Text

Environ Radiation Monitoring Program Rept 19,1986
	ML20210C112
Person / Time
Site:	Pilgrim
Issue date:	12/31/1986
From:	Bird R, Bowman C, Sowdon T; BOSTON EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	BECO-87-068, BECO-87-68, NUDOCS 8705060083
	Download: ML20210C112 (163)
	v • d • e

. _ - - -

PILGRIM NUCLEAR POWER STATION ENVIRONMENTAL RADIATION MONITORING PROGRAM REPORT NO.19 JANUARY 1 THROUGH DECEMBER 31,1986 ISSUED: MAY 1987 BY: NUCLEAR OPERATIONS DEPARTMENT RADIOLOGICAL ENGINEERING GROUP BOSTON EDISON COMPANY sssosiou fi5iVEDISON

$s4e PlP 2888 8taggi,3 g\\\\

R PDR

BOSTON EDIS0N COMPAMY PILGRIM NUCLEAR POWER STATION

- Environmental Radiation Monitoring Program REPORT NO. 19 January 1, 1986 through December 31, 1986 Prepared by:

2:I-

^ - =

ChristineE.BoAan Radiological Engineering Group Leader-f7 Approved by:

db= _

I_-[:- I Tk6mds L. Sow)6n

/

I Radiological 3ection Manager Date of Submittal:

May 1, 1987 i

y

,r

,. - -e-

, - -.. - -, +, -... - _, - -. -,

y.,

w <

.,.,.,,-.-r,-1-,

TABLE OF CONTENTS Section Eagg I

Introduction and Summary 1-1 II Description of Monitoring Program 2-1 III Results of Analyses 3-1 A.

Air Particulates 3-5

-B.

Iodine 3-11 C.

Soil 3-16 D.

Direct Radiation 3-17 E.

Haterborne 3-27 F.

Shellfish 3-30 G.

Algae (Irish Moss) 3-34 H.

Lobster (Arthropods) 3-38 I.

Fish 3-41 J.

Sediments 3-44 K.

Milk 3-50 L.

Cranberries 3-57 M.

Vegetation 3-60 N.

Forage 3-63 IV References 4-1 Appendix A Anonalous Measurement Reports A-1 Appendix B Radioactive Effluents B-1 Appendix C Soil Survey C-1 Appendix D Radiological Environmental Monitoring Program D-1 Appendix E 1986 Garden and Milk Animal Survey E-1 Appendix F Environmental Radioactivity from the Chernobyl Accident F-1 Appendix G Chernobyl-Related Radioactivity Measurements in PNPS Environmental Media G-1 1

LIST OF TABLES IAble Number Eagg I-I PNPS-1 Capacity Factors 1-3 III-A-1 Sample Station Identification Codes 3-3 III-A-2 ERMAP Results - Air Particulate Filters 3-7 III-B-1 ERMAP Results - Charcoal Cartridges 3-13 III D-1 Thermoluminescent Dosimeter Locations 3-20 III-D-2 Results of TLD Measurements - Quarter #1 3-21 III-D-3 Results of TLD Measurements - Quarter #2 3-22 III-D-4 Results of TLD Measurements - Quarter #3 3-23 III-D-5 Results of TLD Measurements - Quarter #4 3-24 III-D-6 Quarterly Average Exposure Rates 3-25 III-D-7 Field Survey Exposure Rates 3-26 III-E-1 ERMAP Results - Haterborne 3-28 III-F-1 ERMAP Results - Shellfish 3-32 1

III G-1 ERMAP Results - Algae 3-36 III-H-1 ERMAP Results - Lobster 3-39 III-I-1 ERMAP Results - Fish 3-42 III-J-l ERMAP Results - Sediments 3-47 a

III-J-2 Results of Sediment Analysis for Plutonium 3-49 III-K-1 ERMAP Results - Milk 3-52 III-L-1 ERMAP Results - Cranberries 3-58 III-M-1 ERMAP Results - Vegetation 3-61 III-N-1 ERMAP Results - Forage 3-64 ii

LIST OF FIGURES Fiaure Number Pagg III-A-1 Gross Beta Activity - Air Particulates -

3-9 Indicator Stations III-A-2 Gross Beta Activity - Air Particulates -

3-10 Control Station III-B-1 Concentrations of I-131 - Charcoal Filter -

3-14 Indicator Stations III-B-2 Concentrations of I-131 - Charcoal Filter 3-15 Control Station III-K-1 Concentrations of Cs-137 in Milk 3-54 III-K-2 Concentrations of Sr-90 in Milk 3-55 III-K-3 Concentrations of I-131 in Milk 3-56 I

111

I. Introduction and Summary This report presents a summary of the results of measurements of direct radiation and radioactivity in environmental media in the vicinity of the Pilgrim Nuclear Power Station - Unit 1 (PNPS-1) and at selected control locations for the period January 1 - December 31, 1986.

The results of this Program indicate that PNPS-1 has had a negligible and most often immeasurably small impact on the environment in the vicinity of the plant. Conservatively, estimated doses resulting from the measured highest station mean concentrations are typically less than 17. of the doses resulting from naturally occurring radionuciides and residual fallout from previous atmospheric nuclear weapons testing.

However, on April 26, 1986, there was an accident at the Chernobyl Nuclear Power Plant in the USSR.

The radioactivity detected in environmental media as a result of this accident is discussed in Appendix F.

A tabulation of the Chernobyl-related radioactivity measurements in environmental media for the PNPS Environmental Monitoring Program is presented in Appendix G.

Estimates of concentrations of radionuclides in vegetation and milk and estimates of dose to man, as quoted in this report, were made using methods

.similar to those described in Regulatory Guide 1.109 and 1.111.

The performance record of the PNPS-1 for the calendar year of 1986 reflects an average capacity factor of 17.57..

PNPS-1 has been shutdown since April 12, 1986. Monthly capacity factors are given in Table I-1.

A tabulation of radioactive effluents from the PNPS-1 is provided in Appendix B for the 1986 calendar year.

There were no Anomalous Measurement Reports made for the calendar year of 1986.

1-1

Essentially, all samples required by the PNPS-1 Technical Specifications were collected on schedule.

The only exceptions were the unavailability of one milk sample location (until March 1,1986), one air sampling location from 9/23/86 through 12/31/86, plus occasional failures of the air samplers, and three fish samples due to unavailability.

In addition, a total of one TLD was found to be missing from their field locations during 1986.

These incidents affected only about 1% of the total number of samples scheduled for collection.

The Plimoth Plantation was not available as a milk sampling location during 1986.

Plimoth Plantation informed Boston Edison in January 1981 that milk producing animals would no longer be available as they disposed of their cow.

This situation had not changed for 1986.

However, as of March 1,1986, a revision to the Radiological Effluent and Environmental Monitoring Technical Specifications (RETS) became effective (Appendix D).

This revision deleted the requirement to obtain a milk sample from Plimoth Plantation, as samples are no longer available from this location.

The East Breakwater air sampling station was without power from 9/23/86 through 12/31/86.

Loss of power to this air sampling station was immediately reported to the Control Room upon discovery on 9/23/86.

The loss of power was caused by a transformer failure and degraded electrical cabling.

1-2

TABLE X-1 PNPS-1 1916 (Based on 670 MWe)

Month Percent Caoacity January 79.5 February 97.7 March 26.9 April 11.9 May 0.0 June 0.0 July 0.0 k

August 0.0 September 0.0 October 0.0 November 0.0 December 0.0 Average 17.5 i

l l-3

II. Descriotion of the Monitorina Proaram The Radiological Monitoring Program conducted in accordance with the PNPS-1 Technical Specification is included as Appendix D.

The program has been slightly revised and incorporates supplemental provisions as specified in the Settlement Agreement between the Massachusetts Hildlife 2

Federation and Boston Edison Company, June 9, 1977. The exceptions to the program is as follows:

1)

There is no TLD station at Saquish Neck since the Mass Hildlife Federation has not yet provided a means for placement and retrieval

=

of the TLD as prescribed by the agreement noted above.

s-The 1986 site Census conducted according to Technical Specification requirements determined that there are several vegetable gardens near the site boundary in the H-HNH and SE-ESE sectors (see Appendix E).

In the ESE sector, the nearest garden is at the J. B. Work residence (0.6 miles ESE). A sample of red lettuce and spinach was collected on 9/16/86.

In the west direction, the location of the nearest observed garden of g

approximately 500 square feet was at the Jenkins residence (1.0 miles H).

A sample of rhuhbarb was collected from this location on 9/16/86.

In the SE direction, the location of the nearest observed garden was at the Malmgren residence (1.0 miles SE). A sample of rhubbarb was collected on l

9/16/86.

l In addition to the above, a sample of spinach was obtained from the H.

Moon residence (1.25 miles SSH) on 9/17/86.

1 2-1

The Plymouth County Farm (3.5 miles H) is the established indicator station for milk-producing animals for PNPS.

The only other available milk-producing cow within 5 miles of PNPS is located on Beaver Dam Road (2.5 miles S) and is owned by C. Mann. Mr. Mann has not participated in the Environmental Monitoring Program since the first quarter of 1984.

In perspective, cows and goat locations within a 5 mile radius of PNPS-1 are rare and transitory at best.

It is extremely unlikely that the cow-milk pathway could be responsible for even small doses to any member of the general public.

l l

2-2

III.Results and Analyses This section summarizes the results of the analyses of environmental media samples in compliance with the monitoring program described in Appendix D.

The section is divided into sub-sections, each of which describes a particular media or potential exposure pathway.

The results of analyses conducted on environmental media are maintained in

~

a computerized data file which constitutes a data base used for 3

statistical analyses by a computer code entitled ERMAP,

ERMAP calculates a set of statistical parameters for each radionuclide whose concentration is reported in a given environmental medium.

This set of statistical parameters includes separate analyses for (1) the indicato:

stations, (2) the control stations, and (3) the station having the highest annual mean concentration.

For each of these three groups of data, ERMAP calculates:

1) the mean value of all measured concentrations; 2) the square root of the mean square deviation (this is an estimate of the sample variance);

3) the lowest and highest calculated concentrations; 4) the number of positive measurements divided by the total number of measurements.

3-1

Entries listed under the heading LLD* are the mean of all LLD values, where each LLD equals 4.67 times the standard error of the associated background measurement.

The results of ERMAP are provided in each subsection for the appropriate media.

In addition, plots of measured concentration as a function of sampling time are included for certain isotopes in certain media in an effort to simplify interpretation of the results.

Sample station identification numbers used by the ERMAP program are provided in Table III-A-1.

Y ll I

Lower Limit of Detection l

1 l

l 3-2 m.

TABLE III-A-1 Samole Station Identification Codes Media Station Code Station Location Number Air Particulate 00 Warehouse (0.2 mi-SSE) and 01 Rocky Hill Road (0.8 mi-SE)

Iodine Filters 03 Rocky Hill Road (0.3 mi-WNW) 06 Property Line (0.11 mi-W-WNW) 07 Pedestrian Bridge (0.17 mi-NNW) 08 Overlook Area (0.17 mi-WSW) 09 East Breakwater (0.26 mi-ESE) 10 Cleft Roak (0.9 mi-S) 15 Plymouth Center (4.0 mi-H-WNW) 17 Manomet Substation (2.25 mi-SSE) 21 East Weymouth (control-23 mi-NW)

Waterborne 11 Discharge Canal 17 Bartlett Pond (1.7 mi-SE) 23 Powder Point (control 7.8 mi-NNW)

Shellfish 11 Discharge Canal Outfall 12 Warren Cove 13 Duxbury Bay 15 Manomet Point 24 Marshfield (Control)

!l Algae (Irish Moss) 11 Discharge Canal Outfall 15 Manomet Point 22 Ellisville (Control, 8 mi-SSE))

34 Brant Rock (Control, 12 mi-NNW)

Lobster (Arthropods) 11 Vicinity of Discharge Canal Off-shore 15/19 Offshore (Control) 25 Scituate (Control)

Fish 2

Round Hill Point-Offshore-(Control) 11 Vicinity of Discharge Canal 12 Warren Cove 13 Duxbury Bay (Control) 14 Vicinity of Plymouth Beach 19 White Horse Beach 21 Auto Trawl Station-Offshore-(Control) 22 Offshore-(Control) 28 Cataumet, Bourne-(Control) 29 Priest Cove-Offshore-(Control) 96 Mouth of North River-Hanover (Control) 97 Nantucket Sound (Control) 99 Provincetown-Offshore (Control)

Sediment 11 Rocky Point 12 Warren Cove 13 Duxbury Bay 14 Plymouth Beach 15 Manomet Point 24 Marshfield (Control) 3-3

l TABLE III-A-1 Samole Station Identification Codes Media Station Code Station Location Number Milk 11 Plymouth County Farm (3.5 mi-H) 21 Whitman Farm (Control-21 mi NH)

Cranberries 13 Manomet Point Bog (2.6 mi-SE) 14 Bartlett Road Bog (2.8 mi-SSE/S) 23 Pine St. Bog (Control-17 mi-HNH)

Vegetation 11 Plymouth County Farm (3.5 mi-H) 16 Hork Residence (0.6 mi-ESE) 27 Bridgewater Farm (Control-20 mi-H) 43 Whipple Farm (1.5 mi-SSH) i 75 Malmgren Residence (1.0 mi-SE) 76 Jenkins Residence (1.0 mi-H) 77 Moon Residence (1.25 mi-SSH)

Beef Forage 11 Plymouth County Farm (3.5 mi-H) 21 Whitman Farm (Control-21 mi-H) 3-4

III.A. Alf Particulate Filters Sample collection systems consisting of a cellulose particulate filter and a charcoal filter cartridge are used to collect particulate matter and iodine nuclides respectively. Analyses of the particulate filters for beta radiation is performed weekly.

In addition, quarterly composite particulate samples are analyzed for gamma emitting nuclides. Table III-A-2 presents the results of the ERMAP for air particulate analyses.

(The station identification numbers correspond to the locations identified in Table III-A-1).

For ease of interpretation of these measurements, a plot of gross beta activity vs. time for all indicator stations is provided in Figure III-A-1 and for the control station in Figure III-A-2.

There were a total of thirteen air particulate filters which were not analyzed during the year of 1986. The air particulate filter at Station #09 (East Breakwater) for week numbers 40 through 52 were not analyzed due to a lack of power to the air sampler. The lack of power was due to a transformer failure and degradation of electrical cabling.

During 1986, there were several instances of low sample volume due to a variety of causes, such as power failures, motor failures, and crimped sample lines. Of these, there was one instance which resulted in the HDC not being met.

The HDC was not met for Station #17 (Hanomet Substation) collected on 8/5/86 due to a low sample volume which was the result of the filter falling out of the holder thereby crimping the sample line.

3-5

There were no positive measurements of any nuclides characteristic of reactor operations attributable to PNPS-1 observed in the quarterly composite samples. There were positive measurements of nuclides characteristic of reactor operations attributable to the Chernobyl Nuclear Power Plant accident in the second quarter composite samples.

These nuclides were:

Ru-103, Cs-134 and Cs-137.

The positive measurements were seen at all stations from week #20 through week #24 (late May to early June) with the highest concentrations seen during week #21.

In addition, high concentrations of Be-7 were also seen.

The results of the ERMAP Program for air particulates are presented in Tables II-A-2 and II-A-3 for indicator stations and the control station, respectively.

The highest mean concentration was detected at Station #09 (East Breakwater) for Ru-103, Cs-134 and Cs-137.

The highest mean concentration for Be-7 was detected at Station #17 (Hanomet Substation).

The Cs-137/Cs-134 ratio is approximately 2/1, which was seen at the other New England stations.

Refer to Appendix F for a summary on the radioactivity detected in environmental media due l

to the Chernobyl accident, and Appendix G for a tabulation of the measurements.

In consideration of the natural background dose rate of 80 to 100 mrem-year, there was clearly no significant environmental effect I

observed in the air particulate media as a result of the operation of PNPS-1.

3-6

TABLE III-A-2 ERMAP RESULTS AIR PARTICULATE FILTERS 1986 MED*UP: AIR PARTIC'JLATE UNITS: PCI/CU. M INDICATCR STATICt4S STATICt1 WITH HIGFEST EAN CONTROL STATIONS eseeeeee**+eseeeee eteenseeeeeeeeeeeeeeeeeet eteeeeeeeeeeeeee RADirN n IDES ME41 TAN EAN (N0. 44ALYSES REC #JIRED RANGE STA.

RANCE RANGE (NONOJT:fE U LLD NO. DETECTEDee M).

NO. DETECTEDet NO. ETECTEDen CS-B (553)

.01

(

3.51

.2)E -2 09 ( 4.0 i

.8)E -2

( 3.3 i

.6)E -2

( 0)

( l.4 - 321.0)E -3

( !.4 - 288.0)E -3

( 8.5 - 225.0)E -3 e(504/506),

el 38/ 39),

e( 52/ 521e BE-7

( 43)

(

4.6i

.1)E -2 17

( 5.2 i

.5)E -2

( 5.2 i

.2)E -2

( 0)

( 3.1 -

6.4)E -2

( 4.4 -

6.4)E -2

( 4.8 -

5.9)E -2 et M/ 39)*

et 4/ 4),

et 4/ 4)*

K-40

( 43)

(

4.7t

.6)E -3 01

( 7.1 i 1.6)E -3

( 5.1 i

.8)E -3

( 0)

(-3.9 - 13.4)E -3

( 3.1 - 10.7)E -3

( 3.4 -

7.4)E -3

(

3/ 39)*

e( 1/ 4)e e( 0/ 4)*

Pff-54 ( 43)

(

l.8t 3.0)E -5 17 ( 1.7 i

.2)E -4

( 6.7 f 13.9)E -5

( 0)

(-4.0 -

3.8)E -4

( 1.2 -

2.0)E -4

(-1.2 -

4.7)E -4 et 0/ 39)*

e( 0/ 4),

et 0/ 4)e CO-58 ( 43)

.02

( -4.5t 4.1)E -5 00 ( 1.8 t 1.4)E -4

( 4.8 f 3.0)E -5

( 0)

(-6.8 -

4.6)E -4

(-2.1 -

4.6)E -4

(-3.7 -

9.5)E -5 et 0/ 39)e et 0/ 4)*

(

0/ 4)e FE-59 ( 43)

(

3.5 12.3)E -5 00 ( 5.3 i 2.1)E -4

(-4.0 i 5.3)E -4

( 0)

(-1.6 -

1.7)E -3

( 9.9 - 95.5)E -5

(-1.8 -

.8)E -3

(

0/ 39)e

(

0/ 4)*

(

0/ 4)e C0-60 ( 43)

.02

( -1.5t

.4)E -4 17 ( 7.1 i 9.4)E -5

(-4.6 t 19.0)E -5

( 0)

(-9.0 -

4.5)E -4

(-1.4 -

3.1)E -4

(-4.1 -

4.8)E -4 et 0/ 39),

et 0/ 4),

el 0/ 4)e ZN-65 ( 43)

(

-2.2 7.7)E -5 01

( 2.7 i 3.4)E -4

( 8.5 1 26.7)E -5

( 0)

(-1.1 -

1.3)E -3

(-2.3 - 12.7)E -4

(-3.2 -

8.7)E -4 et 0/ 39)e

(

0/ 4),

(

0/ 4)e ZR-95 ( 43)

(

6.4f 9.1)E -5 06 ( 5.7 i

.5)E -4

(-2.4 1 2.3)E -4

( 0)

(-1.3 -

1.2)E -3

( 4.6 -

6.9)E -4

(-8.2 -

2.2)E -4

(

0/ 39)e e( 0/ 4)*

e( 0/ 4),

e e NON-ROUTIE REFERS TO THE NUMBER CF SEPARATE MEA 9)RETNTS WHICH WEPE GREATER THAN TEN (10, TIMES TFE A'4 RAGE BACKOROLND FOR TK FERIOD OF TT REM)RT.

se THE FRACTION OF SAMFtE ANALYSES YIELDING KTECTABLE EASUREMENTS II.E.13 STD DEVIATICC 15 INDICATED WITH et 1*.

3-7

TABLE III-A-2 (CONTINUED) 5_0:sf: AIR PARTICttATE LHITS: PCI/CU. M INDICATOR STATIONS STAi!9N WITH HIC +1EST MEAN CCNTROL STATION <.

eeeeeeeeee*++*++*

- - - eteneeeeeeee**eeeeee, e++,*********,ee RADI(ttXt DE3 MEAN MEAN EAN (NO. W LHES)

REOUIRED RANCE STA.

Rua'E RANGE (Nnn-FrCTINEl' LLD W. DETECTED n NO.

NO. [ETECTEDH NO. DETECTED ++

Ri:-!O3 ( 43)

(

1.31

.4)E -3 09 ( 1.8 t 1.7)E -3

( l.3 i 1.4)E -3

( 0)

(-4.6 - 63.9)E -4

(-4.6 - 51.1)E -4

(-3.6 - 55.3)E -4

( 10/ 39)*

(

1/ 3)*

(

1/ 4)*

RU-106 ( 43)

(

6.81 3.6)E -4 08

( 2.0 t 1.2)E -3

( 2.7 i 8.3)E -4

( 0)

(-4.8 -

4.6)E -3

(-1.7 -

3.9)E -3

(-1.8 -

1.8)E -3 e( 0/ 39)*

( 0/ 4)*

(

0/ 4)e C5-134 ( 43)

.01

(

!.4t

.4)E -3 09 ( 1.9 t 1.7)E -3

( l.7 t 1.6)E -3

( 0)

(-6.7 - 72.2)E -4

( 7.2 - 530.0)E -5

(-1.2 - 65.0)E -4

( 10/ 39),

(

1/ 3)*

e( 1/ 4)*

CS-137 ( 43)

.01

(

2.81

.8)E -3 09

( 3.3 i 3.1)E -3

( 3.0 t 3.0)E -3

( 0)

(-4.3 - 131.0)E -4

( 9.2 - 956.0)E -5

(-1.3 - 121.0)E -4

( 10/ 37)e

(

1/ 3)e

(

1/ 4)*

BA-140 ( 43)

(

3.21 3.1)E -4 01

( 2.0 t 1.3)E -3

( 3.7 1 4.8)E -4

( 0)

(-3.9 -

5.9)E -3

( 1.3 - 58.8)E -4

(-7.5 - 14.1)E -4 et 0/ 39)*

(

0/ 4),

( 0/ 4)*

CE-141 ( 43)

(

!.0t

.7)E -4 07

( 4.7 i

.4)E -4

(-7.4 t 20.4)E -5

( 0)

(-1.0 -

1.3)E -3

( 3.9 -

5.7)E -4

(-5.9 -

3.9)E -4 et 0/ 39)*

a( 0/ 4)*

(

0/ 4)e CE-144 ( 43)

(

6.7t 13.4)E -5 09

( 7.7 i 9.3)E -4

( 1.7 t 1.9)E -4

( 0)

(-1.4 2.2)E -3

(-9.5 - 22.3)E -4

(-1.7 -

7.01E -4

(

0/ 39)*

et 0/ 3)e

(

0/ 4)*

TH-232 ( 43)

(

2.2t 1.4)E -4 01

( 9.2 i 7.8)E -4

(-6.8 i 16.5)E -5

( 0)

(-1.4 -

2.4)E -3

(-1.2 -

2.2)E -3

(-3.9 -

2.2)E -4

(

0/ 39)e

(

0/ 4)*

(

0/ 4)*

NON-ROUTINE REFERS TO TE NltiBER OF SEPARATE E ASLREMENTS WHICH WERE CE ATER THW TEN (10) TIES TE A'4 RAGE BACKGROLND FOR THE PERIOD OF THE REPORT.

- THE FRACTION OF SANFtE ANALYSES YIELDING DETECTABLE MEASLREMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH et 1*.

3-8

GROSS BET 8 NEBSUREMENTS OF BIR P8RTICULRTE FILTERS INDIC8 TOR ST8TIONS PILGRIM ST8 TION o.so 0 - RP-00 WRREHOUSE

c. ss -

O - RP-01 ROCKY HILL ROAD 1

a - RP-03 ROCKY HILL RORD

+ - RP-06 PROPERTY LINE X - RP-07 PEDESTRIRN BRIDGE o m.

o - RP-08 OVERLOOK RRER l

v - RP-09 EAST BRERKWRTER l

B - AP-10 CLEFT ROCK 85~

M - RP-15 PLYMOUTH CENTER

~o

+ - AP-17 MANOMET SUBSTRTION 5>5i h

N Wb o55M c.33-B "Es-Ws>=

s o*s _

CFQL m

M 8%2a o.m-505 8

E o.ts -

t 0.1D -

0.05-o.=

JfW TEB MR ffR MY JIM JUL HUC SEP OCT NOV DEC 1986

GROSS BETR MERSUREMENTS OF BIR PARTICULRTE FILTERS CONTROL STATION PILGRIM STRTION 0.50 0.15 -

D. to -

D - 8P-21 EAST WEYl10UTH o

sN

"~

g l

Sams w

l m

PEsm l

l L

8 wMw:

$FQT 2 % :2 3' s

ECZ" u,

M x

l B

0.20 -

8 E

0.15 -

0.10 -

0.05 -

0.M JM FT.S tim ffR f1M JUN JUL NJG SEP OCT NOV DEC I

l 1986 l

1 l

III.B. Iodine The same sample collection systems used to collect airborne particulates are used to collect gaseous iodine on a charcoal filter cartridge.

The cartridge is removed and analyzed for I-131 weekly.

The results of the ERMAP program for this media are provided in Table III-B-1.

It is not apparent from this table that the mean value of the calculated concentrations for the indicator stations is greater than the mean value for the control station.

The results of these analyses are presented graphically in Figure III-B-1 for the indicator stations and Figure III-B-2 for the control station.

There were a total of thirteen charcoal filters which were not analyzed during the year of 1986. The charcoal filter at Station #09 (East Breakwater) for week numbers 40 through 52 were not analyzed due to a lack of power to the air sampler.

The lack of power was due to a transformer failure and degradation of electrical cabling.

The MDC for iodine analysis was not met for one sample.

The MDC was not met for Station #17 (Manomet Substation) collected on 8/5/86 due to a low sample volume which was the result of the filter falling out of the holder thereby crimping the line.

The results of the ERMAP Program for charcoal filters is presented in Table III-B-1.

As a result of the Chernobyl accident, positive indications of I-131 were detected in the charcoal filters in all stations from week #20 through week #24 (late May to early June) with the highest concentrations seen during week #21.

The highest mean 3-11

concentration was detected at Station #09 (East Breakwater).

Refer to Appendix F for a summary on the radioactivity detected in environmental media due to the Chernobyl accident, and Appendix G for a tabulation of the measurements.

There was clearly no significant environmental effect observed in the airborne gaseous iodine collection media as a result of the operation of PNPS-1.

I i

3-12 I

l 1

m..

TABLE III-B-1 ERMAP RESULTS CHARC0AL CARTRIDGES 1986 TDIW: CH W 0AL r!LTER lNITS: PCI/0J. M INDICATOR STATIONS STATION WITH HIGHEST EAN CCNTROL STATICNS eeeeeeeeeeeeeeeeee

- eeeeeeeeeeeeeeeeeeeeeen eseeeeeeeeeeeeee RADICtfXLIDES PEAN TAN EAN (W. ANAlv$E5) REC #J! FED RAtGE STA.

RANGE RANCE (NON-ROUTINE)'

LLD NO. DETECTED +e NO.

PT). DETECTEDee NO. MTECTEDee I-131 (550)

.07

(

1.32

.31E -2 09 ( 2.1 i 1.2)E -2

( 1.1 i

.9)E -2

( 2(0

(-2.6 - 42.4)E -2

(-1.6 - 42.4)E -2

(-1.9 - 40.9)E -2 et 45/506)*

et 4/ 39)e e( 4/ 52),

a NON-ROUTINE REFERS TO THE NUMBER CF SEPARATE MEASLREENTS WICH WERE GREATER THAN TEN (10) TIMES TE A'4 RACE BACKCfGND FOR THE PERIOD OF TE REPORT.

ee TE FFACTION OF SAtFLE ANALYMS YIELDING DETECTABLE EASUREENTS (1.E. >3 STD DEVIATIONS! IS INDICATED WITH et le.

l l

l 3-13

10 DINE-131 ON CHARCORL FILTERS INDICRTOR STRTIONS PILGRIM STATION 0.33 0 - AP-00 WAREHOUSE 0.u -

o - AP-01 ROCKY HILL ROAD A - AP-03 ROCKY HILL ROAD

+ - AP-06 PROPERTY LINE 0.s0 -

x - AP-07 PEDESTRIAN BRIDGE o - AP-08 OVERLOOK RRER 0.5 -

V - AP-09 EAST BREAKWATER n

s - AP-10 CLEFT ROCK l

M - AP-15 PLYMOUTH CENTER zoo l

6 0 $0-

+ - AP-17 MANOMET SUBSTATION

%j))

l M85E w

0.35-

@Mdm j

.8 m,9=

9-"-

s " " '

dMW y,W 95

~

M 0.25-

,L B

w

~

8{

0.33-l 0.15 -

0.10 -

0.5 -

0.co l JfW fu ffut FR fWlY JUN JUL fluG SEP OCT NOV DEC 1986

FIGURE III-B-2 CONCENTRATIONS OF I-131 CHARC0AL FILTERS CONTROL STATION tia (1

(!

>E (l(I I

a Il l h

k l1 y

[1 g

d ce c

m i

Ls.1 5

C i

,E l

(

zz 3

0 0

~

C m

o ee n

O cc

( 1 b

E I x

u O Jn

( )

~

zOE o se zJ g

CU g

z, e

z h

y

( le O

lh al d

(I o

Ib d _o

)

e i

5 5

5 8

g 4

q q

q s

a y

d d

O O

8313W *00 / S3!B0000!d 3-15 L_

III.C. Soll Soil surveys at eleven locations are required once every three years in compliance with the revised Technical Specifications which went into effect on April 19, 1977.

These in-situ surveys were conducted during May, October and December of 1982.

The results of these surveys are included in Appendix C of this report.

\\

3-16

III.D. 01ract Radiation 1.

