ML20245G498

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Annual Radiological Environ Surveillance Rept 1988
ML20245G498
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 12/31/1988
From:
YANKEE ATOMIC ELECTRIC CO.
To:
References
NUDOCS 8905030161
Download: ML20245G498 (73)
v • d • e


Text

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I I VERMONT YANKEE NUCLEAR POWER STATION VERMONT YANKEE NUCLEAR POWER CORPORATION ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT January - December 1988 April 1989 I

I I Prepared By:

Yankee Atomic Electric Company l Environmental Engineering Department l 580 Main Street Bolton, Massachusetts 01740

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g e N l g 8905030161 881231 PDR ADOCK 05000271  :

R PDC S

TABLE OF CONTENTS I Eage t

l LIST OF TABLES.................................................... iii l

LIST JF FIGURES................................................... iv

1.0 INTRODUCTION

...................................................... 1 2.0 ENVIRONMENTAL SURVEILLANCE PR0 GRAM................................ 2 3.0

SUMMARY

OF 1988 RADIOLOGICAL ENVIRONMENTAL DATA................... 13 I A.

B.

C.

Air Particulate.............. ................................

Charcoal Filter................................................

M11k..........................................................

15 19 21 Mixed Vegetation.............................................. 26 I D.

E.

F.

Si1 age........................................................

Groundwater...................................................

30 33 G. River Water................................................... 37 I H.

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J.

Sediment......................................................

Fish..........................................................

Direct Radiation..............................................

41 44 48 4.0 QUALITY ASSURANCE PR0 GRAM......................................... 60 5.0 LAND USE CENSUS................................................... 63 6.0

SUMMARY

........................................................... 65

7.0 REFERENCES

........................................................ 66 I

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LIST OF TABLES I Numher Iltle Eag.e 2.1 Radiological Environmental Surveillance Program............. 3 2.2 Radiological Environmental Surveillance Locations........... 4 2.3 Environmental Direct Radiation Monitoring Locations......... 5 3.1 Summary of Direct Radiation Measurements - 1988............. 50 4.1 Intralaboratory and EPA Interlaboratory Results - 1988...... 62 5.1 1988 Land Use Census Results................................ 64 I 1 I

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I IJST OF FIGURES I Humiter Title Eage I 2.1 Environmental Radiological Monitoring Locations in Close Proximity to P1 ant.......................................... 7 I 2.2 Environmental Radiological Monitoring Locations Within 5 Kilometers of P1 ant....................................... 8 2.3 Environmental Radiological Monitoring Locations Greater I Than 5 Kilometers from P1 ant................................ 9 10 2.4 TLD Locations in Close Proximity to Plant...................

2.5 TLD Locations Within 5 Kilometers of Plant.................. 11 2.6 TLD Locations Greater than 5 Kilometers from Plant.......... 12 3.1 Gross-Beta Measurements of Air Particulate Filterc.......... 16 3.2 Cesium-137 in M11k.......................................... 22 1

3.3 Strontium-90 in M11k... .................................... 23 3.4 Cesium-137 in Mixed Vegetation.............................. 27 ,

3.5 Gross-Beta Measurements of Ground Water..................... 34 3.6 Gross-Beta Measurements of River Water...................... 38 3.7 Cesium-137 in F1sh.......................................... 45 3.8 Exposure Rate at Indicator TLDs, DR 01-04, 06, 50........... 52 3.9 Exposure Rate at Site Boundary TLDs, DR 01-08, 41-44........ 53 3.10 Exposure Rate at Site Boundary TLDs, DR 45-49, 51........... 54 3.11 Exposure Rata at Inc r Ring TLDs, DR 09-23 (odd)............ 55 3.12 Exposure Rate at Inner Ring TLDs, DR 25-39 (odd)............ 56 3.13 Exposure Rate at Outer Ring TLDs, DR 10-24 (esen)........... 57 3.14 Exposure Rate Outer Ring TLDs, DR 26-40 (even).............. 36 3.15 Exposure Rate at Control TLD, DR 05......................... 59 I

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1.0 INTR 0DECTION The radiological environmental surveillance program at the Vermont Yankee Nuclear Power Station has been designad snd carried out with specific objectives in mind. They are as follows:

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

To provide assurance to regulatory age.ncies and the public that the station's environmental impact is known and within anticipated limits.

/

To verify the adequacy and proper functioning of station effluent I

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 radioact.ive material. j During 1988, as in the past, Aquatec, Inc., collected all of the aquatic environmental 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. After the initial processing, all samples were sent to the Yankee Atomic Environmental Laboratory in Westborough, Massachusetts for further processing and radionuclides analysis. T1bs were also sent to this laboratory for processing.

This report is a summary of the findings of the Radiological Environmental Surveillance Program for 1988. It is being provided in compliance with plant Technical Specification 6.7.C.3.

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I 2.0 RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAM In this section, Table 2.1 summarizes the surveillance program as j

require /. by plant Technical Specification 3.9.C. Table 2.2 lists the sampling stations and their specific locations with distances measured fro.: the plant stack. Given in Table 2.3 are distances and directions relative to the center of the Turbine Building for all TLD loentions. The sampling locations are shown on maps in Figures 2.1 through 2 3 and the TLD locations are shown on I the maps in Figures 2.4 through 2.6.

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Table 2.1  !

Ra d i ol ogica LEnYironmentalJiu rv e il l an cg_fIngnun Vermont YADkee Nuclear Power Stal. ion m Mgslia Sampling Freauency Required Analy.ggs 3 Air Particulate (AP) - Semimonthly (2) Gross beta

- Quarterly Composite Gamma spectroscopy E

Charcoal Filter (CF) - Semimonthly (2) Iodine-131 Milk (TM) - Monthly (6) Gamma spectroscopy, Iodine-131 Mixed Vegetation (TG) - Quarterly (1) Gamma spectroscopy Silage (TC) - Annually (3) Gamma spectroscopy Groundwater (WG) - Quarterly Gamma spectroscopy, H-3 I River Water (WR) - Monthly (1) (5)

- Quarterly Composite Gamma spectroscopy H-3 Sediment (SE) - Semiannually Gamma spectroscopy Fish (FH) - Semiannually (1) ';amma spectroscopy Direct Radiation (DR) - Quarterly Integrated gamma dose (4)

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

(2) Weekly, when main plant stack effluent release rate of Iodine-131 is equal to or greater than 0.1 uCi/sec.

I (3) Collected at harvest time in reasonable proximity to specified location; subject to m ailability, (4) Outer ring TLDs - De-dose quarterly unless gaseous release LC0 was I exceeded in period.

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

(6) Semimonthly when milk animals are identified as being on pasture.

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Table 2.2 Radiological EnvirpDmental SurveillADcelocatiQns Vermont Yankee Nuclear Power Station I Distance From Plant Direction a

Station Code Stack From Plant Diedia - Stadod Station Description Zong* (km) _ Stack __'

River Station No. 3.3 1.9 I AP/CF/TG-11 1 SSE AP/CF/TG-12 N. Hinsdale, NH 1 3.6 NNW I AP/CF/TG-13 Hinsdale Substation 1 3.1 E AP/CF/TG-14 Northfield, MA 1 11.3 SSE AP/CF/TG-15 Tyler Hill Road 1 3.2 WNW AP/CF/TG-21 Spofford Lake, NH 2 16.1 NNE I IM-11 IM-13 TM-14 Miller Farm Newton Farm Brown Farm 1

1 1

0.8 5.1 2.6 WNW SSE S

TM-15 Coombs Farm 4.5 NW I

1 TM-16 Tall Oaks Farm 1 4.7 WNW TM-20 Ranney Farm 2 17.0 N j TM-21 Moore Farm 2 15.9 N WG-11 VY Plant Well 1 -- On-Site WG-12 Vernon Nursing Well 1 2.0 SSE  !

WG-21 Brattleboro C. C. 2 12.1 NNW WR-11 River Station Nc. 3.3 1 1.9 Downriver WR-21 Rt. 9 Bridge 2 12.8 Upriver FH-11 Vernon Pond 1 -- On-Site FH-21 Rt. 9 Bridge 2 12.8 Upriver SE-11 Shoreline Downriver 1 0.8 On-Sir.e SE-12 N. Storm Drain Outfall 1 0.15 On-Site TC-11 Miller Ferm 1 0.8 WNW 10-13 Newton Farm 1 5.1 SSE (

TC-14 Brown Farm 1 2.6 S 4.5 I' 10-15 Coombs Farm 1 NW 4 TC-16 Tall Oaks Farm 1 4.7 WNW TC-20 Ranney Farm 2 17.0 N TC-21 Moore Farm 2 15.9 N I

  • 1 = Indicator Station; 2 = Control Station.

