ML20034C481

Yankee Nuclear Power Station Annual Radiological Environ Operating Rept,1989

ML20034C481
Person / Time
Site:	Yankee Rowe
Issue date:	12/31/1989
From:	Papanic G YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYR-90-62, NUDOCS 9005030379
Download: ML20034C481 (71)

Text

{{#Wiki_filter:_ YANKEWATOMICELEdTRIC COMPANY "C"H".g*g'O."*;" g '580 Main Street, Bolton, Massachusetts 01740-1398 v. April 27, 1990 BYR 90-62 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

(a) License No. DPR-3-(Docket No. 50-29)

Subject:

Annual Radiological Environmental Operating Report

Dear Sir:

Enclosed please find the Annual Radiological Environmental Monitoring Report.for the Yankee Nuclear Power Station. This report contains a summary and analysis of the radiological environmental data collected for~the year 1989 and is submitted as required by Technical Specification 6.9.5(a). We trust that you will-find this submittal satisfactory; however, if you' have any questions, please contact us.- Very truly yours, YANKEE ATOMIC EL CTRIC COMPANY Georg a anic, Senior Project Engineer Licensing GP/tlp/WPP72/47 Enclosure cc: USNRC Region I USNRC Resident Inspector, YNPS 1 .) .kDR ADOCK 03000029 p i ( 4 roc ]

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r s l' (( YANKEE NUCLEAR POWER STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January - December 1989 l2 April.1990 l t-- .i i l l l LI I .( l '^ Prepared by: l' Yankee Atomic Electric Company Environmental Engineering Department 580 Main Street Bolton, Massachusetts 01740 2 .. ~.. ..-..~...-....... -... --. -.

TABLE OF CONTENTS [ .EAEC -t LIST OF TABLES.................................................~... iii LIST OF FIGURES................................................... iv

1.0 INTRODUCTION

............................................~.......... 1. ~{ 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PR0 GRAM..................... 2- ,I 3.0

SUMMARY

OF RADIOLOGICAL ENVIRONMENTAL DATA........................ 14 3.1 Air Particulate..........~................................... 16 1 -3.2 Charcoal Filter............................................. 20 l 3.3 M11k........................................................ 22 ig 3.4 Food Crop / Broad Leaf Vegetation............................. 26

g 3.5 ~ Maple Syrup.................................................

29-3.6 Groundwater................................................. 32 q 3.7 River Water................................................. 36 3.8 Sediment.................................................... 39 l 3.9 Fish........................................................ 43 3.10 Direct Radiation............................................ 47 4.0 QUALITY ASSURANCE PR0 GRAM......................................... 57 5.0 LAND USE CENSUS....'..................................~............. 61 6.0

SUMMARY

63

E

7.0 REFERENCES

64 ,3 I I l. WFP12/25 I. -~ -

s o i LIST OF' TABLES 7 i Nn=her Title Page-2.1 Radiological Environmental Monitoring Program 3 2.2 Radiological Environmental Monitoring Locations 4 3.1 Sunenary of Direct Radiation Measurements - 1989 56 4 4.1 Intralaboratory and EPA Interlaboratory Results - 1989 58 'I -5.1 1989 Land Use Cansus Results~ 62 ( !It i 'I I lI k ll e lI WPP12/25

-1 I LIST OF FIGURES s I' Eumbar Title Eags i 2.1' Yankee Plant. Radiological Environmental Monitoring Locations Within 1 Mile (Airborne, Waterborne, and i Ingestien Pathways) 7 2.2 Yankee ?lant Radiological Environmental Monitoring -Locations Within 12 Miles (Airborne, Waterborne, and 8 Ingestion Pathways). I-2.3 Yankee Plant Radiological-Environmental M'onitoring Locations Outside 12 Miles (Airborne, Waterborne, and - Ingestion Pathways) 9 l 2.4 Yankes Plant Radiological Environmental Monitoring' Locations at the Restricted Area Fence (Direct' ) Radit. tion Pathway) 10 2.5 ~ Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mlle (Direct Radiation Pathway) 11-L q L 2.6 Yankee Plant Radiological Environmenta1' Monitoring. Locations Within 12 Miles (Direct Radiation Pathway) 12 2.7 Yankee Plant Radiological Environmental Monitoring Locations Outside 12 Miles (Direct Radiation Pathway) 13 i ~ 3.1 Gross-Beta Measurements of Air Particulate Filters 17 3.2 Cesium-137 in Milk 23 i 3.3 Gross Beta Measurements of Ground Water 33 3.4 Cesium-137 in Sediment 40 I l 3.5 Cesium-137 in Fish 44 i 3.6 Exposure Rate at. Indicator TLDs, GM 01-07 49 3.7 Exposure Rate at Indicator TLDs, GM 08-12, 40 50 3.8 Exposure Rate at Outer Ring TLDs, GM 24-31 51 3.9 . Exposure Rate at Outer Ring TLDs, GM 32-39 52 3.10 Exposure Rate at Fenceline TLDs, GM 13.21 53 3.11 Exposure Rate at Control TLDs, GM 22-23 54 WPP12/25 1

1.0 INIRODUCTION-1 The radiological environmental surveillance program for the Yankee i Nuclear Power Station (YNPS) has been designed and carried out with specific objectives'in mind. They are as follows: To provide an early indication'of the appearance or accumulation of any radioactive material in the environment caused by the operation- -of-the nuclear power station. To provide assurance to regulatory agencies and the public that the station's environmental' impact is known and within anticipated limits. i 1 To verify the adequacy and proper functioning of station effluent controls and monitoring systems. To provide standby'monittting capability for rapid assessment of I risk to the general public in the event of unanticipated or accidental releases of radioactive material.- During 1989, the plant staff collected all environmental samples, including environmentel thermoluminescent dosimeters (TLDs). All samples were l sent to the Yankee Atomic Environmental Laboratory for further processing and radionuclide analysis. TLDs were also sent to this laboratory for processing. This report is a summary of the findings of the Radiological Environmental Surveillance Program for 1989. It is being provided in compliance with plant Technical Specification 6.9.5.a.

WPP12/25 1

' I 2.0 RADIOLOGICAL ENVIRONMbiVAL MONITORING PROGRAM In this section. Table 1.1 outlines the monitorin's program as required = by plant Technical Specification 3/4.12.1. 7 d le 2.2 lists the sampling stations and their specific locations (distances are measured from the center of the containment building). The sampling locations are shown on maps in f Figures 2.1 through 2.7. lI i g. !I i r lI 1 'I 'I I l l 1 'I WPP12/25

+ 1 . Table'2.[ l Radiological Environmental' Monitoring Program 1 Yankee Nuclear Power Station l Media Sampling Frequency Required Analyseg Weekly-Gross beta l_' Air Particulate (AP) Quarterly Composite Gansna spectroscopy Charcoal Filter (CF) bekly I-131 [ Milk (IM) - Monthly; once per Gamma spectroscopy, 2 weeks from June 1 I-131 to Nov. 1 Annually (Harvest) Gamma spectroscopy ( Food Crop (TF) Annually.(Harvest) I-131 Broad Leaf Vegetation (TV) Quarterly Gamma spectroscopy, j Groundwater (WG) i H-3 ] Monthly (Composite) Gross. beta, i River Water (WR) [g g. Gamma spectroscopy Quarterly Composite H - i 3 ( Sediment (SE) Semiannually = Gamma spectroscopy l Fish (FH) Seasonal or-Gamma spectroscopy l ~ Semiannually Direct Radiation (GM) Quarterly _ De -dose only i (Outer ring TLDs) (g - Quarterly Integrated gansna g (All other TLDs) dose-I lI .I I l WPP12/25 I

~' , I. i: Imble 2 8 Radiolonical Environmental Monitorine Locations Yahkee Nuclear Power Station lI l Distance l Station Code From Plant Direction (Media - Sta. No.) Station Descriotion Zone * (km) From Plant i AP/CF-11 Observation' Stand-1 0.5 NW AP/CF-12 Monroe Bridge 1 1.1 SW AP/CF-13 Rowe Schoo1~ 1 4.2 SE AP/CF-14 Harriman. Station. 1 3.2 N ig AP/CF-21 Williamstown, MA 2 22.2 W- !g AP/CF-31** YAEC Visitor's Information Center 1-0.8 SW AP/CF-32** Heartwellville, VT 2 12.6 NNW IN-12 Readsboro, VT 1 6.1 N IM-13 Whitingham, VT 1 8.4 ENE TM-21 Williamstown, MA-2 21.0 WSW TF-11 Monroe Bridge, MA 1, 1.3-SW !g TF-13 Monroe, MA. 1 1.9 WNW g TF-21 Williamstown, MA 2 21.0 WSW i TF-31 Readsboro, VT 1 3.5 N l TF-33 Rowe, MA 1 -1.0 S (Maple Syrup)** TF-44 Hancock, MA-2 -30.7 SW (Maple Syrup)** ,j TF-46 Whitingham, VT 1 9.3 NE

g' (Maple Syrup)**

IV-11 Monroe Bridge, MA 1 1.3 SW iI' f WG-11 Plant Potable 1 On-Site WG-12. Sherman Spring 1-0.2' NW WR-11 Bear Swamp Lower Res. 1 6.3 Downriver. l WR-21 Harriman Reservoir 2 10.1 Upriver WR-31 Sherman Pond 1 0.1 N' l SE-11 No. 4 Station 1 36.2 Downriver. I SE-21 Harriman Reservoir 2 10.1 Upriver SE-91 Sherman Pond 1 0.1 N SE-92 Sherman Pond 1 0.8 N j SE-93 Sherman Pond 1 1.3 N I-SE-94 Sherman Pond 1 1.1 N SE-95 Sherman Pond 1 0.1 N l SE-96 Sherman Pond 1 1.9 N WPP12/25 ,L m l

I Imble 2.2 (Continued) I l

E Radiological' Environmental Monitoring Locations Yankee Nuclear Power Station Distance d

Station Code From Plant

Direction (Media - Sta. No.)

Etation Descriotion Zone * (km) . From Plant i j FH-11 Sherman Pond 1 1.5 N i 3 FH-21 Harriman Reservoir 2 10.1 Upriver' GM-1 YAEC Visitor's I Information Center 1 0.8 SW GM-2 Observation Stand 1 0.5 -NW-GM-3 Rowe School 1 4.2 SE I GM-4 Harriman Station 1 3.2 N GM-5 Monroe Bridge 1 1.1 SW' GM Readsboro Road Barrier 1 -1,3 N I GM-7 Whitingham Line 1 3.5 NE GM-8 Monroe Hill Barrier-l' 1.8 S -l GM-9 Dunbar Brook 1-3.24 SW: i, GM-10 Cross Road 1 3.5 E GM-11_ Adr.ms High Line 1 2.1 WNW j 'GM-12 Readsboro, VT 1 5.5 NNW GM-13 Restricted Area Fence F -0.08 WSW I GM-14 Restricted Area Fence F 0.11 WNW j GM-15 Restricted Area' Fence F 0.08 'NNW GM-16 Restricted Area Fence F 0.13 NNE GM-17 Restricted Area Fence F 0.14 ENE } I GM-18 Restricted Area Fence F 0.14. ESE I GM-19 Restricted Area Fence F 0.16 SE CM-20 Restricted Area Fence F 0.16 SSE I GM-21 Restricted Area Fence-F 0.11 SSW GM-22 Heartwellville, VT 2 12.6 NNW GM-23 Williamstown Substation 2 22.2' W GM-24 Harriman Dam 0 7.3 ' N I GM-25 Whitingham, VT 0 7.7 .NNE GM-26 Sadoga Road 0 7.6 NE-I GM-27 Number 9 Road 0 7.6 ENE GM-28 Number 9 Road 0 6.0 'E i GM-29 Route 8A-0 8.2 ESE GM-30 Route 8A 0 9.4 SE GM-31 Legate Hill Road 0 7.6 SSE GM-32 Rowe Road 0 7.9 S GM-33 Zoar Road 0; 6.9 SSW i GM-34 Fife Brook Road 0 6.4 SW GM-35 Whitcomb Summit 0 8.6 WSW ~5-WPP12/25 I

