ML20199G373

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Annual Radiological Environ Surveillance Rept,1985
ML20199G373
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 12/31/1985
From: Capstick R
VERMONT YANKEE NUCLEAR POWER CORP.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
FVY-86-35, NUDOCS 8606250203
Download: ML20199G373 (63)
v • d • e


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I VERMONT YANKEE NUCLEAR POWER CORPORATION ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT January - December 1985 L

i I April 1986 I -

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I I Prepared By: Yankee Atomic Electric Company Environmental Engineering Department I 1671 Worcester Road Framingham, Massachusetts 01701 l 8606250203 851231 49)\f s/

ADOCK 05000271 l I PDR R PDR y(

I TABLE OF CONTENTS Page LIST OF TABLES. . .. . . .. ..... .. . iii LIST OF FIGURES... .. .. . . . . ... ............ iv

1.0 INTRODUCTION

. .. . . .. . . .. . . ........... . ... . 1 2.O ENVIRONMENTAL SURVEILLANCE PROGRAM. . . . .. ...... ... 2 3.O

SUMMARY

OF 1985 ENVIRONMENTAL DATA. . . . .. .. ... ..... 14 A. Air Particulate., ..... . ... . .. . ...... . ......... 16 B. Charcoal Filter. .. . . .. 20 C. Milk. . . .. . . ... . . .. ... . . .. 22 D. Mixed Vegetation. . . . .. . . .. . .

25 E. Food Crop. . . . . . .

28 F. Meat, Poultry, Eggs. .. . .... .. . ... . . . . ...

29 G. Silage. .. . . . . ... .. . .. ..

30 I

H. Ground Water. ... . .. ... . . . . . . .

33 I. River Water.. . ... .. . . . ... .... .. ..... .... .. . 36 I J.

K.

L.

Aquatic Vegetation.

Sediment.

Finfish.

39 40 43 M. Direct Radiation.

I 46 l 4.O QUAllIY ASSURANCE PROGRAM. . ... . ..

51 5.0 LAND USE CENSUS.

55 6.0

SUMMARY

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7.0 REFERENCES

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I LIST OF TABLES Number Title Pago 2.1 Radiological Environmental Surveillance Program (Before April 1, 1985)... .. .. .. . . . .. ...... .. 3 2.2 Radiological Environmental Surveillance Program (After April 1, 1985).. .................... .......... 4 2.3 Radiological Environmental Surveillance Locations... . .... 5 3.1 Summary of Direct Radiation Measurements - 1985. . .. 48 3.2 Ratio of Zone 1 to Zone 2 Exposure Rates. .. . 50 C

g 4.1 Intralaboratory and EPA Interlaboratory Results - 1985..

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53 5.1 1985 Land Use Census Results. . .. .. .. . .

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LIST OF FIGURFS Number Title Page I 2.1 Environmental Radiological Monitoring Locations in Close Proximity to Plant. .. ...... ... .. .. .. .. . .. ..... 8 2.2 Environmental Radiological Monitoring Locations Within 5 Kilometers of Plant. .. ..... ......................... 9 2.3 Environmental Radiological Monitoring Locations Greater Than 5 Kilometers from Plant.............. ............ . . 10 2.4 TLD Locations in Close Proximity to Plant., . .. 11 2.5 TLD Locations Within 5 km of Plant.......................... 12 2.6 TLD Locations Greater than 5 km from Plant. . ... ....... 13 E 3.1 Gross Beta Measurements of Air Particulate filters at Vermont Yankee. .. . . ...... . .. ........ 17 I

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1.0 INTRODUCTION

I The radiological environmental surveillance program at Vermont Yankee has boon designed and carried out with specific objectivos in mind. They are as follows:

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To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation I of the nuclear power station.

To provido assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated.

limits.

I To verify the adequacy and proper functioning of station effluent controls and monitoring systems.

lo provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.

l Ouring 1985, as in the past, Aquatoc, Inc., collected all of the aquatic environmental samples, while the Chemistry and Health physics staff I collected the bulk of the torrestrial environmental samplos and processed all environmental thermoluminescent dosimeters (TLDs) for direct radiation measuromonts. After the initial processing, all non-TLD samplos wore sont to the Yankee Atomic Environmental Laboratory in Westboro, Massachusetts for l

1 further processing and radionuclido analysis.

Significant changes in the radiological environmental surveillance

!' program were made with the implomontation of the new Radiological Effluent i l

l Technical Specifications (RETS) on April 1, 1985. Results from this program l and the former program are presented in this report.

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I 2.0 ENVIRONMENTAL SURVEILLANCE PROGRAM In this section, Table 2.1 outlines the surveillance program as required by the plant Technical Specifications. Table 2.2 lists the sampling I stations and their specific locations (distances are measured from the conter of the Containment Building). The monitoring locations are shown on maps in I Figures 2.1 through 2.3.

In the transfer to the new Radiological Effluent Technical Specifications on April 1, 1985, the two-digit codos for many sampling locations were changed. Likewise, the two-digit codes for some of the sampling locations terminated after April 1985 were given to now locations.

I Table 2.3 gives the pre-April I code and the post-April I code, as well as the codo used in this report.

Below are listed the two-letter media code letters and what they represent:

I AP Air Partic late CF Charcoal F11ter TM Milk I WG WR Ground Water River Water IG Mixed Vogolation I. TC Silage IF Food Crop T7 Meat, Poultry, Eggs TS Soil SL Sediment Fil Finfish l

I AV DR Aquatic Vegetation Direct Radiation (TLD)

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I Table 2.1 Vermont Yankee Radiological Environmental Surveillance Progry (Hefore April 1, 1985)

Media Sampling Frequency _Re_ quired Analyses I Air Particulate (AP) - Weekly

- Quarterly Composite Gross beta, Sr-89/90 (2)

Gamma spectroscopy Charcoal Filter (CF) - Weekly I-131 Milk (TM) - Monthly Gamma spectroscopy, I-131

- Quarterly Composite Sr-89/90 Mixed Vegetation (1G) - Quarterly (1) Gamma spectroscopy I Food Crop (TF) - Annually (4) Gamma spectroscopy, I-131 on green leafy portions of vegetables Meat, Poultry, Eggs (TZ) - Annually (3) Gamma spectroscopy I Silage (TC) -

Annually (4) Gamma spectroscopy I Ground Water (WG) Quartorly

- Once Per 3 Years Gross beta. H-3, gamma spectroscopy, Sr-89/90 (2)

Ra -2 26 -

River Water (WR) -

Monthly (1) Gross beta, gamma spectroscopy H-3,

- Quarterly Composite Sr-89/90 (2)

  • Aquatic Vegetation (AV) - Semiannually Gamma spectroscopy, Gr-89/90 (2)

Soil (TS) - Once Per 3 Years Gamma spettroscopy, SR-89/90 (2)

Sediment (SE) - Somiannually Gamma spectroscopy, Sr-89/90 (2)

I Finfish (FH) - Semiannually (1) Gamma spectroscopy, Sr-89/90 (2)

Direct Radiation (GM) - Monthly Integrated gamma doso (1) Collection frequency dependent upon availability of samples during winter.

, (2) Performed whenever plant-related Cs-137 concentration is 10X non-plant-related Cs-137 concentration.

(3) Subject to availability at end of grazing season.

I (4) Collected at harvest time in reasonable proximity to specified location; subject to availability.

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I Table 2.2 I Vermont Yankee Radiological Environmental Surveillance Program (After April 1, 1985)

Media Sampling Frequency R_e_ quired Analy se_s I Air Particulate (AP) - Semimonthly (2)

- Quarterly Composite Gross beta Gamma spectroscopy Charcoal Filter (CF) - Semimonthly (2) I-131 1 Milk (TM) - Monthly (7) Gamma spectroscopy, I-131 Mixed Vegetation (TG) - Quarterly (1) Gamma spectroscopy Silage (TC) - Annually (4) Gamma spectroscopy Ground Water (WG) - Quarterly Gamma spectroscopy, H- 3 River Water (WR) - Monthly (1) (6) Gamma spectroscopy

- Quarterly Composite H-- 3 Sediment (SE) - Semiannually Gamma spectroscopy Finfish (FH) - Semiannually (1) Gamma spectroscopy Direct Radiation (DR) - Quartorly Integrated gamma doso(5)

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I (1) Collection frequency dependent upon availability of samples during winter.

(2) Wookly, when main plant stack offluent release rato of I-131 is equal to 1 or greater than 0.1 uCi/sec.

(3) Subject to availability at end of grazing season.

(4) Collected at harvest time in reasonable proximity to specified location;

'I subject to availability.

(5) Outer ring TLDs - De-dose quarterly unless gaseous release LCO was exceeded in period.

(6) Composite sample collected over month at downstream location.

I (7) Semimonthly when milk animals are identified as being on pasturo.

