BECO-86-055, Station,Environ Radiation Monitoring Program Rept 18,1985

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Station,Environ Radiation Monitoring Program Rept 18,1985
ML20199F509
Person / Time
Site: Pilgrim
Issue date: 12/31/1985
From: Bowman C, Harrington W, Sowdon T
BOSTON EDISON CO.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
BECO-86-055, BECO-86-55, NUDOCS 8606240352
Download: ML20199F509 (152)
v • d • e


Text

,

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PILGRIM NUCLEAR POWER STATION I

I ENVIRONMENTAL RADIATION MONITORING PROGRAM g

REPORT NO.18 I

'I JANUARY 1 THROUGH DECEMBER 31,1985 i

g ISSUED: MAY 1986 I

BY: NUCLEAR OPERATIONS DEPARTMENT ENVIRONMENTAL AND RADIOLOGICAL l

HEALTH AND SAFETY GROUP I

I BOSTON EDISON COMPANY I

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l MBOSTON

'y%s6 GiniiVEDISON l

[88'"28858sa88ha h<

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BOSTON EDIS0N COMPAMY PILGRIM NUCLEAR POWER STATION Environmental Radiation Monitoring Program REPORT NO. 18 January 1, 1985 through December 31, 1985 I

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Prepared by:

M I

Ch'ffstine E. 'Bo@an Senior Radiological Engineer I

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Approved by:

a o

M omas L. Sofdon' Radiological Section Manager I

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Date of Submittal:

May 1, 1986 I

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TABLE OF CONTENTS Section D3e I

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.

Soi?

3-15 D.

Direct Radiation 3-16 E.

Waterborne 3-28 F.

Shellfish 3-31 G.

Algae (Irish Moss) 3-34 H.

Lobster (Arthropods) 3-38 I.

Fish 3-41 J.

Sediments 3-44 K.

Milk 3-51 L.

Cranberries 3-57 M.

Vegetation 3-60 N.

Forage 3-65 IV References 4-1 Appendix A Anomalous Measurement Reports A-1 Appendix B Radioactive Effluents B-1 Appendix C Soil Survey C-1 Appendix 0 Radiological Environmental Monitoring Program 0-1 Appendix E 1985 Garden and Milk Animal Survey E-1 i

l

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LIST OF TABLES I

Table Number Page 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 3-12 I

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 I

III-D-6 Quarterly Average Exposure Rates 3-25 III-D-7 Field Survey Exposure Rates 3-26 III-E-1 ERMAP Results - Waterborne 3-29 III-F-1 ERMAP Results - Shellfish 3-32 III G-1 ERMAP Results - Algae 3-36 III-H-1 ERMAP Results - Lobster 3-39 III-I-l ERMAP Results - Fish 3-42 III-J-l ERMAP Results - Sedime its 3-47 III-J-2 Results of Sediment Analysis for Plutonium - 1985 3-49 III-J-3 Results of Sediment Analysis for Plutonium - 1984 3-50 II:-K-1 ERMAP Results - Milk 3-53 III-L-1 ERMAP Results - Cranberries 3-58 III-H-1 ERMAP Results - Vegetation 3-61 III-N-1 ERMAP Results - Forage 3-66 I

11

LIST OF FIGURES l

l Figure Number Page l

III-A-1 Gross Beta Activity - Air Particulates -

3-09 Indicator Stations III-A-2 Gross Beta Activity - Air Particulates -

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

3-13 Indicator Stations III-8-2 Concentrations of I-131 - Charcoal Filter 3-14 Control Station III D-1 Environmental Radiation Levels at Beaches Near 3-27 Pilgrim Station III-K-1 Concentrations of.Cs-137 in Milk 3-55 III-K-2 Concentrations of Sr-90 in Milk 3-56 I.

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I.

Introduction and Summary I

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 Pawer Station - Unit 1 (PNPS-1) and at selected control locations for the period January 1 - December 31, 1985.

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 1% of the doses resulting from naturally occurring radionuclides and residual fallout from previous atmospheric nuclear weapons testing.

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 1985 reflects an average capacity factor of 84.4%. 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 1985 calendar year.

I There were no Anomalous Measurement Reports made for the calendar year of 1985.

i 1-1 I

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; seven air particulate samples; seven charcoal filter samples; plus occasional failures of the air samplers; one hay sample due to unavailability; and two fish samples.

In addition. a total of four TLDs were found to be missing from their field locations during 1985.

6 These incidents affected only about 2% of the total number of samples scheduled for collection.

The Plimoth Plantation was not available as a milk sampling location during 1985.

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 1985.

1-2 l

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I TABLE I-1 PNPS-1 I

CAPACITY FACTORS 1985 (Based on 670 MWe)

~

Month Percent Capacity January 54.0 February 59.3 March 81.8 April 90.8 May 94.3 June 85.0 July 96.9 August 96.5 September 71.4 October 95.4 November 88.1 December 99.1 I

Average 84.4 I

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1-3 I

I

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

The program is essentially identical to that conducted during 1982 and incorporates supplemental provisions as specified in the Settlement Agreement between the Massachusetts Wildlife Federation and Boston Edison Company, June 9, 2

1977.

The exceptions to the program are 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.

2)

There is no longer a milk producing cow at Plimoth Plantation.

The Plimoth Plantation location has been unavailable since 1981.

The nearest dependable cow location is at the Plymouth County Farm, which is 3.5 miles from PNPS in the West sector.

3)

There is no longer a Karbott Farm.

Vegetable samples are now collected at the two nearest gardens near the H and ESE site boundaries.

The 1985 site Census conducted according to Technical Specification requirements determined that there are several vegetable gardens near the site boundary in the H-WNW 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 lettuce was collected on 10/03/85.

In the west direction, the location of the nearest observed garden of approximately 500 square feet was at the Malmagren residence '.0 miles W).

During 1983, the nearest observed garden in the west direction was Evan's residence (0.7 miles H).

This location did not have a garden in 1984 or 1985. A sample c~ vegegable leaves was collected from the Malmagren residence on 2-1 4

10/03/85. Additional samples of vegetable leaves were collected on 10/03/85 from the Jenkins residence (1 mile SE) and from the Whipple Farm (1.5 miles SSW).

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.

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2-2 I

____.m..__

1 III.Results and Analyses E

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

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

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 I

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l 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.

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

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  • Lower Limit of Detection I

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I TABLE III-A-1 Sample Station Identification Codes

-Media Station Code Station Location Number Air Particulate 00 Warehouse (0.03 mi-SSE)

I and 01 Rocky Hill Road (0.8 mi-SE)

Iodine Filters 03 Rocky Hill Road (0.3 mi-WNW) 06 Property Line (0.34 mi-NW)

I 07 Pedestrian Bridge (0.14 mi-N) 08 Overlook Area (0.03 mi-W) 09 East Breakwater (0.35 mi-ESE) 10 Cleft Roak (0.9 mi-S)

I 15 Plymouth Center (4.0 mi-N-WNW) 17 Manomet Substation (2.5 mi-SSE) 21 East Weymouth (control-21 mi-NW)

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

Shellfish 11 Discharge Canal Outfall 12 Warren Cove I

13 Duxbury Bay 15 Manomet Point 24 Marshfield (Control)

  • I Algae (Irish Moss) 11 Discharge Canal Outfall 15 Manomet Point I

22 E111sv111e (Control, 8 mi-SSE))

34 Brant Rock (Control, 12 mi-NWN)

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

Fish 2

Round Hill Point-Offshore-(Control)

I 11 Vicinity of Discharge Canal 12 Warren Cove 13 Duxbury Bay (Control) 14 Vicinity of Plymouth Beach I

19 White Horse Beach 21 Auto Trawl Station-Offshore-(Control)

I 22 Offshore-(Control) 28 Cataumet, Bourne-(Control) 29 Priest Cove-Offshore-(Control) 96 Mouth of North River-Hanover I

(Control) 97 Nantucket Sound (Control) 99 Provincetown-Offshore (Control)

I Sediment 11 Rocky Point 12 Warren Cove I

13 Duxbury Bay 14 Plymouth Beach 15 Manomet Point 24 Marshfield (Control) 3-3

TABLE III-A-1 Sample Station Identification Codes I

Media Station Code Station Location Number I

Milk 11 Plymouth County Farm (3.5 mi-W) 21 Whitman Farm (Control-21 mi NW)

Cranberries 13 Manomet Point Bog (2.5 mi-SE) 14 Bartlett Road Bog (2.8 mi-SSE/S) 1 23 Pine St. Bog (Control-17 mi-WNW)

I i

Vegetation 11 Plymouth County Farm (3.5 mi-W) 16 Work Residence (0.6 mi-ESE)

I 17 Evans Garden (0.7 mi-W) 27 Bridgewater Farm (Control-20 mi-W) 43 Whipple Farm (1.5 mi-SSW)

I 75 Halmgren Residence (1.0 mi-W) 76 Jenkins Residence (1.0 mi-SE)

Beef Forage 11 Plymouth County Farm (3.5 mi-W) 21 Whitman Farm (Control-21 mi-W)

.7 27*

Bridgewater Farm (Control-20 mi-W)

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  • Unavailable during 1985.

3-4 I

III.A. Air Particulate Filters Sample collection systems consisting of a cellulose particulate filter and a charcoal filter cartridge are used to collect particulate matter and lodine nuclides respectively.

Analyses of the particulate filters for beta radiation is performed weekly.

In addition, quarterly composite particulate samples are analyzed for gamma emitting I

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).

I 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.

I l

There were a total of seven air particulate filters which were not anlayzed during the year of 1985.

The air particulate filter at Station #09 (East Breakwater) for week numbers 01 and 02 were not analyzed due to a lack of power to the air sampler.

In addition, power was not available to Station #17 (Manomet Substation) for week numbers 47 through 51 (11/20/85 to 12/17/85).

The loss of power was due to a blown fuse.

Thus, the air particulate filters for this station were not analyzed for the above time frame.

During 1985, there were several instances of low sample voltme due to power and motor feilures, and broken fittings. Of these, there were two instances which resulted in the MDC not being met.

The M'DC was not met for Station #09 (East Breakwater) collected on 5/28/85 due to a low I

3-5 I

sample volume thich tas the result of a pump malfunction of the air sampler.

In addition, the MDC was not met for Station #17 (Manomet Station) collected on 9/17/35 due to a low sample volume which was the result of a power loss to the sampling station.

There were no positive measurements of any nuclides characteristic of reactor operations observed in the quarterly composite samples.

The only positive measurements observed in the quarterly composite samples were due to naturally occurring nuclides (Be-7 and K-40).

In consideration of the natural background dose rate of 80 to 100 mrem-year, there was clearly no significant environmental effect observed in the air particulate media as a result of the operation of PNPS-1.

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3-6

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TABLE III-A-2 ERMAP RESULTS-AIR PARTICULATE FILTERS I

EDIlli: AIR FMTICILATE LNITS: PCI/CU. M INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROLSTATIONS I

m *** m e m ** m

      • m m m e m **** m **

m e m ** m e m RADICNUCLICES EAN MEAN EAN (N0. AN RY"S) REQUIRED RANGE STA.

RANCE RANCE (NON-ROUTINE)*

LLD NO. DETECTED **

NO.

NO. [ETECTEDet N0. IETECTEDe*

I GR-B (577)

.01

(

2.2t

.1)E -2 09 ( 2.9 i

.9)E -2

( 2.4 t

.2)E -2 I

( 1)

(-4.7 - 44.7)E -2

(-4.7 - 44.7)E -2

( 8.8 - 84.2)E -3

  • (509/524)*
  • ( 48/ 51)*
  • ( 53/ 53)*

BE-7 ( 44)

(

4.0

.1)E -2 01

( 4.5 t

.4)E -2

( 4.3 i

.3)E -2 I

( 0)

( 2.2 -

5.7)E -2

( 3.5 -

5.2)t -2

( 3.5 -

4.8)E -2

  • ( 40/ 40)*
  • (

4/ 4)*

  • (

4/ 4)*

K-40 ( 44)

(

5.2t

.6)E -3 09 ( 9.6 t 2.1)E -3

( 4.2 t 2.3)E -3

( 0)

(-3.9 - 13.2)E -3

( 3.6 -

13.2)E -3

(-2.4 -

8.2)E -3

.7

  • (

4/ 40)*

  • (

2/ 4)*

  • (

0/ 4)*

MN-54 ( 44)

(

2.12 3.3)E -5 03

( 2.4 i 1.6)E -4

(-2.9 i 7.2)E -5

( 0)

(-4.0 -

6.6)E -4

(-7.7 - 655.0)E -6

(-1.7 -

1.6)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

C0-58 ( 44)

.02

(

2.7t 5.2)E -5 01

( 2.1 i

.8)E -4

(-1.4 i

.8)E -4

( 0)

(-1.2 -

.7)E -3

(-1.3 - 35.0)E -5

(-3.3 -

.6)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

FE-59 ( 44)

( -1.8i

.9)E -4 08 ( 2.2 i 4.0)E -4

(-3.3 i

.8)E -4 I

( 0)

(-1.6 -

1.3)E -3

(-5.7 - 12.8)E -4

(-4.9 -

-1,6)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

CO-60 ( 44)

.02

( -2.2t 4.1)E -5 07 ( 3.5 t

.6)E -4

( 6.5 i 5.3)E -5 I

( 0)

(-6.5 -

4.5)E -4

( 2.1 -

4.5)E -4

(-2.7 - 18.1)E -5

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

I Zt -65 ( 44)

( -8.0t 8.4)E -5 21

( 4.2 t 1.3)E -4

( 4.2 i 1.3)E -4

( 0)

(-2.1 -

.8)E -3

( 1.7 -

7.0)E -4

( 1.7 -

7.0)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

ZR-95 ( 44)

( -10.0t 6.7)E -5 15

( 2.8 t 2.3)E -4

( 8.7 t 24.9)E -5

( 0)

(-9.4 - 11.7)E -4

(-2.2 -

6.7)E -4

(-3.4 -

7.7)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

I I

  • NON-ROUTINE REFERS TO THE NLMBER OF SEPARATE EASLREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE FERIOD OF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEAstREMENTS I

(I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

3-7

I TABLE III-A.2 (CONTINUED)

I EDIlN: AIR PARTICULATE LNITS: PCI/CU. N I

INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATICNS I

euennenneen*

          • ueuusu nee n***
  • unut***ueue RADIONUCLIDES EAN MEAN EAN (NO. ANALYSES) REQUIRED RANCE STA.