Continuous Thermoluminescent Dosimetry Thermoluminescent dosimeters (TLD) of the CaSO (Dy) type are used 4

to record direct gamma radiation from all sources including direct and scattered radiation from Nitrogen-16 in the turbine building, and cosmic and other natural and artificial gamma radiation.

TLD's are installed at the locations identified in g

Table III-0-1.

Tables III-D-2 through III-D-5 show quarterly average doses from direct gamma radiation in uR/hr at these stations.

In addition to average doses for each TLD for each readout period, geographic regional average doses for sectors of different nearness are computed; viz, in immediate proximity to PNPS, more distant but near the site boundary, up to several miles away

" neighborhood", and far away (background).

Each set of data show consistent trends; the near plant dosimeters (primarily 0A, PB, and HS) stand out among all readings and have an average above the dose rates further away.

The next region has a lower average dose rate, and beyond 0.7 miles (distant neighborhood and background) the dose rates are statistically consistent.

In all cases, the near plant levels are distinctly higher than those off-site and off-site dose rates are not significantly sensitive to distance variations beyond the site i

3-17

itself.

Thus, beyond the " exclusion area" (for this purpose, the 0.25-0.7 mile region), dose rates show no significant plant effect; populated areas are therefore beyond the limits of elevated dose rates.

2.

Field Survey A gamma exposure survey of Plymouth Beach and Priscilla/Hhite Horse Beach was conducted during August of 1986. The results of this most recent survey are in agreement with the last nine beach surveys conducted for 1977 through 1985.

In addition, a comprehensive soil survey of 11 locations was conducted during August of 1985.

This study included both gamma exposure rate

_J 1

measurements and in-situ gamma spectrometry analysis for each location.

Laboratory soil analyses were also conducted for selected locations.

The results of this study are presented in Appendix C.

The latest gamma exposure survey was conducted using a Reuter Stokes RS-111 high pressure ion chamber (HPIC), Serial Number 4-1656.

The design and calibration of this instrument were described in the above report.4 The present survey was designed to detect differences in the external exposure rate encountered at beaches near the plant (Plymouth and White Horse) and a control location (Duxbury).

The detector's calibration was checked before each measurement.

The data (Table III-D-7) indicate that the exposure rates at Plymouth Beach (behind Berts Restaurant) and White Horse Beach are not significantly different from the exposure rates measured at the control station in Duxbury.

3-18

Granite beach stones and gravel are present at t.hese three locations.

It has been demonstrated that proximity to beach stones.results in higher exposure rates than in sandy areas (see Annual Report No. 10).

This survey indicates that the natural background exposure rate at beaches near Pilgrim Station is probably 6-11 UR/hr. These results are in complete agreement with similar measurements performed in Maine 5, where the natural background exposure rate at shoreline locations was found to vary between 6.6 and 14.5 uR/hr.

These exposure rates were also found to vary directly with the size and proximity of granite outcroppings 5, These latest measurements are also in agreement with the soil survey mentioned earlier. The results of that survey indicate that off-site dose rates have a range of 9.3 to 10.5 uR/hr with an average of 9.7 uR/hr.

The survey results are within the expected natural background exposure rates in the northeastern part of the United States.

3-19

r- -

Levet11 ar Statt ama St.atti a $aaf t fMg[ian emer Meat sect.eten aree stateat metenterhood sectoremad Stet ten see Itea e etstance t o.a ta et t es t ta M-a.n to es4.s stimmi (s-n stimmt fade F6e.

ene.

Jedest Dire 11tga_,

Overfose aree 04 II4 9

0.17 ww w5 II-2 23 9.2 SSE Nerone.se 9edestries PS II-2 0

0.17 toes aridge Public Part6ag P4 Il-2 7

0.17 pas area a

II4 5

0.15 Sw-wSW

Property Llae P

83 4 2

0.12 see m

vraperty Llee

Esot great eter 18 II4 10 0.26 ISE Mg~

Property Line S

II4 13 0.28 55f-5 tia O.,

5-$s.,

,re,erty Lle.,,,,

Property time i

II-2 3

0.1 thane.

c

Preserty tone Pt

!!-2 24 0.11 tHand 3g 9re,erty ties e

II-2 i

o.i?

m-man graperty Line t

II-2 22 0.27 f5t gyg wresorty tlae MS I!4 12 8.32 St UD

--(

O D

vreperty Liae C

II4 11 0.3 E5f-5E M

9reperty 14 e II-2 4

0.15 w-tan' 2

(west)

--4 rvy g

sect, wt11 seed tat II4 13 0.3 taas N

(West)

[

o

..re e

or e.1 I4 i.

.0 5

y, e_e Clef t sect area (e

!!-t

?

8.9 5

e-a B

Z U

Rocky utti teed ER II-2 21 08 5E m

e (last) y g

-tey Shere Delee to II-I 6

0.9 tHaed m

Emersen Seed ER II-2 15 1.0 5t-55(

"U 9eeperty Llae J

II-2 19 1.2 5-SSE p

Wreporty Llee (seeth)

E II-2 17 1.2 5

o

" white peerse Boed taf II-2 16 1.25 55E O

4reperty Line a

II4 20 9.2 5-55E Dd neaeast Potat se 13-t e

2.25 r5E-$e Menomet Elem. Scheel ME Il-1 9

2.0 5f O

Rameset Substetten MS II-1 10 2.25 45i 2

M Soutes Plymouth SP II-5 5

3.0 W

Measset teach MS II-I II 3.50 W

Plymouth Center PC II-t 4

4.0 W taed IIerth Plymouth IsP II-1 3

6.0 nasd "Steadish shores (Due) 55 II-t t

7.0 m

Cellege Pead CP II-I 12 5.0 55w-5W Sheemen Alepert (Fly)

SA II-I 14 0.5 WW Cederwille Sub. (Seg)

(5 II-I 13 10.0 5-55E Elagsten Substotloa a5

!! I 2

10.25 han#

East toegesuth Ett 51-1 15 23.0 ene

'not regw6ted by operettag license.

94stences measured fre Ifatt I reetter solid 6ag.

c-GAMMA EXPOSURE (

DA A bRQUARTER#11986 4

Micor/

Station Hour-2 Siama CP 16.28

+-

4.48 CR 18.35

+-

5.05 '

CS 10.80

+-

2.97' ER S

-15.39-

+-

4.24 EH 17.33

+-

'4.77 KS

-20.27

+-

5.58 MB 21.74

+-

5.99-U ME' 15.37

+-

-4.23 MP 16.57

+-

4.56' MS 15.69-

+-

4.32 NP 23.23

+-

6.40 PC

-13.94

+-

3.84 e

SA 26.34

+-

7.25 SP 18.92

+-

5.21 SS

17.48

+-

4.81 l

21.02

+-

5.79 i

HR BD 19.10

+-

5.26 EB 18.65

+-

5.13 EM 13.00

+-

3.58 l

MT 17.44

+-

4.80 OA 25.45

+-

7.01 PA 16.74

+-

4.61 i

PB 26.03

+-

7.17 HH 12.44

+-

3.42 A

16.15

+-

4.45 B

18.21

+-

5.01 18.67

+-

5.14 C

s 0-11.99

+-

3.30 E

21.74

+-

5.99 F

14.04

+-

3.86-G 18.34

+-

5.05 H

9.63

+-

2.65 I

13.61

+-

3.75 J

14.65

+-

4.03 K

17.30

+-

4.76 L

25.01

+-

6.89 PL 19.82

+-

5.46 HS '

29.58

+-

8.14 HB 16.26

+-

4.48 RL 1.61

+-

0.44 l

PL 1.48

+-

0.41 fr.

Geographical Regional Averages for this period are:

l Near Plant (0.16 m!.)

24.45

+-

6.73 Exclusion Area (.25.68 mi.)

17.16

+-

4.72 Distant Nbrhood (.7-6.5 mi.)

17.02

+-

4.69 Background (8-21 mi.)

18.68

+-

5.14 3-21

\\

T' L

.[

TABLE III-D-3 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #2 1986 Micor/

Stationk

_ Hour 2 Siam _a CP 26.35

+-

12.46 CR 8.27

+-

3.91 CS 15.53

+-

7.34 ER 12.14

+-

5.74 EH 13.46

+-

6.36 KS 21.46

+-

10.14 MB 11.25

+-

5.32 ME 16.85

+-

7.96 i

'MP 14.94

+-

7.06 MS 13.64

+-

6.45 NP 15.08

+-

7.13 PC 8.91

+-

4.21 l

SA 11.85

+-

5.60 i

SP 14.53

+-

6.87 l

SS 13.00

+-

6.14 HR 14.08

+-

6.66 l

BD 12.41

+-

5.87 EB 10.94

+-

5.17 l

EM 12.13

+-

5.73 MT 13.61

+-

6.43 l

OA 12.45

+-

5.88 PA 15.08

+-

7.13 PB 19.35

+-

9.15 HH 13.30

+-

6.29 A

14.80

+-

7.00 B

19.83

+-

9.37 C

15.56

+-

7.36 D

ND*

+-

ND E

12.56

+-

5.94 F

13.46

+-

6.36 G

17.20

+-

8.13 H-15.12

+-

7.15 I

9.91

+-

4.68 J

10.66

+-

5.04 K

30.94

+-

14.63 L

31.23

+-

14.76 PL 11.56

+-

5.46 HS 18.80

+-

8.89 HB 17.01

+-

8.04 RL 0.88

+-

0.42 PL 1.78

+-

0.84 Geographical Regional Averages for this period are:

Near Plant (0.16 mi.)

16.42

+-

7.76 Exclusion Area (.25.68 mi.)

15.60

+-

7.37 Distant Nbrhood (.7-6.5 mi.)

15.30

+-

7.23 Background (8-21 mi.)

15.56

+-

7.36 i

ND - No Data due to missing TLD.

3-22

TABLE III-D-4 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #3 1986 Micor/

Station Hour 2-2 Siama CP 5.33

+-

1.16 l

CR 4.88

+-

1.06 CS 9.32

+-

2.02 ER 5.48

+-

1.19 EH 10.06

+-

2.18 KS 4.88

+-

1.06 l

MB 5.03

+-

1.09 l

ME 9.77

+-

2.12 l

MP 5.33

+-

1.16 MS 6.36

+-

1.38 l

NP 7.40

+-

1.60 PC 4.14

+-

0.90 SA 3.85

+-

0.83 SP 12.58

+-

2.73 SS 7.84

+-

1.70 HR 5.48

+-

1.19 i

BD 5.33

+-

1.16 EB 5.03

+-

1.09

-EM 6.07

+-

1.32 MT 6.81

+-

1.48 0A 13.76

+-

2.98 l

PA 10.80

+-

2.34 PB 15.54

+-

3.37 l

HH 9.62

+-

2.08 l

A 5.62

+-

1.22 l

B 6.07

+-

1.32 C

11.54

+-

2.50 0

7.99

+-

1.73 E

3 11

+-

6.74 i

F 4.14

+-

0.90 l

G 5.03

+-

1.09 H

4.44

+-

0.96 I

5.92

+-

1.28 J

3.55

+-

0.77 K

4.14

+-

0.90 L

4.74

+-

1.03 PL 4.06

+-

0.88 HS 4.83

+-

1.05 HB 4.59

+-

0.99 RL 3.26

+-

0.71 PL 7.70

+-

1.67 Geographical Regional Averages for this period are:

Near Plant (0.16 mi.)

11.23

+-

2.43 Exclusion Area (.25.68 mi.)

5.71

+-

1.24 Distant Nbrhood (.7-6.5 mi.)

6.45

+-

1.40 Background (8-21 mi.)

7.03

+-

1.52 3-23 l

W TABLE III-D-5 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #4 1986 Micor/

Station Hour 2 Sigma CP 41.14

+-

10.24 CR 19.83

+-

4.94 CS 9.18

+-

2.28 ER 20.13

+-

5.01 EH

-23.83

+-

5.93 KS 40.11

+-

9.99 MB 22.22

+-

5.53 ME 33.00

+-

8.22 MP 24.27

+-

6.04 MS 20.72

+-

5.16 NP 22.50

+-

5.60 PC 8.44

+-

2.10 SA 19.83

+-

4.94 SP 23.09

+-

5.75 SS 11.99

+-

2.99 HR 25.46

+-

6.34 BD 19.96

+-

4.97 EB 19.54

+-

4.86 EM 19.09

+-

4.75 MT 26.34

+-

6.56 OA 20.72

+-

5.16 PA 26.20

+-

6.52 PB 14.21

+-

3.54 HH 19.54

+-

4.86 A

14.50

+-

3.61 0

19.83

+-

4.94 C

23.83

+-

5.94 D

19.83

+-

4.94 E

22.79

+-

5.67

.F 23.24

+-

5.79 G

18.35

+-

4.57 H

14.65

+-

3.65 I

5.62

+-

1.40' J

17.17

+-

4.28 K

52.24

+-

13.01 L

41.88

+-

10.43 PL 29.60

+-

7.37 HS 23.98

+-

5.97 HB 19.68

+-

4.90 RL-19.24

+-

4.79 PL 25.16

+-

6.26 Geographical Regional Averages for this period are:

Near Plant (0.16 mi.)

21.28

+-

5.30 Exclusion Area (.25.68 mi.)

21.31

+-

5.31 Distant Nbrhood (.7-6.5 mi.)

24.16

+-

6.02 Background (8-21 mi.)

23.24

+-

5.79 3-24

g........................u.............o.

L.

O)

I. 444 64444 4 644444444644 444a444444444446&&44 t 5444 uL e g

m I s

I Cr E.I

.n.:. :................s.........e.......I...........:.....................4...

I I...

.c I

} :*:.

u*

{.

j..............................I,}

i.......................................... - -.

I L.

a) *.Suu4uu4neumsuesuenu44unu4u un u I I

.L I

e m

o I w

I u..n H

s p il n...n..u. n.u..n.

..,u.n.uun.u.n..n..u-3 g

er cr n.

m l...

t j...

w n

I m

m

)

e I m

...t 8

O c

o.

3. nu.n.unn. nun

.n.u 3

5

~

w Lf) w ca m

CD Ch am w

cc J

m jn........n..n..e..-.......n....e....

CO W

c::

=

H cr I

L =

444464448444&&44444&&4&&444444444444464&&

&&44 w

L,

H

G l

g....,

m s

cr g g g o........

..........n....on..

c_,.

aun

....u u...-unn on=....

CT T [

f.G I

C 6

N I j...e!"..

g *t

.S

.i )'g j oon...

..u...oun.

M.

....._.......4...*....t..............H.,

I L

l. announasauunusunaesuusuun I as44 aJ uL 8

{

r0 I

) 1.3 u. n.u.u=n..unu. u.n..n.n.u. a.u...u.

I n.n.

suu n

s

=uw..

e n-

...n.-.

s cr I..

p l l..-

th g I.f ^ {

e-4 1,

' Il n

3, 3.uu n..

.on.n.

n I

l

TABLE III-D-7 1986 DIRECT RADIATION SURVEY RESULTS Exposure Rate Location

.(UR/hr+-l siama).

Beach Terrain White Horse Beach 7.0 0.3 Sandy.

Few granite (near Hill P. Avenue) boulders within thirty feet.

White Horse Beach 7.4 0.6 Sandy with small amount (in back of Blue Sail Bar) of gravel.

Plymouth Beach 6.8 0.3 Sandy.

(outer beach)

Plymouth Beach 6.0 0.5 Sandy.

(inner beach)

Plymouth Beach 7.7 0.5 Sandy.

Breakwater and behind Berts Restaurant seawall nearby.

Duxbury Beach'(Control) 7.7 0.5 Sandy with course gravel.

(ccean side)

P i

r l

3-26 i

III~.E. Haterborne Samples of seawater are collected at three locations, the Discharge Canal (Station 11), Bartlett Pond (Station 17-1.7 mi-SE) and Powder-Point (Station 23-7,8 mi-NNW). The Discharge Canal sample is collected by a continuously compositing sampler which extracts a sample of about 20 ml of water from the Discharge Canal every one-half hour. Grab samples are taken weekly from each of the other two locations.

The results of the ERMAP program for seawater samples are presented in Table III-E-1.

There were no positive measurements of nuclides characteristic of reactor operation observed at any of the three sampling locations.

The only positive measurements observed were due to naturally occurring nuclides (K-40 and AcTh-228).

Therefore, there was clearly no significant environmental effect observed in the seawater media as a result of the operation of PNPS-1.

3-27

TABLE III-E-1 ERMAP RESULTS WATERBORNE 1986 EDIUM: SEAWATER LNITS: PCI/KG INDICATCR STATICNS STATION WITH HIGEST EAN CONTROL STATICNS nuvenenennu neuenennuununn unnenennu RADICNUCLICES EAN EAN EAN (NO. ANALYSES)

REQUIRED RAl0E STA.

RANGE RANGE (NON-ROUTINEl' LLD NO. IETECTEDee NO.

NO. DETECTEDee NO. DETECTEDen BE-7

( 36)

(

2.3t 1.5)E O 17 ( 5.0 1 2.0)E O

(-3.2 f 2.1)E 0

( 0)

(-1.4 -

1.9)E 1

(-3.8 - 19.4)E O

(-1.1 -

1.0)E 1 et 0/ 24)*

(

0/ 12)*

et 0/ 121e K-40

( 36)

(

l.5i

.3)E 2 11

( 3.1 i

.1)E 2

( 2.9 i

.1)E 2

( 0)

(-2.4 - 33.7)E 1

( 2.8 -

3.4)E 2

( 2.6 -

3.2)E 2 a( 12/ 24)*

( 12/ 12)*

( 12/ 12)e FN-54 ( 36) 15.

(

1.8t 1.5)E -1 17 ( 1.8 i 1.8)E -1

(-4.5 t 2.7)E -1

( 0)

(-1.9 -

1.3)E O

(-9.0 -

9.7)E -1

(-1.6 -

.9)E O et 0/ 24)*

(

0/ 12)e et 0/ 12)e CO-58 ( 36) 15.

( -1.11 1.8)E -1 17

(-5.7 i 30.6)E -2

(-4.9 i 2.8)E -1

( 0)

(-1.8 -

2.1)E O

(-1.8 -

2.1)E 0

(-2.7 -

1.01E O

(

0/ 24)*

(

0/ 12)*

(

0/ 12)e FE-59 ( 361 30.

(

1.3t

.4)E O 17 ( 2.1 i

.4)E O

( l.4 i

.8)E 0 4.9)E O

(-5.1 - 49.0)E -1

(-4.0 -

4.5)E 0

( 0)

(-4.1

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

CD-60 ( 36) 15.

( -5.5f 1.9)E -1 23

(-3.1 i 3.4)E -1

(-3.1 1 3.4)E -1

( 0)

(-2.6 -

1.4)E 0

(-2.2 -

1.6)E 0

(-2.2 -

1.6)E O

(

0/ 24)*

(

0/ 121e et 0/ 12)e IN-65 ( 36) 30.

( -3.0t 52.6)E -2 17 ( 3.6 i 7.1)E -1

(-5.3 i 5.2)E -1

( 0)

(-6.1 -

5.0)E 0

(-3.4 -

4.7)E 0

(-3.9 -

2.1)E O et 0/ 24)*

(

0/ 12)e et 0/ 12)e ZR-95 ( 36) 15.

( -2.9t 3.4)E -1 17

(-5.0 i 571.4)E -3

(-2.8 i 4.4)E-1

( 0)

(-3.9 -

3.3)E 0

(-3.9 -

3.3)E 0

(-3.1 -

1.8)E 0

(

0/ 24)*

(

0/ 12)*

(

0/ 12)e RU-103 ( 36)

( -5.8t 2.7)E -1 11

(-5.0 i 4.0)E -1

(-5.1 i 2.8)E -1

( 0)

(-2.4 -

2.2)E O

(-2.4 -

2.2)E O

(-1.5 -

1.6)E 0 e( 0/ 24)e

(

0/ 12)*

a( 0/ 12)*

NON-ROUTIE REFERS TO TE NUPEER OF SEPARATE EASLREENTS WHICH ERE GREATER THAN TEN (10) TIES TE AVERAGE BACK0R0thT; FOR TE FERIOD OF TE REPORT.

n TE FRACTICN OF SAMPLE ANALYSES Y!ELDING DETECTAltE EAAREENTS (1.E. >3 STD DEVIATICNS) IS INDICATED WITH et le.

3-28 l

TABLE III-E-1 (CONTINUED)

EDilN: SENATER LNITS: PCI/KG INDICATCR STATIONS STATION WITH HIGHEST EAN CONTRCL STATIONS enunennunu unnennunenunen eunnennun AADIO*.UCLIDES MEAN EAN EAN (NO. ANALYSES) RENIFED RANGE STA.

RAKE RANCE (NON-RX! TINE)'

LLD NO. DETECTED **

NO.

NO. DETECTED **

RU-106 ( 36)

( -7.91 14.3)E -1 23 (1.11 2.1)E O (1.11 2.1)E O

( 0)

(-1.3 -

1.1)E 1

(-9.7 - 17.9)E O

(-9.7 - 17.9)E O at 0/ 24)*

(

0/ 12)*

st 0/ 12)e 1-131 ( 36) 1.

( -5.51 16.2)E -2 23

( 3.2 i 2.4)E -1

( 3.2 1 2.4)E -1

( 0)

(-3.6 -

1.1)E O

(-2.9 - 29.0)E -1

(

0/ 24)*

a( 1/ 12)*

(

1/ 121e l

CS-134 ( 36) 15.

( -3.21 1.8)E -1 11

(-3.1 i 2.7)E -1

(-9.5 i 1.8)E -1 l

( 0)

(-1.8 -

1.3)E 0

(-1.8 -

1.2)E O

(-2.4 -

.1)E O

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

CS-137 ( 36) 18.

(

!.71 1.9)E -1 11

( 4.9 i 2.7)E -1

( 4.7 t 3.0)E -1

( 0)

(-1.4 -

1.9)E 0

(-1.2 -

1.9)E O

(-1.3 -

2.1)E O

(

0/ 24)*

a( 0/ 12)*

(

0/ 12)*

BA-140 ( 36) 15.

( -7.21 5.2)E -1 23

(-1.5 i 6.5)E -1

( 0)

(-6.2 -

3.3)E 0

(-3.2 -

3.9)E 0

(-3.2 -

3.9)E O

(

0/ 24)*

(

0/ 12)*

e( 0/ 12)*

CE-141 ( 36)

(

2.Si 4.2)E -1 17

( 4.7 i 6.1)E -1

(-3.2 i 5.8)E -1

( 0)

(-3.4 -

3.9)E 0

(-2.4 -

3.9)E 0

(-2.6 -

3.1)E 0

(

0/ 24)e

(

0/ 12)*

(

0/ 12)*

CE-144 ( 36)

(

9.7i 9.8)E -1 17

( 2.7 i 1.4)E 0

( 2.0 i 2.0)E O

( 0)

(-1.1 -

.9)E 1

(-4.6 -

9.3)E 0

(-7.2 - 14.4)E 0 et 0/ 24)e

(

0/ 12)*

(

0/ 12)*

TH-232 ( 36)

(

2.41

.5)E O 11

( 3.0 t

.9)E 0

( 1.8 i 1.0)E O

( 0)

(-1.2 - 10.6)E O

(-5.9 - 106.0)E -1

(-4.2 -

6.5)E 0

(

1/ 24)*

(

1/ 12)*

(

0/ 121e H-3

( 12) 3000.

(

l.81

.5)E 2 11

( 1.9 i

.9)E 2

( 1.0 i 1.4)E 2

( 0)

(-7.0 - 35.0)E 1

(-7.0 - 34.0)E 1

(-2.9 -

3.9)E 2

(

0/ Ble

(

0/ 4)*

(

0/ 4)*

NEN-ROUTIE REFERS TO TE NLMBER OF SEPARATE EASUREENTS WHICH WERE GREATER l

THAN TEN (10) TIES TE A'4 RAGE BACK0ROUND FCR THE PERIOD 0F TE REPORT.

l

- THE FRACTION OF SAPPLE ANALYSES YlELDING XTECTABLE EASUREENTS (1.E. 33 STD DEVIATIONS) IS INDICATED WITH *(

)*.

3-29 i

-III.F. Shellfish Shellfish are normally sampled quarterly from 5 locations: the Station Discharge Canal, Duxbury Bay, Manomet Point, Harren Cove and Marshfield.

The results of the ERMAP program for shellfish are presented in Table III-F-1.

It is clear from this table that there have been positive measurements of Be-7, Mn-54, Co-6G, AcTh-228 and K-40.n samples from the Discharge Canal.

In addition there have been positive measurements of Be-7, Mn-54, Co-60, AcTh-228 and K-40 at Manomet Point; Be-7, AcTh-228 (peak) and K-40 at Harren Cove; AcTh-228 and K-40 at Duxbury Bay; and, Be-7, AcTh-228 and K-40 at the control station in Marshfield. There was one positive measurement of Ru-103 at Manomet Point in a sample which was collected on 7/8/86.

The observed concentrations of Mn-54 and Co-60 were the result of PNPS-1 liquid releases.

However, the observed concentration of Ru-103 occurred in early July when radioactivity from the Chernobyl accident l

was still being detected in environmental media.

Since Ru-103 was not detected in samples collected from the Discharge Canal, the contribution of Ru-103 was due to Chernobyl-related radioactivity.

Refer to Appendix F for a summary on the radioactivity detected in environmental media due to the Chernobyl accident.

The observed concentrations of Be-7, AcTh-228 and K-40 are due to the natural occurrence of these nuclides.

3-30

However, even if a person were to consume the maximum. annual quantity of seafood (5 kilograms / year) with the highest mean concentrations of the above nuclides, _ they would receive a dose of less than 0.007 mrem i

to the total body and less than 0.02 mrem to the most restrictive organ (Adult, GI-LLI).

When compared to the natural background dose rate of 80-100 mrem / year, there was clearly no significant environmental impact observed in shellfish as a result of the operations of PNPS-1.

3-31

. TABLE III-F-1 ERMAP RESULTS SHELLFISH 1985 EDILM SHELLFISH LEITE: PCI/KG WET INDICATOR STATIONS STATICN WITH HIGHEST EAN CONTRR S!*TIONS ffffttitiftfiftffe itif9ffffffffffffftttffff eleffffetettffff RADIONUCL!riS NEAN EAN EAN (NO. ANALYSES) REff)! PED RANCE STA.

RANGE RANGE

( 6 -ROUTINEF LLD-NO. IETECTED**

NO.

NO. DETECTED **

NO. IETECTED++

BE-7 ( 40)

(

2.8t

.5)E 1 13 ( 3.5 i 1.1)E I

( 3.2 *

.4)E 1

( 01

(-2.5 - 11.9)E 1

(-7.5 - 92.0)E O

( !.7 -

4.8)E 1

( 10/ 32)*

(

0/ Ble

( 6/ 8)*

K-40

( 40)

(

1.lt

.1)E 3 15 ( l.7 i

.1)E 3

( 9.5 t 2.6)E 2

( 0)

( 5.5 - 248.0)E 1

( 1.6 -

1.9)E 3

( 2.3 - 18.2)E 2

( 29/ 32)*

(

4/ 4)*

e( 8/ Ble MN-54 ( 40) 130.

(

!.51 1.0)E O 12 ( !.8 i 2.0)E O

(-4.4 1 2.7)E -1

( 0)

(-9.8 - 15.5)E 0

(-9.8 - 15.5)E O

(-9.9 - 13.2)E -1 et 2/ 32)*

(

0/ 12)*

(

0/ 8)e C0-58 ( 40) 130.

(

6.4t 9.8)E -1 12 ( 3.1 1 2.3)E O

( 1.3 t 25.1?E -2

( 0)

(-9.8 - 21.7)E O

(-7.9 - 14.1)E -1 at 0/ 32)*

(

0/ 121e

( 0/ Sie FE-59 ( 40) 260.

( 3.Si 25.9)E -1 12 ( 5.1 i 5.6)E O

( 1.3 *

.8)E 0

( 0)

(-4.2 -

4.6)E 1

(-2.0 -

4.6)E 1

(-1.3 -

6.4)E O

(

0/ 321e

(

0/ 12)e et 0/ 8)*

CO-60 ( 40) 130.

(

1.92

.7)E 1 11

( 7.7 t 1.7)E 1

(-6.4 i 4.9)E -1

( 4)

(-1.3 - 13.8)E 1

( 2.0 - 13.8)E 1

(-2.2 -

1.7)E 0

( 10/ 32)e a( 8/ 8)e

(

0/ Ble ZN-65 ( 40) 260.

(

2.12 26.0)E -1 11

( 2.9 t 1.0)E 0

( 1.9 t

.7)E O

( 0)

(-4.0 -

3.6)E 1

(-1.4 -

7.4)E 0

(-2.2 -

4.1)E 0 el 0/ 32)*

(

0/ Ble

(

0/ 8)*

ZR-95 ( 40)

(

!.6t 1.9)E O 12 ( 3.6 i 4.9)E 0

( 1.4 *

.7)E O

( 0)

(-2.5 -

3.3)E 1

(-2.5 -

3.3)E 1

(-9.5 - 46.2)E -1 et 0/ 321e

(

0/ 12)e

( 0/ 8)*

RU-103 ( 40)

(

2.5t !!.2)E -1 13 ( 1.6 i 1.8)E O

(-6.2 i 5.4)E -1

( 0)

(-1.8 -

2.1)E 1

(-8.9 -

5.2)E O

(-3.2 -

2.1)E 0

(

1/ 321e

(

0/ 8)*

(

0/ 8)*

NON-POUTINE REFERS TO TE MBER OF SEPARATE EASLREENTS WHICH WERE GREATER THAN TEN (10) TIMES TE AVERAGE BACKGRL1JND FCR THE PERIOD OF TE REPORT.

- TE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE MEASLREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *f 1*.

3-32

TABLE III-F-1 (CONTINUED)

MEDIUM: SHELL7I91 Le:I!S: PCING ET IND]CATOR STATION 3 STATION WITH HIGHEST MEAN CCNTROL STATI(tis

- - +***+**********

++++++,,,,,es*,eeeeeee*,e RADIONIXLICES EAN MEAN MEAN (N0. ANALYSES!

