ML20073G362
| ML20073G362 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1990 |
| From: | Tremblay L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-91-48, NUDOCS 9105030269 | |
| Download: ML20073G362 (82) | |
Text
, __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _
VERMONT YANKEE NUCLEAR POWER CORPORATION
..- M-4 % ,
Ferry Road, Drattleboro. VT 0$3017002 ,
I,') ENGINEERING OfTICE Lt:0 MA!N biF4f [ f (OL1M M A ct?40 (b3in 7 'p ( 't 1 6
April 30,199i BYY 91/48 -
United States Nuclear Regulatory Commission ATrN: Document Control Desk Washington, DC 20$55
References:
- a. License No. DPR 28 (Docket No. 50 271) ,
Subject:
Vermont Yankee Annual Radiological Environmental Surveillance Report
Dear Sir:
Enclosed please find one copy of the Annual Radiological Envirenmental Surveillance Repon for Vermont Yankee Nuclear Power Station, submitted in accordance with Technical Speel0 cation -
6.7.C.3. This report contains a summary and analysis of the radiological environmental data collected for the calender year 1990.
Should you have any questions regarding this submittal, please contact this office, Very truly yours, ,
VERMONT YANKEE NUCLEAR POWER CORPORATION hb@ A M r.
Leonard A.Tremblay,Jr. \
Senior Licensing Engineer cc: USNRC Region 1 Administrator
. USNRC Resident inspector - VYNPS USNRC Project Manager VYNPS ,
9105030269 901231 PDR ADOCK 05000271 R- POR [g tp
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I VERMONT YA!EEE NUCLEAR POWER STATION VERMO!4T YA!MEE NUCLEAR POWER CORPORATION ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT January - December 1990 I
= April 1991 I
I I
Prepared By; Yankco Atomic Electric Company
'I Environmental Engineering Department 580 Main Street Bolton, Massachusetts 01740 I
I
i -
I IMLLOLCONTRilS I l' age 111 LIST OF TABLES....................................................
iv LIST OF FIGURES...................................................
I
1.0 INTRODUCTION
I 2
1.0 ENVIRONMENTAL SURVEILLANCE PR0 GRAM................................
13 3.0
SUMMARY
OF 1990 RADIOLOGICAL ENVIRONMENTAL DATA...................
15 I A.
B.
C.
Air Particulaa ...............................................
Charcoal Filter...............................................
M11k..........................................................
20 22 30 Mixed Vegetation..............................................
I D.
E.
F.
Silage........................................................
Groundwater...................................................
35 38 43 G. River Water...................................................
48 H. Sediment......................................................
5 1. Fish..........................................................
51 55 J. In Situ.......................................................
57 K. Direct Radiation..............................................
76 4.0 QUALITY ASSURANCE PR0 GRAM.........................................
80 5.0 LAN D U S E C EN S U S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
82 6.0
SUMMARY
I I
1 I
I I
I WFP12/26 1
I
?
.I LISLOLIMLLS iI I
Numher lille face 3
2.1 Radiological Environmental Surveillance Program. . . . . . . . . . . . .
4 2.2 Radiological Environmental Surveillance Locations. . . . . . . . . . .
2.3 Environmental Direct Radiation Monitoring Locations......... $
Summary of In Situ Measurements............................. 56 3.1 Sungnary of Direct Radiation Measurement s . . . . . . . . . . . . . . . . . . . . 60 3.2 Intralaboratory and EPA Interlaboratory Results - 1990...... 79 4.1 81
$.1 1990 Land Use Census Results................................
I E
I I
I I
I I
i 1
I WPP12/26
-111-I I
LigZ Or FICy}1$
1 Number Il11e l'ase I 2.1 Environmental Radiological Monitoring Locationn in Close Proximity to P1 ant.......................................... 7 Environmental Radiological Monitoring Locations Within I 2.2 5 Kilometers of P1 ant....................................... 8 2.3 Environmental Rediological Monitoring Locations Greater Than $ Rilometers from P1 ant................................ 9 8
2.4 TLD Locations in Close Proximity to Plant................... 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 on Air Particulate Pilters.......... 16 3.2 Gross-Beta Measurements on Air Particulate Filters.......... 17 3.3 C e s i um - 1 3 7 i n M 1 1 k . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 3.4 Cesium-137 in M11k.......................................... 24 3.5 Strontium-90 in Milk.. ..................................... 25 I 3.6 Strontium-90 in M11k........................................ 26 3.7 Cesium-137 in Mixed Grasses................................. 31 3.8 Cesium-137 in Mixed Grasses................................. 32 3.9 Gross-Beta Measurements on Ground Water..................... 39 3.10 Gross-Beta Measurements on River Water...................... 44 3.11 C e s i wn- 13 7 i n F i s h . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 3.12 Exposure Rate at Indicator TLDs, DK 01-03................... 62 3.13 Exposure kate at Indicator TLDs, DR 04, 06, 50.............. 63 3.14 Exposure Rate at Site Boundary TLDs, DR 07-08, 41-42........ 64 3.15 Exposure Rate at Site Boundary TLDs, DR 43-46............... 65 3.16 Exposure Rate at Site Boundary TLDs, DR 47-49, 51........... 66
-iv-WPP12/26 I
I
I Llil_.QE_.ElGURES i (Continued) 1 HumbcI lille lagt 3.17 Exposure Rate at Inner Ring TLDs, DR 09-15 (0dd)............ 67 1
3.18 Exposure Rate at Inner Ring TLDs, DR 17-23 (0dd)............ 68
- 3.19 Exposure Rate at Inner Ring TLDs, DR 25-31 (0dd)............ 69 3.20 Exposure Rate at Inner Ring TLDs, DR 33-39 (0dd)............ 70 3.21 Exposure Rate at Outer Ring TLDs , DR 10-16 (Even ). . . . . . . . . . . 71 3.22 Exposure Rate at Outer Ring TLDs, DR 18-24 (Even)........... 72 3.23 Exposure Rate at Outer Ring TLDs , DR 26-32 (Even ) . . . . . . . . . . . 73 3.24 Exposure Rate at Outer Ring TLDs, DR 34-40 (Even)........... 74 3,25 Expos ure Ra t e a t Cor t rol TLD, DR-05. . . . . . . . . . . . . . . . . . . . . . . . . 75 t
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-v-
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. 1.0 IN HO ECH ON f The radiological envirotutiental surveillance program at the Vermont Yankee Nuclear Power Station has been designed and carried out with specific S 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 y
of the nucicar power station.
- To provide assurance to regulatory agencies and the public that the station's environmenta impact is known and within anticipated limits.
- To verify the adequacy and proper functioning of station effluent 1 controls and monitoring systems.
- To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.
During 1990, as in the past, Aquatec. Inc. collected all of the aquatic eovironmental samples, while the plant Chemistry staff collected the bulk of the terrestrial environmental samples (including ground water) and the I environmental thermoluminescent dosimeters (TLDs) for direct radiation measurements. AfLer the initial processing, all samples were sent to the Yankee Atomic Environmental Laboratory in Westborough, Massachusetts for I
- further processing and radionuclide analysis. TLDs were also sent to this laboratory for processing.
This report is a summary of the findings of the Radiological Environmental Surveillance Program for 1990. It is being provided in compliance with plant Technical Specification 6.7.C.3.
WPP12/26
I 2.0 MMOL0rdCAL14UROHt1Ltil&lVMELLudiCE_fAQGEM in this section Table 2.1 senarizes the surveillance program as required by plant Technical Specification 3.9.0. Table ?. 2 lists the sampling I 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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t I WPp12/26 I l I
!I IMIL211 RadiologicaLEnvironmentaLSurnillance_Eregram YermanLXankeeluclear Power station I tiedia Sampling.,Erequency Required _Analyns Gross beta I Air Particulate (AP) -
Semimonthly (2)
Quarterly Composite Gamma spectroscopy Charcoal Filter (CF) - Semimonthly (2) Iodine-131 Milk (m ) - Monthly (6) Gamma spectroscopy, Iodine-131 Mixed Vegetation (TC) - Quarterly (1) Ganana spectroscopy Silage (TC) - Annually (3) Gamma spectroscopy Groundwater (WG) - Quarterly Ganuna s pec t ros copy , 11-3 River Water (WR) - Monthly (5) Gamma spectroscopy
- Quarterly Composite H-3 Sediment (SE) - Semiannually Gamma spectroscopy Fish (FH) - Semiannually Gamma spectroscopy Direct Radiation (DR) - Quarterly Integrated gamma dose (4) 1 I
I I (1) Collection frequency dependent upon availability of samples during winter.
(2) Weekly, when main plant stack effluent release rate of Iodine-131 is I equal to or greater than 0.1 uC1/sec.
(3) Collected at harvest time in reasonable proximity to specified location; subject to availability.
(4) -Outer ring TLDs - De-dose quarterly unless gaseous release LCO was exceeded in period.
(5) Composite sample collected over month at downstream location.
(6) Semimonthly when milk animals are identifled as being on pasture.
I -WPP12/26 j I
I I BB1LL2 Radiological EnvironmentaLSurrailliuttelo. cations Yenoont_XankerJiuclear_hrer_ Station I Distance From Plant Direction Stack From Plant S.tation Code ZQnc* (km) S. tack __
Diedia - Stadh_) Station Descriptier AP/CF/TG-11 River Station No. 3.3 1 1.9 SSE N. Ilinsdale , Nil 1 3.6 NNW l
E AP/CF/TG-12 AP/CF/TG-13 Hinsdale Substation 1 3.1 E AP/CF/TG-14 Northfield, MA 1 11.3 SSE I AP/CF/TO-15**
AP/CF/TG-21 Tyler Hill Road Spofford Lake, Nil 1
2 3.2 16.1 WNW NNE 0.8 WNW I m -11** Miller Farm 1 TM-12** Dominick 1 5.2 E TM-13 Newton Farm 1 5.1 SSE m -14 Brown Farm 1 2.6 S I m -16 m-19**
m-20 Tall Oaks Farm Mitchell Farm Ranney Farm 1
1 2
4.7 4.0 17.0 WNW NNE 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 Rt. 9 Bridge 2 12.8 Upriver i
WR-21 Fil-11 Vernon Pond 1 -- On-Site Fil 21 Rt. 9 Bridge 2 12.8 Upriver SE-11 Shoreline Downriver 1 0.8 On-Site SE-12 N. Storm Drain Outfall 1 0.15 On-Site TC-11** Miller Farm 1 0.8 WNW TC-12** Dom.inick 1 5.2 E TC-13 Newton. Farm 1 5.1 SSE I TC-14 TC-16 TC-19**
Brown Farm Tall Oaks Farm Mitchell Farm 1
1 1
2.6 4.7 4.0 S
WNW NNE TC-20 Ranney Farm 2 17.0 N
- 1 = Indicator Station; 2 = Control Station.
