and monitoring systems.
To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.
During 1986, as in the past, Aquatec, Inc., collected all of the aquatic environmental samples, while the Chemistry and Health Physics staff collected the bulk of the terrestrial environmental samples and processed all environmental thermoluminescent dosimeters (TLDs) for direct radiation measurements. After the initial processing, all non-TLD samples were sent to the Yankee Atomic Environmental Laboratory in Westborough, Massachusetts for further processing and radionuclide analysis.
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s 2.0 ENVIRONMENTAL SURVEILLANCE PROGRAM In this section, Table 2.1 outlines the surveillance program as required by the plant Radiological Effluent Technical Specifications (RETS).
Table 2.2 lists the sampling stations and their specific locations with distances measured from the plant stack. The monitoring locations are shown on maps in Figures 2.1 through 2.3.
Below are listed the two-letter media code letters and what they represent:
AP Air Particulate CF Charcoal Filter TM Milk WG Groundwater WR River Water TG Mixed Vegetation TC Silage TF Food Crop SE Sediment FH Finfish DR Direct Radiation (TLD) 2896R
Table 2.1 Vermont Yankee Radiological Environmental Surveillance Program Media Sampling Frequency Required Analyses Air Particulate (AP) - Semimonthly (2) Gross beta
- Quarterly Composite Gamma spectroscopy Charcoal Filter (CF) - Semimonthly (2) Iodine-131 Milk (TM) - Monthly (7) Gamma spectroscopy, Iodine-131 Mixed Vegetation (TG) - Quarterly (1) Gamma spectroscopy Silage (TC) - Annually (4) Gamma spectroscopy Groundwater (WG) - Quarterly Gamma spectroscopy, H-3 River Water (WR) - Monthly (1) (6) Gamma spectroscopy
- Quarterly Composite H-3 Sediment (SE) - Semiannually Gamma spectroscopy
. Finfish (F.H) .
Semiannually (1) Gamma spectroscopy Direct Radiation (DR) - Quarterly Integrated gamma dose (5)
(1) Collection frequency dependent upon availability of samples during winter.
(2) Weekly, when main plant stack effluent release rate of Iodine-131 is equal to or greater than 0.1 uCi/sec.
(3) Subject to availability at end of grazing season.
(4) Collected at harvest time in reasonable proximity to specified location; subject to availability.
(5) Outer ring TLDs - De-dose quarterly unless gaseous release LCO was exceeded in period.
(6) Composite sample collected over month at downstream location.
(7) Semimonthly when milk animals are identified as being on pasture.
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Table 2.2 Vermont Yankee Radiological Environmental Surveillance Locations Distance From Plant Direction Station Code Stack From Plant iMedia - Sta. No.) Station Description Zone * (km) Stack AP/CF/TG-11 River Station No. 3.3 1 1.9 SSE AP/CF/TG-12 N. Hinsdale, NH 1 3.6 NNW
/P/CF/TG-13 Hinsdale Substation 1 3.1 E AP/CF/TG-14 Northfield, MA 1 11.3 SSE AP/CF/TG-15 Tyler Hill 1 3.4 WNW AP/CF/TG-21 Spofford Lake, NH 2 16.1 NNE TM-11 Miller Farm 1 0.8 WNW TM-12 Whitaker Farm 1 2.6 S TM-13 Newton Farm 1 5.1 SSE TM-14 Brown Farm 1 2.1 SSW TM-15 Coombs Farm 1 4.7 NW TM-16 Tall Oaks Farm 1 4.7 WNW TM-21 Moore Farm 2 15.9 N WG-11 VY Plant Well 1 -- On-Site WG-12 Vernon Nursing Well 1 2.0 SSE WG-21 Brattleboro C. C. 2 12.1 NNW WR-11 River Station No. 3.3 1 1.9 Downriver KA-21 Rt. 9 Bridge 12.8 12.8 Upriver FH-11 Vernon Pond 1 -
On-Site FH-21 Rt. 9 Bridge 2 12.8 Upriver lllll6 SE-11 Shoreline Downriver 1 -- On-Site SE-12 N. Storm Drain Outfall 1 -- On-Site TC-11 Miller Farm 1 0.8 WNW TC-13 Newton Farm 1 5.1 SSE TC-14 Brown Farm 1 2.1 SSW TC-21 Moore Farm 2 15.9 N DR-1 River Station No. 3.3 1 1.9 SSE DR-2 N. Hinsdale, NH 1 3.6 NNW DR-3 Hinsdale Substation 1 3.1 E DR-4 Northfield, MA 1 11.3 SSE DR-5 Spofford Lake, NH 2 16.1 NNE DR-6 Vernon School 1 0.6 SW 2896R
l Table 2.2 (Continued)
Vermont Yankee Radiological Environmental Surveillance Locations Distance From Plant Direction Station Code Stack From Plant Station Description Zone * (km) Stack (Media - Sta. No.)
DR-7 Site Boundary 1 0.32 SSW DR-8 Site Boundary 1 0.45 S DR-9 Inner Ring - 1.8 N DR-10 Outer Ring - 4.3 N DR-11 Inner Ring - 1.8 NNE DR-12 Outer Ring - 3.4 NNE DR-13 Inner Ring - 1.2 NE DR-14 Outer Ring - 4.2 NE DR-15 Inner Ring - 1.4 ENE DR-16 Oater Ring - 2.9 ENE DR-17 Inner Ring - 1.3 E DR-18 Outer Ring - 3.1 E DR-19 Inner Ring - 3.6 ESE DR-20 Outer Ring - 5.5 ESE DR-21 Inner Ring - 2.1 SE
- DR-22 Outer Ring - 3.5 SE DR-23 Inner Ring - 2.1 SSE DR-24 Outer Ring - 4.2 SSE DR-25 Inner Ring - 2.3 S DR-26 Outer Ring - 4.0 S DR-27 Inner Ring - 1.2 SSW DR-28 Outer Ring - 2.4 SSW DR-29 Inner Ring - 0.8 SW DR-30 Outer Ring - 2.4 SW DR-31 Inner Ring - 0.8 WSW DR-32 Outer Ring - 5.0 WSW DR-33 Inner Ring - 0.8 W DR-34 Outer Ring - 4.8 W DR-35 Inner Ring - 1.2 WNW DR-36 Outer Ring - 4.5 WNW DR-37 Inner Ring - 2.7 NW DR-38 Outer Ring - 7.4 NW DR-39 Inner Ring - 2.9 NNW DR-40 Outer Ring - 4.8 NNW DR-41 Site Boundary 1 0.630 S DR-42 Site Boundary 1 0.920 S DR-43 Site Eoundary 1 0.760 SSE DR-44 Site Boundary 1 0.480 SSE 2896R
Table 2.2 (Continued)
Vermont Yankee Radiological Environmental Surveillance Locations Distance From Plant Direction Station Code Stack From Plant (Media - Sta. No.) Station Description Zone * (km) Stack DR-45 Site Boundary 1 0.315 SE DR-46 Site Boundary 1 0.027 N DR-47 Site Boundary 1 0.160 NNW DR-48 Site Boundary 1 0.395 NW DR-49 Site Boundary 1 0.315 WNW DR-50 Governor Hunt House 1 0.630 S DR-51 Site Boundary 1 0.300 SSW
- 1 = Indicator Station; 2 = Control Station.
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t 3.0 SUfftARY OF 1986 ENVIRONMENTAL DATA The following pages summarize the analytical results of all the environmental samples which were collected during 1986. Each environmental media category is presented as a separate subsection. A discussion of the compling program and results is followed by a table which summarizes the y:Or's data for each category. The tables, for all media but Direct Radiation, were generated by the computer program, ERMAP. At the top of each i tchle, ERMAP lists the units of measurement for each medium. The left hand column contains the radionuclide which is being reported, total number of cnalyses of that radionuclide, and the number of measurements which exceeds tcn times the yearly average of control measurements. The latter are cicssified as "non-routine" measurements. The next column lists the Lower Lirit of Detection (LLD) for those radionuclides which have detection c:pability requirements as specified in the RETS.
~Those sampling stations which are adjacent to the plant and which could conceivably be affected by the operation of Vermont Yankee are called
' " indicator" or " Zone 1" stations. Distant stations, which are beyond plant influence are called " Control" or " Zone 2" stations. Direct radiation (TLD) monitoring locations are further subdivided into site boundary, inner ring, cnd outer ring'(emergency response) stations.
ERMAP calculates a set of statistical parameters for each r dionuclide. This set of statistical parameters includes separate analyses I
for (1) the indicator stations, (2) the control stations, and (3) the station having the' highest annual mean concentration. For each of these three groups cf data, ERMAP calculates:
o The mean value of a1f concentrations.
l o The standard error of the mean.
I o The lowest and highest concentration.
l 2896R 1
. - - . ~ . - - . . - - - - . . _ , . - -, . . _ _ = ~ . - , - .
o The number of positive measurements (a concentration which is greater than the a posteriori LLD for that analysis) divided by the total number of measurements.
Each single radioactivity measurement datum in this report is based on a cingle measurement and is reported as a concentration plus or minus a one standard deviation uncertainty. The quoted uncertainty term represents only the random uncertainty associated with the radioactive decay process (counting stctistics), and not the propagation of all possible uncertainties in the cnalytical procedure.
Based on the requirement of RE1S Table 4.9.3 (Footnote f), any c:ncentration below the LLD for its analysis is reported as "not detected."
These values are set to zero for averaging purposes. Where a range of values in reported in the tables of this section, values less than the a posteriori LLD for the analysis are reported as zero.
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_ _ _ _ . - - - - - - - . - - _ - - - - - - - - - . - I
A) Air Particulate Air monitoring stations were established at a total of six locations (five are required by Technical Specifications). Five of these locations are indicators, while the remaining one is a control station. Airborne particulates are collected by passing the air through a glass-fiber filter. These filters are collected semimonthly and held for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> before being analyzed for gross-beta activity (indicated as GR-B in tables) to allow for the decay of radon and thoron daughter products. Quarterly composite air filters from each location are analyzed for gamma emitting radionuclides.
Gross-beta counts (Figure 3.1) showed random fluctuation through much of the year at indicator stations and controls, thereby indicating that any plant contribution was negligible. During the week ending June 8, 1986, it was noted that Station AP-11 had a disproportionately high gross-beta concentration. This can be seen in Figure 3.1. A loss of power during the latter half (approximately) of the week, together with a downward trend off the peak of the second Chernobyl " spike" (see Figure 3.1) might have l
1ed to a disproportionately high concentration for the week at that station. In other words, the concentration during the first half of the week was probably higher than the latter half or the entire week on the average. A gamma spectroscopy analysis done on thic filter and the filter for the same week at Control Station AP-21, showed concentrations of Cs-137, Cs-134, and Ru-103 that were in the same approximate proportions, indicating Chernobyl fallout.
l Pump malfenctions resulted in a low sample volume on two occasions l during 1986: 1) at Station AP-12 during the February 16 through March 2, 1986 period; and 2) at Station AP-21 during the November 3 through November 18, 1986 period. During the period of June 1 through June 8, 1986, the power was shut off at Station AP-11, for some unknown reason, resulting in a low sample volume.
LLD requirements were met in all cases.
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The increase in gross-beta measurements, as wel'1 as the measurements of Cs-134. Cs-137, Ru-103, and Ru-106 during May and June of 1986 can be attributed to fallout from the Chernobyl accident and is discussed in Section 4. Naturally-occurring K-40 and Be-7 were also detected in many samples.
In several instances during May and June of 1986, gross-beta measurements exceeded ten times the yearly mean of control samples. Technical Specifications require a gamma isotopic analysis on such individual samples. In all cases, the cause of the high gross-beta measurements was fallout from the Chernobyl accident. The gamma isotopic analyses were nonetheless performed, and the results confirmed this. Since all of these filters were included in the quarterly composites, upon which gamma isotopic analyses were performed, their individual gamma isotopic results were not included in the summary tables. This data is on file at Vermont Yankee.
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FIGURE 3.1 GROSS BETA MERSUREMENTS OF RIR PARTICULRTE FILTERS VERMONT YANKEE o.s o - RP-11 RIVER STR. 3.3 o.s _ 0 - RP-12 N. HINSDRLE, NH A - RP-13 HINSDRLE SUBSTRTION
+ - RP-14 NORTHFIELD,11R X - RP-1S TYLER HILL o - RP-21 SPDFFORD LRKE e
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EV!!FimENTAL RADIOL'XI(!4 Ff4FF. $lWM:Y VE*W M'rEE MXLEE PC46 S'ATIO: VERNC% VT M.'.A4 - DECE'GEF 1986 EDM: A P Pef t:m '~E UNITS: P:l/CU. M INDICATOR STATIONS STMION WITH HIGHEST PEAN CONTROL STATIONS
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- NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WICH WERE GREATER THAN TEN (10) TIMES THE A'.'ERAGE BACKGROUND FCG THE PERIOD OF THE REPORT.