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Table 2.3 l I Environmental _D1IAGinnladitttionlonitoring Locationa Vermont Yankee Nuclear Power Station l

f i

i I Distance From Center Direction From I Station Cade (Media - StA. No.) Station Description ZQng*

of Turbine Building (km)

Center of Turbine Building _

DR-1 River Station No. 3.3 I 1.6 SSE DR 2 N. Hinsdale, NH I 3.9 NNW DR-3 Hinsdale Substation I 3.0 E DR-4 Northfield, MA I 11.0 SSE DR-5 Spofford Lake, NH 0 16.3 NNE DR-6 Vernon School I 0.46 WSW I DR-7 DR-8 DR-9 Site Boundary Site Boundary Inner Ring SB SB I

0.27 0.25 2.1 W

N SW Outer Ring 0 4.6 N I DR-10 DR-11 DR-12 Inner Ring Outer Ring I

0 2.0 3.6 1.4 NNE NNE DR-13 Inner Ring I NE DR-14 Outer Ring 0 4.3 NE DR-15 Inner Ring I 1.4 ENE DR-16 Outer Ring 0 2.9 ENE g DR-17 Inner Ring I 1.2 E g DR-18 Outer Ring 0 3.0 E DR-19 Inner Ring I 3.5 ESE DR-20 Outer Ring 0 5.3 ESE I DR-21 DR-22 Inner Ring Outer Ring I

0 1.8 3.2 1.8 SE SE SSE DR-23 Inner Ring I I DR-24 DR-25 DR-26 Outer Ring Inner Ring Outer Ring 0

I 0

3.9 2.0 3.7 SSE S

S 1.0 I DR-?7 Inner Rirg I SSW DR-28 Outer Ring 0 2.2 SSW DR-29 Inner Ring I 0.7 WSW DR-30 Outer Ring 0 2.3 SW I DR-31 DR-32 DR-33 Inner ning Outer Rin6 Inner Ring I

0 I

0.8 5.0 0.9 W

WSW WNW I DR-34 DR-35 IS-36 Outer Ring Inner Ring Outer Ring 0

I 0

4.9 1.4 4.7 W

WNW WNW I

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(Continued)

Environmental __Direetion_ladiation MonitDring_Lacationra Vermo-at Yanhe Nuclear Power Station Distance Direction From Center From

!I Station Code of Turbine Building Center of Turbine

)

j

'(Media - Sta. No.)

Slat.ipn Description Zane* (km) Building DR-37 Inner Ring I 3.0 NW DR-38 Outer Ring 0 7.7 NW I DR-39 DR-40 DR-41 Inner Ring Outer Ring Site Boundary I

0 SB 3.2 5.8 0.38 NNW NNW SSW E DR-42 Site Boundary SB 0.60 S R DR-43 Site Boundary SB 0.42 SSE DR-44 Site Boundary SB 0.21 SE DR-45 Site Boundary SB 0.12 NE I DR-46 DR-47 DR-48 Site Boundary Site Boundary Site Boundary SB SB SB 0.29 0.51 0.82 NNW NNW NW I DR-49 DR-50 DR-51 Site Boundary Governor Hunt House Site Boundary SB I

SB 0.27 0.34 0.27 WNW SSW W

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l I = Inner Ring; O = Outer Ring; SB = Site Boundary.

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Figure 2.2 Environmental Radiological Monitoring Locations Within 5 Kilometers of Plant w--

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3.0

SUMMARY

OF 1988 RA.DIOLOGICAL ENVIRONMENTAL DATA I The following pages summarize the analytical results of the environmental samples which were collected during 1988. Each environmental media category is presented as a separate subsection. A discussion of the sampling program and results is followed by a table which summarizes the year's data for each category. At the top of each table are listed the units of measurement for each mediun. The left hand column contains the radionuclides which is being reported, total number of analyses of that radionuclides, 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.

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

" indicator" or " Zone 1" stations. Distant stations, which are beyond plant influence are called " Control" or " Zone 2" stations. Direct radiation (TLD) monitoring locations are subdivided into site boundary, inner ring, and outer ring (emergency response) stations.

I A set of statistical parameters is calculated for each radionuclides.

This set of statistical parameters includes separate analyses for (1) the I indicator stations, (2) the control stations, and (3) the station having the For each of these highest annual mean concentration for that radionuclides.

three groups of data, these pcrameters are as follows:

l o The riean value of all concentrations.

o The standard error of the mean.

o The lowest and highest concentration.

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I 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.

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 I 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."

These values are set to zero for averaging purposes. yhere a range of values ,

is reported in the tables of this section, values less than the a posteriori I LLD for the analysis are reported as zero.

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

I Gross-beta counts (Figure 3.1) showed random fluctuation throughout 1988 at indicator stations and controls, thereby indicating that i any plant contribution was negligible. The abnormally low concentrations shown in Figure 3.1 were due, in one case, to a pump malfunction and, in another case, to a misaligned particulate filter. One slightly elevated gross-beta concentration was noted at Station AP-15 for the week ending July 12, 1988. It is suspected that a faulty sampling system (gas meter and/or vacuum pump), which was replaced that week, may have given an erroneous volume reading, which would have given an erroneous concentration.

lt should be noted, however, that no gamma-emitting radionuclides I were detected on the third quarter composite sample.

Naturally occurring Be-7 was also detected on all samples.

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I- ENVIRONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY 1 DECEMBER 1988) alDIUM: AIR PARTICULATE UNITS: PCl/CU. M lI I INDICATOR STATIONS STAfl0N WITH HIGHEST MEAN CONTROL STATIONS RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)* LLD No. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

GR B (156) .01 ( 2.2 1 0.1)E -2 11 ( 2.4 2 0.1)E 2 ( 2.1 0.1)E -2 I ( 0) ( 0.0 -

  • (129/130)*

4.1)E 2 ( 1.0 -

  • ( 26/ 26)*

4.1)E 2 ( 9.9 - 31.7)E -3

  • ( 26/ 26)*

BE 7 ( 24) ( 6.2 s 0.4)E -2 15 ( 6.7 k 1.1)E -2 ( 6.1 2 1.0)E -2 I

j

( 0) ( 3.8 - 9.3)E -2 ( 4.3 - 9.1)E 2 ( 3.8 - 8.5)E 2 l

  • ( 20/ 20)* *( 4/ 4)* *( 4/ 4)*

I K 40 ( 24)

( 0)

( 0.0 t

  • ( 0/ 20)*

0.0)E O ALL EQUAL (

  • (

0.0 t 0/ 4)*

0.0)E O  ;

MN*S4 ( 24) ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O

( 0)

  • ( 0/ 20)* *( 0/ 4)*

CO 58 ( 24) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 2 0.0)E 0

( 0)

  • ( 0/ 20)* *( 0/ 4)*

FE-59 ( 24) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O

  • ( 0/ 20)* *( 0/ 4)*

Co 60 ( 24) ( 0.0 2 0,0)E 0 ALL EQUAL ( 0.0 2 0.0)E D

( 0)

  • ( 0/ 20)* *( 0/ 4)*

l 0.0 t 0.0)E O I

ZN 65 ( 24) t 0.0 2 0.0)E O ALL EQUAL (

( 0)

  • ( 0/ 20)* *( 0/ 4)*

ZR-95 ( 24) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O I ( 0)

  • ( 0/ 20)* *( 0/ 4)* l I
  • NON ROUTINE REFERS 10 THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKCROUND FOR THE PERIOD OF THE REPORT. f
    • THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (I.E. >A-POSTERIORI LLO) IS INDICATED WITH *( )*. 1 s

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ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 1/ERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 1988)

MEDIUM: AIR PARTICULATE UNITS: PCI/CU. M j I INDICATOR STATIONS STAil0N WITH HIGHEST MEAN CONTROL STATIONS

                                • ee *****e*********ene****ene ee**e******ee**e RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANCE STA. RANGE RANGE (NON ROUTINE)* LLD NO. OffECTED** NO. NO. DETECTED ** NO. DETECTED **

AG 110H( 24) ( 0.0 1 0.0)E 0 ALL EQUAL ( 0.0 2 0.0)E O I ( 0)

  • ( 0/ 20)* *( 0/ 4)*

RU 103 ( 24) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O I ( 0)

  • ( 0/ 20)* *( 0/ 4)*

I RU 106 ( 24)

( 0)

( 0.0 1

  • ( 0/ 20)*

0.0)E O ALL FQUAL (

  • (

0.0 t 0/ 4)*

0.0)E O CS-134 ( 24) .05 ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 20)* *( 0/ 4)*

CS-137 ( 24) .06 ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O

( 0)

  • ( 0/ 20)* *( 0/ 4)*

BA-140 ( 24) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O

  • ( 0/ 20)* *( 0/ 4)*

CE-141 ( 24) ( 0.0 2 0.0)E 0 ALL EQUAL ( 0.0 2 0.0)E O I ( 0)

  • ( 0/ 20)* *( 0/ 4)*

CE 144 ( 24) 0.0 t 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)E D I

(

( 0)

  • ( 0/ 20)* *( 0/ 4)*

TH-232 ( 24) ( 0.0 1 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)E O I ( 0)

  • ( 0/ 20)* *( 0/ 4)*

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  • NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PER100 0F THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (I.E. >A-POSTERICAI LLD) 15 INDICATED WITH *( )*.