RFAIIRED RANGE STA.

RANC{

RANGE (NCN-ROUTINEF LlD NO. [C ECTED+4 NO.

NO. IETECTED+e NO. DETECTE0**

TdJ-106 ( 40)

( -7.61 6.9)E O 11

( !.01 26.9)E -1

(-2.7 1 3.1)E 0

( 0)

(-9.8 -

8.1)E 1

(-1.2 -

1.0)E 1

(-1.6 -

9)E 1

(

0/ 32)*

( 0/ 8)*

( 0/ 8)*

I-131 ( 40)

(

8.3t.5.0)E O 12 ( 2.4 i 1.1)E I

(-1.9 i 1.6)E O

( 0)

(-3,0 -

9.6)E 1

(-2.2 -

9.6)E 1

(-6.9 -

7.8)E 0

(

0/ 32)*

(

0/ 12)*

( 0/ 8)*

CS-134 ( 40) 130.

(

-3.?*

.8)E O 11

(-5.1 i 2.2)E -1

(-1.0 i

.2)E O

( 0)

(-2.1 -

.1)E 1

(-1.2 -

.4)E 0

(-2.2 -

.7)E O

(

0/ 32)*

(

0/ 8)*

(

0/ 8)*

CS-137 ( 40) 130.

(

2.41

.8)E O 12 ( 5.3 i 1.8)E O

( 7.6 i 3.3)E -1

( 0)

(-4.0 - 22.8)E 0

(-7.6 - 228.0)E -1

(-2.4 - 25.0)E -1

(

0/ 32)*

(

0/ 12)*

(

0/ 8)*

BA-140 ( 40)

( -5.71 3.2)E O 11

( 6.7 i - 10.9)E -1

(-5.0 i 11.6)E -1

( 0)

(-6.0 -

3.5)E 1

(-3.7 -

5.0)E O

(-7.1 -- 3.2)E O

(

0/ 32)*

a( 0/ 8)*

(

0/ 8)*

CE-141 ( 40)

(

4.8i 2.4)E O 13 ( 1.5 i

.6)E 1

( !.2 i

.8)E O

( 0)

(-2.1 -

4.1)E 1

(-1.0 -

4.1)E 1

(-2.7 -

4.3)E 0

(

0/ 32)*

(

0/ 8)*

et 0/ 8)*

CE-144 ( 40)

( -7.Si 6.4)E O 15 ( 2.6 i 1.7)E 0

( 1.0 i 1.2)E O

( 0)

( 10. - 11.0)E 1

(-1.1 -

6.4)E 0

(-3.5 -

5.5)E 0

(

0/ 32)*

(

0/ 4)*

(

0/ 8)*

TH-232 ( 40)

(

3.51

.7)E 1 12 ( 5.7 i 1.2)E 1

( 2.1 i

.5)E 1

( 0)

(-3.5 - 12.2)E 1

( 2.6 - 122.0)E O

( 5.6 - 38.3)E O

( 12/ 32)*

(

4/ 12)e

(

4/ 8)*

NON-ROUTINE REFERS TO THE Nlt9ER CF SEPARATE EASLREENTS WHICH ERE GREATER THAN TEN (10) TIES THE AVERAGE BACKGROLND FCR THE PERIOD OF TE REPORT.

- THE FRACTION OF SAPPLE ANALYSES Y!ELDIN0 DETECTABLE MEASLREENTS j

I (I.E. >3 STD DEVIATIONS) IS INDICATED W!TH *(

).

I 3-33 l

i III.G. Alcae (Irish Moss)

Algae, referred to as Irish Moss or Chondrus Chrispus, is sampled quarterly at three locations, the PNPS Discharge Canal, Manomet Point and Ellisv111e.

The results of the ERMAP program for Algae are presented in Table III-G-1.

It is clear from this table that there have been positive measurements of Be-7, Co-60, Ru-103 and K-40 at the Discharge Canal.

In addition, there have been positive measurements of Be-7, Co-60, Ru-103, I-131, AcTh-228 and K-40 at Manomet Point (Station 15-3 miles-SE); and Be-7, l

l Co-60, Ru-103, AcTh-228 and K-40 at the control station of Ellisville (Station 22-8 mi-SSE). Due to the positive measurements of reactor related nuclides at Station #22, samples were collected from another control station for each quarter of 1986.

This control station was established at Brant Rock (Station 34-12 mi-NNW).

The only observed positive measurements of Brant Rock samples were Be-7, Ru-103, AcTh-228 (peak) and K-40.

The measured concentrations of Co-60 at the Discharge Canal are certainly due to liquid effluents from PNPS-1.

The observed concentrations of Co-60 at Manomet Point and Ellisville were the result of PNPS-1 liquid releases.

The highest concentration of Co-60 was seen at the Discharge Canal.

The prevailing surface currents along the shoreline in the Plymouth area is in the southerly direction.

There were no positive measurements of PNPS-1 reactor related nuclides at the control station in Brant Rock, approximately twelve miles away the NNW sector.

3-34

The measured concentrations of Ru-103 at each station and I-131 at Hanomet Point were due to Chernobyl-related radioactivity.

The highest concentration of Ru-103 was seen at the Brant Rock control station.

These samples were all collected during the month of June when radioactivity due to the Chernobyl accident was being detected in various media in the northeastern United States.

Refer to Appendix F for a summary on the environmental radioactivity from the Chernobyl accident, and Appendix G for a tabulation of the measurements.

It is important to note that due to processing and market dilution, the presence of the Co-60 concentrations do not represent a significant potential source of dose to the general public.

In fact, even direct human consumption of Algae (which to our knowledge, does not occur) with the highest mean concentrations would result in a dose rate of about 0.03 mrem /yr to the total body and less than 0.03 mrem /yr to the most sensitive organ (Adult-GI-LLI, using the models presented in Regulatory Guide 1.109) and assuming consumption of 5 kg/ year of unprocessed material. When compared with the natural background dose rate of 80-100 mrem /yr, there was clearly no significant environmental impact observed in Algae as a result of the operation of PNPS-1.

3-35

TABLE III-G-1 ERMAP RESULTS ALGAE 1986 EDIUM: ALC4E UNITS: PCl/KG 'ET INDICATCR STATIONS STATION WITH HIC 4EST EAN CCNTROL STATIONS nunnenennee nununeneen+eemn ennuenunn CDIONUCLIIES MEAN EAN EAN (NG. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (id K CTINE)'

LLD NO. DETECTED **

NO.

NO. DETECTED *e NO. DETECTED *e IE-7

( 20)

(

1.61

.2)E 2 22 ( 2.6 i

.4)E 2

( 2.1 i

.3)E 2

( 0)

( 4.8 - 235.0)E O

( 1.2 -

3.4)E 2

( 9.3 - 34.1)E 1

(

8/ 10)*

(

5/ 5)e

( 10/ 10)*

K-40

( 20)

(

6.42 61E 3 11

( 8.1 i

.4)E 3

( 5.3 *

.3)E 3

( 0)

( 4.1 -

9.4)E 3

( 7.3 -

9.4)E 3

( 4.1 -

7.3)E 3

( 10/ 10)*

(

5/ 5)e

( 10/ I0le tW-54 ( 20) 130.

(

1.81 1.8)E O 11

( 3.8 t 3.1)E O

(-1.1 1 1.2)E O l

( 1)

(-3.9 - 15.2)E O

(-2.7 - 15.2)E O

(-8.1 -

3.7)E O

(

1/ 10)*

(

1/ SH

(

0/ 10)e C0-58 ( 20)

(

2.0t 1.9)E O 11

( 3.2 1 3.9)E 0

(-2.4 t 17.8)E -1

( 0)

(-9.7 - 14.7)E 0

(-9.7 - 14.7)E O

(-1.2 -

.7)E 1

(

0/ I0le

(

0/ 5)*

(

0/ 10)*

l FE-59 ( 20)

( -2.0t 2.5)E O 22 ( 1.6 i 4.6)E 0

( 1.4 i 2.7)E 0

( 0)

(-1.1 1.1)E 1

(-1.2 -

1.2)E 1

(-1.2 -

1.3)E 1

(

0/ 10)*

(

0/ 5)*

(

0/ 10)*

CD-60 ( 20)

(

4.91 1.5)E 1 11

( 8.8

1.7)E 1

( 3.5 i 1.6)E 0

( 4)

(-2.7 - 1160.0)E -1

( 3.3 - 11.6)E 1

(-5.5 - 14.0)E O at 7/ 10)*

(

5/ 5)e et 1/ 10)*

ZN-65 ( 20)

( -5.8t 37.6)E -1 22 ( 7.5 i 5.7)E 0

( 6.7 i 3.6)E O

( 0)

(-1.3 -

2.9)E 1

(-4.7 - 27.6)E 0

(-4.7 - 27.6)E O

(

0/ 10)e

(

0/ 5)*

(

0/ 10)e ZR-95 ( 20)

(

1.51 3.0)E O 15 ( 5.6

3.6)E 0

(-8.0 i 15.0)E -1

( 0)

(-1.2 -

1.9)E 1

(-9.3 - 188.0)E -1

(-8.8 -

5.7)E O

(

0/ 10)e et 0/ Sie

(

0/ 10)*

RU-103 ( 20)

(

6.11 2.7)E O 34

( 8.5 i 6.9)E 0

( 7.8 i 3.5)E 0

( 0)

(-8.8 - 20.0)E O

(-1.7 - 35.8)E O

(-2.5 - 35.8)E O et 2/ 10)e

(

1/ 5)*

(

2/ 10)e e NON-ROUTINE REFERS TO TE NJfGER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES TE A'iRAGE BACKGROLND FOR TE PERIOD OF TE REPORT.

ee TE FRACTION OF SAMFtE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. >3 STD CEVIATIONS) IS INDirATED WITH *(

H.

l 3-36 1

TABLE III-G-1 (CONTINUED)

PEN!S ALC4 UNITS: PCI/r0 WET INDICATM STATI0fG STATION WITH H!C+EST EAN CONTROL STATIONS

nnunennun nen utenen n en a n n nennuttuun RADiCe.1)CLIDES TEAN EAN EAN (NO ANALYSESi K0UIRED RANCE STA.

RANGE RANGE (40N-R0eTINEi' t.LD NO. ETECTED**

NO.

NO. DETECTEDe*

NO. DETECTEDee R'J-106 ( 20)

(

6.2t 11.4)E O 11

( 2.0 i 1.8)E 1

( !.1 i

.8)E 1

( 0)

(-3.7 -

8.61E 1

(-1.9 -

8.6)E 1

(-1.5 -

8.1)E 1

(

0/ I0le

(

0/ Sie

(

0/ 10)e I-131 ( 20)

(

1.42 1.5)E 1 22 ( 2.7 i 3.0)E 1

( 2.1 i 1.5)E 1

( 1)

(-6.7 -

7.4)E 1

(-5.0 - 10.6)E 1

(-5.0 - 10.6)E 1-

(

1/ 10)*

( 0/ 5)*

(

0/ 10)*

CS-134 ( 20)

( -7.lt 10.1)E -1 15

(-3.2 i 9.9)E -1

(-1.5 i

.61E O

( 0)

(-5.7 -

3.9)E O

(-3.1 -

2.2)E O

(-4.4 -

1.8)E 0 of 0/ 10)e et 0/ 5)e et 0/ 10)*

CS-137 ( 20)

(

2.lt 1.3)E 0 11

( 2.9 i 2.3)E O

( 1.4 i

.9)E O

( 0)

(-3.1 -

8.7)E 0

(-3.1 -

8.7)E 0

(-2.4 -

7.1)E O

(

0/ 101s

( 0/ 5)*

(

0/ 10)*

BA-140 ( 20)

( -8.2t 3.9)E O 22 ( !.6 i 4.3)E O

(-3.5 i 29.7)E -1

( 0)

(-2.7 -

.8)E 1

(-7.8 - 17.3)E O

(-1.5 -

1.7)E 1

(

0/ 10)e s( 0/ 5)*

s( 0/ I0le CE-141 ( 20)

(

2.!*

2.2)E O 15 ( 5.1 i 2.1)E O

( 7.5 i 18.1)E -1

( 0)

(-8.6 - 12.01E O

(-1.5 - 120.0)E -1

(-6.7 - 12.4)E O at 0/ 10)e

(

0/ 5)*

(

0/ 10)e CE-144 ( 20)

( -5.4f 6.5)E O 34

( 1.1 t

.4)E 1

( 5.2 t 5.5)E O

( 0)

(-5.4 -

1.3)E 1

( 2.3 - 22.3)E O

(-2.1 -

3.5)E 1 s( 0/ 10)e

(

0/ 5)*

(

0/ 10)e TH-232 ( 20)

(

2.2i

.5)E 1 22 ( 5.9 i

.9)E 1

( 3.6 i 1.0)E 1

( 0)

(-2.0 -

3.9)E 1

( 2.4 -

8.0)E 1

(-2.5 -

8.0)E 1

(

1/ I0le

(

4/ Sie et 5/ 10)*

NON-ROUTIE REFERS TO TE IGBER OF SEPARATE EASLREENTS IMICH ERE CREATER THAN TEN (10) TIES TE AVERAGE BACKCR0lND Fm TE PERIOD OF TE REPET.

H THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE EASLREENTS

(!.E. >3 STD KVIATIONSI IS INDICATED WITH *(

le.

3-37

III.H. Lobster (Arthrocods)

Lobster samples are collected four times per season in the vicinity of the Discharge Canal Outfall area and annually at a distant point offshore.

The results of the ERMAP program for Lobsters are presented in Table III-H-1.

These results are unremarkable in that there were no positive measurements of any isotopes other than K-40 in either the indicator or the control samples (K-40 is a naturally occurring nuclide).

Therefore, there is no evidence of any environmental impact on this media as a result of the operation of PNPS-1.

i l

i 3-38

TABLE III-H-1 ERMAP RESULTS LOBSTER 1986 MED1!!"; LO!GTER UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS

eeeee****e++,eeve seseee*****eeenseeeeeeeee ese***eeeeen,***

RADIONUCLl(Es EAN EAN EAN tNO. ANALYSES) REQUIRED RAfEE STA.

RANGE RANGE 1'ON40VTINEi '

-LLD NO. DETECTED +,

NO.

NO. DETECTEDee NO. [ETECTEDee

=-

BE-7

( 5)

(

8.21 26.3)E O 12 ( 1.1 i

.9)E 2 NO DATA

( 0)

(-4.1 -

10.7)E 1

(

0/ 5).

(

0/ 1)e K-40

( 5)

(

2.31

.1)E 3 12 ( 2.3 i

.2)E 3 NO DATA

( 0)

( 2.1 -

2.5)E 3 et 5/ 5),

(

1/ 1)e NN-54 ( 5) 130.

( -3.21 3.7)E O 11

(-3.2 1 4.8)E O N0 DATA

( 01

(-1.4 -

9)E 1

(-1.4 -

.9)E 1

(

0/ 5)*

(

0/ 4)*

!00-58 ( 51 130.

( -9.9t 32.8)E -1 12 ( 5.4 i 9.9)E O NO DATA

( 0)

(-1.2 -

.5)E 1 et 0/ 5),

(

0/ 1)*

FE-59 ( 5) 260.

( -2.6t 6.3)E O 11

( 2.1 i 73.1)E -1 NO DATA

( 0)

(-1.4 -

1.8)E 1

(-1.2 -

1.8)E 1

(

0/ 5)e et 0/ 4)*

CD-60 ( 5) 130.

(

1.01

.3)E 1 11

( 1.2 i

.4)E 1 NO DATA

( 0)

( 3.8 - 18.3)E 0

( 3.8 - 18.3)E O

(

0/ 5)*

a( 0/ 4),

ZN-65 ( 5) 260.

(

4.2t 10.1)E O 12 ( 3.2 i 2.1)E 1 NO DATA

( 0)

(-3.1 -

3.2)E 1

(

0/ 5)e

(

0/ 1)e ZR-95 ( 5)

( -2.7i 7.0)E O 11

(-2.0 t 8.9)E O NO DATA

( 0)

(-1.6 -

2.2)E 1

(-1.6 -

2.2)E 1

(

0/ 5),

(

0/ 4)*

RI-103 ( 51

( -6.7f 3.3)E O 12 ( 2.9

10.8)E O NO DATA

( 0)

(-1.6 -

.3)E 1

(

0/ 5),

et 0/ 1)*

NON-ROUTINE REFERS TO TE f23ER OF SEPARATE EEREMENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR THE PERIOD OF TE REK1RT.

e.

THE FRACTION CF SAMPLE ANALYES YIELDING DETECTAKE MEASUREENTS II.E. :>? STD [EVIATIOC IS INDICATED WITH et le.

3-39

TABLE III-H-1 (CONTINUED)

MEDIly: ' OFTER LNITS: PCI/f0 WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS ennnonunne nunnennunnenen nununnun CD!0PJfLILE!

MEAN EAN EAN (NO. ANALYSES 1 RE7)! RED PM{

STA.

RAN0E RANCE (NON41)UTIPEl' U_D N0. DETECTED **

NO.

NO. DETECTEDn NO. DETECTED **

R'J-106 ' 5)

(

7.6f 25.9:E O 12 ( 6.4 i 8.2)E 1 N0 DATA

( 0)

(-6.4 -

6.4)E 1

(

0/ Sie

(

0/ 1)*

I-13) ( 5)

( -5.6t 19.5)E O 11

( 1.2 i 1.1)E 1 NO DATA

( 01

(-7.5 -

3.3)E 1

(-2.0 -

3.3)E 1

(

0/ 5)*

(

0/ 4)*

CS-134 ( 5) 130.

( -5.91 4.5)E O 12 ( 6.7 i 10.3)E O NO DATA l

( 01

(-1.9 -

.7)E 1

(

0/ 5)*

(

0/ 1)*

i l

CS-137 ( 5) 130.

(

5.2i 35.2)E -1 11

( 1.1 1 4.5)E O NO DATA

( 0)

(-9.9 -

11.2)E O

(-9.9 - 11.2)E O

(

0/ 5)*

(

0/ 4)e BA-140 ( 5)

( -3.7f 9.1)E O 12 ( 2.2 i 3.0)E 1 NO DATA

( 0)

(-2.9 -

2.21E 1

( 0/ 5)*

(

0/ 11e CE-141 ( 5)

(

1.3t

.6)E 1 11

( 1.7 i

.6)E 1 NO DATA

( 0)

(-4.? - 25.7)E O

( 1. 2 - 25.7)E O

(

0/ 5)*

(

0/ 4)*

CE-144 ( 5)

( -1.41 2.2)E 1 11

(-1.1 i 2.9)E 1 NO DATA

( 0)

(-8.5 -

5.1)E 1

(-8,5 -

5.1)E 1

( 0/ 5)*

(

0/ 4)*

TH-232 ( 5)

(

2.41 1.4)E 1 12 ( 3.0 t 3.8)E 1 N0 DATA

( 0)

(-2.3 -

5.4)E 1

(

0/ 5)e

( 0/ 1)*

NON-ROUTIE REFERS TO THE NUMBER OF SEPARATE EASUREENTS W(ICH ERE C4tEATER THAN TEN (10) TIES TE AVERACE BACK0R0lND FOR TE PERIOD OF TE REPORT.

- TE FRACTION CF SAPPLE ANALYSES YIELDING DETECTABLE EASUREEITS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le.

3-40

III.I. Elih Fish samples of Bottom Oriented (Group I) and Near Bottom (Group II) species are collected quarterly in the vicinity of the Discharge Canal Outfall.

In addition, samples of Anadromous (Group III) and Coastal Migratory (Group IV) species are collected when in season, in this same area.

Lastly, a sample from each group is collected once per year at a distant location offshore.

During 1986, two Group II samples were unavailable in the first quarter, and one Group III sample was unavailable in the second quarter.

l The result of the ERMAP program of fish are presented in Table III-I-1.

There was a positive measurement of Cs-137 at the indicator station (Discharge Canal - Station 11) during the fourth quarter.

A striped bass sample collected on 10/2/86 at the Discharge Canal Outfall Area indicated a positive measurement of Cs-137. The striped l

bass is in the Group III category (Anadromous).

Even if an individual were to consume the maximum annual quantity of fish (21 kilograms / year) with the highest mean concentration of Cs-137, they would receive a dose of less than 0.02 mrem to the total body and about 0.07 mrem to the most restrictive organ (Adult - Liver).

Therefore, there is little evidence of any environmental impact on this media as a result of the operation of PNPS-1.

3-41 t

I e.

=,,

TABLE III-I-l ERMAP RESULTS FISH 1986 MEDIUM: F'NFMN UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIC +EST EAN CONTROL STATION 3 n u n n u nenete nunnennnuneuen nennennun RADICfELIDES MEAN EAN EAN (NO. ANALYSESI REQUIRED FANGE STA.

RANCE RANGE fNON-ROUTINE 1' LLD NO. DETECTEDet NO.

W. DETECTEDet NO. ETECTEDee BE-7 ( 35)

(

t.81 1.4)E 1 90

( 9.9 t 5.8)E 1

( 3.6 i 3.7)E 1

( 0)

(-1.7 -

1.6)E 2

(-8.2 - 12.0)E 1

(

0/ 30)e

(

0/ 1)*

f( 0/ 5)*

K-40

( 35)

(

3.1t

.1)E 3 90

( 3.4 i

.2)E 3

( 3.1 i

.2)E 3

( 0)

( l.5 -

3.8)E 3

( 2.4 -

3.4)E 3

( 30/ 30)*

(

1/ 1)*

(

5/ 5)*

MN-54 ( 35) 130.

(

2.11 17.7)E -1 29

( 1.1 i

.6)E 1

( 4.8 t 4.6)E O

( 01

(-2.8 -

1.5)E 1

( 4.5 - 16.9)E 0

(-5.9 - 16.9)E O a( 0/ 30)*

(

0/ 2)*

(

0/ Sie C0-58 ( 35) 130.

(

2.8f 1.9)E O 29 ( 7.4 i

.6)E O

( 5.7 t

.9)E O

( 01

(-1.7 -

2.5)E 1

( 6.8 -

7.9)E O

( 3.1 -

7.9)E O

(

0/ 30)*

(

0/ 21e e( 0/ 5)*

FE-59 ( 35) 260.

( -4.7i 3.4)E O 99

( 1.1 i

.8)E 1

( 4.7 i 4.0)E O

( 0)

(-4.4 -

3.1)E 1

( 3.3 - 18.7)E 0

(-6.0 - 18.7)E O

(

0/ 30)*

( 0/ 2)*

(

0/ 5)e CD-60 ( 35) 130.

(

1.3t 1.7)E O 25 ( 1.8 t 1.1)E 1

( 1.3 f 4.9)E O

( 0)

(-1.6 -

1.8)E I

(-6.4 - 20.1)E O

(

0/ 30)e

(

0/ 1)*

( 0/ 5)*

IN-65 ( 35) 260.

( -5.8t 3.9)E O 99 ( 3.0 1 2.6)E 1

( 1.6 f 1.3)E 1

( 0)

(-4.0 -

3.7)E 1

( 3.'i - 55.7)E 0

(-9.2 - 55.7)E O

(

0/ 30)*

(

0/ 2)*

e( 0/ 5)e ZR-95 ( 35)

( -2.St 2.8)E 0 29

( 1.2 i

.1)E 1

( 6.3 t 5.3)E 0

( 0)

(-4.1 -

2.4)E 1

( 1.1 -

1.3)E 1

(-1,1 -

1.9)E 1

(

0/ 30)*

(

0/ 2)*

(

0/ 5)*

RU-103 ( 35)

( -2.4i 2.3)E O 90 ( 6.5 t 7.3)E 0

(-4.8 i 5.0)E O

( 0)

(-2.9 -

2.5)E 1

(-1.5 -

.8)E 1

(

0/ 30)*

(

0/ 1)*

e( 0/ 5)*

NON-ROUTIE REFERS TO THE NLMBER OF SEPARATE EASLREENTS WICH ERE GREATER THAN TEN (10) TIES THE A'KRAGE BACK0ROLND FOR THE PERIOD OF TE REPORT.

et TE FRACTION OF SAMPLE ANALYSES YIELDING ETECTABLE TARREENTS (1.E. 13 STD DEV!ATI(WS) 15 INDICATED WITH *(

)*.

3-42

TABLE III-I-1 (CONTINUED)

EDRt': FINFISH LNITS: PCI/tG WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIrK6 etee++,*,,*eteten*

es,+,eeeeee,,,,,

RAD'9N)1IEES MEui MEAN MAN f'O. ##OSES!

REQUIRED RANGE STA.

RANGE RANGE O M ROUTINE '

'.LD NO. DETECTEDt, NO.

NO. DETECTED **

R M 06 ( 05)

(

5.0t 12.9)E O 11

( 1.1 i 1.4)E 1

(-4.3 i 11.3)E O

( 0)

(-1.4 -

1.4)E 2

(-1.4 -

1.4)E 2

(-4.8 -

1.3)E 1

(

0/ 30)*

(

0/ 27)*

(

0/ 5)*

I-131 ( 35)

( -5.9i 8.01E O 19 ( 4.9 i 3.9)E 1

( 3.7 i 22.1)E O

( 0)

(-1.2 -

.8)E 2

(-4.1 -

8.6)E 1

,(

0/ 30)*

(

0/ 1)*

(

0/ 5)*

CS-134 ( 35) 100.

( -4.2t 1.7)E O 99

( 9.7 i 4.5)E O

(-4.2 i 7.0)E O

( 0)

(-1.7 -

1.6)E 1

( 5.2 - 14.2)E O

(-2.2 -

1.4)E 1

(

0/ 30)*

(

0/ 2)*

(

0/ 5)*

CS-137 ( 35) 130.

(

8.91 2.6)E O 90 ( 2.1 i

.8)E 1

( 1.0 i

.3)E 1

( 1)

(-9.7 - 66.7)E O

( 3.7 - 205.0)E -1

(

1/ 30)*

(

0/ 1)*

(

0/ 5)*

BA-140 ( 35)

(

2.91 47.6)E -1 19 ( 9.3 i 19.9)E 0

(-7.7 i 7.3)E O

( 0)

(-5.6 -

4.0)E 1

(-3.2 -

.8)E 1

(

0/ 30)*

(

0/ 1)*

( 0/ 5)*

CE-141 ( 35)

(

1.11

.3)E 1 14 ( 2.8 i 1.6)E 1

(-1.6 1 4.9)E O

( 0)

(-2.2 -

4.4)E 1

(-1.4 -

1.5)E 1

(

0/ 30)*

( 0/ 1)*

( 0/ 5)*

CE-144 ( 35)

( 5.St 8.8)E O 14

( 1.0 i

.5)E 2

(-1.6 i 3.0)E 1

( 01

(-1.3 -

1.0)E 2

(-9.8 -

7.8)E 1

(

0/ 30)*

( 0/ 1)*

(

0/ 5)*

TH-232 ( 35)

(

1. 0t

.6)E 1 29 ( 2.6 i 2.9)E 1

( 1.8 i 1.3)E 1

( 0)

(-5.4 -

7.4)E 1

(-3.1 - 54.9)E 0

(-1.2 -

5.5)E 1

(

0/ 30)*

(

0/ 2)*

(

0/ 5)*

NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE EASLREENTS WHICH WERE CREATER THAN TEN (10) TIES TE AVERAGE BACKGROLND FOR TE PERIOD OF TE REPORT.

- THE FRACTION OF SAMPLE ANALYSES YIELDI!6 DETECTABLE MEASUREENTS (I.E.13 5TD DEVIATICNS) IS INDICATED WITH *(

)*.

l 3-43 i

t

EIII.J. Sediments Sediment samples are taken semi-annually at five indicator stations including Rocky Point, Plymouth Harbor, Duxbury Bay, Plymouth Beach and Manomet Point and a control sample is taken from Marshfield.

There is a detailed subdivision of individual sample cores in which samples are sectioned into 2 cm increments during the first half of the year (this applies to all locations except Plymouth Beach), and samples are sectioned into 5 cm increments during the second half of the year.

The surface and alternate sections are analyzed for gamma emitting i

isotopes.

In addition, the surface section from each core and a mid-depth sect'on from Rocky Point and Plymouth Harbor are analyzed for Pu-238 and Pu-239, 240.

The results of the ERMAP program for sediments are presented in Table III-J-1.

It is clear from this table that positive measurements of Co-60 and Cs-137 were observed. The highest concentration of Co-60 was l

observed in a sediment sample (24-26 cm) taken from Rocky Point (Stat. ion 11) on 5/19/86.

In addition, Co-60 was observed in all of the sediment segments (0-30 cm) obtained from Rocky Point on 5/19/86 and in two sediment segments (16-20 cm) from Duxbury Bay collected on 5/29/86.

The concentrations of Co-60 at Rocky Point are due to liquid effluents from PNPS-1.

The lack of Co-60 at the Plymouth Harbor and Plymouth Beach locations indicate that the positive measurements at Duxbury Bay are probably due to cross-contamination of the samples during the collection process.

3-44

The highest concentration of Cs-137 was observed in a sediment sample (24-26 cm) taken from Duxbury Bay (Station 13).

This sample was collected on 5/29/86.

In addition, Cs-137 was observed in all of the sediment segments (0-30 cm) obtained from Duxbury Bay on 5/29/86, and I

was observed in all of the sediment segments (0-15 cm) collected on 10/22/86.

The observation of Cs-137 was also made at Rocky Point (24-26 cm, collected on 5/19/86; 10-15 cm, collected on 10/15/86),

Manomet Point (0-15 cm, collected on 10/10/86), Plymouth Harbor (0-22 J

cm, collected on 5/27/86; 0-15 cm, collected on 10/6/86), and at Marshfield (0-30 cm, collected on 5/28/86; 0-15 cm, collected on 10/10/86).

The concentration of Cs-137 at the 24-26 cm level from Rocky Point was most likely due to controlled liquid releases from PNPS-1.