RANCE RANCE (NON-RCUTINE)*

LLD NO. DETECTED **

NO.

NO. DETECTED **

NO. DETECTEDu RU-103 ( 44)

( -1,31 52.7)E -6 15 ( 3.0 t

.3)E -4

(-1.6 i 1.1)E -4 I

( 0)

(-7.0 -

8.3)E -4

( 2.4 -

3.5)E -4

(-3.2 -

1.5)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

I RU-106 ( 44)

( -6.St 2.8)E -4 01

( 9.0 i 9.2)E -4

(-6.1 t 8.6)E -4

( 0)

(-5.2 -

3.3)E -3

(-1.2 -

3.3)E -3

(-2.2 -

1.3)E -3

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

CS-134 ( 44)

.01

( -1.01

.4)E -4 15 ( 4.2 i 72.9)E -6

(-4.9 i 12.4)E -5

( 0)

(-8.0 -

3.4)E -4

(-1.4 -

2.0)E -4

(-2.5 -

3.0)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

I CS-137 ( 44)

.01

(

7.31 2.9)E -5 07

( 2.2 t 1.4)E -4

(-1.3 t 8.4)E -5

( 0)

(-2.3 -

6.3)E -4

( 3.3 - 63.0)E -5

(-2.2 -

1.9)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

BA-140 ( 44)

( -3.71 1.6)E -4 21

( 3.0 i 4.0)E -4

( 3.0 t 4.0)E -4

( 0)

(-4.2 -

.8)E -3

(-4.2 - 11.4)E -4

(-4.2 - 11.4)E -4 I

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

CE-141 ( 44)

(

2.2i

.6)E -4 17 ( 6.7 i 3.7)E -4

( 6.0 k 15.5)E -5 I

( 0)

(-5.2 - 17.0)E -4

( 1.9 - 170.0)E -5

(-2.3 -

4.6)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

I CE-144 ( 44)

(

!.lt 1.4)E -4 01

( 4.2 i 5.0)E -4

(-7.9 i 288.6)E -6

( 0)

(-1.9 -

2.0)E -3

(-9.8 - 13.7)E -4

(-5.1 -

7.8)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

l TH-232 ( 44)

(

8.21 10,5)E -5 09

( 5.7 i 3.1)E -4

( 1.5 i 4.2)E -4

( 0)

(-2.0 -

1.3)E -3

(-9.4 - 125.0)E -5

(-8.1 -

8.9)E -4

  • (

0/ 40)*

  • (

0/ 4)*

  • (

0/ 4)*

  • NON-ROUTINE REFERS TO THE NLNBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE A'4 RACE BACKGROLND FOR THE PERIOD OF THE REFT %T.
    • THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASLREMENTS (I.E. >3 STD EEVIATICtG) IS INDICATED WITH *(

)*.

g 3-8 I

m I

FIGURE III-A-1 GROSS BETA ACTIVITY AIR PARTICULATES INDICATOR STATIONS I

a I

n

~

I n

I i

m 4

.m

~

g I

i.

l 8598E8825D sassasssas s

ununununun I

EEEEE**MMMm

    • E mmmmmM y

I I 8 8 8 8 8 I I I E

co<.x...x.

e i

e e

a a

a a

a a

a l

aa. taw no / salanocora 3-9

FIGURE III-A-2 I

GROSS BETA ACTIVITY AIR PARTICULATES CONTROL STATION i

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l 1

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i,

)

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-a

)gg 4

g a

a

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j w

j E

i N

j z

O

-s a-e 1

u>

l 8

ia a

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!l 4

'g 8

8 8

9 9

E 8

i lg o

o o

o o

d d

I 8313W '00 / S3180000Id jg 3

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I 3-10 4

1

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.

I There were a total of seven charcoal filters which were not analyzed during the year of 1985.

The charcoal filter at Station #09 (East Breakwater) for week numbers 01 and 02 were not analyzed due to a lack of power to the air sampler.

In addition, power was not available to Station #17 (Manomet Substation) for week numbers 47 through 51 (11/20/85 to 12/17/85).

The loss of power was due to a blown fuse.

Thus the charcoal filters at this station were not analyzed for the above time frame.

The MDC for lodine analysis was not met for two samples at two different stations.

The MDC was not met for Station #09 (East Breakwater) collected on 5/28/85 due to a low sample volume which was the result of a pump malfunction of the air sampler.

In addition, the MDC was not met for Station #17 (Manomet Substation) collected on 09/17/85 due to a low sample volume which was the result of a power loss to the sampling station.

I There was clearly no significant environmental effect observed in the I

airborne gaseous iodine collection media as a result of the o'pe' ration of PNPS-1.

3-11

TABLE III-B-1 ERMAP RESULTS-CHARCOAL FILTERS EDIlli: CEtVL FILTER UNITS: PCI/CU. It INDICATOR STATIONS STATION WITH HIGHEST E AN CONTROL STAT!0t6 I

nunutenennu anneneneneenennu nueue***ueen RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANCE I

(NCN-ROUTINEle LLD N0. [ETECTEDen NO.

NO. DETECTEDee NO. DETECTEDen 1-131 (577)

.07

(

3.4i 12.2)E -4 09 ( 1.2 i 1.2)E -2

(-8.9 i 14.6)E -4

( 0)

(-1.1 -

5.9)E -1

(-3.8 - 58.8)E -2

(-2.4 -

2.4)E -2

  • (

0/524)e

  • (

0/ 51)*

  • (

0/ 53)*

I e RON-ROUTINE REFERS TO THE NLMBER OF U ~ ATE MEARJREENTS WHICH WERE CREATER I

THAN TEN (10) TIMES THE AVERAGE BACK+JUND FOR THE PERIOD OF THE REPORT.

    • THE FFACTION OF SAMPLE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le.

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I I

I I

 % V

FIGURE III-B-1 I

CONCENTRATIONS OF I-131 CHARCOAL FILTERS INDICATOR STATIONS I

I I

f' I

la 1

l l lu J

l Z xM n

v

~ n s

' jm l.

lq" h

sassasseen I

8888888888 lg gincccccccc

\\

MMmmMMmmmm*EE**EEE5 F

I i

1g i:::::

OO4+Xo>3x+

i e

e e

o o

831 3 *A0 / S3IN0000Id I

3-13

FIGURE III-b-2 e,

I CONCENTRATIONS OF I-131 1pHARCOAL FILTERS j

. CONTROL STATION I

I J

~

1 I

l8 -

G

i I

w

[

I N

'S 1

yji.

"I I

,s l

34 I

a I

me i

M I

E

'o 3

I 4

I a

.i i

i i

e i

i n

e a

a a

a 8313W *n0 / S3IB0000Ici I

%.f I

3-14

III.C. Soil I

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 between August 26 and August 30 of 1985.

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

I I

I

.I I

I I

I I

lI I

I 3-15 I

I

III.D. Direct Radiation 1.

Continuous Thermoluminescent Oosimetry Thermoluminescent dosimeters (TLD) of the CaSO.(Dy) type are used 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 k

radiation.

TLD's are installed at the locations identified in Table III-D-1.

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 im:nediate 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 consist"'. 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 l

neighborhood and background) the dose rates are statistically consistent.

In all cases, the near plant levels are distinctly l

higher than those off-site and off-site dose rates are not i

l significantly sensitive to distance variations beyond the site itself.

Thus, beyond the " exclusion area" (for this purpose, the 0.25-0.7 mile region), dose rates show no significant plant I

l 3-16 1

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 June of 1985.

The results of this most recent survey are in agreement with the last seven beach surveys conducted for 1977 through 1984.

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

This study included both gamma exposure rate measurements and in-situ gamma spectrometry analysis for each I

location.

Laboratory soll 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-Ill high pressure ion chamber (HPIC), Serial Number 4-1656.

The design and calibration of this instrument were described in the above report.'

The present survey was designed to detect differences in the external exposure rate encountered at beaches near the plant (Plymouth and Priscilla/Hhite 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 Priscilla/Hhite Horse Beach are not significantly greater than the exposure rates measured at the control station in D'uxbury.

I 3-17

'I

Th small differences are likely due to the presence of granite beach stones which are essentially absent at the Duxbury location.

Plymouth Beach (Behind Bert's Restaurant) showed a slightly elevated exposure rate most likely due to the presence of a breakwater and seawall nearby.

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

The results of this survey indicate an exposure rate range at beaches near Pilgrim Station of 6.6 to 9.2 UR/hr.

Past gamma radiation surveys indicate that natt.ral background exposure rates at these beaches can vary by several UR/hr (6-12 UR/hr) due to differing types of beach sand and the relative location of granite boulders.

These results are in complete agreement with similar measurements performed in Maine', where the natural background exposure rate at shoreline locations was found to vary I

between 6.6 and 14.5 uR/hr.

These exposure rates were also found l

to vary directly with the size and proximity of granite outcroppings'. All measured exposure rates from 1977 through 1985 are indicated in Figure III.D.I.

It can be seen that the exposure rate at Plymouth Beach (behind Bert's Restaurant) is l

consistently higher than the other stations with greater fluctuations over the years.

This can be explained by the close proximity to the concrete seawall and the large boulders in the adjacent breakwaters.

The beach itself at this location is a j

fairly non-homogeneous mix of sand, small pebbles and larger stones.

Measurements taken here are not very reproducible from year to year since a small change in the measurement location q

e-3-18

il can result in a significant change in the exposure rate.

However, the exposure rate at this location is within natural background levels.

These latest measurements are also in agreement with the soll survey mentioned earlier.

The results of that survey indicate that off-site dose rates have a range of 7.6 to 11.3 UR/hr with an average of 9.2 UR/hr.

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

i

)

3-19

I Table III-D-1 Thermoluminescent Dosimeter Locations I

3 3e

.S..I 1.

3. 3 e.
s..e e.3 I

. w 3

e. e 3J J
3. t+32 3

3 3.s e.s s

3 e.

=

e. = * *..

3 3

3' e m e e es. e es e e 3 s

  • E 333a.

as a 3

3 3 es e. 3 3 a a.4.J #e3 a one 2A

=3 3

.J 3e a-s I

1.i.

.e

....e

... I.

.. e e eseee eeeeeee e-eee e.

ee e

.. e

.a

.e.

_.s 1

l I

8*

........ _. e 3

1

,l 32.: : : :

=

1 1 :

3.y.g

.a..a.u.

g..

3,.g.gg..g.u....

3 w.

a.

.w..

1.

I"i

.L.'

_.1 1, I

1 e

!
  • l, 2;

.A

,... l.

..a.

1 l

3

}f 1'

7

.J,

e.

~

g

.a

.a

,33.3_1 1637-3 I.

a... e. i.I.e. e 3. l 1

i f

3

.s.

.la:,...

l m

a., I,.1. 2 3

..f...

.a. d i

... ass wI i

3.!

.f

.1 I

J 3-

.! ! ; : 1.!.!.!. _!.!..!..!. 2 I:.2 s.

. 3.

.l a.

    • 1.d'....... ".. _. :"..

dd-*-d i

J.

trifrc=f..r.f.f.f.rvj=gl-.a.1 I

-4 ee r

r

=

2

--d rr.1

..A e

4 aua

.a T,.

..s..

......a..

l

.I e

d,i, i

.t a

-* a.!.3 l 1!

l ie.