Table A.A- -(Continued) i Radiolonical Environmental Monitorine Locations Yankee Nuclear Power Station Discance-r Station. Code From Plant Direction (Media - Sta. Nod Station Description Zone * (km) From Plant ~ I r. GM-36 Tilda Road O 6.6 W GM-37 Turner Hill Road-0 6.' 7 ~WNW l GM-38

West Hill' Road -

0 6. 6.' NW .l lg GM-39 Route 100 0 6.8 NNW

)

lg= .GM-40 Readsboro Road. 1 0.5 -W. .j i .j lI \\1 l lI 1 i I W

• 1 = Indicator Stations; 2 = Control Stations;-0 = Outer Ring Incident l

Response TLD;.F = Fenceline. Not required by Radiological' Effluent Technical Specifications or the Off-Site Dose Calculation Manual. i, i WPP12/25 I I i

r I l E $ @ SE-96 / g ; a.3 3,,,, l Yement ' ' ^/ ~~ ~- -~ l . Massachusetts j 8E'84 ' O 500.: i i ( j HETER $ i: t

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(_ - @ SE-92 i -- I ) V j ;. -f-I. f-( h-g @SE-91,h{ AP/CF-11 @ SE-95 E '@ WR-31:~W ? n' @ wc-12 ~ . PLANT W qs? g'WG-11 / = g Z c 3. Y k r W i- % Monroe geggg, l

1. AP/CF-12 e 7,.

33 ] TV-11 %nto - e g,;' %,,

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S& 2 \\' l> Figure 2.1 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Airborne, Waterborne and Ingestion Pathways) J, - -,--,+. ee -A-- -~ .e .- s r

I l 1

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= W e E. SE-21 M rH-21 ._ 5 WHITINGHAM E. TM-12 @ @ TF-46 READSBORO I e WR-21 @ AP/CF-14 ,I _ SitcAnin Pond 1 5i VERMONT i 5.T3gl [ -~ I~ NASSACHLGETTS HONROE BRIDGE ' i "*'- SEE ENTARGEATNT IN FIGURE t.1 I 1 E l4-e l I PLANT I l---- I I $ TF-33 l SCAA Saump touer Reaggyogg @AP/CF-13 I_

• R0WE J @ WR-ll

(-

• HEATH I

'Ctg'. l CQ% 'I Cf CHARLEMONT f f I f f I f f KILOMETERS SE-ll@- SHELBURNE FALLS, I Figure 2.2 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Airborne, Waterborne and Ingestion Pathways)

m-a l l l -BENNINGTON: "O n HEARTWELLVILLE. l n READSBORO ' g I \\ vi. fe vp.u 1 .[!A' WILLIAMSTOWN I E "A @ AP/CF-21 R0WE / @ w 21 I / TF-21 HEATH e ,i

1. Cty,.

CHARLEMONT '&f. SHELBURNE FALLS

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1 i I 1 l O 5 10 15 20 t i t l I PITTSFIELD KILOMETERS e Figure 2.3 Yankee Plant Radiological Environmental lionitoring Locations Outside 12 Miles (Airborne, Waterborne and Ingestion Pathways) 'i...............

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4. i' I

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t l yard gg'.g I 1 Turbine Service i Training hGM-I3 - -l _ Aux. Bay AT'" Vhse. l f, ,I,) Center I N 9 / i a p \\ N' I I Vapor g i 3g.. ..,jg W t,6th.'*** S i i Container' t w, ,,p,, s, j [ g s + i f s 1 g m. O s PAB 1 / e ,.i. 4 8 ~ ' 00 A le 3: Nd! j ne t) i -4 c +, i0 t i seM.u j waste pisposal g i ,/ \\ s_..... 3' l t

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\\ I i \\ \\ l \\ \\ s s 's t 0 9 0 ,,i\\ gGM-18**1, i. i 's - -@ M.%0~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ @'DM-19 i 1 p s,, t I ______a. L i l'- l Figure 2.4 Yankee Plant Radiological Environmental Monitoring Locations at .f the Restricted Area Fence- (Direct Radiation Pathway)

j l i I

h \\.6 [ /[- - g \\- GM M455achusett j I ~

Nig, I

O 500 k I f f f l f HETERS . MRMAN IDN \\ I '\\ i /: 4 / GM.2 y l [z % I y b g i f l s, s / A ~ \\ } GH-1 @ h Monroc Bridge 4 5 1 1 Nnroy .. ~ g) I e Ssp GM-8 1 Figure 2.5 .. Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Direct Radiation Pathway) ). .d W i

s N g,q l N

1. b

) l. ='T -=f Ho4%2 AIM RfACA A H(ARTW[LLVI (t '4 CM-22 1 .=72 ~L: Jr @GM25 ._

• VH1 W. HAM N a g A SBORO Rt GM 12.

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,.c he rend @cM 27 @a 37 GM u i ~!i @,GM7 vtRMoni p' c ~

---

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}_ g3 %,'gpeg, MASSACHustTis ~~' . - ser r#LAErurA7 J# TM vRr t.s gg @GM 36 gi 1 rLMti NGM 10 @GM-28 k 7-- I Ja B ms.,t_ y, U"*3 @CM-29 k@M, G GM34g powg @Gg,33 HEATH @GM-30 8M @GM-31 @GM-32./ $p o 3% %'Cf CHARLtMONT 8 O 5 to l !>1 l ii! i i e i 9 KILOMETERS 666 SHELBURNE FALLS, 1' + Figure 2.6 Yankee Plant Radiologtcal Environm!lnt al Monitorin )Locat ons Within 12 Miles (Direct Radiat. ion Pathway) i t s. it'

I g j l "/ 'g \\ EKNINGTON 10 Miles I \\ ~ [ARTWC(LV LL[ ~ /- I (

• e

.. iriN< 05 BORO ' ~ ~' W / ~ ~ ~ ~ ~ E l ff""q,"",,fm / ..t E V' / o I '4 CHARLEM T f, BURNC FALL $* \\ l kr N g ir 0 5 10 15 20 t i i i i KILOMETERS Ptrisrtito Figure 2,7 Yankee Plant Radiological Environmental Monitoring Locations ~ Outside 12 Miles (Direct Radiation Pathway) - 1 -.4

3.0 EUMMARY OF RADIOLOCICAL INV9RONMENTAL DATA I The following pages summarire the analytical results of the environmental samples which were collected during 1989. Each environmental I 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 medium. The leit hand column contains the radionuclide which is being reported, total number of analyses of that radionuclide, and the number of measurements which exceeds ten times the yearly average for the control station (s). The latter are classified as "nonroutine" measurements. The next column lists the Lower Limit of Detection (LLD) for those radionuclides which have detection capability requirements as specified in the plant's Radiological Effluent Technical Specifications (Table 4.12-1). LLD requirements are not specifled in the Technical Specifications for many of the radionuclides for which analyses are routined conducted. I Those sampling stations which are within the range of influence of the I plant and which could conceivably be affected by its operation are called " indicator" or " Zone I" stations. Distant stations, which are beyond plant influence are called " Control" or " Zone II" stations. Direct radiation monitoring stations are broken down into two additional categories to aid in data analysis. These are fenceline stations and outer ring (emergency response) stations. A set of statistical parameters is calculated for each radionuclide. These include separate analyses for (1) the indicator stations, (2) the control stations, and (3) the station having the highest annual mean concentration for that radionuclide. For each of these three groups of data, these parameters aret The mean value of all concentrations including negative values and o values below LLD. WPP12/25 4

I o The standard error of the mean. I o The lowest and highest concentration. o The number of positive measurements (activity which is three times greater than the standard deviation) divided by the total number of I measurements. Each single radioactivity measurement datum in this report is based on a single measurement and is reported as a concentration plus or minus a one standard deviation uncertainty. The quoted uncertainty _ term represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in.the I analytical procedure. Radioactivity is considered to be present in a sample when the concentration exceeds three times its associated standard deviation. With respect to the plots, all values less than three standard deviations * (i.e., t,.se.,ere no ramacma,.as dete.,ed>. ore,1otted as sero. I I I l I WPP12/25

i E 3.1 Air Particulata a Air monitoring stations are established at a total of seven i locations, five of which are required by the Radiological Effluent Technical Specifications. The air pumps at these l i l locations operate continuously at a flow rate of approximately i c one cubic foot per minute. Airborne particulates are collected by passing the air through a glass-fiber filter. These filters { 4 are collected weekly and held for at least 100 hours before being analyzed for gross-beta activity (indicated as GR-B in tables) to allow for the decay of radon daughter products. Weekly composite air filters from each location are analyzed quarterly for gamma-emitting radionuclides. Gross-beta analyses (Figure 3.1) show environmentally-induced fluctuations through much of the year at all sampling locations, including controls, thereby indicating that any plant contribution is negligible. Two exceptions to this were as fo11cws: I During a period of several weeks during mid-1989, slightly 1 elevated concentrations were measured consistently at control j I station AP-21. Although the exact cause was not identified. faulty sampling equipment is a possible explanation. The l l sampling pump was replaced and the gas meter has since been l calibrated. One other measurement that stands out during 1989, is the December 5,'1989 measurement from AP-32 (a control). This l measurement is not considered reliable due to a gas meter failure, and therefore, a possibly erroneous gas meter reading. (Station AP-32 is not required by Technical Specifications or the Off-Site Dose Calculation Manual.) 'M Naturally occurring Be-7 was also detected in all samples. g E -I t,- l WPP12/25 u E

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I ENVIRONMENTAL RAD 10 LOGICAL PROGRAM $UMMARY j YANKEE NUCLEAR POWER STATION, ROWE, MA I (JANUARY DECEMBER 1989) MEDIUM: Alk PARilCULATE UNIT $t PCl/CU. M l INDICATOR STATIONS $1Afl0N WITH NIGNE$f MEAN CONTROL STAtl0NS f RADIONUCLlDES MEAN MEAN MEAN (NO. ANALYSE $) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)* LLD WD. DETECTED ** Wo. WO. DETECTE0** N0. DETECTED ** e GR B (371) .01 ( 1.9 0.1)E *2 21 ( 2.4 a 0.1)E +2 ( 2.1 : 0.1)E 2 ( 0) ( 2.1 * $9.0)E.3 ( 6.0 * $7.4)E +3 ( 1.5 - 58.0)E 3

• (260/265)*
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0/ 8)* i i I~ WON ROUTINE REFER $ T0 THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE SACKGROUND FOR THE PERIOD OF THE REPORT. THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIAfl0NS) !$ INDICATED WITH *( )*. 'E g .,e. 'E

~ .i i ENYlRONMENTAL RADIOLOGICAL PROGRAM SL89tARY YANKEE NUCLEAt POWER $TATION, ROWE, MA (JANUARY

• DECEMBER 1999)

MEDIUM: Alt PARTICULATE UNITS: PCl/CU H i INDICATOR STAfl0NS $fAfl0N WITH HIGHEST MEAN CONTROL STATIONS eeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeee RADIONUCLIDES MEAN MEAN MEAN I (NO. ANALYSES) REQUIRED kANGE STA. RANGE RANGE i (NON* ROUTINE)* LLD NO. DETECTED ** N0. N0. DETECTED ** NO. DETECTED ** j AG 110N( 28) ( 3.9 a 6.4)E 5 11 ( 1.6 0.9)E 4 ( 3.2 11.1)E 5 ( 0) ( 5.3 - 5.2)E 4 ( 1.3 - 36.9)E 5 ( 6.5 - 4.6)E 4

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• NON ROUT!NE REFER $ TO THE NL848ER OF SEPARATE MEASUREMENTS WHICH WERE GREATER TNAN TEN (10) TIMES THE AVERAGE 8ACKGROUND FOR THE PERIOD OF THE REPORT.
  • THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVI Afl0NS) l$ INDICATED WITH *(

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I 3.2 Charcoal Filters I Charcoal filter cartridges are held in the air sampling filter head, downstream from the air particulate glass-fiber filters. Monitoring stations were located at a total of seven stations, five of which were required by the Technical Specifications. The l air pumps at these locations operate continuously at a flow rate l of approximately one cubic' foot per minute. Charcoal filters were collected and analyzed weekly for I-131. radioactivity. During 1989, no such radioactivity was detected. ll 1l L ru .1 i L w I L-F L, [ WPP12/25-f L