I Table 2.3 Vermont Yankee Radiological Environmental Surveillance Locations Station Code (Media - Station No.) Distance I Before After This Report April 1 April 1 Station Description MMM Zone From Plant Direction (km) From Plan _t i AP/CF/TG-10 10 I 1.2 M Hinsdale, NH NE AP/CF/TG-11 13 11 River Station No. 3.3 1 1.9 SSE Ao/CF/TG-12 11 12 N. Hinsdale, NH 1 3.6 NNW AP/CF/IG-13 12 13 Hinsdale Substation 1 3.1 E I AP/CF/TG-14 AP/CF/TG-15 AP/CF/TG-16 23 15 14 14 15 M

Northfield, MA Tyler Hill fairman Road 1

1 1

11.3 3.4 2.4 SSL WNW SW

,g AP/CF/TG-21 22 21 Spof ford Lake, NH 2 16.1 NNE g AP/CF/TG-22 21 M Hogback Mountain 2 25.0 WNW TM/TC-11 11 11 Miller Farm 1 0.8 WNW TM/TC-12 12 12 Whitaker Farm 1 2.6 S '

TM/TC-11 13 13 Newton For m 1 5.1 SSE TM/TC-14 MM 14 Brown Farm 1 2.1 SSW I TM/IC -15 TM/lC-21 TM/TC-22 Mk 21 l ',

21 Coombs for m Moore F arm Brattleboro Dairy 1

2 2

4./

15.9 15.0 NW N

N WG- 11 11 11 VY Plant Well 1 -

On-Site WG -17 17 12 Vernon Nursing Woll 1 2.0 SSE WG- 13 13 M VT No. 32 Well 1 1.8 SE WG-21 21 21 Brattleboro C C. 2 12.I NNW WR 11 11 11 River Station No. 3.3 1 1.9 Downriver i WR-12 WR-21 FH-11 12 21 17

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11 M Plant Dischargo Rt. 9 Bridge Vernon Pond 1

12.8 12.8 On-Site Upriver 1 -

On -S i t o FH-12 11 M River Station No. 3.3 1 1.9 Downriver FH-21 21 21 Rt. 9 Bridgo 2 12.8 Upriver l SE-11 12 11 Shoreline Downriver 1 -

On-Site 5 SE-12 MM 12 N. Storm Drain Outfall 1 -

On -S i te SE-13 11

  • River Station No. 3.3 1 1.9 Downriver SE-21 21 M Rt. 9 Bridge 2 12.8 Upriver AV-11 11 M Downstream Swamp 1 0.0 Downriver AV-21 21 M Upstream Swamp 2 0.8 Upriver

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I Table 2.3 (Continued)

Vermont Yankee Radiological Environmental Surveillance l ocations Station Code (Media - Station No.) Distance I' Before After This Report April 1 April 1 Station Description MMM From Plant Direction From Plant Zone (km)

DR-1 1.3 1 River Station No. 3.3 1 1.9 SSE DR-2 1.1 2 N. Hinsdale, NH 1 3.6 NNW DR-3 1.2 3 Hinsdale Substation 3.1 E I

1 DR-4 2.3 4 Northfield, MA 1 11.3 SSL DR-5 2.2 5 Spofford Lake, NH 2 16.1 NNE DR- 6 DR-7 1.17 1.8 6

7 Vernon School Site Boundary 1 0.6 0.32 SW SSW g

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D R- 8 1.9 8 Site Boundary 1 0.45 S DR-9 MM 9 Inner Ring -

1.8 N DR-10 MM I 4.3 10 Outer Ring -

N DR -11 Mk 11 Inner Ring -

1.8 NNE DR-12 MM 12 Outer Ring -

3.4 NNL DR-13 1.0 13 Inner Ring -

1.2 NE DR- 14 MW 14 Outer Ring 4.2 NL I. DR-15 MM 15 Inner Ring -

1.4 ENL DR-16 MM 16 Outer Ring -

2.9 ENE I DR-17 MM 17 Inner Ring -

1.3 E DR-18 MM 18 Outer Ring -

3.1 [

DR-19 MW 19 Inner Ring -

3.6 ESE DR-20 MM 20 Outer Ring -

5.5 ESL DR-21 MM 21 Inner Ring -

2.1 SE DR- 22 MM 22 Outer Ring -

3.5 SI DR-23 MM 23 Inner Ring -

2.l SSI I DR-24 MM 24 Outer Ring -

4.2 SSL DR-25 MM 25 Inner Ring -

2.3 G DR-26 MM 26 Outer Ring -

4.0 S DR-27 MM 27 1.2 I

Inner Ring -

SSW DR-28 MM 28 Outer Rir.g -

2.4 SSW DR-29 MM 29 Inner Ring -

0.8 SW DR-30 1.4 30 Outer Ring 2.4 SW I

DR-31 Mk 31 Inner Ring WSW 0.8 DR-32 MM 32 Outer Ring -

5.0 WSW DR-33 Mk 33 Inner Ring -

0.8 W I DR-34 DR-35 DR-36 MM MM 34 35 36 Outer Inner Outer Ring Ring Ring 4.8 1.2 4.5 W

WNW WNW DR-37 MM 37 Inner Ring -

2.7 NW I

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'I Table 2.3 (Continued)

Vermont Yankee Radiological Environmental Surveillance Locations Station Code I (Media - Station No.)

Before After This Report April 1 April 1 Station Description MMM Zone Distance From Plant Direction (km) From Plant DR-38 MM 38 Outer Ring -

7.4 NW i DR-39 MM 39 Inner Ring -

2.9 NNW DR-40 MM 40 Outer Ring -

4.8 NNW g DR-41 1.10 41 Site Boundary 1 0.630 S g DR-42 1.11 42 Site Boundary 1 0.920 S DR-43 1.12 43 Site Boundary 1 0.760 SSE p DR-44 1.13 44 Site Boundary 1 0.480 SSI: L DR-45 1.14 45 Site Boundary 1 0.315 SE DR -46 1.15 46 Site Boundary 1 0.027 N DR-47 1.6 47 Site Boundary 1 0.160 NNW I DR-48 DR-49 DR-50 1.16 1.7 M

48 49 50 Site Boundary Site Boundary Governor Hunt House 1

1 1 0.395 0.315 0.630 NW WNW S

I DR-51 M 51 Site Boundary 1 0.300 SSW DR -52 1.5

  • Tyler Hill 1 3.4 WNW DR-53 2.1 M Hogback Mountain 2 25.0 WNW I

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M Not required by RETS (after April 1, 1985).

MM Added to program af ter April 1, 1985.

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  • MN 1 = Indicator Station; 2 = Control Station.

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I 3.0.

SUMMARY

OF 1985 ENVIRONMENTAL DATA I The following pages summarize the analytical results of all the environmental samples which were collected during 1985. Each environmontal 8 media category is presented as a separate subsection. A discussion of the sampling program and results is followed by a table which summarizes the I year's data for each category. The tables, for all media but Direct Radiation, were generated by the computer program, ERMAP. At the top of each 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 ton timos the yearly average of control moasurements. The latter are classified as "non-routine" measurements. The next column lists the Lower Limit of Detection (LLD) for those radionuclidos which have detection capability requirements as specified in the Radiological Effluent Technical I Specifications.

lhose sampling stations which are adjacent to the plant and which could conceivably be affected by the operation of Vermont Yankee are called

" Indicator" or " Zone 1" stations. Distant stations, which are beyond plant influence are called " Control" or " Zone 2" stations.

I ERMAP calculates a set of statistical parameters for each This set of statistical paramotors includes separate analyses I

radionuclido.

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.

I I o I The standard error of the mean.

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I o The lowest and highest concentration.

o The number of positive measurements (a concentration which is greater than the a posteriori LLD for that analysis) divided by the total number of measurements.

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I Each single radioactivity measurement datum in this report is based on a single measuremont 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 radioactivo decay process (counting statistics), and not the propagation of all possible uncertainties in the I

analytical procedure.

Based on the requirement of RETS Table 4.9.3 (Footnote f), any concentration below the LLD for its analysis is reported as "not detected."

These values are set to zero for averaging purposes. Where a range of values is reported in the tables of this section, values less than the a posteriori LLD for the analysis are reported as zero.

I The program described in the following text represents the post-April 1, 1985 RETS program. For details on the pre-April 1, 1985 I program, see Tables 2.1 and 2.3.

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I A) Air Particulate Air monitoring stations were established at a total of five locations (one additional station was added in August, making the total six). Five of these locations are indicators, while the I remaining one is a control station. Airborne particulates are collected by passing the air through a glass-fiber filter. These I filters are collected semimonthly and held for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> before being analyzed for gross beta activity (indicated as GR-B in tables) to allow for the decay of radon and thoron daughter products. Quarterly composite air filters from each location are analyzed for gamma emitting radionuclides.

Gross-beta counts (Figure 3.1) generally showed the same I fluctuations at indicator stations as at controls, thereby indicating that any plant contribution was negligible. Other than naturally-occurring Be-7, no gamma-emitting radionuclides wore detected on the quarterly composite filters.

I Pump failure resulted in-a low sample volume on three occasions during 1985: .1) at Station AP-22 (Hogback Mt.) during the December 26, 1984 through January 2, 1985 week; 2) at Station AP-22 (Hogback Mt.) during the January 2, 1985 through January 8, 1985 I week; 3) at Station AP-12 (N. Hinsdale) during the December 1, 1985 through December 13, 1985 period. Only in the second was the RETS LLD not met. The RETS were not, however, implemented at that time. Consequently, no LLD requirements were violated.

Five anomalous measurements can be seen in Figure 3.1. In each case, the calculated concentration is suspect due to gas meter malfunction, uncentered particulate filter with subsequent bypass, noticeable light loading on filter due possibly to bypass, low pump I volume due to malfunction, or low measured volume for unknown reason.

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I ENVIR0l# ENTAL RADIOLOGICAL PROEAM SLfftARY VERMONT YAN(EE NUCLEAR POWER STATION. VERNON VT JANUARY - DECEMEER 1985 I EDILM: AIR PARTICLA. ATE (MITSt PCI/CU. M 5 INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS )

mmmmmm mmummemmm. mummum j RADIONUCLIDES MEAN MEAN EAN I (NO. ANALYSES) REQUIRED RANGE (N0HOUTIE)* LLD NO. DETECTEDee STA.

NO.