I

I B) Charcoal FilteIE Charcoal filter cartridges are situated in series with the air particulate glass-fiber filters. Monitoring stations were established at a total of six locations (five are required by Technical Specifications). Five of these are indicators and one is I a control. Charcoal filters from the air sampling stations were collected and analyzed semimonthly for I-131 activity.

I During 1988, no I-lit was detected on charcoal filters.

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E ENVIRONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT I MEDIUM: CHARCOAL FILTER (JANUARY - DECEMBER 1988)

UNITS: PCl/CU. M I ' INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS eee***eeeeeeeeeeee **eeee******************* eeeee****** ....

I RADIONUCLIDES (NO. ANALYSES) REQUIRED (NON ROUTINE)* LLD MEAN RANGE NO. DETECTED" STA.

NO.

MEAN RANGE No. DETECTED **

MEAN RANGE NO. DETECTED ** q I 131 (156) .07 ( 0.0 a 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O I ( 0)

  • ( 0/130)* *( 0/ 26)* ]
  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER J THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERICO 0F THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEAStA :MENTS (1.E. >A-POSTEPIORI LLD) IS INDICATED WITH *( )*.

I I

I I

i I l I.

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I

I C) tillk I Milk samples were collected and analyzed monthly for low level l I-131 and gamma-emitting radionuclides. Monthly samples were composited quarterly and analyzed for Sr-09 and Sr-90 (not a Technical Specification requirement). Semi-cionthly sampling was done at Stations E -14 and m-20 when the cows were on pasture.

In March of 1988, the Moore Farm (m -21) was no longer able to provide samples. It was replaced with the Ranney Farm (TM-20).

I Detectable concentrations of Cs-137 and Sr-90 were measured in milk samples submitted from the indicator and control locations. As I shown in Figures 3.2 and 3.3, concentrations were similar to those detected in previous years. The detected levels are consistent I with those measured in cow milk at other New England locations.

Such levels have been well documented and are attributed to f allout from nuclear weapons tests, although Cs-137 levels after May 1986 were elevated somewhtt due to Chernobyl-related fallout.

Differences between dairy farms can be attributed to differences in feeding practices between farms.

I With five additional samples during 1988, man-made radionuclides concentrations exceeded the a posteriori LLD and were listed as

" detected" (at very low levels) in the following tables. These cases were as follows: (1) Sr-89 at E -14 (indicator) for the first quarter composite, (2) Sr-89 at TM-21 (control) for the first quarter composite, (3) Fe-59 at E -20 (control) on September 21, (4) I-131 at 2 -13 (indicator) on October 1, and (5) Ba-140 at TM-20 (control) on August 18. In each of these cases, the concentration did not exceed the typically used cut-off of three I standard deviations and, consequently, would not have been coasidered as being " detected". (Three of the five samples were from control locations, which are outside of the range of the I 2896R  ;

I

plant's influence). In no case did the next routinely-collected sample at any of the above locations yield a repeat positive measurement.

l I In addition to these radionuclides, naturally occurring K-40 was

( detected in all samples.

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ENVIRONMiN7AL RADIOLOGICAL PROGRAM SUMMAR7 VERMONT YANtCE NUCLEAR POWER STATION, VERNON, VT l

(JANUARY - DECEMBER 1988)

MEDIUM: MILK UNITS: PCl/KG .l INDICATOR STATIONS STAil0N WITH HIGHEST MEAN CONTROL STATIONS

.......e*** ...

I

  • eeeeeeeeeee.*eeee eeeeeeeee***e*e*eeee*e ..

RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)* LLD NO. DETECTED ** h0. NO. DETECTED ** NO. DETECTED **

SR-89 ( 18) ( 1.1 1 1.1)E -1 21 ( 2.2 s 1.8)E O ( 7.2 2 7.2)E -1 I ( 0) ( 0.0 -

  • ( 1/ 15)*

1.6)E 0

  • ( 1/ 1)*

( 0.0 -

  • ( 1/ 3)*

2.2)E O SR-90 ( 18) ( 2.6 2 0.3)E O 13 ( 3.2 t 0.4)E O 2.2 2 0.4)E O I

(  ;

( 0) ( 0.0 - 4.2)E 0 ( 2.5 - 3.7)E O ( 1.5 - 2.8)E O

  • ( St./ 15)* *( 3/ 3)* *( 3/ 3)*

I EE-7 ( 89)

( 0)

( 0.0

  • ( 0/ 70)*

0.0)E O ALL EQUAL ( 0.0 2

  • ( 0/ 19)*

0.0)E O K 40 ( 89) ( 1.3 2 0.0)E 3 21 ( 1.4 2 0.0)E 3 ( 1.3 2 0.0)E 3

( 0) ( 1.2 - 1.6)E 3 ( 1.3 - 1.5)E 3 ( 1.1 - 1.5)E 3

  • ( 70/ 70)* *( 4/ 4)* *( 19/ 19)*

MN-54 ( 89) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E 0

( 0)

  • ( 0/ 70)* *( 0/ 19)*

C0-58 ( 89) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 2 0.0)E D I

( 0)

  • ( 0/ 70)* *( 0/ 19)*

FE 59 ( 89) ( 0.0 t 0.0)E 0 20 ( 5.9 2 5.9)E -1 ( 4.72 4.7)E -1 I ( 0)

  • ( 0/ 70)*

(

  • (

0.0 -

1/ 15)*

8.9)E O ( 0.3 -

  • ( 1/ 19)*

8.9)E O 0.0 2 0.0)E 0 I CO 60 ( 89) 0.0 2 0.0)E O (

( ALL EDUAL

( 0)

  • ( 0/ 70)* *( 0/ 19)*

2N 65 ( 89) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 70)* *( 0/ 19)*
  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER l THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF T!iE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE MEASUREMENTS (1.E. >A POSTERIORI LLD) IS INDICATED WITH *( )*.

I i

l I ENVIRONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

VERM0NT YANKEE NUCLEAR POWER STAT!ON, VERWON, VT I MEDIUM: MILK (JANUARY DECEMBER 1988)

UNITS: PC1/KG lhDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS ee******e .*****ee ***ee.**e e*******ee **** ****e..... e****

I RADIONUCLIDES (NO. ANALYSES) REQUIRED MEAN RANGE STA.

MEAN RANGE MEAN RANGE (NON ROUTINE)* LLD NO. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

ZR 95 ( 89) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 s 0.0)E 0

( 0) g *( 0/ 70)* *( 0/ 19)*

RU 103 ( 89) ( 0.0 2 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)E O

( 0)

  • ( 0/ 70)* *( 0/ 19)*

RU 106 ( 89) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 70)* *( 0/ 19)*

l 131 ( 89) 1. ( 9.8 2 9.8)E -3 13 ( 5.3

  • 5.3)E -2 ( 0.0 2 0.0)E O

( 0) ( 0.0 - 6.9)E -1 ( 0.0 - 6.9)E -1

  • ( 1/ 70)* *( 1/ 13)* *( 0/ 19)*

CS-134 ( 89) 15. ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 70)* *( 0/ 19)*

CS-137 ( 89) 18. ( 3.3 2 1.6)E 1 14 ( 9.0 2 5.1)E -1 ( 0.0 2 0.0)E O

( 0) ( 0.0 - 7.4)E O ( 0.0 - 7.4)E O

  • ( 5/ 70)* *( 3/ 19)* *( 0/ 19)*

BA-140 ( 89) 15. ( 0.0 2 0.0)F 0 20 ( 3.3 2 3.3)E -1 ( 2.6 e 2.6)E 1

( 0) ( 0.0 - 4.9)E O ( 0.0 - 4.9)E O

  • ( 0/ 70)* *( 1/ 15)* *( 1/ 19)*

I CE-141 ( 89) ( 0.0 2 0.0)E O ALL EuthL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 70)* *( 0/ 19)*

I CE 144 ( 89)

( 0)

( 0.0 2

  • ( 0/ 70)*

0.0)E O ALL EQUAL ( 0.0 2

  • ( 0/ 19)*

0.0)E O NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

    • THE FRACTION OF SAMPLE ANALYSES YIELOING DETECTABLE MEASUREMENTS l (1.E. >A POSTERIORI LLD) IS INDICATED WITH *( )*.