I ( ENVIRONMENTAL RADIOLOGICAL PROGRAM 9talMARY l TANKEE NUCLEAR POWER STAfl0N, R0WE, MA (JANUARY DECEMBER 1909) MEDIUM: CHARC0AL FILTER Units: PCl/CU. M INDICATOR $fAfl0NG STATION WITH NIGNE61 NEAN COhikOL $1A110NS ,I RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON kOUTINE)* LLD N0. DETECTED ** NO. NO. DETECTED ** WO. DETECTED ** 1 1 131 (371) .07 ( 1.3 5.3)E 4 21 ( 2.0 e 1.4)E 3 ( 3.5 9.7)E 4 ( 0) ( 2.7 - 2.7)E 2 ( 2.0 - 2.9)E 2 ( 2.2 - 2.9)E 2

• (

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.i. 3.3 tiilk [' Milk samples were collected and analyzed by the schedule shown in i Table 2.1. Strontium 89 and Sr-90 analyses were also performed on quarterly composite milk samples (not required by Technical Specifications). Detectable concentrations of Cs-137 and Sr-90 were measured in many milk samples submitted during 1989. The higher concentration in indicator station samples has been noted for many years. It has been shown in previous reports that the radioactivity in the cows' milk is a result of atmospheric. I nuclear weapons testing radionuclides that persist in the environment (Os-137 and Sr-90 in particular). Differences in farming practices (amount of vegetation and type of vegetation I that the cows are allowed to feed on).can cause significant variations in these radionuclides in milk. The levels of Os-137 detected at indicator stations during 1989 is consistent with that detected in previous years. Additional Cs-137 was introduced into the environment in mid-1986.fo11owing the Chernobyl accident. A slight rise in Cs-137 levels in milk can be seen for this period in Figure 3.2.- Naturally-occurring K-40 was also detected in all milk samples. I I I I 1 WPP12/25 i 1 1

ummF-e 1 T-t I T > U FIGURE 3.2 CESIUM-137 IN MILK YANKEE NUCLEAR POWER STATION, RCHE, MB 30.0 2e.o - 26.0- ' ~ D-TM-12, RERDSBOPO, VT O - Tr:-13, WHITIPGiRrt, VT 22.o-A - TM-21, WIll.IIYtSTOWN, t1R g 20.o-5g se.o-Y is.o - ~ <ng te.o-b 12.0-8 E' 10.0 - 4 e.o - Pr Wd % kin\\dI I gh ~" 5~M A tt J RSOND((MkMJ RSONDJEbHMJ RSONDY MAMJ RSOMb UMRMJ R S 0 k'D (__ - _ _ _ _ _ _ _ _ _ _ _

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0/ 19)* NON ROU11NE REFERS TO THE NUMBER OF $(PARAft MEASUREMEWi$ WHICH WERE GREATER THAN ttW (10) 11MES THE AVERAGE SACKGROUND FOR THE PERIOD OF THE REPORT. THE FRACil0N OF $ AMPLE ANALY$t$ fitLDING DEftCTABLE MEASUREMENTS (1.E. >3 STD DEVI A110NS) 18 INDICAf tD WITH *( )*. i

I (NVIRONMENTAL kAD10 LOGICAL PROGAnh SWN44RY I TANEtE NUCLiAt POWEt STAf10N, kOWE, MA (JANUAtY. DECENett 1989) htDIUM: MILK units: PCl/KG INDICATOR $1A110NB $1Afl0N WifM NIGHilf NEAN CONTROL $1Afl0N1 eenseeneneseese eneenessunneennen essenneenene I RADIONUCLIDE$ NEAN NEAN NLAN (NO. ANALTN 8) ht9UlktD kAu0t $1A. RANGE RANGE (NON

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3.4 Food crop / Broad Leaf Vegetation ~ Samples of swiss chard, lettuce, and tomatoes were collected at harvest time and were analyzed for gamma-emitting nuclides. Other than naturally occurring K-40 and Be-7, no radionuclides were detected in the samples. Three maple syrup samples were I also collected in 1989 and are discussed in Section 3.5. I I I I I I l I I I ' WPP12/25

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0/ 1)* 2N 65 ( 4) ( 3.5 a 124.0)E 1 11 ( 2.4 s 1.9)E 1 ( 1.0 a 1.6)t i I ( 0) (

• 1.7 -

2.4)E i

• (

0/ 3)*

• (

0/ iP

• (

0/ 1P 2R 95 ( 4) ( 2.2 s 9.0)E O 11 ( 1.5 1.5)E 1 ( 7.6 99.2)E.1 ( 0) (

• 1.6 -

1.5)E 1

• (

0/ 3)*

• (

0/ IP

• (

0/ 1)* AG 110h( 4) ( 1.2 2.6)E O 11 ( 4.9

• 11.0)E 0

( 1.5

• 7.2)E 0 I

( 0) ( +3.8

• 4.9)E O i
• (

0/ 3)*

• ( 0/ 1)*
• ( 0/ 1)*

1 NON ROVilNE Riftts TO THE NUM4tR OF SEPARAtt MEASUREMENTS WHICH WEtt GREATER THAN TEN (10) flMES THE AVERAGE BACKGROUND 70R THE PERIOD OF THE REPORT. THE FRACTION Of S W Lt ANALY$tt YlELDING OtitCTABLE MEASUREMENTS I (1.E. 3 $fD DEVI Afl0NS) IS INDICAf tD Wi1H *( )*. 1 =

ENVIRONMENTAL RADIOLOGICAL PROGRAM SLReuRY YANKit WUCLEAR POWER $1Afl0N, R0WE, MA I (JANUARY DICLMetR 1999) f MI*)lL81: 7000 CRDP UN1188 PCl/KG WET I INDICATOR STAfl0NS STA110N WitM NIGN($f MEAN CONTROL $1Atl0NS esseeeeeeeeeeeeees neesseeeeeeeeeeeeeeeeeee seeeeeeeeeeeeeee I RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYtt$) REQUIRED RAN0t STA. RANGE RANot (NON kOUTINt)* LLD MO. DtitCitD" WO. No. DtitCitD** Wo. DtittitD** RU 103 ( 4) ( +4.8 0.3)E 0 13 ( 4.2 s 4.1)E O ( 9.4 : ' 6.9)E 0 ( 0) ( +5.2

• 4.2)t 0
• ( 0/ 3)*
• (

0/ 1)*

• (

0/ 1)* I RU 106 ( 4) ( 1.3 1.6)t 1 21 ( 9.5 5.5)t 1 ( 9.5 5.5)E 1 ( 0) ( 1.2 4.3)E 1 1

• ( 0/ 3)*
• (

0/ 1)*

• (

0/ 1)* l 131 ( 5) ( 8.6 a 11.0)t 0 13 ( i.5 a 1.5)t 1 ( 2.3 a 11.1)E O ( 0) ( 3.8 + 1.5)E 1

• (

0/ 4)*

• (

0/ 1)*

• (

0/ 1)* C$.134 ( 4) 60. ( ~ 7.0 4.1)E O 13 (

• 1.0 s 3.6)E 0

( 1.9 6.8)E O t 0) ( 1.5 -

• 0.1)t 1
• (

0/ 3)*

• (

0/ 1)*

• (

0/ 1)* CS 137 ( 4) 80. ( 2.2 e 3.4)E O 31 ( 7.5 a 7.6)E O ( 1.6 5.9)E O ( 0) ( 4.1 - 7.5)E D I

• ( 0/ 3)*
• (

0/ 1)*

• ( 0/ 1)*

SA*140 ( 4) ( 7.3 a 32.0)E 1 31 ( 2.7 a 17.2)E O (

• 1.1 e 1.1)E 1 I

( 0) ( 7.1 + 2.7)E 0

• (

0/ 3)*

• (

0/ 1)*

• (

0/ 1)* CE 141 ( 4) ( 6.0 a 4.8)E D 11 ( 1.2 a 1.0)E 1 ( 6.9 8.5)E D I ( 0) ( 3.5 - 12.2)E O

• (

0/ 3)*

• ( 0/ 1)*
• (

0/ 1)* CE*144 ( 4) ( 6.6 e 15.4)E 0 31 ( 3.7 3.9)E 1 ( 1.0 a 30.9)E 0 -I ( 0) ( 1.1 + 3.7)t 1 l

• (

0/ 3)*

• ( 0/ 1)*
• (

0/ 1)* TH 232 ( 4) ( 1.8 e 1.$)E 1 13 ( 4.7 g 1.4)E 1 ( g,9 g 3,2)g j I ( 0) ( 3.0

• 467.0)E 1
• ( 0/ 3)*
• (

0/ 1)*

• ( 0/ 1)*

NON RoutlNE Rif tRs TO THE WLasett OF StPARATE MEA $UREMEN18 WHICH WERE GREATER TRAN TEN (10) flMES THE AVERAGE BACKGROUND FOR THE PERIOD Of THE REPORT. 1HE FRACTION OF $ AMPLE ANALY$t$ YttLDING DtitCTABLE MEASUREMENTS (1.E. >3 STD DEVI Afl0NS) 18 INDICAf t0 WITH *( )*. i

'I ) 3.5 Maple Svrup .I Maple syrup grab samples.(not required by Technical Specifications) were collected during April at two indicator and one control location. In addition to naturally occurring K-40 Cs-137 was detected in each sample. Attributed to nuclear I weapons testing fallout, this Os-137 has been detected in most samples since collection was started in 1972. The control station in 1989 had a higher Cs-137 level than detected at either of the indicator stations. I I I I I 1I l L , WPP12/25 g

I i (NVIRONMENTAL R O10 LOGICAL PROGRAN SL8NERY I YANKit WUCLEAR POWit $1Afl0N, ROWE, MA l (JANUARY. DECtMN R 1909) NEDIUN: NAPLE $YRUP UNIT 8: PCl/KG INDICATOR STAfl0NS $f Afl0W WITN HIGNE$1 NEAN CONTROL $1Atl0NS RADIONUCLIDtl NEAN MEAN MEAN (NO. ANALYtt$) At0VIRED kAmet $1A. RANot RANGE (NON*RDullWE)* LLD NO. DtitCitD** NO. NO. DtitCTED** Wo. DtitCTED** SE*7 ( 3) ( 8.9 e 15.3)t 0 33 ( 2.4 e 1.1)t 1 ( 4.6 4.5)E O ( 0) ( 6.4 + 24.2)E O

• ( 0/ 2)*
• (

0/ 1)*

• (

0/ 1)* K 40 ( 3) ( 1.6 a 0.1)E 3 46 ( 1.6 0.1)E 3 ( 1.0 a 0.0)E 3 ( 0) ( 1.5 + 1.6)t 3

• (

2/ 2)*

• (

1/ 1)*

• (

1/ 1)* MW 54 ( 3) ( 7.9 s 15.1)E 1 46 ( 2.3 t 1.3)t 0 ( 6.5 56.1)E 2 ( 0) ( 7.1 + 23.0)E *1

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)* Co 58 ( 3) ( 1.4 s 0.4)E *1 33 ( +9.0 e 159.0)E 2 ( +3.0 t 6.3)E 1 ( 0) ( 1.8 0.9)E *1

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)* FE'59 ( 3) ( 3.6 19.6)E 1 46 ( 1.6 a 2.9)E D ( 2.0 a 1.3)E o ( 0) (

• 2.3 +

1.6)E D

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)* Co 60 ( 3) (

• 2.7 s 0.5)E 0 44 (

6.2

• 8.9)E *1

( 6.2 8.9)E 1 ( 0) ( +3.2 * +2.2)E O 1

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)* ZN'65 ( 3) ( 9.0 s 2.0)E *1 44 ( 1.6 a 1.6)E O ( 1.6 a 1.6)E D s ( 0) ( 1.1 0.7)E O

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)* 2R 95 ( 3) (

• 1.7 a 10.7)E *1 46 (

9.0 s 22.4)E 1 ( 3.5 a 110.0)E 2 ( 0) ( 1.2 0.9)E O

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)* AG 110M( 3) ( 1.0 e 2.6)E 1 44 ( 4.8 s 7.9)E.1 ( 4.8 a 7.9)E.1 ( 0) ( 1,6 - 3.6)E 1 i