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tc :.sc."?.E:.' REOU!PE3 EA*GE EA. RANGE REGE-00; ~ UTIfD' LLD @. DETECTED +t O. NO. DETECTED +* O. DETECTEDt*
RU-103 ( 24) ( !.71 .7)E -3 12 ( 2.6 i 2.2)E -3 '( 1.9 i 2.1)E -3 i 0' (-1.2 - 9.1)E -3 ( 1.4 - ' 91.4)E -4 (-6.6 - 82.2)E -4
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' 0) (-8.9 - CA.1)E -4 f-1.1 - 94.1)E -4 (-4.1 - 74.3'E -4 e 5 2m *( 1/ 4)* *( 1/ Als CS-1T i 24' .06 : 3.9 1.5!E -3 14 ( 4.7 i 4.3?E -3 ( 3.6 3.5)E -?
( Oi (-7.6 - ISS.0)E -4 ( 2.9 - 177.0)E -4 (-2.4 - 140.01E *
+i 5' 20lt *( 1/ 4)+ *f !! 4't BA-140 ( 24) ( -1.?: 7.4)E -4 15 ( ' .7 t 1.6)E -3 ( 2.2 17.1)E '
~; -
O' '-1.1 - .6tE -2 (-1.3 - 6.0)E -3 t-4.2 - 4.0:E '
ec O/ 2eir +: 0/ 41* *( O! 418 CE-141 ( 241 t -3.7t R.s'E-5 21 ' !.9 t 3.2)E -4 ( 1.0 3.2)E -4 (m (-9.2 - 7.11E -4 (-4.4 - 0.2)E -4 t-4.4 - 9.2:E -4
- ( 0/ 20)* *( 0/ 4)* *( 0/ 4)*
CE-144 ( 24; ( -1.6+ 2.2)E -4 11 ( 5.3 i 1.0)E -4 ' 3.9
- 2.5)E -4
( 0) (-2.5 - 1.4)E -3 ( 3.1 - 7.7)E -4 (-7.0 - 110.0)E -5
- ( Of 20)+ *( 0/ 4)* *( 0/ 4)*
J TH-232 ( 24) ( 2.72 2.4?E -4 15 ( !.4 i .3)E -3 ( 1.0 i .6)E -3
( 0) (-2.0 - 2.2)E -3 ( 7.6 - 22.1)E -4 (-1.9 - 22.9)E -4 et 0/ 20)* *( 0/ 41e *( 0/ 4)*
- NON-ROUTIE REFER $ TO THE NUMBER OF SEPARATE EASLREMENTS WHICH ERE GREATER THAN TEN (10) TIES THE AVERAGE BACKGROUND FC6 THE PERIOD OF TE REPORT.
n THE FRACTION OF SAMF1.E ANALYSES YIELDING DETECTABLE EASUREENTS (I.E. 33 S'D CEVIATI0fG! IS INDICATED WITE *: 1*.
B) Charcoal Filters Charcoal filter cartridges are situated in series with the air particulate glass-fiber filters. Monitoring stations were established at a total of six locations (five are required by Technical Specifications). Five of these are indicators and one is a control. Charcoal filters from the air sampling stations were collected and analyzed semimonthly for I-131 activity.
During much of May and June of 1986, I-131 was detected in charcoal filter samples from all locations including controls, as can be seen in-Figure 3.2. This radioactivity originated from the Chernobyl accident and is discussed in Section 4.
Pump malfunctions resulted in a low sample volume on two occasions during 1986: 1) At Station CF-12 during the February 16 through March 2, 1986 period; and 2) at Station CF-21 during the November 3 through November 18, 1986 period. During the period of June 1 through June 8, 1986, the power was shut off at Station CF-ll for some unknown reason, resulting in a low sample volume. LLD requirements were met in all cases.
l i
l l
1 2896R
FIGURE 3.2 10 DINE-131 ON CHRRCORL FILTERS VERT 10NT YRNKEE o.6 0 - CF-11 RIVER STR. 3.3
'5~ O - CF-12 N. HINSDALE, NH a - CF-13 HINSDRLE SUBSTATION
+ - CF-14 NORTHFIELD, MR
@ X - CF-15 TYLER HILL o - CF-21 SP0FFORD LAKE
- 0. 4 -
. 5,g .
y z '
t .
N o.3 -
0 12 8 !
8 L g o.2 -
i 1
t i o.1 -
0.0 = = = = = = .= = :: ..._:==== = = = = .= = = = = =
MAY JUN JUL RUG SEP OCT NOV DEC JRN FEB MAR RPR 1986
m Ot.'I'D.C.%. KADIOLO0? CAL 850GRA'151.ff%RY
. .ER"M* YA'FFE M.(LEV POER STATION, VERfD.', VT S'O#Y - DECEMBEP 195t.
"E' ' t*t": CFA*C M FILTEP t.fil!S: PC1/CU. M INDICATOR STA'!0NS STATION WITH HIGT ST E AN CONTROL STATIONS nunnonunn nennnunnnenone noeneneenen RADI0t!.'CLIIn- ME#1 MEAri ME#1 (NO. ##.YSES; REC /J:EED REE STA. RANGE RANCf
( D -ROUT! net' LLD N0. IETECTEDn NO. NO. DETECTEDee NO. DETECTEDn I-131 (180) .07 ( 2.7t .S;E -2 12 ( 3.2 i 2.0)E -2 ( 2.9 t 1.8)E -2
( 91 (-2.9 - 44.11E -2 (-2.9 - 44.1)E -2 (-1.6 - 40.6)E -2
- ( 24/150), *( 5/ 30), et 5/ 30),
e NON-ROUTItE RErEPi TO THE MMEF Or SEPARATE EA9FE'ENT3 WHICH WERE GREATER T4*: TEN 00) TIMES THE AVEERE BACL'0*0'AD rC6 TFE PEFIOD OF THE REPORT.
++ T4 FWT!(r; Gi SA"PLE ELYtES Y;ELDits IETECTABLE riA9FEMENTS ti.E. D :.T3 D!4'10%) :" !NDICATED W:TH e t le.
4 i
f
C) Milk Milk samples were collected and analyzed monthly for low level I-131 and gamma-emitting radionuclides. Monthly samples were composited quarterly and analyzed for Sr-89 and Sr-90 (this is not a Technical Specification requirement). Semi-monthly sampling was done at Stations TM-14 and TM-21, when the cows were on pasture.
A milk sample was no longer available for collection in March of 1986 at Station TM-12 due to the dairy herd being sold. This location was replaced with Station TM-13, which was already being sampled from (not as a Technical Specification requirement). As a result of the Land Use Census, Stations TM-11 and TM-13 were replaced with TM-14 and TM-15. Station TM-16 was also added to the program as a result of the census.
Detectable concentrations of Cs-137 and Sr-90 were measured in milk samples submitted from the indicator and control locations.
Concentrations were similar to those detected in previous years.
The detected levels are consistent with those measured in cow milk at other New England locations. Such levels have been well documented and are attributed to fallout from nuclear weapons tests, although Cs-137 levels after May 1986 were elevated somewhat due to Chernobyl-related fallout.
! Several radionuclides attributable to the Chernobyl accident were I
detected in milk during 1986. These are Sr-89 (detected in one control sample), Cs-134. I-131, and Cs-137 (which was already present in much milk due to nuclear weapons testing fallout from the late 1970's and 1980). These are shown graphically in Figures 3.3 through 3.5. The impact of the Chernobyl accident on concentrations of radioactivity in milk is discussed in Section 4.
l In addition to these radionuclides, naturally occurring K-40 was detected in all samples.
2896R
FIGURE 3.3 CESIUM-134 IN MILK VERMONT YANKEE 15 11-D - TM-11 MILLER FORM 13 - o - TM-12 WHITRKER FARM A - TM-13 NEWTON FARM 12 - + - TM-14 BROWN F8RM X - TM-1S COOMBS FHRH
!! ~ o - TM-16 CERS0SIMO FBRM V - TM-21 BRRTTLEBORO DAIRY x- 10 -
- x A $ 9-dM g.
N 0
~
7-m
] 6-8
- s-4- 4
+
2- v v oo 1-C C 4
,m
,C C 0 ;; O C C .- . ,-
NOV DEC JUN JUL AUG SEP OCT JAN FEB MAR flPR MAY 1986
~ ~ --- ~-- ~~-~
FIGURE 3.4 CESIUM-137 IN MILK VERMONT YANKEE 15 11-O - TM-11 MILLER FARM 13 - o - TM-12 WHITRKER FARM a - TM-13 NEWTON FARM 12 - + - TM-14 BROWN FRRM X - TM-15 COOMBS FARM 38- + 0 - TM-16 CERS0SIMO FARM BRATTLEBORO DRIRY M
r 10 -
E \ v - TM-21 Y 8 9-d x 8- r V
0 7-E 8 6-8 + N 4
g 5- '
H 4
~ o O
- 's o
x 'x,,,
JUN JUL
\ ,m BUG r,
/ .
OCT
,m NOV DEC JflN FEB MAR f1PR MBY 1986
FIGURE 3.5 10 DINE-131 IN MILK VERMONT YRNKEE 20 19 -
18 -
0 - TM-11 MILLER FARM 17 - 0 - TM-12 WHITRKER FRRM
^ - TM-13 NEWTON FARM gg _ + - TM-14 BROWN FRRM x - TM-IS COOMBS FARM 1s -
o - TM-16 CERS0SIMO FARM li - V - TM-21 BROTTLEBORO DRIRY
, E 13-12 -
Q 11 -
\ 10 -
tu g_
E 8
o 8-O 7-6-
1 5-i 4-3 2- 4
- Ys . - - - -
JUL AUG SEP OCT NOV DEC JAN FEB MAR RPR MAY JUN 1986 i
EV.'IF9."P.T PADIO21CA1 FRGAM Sl*#,"
'U
. 't.i YAME tinEtA SCt EK STATlft VEFt:x VT Jt U 4 - DECEM'-Ei !? M ME;'w : - m (t;! 6: 4.1 ': ,
itCIC* TOR STATIONS STATI(f; WITH HIGHEST MEA'. 00r:TRCL STA'IW
- t ,+r**>++++e+te+++<++e5 +++e**+++,****+;
- +++++++++++++++*
ME# E 4; MED:
RADIOVC'. IDES (NO. AW.' Y!ESi RE(UIFD Pu!CE STA. R#15E K#1:E
~(NrE-ROUTINEP LLD NO. DETECTED +a NO.
___ _ NO. DETECTEL".
. 'C. ..DETECTE5".....
SR-89 ( 22) ( -S.6f 17.2)E -2 12 ( 6.4 1 4.2)E -1 (-8.3 i 48.2)E -2
( 0) f-2.1 - 1.11E O (-1.1 - 1.21E O
- ( 0/ 18:e *( 0/ 1)* *( 1/ 4)+
SR 'O ( 22) ( 2.2t .2)E O 14 ( 3.7 i .5)E O ( 2.1 i .11E O
( 01 ( 6.7 - 43.5)E -1 ( 2.7 - 4.4)E O ( 1.9 - 2 3)E O
- ( 17/ 18)+ *( 4/ 4 ), +i 4/ 414 K-7 ( 74) ( -1.7s 102.1)E -2 15 ( 2.5 1.71E O (-5.o 13.7)E -1
( 01 (-1.7 - 1.6)E 1 (-7.4 - 12.2)E O (-1. 0 - 1.!!E 1
- ( 0/ 571* uf O/ 12)+ +l 0/ 17)+
V-40 ( 74) ( 1.32 .0!E 3 16 ( 1.4 .0)E 3 ( 1.A i .0)E ?
