ML20153B936
| ML20153B936 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/31/1987 |
| From: | Papanic G YANKEE ATOMIC ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| FYR-88-61, NUDOCS 8805060116 | |
| Download: ML20153B936 (72) | |
Text
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YANKEE ATOMIC ELECTRIC COMPANY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January - December 1987 April 1988 D
Prepared By: '
Yankee Atomic Electric Company Environmental Engineering Department 1671 Worcester Road Fra.ningham, Massachusetts 01701 i
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2918R/23.218 8805060116 871231 PDR ADOCK 05000029 R DCD
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TABLE OF CONTENTS Page LIST 0F-TABLES.................................................... iii f
l iv LIST OF FIGURES...................................................
1.0 INTRODUCTION
...................................................... 1
(
' - 2.0 ENVIRONMENTAL MONITORING PR0 GRAM.................................. 2 3.0 SUM 4ARY OF 1987 ENVIRONMENTAL DATA................................ 13 h
3.1 Air Particulate............................................. 15 3.2 Charcoal Filter............................................. 19 3.3 M11k........................................................ 21 3.4 Food Crop................................................... 25 3.5 Broad Leaf Vegetation....................................... 28 4
3.6 Maple Syrup................................................. 30 3.7 Groundwater................................................. 33 3.8 River Water................................................. 38 3.9 Sediment.................................................... 41 3.10 Finfish..................................................... 45 3.11 Direct Radiation............................................ 49 3.12 In Situ..................................................... 59 4.0 _ QUALITY ASSURANCE PR0 GRAM......................................... 61 1 64 5.0 LAND USE CENSUS...................................................
6.0
SUMMARY
........................................................... 66
7.0 REFERENCES
........................................................ 67 2918R/23.218
't LIST OF TABLES Number Title Page f 2.1 Yankee Atomic Radiological Environmental Monitoring L Program 3 2.2 Yankee Atomi.c Radiological Environmental Monitoring Locations 4 3.1 Summary of Direct Radiation Measurements - 1987 58 3.2 Sunmary of In Situ Soil Analyses 60 4.1 Intralaboratory and EPA Interlaboratory Results - 1987 62 5.1 1987 Land Use Census Results 65 i
-lii-2918R/23.218
A LIST OF FIGURES r
Title Page Number 2.1 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Airborne, Waterborne, and 6
Ingestion Pathways) f 2.2 Yankee Plant Madiological Environmental Monitor.1.ng Locations Within 12 Miles (Airborne, Waterborne, and 7
Ingestiot. Pathways)
( 2.3 Yankee Plant Radiological Environmental Monitoring Locations Outside 12 Miles (Airborne, Waterborne, and ,
8 d Ingestion Pathways)
N Yankee Plant Radiological Environmental Monitoring j 2.4 1 Locations at the Restricted Area Fence (Direct 9 %
Radiation Pathway) i 2.5 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Direct Radiation Pathway) 10 2.6 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Direct Radiation Pathway) 11 2.7 Yankee Plant Radiological Environmental Monitoring Locations Outside 12 Miles (Direct Radiation Pathway) 12 16 3.1 Gross-Beta Measurements of Air Particulate Filters 22 3.2 Cesium-137 in Milk Tritium in Sherman Spring Water (WG-12) 34 3.3 35 3.4 Gross Beta Measurements of Ground Water 42 3.5 Cesium-137 in Sediment 46 3.6 Cesium-137 in Fish 51 3.7 Exposure Rate at Indicator TLDs, GM 01-07 Exposure Rate at Indicator TLDs, GM 08-12, 40 52 3.8 Exposure Rate at Outer Ring TLDs, GM 24-31 53 3.9 54 3.10 Exposure Rate at Outer Ring TLDs, GM 32-39 Exposure Rate at Fenceline TLDs, GM 13-21 55 3.11 Exposure Rate at Control TLDs, GM 22-23 56 3.12
-iv-2918R/23.218
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1.0 INTRODUCTION
1
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The radiological environmental surveillance program at Yankee Atomic has been designed and ca ried out with specific objectives in mind. They are es follows:
- To provide en early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation f of the nuclear power station.
- To provide assurance to regulatory agencies and the public that the s'.ation's environmental impact is known and within anticipated limits.
- To verify the adequacy and proper functioning of station effluent controls and monitoring systema.
I
- To provide standby monitoring capability for rapid asse=sment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.
During 1987, the plant staff collected all environmental samples, including environmental thermoluminescent dosimeters (TLDs). All samples were sent to the Yankee Atomic Environmental Laboratory in k'estborough, Massachusetts for further processing and radionuclide analyols. TLDs were also sent to this laboratory for processing.
Tnis report is a summary of the findings of the Radiological Environmental Surveillance Program for 1987. It is being provided in compliance with plant Technical Specification 6.9.5.a.
2918R/23.218
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2.0 EhTIRONMENTAL MONITORING PROGRAM
.t.
In this section, Table 2.1 outlines the monitoring program as required f aby the plant Technical Specifications. Table 2.2'11sts the sampling stations L
and their specific locations (distances are measured from the center of the
. containment building). The sampling locations are shown on maps in Iigures 2.1-through 2.7. +
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2918R/23.218
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5 G Table 2.1 ,
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+ Yankee Atomic Radioltogical Environmental Monitoring Program s
Sampling Frequency Required Analyses
$ Media <
Air Particulate (AP) - Weekly Gross beta-
- - Quarterly Composite Ga n spectroscopy Charcoal Filter (CF) - Weekly I-131" Gamma spectroscopy, Milk IM) - Monthly; once per 1-131 2 weeks from June 1 to Nov. 1 Food Crop (TF) - Annually (Harvest) Gamma spectroscopy Broad Leaf Vegetation (TV) - Annually (Harvest) I-131
- Quarterly Gama spectroscopy.
Groundwe,ter (WG)
H-3 River Water (WR) - Monthly (Composite) Gross beta,
Gamma spectroscopy
- Quarterly Composite H-3
- Semiannually Gamma spectroscopy Sediment (SE)
- Seasonal or Gamma spectroscopy Finfish (FH)
Semiannually Direct Radiation (GM) - Quarterly De-dose only (Outer ring TLDs)
- Quarterly Integrated gamma (All other TLDs) dose a
$-I 2918R/23.218 h =. . . . . .. . . . . . . . . .
s Table 2.2 _
Yankee Atomic Radiological Environmental Monitoring Locations Distance From Plant Dir ee'. ion Station Code From Plant Station Description Zone * (km)
(, (Media - Sta. No.)
Observation Stand 1 0.5 NW AP/CF-11 Monroe Bridge 1 1.1 SW AP/CF-12 Rowe School 1 4.2 SE AP/CF-13 Harriman Station 1 3.2 N AP/CF-14 Williamstown, MA 2 22.2 W AP/CF-21 0.8 SW AP/CF-31** Furlon House 1 Heartwellville, VT 2 12.6 NNW AP/CF-32**
Readsboro, VT 1 6.1 N TM-12 Whitingham, VT 1 8.4 ENE TM-13 Williamstown, MA 2 21.0 WSW TM-21 Monroe Bridge 1 1.3 SW TF-11 Monroe, MA 1 1.9 WNW TF-13 Williamstown, MA 2 21.0 WSW f
TF-21 TV-11 Monroe Bridge 1 1.3 S'4 MS-31** Feadsboro, VT 1 6.1 h MS-42** Williamstown, MA 2 23.3 %SW WG-11 Plant Potable 1 On-Site --
WG-12 Sherman Spring 1 0.2 NW Bear Swamp Lower Res. 1 6.3 Downriver WR-ll Upriver Harriman Reservoir 2 10.1 WR-21 No. 4 Station 1 36.2 Downriver SE-11 Upriver Harriman Reservoir 2 10.1 SE- 21 FH-11 Sherman Pond 1 1.5 N Harriman Reservoir 2 10.1 Upriver FH-21 GM-1 Furlon House 1 0.8 SW GM-2 Observation Stand 1 0.5 NW 4.2 SE GM-3 Rowe School 1 GM-4 Harriman Station 1 3.2 N Monroe Eridge 1 1.1 SW GM-5 2918R/23.218
r Table 2.2 c
(Continued)
Yankee Atomic Radiological Environmental Monitoring Locations 4
Distance
}' From Plant Direction
. Station Code Station Description Zone * (km) From Plant (Media - Sta. No.)
GM-6 Readsboro Road Barrier 1 1.3 N GM-7 Whitingham Line 1 3.5 NE
[ GM-8 Monroe Hill Barrier 1 1.8 S h GM-9 Dunbar Brook 1 3.2 SW GM-10 Cross Road 1 3.5 E GM-11 Adams High Line 1 2.1 WNW GM-12 Readsboro, VT 1 5.5 NNW GM-13 Restricted Area Fence F 0.08 WSW
.GM-14 Restricted Area Fence F 0.11 WNW GM-15 Restricted Area Fence F 0.08 NNW GM-16 Restricted Area Fence f 0.13 NNE GM-17 Restricted Area Fence F 0.14 ENE 0.14 Restricted Area Fence F ESE GM-18 GM-19 Restricted Area Fence F 0.16 SE GM-20 Restricted Area Fence F 0.16 SSE GM-21 Restricted Area Fence F 0.11 SSW GM-22 Heartwellville, VT 2 12.6 NNW GM-23 Williamstown Substation 2 22.2 W GM-24 Harriman Dam 0 7.3 N GM-25 Whitingham, VT 0 7.7 NNE g GM-26 Sadoga Road 0 7.6 NE GM-27 Number 9 Road 0 7.6. ENE GM-28 Number 9 Road 0 6.0 E i GM-29 Route 8A 0 8.2 ESE f GM-30 Route 8A 0 9.4 SE GM-31 Legate Hill Road 0 7.6 SSE GM-32 Rowe Road 0 7.9 S
[ GM-33 Zoar Road 0 6.9 SSW 7
GM-34 Fife Brook Road 0 6.4 SW GM-35 Whitcomb Summit 0 8.6 WSW GM-36 Tilda Road 0 6.6 W GM-37 Turner Hill Road 0 6.7 WNW GM-38 West Hill Road 0 6.6 NW GM-39 Route 100 0 6.8 NNW GM-40 Readsboro Road 1 0.5 W
- 1 = Indicator Stations; 2 = Control Stations; O = Outer Ring Incident Response TLD; F = Fenceline.
C* Not required by Radiological Effluent Technical Specifications or Off-Site Dose Calculation Manual.
2918R/23.218 l
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.:[ PLANT
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5 t AP/CF-31 Monroe Bridge e tr/cF-12
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Figure 2.1 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Airborne, Waterborne and Ingestion Pathways)
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Q @ AP/CF-32 i
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@ AP/CF-14 Sho w n Pond VERMONT l~ ~ " g~ 8 MASSACHUSETT5 T F- 13 @'s 2_:^-
1 MONRDE BRIDCC ,_ Sgg 757 ,9c9537 35 yyg;;pg g, y g
i PLANT I
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@ WR-11
- HEATH
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4.4 49 4
4 CHARLEMON T 0 $
t 1 1 1 1 I t t SE-11 @
KILOMETERS SHELBURNE FALLS ,
Figure 2.2 Yankee Plant Radiological Environmental Monitoring Locations.
Within 12 Miles (Airborne, Waterborne and Ingestion Pathwayb)
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i BENN!NGTON e
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HEARTWELLVILLE n
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- WHITINGHAM k
\ READSBORO *
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r-- - - - - - -- __ __ __ __
PLANT MASSI NNR0E BRIDGE o A' ' g*
j W ' ,y WILLIAMSTOWN
- oat 8 - Rm
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, @ m-21 HEATH TF-21 4,$
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4 CHARLEMONT e
SHELBURNE FALLS y .
O S 10 15 20 t , i , l KILOMETERS PITTSFIELD
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1 Figure 2.3 Yankee Plant Radiological Environmental Monitoring Locations i Outside 12 Miles (Airborne, Waterborne and Ingestion Pathways) l
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l Figure 2.4 Yankee Plant Radiological Environmental Monitoring Locations at tbc Restricted Area Fence (Direct Radiation Pathway)
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@ GM 40 - g fs f _5
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GM-1 @ g Honroe Bridge -
~ -_ ~~ %nro ,
4; ' -
Ssf,, gggg S
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l Figure 2.5 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Direct Radiation Pathway)
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,-.=.-
HEARTWEllVI'lE _
-- ~~~
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- e GM-22 a
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= a
\ 4@r_ [ 1NGtJJi
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GM-39
\ BORO GM-12
- REA o GM-26
@GM-38 \
@GM-37 GM.n .
~~
G.M - 7
~
@y ~~
I l = [ MSSACHUSEf tS srr EN w W rt J# T 2.5 E
/
gg @GM-36 i El PLANT g GM-10 @GM-28 1
t___-._q
$M.3$' ~ GM v ROVE
@cM.29
@ GM-34 @
/
- HEATH
@cM.33
@GM-31
@GM-32 g '
9 et CHARLEMONT i , , , , I , , , , 'i i y[ l KILOMETERS 66T' SHELBURNE FALLS , (
Figure 2.6 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Direct Radiation Pathway) l f - _ _ -_-- -_
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8 f
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"8 4h itEARTWEtty LLE /
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\ 405 BORO '
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- P 23 J M-A0fs
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4 CHARLEHO T g %. . .