The concentrations of Cs-137 at Duxbury Bay may be explained by the fact that the sediment samples have a silty character not common to the other samples. The Plymouth Harbor sediment is very similar to Duxbury Bay.

It may be that the nature of the Duxbury sediment is such that certain materials are retained more strongly than others.

This theory is supported by the fact that the Duxbury station also had the highest mean concentration of K-40, an isotope which is chemically similar to Cs-137. The measured concentration of Be-7, and to some extent Cs-137, at Duxbury Bay, Plymouth Harbor and Marshfield are attributable to the fission products related to fallout from previous weapons testing'.

Analyses for plutonium nuclides in sediment samples are performed by EAL Corporation in Richmond, California.

The results of these analyses for the 1986 samples are presented in Table III-J-2.

In the past, as 3-45

i is indicated in the 1986 analysis results, there was no apparent trend in these data to indicate that the PflPS-1 is contributing measurably to levels of Pu-238 or 239, 240 in the environment since levels of plutonium at Rocky Point are among the lowest measured at any location.

l 1

3-46

TABLE III-J-1 ERMAP RESULTS SEDIMENT 1986 MEDItr,: SED: MENT WITS: PCI/KG DRY INDICATOR STATIONS STATION WITH HIC 4EST EAN CMTROL STATIONS nee ++esenteeseette eseeeeeeeeee++eeeeeeeeee, eneeeeeeeeeeeee, Pl.DIONIXt![(S TAN EAN EAN

90. ANALY?ES' 40VIFED FANGE STA.

RAKE RAKE PCFF.TTINEl' LLD NO. DETECTEDee NO.

NO. DETECTEDee NO ETECTEDee E-7

( 77)

(

4.81 2.11E 1 12

( l.5 t

.9)E 2

( 4.1 i 1.9)E 1

( ?)

(-l.7 -

9.8)E 2

(-5.8 - 98.2)E 1

(-7.6 - 27.6)E 1

(

6/ 58te

(

3/ !!)*

(

1/ 19)e K-40

( 77)

(

1.lt

.0)E 4 13

( !.4 i

.0)E 4

( 9.8 i

.1)E 3

( 0)

( 7.6 -

16.9)E 3

( 1.0 -

1.7)E 4

( 8.7 - 10.8)E 3'

( 58/ 58)e

( 19/ 19)e

( 19/ 19)e it-54 ( 77)

( -3.41

.7)E O 11

(-3.9 i 1.4)E O

(-8.4 t

-1.1)E O

( 0)

(-2.5 -

.3)E 1

(-1.3 -

.3)E 1

(-1.6 -

.1)E 1

(

0/ 581*

(

0/ 11)*

(

0/ 19)*

CO-58 ( 77) 50.

( -4.6t

.7)E O 24

(-7.9 i 11.4)E -1

( 0)

(-1.7 -

.7)E 1

(-10. -

6.4)E 0

(-10. -

6..'

0

(

0/ 58)*

(

0/ 19)e et 0/ 19)e FE-59 ( 77)

(

1.3t 2.4)E O 15 ( 1.1 i

.4)E 1

( !.1 i 3.9)E O

( 0)

(-4.7 -

3.6)E 1

(-1.8 -

3.2)E 1

(-2.6 -

4.8)E 1 l

(

0/ 50)*

(

0/ 11)e

(

0/ 19)*

CD-60 ( 77) 50.

(

2.8f 1.2)E 0 11

( 1.4 i

.2)E 1

(-3.8 t 10.9)E -1

( 7)

(-2.0 -

2.7)E 1

( 4.5 - 27.3)E O

(-7.8 - 10.8)E O

(

7/ 58)*

(

6/ 111e

(

0/ 19)*

l ZN-65 ( 77) 50.

( -3.2t 18.4)E -1 24

( 4.8 i 3.0)E O

( 4.8 i 3.0)E 0

( 0)

(-3.9 -

2.6)E 1

(-2.2 -

3.1)E 1

(-2.2 -

3.1)E 1

(

0/ 58)e

(

0/ 19)e

(

0/ 19)*

ZR-95 ( 77) 50.

(

5.11 1.7)E O 13 ( 9.6 i 3.0)E 0

( 4.3 t 2.2)E O

( 0)

(-2.9 -

3.5)E 1

(-2.9 -

3.5)E 1

(-1.9 -

2.2)E 1

(

0/ 58)*

(

0/ 19)e

(

0/ 19)*

RV-103 ( 77)

( -4.8f 10.7)E -1 11

( 2.8

1.9)E 0

(-1.1 i 1.5)E O

( 0)

(-2.5 -

1.4)E 1

(-8.5 - 12.7)E 0

(-1.2 -

1.1)E 1

(

0/ 58)*

(

0/ 111e

(

0/ 19)*

NON-ROUTINE REFERS 10 TE fuGER OF SEPARATE EASLREENTS IMICH ERE CREATER THM TEN (10) TIES TE AVERAGE BACKGROUND FOR THE PERIOD OF TE REPORT.

se TE FRACTION 0F SMPLE ANALYES YIELDING MTECTAELE MEASLREMENTS (1.E. >3 STD DEV!ATi mS) IS INDICATED WITH st

)+.

3-47

TABLE III-J-1 (CONTINUED)

EDIltt: SEDIMENT l' NITS: PCI/kG TV INDICATCR STATIONS STATION WITH HIGEST MEAN CONTROL STATIONS e***eeeeeeeeeeeee, eteee**eeeeeeeeeeee**ene, e**eeeeeee***ee, RADICN.lCt. IDES MEAN EAN EAN (NO ANALYSES)

REQUIRED RANCE STA.

RANCE RANGE (4]N-ROUTINE)'

LLD NO. DETECTEDee NO.

NO. DETECTEDee NO. DETECTEDee I

FS-1% ( 77)

(

6.8f 5.3)E O 12 ( 1.6 1 1.8)E 1

(-3.1 i 8.7)E 0

( 0)

(-1.2 -

.9)E 2

(-1.2 -

.9)E 2

(-8.9 -

4.8)E 1

(

0/ 58)*

(

0/ 11),

(

0/ 19)*

I-131 ( 77)

(

1.7t 3.7)E 1 15 ( 1.2 i 1.4)E 2

(-4.3 i 9.5)E 1

( 0)

(-1.0 -

.8)E 3

(-1.0 -

.8)E 3

(-1.6 -

.6)E 3

(

0/ 58),

(

0/ 11)e

(

0/ 19)*

CS-134 ( 77) 50.

( -1.31

.6)E O 15

( 9.6 t 10.6)E -1

(-3.9 i

.9)E O

( 0)

(-1.2 -

.9)E 1

(-6.2 -

5.2)E O

(-9.6 -

3.2)E O at 0/ 58),

(

0/ 11)*

(

0/ 19)e CS-137 ( 77) 50.

(

2.9t

.4)E 1 13 ( 5.9 i

.4)E 1

( l.8 i

.2)E 1

( 0)

(-6.8 - 85.9)E O

( 3.6 -

8.6)E 1

( 5.1 - 44.3)E 0 et 30/ 58)*

( 19/ 19)*

( 15/ 19)*

BA-140 ( 77)

( -5.6t 1.1)E 1 12

(-2.4 f 1.2)E 1

(-6.5 k 1.6)E 1

( 0)

(-3.8 -

.4)E 2

(-7.8 -

4.3)E 1

(-2.4 -

.0)E 2

(

0/ 58)*

(

0/ 11)*

(

0/ 19)*

N-141 ( 77)

(

1.21

.2)E 1 14 ( 1.7 i

.5)E 1

( 1.6 i

.4)E 1

( 0)

(-4.0 -

4.8)E 1

(-1.8 - 27.4)E 0

(-1.8 -

6.3)E 1

(

0/ 58)*

et 0/ 6)e et 0/ 19)e G-144 ( 77) 150.

( -2.lt

.4)E 1 11

(-9.5 i 6.3)E 0

(-1.5

.C!E 1

( 0)

(-9.5 -

4.0)E 1

(-4.1 -

3.3)E 1

(-7.7 -

5.61E 1

(

0/ 58)*

(

0/ 11)e

(

0/ 19)*

TH-232 ( 77)

(

4.31

.2)E 2 13 ( 6.1 i

.2)E 2

( 3.3 i

.1)E 2

( 0)

( 1.2 -

7.6)E 2

( 4.5 -

7.6)E 2

( 2.4 -

4.2)E 2 et 58/ 58),

( 19/ 19)*

( 19/ 19)*

NnN-ROUTIE REFERS TO TE MlttEER CF SEPARATE EASUREENTS lei!CH ERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGR0lND FOR TE PERIOD OF TE REPCRT.

- TE FRACTION OF SAELE ANALY?ES YIELDING DETECTABLE EASUREENTS (I.E. >3 STD DEVIATIONS) IS IND:CATED WITH et

)*,

3-48

n TABLE III-J-2 RESULTS OF SEDIMENT ANALYSES FOR PLUTONIUM location Deoth (cm)

Results 7

(

oCi/Ko (drv) +- % Error (1 ) (a) i 238 239,240 Pu Pu Duxb'ry 0-2 0.48 31%

17.5 1 6%

u Plymouth Harbor 0-2 1.38 20%

14.4 i 8%

Plymouth Harbor 16-18 0.86 29%

9.90 10%

Rocky Point.

0-2 0

0.10 pCi/kg 2.05 15%

Rocky Point 16-18 0.16 150%*

2.49 20%*

Manomet Point 0-2

-0.06 1 300%

2.91 16%.

Plymouth Beach 0-5 0.46 56%

1.26 24%

Marshfield-Control 0-2 0.26 72%

1.99 17%

(a)

If the result is zero, the error is in pCi/Kg

Low tracer yield.

3-49 f

III.K. Milk Milk samples were collected at two locations during 1986, the Plymouth

' County Farm (Station 11-3.5 mi-H) and the Whitman Farm (Station 21-21 mi-NH). As stated in Section II, Boston Edison is aware of a milk-producing cow located at Beaver Dam Road (Station 28-2.5 mi-S).

Unfortunately,, samples were unavailable from Beaver Dam Road during 1986. Thus, the only dependable indicator station (within 5 miles) for milk near PNPS-1 during 1986 was from the Plymouth Country Farm.

This was confirmed in the 1986 Census (see Appendix E).

When available, samples were collected semi-monthly when animals are on pasture (generally May through October) and monthly at other times.

The results of the ERMAP program for the milk media are presented in Table III-K-1.

The results of analyses for Cs-137, Sr-90, and I-131

-are presented graphically in Figures III-K-1, III-K-2, and III-K-3 respectively.

The positive measurements or indications of I-131 in the samples from week #19 through week #27 (late May until early July), and the positive measurements of Cs-134 and Cs-137 from week #21 through week #27 were attributable to Chernobyl-related radioactivity.

There was only a small amount of strontium released during the Chernobyl accident which resulted in negligible Sr-89 eid Sr-90 in the Chernobyl-related radioactivity.

Refer to Appendix F for a summary on the environmental radioactivity from the Chernobyl accident, and Appendix G for a tabulation of the measurements.

The highest concentration of Sr-90 occurred at Plymouth County Farm (collected on 9/4/86) and the highest concentration of Sr-89 occurred at the Plymouth County Farm (collected on 6/19/86).

However, there were no positive measurements made of either Sr-89 or Sr-90, there were 3-50

only indications-of the presence of Sr-90 (activity greater than three times the standard deviation).

Station releases for this period exhibited a Sr-90/Sr-89 ratio of about 1/70 and therefore it is unlikely that PNPS-1 is the major source of the indicator station activity since the measured Sr-90/Sr-89 was about 6/1.

J Positive measurements of both Cs-134 and Cs-137 were detected at both sampling locations from week #21 through week #27 (late May until early July), with the highest concentrations observed from week #24 at the Plymouth County Farm (collected on 6/10/86).

These nuclides are attributable to Chernobyl-related radioactivity (Appendix F).

Prior to week #21 and after week #27, the highest concentration of 1

Cs-137 occurred at Plymouth County Farm (3.5 mi-H) in early September (collected on 9/4/86). The absence of Cs-134 at this location would indicate that the primary source of Cs-137 is other than PNPS-1, and was most likely due to fallout from previous atmospheric weapons testing.

Therefore, it is extremely unlikely that there was any environmental impact on milk due to the operation of PNPS.

3-51 s

TABLE III-K-1 ERMAP RESULTS MILK 1986 EDII?: NLV (M!S: PCI/VG INDICF OR STATICNS STATION WITH HIGHEST EAN CONTRCL STATIONS neuennuneen utennuunnounun unenuneun RADIONUCLIDES TAN EAN MEAN

. (NO. ##iLYSESI RE0VIRED RANCE STA.

RANGE RANCE (WJN-RJJTINE)'

LLD NO. MTECTEDet NO.

NO. DETECTEDee NO. DETECTEDen SR-89 ( 36)

( 9.Si 10.4)E -2

( 9.8 i 10.4)E -2

(-2.3 1 9.6)E -2

( 0)

(-8,5 -

7.3)E -1

(-8,5 -

7.3)E -1

(-1.0 -

.5)E O

(

0/ 18)*

(

0/ 18)e e( 0/ 181s SR-90 ( 36)

(

3.01

.2)E O 11

( 3.0 t

.2)E O

( !.5 i

.1)E O

( 0)

( 1.9 -

4.4)E O

( 1.9 -

4.4)E O

( 6.2 - 22.6)E -1

( 18/ 18)*

( 18/ 18)*

( 17/ 18)e E-7

( 36)

( -2.6t 2.5)E O 21

( 1.7 i 24.8)E -1

( 0)

(-2.1 -

2.2)E 1

(-2.2 -

1.5)E 1

(-2.2 -

1.5)E 1

(

0/ 18)e

(

0/ 18)*

a( 0/ 18)*

K-40 ( 36)

(

1.41

.0)E 3 11

( 1.4 i

.0)E 3

( 1.4 i

.0)E 3

( 0)

( 1.3 -

1.5)E 3

( l.3 -

1.5)E 3

( 1.3 -

1.5)E 3

( 18/ 18)e

( 18/ 18)*

( 18/ 18)*

f91-54 ( 36)

( -1.6i 3.0)E -1 21

( 5.2 f 30.5)E -2

( 5.2 i 30.5)E -2

( 0)

(-3.3 -

2.6)E 0

(-3.3 -

2.0)E 0

(-3.3 -

2.01E O

(

0/ 18)e

(

0/ 18)*

(

0/ 18)*

CD-58 ( 36)

( -1.9i 2.0)E -1 21

( 1.2 i 33.9)E -2 (1.21 33.9)E -2

( 0)

(-1.7 -

2.0)E O

(-3.4 -

3.6)E 0

(-3.4 -

3.6)E O

(

0/ 18)*

a( 0/ 18)*

(

0/ 18)e FE-59 ( 36)

(

2.81 9.0)E -1 11

( 2.8 i 9.0)E -1

(-2.0 i 8.5)E -1

( 0)

(-9.4 -

7.1)E O

(-9.4 -

7.1)E C

(-5.2 -

7.6)E O et 0/ 18)e et 0/ 18)*

(

0/ 18)*

CO-60 ( 36)

( -3.31 4.1)E -1 21

(-3.1 1 2.8)E -1

(-3.1 i 2.8)E -1

( 01

(-5.3 -

2.3)E 0

(-2.5 -

1.7)E 0

(-2.5 -

1.7)E O

(

0/ 18)e et 0/ 18)*

(

0/ 18)*

IN-65 ( 36)

( -3.11 7.5)E -1 21

(-7.0 t 74.0)E -2

( 0)

(-7.6 -

4.5)E O

(-7.6 -

4.6)E 0

(-7.6 -

4.61E O

(

0/ 18)*

(

0/ 18)*

(

0/ 18)*

NON-ROUTINE REFERS TO TE NUMBER OF SEPARATE EASLREENTS WICH ERE C4tEATER THAN TEN (10) TIES TE AVERACE BACKC#JUND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAPPLE ARYSES Y!ELDING KTECTABLE TASLREENTS (1.E. >3 STD DEVIATIO C IS INDICATED WITH *(

le.

3-52

TABLE III-K-1 (CONTINUED)

EDIUM:. MILK f*ITS: PCI/KG INDICATOR STATICNS STATION WITH HIGHEST EAN CONTROL STATIONS esteee***********e etee***eee******eetet**e+

eeeetes***eeeee.

RADIONUCLI[ES MEAN EAN MEAN (NO ANALYSES) RE0JIPED RANGE STA.

RANCE RANGE (NON-ROUTINE)'

LLD t0. DETECTED,*

NO.

NO. [ETECTEDee NO. DETECTED **

==-

ZR-95 ( 36)

(

5.Si 5.0)E -1 11

( 5.8 i 5.0)E -1

(-8.8 i 59.7)E -2

( 0)

(-3.2 -

4.9)E O

(-3.2 -

4.9)E O

(-3.7 -

4.8)E O

(

0/ 18),

(

0/ 18)*

(

0/ 18)e RU-103 ( 36)

( -1.lt

.3)E O 11

(-1.1 i

.3)E O

(-1.7 *

.3)E o

( 01

(-3.9 -

1.8)E O

(-3.9 -

1.8)E O

(-4.6 -

1.7)E O

(

0/ 18)e

(

0/ 18)e

(

0/ 18)e RU-106 ( 36)

(

1.01 2.5)E O 11

( l.8 i 2.5)E O

(-4.3 i. 2.0)E O

( 0)

(-2.1 -

2.0)E I

(-2.1 -

2.0)E 1

(-2.5 -

1.1)E 1 et 0/ 18)*

(

0/ 18)e

(

0/ 18)e I-131 ( 36) 1.

(

3.6t 3.1)E O 11

( 3.6 i 3.1)E O

( 2.6 i 2.2)E O

( 1)

(-1.1 - 559.0)E -1

(-1.6 - 390.0)E -1

(

5/ 18)e a( 5/ 18)*

(

3/ 18)*

CS-134 ( 36)

(

7.Si 5.6)E -1 11

( 7.5

5.6)E -1

( 2.2 1 3.8)E -1

( 4)

(-3.0 -

5.4)E 0

(-3.0 -

5.4)E O

(-2.5 -

4.1)E 0 a( 4/ 18)e

(

4/ 18)*

(

1/ 18)e CS-137 ( 36)

. 15.

(

5.11

.8)E O 11

( 5.1 i

.8)E 0

( 2.7 i

.5)E O

( 0)

( 9.5 - 156.0)E -1

( 4.3 - 894.01E -2

( 12/ 18)*

( 12/ 18)*

(

6/ 18)

BA-140 ( 36) 15.

( -7.71 7.2)E -1 21

(-7.2 1 4.8)E -1

(-7.2 i 4.8)E -1

( 0) 1-8.2 -

3.8)E 0

(-5.3 -

2.3)E O

(-5.3 -

2.3)E O

(

0/ 18)*

(

0/ 18)*

(

0/ 18)*

CE-141 ( 36)

(

7.31 5.2)E -1 11

( 7.3 t 5.2)E -1

( 2.6 i 6.2)E -1

( 0)

(-3.3 -

3.8)E O

(-3.3 -

3.8)E O

(-4.8 -

4.6)E O

(

0/ 18)e

(

0/ 18)e

(

0/ 18)*

CE-144 ( 36)

( -1.91 20.0)E -1 21

( 1.4 i 1.7)E 0

( !.4 i 1.7)E 0

( 0)

(-1.5 -

2.0)E 1

(-7.8 - 17.7)E O

(

0/ 18)*

(

0/ 18)*

(

0/ 18)*

NON-60 WINE REFERS TO TE NLMBER OF SEPMATE EASLREENTS WHICH WERE (REATER THAN TEN (10) TIES TE A'KRAGE BACKGROLND FOR TE FERIOD OF TE REPORT.

et TE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE EASLREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

3-53

CESIUM-137 IN MILK PILGRIM STf1 TION 20 l

18-O - TM-11 PLYMOUTH COUNTY FARM o - TM-21 WHITMAN FARM 16 -

o R

11-rnN?

Ee a 12-sem m

b d

%2

k N

10-n d

ob i

E T

B 8-t 8

t i

6-4-

0 2-

.i 0

JAN FIB FWWt fFft F1RY JJN JUL NJG SEP OCT NOV DEC 1986

i FIGURE III-K-2 CONCENTRATIONS OF Sr-90 IN MILK ob 2

u

~h 9

en em x

I d

OM z

E 66

~

o 5C 77 q

E ao T *c

.E c

tb k

e

-Z d

e a-E D;

t 4

o a

a a

a W8S07IX / S3I80000!d 3-55

F?GURE TIl-K-3 CONCENTRATIONS OF I-131 IN MILK Q

U E

t!>

E E

C hj E

U

( I z

E t l o-W E!:

C L s'E E

5z CM E

S kN H

ss f ik Z

~

00 g

to m

i !

~

O r

-J Q

E N

~

![

(

t Ig t r 8w nk

.a o

8 R

S S

S R

R WW890~1IX / S3ISn003Id 3-56

III.L. Cranberries Cranberries are collected from three locations: the Manomet Point Bog (2.5 mi-SE-Station 13), the Bartlett Road Bog (2.8 mi-SSE/S-Station i

14) and the Pine Street Bog (17 mi-HNW-Station 23) at the time of harvest. The results of the ERMAP program for this media are presented l

in Table III-L-1.

The only man-made radionuclide detected was Cs-137 r

l which appeared in the Manomet Point Bog sample (collected on 9/23/86).

i A comprehensive study of cesium uptake in cranberries was performed during 1978.

The results of this study are published in the 1978 l

Environmental Radiation Monitoring Program Report No. 11.

This report identified fallout from previous nuclear weapons testing as the primary i

source of cesium in cranberries.

In addition, this report indicated that cesium uptake in cranberries can be increased when conditions of l

low soil potassium occur, as cesium is a chemical congener of potassium. The results of this study and the fact that no other reactor related nuclides were measured above LLD in cranberry samples makes it extremely unlikely that there was any environmental impact on cranberries due to operation of PNPS-1, but rather that the measured

(

concentration was due to fallout from previous weapons testing and a lack of adequate potassium in the soil.

l 3-57 l

TABLE III-L-1 ERMAP RESULTS CRANBERRIES 1986 MElitt.M: 'TWAEERR?ES UNITS: PCI/tG WET INDICATOR STATIONS STATICN WITH HIGHEST T AN CONTROL STATIONS neeeeeeeee*eeeeee, etenee****eveneseeeeeeee, seeeeeeeeeeeente

' RADl0NU2LICES MEAN TAN EAN (NO. ANALYSES)

REQUIRED RANGE STA.

RANCE RANCE 010N-ROUTUE)'

LLD NO. DETECTED +e NO.

N0. [ETECTEDet NO. DETECTEDee

=

EE-7

-(

3)

(

9.5i 245.5)E -1 13 ( 2.6 i 6.8)E 1

(-9.1 i 51.2)E O

( 0)

(-2.4 -

2.6)E 1

(

0/ 2)*

(

0/ 1)*

et 0/ 1)e K-40

( 3)

(

4.4k

.0)E 2 23 ( 7.6 i 1.4)E 2

( 7.6 i 1.4)E 2

( 0)

( 4.4 -

4.4)E 2

(

1/ 2)*

(

1/ 11e

(

1/ 1)*

IH-54 ( 3)

(

6.9t 6.7)E O 14 ( l.4 i

.6)E 1

(-3.3 i 6.2)E O

( 0)

( 2.4 - 136.0)E -1

(

0/ 2)e

(

0/ 11e

(

0/ 1)*

CO-58 ( 3)

( -4.6t 5.1)E O 14 ( 5.1 t 61.3)E -1

(-1.2 i

.7)E 1

( On

(-9.8 -

.5)E O

(

0/ 2)*

(

0/ 1)*

(

0/ 1)*

FE-59 ( 3)

(

-6.0 4.3)E O 14

(-1.7 t 14.2)E O

(-2.2 i 1.5)E 1

( 0)

(-1.0 -

.2)E 1

(

0/ 2)*

(

0/ 1)*

a( 0/ 1)*

C0-60 ( 3)

( -8.0t

.6)E O 23 ( 4.1.t 10.6)E O

( 4.1 i 10.6)E O

( 0)

(-8.6 -

-7.4)E O a( 0/ 2),

(

0/ 11e

( 0/ 1)*

ZN-65 ( 3)

( -1.41

.9)E 1 23 ( 1.8 i 14.5)E 0

( l.8 t 14.5)E O

( 0)

(-2.3 -

.6)E 1 a( 0/ 2)*

et 0/ 1)*

( 0/ 1)*

ZR-95 ( 3)

(

6.9t 9.5)E O 13 ( 1.6 i 1.5)E 1

(-2.6 i 1.3)E I

( 0)

(-2.6 - 16.4)E O

(

0/ 2)*

et 0/ 1)*

(

0/ 1)*

RU-103 ( 3)

(

5.St

.5)E O 14 ( 6.0 t 7.5)E O

(-1.2 t

.7)E 1

( 0)

( 4.9 -

6.01E O

(

0/ 2)*

(

0/ 1)e

(

0/ 1)*

NON-ROUTINE REFERS TO TE NLMBER OF SEPMATE TKUREENTS lei!CH ERE GREATER THAN TEN I10) TIMES THE AVERACE BACKOROLND FOR TE PERIOD OF TE REPORT.

et TE FRACTION OF 9AMFtE ANALYSES YIELDINO DETECTABLE MEAS 1REMENTS

(!.E. ?3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

3-58

TABLE III-t-1 (CONTI'NUED)

KTII.r: CPAf8FRRIES UNITS: PCI/kG WET INDICATCR STATICNS STATION WITH HIGHEST EAN CONTROL STATIONS nunnennenn nonnenneenenennu uneenenseeee RADICHnIDES MEM MEAN EAN (NO. ANALYSES) REDVIRED RANCE STA.

RANGE RANGE t N:]N-UUT!fEl' LLO NO. DETECTED,*

NO.

NO. DETECTED **

RU-106 ( 31

(

3.12 4.4)E O 13 ( 7.5 i 68.9)E O

(-4.0 i 6.7)E 1

( 0)

(-1.3 -

7.5)E O

(

0/ 2)*

(

0/ 1)*

(

0/ lie I-131 ( 31

( -3.3t 23.8)E O 13 ( 2.1 1 1.8)E 1

( 3.1 i 15.0)E O

( 0)

(-2.7 -

2.1)E 1

(

0/ 2)*

(

0/ 1)*

( 0/ 1)*

CS-134 ( 3)

. 60.

( -3.71 4.4)E O 23 ( 2.3 7.2)E O

( 2.3 i 7.2)E O

( 0)

(-8.1

.8)E O

(

0/ 2)e

(

0/ 1)*

( 0/ 1)*

CS-137 ( 31 60.

(

7.0t 6.2)E 1 13 ( !.3 i

.1)E 2

( 6.5 i 7.3)E O

( !)

( 7.3 - 132.0)E O

(

1/ 2)*

(

1/ 1)*

( 0/ 1)e BA-140 ( 3)

( -9.0t 13.4)E O 14

( 4.3 i 12.3)E O

(-1.2 i 1.2)E 1

( 0)

(-2.2 -

.4)E 1

(

0/ 21e

(

0/ 11e f( 0/ 1)*

CE-141 ( -3)

(

1.61

.2)E 1 13 ( !.7 i 1.2)E 1

( 4.3 i 94.0)E -1

( 0)

( !.4 -

1.7)E 1

(

0/ 2)e

(

0/ lie el 0/ 1)*

CE-144 ( 3)

( 7.2i 21.7)E O 23 ( 4.4 t 3.3)E 1

( 4.4 i 3.3)E 1

( 0)

(-l.5 -

2.9)E 1

(

0/ 2)*

(

0/ 1)*

( 0/ 1)*

TH-232 ( 3)

(

l.81 1.4)E 1 23 ( 6.2 1 3.1)E 1

( 6.2 t 3.1)E 1

( 0)

( 3.6 - 02.6)E 0

(

0/ 2)e et 0/ 1)*

( 0/ 1)*

NJN-RCUTIE REFERS TO THE NUMER OF SEPARATE EARREENTS not!CH ERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKCROLND FM TE PERIOD OF TE REPORT.

- TE FRACTION (F SAELE ANALYSES Y!ELDING DETECTABLE MEASLREENTS

(!.E. >3 STD [EVIATICWS) IS INDICATED WITH *(

le.

3-59

.III.M. Veaetation Samples of tuberous and green leafy vegetables were collected at the time of harvest at five locations: Plymouth County Farm (3.5 mi-W),

Bridgewater Farm (20 mi-H), the Malmgren residence (1.0 mi-SE), the Work residence (0.6 mi-ESE), the Jenkins residence (1.0 mi-H), and the~

Moon residence (1.25 mi-SSW).

The only nuclides observed (other than naturally occurring Be-7, AcTh-228 (peak) and K-40) was Cs-137. A positive measurement of Cs-137 was detected in a vegetation sample from the Work residence (red lettuce, collected 9/16/86), and in a vegetation sample from the Malmgren residence (thubbarb, collected on 9/16/86).

The absence of Cs-134 at this location and the fact that measured Cs-137 concentration is greater than 10,000 times what would be expected at this location based on releases from PNPS-1, strongly indicates that fallout, not PNPS-1, is the primary source of this Cs-137.

However, even if a person were to consume the maximum annual quantity of vegetation with the concentration of Cs-137, they would receive a dose of less than 0.02 mrem to the total body and less than 0.25 mrem to the most restrictive organ (Child, GI-LLI).

Therefore, it is extremely unlikely that there was any environmental impact on vegetation due to the operation of PNPS-1.

3-60

TABLE III-M-1 ERMAP RESULTS VEGETATION 1986 MEDIUM: FOOD CROP UNlts: oCluG WT INDICATOR STATIONS STATION WITH HIGEST MEAN CONTROL STATIONS eeeeseee*eeeeeeeeeeeeeee, esee.. e,*eeen, RADIONUCLICCS EAN TAN EAN (NO. ANALYSES)

REQUIRED RANGE STA.

RANCE RANGE (M)N-ROUTINE)'

LLD NO. DETECTED,e NO.