.I r

y I

32t l

  • 1*1*

iz i

i I

f*

I TABLE III-D-2 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #1 1985 Micor/

2 Sigmc Station Hour

+-

CP 5.82

+-

1.64 CR 8.36

+-

2.78 CS 3.04

+-

Q.86 ER 6.26

+-

2.51 EW 7.87

+-

2.81 KS 9.67

+-

3.09 MB 1.49

+-

0.51 I

ME 3.54

+-

1.58 MP 7.31

+-

3.81 MS 10.46

+-

2.88 I

NP 5.05

+-

1.17 PC 6.13

+-

1.44 SA 15.59

+-

3.97 SP 4.07

+-

1.35 SS 7.65

+-

2.73 WR 8.98

+-

2.28 BD 7.07

+-

1.67 EB ND*

+-

EM 4.59

+-

1.66 MT 1.28

+-

0.31

-I OA 12.01

+-

3.56 PA 6.49

+-

3.94 PB 9.82

+-

2.09 WH 4.10

+-

1.26 A

6.20

+-

2.51 B

O.28

+-

0.10 C

7.98

+-

2.59 I

D hD

+-

E 7.63

+-

4.30 F

4.98

+-

3.02 I

G 9.52

+-

2.45 H

7.92

+-

2.09 I

7.46

+-

2.81 J

ND

+-

I K

7.39

+-

1.53 L

6.72

+-

1.54 PL 9.08

+-

2.20 WS 6.43

+-

1.45 HB 8.35

+-

3.41 RL 1.14

+-

0.35 RL 1.67

+-

0.54 Geographical Regional Averages for this period are:

Near Plant (0.16 mi.)

8.69

+-

3.40 Exclusion Area (.25.68 mi.)

6.57

+-

2.56 Distant Nbrhood (.7-6.5 mi.)

6.31

+-

2.27 Background (8-21 mi.)

9.04

+-

3.36

  • ND - No data due to missing TLD.

3-21

TABLE III-0-3 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #2 1985 Micror/

Station Hour 1-2 Sloma CP 9.52

+-

2.36 CR 2.75

+-

1.22 CS 3.33

+-

1.31 I

ER 1.85

+-

0.81 EH 0.71

+-

0.34 KS 8.52

+-

1.68 MB 0.22

+-

0.12 ME 0.77

+-

0.32 MP 3.52

+-

1.48 MS 1.95

+-

0.83 I

NP 3.49

+-

1.27 PC 2.14

+-

0.85 SA 0.47

+-

0.27 SP 2.19

+-

1.27 SS 1.90

+-

0.45 HR 2.25

+-

0.79 BD 2.37

+-

1.24 EB 1.32

+-

0.30 EM 2.33

+-

0.80 MT 2.39

+-

1.27

-I OA 12.10

+-

5.72 PA 4.28

+-

2.24 PB 5.29

+-

2.57 HH 3.60

+-

1.55 A

0.32

+-

0.08 8

0.86

+-

0.24 C

3.43

+-

0.87 0

0.55

+-

0.22 E

2.82

+-

0.26 F

2.36

+-

0.36 I

G 4.39

+-

1.51 H

4.18

+-

1.29 I

2.97

+-

0.67 J

0.29

+-

0.10 I

K 13.40

+-

3.17 L

8.82

+-

1.66 PL 3.34

+-

1.05 HS 7.37

+-

3.13 HB 4.32

+-

1.00 i

RL 2.11

+-

0.87 RL 3.60

+-

1.97 Geographical Regional Averages for this period are-Near Plant (0.16 mi.)

7.26

+-

4.25 Exclusion Area (.25.68 mi.).

2.23

+-

0.92 Distant Nbrhood (.7-6.5 mi.)

4.36

+-

2.08 i

Background (8-21 mi.)

3.26

+-

1.26 l

S -

3-22 I

TABLE 111-0-4 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #3 1985 Micror/

2 Sigma Station Hour

+-

I CP 12.35

+-

1.73 CR 5.90

+-

1.14 CS 2.32

+-

.38 i.16 ER 4.71

+-

I EH 4.77

+-

0.53 KS 4.74

+-

0.99 MB 10.06

+-

2.18 I

ME 3.32

+-

1.30 MP 7.02

+-

1.17 MS 11.55

+-

1.76 NP 3.94

+-

0.76 PC 3.38

+-

0.81 SA 9.48

+-

1.33 SP 6.21

+-

1.00 I

SS 5.64

+-

1.12 1.20 HR 7.74

+-

80 5.64

+-

0.90 EB 5.97

+-

1.18 EM 7.12

+-

1.24 J

MT 6.20

+-

1.01 OA 16.52

+-

2.68 PA 5.56

+-

1.36 PB 12.42

+-

2.24 HH 6.55

+-

2.15 I

A 5.36

+-

1.45 8

6.82

+-

1.92 C

6.33

+-

1.21 I~

0 5.33

+-

1.63 E

5.92

+-

1.03 F

6.72

+-

1.50 I

G 6.54

+-

0.91 H

7.97

+-

1.00 I

4.17

+-

1.00 J

3.07

+-

0.81 I

K 4.32

+-

0.69 L

11.34

+-

1.75 PL 6.59

+-

1.33 HS 16.42

+-

3.39 HB 0.00

+-

0.00 RL 2.29

+-

0.37 RL 1.54

+-

0.30 Geographical Regional Averages for this period are:

Near Plant (0.16 mi.)

12.73

+-

2.92 Exclusion Area (.25.68 mi.)

6.17

+-

1.34 Distant Nbrhood (.7-6.5 mi.)

6.71

+-

1.49 Background (8-21 mi.)

5.33

+-

1.03 l

3-23

TABLE IIE-D-5 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #4 1985 Micror/

Station Hour n

2 Sigma I

CP 7.87

+-

2.29 CR 3.28

+-

1.02 CS 2.71

+-

0.87 ER 1.57

+-

0.63 I

EH 3.25

+-

1.07 KS 10.04

+-

2.50 MB 3.57

+-

0.74 ME 2.45

+-

0.83 MP 2.57

+-

0.77 MS 1.71

+-

0.60 I

NP 3.87

+-

1.52 PC 1,66

+-

0.38 SA 4.64

+-

1.31 SP 5.36

+-

1.26 I

SS 0.93

+-

0.27 HR 5.07

+-

1.02 BD 6.92

+-

2.10 I

EB 1.31

+-

0.28 EM 1.26

+-

0.40 MT 3.07

+-

0.80

.I OA 13.49

+-

3.59 PA 4.92

+-

2.01 PB 6.66

+-

1.08 HH 3.97

+-

1.05 I

A 5.20

+-

1.41 B

10.22

+-

1.65 C

3.55

+-

.64 I

D 0.00

+-

0.00 E

2.91

+-

0.45 F

3.01

+-

0.48 G

3 87

+-

0.98 I

H i.09

+-

1.31 I

0.96

+-

0.33 J

1.48

+-

0.15 I

K 12.24

+-

1.89 L

13.45

+-

2.50 PL 2.13

+-

0.23 I

HS 6.52

+-

0.80 HB ND*

+-

RL 1.17

+-

0.18 RL 1.04

+-

0.28 Geographical Regional Averages for 4th QTR85 are:

I Near Plant (0.16 mi.)

7.90

+-

2.50 Exclusion Area (.25.68 mi.)

3.83

+-

0.99 Distant Nbrhood (.7-6.5 mi.)

5.07

+-

1.23 Background (8-21 mi.)

5.16

+-

1.81

  • ND - No data due to missing TLD.

I 3-24

M M

M M

M M,*

M M

M M

F I

1 i

I l

QUARTERLY AVERAGES FOR GAMMA EXPOSURE RATES a

1 j

IST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER M ' C f 0f ?

Mirr ov /

0 Cf'Or/

H y yr /

2_S e pa

2jip, Wouy
2. 5 ' P8

% r_

l Statto?

Moor

  • S hte

_W i 73 7 87 2.29 2.36 12 35 1.64 4 52 CP 5 82 3 72 5C 1 I4 3 28 1.02 l

C1t 8 36 2 78 24 0.87

.38 2 71 0.86 3 13

'.1 2 32 C5 3.04

+-

1.'6 l 57 0.63 0 81 4 71 2.51 i.35 ER 6 26 0 53 3.25 1.07 0.34 4 77 l

(w 7.87 2.81

) 73 1.68 4 74 o 99 10.04 2.50 3 C1 4 52 l

r5 9.67 0.74 l

2.18 3.57 0.12 to C6 0.51 0 22 we i.49 1.30 2.45 0 83 0 32 3 32 1.58 0.77 l

"E 3 54 1.i1 2.57 0.77 t.44 7 c7 3.81 3 52 we 7.3:

0.60 0

1 7t 0.P3 11.55

'.95 f.76 2.88 "5

10.46 C

0.76 3 87 1.52 1.27 3

+4 3 41 hP 5.05 t.1; k $3 >

0 si 1.66 0 38 0 85 3 ja q

1.44 2.14 I

pc g.13 oc e t 33 4 64 1.31 3.97 0.47 J 27 9 Ja sa 15.53 I.26 O M ts 1.00 5.36 3.27 6 21 I.35 2 19

+-

g$My W

57 4.c7 1.12 0 93 0 27 0.45 5 64 2.73

1. M

+-

1 20 5.07 1.02 emk

[

$5

7. es 0 79 7 74 2.24 2.25 me 8 ss 2.t0 CD CU H

w 0 90 6.92 3 28 5 64 1.67 2 37

+-

l EC 7.07 H

t.ta 1.31 0.26 0.30 5 97 4.32

+-

h 7

i (B

40*

t.24 1.26.- 0 40 0.83 7.12 1 66 2.31 t

E' 4 59

1. C i 3.07 0.80 4

O 1.27 6.20 0.31 2 39

+-

I m'

1 28

+-

2 68 13.49.-

3.59 M

i 3.56 12. t.)

.- 5 72 16 52 ra t2 ci MO*

f.36 4.92 2.01 2.24 5 5' 3.94 4.29 a

on 6 41 2.C9 52%

  • - 2 51

'? 42 6.66 1.C8 2 24 95 9 42 1.55 6.55 3.97 f.05 1.26 3 60 2.15 w

4.10 t 45 5 20 1.41 2.51

0. 32 0.04 5 36 a

6 23 0.10 0.86 0.24 6 R2 10.22 f.65 1.92 5

0 28

+-

I.2' 3 55

.64 0.87 6 53 2.59 3 43 C

7.94

+-

1.63 0 00 0.00 U 22 5 33 0.55 D

=0 0.26 3 12 2.9) 0 45 4.30 2 82 t o3 0.48

)

E 7.63 0.36 6 72 3 01 3.02 2 36 f.50 F

4 gg 0 91 3 87 0 98 1.51 6.54 2.45 4.39 G

9 52 1.C0 5 09 1.31 1.27 7.17 2.09 4.19

+-

+-

g 2.92 f.00 0 96 0 33 2.81 2 97

  • - 0 47 4.17 1

7.46 0 IO 3 07

'). 81 1.49 0.15 2 29 l

J E0 y.69 12 24 f.89 3.17 4.32 1.53 13 4) l 13 45 e

7.34 2.50 i.66 is.34 1 54 4 52 i,7$

1 6 72

  • ~

1.33 2.13 0.23 8.05 4 54 2.20 3 34 PL 9.c4 3 39 6.52 0 80 3 13 16 42 f.45 7 37 us '

g 43

+-

1.00 0 0; o co o*

3.4 4.32 1

1 we 8.35 0.37 1.17

.- 0 18 0 87 2 yi 0.35 2.11

+-

9t 1.14 0.30 1 04 0 28 I 97

' 54 0 54 30 e i.

I 67 1,

  • ND - No data due to missing TLD.

1 i

I i

I

TABLE 111-0-7 1985 DIRECT RADIATION SURVEY RESULTS I

Exposure Rate Location (uR/hr+-1 sigma)

Beach Terrain White Horse Beach 6.9+-0.5 Sandy, few gra' nite I

(near Hill P. Avenue) boulders within 30 feet.

White Horse Beach 7.7+.04 Sandy with small amount (in back of Blue Sall Bar) of gravel.

I Plymouth Beach 6.6+-0.3 Sandy.

(outer beach)

Plymouth Beach 6.6+-0.6 Sandy.

(inner beach)

Plymouth Beach 9.2+-0.3 Sandy. Breakwater and behind Berts Restaurant seawall nearby.

I Duxbury Beach (Control) 7.4+-0.4 Sandy with course gravel.

(ocean side)

' I I

I I

3-26 I

I I

I FIGURE III-D-1 Environmental Radiation Levels at Beaches near Pilgrim Station E

I M

I E

l l

I i

I

\\

g V

1

-l E

q l

gs E

mei iI dd n

Et

[

~

i B

g e

a

i 11111l

>>aaa

.=

=

l

\\

i d

5 e

i iii a

W101 M3d 8-0831u 3-27 I

Ill.E. Waterborne 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 ml - 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.

I 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 I

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.

I I

I I

I 3-28

TABLE III-E-1 ERMAP RESULTS-WATERBORNE MEDILP: SEAWATER UNITS: FC!/KG IC ICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONG

              • e*****ese RADIONUCLI[ES MEAN MEAN EAN (NO. MALYSES) REQUIRED RANGE STA.

RANCf RANGE I

(NON-R0lrTINE)*

LLD NO. DETECTED **

NO.

NO. DETECTEDee N0. DETECTEDn BE-7 ( 36)

(

2.0t 14.5)E -1 17

( 3.5 t 19.6)E -1

(-3.9 t 3.2)E O

( 0)

(-1.5 -

1.5)E I

(-7.3 -

14.6)E O

(-3.2 -

9)E 1

  • (

0/ 24)e

  • (

0/ 12)*

et 0/ 12)*

I K-40 ( 36)

(

!.6t

.3)E 2 23

( 3.0 t

.1)E 2

( 3.0 t

.1)E 2

( 0)

(-1.9 - 33.5)F 1

( 2.5 -

3.7)E 2

( 2.5 -

3.7)E 2

  • ( 13/ 24)e
  • ( 12/ 12)e
  • ( 12/ 12)e MN-54 ( 36) 15.