BURNE FALLS *
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@y 0 5 to 15 20 t i i i !
KILOMETERS e
Figure 2.7 Yankee Plant Radiological Environmental Monitoring Locations outside 12 Miles (Direct Radiation Pathway) 1 3
3.0
SUMMARY
OF 1987 EhVIRONMENTAL DATA L.
The following pages summarize the analytical results of all the eavironmental 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
( year's data for each category. The tables were generated by the computer program, ERMAP. At the top of each table, ERMAP lists the units of measurement for each medium. The left hand column contains the radionuclide which is being reported, total number of analyses of that radionuclide, and the number of measurements which exceeds ten times the yearly average for the control station (s). The latter are classified as "nonroutine" measurements.
The next column lists the Lower Limit of Detection (LLD) for those radionuclides which have detection capability requirements as specified in the plant's Radiological Effluent Technical Specifications. (Requirements are not given for many of the radionuclides for which analyses are routined c conducted.)
Those sampling stations which are within the range of influence of the plant and which could conceivably be affected by its operation are called "indicator" or "Zone 1" stations. Distant stations, which are beyond plant
/
influence are called "Control" or "Zone II" stations. Direct radiation monitoring stations are broken down into two additional categories to aid in data analysis. These are fenceline stations 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 calculates:
o The mean value of all concentrations including negative values and values below LLD.
o The standard error of the mean.
2918R/23.218
The' lowest and highest concentrstion.
^
o
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~
o The number of positive measurements (activity which is three times greater than the standard deviation) divided by the total number of measurements.
Each single radioactivity measurement datum in this report is based on
(
- a single measurement and is repot ted 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 statistics), and not the propagation cf all possible uncertainties in the
< analytical procedure. Radioactivity is considered to be present in a sample when the concentration exceeds three times its associated standard deviation.
With respect to the plots, all values less than three standard deviations '
(i.e., those where no radioactivity was detected) were plotted as zero.
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3.1 Air Particulate Y
Air monitoring stations are established at a total of seven locations, five of which are required by the Radiological
{ Effluent Technical Specifications. The air pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute. Airborne particulates are collected by passing the air through a glass-fiber filter. These filters are collected weekly and held for at leaFt 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. Weekly composite air filters from each location are analyzed quarterly for gamma-emitting radionuclides.
Gross-beta analyses (Figure 3.1) show random fluctuations through much of the year at all sampling locations including controls, J
thereby indicating that any plant contribution is negligible.
The high levels seen in May and June of 1986 were seen at other locations throughout the northeastern U.S., and are attributed to fallout from the Chernobyl accident. Naturally occurring K-40 and Be-7 were also detected in many samples.
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2918R/23.218
~ _ _ _ _ _ - -- x FIGURE 3.1 1 GROSS BETA MERSUREMENTS OF RIR PARTICULATE FILTERS YANKEE ATOMIC ELECTRIC COMPANY, R0WE, MR 0.8 g
- 0. 7 - 0 - AP-11 OBSERVATION STAND O - RP-12 MONROE BRIDGE A - RP-13 ROWE SCHOOL
+ - RP-14 HRRRIMAN STATION 0.s -. X - AP-21 HILLIAMSTOWN CONTROL l
o - RP-31 FURLON HOUSE d v - RP-32 HERRTWELLVILLE CONTROL g __
' d
- tg 0.5 -
O N o,4_ +
!O
!g c.3--
E 2
0.2 -
0.1 -
1 I ,Y [- ~ '
JAN'FEB MAR FPR MAY JUN JUL'flUG SEP'OCT'NOV'DEC JAN'FEB ISS7 MflR PPR MflY JUN JUL RUG'SEP OCT'NO 1986
EWIROPtENTAL RAD 10L00!CM. PROCRAM SMVRY
> YAl6IE MJCLE#t POWER STATION, R0WE l%
JANUARY - [ECEMBER 1987 UNITS: PCl/CU. M ED!lM: AIR PARTI (1 LATE STATION WITH HIOKST EAN CONTRIX. STATIONS INDICATOR STATIONS
++++++e m esseet
- ...:: : . ::e m emt+mme::::::::::n EAN EAN RADIOMJCLIDES EAN STA. RANCE RANE (NO. MALYSES) EQUIRED RME NO. NO. DETECTED +e NO. ETECTEDee (NON-ft0UTIE)' LLD NO. DETECTED +e
( l.9t .0)E -2 14 ( 2.0 t .1)E -2 ( !.8 i .1)E -2 CR-B (364) .01
(-1.1 - 37.9)E -3
( 0) ( 2.7 - 41.9)E -3 ( 6.2 - 37.5)E -3
- ( 52/ 52)* *(103/104)*
- (260/260)*
( 5.6 t .7)E -2 ( 4.9 2 .4)E -2 M-7 ( 28) ( 5.2t .2)E -2 13
( 4.0 - 7.4)E -2 ( 4.2 - 7.4)E -2 ( 3.6 - 6.9)E -2
( 0)
/
- ( 20/ 20)e e( 4/ 4)* +( 8/ 8)*
e
[
2.0t .5)E-3 21 ( 5.7 t .8)E -3 ( 3.7 t 1.0)E -3 K-40 ( 28) (
(-3.5 - 5.6)E -3 ( 3.8 - 7.6)E -3 (-7.7 - 76.2)E -4
( 0)
- ( 2/ 20)* *( 0/ 4)* *( 0/ 8)*
( 2.0t 2.5)E -5 12 ( 9.2 t 7.9)E -5 (-9.5 i 50.5)E-6 fW-54 ( 28) (-1.5 - 2.2)E -4
( 0) (-1.3 - 2.7)E -4 (-8.9 - 26.7)E -5
- ( 0/ 4)e *( 0/ 8)e
- ( 0/ 20)e
( !.3 t .6)E -4 ( 2.5 t 4.6)E -5 (X)-50 ( 28) ( -4.6t 3.5)E -5 31
(-2.9 - 2.3)E -4 (-5.0 - 22.9)E -5 (-l.3 - 3.1)E -4
( 0) et 0/ 4)* *( 0/ 8)*
et 0/ 20)*
( 2.0f 1.0)E -4 31 ( 2.4 t 1.7)E -4 (-1.9 t 1.2)E -4 FE-59 ( 28) 1.5)E -4
(-5.2 - 10.1)E -4 (-7.8 - 63.8)E -5 (-8.6 -
( 0) et 0/ 20)* *( 0/ 4)* et 0/ 8)e
( 2.22 2.7)E -5 13 ( l.4 * .7)E -4 ( 4.8 t 6.0)E -5 CD-60 ( 28)
(-2.0 - 3.4)E -4 ( 3.2 - 33.6)E -5 (-2.1 - 3.2)E -4
( 0) *( 0/ 8)e
- ( 0/ 20)e *( 0/ 4)* ,
( -2,2t .6)E -4 22 ( l.1 t 1.3)E -4 ( 4.3 t 77.6)E -6 ZM-65 ( 28)
(-6.5 - 2.8)E -4 (-2.8 - 3.4)E -4 (-2.8 - 3.4)E -4
( 0) *( 0/ 8)e et 0/ 20)* *( 0/ 4)*
( 1.62 5.6)E -5 13 ( !.7 t 2.1)E -4 ( 1.9 i 7.2)E -5 ZR-95 ( 28) 3.6)E -4
( 0) (-3.2 - 5.9)E -4 (-3.1 - 5.9)E -4 (-1.7 -
- ( 0/ 20)e et 0/ 4ls et 0/ 8)*
- NM-RCUTIE PIFERS TO TE MMER 7 SEPMATE EASLREENTS W104 ERE CREATER TMM TEN (10) TIPES TE A',EPAE BACTIRIAND FCR TE FERIOD & TK CEKRT.
- TK FRACTION OF SMPLE NLYSES YlELDilO [ETECTABLE EASLFi!ENTS (I.E. >3 STD IEVIAT10fG) IS INDICATED WITH *( )*.
ENVIR0 MENTAL RADIOLOGICAL PROGRAM SttflARY YAM (EE WCLEAR POER STATION, RCWE MA JANY - DEElfER 1987
[ LWITS: PCI/CU. M EDItM: AIR PARTICttATE STATION W!TH HIGEST EAN CONTROL STATIONS INDICATOR STATIONS
- .:: nun nennetanennun**e ***tu tunate EAN M EAN
[ RADIOWCLIDES STA. RME RANT l (NO. ANALYSES) REQVIRED RMGE NO. DETECTEDH LLD NO. DETECTEDH NO. NO. DETECTEDM (NON-ROUTINE)'
AG-110M( 28) ( -1.5t 3.8)E -5 21 ( l.2 i .9)E -4 ( 6.9 i 6.7)E -5
(-2.8 - 39.8)E -5 b 2.4 - 4.0)E -4
( 0) (-3.2 - 2.6)E -4
- ( 0/ 20)* *( 0/ 4)* *( 0/ 8)a
( -4.9t 3.0)E -5 21 ( 1.8 i .7)E -4 ( 3.8 i 6.7)E -5 PtF103 ( 28)
( 0) (-2.7 - 2.1)E -4 ( 6.9 - 35.7)E -5 (-2.6 - 3.6)E -4
- ( 0/ 20)* *( 0/ 4)* e( 0/ 8)*
( -7.01 2.4)E -4 11 ( 3.1
- 73.8)E -5 (-2.0 t 3.2)E -4 RLF106 ( 28)
( 0) (-2.1 - 2.2)E -3 (-22. - 21.5)E -4 (-1.7 - 1.2)E -3 et 0/ 20)e *( 0/ 4)e *( 0/ 8)e
(-5.8 t 14.3)E -5 (-8,5 t 6.8)E -5 CS-134 ( 28) .05 ( -1.5i .2)E -4 32
[ ( 3.5 - 2.8)E -4 (-3.5 - 2.8)E -4 L ( 0) (-4.3 - .6)E -4
- ( 0/ 20)* *( 0/ 4)e *( 0/ 8)*
.06 ( -2.9t 25.2)E -6 32 ( l.5 t .3)E-4 ( 4.9 i 4.3)E -5 CS-137 ( 28)
(-2.7 - ( !.0 - 2.2)E -4 (-1.4 - 2.2)E -4
( 0) 2.1)E -4
- ( 0/ 20)+ *( 0/ 4)* *( 0/ 8)*
( -1.31 ?.2)E -4 31 ( 7.7 i 8.1)E -4 ( 9.5 i 5.5)E -4 M-1401 28) .2)E -3
( 0) (-2.3 - 3.2)E -3 (-3.4 - 31.6)E -4 (-4.5 -
e( 0/ 20)* et 0/ 4)e *( 0/ 8)*
( 6.6i 4.5)E -5 21 ( 2.1 t .4)E -4 ( !.7 i .5)E -4 E-141 ( 2?) (-1.1 - 3.2)E -4
( 0) (-2.0 - 4.7)E -4 ( l.3 - 3.2)E -4
- ( 0/ 20)* *( 0/ 4)* *( 0/ 8)*
f
( l.22 1.1)E -4 13 ( 5.1 t 1.0)E -4 (-7.8 i 21.2)E -5 E-144 ( 28) 8.0)E -4 ( 2.3 - 7.0)E -4 (-1.3 - .6)E -3
( 0) (-18. -
et 0/20)* *( 0/ 4)* *( 0/ 8)*
T)F D2 ( 28) ( !.0t .8)E -4 11 ( 4.5 t 1.1)E -4 ( 2.6 i .9)E -4
( 2.5 - 6.4)E -4 (-1.1 - 6.0)E -4
( 0) (-8.1 - 6.4)E -4
- ( 0/ 20)e et 0/ 4)* *( 0/ 8)+
- NON-ROUTIE REFERS TO TE EMER CF SEPAFATE EA%IDENTS IM104 ERE CFEATER T)W TEN (10) TIES TE AVEPNE IMCKCROUND FOR TE FERIOD CF TE PEMRT.
{ -- -
3.2 Charcoal Filters
- /
' Charcoal filter cartridges are situated in series with the air e
particulate glass-fiber filters. Monitoring stations were located at a total of seven stations, five of which were required by the Radiological Effluent Technical Specifications. The air pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute.
Charcoal filters were collected and analyzed weekly for I-131 activity. During 1987, no such radioactivity was detected.
\
)
2918R/23.218 l .- _ _ - -
E)N!RCNENTAL RADIOLOGICAL PRO @AM SlfWRY
> YAftIE MJ(1 EAR POWER STATICN. R0WEi MA JANUARY - DECDEER 1987 s UNITS: PCI/0J. M EDM: OMRCOM. Fit'ER STATICN WITH H!CEST M C0(TRCL. STAT 10!G INDICATOR STATIONS enmueuew+n+eneen pum pmeen sw ee::.:-:::.:ne RADIOMJCLIDES M M EAN STA. MNGE RANGE (NO. ANALYSES) REQUIRED RM0E NO. NO. DETECTEDH NO. DETECTEDH (NON-ROUTIE)' LLD NO. DETECTED ++
( 4.7 i 9.0)E -4 (-9.8 6.5)E -4 I-131 (3641 .07 ( -8.41 3.9)E -4 11
(-2.5 - 2.5)E -2 (-1.3 - 2.5)E -2 (-2.7 - 1.2)E -2
( 0) et 0/104)*
et 0/260)* *( 0/ 521e j e NCN-ROJTIE REFERS TO TE ItteER OF SEPARATE EASLREENTS Wi101 WERE WEATER T)MN TEN (10) TIES TE AVDWE BACKmCWD FOR TE PERIOD W TE REPTT.
