ML20151T747
| ML20151T747 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1987 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20151T746 | List: |
| References | |
| NUDOCS 8804290143 | |
| Download: ML20151T747 (73) | |
Text
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VERMONT YANKEE NUCLEAR POWER COPPORATION ANNUAL RADIOLOGICAL ENVIR0bEENTAL SURVEILLANCE REPORT January - December 1987
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April 1988 Prepared By:
Yankee Atomic Electric Company Environmental Engineering Department 1671 Worcester Road Framingham, Massachusetts 01701
-- .. . A...
8804290143 880426 \
PDR ADOCK 05000271
.R DCD w w r,
i TABLE OF CONTENTS Page LIST OF TABLES.................................................... iii i LIST OF FIGURES................................................... iv
1.0 INTRODUCTION
...................................................... 1 2.0 ENV I RO NMENTAL S URV E I L LANC E P R0G R AM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.0
SUMMARY
OF 19E7 ENVlFONMENTAL DATA................................ 13 A. Air Particulate............................................... 15 B. Charcoal Filter............................................... 19 C- Milk................... ...................................... 21 D. Mixed Vegetation.............................................. 26 E. Si1 age........................................................ 30 F. Groundwater................................................... 33 G. River Water................................................... 37 H. Sediment...................................................... 41 I. Finfish....................................................... 44 J. Direct Radiation.............................................. 48 K. In Situ....................................................... 60 4.0 QUALITY ASSURANCE PR0 GRAM......................................... 62 5.0 LAND USE CENSUS................................................... 65 6.0
SUMMARY
........................................................... 67
7.0 REFERENCES
........................................................ 68 I
-ii-2896R/23.219
LIST OF TABLES Number Title Page 2.1 Radiological Environmental Surveillance Program............. 3 2.2 Radiological Environmental Surveillance Locations........... 4 2.3 Environmental Direct Radiation Monitoring Locations......... 5 3.1 Summary of Direct Radiation Measurements - 1987............. 50 3.2 Summary of In Situ Soil Analyses............................ 61 4.1 Intralaboratory cnd EPA Interlaboratory Results - 1987...... 64 5.1 198 7 Land Us e Cens us Re s ul t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 66 4
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- l LIST OF FIGURES Number Title Page 2.1 Environmental Radiological Monitoring Locations in Cicse 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 Plan *.................... 10 2.5 TLD Locations Within 5 Kilometers of Plant.................. 11 2.6 TLD Locations Greater than 5 Kilometers from Plant.......... 12 3.1 Gross-Beta Measurements of Air Particulate Filters.......... 16 3.2 Cesium-137 in M11k.......................................... 22 3.3 Strontium-90 in M11k........................................ 23 3.4 Cesium-137 in Mixed Grasses................................. 27 3.5 Gross-Beta Measurements of Ground Water..................... 34 3.6 Gross-Beta Measurements of River Water...................... 38 3.7 Cesium-137 in Fish.......................................... 45 3.8 Exposare Rate at Indicator TLDs, DR 01-04, 06, 50........... 52 i
3.9 Exposure Rate at Site Boundary TLDs, DR 07-08, 41-44........ 53 3.10 Exposure Rate at Site Boundary TLDs, DR 45-49, 51........... 54 3.11 Exposure Rate at Inner Ring TLDs , DR 09-23 (odd) . . . . . . . . . . . . 55 3.12 Exposure Rate at Inner Ring TLDs , DR 25-39 (odd ). . . . . . . . . . . . 56 3.13 Exposure Rate at Outer Ring TLDs , DR 10-26 (even) . . . . . . . . . . . 57 3.14 Exposure Rate Outer Ring TLDs , DR 26-40 (even) . . . . . . . . . . . . . . 58 3.15 Exposure Ra te at Cont rol ILD, DR 05. . . . . . . . . . . . . . . . . . . . . . . . . 59
-iv-2896R/23.219
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 I risk to the general public in the event of unanticipated or accidental releases of radioactive materiel.
During 1987, as in the past Aquatec. Inc., collected all of the aquatic environmental samples, while the Chemistry staff collected the bulk of the terrestrial environmental samples (including ground water) 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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2896R/23.219
2.0 ENVIRONMENTAL SURVEILIANCE PROGRAM In this section. Table 2.1 summarizes 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. Given in Table 2.3 are distances and directions relative to the center of the Turbine Building for all TLD locations. The sampling locations are shown on maps in Figures 2.1 through 2.3 and the TLD locations are shown on the maps in Figures 2.4 through 2.6.
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2896R/23.219
Table 2.1 l
Vermont Yankee Radiological Environmental Surveillance Program i Media Sampling Frequency Required Analyses j Air Particulate (AP) - Semimonthly (2) . Gross beta
- Quarterly Composite Gamma spectroscopy I
Charcoal Filter (CF) - Semimonthly (2) Iodine-131 Milk (TM) - Monthly (6) Gamma spectroscopy, ;
Iodine-131 Mixed Vegetation (TG) - Quarterly (1) Gamma spectroscopy Silage (TC) - Annually (3) Gamma spectroscopy ,
Groundwater (WG) - Quarterly Gamma spectroscopy, H-3 l t
River Water (WR) - Monthly (1) (5) Gamma spectroscopy
- Quarterly Composite H-3 i i
Sediment (SE) - Semiannually Gamma spectroscopy Finfirh (FH) - Semiannually (1) Gaima spectroscopy
)
Direct Radiation (DR) - Quarterly Integrated gamma dose (4) !
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l (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) Collected at harvest time in reasonable proximity to specified location; subject to availability.
(4) Outer ring TLDs - De-dose quarterly unless gaseour release LCO vas exceeded in period.
(5) Composite sample collected over month at downst .ocation.
(6) Semimonthly when milk animals are identified as . .ng on pasture.
2896R/23.219 k
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Tabte 2.2 Vermont Yankee Radiological Environmental Surveillance Locations Distance From Plant' Direction Station Code Stack From Plant l
(Media - Sta. Nq.} Station Descriptien 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 AP/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 Road 1 3.2 WNW AP/CF/TG-21 Spofford Lake, NH 2 16.1 NNE TM-11 Miller Farm 1 0.8 WNW TM-13 Newton Farm 1 5.1 SSE TM-14 Brown Farm 1 2.6 S TM-15 Coombs Farm 1 4.5 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 WR-21 Rt. 9 Bridge 2 12.8 Upriver
)
l FH-11 Vernon Pond 1 -- On-Site l FH-21 Rt. 9 Bridge 2 12.8 Upriver l
SE-11 Shoreline Downriver 1 0.8 On-Site SE-12 N. Storm Drain Outfall 1 0.15 On-Site i
TC-11 Miller Farm 1 0.8 WNW TC-13 Newton Farm 1 5.1 SSE TC-14 Brown Farm 1 2.6 S TC-15 Coombs Farm 1 4.5 NW TC-16 Tall Oaks Farm 1 4.7 -
WNW TC-21 Moore Farm 2 15.9 N 1
a 1 = Indicator Station; 2 = Control Station.
2896R/23.219
Table 2.3 Vermont Yankee Environmental Direction Radiation Monitoring Locations Distance Direction From Center From of Turbine Center
' Station Code Building of Turbine (Media - Sta. No.) Station Description Zone * (km) Building DR-1 River Station No. 3.3 I 1.6 SSE DR-2 N. Hinsdale, NH I 3.9 NNW DR-3 Hinsdale Substation I 3.0 E DR-4 Northfield, MA I 11.0 SSE DR-5 Spof ford Lake, NH 0 16.3 NNE DR-6 Vernon School I 0.46 WSW DR-7 Site Boundary SB 0.27 W DR-8 Site Boundary SB 0.25 SW DR-9 Inner Ring I 2.1 N DR-10 Outer Ring 0 4.6 N DR-11 Inner Ring I 2.0 NNE DR-12 Outer Ring 0 3.6 NNE DR-13 Inner Ring I 1.4 NE DR-14 Outer Ring 0 4.3 NE DR-15 Inner Ring I 1.4 ENE DR-16 Outer Ring 0 2.9 ENE DR-17 Inner Ring I 1.2 E DR-18 Outer Ring 0 3.0 E DR-19 Inner Ring I 3.5 ESE DR-20 Outer Ring 0 5.3 ESE DR-21 Inner Ring I 1.8 SE DR-22 Outer Ring 0 3.2 SE DR-23 Inner Ring I 1.8 SSE LR-24 Outer Ring 0 3.9 SSE DR-25 Inner Ring I 2.0 S DR-26 Outer Ring 0 3.7 S DR-27 Inner Ring I 1.0 SSW DR-28 Outer Ring 0 2.2 SSW DR-29 Inner Ring I 0.7 WSW DR-30 Outer Ring 0 2.3 SW DR-31 Inner Ring I 0.8 W DR-32 Outer Ring 0 5.0 WSW DR-33 Inner Ring I 0.9 WNW DR-34 Outer Ring 0 4.9 W DR-35 Inner Ring I 1.4 WNW DR-36 Outer Ring 0 4.7 WNW 2896R/23.219
Table 2.3 (Continued)
Vermont Yankee Environmental Direction Radiation Monitoring Locations Distatice Direction From Center From of Turbine Center
[ Station Code Building of Turbine l (Media - Sta. No.) Station Description Zone * (km) Building l
l DR-37 Inner Ring I 3.0 NW l DR-38 Outer Ring 0 7.7 NW j DR-39 Inner Ring I 3.2 NNW l DR-40 Outer Ring 0 5.8 NNW DR-41 Site Boundary SB 0.38 SSW DR-42 Site Boundary SB 0.60 S DR-43 Site Boundary SB 0.42 SSE DR-44 Site Boundary SB 0.21 SE DR-45 Site Boundary SB 0.12 NE DR-46 Site Boundary SB 0.29 NNW DR-47 Site Boundary SB 0.51 NNW DR-48 Site Boundary SB 0.82 NW DR-49 Site Boundary SB 0.27 WNW DR-50 Governor Hunt House I 0.34 SSW DR-51 Site Boundary SB 0.27 W I = Inner Ring; O = Outer Ring; SB = Site Boundary.