( 0) ( 1.2 - 1.5)E 3 ( 1.4 - 1.5)E 3 ( 1.3 - 1.5'E 3
- r 57/ Sn e +( 2/ 2;* e' 17/ 17:+
'?!-54 i 7Al ( -1.4d 1.4tE -1 13 ( 1. 2 3.0iE -1 ( 7.6 t 227.SiE -3 F 01 ' - 2. c - 1.7.E O (-1.9 - 1.7)E O f-!.6 - 1.8'E 0
<, ^, 57) ei 0, ::;e c 9. :7),
- CO-56 ' 7 ~. ( -5.4 15.!!E -2 16 9.61 3.2)E -1 t 1. ' i 4 E -;
( 0- '-2.7 -
2.4)E O : 6.5 - 12.SIE -) (- 3. e - 4.TE
- ' 0/ 571+ *( 0! 2)* t O! 17)+
FE-59 ( 74) ( 2.Si 3.3)E -1 15 ( !.5 i .8)E O (-1.' i 6.6)E -)
( 0) (-6.1 - 5.HE O <-2.5 - 5.c)E O (-4.9 - 4.')E o
- ( 0/ 57)+ or 0/ 12)+ +( 0/ 17)e C0-60 ( 74) ( -3.42 1.7)E -1 13 ( 1.5 i 3.4)E -1 (-4.4 i 2.7:E -1
( 0) (-3.3 - 3.3)E 0 (-1.7 - 2.3)E O (-3.2 - .81E O
- ( 0/ 57)* *( 0/ 12)* *( 0/ 17)*
ZN-65 ( 74) ( 9.0i 33.0)E -2 16 ( 3.5 i .4)E O (-1.7 i S 01E -!
( 0) (-5.8 - 7.1)E 0 ( 3.1 - 3.9)E O (-8.3 - 4.2)E O at 0/ 57)e *( 0/ 2)* *( 0/ 17)*
- KtMOUTINE REJERS TO THE NIME:i 0F SEFARATE EASUREMENTS WHICH WE:E OPEATER THAN TEN (10) TIMES THE A'/ERACE BACK0FCGO FOR TFE FBICD CF THE FEPORT.
- THE FRACTION OF SAMPLE ANALYSES YIELD:N3 CETECTAKE MEARFEMENTS (i.E. )3 STD DEVIATIONI) IS DCICA ED W:TH *( 1+.
27-
Eff.'IPONEf.TA' PADi(GICAL FPXJA;' Su*#v VERPir YAMIE ffXtEAR POWER S7A!!0'!. 'GN0% 'r JAN'.AY - DECE?TER 1986 EDitP: MILr UN!TS: FG /t:0 INDICA 70R S7ATIONS STATICN WITH HIGHEST EAN CONTROL $7AT!nN5
- e************************ ***e************
RADIONIXt! DES MEA'; eat! EAri
- 00. ANA' YSE31 RIC8.t!PID RP6E
. STA. RANCE RAPGE (NON-ROUTINEl' LLD NO. DETECTED ++ NO. NO. ETECTEDn Nn. DETECTED ++
2R-95 ( 74) ( -1.8t 2.51E -1 16 ( 9.1 i 9.7)E -1 ( 2.0 i 5.8!E -1
( 0) (-5.1 - 3.9]E O (-5.5 - 189.0)E -2 (-3.7 - 5.7)E O
- ( 0/ 57)* *( 0/ 2)* *( 0/ 17)*
RU-103 i 74) ( -9.8 1.61E -1 16 (-7.6 i 1.2)E -1 (-8.7 1 2.4:E -!
( 01 (-3.1 - 3.0)E O (-8.9 - -6.4)E -1 (-2.5 - .8)E O
- ! 0/ 57), el 0/ 2)* *( 0/ 171*
R'.1-1(r6 ( 74) I 1.cf 9.8)E -1 16 ( 4.( t 6.0)E O ( 4.o i 20.4)E -!
( 01 (-2.4 - 1.4tE 1 (-1.3 - 10.6?E O (-1.4 - 2.01E 1-
- f O! 57)* *( 0/ 2)* t' 0/ 17),
1-13! ( 74) 1. ( 4.31 2.3!E -1 14 ( 8.7 i 7.3)E -1 ( 3.6 i 2.E -1
( 11 f-1. 0 - 124.01E -1 !-8.0 - 1240.0)E -2 (-1.0 - 4?.U E -1
+' O! '.7) * *; 3/ 17)t *f 2? 17)+
C5-134 ( 74) 15. ( -3.4r 18.5)E -2 16 ( 1.8 i .1)E O ( 't.') s ' 1:E -1
(. 51 (-1.9 - 3.8:E O ' 1.7 - !.9)E O (-2.8 - 1.7.E 0
- r 5' 5-)* *( 2/ 21e *s 2/ 17)e CS-137 ( 745 18. ( 2.6t .36E O 14 ( 4.1 t .7)E O ( 2. 7 4)E '
( 0: (-9.0 - 107.01E -1 i-2.3 - 107.0)E -! (-4.e - 69.*;E '
- ( 23/ 57)* *( 11/ 17)* *( 7/ 17)*
I4-140 ( 74) 15. ( -3.91 3.4)E -1 14 ( 2.6 7.5)E -1 (-3.2 1 63.9)E -2
( 01 (-5.3 - 8.0)E O (-4.9 - 8.0)E O (-4.8 - 6.0!E C
- 0/ 57)* *f 0/ 17)* *( O! 17)*
CE-141 ( 74) ( -1.0 3.2)E -1 15 ( 8.8 i 7.3)E -1 (-6.0 1 7.3)E -1
( 0) (-6.0 - 5.1)E O (-4.6 - 5.1)E O (-8.5 - 3.01E O
- ( 0/ 57)* C 0/ 12)* *( 0/ 171*
CE-144 ( 74) ( -2.41 10.7)E -1 14 ( 3.4 i 1.7)E O (-2.1 ! 1.31E 6
( 0) (-2.0 - 1.7)E 1 (-1.2 - 1.7)E 1 (-9.5 - 9.3)E O
- ( 0/ 57)* *( 0/ 17)* *( 0/ 171*
- NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE EASLREENTS WHICH WERE CffATER THAN TEN (10) TIMES THE AVERASE BACKnROUND FOR TE PERIOD OF THE PEPORT.
- TE FRACTION OF SAMPLE ANALYSES YIELDIE DETECTAP.E MEASUREMENTS (I.E. >3 STD DEVIAT10'6) !! INDICATED WITe et le.
28-
D) Mixed Vegetation Mixed vegetation samples were collected during May, July, and September from the six air sampling locations. The vegetation consisted of various types of grasses and were analyzed for gamma emitting nuclides. The results of the gamma spectroscopy analysis on each sample showed that in addition to naturally occurring Be-7, K-40, and Th-232, Cs-137 was detected on many samples. The levels detected in 1986 are less than those measured in previous years (which were shown to have originated from nuclear weapons testing fallout), in spite of the addition of additional Cs-137 from the Chernobyl accident.
In addition to the above, I-131 and Cs-134 were detected on vegetation samples. This is consistent with air and precipitation monitoring results which demonstrate that the source of the radioactivity was fallout from the Chernobyl accident. See Section 4 for a more complete discussion.
Snow cover and lack of the proper vegetation prevented a fourth quarterly sample from being collected during 1986.
l 2896R
EWIP: wet!'A. FAD:MG)(A'. %0:n- RM W
EMX'
. YU3IE VXLEAF PC,EE STAT](& VEF*r/6 VT
- AR" - DECEPSER 1%
. Pe.ML*: '") E? '.'E'.ET '!!0'; ;f;"5: F'I fr3 '.I-it!~';(A*0F STATICr:S STATION WITH H!GHEST M AN CONT R STnt's
++++++++>+++ete+++ ++e++++++++++,++e*+se*+<* *****+tte+++s a RC:CttnitE5 EN: MEA': MEu:
no. AG.ySEE) F97.f! RED RWE S'A. F#dE FOG (NON-RJJTIP.D ' LLD NO [E'ECTE 9 + - NO. NO. [ETECTED++ NO. fETEU E u 1<E-7 ( 18) ( 6.9f 1.5'E 2 14 ( 8.7 t 3.1)E 2 : 7.5 t 3.7.E 2
( 0) (-2.0 - 163.0lE 1 ( 2.7 - 12.8)E 2 ( i.7 - 14.:4E 2
+( 10/ 15 P *( 2/ 3)* +' 2/ 3;*
K-4f? ! !?) ( 4.11 .3:E 3 13 ( 4.3 i .6)E 3 3. c .LE I
( 0: 2.2 - 5.S'E 3 ( 3.3 - 5.3)E 3 ( 3.2 - " 2':
+' 15i 15'+ +( 3/ 3)+ C 3! 5:&
m;-5: f IE' ' -S. 8: 24.3:E -! 21 ( 1. 4 1.0 E 1 f 1.4 : 1. ' i :
( 0) (-2.0 - : 4:E : ! 1.5 - 35.0;E O ( l.8 - ?.. O E
+: c/ !5a +' 0/ 3)* *: O! 5>
CO-5? i !?' ( !.?: 2c.S:E -! 14 ( S.c t 5.?)E O '-1.5 47;E
( 01 I-2.4 - 2. fit I ( 2.0 - 20.4:EO ( *~ 4 - 0:E ?
+1 0/ !s +( 0/ 3)+ a' e-lN FE-5( i IS: ( 7. % 7.!!E C :3 (2?: 2.4)E i ( 9.7 :. 5 E ^
f O' f-3.6 - 7.5:E 1 (-1.5 - 75.2)E O t-2J - to.5+E
- O'10 n .) / 0:* + 6 3,+
C0-65 ( 19' '
-2.52 23.!!E -! 14 ( 0.7 t 6.?>E O '-2.4 - "' !E '-
O (-1. ? - 1.51E ! (-6.; - 14.7;E O (-0. ' '." :
- ( 0/ 15)+ C O! 3)* *( O! 3ie 7N-65 ( IS) ( 7.1 3.6)E O 15 ( 2.2 i .7)E 1 (-S. 7 + 5.9)E (>
l ( 01 i-1. ; - 3.0:E. 1 ( 7.9 - 31.7)E O (-!.5 - .3:E
+t Oi15)e +( 0/ 31* 44 C' 34 i
7R-95 ( 18) ( -1.3 .7)E 1 12 ( 1.4 * .5)E 1 (-9.7 1104.0)E -2 I ( 0) (-7.9 - 2.3)E 1 ( 8.9 - 23.0)E O (-2.2 - 1.5:E 1
+( 0/ 15)+ +( 0/ 3)+ +( O! 3)+
l f 1.2 i i 1.2 t .9)E 1 RU-103 ( 18) ( 5.51 2.6)E O 21 9)E 1
( 0) (-1.0 - 2.7)E 1 (-2.6 - 23.3)E O (-2.6 - 28.3)E O
- ( 0/ 15)* *( 0/ 3)* +I 0/ 3)*
I i.
6
+ N%-ROUTINE REFERS TO THE fME; Oc SEPARATE EARIREENTS WHICH WrFf C#.E4.TER THAN TEN (10) TIE S THE AVERAGE BA0 3 0VND F0D THE PERIOD OF THE REDOR*.
- THE FRACTION OF SAMPLE ANALYSES Y!ELDING EETECTABLE EASLF:EENTS (I.E. >3 STD IEVIATICr:St IS INDIC*.TED WITH *t H.
l I
l g.
4 EW'Kr?Oct4 Ef41D.5ICiv. U:~r E 9 9.m;r VE'?:t(' YA?.UE 'ItJ:' FOC; airirn vEk?O.. */'
, . m m - DE0Ett!ER ! w triiT7.* ; .10 E!
ME0:U: 'OED VEGE*AT!*ei IO!U. TOP S* PION? STATION WITH HIGEST eat Cte;*Et STI. TWT ee++++,e++++>++i+e ee++,eiet,******++++evee6 ++e,etteneter*+a RADIOK.O.IICE. MEA'? ME".'; . S'i
( m. AN.LV!.Esi RE?lIRD RA'GE STA. RtJGE FtJ0E LLD N9. DETECTED +e NO. NO DETECTED +, NO. DETECTED **
, (NON-ROU' NEl' RLt-106 ( 181 (, 2.2f 13.5'E O 21 : 3.5 t 4.61E i ( 3.5 : 4.6)E 1
( 0) (-8.S - 7.9)E 1 (-5.7 - 8.3)E 1 (-5.7 - S.31E 1
- ( 0/ 15)e *( 0/ 3)* *( 0/ 3ie 1-13 ( IS' - ??. t 8.01 2.6;E O 2: ( 2.2 i 1.1)E I ( I.2 : 1.I'E 1
( C. * (-2.6 - 22.?'E O ( 8.7 - 3'4.0)E -1 1. - w .s.E -:
tr 5/ 15)r *f 2/ 3)* +< O' 3'*
2
. CS-IS4 ( 181 60 i 3. : 3.0i! 0 10 f 1.4 i 1.0)E i '
.2 d :2.'.tE ?