I ** This location is not considered a requirement of Technical Specification Table 3.9.3.
g 5 WFP12/26 I ,
I
l TABLE 2.3 Environmental Direction Radiation Monit011ng LocatiQng V.grmont Yankee Nuclear Power Station Distance Direction From Center From of Turbine Center I Slalipn Code Diedia - Sta. Noj Station Description IQnt*
Building (km) of Turbine Building DR-1 River Station No. 3.3 1 1.6 SSE DR-2 N. Hinsdale, NH I 3.9 NNW DR-3 Hinsdale Substation I 3.0 E I DR-4 DR-5 DR-6 Northfield, MA Spofford Lake. NH Vernon School I
0 I
11.0 16.3 0.46 SEE NNE WSW SB 0.27 W I DR-7 Site Boundary DR-8 Site Boundary SB 0.25 SW DR-9 Inner Ring I 2.1 N DR-10 Outer Ring 0 4.6 N I DR-11 DR-12 DR-13 Inner Ring Outer Ring Inner Ring I
0 I
2.0 3.6 1.4 NNE NNE NE 4.3 I Outer Ring 0 NE DR-14 DR-15 Inner Ring I 1.4 ENE DR-16 Outer Ring 0 2.9 ENE DR-17 Inner Ring I 1.2 E I DR-18 DR-19 DR-20 Outer Ring Inner Ring Outer Ring 0
I 0
3.0 3.5 5.3 E
ESE ESE I DR-21 DR-22 DR-23 Inner Ring Outer Ring Inner Ring 0
I I
1.8 3.2 1.8 SE SE SSE Outer Ring 0 3.9 SSE I DR-24 DR-25 9R-26 Inner Ring Outer Ring I
0 2.0 3.7 1.0 S
S SSW DR-27 Inner Ring I I DR-28 DR-29 DR-30 Outer Ring Inner Ring Outer Ring L
0 1
2.2 0.7 2.3 SSW WSW SW 0.8 I Inner Ring DR-31 I 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 I DR-35 DR-36 Inner Ring Outer Ring 0 I 1.4 4.7 WNW WNW I
WPP12/26 l
I
IAELL3 (Continued)
EnY1rcamental_Ilirgstion RadiallotLMQailoringlocailons Eermon tJanken_Nuc l e arlow e r_St a t ion Distance Direction I Sintion Code From Center of Turbine Building From Center of Turbine Ricdia - S t a . No . } SigtLion DescrID11Dn Inng* ()tm) _hnilding_
DR-37 Inner Ring I 3.0 NW l DR-38 Outer Ring 0 7.7 NW
! DR-39 Inner Rin6 I 3.2 NNW DR-40 Outer Ring 0 5.8 NNW DR-41** Site Boundary SB 0.38 SSW DR-42** Site Boundary SB 0.60 S
[I
- DR-43**
DR-44**
Site Boundary Site Boundary SB SB 0.42 0.21 SSE SE DR-45** Site Boundary SB 0.12 NE i
- DR-46** Site Boundary SB 0.29 NNW
DR-50**
DR-51**
Site Boundary Governor ilunt flouse Site Boundary SB I
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.I lI I- .
- I = Inner Ring; O = Outer Ring; SB = Site Boundary.
- This location is not considered a requirement of Technical Specification
-Table 3.9.3.
WPP12/26 I
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3.0 $1ElaL9F__1SLQD RADLQL0glCAL_INylgoNMDQL.JETA The following pages summarize the analytical results of the environmental samples which were collected during 1990. Each environmentcl media category is presented as a separate subsection. A discussion of the I sampling program and results is followed by a table which summarizes the year's data for each category. At the top of each table are listed 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 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 specified in Technical Specification Table 4.9.3.
Those sampling stations which are adjacent to the plant and which could cccceivably be af fected 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.
A set of statistical parameters is calculated for each radionuclide.
This set of statistical parnmeters includes separate analyses for (1) the indicator stations, (2) the control stations, and (3) the station having the highest annual mean concentration for that radionuclide. For each of these three groups of data, these parameters are as follows:
o The mean value of all concentrations, o The standard error of the mean.
o The lowest and highest concentration.
WPP12/26
I o The number of positive msasurements (a concentration which is greater than the L.pnsittitri LLD f or that analysis) divided by the total number of measurements.
I i
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 statistics), and not the propagation of all possible uncertainties in the analytical procedure.
I Pursuant to Technical Specification Table 4.9.3 (Footnote f ), any concentration below the LLD for its analysis is reported as "not detected."
-I These values are set to zero for averaging purposes. Where a range of values l
is reported in the tables of this section, values less than the n_posteriori LLD for the analysis are reported as zero.
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ypp12/26 I
I
A) Air Particulate I Air monitoring stations were established at a total of six locations (five are required by Technical Specifications). Five of I these locations are indicators, while the remaining one is a l
control station. Airborne particulates are collected by passing the air through a glass-fiber filter. These filters are collected bi-weekly and are 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.
Naturally occurring Be-7 was detected on all quarterly composite samples. Bi-weekly gross-beta counts (Figures 3.1 and 3.2) showed I random fluctuation throughout 1990 et indicator stations and controls, thereby indicating that any plant contribution was I
negligible. Several unusually low concentrations in 1990, as shown in Figures 3.1 and 3.2, were due to unknown causes. Each of the low measurements was confirmed with a recount. A slightly but noticeably higher gross-beta measurement for the week of May 15 to May 29 at AP-13 (see Figure 3.1) was due to a gas meter I- malfunction. As such, it cannot be considered a valid measurement.
There were two interruptions in the air particulate sampling program during 1990. The sampler at AP-13 was out of service for approximately 27.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (May 29-30) during the replacement of a malfunctioning gas meter. The sampler at AP-11 was out of service for approximately 16 days (between September 25 and October 12).
I On September 25, it was discovered that power was out at the location due to tree limbs having fallen on the electrical wires.
I- The hour meter for the sampler indicated that the power had been interrupted earlier that day. Repairs to restore power to the site were completed and the sampler resumed operation on October 12.
WPP12/26 I
I
mm m ee M M M M M M M M M .m m a e a Figure 3.1 GROSS BETA MEASUREMENTS ON AIP PARTICULATE FILTERS
- VERMONT YANKEE NUCLEAR POWER STATION -
, , i e i * * * ' '
. _ ,' i
.O.000 i O.070-- __
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E
I ENylRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
YERMONT YANKEE NUCLE AR POWER STAi!ON, VERNON, VI I MEDIUM: AIR PARTICULATE (JANUARY DECEMBER 1990)
UNITS: PCl/CV. M
- I INDICATOR STAil0NS eeeeeeeeeeeeeeeeee STAfloh WitH HIGHEST MEAN eeeeeeeeeeeeeeeeeeeeeeeee CONTROL STAil0NS eeeeeeeeeeeeeee.
RADIONUCLlDES MEAN MEAN MEAN (NO, ANALYSES) REQUIRED RANGE $1A. RANGE RANCE (NON ROVI!NE)* LLD NO. DETECTED ** NO. No. OETECTED** No. DETECTED **
- I. CR B (156) .01 ( 2.2 0.0 -
0.1)E 2 4.4)E 2 12 (
(
2.2 s 0.1)E 2 8.6 - 32.0)E 3
(
(
1.9 a 0.1)E 2 8.5 - 29.3)E 3
( 0) (
- (129/130)* *( 26/ 26)* *( 26/ 26)*
4 BE 7 ( 24) ( 4.9 1 0.4)E 2 15 ( 5.4 1.2)E 2 ( 5.1 0.8)E 2 i
( 0) ( 2.2 - 9.0)E 2 ( 3.7 - 9.0)E 2 ( 3.3 - 7.2)E *2 I
- ( 20/ 20)* *( 4/ 4)* *( 4/ 4)*
K 40 ( 24) ( 0.0 s 0.0)E O ALL EoVAL ( 0.0 s 0.0)E O I
- ( 0/ 204* *( 0/ 4)*
MN 54 ( 24) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O
( 0) l *( 0/ 4 )*
4 *( 0/ 20)*
Co 58 ( 24) ( 0.0 a 0.0)E O ALL EQUAL ( 0.0 4 0.0)E O
( 0)
!I *( 0/ 20)* *( 0/ 4)*
FE 59 ( 24) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 e 0.0)E O 5l
- g
( 0)
- ( 0/ 20)* *( 0/ 4)*
CO 60 ( 24) ( 0.0
- 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O
( 0)
- ( 0/ 20)* *( 0/ 4)*
ZN 65 ( 24) 0.0 t 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O I
(
( 0) i *( 0/ 20)* *( 0/ 4)*
0.0)E O I 0.0)E 0 2R 95 ( 24) ( 0.0 1 ALL EQUAL ( 0.0 m -
( 0)
- ( 0/ 20)* *( 0/ 4)*
- NON ROVilNE REFERS 10 THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGRoukD FOR THE PERICO OF THE REPORT.
- THE FRACil0N OF SAMPLE ANAL,YSES YlELDING DETECTASLE MEASUREMENTS (1.E. >3 STD DEVIA110HS) IS INDICATED WITH *( )*.
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I ENVIRONMENTAL R ADIOLOGICAL PROGRAM
SUMMARY
VERMani 1 ANKEE NUCLE AR POWER ST A110N, VERNON, VI (JANUARY
- DECEMBER 1990)
MEDIUM: AIR F AR11CUL ATE Uhl18: PCl/CU M INDICATOR $1A110NS STAtl0N Vllh H]GHEST MEAN CONTROL $1AT10h5
.................. eeeeeeeeeeeee,eeeeeeeeeee eeeeeeeeeeeeeee.
. RADIONUCLlDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANOE SIA. RANCE RANGE (NON ' ROVil WE )* LLD N0. DETECTED ** Wo. Wo. DETECTED ** NO. DE TECTED**
AG 110M( 24) ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O
( 0)
! *( 0/ 20)* *( 0/ 4)*
l RU-103 ( 24) ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 a 0.0)E O ,
- ( 0) l
- ( 0/ 20)* *( 0/ 4)* j
!" RU 106 ( 24) ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 a 0.0)E O
( 0)
- *( 0/ 20)* *( 0/ 4)*
SB 124 ( 24) ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 s 0.0)E D
( 0)
- ( 0/ 20)* *f 0/ 4)*
, CS 134 ( 24) .05 ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O
- ( 0/ 20)* *( 0/ 4)*
CS 137 ( 24) .06 ( 0.0 s 0.0)E O ALL toVAL ( 0.0 0.0)E O
- ( 0)
- ( 0/ 20)* *( 0/ 4)*
- 6A 140 ( 24) ( 0.0 a 0.0)E D ALL toVAL ( 0.0 s 0.0)E O
- ( 0)
- ( 0/ 20)* *( 0/ 4 )*
CE 141 ( 24) ( 0,0 s 0.0)E O ALL EoVAL ( 0.0 t 0,0)E O l
( 0)
- *( 0/ 20)* *( 0/ 4)*
CE 144 ( 24) ( 0.0 1 0.0)E O ALL EQUAL ( 0.0 4 0,0)E O
( 0)
- ( 0/ 20)* *( 0/ 4 )*
TH 232 ( 24) ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O
- ( 0)
- ( 0/ 20)* *( 0/ 4)*
f g
- NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER 4 THAN TEN (10) TIMES THE AVERAGE BACKCROUND FOR THE PERIOD OF THE REPORT.
" THE FRACTION OF SAMPLE ANALTSES Yl[LDlkG DETECTABLE MEASUREMENTS (1.E. 23 STD DEVIATIONS) IS INDICAIED WlIH *( )*.
lI -se.
I
. I B) ChattanLfilters I Charcoal filter cartridges are situated in series with the air particulate glass-fiber filters. Monitoring stations were I established at a total of six locations (five are required by Technical Specifications). Five of these are indicators and one is a control. Charcoal filters from the air sampling stations were collected and analyzed bi-weekly for 1-131 activity.
I During 1990, no I-131 was detected on charcoal filters.
I There were two interruptions in the charcoal filter sampling program during 1990. The sampler at CF-13 was out of service for I approximately 27.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (May 29-30) during the replacement of a malfunctioning gas meter. The samples at CF-11 was out of service for approximately 16 days (between September 25 and October 12).
On September 25, it was discovered that power was out at the location due to tree limbs having fallen on the electrical wires.
The hour meter for the sampler indicated that the power had been interrupted earlier that day. Repairs to restore power to the site were completed and the sampler was returned to operation on October 12.
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I
I ENV!RONMENTAL RADIOLOGICAL PROORAQ $UMMARY VERMONT YANKEE NUCLEAR POWER $1A110N, VERNON, VI I MEDIUM: CHARCOAL FIL1ER (JANUART
- DECEMBER 1990)
UN!!$1 PCl/CU. M I INDICA 10R $1A110NS e...eeeeeeeeeeeeee
$1All0N Wl1H NIGNE$1 ME AN seeeeeeeeeeeeeeeeeee.....
CONTROL STA110N$
I RADIONUC(IDES (ND. ANALYSE $)
(NON'ROU11NE)*
REQUIRED LLD MEAN RANCE N0. DETECTED"
$1A.
No.
MEAN RAkCE No. DETECTED **
MEAN RANCE NO. DETECTED" 1 131 (156) .07 ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O
( 0)
- ( 0/130)* *( 0/ 26)*
I
- NON ROUTINE REFER $ 10 THE NUMBER OF $EFARATE MEA $UREMENil WHICH WERE GREATER I "
THAN TEN (10) 11MES THE AVERACE IsACKGROUND FOR THE FERIOD OF THE REPORT.
1HE FRAC 110N OF SAMPLE ANALY$il flELDING DETECI ABLE HEASUREMEWi$
(1.E. >3 STD DEVIA110NS) l$ INDICATED W11H *( )*.
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C) tiin Milk samples were collected and analyzed monthly for low level 1-131 and gamma-emitting radionuclides. Monthly samples were
- composited quarterly and analyzed for Sr-89 and Sr-90 (not a Technical Specification req;irement). Semi-monthly sampling was done at Stations 2 -12, E-14, and m -20 when the cows were on pasture.
I Following the Land Use Census in 1990, the Mitchell Farm ( m -19) was added to the milk sampling program (for goat milk). Due to limited availability, samples will only be collected there as available.
I Detectable concentrations of Cs-137 and Sr-90 were measured in milk samples submitted from most indicator locations during 1990. As shown in Figures 3.3 and 3.4. concentrations were similar to those detected in previous years. The two new locations (m -12 added to the progtam in 1989 and m-19 in 1990) show significant levels of Cs-137 and Sr-90 also. The detected levels are consistent with those measured in cow milk and goat milk at other New England locations and are not believed to be caused by plant emissions.
I Such levels have been well documented and are attributed to fallout from nuclear weapons tests, although Cs-137 levels after May 1986 were elevated somewhat due to Chernobyl-related fallout.
L Differences between dairy farms can be attributed to differences in feeding practices between farms. A much higher transfer coefficient for Strontium and Cesium (from vegetation to milk) for goats alta causes greater Sr-90 and Os-137 concentrations in goat milk.
In addition to these radionuclides, naturally occurring K-40 was detected in all samples. No I-131 was detected in any of the samples.
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- VERMONT YANKEE NUCLEAR POWER STATION -
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Uh!!!: PCl/KG I INDICATOR STA110NS stall 0N WITH HIGHEST MEAN CONTROL stall 0NS e...............
I RADIM UCLIDES (NO. AhALYSES) REQUIRED (NON ROUTINE)* LLD MEAN RANGE No. DETECTED **
STA.
No.
MEkN RANGE No. DETECTED **
MEAN RANGE No. DETECTED" SR 89 ( 25) ( 0.0 2 0.0)E D ALL EQUAL ( 0.0 1 0.0)E 0
( 0)
- ( 0/ 21)* *( 0/ 4)*
I SR 90 ( 25)
( 0)
(
(
2.4 0.0
- 0.4)E O 6.0)E D 12 (
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5.0 t 3.3 -
0.6)E 0 6.0)E O
(
(
1.0 s 0.0 -
0.6)E O 2.0)E 0
- ( 16/ 21)* *( 4/ 4)* *( 2/ 4)*
BE 7 (100) ( 0.0 1 0.0)E D ALL EQUAL ( 0.0 a 0.0)E O
( 0)
- ( 0/ 81)* *( 0/ 19)*
K 40 (100) ( 1.5 1 0.0)E 3 12 ( 1.9 0.0)E 3 ( 1.3 1 0.0)E 3
( 0) ( 10.0 - 21.5)E 2 ( 1.5 - 2.2)E 3 ( 1.2 - 1.4)E 3 I MN 54 (100) (
- ( 81/ 81)*
0.0 1 0.0)E O
- ( 19/ 19)*
ALL EQUAL (
- ( 19/ 19)*
0.0 t 0.0)E O I
( 0)
- ( 0/ 81)* *( 0/ 19)*
Co 5B (100) ( 0.0 a 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O I ( 0)
- ( 0/ 81)* *( 0/ 19)*
FE 59 (100) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O I ( 0)
- ( 0/ 81)* *( 0/ 19)*
CO 60 (100) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O I ( C)
- ( 0/ 81)* *( 0/ 19)*
ZN 65 (100) ( n.0 1 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O I' ( 0)
- ( 0/ 81)* *( 0/ 19)*
NON ROVIINE REFERS TO THE NUMBER OF SEPARATE MEASUREMrNIS WHICH WERE GREATER THAN T!N (10) IIMES THE AVERAGE BACKGROUND FOR THE PERICO OF THE REPORI.
- iHE FRe CTI0ts OF SAMPLE ANALYSES YlELDING DETECTA8LE MEASUREMENTS (I J.. >3 STD DEV! Afl0NS) IS INDICATED WITH *( )*.
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SUMMARY
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VERMONT Y ANKEE NUCLE AR POWER ST ATION, VERNON, Vi l l
(JANUARY
- DECEMBER 1990)
MEDIUM: MILK UNITS PCl/KG INDICATOR STATIONS STAT 10N WifM HIGHEST MEAN CONTROL stall 0NS RADl0NUCLIDES MEAN MEAN MEAN (NO. AAALYSES) REQUIRED RANCE S(A. RANGE RANGE (NON*ROVilNE)* LLD No. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **
ZR 95 (100) ( 0.0 a 0.0)E O ALL EQUAL ( 0.0 a 0.0)E O
( 0)
- ( 0/ 81)* *( 0/ 19)*
AG.110M(100) ( 0.0 a 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)E O
( 0)
- ( 0/ 81)* *( 0/ 19)*
I RU 103 (100)
( 0)
( 0.0 s 0.0)E O ALL EQUAL ( 0.0 t 0.0)E D
- ( 0/ 81)* *( 0/ 19)*
1 RU 106 (100) ( 0.0 a 0.0)E O ALL EQUAL ( 0.0 a 0.0)E O
- ( 0/ 81)* *( 0/ 19)*
SB 124 (100) ( 0.0 1 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O
- ( 0/ 81)* *( 0/ 19)*
1 131 (100) 1. ( 0.0 a 0.0)E O ALL EQUAL ( 0.0 t 0.0)E D
( 0)
I CS 134 (100) 15. (
- ( 0/ 81)*
0.0 a 0.0)E O ALL EQUAL (
- ( 0/ 19)*
0.0 1 0.0)E O I
( 0)
- ( 0/ 81)* *( 0/ 19)*
CS 137 (100) 18. ( 2.3 2 0.5)E O 12 ( 6.4 t 1.6)E O ( 0.0 a 0.0)E 0 I ( 0) ( 0.0 -
- ( 21/ 81)*
2.8)E 1 ( 0.0 *
- ( 11/ 19)*
2.8)E 1
- ( 0/ 19)*
BA 140 (100) 15. ( 0.0 a 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O I ( 0)
- ( 0/ 81)* *( 0/ 19)*
0.0 1 0.0)E O 0.0 1 0.0)E O I
CE 141 (100) ( ALL EQUAL (
( 0)
- ( 0/ 81)* *( 0/ 19)*
NON ROUTINE REFERS 10 THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE CREATER THAN TEN (10) TIMES THE AVERACE BACKGROUND FOR THE PERIOD OF THE REPORT.
- THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (I.E. >3 STD DEVIATIONS) l$ (NDICATED WITH *( )*.
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I ENVIRONMENTAL kAD10 LOGICAL PROGR M
SUMMARY
VERM0h1 Y ANKEE NUCLE AR POWER ST A110N, VERNON, VT I MEDIUM: MILK (JANUARY DECEMSZR 1990)
UN!1t: PCl/KG I INDICATOR $1A110h5
$1A110N WlIH NIGHEST MEAN
........................e CONTROL STAtl0NS MEAN I RADIONUCLIDES MEAN MEAN RANCE $1A. RANGE RANGE (No. ANALYSES) REQUIRED LLD NO. DETECTED" k0. NO. DETECTED" NO. DETECTED" (NON ROVIINE)*
CE 144 (100) ( 0.0 a 0.0)E O ALL EQUAL ( 0.0 a 0.0)E O E ( 0)
- ( C/ 81)* *( 0/ 19)*
" TH 232 (100) ( 0.0 a 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O
- ( 0/ 81)* *( 0/ 19)*
- WON *R0011NE REFERS 10 THE NUMBER OF SEPARATE MEASUREMEN15 WHICH WERE GREATER I "
THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERICO OF THE REPORT.
THE FRAC 110N OF SAMPt,E AkALYSES YlELDlWG DETECTABLE MCASUREMENTS (1.E. >3 STD DEylA110NS) l$ INDICATED W11H *( )*.
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I D) tibu:LXtst1Alion Mixed vegetation samples were collected during May, July, and September irom the six air satopling locations. Sarnples were not available during the winter months. The vegetation consisted of various types of grasses and were analyzed for gamma emitting I nuclides. The results of the gamma spectroscopy analysis on each sarnple showed that, in addition to naturall/-occurring Be-7 on most satoples and K-40 on all samples, Cs-137 was detected on two sarnple s . The levels detected in 1990 are consistent with those nicasured in previous years, as shown in 'r'igures 3.7 and 3.8. and ere believed to be caused by nuclear weapons testing fallout that has persisted in the environment. The highest measured value for 1990 at Station T0-11 is approximately two percent of the reporting level for Cs-137 in vegetation given in Technical Specification I Table 3 9.4. The highest level for any station over the five-year period shown in Figures 3.7 and 3.8 was a single quarterly measurement in 1988 at Station 70-15. This measurement was approximately 9 percent of the reporting level. (These comparisons are only made to put the values in perspective. Reporting levels apply only to radionuclides emitted from the plant.)
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- DECIMBER 1990)
MEDlVM: M11tD Vitt1 A110N UN118: PCl/RG Vt1 INDICA 10R $1 All0kl $1A110N W11H HlCHill MEAN CONTROL $1 AllDk$
eeeeeeeeeeeeeeeese e eeeeeeeeeeeeeeeeeeeeees e eeeeeeeeeeesse MIAN RADIONUCL ibt s MEAN MEAN
$1A. RANGt RAW 0t (WD. AkAlt$tt) RIOUIRED RAW 0t (WON kouttkt)' LLD WD. OttititD h0. Wo. OtitC1LD WO. OtttCILD*'
$t.7 ( 18) ( 2.5 0.8)t 2 21 ( 6.5 a 2.4)E 2 ( 6.5 t 2.4)t 2
( 0) ( 0.0 - 8.1)t 2 ( 3.3 - 11.2)E 2 ( 3.3 - 11.2)E 2
- ( 7/ 15)* '( 3/ 3)* '( 3/ 3)*
.I. E 40 ( 18) ( 5.3 s 2.8 -
0.3)t 3 6.8)t 3 21 (
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( 0) (
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I MN 54 ( 18)
( 0)
( 0.0 a 0.0)t 0 ALL touAL ( 0.0 a 0.0)E D
- ( 0/ 15)* *( 0/ 3)*
Co 58 ( 18) ( 0.0 s 0.0)t 0 ALL touAL ( 0.0 a 0.0)t 0
- ( 0/ 15)* '( 0/ 3)'
it 59 ( 18) ( 0.0 s 0.0)t 0 ALL touAL ( 0.0 a 0.0)! 0
( 0)
- ( 0/ 15)* *( 0/ 3)'
CD 60 ( 18) ( 0,0 0.0)t 0 ALL touAL ( 0.0 s 0.0)t 0
( 0)
'( 0/ 15)* *( 0/ 3)*
2N 65 ( 18) ( 0.0 t 0.0)! O ALL touAL ( 0.0 t 0.0)t 0
( 0)
'( 0/ 15)* *( 0/ 3)'
2R 95 ( 18) ( 0.0 t 0.0)t 0 ALL touAL ( 0.0 t 0.0)t 0
( 0)
- ( 0/ 15)* '( 0/ 3)*
AG 110M( 18) ( 0.0 t 0.0)! O ALL touAL ( 0.0 s 0.0)t 0 I ( 0)
- ( 0/ 15)* *( 0/ 3)*
- WON *R0011ht RtitR$ TO THE WUMBit OF $EPARAll MEASUREMEWi$ WHICH WERE CRI AllR 1HAN TEN (10) 11 MIS THE AVERA0E BACKCROUND FOR THE PERICO OF THE REPORT.
1HE FRAC 110h 0F SAMPLE AhALY5t$ fl!LDlhG DtitCI ABit MEASUREMENil (1.E. >3 $1D ttVI A110N5) IS INDICA 1[D W11H '( )'.
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i (EVlROMIW1 AL RADIOLOGICAL FR00 RAM SLMMARY VERMONT YAkttl WVCLEAR POWER $1 ATIDW, VERWoh, Vi !
(.lAWUARY LICtMBtR 1990)
MIDIUM: M!ktD VEttTATION UWills FCl/KU WIT I INDICATOR $1 Aft 0hl e.................
$1Afl0W Vl1H MIGHt$1 MEAN eeeeeeeeeeeeeeeeeeeeee-ee.
CONTROL $1A110h8
...............e I
RAD 10WUCL10t$ MEAN MIAN MIAN (WO. ANALY$tl) Rt0V! RID RAhGC STA. RAhCE RANCE ,
(WON ROUllht)* LLD WO. Dt1[CftD** WD. WO. DtitCitD*' WO. DtitCitD" i RU 103 ( 18) ( 0.0 s 0.0)! O ALL toJAL ( 0.0 s 0.0)t 0
( 0)
- ( 0/ 15)* '( 0/ 3)'
I RU 106 ( 16)
C 0)
( 0.0 s 0.0)I 0 ALL touAL ( 0.0 s 0.0)E O J
l
- ( 0/ 15)* *( 0/ 3)*
I $8 124 ( 18)
( 0)
( 0.0 s 0.0)t 0 ALL EQUAL ( 0.0 s 0.0)t 0
- ( 0/ 15)* *( 0/ 3)*
l 131 ( 18) 60. ( 0.0 s 0.0)! O ALL 10UAL ( 0.0 s 0.0)t 0
( 0)
- ( 0/ 15)* *( 0/ 3)'
CS 134 ( 18) 60. ( 0.0 s 0.0)t 0 ALL 10UAL ( 0.0 s 0.0)t 0
- ( 0/ 15)* *( 0/ 3)*
C$ 137 ( 18) 80. ( $.4 s 3.7)E o it ( 1.4 s 1.4)! 1 ( 0.0 s 0.0)E D
( 0.0 - 4.3)t 1 ( 0.0 - 4.3)! i I
( 2)
'( 2/ i$)* '( 1/ 3)* '( O! 3)'
SA 140 ( 18) ( 0.0 s 0.0)! O ALL touAL ( 0.0 s 0.0)E O I ( 0)
Cl 141 ( 18) (
- ( 0/ 15)*
0.0 s 0.0)E O ALL touAL (
- ( 0/ 3)*
0.0 s 0.0)E D I ( 0)
- ( 0/ 15)* *( 0/ 3)*
Ct 144 ( 18) ( 0.0 s 0.0)E 0 ALL touAL ( 0.0 s 0.0)E O
( 0)
- ( 0/ 15)* '( 0/ 3)*
TH 232 ( 18) 0.0 s 0.0)E O ALL CouAL ( 0.0 s 0.0)t 0 I
(
( 0)
- ( 0/ 15)* *( 0/ 3)'
' WON ROVilk! REFtR$ 10 THE WUMBER OF $tPARATE NEASUREMtWi$ VHICH WERE CktAf tR ThAN TEN (10) TIMi$ THE AvtRACE BACKGROUND FOR THE ttRIOD OF THE REPORI.
- THE FRAC 1!ON OF $ AMPLE AAALY$ts YttLolkG Dif!CTABLE MEA $UREMENTS (1.E. >3 StD Dtyl AT10NS) l$ ikDICATED Wlf H *( )'.
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Silage san'ples were collected at the milk sampling stations during October of 1990. Eas.h sample was analyred f or gansna-emit ting I radionuclides and 1-131.
Naturally-occurring K-40 was detected in all sileSe samples, and naturally-occurring Be-7 was detected in most. No man-made radionuclides were detected in any of them.