(

2.0t 2.1)E -1 17

( 5.2 i 3.2)E -1

(-5.4 t 2.3)E -1

( 0)

(-1.7 -

2.0)E O

(-1.2-2.8)E O

(-2.4 -

.9)E O

  • (

0/ 24)*

  • (

0/ 12)e

  • (

0/ 12)*

CO-53 ( 36) 15.

( -4.3t 2.0)E -1 25

( 5.6 i 2.6)E -1

( 5.6 t 2.6)E -1

( 0)

(-2.6 -

1.5)E O

(-7.7 - 21.7)E -1

(-7.7 - 21.7)E -1 et 0/24)e

  • (

0/ 12)*

  • (

0/ 12)*

FE-59 ( 36) 30.

(

2.8t 3.4)E -1 23

( l.2 i 1.1)E O

( l.2 t 1.1)E O

( 0)

(-2.8 -

4.8)E O'

(-4.9 -

9.8)E O

(-4.9 9.8)E O I

  • (

0/ 24)e

  • (

0/ 12)e

  • (

0/ 12)e CO-60 ( 36) 15.

( -3.it 2.7)E -1 11

( 2.6 t 332.8)E -3

(-1.5 28.5)E -2

( 0)

(-3.0 -

2.1)E O

(-1.8 -

2.0)E O

(-1.7 -

1.1)E 0

  • (

0/ 24)*

e( 0/ 12)*

  • (

0/12)e IN-65 ( '46) 30.

( -3.6t 3.7)E -l

(-7.8 t 47.9)E -2

(-8.9 i 5.0)E -1

( 0)

(-3.4 -

3.6)E O

(-2.5 -

3.6)E O

(-4.1 -

1.6)E O

  • (

0/ 24)*

  • (

0/ 12)*

  • (

0/121e IR-95 ( 36) 10.

(

!.31 34.4)E -2 17

( l.9 t 4.8)E -1

( l.0 t 50.1)E-2

( 0)

(-3.3 -

3.4)E O

(-2.5 -

3.4)E O

(-2.7 -

2.4)E O

  • (

0/24)*

  • (

0/ 121e

  • (

0/ 12)*

RU-103 ( 36)

( -1.2t

.2)E O 23

(-1.1 *

.3)E O

(-1.1 i

.3)E O

( 0)

(-2.9 -

.9)E O

(-3.2 -

1.3)E O

(-3.2 -

1.3)E O

  • (

0/ 24)*

  • (

0/ 12)*

  • (

0/ 12)e

  • NON-ROUTDE REFERS TO THE NUMBER OF SEPARATE MEASUFEMENTS WHICH WERE OPEATER THAN TEN (10) TIMES THE AVERAGE BA M &J M FOR THE PERIOD OF THE REPORT.

I n THE FRACTION OF SAffLE ANALYSES YIELDING DE1ECTABLE MEASUREMENTS (f.E. >3 STD DEVIATIONS) IS INDICATED WITH e(

) *,

3-29

TABLE III-E-1 (CONTINUED)

ED!tr.: SEAWATER UNITS: PCI/kG NDICATOR STATIONS STATION WITH HIGHEST EAN CCNTR(t. STATIONS neeseeeeeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeene eteeeeeeeeeeeeen RADIONUCLIOES EAN EAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NIN-ROUTINE)*

LLD NO. DETECTEDee NO.

NO. DETECTEDet NO. DETECTEDee RU-106 ( 36)

(

8.9t 19.2)E -1 23

( ?.7 t 2.6)E O

( 2.7 1 2.6)E O

( 0)

(-2.0 -

2.6)E 1

(-1.0 -

1.9)E 1

(-1.0 -

1.9)E 1

  • (

0/ 24)*

  • (

0/ 12)*

  • (

0/ 12)*

I I-131 ( 36)

( 5.2t 39.9)E -2 23

( 4.4 t 5.9)E -!

( 4.4 5.9)E -1

( 0)

(-3.5 -

3.7)E 0

(-3.6 -

4.0)E O

(-3.6 -

4.0)E O

  • (

0/ 24)e a( 0/ 12)e

  • (

0/ 121e CS-134 ( 36) 15.

( -6.42 2.1)E -1 11

(-2.7 i 3.0)E -1

(-8.6 i 2.4)E -1

( 0)

(-2.2 -

1.7)E O

(-1.3 -

1.7)E O

(-2.3 -

.5)E O a( 0/ 24)e

  • (

0/ 12)e

  • (

0/ 12)e CS-137 ( 36) 15.

( -5.5t 18.8)E -2 11

( 2.5 1 3.0)E -1

(-9.2 i 19.4)E -2

( 0)

(-1.4 -

1.7)E 0

(-1.4 -

1.7)E O

(-7.1 - 15.4)E -1 et 0/ 24)*

e( 0/ 12)e

  • (

0/ 12)*

BA-140 ( 36) 15.

( -2.3t 4.3)E -1 11

(-1.9 i 5.3)E -1

(-3.1 i 5.1)E -1

( 0)

(-5.2 -

4.4)E O

(-5.0 -

1.8)E 0

(-4.6 -

1.4)E O I

e( 0/ 24)e

  • (

0/ 12)*

  • (

0/ 12)e CE-141 ( 36)

(

7.21 27.9)E-2 11

( l.9 t 4.7)E -1

(-3.1 t 4.9)E -1 I

( 01

(-3.5 -

2.8)E O

(-3.5 -

2.8)E 0

(-5.1-1.7)E 0 et 0/ 24)*

et 0/ 12)*

e( 0/ 121e CE-144 ( 36)

(

3.8f 120.2)E -2 11 (l91 1.5)E O

( l.0 t 2.1)E O

( 0)

(-1.4 -

1.0)E I

(-6.6 -

9.9)E 0

(-9.3 - 11.9)E 0 e( 0/ 24)*

  • (

0/ 12)*

  • (

0/12)*

TH-232 ( 36)

( -6.3t 7.4)E -1 23

(-1.6 t 6.4)E -1

(-1.6 i 6.4)E -1

( 0)

(-7.9 -

5.4)E O

(-4.3 -

2.2)E O

(-4.3 -

2.2)E O

  • (

0/ 24Ie

  • (

0/ 12)e et 0/ 12)e H-3

( 12) 330.

(

5. it 2.1)t i 17

( 8.1 i 3.1)E I

( !.5 t 3.6)E I

( 0)

(-8.3 -

17.0)E I

( 3.6 -

17.0)E 1 H.5 -

II.1)E 1

  • (

0/ 8)e

  • (

0/ 4)*

e( 0/ 4)#

I e NON-ROUT!NE REFERS TO THE NMER OF SEPARATE MEGFEMENTS WHICH WERE GREATER THAN TEN (10) TIME 3 THE AVERAGE DACKGROUND FOR THE PERIOD OF THE REPORT.

I et THE FRACTION OF SAMFLE ANALYSES Y!ELDING [ETECTAEtE MEASUREMENTS

(!.E. >3 STD [CVIATIONS) !$ INDICATED WITH e(

le.

3-30

j III.F. Shellfish Shellfish are normally sampled quarterly from 5 locations: the Statien Discharge Canal, Ouxbury 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, Cs-137, 2n-65, Co-60, AcTh-228 and K-40 in samples from the Discharge Canal.

In addition there have been positive measurements of Be-7, 2n-65, Cs-137, Co-60, AcTh-228 (peak) and K 40 at Manomet Point; Be-7, Co-60, Cs-137, ACTh-228 (peak) and K-40 at Harren Cove; AcTh-223 and K-40 at Duxbury Bay; and, Be-7, AcTh-228 and K-40 at the control station in Marshfield.

The observed concentrations of Mn-54, Cs-137 Co-60, and Zn-65 were the l

result of PNPS-1 liquid releases.

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

I However, even i' a person were to consume the maximum annual quantity of seafcod (5 kilograms / year) with the highest mean concentrations of the above nuclides, they would receive a dose of less than 0.02 mrem to the total body and less than 0.20 mrem to the most restrictive organ l

(Adult, GI-LLI).

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

3-31 l

l

TABLE III-F-1 ERMAP RESULTS-SIIELLFISH I

KD lti: SHELLFISH I. NITS: PCI/KG WET INDICATOR STATICNS STATION WITH HIGHEST MEAN CONTROL STATI0rd e**eeeeeeeeeeeeeee eeeeeeeee***es**eseeeeene eneeeeeeeeeeeeee RADIONUCLIDES MEAN MEAN TAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-RiUTINE)*

LLD PC. DETECTED *e NO.

N0. DETECTEDee NO. DETECTEDee SE-7 ( 40)

(

6 lt 10.5)E O 24

( 2.4 i

.3)E 1

( 2.4 i

.3)E 1 I

( 0)

(-2.0 -

1.3)E 2

( l.2 -

3.6)E 1

( !.2 -

3.6)E 1 et 9/ 32)e

  • (

4/ 8)e

  • (

4/ 8).

K-40 ( 40)

( 10.0t 1.0)E 2 15 ( !.2 t

.1)E 3

( 8.4 t 2.3)E 2 I

( 0)

( 8.1 - 204.0)E i

( l.2 -

1.4)E 3

( 2.1 - 16.4)E 2

  • ( 31/ 32)e e( 4/ 4)e e( 8/ 8)e itE54 ( 40) 130.

( -1.6t 9.2)E -1 11

( !.6 t

.7)E O

(-4.5 i 3.1)E -1

( 0)

(-1.5 -

1.2)E 1

(-3.8 - 60.1)E -1

(-1.9 -

.8)E O

  • (

2/ 32)e

  • (

2/ 8),

of 0/ 8),

00-58 ( 40) 130.

(

l.2t

.9)E O 12

( 2.6 t 1.8)E O

(-2.5 t 2.7)E -1

( 0)

(-8.7 - 17.9)E O

(-4.9 -

17.9)E O

(-1.7 -

.7)E O

  • (

0/ 321e e( 0/ 12)*

  • ( 0/ 8)*

FE-59 ( 40) 260.

( -2.41 2.1)E O 15

(-3.0 t 130.1)E -2

(-1.7 1 1.0)E O

( 0)

(-2.9 -

2.5)E I

(-3.5 -

2.7)E O

(-6.9 -

1.3)E O

  • (

0/ 32)*

  • (

0/ 4)*

et 0/ 8)e

[.- 60 ( 40) 130.

( 5.4t 2.2)E 1 11

( 2,0 t

.7)E 2

(-3.3 i 3.0)E -1

( 6)

(-1.4 - 61.9)E I

( 2.3 - A1.9)E I

(-1.8 -

1.2)E O e( 12/ 32),

e( 8/ 8)e a( 0/ 8),

ZN-65 ( 40) 260.

(

4.5 21.5)E -1 11 f 8.8 t 3.6)E O

( !.6 i

.6)E O I

( 0)

(-2.3 -

3.0)E 1

(-2.4 - 27.9)E O

(-1.0 - 55.1)E -1 et 5/ 32),

  • (

4/ Sie el 0/ 8),

ZR-95 ( 40)

( -4.01 2.2)E O 24

( l.9 i

.6)E 0

( !.9 i

.6)E O

( 0)

(-5.4 -

.7)E I

( l.0 - 40.1)E -1

( l.0 - 40.llE -l

  • (

0/ 32)*

  • (

0/ Ole et 0/ 8)e RU-103 ( 40)

( -9.Si 10.9)E -1 11

( 3.5 1 4.4)E -1

(-6.3 t 2.8)E -1

( 0)

(-2.4 -

1.6)E 1

(-1.3 -

2.5)E O

(-2.5 -

.1)E O

  • (

0/ 32),

  • (

0/ 8)e

  • (

0/ 8)e I

e NON-ROUTIE REFERS TO THE NUMBER OF SEFARATE MEAStFEMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE A'/ERACE BACKGPOUND FOR THE PERIOD OF THE REPORT.

n THE FRACTION OF SAPFLE AtiALYSES Y!ELDING DETECTABLE MEASLEEMENTS

'I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le.

3-32

TABLE III-F-1 (CONTINUED)

EDIUM: SHELLFISH UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST K AN CONTROL STATIONS etee++eeeeeeeeeee, eneeeeeeeeeeeeeeeeeeeeene enseeeeeeeeee***

RA?!ONUCLIES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANCE RANGE (NCN-ROUTINEle LLD NO. DETECTEDee W.

NO. DETECTEDee NO. DETECTEDe*

RU-106 ( 40)

( -8.41 76.0)E -1 12

( 2.5 i 19.4)E 0

(-4.1 i 24.4)E -1 I

( 0)

(-1.3 -

1.3)E 2

(-1.3 -

1.3)E 2

(-1.3 -

1.0)E 1 et 0/ 32)e e( 0/ 12)*

e( 0/ 8)*

I-131 ( 40)

( -1.0t

.9)E 1 11

( l.2 t 1.2)E O

(-5.5 t 23.6)E -1

( 0)

(-2.7 -

.4)E 2

(-3.8 -

5.8)E O

(-9.0 - 12.7)E O

  • (

0/ 32),

  • (

0/ 8)e

  • (

0/ Ble I

CS-134 ( 40) 80.