I 11 '-1.2 -
3.5tE 1 ( 0. 8 - 34.E'E O t-4.4 - ?.5:E 5
- ! 1.'15i+ *t Oi ?)+ H O! ?'t CS-13' f 19 80. ( :.7f 4)E : U ' 2. 6 + 9;E : ' 2.2 : 1
'r
( O' ' 5.5
'4?.5'E O ( o. S - 37.51E O ( 3.5 - 45.2'E O
+ p 15=+ n 0; sie e 1' re BA-140 ( 181 i 1.4 5.7)E ? 12 2.T : 1.6)E 1 f-0.0 f 1.?'E 1
( 01 4.' -
- 9. C E : ' S.) - 58.9)E O i-4.5 - 1.41E 1 e: 0 Ira e c 3u o 0 sp 4 '
CE-!!! ( 19) ! 4.?: 4.5'E O !? f -1. 4 1.5:E 1 :-5.2
- OE 4 -2 E - 43.3)E O (-1. e. - 1.0 E ;
' Ot 4-2.~ -
- . S:E 1
- ! O/ 15)* *( C/ 3)+ H 0/. 3)&
CE-144 ( 18; ( -6.6.+ ?.21E O 2: : 3.4 + 5.81E 1 ( 3.4 t 5.6?E i
( 01 (-1.0 - .51E 2 (-4.0 - 14.8)E 1 f-4.0 - 14.9 E !
- ( 0' 15)* +( 0/ 31* +( 0/ 3)+
TH-232 ( 18) ( 5.02 1.0)E 1 11 ( 7.3 i 1.SIE 1 (A0i .7)E 1
( 3) (-7.6 - 106.0)E O ( 3.7 - 9.5)E 1 ( 2.8 - 5.3)E 1
- f 3/ 15)+ H 1/ 3)* *( O! 31+
l l
e NON-RXITIE REFERS TO TE NltfBER OF SEPARATE EASLREENTS WHICH WERE GREATER
- THAN TEN (10) TIES THE AWREE BACK0ROLMD FOR TE PERIOD OF THE REPORT.
4 31-1 I
, , c-,. , . - - - , , _ . , , , - -. , - - - - . .
E) Silage Silage samples were collected at the milk sampling stations during October of 1986. Each sample was analyzed for gamma-emitting radionuclides and I-131. Local, fresh silage was not available for collection during 1986 at Station TM-15. The owner of the farm purchases already-cured silage which is from a previous growing cycle.
Naturally-occurring Be-7, Th-232, and K-40 were detected in most samples. No man-made radionuclides were detected in any of the silage samples.
- a i
i 2896R
i EWIV#ENTA.. RAD:0LC611 A: P::ta . strwa
~ VEEtEr;T Y/#IE N'XLE3. K410 $?A'l0*.. VEM% V' J40AFit - DECEMPEc: lo'n r;1T$t W./U. K '
E0:ir: Et.TTLE FEED STATION WITH HIOPEST EAN
& ;T MC ST Tl0'*-
INDirATCc STATIONS
(NCtJ-ROUTINE)'
E-7 ( 4) -( 3.41 .8)E 2 13 ( 5.0 i 1.0!E 2 ( 4.4 1 .81E
( 0) ( 2.3 - 5.0)E 2
- ( 2/ 3)+ *( 1/ 1)* *( 1/ 1)*
V-40 ( 41 ( 2.St .6)E 3 21 ( 4.0 i .3)E 3 ( 4.0 : .31E 3
( 0) ( 1.7 - 3.9)E 3 el 3/ 3)+ +! 1/ 1)* *( 1/ 1)+
J FN-54 ( 4! l 4.4 63.31E -1 11 ( 1.1 .6)E i (-!.4 t ! . '" E :
( 0) '-1.1 - 1.1)E 1
- ( 0/ 31+ *( 0/ 1)* *( 0/ 1)+
CC43 ( 4) ( 4.5 2.3)E O 13 ( 8.3 t 10,5)E 0 (-9.0 : 16. 0 E O
( O! ( 5.4 - 83.31E -1 e' 0/ 3)+ *! O! 1)+ +f 0/ ;<
FE-59 ( 4) ( 3.51 15.7)E O 13 ( 3.5 t 2.21E 1 (-5.3 i 3.f'E :
( 01 f-1,3 - 3.5'E 1 4 (- 'C r +' Of 1)4 t; (' / 11+
r0-60 ( 4: ( -4.62 2.4!E O 11 (-1.6 i ?T.4E -1 f-5.3 t 'f." E
( Of f- M - .2 E O ef 0/ 3)+ *( 0/ 11* H 0/ 1)*
-1.St 2.0:E ! 13 ( .3 ! 2.21E ! (- 5 t 28.s'F C' IN-6* ( o t 0, I-5.5 - .3:E 1
- 0/ 3)+ *( 0/ !)* *( 0/ 1)+
IR-95 ( 41 ( 9.1: 14.3;E O 14 ( 3.4 t 1.8)E i ( '.5 20.0 E O i
( 0) (-1.5 - 3.4)E 1 ,
- O! 3)* *( 0/ 1)* t' 0/ 1)*
[
l RU-103 ( 4) ( 3.7f. 49.1)E -1 11 ( 6.2 ! 6.8)E O (-1.0 1.2)E 1
( 0) (-9.4 - 6.2)E O
- f 0/ 3)+ sf 0/ 1)* *( 0/ 1)*
i e NON-ROUi!NE REFERS TO THE N'#BER OF SEPETE EASUREMENTS WHICH WERE GREATEF THAN TEN (10) TIME 5 THE A'KRA3E BACyrAOLND FOA THE PERIOD OF THE REPORT.
- THE FRACTION OF SATtE ANALYSES VIELDIO DETECTABLE MEA 9JOENT3 (I.E. )3 STD DE','IAT10N21 IS IN0'CATED WITH *( lt.
3 Ef/.'IRXME?.'?!.. Rt010L%!rA. MGV. S'.P.*.AU
' VEP"X' YAPA EE Rr.EA:. POWER :.!!Clff.. tiv: A t'T
$VJM - TEEMEEF 1*S6
- ME:!UM: CATTLE FEED.
- nr' F:1'r64 :
INDICATOR STATIONS STATION WIT 4 HICE 3' ME4 CONTRCt. S't.T'ff':
- ete+++++>ee.*ee ++eee*****+e*****+,****** + e te +,+++ s , +, e t e RADIOPff;.! DEI MEAN EAN eat.
STA. -RANCE RANGE (NO ANA'.v5E31 REPUIEED RA*3E LLD NO. DE!ECTEine NO. NO. DETECTED ** NO. DETECTED >f (NON-Rr.8)TIPEl' RU-106 ( 41 ( -1.2: 4?E 2 21 (-3.31 10,5)E 1 (-3.3 t 10.51E 1
( ' 0) (-1.9 - .6)E 2
- ( 0/ 31+ *( 0/ 1)+- *( 0/ 11*
l-131 ( 41 60. ( -4.2: 2.5)E-1 NO DATA ;-1.5 t 1.2)E O
( 0) (-8,5 - .0)E -1
+( 0/ 3)+ +! 0/ Ile
!! ( 4.0 6.2 E o (-2.2 e 12.9'E f.
C5-154 ( 4! 60. ( -7.1+ 6.1)E O
( 0? (-1.7 - 4?E 1
+( 0/ 3)* +: 0/ 11+ +t 0? 11, CS-137 f 41 80. ( 6.7: 5.61E O 13 f 1.6 i 9)E ' 1 ( 2.9 t 10.51E O
( oi (-3.6 - 15.?'E 6
+( 0/ ti+ *t 0/ lie 0- 1)*
~
Fa-14^ ' 4; i -1.2t .6)E 1 21 '2.31 2.0)E 1 ( 2.3 t 2.0'E t 0) (-2.3 - .3)E '
et 0/ 3)+ + 0' 11+ +t 0/ th (1-141 ( di f 4.82 70.21E -1 14 f 1.6 1.5'E 1 f-5.4 + 15.* /'
' 0: f-5.2 - 16.31E O
- ( 0/ Sie ei O/ 1)+ +! O/ 1)*
r.E-142 f 4 : -3.7 13.01E O 14 ( 1.8 i 4.9)E 1 -2.1 : 5.2)E I
- ( 01 (-2.7 - 1.e g ;
+t 0/ 31+ *r 0/ 1)* *( 0/ 11+
TH-232 ( 4) (. -3.0f 23.2)E O 13 ( 3.6 1 4.6)E 1 ( 3.1 i 5.21E !
( 0) (-4.4 - 3.61E 1
- ( 0/ 3)+ *( 0/ 11e *( 0/ 11*
- MX-ROUTINE REFERS TO THE N.r$ER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (101 TIES THE AVERAGE BACKGROUN3 F0P TE PERIOD OF TE REPORT.
- THE FRACTION OF SAPLE ANALYSES YIELDING DETECTABLE MEASLFEMENTS (f.E. >3 STD DE','IATIORS) IS IND'CATED WITH +' 1+.
. 34 -
F) Groundwater Groundwater grab samples were collected from two indicator (only one is required by Technical Specifications) and one control station on a quarterly basis. These samples were analyzed for H-3 and gamma-emitting radionuclides. Additionally, gross-beta analyses were performed, although they are not required.
Gross-beta radioactivity was detected in indicator and control stations during 1986 and the concentrations are typical of those made over the past few years. No gamma-emitting radionuclides were detected in groundwater during 1986.
2896R l
l
EV.'!KMENTAL RA3!CW: CAL PROCAAM SUPr.AP' VE E V YAN5EE MXLEM Kn.EE STAf!OL VER O . VT JANUAct - DECEMBER 1986 MEDRM: CM K WATER LNITS: Klil5.
INDICATOR STATICN! STATION WITH HICEST EAN CCWTROL S'A*!rns eteeeeeeeeeeeeeeee seeeeeeee****eeeeeeeeee*+ eeeeee+,eeeeee+e RADIONXLICES EAN EAN MEA *!
(NO. ANALYSESl REQUIREf- RA%E STA. RAE( RANCE (NCN-ROUTIE)' LLD NO. [ETECTEDee NO. NO. DETECTED +e NS DETECTEDee OR-B ( 12) 4. ( 2.?f .3)E O 11 ( 2.7 i .5)E O ( 1.4 t .2)E O
( 0) ( 1.2 - 3.5'E O ( 1.4 - 3.5)E O ( 8.4 - 17.51E -1 e( 7/ 81, e( 4/ Ale e( 3/ 4).
If-7 ( 12) ' 3.6t 2.9)E O 11 ( 4.1 t 3.2)E O ( 7.1 t 24.0!E -! '
( 0) (-1.0 - 1.4)E 1 (-3.9 - 11.5)E O t-3.7 - 7.3)E e' O! 8), *( 0/ 4), et 0/ 49 K-40 ( 12) ( -6.lt 4.1)E O 12 (-5.5 t 5.7)E O (-6.7 i c. 71E C-( 0) (-2.1 - .9)E 1 (-1.7 - .7)E 1 '-2.3 - 9'E 1
- f 0/ Sie e( 0/ 4), of (t/ 44
% 54 ( 12) 15. ( -6.9f 24.8)E -2 11 ( 3.1 t 2.0)E -1 (-8.7 i 3.1 'E - 1
( 01 f-1,3 - .8)E O (-4.0 - 8.2)E -1 (- .3 - .0'E 0
- e. c/ ('+ ec O! 49 +( 0. 4:+
C'-5t i 1:1 15. i -1.; 3.7iE -1 !! ( 5.1 t 5.6)E -! i-5.f t 3.7.E -1
' O! : 2.1?E O t-4.1 - 20.5'E -1 ' !.5 -
.0 E A
,, 0: Fa e. 1 49 u 0 4)+
FE-5; i 121 30. 2.4t 8.OE -1 it ( 2.0 t 1.!!E O ( :.0 : 1.11E C .-3,2 -
4.6?E O (-5.4 - 4?.HE -: :-5.4 - r *:E e: Oi 8), of Oi 4), et (>/ 4'+
CD-66 ( 12> 15. ! -1.4t 3.6)E -1 11 ( 3.8 t 6.01E -1 (-6.2 i 6.6)E -
i 0; (-1.3 - 1.6?E O (-1.1 - 1.61E o f - 1. 8 - 1. T E et 9/ 8)* *( O! 41e et O! 41, ZN-65 ( 12) 30. ( 4.3t 7.8)E -1 11 ( 5.5 t 13.0)E -1 (-3.9 t 4.01E -1 l
( 0) (-3.1 - 2.7)E O (-3.1 - 2.7)E 0 (-1.2 - .41E O
- ( 0/ 8), *( 0/ 4le et 0/ 4)e IR-95 ( 12) 15. ( -8.3t 5.9)E -1 12 (-4.5 t 103.6)E (-2.8 t 4.5)E -1
( 0) (-2.4 - 2.9)E O (-1.9 - 2.9)E 0 (-1,3 - .6)E O
- ( 0/ Ble et 0/ 4le et 0/ Ale e NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE EASLREMENTS WHICH WERE CREATER THAN TEN (10) TIMES THE AYERACE BACKCfp!. FOR THE PERIOD OF THE PEC'0FT.