NO. DETECTEDu NO. DETECTED **

l_

l~E-7

( 12)

(

5.52 3.2)E 1 16 ( l.3 t

.6)E 2

( 4.5 i 5.3)E 1

( !)

(-6.0 - 23.4)E 1

( 2.3 - 23.4)E 1

(-4.9 - 13.3)E 1

(

1/ 9),

(

1/ 3)e e( 0/ 3)*

K-40

( 12)

(

2.91 4)E 3 77 ( 4.7 i

.2)E 3

( !.8 i

.3)E 3

( 0)

( l.1 -

4.7)E 3

( 1.1 -

2.3)E 3 l

(

9/ 9)*

(

1/ 1)*

e( 3/ 3)*

tW-54 ( 12)

(

5.5 26.0)E -1 16 ( 3.8 i 3.1)E O

( 1.2 i 7.9)E O l

( 0)

(-8.0 - 16.3)E O

(-2.0 -

8.8)E 0

(-1.2 -

1.6)E 1 l

(

0/ 9)*

<< 0/ 3)*

(

0/ 3)*

I CO-58 ( 12)

(

7.0 24.3)E -1 16

( 6.3 i 4.8)E O

(-1.8 t

.4)E 1

( 0)

(-7.3 - 15.6)E O

(-7.5 - 156.0)E -1

(-2.6 -

-1.1)E 1 l

(

0/ 9)e

(

0/ 3)e

(

0/ 3)*

l l

FE-59 ( 12)

( -5.3t 6.9)E O 77

( 1.5 i 1.6)E 1

(-8.0 t 24.0)E -1 l

( 0)

(-3.0 -

3.2)E 1

(-4.1 -

3.9)E 0 l

(

0/ 9)*

st 0/ Ile

(

0/ 3)*

CD-60 ( 12)

(

8.11 25.7)E -1 11

( 5.8 i 2.3)E 0

(-8.0 t 3.7)E O

( 0)

(-1.5 -

1.0)E 1

( 2.3 - 10.0)E 0

(-1.4 -

.1)E I a( 0/ 9)e

(

0/ 3)*

(

0/ 3)*

IN-65 ( 12)

( -4.5t 4.0)E O 77 ( 5.3 i 17.0)E O

(-3.5 t 8.9)E O

( 0)

(-1.9 -

1.8)E I

(-2.0 -

1.1)E I

(

0/ 9)e a( 0/ lie a( 0/ 3)*

ZR-95 ( 12)

( -3.9t 392.2)E -2 11

( 8.9 t 10.6)E O

( 4.9 i 46.9)E -1 i

( 0)

(-1.2 -

2.4)E 1

(-l.2 -

2.4)E 1

(-5.5 -

9.7)E 0 l

et 0/ 9)e et 0/ 3)*

(

0/ 3)*

RU-103 ( 12)

(

1.2t 2.3)E O 16 ( 6.5 i 4.7)E O

(-7.2 i 4.7)E O

(

( 0)

(-8.4 15.0)E O

(-1.2 - 15.0)E O

(-1.7 -

.2)E 1 l

(

0/ 9)*

(

0/ 3)*

et 0/ 3)*

MW-ROUTINE REFERS TO THE M.MBER OF SEPARATE TASLREMENTS WHICH WERE REATER TWW TEN (10) TIES TT A'KRACE BACK0ROLND FOR THE PERIOD OF TE REPORT.

- THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE '1EASLREMENTS (1.E. 33 STD [CVIATIONS) !$ INDICWED WITH *(

le.

3-61

TABLE III-M-1 (CONTINUED)

ED!le: FCOD CRP (WITS: PCI/VG IET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS mmnummu mmnenmmunen*

- umuneme RADICNXLICES EAN MEAN EAN

.(NO. ANALYSES) REQUIRED RANCE STA.

RANCE RANGE (NON-ROUTINEF LLD NO. CETECTEDu NO.

NO. DETECTEDee NO. DETECTEDee

_.===

4 R'J-106 ( 12)

(

3.It 24.5)E O 16 ( 5.1 i 5.8)E 1

( 2.8 t 4.8)E 1

( 0)

(-1.1 -

1.7)E 2

(-2.0 -

16.6)E 1

(-3.2 - 12.2)E 1 et 0/ 9)*

(

0/ 3)*

(

0/ 3)*

I-131 ( 12)

(

-7.9*

2.6)E O 75 ( l.0 t 12.9)E O

(-2.5 t 4.8)E O l

( 0)

(-1.8 -

.7)E 1

(-1.1 -

.5)E 1

(

0/ 9)*

(

0/ lie et 0/ 3)*

CS-134 ( 12) 60.

( -6.6f 3.1)E 0 27

( 1.2 i 2.2)E O

( 1.2 t 2.2)E 0 r

l

( 0)

(-2.1

.9)E 1

(-3.1 -

4.2)E 0

(-3.1 -

4.2)E O

(

0/ 9)*

( 0/ 3)*

et 0/ 3)*

l l

CS-137 ( 12) 60.

(

7.7t 3.3)E O 16

( 1.6 i

.7)E 1

( 3.1 i 6.5)E 0 t

( 2)

(-5.5 - 29.1)E O

( 8.1 - 29.1)E 0

(-8.2 - 14.1)E 0

(

2/ 9)*

(

1/ 3)*

(

0/ 3)e BA-140 ( 12)

( -5.4i 4.3)E O 27

( 1.2 t 1.6)E 1

( 1.2 i 1.6)E I

( 0)

(-2.5 -

1.7)E 1

(-1.5 -

4.0)E 1

(-1.5 -

4.0)E 1 et 0/ 9)*

st 0/ 3)e et 0/ 3)e CE-141 ( 12)

(

3.9t 3.6)E 0 76 ( 1.4 i

.7)E 1

(-4.2 i 3.0)E 0

( - 0)

(-1.6 -

1.6)E 1

(-7.6 -

1.8)E O

(

0/ 9)*

(

0/ 11e e( 0/ 3)*

I CE-144 ( 12)

(

4.6f 109.2)E -1 27 ( 3.3 i 2.1)E 1

( 3.3 i 2.1)E 1

( 0)

(-7.3 -

2.9)E 1

(-9.1 - 58.4)E O

(

0/ 9)*

(

0/ 3)*

(

0/ 3)*

TH-232 ( 12)

(

l.6i 1.3)E 1 75 ( 8.1 t 3.4)E 1

( 8.9 i 16.9)E O

( 0)

(-3.8 -

8.1)E i

(-1.9 -

4.01E 1 et 0/ 9)*

(

0/ 1)e

(

0/ Sie e NON-ROUTINE REFERS TO TE NLMBER OF SEPARATE EASLREENTS IMICH ERE GREATER THAN TEN (10) TIES TE AWRAGE BACKGR0lND FOR TE PERIOD OF TE REPORT.

- THE FRACTION OF SAPFLE ANALYSES YIELDING DETECTABLE MEASLREMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

3-62

III.N. Foraae Beef forage is collected from two locations annually: the Plymouth County Farm (3.5 mi-H-Station Number 11) and the Whitman Farm (21 mi-NH-Station 21).

The results of the ERMAP program for the media are presented in Table III-N-1.

The following positive measurements were detected at both stations:

Be-7, Ru-103, Cs-134. Cs-137 and K-40.

The beef forage samples were both collected on 6/19/86.

The contribution of Ru-103, Cs-134 and Cs-137 were due to the Chernobyl accident.

Radioactivity from Chernobyl was seen in various media in the northeastern section of the United States during late May through early July.

Refer to Appendix F for a summary on the radioactivity detected in environmental media due to the Chernobyl accident, and Appendix G for a tabulation of the measurements.

Therefore, it is extremely unlikely that there was any environmental impact on forage due to the operation of PNPS-1.

3-63

r TABLE III-N-1 ERMAP RESULTS FORAGE 1986 TDitM: CrTLE FEED INITS! P!'/tG WE' INDICATOR STATIOR3 STATION WITH HIC +EST E*W C0hTR')L STATICWS ennenunenne nanonenonennuen enennunnu Rt.DICNJCLICES TAN EAN TAN (NO. ANALYSES) RENIRED R/#;E STA.

RANCE RANGE (NON49) TINE)

LLD Nn. CETECTED*e NO.

NO. CETECTEDu NO. DETECTED n BE-7 ( 2)

(

!.9t

.2)E 3 11 i 1.9 i

.2)E 3

( l.4 t

.2)E 3

( 0)

(

1/ 1)*

et 1/ 1)e of 1/ 1)e K-40 ( 2)

(

7.7t

.4)E 3 21

( 2.3 i

.1)E 4

( 2.3 i

.1)E 4 i

( 0)

(

1/ 1)e e( 1/ 1)e

(

1/ 1)e MN-54 ( 2) 130.

(

9.9t 152.0)E -1 11

( 9.9 1 152.0)E -1

(-1.4 t 1.8)E 1

( 0) et 0/ 1)e et 0/ 1)*

(

0/ 1)*

CO-58 ( 2) 130.

(

!.7t 1.7)E 1 11

( 1.7 1 1.7)E 1

(-6.3 1 22.3)E O

( 0) et 0/ Ile et 0/ 1)e

(

0/ 11e FE-59 ( 2) 260.

(

9.81 39.2)E 0 11

( 9.8 i 39.2)E O

(-4.0 t 5.8)E 1

( 0)

(

0/ 1)*

(

0/ 1)*

e( 0/ lie CO-60 ( 2) 130.

( -1.4t 2.5)E 1 21

( 3.4 t 2.4)E 1

( 3.4 i 2.4)E i

( 0)

( 0/ 1)*

e( 0/ lie

(

0/ 11e ZN-65 ( 2) 260.

( -1.9t 35.3)E O

(-1.9 t 35.3)E 0

(-3,0 1 4.4)E 1

( 0) et 0/ lie

( 0/ 1)*

(

0/ 1)e ZR-95 ( 2)

(

7.4t 32.9)E O 21

( 1.7 i 3.9)E 1

( l.7 t 3.9)E I

( 0) et 0/ 1)*

et 0/ 1)e et 0/ 1)*

RU-103 ( 2)

(

7.0t 1.9)E 1 21

( 2.3 i

.3)E 2

( 2.3 t

.3)E 2 l

( 0)

(

1/ lie e( 1/ 1)*

e( 1/ 1)*

NON-ROUTINE REFERS TO TE NLNEER OF SEPARATE EASLREENTS WHICH ERE CREATER THAN TEN (10) TIES TK AVERACE BACEROUND FCR TE PERIOD OF THE REPORT.

n THE FRACTION OF SAMPLE ANALYSES YIELDING IETECTABLE TARREMENTS (f.E. >3 STD DEV!ATICN31 IS INDICATED WITH et le.

3-64

TABLE III-N-1 (CONTINUED) l TDIUM: CATTLE FEED

!3dTS: PC!!KG WT INDICATOR STATIONS STATION WITH HIGHEST EAN CtNTRCL STAT!rfis seeeeee****esetees eeeeeeeeeeeeeeeeeeeeeeeen eeeeeeeenseeeeen l

RADICHUCLICES MEAN EAN EAN (NO. ANALYEES) REQUIFED RANCE STA.

RANCE RANCE (NON-ROVi!NE)'

LLD NO. [ETECTEDee NO.

NO. DETECTED **

NO. DETECTEDee RU-106 ( 2)

(

5.0f 14.9)E !

21

( 6.4 i 13.6)E 1

( 6.4 1 13.6)E 1

( 0) e' 0/ 1),

(

0/ 1)*

(

0/ 118 t

l l

1-131 ( 2)

(

7.7t 8.01E 1 21

( 3.6 t 2.6)E 2

( 3.6 i 2.6)E 2

( 0)

(

0/ 1)*

e( 0/ 1),

( 0/ 1)*

CS-134 ( 2)

(

4.81 1.3)E 1 21

( l.2 i

.1)E 2

( !.2

.1)E 2 l

( 0) l

(

1/ 1)*

(

1/ !)*

et 1/ lie CS-137 ( 2)

(

1.6t

.2)E 2 21

( 2.4 t

.2)E 2

( 2.4 t

.2)E 2

( 0)

(

1/ 11e

(

1/ 1)*

(

1/ 1)e BA-140 ( 2)

( -2.6t 5.0)E 1 11

(-2.6

5.0)E 1

(-5.3 i 9.5)E 1 l

( 0)

(

0/ lie

(

0/ 1),

(

0/ 11e j

CE-141 ( 2)

(

4.6i 2.7)E 1 11

( 4.6 i 2.7)E 1

( !.1 1 3.6)E 1 l

( 0)

(

0/ 1)e

(

0/ lle et 0/ 1)e CE-144 ( 2)

(

1.12

.7)E 2 11

( !.1 i

.7)E 2

( 8.8 i 8.0)E 1

( 0)

(

0/ Ile et 0/ 1)*

( 0/ 1)*

TH-232 ( 2)

(

7.it 6.6)E 1 21

( 1.4 i

.7)E 2

( l.4 i

.7)E 2

( 01 l

(

0/ 1)*

(

0/ 1),

( 0/ 1)*

NON-ROUTINE REFERS TO TE NLMER OF SEPARATE EASLREENTS let!CH ERE (REATER THAN TEN (10) TIES TE AVERAGE BACKGROLND FCR TE PERIOD OF TE REPORT.

u THE FRACTICN OF S#ftE ANALYSES YIELDING DETECTABLE TAslREMENTS (f.E. >3 STD IEV!ATIONSI IS INDICATED WITH el 18, 3-65

'IV.

References 1.

Regulatory Guide 1.109 - Calculation of Annual Doses to Man from Routine Releases of Reactor Effulents for the Purpose of Evaluating Compliance with 10 CFR PART 50, Appendix I -

Revision 1, October 1977.

2.

Settlement Agreement Between Massachusetts Hildlife Federation and Boston Edison Company Relating To Offsite Radiological Monitoring - June 9, 1977.

3.

Yankee Atomic Electric Company - Program "ERMAP", Version 3.1

-January 9, 1979, Author - J. E. Vossahlik.

4.

Memorandum, Yankee Atomic Electric Company,1986 Annual Direct Radiation Survey, REG 296/86, October 24, 1986, E. R. Cumming.

5.

Memorandum, Yankee Atomic Electric Company, REG. 211/76, A. E. Desrosiers.

6.

Report on Accumulation of Cesium - 137 in Cranberries, March 1979, Yankee Atomic Electric Company, M. Strum.

7.

Yankee Atomic Electric Company Report YAEC 1566, " Evaluation of Environmental Radioactivity Resulting from the Chernobyl Accident Measured by the Yankee Atomic Electric Company Environmental Laboratory", March 26, 1987, S. Farber.

8.

IE Information Notice 86-32, " Request for Collection of Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident", May 2, 1986.

4 4-1

I l

APPENDIX A - AN0MALOUS MEASUREMENT REPORTS 1

l l

A-1 i

4 There were no Anomalous Measurements for the year of 1986.

A-2

APPENDIX B - 1986 RADI0 ACTIVE EFFLUENTS B-1

EFFLUENT AND CASTE DISPOSAL SEMIANNUAL REPORT Supplemental lnformation January - June 1986 Facihr. Pilgrim Nuclear Power Station Ucensee DPR-35 1.

Itegulatoc) Umits b

A

I

.25/E + 0.10/E a.

Fissnm and activanon rases h haines 2 Ci/Qtr.

S.

Pariwulaies. hatt-hves >x day s 13[(Qs x 1.84E4) + (Qv x 1.8E5)] ~< 1 d.

Lquid einuems 10 C1/Qtr.

2.

Masimum Permissible Concentration Pnmde the MPCs uwd m delernunmg allowable release raies or soncenitatians Fissnm and astnainm gases 10 CFR 20 J.

h.

lodmes Appendia B c.

Part wutates. half.hves >x da,ss-Table II d.

Liquid eIduenis H 3 = 1 X 101 FCi/ml;all test,10 CFR 20, Appendix B. Table 11 3.

Average Energs Provide the aveiaye energy til of the radamu6hde mniure in release of fission and activanon pawn. It appheable. E = 1 Mew 4.

Measurement: and Approsimations of Total Radioactivity Pnmde the metinids used to nwasur or appuniinsic the 0141 radioactmt3 in ef duents and tie nwthods uwd in determme radamu hde compnsioon a.

Fissnm and 4 tivatain pases o,ti h.

lodmes-g,,;,

c.

Parti.ulates-d.

bquid ethents:

^^*I"

5.

Asteh fieleones Piovide ihe sullowing information retaimp io batch reicases of radniactive materials in hquid and passous efnuents.

a.

Uquid 1.

Number of batch releaws-143

~

2.

Toral time penoJ tot hatch releases 368.7 hr.

3.

Masimum tinw perud for a batch release. - 8.42 hr.

4.

Average time period for bahh releases 2.57 hr.

5.

Minimum tune penod foi a hatch release: - 0 2 5 hr.

6.

Averspe stream nom dunng penods of relesw ofefiTueni mio a Ikiwmg stream: 2.34E5 gpm b.

Caneous (Not Appucable) 6.

Abnormal Releases

[,None w

2 1

1 TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES January - June 1986 Quarter Quarter Est. Total Unit 1

2 Error. %

A. Fission and activation gases

1. Total release Ci 1.25E2 8.86E-1 35 l

2. Average release rate for period pCi/sec 1.59El 1.13E-1

3. Percent of Technical Specification limit 5.91E-3 5.76E-4 B. Iodines

1. Total iodine 131 Ci

< 7.24E-3

< 6.50E-4 30 l

2. Average release rate for period pCi/sec

< 9. 21E-4

< 8. 26E-5

3. Percent of Technical Specification limit

< 3. 62E-1

< 3.25E-2 C. Particulates

~

1. Particulates with half. lives > 8 days Ci

< 2. 31 E-3

< 8.65E-4 30 l

2. Average release rate for period uCi/sec

< 2,94E-4

<1.10E-4

3. Percent of Technical Specification limit

< 5.43E-2

< 2.17E-2

4. Gross alpha radioactivity Ci

< 8. 29E-7

< 6. 84E-7 D. Tritium

1. Total release Ci 3.94E0 4.86E-1 42 l

2. Average release rate for period uCi/sec 5.01E-1 6.17E-2

3. Percent of Technical Specification limit b

3

/

TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986 )

GASEOUS EFFLUENTS - ELEVATED RELEASE January - June 1986 CONTINUOUS MODE BATCH MODE l Nuclides Released l

Unit l

Quarter 1l Overter 2l Quarter l

Quarter l

1. Fission gases krypton 85 Ci 2.72E-3 krypton-85m Ci 1.62El krypton 87 Ci krypton 88 Ci o_RRrn xenon.133 Ci 8.74E1 xenon 135 Ci 7.30E-1 xenon 135m Ci xenon 138 Ci e

menon 131m Ci xenon 137 Ci xenon 133m Ci Total for period Ci 1.14E2

2. lodines

Plant Shutdown 2nd Quarter 1986 iodine 131 Ci

< 3.28E-3

< 2.23E-4 iodine-133 Ci

< 7.85E-3

< 5.36E-4 lodine-135 Ci

< 5.65E-3

< 1.31E-3 Total for period Ci e 1.68E-2

< 2.09E-3

3. Particulates strontium 89 Ci 9.41E-5

< 5.66E-6 strontium 90 C1 1.92E-6

< 1.00E-7 cesium 134 Ci cesium 137 Ci

< 1.92E-5

< 1.97E-5 barium lanthanum 140 Ci e 3.24E-4

< 5.91E-5 chromium 51 Ci manganese 54 Ci 3.51E-6

< 5.24E-6 cobalt 58 Ci

< 4.16E-6 iron 59 Ci

~~

cobalt 60 Ci

< 9.91E-5

< 5.60E-5 zine 65 Ci zirconium niobium 95 Ci cerium.141 Ci cerium 144 Ci ruthenium 103 Ci ruthenium 106 Ci 4

TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

GASEOUS EFFLUENTS GROUND LEVEL RELEASE January - June 1986 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Guarter 1 Quarter 2 Quarter Quarter

1. Fission gases krypton 85 Ci I

krypton 85m Ci 7.97E-1 i

krypton 87 Ci 2.48E0 krypton 88 Ci 2.64E0 xenon 133 Ci 1.46E0 I

xenon 135 Ci 3.92E0 8.86E-1 menon 135m Ci menon 138 Ci Total for period Ci 1.13E1 8.86E-1

~

2. Iodines iodine-131 Ci

< 3.96E-3

< 4.27E-4 iodine 133 Ci

< 2.55r-2

< 8.89E-4 lodine 135 Ci

< 4.60E-2

< 5.58E-3 Total for period Ci

< 7.55E-2

< 6.90E-3

/

3. Particulates strontium 89 Ci 1.96E-4

< 9.24r-6 strontium 90 Cl 1.08E-6

< 4.50E-7 cesium 134 Ci cesium 137 Ci

< 6.59E-5

< 6.64E-5

< l.27E-3

< 5.55E-4 barium lanthanum 140 Ci manganese 54 Ci

< 1.23E-5

< 1.18E-5 cobalt 58 Ci

< l.47E-5 l

iron 59 Ci

< 3.78E-6 cobalt 60 Ci

< 1_RAr-4

< s _ ur_;

sine 65 Ci airconium niobium 95 Ci cerium 141 Ci 4.00E-5 ruthenium 103 Ci ruthenium 106 Ci t

5

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

LlOUlD EFFLUENTS-SUMMATION OF ALL RELEASES January - June 1986 Quarter Quarter Est. Tc'.at Unit 1

2 Error, %

A. Fission and activation products

1. Total release (not including tritium, Ci

< 7. 39E-2

< 4.61E-2 30 noble gases, or alpha)

2. Average diluted concentration yCi/ml

< 1.08E-8

< 5.38E-9 during period

3. Percent of applicable limit

< 7. 39E-1

< 4. 61E-1 B. Tritium

1. Total release Ci 5.90E0 2.21EO 30

2. Average diluted concentration yCi/ml during period 8.60E-7 2.58E-7

3. Percent of applicable limit 8.60 2.58 C. Dissolved and entrained gases

1. Total release Ci 1.30E-3 7.56E-3 40 l

2. Average diluted concentration pCi/ml during period

3. Percent of applicable limit D. Gross alpha radioactivity l

1. Total release l

Ci l < 1.47E-4 l<2.nir-a l

l An E. Volume of waste released (prior liters 2.76E6 3.55E6 20 to dilution)

F. Volume of dilution water used liters 6.86E9 8.57E9 20 during period l

t l-l I

l 6

1 TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)

LIQUID EFFLUENTS January - June 1986 CONTINUOUS MODE BATCH MODE i

Nuchdes Released Unit Quarter 1 Quarter 2

Quarter Quarter strontium 89 Ci

< 2.02E-4

< 6.76E-5 strontium-90 Ci

< 6.86E-5

< 1.90E-5 cesium 134 Ci 4.26E-4 9.48E-6 l

cesium 137 Ci 9.44E-3 1.57E-3 i

iodine 131 Ci 8.49E-4 7.81E-5 cobalt 58 Ci 8.13E-5 5.68E-4 l

cobalt 60 Ci 7.86E-3 6.78E-3 l

iron 59 Ci 3.06E-4 an:WNkx Sr Ci 4.27E-7 I

manganese 54 Ci 7.64E-5 1.23E-3 chromium 51 Ci 1.06E-3 1

i zirconimum niobium-95 Ci 2.56E-6 p 1-135 4.58E-4 tarkastamax99mx Ci l

barium lanthanum 140 Ci 1.19E-5 cerium 141 Ci 1.72E-6 1.43E-5 1

iodine-133 Ci 2 sor_q 7.ggv_s cerium 144 Ci 2.67E-4 silver 110m Ci fron 55 Ci

< 2.80E-2 unidentified l

Ci l

2.39E-2l 3.41E-2l l

l Total for period (above)

Ci

< 7.39E-2

< 4.61E-2 xenon 133 Cl 1.72E-4 1.71E-3 xenon 135 C1 1.13E-3 5.85E-3 7

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information (July-Dece;;.ber 1986)

Faciht) Pilgrim Nuclear Power Station Ucenwe DPR-35 1.

Regulatory Umits

a. Noble Gases :

4 500 mrem /yr total body and 4 3000 mrem /yr Tor skin at site Boundary h.

lodmes

/ month for/vr to any oraan_ at Site Boundary 41500 mrem c.

Particui2ies. hair.hves >x dass total body arfd 0.20 mrem / month d.

oquid einuenis: 0.06 mr for any organ without Radwaste Treatment.

2.

Mnimum Permissible Concentration Piovide the MFrs uwd in deiermimng allowable release rates or concentrations.

a.

Fessen and activation gases:

to CFR 20 h.

lodmes Appendix B t.

Pariiculates. half-hves >M dayt Table II d.

Liquid etnuenis. u. 3.

x so-s pCi/mt;all rest,10 CFR 20, Appendix B. Table II 3.

Average Energv Provide alw aveuge energy (U of the radamuchde miunte m releases os tisuon and astivation gases. it appheable.

13(Qs x 1.84E4 + Qv x 1.8E5) 4 1 4.

Measurements and Approsimations of Total Radioactiv@

Provide the methods used 1o measur or appmumate the total radioacimiy m etnuenis and the nwthods used to determine radamushde comrnsition a.

Fissen and a.tivainm gases.

Geu h.

lodines istopic c.

Part:(utates d.

oquid einuenis:

Analysis 5.

Ratch Releases Piovide tir followmg information relaimg to batsh releases of radioactive materials m hquid and gaseous ernuents.

a.

Uquid I.

Number of batch relesws: 125 216.7 Hours 2.

Total time permd for hatch releases 3.

Maximum tmw pernsi for a batch release:- 10.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 4.

Avenge time permd for hatsh releases-1.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 5.

Mmimum tmw penod for a hatch release 0.08 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 6.

Average stream now dunng penods of releaw of efITuem mio a nowmg stream.

1.55E5 GPM b Gawous (Not Applicable) 6.

Abnormal Relesws Gaseous a,

b. Liquid flone 2

3s g

\\~

s TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT (19E6; GASEOUS EFFLUENTS. SUMMATION OF ALL RELEASES (July - Decerter 1936) j l

Quarter Quarter Est Total Urut

(

i 3

}

g Error. 9 A. Fission and activation gases j

1. Total release Ci i

l

2. Average release rate for penod

, uCi'sec !

[

3. Percent of Technical Specification limit j i

l B. lodines

1. Total iodine.131 -

C1 41.26E-4 I4 1.56E 4 30 i

2. Average relesse rate for period u ci'sec 4 1.60E-5 j4 1.98E-5 t

i i

j

3. Percent of Technical Specification hmit l

1.43E-2 l 1.77E-2 l

l C. Particulates

1. Particulates with half. lives > 8 days Ci 44.56E-4 4 6.06E 4 30

2. Average relene rate for period uCi/sec 4 5.79E-5 47.70E-5 l

3. Percent of Technical Specification limit 1.25E-2 1.23E-2 j

4. Gross alpha radioactivity Ci l 4 6.07E-7 4 7.58E-7 D. Tritium

1. Total release Ci 1.39E-1 1.66E-1 42 l

2. Average release rate for period uCi/see 1.77E-2 2.11E-2 l

3. Percent of Technical Specification limit 1.74E-2 2.10E-2

Plant Shutdoun 3rd a 4th Quarter 1986 0

\\

L..

I e

t l

l t

TABLE SB EFFLUENT AND WASTE DISPOSAL SEMI AWNUAL REPORT i 1Ef f i GASEOUS EFFLUENTS - ELEVATED RELEASE

(.Nij - :e:e-ter 192E)

CONTINUOUS MODE BATCH MODE Quarter 3 Quarter 1. l Quarter l

Qua*te.

Nuchoes Released Urut i

1. Fission gases krypton 55 Ci l

l l

l krypton 55m i

Ci i

l krypton 5.

i Ci 1

j l

}

i krypton SS I

C

- xenon 133 I

Ci I

xenon 135 l

Ci l

l l

xenon 135m Ci l

xenon 136 Ci i

l xenon 131m Ci l

1 xenon 137 Ci

~

l l

xenon 133m Ci l

e Total for p+nou Ci l

l j

Plant Stutdown 3rd + 4th Guarter 1986

2. lodim iodine 131 Ci e 2.51E-5 4 2.89E-5 l

iodine 133 Ci 4 8 76E-5 e.8.97E-5 iodme 135 '

Ci e 8.llE-4 j < T 8E-4 Total for penod Ci 4 9.25E-4 'l 4 9.86E-4,

i

3. Particulates l

l Ci 4 7.06E-7 ) < 3.59E-7 strontium 89 I

strontium 90 Ci 4'1 qqr.7 4 3_ggr_7 cesium 134 Ci i

cesium 137 Ci 4 4.45E-6 e 3.86E-5 l

banum lanthanum 140 Ci 4 3.44E-5 4 5.45E-5 I

chromium-51 Ci l

manganese 54 5i Ci cobalt 58 Ci tron 59 r

Ci cobalt 60 1

Ci 4 2 48E-5 4 3.12E-5 j

zinc.65 Ci

)

r

{

zircomum mobium 95 Ci cenum 141 Ci 1.35r.7 l

l cenum 144 Ci 4

(.

t n

i' ruthemum 105 Ci ruthenium 10C' Ci l

3 4

x c

TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT (1786)

GASEOUS EFFLUENTS GROUND LEVEL RELEASE

(.1uly - Decec er 19E6)

CONTINUOUS MODE BATCH MODE Nuchdes Released l

Urut j

Quarter 3-Quarter l

Ouarter l Ouarte.