- TE FRACTION OF SAELE AfMLYSES YIELDING CETECTAR.E EA9.REVENTS f (f.E. >3 STD DEVIATIONS) IS INDICATED WITH *(
)*.
l 1
l ----
s s
3.3 Milk s
g.
L Milk samples were collected and analyzed by the schedule shown in Table 2.1. Strontium 89 and Sr-90 analyses were performed on quarterly composite milk samples even though not required by Technical Specifications.
Detectable concentrations of Cs-137 and Sr-90 were measured'in milk sampics submitted from the indicator and control locations.
( The higher concentration in indicator station samples has been noted for many years. It has been shown in previous reports that y
the. radioactivity in the cows' milk is a result of atmospheric nuclear weapons testing radionuclides that persist in'the environment (Cs-137 and Sr-90 in particular). Differences in farming practices (amorat of vegetation and type of vegetation that the cows are allowed to feed on) can cause significant variations in these radionuclides in milk. Additional Cs-137, as well as Cs-134, was introduced into the environment in mid-1986 following the Chernobyl accident. A slight rise in Cs-137 levels in milk can be seen for this period in Figure 3.2.
The Cs-134 detected in two milk samples collected in February (at Stations TM-12 rad TM-13) was due to Chernobyl fallout on stored feed grown durir.g 1986 and fed to the cows in 1987. No Cs-134 f was detected by air sampling systems during early 1987, nor was any detected in other sampling media. It was detected in 1986, however, following the Chernobyl accident, in air, milk, f
precipitation, and vegetation throughout much of the northeastern U.S.
2918R/23.218 l- . .
- ~ - - - - - - ~~ ~ ~
FIGURE 3.2 CESIUM-137 IN MILK YANKEE ATOMIC ELECTRIC COMPANY, R0WE, MR so !
2e_
O - TM-12 READSBORD,VT 2s.
o - TM-13 WHITINGHAM,VT A - TM-21 WILLIAMSTOWN.M8 3
i y
@ 20-ts a 3 is-Y G 28 - q3 s
0 24-E B 22-8 (
E 20-I _ i D
OD_ MMJ OD MMJ 00 MMJ 00 MMJ OD MMJ 0 JMMJ OD MMJ OD MMJ 1982 1983 1984 1985 1986 1987 1980 1981
ENVIR0 MENTAL RADIOLOGICAL Mt00 RAM RMMARY
/ YAf*IE NII. EAR POER STAi!0N, R0WE MA JANJARY - DECOEG 1987
( LNITSr PCI/KG EDitM: MILK STATICN WITH HIGEST EAN CONTROL STATIONG INDICATOR STAT 10N3
- . . .: ::: :" e n m + n u n *++ n
- m m +++nem * * *nn M EAN EAN RADIONJCLIDES (NO. ANALYSES) REQUIRED RANGE STA. RANE RANGE NO. DETECTED ** NO. NO. DETECTED ** N0. DETECTEDH (NON-ROUTIE)' LLD ~
SR-89 ( 12) ( -6.7t 43.7)E -2 21 ( 2.2 i 34.6)E -2 ( 2.2 t 34.6)E -2 1.4)E O (-6.4 - 9.5)E -1 (-6.4 - 9.5)E -l
( 0) (-2.1 -
- ( 0/ 8)* *( 0/ 4)* *( 0/ 4)*
SR-90 ( 12) ( 3.lt .4)E O 12 ( 4.1 t .4)E O ( l.7 t .1)E O
( 0) ( l.9 - 5.1)E O ( 3.3 - 5.1)E O ( l.4 - 2.1)E O
- ( 8/ 8)* *( 4/ 4)* *( 4/ 4)*
l.4i .0)E 3 13 ( l.4 t .0)E 3 ( l.4 t .0)E 3 K-40 ( 57) (
( 0) ( l.3 - 1.6)E 3 ( l.3 - 1.6)E 3 ( l.3 - 1.5)E 3
- ( 30/ 38)* *( 19/ 19)* *( 19/ 19)*
( 4.lt 16.4)E -2 12 ( l.1 1 3.0)E -1 (-3.8 i 1.9)E -1 19f-54 ( 57)
(-3.3 - 2.3)E O (-3.3 - 2.3)E O (-1,6 - .8)E 0
( 0)
- ( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
( -2.6t 1.6)E -1 13 (-2.0 1 2.7)E -1 (-4.4 i 2.6)E -i
[
CO-58 ( 57)
(-2.1 -
2.5)E 0 (-2.1 - 2.5)E 0 (-2.7 - 1.7)E O
( 0!
- ( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
( 7.6f 5.4): -l 13 ( l.6 t .9)E O ( 9.0 t 9.7)E -1 FE-59 ( 57) 9.9)E O
( 0) (-8.3 - 10.9)E O (-4.6 - 10.9)E 0 (-6.3 -
- ( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
( -4.0t 1.8)E -1 21 (-8.1 i 32.5)E -2 (-8.1 t 32.5)E -2 CD-60 ( 57) 2.5)E O
(-2.7 - 1.5)E O (-3,0 - 2.5)E 0 (-3.0 -
( 0)
- ( 0/ 30* *( 0/ 19)* *( 0/ 19)*
( -2.0t 51.7)E -2 13 ( 4.6 i 9.3)E -1 (-9.5 t 6.1)E -1 ZN-65 ( 57) i 0) (-6.4 -
10.9)E O (-6.4 - 10.9)E 0 (-8.0 - 2.7)E 0
{ *( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
ZR-95 ( 57) ( 3.9t 3.5)E-1 12 ( 6.9 i 5.7)E -1 (-9.0 t 4.6)E -1
( (-5.4 - 5.8)E O (-4.5 - 3.1)E 0
( 0) (-5.4 -
5.8)E 0
( *( 0/ 19)* *( 0/ 19)*
- ( 0/ 3P)*
[
( THM TEN (10) TIES TE #.9 AGE BACKmCI.ND FCR TT FDIOD 7 TE FEKRT.
H TE FMCTION OF SMtf NW.YSES Y!ELDIW DETECTAELE EARFEENTS (I.E. >3 STD DEVIAT!0NS) IS INDICATED WITH *(
)*,
ENVIR0 MENTAL RADIOLCCICN. PRO @#( Slft%RY YAEEE MJCLEAR POER STATION. RM. MA JAMY - DEC99ER 1987 LMITS:PC1/KO ED!lM: MILK STATION WIT){ HIGEST EAN COER0L STATIOPG b INDICATOR STATIONS
- .::::: :::non
- ": ::::: :n un:::: :: :::::non*
EAN EAN MAN RADI(NJCLIDES STA. RANGE RANGE (ND. APMLYSES) REQUIRED RANE NO. ETECTEDie ND. NO. DETECTEDH W. DETECTED ++
(N0lH10UTIE)' LLD AG-110Mt 57) ( -4.21 3.3)E -1 12 ( 3.9 t 4.7)E -1 ( 2.5 t 2.2)E -1
( 0) (-6.0 - 4.9)E O (-3.2 - 4.9)E 0 (-2.1 - 1.7)E 0
- ( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
( -6.9t 1.8)E -1 13 (-6.5 t 2.8)E -1 (-1.2 t .4)E 0 RL)-103 ( 57)
( 0) (-2.3 - 2.2)E O (-2,3 - 2.2)E 0 (-4.4 - 3.6)E O
- ( 0/ 33)* *( 0/ 19)* *( 0/ 19)*
{
Ril-106 ( 57) ( -1.8t 1.3)E O 12 (-8.3 t 18.4)E -1 (-9.7
- 22.3)E -1
( 0) (-2.0 - 1.2)E i (-1.9 - 1.2)E 1 (-3.2 - 2.0)E 1
- ( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
I-131 ( 57) 1. ( 1.11 .9)E -2 13 ( l.9 t 1.3)E -2 ( l.3 t 1.4)E -2
( 0) (-6.1 -
19.0)E -2 (-6.1 - 19.0)E -2 (-7.0 - 13.4)E -2
- ( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
CS-134 ( 57) 15. ( -2.9t 2.0)E -1 21 (-1,6 t 3.2)E -1 (-1.6 t 3.2)E -1
( 0) (-3.2 - 2.1)E O (-2,3 - 2.4)E O (-2.3 - 2.4)E O
- ( 2/ 38)* *( 0/ 19)* *( 0/ 19)*
CS-137 ( 57) 18. ( 4.2t .3)E O 12 ( 4.3 t .3)E O ( 1. 6 * .3)E 0
( 0) (l.3 - 8.2)E O ( !.4 - 6.6)E O (-1.5 - 6.1)E O
- ( 29/ 38)* *( 16/ 19)* *( 3/ 19)*
BA-140 ( 57) 15. ( -4.21 2.2)E -1 21 (-3.4 1 4.6)E -1 (-3.4 t 4.6)E -l
( 0) (-4.9 - 4.5)E O (-3.3 - 5.5)E 0 (-3.3 - 5.5)E O
- ( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
CE-141 1 57) ( -5.21 3.9)E -1 12 ( 6.9 i 4.6)E -1 ( 5.2 t 31.6)E -2
( 0) (-6.5 - 3.5)E o (-5.6 - 3.5)E 0 (-2.6 - 2.8)E O
- ( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
f E-144 ( 57) ( -7.5* 10.2)E -l 13 (-1.1 i 15.6)E -1 (-8.2 t 15.3)E -1
( 0) (-1.8 - 1.2)E 1 (-1.8 - 1.2)E 1 (-1.5 - .8)E 1
{ *( 0/ 38)* *( 0/ 19)* *( 0/ 19)*
- POHt0UTIE REFERS TO M N.MBER OF SEPARATE EASLREENTS WH10i ERE @ EATER T)%N TEN (10) TIES TE AWRAE BACXCfMC FOR TE PERIOD CF M REPCRT.
f ** TE FRACTION CF S/#ti ANALYES YlELDING ETECTABLE EMEENTS
(!.E. >3 STD DEVIATIONS) l$ INDICATED WITH *( )*.
s 3.4 Food Crop s
Tomato samples were collected at harvest time at each of three locations and analyzed for gamma-emitting nuclides. Other
[ ..
than naturally occurring K-40, no radionuclides were detected in the samples.
(
e f
f l
4 2918R/23.218 f - - - - - - - - - - -
ENVIR0ffENTAL RADIOLOGICAL PROGRAM Slft(ARY YAPDIE RT.I.ENt P06 STATION, ROE MA JAR $RY - DEti!9ER 1987
' lNITS: PCl/XG ET EDIUM: F000 CROP I
' STATICH WITH H10EST EiVi CONTROL STATIONS INDICATOR STATIONS
- >**mun :: .: : ::.: He**** n * *mumnem EAN EAN RADIONUCLIDES E?N
( (NO. ANALYSES) REQUIRED RANGE STA. RNEE NO. NO. DETECTED H R#0E NO. DETECTED ++
(NDH0llTIE)' LLD NO. 0ETECTED++
( 4.7t 13.5)E O ( l.8 i 6.6)E 1 ( 5.7 t 60.2)E O BE-7 ( 3) 11
( 0) (-8.8 - 18.2)E 0
- ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*
.5)E 3 ( 2.9 k .3)E 3 ( 2.4 i .2)E 3 K-40 ( 3) ( 2.4f 11
( 0) ( l.9 - 2.9)E 3
- ( 2/ 2)* *( 1/ 1)* *( 1/ 1)*
( 8.lt 1.1)E 0 11 ( 9.1 t 9.5)E O ( 4.5 i 82.4)E -1 IW-54 ( 3)
( 0) ( 7.0 - 9.2111 0
- ( 0/ 2)* *( 0/ lie *( 0/ 1)*
( -6.9t 5.7)E O 13 (-1.2 t 3.8)E 0 (-4.9 i 7.5)E O CO-58 ( 3)
( 0) (-1.3 - .1)E 1
- ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*
( -2.6i 3.3)E 1 21 ( 3.0 t 1.4)E 1 ( 3.0 t 1.4)E I f FE-59 ( 3)
( 0) (-5.9 - .7)E 1
- ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*
CO-60 ( 3) ( 4.2t 8.0)E O 21 ( l.5 t 1.5)E I ( l.5 t 1.51E I
( 0) (-3.8 - 12.2)E O
- ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*
( -1.91 .8)E 1 21 ( 8.0 t 18.5)E O ( 8.0 t 18.5)E O ZN-65 ( 3)
( 0) (-2.7 - -1,1)E 1
- ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*
f
( 5.5t 13.3)E 0 !! ( 1.9 t 1.7)E 1 (-5.6 i 13.3)E 0 ZR-SS ( 3)
( 0) (-7.9 - 18.8)E O
{ *( 0/ 2)* *( 0/ 1)* *( 0/ 1)*
AG-110M( 3) ( !.4f 5.4)E O 11 ( 6.8 t 13.0)E O (-3.7 i li.0lE O
( 0) (-4.0 - 6.8)E O
- ( O' 2)* *( 0/ 1)* *( 0/ 1)*
- NDHOUTIE REFETC TO TE NUlfER 7 SEPr# ATE EASWE)E(TS Wi!CH WERE @ EATER T)M TEN (10) TIES TE AGACE BACKCRO.ND FOR TE FT.RIOD CF TE REKRT.