1 4

}

l t

I D) Mixed Vegetation Mixed vegetation samples were collected during May, June, and l September from the six air sampling locations. The vegetation consisted of various types of grasses and were analyzed for gamma emitting nuclides. The results of the gamma spectroscopy analysis on each sample showed that, in addition to naturally occurring Be-7, Th-232, and K-40 on many samples, Cs-137 was detected on three samples. The levels detected in 1988 are consistent with those measured in previous years, as shown in Figure 3.4, and are believed to be caused by nuclear weapons testing fallout that has persisted in the environment. The highest measured value at Station TG-15 is less than one-tenth of the reporting level for Cs-137 in vegetation given in Technical Specification Table 3.9.4.

In addition to the above, Ag-110m was listed as being " detected" in one sample from Station TG-14 because its a_posteriori LLD had been exceeded. The typically used cut-off of three standard deviations was not exceeded, indicating that Ag-110m was not detected. Based on sample collection dates, this radionuclides would have to have been deposited on the grass during the third or late second quarter of 1988. No such radioactivity was released from the plant during this time, further supporting the conclusion that Ag-110m was not I

actually detected.

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ENVIRONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT

(JANUARY - DECEMBER 1988)

MEDIUM: MIXED VEGFTAT'ON UNITS: PCI/KG WET I INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS e**............... ....e****e ** ****.e.*** **e....**** ....

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

BE-7 ( 18) ( 5.5 1 1.5)E 2 14 ( 7.2 2 4.9)E 2 ( 4.9

  • 1.4)E 2

( 0) ( 0.0 - 1.7)E 3 ( 0.0 - 1.7)E 3 ( 3.4 - 7.7)E 2

  • ( 10/ 15)* *( 2/ 3)* *( 3/ 3)*

K 40 ( 18) ( 4.2 t 0.4)E 3 14 ( 5.4 2 0.1)E 3 ( 5.22 0.4)E 3 I ( 0) ( 1.1 -

  • ( 15/ 15)*

6.5)E 3 ( 5.2 -

  • ( 3/ 3)*

5.6)E 3 ( 4.7 <

  • ( 3/ 3)*

6.1)E 3 I MN 54 ( 18)

( 0)

( 0.0 2

  • ( 0/ 15)*

0.0)E O ALL EQUAL (

  • (

0.0 2 0/ 3)*

0.0)E O Co 58 ( 18) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 i 0.0)E O

( 0)

  • ( 0/ 15)* *( 0/ 3)*

FE-59 ( 18) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 15)* *( 0/ 3)*

Co 60 ( 18) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 1 0.0)E 0

  • ( 0/ 15)* *( 0/ 3)*

2N-65 ( 18) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O I ( 0)

  • ( 0/ 15)* *( 0/ 3)*

2R-95 ( 18) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 15)* *( 0/ 3)*

AG 110M( 18) ( 2.4 t 2.4)E O 14 ( 1.2 2 1.2)E 1 ( 0.0 t 0.0)E O

( 0) ( 0.0 - 3.5)E 1 ( 0.0 - 3.5)E 1

  • ( 1/ 15)* *( 1/ 3)* *( 0/ 3)*
  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (I.E. >A POSTERIORI LLD) !$ INDICATED WITH *( )*,

_ _ _ _ _ _ _ _ _ . _ _ _ J

I J,NtflRONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 VERMONT YANLEE NUCLEAR POWER STATION, VERNON, VT I MEDIUM: MIXED VEGETATION (JANUARY - DECEMBER 1988)

UNITS: PC1/KG WET INDICATOR STATIONS STATION WITH H1GHEST MEAN CONTROL STATION $ {

.................. ......................... ................ j RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE)* LLD NO. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

RU-103 ( 18) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O I ( 0)

  • ( 0/ 15)* *( 0/ 3)*

RU 106 ( 18) ( 0.0 2 0.0)E 0 ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 15)* *( 0/ 3)*

I l 131 ( 18)

( 0)

60. ( 0.0 t
  • ( 0/ 15)*

0.0)E O ALL EQUAL (

  • (

0.0 2 0/ 3)*

0.0)E O CS 134 ( 18) 60. ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E D

( 0)

  • ( 0/ 15)* *( 0/ 3)*

CS-137 ( 18) 80. ( 1.8 2 1.2)E 1 15 ( 7.7 1 5.0)E 1 ( 0.0 2 0.0)E O

( 3) ( 0.0 - 1.7)E 2 ( 0.0 - 1.7)E 2

  • ( 3/ 15)* *( 2/ 3)* *( 0/ 3)*

BA 140 ( 18) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E D

  • ( 0/ 15)* *( 0/ 3)*

CE-141 ( 18) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O I ( 0)

  • ( 0/ 15)* *( 0/ 3)*

0.0)E O I 0.0)E O CE-144 ( 18) ( 0.0 2 ALL EQUAL ( 0.02

( 0)

  • ( 0/ 15)* *( 0/ 3)*

TM 232 ( 18) ( 0.0 2 0.0)E O 21 ( 4.3 t 4.3)E 1 ( 4.3 1 4.3)E 1

( 0) ( 0.0 - 1.3)E 2 ( 0.0 - 1.3)E 2

  • ( 0/ 15)* *( 1/ 3)* *( 1/ 3)*
  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERICO OF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (I.E. >A-POSTERIORI LLD) IS INDICATED WITH *( )*.

I E) Silagg Silage samples were collected at the milk sampling stations during October of 1988. Each sample was analyzed for gamma-emitting radionuclides and I-131. Local, fresh silage was not available for collection during 1988 at Station TM-15. The owner of the farm purchases already-cured silage which is from a previous growing cycle.

I In March of 1989, the Moore Farm (TC-21) was no longer able to provide samples. It was replaced with the Ranney Farm (TC-20).

Naturally ocicrring Be-7 and K-40 were detected in all silage samples. No man-made radionuclides were detected in any of them.

I ,

4 I

lI l

2896R 1

I

ENV!RONMENVAL RADIOLOGICAL PROGRAM

SUMMARY

J VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 1988)  ;

I l

MEDIUM: SILAGE UNITS: PCl/KG WET l INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STAtl0NS RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE l (NON ROUTINE)* LLD NO. DETECTED ** N0. NO. DETECTED ** NO. DETECTED ** I g

1 BE 7 ( 5) ( 3.9 t 0.5)E 2 20 ( 5.9 2 0.6)E 2 ( 5.9 2 0.6)E 2 2.9 - 5.4)E 2 I

( 0) (

  • ( 4/ 4)* *( 1/ 1)* *( 1/ 1)*

Y 40 ( 5) ( 2.5 t 0.5)E 3 20 ( 4.8 2 0.2)E 3 ( 4.8 0.2)E 3 I ( 0) (

  • (

1.3 -

4/ 4)*

3.7)E 3

  • ( 1/ 1)* *( 1/ 1)*

I MN-54 ( 5)

( 0)

(

  • (

0.0 2 0/ 4)*

0.0)E O ALL EQUAL ( 0.0 2

  • ( 0/ 1)*

4.6)E O Co-58 ( 5) < 0.0 2 0.0)E O ALL EQUAL ( 0.0 t 5.3)E O

( 0)

  • ( 0/ 4)* *( 0/ 1)*

FE 59 ( 5) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 1.5)E 1

( 0)

  • ( 0/ 4)* *( 0/ 1)*

CO-60 ( 5) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 t 7.0)E O

  • ( 0/ 4)* *( 0/ 1)*

ZN 65 ( 5) ( 0.0 t u.")E O ALL EQUAL ( 0.0 2 1.3)E 1 I ( 0)

  • ( 0/ 4)* *( 0/ 1)*

0.0 t 0.0)E O ( 0.0 1 1.1)E 1 I

ZR-95 ( 5) ( ALL EQUAL

( 0)

  • ( 0/ 4)* *( 0/ 1)*

I AG 110M( 5)

( 0)

( 0.0 1

  • ( 0/ 4)*

0.0)E O ALL EQUAL ( 0.0 2

  • ( 0/ 1)*

6.8)E O l

I

  • NON ROUTlWE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

I ** THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS

(:.E. >A POSTERIORI LLD) l$ INDICATED WITH *( )*.