1. Fission gases krypton 55 l

Ci j

krypton 55m Ci krypton 87 i

C krypton SS l

Ci j

xenon 133 i

C i

~

l xenon 135 i

Ci xenon 135m l

Ci l

I xenon 135 Ci l

l Total for period Ci l

Plant Shutdown 3rd+4th Quarter 1956

2. lodines l

iodme-131 Ci

<- 1. 01 E-4 1 4 1.27E-4 '

iodine 133 C

e 3.62E-4 4 3.22E-4 l iodine 135 Ci e 3.66E-3 e-3.57E-3 i i

Total for period Ci c 4.12E-3 44.01E-3l

3. Particulates a

strontium 89 Ci e.l.70E-6 1 4: 1. per-06 l strontium 90 Ci 4 4.e6E-7 i e 5.19E-07 cesium 134 Ci cesium 137 Ci 4 2.58E-5 l 4 9.05E-5 I

barium lanthanum 140 Ci e.2.27E-4 4 2.69E-4 I manganese 54 Ci cobalt SS Ci iron 59 Ci cobalt 60 C2 e 1.37E-4 1.18E-4 zme 65 Ci I

zirconium mobium 95 Ci l

1.16E-6 cerium 141 Ci j

ruthenium 103 Ci l

ruthemum 106 Ci 1

r" l

5

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (19865 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES (July'- Dece.ber 1956';

f Quarter Quarter Est Total i

Urut 1

3 4

E rror. --e A. Fission and activation products j

1. Total release enot including tritium.

Ci 4 3.69E-2 4 5.3SE-2 30 i

noble gases, or alphai

2. Average diluted concentration uCi ml 1.49E-8

1. 04 E-8 i

dunng period l

3. Percent of applicable limit 4.70E0 7.25E0 B. Tritium

1. Total release ci 5.76E-1 1.35E0 30 I

2. Aserage diluted concentration uCi ml

~

during penod

3. Percent of applicable limit 4.13E0 9.70E0 C. Dissolved and entrained gases l

1. Total release Ci 2., Average diluted concentration uC'ml dunng period

3. Percent of applicable limit D. Gross alpha radioactivity l

1. Total release l

Ci l

5.88E-5 l 1.60E-4 l 40 l

E. Volume of waste released (pnor liters 8.86E5 2.86E6 20 to dilutioni F. Volume of dilution water used liters 2.47E9 5.16E9 20 during penod

Plant Shutdown 3rd and 4th Quarter 1986 Note:

Radwaste Treatment System in Use.

6

i l

I TABLE 2B.

' EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT (19EE)

. LIQUID EFFLUENTS

' July - Dece-ter 19Ef)

[

CONTINUOUS MODE BATCH MODE i

l.

Ruchees Releasee i

l ouarter 3 ouarter 2 umt ouarter cuarter 5 ront:um 59 I

Ci 3.06E-E 4 9.42E-05 strontium 90 i

Ci 2.76E-5, g,gg g3 t

cesium 134 i

ci 3.78E-5 1 6.E:E-5 l

cesium 137 i

Ci 1.E1E-3 l 4.35E-3 j

iodme 131 l

Ci l

- ]

l cobalt 58 Ci l

7.31E-5I 7.6:E,

cobalt 60 -

Ci l

6.85E-[j 1.31E-2 i iron 59 Ci I

6.44E-6 5.62E-E-zin:-5E Ci l

2.81E-5 manganese 54 Ci 6.00E-4

-2.1 E-3 chromium 51 Ci 7.02E-5l 9

I zirconinw niobiu', 95 Ci n

mlybdent ~

~

tecenetion-99m Ci barium lanthanum 140 Ci cenum 141 Ci iodme 133 Ci l

I cenum 144 Ci l

silver-110m Ci l

iron 55 Ci 3 g3r-p

s. 52 E- 0 3' l

umdentified l

Ci l

l l

8.34E-3l 2.52E-2l l

3.69E-2 5,33g.pj Total for penod tabotel C

xenon 133 l

Ci l

xenon 135 l

Ci l

l g

7

APPENDIX C-SOIL SURVEY t

C-1 O

6

INTRODUCTION In compliance with Boston Edison's *.echnical Specifications for Radiological Monitoring of the environment, in-situ gamma spectrometry analyses were performed at the eleven routine air particulate stations between August 26 and August 30, 1985.

Gamma spectrometry measurements were performed using a High Purity Germanium detector (HPGe) in conjunction with the Yankee Atomic Environmental Laboratory (YAEL) portable computer system. Measurements were also taken with a High Pressure Ionization Chamber (HPIC) for assessment of total exposure rates. Soil core samples were obtained at Station 07 (Pedestrian Bridge) for comparison to the in-situ analysis at that station.

METHODOLOGY

'itu gamma spectrometry analysis is used to evaluate the presence of radionut'. des in soil.

Using assumptions concerning the soil composition and distribution of the radionuclide of interest, the exposure rate and activity

. concentration of that radionuclide can be calculated. This is done through the evaluation of a spectrum obtained with an unshielded Germanium detector placed on a tripod such that the detector's sensitive volume is one meter above the ground.

The spectral evaluation accounts for detector specific parameters such as ef ficiency and resolution. The radionuclides of interest are fallout and plant related fission and activation products, as well as naturally occurring radionuclides such as thorium and uranium.

In evaluating the activity concentration and exposure rate for a given radionuclide, a parameter describing radionuclide depth distribution, s/p, must be evaluated.

For naturally occurring radionuclides a value of zero is assumed, implying no increase or decrease in the concentration with soil depth. For radionuclides present only on the surface, such as those from.

fresh fallout, a planar source is assumed and a value of infinity is used.

(Infinity is also used for calculations of apparent activity concentrations and exposure rates for those radionuclides not identified during the peak search.)

For manmade radionuclides found in the soil and not believed to be

~

recently deposited, an exponential distribution is assumed with an a/p of 0.206.

This value is a good compromise between deep distribution and surf ace deposition, and laboratory analysis usually confirms that these radionuclides I

1

';4NKEE ATOMIC ELECTRIC COMPANY Tc'cohone te ") s'2-8100 TWX 710 380 7619 U~ '95

'd h

1671 Worcester Road, Framingham, Massachusetts 01701

. ~ -

A lk E

/

February 6, 1986 EL 043/86 Christine Bowman Boston Edison Company 25 Braintree Hill Office Park Braintree, MA 02184

Dear Chris:

Enclosed please find the 1985 In-situ report for Boston Edison.

If there are any questions please call me at Extension 2510.

Sincerely,

d. C. Murray Environmental Laboratory JCM/fsf cc:

B. Lunn (BEco)

E. Cumming D. E. McCurdy C. L. Harrington E. L. Laurenzo

are present throughout the first six inches of soilo implying a period of migration. This procedure of in-situ gamma spectrometry is explained in detail in References 1 and 2.

t The HPIC measurements include all components of the exposure rate including terrestrial.

At control stations, away from the plants influence, the HPIC measurement is used to check the in-situ results.

The sum of the 3.6 pR/h cosmic contribution and the terrestrial exposure. rate calculated using the in-situ methodology should closely approximate the HPIC results(3).

When warranted, soil core samples were also taken and analyzed at the l

YAEL to confirm the presence of radionuclides in the soil which have been identified in the in-situ analysis.

In this way, the source term is identified as soil or unknown.

In addition, analysis of the different core sections aids in defining the depth distribution of the radionuclide.

RESULTS Tables 1-11 contain the results f rom the in-situ ganna analysis for the eleven stations.

Each table lists the apparent exposure rate and activity concentration for each of thirteen fission and activation products, as well as for three naturally occurring radionuclides.

Lower Limit of Detection (LLD) values were not calculated for nuclides with more than one peak, as in these cases all of'the peaks found were used to calculate the total weighted exposure rate and activity concentration for that nuclide or series. Table 12 contains all positive in-situ results as well as HPIC measurements for comparison.

For ten of the eleven stations evaluated, no atypical levels of Cs-137 or naturally occurring radionuclides were detected. The Cs-137 is considered to be a result of weapons testing and is found throughout the environment.

The one station where non-fallout related radionuclides were identified was Station 07 (Pedestrian Bridge). The presence of Co-60 was identified during the in-situ analysis and confirmed by Laboratory soil analysis. The Co-60 concentration calculated by the in-situ methodology was 122.6 6.5 pCi/kg, assuming a value for a/p of 0.206, while laboratory soil analysis 2

= - - -. -

i I

i calculated a Co-60 concentration in the first two inches of soil of 55.6 2 9.1 pCi/kg.

The value for e/p is likely to be greater than 0.206, i.e., the distribution of Co-60 was probably more planar, since Co-60 was not found in the 2" - 4" or 4" - 6" core sections.

The increased a/p value would result in a lower value for the Co-60 concentration calculated by the in-situ

methodology. Using an a/p of infinity, the in-situ methodology calculated a Co-60 concentration of 37.9 2.0 pCi/kg which is in agreement with the Co-60 concentration of 55.6 9.1 pCi/kg calculated by laboratory soil analysis (4).

It should be noted that in either case, the contribution of the Co-60 to the total exposure rate is not sufficient to raise the total exposure rate above that which was measured at the control station (Table 12).

The Cs-137 concentration measured at Station 07 cr.n also be compared to the laboratory soil core analysis. An m/p of 0.206 was shown by the core analysis to be the best estimate of the distribution of the Cs-137 in the soil since positive Cs-137 concentrations were detected in all three sections.

In t

addition, the Cs-137 concentration of 154 1 14 pCi/kg calculated by the in

' situ methodology is in agreement with the top core section result of 200 i 10 pCi/kg (4).

For comparison purposes, the in situ and HPIC measurements were regarded as duplicate analyses and were evaluated according to the YAEL criteria for precision and accuracy. At most stations, the HPIC measurements agreed well with the in-situ results when a cosmic contribution of 3.6 yR/h was added. At Stations 00, 07 and 08, higher exposure rates were found using the HPIC.

These sites are all within 0.15 miles of the plant, and the higher background exposure. rates were likely a result of some source term other than the soil, f It should be pointed out that the 1985 Station 00 (Warehouse) location is different from the location analyzed in 1982. Access to the 1982 location was prevented by excavation near that site. The location evaluated in August,'

1985 is 100 feet southwest of the warehouse air sampler, and the old location is 150 feet east of the air sampler.

3

REFERENCES 1.

YAEL Procedure 510, Rev. 2 " Identification and Quantitative Determination of Radionuclides in Soil by Gamma-Ray In-situ Spectrometry."

2.

HASL-258, "In-Situ Ge(Li) and NaI(TI) Gamma-Ray Spectrometry," September 1972.

3.

" Cosmic-Ray Ionization in the Lower Atmosphere," Wayne M. Londer and Harold Beck, Journal of Geophysical Research, Vol.17. No.19, October 1, 1966.

4.

YAEL Procedure 740, Attachment I, " Yankee Atomic Environmental Laboratory Criteria for Quality Assurance Agreement for Accuracy and Precision."

m O

4

TABLE 1 LOCATION:

WAREHOUSE LOCATION 4:

00 COUNT TIME:

6000sec COUNT DATE:

082985 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION microR/hr picoCi/Kgram NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

( 36+- 20) E-4 73E-4

( 163+- 91) EO 330E O Ce-141

(

1+- 17) E-4 63E-4

(

1+- 19) EO 68E O I-131

( 55+- 43) E-4 150E-4

( 76+- 59) E-1 210E-1 Sb-125

(-4+- 13) E-3 48E-3

(-4+- 15) EO 54E O Ru-103

(

19+- 47) E-4 170E-4

( 18+- 45) E-1 160E-1 Ba-140

(-20+- 67) E-4 240E-4

(-5+- 16) EO 57E O Re-106

(

11+- 18) E-3 65E-3

( 23+- 39) EO 140E O 0+

Cs-137

( 958+- 85) E-4 260E-4

( 174+- 15) EO 47E O Zr-95

(

5+- 12) E-3 46E-3

( 26+- 67) E-1 250E-1 Nb-95

(-121+- 73) E-4 280E-4

(-62+- 37) E-1 140E-1 La-140

(-22+- 84) E-3 310E-3

(-3+- 11) EO 40E O Mn-54

(-35+- 78) E-4 290E-4

(-16+- 35) E-1 1.30E-1 Co-60

(

B+- 25) E-3 94E-3

(

11+- 32) E-1 120E-1 a+ K-40

( 1975+- 47) E-3 110E-3

( 1103+- 26) E1 60E 1

( 715+- 32)'E O 0+

Th-232

( 2016+- 90) E-3

( 638+- 31) E0 o+ U-238

( 1160+- 57) E-3 Notes e

Activity greater than 3* standard deviation

+

Peak is found LLD is not calculated

l TABLE 2 l

LOCATION:

EAST ROCKY HILL ROAD LOCATION #:

01 COUNT TIME:

6000sec COUNT DATE:

082885 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION microR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE C'a-144

(-20+- 13) E-4 47E-4

(-91+- 58) EO 210E O Co-141

( 11) E-4 41E-4

(-5+- 12) EO 44E O I-131

(

2+- 29) E-4 110E-4

( 2+- 40) E-1 150E-1 Sb-125

(-29+-

95) E-4 340E-4

(-3+- 11) E0 39E O Rv-103

( 64+-

33) E-4 110E-4

( 61+- 31) E-1 110E-1 Bo-14,0

(

10+~ 47) E-4 170E-4

( 2+- 11) EO 39E D Rv-106

(-5+- 13) E-3 48E-3

(-12+- 28) EO 110E O C+ Cs-137

( 361+- 10) E-3 24E-3

( 657+- 18) EO 43E O Zr-95

( 114+- 83) E-4 300E-4

( 62+- 45) E-1 160E-1 Nb-95

( 103+- 50) E-4 180E-4

( 53+- 26) E-1 93E-1 Lc-140

-(

47+- 56) E-3 200E-3

( 60+- 71) E-1 260E-1 Mn-54

(

0+- 54) E-4 200E-4

(

0+- 24) E-1 91E-1 Co-60

( 23+- 16) E-3 5BE-3

( 30+- 20) E-1 75E-1 c+ K-40

( 1363+- 35) E-3 58E-3

( 761+- 20) E1 33E 1

( 616+- 22) EO 0+ Th-232

( 1737+- 63) E-3

( 584+- 23) EO o+ U-238

( 1063+- 41) E-3 Notos:

u Activity greater than 3* standard deviation

+

Peak is found LLD is not calculated

TABLE 3 LOCATION:

WEST ROCKY HILL ROAD LOCATIONS:

03 COUNT TIME:

6000sec COUNT DATE:

082885 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION nicroR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

(-2+- 14) E-4 52E-4

(-9+- 65) EO 230E O Ce-141

(-12+- 13) E-4 45E-4

(-13+- 13) EO 49E O I-131

(

17+- 33) E-4 120E-4

( 23+- 45) E-1 160E-1 Sb-125

( 20+- 11) E-3 37E-3

( 23+- 12) EO 42E O Rv-103

(

9+- 37) E-4 130E-4

(

9+- 35) E-1 130E-1 Ba-140

( 20+- 55) E-4 200E-4

(

5+- 13) EO 46E O Ru-106

(-4+- 15) E-3 54E-3

(-10+- 32) EO 120E 0 0+ Cs-137

( 561+- 65) E-4 190E-4

( 102+- 12) EO 35E O Zr-95

(

0+- 10) E-3 39E-3

(

1+- 56).E-1 210E-1 Nb-95

(-55+- 64) E-4 240E-4

(-28+- 33) E-1 120E-1 La-140

(-34+- 70) E-3 260E-3

(-43+- 90) E-1 340E-1 Mn-54

( 21+- 67) E-4 250E-4

( 10+- 30) E-1 110E-1 Co-60

( 25+- 17) E-3 61E-3

( 33+- 21) E-1 7BE-1 o+ K-40

( 2558+- 48) E-3 76E-3

( 1429+- 27) E1 42E 1

( 888+- 28) EO Q+ Th-232

( 2504+- 79) E-3

( 672+- 26) EO, m+ U-238

( 1224+- 48) E-3 Notes:

Activity greater than 3ustandard deviation

+

Peak is found LLD is not calculated

i TABLE 4 LOCATION:

PLYMOUTH CENTER LOCATION 4:

04 COUNT TIME:

6000sec COUNT DATE:

082985 InSito COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION nitroR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

(

18+- 16) E-4 56E-4

( B2+- 70) EO 250E O Ce-141

(-28+- 14) E-4 50E-4

(-30+- 15) EO 53E O I-131

( 65+- 36) E-4 130E-4

( 89+- 49) E-1 180E-1 Sb-125

(

4+- 11) E-3 41E-3

( 5+- 13) EO 47E O Ru-103

(-65+- 41) E-4 150E-4

(-61+- 39) E-1 140E-1 Ba-140

( 95+- 59) E-4 210E-4

( 22+- 14) EO 49E O Ru-106

(

5+- 16) E-3 58E-3

( 12+- 35) EO 130E 0 c+ Cs-137

( 325+- 11) E-3 32E-3

( 591+- 21) EO 5GE O Zr-95

(-7+- 11) E-3 42E-3

(-35+- 61) E-1 230E-1 Nb-95

( 60+- 68) E-4 250E-4

( 31+- 35) E-1 130E-1 La-140

(-106+- 74) E-3 280E-3

(-135+- 95) E-1 360E-1 Mn-54

(-73+- 71) E-4 270E-4

(-33+- 32) E-1 120E-1 Co-60

(-7+- 19) E-3 73E-3

(-10+- 24) E-1 93E-1 a+ K-40

( 2685+- 48) E-3 65E-3

( 1500+- 27) E1 36E 1

( 1014+- 29) EO o+ Th-232

( 2860+- 80) E-3

( 1011+- 2Y) E0 0+ U-238

( 1840+- 52) E-3 Notes:

O Activity greater than 3ostandard deviation

+

Peak is found LLD is not calculated

TABLE 5 LOCATION:

PROPERTY LINE LOCATION 4:

06 COUNT TIME:

6000sec COUNT DATE:

082685 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION microR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

(-15+- 13) E-4 48E-4

(-67+- 60) E0 220E O Ce-141

( 13+- 12) E-4 42E-4

(

14+- 12) EO 45E O I-131

(-12+- 30) E-4 110E-4

(-16+- 40) E-1 150E-1 Sb-125

(-39+- 92) E-4 330E-4

(-4+- 10) EO 38E O Ru-103

( 42+- 32) E-4 110E-4

( 40+- 30) E-1 110E-1 Ba-140

(-31+- 49) E-4 180E-4

(-7+- 11) EO 41E O Ru-106

(

0+- 13) E-3 47E-3

(

0+- 28) EO 100E O 0+ Cs-137

( 1361+- 72) E-4 190E-4

( 247+- 13) EO 34E O 2r-95

( 136+- 91) E-4 330E-4

( 73+- 49) E-1 180E-1 Nb-95

(-13+- 54) E-4 200E-4

(-7+- 28) E-1 100E-1 La-140

(-11+- 60) E-3 220E-3

(-14+- 77) E-1 290E-1 Mn-54

(-44+- 55) E-4 210E-4

(-20+- 25) E-1 94E-1 Co-60

(-7+- 15) E-3 57E-3

(-9+- 19) E-1 74E-1 0+ K-40

( 1772+- 39) E-3 55E-3

( 990+- 22) E1 31E 1

( 545+- 22) EO n+ Th-232

( 1536+- 62) E-3

( 451+- 21) EO f----

( B21+- 38) E-3 0+ U-238 Notes a

Activity greater than 3* standard deviation

+

Peak is found LLD is not calculated

TABLE 6 LOCATION:

PEDESTRIAN BRIDGE LOCATIONS:

07 COUNT TIME:

6000sec COUNT DATE:

082785 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION microR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

( 24+- 22) E-4 80E-4

( 106+- 99) EO 360E O Ce-141

( 3O+- 19) E-4 69E-4

( 32+- 20) EO 74E O I-131

(-55+- 40) E-4 150E-4

(-75+- 55) E-1 200E-1 Sb-125

(

6+- 12) E-3 42E-3

( 7+- 13) EO 48E O Ru-103

( 52+- 40) E-4 140E-4

( 50+- 38) E-1 140E-1 Ba-140

(-70+- 60) E-4 220E-4

(-16+- 14) EO 51E O Ru-106

(

8+- 16) E-3 5BE-3

( 18+- 34) E0 130E O o+ Cs-137

( B4B+- 76) E-4 230E-4

( 154+- 14) EO 41E O Zr-95

(-1+- 10) E-3 3BE-3

(-5+- 55) E-1 210E-1 Nb-95

(-27+- 61) E-4 230E-4

(-14+- 32) E-1 120E-1 La-140

(-150+- 69) E-3 260E-3

(-191+- 88) E-1 340E-1

~

Mn-54

( 11+- 67) E-4 250E-4

( 5+- 30) E-1 L10E-1 o+ Co-60

( 398+- 21) E-3 100E-3

( 1226+- 65) E-1 310E-1 o+ K-40

( 1380+- 36) E-3 61E-3

( 771+- 20) E1 34E 1

(.517+- 19) EO o+ Th-232

( 1458+- 53) E-3

-- =-

( 374+- 23) EO o+ U-238

( 681+- 41) E-3 Notes:

e Activity greater than 3* standard deviation

+

Peak is found LLD is not calculated

l TABLE 7 LOCATION:

DVERLOOK LOCATIONS:

08 COUNT TIME:

6000sec COUNT DATE:

082785 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION nicroR/hr picoCi/Kgran NkME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD I

RATE Ce-144

(-48+- 30) E-4 110E-4

(-22+- 13) E1 49E 1 Ce-141

(-13+- 26) E-4 93E-4

(-14+- 28) EO 100E O I-131

(-33+- 61) E-4 220E-4

(-45+- 83) E-1 300E-1 Sb-125

(

6+- 18) E-3 66E-3

( 7+- 21) EO 74E O Ru-103

( 44+- 66) E-4 240E-4

( 41+- 63) E-1 230E-1 Ba-140

(-44+- 91) E-4 330E-4

(-10+- 21) EO 77E O Rv-106

(-1+- 24) E-3 90E-3

(-3+- 53) EO 200E O c+ Cs-137

( 58+- 11) E-3 35E-3

( 105+- 19) EO 63E O 2r-95

(-9+- 17) E-3 62E-3

(-47+- 90) E-1 340E-1 Nb-95

( 276+- 96) E-4 350E-4

( 142+- 49) E-1 180E-1 La-140

(

9+- 11) E-2 42E-2

( 11+- 15) EO 54E O Mn-54

(

9+- 11) E-3 39E-3

( 41+- 48) E-1 180E-1 Co-60

('40+- 36) E-3 140E-3

( 52+- 46) E-1 170E-1 0+ K-40

( 1915+- 51) E-3 130E-3

( 1070+- 29) E1

'71E 1

( 647+- 47) E0 o+ Th-232

( 182+- 13) E-2

( 334+- 26) EO o+ U-238

( 607+- 47) E-3 Notes o

Activity greater than 3* standard deviation

+

Peak is found LLD is not calculated d

i

TABUE 8 LOCATI0ti:

EAST BREAKWATER LOCATION 4:

09 COUNT TIME:

6025sec COUNT DATE:

082885 InSitu COUNTING RESULTS I

NUCLIDE ID EXPOSURE RATE CONCENTRATION nicroR/hr picoCi/Kgran

.NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Co-144

( 10+- 13) E-4 44E-4

( 45+- 56) EO 200E O Co-141

(-2+- 11) E-4 38E-4

(-2+- 12) EO 41E O I-131

(-66+- 28) E-4 99E-4

(-90+- 38) E-1 140E-1 Sb-125

( 156+- 87) E-4 300E-4

( 177+- 98) E-1 340E-1 Ru-103

(-2+- 31) E-4 110E-4

(-2+- 30) E-1 100E-1 Bo-140

( 57+- 46) E-4 160E-4

(

13+- 11) EO 37E 0 Rv-106

(

0+- 13) E-3 46E-3

(-1+- 28) EO 100E 0 O+ Co-137

( 665+- 79) E-4 260E-4

( 121+- 14) EO 47E O Zr-95

(-102+- 89) E-4 330E-4

(-55+- 48) E-1 180E-1 Nb-95

(

4+- 52) E-4 190E-4

(

2+- 27) E-1 97E-1 Lo-140

.( 29+- 59) E-3 210E-3

( 37+- 75) E-1 270E-1 Mn-54

( 3+- 53) E-4 190E-4

(

1+- 24) E-1 BBE-1 l

Co-60

( 39+- 15) E-3 53E-3

( 50+- 19) E-1 6BE-1 0+ K-40

( 234B+- 44) E-3 53E-3

( 1311+- 25) E1 30E 1

( 706+- 25) EO 0+ Th-232

( 1990+- 69) E-3

( 577+- 23) EO o+ U-238

( 1050+- 41) E-3 Notos a

Activity greater than 3Mstandard deviation

+

Peak is found LLD is not calculated i

TABLE 9

~

1 LOCATION:

CLEFT ROCK LOCATIONS:

10 COUNT TIME:

6000sec COUNT DATE:

002785 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION microR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

(-27+- 14) E-4 52E-4

(-120+- 65) EO 240E O Ce-141

(-19+-

13) E-4 46E-4

(-21+- 13) EO 49E O I-131

(

14+- 34) E-4 120E-4

(

19+- 46) E-1 170E-1 Sb-125

(

6+- 11) E-3 38E-3

(

7+- 12) EO 43E O Rv-103

(-27+- 39) E-4 140E-4

(-26+- 37) E-1 140E-1 Ba-140

(

14+- 57) E-4 200E-4

(

3+- 13) ED 4BE O Ru-106

(-24+- 15) E-3 58E-3

(-54+- 34) E0 130E O 0+

Cs-137

( 331+- 11) E-3 2BE-3

( 602+- 20) EO 51E O

.2r-95

(-2+- 11) E-3 39E-3

(-13+- 57) E-1 210E-1 Nb-95

(-38+- 63) E-4 240E-4

(-19+- 32) E-1 120E-1 La-140

( 170+- 67) E-3 240E-3

( 217+- 86) E-1 310E-1 Mn-54

(-67+- 67) E-4 250E-4

(-30+- 30) E-1 110E-1 Co-60

( 28+- 19) E-3 70E-3

( 35+- 24) E-1 90E-1 0+

K-40

( 2594+- 50) E-3 88E-3

( 1449+- 28) E1

'47E 1

( 744+- 25) E0 0+ Th-232

( 2098+- 71) E-3

( 596+- 25) EO 0+

U-238

( 1005+- 46) E-3 Notes o

Activity greater than 3* standard deviation

+

Peak is found LLD is not calculated I

TABI.E 10 LUCATION:

EAST WEYMOUTH CONTROL LOCATION 4:

15 COUNT TIME:

6000sec COUNT DATE:

083085 InSit u COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION microR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

(-20+- 14) E-4 51E-4

(-90+- 63) EO 230E O Ce-141

(-1B+- 12) E-4 45E-4

(-19+- 13) EO 4GE O I-131

(-17+- 33) E-4 120E-4

(-23+- 45) E-1 160E-1 Sb-125

(-5+- 11) E-3 38E-3

(-5+- 12) E0 43E O Rv-103

(-11+- 38) E-4 140E-4

(-10+- 36) E-1 130E-1 Da-140

( 62+- 54) E-4 190E-4

( 14+- 13) E0 4GE O Rv-106

(

17+- 14) E-3 52E-3

( 37+- 31) EO 110E O 0+

Cs-137

( 1683+- 91) E-4 270E-4

('306+- 16) EO 49E O Zr-95

(-4+- 11) E-3 40E-3

(-22+- 57) E-1 210E-1 Nb-95

( 72+- 61) E-4 220E-4

( 37+- 32) E-1 120E-1 La-140

(-150+- 70) E-3 270E-3

(-191+- 89) E-1 340E-1 Mn-54

(-34+- 66) E-4 250E-4

(-15+- 30) E-1 110E-1 Co-60

(

2+- 19) E-3 73E-3

( 3+- 25) E-1 93E-1 c+ K-40

( 2582+- 47) E-3 67E-3

( 1442+- 27) E 1.

3BE 1

( 665+- 20) EO M----

0+

Th-232

( 1874+- 57) E-3

( -1094+- 28) EO C+ U-238

( 1992+- 51) E-3 Notes:

u Activity greater than 3* standard deviation

+

Peak is found LLD is not calculated

I TABLE 11 LOCATION:

MANOMET SUBSTATION LOCATION 4:

17 COUNT TIME:

6000sec COUNT DATE:

082985 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION nitroR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Co-144

(-10+- 12) E-4 42E-4

(-44+- 55) EO 190E O Ce-141

( 21+- 11) E-4 37E-4

( 22+- 11) EO 39E O I-131

(-35+- 29).E-4 100E-4

(-48+- 40) E-1 140E-1 Sb-125

(

16+- 92) E-4 320E-4

( 2+- 10) EO 36E O Ru-103

(

14+- 33) E-4 120E-4

(

14+- 32) E-1 110E-1 Bo-140

( 44+- 49) E-4 170E-4

( 10+- 11) EO 39E O Ru-106

( 18+- 13) E-3 46E-3

( 40+- 29) EO 100E 0 o+ Cc-137

( 2090+- 86) E-4 220E-4

( 380+- 16) EO 39E O Zr-95

( 92+- 90) E-4 320E-4

( 49+- 49) E-1 170E-1 Nb-95

(-32+- 55) E-4 200E-4

(-16+- 28) E-1 100E-1 Le-140

(-50+- 62) E-3 230E-3

(-64+- 79) E-1 290E-1 Mn-54

(

68+- 57) E-4 200E-4

( 31+- 26) E-1 92E-1 Co-60

(

1+- 16) E-3 61E-3

(

2+- 21) E-1 78E-1 o+ K-40

( 2682+- 49) E-3 76E-3

( 1498+- 27) E1 42E 1

( 816+- 25) EO L---

o+ Th-232

( 2300+- 71) E-3

( 595+- 23) EO c+ U-238

( 1083+- 42) E-3 Netos:

o Activity greater than 3* standard deviation

+

Peak is found LLD is not calculated

- ~.

1985 In-Situ Results. Comp;riscn cf Germanium System

_TA8LE 12.

an4 High Pressure Ionization Chamber Results.

Positive Germanium Results (vR/h t lo)

Total

HPIC Description Site (Distance in miles

.K-40 Cs-137 Other (vR/h)

(vR/h)

N1.

from plant)

U-238 Th-232 1.16 i 0.06 2.02 i 0.09 1.98 i 0.05 0.10 t 0.01 8.85 i 0.12 21.9 i 0.91 00 Warehouse (0.03 SSW) 01 Rocky Hill Rd. E.