2896R/23.219
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Figure 2.5 TLD Locations within 5 Kilomet6rt of Plant
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3.0
SUMMARY
OF 1987 ENVIRONMENTAL DATA The following pages summarize the analytical results of all the I
environmental samples which were collected during 1987. Each environmental media category is presented as a separate subsection. A discussion of the sc.mpling program and results is followed by a table which summarizes the year's data for each category. The tables, for all media but Direct Rtdiation, were generated by the computer program, ERMAP. At the top of each tchie, ERMAP lists the units of measurement for each medium. The left hand column contains the radionuclide which is being reported, total number of enalyses of that radionuclide, and the number of measurements which exceeds ten times the yearly average of control measurements. The latter are classified as "non-routine" measurements. The next column lists the Lower Limit of Detection (LLD) for those radionuclides which have detection ecpability 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 Vernent Yankee are called "indicator" or "Zone 1" stations. Discant stations, which are beyond plant influence are called "Control" or "Zone 2" stations. Direct radiation (TLD) monitoring locations are subdivided into site boundary, inner ring, and outer ring (emergency response) stations.
ERMAP calculates a set of statistical parameters for each radionuclide. This set of statistical parameters includes separate analyses 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 of data, ERMAP calculatest o The mean value of all concentrations, o The standard error of the mean.
o The lowest and highest concentration.
2896R/23.219 I
3.0
SUMMARY
OF 1987 EhTIR0hHENTAL DATA The following pages summarize the analytical results of all the environmental samples which were collected during 1987. Each environmental media category is presented as a separate subsection. A discussion of the sampling program and results is followed by a table which summarizes the ysar's data for each category. The tables, for all media but Direct
-Acdiation, were generated by the computer program, ERMAP. At the top of each tcble, ERMAP lists the units of measurement for each medium. The left hand column contains the radionuclide which is being reported, total number of enalyses of that radionuclide, and the number of measurements which exceeds ten times the yearly average of control measurements. The latter are classified as "non-routine" measurements. The next column lists the Lower Limit of Detection (LLD) for those radionuclides which have detection capability 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 subdivided into site boundary, inner ring, and outer ring (emergency response) stations.
ERMAP calculates a set of statistical parameters for each radionuclide. This set of statistical parameters includes separate analyses j 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 of data, ERMAP calculates:
o The mean value of all concentrations.
o The s'andard error of the mean.
o The lowest and highest concentration.
2896R/23.219
}
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 single 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 I statistics), and not the propagation of all possible uncertainties in the analytical procedure.
Pursuant to Technical Specification Table 4.9.3 (Footnote f), any concentration 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 is reported in the tables of this section, values less than the a posteriori LLD for the analysis are reported as zero.
2896R/23.219
A) Air Particulate Air monitoring ctations 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 daughter products. Quarterly composite air filters from each location are analyzed for gamma emitting radionuclides.
Gross-beta counts (Figure 3.1) showed random fluctuation throughout 1987 at indicator stations and controls, thereby indicating that any plant contribution was negligible.
The increase in gross-beta measurements during May and June of 1986 can be attributed to fallout from the Chernobyl accident and is discussed in Reference 1. A pump malfunction and a loss of power may have caused the high concentrations seen in Figure 3.1 at Station AP-11 in June 1986 and at Station AP-21 in November 1986.
This is discussed more fully in Reference 1. Naturally-occurring K-40 and Be-7 were also detected in many samples.
4; W.
2896R/23.219
FIGURE 3.1 GROSS BETA MERSUREMENTS OF RIR PARTICULRTE FILTERS VERMONT YANKEE NUCLERR POWER STATION, VERNON, VT D.60 0.55-O - AP-11, RIVER STATION NO. 3.3 a.m - O - RP-12, N. HINSDRLE, NH A - RP-13, HINSDALE SUBSTATION i
+ - AP-14, NORTHFIELD, MR o.45 - O X - RP-15, TYLER HILL RORD o - RP-21, SPDFFORD LRKE CONTROL 5 c.+c- n
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JAN ITB tt9R APR MAY JUN JUL HUG SEP DCT NOV DEC Jf!N 1987 FEB MflR flPR tt9Y JUN JUL flUG SEP OCT t.TIV 1986
E)WIRCetENTAL RADIOLOGICAL PR0mAM 9MnRY VUVO(T YM6EE N. CLEAR PWER STATION. ERNW. VT JANY - IECMER 1987 EDILN: AIRPART!CtLATE WITSt K!/QJ. M INDICATM STATIONS STATION WITH H10EST EM O WTROL STAT! W S euennumutu usueenenneneeenne euetintunne PCIONUCLl[ES EAN EAN EM STA. RMCC RANGE (NO AMLYSES) REQUIRED RANT NO. CETECTE0e* NO. NO. LETECTEDu 10.IETECTEDee (NON-ROUTIE)' LLD m-B (162) .0: ( 2.01 .1)E -2 13 ( 2.1 t .1)E -2 ( 2.0 t .1)E -2
( 0) ( .0 - 4.0)E -2 ( t.3 - 3.1)E -2 ( l.1 - 3.5)E -2
- (133/135)* et 27/ 27)e et 27/ 27)e K-7 ( 24) ( 5.4t .3)E -2 14 ( 5.8 t .7)E -2 ( 5.6 i .8)E -2
( 0) ( 3.2 - 7.8)E -2 ( 5.0 - 7.8)E -2 ( 3.8 - 7.3)E -2 et 20/ 20)', et 4/ 4)e *( 4/ 4)*
l E EQUAL ( .0 t .0)E 0 f K-40 ( 24) ( .0t .0)E O
( 0)
- ( 0/ 20)* et 0/ 4)*
IW-54 ( 24) ( .0t .0)E 0 E EQUAL ( .0 t .01E O l
( ( 0)
- ( 0/ 20)e *( 0/ 4)e f
CO-58 ( 24) ( .01 .0)E O ALL EQU4. ( .0 t .0)E O l ( 0)
I et 0/ 20), et 0/ 4)e FE-59 ( 24) ( . 0.t .0)E O E EQUN. ( .0 t .0)E 0 i ( 0)
- ( 0/ 20)* *( 0/ Alt CD-60 ( 24) ( .0t .0)E O E EQu't ( .0 t .0)E 0
( 0)
- ( 0/ 20)e et 0/ 4)e IN-65 ( 24) ( .0t .0)E O E E0% ( .0 t .0)E O
( 0)
- ( 0/ 20!* el 0/ 4)*
ZR-95 ( 24) ( .0t .0)E 0 E EQUAL ( .0 t .0)E 0
( 0)
- ( 0/ 20)* *( 0/ 4)*
l e N0HOUTIE REFIRS TO M NMER CF SEPARATE EASLPDENTS %CH ERE OREATER THAN TD (10) TIES M AERAGE BACK@0LDO FOR M KR100 0F TE REKRT.
n M FRACTION OF S4ftE AMLYES Y!ELDING CETECTABLE EA$lRD0fiS (I.E. >A MISTERIORI LLD) IS INDICATED WITH et le.
l
ENVIRCN1ENTfL RADIOLOGICAL FRYFM S(MWN
\UeDiT YWIE ffJCIIAR PWER STATION, \D$N, 47 JMAY - DECDEER 1997 ED!lM: AIRPARTICtLATE LN!TS Ft!/CU. M
!@!CATm STATIONS STATION WITH HIGEST EM (CETROL STATICNS 1 nusununnus ssninununususssu unnusunsu RADIONJQ.!IES EM EM EM STA. RMCE PANCE (W. MALYSES) RE0VIFED P#4.1E (D-ROVilE)' LLD N). [ETECTEDet NO. NO. IETECTED++ W. CETECTEDee AG-110M( 24) ( .0t .0)E 0 ALL EU A ( .0 t .0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)'
RU-103 ( 24) ( .0t .0)E O (LL EQlR ( .0 t .0)E O
( 0)
- ( 0/ 20)* a( 0/ 4)*
RU-106 ( 24) ( .02 .0)E O ALL ECUAL ( .0 t .0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)*
CS-134 ( 24) .05 ( .01 .0)E 0 E EUA ( .0 t .0)E O l ( 0) et 0/ 20!* e( 0/ 4)*
C5-137 ( 24) .06 ( .0t .0)E O ALL EU A ( .0 t .0)E O
( 0)
I et 0/ 20)* et 0/ 4)*
!A 1M' 24) ( .01 .0)E O ftL EUA ( .0 t .0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)*
CE-141 ( 24) ( . 01 .0)E O ILL EUA ( .0 t .0)E O
( 0)
- ( 0/ 20)e et 0/ 4)e CE-144 ( 24) ( .01 .0)E O ILL EQU4. ( .0 t .0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)*
TH-232 ( 24) ( .0t .0)E 0 ftL EUA ( .0 t .0)E 0
( 0)
+( 0/ 20)* e( 0/ 4)*
- N]N-ROUT!E REFERS TO TE NJMRER OF SEPAFATE EASLFfENTS *!CH EFE GEATER THAN TEN (10) TIES TE A\GACE EV&@0LHD FOR TE FERIOD CF TE PEPORT.
B) pharcoal 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 I Technical Specifications). Five of these are indicators and one is a control. Charcoal filters from the air sampling stations were l
collected and analyzed semimonthly for I-131 activity.
J During 1987, no I-131 was detected on charcoal filters.
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l l, 2896R/23.219 s .. .. . .
ENV!KrtENTAL PADICLOGICAL FROCRAM SLN%RY WKNT YtMIE Maite FTWER STATICN. tDKW, VT JWIARY - DEEEER 1967 MEDIl5: CW#at FILTER LNITS PC!/CU. M
!NDICATC6 STATICN3 STATICN WITH HIGEST EAN CCHTRCL STATICH3 estesete+++eesette esteeseeeeeee+eeeeeeeeeee e&vesteese***eet RADICNR![ES EM EAN &
( W. (WLYSES) FEQUIRED PME STA. RME PME W). 10. CETECTELee NO. DETECTEDee (NON-f0JTIT)' LLD W. CETECTEDee 1-131 (162) .0/ ( .0t .0)E O ALL EQlR. ( .0 t .0)E O
( 0) et 0/135)e et 0/ 271e e KH-KUTIE REFEFS TO M NUMBER OF SEP/ FATE KARFDENTS WHICN KFE CFEATER THAN TEN (10) TITS M A'4 RACE EntTCRCtND FCR M FER100 CF M FEPORT.
ee M FFACTim 0F S/tFtf t#4YSES Y!ELDIE CETECTABLE EAstFEENTS (1.E. A PCGTERIORI LLD) IS INDICATED WITH *( le.
l 1
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 Specit'1 cation requirement). Semi-monthly sampling was done at Stations TM-14. D1-16, and 21-21 when the cows were on pasture.