( -2.92 1.2)E O 13

( !.1 t 2.8)E O

(-6.3 t 5.1)E -1

( 0)

(-1.8 -

1.6)E 1

(-1.3 -

1.6)E 1

(-3.0 -

2.2)E O e( 0/ 321e of O/ 8)e

  • (

0/ 8)e CS-137 ( 40) 90.

( 5.2t 8.9)E -1 11

( 2.4 t 2.1)E O

( 4.3 1 1.7)E -1

( 0)

(-1.4 -

1.7)E 1

(-3.9 - 167.0)E -1

(-3.4 - 12.1)E -1 e( 5/ 32),

  • (

1/ 8),

e( 0/ 8)e BA-140 ( 40)

( -1,3t 1.9)E 0 12

(-8.6 t 43.5)E -1

(-2.4 i 1.1)E 0

( 0)

(-2.9 -

2.2)E I

(-2.9 -

2.2)E 1

(-7.6 -

1.0)E O at 0/ 32)e

  • (

0/ 12)*

  • (

0/ 8)*

CE-141 ( 40)

(

l.31 1.9)E O 24

( 2.1

.7)E O

( 2.1 i

.7)E O

( 0)

(-4.2 -

2.3)E 1

(-1.4 -

4.4)E O

(-1.4 -

4.4)E O

  • (

0/ 32)*

  • (

0/ Ble

  • (

0/ 8)e CE-144 ( 40)

( -9.2t 3.9)E O 11

( 2.0 t 1.7)E O

(-9.1 i 19.1)E -1 I

( 0)

(-7.0 -

3.9)E I

(-3.1 - 11.7)E O

(-1.3 -

.5)E 1

  • (

0/ 321e

  • (

0/ 8)*

  • (

0/ 8)*

TH-232 ( 40)

(

3.3t

.9)E I 12

( 5.2 t 1.6)E 1

( l.6 i

.3)E 1

( !)

(-2.8 - 18.3)E 1

(-4.4 - 1830.0)E -1

( 3.4 - 28.8)E O

  • ( 10/ 32)e
  • (

3/ 12)e

  • (

4/ 8)*

e NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE E A9)REMENTS WHICH WERE OFEATER THAN TEN (10) TIMES THE AVERAGE BACKGRCOND FOR THE PERIOD OF TIE REPORT.

H THE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTAKE MEASVREMENTS (I.E. >3 STD DEVIAT10%) IS INDICATED WITH *(

le.

3-33

III.G. Algae (Irish Moss)

)

Algae, referred to as Irish Moss or Chondrus Chrtspus, is sampled l

quarterly at three locations, the PNPS Discharge Canal, Manomet Point and Ellisville.

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 and K-40 at the Discharge Canal.

In addition, there have been positive measurements of Be-7, Co-60, AcTh-228 and K-40 at Manomet Point (Station 15 - 3 miles - SE); and Be-7, Co-60, AcTh-228 and K-40 at the control station of Ellisville (Station 22 - 8 mi -

SSE). Due to the positive measurements of a reactor related nuclide at Station #22, samples were collected from another control station for the second, third and fourth quarters of 1985.

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

The only observed positive measurements of Brant Rock samples were K-40.

The measured concentrations of Co-60 at the Discharge Canal, Manomet Point and E111sville were due to liquid effluents from PNPS-1.

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

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

There were no positive measurements of reactor related nuclides at the control station in Brant Rock, approximately twelve l

miles away the NNW sector.

3-34 I

1 It is important to note that due to processing and market dilution, the presence of the Co-60 concentrations do not represent a significant i

1 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 0.05 mrem /yr to the total body and about 0.40 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 w'ith 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.

i I

3-35

~ _. _ -. _ _ _ _.... _ _,. - _

TABLE III-G-1 ERMAP RESULTS-ALGAE EDIUM: IRISH MOSS UNITS: PCI/r0 WET INDICATOR STATIOR3 STATION WITH HIGHEST E AN CONTROL STATIONS eeeeee+++,eeeeeeee eteeeeeeeeneteeeeeeeeeeee ese++eeeeeee++ee RADI0fLCLIDES EAN MEAN EAN (N0. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTINE)*

LLD

10. DETECTEDee NO.

NO. DETECTEDee NO. DETECTEDee BE-7 ( 15)

(

l.0+.

.3)E 2 15 ( 1.3 i

.3)E 2

( 9.9 t 1.3)E 1

( 0)

(-2.5 - 19.1)E 1

( 5.2 - 19.1)E 1

( 5.6 - 14.2)E 1 et 3/ 8)e e( 2/ 4)e

  • (

2/ 7)e K-40

( 15)

(

6.51

.6)E 3

( 8.1 i

.3)E 3

( 5.0 t

.3)E 3

( 0)

( 4.1 -

8.9)E 3

( 7.4 -

8.9)E 3

( 3.9 -

6.0)E 3 at 8/ 8)e

  • (

4/ 4)e

  • (

7/ 7)*

MN-54 ( 15) 130.

( 5.et 3.2)E 0 11

( 5.9 t 6.4)E O

(-4.5 t 13.6)E -1

( 0)

(-4.8 - 24.0)E O

(-4.0 - 24.0)E O

(-6.7 -

4.3)E O E

  • (

0/ 8)e

  • (

0/ 41e et 0/ 7)e C0-58 ( 15) 130.

(

2.31 21.3)E -l

( 3.0 t 3.6)E O

( 3.6 i 10,5)E -1

( 0)

(-7.5 - 12.6)E 0

(-4.8 -

12.6)E O

(-3.5 -

2.9)E O

  • (

0/ 8)e

  • (

0/ 4)*

  • (

0/ 7)e FE-59 ( 15) 260.

(

7.0t 6.5)E 0

( 1.4 t 1.1)E I

(-2.0 t 1.4)E O

( 0)

(-1.7 -

3.6)E 1

(-1.7 -

3.6)E 1

(-6.8 -

2.8)E 0 et 0/ 8)e et 0/ 4)e et 0/ 7)e CD-60 ( 15) 130.

(

4.2f 2.1)E 2

( 7.2 t 3.0)E 2

( !.! t

.7)E 1 I

( 5)

( 3.1 - 186.0)E 1

( !.9 - 18.6)E 2

(-6.0 - 51.0)E 0 et 8/ Ble

  • (

4/ 4)*

et 3/ 7)e ZN-65 ( 15) 260.

(

!.3t

.4)E 1 15 ( l.4 *

.2)E 1

(-2.2 f 30.0)E -1

( 0)

(-5.1 - 32.2)E O

( 8.2 -

17.9)E O

(-1.2 -

.9)E !

  • (

0/ 8)e

  • (

0/ 4)e

  1. ( 0/ 7)e ZR-95 ( 15)

(

l.2t 5.1)E O 34

( 7.2 i 6.8)E O

( 3.9 t 3.7)E O

( 0)

(-2.3 -

1.9)E !

(-2.2 - 20.5)E O

(-6.1 - 20.5)E O at 0/ Ole

  • (

0/ 3)*

  • (

0/ 7)*

RU-103 ( 15)

( 9.1t 16.1)E -1 11

( 2.7 t 1.9)E O

(-1.9 i 15.3)E -1

( 0)

(-6.8 -

8.2)E O

(-3.1 - 82.0)E -1

(-5.7 -

5.3)E o at 0/ 8)e

  • (

0/ 4)*

  • ( 0/ 7)*

I e NON-ROUTIPE REFERS TO THE NUMBER OF SEPAPATE MEA!WEMENTS WHICH WERE CREATER THAN TEN (10) TIMES TE AVERAGE BACMJND FOR THE PERIOD OF THE REPORT.

    • THE FRACTION OF SMPLE ANALYSES Y!ELDING DETECTARE MEA 9)REMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH e(

le.

3-36

TABLE III-G-1 (CONTINUED)

ED!lm IRISH MOSS LNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGE ST TAN CONTROL STATIONS I

eeseeeeee neeneen einese********eenesesee eve **eeeeeeeeeet RADIONLCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RA'KE STA.

RANCE RANGE (NON-ROUTINEle LLD NO. DETECTED n NO.

NO. DETECTEDee NO. DETECTEDu RU-106 ( 15)

(

2.82 21.7)E O 34

( !.7 i 1.8)E I

( l.5 t 1.0)E 1

( 0)

(-1.0 -

.7)E 2

(-1.9 -

3.7)E I

(-1.9 -

4.9)E 1

  • (

0/ 8),

et 0/ 3)e

  • (

0/ 7)e I-131 ( 15)

( -4.4i 3.5)E 1 22

( l.9 t 1.7)E O

( 5.3 t 43.9)E -1

( 0)

(-2.7 -

.2)E 2

(-2.1 -

5.8)E O

(-2.0 -

1.9)E 1 e( 0/ 8)*

  • (

0/ 4)*

  • (

0/ 7)e CS-134 ( 15) 80.

( -4.0t 16.8)E -l

( l.7 i 3.1)E O

(-1.4 i 1.2)E 0

( 0)

(-5.9 -

8.7)E O

(-5.9 -

8.7)E O

(-8.2 -

1.7)E O

  • ( 0/ 8)*
  • (

0/ 4)e

  • (

0/ 7),

C5-137 ( 15) 80.

(

4.lt 2.1)E O 11

( 5.4

  • 2.1)E O

(-5.2

  • 8.6)E -1

( 0)

(-8.1 - 10.6)E O

( 2.3 - 106.0)E -1

(-4.4 -

2.2)E O et 0/ 8)*

  • (

0/ 4)*

ef 0/ 7)*

BA-140 ( 15)

(

-2.6*

4.3)E 0 15

( 3.2 i 6.3)E O

(-7.5 t 6.2)E O

( 0)

(-2.1 -

1.7)E 1

(-1.3 -

1.7)E 1

(-4.5 -

.2)E 1 el 0/ 8)e

  • (

0/ 4)*

  • (

0/ 7)e CE-141 ( 15)

( -9.4t 39.8)E -1 22

( 4.0 t

.9)E O

( 7.9 t 367.2)E -2

( 0)

(-2.1 -

1.5)E 1

( 2.3 -

6.6)E O

(-2.0 -

.8)E 1

  • (

0/ Ole

  • (

0/ 4)*

e( 0/ 7)e CE-144 ( 15)

( -1.6i 69.9)E -1 11

( l.1 t

.7)E I

(-6.5 t 7.8)E O I

( 0)

(-4.0 -

2.5)E 1

(-5.3 - 24.6)E O

(-4.6 -

1.6)E 1

  • (

0/ 8)e e( 0/ 4)*

  • (

0/ 7)*

TH-232 ( 15)

(

2.52

.7)E 1 22

( 3.3 t 1.5)E I

( 2.6 t

.9)E I

( 0)

(-4.3 - 60.!)E O

( 7.9 - 77.2)E O

( 5.3 - 77.2)E O

  • (

0/ 8),

  • (

2/ 4)e

  • (

2/ 7)e I

e NON-ROUTINE REFERS TO THE NUMPER OF SEFARATE EASLREMENTS WHICH WEFE GREATER THAN TEN (10) TIMES THE A'KRAGE FACK0ROLND FOR THE PERIOD OF THE FEPORT.

se THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTAELE MEASLFEMENTS (i.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le.

l 3-37

III.H. Lobster (Arthropods)

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 nuclides other than K-40 in either the indicator or the control sa~11es (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 I

3-38 m

l TABLE III-Il-1 E

ERMAP RESULTS-LOBSTER EDIle': LOPSTER LNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATICNS

    • eeeeeeeeeeeeeeen eeeeeeeeeeeeneeee++eense seineenneene RADION'ILIDES EAN MEAN EAN (NO. f.NALYSES) REQUIRED RAtKE STA.

RANGE RANCE (tCN-ROUTINEle LLD NO. DETECTEDn NO.

NO. DETECTEDet NO. DETECTEDee BE-7 ( 5)

(

6.5f 5.1)E 1 19

( 7.4 i 10.2)E 1

( 7.4 i 10.2)E 1

( 0)

(-1.8 - 21.3)E 1

  • ( 0/ 4)*

e( 0/ 1)*

  • ( 0/ 1)*

K-40

( 5)

( 2.7t

.1)E 3 11

( 2.7 i

.1)E 3

( 1.5 t

.2)E 3

( 0)

( 2.4 -

2.9)E 3

( 2.4 -

2.9)E 3

  • (

4/ 4)e

  • (

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

MN-54 ( 5) 130.

( -4.4t 9.4)E 0 19 ( 2.4 t 12.9)E O

( 2.4 i 12.9)E O

( 0)

(-3.2 -

1.1)E 1

  • (

0/ 4)e et 0/ 1)*

e( 0/ 1)*

CD-53 ( 5) 130.

(

!.6t 10.9)E O 19 ( 2.4 i

!!.2)E O

( 2.4 t

!!.2)E O

( 0)

(-2.4 -

2.4)E 1

  • (

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

  • (

0/ 1),

FE-5? ( 5) 260.