++ TE FRACTION OF S#PLE ANALYSES YlELDING DETECTABLE EASLREENTS f (1.E. >3 STD [EVIATICHT !S INDICATED WITH *( 1*.
s EFilRMENTfJ. RADIOLOGICAL H10mM SlMtARY VM'EE IU1EM POER STATION R0WE. MA JN b W - DE & MBER 1987
" (MITS! PCl/KG ET EDitM: FOOD CRT STA!!0N WITH HIGEST EM CONTROL STATIONS INDICATOR STAT 106
- ... . : ::::* ** ue+u +++ a n ++++ n ue :. :: : :::***
RADIONJCl. IDES EAN EM EAN STA. RMGE IWIGE f (NO. MALYES) REQlJIRED RANT N0. NO. DETECTEDH NO. DETECTEDH (NON-R0llTIE)' LLD NO. DETECTED *+
RL)-103 ( 3) ( -3.81 6.3)E O 21 ( 2.9 i 6.9)E O ( 2.9 i 6.9)E O
( 0) (-1.0 - .2)E 1
- i 0/ 2)* *( 0/ 1)* *( 0/ 1)*
( -3.81 4.2)E 1 13 ( 3.7 t 37.3)E O (-5.1 i 8.0)E i Ril-106 ( 3)
( 0) (-8.0 - .4)E 1
- ( 0/ 2)* *( 0/ 1)* *( 0/ !)*
( 5.0t 6.1)E 0 13 ( !.1 i .6)E I (-1.3 t 1.2)E 1 l-131 ( 3)
( 0) (-1.0 - II.llE O
- ( 0/ 2)* *( 0/ 1)* *( 0/ lie CS-134 ( 3) M. ( l.0t 610.0)E -2 21 ( !.0 t .9)E 1 ( l.0 t .9)E 1
(-6.1 - 6.1)E O f ( 0)
- ( 0/ 2)* *( 0/ 1)* *( 0/ lie
( 5.8t 8.2)E 0 11 ( !.4 i .8)E I (-8.6 t 8.6)E 0 CS-137 ( 3) 80.
f ( 0) (-2.5 - 14.0)E O
- ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*
BA-140 ( 3) ( l.0t 158.0)E -1 13 ( l.6 i .6)E i (-4.3 t 12.9)E O
( 0) (-l.6 - 1.6)E 1
- ( 0/ 2)* *( 0/ 1)* *( 0/ t)*
&-141 ( 3) ( -1.2t 7.1)E -1 11 ( 5.9 t !!9.0)E -! (-9.9 t 10.2)E O
( 0) (-8.3 - 5.9)E -1
- ( 0/ 2)* *( O! !)* *( 0/ 1)*
{
( -2.71 3.4)E 1 13 ( 7.4 i 20.4)E O (43i 3.9)E I CE-144 ( 3)
( 0) (-6.1 - .7)E 1
- ( 0/ 2)* *( 0/ 1)* *( c/ lis 4 TH-232 ( 3) ( 4.8t .5)E O 11 ( 5.4 t 36.3)E O (-5.5 t 36.8)E 0
( 0) ( 4.3 - 5.4)E 0 f *( 0/ 2)* *( 0/ De *( 0/ 1)*
- IOHDJTIE KFERS TO M IUEER CF SEPAPATE EARREENTS WilCN WEPS @ EATER T)WI TEN (10) TIES M MUAGE BACKm0lMD FM M CERIOD OF M REKIRT.
u M FRACTION CF S/#LE ## LYSES YlELDINO DETECTfRE EARFDENTS (I.E. >3 STD DEVIATICNS) IS IMD1CATED WITH *( )*.
k 3.5 Broad Leaf Vegetation The Radiological Effluent Technical Specifications require that one sample of broad leaf vegetation be sampled at harvest time.
l In 1987, a sample of mustard greens was collected from Station IV-11. The required I-131 analysis showed no detectable radioactivity.
l l
i 1
d 2918R/23.218
E)NIR0lfENTM. RAD 10 LOGIC 4. PROCM SlMIMY YAWEE 10 CLEAR POER STATION, ROE,11A JANJARY - DECD9ER 1987
' LNITS: Kl/KG ET EDim: BROAD LEAF VEGETATION
[ INDICATM STATIONS STATION WITH HIGEST M CONTROL STATIONS mmunmm unummemn m **mm+m mmu EAN G M PADIONAIDES
[ STA. RM0E RANCE L (M). AMLYSES) EQUIRED RfdC NO. to. DETECTEDu NO. DETECTEDH (NON-ROUTIEl' LLD NO. DETECTEDH 1-131 ( 11 60. ( l.0t 3.0)E O 11 ( 1.0 t 3.0)E O NO DATA
( 0)
- ( 0/ 1)* et 0/ Ile
- N0N40VTIE REFERS TO TE NUPSER OF SEPARATE EASURDENTS WICH ERE MEATER Tim TEN (10) TIES TE A'4RAE BACK0RDED FOR TE PERIOD OF TE REPORT.
H TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTAR.E EASmDENTS
(!.E. >3 STD [EV!ATIONS) IS INDICATED WITH a( )*.
l
{
{
b l
l l
a
\
3.6 M3ple syrup r
L Maple syrup grab samples (not required by Technical.
r Specifications) were collected during April at one indicator and L one cactrol location. In addition to naturally occurring K-40 Cs-tJ7 was detected in each sample. Attributed to nuclear weapona tecting fallout, this Cs-137 has been detected in most samples since collection was started in 1972. The control station in 1987 had a higher Cs-137 level than detected at the f
indicator station.
l 2918R/23.218
I e4 s
EWIR0lfENTAL RADIOLOGICAL PROGRMI SuttARY
- YAINE RJCLEAR KWR STATION, RGdEi MA L JANUARY - DECEMBER 1987 LNITS: K!/KO
- lC:'Jt: 1%PLE SYRtP STATION WITH HIGEST EAN C0NTROL STATIOPG ll@lCATOR STATIONS m+n+ ++***+ne m ** neen u n m m e m +++++++ n +w nee EM EAN IGN RADIONLO.lDES (NO. ANALYSES) EQUIRED RANCE STA. RAltE RANCE NO. NO. DETECTEDee NO. DETECTEDee (NGHl0VTIEl' LLD NO. DETECTEDH
( -7.4i 9.5)E O 42 ( 2.5 t 6.7)E O ( 2.5 t 6.7)E O BE-7 ( 2)
( 0)
- ( 0/ 1)* *( 0/ 11e *( 0/ 1)*
K-40 ( 2) ( l.9t .0)E 3 31 ( l.9 t .0)E 3 ( l.4 i .0)E 3
( 0)
- ( 1/ 1)* *( 1/ 1)e *( 1/ 1)*
l.0t 1.2)E 0 31 ( l.0 t 1.2)E 0 ( 2.8 i 8.2)E -1 IW-54 ( 2) (
( 0) et 0/ 1)e *( 0/ lie et 0/ 1)*
( -2.7t ll.3)E -1 42 ( 4.4 t 8.6)E -1 ( 4.4 i 8.6)E -1 CO-58 ( 2)
( 0) *( 0/ 1)*
- ( 0/ 1)* *( 0/ 1H
(-1.8 t 2.1)E 0 (-1.8 t 2.1)E O FE-59 ( 2) ( -3.2 3.2)E 0 42
( 0) et 0/ 1)* *( 0/ 1)* *( 0/ 1)f
( !.8t 15.2)E -1 42 ( 5.1 i ll.8)E -1 ( 5.1 t II.8)E -1 CD-60 ( 2)
( 0)
- ( 0/ 1)e *( 0/ lie *( 0/ lie 3.2)E 0 (-2.4 t 3.2}E 0 (-4.7 1 2.3)E 0 ZN-65 ( 2) ( -2.42 31 et 0/ 1)* *( 0/ 1)* *( 0/ 1)*
f
( -5.3t 2.0)E 0 42 (-1.8 t 1.5)E O (-1.8 i 1.5)E O IR-95 ( 2)
( 0) f *( 0/ 1)* *( 0/ lie *( 0/ lie
( -5.3t 19.0)E -1 31 (-5.3 t 19.0)E -1 (-1.9 i 1.3)E 0 A0-110M( 21
[
1 ( 0)
- ( 0/ 1)* *( 0/ 1)* a( 0/ !)*
e IDHIDUTIE REFERS TO M ) DEER OF SEPMATE EA$lREENTS IM101 IDE CREATER THM TEN (10) TIES M AWRACE BACXCROLND FOR TE PERIOD OF M REMRT.
- M FRACTION OF SNFLE NeLYSES YlELDING DETECTAILE EASLREENTS
(!.E. >3 STD DNIATIONS) IS INDICATED WITH *( le.
a s
EWIR0leENTAL RAD 10 LOO! CAL PROGRM SlffMRY YAf0(EE ltREAR POER STATION, RGiE MA JAMY - ECDEER 1997 UNITS: PC1/KG i EDitti: 1%PLI SYRLP r
STATION WITH HIGEST EAN CONTROL STATIONS INDICATORSTATIONS
- ::::: : ::.::n n+n++nuneenenn+n ****+++ ne n++n EAN KAN RAD 10linifES KAN STA. RANCE RANGE (NO. AleLYSES) EQVIRED PME NO. NO. DETECTEDu NO. DETECTEDH (N0lHt0UTIE)' UD NO. ETECTEDH 11.3)E-1 31 ( 6.3 i ll.3)E -1 (-8.8 & 8.4)E -1 R)-103 ( 2) ( 6.3
( 0)
- ( 0/ 1)* *( 0/ 1)* *( 0/ 1)*
( -2.81 1.0)E 1 42 ( 3.8 i 7.5)E O ( 3.8 t 7.5)E O RU-106 ( 2)
( 0)
- ( 0/ 1)* *( 0/ 1)* *( 0/ 1)*
6.8* 18.9)E -1 42 ( 1.1 t 1.4)E O ( l.1 t 1.4)E 0 I-131 ( 2) (
( 0)
- ( 0/ 1)* *( 0/ 1)* *( 0/ !)*
( -1.4i 1.1)E O 31 (-1.4 i 1.1)E O (-1.5 t .9)E O CS-134 ( 2) 60.
( 0)
- ( 0/ 1)* *( 0/ 1)* *( 0/ 1)*
- 80. ( l.3t .!)E 1 42 ( 8.I t .2)E I ( 8.1 i .2)E 1 CS-137 ( 21
( 0)
- ( 1/ 1)* *( 1/ 1)* *( 1/ 1)*
BA-140 ( 2) ( -1.3t 1.5)E O 31 (-1,3 1 1.5)E O (-l.3 t 1.0)E O
( 0) 0/ 1)*
- ( 0/ 1)* *( 0/ 1)* *(
l.3* 2.0)E O 31 ( l.3 i 2.0)E 0 (-1.9 t 1.4)E O E-141 ( 2) (
( 0)
- ( 0/ 1)* *( 0/ 1)* *( 0/ 1)*
( 2.51 7.6)E 0 42 ( 7.1 i 5.21E 0 ( 7.1 1 5.ME 0 E-144 ( 2)
( 0)
- ( 0/ 1)* *( 0/ 1)* *( 0/ 1)*
TH-232 ( 2) ( -2.6t 5.1)E O 42 ( 5.0 t 3.1)E O ( 5.0 t 3.1)E O
( 0)
- ( 0/ 1)* *( 0/ 1)* *( 0/ 1)*
J
- N0lHt0 lit!IE REFERS TO TE f(FEER CF SEPMATE EASLREENTS IMIQ! WEPE CEEATER TIMN TEN (10) TIES TE AVERAE BACKCR0l#O FOR TE PERIOD OF TE REPt%T.
f
- TE FRACTION OF SAMI AIMLYSES VIELDING CETECTARI KASLREENTS (I.E. >3 STD E VIATIONS) IS INDICATED WITH *( )*.
[ --- - - - ----- -- - _ _ _ _ __
s 3.7 Groundwater L
Groundwater grab samples were collected from two indicator stations on a monthly basis. (Technical Specifications require a
[
L quarterly collection.) Each of these samples was analyzed for gross-beta H-3, and gamma-emitting radionuclides.
Tritium (H-3) was detected in all of the Station WG-12 samples
( and none of those from Station WG-11. Since the water from WG-12 (Sherman Spring) is not used for drinking water, and since the Deerfield River into which it empties is also not used for
[
drinking, there would be no impact on man from the low levels detected. In any case, the calculated total body dose to an average adult who is assumed to ingest 370 kilograms per year of this water (undiluted) at the average 1987 concentration of 970 pCi/ kilogram, would be approximately 0.04 mrem, using USNRC Regulatory Guide 1.109 methodology (Reference 1). The annual mean H-3 concentration has decreased steadily for most of the past ten years (see Figure 3.3).
Gross-beta radioactivity was detected in all groundwater samples. Caused primarily by naturally occurring radionuclides in groundwater, the gross-beta levels were similar to those of the past several years (see Figure 3.4).