• (

0/ 2)*

• ( 0/ 1)*
• (

0/ 1)* l NON. ROUTINE refit $ TO INE NL948tR OF $EPARATE MEASUREMENT $ WHICH Wttt GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND IOR THE PERIOD OF THE REPORT. L THE FRACTION OF SAMPLE ANALY$tt YlELDlWG DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIAfl0NS) l$ INDICATED WlfH *( )*. L .i ;

ECVIRONMtWTAL RADIOLOGICAL PROGRAM SulmARY Y MKEE NUCLEAR POWER $1A110N, RUWE, MA I (JANUARY

• DICENDER 1989) l MEDIUM MAPLt SYRUP UNitti PC1/KG INDICAf0R STAfl0N$

$1Afl0N WifH NIGNill NEAN CONTROL $1Afl0N$ I kAD10NUCL1DE$ MtAN NEAN MEAN (NO. ANALYtt$) Rt0Vitt0 kANGE STA. RANGE RANGE (NON*kOUTINE)* LLD WO. DtitCitD** N0. No. DtfECTED" No. DtitCTED" RU 103 ( 3) ( 4.2 s 14.$)E *1 46 ( 1.9 a 1.2)E D ( +2.6 6.1)E *1 ( 0) (

• 1.0
• 1.9)E D
• (

0/ 2P -

• (

0/ IP

• (

0/ 1)* RU 106 ( 3) ( +8.0 4.6)E 0 44 ( 1.0 46.9)E *1 ( 1.0 46.9)t 1 ( 0) (

• 1.3 -
• 0.3)E 1 1
• (

0/ 2P

• (

0/ 1P

• (

0/ 1)* l'i31 ( 3) ( 1.9 a 28.7)E *1 33 ( 3.0 4.0)t 0 (

• 2.7 a 10.1)E *1

( 0) (

• 2.7 -

3.1)t 0 1

• ( 0/ 2)*
• (

0/ 1P

• (

0/ 1)* C5 134 ( 3) ( +2.6 s 0.4)E 0 44 ( 3.1 5.4)E *1 ( 3.1 a 5.4)t +1 ( 0) ( 3.0 -

• 2.3 )E 0
• (

0/ 2)*

• (

0/ 1)*

• (

0/ IP CS 137 ( 3) ( 1.6 0.8)t 1 44 ( 3.0 s 0.1)E 1 ( 3.0 s 0.1)E i ( 0) ( 8.6 - 24.5)E O

• (

2/ 2)*

• (

1/ 1p

• (

1/ 1)* BA 140 ( 3) ( 1.2 a 1.6)E O 33 ( 2.8 s 2.7)E O ( 6.7 a 8.7)E *1 ( 0) ( 3.1 - 28.2)E *1 1

• (

0/ 2P

• (

0/ iP

• (

0/ 1)* CE*141 ( 3) (

• 1.2 s 2.9)E *1 44

( 8.9 s 10.6)E *1 ( 8.9 s 10.6)E *1 .I ( 0) ( 4.2 - 1.7)E.1

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)* CE 144 ( 3) (

• 4.5 a 8.3)E O 33

( 3.8 e 9.3)E O ( +4.7 4.1)E O I ( 0) (

• 1.3 -

0.4)E 1

• (

0/ 2)*

• (

0/ iP

• (

0/ iP i TM 232 ( 3) ( 6.6 4.3)E O 33 ( 1.1 0.7)E 1 ( 1.7 a 2.7)E O I ( 0) ( 2.2 - 10.9)E 0

• (

0/ 2P

• (

0/ 1P

• (

0/ 1)* NON ROUTINE kEFERS TO THE NUM8tt OF $EPARATE MEASUREMEWil WHICH WERE GREATER THAN TEN (10) flMES THE AVERAGE BACKGROUND FOR THE PEkl0D Of THE REPORT. THE FRACfl0N OF SAMPLE ANALYSES YttLDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIAi!0NS) is INDICAftD WITH *( )*. j l _.. --_______________a

I 3.6 Groundwater I Groundwater grab samples were collected from_two indicator stations on a monthly basis. (Technical Specifications require a quarterly collection.) Each of these samples was analyzed for I gross-beta, H-3, and gamma-emitting radionuclides. Tritium (H-3) was detected in all of the Station WG-12 samples and none of those from Station WG-11. Since the water from WG-12 (Sherman Spring) is not used for drinking water, and since the Deerfield River into which it empties is also not used for drinking, there would be no impact on man from the ' low levels detected. In any case, the calculated critical organ (total body) dose to an average child who is assumed to ingest

l 260 kilograms per year of this water (undiluted) at the average m

1989 concentration of 740 pCi/ kilogram, would be approximately l 0.04 mrem, using USNRC Regulatory Guide 1.109 methodology (Reference 1). The maximum monthly concentration of 940 pCi/kg-l in May of 1989 did not exceed the 30,000 pCi/kg reporting level for H-3 in water. The annual mean H-3 concentration has l decreased steadily for most of the past ten years, as shown in previous Radiological Environmental Monitoring Reports. I Gross-beta radioactivity was detected in all groundwater samples. Caused primarily by naturally occurring radionuclides L in groundwater, the gross-beta levels were similar to those of the past several years (see Figure 3.3). For a three-month I period, the gross-beta level at Station WG-12 was slightly-elevated. There is no explanation for this.. It should be noted though, that no gamma-emitting radionuclides were detected in the samples, and the H-3 levels do not parallel the gross-beta ones. A temporary elevation in naturally-occurring radionuclides is the most likely explanation. No gamma-emitting radionuclides were detected in the groundwater samples. WPP12/25 i

W W'M i ) W FIGURE 3.3 GROSS BETA MERSUREMEfJTS OF GROUtJD WRTER YRilKEE TJUCLERR POWER STRTI0tl, ROWE, MR 10.0 9.0 - D-HG-11, PLPfiT POTROLE O - WG-12, SHERmti SPRIPS - 7.0 - O 6.0 - g i' E ) s.0 - g o e u x Q 4.0 - 6 i o 3 8~ U 3 2.0 1.0 -- 0.0 1985 1986 1987 1988 1989

ENVIRONMENTAL RADIOLOGICAL PROGAAM

SUMMARY

+ TANKEE NUCLtAR POWER STATION, R0WE, MA (JANUARY DECEMBER 1989) MEDIUM: GROUND WATER UNITS: PCl/KG INDICATOR STAtl0NS STAfl0N WITM MIGNEST MEAN CONTROL STAtl0NS ... **ee........ I kAD10NUCLIDE5 MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)* LLD N0. DETECTED ** NO. NO. DETECTED ** WO. DETECTED ** OR.B ( 24) 4 ( 3.6 s 0.2)E 0 11 ( 3.7 a 0.1)E 0 N0 DATA ( 0) ( 1.8 - 6.1)t 0 ( 3.0 - 4.2)E 0

• ( 24/ 24)*
• ( 12/ 12)*

1 K 40 ( 24) ( 4.9 a 24.9)E 1 11 -( 1.5 e 3.6)E 0 No DATA ( 0) ( 2.2 - 2.2)E 1 ( 1.9

• 2.2)E 1
• (

0/ 24)*

• (

0/ 12)*- MW 54 ( 24) 15. ( 1.6 3 1.8)E.1 11 ( 7.7 3 24.4)! *2 NO DATA ( 0) ( 1.7 - 1.7)E O (

• 1.7 -

1.2)E 0

• (

0/ 14)*

• (

0/ 12)* Co 58 ( 24) 15. ( 8.0 s 2.2)E 1 12 ( +3.8 a 3.3)E *1 NO DATA ( 0) ( 3.2 - 1.5)E 0 ( 2.5 + 1.5)E O

• (

0/ 24)*

• (

0/ 12)* FE 59 ( 24) 30. ( 5.5 a 4.3)E 1 11 ( 5.5 a 7.3)E *1 NO DATA g ( 0) ( 5.6 - 3.1)E O ( 5.6 - 3.1)E O

• (

0/ 24)*

• (

0/ 12)* Co 60 ( 24) 15. ( 1.7 a 2.0)E 1 12 ( 2.8 s 2.4)E *1 NO DATA ( 0) ( 2.2 - 1.7)E D ( 1.2 - 1.7)E O I

• (

0/ 24)*

• (

0/ 12)* j 2N 65 ( 24) 30. ( 6.0 s 3.2)E *1 11 ( 6.1 8 4.8)E 1 NO DATA 1 ( 0) ( 2.0 - 3.5)E O ( 1.6 - 3.5)E 0

• (

0/ 24)*

• (

0/ 12)* 2R 95 ( 24) 15. ( 1.6

• 2.8)E 1 12 (

2.7 3.9)E.1 No DATA I ( 0) ( 2.5 - 1.4)E O ( 2.5 - 1.4)E 0

• (

0/ 24)*

• (

0/ 12)* ) AG 110M( 24) ( 2.7 a 3.1)E 1 12 ( 2.7 4.7)E 1 NO DATA I ( 0) ( 2.7 - 3.2)E 0 ( 1.7

• 3.2)E 0
• (

0/ 24)*

• (

0/ 12)* NON.kOUTlWE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER TRAN TEN (10) TIMES THE AVERAGE SACKGROUND FOR THE PERIOD OF THE REPORT. THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (I.E. >3 STD DEVIAfl0NS) IS INDICATED WITH *( )*. l l i l

.._~ _._ _ _- I t I ENVIRONMENTAL kAD10 LOGICAL PROGRAM SUMM&tY l TAWKEE NUCLEAR PChdER STATION, kOWE, MA I (JANUARY

• DECEMBit 1999) i MEDIUMt OROUND WAftR UNITS PCI/KG INDICATOR STAfl0NS

$TATION WITH NIGNE$T MEAN CONTROL $1Afl0NS e RADIONUCLIDE$ MEAN MtAN MEAN (NO. ANALYS($) R(0UIRED RANGE $fA. RANGE RANGE t (NON ROUTINE)* LLD NO. DtitCTED** N0. No. DtitCTED** WO. DETECTED ** l I RU 103 ( 24) ( 3.9 e 1.8)E *1 11 ( +8.8 s 26.4)E +2 No DATA ( 0) ( 2.2 1.2)E D (

• 1. 6
• 1.2)E O r
• (

0/ 24)*

• (

0/ 12)* RU 106 ( 24) ( 2.8 e 1.6)E D 12 ( +2.3 s 2.9)E O No DATA ( 0) ( 2.3 - 1.4)E 1 ( 2.3 - 1.4)E 1

• (

0/ 24)*

• (

0/ 12)* l 131 ( 24) 1. ( 4.7 : 4.6)t +1 12 ( 1.0 s 0.6)E O NO DATA ( 0) ( +3.8 - 6.2)E 0 ( +1.9 + 6.2)E 0

• (

0/ 24)*

• (

0/ 12)* C$a134 ( 24) 15. ( +7.0 a 23.8)E 2 11 ( 5.3 3.2)t 1 NO DATA ( 0) ( 1.8 - 2.4)E O ( +1.3 - 2.4)E O

• (

0/ 24)*

• (

0/ 12)* C$*137 ( 24) 18. ( 2.6 e 2.2)E 1 12 ( 2.1 a 2.0)E *1 NO DATA ( 0) ( 2.9 - 1.4)E 0 ( +1.2 - 1.4)t- 0

• (

0/ 24)*

• (

0/ 12)* BA 140 ( 24) 15. ( 1.6 a 39.0)t 2 11 ( 4.0 a 6.5)E *1 NO DATA ( 0) ( +3.5 - 3.3)E D ( 3.5 + 3.3)E O

• (

0/ 24)*

• (

0/ 12)* F i i CE 141 ( 24) ( 2.2 s 3.3)E *1 11 ( 2.7 5.5)E *1 NO DATA ( 0) ( 3.7 - 3.1)E D ( 3.7 - 3.1)E O

• (

0/ 24)*

• (

0/ 12)* FU CE*144 ( 24) ( +7.4 a 16.9)E 1 12 ( 3.5 a 18.5)E *1 No DATA ( 0) ( 1.6 - 1.6)E 1 (