I

ENif!RONME07AL RADIOLOGICAL PROGRAM $UMMARY VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT  !

(JANUARY - DECEMBER 1988)

MEDIUM: SILAGE UNITS: PCl/KG WET I INDICATOR STATIONS STATION WITH HIGMEST MEAN CONTROL STATIONS RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)* LLD NO. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

RU 103 ( 5) ( 0.0 t 0.0)E O ALL EQUAL ( 0.01 6.8)E O I ( 0)

  • ( 0/ 4)* *( 0/ 1)*

RU 106 ( 5) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 t 4.1)E 1 I ( 0)

  • ( 0/ 4)* *( 0/ 1)*

I I-131 ( 5)

( 0)

60. (
  • (

0.0 t 0/ 4)*

0.0)E O ALL EQUAL (

  • (

0.0 t 0/ 1)*

8.1)E O CS-134 ( 5) 60. ( 0.0 t 0.0)E D ALL EQUAL ( 0.0 1 4.9)E O  !

( 0)

  • ( 0/ 4)* *( 0/ 1)*

I CS 137 ( 5)

( 0)

80. ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 t 4.7)E O l
  • ( 0/ 4)* *( 0/ 1)*

BA-140 ( 5) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 2.1)E 1

  • ( 0/ 4)* *( 0/ 1)*

l CE-141 ( 5) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 2 8.7)E O I ( 0)

  • ( 0/ 4)* *( 0/ 1)*

CE 144 ( 5) 0.0 2 0.0)E O 0.0 t 2.3)E 1 I

( ALL EQUAL (

( 0)

  • ( 0/ 4)* *( 0/ 1)*

I TM 232 ( 5)

( 0)

( 0.0 2

  • ( 0/ 4)*

0.0)E O ALL EQUAL ( 0.0 2

  • ( 0/ 1)*

2.4)E 1 I

  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WEPE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.
    • THE FRACTION OF SAMPLE AhALYSES YIELOING DETECTABLE MEASUREMENTS (1.E. >A-POSTERIORI LLD) l$ INDICATED WITH *( )*. l I

I F) Groundwater Groundwater grab samples were collected from two indicator (only L-one is required by Technical Specifications) and one control station on a quarterly basis. These samples were analyzed for H-3 1

and gamma-emitting radionuclides. Additionally, gross-beta analyses were performed, although they are not required.

1 The gross-beta concentrations at WG-11 were elevated for the first i three quarters of 1987 and all four quarters of 1988. No explanation for these levels has been found, although a problem with low well-water levels may have caused raised levels of radon or its daughters. Additionally, some 1988 samples represented water drawn from a new well which had not previously been monitored. No gamma-emitting radionuclides, plant-related or I naturally-occurring, were detected in groundwater during this time, however.

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I INUIRONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 VERMONT YANKEE NUCLCAR POWER STATION, VERNON, VT (JANUARY DECEMBER 1988)

MEDIUM: GROUND WATER UNITS: PCl/KG I INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STAfl0NS e........ **ee **e ******eeeeee*******e***** e ***********e .

RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)* LLD NO. DETECTED ** NO. L'O. DETECTED ** NO DETECTED **

GR B ( 12) 4 ( 4.6 s 0.9)E O 11 ( 6.9 t 0.6)E O ( 7.7 s 4.8)E -1 I ( 1) ( 2.0 -

  • ( 8/ 8)*

8.4)E O ( 5.7 -

  • ( 4/ 4)*

8.4)E D ( 0.0 -

  • ( 2/ 4)*

2.0)E 0 BE-7 ( 12) ( 0.0 0.0)E 0 ALL EQUAL ( 0.0 s 0.0)E O I ( 0)

  • ( 0/ 8)* *( 0/ 4)*

I MN 54 ( 12)

( 0)

15. ( 0.0 t
  • ( 0/ 8)*

0.0)E O ALL EQUAL ( 0.0 2

  • ( 0/ 4)*

0.0)E O CO-58 ( 12) 15. ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O i

( 0)

  • ( 0/ 8)* *( 0/ 4)*

I FE 59 ( 12)

( 0)

30. ( 0.0 s 0.0)E 0 ALL EQUAL ( 0.0 s 0.0)E O j
  • ( 0/ 8)* *( 0/ 4)*

CO-60 ( 12) 15. ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

  • ( 0/ 8)* *( 0/ 4)*

ZN 65 ( 12) 30. ( 0.0

  • 0.0)E O ALL EQUAL ( 0.0 2 0.0)E D I ( 0)
  • ( 0/ 8)* *( 0/ 4)*

ZR 95 ( 12) 0.0 2 0.0)E O 0.0 t 0.0)E O I

15. ( ALL EQUAL (

( 0)

  • ( 0/ 8)* *( 0/ 4)*

I AG 110M( 12)

( 0)

( 0.0 2

  • ( 0/ 8)*

0.0)E O ALL EQUAL ( 0.0 t

  • ( 0/ 4)*

0.0)E O I

  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD GF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS l

(I.E. >A POSTERIORI LLD) is IWDICATED WITH *( )*.

I

I- ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 I

VERMONT YAAKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 1988) i ME01UM: GROUND WATER UNITS: PCI/KG INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS I

      • ee **eeee**ee.. e e eeeeeee****e*e*eeeeee ee** ********ee RADIONUCLIDES MEAN MEAN MEAN l (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE)* LLD NO. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

RU 103 ( 12) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 s 0.0)E 0 I ( 0)

  • ( 0/ 8)* *( 0/ 4)*

RU 106 ( 12) < 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

-I ( 0)

  • ( 0/ 8)* *( 0/ 4)*  ;

I I 131 ( 12)

( 0)

( 0.0 2

  • ( 0/ 8)*

0.0)E O ALL EQUAL ( 0.0 2

  • ( 0/ 4)*

0.0)E O CS 134 ( 12) 15. ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O

( 0)

  • ( 0/ 8)* *( 0/ 4)*

CS-137 ( 12) 18. ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 8)* *( 0/ 4)*

BA 140 ( 12) 15. ( 0.0 2 0.0)E 0 ALL EQUAL ( 0.0 2 0.0)E 0 I

( 0)

  • ( 0/ 8)* *( 0/ 4)*

CE-141 ( 12) ( 0.0 s 0.0)E O ALL EQUAL ( 0.0 s 0.0)E O

( 0)

  • ( 0/ 8)* *( 0/ 4)* j I CE 144 ( 12)

( 0)

( 0.0 t

  • ( 0/ 8)*

0.0)E O ALL EQUAL (

  • (

0.0 s 0/ 4)*

0.0)E O H-3 ( 12) 3000. ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 8)* *( 0/ 4)*

I

  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS VHICH WERE GREATER I THAN TEN (10) 11MES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (1.E. >A-POSTERIORI LLD) IS INDICATED WITH *( )*.

I l

I G) River Water I River water is analyzed monthly for gamma-emitting radionuclides 4

and gross-beta (not required by Technical Specifications), The .

monthly samples are compocited and analyzed for H-3 on a quarterly j bacis. A composite sampler is used at Station WR-11 and grab I samples are taken at Station WR-21.

Gross-beta radioactivity was detected in most samples during 1988.

Considerable fluctuation in gross-beta levels at both the indicator and control locations over the past nine years is evident in Figure 3.6. The mean value, however, for the indicator stations was similar to that of the control station and to that of previous years, indicating that those radionuclides detected are not due to p plant operations, but are due to naturally occurring radioactivity.