+e THE FRACTION OF SAMoLE ANALYSES Y!ELDING DETECTABLE MEASLREENTS (i.E. >3 STD DEVIATION 3) IS INDICATED WI m e' u.
Eff/IP0eEGL RO!(WCAL PR.6R4 9J*72 WRMXT YAWEE NUCLEAR P:.%ER 5%T!% VENE '.'T JWJARY - DECE%ER 19:.4 EDRM: GROI.PO WATER ' NITS: P',Ils 6 INDICATOR STATIOM STATION WITH HIOEST EAN (ONTROL STATIONS e+ee,++e***++++e++ e+++++,e*******e.e+e***+c **++++++eeeee+++
RADICNJCl.! DES EE MEav MEAN (NO. IN, LYSES' PEPJIRED RWE ' STt.. RAfCE M*0E (NnN-ROUTINE)' LLD NO. DETECTED +e NO. NO. DETECTED ++ NO. DETECTED ++
RU-103 ! 12) ( -5. 6.+ 3.9)E -1 12 ( 3.2 f 208.0)E -3 (-2.1 i 4.7)E -1
( 0) (-2.3 - .5)E O (-3.5 - 5.2)E -1 '-1.4 - .8)E O
+( O! 8)+ *( 0/ 4)* *( 0/ 4)*
RU-106 ( !?! ( 2.42 214.9)E -2 21 ( 4.5 4.4)E O ( 4.5 2 4.4)E O
( 0) (-7.3 - 9.71E O (-1,1 - 17.4)E O (-1.1 - 17.4)E O et 0/ 8t* *( 0/ Alt *( 0/ 41*
I-!31 ( 12) ( -1.52 1.41E 0 21 ( 1.5 t 1.4!E O ( 1.5 1,4)E "
( 0: f-5.9 -
4.6)E O (-2.8 - 3.31E O (-2.8 - I.3'E O e' 0/ 81+ *( 0/ 4)* +( a? 4).
CS-!?* ( 121 15. ( -4.2t 2.7)E -1 11 (-4.1 f 2.6)E -1 (-7.".t 4.C E -!
I ni t-!.o - .61E O '-1,1 - .1'E G (-1.4 - 4!E ^
+< m g,s +t 0: 4.+ +: - asr CT- ~' ( 12' 16. ' -3.3t 27.8 E -2 11 *5t
. 4.0)E -1 (-:.0 .MF
( 01 (-1.1 -
1.2 E s (-7.1 - 12.2)E -1 t-2.5 - .21
+4 or su e: 0- 43 et o' 4:.94-140 ( 125 !!. ( -:.41 1.3tE O 21 t -6. 5 t 11.6)E -1 (-8,5 t 11.' C -
( Oi ( o. ^ - 4.vE O (-2.e - 2.1)E O l- 2. 's -
2 l'E
- 0/ 8)* *: 0/ 4)* *: O! Ale CE-141 ( 121 ( -1.4 10.7)E -1 2' ( 9.5 14.4)E -1 ( 9.5 t 14.41E -i
( 01 (-4.0 - 5.61E O (-2.? - 4.7)E O (-2. 3 - 4.7:E 4
+4 0/ 8)* *( 0/ 4)+ *( 0/ 4)*
CE-144 ( 12) ( -1.9t 2.31E O !! (-3.4 1 30.6)E -1 (-4.1 t 38.5)E -1
( 0) (-1.1 - .7)E 1 (-7.3 - 6.8)E O (-9.8 - 0.0)E O
- ( 0/ 8)+ *( 0/ 4)* *( 0/ 41*
H-3 ( 121 3000. ( 8.2f 4.4)E 1 21 ( 1. 6 * .8)E 2 ( 1.6 t .8tE 2
( 0) (-3.4 - 37.6)E I ( .0 - 3.2)E 2 ( .0 - 3.2)E 2
- ( 0/ 8), *( 0/ 4)* *( 0/ 4)*
- NON-ROUTINE REFERS TO THE NUMBE0 CF SEPARATE EA9)REENTS WHICH WERE L'REATER THAN TEN (10) TIMES TE AVERAGE PACKCAL1E FOR THE PEFIOD Oc THE REPORT.
- THE FRACTION OF SMPLE AW. LYSES Y!ELDING DETECTABLE MEA $lREMENTS
(!.E. >3 STD DEV!ATIONS) IS INDICATED WITH of )*.
G) River Water River water is analyzed monthly for gamma-emitting radionuclides and gross-beta (not required by RETS). The monthly samples are composited and analyzed for H-3 on a quarterly basis. A composite sampler is used at Station WR-11 and grab samples are taken at Station WR-21. During the period April 16 through May 14, 1986, the automatic composite water sampler at Station WR-11 was out of I
service. A grab sample was collected on May 14, 1986 in place of the composite sample.
Gross-beta radioactivity was detected in all but three samples during 1986. The mean value for the indicator stations was similar
- to that of the control station and to that of previous years, indicating that those radionuclides detected are not due to plant operations. Naturally-occurring K-40 was detected in one sample,-
and Cs-137 and I-131 both were detected in a single sample from Station WR-11, collected with a grab sample on May 14, 1986. These radionuclides are consistent with measurements of air and precipitation, both of which contained Chernobyl-related fallout at the time. See Section 4 for a more complete discussion of Chernobyl fallout.
l 2896R
ENV!EteENTA. FACICWICA. CRT65AM 9.rMi VERT *!i YAWEE RXtE/I FtWEF: STION, VL5Kri. V' JA4 # 1 - DECEMEEF 1 %
EDIlm RIE WaTEC LNITS: PCl/KG INDICAT00 STATION 3 STATION WITH HIGHEST EAN CONTROL STATI? G etee*+++,*ee++,eee eeeeeee++++ee+++e++++,ete ee++ee+eeeeeee**
RADIO 4XLIDES MEAN ME.VJ EAN (NO. ANALYSES) REDVIFED rat 5E STA. RANGE FANGE (NON-ROUTINEl' LLD NO. DETECTED +e NO. NO. DETECTED +e NG. DETECTED ++
GR-B ( 24) 4. ( 2.0t .3)E O 11 ( 2.0 t .3)E 0 ( 1.8 i .!)E G
( 01 ( 1.2 - 4.1;E O ( 1.2 - 4.1)E O ( 6.2 - 25.6)E -1
- ( 10/ 121+ *( 10/ 12)* *! 11/ 12)*
BE-7 ( 24) ( 3.0t 2.5)E O 1) ( 3.0 t 2.51E O ( 2.0 f 1.9)E O
( O' (-8.4 -
23.01E O (-8.4 - 23.0)E O (-1.2 - 1.5'E 1
+' 0/ 121+ *f 0/ 12)* *( O'12)*
t- ^ ( 24) ( 6.42 $.7)E 1 11 ( 6.6 i 6.71E 1 1.3 t 3e 6'E ':
( 11 f - 2. ". - 8C.U E 1 (-2.5 - 80.6)E 1 t-2.4 - :.mE 1 4
er :/ 12)+ *( 1/ 12), *( O' 10i+
ftJ-54 ( 24) 15. t 4.? 3.5)E -1 11 ( 4.S 3.5)E -1 (-1.! t :.ME '
( O! ( -1. 7 - 3.N E '- .7 - 3.01E ^ H.'- 1. t E
. *' 0 ' 12 e + +? 0' 123* e- 1: "
CO 'S f 2') 15. ( -1. lt 2.3)E -1 11 (-1.1 t 2.3)E -1 (-3.4 i :.5E -!
' 0) '-1.6 -
1.0 E O (-1,6 - 1.0)E O :-2.^ - 'M.
+- 0! 12i+ +4 0/ 12), +i 0/ 1; ,
FE-5; i 24: 30. ( 6.7t 50.c;E -2 11 ( 6.7 t 50.9)E -2 (-9.? t 7.o:E -1
( 0) :-a ? - 2.5:E O '-4.3 - 2.5)E O (-8.3 - 3.2iE
- ( 0/ 12)* *t 0/ 12)* *( O' 121e 00-69 ( 241 15. ( -0.2 ?.2)E -1 11 (-2.2 ! 3.2)E -! (-7.0 2 1.OE -1
( 01 (-1.0 - 1.6;E O (-1.9 - 1.6 E O (-2.1 - .2iE O i *( 0/ 121+ *( 0/ 121e *( 0/ 121e ZN-65 ( 24) 30. ( -8.7t 5.9)E -1 21 (-1.4 t 46.2)E -2 (-1.4 i 46.2)E -2 i ~( 0) (-4.1 - 2.6)E 0 (-2.7 - 3.1)E O (-2.7 - 3.1)E O
! *( 0/ 12)* *( 0/ 12)* *( 0/ 12)e l
l 2R-95 ( 24) 15. ( 6.92 46.1)E -2 11 ( 6.9 i 46.1)E-2 (-1,6 t 4.8)E -1 l ( 0) (-2.8 - 2.4)E O (-2.8 - 2.4)E O (-2.0 - 4.2)E O
- ( 0/ 12)* *( 0/ 12)* *( 0/ 12)+
1 e M)N-ROUTINE REFERS TO THE NUMBER CF SEPARATE MEA 9)REMENTS WHICH IERE CREATEP THAN lEN (10) TIES THE AWRACf BACKGROUND FOR THE PERIOD OF THE REPORT.
- THE FRACTICN OF SAfFtE ANALYSES YIELD 14', EETECTABLE MEA 9)REMENTS
(!.E. >3 STD DEVIATIOUS) IS INDICATED WITH *t 16, i
l
i e ENVIFONMENTAL RAIICt0n; CAL PFOGFAM Sl&ARY VERF//fT Y/#EE NUCLEAR PCalER STATICW. VEM& '.1 JANUARY - DECEMBER 1986 MEDIUP': RIVER WATER tri!TS: PCIAG INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STt.!!0rn e,++,eee+ee,+++,e, e,++e,++e++e+ee+++eveeee+ ++ee,*++++e+eese RADIOTXLIDES met.N EA': E#J REPJIRED. 94 6 574. RANGE RANGE (NO. ANI.'.YSES)
(Nr.W-ROUTINE)' LLD NO. DETECTED ++ NC. NO. DETECTED ++ NC. K TECTED*+
RU-103 ( 241 ( -3.2f 4.7)E -1 11 (-3.2 t 4.7)E -1 (-7.8 i 2.9)E -1
( 0) (-3.5 - 1.9)E O t-3.5 - 1.9)E O (-2.6 - 1.2)E O
- ( 0/ 12)* *( 0/ 12)* *( 0/ 121+
RU-106 ( 24) ( -1.5: 1.8)E O 21 ( 1.5 i 1.8)E O ( l.5 t 1.8)E O f 0 (-1.4 - .7)E 1 (-1.0 - 1.0)E 1 i-1.0 - :.0)E 1
- ! O/ 121e *: 0/ 12)* *: O! 12)*
I-131 ( 24 ( 1. 5 2.3)E O !! i 1.5 t 2.3)E O i-!.! t !! ~)E .
( !; (-7.7 - 24.1?E O (-7.7 - 24.1:E O (-7.5 - 1:.7:EO
- ( 1/ 12)* *' 1/ 12H ** O! 12)*
CS-134 t 241 15. f -4.2+ 2.0)E -1 11 (-4.2 t 2.0)E -1 1-4.~ t 1.o1E -1
( 0) (-1.5 - 1.1'E O (-1.5 - 1.1)E O ' - 1. '. - .5)E 6
+' 0/ 12)+ *( 0/ 12)+ U 4/ 12)>
C5-137 ( 24! 18. ( 2.2t 3.1)E -1 21 ( 4.0 1 3.31E -1 ! 4. ) t 3.31E -:
( !) f-1,9 - 2.4)E C '-1. 2 - 3.11E 6 ( '. 2 - ? itE '
+1 1/ 12)+ +t Of 12s +.