Detectable concentrations of Cs-137 and Sr-90 were measured in milk samples submitted from the indicator and control locations. As shown in Figures 3.2 and 3.3, concentrations were similar to those detected in previous yeara. The detected levels are consistent with thoss measured in cow milk at other New England locations.
Such levels have been well documented and tre attributed to fallout from nuclear weapons tests, although Cs-137 levels after May 1986 were elevated somewhat due to Chernobyl-related fallout.
Differences between dairy fares can be attributed to differences in feeding practices (i.e., what the cow eats).
Cesium-134 was detected in the winter and spring samples (five samples total) at Station n!-14. Since the cows are fed only j stored feed during this time, and since Cs-134 was detected in milk and other environmental media throughout the northeastern U.S. )
following the 1986 Chernobyl accident, it can be said that the i
Cs-134 in milk was due to contaminated feed from the Chernobyl I fallout.
In addition to these radionuclides, naturally occurring K-40 was detected in all samples.
k 2896R/23.219
FIGURE 3.2 CESIUM-137 IN MILK VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT w
28-O - TM-11, MILLER FARM 24- O - TM-13, NEHTON FARM A - TM-14' BROWN FARM 22- * +
X -- TM-16 TM-15', COOMBS TALL DAKS FARM FARM o - TM-21, MOORE FARM g 20-3 is-u R 16-0 14-x b 12-8 E io- ,
^
8-b -
A ,
N[$
[N b O D 1981 1982
~
l bJ OD MMJ 0D NMJ'0D NMJ 1983 th k 13 h OD MMJ 1984 1985 kfIh OD MHJ Od~MMJ 1986 1987 0 1980
FIGURE 3.3 STRONTIUM-90 IN MILK VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT 8
7-0 - TM-11, MILLER FARM o - TM-13, NEWTON FARM A - TM-14, BROWN FARM 6' + - TM-15, COOMBS FRRM j X - TM-16, TRLL ORKS FARM '
o - TM-21, MOORE FRRM g I 5 5- l B #
I e G U' s /
- o m
U N
s 5 #
3- f A 4 !
j 1-l 4 '
IV I 'II I 'II IV' I II IV I 'II IV I II IV I ' I I' 'IV'I II1985 'I IY II 1986 1987 IV 1990 1981 1982 1983 1984 l
EWIRONENTAL RAD 10LOGICf4. F90mM 9M%RY
'4RfGT YAf4EE N.ELEM POER STATION E1)N. VT l JANUARY - DECD GER 1987 EDllM: MILK LMITS: PCI/KG INDICATOR STATIONS STATION WITH HIGEST M CONTROL STATIONS neun m n'unt Mun+wu****nn**u nunnensun l j RADIONUCLIDES EAN EM EM l STA. RANE RANGE (NO. ANAi.YSES) EQU! FED RAEE NO. DETECTED ** W. W. DETECTED ** NO. DETECTED n (NON-R0llTINE)' LLD
, SR-89 ( 24) ( .0 .0)E O ALL EQUAL ( .0 t .01E 0 l ( 0)
- ( 0/ 20)e it 0/ 4)*
SR-90 ( 24) ( 2.0t .2)E O 14 ( 3.2 * .2)E 0 ( 2.2 t .1)E 0
( 0) ( .0 - 3.9)E O ( 2.8 - 3.9)E O ( 2.1 - 2.4)E O
- ( 20/ 20)* *( 4/ 4)* *( 4/ 4)*
BE-7 ( 90) ( .0f .0)E O ALL EQUfL ( .0 t .0)E 0
( 0)
- ( 0/ 72)* *( 0/ 18)*
CC-40 ( 90) ( l.4t .0)E 3 15 ( l.4 t .0)E 3 ( l.4 i .0)E 3
( 0) ( 1.2 - 1.6)E 3 ( l.3 - 1.4)E 3 ( 1.3 - 1.5)E 3
- ( 72/ 72)* *( 12/ 12)* *( 18/ 18)*
l9i-54 ( 90) ( . Cr. 0)E O In EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 72)* *( 0/ 18)*
CO-58 ( X: ( .0t .0)E O ALL EQlR. ( .0 t .01E O
( 0)
- ( 0/ 72)* *( 0/ 18)*
FE-59 ( 90) ( .0f .0)E O #LL EOUAL ( .0 t .01E 0
( 0)
- ( 0/ 72)* *( 0/ 18)*
CO-60 ( 90) ( .0f .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 72)* *( 0/ 18)*
ZM-65 ( 90) ( .0t .0)E 0 ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 72)* *( 0/ 18)*
- NON-f0JTIE RETERS TO M NJ9ER OF SEPMATE EASmEENTS lei!CH WERE OREATER T)%N TEN (10) TIES M AYERAGE BACX0FRND FM M PERIOD CF M REPORT.
n M FRACTICH CF S/tfti APMLYSES Y!ELDIE ETECTABLE EASLRDOTS (1.E. >A KGTERIORI LLD) IS INDICATED WITH *( )*.
E)NIR0ffENTAL RADIOLOGICN. PROGRAM SMY MONT YAEEE N.Q. EAR POER STATION, VERNE VT JMUARY - DECOSER 1987 ED!lMt MILK (NITS PCl/KO STATION WITH HIGEST EM CONTROL STATIONS 121CATOR STATIONS GMHHH44HHHf M44 M4MHilH444H4f M4 tM+MfMMMtH EAN EAN RADIONJCLIDES EAN (NO. NMLYES) RE9J1 RED RMCE STL RMI RANCE NO. NO. [ETECTEDH W. DETECTED ++
(NON-ROUTIEl' LLD 10. DETECTED ++
( .0t .0)E O ALL EQUAL ( .0 t .0)E 0 ZR-95 ( 90)
( 0)
- ( 0/ 72)+ *( 0/ 18)*
( .0t .0)E O ALL EQUAL ( .0 t .0)E O RlM 03 ( 90)
( 0)
- ( 0/ 72)* *( 0/ 18)*
( .0i .0)E O ALL EQUAL ( .0 t .0)E O RD-106 ( 9C'
( 0)
- ( 0/ 72)e *( 0/ 18)+
I-131 ( 90) 1. ( .0t .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 72)* *( 0/ 18)e CS-134 ( 90) 15. ( l.6f .7)E -1 14 ( 6.4 i 2.6)E -1 ( .0 i .0)E O
( 0) ( .0 - 3.2)E O ( .0 - 3.2)E O
- ( 5/ 72)* *( 5/ 18)e *( 0/ 18)*
CS-137 ( 90) 18. ( !.Si .3)E 0 14 ( 3.0 t .8)E O ( 6.9 i 3.2)E -1
( 3) ( .0 - 8.6)E O ( .0 - 8.6)E 0 ( .0 - 3.8)E O
- ( 24/ 72)* e( 9/ 18)* *( 4/ 18)e BA-140 ( 90) 15. ( .0i .0)E O ALL EQUAL ( .0 t .0)E O
( 0) '
- ( 0/ 72)e *( 0/ 18)*
-141 ( 90) ( .0t .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 72)* *( 0/ 18)e l CE-144 ( 90) ( .0t .0)E O ALL EQUN. ( .0 t .0)E 0
< 0)
- ( 0/ 72), *( 0/ 18)*
l l
- NON-WJTIE REFERS TO M NMER CF SEPAPATE EASURDENTS WICH WRE CREATER THAN TEN (10) TIES M AYERACE BACK0RCWD FOR M FERIOD OF M HJWT.
l
D) Mixed Vegetation l
Mixed vegetation samples were collected during May, June, August, and September.from the six air sampling locations. The vegetation consisted of various types of grasses and were' analyzed for gamma j
emitting nuclides. The results of the gamma' spectroscopy analysis.
( on each sample showed that, in addition to naturally occurring ~Be-7 and-K-40, Cs-137 was detected on one sample. The level detected in 1987 is less than those measured in previous years, which were l
shown to have originated from nuclear wecpons testing fallout.
1 I
i l
1 l.
I I
l 2896R/23.219 l l
J
FIGURE 3.4 CESIUM-137 IN MIXED GRASSES VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT
- l 0 - TG-11, RIVER STATION NO. 3.3 sm- O - TG-12, N. HINSDRLE NH A - TG-13, HINSDRLE SU$STRTION
+ - TG-14, NORTHFIELD, MR X - TG-15, TYLER HILL RORD o - TG-21, SPDFFORD LRKE (CONTROL) p 400--
as S
R x
Y
}m-u 8 .
E /
~ u- ;
I 200 -
\ d rsrnrwrrararrarwr; rnrrarwrnrwTa arre a 1984 1985 1986 1987 1980 1981 1982 1983
\
E)NIR0PtENTAL RADIOLOGICAL PROGRAM SlftMY WRMONT YAEEE REAR FOER STATION. VERHON, VT JMUARY - IECDGER 1997 lNITS: PCI/KO ET
) EDIW: MIIED WETATION STATION WITil HIGEST M CONTRQ. STATIONS IEICATOR STATIONS
( 1.1 i .5)E 3 ( 6.1 e 1.0)E 2 BE-7 ( 24) ( 7.21 1.6)E 2 14 8.9)E 2
( .0 - 2.5)E 3 ( 3.6 - 25.3)E 2 ( 3.9 -
( 0)
- ( 16/ 20)# *( 4/ 4)* *( 4/ 4ie
.3)E 3 15 ( 6.1 i .9)E 3 ( 5.8 t .7)E 3 K-40 ( 24) ( 5.ti 7.6)E 3
( 0) ( 3.1 - 8.9)E 3 ( 4.9 - 8.9)E 3 ( 4.5 -
- ( 20/ 20)* *( 4/ Os *( 4/ 4)*
.0i .0)E O AU. EQUAL ( .0 * .0)E 0 IH-54 i 24) (
( 0)
- ( 0/ 20)e *( 0/ 4)*
( .0f .0)E O ALL EQL#t. ( .0 f .0)E O CD-58 ( 24)
( 0)
- ( 0/ 20)* #( 0/ 4)*
( .02 .0)E O ALL EQU/L ( .0 t .0)E O FE-59 ( 24)
( 0)
- ( 0/ 20)* *( 0/ die
( .0 .0)E O ALL EQUAL ( .0 i .0)E O CO-60 ( 24)
( 0) a( 0/ 20)* e( 0/ 4)*
( .02 .0)E O ALL EQUfL ( .0 t .0)E O ZN-65 ( 24)
( 0) *( 0/ 4)e
- ( 0/ 20)*
( .0 t .0)E O IR-95 ( 24) ( .0i .0)E O ALL EQUAL
( 0)
- ( 0/ 20), *( 0/ 4),
l 1
( .02 .0)E O /LL EQt#L ( .0 t .0)E O !