No gannna-emitting radionuclides were detected in the groundwater samples, l
2918R/23.218 l
(
FIGURE 3.3 TRITIUM IN SHERMAN SPRING WRTER (WG-12) t00fiRTERLY RVERAGE)
YANKEE RTOMIC ELECTRIC COMPANY, ROWE, MR I
8000 7000-m .. .
s sxu-
- S E G
' co0_
l 0 2
8 g axe-E 1 ' S l
I 2000-y 2000 -
'IV I II1986 IV' I II1987 'IV
^ '
I II
'IV'I'II1981 'IV I 'II1982 IV'I 'II1983 'IV' I 'II1984 'IV I 'II 1985 1980
~ ~ -
FIGURE 3.4 GROSS-BETR MERSUREMENTS OF GROUNO WATER COURRIERLY RVERRGE)
YANKEE ATOMIC ELECTRIC COMPANY, ROWE, MR 10 9-0 - HG-11 PLRNT POTRBLE 0 - WG-12 SHERMAN SPRING e-7-
E
. N g
g 6-G
' 1 s-0 3 STD DEY!ATIONS) IS INDICATED WITH *( )*.
E)N!R0ltENTAL RADIOLOGICAL PR0mm Stft%RY YNIE MREAR POER STATICN. R0Ei M
/ JWlMY - DEEPEER 1987
' LNITS: PC1/KO EDIUM: 20lND WAB STATION WITH HIGEST EM CONTROL STAT!0lf3 INDICATOR STATIONS
++w o ut***++ m e e+*:::::..: ::neme** ++++++ ++mu n e EM EAN EM RADIOMRIES STA. RMCE RANE (NO. MALYSES) REQUIRED RAN3E NO. N0 DETECTED +e NO. DETECTED +e (NON-ROUTIE)' LLD NO. DETECTEDu RU-103 ( 24) ( -1.2t .2)E 0 12 (-8.6 t 1.9)E-1 NO DATA
( 0) (-2.4 -
.2)E 0 (-1.7 - .2)E 0 et 0/ 24)* *( 0/ 12)*
RLF-106 ( 24) ( -1.7t 1.6)E O 12 (-5.9 t 16.0)E -1 NO DATA
( 0) (-2.3 - 1.1)E 1 (-8.6 - 10.6)E 0
- ( 0/ 24)* *( 0/ 12)e I-131 ( 24) 1. ( -6.0t 6.0)E -1 12 (-5.7 i 8.01E -1 NO DATA
( 0) (-8.3 - 5.0)E 0 (-8.3 - 3.3)E O at 0/ 24)e et 0/ 121e CS-134 ( 24) 15. ( -5.6t 1.8)E -1 11 (-4,5 t 2.7)E -1 M) DATA
( 0) (-2.4 - 1.2)E 0 (-2,4 - 1.2)E O et 0/ 24)* et 0/ 12)*
CS-137 ( 24) 18. ( -1.81 2.3)E -1 12 ( 2.7 t 2.0)E -1 M) DATA
( 0) (-2.7 - 1.3)E O (-1.4 - 1.3)E O et O! 24)* *( 0/ 12)*
BA-140 ( 24) 15. ( -6.9t 3.2)E -1 11 (-9.5 t 48.7)E -2 NO DATA
( 0) (-3.2 - 1.7)E O (-3.1 - 1.7)E O
- ( 0/ 241e et 0/ 12)e E-141 ( 24) ( 3.0t 3.8)E -1 12 ( 4.0 t 4.9)E -1 NO DAT A
( 0) (-3.4 - 3.4)E 0 (-2.0 - 3.4)E O et 0/ 24)* *( 0/ 12)*
CE-144 ( 24) ( 5.7t 12.1)E -1 11 ( 3.8 t 1.3)E O NO DATA
( 0) (-1.2 - 1.0)E 1 (-5.3 - 9.9)E O et 0/ 24)* *( 0/ 12)e H-3 ( 25) 2000. ( 4.91 1.0)E 2 12 ( 9.7 t .8)E 2 NO DATA
( !!) (-1.1 - 12.9)E 2 ( 5.3 - 12.9)E 2 f *( 11/ 25)e *( 11/ 12)e
(
- NON-ROUTIE REFERS TO TE MMER OF SEPMATE EAstRDtMS Wi!O4 ERE WEATER T)N TEN (10) TIES TE AVERAE BACXm0lMD FOR TE PERICD 0F TE REPORT.
H TE FRACTION OF SMPLE AMLYSES Y!ELDIN0 DETECTAR.E EASLRDCNTS (1.E. >3 SfD DEVIATIONS) IS INDICATED WITH *( la.
l f -_
(
3.8 River Water I
L Composite samplers were used at the two required sampling locations and samples from each of these were collected monthly and analyzed for gross-beta and ganna-emitting radionuclides.
Quarterly composites were analyzed for H-3.
From July 13 to October 7, 1987, the composite sampler at Station WR-11 (Bear Swamp Lower Reservoir) was relocated to the Fife Brook Hydro Station (1/4 mile downstream of WR-11) due to a repair and inspection outage at the former. A total of three monthly samples were collected at this location.
The first quarter composite sample showed a detectable level of H-3 at Station WR-11 (Bear Swamp Lower Reservoir). Since the Deerfield River is not used for drinking water, the low levels of H-3 found will have no impact on man. If one was to calculate, however, the dose to an adult who consumed his entire yearly intake of water (370 kilograms per year) from the Deerfield River at the above sampling location, with the average concentration of
{ 730 pCi/ kilogram during the first quarter, it would be shown that the dose would be approximately 0.01 mrem per year, using USNRC Regulatory Guide 1.109 methodology (Reference 1). This concentration of 730 pCi/ kilogram during the first quarter of 1987 did not exceed the 30,000 pCi/ kilogram reporting level.
Gross-beta radioactivity, primarily from naturally occurring radionuclides in river water, was detected in most samples. The mean and range were similar to those measured in previous years.
The control and indicator station mean concentrations were approximately equal in 1987. No ganna-emitting radionuclides were detected in the 1987 river water samples.
(
2918R/23.218
[ - - - - - - - - _
s EINIROWNTAL RAD 10l10! CAL PP00 RAM RN%RY
- YNMI PUCLEM POER STAT!06 R9E. M J M RY - DECD GER 1987 LNITS FCl/KG EDILE: RIst WATER STATICM WITH HIGEST EAN CONTROL STATIONS INDICATOR STATIONS wwmewumm n+++ w m u m e+e m + m ennenmmu EAN EM EMI MDIGOCLIES (NO. ANALYSES) REQUIRED RANGE STA. RNE RANE PC. NO. OETECTEDet NO. DETECTEDM (NON-ROUTIEl' 1.LD PC. ETECTED++
(R-B ( 24) 4. ( l.9t .1)E 0 21 ( l.9 i .2)E O ( l.9 t .2)E 0
( 0) ( 1.3 - 3.1)E O ( 1.1 - 4.2)E O ( l.1 - 4.2)E 0 et 12/ 12)* *( 11/ 12)e *( 11/ 12)+
( -8.6i 32.1)E -1 21 (-2.5 t 35.5)E-1 (-2.5 t 35.5)E -1 K-4s ( 24)
(-1.6 - 1.5)E 1 (-2.2 - 2.3)E I (-2.2 - 2.3)E 1
( 0) et 0/ 12)* et 0/ 12)* *( 0/ 12)*
PW-54 ( 24) 15. ( 2.8f 2.3)E-1 11 ( 2.8 t 2.3)E -1 (-1.8 i 3.0)E -1
( 0) (-8.8 - 19.5)E -1 (-8.8 - 19.5)E -1 (-1.8 - 1.5)E O
- ( 0/ 12)* *( 0/ 12)* *( 0/ 12)e CD-58 ( 24) 15. ( -3.7t 2.1)E -1 21 ( !.6 t 3.0)E -1 ( !.6 t 3.0)E -1
( 0) (-1,3 - 1.0)E O (-1.3 - 2.5)E O (-1.3- 2.5)E O P
- ( 0/ 12)e *( 0/ 12)e *( 0/ 12)*
( 6.5t 6.0)E -1 21 ( l.0 t .8)E 0 ( l.0 t .8)E O FE-59 ( 24) 30.
(-2.4 - 4.1)E 0 (-3.3 - 5.9)E O (-3.3 - 5.9)E O
( 0)
- ( 0/ 12)* e( 0/ 12)e *( 0/ 12H
- 15. ( -1.lt 2.6)E -1 11 (-1.1 t 2.6)E-1 (-5.2 i 2.6)E -1 CD-60 ( 24) .8)E O
(-1.4 -
2.1)E O (-1.4 - 2.1)E O (-2.4 -
( 0)
- ( 0/ 12)e *( 0/ 12)* *( 0/ 12)*
ZN-65 ( 24) 30. ( 8.72 53.7)E -2 11 ( 8.7 t 53.7)E -2 (-2.9i 4.1)E -1
(-3.5 - 2.5)E O (-3.5 - 2.5)E O (-2.4 - 1.6)E O
( 0) et 0/ 12)* *( 0/ 12)* *( 0/ 12)*
( .4)E 0 11 ( l.1 i .4)E O (-7.4 t 3.7)E-1 ZR-95 ( 24) 15. !.it
(-1.8 - 3.7)E O (-3,0 - 1.5)E O
( 0) (-1.8 - 3.7)E O
- ( 0/ 12)+ e( 0/ 12)e *( 0/ 12H AG-!!0Mt 24) ( -3.4f 2.5)E -1 21 (-6.2 i 32.6)E -2 (-6.2 t 32.6)E -2 r (-2.6 - 1.4)E O
( 0) (-1.7 - 1.5)E 0 (-2.6 - 1.4)E O
[ *( 0/ 12)*
- ( 0/ 12)* *( 0/ 12)*
- NONf0VTIE REFERS TO TE PUBER OF SEPARATE EASlFEENTS leilCH ERE OREATER THAN TEN (10) T!ES TE AVERACE BACXCROLND FOR TE PER100 0F TE RERRT.
H T)E FRACTICH CF SNPLE #RYSES Y!ELDl'4 KTECTAILE EASLREENTS (I.E. >3 STD E VIATIONS) IS INDICATED WITH *( )*.
' _39 i
s E)WIROMOTAL RADIMICAL PROCRM Strf%RY
- YN#'EI IUlEM POER STATION. RM f%
JfdlARY - DECD 9ER 1937
' WITS: FCI/KG ED!W: RIWR WATER STATION WITH HIGEST M CtXTROL STATIONS L INDICATOR STATIONS HM*HMM* MMH *H MMMMe * *H'H+ H + + + H H H H H e**H e EAN EAN M RAD!WUCLIDES RANCE (0,ANALYES) REQUIRED RANGE
( (NON-ROUTIE)' LLD NO. DETECTED **
STA.
W.
RANGE NO. IETECTED** NO. CETECTEDee RU-103 ( 24) ( -1.2t .3)E O 21 (-9.3 1 40.9)E -2 (-9.3 t 40.9)E -2
(-2.6 - .3)E O (-2.8 - 1.6)E O (-2.8 - 1.6)E O
( 0)
- ( 0/ 121e et 0/ 12)e *( 0/ 12)*
( -2.3t 3.7)E O 21 (-2.0 t 2.6)E O (-2.0 t 2.6)E O RU-106 ( 24)
(-2.0 - 2.2)E 1 (-2.4 - .9)E 1 (-2.4 - .9)E 1
( 0)
- ( 0/ 12)e et 0/ 12)* *( 0/ 12)*
8.7 7.3)E -1 11 ( 8.7 1 7.3)E -1 (-1.8 1 1.2)E 0 I-131 ( 24) (
.4)E 1
( 0) (-4.6 - 5.4)E O (-4.6 - 5.4)E O (-1.1 -
- ( 0/ 121e *( 0/ 12)* *( 0/12)*
(-5.0 t 2.0)E -1 (-5.0
- 2.0)E -1 CS-134 ( 24) 15. ( -7.6t 2.0)E -1 21
(-1.9 - .1)E O (-1.7 - .4)E O (-1.7 - .4)E O
( 0)
- ( 0/12)* *( 0/ 12)* *( 0/ 12)e CS-137 ( 24) 18. ( l.lt 2.3)E -1 11 ( l.1 t 2.3)E -1 (-3.6 i 27.7)E -2
(-1.3 - 1.2)E O (-l.3 - 1.2)E O (-1.8 - 1.7)E O
( 0)
- ( 0/ 12)* st 0/ 12)* *( 0/ 121e BA-140 ( 24) 15. ( -7.St 6.1)E -1 21 (-7.6 1 6.0)E -1 (-7.6 i 6.0)E -1
(-6.5 - 2.2)E O (-5.1 - 2.6)E O (-5.1 - 2.6)E 0
( 0)
- ( 0/ 12)e e( 0/ 12)* *( 0/ 12)*
' ( -6.0t 7.2)E -1 21 (-3.3 t 5.6)E -1 (-3.3 t 5.CE-1 CE-141 ( 24)
(-4.4 - 2.9)E O (-3.4 - 3.2)E 0 (-3.4 - 3.2)E O
( 0)
- ( 0/ 12)* *( 0/ 12)e *( 0/ 12)*
CE-144 ( 24) ( -4.!t 10.4)E -1 11 (-4.1 i 10.4)E -1 (-2.0 t 2.2)E O
( 0) (-9.0 - 3.7)E O (-9.0 - 3.7)E 0 (-2.1 - .6)E 1
- f 0/ 12)* st 0/ 12)* et 0/ 12)e H-3 ( 8) 2000. ( 2.82 1.7)E 2 11 ( 2.8 t 1.7)E 2 (-1.2 i .9)E 2
( !) (-1.2 - 7.3)E 2 (-1.2 - 7.3)E 2 (-2.6 - 1.3)E 2
- ( 1/ 4)* *( 1/ 4)* *( 0/ 4)*
(
e NON-ROUTIE FGERS TO M M.PIEG 0F SEPMATE EASWDOTS lei!CH NEE GREATER T)%N TEN (10) TIES M AWRAE BACXCROWD FOR M PERIOD OF M REKRT.