RANGE NO. DETECTED **

RANGE NO. DETECTED **

I GR-B (225)

( 0)

.01 ( 2.21

( 0.0 -

.0)E -2 4.8)E -2 10 ( 2.6 i

( !.7 -

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( 2.2 i

( 1.1 -

.1)E -2 5.5)E -2

  • (177/179)e a( 14/ 14)* *( 46/ 46)*

BE-7 ( 25) ( 5.71 .3)E -2 22 ( 6.7 i .4)E -2 ( 5.9 i .7)E -2

( 3.5 - ( 3.5 - 7.5)E -2 I

( 0) 7.3)E -2

  • ( 20/ 20)* *( 1/ 1)* *( 5/ 5)*

K-40 ( 25) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O

( 0)

I *( 0/ 20)e *( 0/ 5)*

IN-54 ( 25) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0 I ( 0)

  • ( 0/ 20)* *( 0/ 5)*

CO-58 ( 25) ( 0.0i 0.01E O ALL EQUAL ( 0.0 i 0.0)E O

( 0)

  • ( 0/ 20)e *( 0/ 5)e 8 FE-59 ( 25) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0 i

( 0)

  • ( 0/ 20)* *( 0/ 5)*

CO-60 ( 25) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

  • ( 0/ 20)* *( 0/ 5)*

ZN-65 ( 25) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O I ( 0)

  • ( 0/ 20)* *( 0/ 5)*

ZR-95 ( 25) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O I ( 0) et 0/ 20)* *( 0/ 5)*

I e N0H0lfilE REFERS TO TE NUMBER OF SEPARATE EASUREENTS WHICH WERE GREATER I THAN TEN (10) TIES TE AVERAGE BACK0R0lMD FOR TE PERIOD OF TE REPORT.

    • TE FRACTION OF SAlfLE ANALYSES YIELDING DETECTABLE EASUREENTS (I.E. > A POSTERIORI LLD) IS INDICATED WITH *( )*.

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I ENVIROWENTAL RADIOLOGICAL FROGRAM Slft1ARY VERMONT YAM (EE NLICLEAR POWER STATION, VERNON. VT JANUARY - DECEMBER 1985 I EDIlM: AIR PARTIClLATE UNITS: PCI/CU. M l

INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONG RADIONta. IDES EAN EAN I

MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-R0llTIE). LLD NO. DETECTED.. NO. NO. DETECTED.* NO. DETECTED.. )

AG-1!0M( 25) ( 0.0i 0.0)E O All EQUAL ( 0.0 1 0.0)E O

( 0)

  • ( 0/ 20)* et 0/ 5)*

Rl)-103 ( 25) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O at 0/ 20)e a( 0/ 5).

RU-1% ( 25) ( 0.0i 0.0)E O E EQUAL ( 0.0 i 0.0)E 0

( 0)

I *( 0/ 20). *( 0/ 5).

CS-134 ( 25) .05 ( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O  ;

l

( 0)

  • ( 0/ 20)* *( 0/ 5)*

l CS-137 ( 25) .06 ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O '

l ( 0)

  • ( 0/ 20)* *( 0/ 5)*

BA-140 ( 25) ( 0.01 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O

( 0)

  • ( 0/ 20)* *( 0/ 5)e CE-141 ( 25) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0

( 0)

.( 0/ 20). *( 0/ 5)*

CE-144 ( 25) ( 0.0t 0.0)E .0 ALL EQUAL ( 0.0 i 0.0)E O I

( 0)

  • ( 0/ 20). , et 0/ 5)*

TH-232 ( 25) ( 0.0i 0.0)E O ALL EWAL i 0.0 1 0.0)E 0 I ( 0)

  • ( 0/ 20)* *( 0/ 5)e I

. NON-R0lfTIE REFERS TO TE NJMBE9 0F SEPARATE EASUREENTS lHICH WERE GREATER THAN TEN (10) (IES TE AVERAGE BACATRAJNLI FOR TE PERIOD OF TE REPORT.

I TE FRACTION OF SAPPLE ANALYSES YIELDINO DETECTABLE EASUREENTS

(!.E. > A POSTERIORI LLD) IS INDICATED WITH .( )*.

I

E B) Charcoal Filters I Charcoal filter cartridges are situated in series with the air <

particulate glass-fiber filters. Monitoring stations were established at a total of five locations (one additional station was added in August, making the total six). Five of these are I indicators and one of these is a control. Charcoal filters from the air sampling stations were collected and analyzed semimonthly for I-131 activity. No radioactive I-131 was detected on any 1985 charcoal filter sample.

I Pump failure resulted in a low sample volume on three occasions during 1985: 1) At Station CF-21 (11ogback Mountain) during the 12/26/84 -- 1/2/85 week; 2) at Station CF-21 (Hogback Mountain) <

during the 1/2/85 - 1/8/85 week; and 3) at Station CF-12 (N.

l Hinsdale, NH) during the 12/1/85 - 12/13/85 period. Only in the second case was the RETS LLD not met. The RETS were not, however, implemented at that time. Consequently, no LLD requirements were violated.

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I ENVIR0KNTfL RADIOLOGICAL PROGRM SLM%RY WRMONT YA10(EE NUCLEAR POWER STATION. VERNON. VT JANUARY - DECEMBER 1985 I EDILM: CHARCOAL FILTER LMITS: PCI/CU. M

!!OICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS I RADIONU(2. IDES (ND. Al# LYSES) REQUIRED RANGE (N0HOUTIE). LLD EAN NO. DETECTEDH NO.

MEAN STA. RANGE NO. DETECTED.i EAN RANGE NO. DETECTED 8 I-131 (225) .07 ( 0.0t 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

( 0)

.( 0/179). .( 0/ 46).

I . N0HOUTIE REFERS TO TE NLf9ER OF SEPARATE EASWEENTS lei!CH ERE WEATER THAN TEN (10) TIES TE AVERAGE BACKGROLM) FOR TE PERIOD OF TE REPORT.

.. TE FRACTION OF SAfFLE ANALYSES YIELDINO DETECTABLE EASUREENTS I (I.E. > A POSTERIORI LLD) IS Il0!CATED WITH .( )..

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I C) Milk I Milk samples were collected and analyzed monthly for low level I-131 and gamma -omitting radionuclidos . Monthly samples were 5 composited quarterly and analyzed for Sr-89 and Sr-90 (this is not a RETS requirement).

I Detectable concentrations of Cs-137 and Sr-90 were measured in milk samples submitted from the indicator and control locations.

Concentrations were similar to those detected in 1984. The detected levels are consistent with those measured in cow milk at other New England locations. Such levels have been well documented and are attributed to fallout from nuclear weapons tests.

In addition to these radionuclides, naturally occurring K-40 was detected in all samples.

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I EWIROMENTAL RADIOLOGICAL PROGRAM SLM%RY VERMONT YAEEE NUCLEAR FTlWER STATION, VERNON, Vi I EDILM: MILK JANUARY - DECEMBER 1985 LNITS: PCI/KG B IIE)lCATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS MMeeHitHetMae GM MfM M M Mi4 H HettM e+MHHtMitHe I RADIONUCLIDES (NO. ANALYSES) REQUIRED RANGE (NON-ROUTIEle LLD EAN NO. DETECTEDe*

STA.

NO.

EAN RANCE NO. DETECTED **

EAN RANGE NO. DETECTEDH j SR-69 ( 18) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0

( 0) et 0/ 14)e *( 0/ 4)e SR-90 ( 18) ( 2.3i .2)E O 14 ( 3.8 i .3)E 0 ( 2.6 i .1)E O

( 1.3 - ( 2.5 - 2.8)E 0 I 3.8)E O

( 0)

  • ( 14/ 14)e *( 1/ 1)* *( 4/ 4)e K-40 ( 52) (  !.3i .0)E 3 22 ( 1.5 t .0)E 3 ( !.4 i .0)E 3 I ( 0) ( 1.2 -

a( 40/ 40)*

1.5)E 3 ( 1.4 -

a( 4/ 4)*

1.5)E 3 ( 1.3 -

  • ( 12/ 12)*

1.5)E 3 I PN-54 ( 52)

( 0)

( 0.0i 0.0)E O

  • ( 0/ 40)e ALL EQUAL ( 0.0 1
  • ( 0/ 12)*

0.0)E O CO-58 ( 52) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O

( 0)

  • ( 0/ 40)e *( 0/ 12)*

FE-59 ( 52) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0

( 0)

  • ( 0/ 40)* et 0/ 12)*

CD-60 ( 52) ( 0.0f 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

  • ( 0/ 40)e *( 0/ 12)*

ZN-65 ( 52) ( 0.0f 0.0)E O ALL EQUAL ( 0.0 i 0.0)E 0

( 0)

I *( 0/ 40): *( 0/ 121e ZR-95 ( 52) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0 I ( 0) e( 0/ 40)* *( 0/ 12)e

~

I I e NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREENTS lHICH WERE GREATER TIMN TEN (10) TIES TE AVERAGE BACK0R0lM) FOR TE PERIOD OF TE REPORT.

H TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTABLE EASLREENTS (1.E. > A POSTERIORI LLD) IS INDICATED WITH et le.

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ENWR0ffENTAL RADIOLOGICAL PROGRAM SltttARY VERMONT YAEEE MJCLEAR POER STATION. VERM)N VT JANUARY - DECEMBER 1985 i EDItti: MILK (MITS: PCl/KG j INDICATOR STATIONS STATION WITH HIGEST M CONTROL STATIONS

.e e* - e***e ...e*** ee

  • e*

M M I

RADIONUCLIDES EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON40VIIE)* LLD NO. DETECTED.* NO. NO. DETECTED.* NO. DETECTED RU-103 ( 52) ( 0.0i 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E 0

( 0)

.( 0/ 40)* et 0/ 12)*

RU-106 ( 52) ( 0.0 0.0)E O ALL EQUAL ( 0.0 i 0.0)E 0 a( 0/ 40)e *( 0/ 12)*

I-131 ( 52) 1. ( 0.0t 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O I ( 0)

  • ( 0/ 40). *( 0/ 12)*

CS-134 ( 52) 15. ( 0.0t 0.0)E O ALL EQUfL ( 0.0 t 0.0)E O I ( 0)

  • ( 0/ 40)* a( 0/ 12)*

I CS-137 ( 52)

( 0)

18. ( 2.7t

( 0.0 -

  • ( 4/ 40)*

1.4)E -1 3.7)E O 14 ( 3.5 t

( 3.4 -

  • ( 2/ 2)*

.1)E O 3.7)E O

( 4.4 i

( 0.0 -

  • ( 2/ 12)*

3.1)E -1 3.4)E O BA-140 ( 52) 15. ( 0.0t 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E O

( 0) l

  • ( 0/ 40)e *( 0/ 12)* l I CE-141 ( 52) ( 0.0t 0.0)E 0 ALL EQUAL ( 0.0 1 0.0)E O

( 0)

  • ( 0/ 40)* .( 0/ 12)e CE-144 ( 52) ( 0.0i 0.0)E 0 ALL EQUAL (0.01 0.0)E O

( 0)

I *( 0/ 40)* *( 0/ 12)e TH-232 ( 52) ( 0.0t 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

( 0) 5 *( 0/ 40)* *( 0/ 12)e

  • NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASLREENTS IMICH ERE GREATER THAN TEN (10) TIES TE AVERACE BACK0ROLND FOR TE PERIOD OF TE REPORT.