• 1. 0 +

1.2)E 1

• (

0/ 24)*

• (

0/ 12)* g N3 ( 24) 2000. ( 3.3 0.9)E 2 it ( 7.4 a 0.4)E 2 NO DATA ( 11) ( +2.5 - 9.4)E 2 ( 4.6 - 9.4)E 2 7

• ( 11/ 24)*
• ( 11/ 12)*
• NON ROUTINE REFER $ TO THE NtateER OF $tPARATE MEASUREMENTS WHICN WERE GREATER TNAN TEN (10) TIMES ThE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.
  • THE FRACTION OF $ AMPLE ANALY$tt YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIAfl0NS) l$ INDICATED WITH *(

)*. -as-

3.7 Rirer_ Water Coniposite samplers were used at the two required sampling ~ locations and samples from each of these were collected monthly and analyzed for gross-beta and gamma-emitting radionuclides. Quarterly composites were analyzed for.H-3. The third quarter composite sample showed a detectable level of H-3 at Station WR-11 (Bear $wamp Lower Reservoir). Since the Deerfield River is not used for drinking water, the low levels of H-3 found will have no impact on man. If one was to calculate, however, the critical organ (total body) dose to an average child I who consumed his entire yearly intake of water (260 kilograms per year) from the Deerfield River.at the above sampling location, with the average concentration of 370 pCi/ kilogram over the I entire year, the dose would be approximately 0.02 mrem per year, using USNRC Regulatory Guide 1.109 methodology (Reference 1). The maximum quarterly concentration of 1,070 1270 pCi/ kilogram during the third quarter of 1989 did not exceed the,30,000 pCi/ kilogram reporting level for H-3 in water. Gross-beta radioactivity, primarily from naturally occurring radionuclides in river water, was detected in most samples. The mean and range were similar to those measured in previous years. The control and indicator station mean concentrations were again approximately equal in 1989. No gamma-emitting radionuclides were detected in the 1989 river water samples. I i 1 i 3,. WPP12/25 I I l l

I l ENVikONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

TAWKEt NUCLEAR POWER $1Afl0N, ROWE, MA (JANUARY

• DECCMBEk 1989) l NEDIUM: RIVER WATER UNIft: PCl/KG I

INDICATOR stall 0NS $fAfl0N WITH NIGNtti MEAN CONTROL STAfl0NS eeeeeeeeeeeeeeeeee ....eeeeeeeeeeeeeeeeeeeee RADIONUCLIDES MEAN NEAN MEAN (NO. ANALYttl) RIOVikED RANGE $1A. RANQt RANGE (WON ROVilWE)* LLD NO. DtitCitD** No. No. DtitCitD** No. OtttCTED** OR $ ( 36) 4 ( 2.0 a 0.2)E O 21 ( 2.1 s 0.2)E 0 ( 2.1 a 0.2)E O l' ( 0) ( 9.7 - 53.7)E *1 ( 1.3

• 3.3)E O

( 1.3 + 3.3)E O

• ( 22/ 24)*
• ( 12/ 12)*
• ( 12/ 12)*

K+40 ( 36) ( 0.3 a 22.1)E 1 31 (

• 1.3 a 26.4)E 1

( +7.5 a 30.4)E 1 ( 0) ( 2.4

• 2.4)t 1

( 1.1 - 1.8)E i (

• 1.3 -

2.4)E 1

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* MN 54 ( 36) 15. ( 1.3 e 2.1)E *1 21 ( 3.5 s 2.9)E 1 ( 3.5 a 2.9)t 1 ( 0) (

• 2.2 -

2.0)E D ( 1.7 - 1.9)E 0 (

• 1.7 -

1.9)E O

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* CO 58 ( 36) 15. (

• $.9 a 16.7)E 2 21

( 1.1 1.6)E *1 ( 1.1 1.6)(.1 l ( 0) ( 1.7 - 1.2)E O ( 1.2 - 0.7)E 0 (

• 1.2 -

0.7)E 0

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* FE 59 ( 36) 30. ( 2.8 e 2.9)E *1 31 ( 5.9 a 4.7)E *1 ( 4.2 s 61.8)E 2 ( 0) (

• 1.7
• 3.5)E 0

(

• 1. 7
• 3.5)E O

( 2.7 - 3.4)E O I

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* Co 60 ( 36) 15. ( 5.3 1.7)E *1 11 ( 4.4 e 2.4)E *1 ( 8.6 s 4.4)E 1 ( 0) (

• 1.8
• 0.9)E O

( 1.6 - 0.6)E O ( +3.5

• 2.7)E 0 I
• (

0/ 24)*

• (

0/ 12)* '( 0/ 12)* 2N 65 ( 36) 30. ( 9.7 3.7)E 1 11 ( 9.0 s 5.3)E *1 ( 9.9 5.2)E *1 I ( 0) ( 4.7 - 2.5)E D ( 4.7 - 1.8)E O ( 5.5 - 1.4)E O

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* i 2R 95 ( 36) 15. ( 1.2 e 3.2)E 1 11 ( 2.4 a 3.9)E 1 ( 7.5 a 354.1)E 3 I ( 0) ( 2.7

• 3.5)t 0

( 1.2 - 3.5)E O (

• 1.3 -

1.9)E 0

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* AG 110N( 36) ( 4.8 e 2.4)E *1 21 ( 2.3 a 2.7)E.1 ( 2.3 s 2.7)E *1 I ( 0) ( 2.7 - 2.0)E 0 ( 1.9 - 1.5)E O (

• 1.9 -

1.5)E 0

• (

0/ 24)*

• (

0/ 12)*

• (- 0/ 12)*

WON ROUTINE REFER $ 10 THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREAftR THAN ftW (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT. THE FRACTION of $ AMPLE ANALYtt$ YttLDING OtitCTABLE MEASUREMENis (I.E. >3 stD DEVIAll0NS) 18 INDICATED WifH *( )*. _

I l ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMMART TAEKEE NUCLEAR POWER STAfl0W, kOWE, MA I (JANUART

• DECEMBER 1989)

MEDIUN k!VER WATER UNIT $1 PC1/KG I INDICATOR $1Afl0NS $1Afl0N WITH HIGNElf MEAN CONTROL STATIONS eeeeeeeeeeeee..... e....eeeeeeeeeeeeeee..... eeeeeeeeeeeeeee. I RADIONUCLIDES hEAN MEAN MEAN (NO. ANALTSES) REQUlkED RANGE STA. kANGE RANGE (NON ROUTINE)* LLD

80. DETECTED **

NO. NO. DETECTED ** WO. DETECTED ** RU 103 ( 36) ( +3.3 e 1.9)E *1 31 ( 4.3 e 26.2)E 2 (

• 1.7 a 3.5)E *1

( 0) ( 2.0 - 1.7)t 0 ( 1.6 - 1.7)E 0 ( +1.5 - 2.5)E O

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* I RU 106 ( 36) ( 1.9 a 1.6)E O 21 ( 4.7 a 256.6)E 2 ( 4.7 a 256.6)E 2 ( 0) ( 1.3 - 1.4)E 1 (

• 1.5 -

1.1)E 1 (

• 1.5 -

1.1)E 1

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* l 131 ( 36) ( 3.0 t 6.7)E.1 31 ( 7.8 s 6.3)E 1 ( +7.0 a 9.7)E 1 ( 0) ( 1.1 0.5)E 1 ( 5.0 - 3.3)E D ( +5.5 - 6.4)E O

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* CS 134 ( 36) 15. ( 8,5 a 1.4)E 1 21 ( 5.7 s 2.4)E 1 ( 5.7 a 2.4)E.1 ( 0) ( 2.1 0.6)E O ( 2.0 - 0.8)E 0 ( +2.0 - 0.8)E o

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* CS 137 ( 36) 18. ( 5.2 18.4)E 2 11 ( 3.6 s 2.3)E 1 ( 3.0 a 1.6)E 1 ( 0) ( .t.7 1.7)E D ( 8.6 - 16.7)E 1 ( 6.1 - 12.8)E.1 I

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* BA 140 ( 36) 15. ( 4.0 a 44.0)E 2 31 ( 1.5 s 5.9)E 1 ( 6.3 4 5.5)E 1 I ( 0) ( 5.1

• 3.5)E O

( 3.7 - 3.5)E D ( +3.6 - 2.4)E O

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* CE 141 ( 36) ( 3.6 34.5)E 2 31 ( 2.6 4.8)E *1 ( 6.1 2 63.0)E 2 I ( 0) ( 2.8 - 2.7)E O ( 2.1 - 2.6)E O ( + 4.7 + 3.5)E 0

• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* CE.144 ( 36) ( 7.4 11.3)E *1 21 ( 3.7 e 11.8)E 1 ( 3.7 a 11.8)E 1 ( 0) (

• 1.5 -

0.6)E 1 ( 6.8 - 7.6)E O ( +6.8

• 7.6)E 0 B
• (

0/ 24)*

• (

0/ 12)*

• (

0/ 12)* H3 ( 12) 2000. ( 2.4 e 1.3}E 2 11 ( 3,7 1 2.4)E 2 ( +4.7 s 6.2)E 1 I ( 1) ( 9.2 - 107.0)E 1 ( 4.4 - 107.0)E 1 ( 2.3 - 0.3)E 2

• (

1/ 8)*

• (

1/ 4)*

• (

0/ 4)* NON ROUTINE REFERS TO THE NUMBER Of SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE SACKGROUND FOR THE PERl(D OF THE REPORT. THE FRACTION OF SAMPLE ANALTSES TIELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) is INDICATED WITH *( )*.. _. _.. _ _.,.. _ _

l E 3.8 Sediment l ~I Sediment cores were collected semiannually from two locations j (SE-11 and SE-21). Each core was separated into three 5 cm { segments, which were analyzed for gamma-omitting radionuclides. l Cesium-137 was detected in most samples. The levels measured at I-the indicator location were consistent with what has been measured in the previous several years (see Figure 3.4) and are f attributed to nuclear weapons testing fallout that has persisted in the environment. I i The data tables show results for 21 additional samples that were. collected from Sherman Pond in May and October of 1989. They f I-were collected-from three shoreline locations and three deep t water locations (SE-91 through SE-96).- In addition to naturally occurring K-40 and Th-232, the samples showed detectable levels 5 of Co-60 and Os-137. All samples'with Co-60, and all those with Cs-137 levels higher than anticipated from residual weapons l testing fallout were taken in deep water, well away from the i shoreline (maximum concentration of-202 127 pCi/ kilogram Co-60 f and 3,290 50 pCi/ kilogram Cs-137, both near the plant discharge). None of.this plant-related radioactivity'is involved i in any pathway of exposure to man. Specifically, none has been. detected in water, fish, or on the shoreline (with the exception of expected Cs-137 from weapons testing fallout'in fish and i sediment), thereby ruling out dose from direct exposure, fish or water consumption, and recreational activities on Sherman Fond. 4 a Other than naturally occurring K-40 Th-232. Be-7, and the above nuclides, no gamma-emitting radionuclides were detected in 1989 sediment samples. l I WPP12/25 l I; 1

ug rua ru q E g-gz 1 37 g g 3'Wgge e g .+- 6 FIGURE 3.4 CESIUM-137-IN-SEDIMENT YRNKEE NUCLERR POWER STRTION,'ROWE, MR .3000 [ i ~ 2700-1 ' i O - St.-iN N0i 4 STF1., b 5 CM ~~ ..o - SE-il NO. 4 STi?., '5-10 f41 ' ~ amo- ~' ~' 7' % A - SE-11 NO. 4 isTfl.,10-15 CH w + - SE-21 Hf1RRIMfWFRES., 0-5 CM N s '~ g 2 00-X - SE-21; iiaRRIMRN RES., 5-10 CH -W a 0 - SE.-21 HRRRIMRN RES., 10-15 CM j, ~u E 800-1 l~ ^,: ~ ~ Eg 'i c 1~ - o ea ,._J, .._m. ~~. : ? - x ~1$30-4 a N ,.g ~ v- ^ ' / '?;- [ ^ .f ~ - 1E ) a -:. -- ,qt og o c - - ln -7,. +__~.,n -") Ng 7 ~x ;-

,v ~

~ \\ py

rg-a.