- M FRACTION OF S#fLE #% LYSES Y!ELDIE DETECTAILE EASWDOTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *( 16 g
~
3.9 Sediment L
Sediment cores were collected semiannually from two locations.
Each core was separated into 5 cm segments, which were analyzed f
for ganna-emitting radionuclides. Cesium-137 was detected in most camples. The levels measured at the indicator location were consistent with what has been measured in the previous several years (see Figure 3.5) and are attributed to nuclear weapons
( testing fallout.
Other than naturally occurring K-40, Be-7, and Th-232, no other gamma-emitting radionuclides were detected in 1987 sediment samples.
i t
3 2918R/23.218 f - - - - - - - - - - - - - - - - - - - --------
FIGURE 3.S CESIUM-137 IN SEDIMENT YANKEE ATOMIC ELECTRIC COMPRNY, ROWE, MR sooo 4500- O - SE-11 NO. 4 STA., 0-5 CM O - SE-11 NO. 4 STA., 5-10 CM A - SE-11 10-IS CM
+ - SE-21 NO.4STA.ES., 0-S CM -
HRRRIMAN R 4000 ~ X - SE-21 HARRIMAN RES., S-10 CM o - SE-21 HRRRIMHN RES., 10-IS CM y 3soo-l E 3000- -
, ai 0' S G 2soo-N EO g 2000-B o
S 1sco-n.
2000-i
"~
/ .
< W/ %/ ' RNy 0 .... . . . . . . . . . . h. . . . . .
1982 1983 1984 1985 1986 1987 1980 2981
__ o
ENVIR0ldOTAL RADIOLOGICAL PROCRAM SuttARY YMEE NUllEAR POER STATICN. RCWE M JANUARY - DECD BER 1987 (MITS: PCl/r0 DRY EPil?t: SEDIENT STATION WITH H10EST M CtNTROL STATIONS INDICATOR STATIONS mm.*m .mt m m *** m *** m ** m ** t m . m ** m ***
M M M RAD 10lullDES (NO. AMLYSES) REQUIRED RANCE STA. RME RANGE NO. NO. DETECTED ++ NO. DETECTED ++
(NOG-ROUTIEl' LLD N0. DETECTED **
( 12) ( l.3t .9)E 2 11 ( l.3 i .9)E 2 ( 3.4 i 19.2)E 0 BE-7
(-4.7 - 55.9)E I (-5.0 - 5.7)E 1
( 0) (-4.7 - 55.9)E I
- ( 1/ 6)* *( 1/ 6)* *( 0/ 6)*
l.2k .1)E 4 21 ( l.4 t .1)E 4 ( l.4 i .1)E 4 K-40 ( 12) (
( 0) ( l.0 - 1.3)E 4 ( !.0 - 1.0)E 4 ( !.0 - 1.8)E 4
- ( 6/ 616 *( 6/ 6)* *( 6/ 6)*
( -9.3t 3.6)E O 11 (-9.3 t 3.6)E O (-1.3 i .2)E I O-54 ( 12) (-2.0 - .7)E 1
( 0) (-2.5 - .2)E I (-2.5 - .2)E 1
- ( 0/ 6)* *( 0/ 6)* *( 0/ 6)*
s
( -6.21 1.9)E O 21 ( 8.2 i 21.5)E -1 ( 8.2 t 21.5)E -1 CD-58 ( 12)
( 0) (-1.3 - .2)E 1 (-5.2 - 8.3)E 0 (-5.2- 8.3)E 0
- ( 0/ 6)* *( 0/ 6)* *( 0/ 6)*
( -1.21 .6)E 1 21 (-0.3 1 13.6)E 0 (-8.3 t 13.6)E 0 FE-59 ( 12) 2.5)E 1
(-2.9 - .9)E 1 (-4.6 - 2.5)E 1 (-4.6 -
( 0) 0/ 6)*
- ( 0/ 6)* *( 0/ 6)* *(
( -3.42 2.1)E O 21 (-2.8 t 3.2)E O (-2.8 1 3.2)E O CO-M ( 12) (-l.4 - .7)E 1
( 0) (-8.7 - 5.9)E 0 (-1.4 - .7)E 1
- ( 0/ 6)* *( 0/ 6)* *( 0/ 6)*
!.42 .8)E 1 11 ( l.4 i .8)E 1 (-3.2 t 7.5)E 0 N 65 ( 12) (
(-2.7 - 1.7)E 1
( 0) (-3.8 - 45.2)E O (-3.8 - 45.2)E 0
- ( 0/ 6)* *( 0/ 6)* *( 0/ M6
( 4.0t 7.2)E 0 21 ( !.8 i .9)E I ( l.8 t .9)E 1 ZR-95 ( 12)
(-1.5 - 3.1)E 1 (-5.7 - 51.1)E 0 (-5.7 - 51.1)E O
( 0)
- ( 0/ 6)* *( 0/ 6)* *( 0/ 61*
4.0)E 0 ( 3.7 i 4.0)E 0 (-3.4 t 4.5)E O AG-110Mt 12) ( 3.7* 11
( 0) (-7.3 - 13.6)E O (-7.3 - 13.6)E 0 (-2.2- 1.1)E 1
- ( 0/ 6)* *( 0/ 6)* *( 0/ 6)*
- N0HDUTIE RETIRS TO M IO9ER OF SEPARATE EASURDDTS IMICH ERE REATER TWAl TEN (10) TIES M A'4 RACE BACXmf1M) FOR M PERIOD F M REPmi.
- . M FRACil0N F SMPLE NLYSES Y!ELDING IETECTABLE EASLRDOTS (1.E. >3 STD DEVIATIONS) !$ ICICATED WITH *( )*.
E)NIROWOfiAL FMD10 LOGICAL FROGRM SIMMRY J YN6IE WCLEAR POER STATION. ROE f%
JAM.lARY - EE)SER 1987
( LMITSt PCI/KG DRY MEDIUM: SEDI M STATICH WITH HIGEST M C0NTRCL STATIONS 12 1CATOR STATIONS uneme m**m H++mem***me nme mummH+H M M M i%DIONJCLIDES
( O. ANALYSES) GIED RNE STA. RNE R#dCE NO. 10.ILTECTED*e NO. ETECTEDH (N0K-90llTIEP LLD 10. DE'ECTEDH
( -4.8t 4.0)E 0 21 ( 3.4 i 3.5)E 0 ( 3.4 t 3.5)E O RLF103 ( t2)
( 0) (-1.9 - .8)E 1 (-3.5 - 19.2)E 0 (-3.5 - 19.2)E 0
- ( 0/ 6)* *( 0/ 6)* et 0/ 6)*
( -6.3t 3.1)E 1 21 (-3.6 t 3.1)E 1 (-3.6 t 3.1)E I f0-106 ( 12) .3)E 2
(-1.7 - .7)E 2 (-1.8 - .3)E 2 (-1.8 -
( 0)
- ( 0/ 6)e *( 0/ 614 *( 0/ 6)e
( -2,4i 2.1)E 1 11 (-2.4 t 2.1)E I (-8,5 t 1.1)E 1 1-131 ( 12) .4)E 2
( 0) (-1.0 - .4)ti 2 (-1.0 - .4)E 2 (-1.1 -
et 0/ 6)e et 0/ 6)* e( 0/ 6)*
( -4.5 421.4)E -2 21 ( 2.6 t 4.0)E O ( 2.6 t 4.0)E 0 CS-134 ( 12) 150.
( 0) (-l,4 - 1.1)E I ( 8.7 - 18.2)E O (-8.7 - 18.2)E O at CI 6)e *( 0/ 6)* *( 0/ 6)*
CS-137 ( 12) 180. ( 1.92 .2)E 2 21 ( 5.7 t 3.2)E 2 ( 5.7 t 3.2)E 2
( 0) ( !.2 - 2.8)E 2 ( 3.3 - 2000.0)E 0 ( 3.3 - 2000.0)E 0 et 6/ 6)* *t 4/ 6)e *( 4/ 6)*
( -2.9 1.41E 1 11 (-2.9 t 1.4)E 1 (-5.0 t .9)E 1 BA-140 ( 12)
( 0) (-8.0 - 2.4;E 1 (-8.0 - 2.4)E I ( 7.5 - -2.7)E 1
- ( 0/ 6)e *( 0/ 6)e et 0/ 6)*
E -141 ( 12) ( 2.4t .71E 1 !! ( 2.4 i .7)E 1 ( l.2 i .9)E I
(-1.0 - 3.7)E 1 (-1.0 - 3.7)E I (-2.1 - 3.4)E 1
( 0)
- ( 0/ 6)e *( 0/ 6)* *( 0/ 6)*
E 144 ( 12) ( -6.92 1.2)E 1 21 (-4.1 1 2.5)E I (-4.1 t 2.5)E 1
( 0) (-9.8 - -2.0)E 1 (-1.1 - .5)E 2 (-1.1 - .5)E 2
- ( 0/ 614 et 0/ 6)* *( 0/ 6)e
( 7.0i 4)E 2 11 ( 7.0 t .4)E 2 ( 5.3 t 4)E 2 TH-232 ( )2)
( 0) ( 5.6 - 8.3)E 2 ( 5.6 - 8.3)E 2 ( 4.6 - 7.2)E 2
- ( 6/ 6)* *( 6/ 6)e et 6/ 6)*
f e N0H0llTIE FGERS TO M MMER CF SEPARATE EMEMS IMICH ERE @ EATER l T)W( TEN (10) TIES M AGCE BACKm0LND FOR M PERIOD CF M REPET.
H TE FRACTION OF SNRE #MLYSES YlELDIE DETECTABLE EAST.REENTS (l.E. >3 STD DEVIATIONS) IS INDICATED WITH *( le.
j 3.10 Finfish
)
l Fish samples were collected semiannually from two locatioas.
Each vas analyzed for gamma-emitting radionuclides.
[
Cesium-137 was deter ted in all samples. Over the past several years, the levels haso been comparable between Station FH-11 and /
Station FH-21 fif., as can be seen in Figure 3.6. These levels are consistent with well-documented environmental levels and are
( attributed to nuclear weapons testing f allout.
Other than Cs-137 and naturally occurring K-40, no gamma-emitting
' radionuclides were detected in 1987 fish samples.
f I
< 2918R/23.218 f .
-: ~ - .
FIGURE 3.6 CESIUM-137 IN FISH YRNKEE RTOMIC ELECTRIC COMPANY, ROWE, MR se f
l zn- l l
a D - FH-11 SHERMf1N POND l 0 - TH-21 HflRRIMflN RESERVOIR l
E 2*~
5 S
- G N
250 -
0 E
B \s l
8 E 100- \
as 50-
/
\,
o ......... ................. ............
,,,,,,,,,.........................L ......n.........
JMMJ OD MMJ DD M 11 19G2 J DD MMJ 1983 OD MMJ 1984 DD MMJ 1985 OD MMJ 3906 DD MMJ 1987 0 1980 1981 e
ENVIROGUTAL IMD10LLCICAL FPO@AM RfmARY Y#6IE NUC1. EAR POER STATIM. kOWE. M J#llWtY - KCD9ER 1987 L
(JNITS PCI/KO ET EDIL*(' FN191 s
STATION WITH HIGEST M C0NTROL STATICN3 1910AT E STATI MS m n+n++m mee m m + m e n m e n u n +4 mmememn 6 M M 1%D10M.ICLIES (NO. #tALYSES) EMED RNCE STA. RW.E IMNCE NO. NO. DETECTED ++ NO. ETECTEDn (NON-440(JllE)' LLD NO. DETECTED +e l.2t .5)E 1 ( !.2 i .51E 1 (-4.8 t 7.5)E 1 BE-7 ( 4) ( 11
(-1.2 - .3)E 2
( 0) ( 6.4 - 16.9)E 0 ( 6.4 - 16.9)E 0
- ( 0/ 2)* *( 0/ 2)e et 0/ 2)*
( 2.71 .1)E 1 ( 2.9 i .1)E 3 ( 2.9 t .1)E 3 X-40 ( 4) 21 3.0)E 3
( 0) ( 2.6 - 2.8)E 1 ( 2.7 - 3.0)E 3 ( 2.7 -
- ( 2/ 2)e et 2/ 2)e et 2/ 2)e IN. ( -6.3t 3.5)E O 21 ( 5.0 t 741.0)E -2 ( 5.0 t 741.0)E -2 191-54 ( 4)
(-9.8 - -2.9)E O (-7.4 - 7.5)E O (-7.4 - 7.5)E O
( 0)
- ( 0/ 2)e et 0/ 2)e et 0/ 2)e
( -5.2t 4.2)E 0 21 (4.8t 2.9)E 0 i 4.8
- 2.9)E o CO-58 ( 4) 130.