.* TE FRACTION OF SAWLE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. > A POSTERICRI LLD) IS INDICATED WITH *( )*.

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1 D) Mixed Vcqetation I Mixed vegetation samples were collected during May, July, and October from the five air sampling locations. The vegetation consisted of various types of grasses and were analyzed for gamma emitting nuclides. The results of the gamma spectroscopy analysis I on each sample showed that in addition to naturally occurring Be-7, K-40, and Th-232, Cs-137 was detected on many samples. The levels l

detected in 1985 are consistent with those measured in previous years, which were shown to have originated frem nuclear weapons testing fallout.

I Snow cover and lack of the proper vegetation prevented a fourth quarterly sample from being collected during 1985.

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I ENVIR0 MENTAL RADIOLOGICAL PROGRAM SLMMARY I

WONT YAMEE MILEAR POWER STATION, VERNON. VT JANUARY - DECO SER 1985 EDIlms MIXED WOETATION LMITS PCI/KG ET I IM)lCATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS GHMMe*MHHeH *HH e* *H H e * *H* H e Me * *HeH*H*HH H I RADIONUCLIDES (NO. AMLYSES) REQUIRED RANGE (NDHOUTIEle LLD EAN NO. DETECTED *e STA.

NO.

EAN RAME NO. DETECTED **

EAN RANGE M). DETECTED 6e I BE-7 ( 15)

( 0)

( 9.11 2.2)E 2

( 2.0 - 25.0)E 2 14 ( 1.2 i .7)E 3

( 2.1 - 25.0)E 2

( 2.9 i

( 0.0 -

1.4)E 2 4.4)E 2 et 12/ 12)e e( 3/ 3)e *( 2/ 3)e K-40 ( 15) ( 4.81 .4)E 3 13 ( 5.3 i .5)E 3 ( 5.3 i .3)E 3

( 2.7 - 7.3)E 3 ( 4.7 - 6.3)E 3 ( 4.8 - 5.9)E 3 I

( 0) a( 12/ 12)e a( 3/ 3)e e( 3/ 3)*

19RA ( 15) ( 0.0 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E 0 I ( 0) et 0/ 12)e et 0/ 3)*

I CO-58 ( 15)

( 0)

( 0.0i 0.0)E O

  • ( 0/ 12)*

ALL EQUAL ( 0.0 i

  • ( 0/ 3)e 0.0)E O FE-59 ( 15) ( 0.0i Og0)E 0 ALL EQUAL ( 0.0 i 0.0)E O

( 0)

  • ( 0/ 121e *( 0/ 3)*

I 00-60 ( 15)

( 0)

( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0 l

l

  • ( 0/ 12)* *( 0/ 3)*

ZN-65 ( 15) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0

  • ( 0/ 12)* *( 0/ 3)e ZR-95 ( 15) ( 0.01 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O

( 0)

I *( 0/ 12)e et 0/ 3)*

( 0.0 i I 0.0)E O AG-110M( 15) ( 0.0t 0.0)E O ALL EQUR.

( 0) a( 0/ 12)* *( 0/ 3)e I

I e NON-ROUTIE REFERS TO TE NUPSER OF SEPARATE EASUREMENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUM) FOR TE PERIOD OF TE REPORT.

    • TE FRACTION OF SAPOLE AMLYSES YIELDING DETECTABLE EAS! DENTS

(!.E. > A POSTERIORI LLD) IS INDICATED WITH *( 15 I

I E)NTR0 MENTAL RADIOLOGICAL PR00 RAM

SUMMARY

VERN0NT YAM (EE NUCLEAR POWER STATION. ENON. VT I EDILM: MIXED VEGETATION JANUARY - DECEMBER 1985 LMITS PCI/KG WET IM)lCATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS HHHe eHe**HHe Hee *****H H HeH eH Hee *HeteHeHeeeH EAN EAN EAN I

RADIONUCLIDES (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTIEle LLD NO. DETECTED ** NO. NO. DETECTEDH NO. DETECTED **

I RU-103 ( 15)

( 0)

( 0.01 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E 0 et 0/ 12)e a( 0/ 3)e RU-106 ( 15) ( 0.01 0.0)E O ALL EQUAL ( 0.0 i 0.0)E 0

  • ( 0/ 12)* *( 0/ 3ie I-131 ( 15) 60. ( 0.0i 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E O I ( 0)
  • ( 0/ 12)* a( 0/ 3)*

CS-134 ( 15) 60. ( 0.01 0.0)E 0 ( 0.9 i 0.0)E 0 I

ALL EQUAL

( 0)

  • ( 0/ 12)e *( 0/ 3)*

I CS-137 ( 15)

( 2)

80. ( 2.71

( 0.0 -

  • ( 4/ 12)*

1.8)E 1 2.1)E 2 13 ( 7.1 1 7.1)E 1

( 0.0 - 2.1)E 2

  • ( 1/ 3)e

( 4.3 i

( 0.0 -

a( 1/ 3)e 4.3)E O 1.3)E 1 BA-140 ( 15) ( 0.0i 0.0)E 0 ALL EQUAL (0.01 0.0)E 0

( 0)

  • ( 0/ 12)* *( 0/ 3)*

I CE-141 ( 15)

( 0)

( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

  • ( 0/ 12)e *( 0/ 3)*

CE-144 ( 15) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O I

( 0)

  • ( 0/ 12)* *( 0/ 3)e TH-232 ( 15) ( 5.0i 3.9)E 1 13 ( 1.5 i 1.5)E 2 ( 2.3 1 2.3)E 1 I ( 1) ( 0.0 -
  • ( 2/ 12)e 4.5)E 2 ( 0.0 -

e( 1/ 3)*

4.5)E 2 ( 0.0 - 7.0)E 1

  • ( 0/ 3)e I

e NON-R0lff!E REFERS TO TE NUMBER OF SEPARATE EASLREMENTS Wi!CH ERE GREATER I THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF TE REPORT.

    • TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. > A POSTERIORI LLD) IS INDICATED WITH *( le.

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I E) Food Crop I

No samples werc available locally prior to the April 1, 1985 RETS implementation date, and samplos were not required under tho. RETS after April 1, 1985.

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I F) Meat, poultry, Eqqs I No meat, poultry, or egg samples were available locally prior to the April 1, 1985 REIS implementation date, and sample colleci. ion was not required under the RETS after April 1, 1985.

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I G) Silage Silage samples were collected at the four milk sampling stations during 1985. Each sample was analyzed for gamma-emitting radionuclides. l I Naturally-occurring Oc-7, Th-232, and K-40 were detected in most samples. The only man-made radionuclide detected in silage was Cs-137 in a sample from Station TC-12 (14.1 1 2.1 pCi/kg).

Cesium-137 is associated with fallout from atmospheric nuclear weapons tests and the above level is consistent with well-documented environmental levels found in vegetation.

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ENVIR010 ENTAL RADIOLOGICAL PROGRAM SUMARY I

VERMONT YAEEE NUCLEAR POER STATION, VERNON. VT l

JAMJARY - DECDEER 1985 l EDIUM: SILACE LNITS: PCI/KG WET  :

I INDICATOR STATIONS STATION WITH HIGEST M CONTROL STATIONS

++ n n++ n*++ m n m ** m e m *++++ne*+++e n+++++++neu n II RADIOMJCLIDES (NO. ANALYSES) REQUIRED RANCE EAN STA.

EAN PANrE EAN RANCE (NON-ROUTIE)* LLD NO. DETECTED +e NO. NO. DETECTED ** NO. DETECTED **

E-7 ( 4) ( 5.51 .9)E 2 12 ( 7.1 i .3)E 2 ( 6.2 i .5)E 2

( 0) ( 4.1 - 7.1)E 2 I

I *( 3/ 3)* *( 1/ 1)e *( 1/ 1)*

K-40 ( 4) ( 3.6i .2)E 3 12 ( 3.9 i .1)E 3 ( 2.4 i .1)E 3 I ( 0) ( 3.1 - 3.9)E 3

  • ( 3/ 3)e *( 1/ 1)* *( 1/ 1)*

I M-54 ( 4)

( 0)

( 0.0f 0.0)E O

  • ( 0/ 3)*

ALL EQUAL ( 0.0 1

  • ( 0/ 1)*

0.0)E O I CO-58 ( 4)

( 0)

( 0.01 0.0)E 0

  • ( 0/ 3)*

ALL EQUAL ( 0.0 t 0.0)E O

  • ( 0/ 1)*

FE-59 ( 4) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

( 0)

  • ( 0/ 3)* *( 0/ 1)*

CO-60 ( 4) ( 0.01 0.01E O ALL EQUAL ( 0.0 i 0.0)E 0

( 0)

  • ( 0/ 3)* *( 0/ 1)*

ZN-65 ( 4) ( 0.0f 0.0)E O ALL EQUAL ( 0.0 i 0.0)E 0

( 0)

I *( 0/ 3)* *( 0/ 1)*

ZR-95 ( 4) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0

( 0) ,

  • ( 0/ 3)* e( 0/ 1)s I AG-110M( 4)

( 0)

( 0.0f 0.0)E O f( O! 31*

ALL EQUAL ( 0.0 1 a( 0/ 1)*

0.0)E 0 I

I e NON-ROJTIE REFERS TO T){ MMIER OF SEPARATE EASURDENTS WHICH WERE GEATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF TE REPORT.