1.06 i 0.04 1.74 0.06 1.36 t 0.04 0.36 0.01 8.12 t 0.08 7.85 i 0.64 (0.85 E) 10.00 1 0.14 10.09 1 0.64 03 Rocky Hill Rd. W.

1.22 0.05 2.57 t 0.08 2.56 0.05 0.06 t 0.01 (0.3 WNW) 04 Plymouth Center 1.84 0.05 2.86 i 0.01 2.68 i 0.05 0.32 t 0.01 11.31 i 0.12 11.35 i 0.52 (4.5 WNW) 06 Property Line 0.82 t 0.04 1.54 i 0.06 1.77 i 0.04 0.14 t 0.01 7.86 1 0.08 8.72 i 0.86 (0.34 NW) 07 Pedestrian Bridge 0.68 i 0.04 1.50 0.07 1.38 0.04 0.08 i 0.01 0.40 0.02 7.64 1 0.09 11.76 i 0.75 (a)

(0.14 N) 08 Overlook 0.61 i 0.05 1.82 i 0.13 1.92 0.05 0.06 t 0.01 8.00 0.15 47.56 i 0.81 (b)

(0.03 W) 9.06 1 0.09 9.11 t 0.47 09 East Breakwater 1.05 i 0.04 1.99 i 0.07 2.35 0.04 0.07 0.01 (0.35 ESE) 10 Cleft Rock 1.08 0.04 2.31 i 0.08 2.59 i 0.05 0.33 t 0.01 9.92 1 0.11 9.25 t 0.43 (0.9 S) 15 E. Weymouth Control 1.99 0.05 1.81 1 0.07 2.58 t 0.05 0.17 i 0.01 10.15 t 0.10 9.64 1 0.40 (23 NW) 17 Manonomet Substation 1.08 i 0.04 2.30 1 0.07 2.68 0.05 0.21 1 0.01 9.87 t 0.10 8.06 i 0.58 (2.5 SE)

Total of Germanium System plus 3.6 yR/h cosmic contribution Co-60 found in in-situ and confirmed by Laboratory soil analysis.

i (a) l (b) Weighted average Th-232 exposure Fate does not include 2614.7 kev gamma for this station only.

l

YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY FEB 10 B86 Initial Analysis Report YAEC ENVIRONMENTAL LAB.

, Customer : Boston Edison Company Report Date: 09/19/85

,AttGntion: MS. CHRISTINE E.

BOWMAN Analysis Date: 9 /5 /85 MR. EDWARD CUMMING Date Received: 9 /3 /85 Reference Date: 8 /27/85 Soil Senplo Amount: 0.32 Kg.

Lab Sample No.:

G54204 Sample Submission Code: PTS 0713585 Elopaed Time : 9.28 days Other Analysis Requested:

None Comment:

0-2 Station No.:

07 Pedestrian Bridge (PB)

DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC CORRECTION

[

Pico Curie / Kilogram-Wet

]

190 E 1 Np-239 6.48E-02

( 149 +- 57 ) E 1 03-57 9.77E-01

(-2 +- 43 ) E-1 140 E-1 Ce-144 9.78E-01

(-3 +- 34 ) E O 110 E O Co-141 8.21E-01

( 45 +- 92 ) E-1 310 E-1 Mo-99 9.90E-02

(-19 +- 74 ) E 1 250 E 1 l

Se-75 9.48E-01

( 67 +- 72 ) E-1 240 E-1 Cr-51 7.93E-01

( 2 +- 54 ) E O 180 E O I -131 4.49E-01

( 4 +- 12 ) E O 39 E O Co-7 8.86E-01

(-46 +- 53 ) E O 180 E O Ru-103 8.49E-01

(-19 +- 62 ) E-1 210 E-1 xI -133

~6.44E-04 Ba-140 6.05E-01

(-15 +- 11 ) E O 35 E O Cs-134 9.91E-01

( 28 +- 72 ) E-1 240 E-1 Ru-106 9.83E-01

(-5 +- 47 ) E O 160 E o 0+

Cs-137 9.99E-01

( 200 +- 10 ) EO 21 E O Ag-110M 9.75E-01

( 39 +- 82 ) E-1 270 E-1 Er-95 9.06E-01

( 22 +- 11 ) E O 3 6 E 0-Co-58 9.13E-01

( 188 +- 64 ) E-1 230 E-1 Mn-54 9.80E-01

(-154 +- 64 ) E-1 220 E-1 0+

AcTh228 1.00E 00

( 447 +- 34 )EO 95 E O Tel-132 1.38E-01

(-40 +- 26 ) E1 86 E 1 Fe-59 8.67E-01

( 8 +- 14 ) E O 46 E O En-65 9.74E-01

( 1 +- 15 ) E O 51 E O o+

Co-60 9.97E-01

( 556 +- 91 ) E-1 280 E-1 c+

K -40 1.00E 00

( 658 +- 20 ) E1 32 E 1 Sb-124 8.99E-01

( 12 +- 12 ) EO 40 E O Notes:Activity greater than 3* standard deviation e

Approved by

+

Peak is found Decay correction less than.01 x

d.

E. L. Laurenzo i

MAILED y,,,,,ox1c EtEC m c Cox m Y ENVIR NMENTAL IABORATORY FEB 10886 Initial Analysis Report YAEC Cuatc3Gr : Boston Edison Company Report Date: 09/19/85 Attention: MS. CHRISTINE E. BOWMAN Analysis Date: 9 /5 /85 MR. EDWARD CUMMING Date Received: 9 /3 /85 Reference Date: 8 /27/85 Soil Occplo Amount: 0.37 Kg.

Lab Sample No.:

G54205 Sample Submission Code: PTS 0723585 Elepacd Time : 9.28 days Other Analysis Requested:

None Comment:

2-4 Station No.:

07 Pedestrian Bridge (PB)

DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA.

MDC CORRECTION

(

Pico Curie / Kilogram-Wet

]

Np-239 6.48E-02

( 128 +- 64 ) E 1 210 E 1 Cc-57 9.77E-01

(-52 +- 44 ) E-1 150 E-1 Co-144 9.78E-01

(-80 +- 34 ) E O 110 E O C3-141 8.21E-01

( 85 +- 90 ) E-1 300 E-1 M3-99 9.90E-02

(-56 +- 75 ) E 1 250 E 1 S3-75 9.48E-01

( 57 +- 65 ) E-1 220 E-1 Cr-51 7.93E-01

(-57 +- 47 ) E O 160 E O I -131 4.49E-01

( 20 +- 10 ) E O 33 E O Be-7 8.86E-01

(-78 +- 51 ) E O 170 E O Ru-103 8.49E-01

( 11 +- 65 ) E-1 220 E-1 xI -133 6.44E-04 Ba-140 6.05E-01

(-3 +- 10 ) E O 34 E O C3-134 9.91E-01

(-80 +- 65 ) E-1 220 E-1

.Ru-106 9.83E-01

(-90 +- 53 ) E O 170 E O o+

Cs-137 9.99E-01

( 697 +- 61 ) E-1 140 E-1 Ag-110M 9.75.E-01

( 167 +- 72 ) E-1 240 E-1 Zr-95 9.06E-01

( 25 +- 10 ) E O 34 E O_

Co-58 9.13E-01

(-27 +- 56 ) E-1 190 E-1 Mn-54 9.80E-01

(-166 +- 59 ) E-1 200 E-1 c+

AcTh228 1.00E 00

( 575 +- 31 ) EO 76 E O TeI-132 1.38E-01

(-32 +- 28 ) E1 94 E 1 Fa-59 8.67E-01

(-17 +- 14 ) EO 47 E O Zn-65 9.74E-01

(-31 +- 17 ) EO 57 E O Co-60 9.97E-01

( 155 +- 74 ) E-1 270 E-1 C+

K -40 1.00E 00

( 953 +- 21 ) E 1 29 E 1 Sb-124 8.99E-01

( 14 +- 12 ) E O 41 E O Netcc:Activity greater than 3* standard deviation o

+

Peak is found Approved by x

Decay correction less than.01 k

E. L. Laurenzo

MAILED vANxEE ATOXIC EtECTRIC CON,ANY ENVIRONMENTAL LABORATORY FEB 10986 Initial Analysis Report

~~------------~~~-

YAEC Cu ot Edison Company Report DAtte: 09/19/85 Attontion: MS. CHRISTINE E. BOWMAN Analysis Date: 9 /5 /85 MR. EDWARD CUMMING Date Received: 9 /3 /85 Reference Date: 8 /27/85 Soil Senplo Amount: 0.33 Kg.

Lab Sample No.:

G54206 Sample Submission Code: PTS 0733585 l

Elepcod Time : 9.28 days Other Analysis Requested:

None Comment:

4-6 Station No.:

07 Pedestrian Bridge (PB)

DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC CORRECTION

(

Pico Curie / Kilogram - wet )

~~----------~~---~~-~~-----~~--------------------

Np-239 6.48E-02

( 226 +- 88 ) E 1 290 E 1 Co-57 9.77E-01

( 81 +- 61 ) E-1 200 E-1 C,e-144 9.78E-01

( 42 +- 45 ) E O 150 E O Ce-141 8.21E-01

( 10 +- 12 ) E O 41 E O Mo-99 9.90E-02

( 41 +- 100 ) E 1 330 E 1 Se-75 9.48E-01

(-96 +- 86 ) E-1 290 E-1 Cr-51 7.93E-01

( 111 +- 61 ) E 0 200 E O I -131 4.49E-01

( 7 +- 14 ) E O 45 E O Co-7 8.86E-01

(-32 +- 56 ) E O 190 E O Ru-103 8.49E-01

(-119 +- 72 ) E-1 240 E-1 xI -133 6.44E-04 Ca-140 6.05E-01

(-32 +- 14 ) E O 46 E O Cs-134 9.91E-01

(-2 +- 80 ) E-1 270 E-1 Ru-106 9.83E-01

( 85 +- 67 ) E O 220 E O c+

Cs-137 9.99E-01

( 687 +- 98 ) E-1 280 E-1 Ag-110M 9.75E-01

(-130 +- 100 ) E-1 330 E-1 Er-95 9.06E-01

(-10 +- 14 ) E O 47 E O_

Co-58 9.13E-01

(-170 +- 77 ) E-1 260 E-1 Mn-54 9.80E-01

(-34 +- 75 ) E-1 240 E-1 0+

AcTh228 1.00E 00

( 582 +- 42 ) E O 110 E O Tel-132 1.38E-01

( 22 +- 30 ) E1 99 E 1 Fe-59 8.67E-01

(-10 +- 16 ) E O 54 E O En-65 9.74E-01

( 5 +- 19 ) E O 63 E 0 Co-60 9.97E-01

(-10 +- 10 ) E O 40 E O C+

K -40 1.00E 00

( 901 +- 25 ) E1 39 E 1 Sb-124 8.99E-01

(-10 +- 15 ) E O 49 E O Netos:

Activity greater than 3* standard deviation

+

Peak is found Approved by x

Decay correction less than.01 J

E. L. Laurenzo

d Attachment I Yankee Atomic Environmental Laboratory Criteria

)

for Quality Assurance Agreement for Accuracy and Precision January 30, 1980 Introduction The purpose of any quality assurance program is to ensure that the quality of the product or service under consideration meets some pre-established acceptance criteria. The intent of this document is to summarize the quality control criteria which the Laboratory staff find technically acceptable in view of the three quality control programs currently being implemented for the VAEC Environmental Laboratory operations. The information presented reaffirms the Laboratory's initial criteria for precision and accuracy when a known caount of a N8S traceable standard has been added in sufficient quantity to a sample or set of samples, and also provides acceptance criteria for blind duplicate or replicate environmental samples which have not had a known amount af activity added.

For the latter case, the true radionuclide concentration cf the sample set is unknown and a simple comparison of the range (to some statistical confidence level, to) of concentration of the individual samples can be made. As a final note, although the criteria presented below are only

~

cpplicable for small sample sets (2-5 samples), the information gathered could be utilized to detect long-term biasing or a procedure giving non-reproducible results.

Discussion The previous criteria for agreement utilized by the Laboratory were based solely on the deviation of individual analyses from the mean of all results for precision, and the deviation of any individual analyses or the mean for a series of analyses, from the known value for accuracy.

In both instances, the criteria for agreement were i 15 percent. These criteria had been previously -

approved by the Laboratory Quality Control Audit Committee and are certainly valid in cases where the statistics associated with the random nature of radioactive decay are not significant in relation to the preset criteria.

Such is the case in the analysis of internal Laboratory prepared spiked samples which are usually prepared at an activity level high enough to minimize the contribution of counting statistics when the sample is analyzed for routine analysis times. However, certain EPA cross checks, IAEA cross checks, and many blind duplicate samples (analyzed utilizing routine analysis times, quantities and procedures) yield one sigma uncertainties (due solely to the random decay process) of eight to ten percent of the analyzed values.

Uncertainties in instrument calibrations, carrier standardization, sample to detector placements and analytical weighings are not included in the one sigma uncertainty but each may introduce an uncertainty ranging from one to five percent of the analyzed value. With these facts in mind, it can be readily seen that agreement with a known value to within 1,15 per;ent may not be achievable if the one sigma uncertainty associated with the measurements approaches or exceeds the preset percentage. As an example, the triplicate analysis of a sample for strontium-90 (known value = 5pci/kg) yielded values of 311, 411 and SilpC1/kg with a mean value of 4t pCi/kg. Note that the l

www

-ww~w-w--

m--m--w---www w m w e

=w

i statistics associated with the individual values range from twenty to thirty percent of the analyzed value and that the mean value dif fers from the known value by twenty percent (well outside the 115 percent criteria).

However, the range of acceptable values for the mean (at the 95 percent confidence limit or 2a) would be 2 to 6pti/kg indicating the mean value is not statistically different from the known value. The same result would occur if this. approach was applied to the individual values.

These same arguements can be applied to the determination of precision.

In erder to reduce the amount of bias generated by the analysis of low-level known or blind duplicate samples, the Laboratory will adopt a dual level criteria of agreement encompassing aspects of both the 115 percent criteria and agreement at the 95 percent confidence level.

Criteria for Accuracy and Precision A.

For the Determination of Accuracy: Known Spikes EPA Crosschecks. IAEA, ect.

A1. All known values will be utilized without associated statistics.

A2. Wherever possible, individua.1 values will be investigated with regard to agreement with the known. However, mean values may be utilized if necessary.

A3. An analysis is considered in agreement if the individual value is within 115 percent of the known value.

A4. If condition A3 is not met, establish the two sigma range about the analyzed value (e.g. the two sigma range for an analysis quoted as 51 pci/kg would be 3-7pC1/kg).

If the known value falls within the 1

specified range, the analysis is considered in agreement.

B.

For the Determination of Precision (Greater than Two Determinations):

Known Spikes, EPA crosschecks. IAEA, etc.

Pl. All mean values will be utilized without associated statistics.

P2. The individual values will be investigated with regard to agreement.._

with the mean value of all pertinent analyses.

P3. An analysis is considered in agreement for precision if the individual value is within 115 percent of the mean value.

P4. If condition P3 is not met, establish the two sigma range about the i

analyzed value.

If the mean value falls within the specified range, the, analysis is considered in agreement.

4 C.

Determination of Precision:

Duplicate or Replicate Analysis of Environmental - Activity Unknown i

i

01. For duplicate or replicate analyses conducted at the same laboratory, neither value can be considered the "true" value regardless of the uncertainties associated with the measurements.

J j

g

02. The average value is the best available approximation of the true value.

Determine the average value for the duplicate or replicate measurements.

03.

If either individual value is within 115 percent of the average value, agreement between the analyses has been obtained.

D4.

If condition 03 is not met, establish the two sigma range for l

duplicates (three sigma range for replicates) for ggch of the l

analyses.

If the ranges overlap, the analyses cannot be said to be statistically different and agreement is obtained. An example of the use of this criteria is shown below:

Analysis A Analysis 8 3ilpci/kg 511pti/kg Average value 4pti/kg Percent Deviation from Average = 100x11-41 = 25 percent 4

No agreement by 03.

to Range A 2e Range B 1-5 3-7 Ranges overlap and analyses are in agreement.

There are certain precautions which must be exercised in the implementation of this criteria.

It must be recognized that the augmented statistical agraesent criteria is susceptible to biasing by analyzing the samples to a high level of statistics (i.e. a shorter counting time).

In order to preclude this biasing, 011 samples will be analyzed for lengths of time approximating that of routine samples of the appropriate media.

S 10

N

~E k

i 1

,/

4 f.f e

[I

+

t i

a l

'),

i W

4

p. 6-g

,+.

t ft f(

j

,1

is

l t-

']-,s APPENDIX D - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM d'

/

f 4

(

/4

. -e -

D-1

OPERATIONAL OBJECTIVES SURVEILLANCE REQUIREMENTS 7.0 RADIOLOGICAL ENVIRONMENTAL 8.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MONITORING PROGRAM 7.1 Monitoring Program 8.1 Monitoring Program Applicability:

Specification:

At all times.

A.

ENVIRONMENTAL MONITORING Specification:

The radiological environmental monitoring samples shall be A.

ENVIRONMENTAL MONITORING collected pursuant to Table 8.1-1 from the specific locations given An environmental monitoring program in the table and figure (s) in the shall be conducted to evaluate the Offsite Dose Calculation Manual effects of station operation on the (ODCM) and shall be analyzed environs and to verify the pursuant to the requirements of effectiveness of the source Table 8.1-1 and the detection controls on radioactive materials.

capabilities required by Table 8.1-4.

The radiological environmental monitoring program shall be 1.

Cumulative dose contributions conducted as specified in Table for the current calendar year 8.1-1.

from radionuclides detected in environmental samples Action:

shall be determined in accordance with the

1. With the radiological methodology and parameters in environmental monitoring program the ODCM.

These results will not being conducted as specified be reported in the Annual in Table 8.1-1, prepare and Radiological Environmental submit to the Commission, in the Monitoring Report.

Annual Radiological Environmental Monitoring Report required by Specification 6.9.C.2, a description of the reasons for not conducting the program as required and the a

plans for preventing a recurrence.

2. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 7.1-1 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, a special report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken Amendment No. 89 229

OPERATIONAL OBJECTIVES SURVEfLLANCE REQUIREMENTS 7.1.A ENVIRONMENTAL MONITORING (Continued) to reduce radioactive effluents so that the potential annual

~

dose to a member of the public is less than the calendar year limits of Specifications 7.2, 7.3, and 7.4.

When more than one of the radionuclides in Table 7.1-1 are detected in the sampling medium, this report shall be submitted if:

concentration (1)

+

concentration (2)

> 1.0

+

reporting level (1) reporting level (1)

When radionuclides other than those in Table 7.1-1 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a member of the public is equal to or greater than the calendar year limits of Specifications 7.2, 7.3, and 7.4.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Monitoring Report.

3. With milk or fresh leafy vegetable samples unavailable from one or more of the sample l

locations required by Table 8.1-1, identify locations for obtaining replacement samples and add them to the Radiological Environmental i

Honitoring Program within 30 days.

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Amendment No. 89 230

OPERATlONAL OBJECTIVES SURVE!LLANCE REQUIREMENTS 7.1.A ENVIRONMENTAL MONITORING (Continued)

Pursuant to Specification 6.9.C.2, identify the cause of the unavailability of samples and identify the new location (s) obtaining replacement samples in the next Annual Environmental Radiation Monitoring Report and also include in the report the table for the ODCM reflecting the new location (s).

B.

LAND USE CENSUS B.

LAND USE CENSUS A land use census shall be The land use census shall be conducted and shall identify, conducted during the growing within a distance of 8 km (5 season, at least once per 12 miles), the location in each of months using that information that the 16 meteorological sectors of will provide the best results, the nearest milk animal, the such as by a door-to-door survey, nearest residence and the nearest aerial survey, or by consulting garden of greater than 50 m' local agriculture authorities.

2 (500 ft ) producing broad leaf The results of the land use census vegetation.

(For elevated shall be included in the Annual I

releases as defined in Regulatory Radiological Environmental Guide 1.111, Revision 1, July Monitoring Report.

1977, the land use census shall also identify, within a distance Broad leaf vegetation sampling of of 5 km (3 miles), the locations at least three different kinds of in each of the 16 meteorological vegetation may be performed at the sectors of all milk animals and site boundary in each of the two all gardens of greater than 50 different direction sectors with 7m producing broad leaf the highest predicted D/Qs, in vegetation.

lieu of the garden census.

Specifications for broad leaf Action vegetation sampling in Table 8.1-1 shall be followed, including

1. With a land use census analysis of control samples.

identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 8.4.A, identify the new location (s) in the next Annual Environmental Radiological

~

Honitoring Report.

Amendment No. 89 231

OPERATICNAL OBJECTIVES SURVEILLANCE REQUIREMENTS 7.1.8 LAND USE CENSUS (Continued)

2. With a land use census identifying a location (s) that yleids a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 7.1, add the new location (s) to the Radiological Environmental Monitoring Program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

Identify the new location (s) in the next Annual Environmental Radiological Monitoring Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

7.2 Dose - Liquids 8.2 Dose - Liquids Applicability:

Specification:

At all times.

A.

Dose Calculations - Cumulative dose contributions from liquid Specification:

effluents shall be determined in accordance with the ODCM for each A.

The dose or dose commitment to a calendar month during which member of the public from releases occurred.

radioactive materials in 11guld effluents released at and beyond the site boundary shall be limited:

1. During any calendar quarter to 1 1.5 mrem to the total body

~

and to 1 5 mrem to any organ, and

2. During any calendar year to 1 3 mrem to the total body and to 1 10 mrem to any organ.

l Amendment No.

89 232 I

I

OPERATIONAL OBJECTIVES SURVEILLANCE REQUIREMENTS 7.2 Dose - Liquids (Continued)

Action With the calculated. dose from the

. release of radioactive materials in

~

liquid effluents exceeding any of the above' limits, prepare and submit to the Commission within 30 days, a special report that identifies the cause(s), corrective actions taken, and corrective actions to be taken.

7.3 Dose - Noble Gases 8.3 Dose - Noble Gases Applicability:

Specification:

At all times.

A.

Dose Calculations - Cumulative dose contributions for the total Specification:

time period shall be determined in accordance with the ODCM for A.

The air dose in areas at and beyond each calendar month during which the site boundary due to noble gases releases occurred.

released in gaseous effluents shall be limited to the following:

1.

During any calendar quarter, to i 5 mrad for gamma radiation and i 10 mrad for beta radiation; and 2.

During any calendar year, to 1 10 mrad for gamma radiation and i 20 mrad for beta radiation.

Action With the calculated air dose from radioactive noble' gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, a special report which identifies the cause(s), the corrective actions taken, and corrective actions to be taken.

k Amendment No. 89 233

OPERATIONAL OBJECTIVES SURVEILLANCE REQUIREMENTS 7.4 Dose - Iodine-131 Iodine-133, 8.4 Dose - Iodine-131, Iodine-133, Radioactive Material in Radioactive Material in Particulate Form, and Tritium Particulate Form, and Tritium Applicability:

Specification:

~

At all times A.

Dose Calculations - Cumulative dose contributions for the total Specification:

time period shall be determined for iodine-131, iodine-133, A.

The dose to a member of the public radioactive material in from iodine-131, iodine.133, particulate form with half-lives radioactive materials in greater than 8 days, and tritium particulate form with half-lives in accordance with the ODCM for greater than 8 days, and tritium each calendar month during which in gaseous effluents released to releases occurred.

areas at and beyond the site boundary shall be limited to the following:

1.

During any calendar quarter to i 7.5 mrem to any organ, and 2.

During any calendar year to i 15 mrem to any organ.

Action With the calculated dose from the release of iodine-131, iodine-133, radioactive materials in particulate form, and tritium in gaseous effluents exceeding any of the above limits; prepare and submit to the Commission within 30 days, a special report which identifies the cause(s),

corrective actions taken, and the corrective actions to be taken.

7.5 Total Dose 8.5 Total Dose Applicability:

Specification:

At all times.

A.

Dose Calculations - Cumulative dose contributions from liquid Specification:

and gaseous effluents shall be determined in accordance with A.

The dose or dose commitment to any Specifications 7.2'.A, 7.3.A, and member of the public from Pilgrim 7.4.A; and in accordance with the Station sources is limited to 1 25 ODCM.

J mrem to the total body or any organ (except the thyroid, which Amendment No.

89 234

f OPERAT10NAL OBJECTIVES SURVEILLANCE REQUTREMENTS 7.5 Total Dose (Continued) is limited to < 75 mrem) over a period of any calendar year.

Action With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 7.2.A 7.3.A. or 7.4.A; prepare and submit a special rescrt to the Commission and limit IFe subsequent releases such that the dose or dose commitment to any member of the public from all uranium fuel cycle sources is limited to 1 25 mrem to the total body or any organ (except thyroid, which is limited to 1 75 mrem) over any calendar year.

This special report shall include an analysis which demonstrates that radiation exposures to all members of the public from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR, Part 190 standard.

Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR, Part 190 standard.

i Amendment No. 89 235

TABLE 7.1-1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPL Reporting Levels Water Airborne Particulate Fish Milk Vegetables Analysis (pCl/L) or Gases (pCl/M')

(pCl/kg, wet)

(pCl/1)

(pCl/kg, wet)

H-3 2 x 10*

Mn-54 1 x 10' 3 x 10*

1 x 10*

Fe-59 4 x 10 Co-58 1 x 10' 3 x 10*

Co-60 3 x 10' 1 x 10' Zn-65 3 x t'0' 2 x 10*

Zr-95 4 x 10' I-131 2

0.9 3

1 x 10' Cs-134 30 10 1 x 10' 60 1 x 10' Cs-137 50 20 2 x 10' 70 2 x 10' Ba-140 2 x 10' 3 x 10' Amendment No. 89 236

TABLE 8.1-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Locations Exposure Pathway (Direction-Distance)

SampIlng and Type and Frequency or Sample Type from Reactor Collection Frequency of Analysis AIRBORNE Particulates 11 Locations (See Continuous sampling over Gross beta radioactivity Table 8.1-2) one week 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after filter change' Quarterly 11 Locations (See Composite (by location) for Table 8.1-2) gamma isotopic

Radiolodine 11 Locations (See Continuous sampling with Analyze weekly for I-131 Table 8.1-2) canister collection weekly DIRECT' 40 Locations (See Quarterly Gamma exposure quarterly Table 8.1-3)

)

Plymouth Beach and Annually Gamma exposure survey' Priscilla/ White Horse Beach 1

NATERBORNE Discharge Canal Continuous composite Gasse isotopic" monthly, (Surface Water) sample and composite for H-3 Bartlett Pond Weekly grab sample analysis quarterly' (SE-1.7 ml)

Powder Point Weekly grab sample (NNW-7.8 ml)*

AQUATIC Shellfish Discharge outfall Quarterly (at approximate Gamma isotopic" '

(clams, mussels Duxbury Bay 3-month intervals) or quahogs as Manomet Point available)

Plymouth or Kingston Harbor Marshfield*

2' 7 3

Amendment No.

89

TABLE 8.1-1 (Continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Locations Exposure Pathway (Direction-Distance)

Sampling and Type and Frequency or Sample Type _

from Reactor Collection Frequency of Analysis Lobster Vicinity of discharge Four times per season Gamma isotopic

on edible portions point Offshore

Once per season Fish Vicinity of discharge Quarterly (when particular Gamma isotopic" on point species available) for Groups edible portions' Offshore

I and II', in season for 5

Groups III and IV,

annually for each group Sediments Rocky Point Semlannually Gamma Isotopic * ' '

Plymouth Harbor Duxbury Bay Plymouth Beach Manomet Point Marshfield INGESTION (Terrestrial)

Milk Plymouth County Farm, Semimonthly during Gamma isotopic', radio-when available periods when animals are lodine analysis all samples (W-3.5 ml)*

on pasture, otherwise Whitman Farm monthly (NW-21 ml)*

Cranberries

-Manomet Point Bog At time of harvest Gamma Isotopic" on edible (SE-2.6 ml) portions Bartlett Rd. Bog (SSE/S-2.8 mi)

Pine St. Bog (WNW-17 mi)*

Amendment No.

89 238

TABLE 8.1-1 (Continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Locations Exposure Pathway (Direction-Distance)

Sampling and Type and Frequency or Sample Type from Reactor Collection Frequency of Analysis Tuberous and green Plymouth County Farm At time of harvest Gamma Isotopic' on edible leafy vegetables (W-3.5 ml)*

portions Bridgewater Farm (W-20 ml)*

Beef Forage Plymouth County farm Annually Gamma Isotopic *

(W-3.5 mi)'

Whitman Farm (NH-21 mi)*

i-Amendment No. 89 239

i TABLE 8.1-1 (Continued)

NOTES If gross beta radioactivity is greater than 10 times the control value, gamma isotopic will be performed on the sample.

Gamma isotopic means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

If integrated gamma activity (less K-40) is greater than 10 tiines the control value (less K-40), strontium-90 analysis will be performed on the sample.

Indicates control location.

Fish analyse' will be performed on a minimum of 2 sub-samples, consisting of approximately 400 grams each from each of the following groups:

I.

Bottom Oriented II.

Near Bottom III. Anadromous IV.

Coastal Distribution Migratory Winter flounder Tautog Alewife Bluefish Yellowtail founder Cunner Rainbow smelt Atlantic herring Atlantic cod Striped bass Atlantic menhaden Pollock Atlantic mackerel Hakes Mussel samples from four locations (immediate vicinity of discharge outfall, Manomet Point, Plymouth or Kingston Harbor, and Green Harbor in Marshfield) will be analyzed quarterly as follows:

One kilogram wet weight of mussel bodies, including fluid within shells will be collected.

Bodies will be reduced in volume by drying at about 100*C. Sample will be compacted and analyzed by Ge(L1) gamma spectrometry or alternate technique, if necessary, to achieve a sensitivity of 5 pC1/kg for Cs-134. Cs-137, Co-60, Zn-65, and Zr-95; and 15 pC1/kg for Ce-144. Sensitivity values are to be determined in accordance with a 95% confidence level on k. and a 50% confidence level on k. (See HASL-300 for definitions).