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- VERM3ht T Aktli WUCLE AR 0;bilt $1 A110W, VtLbON, VI (JAWJARY
- DECIMLtR 19?0)
MtDluM $1 Lact uhlil PCl/AG Vt1 INDICATOR 11A110NS $1A110N WifH HICHilt ktAN CON 1ROL ST All0kl NtAN MtAN MIAW LADIONUCLIDtl
( AW;t liA. RAWGE rah 0E (No. ANAtittl) Ft0 VIRID
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WD. DF1tCftD*8 hQ. Wo. OtitCitD** WQ. DtitCIED*'
(kON ROJilht)' LLD 6t.7 ( ?) ( 4.4 s 2.6)t 2 14 ( 1.7 s 0.!)E 3 ( 4.9 0.9)! 02
( 0) ( 0.0
- 1.7)t 3
- ( 4/ 6)* '( 1/ 1)* *( 1/ 1)*
R.40 ( 7) ( 6.1 e 1.9)t 3 12 ( 1.4 e 0.1)! 4 ( 2.9 0.2)t 3
( 0) ( 2.0 14.1)E 3
- ( 6/ 6)* *( 1/ 1)* '( 1/ 1)*
MN $4 ( 7) ( 0.0 s 0.0)t 0 Att toJAL ( 0.0 s 0.0)t 0
- ( 0/ 6)* '( 0/ 1)'
C0 $8 ( 7) ( 0.0 s 0.0)t 0 ALL touAL ( 0.0 s 0.0)t 0
( 0)
- ( 0/ 6)' *( 0/ 1)*
1 ALL touAL ( 0.0 s 0.0)L 0 I( 59 ( 7) ( 0.0 s 0.0)f 0 g ( 0)
- ( 0/ 6)' '( 0/ 1)*
to 60 ( 7) ( 0.0 s 0.0)E O ALL touAL ( 0.0 s 0.0)t 0
( 0)
- ( 0/ 1)*
1 *( 0/ 6)*
IN 65 ( 7) ( 0.0 a 0.0)t 0 A'.L touAL ( 0.0 a 0.0)t 0
( 0)
I *( 0/ 6)* *( 0/ 1)*
2R 95 ( 7) ( 0.0 a 0.0)E O ALL touAL ( 0.0 s 0.0)( 0
( 0)
- ( 0/ 6)' *( 0/ 1)*
AC.110M( 7) ( 0.0 s 0.0)E O ALL touAL ( 0.0 a 0.0)E O
( 0)
't 0/ 6)* *( 0/ 1)'
' NON ROUilNE Rif tt$ 10 THE NUMBER Of $tPARATE MEASUREMEWi$ VHICH WERE GREAlte ThAN TEN (10) 11MES THE AVERAGE CACECROUND FOR THE PERIOD OF ikt REPORT.
- THE FRACTION Ot SAMPLt AhALYSt$ fitLDlhG DtitCIABLE MEASUREMtWil (1.E. >3 $1D DtVlA110NS) 15 thDICAltD W11H *( )*.
- 3 f;-
" (WVIRONMth1 AL RADIOLOGICAL PROGRAM $UMMARY Y[RMONT T AhKit NUCLE AR POWIR $1 All0W, VLRNON, VI (JANUART
- Ottt4tR 1990)
' UW1181 Kl/RG Wil EIDIUM: $1LA0t 1
lhDICA10R $1All0NS $1A110N WITN NIGkt$1 MIAN CONTROL $1A110NS
~ ..... eeeeee...eeeeeeeeee ................
eeeeeeeeeeeeeeeee.
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' R AD10NUCL IDE $ MtAN MtAN MtAN RAN0t $1A. RAWGE RANGE (ND. AhAltst$) REQUIRtD J (NON.ROU11AE)* LLD WD. OtttCitD** WO. WD. OttttitD** WO. Ot ttCitD" RU 103 ( 7) ( 0.0 s 0.0)! O ALL toVAL ( 0.0 t 0.0)E O
( 0)
- ( 0/ 6)* *( 0/ 1)*
RU 106 ( 7) ( 0.0 t 0.0)t 0 ALL toVAL ( 0.0 s 0.0)t 0
( 0)
- ( C/ 6)* *( 0/ 1)*
St 124 ( 7) ( 0.0 t 0.0)t 0 ALL toVAL ( 0.0 a 0.0)E O
( 0)
- ( 0/ 6)* *( 0/ 1)*
1 131 ( 7) 60. ( 0.0 s 0.0)E O ALL toVAL ( 0.0 t 0.0)E 0
( 0)
- ( 0/ 6)* *( 0/ 1)*
C5 134 ( 7) 60. ( 0.0 0.0)E 0 ALL touAL ( 0.0 t 0.0)t 0
- ( 0/ 6)* *( 0/ 1)*
C5 137 ( 7) 80. ( 0.0 s 0.0)E O ALL touAL ( 0.0 2 0.0)! O
( 0)
- ( *( 0/ 1)*
I 0/ 6)*
0.0 s 0.0)E 0 ALL toVAL ( 0.0 a 0.0)E O BA.140 ( 7) (
( 0)
I *( 0/ 6)*
0.0 a 0.0)E 0 ALL touAL (
- ( 0/ 1)*
0.0 s 0.0)E O CE.14) ( 7) (
( 0)
- ( 0/ 6)* *( 0/ 1)*
Ct.144 ( 7) ( 0.0 a 0.0)E O ALL touAL ( 0.0 s 0.0)E O
( 0)
- ( 0/ b)* *( 0/ 1)*
1H.232 ( 7) ( 0.0 s 0.0)E O ALL touAL ( 0.0 a 0.0)t 0
( 0)
- ( 0/ 6)* *( 0/ 1)*
- WON.R3Jilkt REFER $ 10 THE NUMBER OF SEFARATE MEASUREMENTS WHICH Wikt CREAltR IMAN TEN (10) 11Mt$ THE AVERAGE BACKCR3JWD FOR Tht PERIG) 0F TML REPORT.
" THE F*,AC110N OF SAMPLE AkALY$ts YttLDlWG Ot1ECTABLE MEASUREMENil (1.E. >3 $1D CtvlA110NS) 15 IN01CAltD W11H *( )*.
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F) GrQuadvAttr f Groundwater grab samples were collected irom 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 y analyses were performed, although they are not required.
The gross-beta concentrations at WG-11 have been elevated since 1987, as can be seen in Figure 3.9. No explanation for these levels has been found, although a problem with low well-water levels and moving to a new well may have caused a change in naturally-occurring radioactivity. Elevated radium levels at WG-11 I are suspected, as confirmed by a sample collected there in August of 1988. The gross-beta levels in 1990 are consistent with those in the previous several years. No gamma-emitting radionuclides or 11-3 were detected in groundwater during this time.
During February of 1990, the control water sample at WG-21 was not available. An alternate control sample for that period was collected at the Southern Vermont Engineering Company.
I I
WPP12/26 I
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MEDIUM: CROUWD WAllR Uhlill FCl/KG INDICA 10R $1Afl0h5 $1 All0W WITH NICHt$1 ME AN C0h1ROL STAT 10h5
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- WON ROUT!ht RtitR$ 10 THE NUMBER OF SEFARAft HEASUREMEWi$ WHICH WERI GREAltR THAN TEN (lu) TIMES THE AVERAGE BACKCROUND FOR THE PERIOD OF THE REPORI.
- THE FRACil0N OF $ AMPLE AhALY$tt YitL0lWG DETECI ABLE MtA$URtdtWi$
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I (WVIROAMlh1 AL RADIOLOGICAL PROGRAct SWARY VlRMDh1 1 Aktti WUCLE AR PChl!R $1 A110N, VIRWON, VI (JANUARV DICLMBit 1590)
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" 1HE f R AC110h of $ AMPLE AhAL15t$ VitLDlhG DtitC1 A$tt MLASURIMth15 (1.E. 3 $1D DtVIAllDAS) 15 INDICAltD W11H *( )*.
I I
I I
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I
G) Pdytr_ Mater p River water is analyzed monthly for gamma-emitting radionuclides and gross-beta (not required by Technical Specifications). The J monthly samples are composited and analyzed f or 11-3 on a quarterly basis. A composite s:.mpler is used at Station WR-11 and grab samples are taken at Str. tion WR-21.
Gross-beta radioactivity was detected in all samples during 1990.
Considerable fluctuation in gross-beta levels at both the indicator and control locations over the past nine years is evident in Figure 3.10. 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 due to plant operations, but are due to naturally occurring radioactivity. No gamma-emitting radionuclides or 11-3 were detected in any of the samples.
I On one occasion during 1990, the automatic composite sampling
- ystem at WR-11 was temporarily out of service. On September 25, it was discovered that power was out at the sampling location due to tree limbs having fallen on the electrical wires. The hour I meter on the adjacent air sampler indicated that the power had been interrupted earlier that day. Repaits to restore power to the site were completed and the sampler resumed operation on October 12.
Consequently, the composited sample for the month represents the periods of September 13-25 and October 12-16.
WPP12/26
Figure 3.10 GROSS-BETA MEASUREMEt1TS ON RIVER WATER
- VERMOtJT YATJKEE rJUCLEAR POWER STATIOtt -
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- WON ROU11NE REFER $ 1018E WUMBER OF $EPARAf t MEASURtMtWIS WHICH WERE GREAf tR 1 hah IEN (10) 11Mi$ THE AVERAGE BACAGROUND f 0R THE PERIOD OF Tht REPORI.
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- THE FRAC 110h 0F $AMrLt AkALY5tl YttLDlho DtitC1ABLE HEASUttMINil (l.t. *) 510 Dtyl A110N5) IS INDICAltD WilH *( )*.
I 4
l l
E H) Erdiment I During 1990, sediment samples were collected Irom two locations in May and October. Each semple was analyzed for gamma-emitting I radionuclides. One grab sample was collected at Station SE-11 and 1 20 grab samples at Station SE-12 during May. During October, one !
I was again collected at SE-11 and 60 at SE-12.