I I  :

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I ENVIRONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

l I

VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY DECEMBER 1988)

MEDIUM: RIVER WATER UNITS: PC!/KG INDICATOR STAi!ONS STATION WITH HIGHEST MEAN CONTROL STATIONS l eeeeeeeeeee***** e eeeeeeeeeeeeeeeeeeee****. ****************

RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYRES) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)* LLD NO. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

GR B ( 24) 4 ( 1.4 2 0.2)E 0 21 ( 1.6 2 0.3)E O ( 1.6 2 0.3)E O I ( 0) ( 0.0 -

  • ( 10/ 12)*

1.9)E O ( 0.0 -

  • ( 10/ 12)*

3.5)E O ( 0.0 -

  • ( 10/ 12)*

3.5)E O 0.0)E 0 0.0

  • 0.0)E O I

BE-7 ( 24) ( 0.0 2 ALL EQUAL (

( 0)

  • ( 0/ 12)* *( 0/ 12)*

I MN 54 ( 24)

( 0)

15. ( 0.0 t
  • ( 0/ 12)*

0.0)E D ALL EQUAL ( 0.0 2

  • ( 0/ 12)*

0.0)E O Co 58 ( 24) 15. ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 0.0)E O

( 0)

  • ( 0/ 12)* *( 0/ 12)*

I FE 59 ( 24)

( 0)

30. ( 0.0
  • 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O
  • ( 0/ 12)= *( 0/ 12)*

Co 60 ( 24) 15. ( 0.0 t 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)E 0 I

( 0)

  • ( 0/ 12)* "( 0/ 12)*

ZN 65 ( 24) 30. ( 0.02 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O I ( 0)

  • ( 0/ 12)* *( 0/ 12)*

I ZR 95 ( 24)

( 0)

15. (
  • (

0.0 2 O/ 12)*

0.0)E O ALL EQUAL ( 0.0 t

  • ( 0/ 12)*

0.0)E O AG 110M( 24) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 12)* *( 0/ 12)* 1
  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER I THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (1.E. >A+POSTERIORI LLD) IS INDICATED WITH *( )*.

/

I

l g

ENtf!RONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 1988)

MEDIUM: RIVER WATER UNITS: PCl/KG I -

INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS ee*************e

)

eeeeeeeeeeee****** **e.............e.......e )

RADIONUCLIDES MEAN MEAN MEAN l (NO. ANALYSES). REQUIRED RANGE STA. RANGE RANGE

{

I (NON ROUTINE /,* LLD No. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

RU 103 ( 24) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O I

( 0)

  • ( 0/ 12)* *( 0/ 12)*

RU 106 ( 24) ( 0.0 2 0.0)E 0 ALL EQUAL ( 0.0 2 0.0)E O I ( 0)

  • ( 0/ 12)* *( 0/ 12)*

I l-131 ( 24)

( 0)

( 0.0 2

  • ( 0/ 12)*

0.0)E 0 ALL EQUAL ( 0.0 2

  • ( 0/ 12)*

0.0)E O CS-134 ( 24) 15. ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 12)* *( 0/ 12)*

I v

CS 137 ( 24) 18. ( 0.0 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

. *( 0/ 12)* *( 0/ 12)*

BA 140 ( 24) 15. ( 0.02 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

  • ( 0/ 12)* *( 0/ 12)*

CE-141 ( 24) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 1 0.0)E O

( 0)

  • ( 0/ 12)* *( 0/ 12)*

CE 144 ( 24) 0.0 t 0.0)E 0 ( 0.0 2 0.0)E O I

( ALL EQUAL

( 0)

  • ( 0/ 12)* *( 0/ 12)*

I H3 ( 8)

( 0) 3000. (

  • (

0.0 2 0/ 4)*

0.0)E O ALL EQUAL ( 0.0 2

  • ( 0/ 4)*

0.0)E O I

  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

I ** THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (1.E. >A POSTERIORI LLD) 1$ IN0!CATED WITH *( )*.

I I

I H) Eeflimcat I During 1988, sediment samples were collected from two locations in May and October. Each sample was analyzed for gamma-emitting radionuclides. One grab sample was collected at Station SE-11 and 21 grab samples at Station SE-12 during May. During October, one I was again collected at SE-11 and 22 at SE-12.

Cesium-137 was detected in all samples. As has been discussed in previous Vermont Yankee Radiological Environmental Surveillance Reports, this radioactivity has been due to nuclear weapons testing fallout. Since there were no liquid releases during 1982 through

r. 1988, it can be concluded that the levels of Cs-137 in 1988 sediment samples were due also to nuclear weapons testing f allout.

This is further supported by the fact that similar levels have in I the past been detected at Station SE-21, a control station, and at control locations at other plants. Low levels of Co-60 have been detected in many samples collected. at Station SE-12 (N. Storm Drain Outfall) during 1988 and in previous years. This subject has been discussed in previous reports.

It should be noted here that the statistics given in the following table are heavily weighed toward Station SE-12, since 43 of the 45 samples $ tere collected there. No Co-60 was detected at Station I SE-11.

In addition to the above, Ce-141 was lirted as being " detected" at a very low level in one sample from SE-12 because its concentration exceeded the a_posteriori LLD. The typically used cut-off of three standard deviations was not exceeded, indicating that the Ce-141 was, in fact, not detected.

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

I I 2896R I 4

I ENtf!RONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

I VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 1988)

MEDIUM: SEDIMENT UNITS: PC1/KG DRY I INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS I

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

RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)* LLD NO. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

I ............. ........

BE 7 ( 45)

( 2.8 2 0.8)E 2 12 ( 2.8 2 0.8)E 2 NO DATA

( 15) ( 0.0 - 2.2)E 3 ( 0.0 - 2.2)E 3

  • ( 15/ 45)* *( 14/ 43)*

K 40 ( 45) 1.3 2 0.0)E 4 0.0)E 4 I

( 11 ( 1.3 2 NO DATA

( 0) ( 1.0 - 1.7)E 4 ( 1.0 - 1.3)E 4

  • ( 45/ 45)* *( 2/ 2)*

MN-54 ( 45) 0.0 t 0.0)E O I- ( 0)

( ALL EQ'JAL NO DATA

  • ( 0/ 45)*

Co-58 ( 45) ( 0.0

  • 0.0)E O ALL EQUAL No DATA

( 0)

  • ( 0/ 45)*

I FE 59 ( 45)

( 0)

( 0.0 s 0.0)E O ALL EQUAL NO DATA

  • ( 0/ 45)*

CO-60 ( 45) ( 6.4 2 1.2)E 1 12 ( 6.7 1 1.2)E 1 NO DATA

( 24) 0.0 - 2.9)E 2 0.0 - 2.9)E 2 I

( (

  • ( 24/ 45)* *( 24/ 43)*

2N 65 ( 45) ( 0.0 0.0)E O ALL EQUAL NO DATA I ( 0)

  • ( 0/ 45)*

I ZR 95 ( 45)

( 0)

( 0.0 2

  • ( 0/ 45)*

0.0)E O ALL EQUAL NO DATA AG-110M( 45) ( 0.0 1 0.0)E 0 ALL EQUAL NO DATA

( 0)

  • ( 0/ 45)*

NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

    • THE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE MEASUREMENTS (1.E. >A-POSTERIORI LLD) l$ INDICATED WITH *( )*.

I f -

I -

ENVIRONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

, VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 1988)

MEDIUM: SEDIMENT UNITS: PC1/KG DRY I INDICATOR STATIONS e......eeee**ee**e STATION WITH HIGHEST MEAN

. ************eee* e**ee.

CONTROL STATIONS I RADIONUCLIDES (No. ANALYSES) REQUIRED (NON ROUTlWE)* LLD MEAN RANGE NO. DETECTED **

STA.

NO.

MEAN RANCE No. DETECTED **

MEAN RANGE NO. DETECTED **

RU-103 ( 45) ( 0.0 t 0.0)E O ALL EQUAL NO DATA I

( 0)

  • ( 0/ 45)*

RU-106 ( 45) ( 0.0 2 0.0)E O ALL EQUAL NO DATA I ( 0)

  • ( 0/ 45)*

l-131 ( 45)

I ( 0.0 2 0.0)E O ALL EQUAL NO DATA

( 0)

  • ( 0/ 45)*

I CS-134 ( 45)

( 0) 150. ( 0.0 1

  • ( 0/ 45)*

0.0)E O ALL EQUAL NO DATA CS-137 ( 45) 180. ( 2.2 2 0.1)E 2 12 ( 2.3 2 0.1)E 2 No DATA

( 0) ( 5.8 - 48.1)E 1 ( 5.8 - 48.1)E 1

  • ( 45/ 45)* *( 43/ 43)*

BA-140 ( d5) ( 0.0 2 0.0)E O ALL EQUAL NO DATA

( 0)

  • ( 0/ 45)*

CE 141 ( 45) ( 1.9 2 1.9)E 0 12 ( 1.9 t 1.9)E O No DATA 0.0 -

I ( 1) (

  • ( 1/ 45)*

8.4)E 1 ( 0.0 -

  • ( 1/ 43)*

8.4)E 1 CE 144 ( 45) ( 0.0 2 0.0)E O ALL EQUAL NO DATA j I ( 0)

  • ( 0/ 45)*

I '" 2'2 ( ) ( * a 2 ( * a " "o o^'^

g ( 0) ( 4.4 - 13.8)E 2 ( 4.4 - 13.8)E 2

  • ( 45/ 45)* *( 43/ 43)*

I

  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER
THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

l

    • THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (I.E. >A-POSTERIORI LLD) IS INDICATED WITH *( )*.