A0-110M( 24)
( 0)
- ( 0/ 20)* *( 0/ 4)* l
- N0HOUTIE REHRS TO TE NJPEER CF SEPMATE EASWEENTS WHim ERE REATER f TIM TEN (10) TIES TE AWRAE BACXmotND FM TE ERIOD CF TE Femi.
- TIE FRACTICN CF SAfftE (WLYSES Y!ELDlW; CETECTAKE EASWEENTS
(!.E. >A POSTERIORI LLD) l$ INDICATED WITH *( le.
l l
E)NIR0PfENTAL RADIOLOGICAL PR0mM SUPf%RY VERPt)NT YAM (EE NJ(LEAR POER STAT 10N, WRNON. VT JANUARY - DEEMBER 1987 EDILM: MIIED VEETATION LMITS: PCl/KG ET ,
INDICATOR STATIONS STATION WITH HIGEST EAN CCNTRa. STATIONS wmummmu mem+memem+m** ::. . . . . . :nm RADION.lCt.! DES EM EM EM (NO. ANALYSES) REQUIRED RAN7 STA. RANCE RANGE (M)N-ROUTIE)' LLD NO. DETECTED H NO. NO. DETECTED ** 10. DETECTED **
RU-103 ( 24) ( .0f .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)*
RU-106 ( 24) ( .0t .0)E O ALL EQUN. ( .0 t .0)E O
( 0)
- ( 0/ 20)s *( 0/ 4)*
I-131 ( 24) 60. ( .0t .0)E O All. EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)*
CS-134 ( 24) 60. ( .0t .0)E O ALL EQUN. ( .0 t .0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)*
CS-137 ( 24) 80. ( 7.7t 7.7)E -1 15 ( 3.8 t 3.9)E O ( .0 t .0)E 0
( !) ( .0 - 1.5)E I ( .0 - 1.5)E 1
- ( 1/ 20)* *( 1/ 4)* *( 0/ 4)*
BA-140 ( 24) ( .0t .0)E 0 ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)*
CE-141 ( 24) ( .0t .0)E 0 ALL EQlAL ( .0 t .0)E O
> ( 0)
- ( 0/ 20)* *( 0/ 4)*
G-144 ( 24) ( .0t .0)E O ALL EQUAL ( .0 t .0)E 0
( 0)
- ( 0/ 20)* *( 0/ 4)*
Tif-232 ( 24) ( .0f .0)E O ALL EQuN. ( .0 t .0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)*
- NOPHiQlTIE REFERS TO M N.99ER OF SEPARATE EA9.REENTS WICH ERE 0 EATER THAN TEN (10) TIES M ASAE BACXOROLND FM M FER100 CF M REPET.
to M FRACTICN OF SMPLE ANALYSES YlEl. DING DETECTAILE EAStREENTS
(!.E. >A POSTERI M I LLD) IS INDICATED WiiH *( )*,
E) . Silage l
Silage-samples were collected at the milk sampling stations.during l October of 1987. Each sample was analyzed for gamma-emitting radionuclides and I-131. Local, fresh silage was not available for
[
collection during 1987 at Station TM-15. The owner of the farm purchases already-cured silage which is from a previous growing cycle.
i Naturally-occurring Be-7 and K-40 were detected in most silage samples. No man-made radionuclides were detected in any of them.
t 4
I
.i 2896R/23.219
ENVIRGtENTAL RADIOLOGICAL PROGRM S(M%RY VERMONT YAWEE MREAR F0WER STATION. WRNON VT JA N Y - DECD GER 1987 (NITS PCl/KG WET EDIUM: CATTLE FEED STATION WITH HIGEST M CONTRCL STATIONS INDICATOR STATIONS H+M4HtH4 HHH H+HHHHHHHH+HH+ *MMfM4H+MM RADIONLRIES M M EAN STA. RANI RAME
( W. ANALYSES) REQUIRED RAKE PC. NO. DETECTEDH 10. DETECTED **
(NON-ROJTIE)' LLD NO. ETECTEDH I
BE-7 ( 5) ( 5.3t 1.2)E 2 21 ( 7.5 i 1.1)E 2 ( 7.5 t 1.1)E 2
( 0)' ( 2.0 - 7.4)E 2
- ( 4/ 4)* *( 1/ 1)* *( 1/ 1)*
( 2.9t .3)E 3 16 ( 3.4 i .2)E 3 (l8t .2)E 3 K-40 ( 5)
( 0) ( 2.1 - 3.4)E 3
- ( 4/ 4)* *( 1/ 1)* *( 1/ 1)*
IW-54 ( 5) ( .0 .0)E O N0 M TA ( .0 t .0)E O
( 0) et 0/ 4)+ *( 0/ !)*
CO-53 ( 5) ( .0t .0)E O PC DATA ( .0 t .0)E O
( 0)
- ( 0/ 4)+ *( 0/ lie FE-59 ( 5) ( .0t .01E O NO DATA ( .0 t .0)E O
( 0)
- ( 0/ 4)+ *( 0/ 1)+
CO-60 ( 5) ( .0i .0)E O NO DATA ( .0 t .0)E O
( 0)
- ( 0/ 4)* *( 0/ 1)*
IN-65 ( 5) ( .0t .0)E 0 PC MTA ( .0 t .0)E O
( 0)
- ( 0/ 4)* *( 0/ Ile IR-95 ( 5) ( .0t .0)E O PC DATA ( .0 t .0)E 0
( 0) e( 0/ 4)e *( 0/ 1)*
A0-11Gi( 5) ( .0f .0)E O N0 M TA ( .0 t .0)E O
( 0)
- ( 0/ 4)* *( 0/ 1)e
- NDHOUTIE REFERS TO TE PUEER OF SEPfdATE EASLREENTS te(ICH WEFS GEATER T}%N TEN (10) TIES TE AVERACE ECCRO.ND FOR TE PERIOD OF TE REPORT.
- Tif FRACTION OF SAPFtf WLYES YlELDilo DETECTAR.E EA9.FEENTS (1.E. M POSTERIORI LLD) IS INDICATED WITH *( le.
ENVIROMNTAL RADIOLOGICAL PR0mM SlMWtY VERf0NT YAME MILEAR POER STATION, VERNON, VT JANUARY - DECEMER 1987 EDIUM: CATTLE FEED LNITS: FCI/KG ET INDICATOR STATICHS STATION WITH HIGEST EAN CONTROL STATIONS e m e m ***n m ** :. ::::. : m + m u m ** m m e m e m **
Pfd10NUCLIDES EAN EAN EAN I
STA. RANE RANCE (Kl. # MLYSES) EQUIRED RANE NO. DETECTEDH NO. DETECTED **
(N0rHt0lfi!E)' LLD NO. DETECTED ++ NO.
RU-103 ( 5) ( .0t .0)E O NO DATA ( .0 .0)E o
( 0)
- ( 0/ 4)* *( 0/ 1)*
RU-106 ( 5) ( .0t .0)E O NO DATA ( .0 t .0)E 0
( 0)
- ( 0/ 4)* *( 0/ 1)*
l-131 ( 5) 60. ( .0t .0)E O NO DATA ( .0 i .01E O
( 0)
- ( 0/ 4)* *( 0/ 1)*
CS-134 ( 5) 60. ( .0t .0)E O NO DATA ( .0 t .0)E O
( 0)
- ( 0/ 4)* *( 0/ 1)*
CS-137 ( 5) 80. ( .0i .0)E 0 NO DATA ( .0 t .0)E 0
( 0) t *( 0/ 4)* *( 0/ 1)*
BA-140 ( 5) ( .0t .0)E O 10 DATA ( .0 t .0)E O
( 0) l
) *( 0/ 4)* *( 0/ 1)*
CE-141 ( 5) ( .0t 0)E 0 10 DATA i .0 t .0)E O i ( 0)
- ( 0/ 4)* *( 0/ 1)*
CE-144 ( 5) ( .0t .0)E O NO DATA ( .0 t .0)E 0
( 0)
- ( 0/ 4)* *( 0/ 1)* ,
1 Tif-232 ( 5) ( .0t .0)E O NO DATA ( .0 t .0)E O l
( 0)
- ( 0/ 4)* *( 0/ lie l
l I
- N(N40UTIE REFERS TO M LOSER CF EPMATE EA9.REENTS WHICH ERE mEATER TIMN TEN (10) TIES M A',9AE BA70FD.ND FCR M F9100 CF M REKRT.
- M FRACTICN CF $#ftE #eLYSES YlELDIE MTECTAKE EASLREENTS
(!.E. X POSTERIORI LLD) IS INDICATED WITH *( )*.
l l
a F) Groundwater F 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.
i The gross-beta concentrations at WG-11 were elevated for the first
' three quarttrs of 1987. No explanation for these levels has been found, although a problem with low well-water levels may have caused raised levels of radon or its daughters. No gamma-emitting radionuclides, plant-related or naturally-occurring, were detected in groundwater during 1987.
?
l l
2896R/23.219 i
1
m FIGURE 3.5 GROSS-BETA MERSUREMENTS OF GROUND WRTER VERMONT YRNKEE NUCLERR POWER STATION, VERNON, VT 24 22-
- 0 - WG-11, PLflNT WELL o - WG-12, VERNON NURSING WELL A - WG-21, BRflTTLEBORD CC tCONTROL) 18-E Is-
!s 14-x b 12-b E
g 1.- p 8
E 8-6-
4-
\ .