The mussel shell sample from one location will be analyzed each quarter.

One additional mussel shell sample will be analyzed semiannually.

Unscrubbed shells to be analyzed will be dried, processed, and analyzed similarly to the mussel bodies.

Amendment No.

89 240

TABLE 8.1-1 (Continued)

NOTES Because of the small volume reduction in pre-processing of shells, sensitivities attained will be less than that for mussel bodies.

The equipment and counting times to be employed for analyses of shells will be the same or comparable to that employed for mussel bodies so that the reduction in sensitivities (relative to those for mussel bodies) will be strictly limited to the effects of poorer geometry related to lower l

sample volume reduction. Shell samples not scheduled for analysis wili be reserved (unscrubbed) for possible later analysis.

If radiocesium (Cs-134 and Cs-137) activity exceeds 200 pC1/kg (wet) in mussel bodies, these samples will be analyzed by radiochemical separation, electrodeposition, and alpha spectrometry for radioisotopes of plutonium, with a sensitivity of 0.4 pC1/kg.

Sediment samples from four locations (Manomet Point, Rocky Point, Plymouth Harbor, and head of Duxbury Bay) will be analyzed once per year (preferably early summer) as follows:

Cores will be taken to depths of 30-cm, minimum depth, wherever sediment conditions permit, by a hand-coring sampling device.

If sediment conditions do not permit 30-cm deep cores, the deepest cores achievable with a hand-coring Levice will be taken.

In any case, core depths will not be less than 14-cm. Core samples will be sectioned into 2-cm increments; surface and alternate increments will be analyzed, all others will be reserved.

Sediment sample volumes (determined by core diameter and/or number of individual cores taken from any single location) and the counting technique will be sufficient to achieve sensitivities of 50 pC1/kg dry sediment for Cs-134, Cs-137, Co-60, Zn-65, and Zr-95 and 150 pCi/kg for Ce-144.

In any case, individual core diameters will not be less than 2 inches.

The top 2-cm section from each core will be analyzed for Pu isotopes (Pu-238, Pu-239, and Pu-240) using radiochemical separations, electrodeposition, and alpha spectrometry with target sensitivity of 25 pCi/kg dry sediment.

Two additional core slices per year (mid-depth slice from two core samples) will be similarly analyzed.

These locations may be altered in accordance with results of surveys discussed in Specification 8.1.B.

Hinimum sensitivities for gamma exposure measurements are as follows:

Gamma exposure - 1 R/hr average exposure rate.

Gamma exposure survey - 1 R/hr exposure rate.

Amendment No. 89 241

TABLE 8.1-2 AIR PARTICULATES, GASEOUS RAD 10 LOD 1NE, AND SOfL SURVEfLLANCE STATf0NS Sampling Location Distance and (Sample Designation)

Direction from Reactor Offsite Stations c

East Weymouth (EW) (Control Station) 21 miles NW l

l Plymouth Center (PC) 4.0 miles W-WNW Manomet Substation (MS) 2.5 miles SE Cleft Rock Area (CR) 0.9 miles S l

Onsite Stations Rocky Hill Road (ER) 0.8 miles SE Rocky Hill Road (WR) 0.3 miles W-WNW Overlook Area (0A) 0.03 miles W 1

l Property Line (PL) 0.34 miles NW Pedestrian Bridge (PB) 0.14 miles N East Breakwater (EB) 0.35 miles ESE Warehouse (WS) 0.03 miles SSE

'e Amendment No.

89 242

TABLE 8.1-3 EXTERNAL GAMMA EXPOSURE SURVEILLANCE STATIONS' Distance and Dosimeter Location (Designation)

Direction from Station ONSITE STATIONS Property Line (D) 0.17 miles NNW Property Line (F) 0.12 miles NW Property Line (I) 0.14 miles W Property Line (G) 0.20 miles WSW Rocky Hill Road (A) 0.12 miles SW Property Line (H) 0.21 miles SSW Public Parking Area (PA) 0.07 miles N-NNE Pedestrian Bridge (PB) 0.1 miles NE Overlook Area (OA) 0.03 miles W East Breakwater (EB) 0.26 miles ESE Property Line (C) 3.3 miles ESE-SE Property Line (HB) 0.34 miles SE Rocky Hill Road (B) 0.26 miles SSE Microwave Tower (MT) 0.38 miles S Emerson Road (EM) 0.68 miles SE-SSE White Horse Road (WH) 0.89 miles SE-SSE Property Line (E) 0.75 miles SSE-S Rocky Hill Road (WR) 0.3 miles W-WNW Property Line (J) 1.36 miles SSE-S Property Line (K) 1.42 miles SSE-S Rocky Hill Road (ER) 0.8 miles SE Property Line (L) 0.40 miles E Amendment No.

89 243

TABLE 8.1-3 (Continued)

EXTERNAL GAMMA EXPOSURE SURVEILLANCE STATIONS' Distance and Dosimeter Location (Designation)

Direction from Station ONSITE STATIONS (Continued)

Warehouse (WS) 0.1 miles SE Property Line (PL) 0.3 miles W OFFSITE STATIONS Duxbury (SS) 6.25 miles SSW-SW Kingston (KS) 10 miles WNW North Plymouth (NP) 5.5 miles WNW Plymouth Center (PC) 4.0 miles W-WNW South Plymouth (SP) 3 miles WSW Bayshore Drive (BD) 0.7 miles W-WNW Cleft Rock Area (CR) 0.9 miles S Manomet (MP) 2.25 miles ESE-S Manomet (ME) 2.5 miles SE Manomet (MS) 2.5 miles SSE Manomet (MB) 3.5 miles SE-SSE College Pond (CP) 6.5 miles SSW-SW Sagamore (CS) 10 miles SSE-S Plymouth Airport (SA) 8 miles WSW East Weymouth (EW)*

21 miles NW Saguish Neck (SN)'

4.6 miles NNW Thermal Luminescent Dosimeters (TLDs)

Control Station TLDs for this location will be provided to a third party and will be analyzed for gamma exposure whenever returned to Boston Edison Company.

Amendment No. 89 244

TABLE 8.1-4 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)*

Nater Airborne Particulate Wet Solids Milk Food Products Dry Solids t

Analysis (pC1/kg) or Gas (pCl/M'L (pC1/kg, wet)

(pCl/q)

(pCl/kg, wet)

(pC1/kg, dry) l groes beta 4*

I x 10-8

'M 2000*

- Mn 15 130 i

Fe 30 260

" "Co 15 130 50

Zn 30 260 50 i

j

Zr 15 50 i

I 1

7 x 10-2 1

60*

' ' * ' "Cs 15, 18 1 x 10-*

130 15 60 50

'**Ba 15 15

- - Ce 150 l

Refer to 00CM for LLD definition.

LLD for surface water.

3

LLD for leafy vegetables.

1

If no drinking water pathway exists, a value of 3000 pct /1 may be used.

.i i

4 Amendment No. 89 245

BASES 7/8.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 7/8.1 Monitoring Program 7/8.1.A ENVIRONMENTAL MONITORING An environmental radiological monitoring program is conducted to verify the adequacy of in-plant controls on the release of radioactive saterials.

The program is designed to detect radioactivity concentrations to ensure that radiation doses to individuals do not exceed the levels set forth in 10 CFR 50, Appendix I.

A supplemental monitoring program for sediments and mussels has been incorporated into the basic program (see Notes 6 and 7 to Table 8.1-1) as a result of an agreement with the Massachusetts Wildlife Federation. This supplemental program is designed to provide information on radioactivity levels at substantially higher sensitivity levels in selected samples to verify the adequacy (or, alternatively, to provide a basis for later modifications) of the long-term marine sampling schedules. As part of the supplemental program, analysis of mussels for isotopes of plutonium will be performed if radiocesium activity should exceed 200 pC1/kg in the edible portions.

The 200 pC1/kg radiocesium " action level" is based on calculations which show that if radiocesium from plant releases reached this level, plutonium could possibly appear at levels of potential interest.'

The calculations also show that the dose delivered from these levels of plutonium would not be a significant portion of the total dose attributable to 11guld effluents.

The program sas aisc designed to be consistent, wherever applicable, with NUREG 0473.

Groundwater flow at the plant site is into Cape Cod Bay; therefore, terrestrial monitoring of gtoundwater is not included in this program.

Detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD). The LLD in Table 8.1.4 is considered optimum for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurtment.

Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), curie, L.A.; " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry", Anal. Chem. 40, 586-93 (1968); and Hartwell, J.

K.,

" Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

In measurable quantities having a potential dose (human food chain)

L significance comparable to other nuclides if present at their detection i

limits.

Amendment No. 89 246

BASES 7/8.1.8 LAND USE CENSUS This section is provided to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census.

The best information from the door-to-door survey, from aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of 10CFR50, Appendix I, Section IV.B.3.

Restricting the census to gardens of greater than 50 m' provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored, since a garden of this size is the minimum required to produce the quantity (26 kglyear) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.

To determine this minimum garden size, the following assumptions were made:

1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2

2) a vegetation yield of 2 kg/m.

7/8.2 DOSE - LIQUID This section is provided to implement the requirements of Sections II.A, III.A, and IV.A of 10CFR50, Appendix I, to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Because Pilgrim is not a site where plant operations can conceivably affect drinking water, none of these requirements are intended to assure compliance with 40 CFR 141.

The dose calculations in the 00CM implement the requirements of 10CFR50, Appendix I, Section III.A to ensure that the actual exposure of a member of the public through appropriate pathways is unilkely to be substantially underestimated.

The equations specified in the 00CM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,"

April 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

Amendment No. 89 247

BASES 7/8.3 DOSE - NOBLE GASES This section is provided to implement the requirements of 10CFR50, Appendix I, Sections II.B. III.A, and IV.A to ensure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The surveillance requirements implement the requirements of 10CFR50, Appendix I, Section III.A to ensure that the actual exposure of a member of the public through the appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the 00CM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1 July 1977.

The ODCM equations provided for determining the air doses at and beyond the site boundary will be based upon the historical average atmospheric conditions.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

7/8.4 DOSE - 10 DINE-131, 10 DINE-133, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND TRITIUM This section is provided to implement the requirements of Sections II.C, III.A and IV.A of 10 CFR50, Appendix I, to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements of 10CFR50, Appendix I, Section III.A to ensure that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated.

The 00CM calculational methods approved by the NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guides 1.109 and 1.111.

These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for iodine 131, radioactive material in particulate form with half-lives greater than 8 days, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in areas at and beyond the site boundary.

The pathways which are examined in the development of these calculations are:

1) individual inhalation of airborne radionuclides, 2) deposition of radicnucildes onto green leafy vegetation with subsequent consumption by man, 3) deposition,onto grassy areas where milk animals and meat producirig animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

Amendment No.

89 248

- - ~

BASES 7/8.5 TOTAL DOSE This section is provided to meet the dose limitations of 40CFR190 that have now been incorporated into 10CFR20 by 46 FR 18525. The specification requires the preparation and submittal of a special report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of 10CFR50, Appendix I.

For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40CFR190 if the individual reactors remain within the reporting requirement level. The special report will describe a course of action that should result in the limitation of the annual dose to a member of the public to within the 40CFR190 limits.

For the purposes of the special report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, except dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

If the dose to any member of the pub 'c is estimated to exceed the limits of 40CFR190, a request for a variance in a special report in accordance with 40CFR190.11 and 10CFR20.405C is considered to be a timely request and fulfills the requirements of 40CFR190 until NRC staff action is completed. This is provided that the release conditions resulting in violation of 40CFR190 have not already been corrected.

The variance only relates to the limits of 40CFR190, and does not apply in any way to the other requirements for dose limitation of 10CFR20. An individual is not considered a member of the public during any period in which he/she is engaged in any operation that is part of the nuclear fuel cycle.

l Amendment No. 89 249

APPENDIX E - 1986 Garden & Milk-Producing Animal Survey E-1

0FFICE HEMORANDUM Boston Edison Company MG Control Number To: T. L. Sowdon From: C. E. Bowman Record Type A4.08 Date: April 23, 1987 Dept. Doc. REG 87-31 Safety Related

Subject:

1986 GARDEN & HILK-PRODUCING ANIMAL CENSUS Distribution:

As required by PNPS Radiological Environmental Technical Specifications, the 1986 Garden and Hilk-Producing Census was conducted in September of 1986 in a street-by-street search of the area within one mile of PNPS.

The existence of a garden near the site boundary of 0.6 miles ESE was ccnfirmed. The garden near the site boundary of 0.7 miles H did not exist in 1984, 1985 nor 1986; however, a garden 1.0 miles H of the site boundary was identified in 1984, and was still available in 1986.

In addition, a garden 1.0 miles SE of the site boundary was identified in 1985 and was still available in 1986. These gardens are the closest and largest in the near vicinity (1 mile) of PHPS, and are less than 500 square feet. They do represent conservative garden locations for sampling analysis. With the assistance of Mr. Robert Tis, vegetation samples were collected from three locations on 9/16/86 and from one location on 9/17/86. Only one location was greater than one mile from PNPS. A sample of red lettuce and spinach was collected from the J. Work residence (0.6 miles ESE) on John Alden Road; thubbarb was obtained from the Jenkins residence (1.0 miles H) and from the Malmgren residence (1.0 miles SE) on Rocky Hill Road; and a sample of spinach was collected from the H. Moon residence (1.25 miles SSH) on River Road.

Samples were unavailable from the Whipple Farm (1.5 miles SSH) off Dotem Road during this time frume in 1986.

In addition, no cows or goats or structures which would indicate the presence of such animals within one mile of PNPS were observed. The Plymouth Animal Inspector forwarded a letter to Boston Edison in 1984 indicating that the only cilk-producing animals within five miles of PNPS are located at the Plymouth County Farm. However, as in 1985, Boston Edison was unable to receive a written reply from the Plymouth Animal Inspector for the year of 1986. The v

Plymouth Animal Inspector did indicate that there was no change in the location of milk-producing animals from 1985.

The Plymouth County Farm is a participant in the Environmental Monitoring Program. During +ie 1982 Census, a milk-producing cow was located on Beaver Dam Road (2.5 miles S).

The owner has not participated in the Environmental Monitoring Program since the first quarter of 1984 (3/1/84).

In conclusion, the 1986 Census indicates that there are no additional indicator stations available for milk sampling.

CEB/1j

APPENDIX F - ENVIRONMENTAL RADI0 ACTIVITY FROM THE CHERNOBYL ACCIDENT t

f F-1 i

ENVIRONMENTAL RADI0 ACTIVITY FROM THE CHERN0BYL ACCIDENT Following the Chernobyl Nuclear Plant accident on April 26, 1986, increased levels of fission-related radionuclides were measured in fresh fallout throughout much of the northern hemisphere, including New England.

The amcunt and type of radioactivity seen in this fallout were roughly comparable to that observed in fallout from the most recent atmospheric nuclear weapons tests conducted by the People's Republic of China during the late 1970s and in 1980.

Chernobyl-related fallout was seen during 1986 in many types of environmental samples, both near the nuclear power plants and at distant control locations, including the Yankee Atomic Environmental Laboratory in Hestboro, Massachusetts. An in-depth discussion of this entire subject may be found in Reference 7.

This section contains a brief summary of the measured radiological environmental impact in northern New England during 1986 from the Chernobyl accident. Selected monitoring results from several of the plants in New England have been compiled for this summary. Many of the measurements were previously reported to the Nuclear Regulatory Commission (via telephone) in response to a request in IE Information Notice 86-32 (Reference 8).

Airborne radioactivity levels as measured by gross-beta analysis (see Figure F.1) show a marked increase during the first week of May. Although the magnitude of the measured concentrations varied slightly across New England, the curves were virtually identical. Very evident in the curves are the first Chernobyl release, measured during the first week of May, and the second release, measured during the last week of May and the first week of June.

Several radionuclides were identified on air particulate filters by gamma spectroscopy. These were Cs-134, Cs-137 and Ru-103. They are shown in Figures F.2, F.3 and F.4, respectively.

Iodine-131 was detected on charcoal filters at all monitoring stations.

Its curve, shown in Figure F.5, is similar to that for gross-beta measurements for air particulate filters.

Several radionuclides were detected in milk samples shortly after their detection on air particulate or charcoal filters.

These were Cs-134, Cs-137 and I-131.

Since the deposition of this radioactivity occurred after the start of pasture season (for those cows that are pastured), it worked into the milk pathway readily. Due to its short half-life (8 days), the I-131 was not very persistent in the environment, however (see Figure F.8).

For many years Cesium-137 has been detected in cows milk from many locations around New England and the world as a result of the nuclear weapons tests in the 1970s and in 1980. Cesium-137 levels (see Figure F.7) at most locations increased during Hay due partly to the start of the pasture season (if applicable) and the consequent re-introduction of old Cs-137 into the food chain, and partly due to an increase of Cs-137 levels on pasture vegetation from Chernobyl-related fallout. Cesium-134 was also detected in milk samples.

This isotope of c.esium is entirely attributable to Chernobyl, since its relatively short half-life (2 years) has effectively removed any left over from previous weapons testing fallout. A Cs-137/Cs-134 ratio of approximately 2.0 was noted on air particulate filters, and as one would expect to follow, in milk.

The virtual absence of Sr-89 or Sr-90 in the fallout was notable.

This was due to the small amount of strontium released during the accident.

F-2

Unlike the gross-beta en air particulate filters and I-131 on charcoal filters, the Cs-134, Cs-137 and I-131 levels in milk varied considerably from location to location due to differences in farming practices.

Specifically, the types of vegetation fed on by cows and the amount of stored feed given them, as well as localized differences in deposition of fallout and many other less important factors, have a marked effect on the levels of radioactivity in cilk. Hith respect to milk in samples in the winter of 1986/1987, it is expected that the Cs-134 and Cs-137 levels might increase at some locations during the winter months when cows are given feed that was contaminated by fallout during the sprir.g of 1986.

Figures F.6 and F.7 show some early evidence of this during the fall of 1986 at several locations.

As cne would expect, fallout from Chernobyl was measured in other environmental media such as precipitation and vegetation. Measurements for selected radionuclides in precipitation are shown in Tables F.1 and F.2 for the Yankee Atomic Environmental Laboratory and the EPA ERAMS Network, respectively.

F-3

Table F.1 Chernobyl-Related Radioactivity in Precipitation Yankee Atomic Environmental Laboratory, Westboro, MA (pCi/kg i one std. dev.)

C@llection Rainfall Period (1986)

Cs-134 Cs-137 Ru-103 I-131 (inches)

May 7-9

(-0.3 1 1.4)

(0.9 1 1.4)

(-1.5 i 1.3) 20.4 1 2.8 0.13 May 12 6.9 1 0.3 12.6 i 1.4 15.4 1.6 47215 0.027 May 17 6.1 1 1.1 11.9 1 1.2 11.4 1 1.2 68.4 1 2.2 0.31 May 21-22

(-0.6 1 0.5) 1.7 1 0.4 (0.1 1 0.4) 8.9 1 0.6 0.06 May 23-25 2.1 1 0.6 5.0 1 0.9 9.1 1 1.1 49.6 1 3.4 0.79 May 30-June 1 2.5 1 0.5 7.3 1 0.8 6.6 1 0.8 14.8 1 1.4 0.74 June 5-8

(-1.6 1 0.9) 1.9 1 0.6 (0.8 1 0.8)

(0.6 1 1.2) 5.10 June 11-13 (2.7 1 1.0)

(0.4 1 1.2)

(-0.3 1 1.2)

(3.0 1 1.7) 1.16 June 22-24

(-1.0 1 1.3)

(2.2 1 1.3)

(-2.3 2.0)

(-6.01 14) 0.07 July 2

(-0.5 1 0.8)

(1.1 1 0.8)

(0.1 1 1.1)

(1.3 i 8.7) 1.79

-

B

~~'k l$~~

.a

=

~~m6 Ej~~

~~- f[ E~~

~'

~~6 b~~

8

~~5 i~~
I iE o
l o
,5 4.
4
.4 4
4
~~4. 4.~~
4
.4 4
.4 4.
4 4
8313W '00 / $31Wn0001d l
F-8
RU-103 DN AIR PARTICULRTE PILTERS NEM ENGLAND CONTROLS 0,10 0,00-D-WILLNWtST06M, etR o - DESTERRM1.D, Mi C
A-MTH FE n
8'" '
+-
fE
=39 X " c.
EEm o-rtR z
V - WE:STBORD, 9s#n R
PERE
=sse w
m OA-CF5m O M o,.'
o gm 0,os-amF N
0 GGa 98 m
0,os-l
(
E 0,0s -
0,03-
'b 0,01-1 1.
A 0,=
JWI PEB fWt frit
..PftY
.AM
.AL NJB StP 007 tWV OED 1986
C0nctnTR$S$Sd1-ui CHARC0AL FILTERS MEAN OF ALL STATIONS a
1 a
Ilhl13 8
m a
a.
ai 3
=
<I a
8 8
E 6
E E
E E
4 5
i i
i i
i i
satz no / saranocols F-10
FIGURE F.6 CONCENTRATIONS OF Cs-134 IN MILK Ncd ENGLAND CONTROLS P
N ii, 1
1
$g e
I d4-
!h d
E g
f eie1 a
4 co<+xo M
g u,
I 8
R t
E i
.g I I l
I l
~~h l~~
k
.k k
k k
h k_
tt
=
3 o
i MMKTlIX / S3IUf)3001d s
\\
\\\\
F-11
\\\\
'\\\\
'ii i
FIGURE F.7 CONCENTRATIONS OF Cs-137 IN MILK NEW ENGLAND CONTROLS l
l te,
1lli
'a l ig s
a i
I a
=
M[
Ali???
E8
/
'*.g 4
o=
2 g
>g i
l i
5 i
>R
^
4 4
4 4
4 s
l R
R R
C E
WWWO11M / S3IMD00Id F-12 i
FIGURE F.8 CONCENTRATIONS OF I-131 IN MILK NEW ENGLAND CONTROLS n
i E
i i t t
$g
!lih tl I
i s
a:m E
I it 3 9 il 65 4
A5 E
I
,g l l E
s i
<,{
'E 4
4 4,
4 4
4 4
4 4
QlAl0(T1D / S318(D001d F-13 l
APPENDIX G - CHERN0BY-RELATED RADI0 ACTIVITY MEASUREMENTS IN PNPS ENVIR0f4 MENTAL MEDIA L.
I j
G-1
The Chernobyl-related radioactivity measurements in environmental media for the PNPS Environmental Monitoring Program is tabulated in the following pages.
G-2
TABLE G.1 Chernobyl-Related Radioactivity in Air Particulates Gross Beta Measurements Gross Beta Measurements (pCi/kg)*E-4 Station Station Collection Period (5/6/86 - 6/10/86) location Desianation Week #20 Heek #21 Heek #22 Week #23 Heek #24 Harehouse HS 564 35 2152 36 188 40 941 27 1687 32 East Rocky Hill Rd.
ER 1806 37 2734 41 792 42 1298 30 1036 22 West Rocky Hill Rd.
HR 1799 35 2757 42 630 26 1324 31 1181 26 Property Line PL 1722 36 3040 43 792 27 1776 36 760 21 Pedestrian Bridge PB 1167 30 2801 43 360 23 851 26 634 20 Overlook Area OA 2093 39 3086 43 777 27 910 28 1709 2 30 East Breakwater EB 1451 31 2879 43 699 25 1582 33 887 23 Cleft Rock CR 2237 40 2855 41 659 25 1374 31 1041 24 Plymouth Center PC 1419 36 3011 42 823 26 1722 36 1300 28 Manomet Substation MS 1553 34 3209 43 778 27 2315 89 1135 27 East Heymouth EH 2043 37 2247 37 1097 27 196 18 1489 29
~~Note: All measurements are greater than three times standard deviation.~~
s G-3 e
TABLE G.2 Chernobyl-Related Radioactivity in Air Particulates Second Ouarter Comoosite Measurements Station Station Second Ouarter Comoosite Measurements (oCi/ka)*E-5 LocaliQD Desianation Ru-103 Cs-134 Cs-137 A
Warehouse HS 474 46 467 31 881 45 East Rocky Hill Rd.
ER 507 43 560 37 1046 46 West Rocky
~
Hill Rd.
WR 618 51 551 38 1193 50 Property Line PL 639 65 644 55 1153 60 Pedestrian Bridge PB 258 49 377 39 691 50 Overlook Area OA 550 59 722 51 1311 62 East Breakwater EB 511 49 530 42 956 54 Cleft Rock CR 521 48 614 46 1274 56 Plymouth Center PC 471 44 527 37 1088 49 Manomet Substation MS 487 49 617 39 969 47 East Weymouth EW 553 47 650 46 1214 51 1
G-4
TABLE G.3 Chernobyl-Related Radioactivity in Charcoal Filters Iodine Measurements Iodine Measurements (pCi/kg)*E-4 Station Station Collection Period (5/6/86 - 6/10/86)
Location Designation Week #20 Week #21 Week #22 Heek #23 Heek #24 Harehouse HS 3820 110 1514 77 (93 79) 581 89 298 70 East Rocky Hill Rd.
ER 3100 97 1867 87 60 130 502 78 197 53 West Rocky Hill Rd.
HR 2732 100 2328 85 343 87 494 83 254 67 Property Line PL 3050 110 2108 74 419 77 446 77 (117 91)
Pedestrian Bridge PB 2780 110 2110 91 415 2 86 458 87 229 43 Overlook Area OA 3490 100 2158 91 480 88 636 89 301 61 East Breakwater EB 4240 100 2120 95 439 86 457 79 (-30 110)
Cleft Rock CR 3350 13 2076 89 330 76 615 82 390 80 Plymouth Center PC 3750 110 2176 85 480 2 86 550 91 361 81 Manomet Substation MS 3660 110 2145 81 498 79 700 19 (190 170)
East Heymouth EH 4090 110 1815 85 678 87 (52 82) 288 72
~~Note: All measurements are greater than three times standard deviation.~~
( ): Measurements less than three times standard deviation.
G-5 l
TABLE G.4 Chernobyl-Related Radioactivity in Precioitation Station Collection Nuclide Measurements (oCi/kg)*E-1 Location Period I-131 Ru-103 Cs-134 Cs-137 8 mi W 5/23/86 176 26 6/9/86 8.7 2.7 6/13/86 (1.2 5.5) 12 mi S 5/23/86 123 16 45 mi NW 5/9/86 2130 190 317 78 385 82 5/23/86 205 17 5/26/86 365 29 6/6/86 14.7 1.0 49 11 90 mi NW 5/21/86 354 53 6/9/86 17.7 8.0
( ): Measurements less than three times standard deviation.
G-6
TABLE G.5 Chernobyl-Related Radioacitivity in Algae for Second Ouarter of 1986 Collection Station Nuclide Measurements (DCi/ka)*E-1 Period Location I-131 RU-103 6/24/86 Rocky Point 200 58 6/9/86 Manomet Point 740 210 171 29 6/25/86 Ellisville - CNTRL 147 39 6/10/86 Brant Rock - CNTRL 358 71 E
1 G-7 l
[
TABLE G.6 Chernobyl-Related Radioactivity in Cattle Feed Collection Station Nuclide Measurements (oCi/ka)*E0 Period Location Ru-103 Cs-134 Cs-137 6/19/86 Plymouth County Farm 70 19 48 13 161 18 6/19/86 Whitman Farm 228 27 123 14 239 20 I-L 1
50 I
G-8
TABLE G.7 Chernobyl-Related Radioactivity in Milk Iodine Measurements Iodine Measurements (pCi/kg)*E-2 Station Collection Period (5/8/86 - 7/3/86)
(I Location Week #19 Heek #21 Heek #23 Heek #24 Heek #25 Week #26 Heek #27 i
Plymouth County 39.8 E.7 5591 96 572 34 152 15 45 i 14 Whitman Farm 33.3 4.4 3903 83 689 43 (27
~~11) (29 15)~~
^
( ): Measurements less than three times standard deviation.
G-9 4.
i TA8LE G.8 Chernobyl-Related Radioactivity in Milk GeLi Analyses Station Collection GeLi Analyses (DCi/kg)*E-1 Location Period Cs-134 Cs-137 Plymouth County Farm 5/22/86 50.4 8.8 114 12 6/10/86 54.3 8.5 156 14 6/19/86 31.0 5.5 69.4 9.6 7/3/86 25.8 5.6 47.8 7.7 Whitman Farm 5/19/86 52.0 12 6
6/2/86 41.2 7.4 89.4 9.4 6/27/86
(-5.7 9.1) 46.8 8.3 7/3/86 (5.3 7.2) 39.4 6.9 l
( ): Measurements less than three times standard deviation.
I G-10 m
PNPS Technical Specifications Section 6.9.C.2
-h eosamsw Executive Offices 800 Boylston Street Boston, Massachusetts 02199 BECQ 87- 068 April 30, 1987 Ralph G. Bird Senior Vice President - Nuclear U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Hashington, DC 20555 Annual Environmental Radiation Monitorina Program Reoort
~~Dear Sir:~~
In accordance with the Pilgrim Nuclear Power Station Technical Specification Section 6.9.C.2, the Boston Edison Company submits the Annual Environmental Radiation Monitoring Program Report for 1986 (Report #19).
Should you have any questions regarding this matter, please contact Mr. T. L.
Sowdon at 617-746-7905 X8116.
C
. G.
ird MTL/ pac Attachment l
cc:
U. S. Nuclear Regulatory Commission l
Region I 631 Park Avenue King of Prussia, PA 19406 Senior NRC Resident Inspector Pilgrim Nuclear Power Station b
i t
t
_

BECO-87-068, Environ Radiation Monitoring Program Rept 19,1986

Contents

Text

Dear Chris:

Subject:

Dear Sir:

Navigation menu

BECO-87-068, Environ Radiation Monitoring Program Rept 19,1986

Text

Dear Chris:

Subject:

Dear Sir:

Navigation menu

Search