/ -- m.. - ll ~_ f w

,m ;-_..

y - O o <~' t -J \\ -.y.' __ y ,< 1 m y . ~, _ = 300-3 f

)

x. c' 1._ .o ,,,-,,..-,,.,.~,,,,,,,,s .. ~. ,.......-,,,,,m .~ g ' 4 J r H A N J J R S O N D J r M M M J J R S O N U J T M R M J J P..S D N VJ F M R H J J R S O N D J F M R H J J A S O N D i-f -. 19 4 1986 1987' IS!!!S ' 1999 '7 g m ~, _ ~ ~ )T ~-. a,_ g-^ v.g:'" % ' [ " ~ _ j.A. j ~2 q:- .+. s + S #' -y ~u ? ~ ,n. r <y ','s

y y

.T.- e j ' ' ~ y ]M.. ~ U._ ^ , ;1.. ,5 ~.. - _______.,m_.__.a.,,,_____. ~.

?)/ O i n. ENVIRONMENTAL RADIOLOGICAL PROGRAM SLMIARY H YANKEE NUCLEAR POWER STATION, R0WEi MA. ] (JANUARY

• DECEMBER 1989)

' MEDIUNr $fDINENT UNITS: PCI/KG DRY I IN0lCATOR STATIONS-STAfl0N WITH MIGHEST MEAN CONTROL STAfl0NS eeeeeeeeeeeeeeeeee eeeeeeee**eeeeeeeeeeeeeee eeeeeeeeeeeeeeee l d T RADIONUCLIDES MEAN MEAN MEAN r (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE h (NON ROUTINE)* LLD NO. DETECTED **' No. No. DETECTED" No. DETECTEE** ( e j BE 7 ( 33) -t ' 3.8 4.0)E 11 11 ( 2.1 1.2)E ' ( e.1 e. 3.6)E I 2 ( 0) l' '( 3.4 - 5.9)E 2 ( +2.1

• 59.3)E' 1

(

• ).F-21.1)E.1

'I ~ O

• (

2/ 27)*

• (

2/ 6)* 4 1/ 6)* s K 40 - ( 33) ( 1.9 0.1)E 4 93 ( 2.4 s 0.1)E 4 ( 1.6 0.1)E 4 ( 0) ( 1.0 - 2.7)E 4 ( 1.0 - R.5)E 4-( 1.0 - 2.0)E 4 3'

• ( 27/ 27)*
• ( 3/ 3)*

- *( 6/. 6)* MN 54 f 33i' ( +9.1 s 2.0)E- 0 96 ( 4.4 1 48.5)E *1 ( 2.5 a 2.8)E 0 i ( 0) ( 3.0 - 1.1)E i ( +7.5

• 9.2)E 0

(

• 1.1 -

0.4)E 1. 7

• (

0/ 27)*

• (

0/ 3)*

• (

0/ 6)* C0 58 ( 33) (

• 1.2 s 0.3)E 1 94

(

• 3.9 5.6)E O

( 7.4 4.0)E O ( 0) ( 4.1 + 1.0)E 1 (

• 1.5 -

0.3)E 1 ( 2.'2 - 0.4)E - 1

• (

0/ 27)*

• (

0/ 3)*

• (

0/ 6)* I FE 59 ( 33) (

• 1.0 0.7)E -1 21

( 1.5 0.9)E 1 ( .1.5

• 0.9)E 1

( 0) ( 8.8 - 6.4)E 1 ( 9.8 - 47.5)E O ( +9.8 - 47.5)E O

• (

0/ 27)*

• (

0/ 6)*

• (

0/ 6)* CO 60 ( 33) ? -( 3.7

• 1.2)E 1 91

( 1.4 a 0.2)E 2 '( 2.2 : '6.4)E O I_ ( 7) .( 1.1

• 20.2)E 1

(- 7.1

• 20.2)E 1

( 2.7 - 2.2)E 1.

• (

7/ 27)*

• (

6/ 6)*

• (

0/ 6)* ZN 65- ( 33) \\ ( 1.0 s 0.6)E-1 92 ( 2.6

• 2.9)E 1

( 5.8 s 12.4)E O 'I ( 0) ( 5.8 - 8.4)E 1 ( 2.3 - 7.7)E 1 ( 4.6 - 4.3)E 1

• (

0/ 27)* -*( 0/ 3)*

• (

0/ 6)* 'ZR 95 -( 33) ( 1.9

• 0.6)E 1 93

-( 5.4 1 0.9)E 1 ( 1.2

• 0.6)E 1 I'

( 0) ( +4.0 - 11.0)E 1 ( 4.4 - 7.2)E 1 ( +3.9 + 31.9)E' 0

• (

0/ 27)*

• (

0/ 3)*

• (

0/ 6)* AC 110M( 33) ( 5.4 s 3.0)E 0 21 ( 4.4 1 3.0)E O ( 4.4 3.0)E D I ( 0) ( 3.5 - 3.5)E 1 ( 2.8 - 16.2)E- 0' ( 2.8 - 16.2)E O' H

• (

0/ 27)*

• (

0/, 6)*

• (

0/ 6)* iL-NON ROUTINE REFERS To THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN' 3 (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT. THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >3 GTO DEV!Afl0NS) IS INDICATED WITH *( )*.

• h w-y L.

I I. Y

( l e

1 a ((. yl = ~ -.

ENVIRONMENTAL RAD 10 LOGICAL PROGRAM tule4 ART YANKEE NUCLEAR POWER STAfl0N, ROWE, MA (JANUARY DECEMBER 1999) MEDIUM: SEDIMENT UNITS: PCl/KG DRY r INDICATOR STAfl0NS STATION WITH HIGNEST MEAN CONTROL STAfl0NS' { e................ eeeeeeeeeeeeeeeeeeeeeeeee RADIONUCLIDES MEAN MEAN MEAN ~ (No. ANALYSES) REQUIRED RANGE STA. RANGE RANGE-(NON ROUTINE)* LLD Wo. DETECTED ** No. No. DETECTED ** No. DETECTED ** RU 103 (-33) ( 2.8 a 32.0)E *1 93 ( 1.8 & .1.6)E 1 -( 5.3 4.3)E O' l ( 0) ( 3.6 - 5.1)E 1-( 5.3 - 510.0)E 1 ( 6.8 - 19.9)E O l

• (

0/ 27)*

• (

0/ 3)*

• (

0/ 6)* '= RU 106 ( 33) ( 8.3 e 15.5)E O 96 ( 6.1 s 2.8)E 1 ( 9.5

• 25.0)E 0

( 0) ( 2.2 - 1.7)E 2 ( 2.6 - 11.5)E 1 ( 7.5 - 8.5)E 1

• (

0/ 27)*

• (

0/- 3)*

• (

0/ 6)* l 131 ( 33) ( 2.5 s 2.3)E 1 96 ( 8.1 a 2.9)E 1 ( 1.5

• 60.4)E 1

.3 ( 0) ( 3.9 - 1.6)E 2 ( 4.2

• 13.8)E 1

( 2.8 - 1.2)E 1 ~

• (

0/ 27)*

• (

0/ 3)*

• (

0/ 6)* { CS 134 ( 33) 150. ( 1.2 e 2.5)E O 95 ( ).1 s. 0.5)E 1 ( 3.4 s 2.2)E O.. ( 0) ( 2.9 - 2.0)E 1 ( 2.1 + 18.3)E 0 ( 1.1 - 0.4)E 1

• (

0/ 27)*

• (

0/ 3)*

• (

0/ 6)* CS 137 ( 33) 180 ( 1.0 t 0.2)E 3 91 ( 2.6

• 0.2)E 3

( 1.1 1.0)E 1-( 23) ( 1.5 - 332.0)E'1 ( 2.0 - 3.3)E 3. ( 6.2 - 60.9)E O 1

• ( 25/ 27)*
• (

6/ 6)*

• (

2/ 6)* SA 140 ( 33) ( 4.3 a 0.9)E 1 91 ( 7.0

• 3.3)E -1

( 1.8 a 0.5)E 1 I ( 0) ( 3.2 - 21.7)E 1 ( 0.0 - 2.2)E 2 ( 6.8 - 28.1)E O

• (

0/ 27)*

• (

0/ 6)*

• (

0/ 6)*. CE 141 ( 33) ( 2.8 0.6)E i 93 ( 6.0 a 1.5)E 1 ( 6.0 t 5.9)E D ( 0) ( -1.7 - 8.4)E 1 ( 3.0 - 8.1)E 1 ( 1.3 - 2.2)E 1 j

• (

0/ 27)*

• (

0/ 3)*

• (

0/ 6)* CE 144 ( 33) ( 4.4 s 16.0)E 0 93 ( 3.0 s 2.8)E 1 ( 4.2

• 19.2)E O l

( 0) ( 1.9 - 1.6)E 2 ( 2.2 - 7.2)E 1 ( 6.4'- 5.7)E -1

• (

0/ 27)*

• (

0/ 3)*

• (

0/ 6)* TH 232 ( 33) ( 1.1 1 0.1)E 3 91 ( 1.8 a 0.1)E 3 ( 4.4 a 0.2)E 2 I ( 0) ( 4.9 - 21.2)E 2 ( 1.5 - 2.1)E 3 ( 3.9 - 5.1)E.2'

• ( 27/ 27)*
• (

6/ 6)*

• (

6/ 6)* 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 (1.E. >3 STD DEVIAT!DNS) IS INDICATED WITN *( )*. I l f l

_.~ 8' ? 3.9 Eish Fish samples were collected semiannually from two locations Each was analyzed for gamma-omitting radionuclides. l Cesium-137 was detected in all control samples and one of the -j I indicators. Over the past several years, the levels have been comparable between Station FH-11'and Station FH-21 fish,' as can-be seen in Figure 3.5. These levels are consistent with l q 5 well-documented environmental levels and are attributed to. nuclear weapons. testing fallout. -{ Other than Cs-137 and naturally. occurring K-40, no gamma-emitting l radionuclides were detected in 1989 fish samples. i

I I

l u l I I WPP12/25-l- I .r ...---n -,4-.- a-- ,n.. a

-~~M M M M FIGURE 3.5 CESIUM-137 IN FISH YANKEE NUCLERR POWER STRTION, ROWE, MR mo 180- ~ D - FH-11 SHERf1AN POND o - FH-21 HRRRI!1RN RESERVOIR 140 - s d,-- 6 ? N 300 0 EB so-8 E 80-40-C u u 20-0 JrMAMJJRSONDJrHRMJJASONDJrMANJJRSONDJrHRMJJASONDJrMANJJASOND 1985 1986 1987 1988 1989

I ENVIRONMENTAL RADIOLOGICAL PROGRAM

SUMMARY

YANKEE NUCLEAR POWER STAfl0N, R0WE, MA-I- . JANUARY

• DECEMSER 1989)

( . MEDIUM: FISH UNITS: PCl/KG WET lI I INDICATOR STATIONS STAT 10N WITH NIGHEST MEAN CONTROL STAfl0NS .........eeeeeeeee .....w w we ee..........- e eeeeeeeeeeeee. o ll-RADIONUCLIDES MEAN. MEAN MEAN- .g (NO. ANALYSES) REQUIRED RANGE STA. RANGE-RANGE (NON ROUTINE)* LLD No. DETECTED ** NO. NO. DETECTF.D" NO. DETECTED" K 40 ( 4) ( 2.7 a 0.4)E 3 11 ( 2.7 0.4)E 3 ( '2.4

• 0.2)E 3

( 0) ( 2.3 - 3.1)E 3 ( 2.3 - 3.1)E 3 -( 2.2 - 2.7)E 3

• (

2/ 2)*

• (

2/ 2)*

• (

2/ 2)* .I-MN 54 ( 4) 130 ( 2.9

• 4.9)E O 21

't 6.7

• 5.6)E O

( 6.7 s 5.6)E 0 ( 0) ( 2.0 - 7.8)E 0 (- 1.1 - 12.3)E O ( 1.1

• 12.3)E O
• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* CD-58 ( 4) 130. ( 2.7 7.4)E' 0 11 ( 2.71 7.4)E O ( 5.6 1.3)E 0-( 0) ( 1.0 - 0.5)E 1 ( 1.0 - 0.5)E - 1 ( 6.9 '. 4.3)E O

• (

0/ 2)*

• (

0/ 2)*

• ( 0/ 2)*

i FE 59 ( 4) 260 ( 1.8 e 2.2)E 1 11 ( 1.8 s 2.2)E 1 '( 2.9

• 20.2)E D

( 0) ( '4.1

• 39.6)E 0

( 4.1 - 39.6)E O ( 1.7 - 2.3)E 1

• (

0/. 2)*

• (

0/ 2)*

• (

0/ 2)* j. CO-60 ( 4) 130. ( 1.6

• 1.5)E O 21

( 3.0 t 0.6)E O (. 3.0

• 0.6)E O g.