2 g . 7,_ ,, . , . , , . . ,, . , , , . . . , . ,, . = . 3. , . s . . ,, . , . , , . . ,, .1 . s . . ,, . 3 . s _ ,,
1982 1983 1984 1985 1986 1987 1980 1981
E)NIROMOTAL RADIOLOGICAL PR0mM SLMmRY VERMCNT YAWEE NIdAR PCER STATION MON VT JA N Y - DECEMBER 1987 LMITS: PCl/KG EDILM: m0VHD WATER STATIM WITH HIGEST M CONTROL STAT!(MS IlOICATOR STATICHS unem**m+nn +n++nnuunnennen ++n**nunon' M EAN EAN RADIONUQ.10ES (NO. MALYSES) EQUIRED RANCE STA. RANI RANGE NO. DETECTEDn NO. NO. ETECTEDH NO. DETECTEDH (NON-ROUTIE)' 11D l
l E-B ( 12) 4. ( 4.3f 1.3)E O 11 ( 6.6 i 1.8)E O ( 7.5 i 4.3)E -1
( l.3 - 9.8)E O ( .0 - 1.6)E O
( 2) ( .0 - 9.8)E O
- ( 7/ 8)* *( 4/ 4)* *( 2/ 4)*
BE-7 ( 12) ( .0* .0)E O ALL EQUAL ( .0 t .0)E 0
( 0)
- ( 0/ 8)* *( 0/ 4)*
19 -54 ( 12) 15. ( .01 .0)E O ALL EQUN. ( .0 .0)E 0
( 0)
- ( 0/ 8)* *( 0/ 4)*
CO-58 ( 12) 15. ( .0* .0)E O ALL EQUN. ( .0 t .0)E O
( 0)
- ( 0/ 8)* *( 0/ 4)*
FE-59 ( 12) 30. ( .0f .0)E O E EQUN. ( .0 t .0)E O
( 0)
- ( 0/ 8)* *( 0/ 4)*
CD-60 ( 12) 15. ( .0f .0)E O E EQUAL ( .0 t .0)E O l
( 0)
- ( 0/ 8)* *( 0/ 4)*
ZW-65 ( 12) 30. ( .0t .0)E O E EQUAL ( .0 i .01E O
( 0)
- ( 0/ 8)* *( 0/ 4)*
ZR-95 ( 12) 15. ( .0t .0)E O E EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 8)* *( 0/ 4)*
l AG-110M( 12) ( .0t .0)E 0 E EQUN. ( .0 i .0)E O
( 0)
- ( 0/ 81* *( 0/ 4)*
- NCN-ROUTIE REFERS TO TE MMER CF SEP/(ATE EASWE)DTS Wi!CH WEE OREATER T)%N TEN (10) TIES TE AVEPACE BACKm0lND FOR TIE KRIOD 0F TE REPORT.
EWIR0ffENTAL RADIOLCGICAL PR0mAM SUNRY V9MONT YA*EE NJCX. EAR POWER STATION VERNW, VT JANUARY - DECE EER 1987 UNITS: PCI/KG E DIUM: ROUND WATER STATION WITH HIGEST EAN CONTROL STATION 3 INDICATOR STATIONS H Het He He H H ee HHHHetem**m* **m emHeWHHH EAN EAN EAN RADIOMXLIDES STA. RANGE RANGE (NO. ANALYSES) REQUIREI) RAMI NO. NO. DETECTEDH NO. DETECTED **
(HM-ROUTIE)' LLD NO. 0ETECTEDe*
R0-103 ( 12) ( .0f .0)E O ALL EQUAL ( .0 t .01E O s ( 0)
- ( 0/ 8)* *( 0/ 4)*
RU-106 ( 12) ( .0f .0)E O ALL EQU/L ( .0 t .0)E O
( 0)
- ( 0/ 8)* *( 0/ 4)*
.0f .0)E O E EQUAL ( .0 t .0)E 0 l-131 ( 12) (
( 0)
- ( 0/ 8)* *( 0/ 4)*
CS-134 ( 12) 15. ( .0f .0iE O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 8)* *( 0/ 4)*
CS-137 ( 12) 18. ( .02 .0)E 0 ALL EQU/L ( .0 t .0)E O
( 0)
- ( 0/ 8)* *( 0/ 4)*
BA-140 ( 12) 15. ( .0f .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 8)* *( 0/ 4)*
CE-141 ( 12) ( .0f .0)E O ALL EQUN. ( .0 i .0)E O
( 0)
- ( 0/ 8)* *( 0/ 4)*
CE-144 ( 12) ( .0s .0)E O E EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 8J *( 0/ 4)*
7 ( .0 t .0)E O H-3 ( 121 3000. ( .0f .0)E O ALL EQUAL
( 0)
- ( 0/ 8)* *( 0/ 4)*
- NON-ROUTINE REFERS TO TE M.MBER OF SEPMATE EA$lREENTS WilCH WERE @ EATER T)%N TEN (10) TIES TE AVERACE BACXCEIMD FM TE FERIOD OF TE REPORT.
. . - . = . . - .
G) River Water River water is analyzed monthly for gamma-emitting radionuclides and gross-beta (not. required by RETS). The monthly. samples are f
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 I ' Station WR-21.
Gross-beta radioactivity was detected in all samples during 1987.
I Considerable fluctuation in gross-beta levels at both the indicator and control'1ocations over the past nine years is evident in Figure 3.6. The mean value, however, 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 fue to plant operations.
t 1
}
)
I 2S96R/23.219
FIGURE 3.6 GROSS BETA MERSUREMENTS OF RIVER WATER VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT 8
1 7-6- 0 - WR-11 RIVER STATION NO. 3.3 o- WR-21$ ROUTE 9 BRIDGE (CONTROL)
= 0 n s- n 3
. R o n Y '4- 9 13 i n E 9 o q 8 1 a 83-
~ ,
t F n \l % o
" (
,b T{s 'f'fo v>sy}y
' n
- R g 1 ,
- 3 J. 1 .. J. .. J. L _ d1 .. 1
,3.g .g 3 . .g .g .g g . .g g . .g g .g 3 .g g . .g .g . .ggg .g 3 . g 3 3 7 g .3 . .g .g . .g .g .j . .g .
1981 1982 1983 1984 1985 1986 1987 1980 9
i E)N!ROMNTAL RADICLOGICAL PRONM SLNMRY VERMONT YAME NXLEAR POER STATION, VERNON. VT JfMJARY - DECOBER 1987 ED!lM: RIS WATER WITS: PCl/KG l
INDICATOR STATIONS STATION WITH HICEST M CMTRCL STATICNS tM4H4HHfMHH TMH 4H HMMMMHf HH 6MMMM44H4H RAD 10NX110ES M M N (NO. ANALYSES) REQUIRED RANCE STA. RNE RANCE NO. DETECTEDH NO. NO. 0ETECTEDH NO. DETECTEDH (h0N-ROUTINE)' LLD CR-B ( 24) 4. ( 2.2t .3)E o 11 ( 2.2 t .3)E 0 ( 2.1 t .2)E O
( 0) ( !.4 - 4.8)E O ( !.4 - 4.8)E O ( 1.5 - 2.9)E O I *( 12/ 12)+ *( 12/ 12)* *( 12/ 12)*
BE-7 ( 24) ( .01 .0)E O E EQUAL ( .0 t .01E O
( 0)
- ( 0/ 12)* *( 0/ 12)*
IW-54 ( 24) 15. ( .0t .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 12)* *( 0/ 12)*
CO-58 ( 24) 15. ( .0t .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 12)e et 0/12),
FE-59 ( 24) 30. ( .0t .0)E O E EQUN. ( .0 t .0)E O
( 0)
- ( 0/ 12)* *( 0/ 12)#
\
CO-60 ( 24) 15. ( .0t .0)E 0 ALL EQUAL ( .0 t .0)E O l
( 0)
- ( 0/ 12)* *( 0/ 12)e Df-65 ( 24) 30. ( .0t .0)E O ALL EQUAL ( .0 t .0)E O
( 0) et 0/ 12)* et 0/ 12)*
ZR-95 ( 24) 15. ( .0t .0)E O E EQUAL ( .0 t .0)E O
( 0) !
- ( 0/ 12)* *( 0/ 12)* l l
AG-110M(24) ( .0t .0)E O EL EQUE. ( .0 t .0)E O
( 0)
- ( 0/ 12)e *( 0/ 12)*
]
- NON-ROUTIE PIFERS TO TE NJPEER CF SEPMATE EASWEENTS WIDIIGE WEATER TliM TEN (10) TIES TE AEACE BACKmCt.ND FOR TE PERIOD OF TE REPmi.
H T)E FRACTICH CF 'M #@LY!ES YIELDIPO KTECTAILE EASWOOTS (1.E. >A POSTERI @ l LLD) IS INDICATED WITH #( )*.
i
EN/IENENTAL RADIOLOGICAL PROGRAM SLffWh' VERWT YAME NJCLEAR P06 STATION, EPG. VT JMUARY - ECO9ER 1987 (NITS! PCI/KO EDIUM: RI E WATER STATION WITH HIGEST M CONT 10. STATIONS INDICAim STATIONS n+nennuneen unenweuuneuenne wwweenenne RADIONUCLIDES EAN M EAN STA. R20E Rm0E (W. ANALYSES) REQUIRED RANE NO. ETECTEDet NO. W. DETECTEDH W. DETECTEDH (NON-ROUTIEl' LLD RU-103 ( 24) ( .0t .0)E O E EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 12)e *f 0/ 12)e RU-106 ( 24) ( .0f .0)E O ALL EQ M. ( .0 t .0)E O
( 0)
- ( 0/ 12)* *( 0/ 12)*
I-131 ( 24) ( .0f .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 12)e *( 0/ 12)*
CS-134 ( 24) 15. ( .0t .0)E O NJ. EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 12)e *( 0/ 12)e CS-137 ( 24) 18. ( .0t .0)E O ALL EDUAL ( .0 t .0)E O
( 0)
- ( 0/ 12)* *( 0/ 12)*
BA-140 ( 24) 15. ( .01 .0)E 0 ALL EQUN. ( .0 t .0)E O
( 0)
- ( 0/ 121e *( 0/ 12)e i
E-141 ( 24) ( .0t .0)E O ALL EQUAL ( .0 t .0)E O
( 0) l *( 0/ 12), *( 0/ 12)*
\
CE-144 ( 24) ( .0f .0)E O ALL EQUAL ( .0 t .0)E O )
( 0) !
- ( 0/ 12)* *( 0/ 121e it-3 ( 8) 3000. ( .0i .0)E 0 ALL EQUN. ( .0 t .0)E 0
( 0)
- ( 0/ 4)e *( 0/ 4)*
- NON-ROUTIE REFERS TO TE MMER OF SEPMATE EASUEENTS lei!Cd EE GEATER THAN TEN (10) TIES TE ABACE BACXm0JND FOR TE PERICO 0F TE EPORT.
H T)E FRACTICN OF SWRE WLY!ES YIELD 12 DETECTABLE EASlfDDITS (1.E. >A POSTERIORI LLD) IS INDICATED WITH et le. f l
l I
i l
c I l
r H) Sediment f
During 1987, sediment samples were collected from two locations in May and October. Each sample was analyzed for gamma-emitting ,
radionuclides. One grab sample was collected at Station SE-11 and fifteen grab samples at Station SE-12 during May. During October, one was again collected at SE-11 and nineteen at SE-12.