( -4.31 1.6)E 1 19

(-8.8 t 25.4)E O

(-8.8 t 25.4)E O

( 0)

(-8.6 -

-1,6)E 1

  • (

0/ 4)e

  • (

0/ lie ei 0/ 1)*

CO-60 ( 5) 130.

(

4.0t 13.3)E O 19 ( 2.1 t 1.7)E 1

( 2.1 i 1.7)E 1

( 0)

(-2.4 -

3.3)E 1 a( 0/ 4)*

  • (

0/ 1)*

  • ( 0/ 1)*

ZN-65 ( 5) 260.

( -7.6t 16.7)E O 11

(-7.6 i 16.7)E O

(-1.4 t 2.6)E 1

)

( 0)

(-3.7 -

4.0)E 1

(-3.7 -

4.0)E 1

  • (

0/ 4)*

  • (

0/ 4)*

  • (

0/ 1)e ZR-95 ( 5)

(

1.lt

.5)E 1 11

( !.1 i

.5)E 1

(-1.7 t 19.2)E O

( 0)

( 2.3 - 24.9)E O

( 2.3 - 24.9)E O

  • ( 0/ 4)*
  • (

0/ 4)*

  • ( 0/ 1)*

RU-103 ( 5)

( -6.11 77.2)E -1 19 ( 3.7 t 119.0)E -1

( 3.7 t 119.0)E -1

( 0)

(-1.5 -

2.1)E 1

  • (

0/ 4)e

  • (

0/ 1)*

  • (

0/ 1)#

  • NON-ROUT!fE REFERS TO THE NUMEER CF SEPARATE EA9FEMENTS WHICH WEFI GREATER THAN TEN (10) TIMES THE A',' ERA 0E BACKGROLND FOR THE PERIOD OF TE REPORT.
    • THE FRACil0N CF SAMPLE ANALYSES Y!ELDING DETECTABLE MEASUREMENTS

~

(I.E. >3 STD DEVIATIONS) IS ItO!CATED WITH *(

le.

=-

3-39

I TABLE III-H-1 (CONTINUED)

ED!lP: LOPSTER UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS ennenne**nne un***entununenne

      • nenten**n RADIONUCLIDES MEAN MEAN EAN (h'0. ANALYSES)

REQUIRED RANGE STA.

RANGE RANGE (Nf.f4-ROUTINE)*

LLD NO. DETECTED **

NO.

NO. DETECTED **

NO. ETECTEDee RU-105 ( 51

( -6.3t 8.8)E 1 11

(-6.3 i 8.8)E I

(-9.2 i 10.8)E 1

( 0)

(-2.9 -

1.3)E 2

(-2.9 -

1.3)E 2

  • (

0/ 4)*

  • ( 0/ 4)*
  • (

0/ 1)*

I-131 ( 51

( -1.5t 1.7)E 1 11

(-1.5 t 1.7)E 1

(-2,2 i 1.8)E 1

( 0)

(-5.0 -

1.8)E 1

(-5.0 -

1.8)E 1

  • (

0/ 4)*

  • (

0/ 4)*

  • (

0/ 1)*

CS-134 ( 5) 80.

( -1.31

.7)E 1 11

(-1.3

.7)E 1

(-2.0 i 1.3)E 1

( 0)

(-2.9 -

.1)E 1

(-2.9 -

.1)E 1

  • (

0/ 4)*

  • (

0/ 4H

  • (

0/ 1)*

CS-137 ( 51 80.

(

1.2t

.6)E 1 11

( !.2 i

.6)E 1

( 8.8

  • 118.0)E -1

( 0)

(-2.6 - 25.9)E O

(-2.6 - 25.9)E O

  • (

0/ 4)*

  • (

0/ 4)*

  • ( 0/ 1)*

BA-140 ( 5)

(

8.51 13.4)E O 19

( 1.0 t 1.7)E 1

( !.0 t 1.7)E 1

( 0)

(-2.7 -

3.8)E 1

  • (

0/ 4)*

  • (

0/ 1)*

  • (

0/ 1)*

CE-141 ( 5)

(

3.2t 4.4)E O 11

( 3.2 t 4.4)E O

(-4.6 i 17.1)E O I

( 0)

(-5.2 - 14.5)E O

(-5.2 - 14.5)E O

  • (

0/ 4)*

  • (

0/ 4)*

  • (

0/ 1)*

CE-144 ( 5)

( -1.91 4.5)E 1 11

(-1.9 i 4.5)E 1

(-5.5 t 6.3)E 1

( 0)

(-1.5 -

.3)E 2

(-1.5 -

.3)E 2

  • (

0/ 4H

  • (

0/ 4)*

  • (

0/ 1)*

TH-232 ( 5)

(

1.It 2.1)E 1 19

( 2.3 i 5.7)E 1

( 2.3 t 5.7)E 1

( 0)

(-2.6 -

7.0)E 1 i

  • (

0/ 4)*

  • ( 0/ 1)*
  • ( 0/ 1)*
  • NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUFEMENTS WHICH WERE GREATER Ti%N TEN (10) TIMES THE AVERAGE BACRROUND FOR THE PERIOD OF TT REPORT.
    • THE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE MEASUREMENTS (f.E. >3 STD KVIATIONS) IS INDICATED WITH *f H.

l

III.I. Fish 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 1985, one Group II sample was unavailable in the first quarter, and one Group III sample was unavailable in the third quarter respectively.

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

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

A Bluefish sample collected on 6/15/85 at the Discharge Canal Outfall Area indicated a positive measurement of Cs-137.

The Bluefish is in the Group IV category (Coastal Migratory). Although the collection of salmon is not required per Technical Specifications, salmon is collected and analyzed when available. A salmon sample collected on 11/7/85 at the Mouth of the North River (Hanover) indicated a positive measurement of K 40 only.

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 less than 0.03 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 I

TABLE III-I-l ERMAP RESULTS-FISH ED!lr.: FINFI94 UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIQiEST EAN CONTROL STATIONS eeeeeeeeeeeeeeeeen eeeeeeeeeee********ee****

eeeeeeeee**eesee RADION' CLIDES EAN EAN EM J

(NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTINEle LLD NO. DETECTED *e NO.

NO. DETECTEDee NO. DETECTED ++

I BE-7 ( 32)

( 3.91 21.1)E O 15 ( 8.8 i 5.1)E 1

(-1.2 t 2.7)E 1

( 0)

(-2.7 -

1.9)E 2

(-1.2 -

.8)E 2

  • (

0/ 26)*

  • (

0/ 11e

(

3.11

.1)E 3 29 ( 3.4 i

.1)E 3

( 3.0 t

.2)E 3

( 0)

( 2.4 -

4.0)E 3

( 3.3 -

3.7)E 3

( 2.3 -

3.7)E 3

  • ( 26/ 26),
  • (

3/ 3),

  • (

6/ 6),

PN-54 ( 32) 130.

(

1.2t 1.7)E 0 14

( 4.0 t 9.8)E O

(-1.0 t 2.4)E O

( 0)

(-1.5 -

1.7)E 1

(-1.1 -

.7)E 1 et 0/ 26)e

  • (

0/ 1)*

  • (

0/ 6),

00-58 ( 32) 130.

( -3.4t 2.0)E 0 30

( 8.8 i 9.1)E O

( 1.2 t 2.7)E O

( 0)

(-2.4 -

2.1)E 1

(-7.6 -

8.8)E O

  • (

0/ 26)e

  • (

0/ 1)*

e( 0/ 6)e FE-59 ( 32) 260.

(

2.41 5.1)E O 98

( 2.7 i

.5)E 1

( 3.6 i 8.9)E O

( 0)

(-4.6 -

6.7)E 1

( 2.2 -

3.2)E 1

(-2.8 -

3.2)E 1 el 0/ 26),

e( 0/ 2)*

e( 0/ 6)e CO-60 ( 32) 130.

( -3,0i 18.7)E -1 30 ( 3.8 i 10.8)E O

( 3.6 i 437.8)E -2

( 0)

(-1.4 -

3.3)E 1

(-1.9 -

1.3)E 1

  • (

0/ 26),

  • (

0/ 1)*

  • (

0/ 6)*

ZN-65 ( 32) 260.

( -2.6i 4.6)E O 19 ( 3.4 i 1.7)E 1

(-1.9 i 1.1)E 1

( 0)

(-7.3 -

3.4)E 1

(-4.8 -

.9)E 1 e( 0/ 26),

  • (

0/ 1)*

f( 0/ 6)e ZR-95 ( 32)

( -2.2f 3.4)E O 14

( 1.0 i 1.6)E 1

(-1.3 i

.9)E 1

( 0)

(-4.1 -

2.5)E 1

(-4.4 -

2.0)E 1

  • (

0/ 26)e e( 0/ 1)*

  • (

0/ 6)*

RU-103 ( 32)

(

1.51 2.3)E O 14

( 9.7 i 10.1)E 0

(-1.1 i 3.8)E O

( 0)

(-2.4 -

2.4)E 1

(-9.9 - 15.3)E O

  • (

0/ 26)*

  • (

0/ 11,

  • (

0/ 6)e e NON-ROUTIhE REFERS TO THE NUMBER OF SEPARATE MEASUREENTS WHICH WERE GREATER TW.N TEN (10) TIES THE AVERASE BACKGROLND FOR THE PERIOD OF THE REPORT.

et THE FRACTION OF SAFLE ANALYSES YIELDING DETECTABLE EASLEEMENTS (I.E. 33 STD DEVIATIONS) IS INDICATED WITH et le.

3-42

l TABLE III-I-l E

(CONTINUED)

EDIUM: FINFISH UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS eteve++*eenene+e eteeeeeeeeeeeeeee****e ne eneeee***eseeeen RADIONUCLIDES EAN EAN EAN

(?(). AtiALYSES)

REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTINE),

LLD NO. DETECTEPee NO.

NO. DETECTED **

NO. IETECTED+*

R'J-106 ( 32)

( -1.8f 1.3)E 1 30 ( 3.9 i 5.7)E 1

(-3.8 i 32.7)E 0 I

( 0)

(-1.6 -

1.01E 2

(-1.2 -

1.2)E 2

  • (

0/ 26)e

  • (

0/ 1)*

  • (

0/ 6),

I-131 ( 32)

( -5.41 10.3)E O 15 ( 2.0 i 1.7)E 1

(-1.2 i 4.4)E O

( 0)

(-1.5 -

.8)E 2

(-2.3 -

.6)E 1

  • (

0/ 26),

  • (

0/ 1)*

  • (

0/ 6).

CS-134 ( 32) 80.

( -6.31 1.4)E O 15

(-4.7 i 7.8)E O

(-6.6 i 1.2)E O

( 0)

(-1.9 -

1.1)E 1

(-1.1 -

.4)E 1

  • (

0/ 26).

  • (

0/ 1)*

e( 0/ 6),

CS-137 ( 32) 80.

(

5.0 1.7)E O 98 ( 7.1 i 9.1)E O

( 1.3 i 4.8)E O

( 0)

(-1.0 -

2.2)E 1

(-2.0 - 16.2)E O

(-1.5 -

1.6)E 1

  • (

0/ 26),

  • (

0/ 2)*

e( 1/ 6)e BA-140 ( 32)

( -5.0t 5.6)E 0 14

( 1.1 i 1.4)E 1

( 7.8 t 3.7)E O

( 0)

(-8.1 -

4.3)E 1

(-4.6 - 18.8)E O et 0/ 26)*

  • (

0/ 1),

  • ( 0/ 6)e CE-141 ( 32)

( -1.4i 3.2)E 0 14 ( 2.3 i 1.3)E 1

(-3.5 i 4.2)E O

( 0)

(-3.1 -

3.1)E 1

(-1.2 -

1.5)E 1

  • (

0/ 26)*

  • (

0/ 1)*

  • (

0/ 6)e CE-144 ( 32)

( -5.51 9.7)E O 30 ( 6.4 i 3.9)E 1

( 8.4 i 13.9)E O

( 0)

(-1.2 -

.9)E 2

(-1.6 -

6.4)E 1

  • (

0/ 26)*

  • (

0/ 1)*

  • (

0/ 6),

I TH-232 ( 32)

(

1.2f

.5)E 1 98 ( 2.9 i 1.2)E 1

( 7.7 i 10.4)E O

( 0)

(-3.4 -

5.9)E 1

( 1.7 -

4.0)E 1

(-3.4 -

4.0)E 1

  • (

0/ 26)*

  • (

0/ 2),

  • (

0/ 6),

I 1

e NON-ROUTINE REFERS TO THE NLHBER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES THE AVEPAGE BACK0R11ND FOR THE PERIOD OF THE REPORT.

H THE FRACTION OF SAELE ANALYSES YIELDING DETECTABLE EASUREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

=-

3-43

III.J. Sediments Sediment samples are taken semi-annually at five indicator stations including Rocky Point, Plymouth Harbor, Duxbury Bay, Plymouth Beach and Hanomet 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 isotopes.

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

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

It is clear from this table that the highest mean concentration of Cs-137 was observed in the sediment samples taken from Duxbury Bay (Station 13).

The highest value of Cs-137 was observed in the 5-10 cm segment.

This sample was collected on 10/16/85.