    • TE FRETION OF SAPPLE ANALYSES YIELDING DETECTABLE EASUREENTS (1.E. > A POSTERIORI LLD) IS INDICATED WITH *( i s.

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I ENVIR0 MENTAL RADIOLOGICAL PROGRM SUMARY I EDILM: SILAGE VERMONT YAEEE NUCLEAR POWER STATION. VERNON VT JANUARY - DECEMBER 1985 LMITS: PCl/KG ET I INDICATOR STATIONS

+++uememeten STATION WITH HIGEST EAN uneeeneenewu+eeneu CONTROL STATIONS

+++e+++++e+++ m I RADIONUCLIDES (NO. ANALYSES) REQUIRED RANGE (NON-ROUTIE)* LLD M

NO. DETECTEDee STA.

NO.

EAN RANGE NO. DETECTED +e MEAN RANGE NO. DETECTED **

I Rt)-103 ( 4) ( 0.0t 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)E 0 e( 0/ 3)e *( 0/ lie RU-106 ( 4) ( 0.0f 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O I ( 0)

  • ( 0/ 3)* *( 0/ 1)*

I-131 ( 4) 0.0t 0.0)E O ( 0.0 t

'I

60. ( ALL EQUAL 0.0)E O

( 0)

  • ( 0/ 3)* *( 0/ 1)*

CS-134 ( 4) 60. ( 0.01 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O

( 0)

  • ( 0/ 3)* a( 0/ 1)*

CS-137 ( 4) 80. ( 4.71 4.7)E 0. 12 ( 1.4 i .2)E 1 ( 0.0 t 0.0)E O

( 1) ( 0.0 - 1.4)E 1 et 1/ 3)* *( 1/ 1), *( 0/ 1)*

BA-140 ( 4) ( 0.0t 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O

( 0)

  • ( 0/ 3)e *( 0/ 1)*

CE-141 ( 4) ( 0.0t 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O I

( 0)

  • ( 0/ 3)* *( 0/ 1)e CE-144 ( 4) ( 0.0t 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O I ( 0) et 0/ 3)* *( 0/ lie I TH-232 ( 4)

( 1)

(  !.71 1.7)E 1

( 0.0 -

et 1/ 3)*

5.1)E 1 12 ( 5.1 i

  • ( 1/ 1)e 1.1)E 1 ( 0.0 t
  • ( 0/ 1)e 0.0)E O l

lI e NON-R0llTIE REFERS TO TK NUMBER OF SEPARATE EASUREENTS WICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACX0ROUND FOR TE PERIOD OF TE REPORT.

se TE FRACTION OF SMPLE MALYSES YIELDING IETECTABLE EASUREENTS I (!.E. > A POSTERIORI LLD) IS INDICATED WITH *( )*.

I

H) Ground Water I Ground water grab samples were collected from two indicator and one control station on a quarterly basis. These samples were analyzed for H-3 and gamma-emitting radionuclides. Additionally, gross-beta I analyses were performed, although they are not required.

Gross-beta radioactivity was detected in indicator and control

{ stations during 1985 and the concentrations are typical of those made over the past few years.

Cobalt-60 (48 1 2.5 pCi/kg) was detected in one ground water sample taken on May 8, 1985 at the Station 21 control. An investigation indicated that the Co-60 originated from contamination on the sample container.

I No other radionuclides were detected in the 1985 ground water samples.

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l ENVIRONMENTAL RADIOLOGICAL FROGRAM S(M1ARY I

VERMONT YAP 8(EE NUCLEAR POER STATION. VERNON. VT JANUARY - DECEMBER 1985 EDIUM: CR0lM3 WATER LMITS: PCI/KG Il()!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS

. .e.. .... ...e e. . .. ... . . . . . . .

I EAN EAN EAN RADIONUCLIDES (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTIE)* LLD NO. DETECTED.* NO. NO. DETECTEDie NO. DETECTED.*

I GR-B ( 13)

( 0)

4. ( 4.31

( 0.0 -

.9)E 0 9.8)E 0 13 ( 9.8 i .9)E 0 ( 1.5 i

( 1.2 -

.2)E 0 1.9)E 0 l

  • ( 8/ 9)* a( 1/ Ile *( 3/ 4)*

K-40 ( 13) ( 0.0t 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0

  • ( 0/ 9)e et 0/ 4)*

Pti-54 ( 13) 15. ( 0.0i 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)E 0 I ( 0)

  • ( 0/ 9)* .( 0/ 4)e I CO-58 ( 13)

( 0)

15. ( 0.01 0.0)E 0
  • ( 0/ 9)*

ALL EQUAL ( 0.0 i

  • ( 0/ 4)*

0.0)E O I FE-59 ( 13)

( 0)

30. ( 0.0i 0.0)E O
  • ( 0/ 9)*

ALL EQUAL ( 0.0 i

  • ( 0/ 4)*

0.0)E O CD-60 ( 13) 15. ( 0.0i 0.0)E O 21 ( 1.2 i 1.2)E 1 ( !.2 i 1.2)E 1

( 0) ( 0.0 - 4.8)E 1 ( 0.0 - 4.8)E 1

  • ( 0/ 9). *( 1/ 4)* a( 1/ 4)e ZN-65 ( 13) 30. ( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

( 0)

  • ( 0/ 9)* a( 0/ 4)*

ZR-95 ( 13) 15. ( 0.01 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E O I ( 0)

  • ( 0/ 9)* *( 0/ 4)e l

RU-103 ( 13) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O

( 0) l *( 0/ 9)e et 0/ 4)e I

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I e NON-ROUTIE REFERS TO TE NUMBER 0F SEPARATE EASUREENTS lHICH ERE CREATER THAN TEN (10) TIES TE AVERAGE BACK0R0lMD FOR TE PERIOD OF TE REPORT.

TE FRACTION OF SAff'LE MALYSES YIELDING DETECTABLE EASLREENTS j

{

(I.E. > A POSTERIORI LLD) IS INDICATED WITH *( )*.

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I ENVIROM1ENTR. RADIOLOGICAL PROGRAM SLMtARY VER!O(T YAM (EE NUCLEAR P06 STATION. VERNON. VT I EDILM: GROLMD WATER JANUARY - DECDEER 1985 LMITS: PCI/KG IlOICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATION?

  • Hef*Me**fHe*H #4HitHHHitMie64He** HH44HHHHH RADIOMJCLIDES EAN EAN EAN l (NO. A MLYSES) REQUIRED RANGE STA. RANGE RANGE j (N0HOUTIE)* LLD NO. DETECTED ++ NO. NO. DETECTEDe* NO. DETECTED ++

I RU-106 ( 13) ( 0.0 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E O

( 0)

  • ( 0/ 9)e et 0/ 4)*

I-131 ( 13) ( 0.0t 0.01E 0 ALL EQUAL ( 0.0 i 0.0)E 0 I

et 0/ 9)e et 0/ 4)*

CS-134 ( 13) 15. ( 0.0i 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O I ( 0)

  • ( 0/ 9)* a( 0/ 4)*

CS-137 ( 13) 18. ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O l ( 0)

  • ( 0/ 9)* a( 0/ 4)e BA-140 ( 13) 15. ( 0.0i 0.0)E 0 ALL EQUAL ( 0.0 1 0.0)E 0

( 0)

  • ( 0/ 9)e e( 0/ 4)e CE-141 ( 13) ( 0.0i 0.0)E 0 ALL EQUAL ( 0.0 1 0.0)E O

( 0)

  • ( 0/ 9)e I CE-144 ( 13)

( 0)

( 0.0 0.0)E O ALL EQUAL et 0/ 4)e

( 0.0 1 0.0)E O

  • ( 0/ 9)* *( 0/ 4)*

TH-232 ( 13) ( 0.01 0.0)E 0 ALL EQUAL ( 0.0 1 0.0)E O I ( 0)

  • ( 0/ 9)* e( 0/ 4)e H-3 ( 13) 3000. ( 0.0i 0.0)E O ( 0.0 1 0.0)E O I

ALL EQUAL

( 0)

  • ( 0/ 9)* *( 0/ 4)*
  • N0HOUTIE REFERS TO TE NUISER OF SEPARATE EASUREENTS lollCH ERE GREATER THAN TEN (10) TIES TE AVERAGE BACK0ROLMD FOR TE PERIOD OF TE REPORT.
    • TE FRACTION OF SAtFLE ANALYSES Y!ELDING DETECTABLE EASLRE!O(TS (1.E. > A POSTERIORI LLD) IS INDICATED WITH a( le.

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I) River Water River water is analyz~ed monthly for gamma-emitting radionuclides and gross-beta (not required by RETS). The monthly samples are composited and analyzed for H-3 on a quarterly basis. A composite I sampler is used at Station WR-11 and grab samples are taken at Station WR-21.

Gross-beta radioactivity was detected in all but four samples during 1985. The mean value, as well as the range of values, 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.