Cesium-137 was detected in all samples. As has been discussed in
, previous Vermont Yankee Radiological Environmental Surveillance Reports, this radioactivity has been due to nuclear weapons testing fallout. Since there were no liquid releases during 1982 through 1987, it can be concluded that the levels of Cs-137 in 1987 f
sediment samples were due n!.so to nuclear weapons testing fallout.
This is further supported by the fact that similar levels have in the past been detected at S:ation SE-21, a control station, and at control locations at other plants. Low levels of Co-60, as well as 2n-65 and Cs-134, have been detected in samples collected at Station 12 (N. Storm Drain Outfall). This subject was discussed in previous reports.
It should be noted here that the statistics given in the following table are heavily weighed toward Station SE-12, since 34 of the 36 samples were collected there. No Co-60, 2n-65, or Cs-134 was detected at Station SE-11.
Naturally-occurring Be-7, K-40, and Th-232 were also detected in ,
I many samples.
l I
1 i
2896R/23.219 f
1 1
I l
e EN/lRON9TAL PAD 10 LOGICAL PRO @/ft SufiARY VERKHT YIKEE MJCLEM POWER STATICHi VERNON, VT JMJARY - DECDEER 1987 EDIUM: SEDIENT WITS: PCI/KG DRY INDICAT E STATIONS STATICH WITH HIGEST EM C0NTROL STATIOC HfH+Hilif f H ef t HHf HH4HHHelHfHH ffH4H4fHittti RADIONJCLICES EAN EM EM STA. RANCE RANGE (NO ANALYSES) FE9JIFED RIME M). W. DETECTEDH NO. DETECTEDH (NCH-f0JTIE)' LLD NO. CETECTED++
BE-7 ( 36) ( l.81 .5)E 2 12 ( l.8 i .5)E 2 N) DATA
( 11) i .0 - 9.1)E 2 ( .0- 9.1)E 2
- ( 11/ 36)* *( 10/ 34)*
K-40 ( 36) ( 1.21 .0)E 4 12 ( !.2 i .0)E 4 NO DATA
( 0) ( 2.8 - 15.1)E 3 ( 8.8 - 15.1)E 3
- ( 36/ 36)+ *( 34/ 34)*
PN-54 ( 36) ( .0f .0)E O EEm N) DATA
( 0) et 0/ 36)*
CO-58 ( 36) ( .0t .0)E O It.L EM NO DATA
( 0)
- ( 0/ 36)*
FE-59 ( 36) ( .0 .0)E O ALL E9JL NO DATA
( 0)
- ( 0/ 36)e CO-60 ( 35) ( 6.21 1.4)E 1 12 ( 6.6 i 1.5)E 1 NO DATA
( 24) ( .0 - 4.4)E 2 ( .0 - 4.4)E 2
- ( 24/ 36)* *( 24/ 34)*
ZN-65 ( 36) ( 4.lt 4.1)E O 12 ( 4.3 i 4.3)E 0 NO DATA
( 0) ( .0 - 1.5)E 2 ( .0- 1.5)E 2
- ( 1/ 36)* +( 1/ 34)*
ZR-95 ( 36) ( .0f .0)E O (11 EM NO DATA
( 0)
- ( 0/ 36)*
k A0-Il0M( 36) ( .0t .0)E O ALL EQUAL M) DATA
( 0)
- ( 0/ 36)*
r
- KNMIE Ff7ERS TO M N.rEER CF SEPMATE E/.SWEENTS WilCH ERE @ EATER TWdi TEN (10) TIES M A'KPN.E BACXm0WD FOR M FER100 0F TV4 FEPWT.
H M FPACTION CF SAPFLE WLYSES YIELDING CETECTAELE EA970ENTS (1.E. >A FMTERIORI LLD) IS INDICATED WITH *( 16
E)N!ROMOTAL RADICLOGIC4. PROEM Slft%RY VEMNT Yf#:EE MJCLEAR POWER STAT 10N. VERKN, VT JANY - DEEMBER 1987 LNITS: PCl/KG DRY EDlW: SEDIENT I O!CATE STATIONS STATICN WITH HIGEST EM CCNTROL STATION 3 nmununeun utunnetteennuneu ++enen+neene EM EAN EAN RADIONUCt!IES (W. ANALYSES) REOJ! FED RANT STA. PME REE LLD W. DETECTEDet NO. NO. DETECTEDee NO. IETECTEDee (NON-ROUTIE)'
( .01 .0)E 0 N.L EQlML NO DATA RU-103 ( 36)
( 0)
- ( 0/ 36)e
( .0t .0)E O (LL EQUAL W MTA RU-1% ( 36)
( 0)
- ( 0/ 36)*
.0)E O ALL 60JAL M DATA l-131 ( 36) ( .01
( 0) et 0/ 36)*
CS-134 ( 36) 150. ( 6.11 6.1)E -1 12 ( 6.4 i 6.4)E -! K) DATA
( 1) ( .0 - 2.2)E 1 ( .0- 2.2)E 1
- ( 1/ 36)* *( 1/ 34)*
CS-137 ( 36) 100. ( 2.0t .1)E 2 12 ( 2.1 i .1)E 2 NO DATA
( 0) ( 5.3 - 38.7)E 1 ( 8.8 - 38.7)E 1
- ( 36/ 36)e *( 34/ 34)e BA-140 ( 36) ( .0t .0)E O M1 E7R. NO MTA
( 0)
- ( 0/ 36)*
E-141 ( 36) ( .0t .0)E O lLL E0JAL K) DATA I ( 0)
- ( 0/ 36)*
CE-144 ( 36) ( .01 .0)E O ALL EQUAL 2 DATA
( 0) et 0/ 36)*
I TH-232 ( 36) ( 7.9t .3)E 2 12 ( 8.1 i .3)E 2 NO DATA I ( 0) ( 3.7 - 12.0)E 2 ( 4.2 - 12.0)E 2
- ( 36/ 36)* et 34/ 34)*
I 1
- NCN-ROJTIE REFERS TO M M. Nest CF SEP/# ATE EASLEEENTS INICH lOf @ EATER THAN TEN (10) TIES M RVERAE B/&GROJND Fm M FERIOD OF M FmRT.
++ M FPACTICH CF SIMtE /# LYSES Y!ELDIE CETECTABLE EASJREENTS
(!.E. >A POSTERI M I LLD) IS INDICATED WITH *( )*.
4
- p. I)- Finfish Finfish samples were collected from two locations during May and again in October of 1987. Each sample consisted of mixed fresh water species, generally perch and bass. All were analyzed for gamma-emitting radionuclides. Cesium-137 was detected in both of the samples collected at indicator Station FH-11. The levels are consistent with well-documented environmental levels caused by nuclear wenpons testing fallout. The levels for the indicator station are similar to those of the control in 1986. No other radionuclides were detected except for naturally-occurring K-40.
l i
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.l l
l l
l l
)
2896R/23.219
FIGURE 3.7 CESIUM-137 IN FISH VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT 300 m- D - FH-11, VERNON POND (FH-12 BEFORE 1985)
, T 5 Bit D 2m-210 -
E E
g 180-U -
IT-l j l H s
g 120-a 90 d
$ /
30 - !
n n A N N bb N N $ b N N N $ N N N N ON EN b N N E b 0 O N N b ' N N ' N $~A 'b 1980 1981 1982 1983 1984 1985 1986 198/
ENVIR0ftaTtt RADIOLOGICtt PROGRM SUERY YEMNT YAWEE NJCLEAR POER STAT!m, VERNON, VT JARJARY - IECOGER 1987 E0!lm FlWISH LNITS: PCI/KG W T INDICATE STATIONS STATICH WITH HIGEST EM C W TROL STATICtG eunmunemee unnemmnemnem monummee RADIONUCLIDES EM EAN EAN (W. AWLYES) REQUIRED RAEE STA. RANCE RAEE (NCH-ROJTIEl' LLD PC. DETECTEDee NO. PC. DETECTEDee NO. DETECTEDee BE-7 ( 4) ( .0t .0)E O /LL EQUfL ( .0 .0)E O
( 0)
- ( 0/ 2)* e( 0/ 2)*
K-40 ( 4) ( 2.8t .1)E 3 21 ( 2.8 i .0)E 3 ( 2.8 t .0)E 3
( 0) ( 2.7 - 2.9)E 3 ( 2.8 - 2.9)E 3 ( 2.8 - 2.9)E 3
- ( 2/ 2), *( 2/ 2)* *( 2/ 2)*
PN-54 ( 4) 130. ( .0 .0)E 0 /LL EQU/L ( .0 t .0)E O
( 0)
- ( 0/ 2)e *( 0/ 2)*
CO-58 ( 4) 130. ( .0t .0)E O ALL E0#L ( .0 t .0)E O
( 0)
- ( 0/ 2)e *( 0/ 2)*
FE-59 ( 4) 260. ( .0i .0)E O (LL EQUfL ( .0 t .0)E O
( 0) e( 0/ 2)* *( 0/ 2)e CO-M ( 4) 130. ( .0t .0)E O (LL EQU/L ( .0 1 .0)E O
( 0) et 0/ 2)e *( 0/ 2)e IN-65 ( 4) 260. ( .0t .0)E O (LL EQUAL ( .0 t .0)E O
( 0) e( 0/ 2)e *( 0/ 2)*
ZR-95 ( 4) ( .0t .0)E O ALL EQUAL ( .0 * .0)E o
( 0)
- ( 0/ 2)e *( 0/ 2)e AG-110M( 4) ( .0t .0)E O ILL EQUN. ( .0 t .0)E O
( 0) st 0/ 2)* et Oi 2)e l
I e NOPHKUTIE EFEPS TO TE M.NER CF SEPARATE EA50FESTS Wi!CH ERE OFiATER THAN TEN (10) T!ES TT AYERACE BVX@CI.ND im TE PERIOD CF TM EPORT.
H TE FPACTICH CF SAPFLE f# LYES Y!ELDIO DETECTABli KASUREMNTS
(!.E. >A FOSTERICRI LLD) IS 10!CATED WITH e( le.