1 o

I

I) Elah

I Fish samples were collected from two locations during May and again in October of 1988. Each sample consisted nf mixed fresh water species, generally perch and bass. All were analyzed for gamma-emitting radionuclides. Cesium-137 was detected in both of the samples collected at Indicator Station FH-11 and in one sample

. from Control Station FH-21. The levels are similar to those in past years (see Figure 3.7) 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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ENVIRONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT (JANUARY - DECEMBER 1988)

MEDIUM: FISH UNITS: PCl/KG WET

(

INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS j .................. ......................... .............**.

RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON ROUT 3NE)* LLD NO. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

............. ........ ..................... ......s................... .....................

BE 7 ( t. ) ( 0.0 2 0.0)E 0 ALL EQUAL ( 0.0 t 0.0)E O

( C)

  • ( 0/ 2)* *( 0/ 2)*

K 40 ( 4) ( 2.4 2 0.4)E 3 21 ( 2.7 2 0.255 3 ( 2.7 2 0.2)E 3 I ( 0) ( 2.0 -

  • ( 2/ 2)*

2.9)E 3 ( 2.5 -

  • ( 2/ 2)*

2.9)E 3 ( 2.5 -

  • ( 2/ 2)*

2.9)E 3 I MN 54 ( 4)

( 0) 130. (

  • (

0.0 2 0/ 2)*

0.0)E O ALL EQUAL (

  • (

0.0 t 0/ 2)*

0.0)E O CO-58 ( 4) 130. ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 t 0.0)E D

( 0)

  • ( 0/ 2)* *( 0/ 2)*

FE-59 ( 4) 260. ( 0.0 1 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O i

( 0)

  • ( 0/ 2)* *( 0/ 2)*

Co 60 ( 4) 130. ( 0.0 1 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 2)* *( 0/ 2)*

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

( 0)

  • ( 0/ 2)* *( 0/ 2)*

ZR-95 ( 4) ( 0.0 2 0.0)E 0 ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 2)* *( 0/ 2)*

AG 110M( 4) ( 0.0 1 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 2)* *( 0/ 2)*
  • NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT. l I ** THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >A-POSTERIORI LLD) IS INDICATED WITH *( )*.

4; E

i ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 VERMONT YANKEE NUCLEAR POWER STATION, VERNON, VT

.I (JANUARY - DECEMBER 1968)

MEDIUM: FISH UNITS: PCl/KG WET INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS

        • ee**+e**ee. ** ************ee**********e .........e***e..

RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)* LLD NO. DETECTED ** NO. NO. DETECTED ** NO. DETECTED **

RU 103 ( 4) ( 0.0 2 0.0)E 0 ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 2)* *( 0/ 2)*

RU 106 ( 4) ( 0.0 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O l

( 0) I

  • ( 0/ 2)* *( 0/ 2)* l f

I-131 ( 4) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0) )

I

  • ( 0/ 2)* *( 0/ 2)*

CS 134 ( 4) 130. ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 2)* *( 0/ 2)*

CS-137 ( 4) 150. ( 3.72 0.3)E 1 11 ( 3.72 0.3)E 1 ( 1.4 2 1.4)E 1

( 0) ( 3.4 - 4.0)E 1 ( 3.4 - 4.0)E 1 ( 0.0 - 2.9)E 1

  • ( 2/ 2)* *( 2/ 2)* *( 1/ 2)*

BA 140 ( 4) ( 0.0 1 0.0)E O ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 2)* *( 0/ 2)*

CE-141 ( 4) ( 0.0 2 0.0)E 0 ALL EQUAL ( 0.0 2 0.0)E O

( 0)

  • ( 0/ 2)* *( 0/ 2)*

CE 144 ( 4) ( 0.0 2 0.0)E O ALL EQUAL ( 0.0 t 0.0)E O !

( 0)

  • ( 0/ 2)* *( 0/ 2)*

TH 232 ( 4) ( 0.0 t 0.0)E O ALL EQUAL ( 0.0 2 0.0)E D

( 0)

  • ( 0/ 2)* *( 0/ 2)*

11

  • NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER I

THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

    • THE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE MEASUREMENTS (1.E. >A POSTERIORI LLD) IS INDICATED WITH *( )*.

I _ _ _ _ _ _ _ _ _ _ _ _ _

i i

J) Direct Radiation Direct gamma radiation exposure was determined from the use of thermoluminescent dosimeters (TLDs). Beginning in 1988,

~

Panasonic UD-801AS1 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 16 at outer ring stations. Twelve were located at the site boundary, six were at special interest locations, and one was a control.

Summaries of the results for 1988 can be seen in the table below.

A complete station-by-station summary is given in Table 3.1. In this table, the quarterly averages for inner ring stations (i.e.,

I those locations that could possibly be influenced by plant operations) can be compared with those for the outer ring stations (i.e., those locations outside of the range of influence of the plant). Upon examining the quarterly exposure rates in the table, it is also evident that the inner ring exposure rates are not statistically different from those of the outer ring.

I Upon examining Figure 3.10, it is evident that Station DR-45 has a higher average exposure rate than any other station. This is not I surprising in that DR-45 is actually located on-site in close proximity to the plant (see Figure 2.4). Station DR-6 also had a high reading during the third quarter of 1987. Over-response of the TLDs is suspected. Panasonic TLDs from the Yankee Environmental ' Laboratory were co-located with the standard Victoreen during 1987. The Panasonic TLD at DR-6 during the third quarter gave a reading of 7.2 micro-R per hour.

Additionally, two TLD stations (DR-7 and DR-8) located between the plant and DR-6 had readings of 11.36 and 10.81 micro-R per hour, I which is substantially lower than the 24.04 micro-R per hour at DR-6.

2896R I

I

Environmental Radiological Program Summary Vermont Yankee Nuclear Power Station January - December 1988 Medium: Direct Radiation Units: Micro-R per Measurements (TLD) Hour Station With Inner Ring Highest Mean fluter Ring Mean Mean Mean Range Station Range Range I _(Ha _ Meas.J* No. (No. Meas.)* (No. Meand*

7.0 10.5 22.5 114.8 7.2 10.7 5.9 - 8.3 45 13.4 - 44.5 5.8 - 8.8 i (88) (4) (68)

I

  • Most measurements based on five readings per station.

I I 2896R I

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Iable 3.1 Eumlary_nf Direct Radiationlaaaurements - 1988 i Virmant YankesJuglear Power Station f (Micro-R Per Hour) 1 Location Zype* QIR_1 QTR 2 OTR 3 QIR_h Yeariv Mean DR-1 1 6.5 6.4 7.1 6.6 6.7 DR-2 I 6.2 6.7 7.2 6.8 6.7 DR-3 I 6.9 8.0 8.3 8.2 7.9

.I' DR-4 DR-5 I

0 5.9 6.3 6.2 7.3 6.7 7.5 6.1 6.9 6.2

/.0 DR-6 I 6.1 7.4 7.6 7.0 7.0 I DR-7 DR-8 DR-9 SB SB I

7.7 8.6 6.5 9.1 9.0 6.9 9.3 9.6 7.1 9.1 9.4 6.7 8.8 8.9 6.8 5.9 I DR-10 DR-11 DR-12 0

I 0

5.9 6.3 6.0 5.8 6.5 6.5 5.9 6.8 6.6 6.1 6.3 6.4 6.5 6.4 i h

DR-13 I 6.4 6.9 6.7 6.8 6.7 DR-14 0 7.4 8.1 8.2 7.9 7.9 DR-15 I 7.1 7.3 7.4 7.3 7.3 DR-16 0 7.8 7.4 7.8 7.5 7.6 DR-17 I 6.3 6.9 7.2 6.7 6.8 DR-18 0 6.8 7.5 7.8 7.6 7.4 DR-19 I 6.7 7.6 7.7 7.2 7.3 7.1 8.1 8.7 8.1 8.0 I DR-20 DR-21 DR-22 0