( 0) ( 3.1 - 0.0)E O ( 2.4 - 3.6)E 0 (' 2.4 - 3.6)E 0 g

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* l ZN 65 ( 4) 260. ( 7.0 a 10.2)E D 11 ( 7.0 10.2)E 0 ( 9.9 1.0)E 0 i ( 0) ( 3.2

• 17.2)E O

( 3.2 - 17.2)E O ( 1.1 - 0.9)E 1'

• (

0/ 2)*

• (

0/ 2)* ' *( 0/ 2)* SE 75 ( 4) ( 4.4 2 4.0)E O 21 ( 7.5 a 3.4)E O ( 7.5

• 3.4)E~

0 I-( 0) ( 3.7 - 83.5)E 1 ( 4.1 - 10.9)E O ( 4.1 - 10.9)E O

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* I ZR*95 ( 4) ( 2.9 1 0.6)E O 21 ( 3.8

• 4.7)E O

( 3.8 2 4.7)E O I-( 0) ( 3.5 - 2.3)E O ( 9.3 - 84.7)E 1 ( 9.3 - 84.7)E *1

• ( 0/ 2)*
• (

0/ 2)*

• (

0/ 2)* AG 110M( 4) ( 3.82 15.9)E O 21 ( 1.9

• 1.2)E 1

( 1.9 1.2)E 1 ~ ( 0) ( 1.2 - 2.0)E 1 ( 7.3 - 31.4)E 0 ( 7.3 - 31.4)E O r'

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* !=w-NON* ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER p. THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT. L THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *( )*. i bc i IL r 1

) l ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMMART TANKEE NUCLEAR POWER ITAil0N, ROWE, MA (JANUART DECEMBER 1989) MEDIUM: FISH UNIT $i PCl/KG WET f e I INDICATOR STATIONS STATION WITH HIGNEST MEAN. CONTROL STAfl0NS eeeeeeeeeeeeeeeee, eeeeeeeeeee***eeeeeeeeeee ..............e RADIONUCLlDES MEAN MEAN MEAN f (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE i (NON ROUTINE)* LLD No. DETECTED ** N0. NO. DETECTED ** No. DETECTED ** RU 103 ( 4) ( 9.2 s 4.0)E 1. 21 ( 7.4 s 0.2)E O (- 7.4

• 0.2)E O j

( 0) ( 5.2 ~ 13.2)E *1 ( 7.2 - 7.5)E O ( 7.2 - 7.5)E 0

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* i l-l3-RU 106 ( 4) ( 6.8 s ' 10.4)E 1 11 ( 6.8 a 10.4)E 1 ( 5.0 t 10.3)E 1 d ( 0) ( 3.6 - 17.2)E 1 ( 3.6 - 17.2)E 1 ( 1.5 - 0.5)E 2

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* SB 124 ( 4) ( 4.3

• 62.2)E 1:

11 (- 4.3 2 62.2)E 1 (- 2.7

• 3.6)E 0

( 0) ( 5.8 - 6.7)E D (' 5.8 - 6.7)E- 0 (. 6.3 - 0.9)E O

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* j l 131 ( 4) ( 1.5 a 2.0)E 1 21 (

• 1.5 s 0.1)E 1"

( 1.5 s 0.1)E 1 4 ( 0) ( 3.6 - 0.5)E 1

('

1.6 - 1.3)E 1 ( 1.6 - 1.3)E 1 l

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* CS 134 ( 4)- 130. ( 9.1

• 4.3)E O 11

( 9.1

• 4.3)E O

( 1.0 s 0.4)E 1 ( 0) ( 1.3 - 0.5)E 1 ( 1.3 - 0.5)E 1 ( 1.4 - 0.6)E 1

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* l CS 137 ( 4) 150. ( 4.2 a 0.9)E 1 21 ( 6.2 s 2.8)E 1' ( 6.2 '2.8)E 1 (- 0) ( 3.3 - 5.1)E 1 ( 3.3 - 9.0)E 1 ( 3.3 - 9.0)E 1 I-

• (

2/ 2)*

• (

2/ 2)*

• (

2/- 2)* i BA 140 ( 4) ( 1.9 s 1.4)E 1 11 ( 1.9 s 1.4)E 1 ( 2.2

• 6.1)E O

( 0) ( 5.8

• 33.1)E O

( 5.8 - 33.1)E O ( 8.3 - 3.9)E O

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* i j CE 141 ( 4) ( 2.6

• 3.1)E O 21

( 3.2 s 2.3)E 0 ( 3.2

• 2.3)E O ig

( 0) ( 4.4 - 57.4)E 1 ( 9.3 - 55.0)E 1-( 9.3 - 55.0)E 1 M

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* i l CE 144 ( 4) ( 1.7

• 2.3)E 1 21

( 3.7

• 5.2)E 1

( 3.7 * - 5.2)E 1 I ( 0) ( 4.0 - 0.6)E 1 ( 1.5 - 9.0)E 1 ( 1.5 - 9.0)E 1

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)* I-NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TlHES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT. THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *( )*. l l I I. L

I 3.10- DittrJ; Radlation I Direct gama radiation exposure was determined from the use of thermoluminescent dosimeters (TLDs).. Specifically, Panasonic UD-801AS1 and UD-814AS1 calcium sulfate dosimeters were used, with a total of five elements in place'.at each monitoring I -location. A total of thirty-eight stations is required by.the Radiological Effluent Technical Specifications.'.TLDs from twenty-two must be read out quarterly, while those from the-remaining sixteen incident response (outer ring): stations-need only be de-dosed (annealed)-quarterly, unless'a gaseous release. LCO was exceeded during the. period. During-1989,Lall.TLDs_were routinely readout on a quarterly schedule. : Table 3.1 provides-a summary of the results. ' Figures 3.7 to 3.12 show the TLD results ~ graphically.. j Distinct annual cycles can be seen in the TLD data from each' category of monitoring station (see Figures 3.7 to 3.12).- The lowest point of the cycle occurs during the winter months.- This is due primarily to the attenuating effect of the snow cover during those months. The effect is not as noticeable with the ~ fenceline TLDs, since the plant contributiontto radiation levels at these sites tends to obscure seasonal fluctuations in the environment. The fenceline where TLDs-are situated'is' located j well within the site boundary. The natural background radiation level at each site varies for= l. many reasons. The one that best explains the consistent differences between sites is the radioactive composition-of the underlying and nearby soil and rock.- Conspicuous deviations from any of these trends would indicate some abnormal condition, possibly a power plant contribution to the radiation levels. No such abnormalities were detected off-site during 1989, as can be seen in Figures'3.7 to 3.12. WPP12/25 c 1 l

Missina TLDs: The TLDs from Station GM-4 were missing-in the field during the fourth quarter of 1989. .\\ I .g i i ) i r i i L l l W i k ~ I i 'I l l-2 I l I; I IH (-. WPP12/25 l l

.'. W W ~ W LM M FIGURE 3.6 ~ EXPOSURE RATE RT INDICATOR TLDS, GM 01-07 YANKEE NUCLERR POWER STATION, ROWE, MR 20 19 - so-O - GN-01 VISITOR CENTER o - GN-02 DBSERVflTION STf1ND 17~ A - GM-03 ROHE: SCHOOL + - GM-04 HFIRRINFIN STflTION is - X - GM-05 110NROC BRIDGE 15-0 - GN-06 REf1DSBORO RD. BARRIER v - GN-07 HHITINGHflN LINE 3, _ 13- ? g li-n. 10-E \\ 9-e e-O y-t s-S- 4-3- 2-1- I' ' II 'III' IV ' I ' II 'IIIIV ' - I ' II - 'III' IV ' I ' II 'III' IV ' I ' II 'III' IV - 1985 1986 1987-1988 1989 s- ,_~~m.,, ,,m..w. .g

i l z j If I- -r g 3 I J - l l =- y V a = l' st ~ s mw a _s 3 l. b .hlh31 l ' b ~ "RU = dE6 -~N I l esa s =~ 7 te '2 I g5 I !gg i e s Ilii! gg W I yg 1 D lM Cf) k' YY 's t u Esssus il l i I I O O <1+ X 0 \\ .*~ O M N O O~ O Un0H H3d 8-0W0lW e i;

I -1 I FIGURE 3.8 EXPOSURE RATE RT GUTER RING TLDS, GM 24-31 4 YRNKEE N8JCLERR PGHER STRTION, ROWE, Mf1 20 19-1s-O - GM-24 HRRRIMRN Of1M o - GM-25 : WHITINGHRM, VT 17-A - GM-26 SRD0GT1 ROAD .I + - GM-27 NUMBER 9 RORD I t '8~ X - GM-28 NUMBER 9 RORD .) + is - o - BM-29 ROUTE 8R

l V - GM-30 ' ROUTE 88 14-B - GM-31 LEGATE HILL ROAD 13-5 l

o 12-i Q. v e. e. e-7- s-l -l l 5-4- 3-i 2-I 1-i 5 0 I II' III IV-I II III IV I II III. IV I II~ III IV -I II III IV 19C3 1986 - 1987 1988 1989 'I L i .. ~ ~.. ... -.,. ~ ~ _ -n

+,

n..- .. ~, .c

g g

;. '

' g n Ag FIGURE 3.9 EXPOSURE RATE AT DUTER RING TLDS GM 32 YANKEE NUCLEAR POWER STATION, RdHE, t1R ao 19-D - GM-32. R0WE ROAD to-O - SM-33 ZOAR ROAD A - 9M-34 FIFE BROOK ROAD 17 ~

+ - 9M-35 NHITC0rs SUMMIT x - SM-36 TILDR ROAD 1s - o - 9M-37 TURtER HILL RDAD 1s-v - GM-38 NEST HILL ROAD is - BM-39 ROUTE 100 3,, 13-5 o, 3: m 11-y g r a. 10-( 6 e l 68-5 ' e-I 7_ C I _g o 8-5- 4-3- 2-1- I II 'III' IV '>I ' II IIIIV'LI ' TI.'III' IV' I II' III' IV ' -I II-III'.IV- ^ 1985 1986 127 1988 1989 _ _. ___ 2 ._._ _ _._ _ _ 2__

FIGURE 3.10 EXPOSURE RATE RT FENCELINE TLDS, GM 13-21. YANKEE NUCLEAR POWER STATION, ROWE,'MR-l 1 l ..0 - BM-13 HSH 0.08 KM O - GM-14 leN- 0.11 KM 45-A - GM-15 : f#N 0.08 KM~ + - GM-16 NNE 0.13 KM l X - SM-17 ENE 0.14 KM 40-o - SM-18 ESE 0.14 KM V - SM-19 SE 0.16 KM N - BM-20 SSE 0.16 KM M - BM-21 SSH 0.11 KM 3_ s e } o 30-r 6 1 " r ? 4, E I k E /\\ o 2-7 \\ l 35 - h [- s i \\ Y l 3 A t s s 10-I s-J 0 4 j 'I II III IV I II III.IV 'I -II III IV I. .' II III IV I-II-III IV .1985. 1986 1987 1988 1989 m_ m. ... _ -. ~ _ -.. _., _. m,__a ,__m .,_____a

a -.- ' ~ 3 l-e . I 6 I M-k -"l f ~ nk . m N a m .g O } ene ,x. g M .Og i ) G h m l w.1 30 m M% Oh-D E u. - N: I:. $O O a g~ MH }l m 14 e IJ ~ -a e%m Z m i td %y