EWIR0tENTAL RADIOLOGICAL PRO @M SlmRY VETENT YAWIE NXLEAR POWER STATION, VERNCH, VT JtRIARY - DECDGER 1987 ED!lti: FI W ISH LNITS: PCI/KG ET IE!CATM STATICN3 STATIM WITH HIGEST EAN CONTROL STATIONS aueueentenesee unnenennenesteun ++++ ++e n t*
- e e n RADICNUCLIDES EM EM EAN W. M4.YSES) REQUIRED PANCE STA. RANCE RMOE (NCNfJUTIE)' LLD NO. ETECTEDet NO. NO. CETECTEDu NO. DETECTEDee RU-103 ( 4) ( .0t .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 2)e *( 0/ 2)e RU-106 ( 4) ( .0f .0)E O ALL EU A ( .0 t .0)E O
( 0)
- ( 0/ 2)e *( 0/ 2)*
l-131 ( 4) ( .01 .0)E O ALL EQUAL ( .0 i .0)E O
( 0)
- ( 0/ 2)e *( 0/ 2)e C$-134 ( 4) 130. ( .0f .0)E O ALL EQUAL ( .0 t .0)E O
( 0)
- ( 0/ 2)* *( 0/ 2)*
CS-137 ( 4) ;50. ( 2.St .2)E 1 11 ( 2.8 t .2)E 1 ( .0 t .0)E O
( 2) ( 2.6 - 3.0)E 1 ( 2.6 - 3.0)E 1
- ( 2/ 2)* et 2/ 2)e e( 0/ 21e f4-140 ( 4) ( .0 .0)E O ALL EQU/L ( .0 t .0)E O t 0)
- ( 0/ 2), *( 0/ 2)e E-141 ( 4) ( .0f .0)E O ALL F90AL ( .0 t .0)E O
( 0)
- ( 0/ 2)e *( 0/ 2)e E-lu ( 4) { .0 .0)E O All EQUAL ( .0 t .0)E O
( 0)
( 0/ 2)e *( 0/ 2)e TH-232 ( 4) ( .0t .0)E O /LL EQUfL ( .0 t .0)E O
( 0)
- ( 0/ 2)* *( 0/ 2)e e IOHOUTIE FEFERS TO TE NJGER OF SEP/PATE EASLFDENTS lei!CH WEFE CREATER TWN TEN (10) TIES TE AVERAri EC0R0lND FCR TE FGICO CF TE EKRT.
, u TE FRACTICN CF S/MtE MALYSES Y! ELD!W CETECTABLE EASLPIENTS (I.E. X POSTER!m! LLD) IS INDICATED WITH e( )*.
l
J) Direct Radiation Direct gamma radiation exposure wa's determined from the use of thermoluminescent dosimeters (TLDs). Two CaF :Mn TLDs were 2
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.
Summaries of the results for 1987 can be seen in the table below.
A complete station-by-station summary is given in Table 3.1.
In Table 3.1, the quarterly averages for inner ring stations (i.e.,
those locations that could possibly be influenced by plant operations) can be compared with those for the outer ring stations (i.e., those locations outside of the range of influence of the plant). Upon examining the quarterly exposure rates in the table, it is also evident that the inner ring exposare rates are not statistically different from those of the outer ring.
Upon examining Figure 3.10, it is evident that Station DR-45 has a higher average exposure rate than any other station. This is not surprising in that DR-45 is actually located on-site in close proximity to the plant (see Figure 2.4). Station DR-6 also had a high reading during the third quarter of 1987. Over-response of the TLDs is suspected. Panasonic TLDs from the Yankee Environmental Laboratory were co-located with the standard Victoreen during 1987. The Panasonic TLD at DR-6 during the third quarter gave a reading of 7.2 micro-R per hour.
Additionally, two TLD stations (DR-7 and DR-8) located between the plant and DR-6 had readings of 11.36 and 10.81 micro-R per hour, which is substantially lower than the 24.04 micro-R per hour at l
l DR-6.
2896R/23.219
1 Environmental Radiological Program Summary Vermont Yankee Nuclear Power Station, Vernon, Vermont January - December 1987 Madium:. Direct Radiation Units: Micro-R per Measurements (TLD) Hour Station With Inner Ring Highest Mean Guter Ring Mean Mean Mean Range Station Range Range (No. Meas.)* No. (No. Meas.)* (No. Meas.)*
12.2 41.4 12.1 7.9 - 24.0 45 26.2 - 66.8 6.4 - 17.0 (88) (4) (68)
- Most measurements based on readings from two TLDs.
4 4
\
2896R/23.219 f
T_able 3.1 I
Summary of Direct Radiation Measurements - 1987 i
V_er:ent Yankee QTR 3 QTR 4 Yearly Mean Location Type
- QTR 1 OTR 2 DR-1 I 11.78 12.77 10.94 12.84 12.08 DR-2 I 12.30 10.29 12.28 11.01 11.47 ,
DR-3 I 12.39 11.81 10.79 13.50 12.12 '
DR-4 I 11.91 11.41 10.59 13.22 11.78 DR-5 0 11.12 11.31 9.21 12.73 11.09 DR-6 I 7.86 9.79 24.04 14.74 14.11 DR-7 SB 11.12 13.60 11.36 14.98 12.77 DR-8 SB 11.97 13.67 10.81 14.33 12.70 DR-9 I 10.80 9.44 12.40 11.12 10.94 DR-10 0 11.19 13.46 12.08 6.41 10.79 I DR-11 I 10.72 11.82 10.32 9.32 10.55 DR-12 0 11.93 12.33 10.21 9.75 11.05 ;
DR-13 I 14.29 10.65 9.92 11.67 11.63 DR-14 0 14.06 13.60 11.09 10.96 12.43 I DR-15 I 10.77 14.36 10.58 12.59 12.08 ;
DR-16 0 14.53 11.14 13.86 12.61 13.04 :
DR-17 I 13.13 8.46 10.90- 18.34 12.71 l
- DR-!8 0 12.37 11.76 11.09 12.11 11.83 !
Dk-19 I 12.71 8.33 12.46 17.21 12.68 !
DR-20 0 12.01 10.87 13.60 9.72 11.78 DR-21 I 11.67 14.81 15.91 12.12 13.63 I DR-22 0 13.71 13.22 12.27 12.23 12.86 DR-23 I 9.67 11.09 13.57 11.50 11.46 i DR-24 0 14.75 8.14 12.00 9.17 11.02 i DR-25 I 11.77 12.05 17.51 12.94 13.57' DR-26 0 12.44 16.53 13.71 12.57 13.81 DR-27 I 13.41 13.06 12.52 13.49 13.12 ;
DR-28 0 10.50 11.90 12.43 10.44 11.32 i DR-29 I 11.57 13.10 17.20 11.31 13.30 l 12.16 ;
DR-30 0 11.01 10.98 15.68 10.97 DR-31 I 12.94 14.71 12.83 12.62 13.28 DR-32 0 17.01 12.19 13.47 13.89 14.14 DR-33 I 12.85 10.04 11.43 11.91 11.56 DR-34 0 11.82 10.82 12.72 12.99 12.09
. DR-35 I 10.77 10.06 10.89 13.17 11.22 4 DR-36 0 11.85 12 60 15.65 12.02 12.88 DR-37 I 12.16 1r 13.63 '9.86 12.10 DR-38 0 10.48 13.22 12.33 14.26 12.57 DR-39 1 11.74 13.32 10.40 12.64' 12.03 l DR-40 0 10.98 11.14 13.21 11.01 11.59 DR-41 SB 14.61 15.36 11.24 13.11 13.61 1 DR-42 SB 9.34 14.17 12.87 10.94 11.83 DR-43 SB 10.71 12.38 12.64 13.03 12.19 DR-44 SB 12.47 12.88 13.55 12.03 12.75 2896R/23.219
Table 3.1 (Continued)-
Summary of Direct Radiation Measurements - 1987 Vermont Yankee Location Type * -QTR 1 QTR 2 QTR 3 OTR 4 Y,early Mean DR-45 SB 26.18 27.82 44.96 66.78 41.43 DR-46 SB 11.48 17.32 17.58 16.08 15.62 DR-47 SB 12.10 10.71 13.86 16.47 13.29 DR-48 SB 9.61 11.36 14.28 13.05 12.08 DR-49 SB 10.41 10.49 11.28 10.52 10.68 DR-50 I 11.06 12.44 12.57 11.47 11.89 DR-51 SB 12.20 14.3F 12.55 11.49 12.66 QTR Mean 11.74 11.66 12.89 12.21 Inner Ring ! .37 1 3 89 1 2 28 3 23 09 QTR Mean 12.51 12.04 12.62 11.40 Outer Ring 1 79 1 1 75 1 2 70 1 21 94 QTR Mean 12.68 14.51 15.59 17.74 1 Site 1 48 4 1 62 4 19.43 115.56 Boundary J
- I = Inner Ring; O = Outer Ring; SB = Site Boundary.
2896R/23.219
FIGURE 3.8 EXPOSURE RATE AT INDICATOR TLDS, DR 01-04,06,50 VERMONT YANKEE NUCLEAR POWER STRTION, VERNON, VT ss so_
D - DR-01, RIVER STO. NO. 3.3 0 - DR-02, N. HINSDRLE. NH A - DR-03, HINSDALE SUBSTATION
+ - DR-04 NORTHFIELD, MR X - DR-06 VERf;0N SCHOOL 25- 0 - DR-50 GOVERNOR HUNT HOUSE 5
S 20-
$- b e e '
o 15--
.h Q /'
l k[< ,
IU~
'.// g r
\ ,
5-
'IV' I 'II' IV I'II' 'IV I'II'1984
~
IV I'II' 'IV' I 'II' 'IV' I 'II' IV I'!!' IV' I ~ II 1981 1982 1983 1985 1986 1987 1980
FIGURE 3.9 EXPOSURE RATE AT SITE BOUNORRY TLDS, DR 07-08,41-44 VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT 35 , -
3a -.
O - DR-07, W 0.27 KM O - DR-08, SW 0.25 KM A - DR-41, S 0.630 KM
+ - DR-42, S 0.920 Kd X - DR-43, SSE 0.760 XM 25- 0 - DR-44, SSE 0.480 KM 5
- e x.
h
?