1:a BA-140 ( 24 15 i -1.7 7:EO 21 8 6.4 t 6.4)E -1 'o4t 6.4'E '
( 01 (-8.2 - .9tE O t-3,3 - 3.5)E O K.3 - 3 OE O
- ( 0/ 12)+ *( 0/ 12)* *( 0/ 12 e CE-14! ( 24) ( -0.1.+ 8.9)E -1 21 ( 1.6 f 3.S'E -1 i 1.8 i ?.ME -1 f 0) (-5.7 - 4.4:E O (-1.3 - 3.5)E O (-1,3 - ~'E '
- ( 0/ 12)+ F 0/ 12i+ t. 0/ 12h CE-144 ( 24; ( 3.8t 13.9)E -1 21 ( 1.0 i 1.8)E O ( 1.8 t 1.E)E O
( 0) (-9.3 - 5.9)E O (-6.1 - 17.5)E 0 (-6.1 - 17.5)E O
- ( 0/ 12)* e( 0/ 12)* *( 0/ 121*
H-3 ( 8) 3000. ( 2.7t .7)E 2 11 ( 2.7 i .7)E 2 ( !.9 t 1.0)E 2
( 0) ( 6.6 - 36 1)E 1 ( 6.6 - 36.1)E 1 (-1.9 - 43.0!E 1 l *( 0/ 4)* *( 0/ 4)* *( 0/ 4)*
- NON-ROUTINE REFERS TO THE NLMBER CF SEPARATE EASLREENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUN3 FOR THE PERIOD CF THE REPORT.
?
H)'dediment During 1986, sediment samples were collected from two locations in May and October. Each samfl e was analyzed for gamma-emitting radionuclides. One grab sample was collected at Station.SE-11 and eight grab samp1.es at Station SE-12 during May. During October, one was again collects'd at SE-11 and eleven at SE-12.
4-Cesium-137 was detected in all samples. As has been discussed in previous Vermont Yankee Radiological! Environmental Surveillance l Reports, this radioactivity!has been due to nuclear weapons testing
$ fallout.. Since there were'no liquid releases'during 1982 through 1986, it can be concluded that the levels of Cs-137 in 1986 sediment samples were due also to nuclear weapons testing fallout.
This is further supported by the fact that similar levels have in the past been detected at Station SE-21, a control station, and at control locations at other plants. Low levels of Co-60 have still been detected in s'amples collected at Station 12 (N. Storm Drain
- Outfall). This subject was discussed in Reference 1.
It should be noted here that the statistics given in the following table are heavily weighed toward Station SE-12, since 19 of the
(
21 samples were collected there. No Co-60 was detected at Station SE-11.
Naturally-occurring Be-7, K-40, and Th-232 were also detected in many samples.
7 2896R
Er.'tivt4Mir.7/4 FADIOLOGICK PROGW 9.titARY "EPfCNT YA9 EE N'AEAR PCG STATION. VERNrA VT JA4 W 3 - KCEMBER 1986 MEN'.M: SE.'IMD? LNITS: PCI/LG : D ICICA'OR STATIONS STATION WITH HIGHEST EAN CONTR0'. STATI?;E tittfliftfflitttit titt+++ttetitittfitetttt) ftttifttttttt++6 RCI0rt?" LICE!. ME#. MEN. EA?!
(NO. #A'.YSEP RE M FD FA'GE STA. R#GE R#GE
(?O!- R1' TINE F LLD NO. DE'ECTEDn NO. NO. DETECTEDn NO. DETECTEDft
. =. .. ..
BE-7 ( 211 ( 2.4 .5)E 2 12 ( ?.7 t .5)E 2 NO DATA
( 4) (-2.2 - 8.6'E 2 (-1.7 - 8.6)E 2
- ( 4/ 21)f *( 4/ 19)*
K 40 -( 21) ( 1.2t .0)E 4 11 ( !.2 t .2)E 4 NO DATA
( OS f 8.4 - 15.1)E 3 ( 1.0 - 1.4)E 4
- ( 21/ 21)e tf 2/ 219 MN-54 ( 2D ( -1.5 .3)E 1 12 (-1.4 t .3)E 1 r0 DATA
( 0) (-3.8 - 1.7)E 1 '-3.8 - 1.7)E 1
- ( 0/ 21)* *f 0/ 191*
CO-53 ( 21) ( -7.61 3.41E O 11 (-3.9 i 20.05E O NO DATA
( 01 (-3.1 - 1.7)E 1 f-2.4 - 1. 9 E
, *( Ot Opt f( 0/ 2i+
FE-59 ( ?!) ( 2.5+ .95E I 11 t 4.2 t 4.4)E 1 N0 ret
( 0: '-?.2 -
- 51E I
. (-2.4 - SS.5'E O
- ' OI 2:14 f: of O'+
00-63 ( :? - ( 5.T2 2.2?E 1 12 I 6.4 2.31E 1 NO D;T;
( 9: 1-1. 9 - 45.SiE 1 :-).5 - 45.?!E 1
- ( 9/ 2119 *( 9/ 19)*
IN-65 ( 21 ( 9.0t 64.0!E -l 11 ( 5.3 31.3)E O N? DATA i 0~) (-5.? - 4,9)E i f-2.6 - 3.7)E 1
- f 0/ 21)f *f 0/ 2)*
ZF-95 ( 21' ( !.3t 8.3]E O 12 ( 4.4 i 8.3)E O v0 re.TA
( 0) (-7.2 - S.7)E 1 (-7.2 - S.7)E 1 ef p/21)f *( 0/ 19)f s
l R'J-103 ( 2!) ( 3.2t 45.11E -1 12 ( 4.9 i 3.5)E O NO DATA
( 0) (-4.6 - 5.01E 1 (-2.4 - 5.01E 1 e( O! 21)* *( 0/ 19)*
1
.
- NON-PO'JiiNE REFERS TO THE N'JGER Or SEPARATE MEAstFSMENTS WHICH WEFS GREATER THAN TEN (ifa TIMES THE AVERAGE BACKGR0lND FOR THE PEFIOD OF THE REPORT.
es THE FRACTI(t! 0F SARE AN#.Y55 YIELDING DETECTAKE MEA 511RE". ENTE
!'.E. >3 STD DEv;ATinNs; 13 IND! RATE: '.'1TH ef 19
E*.! .T:#E*;TR KADICq.0GICAL PROCM 9.mACY
'FPUC YAflJEE ELEAF, FGER STATIC 4 VE406 VT M JAR'l - DECEM9ER 19?6 G .N SE! I. C Ltlis: FCI/KG DRY INDICATOR STATIONS STATICN WITH HIC 4EST MEAN CONTROL STATIONS seeeeeeee+,eeeeee, eeeeeeeee+eeeeeeeeeeeeeee eteeeeeeeeeeeeee RADION'JC.IIG MEAN EA4 E4; (NO. ANALViE l RER' IRED PAtr.'E STA. RANC( RANCE (e-R0'JTINEl' LLD !O. DETECTEDet N9. NO. DETECTED +e NO. DETECTED +e RU-106 ( 21) ( 4.71 3.0)E 1 12 ( 5.4 3.2)E 1 NO DATA I 0) (-1.6 - 4.3)E 2 (-1.6 - 4.3)E 2 '
e( 0/ 21)e *( 0/ 19),
I-131 ( 2;) ( -5.01 6.5)E 1 11 ( 1.9 i .9)E 2 NO DATA
( 01 (-5.9 - 6.7)E 2 ( 1.0 - 2.8)E 2
- ( 0/ 21), e( 0/ 21, C5-134 ( 211 150. ( 8. 3 4.7)E O 12 ( 1.1 i .5)E 1 NO 0ATt.
( !! (-2.9 - 5.1)E 1 (-2.6 - 5.1)E 1
- I 1/ 2 )* *( 1/ 19),
CS-137 ( 21) 190. ( 2.tr .2)E 2 12 ( 2.1 i .2)E 2 NO DATA
( O! ( 4.9 - 37.61E 1 ( 4.8 - 37.6)E 1 el 21/ 2;)+ e t 10/ 101+
BA-140 , 2:6 ( -1.61 .aiE 2 12 (-1.4 i .41E 2 NO DATt.
~
- 0) f-7.1 - . ".E 2 (-5.? - . E 2 e' O! D )+ +( 0/ 191t tI-14 ' 20 '
9.12 6.6:EO 12 ( 1.0 f 7)E 1 NO DATA
. i 07 (-3.7 - 5.o;E i i-5. 7 - 5.9)E 1 e( 0/ 211e et 0/ 19),
CE-144 f 211 ( -5.2t 2.1)E 1 11 (-2.3 i 1.9)E 1 NO DATA
( 0) (-2.3 - 2.01E 2 (-4.3 - .4)E 1 et 0/ 2: 1+ ef 0/ 2)*
TH-232 ( 21) ( 7.61 4)E 2 11 ( 9.7 i 1.6?E 2 NO DATA l
( 0) ( 4.0 - 12.3)E 2 ( 8.1 - 11.3)E 2 e( 21/ 21), *( 2/ 21e e NON-ROUTINE REFERS TO THE NLPSER OF SEPARATE EASLREENTS WHICH WERE GREATER THAN TEN (10) TIMES TE AVEPAGE BACKGROUND FOR TE PERIOD OF TE REPORT.
ee TE FRACTION CF SAMFtE ANALYSES YIELDING DETECTABLE EASLREENTS
(!.E. >3 STD DEVIATIOND IS I C CATED WITH et le.
r-I) Finfish Finfish samples were collected from two locations during May and again in October of 1986. Each sample consisted of mixed fresh water species, generally perch and bass. All were analyzed for gamma-emitting radionuclides. Cesium-137 was detected in all of the four samples collected. The levels are consistent with well-documented environmental levels caused by nuclear weapons testing fallout. The levels for the indicator station are similar to those in 1985, as well as to that of the control in 1986. No other radionuclides were detected except for naturally-occurring K-40.
2 l
i 2896R
EWIRCmENTAL RADIOLOGICAL PROGRAM SlfftARY VEWen Y.tVEE tar.' EAF P0;O STAi!0ti. VERNCN, VT s.iA m i - DECErcER 1 %
ME2: ?: F1 7:18 UNITS: PCI/KG WET INDICATCR STA'ICf6 STATION WITH HIGHEST EAN CONTROL STATIOT:
- +++ee****,,e+++, e++++,*******,,,,,*ee+++, *****+te++e+++,+
RADIO @.iCLIKS MEA'! EAN TA':
(N3. ANALYSES) FIOUIRED RA G STA. RANGE RANGE NO. IETECTEDet NO. NO. DETECTED ++ NO. DETECTED ++
(NON-RTTINE)' LLD E-7 ( 4) ( -3.21 3.8:E 1 21 (-1.7 t 1.4)E 1 (-1.7 t 1.4)E I
( 0) -(-7.0 -
.51E 1 (-3.1 - .3)E 1 (-3.1 - .31E 1
- ( 0/ 2)* *( 0/ 2)* *( 0/ 2)*
K-40 ( 4) ( 3.0f .0)E 3 11 ( 3.0 t .01E 3 ( 2.9 i .3)E 3
( 0) ( 3.0 - 3.0)E 3 ( 3.0 - 3.0)E 3 ( 2.6 - 3.2)E 3
- t 2/ 21* *! 2/ 2)* *( 2/ 2)*
MN-54 ( 4! 130. t 1.5f 1.2:E 1 11 ( 1.5 t 1.2)E 1 ( 2.8 t 1.3!E 0
( - 01 ( 3.2 - 27.0]E O ( 3.2 - 27.01E O ( !.5 - 4.2tE C
- 0/ 2)* *( 0/ 2)* +( 0/ 2'+
CO-58 ( 4) 130 5.72 6.6'E O 11 ( 5.7 6.6:E O ( 1.6 t 8.5'E O 01 M7 - 103.0:E -1 f-9.7 - 123.0!E -1 !-6.5 - It.:'E s e ' 2n at 0/ 2)+ +: c. 2 FE-59 ( 41 26>: . t
.7t ~.4'E : S (-2.6 i .0'E 1 (-2. 6 i .0'E .
~a - -1.31E 1
+ c' 2p r. 0: 2i+ v 0: 2e CC-6') ( 4) 130, i 1.7: 13. 0!E '. 11 ' 1.7 i 13.0;E O (-5.7 3.2iE O O! i-1.1 -
1.5'E 1 (-1.1 - 1.5:E 1 (-8.o - -2.4'E
- 0 2* *( 0/ 2)+ *( 0/ 2)*
ItJ-65 i di 260. ( 2.5f 1.0!E 1 11 ( 2.8 t 1.01E 1 ( 3.5 t 1.2'E ^
i ( O' ( 1.8 - 3.8;E 1 ( !.8 - 3.8)E 1 ( 2.3 - 4.~;E O 1
' e' 0/ 21* *( 0/ 25+ *( 0/ 2)*
2R-95 ( 41 ( -2.0 9)E 1 21 ( 1.9 t .5)E 1 ( 1.9 i .5)E 1
( 01 (-2.8 - -1.1)E 1 ( 1.4 - 2.4)E 1 ( 1.4 - 2.41E 1
- ( 0/ 2)* *( O! 2)* e( 0/ 2)*
RU-103 ( 41 ( 2.81 18.8)E O 11 ( 2.8 t 18.8)E O (-1.2 t .7)E 1
! ( 0) (-1.6 - 2.2)E 1 (-1.6 - 2.2)E 1 (-1.9 - .5)E 1
- ( O! 2)* *( 0/ 2)* *( 0/ 2)*
- NON-ROUTINE RErERS TO THE N'MER OF SEPARATE EAstREMENTS W!CH WEPE CFEATER THAN TEt! (10: TIMES THE A','ERAGE BACKGRlVfD FOR THE PERIOD OF THE REPORT.