1 I
Cesium-137 was detected in all samples. Since there were no liquid releases during 1982 through 1990, it can be concluded that the levels of Cs-137 in 1990 sediment samples were due to nuclear weapons testing fellout, as has been discussed in previous Vermont Yankee Radiologicel Environmental Surveillance Reports. This is I further supporte.: by the fact that similar levels have in the past been detected at Station SE-21. a control station, and at control locations at other power plants. 1,ow icvels of Co-60 have been detected in mary samples collected at Station SE-12 (N. Storm Drain Outfall) during 1990 and in previous years. The activity is localized to a small area and is due to plant operations. The Co-60 levele in 1990 were similar to those reported in previous years, and are vell under the reporting level specified in plant Technical Specifications.
I It should be noted here that the statistics given in the following table are heavily weighted toward Station SE-12. since 60 of the 62 samples were collected there. No Co-60 was detected at Station SE-11.
Naturally occurring Be-7. K-60, and Th-232 were also detected in most samples.
I I
I WPP12/26
-Le-I I
- . . . - . - ~ . - - - _ . .
" (WVIRONMth1 AL RADIOLOGICAL IROMAM $WMART VERMDh1 1 Abitt WUCLt AR IWit $1 All(W, VERW'*, VI
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- THE FRAC 110N OF SAMFLt AhALYsts YttLDlhG DtitCIASLE MEASURIMikis (1.t. >3 $10 Dty! ATIONS) 15 INDICATLD VITH *( )*.
I I
- 1) fish Fish samples were collected from two locations during May and again in October of 1990. Each sample consisted of mixed samples of I
l yellow perch and smallmouth bass. All were analyzed for l gamma-emitting radionuclides. Cesium-137 was detected only at the l control location. The detected level is similar to those in past years (see Figure 3.11) and is consistent with well-doeurnented environmental levels caused by nucleer weapons testing fallout. No other radionuclides were detected except for naturally-occurring K-40.
- I l
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,I ypp12/26 I
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i CESIUM-137 It1 FISH
' - VERMONT YANKEE NUCLEAR POWER STATION - t i
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0.2)! 3 3.0)E 3
- '( 2/ 2)* *( 2/ 2)* *( 2/ 2)*
4 MN 54 ( 4) 130. ( 0.0 s 0.0)E O ALL touAL ( 0.0 s 0.0)t 0 1 ( 0)
- ( 0/ 2)* *( 0/ 2)*
C0+58 ( 4) 130. ( 0.0 s 0.0)E O ALL fouAL ( 0.0 s 0.0)t 0 l *( 0/ 2)* '( 0/ 2)*
i FE 59 ( 4) 260. ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O
( 0) i I Co 60 ( 4) 130. (
- ( 0/ 2)*
0.0 s 0.0)t 0 ALL EouAL (
- ( 0/ 2 )
0.0 s 0.0)E O 3 ( 0) g *( 0/ 2)* *( 0/ 21' 2N 65 ( 4) 260. ( 0.0 s 0.0)E D ALL EQUAL ( L.0 s 0.0)E O I ( 0)
'( 0/ 2)* *( 0/ 2)*
0.0 s 0.0)E D 2R 95 ( 4) ( 0.0 s 0.0)E C ALL touAL (
I ( 0)
- ( 0/ 2)* *( 0/ 2)*
AC 110M( 4) 0.0 s 0.0)! O ALL EQUAL ( 0.0 s 0.0)E O I
(
( 0)
- ( 0/ 2)* *( 0/ 2)*
- NON* ROUTINE REFERS to THE WUMBER OF $EFARATE MEASUREMEWIS WHICH WERE CREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUNO FOR TOE PERICO OF THE REPORT.
" THE FRACT!Ok OF SAMPLE ANALi$t$ YlELDikG DETICIABLE MEASUREMENTS
. (l.E. >3 $1D DEVI ATIONS) l$ INDICAf f0 WITH *( )*.
I g .m.
I (WylkDNMENTAL RADlos0GICAL PROGRAN
SUMMARY
VIRH0h1 TAkKit WUCLEAR POVER $1All0N, VIRNDN, VI
(.lANUARY
- DECEMBER 1990)
MEDlVM FISH UNlIS PCl/KG Vti 1NDICATOR STATIOkl $1All0N WITN HIGHEST MEAN CONTROL $1Afloh$
RADIONUCLlDES MEAN MEAN MEAN (NO. AhALY$t$) R10VIRED RAN01 STA. RAN0E RANGE (h0N'ROVilNI)* LLD No. DtitCitD** NO. No. OfftCitD*' NO. OtitCitD
RU 1C3 ( 4) ( 0.0 s 0.0)E O ALL IQUAL ( 0.0 s 0.0)t 0
( 0)
- ( 0/ 2)* *( 0/ 2)'
RU 106 ( 4) ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 t 0.0)t 0
( 0)
'( 0/ 2)* '( 0/ 2)*
$B 124 ( 4) ( 0.0
- 0.0)t 0 ALL E0uAL ( 0.0 s 0.0)t 0
( 0)
'( *( 0/ 2)*
I 0/ 1)'
1 131 ( 4) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 s 0.0)t 0
( 0)
- ( 0/ 2)* *( 0/ 2)*
C$ 134 ( 4) CO. ( 0.0 1 0.0)E 0 ALL EQUAL ( 0.0 s 0.0)t 0 j
- ( 0/ 2)* *( 0/ 2)*
CS 137 ( 4) 1$0. ( 0.0 s 0.0)E o 21 ( 8.9 : 8.9)E 0 ( 8.9 a 8.9)! 0
( 0) ( 0.0 - 1.8)E 1 ( 0.0 a 1.8)E 1
- ( 0/ 2)* *( 1/ 2)* *( 1/ 2,*
OA 140 ( 4) ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 a 0.0)t 0 I
( 0)
- ( 0/ 2)* *( 0/ 2)*
Ct 141 ( 4) ( 0.0 s 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)t 0 I ( 0)
'( 0/ 2)'
9.0 a 0.0)E O ALL ( E L (
- ( 0/ 2)*
0.0 a 0.0)E C CE*144 ( 4's (
I ( 0)
- ( 0/ 2)* *( 0/ 2)*
TH 232 ( 4) ( 0.0 0.0)E O ALL EQUAL ( 0.0 s 0.0)E 0 I ( 0)
- ( 0/ 2)' *( 0/ 2)*
- NON ROVI!NE refit $ TO THE NUMBER OF stPARAM MEASUREMENTS WHICH WERE CREATER THAN itN (10) TIMES THE AVERACE BACKCROUND FOR THE PERIOD OF THE REPORT.
- THE FRACTION OF SAMPLE ANALYSES YIELDING DtitCIABLE MEASUREMENTS (1.E. >3 $fD Otvl Afl0NS) l$ INDICATED WITH 't )*.
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I J) la_ Situ I During the period October 19 through 21, 1990, an ilLailu survey was performed at selected sites surrounding the Vermont Yankee I plant. A Canberra portable, down-looking, high-purity Germanium detector coupled to a PC-interfaced 8000-channel multichannel analyzer was used for gamma spectroscopy. A Reuter Stokes RS-112 liigh Pressure Ionization Chamber (llPIC) was used for direct exposure rate measurements.
The sites chosen for the survey represent the six air sampling locations, two off-site locations and three on-site or fenceline locations. Since these sites were monitored at only one time during 1990, they are not listed as routine rnonitoring locations in Table 2.2. They are shown, however, in Table 3.1.
Table 3.1 shows the results for both the Germanium iltallu and !!PIC rnea surement s . The first four columns of data give exposure rates for the four radionuclides detected, based on the Germanium spectra. The fifth column of data gives the total exposure rate from those four terrestrial radionuclides. The sixth (last) column lists the total measured 11010 exposure rate, which includes I terrestrial and cosmic radiation.
between the Germanium and !!PIC methods is explained by the cosmic The difference in exposure rates ray contribution to the total exposure sneasured by the liPIC (estimated at 3.7 to 3.8 uR/hr).
E It can be seen from Table 3.1 that most of the exposure is due to radiation from naturally occurring Th-232. U-238, and K-40, as well as from cosmic radiation. A small residual amount of Cs-137 from atmospheric nucient weapons testing fallout adds a small amount to the total exposure at all locations, including the controls.
I I WPP12/26
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I IAll.L321 SummarL_ clin _SiluJitasurements_ ._.0ciobtr._ll.lhrustt_2h_1990 Y.ermonLlankteJiuc1catJwer Siation (uR/ hour il standard deviation)
IILQt_1n_ Sit u - _
Terrestrial Total I Locatten Ih:212 LL-133 E-M CM Total J1EIC 9.5 10.5 Spofford Lake 1.94 10.20 1.09 10.17 2.10 +0.22 0.04 10.01 5.2 +0.3 I (Control) 3.7 10.2 7.7 10.4 Brattleboro 1.28 10.14 0.78 10.12 1.36 0.14 0.24 10.04 CC (Control)
Vernon Nursing 1.31 10.14 0.87 10.14 1.53 30.16 0.18 0.03 3.9 10.3 8.1 +0.4 Ilome Tyler 11111 Road 2.14 10 22 1.09 10.17 1.59 0.17 0.14 10.02 5.0 10.3 9.5 10.5 Governor ilunt 1.58 10.17 0.83 10.13 1,56 0.16 0.10 0.02 4.1 +0.3 8.8 10.5
!!ouse North llinsdale 1.60 d0.17 0.04 0.13 1.56 +0.16 0.11 10.02 4.1 30.3 8.1 30.4 Ilinsdale 1.68 10.18 1.05 30.17 1.49 0.16 0.14 10.02 4.4 30 3 8.7 30.4 Substation Northfield 1.49 10.16 0.92 +0.14 1.41 0.15 0.05 +0.01 3.9 +0.3 8.0 to.4 I River Station 3.3 1.48 10.16 0.84 10.13 1.39 30.15 0.02 10.01 3.7 30.3 Bel 30.4 1.55 0.16 0.07 +0.01 4.1 10.3 8.7 +0.4 I North-40 Well No. 111 (On-Site) 1.57 10.16 0.94 +0.15 3.7 10.3 8.4 0.4 North-40 1.37 10.17 0.77 0.13 1.55 +0.17 0.04 30.02 Well No. 113-S (On-Site)
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I WPP12/26 I
I K) Dirget Rad 1 @
I Direct gamma radiation exposure was determined from the use of thermoluminescent dosimeters (TLDs). Beginning in 1988, Panasonic UD-801ASl and UD-814AS1 calcium sulfate dosimeters were used, replacing the previous Victoreen CaF 2 Mn dosimeters. A total of five elements were in place at each monitoring location.