- 1
@ 15- Y )
o -
s
-I /
10- ) (,
5-
'IV I II' 'IV' I 'II1986 'IV I 'II1987 'IV
' ' ' ^
'IV I 'II
' ^ '
I II' IV I II 'IV I II 'IV'I II 1984 1985 1980 1981 1982 1983
m FIGURE 3.10 EXPOSURE RATE AT SITE BOUNDARY TLDS, DR 45-49,51 VERMONT YANKEE NUCLEAR POWER SfRTION, VERNON, VT 100 90-D - DR-45, SE 0.315 KM o - DR-46, N 0.C27 KM 80- A - UR-47, NNW 0.160 KM
+ - DR-48, NH 0.395 KM Q X - DR-49, WNW 0.315 KM l
- .o _
60-6 m
- i. a. m_ j Y
E f u-r 30- ,
20-kWxa%: '
'Iy'I 'II' 'Iy'I'Ig
'gy'y'gy' 'gy'y'gg' 'gy i
I II' 'IV I'II1981 IV' I II
'I y'I'II' 1984 1985 1986 1987 19i 1982 1983 i
FIGURE 3.11 EXPOSURE RATE RT INNER RING TLDS, DR 09-23 (0D0 NUMBERS)
VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT ss O - DR-09, N 2.1 KM o - DR-11, NNE 2.0 KM ,
m_
A - DR-13, NE 1.4 KM
+ - DR-15, ENE 1.4 KM X - DR-17, E 1.2 KM o - DR-19, ESE 3.5 KM v - DR-21, SE 1.8 KM 25- G - DR-23, SSE 1.8 KM E z_
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FIGURE 3.12 EXPOSURE RATE AT INNER RING TLDS, DR 25-39 (DDD NUMBERS)
VERMDNT YANKEE NUCLERR POWER STRTION, VERNDN, VI ss 0 - DR-25, S 2.0 KM SSW 1.0 KM o
A -- DR-27, DR-29,WSW 0.7 KM
- + - DR-31, W 0.8 KH X - DR-33, WNW 0.9 KM o - DR-35, WN4 1.4 KM V - DR-37, NW 3.0 KM s_ a - DR-39, NNW 3.2 KM 5
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FIGURE 3.13 EXPOSURE RATE AT GUTER RING TLDS, DR 10-24 (EVEN NUMBERS)
VERMONT YRNKEE NUCLEAR POWER STATION, VERNON, VT z
O - DR-10, N 4.6 KM O - DR-12, NNE 3.6 KM m_
A - DR-14, NE 4.3 KM
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X - DR-18, E 3.D KM o - DR-20, ESE 5.3 KM v - DR-22, SE 3.2 KM 25- D2 - DR-24, SSE 3.9 KM 9 20-5 5 a.
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FIGURE 3.14 EXPOSURE RATE AT OUTER RING TLDS, DR 26-40 (EVEN NUMBERS)
VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT ss 0 - DR-26, S 3.7 KM o - DR-28, SSH 2.2 KM 30- A - DR-30, SW 2.3 KM
+ - DR-32, WSW 5.0 KM X - DR-34, W 4.9 KM o - DR-36, WNW 4.7 KM v - DR-38, NW 7.7 KH 25- 52 - DR-40, NNW 5.8 KM 20-
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K) In Situ In situ gamma spectrometry analyses were performed at nine locations from September 15 to 17, 1987. Gamma spectrometry measurements were performed by the Yankee Atomic Environmental Laboratory (YAEL) using a high purity germanium detector and multi-channel analyzer. Measurements were also taken with a high pressure ionization chamber (HPIC) for assessment of total exposure rates. Soil core samples were obtained at six of these nine locations and analyzed at the YAEL for comparison to the in situ analyses.
The naturally-occurring radionuclides K-40 Th-32, and U-238 were the predominant gamma-emitters, as can be seen in Table 3.2.
These, along with Cs-137, were detected in all samples including controls. The Cs-137 levels are consistent with well-documented environmental levels, and can be attributed to fallout from atmospheric nuclear weapons tests, i
2896R/23.219
Table 3.2 .,
Sumunary of In Situ Soil Analyses Exposure Rate (pR/hr) i 1 Std. Dev. +
Location Cs-137 K-40 Th-232 U-238 Total
- HPIC North Hinsdale 0.1410.01 1.6210.05 1.6510.10 0.8420.04 7.8410.12 8.5710.39 Vernon Nursing Well 0.0910 01 1.6410.05 1.0910 07 0.8120.04 7.2213.10 8.0810.37 Hinsdale Substation 0.18 10.01 1.4910 05 1.9810.08 1.2110.05 8.4310.11 8.7910.48 l Nocthfield 0.06 10.01 1.5610.05 1.6110.08 1.2520.05 8.0710.11 8.1310.47 Tyler Hill 0.2520.01 2.0020.05 2.4010.09 1.2710.06 9.5110 12 9.3310.52 Hunt House 0.14+0.01 1.62+0.05 1.65+0.10 0.84+0.04 7.84+0.12 8.09+0.41 1 ,
i , Brattleboro C. C. 0.2810.01 1.4810.04 1.4010.07 1.0410.05 7.7910 09 7.8110.46 l =*
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' Spofford Lake 0.0810 01 2.0410.05 2.1910.09 0.9710.05 8.8710.11 8.9010.43 River Station 0.0410.01 1.6810.05 1.5410.08 0.9710.05 7.8210.11 7.9010.45 1
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- To' I of portable germanium system plus 3.59 pR/h cosmic contribution.
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2896R/23.219
4.0 QUALITY ASSURANCE PROGRAM Three separate Quality Assurance programs were performed during 1987 to ,
dtmonstrate 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 result = of the cross-check analysis fall outside of the control limit, an investigation'is made to determine the cause of the problem and corrective measures are taken.
1 YAEL maintains an intralaboratory quality control program to assure the validity and reliability of the data. This program includes quality control of laboratory equipment, use of reference standards for calibration, and enalysis 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 from five nuclear plants, including Vermont Yankee, 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 laboratory analyses.
EPA Interlaboratory and Intralaborgtory 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 eccuracy and precision for laboratory analyses in 1987 for intralaboratcry analyses, and EPA interlaboratory cross-check analyses. For accuracy, 61.7 and 87.4 percent of the results were within 5 and 10 percent of the known values, respectively, with 96.2 percent of all results falling within the laboratory criteria of 15 percent. For precision, 86.4 and 97.5 percent of the results were within 5 and 10 percent of the mean, respectively, with 99.6 percent of all results meeting the laboratory criteria of 15 percent.
2896R/23.219 ,
The results of the EPA Interlaboratory Comparison program, when considered apart from the remainder of the Quality Assurance program, were satisfactory in 1987. One-hundred and sixty-eight analyses were performed on air particulate' filters, food, milk, urine, and water. Based upon this sample analysis total,166 analyses (i.e., 99.07.) met the EPA's definition of mean value criteria. The sample analyses that did not meet the criteria were a Ru-106 analysis in a water sample and a gross beta analyeis, also in a water scmple. A recount of the beta samples yielded measurements that met the above criteria. (Details of this may be found in Reference 2.)
Blind Duplicate Program f
A total of 49 paired samples were submitted by the five participating plants for analysis during 1987. The data base used for the deplicate analyses consisted of paired measurements of 26 gamma eritting nuclides H-3, ;
Sr-89, Sr-90, low level I-131 and gross beta. A dual level criteria for agreement was established. If the paired measurements fall within 15 percent of their average value, then agreement between the measurements has bsen met. If the value falls outside of the i 15 percent, then a two standard deviation range (95 percent confidence level) is established for each of the '
analyses. If the ranges overlap, agreement is obtained.
One thousand two hundred and forty-two paired duplicate measurements !
I were analyzed for 1987. A total of 99.5 percent of all measurements fell within the established criteria discussed above. The six measurements that did not meet the criteria were measurements of Ag-110m in milk Mo-99 in milk, Fe-59 in ground water, Sb-124 in estuary water, Fe-59 in seawater, and Mo-99 in mussel bodies. In all of the above cases, the radionuclide in question was not detected in the sample and a three-standard deviation accept.ance criteria was met. The six duplicate measurements represent 0.5 percent of all the blind duplicate paired measurements made during 1987. No trend was evident with respect to repeated failings of measurements for the above radionuclides.
l 2896R/23.219 i'
Table 4.1 Intralaboratory and EPA Interlaboratory Results - 1987 Accuracy Total Number of Measurements 0 to 5% 0 to 10% 0 to 15%*
729 450 637 701 (61.7%) (87.4%) (96.2%)
Precision Total Number of Measurements 0 to 5% 0 to 10% 0 to 15%*
721 623 703 718 (86.4%) (97.5%) (99.6%)
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- This category also contains those samples having a verified zero )
concentration which were analyzed and found not to contain the isotope of i interest.
2896R/23.219
l 5.0 LAND USE CENSUS The Vermont Yankee Technical Specifications require that a Land Use Census be conducted annually between June 1 and October 1 of each year. The census identifies the location 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 nearest 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 sectors due to elevated releases from the plant stack. - Dosimetric analyses are then carried out to determine whether any identified milk animal represents a significantly butter milk sampling-1 location than those currently being used.
The 1987 Land Use Census at Vermont Yankee was carried out between the dates of June 1 and October 1, as required by Technical Specifications. .The identified locations can be found in Table 5.1. As_a result of the dosimetric comparisons, no changes were required or made in the milk sampling locations. ,
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2896R/23.219
Table 5.1 Vermont Yankee 1987 Land Use Census Results Nearest Residence Milk Animals Sector (km) km Cow or Goat 1.6 * --
N 1.6 * --
NNE NE 1.3 4.2 Goats ENE 1.0 --
E 1.0 2.4 Cows 2.8 * --
ESE 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 * --
- No milk animals found within 5 miles.
2896R/23.219
6.0
SUMMARY
During 1987, samples collected as a part of the radiological snvironmental mon!*oring program at Vermont Yankee showed detectable levels of man-made radionuci 's in cow milk, mixed vegetation, fish, and sediment. As reported in the pas. for sediment, low levels of Co-60, 2n-65, and Cs-134 were datected in the immediate vicinity of the North Storm Drain Outfall. The radioactivity from this drain has been detected only at this location. In all other cases, the low levels 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. The radiological environmental monitoring program has therefore demonstrated that plant operations have had no significant impact on the environment.
l 2896R/23.219
7.0 J.EFERENCES
- 1. Annual Radiological Environmental Surveillance Report, 1986, Vermont Yankee Nuclear Power Corporation.
- 2. YAEL Quarterly Status Report, April-June 1987. Environmental Laboratory Group, Yankee Atomic Electric Company.
- 3. YAEL Quarterly Status Report, October-December 1987 Environmental Laboratory Group, Yankee Atomic Electric Company.
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