• h Y

v, On x n. 'NN l ii I n 00 -g - m

.1 i

w w l: H L , i i ;iiiii;iu: Un0H W3cl B-0WJIW e .,... ~ _... _.... -.r,

c- - -.. I Environmental Radiological Program Summary, -Yankee Nuclear Power Station, Rowe, Massachusetts Januarv - Decamber 1989 Medium: Direct Radiation Measurements (TLD) Units: Micro-R per Hour Indicator Outer-Ring Restricted -Control I. $1AkiDRg_ Stations _ Area Fence Stations Mean Mean-Mean Mean j Range Range Range Range (No. Maas.)* (No. Meas.)* (No. Meas.)* (No. Meas.)* 7.1 & 1.1 7.0 1 1.2 17.9 A 5.8 7.7 1 0.8 5.3 - 9.2 4.7 - 9.5-11.0 - 30.1 6.2 - 8.9 (52) (63) (36) (8) i i All measurements based on the mean of five readings per station (quarterly readout). I I B I WPP12/25

l 'I 'Ishle 3.1 S A-a ry of Direct Radiation Measurements - 1983 -Yankee Nuclear Power Station (Micro-R Per Hour) I First Second-Third Fourth Yearly Station Distance (km) Direction Quarter Quarter Ouarter Quarter Maan GM-1 0.8 SW 7.0 6.5 7.4 7.6 7.1 GM-2 0.5 NW 6.6 6.4 7.2 7.5 6.9 GM-3 4.2 SE 5.8 5.3 6.1 6.0 5.8 GM-4 3.2 N 6.4 6.3 7.0 7.3 6.8 GM-5 1.1 SW 8.4 8.2 9.0 9.2 8.7 I-- GM-6 1.3 N 6.9' 6.9 8.0- .7.6 7.4-GM-7 3.5 NE 6.2 5.9 6.8 7.5 6.6 GM-8 1.8 6 6.1: 5.9 6.9 6.8- '6.4-I GM-9 3.2 SW 6.6 6.5 7.7 7.5 7.1 GM-10 3.5 E 5.9 6.1 7.0 6.6 6.4 GM-11 2.1 WNW 6.8 6.8 8.1 7.8 7.4. GM-12 5.5 NNW 7.2 6.9 7.8 7.8 7.4 I I-GM-13 0.08-WSW 16.7 15.0 17.1 17.7 16.6 i GM-14 0.11 WNW 11.3 11.0 11.9 12.5 11.7 l GM-15 0.08 NNW 11.6 11.0 12.8 12.2 11.9 1 I GM-16 0.13 NNE 14.4 13.3 13.3 13.4 13.6. GM-17 0.14 ENE 17.5 16.3-18.1 17.6 17.4 GM-18 0.14 ESE 30.1 26.1, 28.9 28.8 28.5 I-GM-19 0.16 SE 27.8 23.7 25.7 24.7 25.5 i i GM-20 0.16 SSE 20.8 18.4 19.5 18.5 19.3 GM-21 0.11 SSW 17.6 15.9 17.0 17.0 16.9-GM-22 12.6 NNW 6.2 7.4 7.7 7.4 7.2 l I GM-23 22.2 W 8.0 7.8 '8.1 8.9 8.2 GM-24 7.3 N' 7.4 7.8 8.5 -8.4 8.0 l GM-25 7.7 NNE 6.1 6.3 6.9 6.7 6.5 I I GM-26 7.6 NE 5.9 6.4 7.2 6.7 6.6 I GM-27 7.6 ENE 5.6 6.2 6.6 6.1-1 GM-28 6.0 E 6.6 6.8 7.1 7.3 6.9-GM-29 8.2 ESE 4.7 4.9 5.4' 5.4 5.1 I I GM-30 9.4 SE 5.3 5.6 6.3 6.4 5.9 GM-31 7.6 SSE 6.0 6.4 .7.0 6.7 6.5 GM-32 7.9 S 5.9 6.4 6.7-6.6 6.4-I GM-33 6.9 SSW 6.7 6.5 7.1 7.3 6.9 GM-34 6.4 SW 8.8 8.7 9.3 9.5 9.1 i GM-35 8.6 WSW 6.5 7.1 7.7 7.3 7.1 I-GM-36 6.6 W 6.5 7.1 7.7 7.4 7.2 GM-37 6.7 WNW 7.2 7.6 8.3 8.2 7.8 GM-38 6.6 NW 7.0 8.1 9.0 8.5 8.2 GM-39 6.8 NNW 7.0 8.4 9.3 9.0 8.4 GM-40 0.5 W 6.3 6.7 7.6 7.2 6.9

• Missing TLD.

I-WPP12/25 I

-) i '4.0 QUALITY ASSURANCE PRQ2BM

I l

Three separate Quality Assurance programs were performed during 1989 to j l demonstrate the validity of laboratory analyses by the Yankee Atomic Environmental Laboratory (YAEL). YAEL participates in the EPA Interlaboratory Comparison (cross-check)- E jg This provides an independent check of accuracy and precisien 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, as appropriate. 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 equipment, use of reference standards for calibration, and analysis of blank and spiked. samples. The records of the quality control f program are reviewed by the responsible cognizant individual, and corrective j measures are taken whenever applicable. il A blind duplicate program is maintained in which paired samples from five nuclear plants, including Yankee Atomic, are prepared from homogenous media and sent to the laboratory for analysis.- The results from this blind I duplicate program are used to check for precision in laboratory analyses. Intralaboratory and EPA Interlaboratorv Results The Quality Assurance Program implemented at the analytical laboratt.ry indicated good precision and accuracy in reported values. Table 4.1 shows the results of accuracy and precision for laboratory analyses in 1989.for intralaboratory analyses and EPA interlaboratory cross-check analyses. I i M-i. WPP12/25 I lI . - ~..

I ); Table 4.1' Intralaboratory and EPA Interlaboratory Resulta - 1989 Accura.cy-Total Number 0 to 5% 0 to 101 0 to 151* gf Measurements 717 448 619 689 (62.5%) (86.3%) (96.1%)' Precision Total Number-O to 5% 0 to 101 0 to 151* of Measurements 714 599 675 710- -l (83.9%) (94.5%) (99.4%) i i I I I I I I This category also contains those samples having a verified zero concentration which were analyzed and found not to contain the isotope of

interect,

. WPP12/25

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 1989. One hundred and ] fifty-nine analyses were performed on air particulate filters, milk, and water. The sample analyses that did not meet the mean value criteria were a Sr-89 and a Sr-90 analysis on a milk sample set. The mounted samples were reanalyzed for Sr-90, and the new mean values fell within the EPA control limits. (Details of this may be found in References 2 and 3.) The above EPA Interlaboratory Comparison Program results are provided in compliance with Technical Specification 4.12.3. Blind Duplicate Program A total of 51 paired samples were submitted by the five' participating I plants for analysis during 1989. The data base used for the duplicate analysis consisted of paired measurements of 26 gamma-emitting nuclides, H-3, Sr-89, Sr-90, low level I-131, and gross beta. A dual level criteria for agreement was established. If the paired measurements fall within 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. One thousand three hundred and fourteen paired duplicate measurements were analyzed for 1989. A total of 99.2 percent of all measurements fell within the established criteria discussed above. The eleven measurements that j did not meet the criteria were measurements of Mo-99 in milk, Be-7 in milk, Np-239 in milk, Ba-140 in milk, Sr-89 in milk, Zn-65 in milk, and Co-57 in groundwater, Ba-140 in groundwater, co-60 in estuary water, Ce-144 in 1 seawater, and Np-239 in estuary water. In all of the above cases, the 5 radionuclide in question was not detected in-the sample (i.e., the l concentration was less than three standard deviations) and the three-standard deviation ranges of the paired samples overlapped. The eleven duplicate l l WPP12/25 I I l

.... - ~.. t.. i measurements represent:0.8 percent of all.'he blind duplicate' paired t I measurements made during 1989.. No-trend was evident with respect to repeated. failings'of measurements-for.the above radionuclides. I i !I f i ) i. .~ i o !I ]I I 1 'I L lI s 1 ! WPP12/25 E

t 5.0 LAND USE CENSUS I Specification 3/4.12.2 of the Radiological Effluent Technical specifications requires that a land use census be conducted after June 1 and before October 1 of each year. The census'is used to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of I greater than 500 square feet producing fresh leafy vegetables in each of the sixteen meteorological sectors within a distance of five miles. The 1989 census was completed within the above dates. The distance and direction from ~t the plant for each of the above' locations are shown in Table 5.1. I The land use census for this reporting period identified three milk animal locations which yielded a calculated dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from which 5a Specification 3.12.1. Specifically, these milk animal locations were found at: WNW, 1.9 km; NE, 3.7 km; and SE, 3.2 km. None of the locations, however, would be able to provide samples of sufficient size over an extended period l due to the small number of milking cows owned. Consequently, the two existing locations, m-12 and 2-13 were kept as official sampling locations in compliance with Technical Specification 3.12.2.b. i No garden locations were identified that yielded a calculated dose or 1 dose commitment at least 20 percent greater than that at the existing food crop sampling locations. Consequently, the food crop sampling locations were-not changed in 1989 as a result of the Land Use Census. Following the census, Technical Specification 3.12.2.a requires the identification in the Semi-Annual Effluent Release Report of any location (s) identified in the census which yields at least a 20 percent greater dose or l dose commitment than the values currently being calculated in Technical Specification 4.11.2.3. No such locations were identified. l l WPP12/25 l

I Table 5.1' 1989'f and Use Ceaans Resulta. Yankie Nuclear Power Station l Nearest- ' Nearest Nearest Residence Milk Animal Garden Sector (km) (km) (km) N 2.4 6.1 3.5 -NNE 4.7 5.3

NE 3.7 3.7 3. 7 --

ENE 3.1 8.4 -7.4 E 3.1 3.1 .I-ESE 3.4 7.9 3.4 SE 2.3 3.2 2.3- .] SSE 2.1 2.9 S 2.3 2.3-SSW E SW 1.3 1.3 WSW 1.3 1.3 W 1.9 i 2.7 WNW 1.9 1.9 1.9 'NW 0.45 4.6 NNW. 2.9 '3.9 i I i 1 WPP12/25 I

6.0 EUMMARY lI During 1989, as in all previous years of plant operation, a program was conducted to assess the levels of radiation or radioactivity in the Yankee Atomic environment. 'Over 1,000 samples were collected (including TLDs) over the course of the year, with a total of over 5,000 radionuclide or exposure i rate analyses being performed on them. The samples included ground water, river water, sediment, fish, locally grown food products, maple syrup, and milk. In addition to these samples, the air. surrounding the plant was sampled continuously and the radiation levels were measured continuously with environmental TLDs. Low levels of radioactivity from three sources were detected. Most samples had measureable levels of K-40, Be-7, Th-232, or radon daughter products.. These are the most common of the naturally-occurring radionuclides. Many-I samples (milk and sediment in particular) had fallout radioactivity from atmospheric nuclear weapons tests conducted primarily from the late 1950's through 1980, or from fallout originating at the Chernobyl plant in 1986. Several samples had low levels of radioactivity resulting from emissions from the Yankee plant. These were all collected in the immediate' vicinity of the plant or from on-site locations.- In all cases, the possible radiological impact was negligible with respect to exposure from natural background radiation. In no case did the detected levels approach or exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment. lI 1I I I 5 (l WPP12/25 I-

I l

7.0 REFERENCES

1. USNRC Regulatory Guide 1.109, " Calculation of Annual-Doses to Man from Routine Releases of Reactor Effluents for.the Purpose of Evaluating Compliance with 100FR50, Appendix I," 1977. 2. Yankee Atomic Environmental Laboratory Semiannual Quality Assurance Status Report, January-June 1989, Yankee Atomic Electric Company. '3. Yankee Atomic Environmenta1' Laboratory Semiannual Quality' Assurance Status Report, July-December 1989,- Ycnkee Atomic Electric Company. I I I I I I I I I , WPP12/25 .}}