I 0

6.5 7.1 7.3 7.2 7.8 7.6 7.3 7.3 7.2 7.3 l

{

DR-23 I 62 6.7 7.3 6.9 6.8 I DR-24 DR-25 DR-26 0

I 0

5.8 7.0 6.6 6.3 6.9 7.3 6.7 7.2 7.5 7.8 7.1 7.2 6.7 7.1 7.2 I DR-27 DR-28 DR-29 I

0 I

6.4 6.4' 6.4 7.1 7.2 7.0 7.2 7.9 7.4 7.2 7.5 7.3 7.0 7.3 7.0 DR-30 0 6.3 7.0 7.4 7.0 6.9 I DR-31 DR-32 I

0 6.6 6.2 7.3 7.0 7.5 7.6 7.5 7.2 7.0 7.2 7.0 7.1 DR-33 I 6.7 7.1 7.5 I DR-34 DR-35 DR-36 0

I 0

6.5 6.6 7.0 7.7 6.9 8.5 8.1 7.5 8.8 7.6 6.9 8.3 7.5 7.0 8.2 7.3 7.1 I DR-37 DR-38 DR-39 I

0 I

6.0 6.9 6.3 7.3 7.6 7.1 7.8 7.8 7.4 7.4 6.9 7.4 6.9 DR-40 0 6.5 7.0 7.2 6.6 6.8 I DR-41 DR-42 DR-43 SB SB SB 7.3 5.9 6.3 8.1 7.4 7.9 8.4 7.7 8.1 8.2 6.9 7.6 8.0 7.0 7.5 DR-44 SB 9.2 8.3 8.6 8.3 8.6 2896R ll

Inhie 3.1 (Continued)

Summary of_ Dire.ct._Radia1Lon_Meaantementa_ _118B yermont Yankee Nuclear Power Station Lncation Iy2e* QIR_1 DIR_2 OTR 3 QIR_4 Year 1v Mean*

DR-45 SB 44.5 13.4 14.1 18.1 22.5 DR-46 SB 8.2 9.0 9.2 9.2 8.9 DR-47 SB 7.1 8.5 8.9 8.4 8.2 I DR-48 DR-49 SB SB 5,9 6.2 6.6 7.7 7.3 7.4 7.9 7.5 8.2 7.4 7.3 7.4 7.2 7.1 7.4 DR-50 I DR-51 SB 7.6 9.4 9.3 8.7 8.8 1

7.0 7.4 7.0 I QTR Mean Inner Ring 6.5 0.34 0.41 0.42 0.44 QTR Mean 6.6 7.3 7.6 7.3 1 Outer Ring 10.54 10.6, 10.72 10.59 QTR Mean 10.4 8.7 9.1 9.1 I Site Boundary 10.80 11.63 11.73 12.96 l

I I

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i I *I = Inner Ring; O = Outer Ring; SB = Site Boundary.

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I 4.0 QUALITY ASSURANCE PROGRAM j Three separate Quality Assurance programs were performed during 1988 to l demonstrate the validity of laboratory analyses by the Yankee Atomic l Environmental Laboratory (YAEL).

\

l'AEL participates in the EPA Interlaboratory Comparison (cross-check) ]

program for those species and matrices routinely analyzed by the laboratory. i 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 corrective measures are taken.

I YAEL maintains an intralaboratory quality control program to assure the validity and reliability of the data. This program includes quality control I of laboratory eqttipment, use of reference standards for calibration, and analysis of blank and spiked samples. The records of the quality control program are reviewed by the responsible cognizant individual, and corrective measures are taken whenever applicable.

I A blind duplicate program is maintained in which paired samples from five nuclear plants, including Vermont Yankee, are Frepared from homogenous I media and sent to the laboratory for analysis. The results from this blind duplicate program are used to check for precision in laboratory analyses.

I EPA Interlaboratory and Intralaboratory Results I The Quality Assurance Program implemented at the analytical laboratory indicated good precision and accuracy in reported values. Table 4.1 shows the results of accuracy and precision for laboratory analyses in 1988 for intralaboratory analyses, and EPA interlaboratory cross-check analyses. For accuracy, 65.0 and 86.5 percent of the results were 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 percent. For precision, 84.7 and 96.7 percent of the results were within 5 and 10 percent of the mean, respectively, with 99.8 percent of all results meeting the laboratory criteria of 15 percent.

I 2876R 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 preefsion in 1988. Two hundred and nineteen analysee were performed on air particulate filters, food, milk, urine, and water. Based upon this sample analysis total, 217 analyses (i.e.,

99.17.) met the EPA's definition of mean value criteria. The sample analyses that did not meet the criteria were a Sr-90 analysis on a milk sample and a Ra-226 analysis on a water sample. (Details of this may be found in References 1 and 2.) Two of the three milk samples had been remilked and analyzed for Sr-90 before the EPA recalts were received. The new Sr-90 mean value, using the above results, fell within the EPA control limits. With respect to the Ra-226 results, no new Radium analyses have been performed since the receipt of these results, and the beta-gamma coincidence system for I Ra-226/Ra-228 is scheduled for recalibration in 1989.

I The above EPA Interlaboratory Comparison Program results are provided in compliance with Technical Specification 4.9.E.

I B1ind Duplicate Proflam I A total of 51 paired samples were submitted by the five participating plants for analysis during 1988. The data base used for the duplicate I analyses consisted of paired measurements of 26 gamma emitting nuclides, H-3, Sr-89, Gr-90, low level I-131, gross beta, Ra-226, and Ba-228. A dual level I. criteria for agreement was established. If the paire6 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 range (95 percent confidence level) is established for each of the analyses. If the ranges overlap, agreement is obtained.

I One thousand three hundred and seventeen paired duplicate measurements were analyzed for 1988. A total of 99.5 percent of all measurements fell

-I withir: the established criteria discussed above. The six measurements that did not meet the criteria were measurements of 2n-65 in ground water, Mo-99 in I 2896R I

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milk, TeI-132 in ground water, Zr-95 in cranberries, Ba-140 in milk, and I Sb-124 in milk. In all of the above cases, the radionuclides in question was not detected in the sample and a three-standard deviation acceptance criteria was s.it. The six duplicate measurements represent 0.5 percent of all the l

blind duplicate paired measurements made during 1988. No trend was evident with respect to repeated failings of measurements for the above radionuclides.

I i I l, I l I 4 I

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I I

I I 2896R I

Iable 4.1 latralahDIatDIy__And EPA Interlahoratory Results - 1988

)

Accuracy Total Number nLEeaEurententE O to 5% 0 to 10% 0 to 15%*

654 425 566 632 1 1

(65.0%) (86.5%) (96.6%)

Precision I

Total Number of Measurements 0 to 5% D_to 10% 0 to 15%*

633 536 612 632 (84.7%) (96.7%) (99.8%)

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

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5.0 IAND USE CENSU.S l I 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 plant. It also identifies the nearest milk animal (within 3 miles of the plan t .) 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 1988 Land Use Census at Vermont Yankee was carried out between the dates of June 1 and October 1, as required by Technical Specifications. The I 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 locations.

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I l 2896R

Iable 5.1 I

1988_ land _Ute_Cenana Results Vermont Yankee Nuclear Power Station I Nearest Residence (km)

Milk Animala*__

CQw or Goat Saslor km N 1.6 ** -

1.6 **

I NNE NE 1.3 4.2 Goats ENE 1.0 ** --

E 1.0 2.4 Cows ESE 2.8 ** -- i SE 1.8 3.4 Cows SSE 2.0 5.1 Cows S 0.5 ** -

SSW 0.5 2.1 Cows 0.5 7.2 Cows I

SW WSW 0.5 ** --

W 0.5 7.2 Goats WNW 0.6 0.8 Cows WNW --

4.7 Cows NW 1.2 4.7 Cows NNW 2.1 ** --

1 1

j I i I

I

    • No milk animals found within 5 miles. l l

f fl 2896R l

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_ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ i

6.0 SilMtiARY I During 1988, samples collected as a part of the radiological environmental monitoring program at Vermont Yankee showed detectable levels of I 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  :

nucleer 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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7.0 REFERENCES

I-l* 1. Yankee Environmental Radiation Measurement Laboratory, Semi-Annual Quality Assurance Status Report, January to June 1988, Yankee Atomic Electric Company.

2. Yankee Atomic Environmental Laboratory, Semi-Annual Quality Assurance
Status Report, July to December 1988, Yankee Atomic Electric Company. '

t

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