7.7)E O
( 0) (-9.4 - ,9)E 0 ( l.9 - 7.7)E O (!.9-
- ( 0/ 2)* et 0/ 2)e *( 0/ 2)e
( -2.2t 1.7)E 1 21 ( !.6 i .3)E I ( l.6 i .3)E i FE-59 ( 4) 260.
( 0) (-3.9 - .5)E 1 ( l.3 - 1.8)E 1 ( l.3 - 1.8)E 1
- ( 0/ 2)* et 0/ 2)e *( 0/ 2)*
CD-60 ( 4) 130. ( 2.lt .2)E 0 11 ( 2.1 * .2)E O (-3.8 t 11 2)E 0
( 0) ( l.9 - 2.3)E 0 ( !.9 - 2.3)E 0 (-1.6 - .8)E I
- ( 0/ 2)e et 0/ 214 et O! 21e
( -3.41 37.3)E-1 11 (-3.4 t 37.3)E -1 (-2.0 t 10.0)E 0 ZN-65 ( 4) 260.
.8)E !
(-4.1 - 3.4)E 0 (-4.1 - 3.UE 0 (-1.2 -
( 0) et 0/ 2)* st 0/ 216 et 0/ 2)e ZR-95 ( 4) ( -2.8t .5)E 0 21 ( 7.0 t II.0iE O ( 7.0 t !!.0)E 0
( 0) (-3.3 - -2.2)E O (-4.0 - 18.0)E 0 (-4.0 - 18.0)E 0 et 0/ 2)* *( 0/ 2)e e( 0/ 2)e AG-110Mt 4) ( -5.5t 3.6)E O 21 ( 7.9 t 12.2)E 0 ( 7.9 t 12.2)E 0
( 0) (-9.1 - -1.9)E 0 (-4.3 - 20.1)E 0 (-4.3 - 20.1)E O et )/ 21e et 0/ 2)* e( 0/ 2)*
- NON-ROLJTIE REFUtS TO M NLMEF. CF SEPARATE EASLRUOTS WICH OE @ EATER THAN TEM (10) TIES M AGA02 BACXmalDO FOR M FERIOD OF M FOtYtT.
- M FRACTION OF SNRE #iALYES YlE1. DIE DETECTAILE EASURDO!!S
(!.E. >3 STD LEVIATIONS) is INDICATED WITH et )*.
EWIIDOOTAL RADIOLOO!CA(, i9t0GM 9.te%RY
) YAEE NJCLEAR F00 STAT!C% RWE. MA
) JAN # Y - KCD 9ER 1987 WITS FCI/KG ICT ED!W: FIE19(
INDICATOR STA!! WS STATI(N WITH H10EST EM CalTRa. STAT!00 mmmmut*** meenumtemumne *mmmnem EAN EM EM RADI(MILIDES STA. RNE RMCE (NO. M LYSES) EQUIRD RANE
- 10. NO. DETECi Die NO. DETECTED **
(NOBHIOUTIEl' LLD 10. ETECTED+e RJ-103 ( 4) ( -1.4t 2.3)E 0 21 ( !.0 1 22.5)E-1 ( l.0 t 22.5)E -1
( 0) (-3.8 - .9)E 0 (-2.1 - 2.4iE 0 (-2.1- 2.4)E O
- ( 0/ 2)e *( 0/ 21e *( 0/ 2)*
( -1.5t .3)E 1 11 (-1.5 t .3)E 1 (-2.3t .3)E I RD-106 ( 4)
(-1.9 - -1.2)E i (-1.9 - -1.2)E 1 (-2.6 - -2.0)E 1
( 0)
- ( 0/ 2)* *( 0/ 2)* *( 0/ 2)*
( -1.6t 2.5)E 1 (-l.6 t 2.5)E i (-2.9 i 6.2)E 1 l-131 ( 4) 11
.9)E 1 (-9.1 - 3.4)E 1
( 0) (-4.1 -
.9)E i (-4.1 -
4( 0/ 2)* et 0/ 2)* et 0/ 2)*
( -2.3t 7.5)E 0 21 (-1.8 t 6.0)E 0 (-1.0 t 4.0)E 0 CS-134 ( 4) 130.
4.2)E O
(-9.8 - 5.1)E O (-7.7 - 4.21E 0 (-7.7 -
( 0) at 0/ 2)* et 0/ 2)* et 0/ 2)*
( 5.5t 3.2)E 1 11 ( 5.5 t 3.2)E 1 ( 3.3 .0)E 1 CS-137 ( 8) 150.
( 2.3 - 8.7)E 1 < 2.3 - 8.7)E 1 ( 3.3 - 3.3)E 1 f 0)
- ( 2/ 2)* it 2/ ?)* *( 2/ 2)*
( -2.5t .8)E I 21 (-2.3 t 2.9)E O (-2.3 t 2.9)E 0 M-140 ( 4) (-5.2- .6)E O
( 0) (-3.3 - -1.8)E 1 (-5.2 - .6)E 0
- ( 0/ 216 et 0/ 2): *( 0/ 214 E-141 ( 4) ( l.02 .7)E 1 !! ( l.0 t .7)E I ( 9.3 i .4)E C
( 3.9 - 16.9)E O ( 3.9 - 16.9)E 0 ( 8.9 - 9.7)E O
( 0)
- ( 0/ 2)e *( 0/ 2)e et 0/ 2)*
E -144 ( 4) ( -2.11 .9)E 1 11 (-2.1 t .9)E I (-3.4 i 2.2)E 1
( ol (-3,0 - -1.2)E 1 (-3.0 - -1.2)E 1 (-5.5 - -1.2}E 1
- ( 0/ 2)* *( 0/ 2)e et 0/ 2)e TM-232( 4) ( -6.7t 14.4)E O 21 (-5.8 t 19.4)E O (-5.8 t 19.4)E 0
( 0) (-2.1 - ?)E 1 (-2.5 - 1.4)E 1 (-2.5- 1.41E 1
- ( 0/ 2)e *( 0/ 2)* *( 0/ 2)*
- NON-ROUTIE REFERS TO M IOEER OF SEPMATE EASWDOTS lHICH IDE CREATER T)WI TDi (10) TIES M AGGE EACKGRLAND FOR M FGIOD OF M REMRT.
- M FRACTION OF S#ftE AMLYES Y!EU) LNG DETECTAELE EASPDDTS (I.E. >3 STD DEVIATIONS) IS IM)!CATED WITH *( le.
{ - - _ ----
s
('
L 3.11 Direct Radiation Direct gama radiation exposure was determined f rom the use of thermoluminescent dosimeters (TLDs). Specifically, Panaconic UD-801AS1 and UD-B14AS1 calcius sulfate dosimeters were used, with a total of five elements in place et each monitoring location. A total of thirty-eight stations is required by the Radiological Effluent Technical Specifications. TLDs from twenty-two must be read out quarterly, wh!.le those f rom the remaining sixteen incident response (outer ring) stations need only be de-dosed (annealed) quarterly, unless a gaseous release LCO was exceeded during the period. During 1987, all TLDs were routinely readout on a quarterly schedule. Table 3.1 provides a P summary of the results. Figures 3.7 to 3.12 show the TLD results graphically.
Distinct annual cycles can be seen in the 'lLD data from each category of monitoring station (see Figures 3.7 to 3.12). The lowest point of the cycle occurs during the vinter months. This is due primarily to the attenuating effect of the snow cover during those months. The effect is not as noticeable with the fenceline TLDs, since the plant contribution to radiation levels at these sites tends to obscure seasonal fluctuations in the environment. The fenceline where TLDs are situated is located well within the site boundary.
Station GM-5 has had a significantly higher exposure rate than other nonsite boundary stations, as can be seen in Table 3.1 and Figu e 3.3. This is consistent with the results of the in situ f
analytis at the station performed in October of 1984 and September of 1987.
As can be seen in Figure 3.11, elevated exposure rates were noted at several on-site locations during the first quarter of 1981.
This was believed not to have been caused by plant activities, and was discussed in Reference 4.
2918R/23.218 f - - - _
Due to drainage improvement landscaping along the south plant i.
/ fence line during mid-1987, TLD Stations GM 19 and GM-20 had to be relocated. The change in location was minical, however, and is considered insignificant with res.pect te distance f rom the plant (the azimuth of each location remained the same).
Missing TLDs: The following measurements were missing due to apparent theft in the field:
- a. GM-33, first quarter;
- b. GM-34, third quarter; These TLDs were at outer ring-incident response stations whcre readout is not required (since a gaseous release LCO was not exceeded during these periods).
f
(
2918R/23.218 t
- - - ~ - -
FIGURE 3.7 EXPOSURE RATE AT INDICATOR TLDS, GM 01-07 j YRNKEE RTOMIC ELECTRIC COMPRNY, R0WE, MR 2a ,
1 28- O - GM-01 FURLON HOUSE i 0 - GM-02 083ERVRTION STRt!D l
A - GM-03 ROWE SCHOOL
- s- + - GM-04 HRRRIMBN STRION X - GM-OS MONRGE BRIDGE o - GM-06 READSBORO RD. BRRRIER g_ V - GM-07 WHITINGHHM LINE 5
g 12-
~
10- e a
' ' '~ ~ '
8- h _' Q, 6- 4 \ 'l 4-2-
0 . , , .. ,,,,,. ,,..,,,,,, .,,, ,,.,,,.,,...,,,,.,
1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1976
_ _ _ _ __ _ __ m- m - - .
FIGURE 3.8 EXPOSURE RATE AT INDICRIOR TLOS, GM 08--12,40 YANKEE RTOMIC ELECTRIC COMPANY, ROWE, MR 20 28' O - GM-08 MONRDE HILL BRRRIER o - GM-09 DUNBRR BROOK A - GM-10 CROSS RORD
- 6- -+. - GM-11 ADRMS HIGH LINE X - GM-12 READSBORD, VT o - GM-40 RERDSBORO RORD
- 4 -
c" Q
S:2-
- \
l 0, 5
7 3
- a. .o. W , s 5 f l,}
y l f
- y .. ,' .
g' & ,
6-q _.
21 I' 'IV I ' 'IY I ' 'IV I' ' 'IV I ' 'IV I ' 'IV I ' ' 'I/ I ' ' 'li I ' ' 'Ii l '1985'IV I1986
' ' 'Il l ' 'IV 1987 1977 1978 1979 1980 IS81 1982 1983 1984 1976
- - - - - - - - -- - . - ~ -
FIGURE 3.9 EXPOSURE RATE AT GUTER RING TLOS, GM 24-31 YANKEE ATOMIC ELECTRIC COMPANY, R0WE, MR 20
- s~
D - GM-24 HRRRIMAN DRM o - GM-25 HHITINGHAM VT A - GM-26 SRDOGRROR6
- 5 -- + - GM-27 NUMBER 9 ROAD X - GM-28 NUMBER 9 ROAD o - GM-29 ROUTE 8A V - GM-30 ROUTE BR l
- 4 l 2 - GM-31 LEGRTE HILL RORD I
3, 4' 6 a.
' ;g_
x .
b O h
r d- ,-
1 :
I 4-2 --
D. ., ,. .
IV I .IY I IV IV I IV I..
.IV I I .IV I IV I.. .IV I,. .IV I IV I IV I..
1980 1981 1982 1983 1984 1985 1986 1987 1976 1977 1978 1979
FIGURE 3.10 EXPOSURE RATE AT OUTER RING TLDS, GM 32-39 YANKEE RTOMIC ELECTRIC COMPRNY, ROWE, MR 20
- s- D - GM-32 ROWE RORD o - GM-33 ZORR RORD A - GM-34 FIFE BROOK ROAD
'6- -f- - GM-35 WHITCOMB SUMMIT X - GM-36 TILDH ROAD j o - GM-37 TURNER HILL RORD ;
- 4- V - GM-38 WEST HILL RORD j ts - GM-39 ROUTE 100 4
52 9 .
e / ?. .
I k 5 O y , s '
' t;
- g. y4 / .
- w:
r
/
6-4-
2--
0 .. .
IV I IV I . .IY I IY I IV I IV IV I .IV I..
I .IV I IV I.. IY I .IV I..