<* THE FRACTICt. OF SAMPLE A'A'YSES <!ELDING DETECTARE MEcRREENTS (i.E. >3 STD DEVIATICru 19 INDICATEI ;l.TH H )+.
EW:R0hrL94TAL RADIOLOGIU.L PR% RAM SIN 4W VEE *C#lT YANvEE 4.CEAL POWER STATICri VERNff.', VT JAN';Fi J - IECEMBEP 1986 LP !TS: PCI/Fr, ;;ET ED:t!*: N:fW IND?CATOR STATI0'6 STATION WITH I410EST EAN CfWTPOL STAi!Ct6
,++t+++++++++++t+e+e+,*** *+,e++++++++++++
+++++e+++++e++++++
. P4DICNJCLIDE' EAN EE EIS
( D -R F INEl' LLD NO. DETECTEDn 6*J-106 I 4) ( -9.6f 10.9)E 1 21 (-5.5 i 15.4)E O (-5.5 15.4:EO I -0) (-2.0 - . lE 2 (-2.1 - 1.0)E 1 (-2.1 - 1.0;E :
- f 0/ 21+ *( 0/ 29 *( 0/ 2)+
I-13: ( 4? ( -2.A. 2.6'E 2 21 i 3.2 t 1.9)E 2 ( 3. 2 : 1.HE 2 (m (-5.0 - . tie 2 ' l.3 - 5.0!E 2 ( 1. 3 - 5.0;E 2
- f O! 2't t' 0/ 29 *: 0/ 29
'CS-132 4; 130.
-6.7; :.5'E O 21 i 2.7 s 5.::E O r 2. t 5.!!E O
( Oi (-0.2 - -5.3!E O i-2.4 - 7.81E O (-2.4 - 7. DE O n' O! 2B *C O! 25, it 07 21' r$-137 ( 4) 150. ( 3.91 .5)E 1 1: ( 3.9 f .51E 1 ( 2.5 * .1:E. !
( 0) i 3.5 - 4.4'E 1 f 3.5 - 4.4:E : ( 2.~ - 2.c;E -
+' 2/ 2n + 2, :-
e 2/ 2:*
9e la0 ( 4) ' :.3: 1.61E 1 11 ( !.3 i 1.6)E 1 (-4.6 f 23 D E -;
0' (-2. 0 - 20 !)E 6 (-2.9 - 7.DE O (-2.6 - .*'~ C
+ ' c ::e >- C/ 29 v Or : <
CE-131 ( 4) ! 2. 7 3.21E : 11 ! 2.' t 3.2)E 1 ( 1.9 i .21E i Oi f-5.1 - "5EO . t-5.1 - So.5,E 't i 1.0 - 25.i'E
+( O! 2?' it 0/ 2)* *( 0/ 2it CE-]44 ( Ai ( -9.8: 17.2?E O 21 f 2.9 f 2.0)E 1 ( 2.9
- 2.0)E
( 0: (-2.7 - '
. !E I ' ?.2 - 45.7)E O ( 9.2 - 4E."E e 0/ 2R *t 0/ 2;+ *i 0/ 24 TH-232 ( 4) r ?.3 1.HE 1 11 ( 3.3 1.91E i ( !.! 6.0 E . '
( O! ( !.4 -
5.2)E I ( !.4 - 5.2)E 1 (-4.9 - 7.2)E -1
+t 0/ 2)* *( 0/ 2)* *( 0/ 2)*
- NON-ROUTIE REFERS TO TE M19ER OF SEPARATE EASUREENTS leilCH WERE GREATER THAN TEN (10) TIES TE A'KRAGE BACKGROUND FCR THE PERIOD OF TE REPORT.
- THE FRACTION OF SAfFLE ANALYSES Y! ELD!NG DETECTABLE EASLREENTS (I.E. 33 STD DEV!ATI0fE) IS INDICATED WITH er le.
w wy--a---- v - ,
-m,, -- --
3 vr
J) Direct Radiation Direct gamma radiation exposure was determined from the use of thermoluminescent dosimeters (TLDs). Two CaF :Mn 2 TLDs were placed at each of the monitoring stations. Fifty-one sets of TLDs were read out on a quarterly schedule. Sixteen of these were located at inner ring stations and 16 at outer ring stations.
Twelve were located at the site boundary, six were at special
[. interest locations and one was a control.
Nine TLD badges were lost (apparently stolen or destroyed while in the field) during 1986. These badges were from Stations DR-1 and 38 during the first quarter; Stations DR-15, 28, 34, and 36 during the second quarter; and Stations DR-15, 38, and 48 during the third quarter.
Summaries of the results for 1986 can be seen in the table below.
Average exposure rates are given for each station in Table 3.1.
In Table 3.2, the quarterly averages for inner ring stations (i.e.,
those locations that could possibly be influenced by plant ,
operations) were compared with those for the outer ring stations (i.e., those locations outside of the range of influence of the plant). The table only gives data back to the second quarter of 1985, which is when the outer ring stations were implemented with the new Radiological Effluent Technical Specifications. The ratio does not change appreciably from quarter to quarter over this l
period. Upon examining the quarterly exposure rates in the table, it is also evident that the inner ring exposure rates are not statistically different from those of the outer ring.
i 2896R
4 Environmental Radiological Program Sununary Vermont Yankee Nt. clear Power Station, Vernon, Vermont January - December 1986 Medium: Direct Radiation Units: Micro-R per Measurements (TLD) Hour Station With Inner Ring Highest Mean - Outer Ring Mean Mean Mean Range Station Range Range (No. Meas.)* No. (No. Meas.)* (No. Meas.)*
11.6 52.1 11.9 7.8 - 15.2 45 39.4 - 63.7 6.0 - 16.4 (62) (4) (59)
- Most measurements based on readings from two TLDs.
l l
2896R
Table 3.1 Vermont Yankee Summary of Direct Radiation Measurements - 1986 Micro-R Station Description Zone
- Per Hour **
DR-1 River Station No. 3.3 1 13.1 DR-2 N. Hinsdale, NH 1 11.8 DR-3 Hinsdale Substation 1 12.5 DR-4 Northfield, MA 1 11.7 DR-5 Spofford Lake, NH 2 12.3 DR-6 Vernon School 1 11.7 DR-7 Site Boundary 1 14.3 DR-8 Site Boundary 1 13.2 DR-9 Inner Ring I 11.4 DR-10 Outer Ring 0 11.0 DR-11 Inner Ring I 12.1 DR-12 Outer Ring 0 11.6 DR-13 Inner Ring I 12.1 DR-14 Outer Ring 0 12.4 DR-15 Inner Ring I 10.7 DR-16 Outer Ring 0 14.0 DR-17 Inner Ring I 10.9 DR-18 Outer Ring 0 11.6 DR-19 Inner Ring I 11.9 DR-20 Outer Ring 0 12.4 DR-21 Inner Ring I 11.5 DR-22 Outer Ring 0 11.6 DR-23 Inner Ring I 12.3 DR-24 Outer Ring 0 11.1 DR-25 Inner Ring I 11.8 DR-26 Outer Ring 0 12.5 DR-27 Inner Ring I 11.9 DR-28 Outer Ring 0 11.8 DR-29 Inner Ring I 11.4 DR-30 Outer Ring 0 11.2 DR-31 Inner Ring I 11.3 DR-32 Outer Ring 0 11.5 DR-33 Inner Ring I 11.0 DR-34 Outer Ring 0 13.7 DR-35 Inner Ring I 11.7 DR-36 Outer Ring 0 10.0 DR-37 Inner Ring I 11.6 DR-38 Outer Ring 0 11.8 DR-39 Inner Ring I 11.4 DR-40 Outer Ring 0 12.7 DR-41 Site Boundary SB 13.2 DR-42 Site Boundary SB 12.9 DR-43 Site Boundary SB 12.6 DR-44 Site Boundary SB 15.8 2896R
Table 3.1 (Continued)
Vermont Yankee Summary of Direct Radiation Measurements - 1986 Micro-R Station Description- Zone
- Per Hour **
DR-45 Site Boundary SB 52.1 DR-46 Site Boundary SB 15.6 DR-47 Site Boundary SB 13.8 DR-48 Site Boundary SB 12.4 DR-49 Site Boundary SB 11.3 DR-50 Governor Hunt House SB 10.8 DR-51 Site Boundary SB 14.1 4
l 0 Zones: 1 = Indicator; 2 = Control; I = Inner Ring; O = Outer Ring; SB = Site Boundary.
- Annual average exposure rate.
2896R
Table 3.2 Vermont Yankee Ratio of Inner Ring to Outer Ring Exposure Rates Inner Ring
- Outer Ring ** Inner / Outer Y'ar Quarter (uR/hr) (uR/hr) Ratio 1986 4 10.9 0.9 11.4 ! 1.9 0.96 3 13.8 1.5 14.2 1.3 0.97 2 11.5 ! 0.9 11.4 ! 1.4 1.01 1 10.5 ! 1.1 10.8 2 1.3 0.97 1985 4 11.3 0.9 10.7 1.1 1.06 3 10.7 1.3 10.1 ! 1.0 1.06 2 9.2 ! 0.9 9.7 ! 0.7 0.95 I
i l
l 0 Includes all Zone 1 and Inner Ring Stations. Does not include site boundary locations.
C* Includes all Zone 2 and Outer Ring Stations.
, 2896R f
~ -* - , - - - - - . . - . . . - . . <- . . . , _ . _ . , , , , _ _ _ , . , - - , , _ _ _ _ . , . _ . _ . , , _ . _ , , , . _ _ , , , _ . , , _ _ _ _ _ _ _ . , , ,_
4.0 ENVIRONMENTAL RADIOACTIVITY FROM THE CHERNOBYL ACCIDENT Following the Chernobyl nuclear plant accident, increased levels of fission-related radionuclides were measured in fresh fallout throughout much of the northern hemisphere, including New England. The amount and type of r dioactivity seen in this fallout were roughly comparable to that observed in follout from the most recent atmospheric nuclear weapons tests conducted by the Peoples' Republic of China during the late 1970's and in 1980.
Chernobyl-related fallout was seen during 1986 in many types of environmental samples, both near the nuclear power plants and at distant csntrol locations, including the Yankee Atomic Environmental Laboratory in Wistborough, Massachusetts. An in-depth discussion of this entire subject may ba found in Reference 2. This section of this report contains a brief summary of the measured radiological environmental impact in northern New England during 1986 from the Chernobyl accident. Selected monitoring results from osveral of the plants in New England have been compiled for this summary.
Many of the measurements were previously reported to the Nuclear Regulatory Commission (via telephone) in response to a request in IE Information Notice 86-32 (Reference 3).
Airborne radioactivity levels measured by gross-beta analysis (see Figure 4.1) show a marked increase during the first week in May. Although the magnitude of the ineasured concentrations varied slightly across New England, the curves were virtually identical. Very evident in the curves are the first
( Chernobyl release, measured during the first week of May, and the second i ralease, measured during the last week of May and the first week of June.
S;veral radionuclides were identified on air particulate filters by gamma spectroscopy. These were Cs-134 Cs-137, and Ru-103. Ru-106 was also dstected at one location at this same time. They are shown in Figures 4.2, 4.3, and 4.4, respectively. Iodine-131 was detected on charcoal filters at oil monitoring stations. Its curve, shown in Figure A.5, is similar to that i fer gross-beta measurements for air particulate filtert.
Several radionuclides were detected in milk samples shortly after their datection on air particulate or charcoal filters. These were Cs-134, Cs-137, 2896R
cnd I-131. Since the deposition of this radioactivity occurred after the ctart of pasture season (for those cows that are pastured), it worked into the cilk pathway readily. Due to its short half-life (8 days), the I-131 was not v:ry persistent in the environment, however (see Figure 4.8), Cesium-137 has fcr many years been detected in cow milk from many locations around New England and the world as a result of the nuclear weapons tests in the 1970's cnd in 1980. Cesium-137 levels (see Figure 4.7) at most locations increased during May due partly to the start of the pasture season (if applicable) and the consequent re-introduction of old Cs-137 into the food chain, and partly due to an increase of Cs-137 levels on pasture vegetation from Chernobyl-related fallout. Cesium-134 was also detected in milk samples.