Fifty-one sets of TLDs were read out on a quarterly schedule.
Sixteen of these were located at inner ring stations and sixteen at outer ring stations. Twelve were located at the site boundary, six were at special interest locations, and one was a control.
I Summaries of the results for 1990 can be seen in the table below and in Figures 3.12 to 3.25. A complete station-by-station summary is given in Table 3.2. In this table, 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 evident that the inner ring exposure I rates are not statistically different from those of the outer ring.
Upon examining Figure 3.15, it is evident that Stations DR-45 and DR-46 had higher average exposure rate than any other station.
Both locations are on-site, and the higher exposure rates are due to plant operations in the immediate vicinity of the TLDs. As can be seen on the map in Figure 2.4 there is no significant dose potential to the surrounding population or any real individual from these sources.
I As can be seen in Figure 3.13, Station DR-6 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 WPP12/26 I
- I 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 DR-6.
I As ,oted in Table 3.2. TLDs were found to be missing in the field for the following locations during 1990: DR-47 for the second quarter, DR-16 for the third quarter, and DR-15 and DR-28 for the fourth quarter.
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I WPP12/26 1
I
I Environmental Radiological Program Summary I Vermont Yankee Nuclear Power Station January - Datember 1990 _
Medium: Direct Radiation Units: Micro-R per Measurements (TLD) llour I inner Rine Mean Site Boundarv Mean Station With liightAt . Mean Mean Outer Ring Mean Range Range Station Range Range (No. Meas . )* .No.
( Meas.)* No. (No . Meas . )* (No. Meas.)*
6.5 10.6 10.2 17.1 31.3 14 7 6.6 10.8 5.1'- 8.2 5.8 - 35.0 46 24.4 - 35.0 4. 9 - 8. 2 (87) (47) (4) (66)
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- Most measurements based on five readings per station.
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WPP12/26 I
-v
I IALLLld I Summary oLDirggLRadini.ign Measurements - 1990 Vermont Yaakt.t_Rucitar 10K.CI_S.LatiQD (Micro-R Per Hour)
I Localian lytt* QIL1 QIR_2 QIR._3 QIR_A Yearly McAn DR-1 I 5.5 6.4 5.8 5.9 5.9 DR-2 1 5.5 6.9 6.4 6.4 6.3 DR-3 I 6.6 8.2 7.7 7.8 7.6 I DR-4 DR-5 DR-6 I
0 I
5.3 5.1 5.5 6.6 6.9 7.1 6.3 6.2 6.5 6.3 6.8 6.8 6.1 6.3 6.5 7.0 9.4 8.1 8.7 8.3 I DR-7 DR-8 DR-9 SB SB I
7.2 5.7 9.1 6.7 7.8 6.1 8.5 6.6 8.2 6.3 5.2 DR-10 0 4.9 5.5 5.1 5.3 DR-11 I 5.1 6,3 5.7 6.0 5.8 DR-12 0 5.2 6.2 5.6 6.2 5.8 DR-13 I 5.8 6.7 6.1 6.3 6.2 DR-14 0 6.7 8.0 7.4 8.0 7.5 I' DR-15 I 6.7 7.0 7.1 7.3 6.6 7.3 6.8 7.2 DR-16 0 5.7 6.9 6.3 6.6 6.4 I
DR-17 I DR-18 0 63 7.3 6.9 7.0 6.9 DR-19 I 6.1 7.1 6.8 7.0 6.8 DR-20 0 6.4 8.0 7.5 7.7 7.4 I DR-21 DR-22 DR-23 C
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5.7 6.3 6.1 7.2 7.2 7.0 6.8 6.8 6.5 6.8 6.7 7.0 6.6 6.8 6.7 DR-24 0 5.3 6.1 5.6 6.0 5.8 6.9 6.2 6.6 6.5 1 DR-25 DR-26 I
0 6.1 5.8 7.2 6.8 7.4 6.8 DR-27 I 5.8 7.2 6.6 6.8 6.6 I DR-28 DR-29 DR-30 0
0 I
5.7 5.9 5.7 7.1 7.2 6.9 6.8 6.6 6.4 7.0 6.6 6.5 6.7 6.4 I DR-31 DR-32 DR-33 1
0 I
5.9 5.7 6.0 7.5 6.9 7.2 6.5 6.5 6.8 7.2 6.8 7.3 6.8 6.5 6.8 6.2 7.4 6.9 7.4 7.0 I DR-34 DR-35 DR-36 0
0 I 6.5 6.5 7.1 8.2 6.4 7.9 7.0 8.0 7.5 6.8 7.7 6.9 DR-37 I 5.7 7.3 6.9 I DR-38 DR-39 DR-40 0
I 0
6.1 5.7 6.0 7.4 6.8 6.8 6.8 6.5 6.2 7.3 7.0 6.9 6.9 6.5 6.5 7.4 I DR-41 DR-42 DR-43 SB S3 SB 6.6 5.8 6.3 7.9 7.3 7.8 7.2 6.5 6.9 8.0-7.2 7.6 6.7 7.2 DR-44 SB 7.6 8.3 C.7 7.6 7.6 WPF12/26 I
I IABLE.3d (Continued)
Eumary__nLDir.ecLRadiation_Menutelnents - 1RQ yermont Yankee Nucitar Power StatiQn QIIL3 QIR_A Yearly _Mean Loca11on Iypc* QIIL1 QILL2
'5.7 14.2 12.6 20.0 15.6 DR-45 SB 31.3 24.4 33.2 35.0 32.5 DR-46 SB 7.9 DR-47 SB 7.0 ** 8.0 8.6 I DR-48 DR-49 SB SB I
6.2 6.3 6.0 7.8 7.2 7.5 6.8 6.4 6.7 7.4 6.9 7.1 7.1 6.7 6.8 DR-50 8.2 DR-51 SB 7.2 9.2 8.0 8.5 5.9 7.0 6.5 6.8 6.5 I QTR Mean Inner King 10.4 10.4 7.1 0.4 6.6 0.5 7.0 10.6 6.6 QTR Mean 5.9 Outer Ring t0.6 10.7 10.7 0.7 10.8 8.9 11.0 10.0 11.0 10.2 QTR Mean 17.1
+8.0 17.6 I Site Boundary 15.5 +7.6 i
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- I = Inner Ring; O = Outer Ring; SB = Site Boundary.
i **TLDs missing in the field.
WPP12/26 I
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M M M LM M M M M M M M M -M M M- M M m r
Figure 3.12 .
EXPOSURE RATE AT INDICATOR TLDS. DR 01-03 '
- VERMONT YANKEE NUCLEAR POWER STATION -
4o l l 30--
}
3 __ __ ,
o a I __ __
n
$ D-- DR-01
-- ~~
0- 20--
O DR-02 m __ --
--h- on-03 i i "
O __ --
1 6 o __ __ j H '
l Z, __ __
10--
M_
me o , I . l i I i I > I 1986 1987 1988 1989 1990 1991 2
4 f
t
})iiIj\i d
M 460 005 RRR DDD M _
nCA M -
- - - ~ _ - - - - - - _ - ~ - _ _
- ~ - - ~ _ - - - - - - _ - _ _
M 1
9 I
9 W!
1 M
0 5
a M 6 0N O 0
.I I 9 4T 9 M 0A T
1 RS D
R _ 4 M SW
.E '
DO -
LP T 9 M 3 R '
8 9
%Ii 3
' TL e
r AC e
u CU g IN '
i D F NE IE K
M TN l91 8
8 AA '
Y E -
TT M AN RO .
M ER RE M UV S 7 8
O - l l91 P
X M E M g&
6
- _ _ _ _ - _ _ _ _ - _ _ _ - - : _ 8
_ _ _ _ - 0 _ _ _ _ - _o _ _ 0 ~__o1 9 o g 1 4 3 M 3oI T$ gIoToHI M
&i M
m 1lf
Figure 3.14 EXPOSURE RATE AT SITE BOUNDARY TLDS. DR 07-08,41-42
- VERMONT YANKEE NUCLEAR POWER STATION -
I
,o __
Wm mm MM mm eW 30-- __
D __
O --
e I ~~
D- DR-07
?' --
~~
O DR-08 E ~~
-A- DR-41
- n. 20-- ~~
E --
-V- DR-42 O --
E u
o __
_m H
1 -- x H
20~- r' "
\ - --
mum WW Wm eW I
g 9 g
199O i99i 1988 19 9 986 1987
m m M M M M M M- M M M M M M M m' W W m Figure 3.15 EXPOSURE RATE AT SITE BOUNDARY'TLDS. DR 43-46
- VERMONT YANKEE NUCLEAR POWER STATION -
I !
I I 100 ! __
me 90-- __
mm 80--- __
ese g 70-- --
D .
$ I go__ __
D- DR-43 Y' g tij O-- D R-4 4 1 50-- --
-A- DR-45 E --
-V- DR-46 o ,o__ --
E
(.) __
H I 30-- --
didM
- - ~
10-~
Q -6 -
l . ! . I 0 : . .
1990 1991 1987 3983 1989 1986 I
l
M M M m M M M M m m M m m m M M M M M Figure 3.16 EXPOSURE RATE AT SITE BOUNDARY TLDS. DR 47-49.51
- VERMONT YANKEE NUCLEAR POWER STATION -
l l
4o l !
30-- __
g __
& I __
D-- DR-47 i tr __
O--- DR-4 8 E 20-- --
-b- DR-49
-V- DR-51 Y
o __
z __
10--
f
- f f
I f
1990 1991 1987 1988 2909 1986 l
M M M M M M M M M M M m m m m m M M M Figure 3.17 EXPOSURE RATE AT INNER RING TLOS. DR 09-15 (Odd)
- VERMONT YANKEE NUCLEAR POWER STATION -
i I ao 30-- -_
J __
o --
i I __
D- DR-09
$. E __ O- DR-11 La --
1 20-- --
-A- DR-13
-V- DR-15 E, _-
O __
E --
o -_
H 1 __
10-- E -
- S
! l . I o ! . ! . >
1991 3933 1989 1990 1986 1987
M M M M M M M M M M M M M mm M M M M Figure 3.18 EXPOSURE RATE AT INNER RING TLDS. DR 17-23 (Odd)
- VERMONT YANKEE NUCLEAR POWER STATION -
i I 40 l
i !