I No other radionuclides were detected in the 1985 river water samples. ,

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EM!IRONENTAL RADIOLOGICAL PROGRAM SIMIARY VERMONT YAMEE WCLEAR POER STATION VERNON, VT JANUARY - DECOEER 1985 ED!lM: RIVER WATER (MITS PCI/KG Ile!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS HeeHHHeHeeHe HeeH HeeHeeHHHeHH HHe***HHHH RADIONUCLIDES EAN EAN EAN I (NO. ANALYSES) REQUIRED RANGE (NON-ROUTIE)e LLD NO. DETECTEDH STA. RANGE NO. NO. DETECTEDet RANGE NO. DETECTEDee GR-B ( 28) 4. ( 1.5i .2)E 0 21 ( 2.2 i .3)E 0 ( 2.2 i .3)E O

( 0) ( 0.0 - 2.6)E O ( 0.0 - 4.0)E 0 ( 0.0 - 4.0)E 0

  • ( 13/ 16)* *( 11/ 12)* *( 11/ 12)e  !

K-40 ( 28) ( 0.0i 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)E 0

  • ( 0/ 16)e et 0/ 12)*

IW-54 ( 28) 15. ( 0.01 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O

( 0) et 0/ 16)e *( 0/ 12)e C0-58 ( 28) 15. ( 0.01 0.0)E O ALL EQUAL ( 0.0 t 0.0)E 0

( 0)

  • ( 0/ 16)* *( 0/ 12)*

I FE-59 ( 28)

( 0)

30. ( 0.0i 0.0)E O
  • ( 0/ 16)*

ALL EQUAL ( 0.0 i a( 0/ 12)*

0.0)E O CO-60 ( 28) 15. ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0

( 0)

  • ( 0/ 16)e *( 0/ 12)*

ZN-65 ( 28) 30. ( 0.0i 0.0)E O ALL EQUAL ( 0.0 t 0.0)E 0

( 0) et 0/ 16)* *( 0/ 12)e ZR-95 ( 28) 15. ( 0.01 0.0)E .0 All EQUAL ( 0.0 1 0.0)E 0

( 0) et 0/ 16)e , *( 0/ 12)*

RU-103 ( 28) -( 0.0 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E 0 I ( 0)

  • ( 0/ 16)* *( 0/ 12)e 1

e NON-ROUTIE (GERS TO TE NUMBtR OF SEPARATE EASUREENTS lHICH ERE GREATER I THAN TEN (10) TIES TE AYE*XE BACKGROUND FOR TE PERIOD OF TE REPORT.

    • TE FRACTION Or SieTLE ANALYSES YIELDING DETECIABLE EASUREE4TS (I.E. > A POSTERIORI LLD) IS INDICATED WITH f( )*.

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I ENVIROWENTAL RADIOLOGICAL PROM SIMIARY VERMONT YAM (EE MJCLEAR poler STATION VERNON. VT JAMJARY - DEElEER 1985 EDI(W RIVER WATER LMITS: PCI/KG IM)ICATOR STATIONS STATION WITH HIGEST M CONTROL STATIONS useweenmesm ************** ******* e+++++e++nenee I RADIONUCLIDES (NO. ANALYSES) REQUIRED RANGE (NON-ROUTIE)* LLD M

NO. DETECTEDee STA.

NO.

M RANGE NO. DETECTEDee EAN RANGE NO. ETECTEDee I RU-106 ( 28) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

( 0)

  • ( 0/ 16)e et 0/ 12)*

I-131 ( 28) ( 0.01 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E O I ( 0)

  • ( 0/ 16)e *( 0/ 12)e CS-134 ( 28) 15. ( 0.01 0.0)E O ALL EQUAL ( 0.0 i 0.0)E 0

( 0)

  • ( 0/ 16)e et 0/ 12)*

CS-137 ( 28) 18. ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

( 0) l et 0/ 16)* et 0/ 12)e l BA-140 ( 28) 15. ( 0.0i 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O

( 0)

  • ( 0/ 16)e *( 0/ 12)e CE-141 ( 28) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

( 0)

  • ( 0/ 16)* *( 0/ 12)*

CE-144 ( 28) ( 0.01 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

( 0)

  • ( 0/ 16)e *( 0/ 12)*

TH-232 ( 28) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O I ( 0) e( 0/ 16)e et 0/ 12)*

H-3 ( 10) 0.02 0.0)E O ( 0.0 i I

3000. ( ALL EQUAL 0.0)E O

( 0)

  • ( 0/ 6)* e( 0/ 4)e e NON400 TIE REFERS TO TE NMER OF SEPARATE EASUREENTS I4(ICH ERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF TE REPORT.
    • TE FRACTICN OF SAfftE ANALYSES YIELDINO CETECTABLE EASLREENTS (I.E. > A POSTERIORI LLD) IS INDICATED WITH *( le.

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I J) Aquatic Vegetation I Samples were not collected prior to the April 1, 1985 RETS implementation date, and collection was not required after that date under the RETS.

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1 I %) Sediment l

i During 1985, sediment samples were collected from two locations in May/ June, and October. Each sample was analyzed for gamma-emitting radionuclides.

Cesium-137 was detected in all samples. As has been discussed in previous Vermont Yankee Radiological Environmental Surveillance 1 Reports, this radioactivity has been due to nuclear weapons testing fallout. Since there were no liquid releases during 1982, 1983, or 1984, it can be concluded that the similar levels of Cs-137 in 1985 sediment samples were due also to nuclear weapons testing fallout.

I This is further supported by the fact that similar levels have in the past been detected at Station SE-21, a control station. Low levels of Co-60 have still been detected in samples collected at I Station 12 (N. Storm Drain Outfall). This subject was discussed in Reference 1.

Naturally-occurring Be-7, K-40, and Th-232 were also detected in many somoles.

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I ENVIR0 MENTAL RADIOLOGICAL PR00 RAM SLMIARY I EDILM: SEDIENT VERNONT YAM (EE NUCLEAR POER STATION VERNON VT JANUARY - DECEMBER 1985 LMITS: PCI/KG DRY t

IM)!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS M*4HeHHHHeH HHe**HHHHeHHHHe HHHeH* Heme RADIONLKLIDES EAN EAN EAN i (NO. ANALYSES) EQUIED RANGE STA. RANGE RANCE (NON-ROUTIE)* LLD NO. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

I BE-7 ( 8) ( 2.01 1.6)E 2 12 ( 2.7 i 2.2)E 2 NO DATA

( 21 ( 0.0 - 1.3)E 3 ( 0.0 - 1.3)E 3

  • ( 2/ 8)* f( 2/ 6)*

K-40 ( 8) ( 1.11 .1)E 4 12 ( 1.1 i .1)E 4 NO DATA

( 0) ( 7.0 - 17.1)E 3 ( 8.2 - 17.1)E 3

  • ( 8/ Ble *( 6/ 6)*

lW-54 ( 8) ( 0.0i 0.0)E 0 ALL EQUAL NO DATA

( 0) '

  • ( 0/ 8)*

I CO-58 ( 8)

( 0)

(

  • (

0.01 0.0)E O 0/ 8)*

ALL EQUAL NO DATA l FE-59 ( 8) ( 0.0t 0.0)E O ALL EQUAL NO DATA

( 0)

  • ( 0/ 8)*

CO-60 ( 8) ( 3.lt 1.0)E 1 12 ( 4.1 i 1.1)E 1 NO DATA

( 5) ( 0.0 - 6.7)E 1 ( 0.0 - 6.7)E 1

  • ( 5/ 8)* *( 5/ 61s ZN-65 ( 8) ( 0.0i 0.0)E O ALL EQUAL NO DATA

( 0)

I IR-95 ( 8)

  • ( 0/ 8)*

( 0.01 0.0)E O ALL EQUAL NO DATA l ( 0)

  • ( 0/ 8)s I

AG-110M( 8) ( 0.0i 0.0)E O ALL EQUAL NO DATA

( 0)

  • ( 0/ 8)*

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I e NON40VTINE REFERS TO TE NUPSER OF SEPARATE EASUREENTS lei!CH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACX0P0lMD FOR TE PERIOD OF TE REPORT.

    • TE FRACTION OF SAPPLE ANALYSES YIELDINO DETECTABLE EASLREENTS (1.E. > A K)STERIORI LLD) IS INDICATED WITH *( le.

I E)NIR0ffENTAL RADIOLOGIC #L PROGRAM SIANARY VERNONT YAf0(EE NUCLEAR POWER STATION, VERNON VT I EDI(M: SEDIENT JNJARY - DECDGER 1985 (MITS: PCI/KG DRY IPEICATOR STATIONS STATION WITH HIGEST M CONTROL STATIONS e ...

RADI0fGJCLIDES M M M (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTIEle LLD NO. DETECTEDen NO. NO. DETECTED.* NO. DETECTED I RU-103 ( 8)

( 0)

( 0.01 0.0)E O ALL EQUAL NO DATA

  • ( 0/ 8)*

RU-106 ( 8) ( 0.0t 0.0)E O ALL EQUAL NO DATA

  • ( 0/ Ble I-131 ( 8) ( 0.01 0.0)E O ALL EQUAL NO DATA

( 0)

I *( 0/ 8)* i l

CS-134 ( 8)

I 150. ( 0.0i 0.0)E 0 ALL EQUAL NO DATA

( 0)

  • ( 0/ 8)*

I CS-137 ( 8)

( 0) 180. ( 1.41 .3)E 2

( 4.4 - 31.8)E 1

  • ( 8/ 8)*

12 ( !.6 i .3)E 2

( 9.4 - 31.8)E 1

  • ( 6/ 6)e NO DATA BA-140 ( 8) ( 0.01 0.0)E 0 ALL EQUAL NO DATA

( 0)

  • ( 0/ 8)*

CE-141 ( 8) ( 0.0f 0.0)E O ALL EQUAL NO DATA

( 0)

  • ( 0/ 8).