1984 1985 1986 1987 1978 1979 1980 1981 1982 1983 1976 1977
FIGURE 3.11 EXPOSURE RATE AT FENCELINE TLDS, GM 13-21 YRNKEE ATOMIC ELECTRIC COMPANY, R0WE, MR oo D - GM-13 WSW 0.08 KM 5' O - GM-14 WNW 0.11 KM O A - GM-15 NNW 0.08 KM So_
+ - GM-16 NNE d.13 KM X - GM-17 ENE 0.14 KM o - GM-18 ESE 0.14 KM 45- V - GM-19 SE 0.16 KM M - GM-20 SSE 0.16 KM M - GM-2; SSW 0.11 KM j.:
40- 1; l '
I / 1 S 35 - f' '\ l 30- \ /
l-jm_ g
~I pf
%/(jf t'
, M -f , '.A g 1 LY lg - 'i 5-I' 'IE I ' 'IE I ' 'II I ' 'IY I ' 'IE I ' I/ I' 'IYIl 'I/ I 'III ' ' 'IY I " ' 'I/ I' 'IV 1980 1981 1982 1983 1984 1985 1986 1987 1976 1977 1978 1979
FIGURE 3.12
) EXPOSURE RATE AT CONTROL TLDS, GM 22-23 YRNKEE RTOMIC ELECTRIC COMPRNY, ROWE, MR 20
- s- O - GM-22 HEflRTWELLVILLE, VT ,
o - GM-23 HILLIf1MSTOW!1 SUBSTflTIOtt
- 6-
- 4-5:
a 2 -- &
I G E
"- :D - -
n .
g .
a u
)
h e-r 9 1 0
6-4-
2-I' 'II I ' 'II I ' 'IV I ' 'I/ I ' 'IV I ' 'III ' ' 'IE I' ' 'IE I ' IEI' Idl IEI' IV 1961 1982 1983 1984 1985 1986 1987 1976 1977 1978 1979 1983
4 Environmental Radiological Program Summary Yankee Nuclear Power Station, Rowe, Massachusetts
/ January - December 1987
[
Units: Micro-R per Hour Medium: Direct Radiation Measurements (TLD)
( Control Indicator Outer-Ring Restricted Area Fence Stations Stations St_ations Mean Mean Mean Mean Range Range Range Range (No. Meas.)* (No. Meas.)* (No. Meas.)*
(No. Meas.)*
7.0 ! 1.2 6.9 1 1.4 15.8 1 4.6 7.7 2 1.4 4.6 - 9.7 4.0 - 9.4 9.3 - 25.1 5.3 - 10.0 (62) (36) (8)
(52)
C All measurements based on the mean of five readings per station (quarterly readout).
2918R/23.218
Table 3.1
' Summary of Direct Radiation Measurements - 1987 s.
(Micro-R Per Hour) {
r l First Second Third Fourth Yearly Quarter Quarter Quarter Quarter Mean Station Distance (km) Direction GM-1 0.8 SW 6.3 8.5 7.6 7.7 7.5 GM-2 0.5 NW 5.0 7.5 7.0 7.1 6.7 GM-3 4.2 SE 4.6 6.6 6.1 5.7 5.8 (
GM-4 3.2 N 5.3 7.9 6.6 6.7 6.6 GM-5 1.1 SW 6.7 9.7 8.8 9.0 8.6 GM-6 1.3 N 5.3 8.5 7.8 7.7 7.3 GM-7 3.5 NE 4.7 7.7 6.6 6.6 6.4 GM-8 1.8 S 5.1 7.7 7.1 7.0 6.7 GM-9 3.2 SW 5.3 8.0 7.2 7.3 7.0 GM-10 3.5 E 4.8 7.7 7.0 6.7 6.6 GM-11 2.1 kNW 5.6 8.7 8.2 7.8 7.6 J GM-12 5.5 NNW 5.8 8.5 7.4 7.6 7.3 GM-13 0.08 WFW 14.0 15.7 17.1 17.8 14.1 GM-14 0.11 L7N 9.3 11.5 12.2 11.8 11.2 GM-15 0.08 NNW 10.2 11.6 11.7 12.5 11.5 GM-16 0.13 NNE 11.6 13.1 13.0 12.5 12.6 GM-17 0.14 ENE 11.8 15.2 15.3 15.0 14.3 GM-18 0.14 ESE 19.8 24.0 25.1 24.7 23.4 GM-19 0.16 SE 15.6 23.1 25.0 24.2 22.0 GM-20 0.16 SSE 12.1 17.5 17.2 17.4 16.1 GM-21 0.11 SSW 12.3 15.4 16.4 15.7 15.0 GM-22 12.6 NNW 5.3 8.7 7.6 7.3 7.2 GM-23 22.2 W 6.9 10.0 8.0 7.9 8.2 GM-24 7.3 N 5.9 8.7 8.2 8.3 7.8 GM-25 7.7 NNE 4.9 6.9 6.6 6.6 6.3 GM-26 7.6 NE 4.6 7.5 6.9 6.9 6.5 GM-27 7.6 ENE 4.4 7.0 6.4 6.5 6.1 ~#
GM-28 6.0 E 5.2 7.4 7.2 7.3 6.8 GM-29 8.2 ESE 4.0 6.0 5.4 5.5 5.2 GM-30 9.4 SE 4.5 6.5 6.5 6.3 6.0 GM-31 7.6 SSE 5.0 7.4 6.8 6.6 6.5 GM-32 7.9 S 5.3 7.1 6.5 6.6 6.4 GM-33 6.9 SSW
- 8.5 7.5 7.6 7.9 GM-34 6.4 SW 7.1 8.9
- 9.4 8.5 GM-35 8.6 WSW 5.0 8.0 7.7 7.3 7.0 GM-36 6.6 W 4.9 8.3 7.6 7.4 7.1 i GM-37 6.7 WNW 5.1 8.8 8.1 7.7 7.4 GM-38 6.6 NW 5.2 9.3 8.8 8.5 8.0 GM-39 6.8 NNW 5.9 9.4 8.6 8.8 8.2 GM-40 0.5 W 4.7 7.8 7.5 7.1 6.8
\
/
2918R/23.218
/4
/
3.12 In Situ <
d In situ gamma spectrometry analyses were performed at seven r
locations on September 22 and 23, 1987. Camma 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 these seven .
f.
locations and analyzed at the YAEL for comparison to the in situ analyses.
The nate. rally-occurring radionuclides K-40 Th-232, 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.
2918R/23.218
w.
w' ,
, Table 302 Summary of In Situ Soil Analyses ,
Exposure Rate (pR/hr) + 1 Std. Dev.
- HPIC Location Cs-137 K-40 1.210.1 9.912 9 10.110.6 Furlon House .0251.007 2.720.1 2.310.1 Rowe School .131.01 1.910 1 1.610.1 .781.04 7.911 2 8.910 4 Harriman Station .151.01 2.410.1 .2.110.1 .861 06 9.21 4 1~ a.710.5 8.721.2 9.310.6 Monroe School .14 .01 2.210 1 1.720.1 .991 05 2.0+0.1 1.2+0.1 .80+.05 7.8+1.1 8.9+0.6
& Observation Stand .19+.01 -<
E y 2.6 0.1 1.610.1 10.6 1.4- 11.010.4 j Monroe Bridge 171.01 2.710.1 9.710.5' )
l Williamstown .152.01 2.710.1 2.610 1 1.410 1 10.511.4 l .
l 0 Includes 3.6 pR/hr cosmic contribution.
2918R/23.218
v 4.0 QUALITY ASSURANCE P?.0 GRAM Three separate Quality Assurance programs were performed during 1987 to demonstrate the va'.idity of laboratory analyses by the Yankee Atomic
[
Environmental Laborcrory (YAEL).
t YAEL participat.s in the EPA Interlaboratory Comparison (cross-check) program for those speci;s and matrices routinely analyzed by the laboratory.
This provides an indepen'ent check of accuracy and precision of the laboratory f
analysis. When the resul.s of the cross-check analysis fall outside of the control limit, an investig, tion is made to determine the cause of the problens and corrective measures are taken, as appropriate.
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 analysis 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 Yankee Atomic, are prepared from homogenous media and sent to the laboratory for analyais. The results from this blind duplicate program are used to check for precision in laboratory analyses.
Intralaboratory and EPA Interlaboratory 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 1987 for intralaboratory 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.
2918R/23.218
Table 4.1 Intralaboratory and EPA Interlaboratory Results - 1987 Accuracy Total Number 0 to 5% 0 to 10% 0 to 15%*
of Measurements 729 450 637 701 (61.7%) (87.4%) (96.2%)
Precision Total Number 0 to 5% 0 to 10% 0 to 15%*
of Measurements 721 623 703 718 (86.4%) (97.5%) (99.6%)
- This category also contains those samples having a verified zero concentration which were analyzed and found not to contain the isotope of interest.
2918R/23.218
The results of the EPA Interlaboratcry Comparison program, when considered apart from the remainder of the Quality Assurance program, were satisfactory with respect to accuracy and precision in 1987. One hundred and
[
sixty-eight analyses were performed on air particulate filters, milk, food, urine, and water. Based upon this sample analysis total, 166 analyses (i.e., 99.0 percent) met the EPA's definition of mean value criteria. The ,
sample analyses thtt did not meet the criteria were a Ru-106 analysis in a water sample t,nd a gross beta analysis, also in a water sample. A recount of the beta samples yielded measurements that met the above criteria. (Details f
of this may be found in References 2 and 3.)
Blind Duplicate Program A total of 49 paired samples were submitted by the five participating plants for analysis during 1987. The data base used for the duplicate analysis consisted of paired measurements of 26 ganna-emitting 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 been met. If the value falls outside of the ! 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 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 groundwater, 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 acceptance 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.
2918R/23.218 l
- _ _ - _ _ _ _ - _ _ _ _ _ _ _ - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____a
5.0 LAND USE CENSUS Specification 3/4.12.2 of the Radiological Effluent Technical
[
specifications requires that a land use census.be conducted after June 1 and before October 1 of each year. The census is used to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the sixteen meteorological sectors within a distance of five miles. The 1987 census was completed within the above dates. The distance and direction from f
the plant for each of the above locations are shown in Table 5.1.
The land use census for this reporting period identified two milk animal locations which yielded a calculated dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from which samples are currently being obtained in accordance with Technical Specification 3.12.1. Specifically, these milk animal locations were found at WNW, 1.9 km and NE, 3.7 km. Neither location, however, would be able to provide samples of sufficient size over an extended period due to the small number of milking cows owned. Consequently, the two existing locations. TM-12 and TM-13, were kept as official sampling locations (see Technical Specification 3.12.2.b).
No garden locations were identified that yielded a calculated dose or dose commitment at least 20 percent greater than that at the existing food crop sampling locations. Consequently, the food crop sampling locations wer.e not changed in 1987 as a result of the Land Use Census.
Following the census, Technical Specification 3.12.2.a requires the identification in the Semi-Annual Effluent Release Report of any location (s) identified in the census which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.11.2.3. No such locations were identified.
2918R/23.218
Table 5.1 Yankee Atomic
- 1987 Land Use Census Results s Nearest Nearest Nearest Residence Milk Animal Garden Sector (km) (km) (km)
N 2.4 6.1 3.5 NNE 4.7 - 4.7 NE 3.7 3.7 3.7 ENE 3.1 8.4 3.1 E 3.1 -
3.1 ESE 3.4 -
3.4 SE 2.3 -
2.3 SSE 2.1 -
2.9 S 2.3 -
2.3 SSW - - -
SW 1.3 -
1.3 WSW 1.3 -
1.3 W 1.9 -
2.7 WNW 1.9 1.9 1.9 NW 0.45 -
4.6 NNW 2.9 -
3.9 2918R/23.218
6.0
SUMMARY
During 1987, samples collected as part of the radiological environmental monitoring program at Yankee Atomic showed detectable levels of
' man-made radionuclides in cow milk, groundwater, river water, sediment, finfish, and maple syrup. The H-3 detected in groundwater (Station WC-12, Sherman Spring) and river water (Station WR-ll, Bear Swamp Lower Reservoir) was the only radionuclide possibly related to plant operations. Since water from the spring or the Deerfield River is not consumed by man, there would be no impact on man from the low levels detected. The dose to an imaginary person who consumed large quantities of the above water was calculated, however, to set an upper bound to the possible consequences of the measured environmental levels of H-3. In both cases (river and groundwaters), the dose to man was negligible when compared to natural background radiation and its yearly fluctuations.
The other man-made radionuclides were due either to residual fallout from nuclear weapons tests conducted in the 1970s and 1980, or fallout from the Chernobyl nuclear plant accident in April and May of 1986. In summary, there was no observable impact on the environment from plant operations.
2918R/23.218
7.0 REFERENCES
- 1. USNRC Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," 1977.
- 2. Yankee Environmental Radiation Measurement Laboratory Quarterly Status Report, April-June 1987, Yankee Atomic Electric Company.
- 3. Yankee Enviror. mental Radiation Measurement Laboratory Quarterly Status Report, October-December 1987, Yankee Atomic Electric Company.
- 4. Yankee Atomic Electric Company, Annual Radiological Environmental Operating Report, January-December 1986.
d 2918R/23.218 L
e p>
- Telephone (617) 872-8100
- f, TWX 710-380-7619 YANKEE ATOMIC ELECTRIC COMPANY y% _
1671 Worcester Road, Framingham, Massachusetts 01701 April 29, 1988 FYR 88-61 United States Nuclear Regulatory Commission r Document Control Desk Washington, DC 20555
Reference:
(a) License No. DPR-3 (Docket No. 50-29)
Subject:
Annual Radiological Environmental Operating Report
Dear Sir:
Enclosed herewith please find the Annual Radiological Environmental ,
Monitoring Report for the Yankee Nuclear Power Station. This report contains a summary and analysis of the radiological environmental data collected for the year 1987 and is submitted a. required by Technical Specification 6.9.5(a).
We trust that you will find this submittal satisfsetory; however, if you have any questions, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY
[
Georg[e Papanic( Jr.
Senior Project Engineer - Licensing GP/25.569 Enclosure cc: USNRC Region I ^
USNRC Resident Inspector, YNPS
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