This isotope of cesium is entirely attributable to Chernobyl, since its ralatively short (2 years) half-life has effectively removed any left over from previous weapons testing fallout. A Cs-137/Cs-134 ratio of approximately 2.0 was noted on air particulate filters, and as one would expect to follow, in milk. The virtual absence of Sr-89 or Sr-90 in the fallout was notable.
This was due to the small amount of strontium released during the accident.
Unlike the gross-beta on air particulate filters and I-131 on charcoal filters, the Cs-134, Cs-137, and I-131 levels in milk varied considerably from location to location due to differences in farming practices. Specifically, types of vegetation fed on by cows and the amount of stored feed given them, cs well as localized differences in deposition of fallout and many other less important factors, have a marked effect on the levels of radioactivity in cilk. With respect to milk samples in the winter of 1986/1987, it is expected that the Cs-134 and Cs-137 levels might increase at some locations during the winter months when cows are given feed that was contaminated by fallout during the opring of 1986. Figures 4.6 and 4.7 show some early evidence of this during the fall of 1986 at several locations.
As one would expect, fallout from Chernobyl was measured in other cnvironmental media such as precipitation and vegetation. Measurements for celected radionuclides in precipitation are shown in Table 4.1 and 4.2 for the Yankee Atomic Environmental Laboratory and the EPA ERAMS Network, respectively.
2896R l
Table 4.1 Chernobyl-Pelated Radioactivity in Precipitation Yankee Atomic Environmental Laboratory, Westborough. Massachusetts (pCi/kg ! one standard deviation)
C211ection Period Rainfall (1986) Cs-134 Cs-137 Ru-103 I-131 (inches)
May 7-9 (-0.3 1.4) (0.9 1 1.4) (-1.5 1.3) 20.4 2 2.8 .13 12.6 1.4 15.4 1 1.6 472 5 .027 May 12 6.9 ! 0.3 May 17 6.1 1 1.1 11.9 1.2 11.4 1.2 68.4 2.2 .31 1.7 ! 0.4 (0.1 0.4) 8.9 1 0.6 .06 May 21-22 (-0.6 ! 0.5) 9.1 1 1.1 49.6 3.4 .79 May 23-25 2.1 2 0.6 5.0 2 0.9 2.5 0.5 6.6 ! 0.8 14.8 1 1.4 .74 May 30-June 1 7.3 2 0.8 June 5-8 (-1.6 0.9) 1.9 2 0.6 (0.8 0.8) (0.6 1.2) 5.10 June 11-13 (2.7 1.0) (0.4 ! 1.2) (-0.3 1.2) (3.0 1.7) 1.16 (2.2 ! 1.3) (-2.3 2.0) (-6.0 14.) .07 June 22-24 (-1.0 ! 1.3)
(1.1 0.8) (0.1 1.1) (1.3 1 8.7) 1.79 July 2 (-0.5 ! 0.8)
Measurements in parentheses indicate radionuclide was not detectable at the three-sigma level.
2896R
Table 4.2*
Iodine-131 In Precipitation EPA ERAMS Network Date Montpelier, Vermont Concord, New Hampshire (1986) pCi/ liter pCi/m pCi/ liter pCi/m May 2 ND ND ND ND May 5 ND ND ND ND May 6 ND ND ND ND May 7 120 480 - --
May 8 ND ND 63 20 May 9 ND ND 33 99 May 11 1,660 12,300 - --
May 12 870 1,740 - -
May 13 - -
53 14 May 17 93 750 160 130 May 19 57 230 -- --
May 20 -- -- -- --
May 21 - -- - --
May 22 -- - 13 78 May 23 14 430 ND ND May 24 -- -- 29 161 May 25 -- - 18 240 May 28 ND ND 80 11 June 2 ND ND ND ND TOTAL 15,930 pCi/m TOTAL 803 pCi/m i
o Taken from Table 20 of Reference 2.
2896R
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5.0 QUALITY ASSURANCE PROGRAM Three separate Quality Assurance programs were performed during 1986 to demonstrate the validity of laboratory analyses by the Yankee Atomic Environmental Laboratory (YAEL).
YAEL participates in the EPA Interlaboratory Comparison (cross-check) program for those species and matrices routinely analyzed by the laboratory.
This provides an independent check of accuracy and precision of the laboratory cnalysis. When the results of the cross-check analysis fall outside of the c:ntrol limit, an investigation is made to determine the cause of the problem cnd corrective measures are taken.
YAEL maintains an intralaboratory quality control program to assure the v:lidity and reliability of the data. This program includes quality control cf laboratory equipment, use of reference standards for calibration, and cnalysis of blank and spiked samples. The records of the quality control program are reviewed by the responsible cognizant individual, and corrective measures are taken whenever applicable.
A blind duplicate program is maintained in which paired samples are prepared from homogenous media and sent to the laboratory for analysis. The results from this blind duplicate program are used to check for precision in 1cboratory analyses.
EPA Interlaboratory and Intralaboratory Results The Quality Assurance Program implemented at the analytical laboratory indicated good precision and accuracy in reported values. Table 4.1 shows the results of accuracy and precision for laboratory analyses in 1986 for intralaboratory analyses, and EPA interlaboratory cross-check analyses. For cccuracy, 66.4 and 88.5 percent of the results were within 5 and 10 percent of the known values, respectively, with 96.8 percent of all results falling eithin the laboratory criteria of 15 percent or two sigma. For precision, 85.9 and 96.0 percent of the results were within 5 and 10 percent of the mean, 2896R
r:spectively, with 100 percent of all results meeting the laboratory criteria cf 15 percent or two sigma.
The results of the EPA Interlaboratory Comparison program, when considered apart f rom the remainder of the Quality Assurance program, were s tisfactory in 1986. Two hundred and twenty-two analyses were performed on cir particulate filters, milk, and water. Of these 222 analyses, 15 were not included in the overall summary of accuracy statistics due to what the Yankee Atomic Environmental Laboratory considers questionable media. The analyses in question represent four sets of samples, all of which are considered questionable from the standpoint of EPA preparation and known-value esiculation. These cases are documented in References 4 and 5. Based upon the corrected sample analysis total (i.e., 207), 206 analyses (i.e., 99.5%)
met the EPA's definition of mean value criteria. The single sample analysis that did not meet the criteria was a Ru-106 analysis in a water sample. A r: count of the sample yielded a measurement that met the above criteria.
(Details of this may be found in Reference 5.)
! Blind Duplicate Program A total of 55 paired samples were submitted by the five participating plants for analysis during 1986. The data base used for the duplicate cualyses consisted of paired measurements of 26 gamma emitting nuclides, H-3, Sr-89, Sr-90, low level I-131 and gross beta. A dual level criteria for cgreement was established. If the paired measurements fall within 15 p:rcent of their average value, then agreement between the measurements has b:en met. If the value falls outside of the 15 percent, then a two standard d;viation range (95 percent confidence level) is established for each of the cnalyses. If the ranges overlap, agreement is obtained.
One thousand three hundred and sixty-four paired duplicate measurements were analysed for 1986. A total of 99.1 percent of all measurements fell eithin the established criteria discussed above. The 12 measurements that did n:t meet the criteria were measurements of 2n-65 in milk, Mo-99 in milk, co-58 in milk, Mn-54 in seawater, Ce-141 in seawater, Ba-140 in seawater, Zr-95 in 2896R
Table 5.1 Intralaboratory and EPA Interlaboratory Results - 1986 Accuracy Total Number 0 to 5% 0 to 10% 0 to 15%*
of Measurements (or within 2 sigma) 840 558 743 813 (66.4%) (88.5%) (96.8%)
Precision Total Number 0 to 5% 0 to 10% 0 to 15%*
of Measurements (or within 2 sigma) 4 815 700 782 815 (85.9%) (96.0%) (100%)
1 0 This category also contains those samples having a verified zero concentration which were analyzed and found not to contain the isotope of interest.
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s ,1 water, Se-75 in mussel bodies, Co-57 in milk, Ru-103 in groundwater, Ba-140 in milk, and K-40 in Irish moss. In all but the last case, the radionuclide in question was not detected in the sample and a three-standard deviation ceceptance criteria was met. In the last case, the reason for the erroneous K-40 concentration was ascertained and the data was corrected. The 12 duplicate measurements represent 0.9 percent of all the blind duplicate paired mersurements made during 1986. No trend was evident with respect to repeated failings of measurements for the above radionuclides.
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6.0 LAND USE CENSUS The Vermont Yankee RETS require that a Land Use Census be conducted cnnually between June 1 and October 1 of each year. The census identifies the 1ccation of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within 5 miles of the plant. It also identifies the n:arest milk animal (within 3 miles of the plant) to the point of predicted highest annual average D/Q value in each of the three major meteorological cactors due to elevated releases from the plant stack. Dosimetric analyses cre then carried out to determine whether any identified milk animal r presents a significantly better milk sampling location than those currently bsing used.
The 1986 Land Use Census at Vermont Yankee was carried ct t between August 6 and August 12, 1986. The identified locations can be found in Table 5.1. As a result of the dosimetric comparisons, Stations TM-14, TM-15, and TM-16 were designated as the required sampling locations in the Off-site Dose Calculation Manual.
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i Table 6.1 Vermont Yankee 1986 Land Use Census Results Neurest Residence Milk Animals Sector (km) km Cow or Goat N 1.6 4.7 Cows NNE 1.6 * -
NE 1.3 4.2 Goats ENE 1.0 * -
E 1.0 2.4 Cows ESE 2.8 * --
SE 1.8 3.4 Cows SE -- , 4.3 Goats SSE 2.0 5.1 Cows S 0.5 * --
SSW 0.5 2.1 Cows
, SSW -- 2.4 Cows SW 0.5 7.2 Cows WSW 0.5 * --
W 0.5 7.2 Goats WNW 0.6 0.8 Cows WNW -- 4.7 Cows NW 1.2 4.7 Cows NNW 2.1 * --
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-0 No milk animals found within 5 miles.
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7.0 SUP91ARY During 1986, samples collected as a part of the radiological cnvironmental monitoring program at Vermont Yankee showed detectable levels of man-made radionuclides in air particulate and charcoal filters, milk, mixed vegetation, river water, finfish, and sediment. In all but one case, the low icvels detected were shown to originate from fallout from atmospheric nuclear weapons tests conducted during the 1970s and 1980, or from fallout from the Chernobyl nuclear plant accident in 1986. As reported in the past, low levels cf Co-60 were detected in river sediment in the immediate vicinity of the North Storm Drain Outfall. The radiological environmental monitoring program has therefore demonstrated that plant operations have had no significant ispect on the environment.
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8.0 REFERENCES
- 1. Annual Radiological Environmental Surveillance Report, 1984, Vermont Yankae Nuclear Power Corporation.
- 2. S. Farber, " Evaluation of Environmental Radioactivity Resulting from the Chernobyl Accident Measured by the Yankee Atomic Electric Company Environmental Laboratory," Yankee Atomic Electric Company, March 26, 1987.
- 3. USNRC IE Information Notice 86-32 " Request for Collection of Licensee Radioactivity Measurements Attributed to the Chernobyl Nuclear Plant Accident," dated May 2, 1986.
- 4. YAEL Quarterly Status Report, April-June 1986 Environmental Laboratory Group Yankee Atomic Electric Company.
- 5. YAEL Quarterly Status Report, October-December 1986. Environmental Laboratory Group, Yankee Atomic Electric Company.
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VERMONT YANKEE .
NUCLEAR POWER C'ORPORATION HD 5, Box 169 Ferry Road. Brattleboro. VT 05301 ,,,,yyo y' ENGINEERING OFFICE 1671 WORCESTER ROAD
+ FRAMINGHAM, MASSACHUSETTS 01701
. TELEPHONE 617472-8100 April 30, 1987 FVY 87-47 United States Nuclear Regulatory Commission Rrgion I 631 Park Avenue King of Prussia, PA 19406 Attention: Regional Administrator R ference (a) License No. DPR-28 (Docket No. 50-271)
Subject:
Vermont Yankee Annual Radiological Environmental Surveillance Report
Dear Sir:
Enclosed please find one copy of the Annual Radiological Environmental Surveillance Ecport for Vermont Yankee Nuclear Power Station submitted in eccordance with Technical Specification 6.7.C.3. This report contains a cummary and analysis of the radiological environmental data collected for the eslendar year 1986.
Should you have any questions regarding this submittal, please contact us.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION 4 l -
R. W. Capstick Licensing Engineer RWC/sj Enclosure
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