30-- __
D __
e O __
e I __
C DR-17 T g __ a 99-19 w --
1 20-- --
-A- DR-21
-V- DR-23 7
0 --
E --
o __
s-4 I _
~~
10~-
b ' "' i- __
dum_
_use
! . ! . I o . l . 1991 1998 1989 1990 1996 1987
rigure 3.19 I
EXPOSURE RATE-AT INNER RING TLDS. DR 25-31 (Odd)
- VERMONT YANKEE NUCLEAR POWER STATION -
l l l l
4o --
~~
30-- --
g __
A I __
D-- DR-25
? g * --
O DR-27 tu 1 20-- --
-A- DR-29 E - -
-V- DR-31 O
T E
o _-
I __
gg--
Y Q -
~~
.L, 25 151 l l 2E l 12ee see7 seee 1
1 l
E E E E E E E E E E M M M M M M- E M Figure 3.20 EXPOSURE RATE AT INNER RING TLDS. DR 33-39 (Odd)
- VERMONT YANKEE NUCLEAR POWER STATION -
l l 4o __
30-- __
g --
J __
o --
I ~~
D - DR-33 y' g __
O-- DR-35 uJ ~~
0- 20-- --
-A- DR-37
-V- DR-39 E, __
O -
E o __
H z __
~~
10--
~
~
m-
_W
{
1999 1990 1991 1987 sges 1986 l
l
M M M M-M M M M M M M M M M M M .M M M Figure 3.21 EXPOSURE RATE AT OUTER RING TLDS. OR 10-16 (Even)
- VERMONT YANKEE NUCLEAR POWER STATION -
i 4o ! __
30-- __
D __
O -_
L I __
C DR-10 T x __ o- 99-12 w -~
Q 20-- ~~
-h- DR-14
-V- DR-16
{ ~~
0 --
T o __
H I __ .
~~
10--
n -
v _
einW
_WW r ! !
I !
O a ! i 1989 1990 1991 190s 1987 1988 1
M M M M M M M m a m .m m a m M M M M M Figure 3.22 EXPOSURE RATE AT OUTER RING TLDS. DR 18-24 (Even)
- VERMONT YANKEE NUCLEAR POWER STATION -
'J l ! .!
4o 30-- _
D __
o --
i I __
D- DR-18 3' g ~~
O DR-20 w --
a- 20-- --
-A- DR-22 C __
-V- OR-24 O __
H -
I __
~~
10-- --
l __
- . p.,
g l 1989 1990 1991 1986 1987 1983
Figure 3.23 EXPOSURE RATE AT OUTER RING TLDS. DR 26-32 (Even)
- VERMONT YANKEE NUCLEAR POWER STATION -
l l l ao l l 30-- --
g --
L I __
O-- DR-26 i' g __ O- DR-28 W --
& 20-- --
-A- DR-30 E --
- V- DR-32 O --
E --
o --
I --
10--
em-gia-
._ _ l
m m m M M M M M e a m m m m M m m m M Figure 3.24 EXPOSURE RATE AT OUTER RING TLDS. DR 34-40 (Even)
- VERMONT YANKEE NUCLEAR POWER STATION -
4o l !
30-- .._
3 __
1, I __
---O - DR-34 i a __
O-- DR-36
$ 3__ ~~
-A- DR-38
-V- DR-40 7
o __
o __
y __ x
__ ~
l 1 O ii 1986 1987 1989 1
m M m~ m m m m m m mm m m m m m e Figure 3.25 EXPOSURE RATE AT CONTROL TLD OR-05
- VERMONT YANKEE NUCLEAR POWER STATION -
l l l 4o l
30-- __
g __
3 __
o __
I __
c,a __
i E __
tts --
3-- DR-05 Q- 20-- __
E __
t o --
E o __
H 1 __
10--
[
l __
! ! , l o l . l . ,
1991 1999 1989 1990 1986 1987
~
4.0 QUALLTLASSUPMCLEFaGPM Three separate Quality Assurance programs were performed during 1990 to
^
demonstrate the validity of laboratory analyses by the Yankee Atomic Environmental Laboratory (YAEL).
7 l
YAEL maintains an extensive intralaboratory quality control program to assure the validity and reliability of the data. This program includes:
instrument calibrations and control checks, process control checks comprised of known activity concentration, blind duplicates, and blank samples. The process control checks comprise approximately ten to fifteen percent of the laboratory sample throughput. The records of the quality control program are reviewed by the responsible cognizant individual, and corrective measures are I taken whenever applicable.
To further verify the accuracy and precision of the laboratory analyses via an independent outside third party YAEL participates in the U.S.
Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies Program for those available species and matrices routinely analyzed by the laboratory. When the results 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, as appropriate. YAEL also participates in independent third party performance testing for environmental TLDs through the University of Michigan.
A blind duplicate program is also conducted 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 chack for precision in laboratory analyses.
EEA_ Int e r l ab o ra tnLY_anLIMr.clahcIat oryy_Re nnLL s 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 in 1990 for intralaboratory analyses and EPA interlaboratory cross-check analyses.
WFP12/26
s The results of the EPA Interlaboratory Comparison Ptogram, when
} considered apart from the remainder of the Quality Assurance program, were r
satisfactory with respect to accuracy and precisicn in 1990. One hundred and eighty-f our analyses were perf ormed on air particulate iliters, milk, and water. The three sample analyses which failed to meet the EPA control limit L, range involved gross-beta analyses made on one performance evaluation intercomparison water sample. Each of the gross-beta measurements in this set narrowly missed the upper end of the control limit range due to a mean bias of
+20.37. and an investigation was initiated. It should be noted that this sample contained a mix of activity including Cs-134, Cs-137, Sr-89, and Sr-90. Since the YAEL gross-beta calibration in water is presently based on Os-137, a positive gross-beta bias is likely whenever mixed higher energy beta activity is present. All the specific radiochemistry analyses performed on I the EPA performance evaluation intercomparison sample set in question for Sr-89/90 and Cs-134 and Cs-137 met YAEL QA perf ormance criteria and EPA control limits.
The above EPA Interlaboratory Comparison Program results are provided in compliance with Technical Specification 4.9.E.
BlindluplictLLc_fugram A total of 52 paired samples were submitted by the five participating plants for analysic during 1990. The data base used for the duplicate H-3, analyses consisted of onired measurements of 26 gamma emitting nuclides Sr-89, Sr-90, low level I-131 and gross beta. A dual level criteria for agreement was used. If the paired measurements fall within t 15 percent of If their average value, then agreement between the measurements has been met.
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 thousaad three hundred and twenty one paired duplicate measurements were analyzed for 1990. A total of 99.8 percent of all measurements fell within the established criteria discussed above. The two measurements that did not meet the criteria were measurements of Th-232 in marine algae and K-40 WPP12/26
-in estuary water. (In both cases, the lhtte standard deviation ranges of the paired samples ovetlapped.) In the case of the Th-232 measurement, there was
~
no radioactivity present in the sample at the three standard deviation level.
In the case of the K-40, this radionuclide was present at the three standard r deviation level. For the initial pair of K-40 analyses, the two samples had been analyzed for different MDC levels. Upon re-analysis, at equal MDCs, the acceptance criteria was met. No trend was evident with respect to repeated f ailings of measurements f or the above radionuclides.
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TABLE 4.1 Intralah2Intory__and EPA .Interlahora. tory _hesults - 1910 u
t&turacy Total Number gLfiggsurements O to 5% 0 to 10% 0 to 15%*
762 519 672 728 (68.1%) (88.2%) (95.5%)
Ettcit. ion Total Number oL Erasurements 0 to 5% 0 to 10% 0 to 153*
763 644 741 761 (84.4%) (97.1%) (99.7%)
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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 interest.
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I 5.0 IMLRSE_GERSilS Vermont Yankee Technical Specification 3/4.9.D requires 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 plaut. 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 better milk sampling location than those currently being used.
I The 1990 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 and an assessment of sample availability at specific farms, no changes were made in the milk sampling program. Due to the relatively high calculated dose potential, however, samples have been collected regularly f ollowing the census at Station DI-19 (NNE sector, 4.0 km). This location was not added to the sampling program as defined in the Off-Site Dose Calculation Manual (ODCM), Table 4.1, however, due to an anticipated irregularity in the I ability to supply samples due to the small size of the goat herd. Samples will continue to be collected there as long as available, or until replaced by a preferable location pursuant to Technical Specification 3/4.9.D.
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IARLLLI
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19.91 Land _Usel ennus_Aeaulis
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Vcrmont Yankee Nuclear Eower Slalinu i
- Nearest Residence _._._t111k_Animala*.__
J;m_ Cow or Coat
{ ggging ()gp}
1.6 ** --
- N NNE 1.6 4.0 Goats 1.3 ** --
NE 1.0 ** --
ENE E 1.0 5.2 Goats 2.8 ** --
ESE SE 1.8 3.6 Cows SSE 2.0 5.1 Cows 0.5 ** --
S I SSW 0.5 2.1 Cows SW 0.5 7.2 Cows 0.5 ** --
Wsw 0.5 ** --
W WNW 0.6 0.8 Cows WNW -- 4.7 Cows NW 1.2 4.7 Cows 2.1 ** --
NNW 1
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- Identified in accordance with Technical Specification 3.9.D.1
- No milk animals found within 5 miles.
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6.0 SERQX During 1990, samples collected as a part of the radiological
{ environmental monitoring program at Vermont Yankee showed detectable levels of r- man-made radionuclides in cow milk, mixed vegetation, fish, and sediment. As L reported in the past for sediment, low levels of Co-60 were detected 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 radiological impact on the environment.
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