In addition, Cs-137 was observed in the rest of the sediment segments (0-5 and 10-15 cm) obtained from Duxbury Bay on 10/16/85, and was observed in all of the sediment segments (0-30 cm) collected on 5/09/85.

The observation of Cs-137 was also made in all of the sediment segments (0-30 cm) collected on 5/14/85 at Warren Cove and in all of the sediment segments (0-15 cm) collected on 10/08/85.

There were only observations of AcTh-228 and K-40 (naturally occurring nuclides) in the 10-15 cm sediment segment collected on 5/24/85 and 10/8/85.

The majority of sediment segments (0-30 cm) collected on 5/8/85 for the

,I 3-o l

l

control station at Marshfield had positive measurements of Cs-137, and there were two observations of Cs-137 in the sediment samples collected on 10/10/85 at the 5-10 cm segments.

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, Harren Cove and Marshfield, are attributable to the fission products related to fallout from previous weapons testing.

In addition to the above, there were eleven positive measurements of Co-60 observed and two indications of the presence of Co-60.

The highest mean concentration of Co-60 was observed at Rocky Point. All eight sediment segments (0-30 cm) collected at Rocky Point on 5/24/85 and three sediment segments (0-15 cm) collected on 10/24/85 indicated a positive measurement of Co-60. One sediment segment (20-22 cm) collected at Manomet Point on 5/24/85 indicated the presence of Co-60 as did one segment sample (0-2 cm) collected at Duxbury Bay on 5/9/85.

Since Duxbury Bay is a control point, and the prevailing water current is in the southerly direction, it is believed that the indication of the presence of Co-60 is most likely due to cross-contamination during the collection process.

The measured concentrations of Co-60 are due to liquid effluents of PNPS-1.

j l

l 1

-s e 3-45 I

i

Analyses for plutonium isotopes in sediment samples are performed by the EAL Corporation (formally LFE Environmental Analyses Laboratories) in Richmond, California.

The results of these analyses for the 1985 samples are presented in Table III-J-2.

The results for the 1984 samples were unavailable for the previous report, and are now presented in Table III-J-3.

In the past, and as is indicated in the 1985 analysis results, there was no apparent trend in these data to indicate that the PNPS-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.

I I

l f

3-46 l

h TABLE III-J-l ERMAP RESULTS SEDIMENT I

EDIUM: SEDIENT UNITS: PCI/KG DRY I

INDICATOR STATICNS STATION WITH HIGEST EAN CONTROL STATICNS I

nunennennu unennuentunnun

    • nu nu* *nn RADIONUCLIDES MEAN MEAN EAN (NO. ANALYSES) RE M RED RANGE STA.

RANGE RANCE (NON-ROUTINE)*

LLD NO. DETECTED **

NO.

NO. DETECTED **

W. DETECTEDn I

BE-7 ( 61)

(

4.71 3.2)E 1 13

( 1.8 i 1.4)E 2

( 4.6 i 3.5)E 1 I

( 1)

(-1.9 - 14.7)E 2

(-1.7 - 14.7)E 2

(-8.3 - 35.7)E 1

  • (

4/ 50)*

  • (

3/ 11)*

  • (

1/ 11)*

I K-40

( 61)

(

1.11

.0)E 4 13

( 1.5 i

.0)E 4

( !.0 t

.0)E 4

( 0)

( 6.9 - 16.4)E 3

( 1.0 -

1.6)E 4

( 9.5 - 11.4)E 3

  • ( 50/ 50)*
  • ( 11/ 11)*
  • ( 11/ 11)*

MN-54 ( 61) 60.

( -7.8i 1.0)E O 24

(-3.8 i 2.1)E O

(-3.8 i 2.1)E O

( 0)

(-2.2 -

1.1)E 1

(-1.3 -

.9)E 1

(-1.3 -

.9)E 1

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ 11)*

CO-58 ( 61) 60.

( -6.2t 1.2)E O 24

(-2.9 i 2.0)E O

(-2.9 i 2.0)E O

( 0)

(-2.3 -

1.6)E 1

(-1.5 -

.8)E 1

(-1.5 -

.8)E 1

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ 11)*

FE-59 ( 61) 120.

( -6.2i 3.0)E O 11

( 3.8 i 51.5)E -1

(-1.6 i 9.5)E O

( 0)

(-6.2 -

5.1)E 1

(-2.5 -

2.8)E 1

(-5.0 -

5.6)E 1

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ 11)*

C0-60 ( 61) 60.

(

1.2i

.4)E 1 11

( 5.4 i

.7)E 1

( 7.7 i 20.5)E -1 I

( 11)

(-2.0 - 10.2)E 1

( 2.2 - 10.2)E 1

(-9.4 - 10.2)E O

  • ( 11/ 50)*
  • ( 11/ 11)*
  • (

0/ 11)*

IN-65 ( 61) 120.

(

4.7f 2.3)E O 15 ( 1.0 t

.6)E 1

( 4.9 i 50.4)E -1 I

( 0)

(-3.1 -

4.4)E 1

(-1.4 -

4.4)E 1

(-1.8 -

4.1)E 1

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ 11)*

l I

ZR-95 ( 61)

(

3. 2i 2.0)E 0 14

( 1.3 i

.6)E 1

( 1.0 i

.3)E 1 l

( 0)

(-3.0 -

3.4)E 1

(-8.2 - 33.8)E O

(-4.0 - 26.2)E O

  • (

0/ 50)*

  • ( 0/ 6)*
  • (

0/ 11)*

RU-103 ( 61)

(

8.7f 11.8)E -1 13

( 5.8 1 1.3)E O

(-4.7 i 2.0)E O

( 0)

(-2.7 -

1.8)E 1

( 3.4 - 138.0)E -1

(-1.7 -

.5)E 1

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ 11)*

I I

  • WN-ROUTINE REFERS TO TE NUMBER OF SEPAPATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERACE BACKGROLND FOR THE PERIOD 0F THE REPORT.

I n THE FRACTION OF SAMPLE ANALYSES YIELDING IETECTABLE MEASUREMENTS (I.E. )3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

3-47

E TABLE III-J-l (CONTINUED)

I EDIUM: SEDIMENT UNITS: PCI/KG DRY INDICATOR STATIONS STATION WITH HICHEST EAN CONTROL STATIONS I

u f ute ne n n u n n u e *

  • u*** *
  • nn e t un e seen***unent RADIONUCLIDES MEAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-R0l' TINE)*

LLD NO. DETECTED **

NO.

NO. DETECTEDu NO. DETECTED **

I RU-106 ( 61)

( -1.41

.8)E 1 11

( 9.5 i 22.0)E O

( 4.8 i 22.8)E O I

( 0)

(-1.3 -

1.6)E 2

(-9.8 - 16.4)E 1

(-1.3 -

1.2)E 2

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ 11)*

I-131 ( 61)

( -2.li 7.2)E O 24

( 1.9 i 1.7)E 1

( !.9 i 1.7)E 1 I

( 0)

(-1.1 -

1.5)E 2

(-8.6 -

9.9)E 1

(-8.6 -

9.9)E 1

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ !!)*

CS-134 ( 61) 150.

( -4.0t

.9)E O 14

(-2.0 i 1.8)E O

(-6.8 i 2.6)E O

( 0)

(-2.6 -

1.6)E 1

(-S.1 -

2.2)E O

(-2.8 -

.4)E 1

  • (

0/ 50)*

  • (

0/ 6)*

  • (

0/ 11)*

CS-137 ( 61) 150.

(

2.61

.4)E 1 13

( 6.5 i

.3)E 1

( 1.6 i

.3)E 1

( 0)

(-7.6 - 83.3)E 0

( 5.0 -

8.3)E 1

(-7.9 - 322.0)E -1

  • ( 25/ 50)*
  • ( 11/ 11)*
  • (

7/ 11)*

BA-140 ( 61)

( -2.61

.5)E 1 15

(-1.6 i

.8)E 1

(-3.3 i

.9)E 1

( 0)

(-1.3 -

.6)E 2

(-5.4 -

3.1)E 1

(-9.4 -

1.6)E 1

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ 11)*

CE-141 ( 61)

(

7.0i 2.0)E O 13

( 1.0 t

.6)E 1

( 6.7 i 3.3)E O I

( 0)

(-2.0 -

4.5)E 1

(-2.0 -

4.5)E 1

(-8.6 - 24.5)E O

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ 11)*

CE-144 ( 61)

( -1.81

.6)E 1 12 ( 3.2 i 12.3)E O

(-5.1 i 1.1)E 1 I

( 0)

(-1.4 -

.9)E 2

(-6.9 -

9.4)E 1

(-1.3 -

.1)E 2

  • (

0/ 50)*

  • (

0/ 11)*

  • (

0/ 11)*

I TH-232 ( 61)

(

3.71

.3)E 2 13

( 6.7 i

.2)E 2

( 3.6 i

.2)E 2

( 0)

( 1.5 -

7.9)E 2

( 5.5 -

7.9)E 2

( 2.6 -

4.2)E 2

  • ( 50/ 50)*
  • ( 11/ 11)*
  • ( 11/ 11)*

4 I

  • NON-ROUTINE REFERS TO TE NUMBER OF SEPARATE MEASLFfMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERASE BATOROUND FOR THE PERIOD OF THE REPORT.
    • THE FRACTICN OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

I S

I

TABLE III-J-2 RESULTS OF SEDZMENT ANALYSES FOR PLUTONIUM i

1985 Samples Location Depth (cm)

Results pC1/Kg (dry) +- 1. Error (1 ) (a) 238 239,240 I

Pu Pu I

Duxbury Bay 0-2 0.64 1 43.

23.1 1 7.

Plymouth Harbor 0-2 0.39 2 31.

6.84 1 7.

Plymouth Harbor 16-18 0.22 1 33.

10.4 1 7.

Rocky Point 0-2 0.22 2 67.

2.64 2 13.

Rocky Point 16-18 0.095 2 150.

2.16 1 16 Manomet Point 0-2 0.050 2 300.

3.83 2 12.

Plymouth Beach 0-2 4.48 1 17.

33.8 1 7.

Marshfield-Control 0-2 0.31 1 40 5.54 i 8.

(a)

If the result is zero, the error is in pC1/Kg 3

I I

I I

3-49 I

l 1

TABLE I11-J-3 RESULTS OF SEDIMENT ANALYSES FOR PLUT0NIUM I

1984 Samples I

  • ' Depth (cm)

Results Location pC1/Kg (dry) +- % Error-(1 ) (a)

I 238 239,240 Pu Pu Duxbury Bay 0-2 0.44 1 37.

6.64 2 8.

Plymouth Harbor 0-2 3.40 1 40.

11.7 2 6.

Plymouth Harbor 16-18 0.030 2 200.

3.92 2 10.

Rocky Point 0-2 0.22 1 50.

1.95 2 15.

Rocky Point 12-14 0.11 2 100.

1.88 3 16.

Hanomet Point 0-2

-0.05 1 200.

2.61 2 14.

J Marshfield-Control 0-2 0.44 -+ 37.

6.64 _+ 8.

(a)

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

I-I I

I I

I I

I 3.,,

I

I TII.K. Milk I

Milk samples were collected at two locations during 1985, the Plymouth County Farm (Station 11 - 3.5 mi - H) and the Whitman Farm (Station 21

- 21 mi - NH).

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 1985.

Thus, the only dependable indicator station (within 5 miles) for milk near PNPS-1 l

I

}

during 1985 was from the Plymouth Country Farm.

This was confirmed in the 1985 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.

i The results of ERMAP program for the milk media are presented in Table I

III-K-1.

The results of analyses for Cs-137 and Sr-90 are presented 4

graphically in Figures III-K-1 and III-K-2 respectively.

There were no positive measurements or indications of I-131 in any of the samples.

I The highest mean concentration of Sr-90 occurred at Plymouth County Farm (collected on 6/20/85) and the highest mean concentration of Sr-89 occurred at the Whitman Farm (collected on 6/6/85). However, there were no positive measurements made of either Sr-89 or Sr-90, there were only indications of the presence of Sr-90 (activity greater than three times the standard deviation).

Station releases for this

{

l i

l 3-51 1

1 I

l

I period exhibited a Sr-89/Sr-90 ratio of about 1/.006 and therefore it is unlikely that PNPS-1 is the major source of the indicator station activity since the measured Sr-89/Sr-90 was about 1/5.

In the case of Cs-137, the highest mean value of concentration occurred at the Whitman Farm (21 mi - W).

The Cs-137 highest mean concentration for Whitman Farm occurred in early August (collected on 8/08/85). The Whitman Farm is the control station and therefore the Cs-137 was most likely due to previous atmospheric weapons testing.

The indicator station, Plymouth County Farm (3.5 mi - W), highest mean value concentration of Cs-137 occurred during mid-September (collected on 9/19/85).

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 I

due to fallout from previous atmospheric weapons testing.

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

I I

I I

I

'~

I I

TABLE III-K-1 ERMAP RESULTS-MILK I

EDILM: MILK UNITS: PCI/KG I

INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTR8L STATIONS eu e n u nee n n u u n u tt u e u unu n eu te nuineuenen RADIONLCLI0ES EAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.

RANCE RAtCE (NON-ROUTINE)*

LLD NO. DETECTED **

NO.