E-144 ( 8) ( 0.0i 0.0)E O ALL EQUAL NO DATA l ( 0)

  • ( 0/ 8)*

TH-232 ( 8) ( 7.5i 1.0)E 2 11 ( 8.8 1 1.5)E 2 NO DATA I ( 0) ( 4.3 - 13.0)E 2 et 8/ 8)*

( 7.3 - 10.3)E 2

  • ( 2/ 2)*

I e NON-ROUTIE REFERS TO TE NUISER OF SEPARATE EASUREENTS lHICH WERE GREATER THW TEN (10) TIES TE AVERAGE BACK0ROLM) FOR TE PERIOD OF TE REPORT. 1

.e TE FRACTION OF SAfFLE ANALYSES YIELDINO DETECTABLE EAStPEENTS (I.E. > A POSTERIORI LLD) IS INDICATED WITH *( le.

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I L) Finfish Twice during 1985, finfish samples were collected from two locations. Each sample consisted of mixed fresh water species.

All were analyzed for gamma-emitting radionuclides. Cosium-137 was I

detected in two of the four samples collected. The levels are lower than those detected in the 1984 control samples, and are consistent with well-documented environmental levels caused by nuclear weapons testing fallout. No other radionuclides were detected except for naturally-occurring K-40.

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I ENVIROMOTAL RADIOLOGICAL PROGRAN SUN %RY YElWONT YAEEE IUCLEAR POER STATION. VERNON, VT JANUARY - DECEMBER 1985 I EDILM: FIEISH LMITS: PCI/KG ET IM)ICATOR STATIONS STATION WITH HIGEST M CONTROL STATIONS RADIOMJCLIDES M EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANCE RANGE (NON-ROUTIE)* LLD NO. DETECTED +. NO. NO. DETECTED NO. DETECTED BE-7 ( 4) ( 0.0i 0.0)E 0 ALL EQUAL ( 0.0 1 0.0)E O

( 0)

I e( 0/ 2), et 0/ 2)e K-40 ( 4) ( 2.8i .2)E 3 21 ( 3.2 * .4)E 3 ( 3.2 t .4)E 3

( 0) ( 2.7 - 3.0)E 3 ( 2.8 - 3.6)E 3 ( 2.8 - 3.6)E 3

  • ( 2/ 2)* et 2/ 2)* *( 2/ 2).

191-54 ( 4) 130. ( 0.01 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O 1 I ( 0)

  • ( 0/ 2)* a( 0/ 2)*

CO-58 ( 4) 0.0i 0.0)E 0 ( 0.0 1 0.0)E 0 I

130. ( ALL EQUAL

( 0) et 0/ 2). *( 0/ 2)e I FE-59 ( 4)

( 0) 260. ( 0.01 0.0)E O

.( 0/ 2).

ALL EQUAL ( 0.0 t

  • ( 0/ 2)*

0.0)E 0  ;

CD-60 ( 4) 130. ( 0.01 0.0)E O ALL EQUAL ( 0.0 f 0.0)E O )

( 0)

  • ( 0/ 2). *( 0/ 2).

I

)

ZN-65 ( 4) 260. ( 0.0i 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O I

( 0) l e( 0/ 2). .( 0/ 2)*

ZR-95 ( 4) ( 0.0i 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E 0  !

( 0)

I *( 0/ 21 a( 0/ 2).

l AG-110M( 4) ( 0.0 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O I ( 0)

  • ( 0/ 2)* a( 0/ 2)*

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e NON-ROUTIE REFERS TO TE EMBER OF SEPARATE EASUREENTS I411CH ERE CREATER I THAN TEN (10) TIES TE AVERAGE BACK0ROUND FOR TE PCRIOD OF TE REPORT.

en TE FRACTION OF SAlfLE ANALYSES YIELDING DETECTABLE EASlREENTS (I.E. > A POSTERIORI LLD) IS INDICATED WITH *( )*.

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I E)NIR0leGTAL RADIOLOGICAL PROGRAM SulWRY VEMONT Yale lEE NUC1. EAR POER STATION, VERNON VT JANUARY - DECEMBER 1935 I EDIlM: FIIFISH UNITS: PCI/KG ET IleICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE I (NON-ROUTIE). LLD NO. DETECTED..

STA.

NO.

RANGE NO. DETECTED..

RANGE NO. DETECTED l RU-103 ( 4) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 t 0.0)E 0

( 0)

.( 0/ 2)e .( 0/ 2).

RU-106 ( 4) ( 0.0t 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E O

.( 0/ 2). .( 0/ 2).

1-131 ( 4) ( 0.0i 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E 0 I ( 0)

.( 0/ 2). .( 0/ 2).

( 0.01 0.0)E O I CS-134 ( 4)

( 0) 130.

.( 0/ 2).

ALL EQUAL ( 0.0 1

.( 0/ 2).

0.0)E O I CS-137 ( 4)

( 2) 150. ( 3.Si

( 2.6 -

.( 2/ 2).

.9)E 1 4.3)E 1 11 ( 3.5 i

( 2.6 -

.( 2/ 2).

.9)E 1 4.3)E 1

( 0.0 i

.( 0/ 2).

0.0)E O BA-140 ( 4) ( 0.0t 0.0)E 0 ALL EQUAL ( 0.0 i 0.0)E O

( 0)

.( 0/ 2). .( 0/ 2).

CE-141 ( 4) ( 0.0f 0.0)E 0 ALL EQUAL ( 0.0 1 0.0)E 0

( 0)

.( 0/ 2). .( 0/ 2).

CE-144 ( 4) ( 0.0i 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O I ( 0)

.( 0/ 2). .( 0/ 2).

TH-232 ( 4) ( 0.0i 0.0)E O ( 0.0 t 0.0)E O I

ALL EQUAL

( 0)

.( 0/ 2). .( 0/ 2).

I I . NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACK0R0lMD FOR TE PERIOD OF TE REPORT.

TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTABLE EASUREENTS (I.E. > A POSTERIORI LLD) IS INDICATED WITH .( )..

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I M) Direct Radiation Direct gamma radiation exposure was determined from the use of thermoluminescent dosimeters (TLDs). Two CaF :Mn TLDs were placed at each of the monitoring stations. The dosimeters at eighteen indicator stations and three control stations were collected and read out on a monthly schedule during the first quarter. During the second, third, and fourth quarters, 51 stations were used (40 are required by the RETS). These were read-out quartorly.

Six TLD badges were lost (apparently stolen or destroyed while in the field) during 1985. These badges were from Stations DR-9, 26, and 35 during the second quarter; Station DR-36 during the third I quarter; and Stations DR-14 and 26 during the fourth quarter.

Summaries of the results for 1985 can be seen in the table below.

Average exposure rates are given for each station in Table 3.1.

In Table 3.2, the annual average exposure rate for each Zone 1 station, and for all of them combined, were compared to the mean of the two Zone 2- stations for that year (s). This approach was used to eliminate any influence from global or regional changes in I ambient radiation levels or from changes in the performance of the TLD system. Zone 1 site boundary stations were not included in the )

comparison since they are on-site locations and are subject to )

I plant-related variations that could obscure seasonal or annual trends.

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By comparing the 1985 ratios with those from other years, it is evident that the Zone 1 ambient radiation levels have not changed significantly over the last seven years with respect to the Zone 2 I levels. Two exceptions are Stations DR-2 (N. Hinsdale) and DR-3 (Hinsdale Substation). Slightly elevated third and fourth quarter I l I l I

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I Environmental Radiological Program Summary Vermont Yankee Nuclear Power Station, Vernon, Vermont January - December 1985 Medium: Dirs>ct Radiation Units: Micro-R por Measurements (TLD) Hour Station With Inner Ring Highest Mean Outer Ring I Mean Range Station Mean Range Mean Range (No. Meas.)*

(No. Meas.)M No. (No. Meas.)M 10.3 34.4 10.2 6.1 - 14.0 45 15.5 - 75.6 8.1 - 13.1 (49) (6) (47)

N Most measurements based on readings from two TLD chips.

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readings at both stations raised the annual mean exposure rato slightly. The reason for this is not known, although one can rule out any plant contribution from direct irradiation due to the distance of the stations from the plant. One can also rule out irradiation from deposited radionuclides since no plant-related radioactivity was detected by the air samplers at both locations.

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I Table 3.1 Vermont Yankee Summary of Direct Radiation Measurements - 1985 I Station Description ZoneM Micro-R Por HourKM DR-1 River Station No. 3.3 1 9.7 DR-2 N. Hinsdale, NH 1 9.9 DR-3 Hinsdale Substation 1 11.1 DR-4 Northfield, MA 1 9.3 DR-5 Spofford Lake, NH 2 10.3 DR-6 Vernon School 1 9.8 I DR-7 DR-8 DR-9 Site Boundary Site Boundary Inner Ring 1

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11.8 10.8 10.0 I DR-10 Outer Ring O 8.6 DR-11 Inner Ring I 10.9 DR-12 Outer Ring 0 8.8 DR-13 Inner Ring I 9.5 DR- 14 Outer Ring O 10.1 UR-15 Inner Ring I 9.9 DR-16 Outer Ring O 10.3 DR -1/ Inner Ring I 10.0 I DR- 18 Outer Ring O 10.0 DR-19 Inner Ring I 10.1 DR-20 Outer Ring O 11.7 10.2 I. DR -21 DR- 22 Inner Ring Outer Ring I

O 10.4 DR-23 Inner Ring I 8.9 I DR-24 DR-25 DR-26 Outer Ring Inner Ring Outer Ring O

I O

9.8 10.5 12.3 I DR-2/

DR-28 DR-29 Inner Ring Outer Ring Inner Ring I

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10.0 10.6 10.7 DR- 30 Outer Ring O 9.4 I DR-31 DR-32 DR-33 Inner Ring Outer Ring Inner Ring I

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10.4 10.1 11.6 I DR-34 DR-35 DR-36 Outer Ring Inner Ring Outer Ring O

I O

10.2 10.9 10.6 10.0 I DR-37 Inner Ring I DR-38 Outer Ring O 10.2 DR-39 Inner Ring I 10.3 DR-40 Outer Ring O 10.1 I DR-41 DR-42 DR-43 Site Boundary Site Boundary Sito Boundary SB SB SB 11.0 10.4 10.6 DR- 44 Site Boundary SD 11.9 I l I

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(Continued)

Vermont Yankee Summary of Direct Radiation Moasurements - 1985 I Mic ro- R Station Description ZoneM Per HourM*

DR-45 Site Boundary SB 34.4 DR-46 Site Boundary SB 12.5 I DR-47 DR-48 DR-49 Site Site Site Boundary Boundary Boundary SB SB SB 10.8 10.2 9.8 12.0 I DR-50 DR-51 DR-52 Governor Hunt House Site Boundary Tyler Hill SB SB 1

13.2 8.8 DR-53 Hogback Mountain 2 8.2 I

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I M Zones: 1 = Indicator; 2 = Control; I = Inner Ring; O = Outer Ring; I SB = Site Boundary.

MM Annual average exposure rate.

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I Table 3.2 Vermont Yankee Ratio

  • of Zone 1** to Zone 2 Exposure Rates I Station Description 1985 Ratio 1984 Ratio 1983 Ratio 1982 Ratio 1978-82 Ratio DR-13 Hinsdale, NH 1.03 1.05 1.04 1.05 1.04 DR-2 N. Hinsdale, NH 1.07 0.95 1.02 1.02 1.00 I DR-3 Hinsdale Substation 1.20 1.11 1.09 1.09 1.10 )

DR-1 River Station No. 3.3 1.05 0.98 1.00 1.03 1.05 DR-30 Fairman Road 1.02 1.10 1.03 1.09 1.08 DR-52 Tyler Hill O.95 1.14 1.08 1.08 1.08 DR-6 Vernon School 1.06 1.04 1.06 1.08 1.10 I

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I N Ratio of the annual average direct radiation exposure for a station to the I mean of the Zono 2 (control) stations for that year.

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I 4.0 QUALITY ASSURANCE PROGRAM I Three separate Quality Assurance programs were performed during 1985 to demonstrate the validity of laboratory analyses by the Yankee Atomic Environmental Laboratory (YAEL).

I YAEL participates in the EPA Interlaboratory Comparison (cross-check) program for those species and matrices routinely analyzed by the laboratory.

This provides an independent check of accuracy and precision of the laboratory analysis. 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 correctivo measures are takon.

I 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 whenover applicable.

I A blind duplicate program is maintained in which paired samplos are prepared from homogonous media and sent to the laboratory for analysis. fho results from this blind duplicate program are used to check for precision in laboratory analyses.

I E_pA. Interlaboratory and Intralaboratory Results The Quality Assuranco 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 1985 for intralaboratory analyses, and EPA interlaboratory cross-check analyses. For accuracy, 60.4 and 84.3 percent of the results wore within 5 and 10 percent of the known values, respectively, with 96.6 percent of all results falling I within the laboratory criteria of 15 porcent or two sigma. For precision, 82.3 and 95.9 percent of the results were within 5 and 10 percent of the mean, I -

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i respactieely, with 100 percent of all results meeting the laboratory criteria of 15 percont or two sigma.

I The results of the EPA Interlaboratory Comparison program, when considered apart from the remainder of the Quality Assurance program, were satisfactory with respect to accuracy and precision in 1985. Ninety-nine samples were analyzed (air particulate filters, food, milk, and water). A total of 204 analyses were performed (beta, Sr-89, Sr-90, I-131, Ba-140, K, Cs-137, Cr-51, Co-60, Zn-65, Ru-106, Cs-134, Ra-226, Ra-228, and H-3).

Of the 204 analyses, 2 (1.0 percent) did not meet the EPA acceptance criteria for accuracy. The first of these was a Sr-90 analysis of food.

Since a blank food sample was not provided with the spiked sample to allow for I the correction for stable strontium, the results were biased high. Such blank samples have been requested by the laboratory and agreed to in concept by EPA. The second was an I-131 analysis of water. In this case, iodine carrier was inadvertently not added at the time of sample preparation, causing a consistent low bias in the laboratory results. The operator was subsequently informed of the proper preservation methodology.

All of the analysos met the EPA acceptance criteria for precision.

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I Teble 4.1 Intralaboratory and EPA Interlaboratory Results - 1985 Accuracy Total Number O to 5% 0 to 10% 0 to 15%N of Measurements _

(or within 2 sigma).

743 449 626 718 )

(60.4%) (84.3%) (96.6%)

Precision Total Number O to 5% 0 to 10% 0 to 15%M of Measurements (or within 2 sigma) 682 561 654 682 (87.3%) (95.9%) (100%)

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  • This category also contains those samples having a verified zero concentration which were analyzed and found not to contain the isotopo of interest.

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I Blind Duplicata Program I A total of 57 paired samples were submitted by the five participating plants for analysis during 1985. The data base used for the duplicato analyses consisted of paired measurements of 76 gamma emitting nuclides, H-3, I

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 i 15 percent of their average value, then agreement between the measurements has been met. If the value falls outside of the i 15 percent, then a two standard deviation rango (95 percent confidence level) is established for each of the analyses. If the ranges overlap, agreement is obtained.

One thousand four hundred and forty-four paired duplicate measuromonto were analyzed for 1985. A total of 99.7 percent of all measurements fell within the established critoria discussed above. The five measurements that I did not meet the criteria were measurements of NP239 in ground water, St>-124 in ground water, So-75 in sea water, Bo-7 in marino algae, and Sr-90 in milk.

All but the Gr-90 were single measurements in a 26-radionuclide gamma spectromotry analysis. The five duplicato measurements represent 0.3 percent of all the blind duplicate paired measurements made during 1985. In the first throo cases, the radionuclide in question was not present at a detectablo level in the sample, and in the last two cases it was. In all cases, a three standard deviation acceptable critoria was mot. With respect to the Sr-90 No reason could be found I

analysis, a reanalysis met the acceptance criteria.

for the initial failing. No trend was evident with respoct to repeated failings of measurements for the above radionuclides.

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I 5.0 LAND USE CENSUS The Vermont Yankee RETS require that a Land Use Census be conducted I annually between June 1 and October 1 of each year. The census identifies the location of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within 5 miles of the plant. It also identifies the nearest milk animal (within 3 miles of the plant) to the point of predicted highest annual average D/Q value in each of the three major meteorological sectors due to elevated releases from the plant stack. Dosimetric analyses are then carried out to determine whether any identified milk animal represents a significantly better milk sampling location than those currently boing used.

The 1985 Land Use Census at Vermont Yankee was carried out between August 21, 1985 and September 25, 1985. The identified locations can be found in Table 5.1. As a result of the dosimetric comparisons, Newton Farm (lM-13) and Miller Farm (TM-11) were replaced with Drown Farm (TM-14) and Coombs Farm (lf4 15). Both Newton and Miller were kept as non-required sampling stations during 1985.

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Table 5.1 -

Vermont Yankee ,

1985 Land Use Census Results j l

l Nearest Residence Milk Animals Sector (km) km Cow or Goat N 1.6 M -

NNE 1.6 M - l 5 NE 1.3 4.2 Goats ENE 1.0 * --

E 1.0 2.4 Cows EGE 2.8 M -

SE 1.8 3.4 Cows SE ---

4.3 Goats SSE 2.0 5.1 Cows S 0.5 2.6 Cows SSW 0.5 2.1 Cows i i

SW 0.5 M -

I WSW 0.5 M - - -

W . 0.5 * -

4 WNW 0.6 0.8 Cows I

WNW --

4.7 Cows NW 1.2 4.7 Cows NNW 2.1 M -

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I 6.0

SUMMARY

During 1985, samples collected as a part of the radiological environmental monitoring program at Ver mont Yankee showed detectable levels of man-made radionuclides in milk, mixed vegetation, cattle feed, finfish, and sediment. In all but one case, the low levels detected were shown to originate from fallout from atmospheric nuclear weapons tests. As reported in I

the past, low levels of Co-60 were detected in river sediment in the immediate vicinity of the North Storm Drain Outfall. The radiological environmental monitoring program has therefore demonstrated that plant operations have had no significant impact on the environment.

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7.0 REFERENCES

1. Annual Radiological Environmental Surveillance Report, 1984, Vermont Yankoo Nuclear Power Corporation.
2. YAEL Quarterly Status Report, October-December 1983, Environmental Laboratory Group, Yankea Atomic Electric Company.
3. YAEL Quarterly Status Report, April-June 1985, Environmental Laboratory Group, Yankee Atomic Electric Company.
4. YAEL Quarterly Status Report, October-December 1985, Environmental Laboratory Group, Yankee Atomic Electric Company.

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VERMONT YANKEE NUCLEAR POWER CORPORATION  ;

, RD 5 Box 169, Ferry Road, Brattleboro, VT 05301 ,,,Ly7g ENGINEERING OFFICE 1671 WORCESTER ROAD FRAMINGHAM, MASSACHUSETTS 01701 I TELEPHONE 617-872-8100 April 30, 1986 FVY 86-35 1

United States Nuclear Regulatory Commission Region I 631 Park Avenue King Of Prussia, PA 19406 Attention: Dr. Thomas E. Murley Regional Administrator l i

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Reference:

(a) License No. DPR-28 (Docket No. 50-271) I

Subject:

Vermont Yankee Annual Radiological Environmental Surveillance Report l

Dear Sir:

Enclosed plaase find three (3) copics of the Annual Radiological I Environmental Surveillance Report for Vermont Yankee Nuclear Power Corporation, as required by our Technical Specification 6.7.C.3, Paragraph one. This report contains a summary and analysis of the radiological environmental data collected for the calendar year 1985.  ;

Should you have any questions regarding this submittal, please contact us.

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I Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION f R. W. Capstick Licensing Engineer RWC/no s

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