NO. DETECTED **

NO. DETECTED **

I SR-89 ( 36) 10.

( -3.lt 1.3)E -1 21

( 9.1 i 12.1)E -2

( 9.1 i 12.1)E -2 I

( 0)

(-1.7 -

.5)E O

(-8.8 - 11.4)E -1

(-8.8 - 11.4)E -1

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

I SR-90 ( 36) 2.

(

3.5t

.2)E O 11

( 3.5 i

.2)E O

( !.8 i

.1)E O

( 0)

( 2.3 -

5.5)E O

( 2.3 -

5.5)E O

( 1.2 -

2.0)E O

  • ( 18/ 18)*
  • ( 18/ 18)*
  • ( 18/ 18)*

BE-7 ( 36)

( -4.01 18.7)E -1 21

(-3.0 i 18.4)E -1

(-3.0 i 18.4)E -1

( 0)

(-2.2 -

1.0)E 1

(-2.4 -

1.1)E 1

(-2.4 -

1.1)E 1

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)t K-40 ( 36)

(

!.4i

.0)E 3 11 (1.4i

.0)E 3

( 1.4 i

.0)E 3

( 0)

( 1.3 -

1.5)E 3

( !.3 -

1.5)E 3

( 1.2 -

1.5)E 3

  • ( 18/ 18)*
  • ( 18/ 18)*
  • ( 18/ 18)*

PN-54 ( 26)

( -4.3i 2.5)E -1 21

( 2.2 i 3.0)E -1

( 2.2 i 3.0)E -1

( 0)

(-2.4 -

1.0)E O

(-2.9 -

2.6)E O

(-2.9 -

2.6)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

CO-58 ( 36)

( -3.31 2.4)E -1 21

( 4.4 22.6)E -2

( 4.4 t 22.6)E -2 I

( 0)

(-2.3 -

2.01E O

(-1.4 -

2.1)E O

(-1.4 -

2.1)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

FE-59 ( 36)

(

1.51 6.0)E -1 11

( 1.5 i 6.0)E -1

( 1.3 i 5.5)E -1 I

( 0)

(-2.9 -

5.7)E O

(-2.9 -

5.7)E O

(-5.2 -

3.9)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

I CD-60 ( 36)

( -3.51 3.4)E -1 11

(-3.5 i 3.4)E -1

(-5.3 i 1.9)E -1

( 0)

(-3.3 -

2.4)E O

(-3.3 -

2.4)E O

(-2.1 -

1.1)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

ZN-65 ( 36)

( -1.8t

.6)E O 21

( 5.9 t 4.9)E -1

( 5.9 i 4.9)E -1

( 0)

(-7.1 -

3.3)E O

(-3.8 -

3.8)E O

(-3.8 -

3.8)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

  • NON-ROUTINE REFERS TO TE NLPGER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPC9T.

u THE FRACTION OF SAMPLE ANALYSES YIELDING [ETECTABLE MEASUREMENTS I

(I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

3-53

TABLE III-K-1 (CONTINUED)

I EDIUM: MILK UNITS: PCI/KG INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTRGL STAT!0r6

! **nnunnenua

    • uutununtuumu n***nnut**u I

RADICH R IDES MEAN MEAN MEAN (NO. ANALYSES)

RE M RED RANGE STA.

RANGE RANGE (NON-ROUTINE)*

LLD NO. DETECTED **

NO.

NO. DETECTEDu NO. DETECTED **

I ZR-95 ( 36)

(

4.51 4.0)E -1 21

( 8.7 i 3.1)E -1

( 8.7 i 3.1)E -1 I

( 0)

(-2.5 -

2.9)E O

(-1.1 -

4.0)E O

(-1.1 -

4.0)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

RU-103 ( 34)

( -8.61 1.7)E -1 21

(-6.1 i 2.7)E -1

(-6.1 i 2.7)E -1 I

( 0)

(-2.1 -

.5)E O

(-2.5 -

1.6)E O

(-2.5 -

1.6)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

RU-10 ( 36)

( -3.it 1.0)E O 21

( 9.0 i 18.6)E -1

( 9.0 i 18.6)E -1

( 0)

(-1.0 -

.5)E 1

(-8.9 - 24.6)E O

(-8.9 - 24.6)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

I-131 ( 36) 2.

(

2.2i

.9)E -2 11

( 2.2 i

.9)E -2

( 1.8 i 1.2)E -2

( 0)

(-5.2 - 12.4)E -2

(-5.2 - 12.4)E -2

(-5.7 - 18.6)E -2

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

CS-134 ( 36) 15.

( -6.21 2.3)E -1 11

(-6.2 i 2.3)E -1

(-8.2 i 2.9)E -1

( 0)

(-2.1 -

.9)E O

(-2.1 -

.9)E O

(-2.8 -

2.7)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

CS-137 ( 36) 15.

(

3.61

.3)E O 11

( 3.6 i

.3)E O

( 2.7 i

.4)E O I

( 0)

( !.4 -

5.6)E O

( !.4 -

5.6)E O

( 7.5 - 78.2)E -1

  • ( 13/ 18)*
  • ( 13/ 18)*
  • (

6/ 18)*

BA-140 ( 36) 15.

( -5.31 2.2)E -1 11

(-5.3 i 2.2)E -1

(-6.1 i 2.9)E -1 I

( 0)

(-2.7 -

.7)E O

(-2.7 -

.7)E O

(-3.9 -

1.0)E O

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

I CE-141 ( 36)

( -1.41 4.3)E -1 21

( 5.2 i 4.9)E -1

( 5.2 i 4.9)E -1

( 0)

(-3.0 -

4.4)E O

(-2.9 -

4.0)E O

(-2.9 -

4.0)E 0

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

CE-144 ( 36)

(

-3.6 15.3)E -1 11

(-3.6 i 15.3)E -1

(-6.2 i 16.7)E -1

( 0)

(-1.4 -

.8)E 1

(-1.4 -

.8)E 1

(-1.6 -

1.4)E 1

  • (

0/ 18)*

  • (

0/ 18)*

  • (

0/ 18)*

I

  • NON-ROUTINE REFER? TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERACE BACKGR')UND FOR THE PERIOD OF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS I

(I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

3-54

FIGURE III-K-1 COT' CENTRA'rIONS OF Cs-137 IN MILK I

~

I a

I 8

I 8

I E

4 3

- b I

I a

55 yn l

G5 g

(

00 b

~

I 4

e e

i 6

6 W8801DI / S3I80000Ici E

l I

3-55

FIGURE III-K-2 CONCENTRATIONS OF Sr-90 IN MILK I

I I

a I

I I

I I

yB I

4 zz 00 E

DO

~

I g

I 4

a e

4 ElBS01DI / S3I80003Ici l

3-56

IfI.L. Cranberries I

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 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 in Table III-L-1.

The only man-made radionuclide detected was Cs-137 which appeared in the Manomet Point Bog sample (collected on 9/24/85).

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

The results of this study are published in the 1978 Environmental Radiation Monitoring Program Report No. 11.

This report identi-fied fallout from previous nuclear weapons testing as the primary source of cesium in cranberries.

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

I I

I g

I

TABLE III-L-1 ERMAP RESULTS-CRANBERRIES I

EDIUM: CRANBERRIES UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST EAN CCNTROL STATICtG futunuuuene unneenueneutu+ue en*uentuun I

RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-h0JTINE)*

LLD NO. DETECTED **

NO.

NO. DETECTED **

NO. DETECTED **

BE-7 ( 3)

(

1.it

.7)E 2 13

( 1.8 i

.8)E 2

( 1.5 t 7.8)E 1 I

( 0)

( 4.5 - 18.1)E 1

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

K-40 ( 3)

(

5.0i

.5)E 2 23 ( 7.6 t 1.6)E 2

( 7.6 i 1.6)E 2 I

( 0)

( 4.5 -

5.6)E 2

  • (

2/ 2)*

  • (

1/ 1)*

  • (

1/ 1)*

PN-54 ( 3) 130.

( -2.51

.3)E O 23 ( 8.9 t 8.2)E O

( 8.9 i 8.2)E O

( 0)

(-2.8 -

-2.1)E O

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

CO-58 ( 3) 130.

(

6.3t 8.7)E O 14

( !.5 i 1.0)E 1

( 3.0 i 8.7)E O

( 0)

(-2.5 - 15.0)E O

  • ( 0/ 2)*
  • (

0/ 1)*

  • ( 0/ 1)*

FE-59 ( 31 260.

( -4.91 21.9)E O 23

( !.7 i 1.6)E 1

( 1.7 t 1.6)E 1

( 0)

(-2.7 -

1.7)E 1

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

CO-60 ( 31 130.

(

4.3t 8.3)E 0 13

( 1.3 i 1.2)E 1

(-7.4 i 12.6)E O

( 0)

(-4.1 - 12.6)E O I

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

ZN-65 ( 31 260.

( -1.41

.1)E 1 13

(-1.3 i 1.7)E 1

(-1.8 f 1.8)E 1 I

( 0)

(-1.5 -

-1.3)E 1

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

I ZR-95 ( 3)

(

!.51 1.4)E 1 13

( 2.9 i 1.4)E 1

(-2.1 f 1.7)E 1

( 0)

( 1.5 - 29.4)E O

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

RU-103 ( 3)

( -2.5

.1)E O 23

( 5.0 i 9.4)E O

( 5.0 i 9.4)E O

( 0)

(-2.6 -

-2.3)E O

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

  • NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE EASLREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERACE BACrGROUND FOR THE PERIOD OF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS I

(I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*,

1,-

3-58

I TABLE III-L-1 (CONTINUED)

EDIUM: CPANBERRIES UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS unun***uutu

      • uneen***uen**ue*

fuen****nuu RADIONUCLIDES EAN EAN EAN (N0. ANALYSES) REQUIRED RANGE STA.

RANCE RANGE (NON-ROUTINE)*

LLD NO. DETECTED **

NO.

NO. DETECTEDu NO. DETECTEDu RU-106 ( 3)

( -2.5i 51.8)E O 13 ( 4.9 i 5.5)E 1

(-1.5 i 7.5)E 1 I

( 0)

(-5.4 -

4.9)E 1

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

I-131 ( 3) 80.

( -5.01 4.8)E 1 13

(-2.3 29.1)E O

(-4.0 t 4.3)E 1 I

( 0)

(-9.8 -

.2)E 1

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

CS-134 ( 3) 80.

( -2.01

.5)E O 14

(-1.5 i 8.2)E O

(-1.4 i 1.0)E 1

( 0)

(-2.5 -

-1.5)E O

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

CS-137 ( 3) 80.

(

1.21 1.1)E 2 13

( 2.3 i

.2)E 2

(-4.6 i 9.2)E O

( 1)

( 3.3 - 230.0)E O

  • (

1/ 2)*

  • (

1/ 1)*

  • (

0/ 1)*

BA-140 ( 3)

( -3.31 3.3)E O 23

( 1.4 t 2.0)E 1

( 1.4 t 2.0)E 1

( 0)

(-6.5 -

0.0)E O

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

CE-141 ( 3)

( -8.0i 144.0)E -1 13

( 1.4 i 1.4)E 1

( 8.1 1 15.7)E O I

( 0)

(-1.5 -

1.4)E 1

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

CE-144 ( 3)

( -2.61 2.9)E 1 14

( 2.3 i 47.51E 0

(-3.7 i 4.8)E 1 I

( 0)

(-5.5 -

.2)E 1

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

I TH-232 ( 3)

(

7.21 1.0)E 1 23

( 8.6 i 3.8)E 1

( 8.6 i 3.8)E 1

( 0)

( 6.2 -

8.3)E 1

  • (

0/ 2)*

  • (

0/ 1)*

  • (

0/ 1)*

I

  • NON-ROUTINE REFERS TO TE NUMBER OF SEPfRATE EASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE A'ERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYEES YIELDING DETECTABLE MEASUREENTS (I.E. >3 STD CEV!ATIONS) IS INDICATED WITH *(

)*.

I

~

I 3-ee

III.M. Vegetation 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 - H), the Work Residence (0.6 mi - ESE), the Jenkins Residence (1.0 mi-SE), and the Whipple Farm (1.5 mi - SSH).

The only nuclides observed (other than naturally occurring Be-7, AcTh-228 (peak) and K-40) was Cs-137 and Co-60. Posi tive measurements of Cs-137 were detected in a vegetation sample from the Work Residence (lettuce, collected 10/03/85) and from the Whipple Farm (vegetable leaves, collected on 10/03/85).

In addition, positive measurements of Co-60 were detected in the vegetation sample from the Whipple Farm and in the vegetation sample (vegetable leaves, collected on 10/3/85) from the Malmgren Residence.

Both the Whipple Farm (SSW) and the Malmgren Residence (H) are in the same quadrant.

The Co-60 measurements, and most likely the Cs-137 measurement at the Whipple Farm, were due to controlled releases from PNPS-1.

The second positive measurement l

of Cs-137 is at the Work Residence (ESE).

This location is in a different quadrant from the above locations with Co-60 measurements.

The absence of Cs-134 at this location and the fact i

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.

Therefore, there was no significant environmental impact observed in vegetation as a result of the operations of PNPS-1.

3-60 l

I TABLE III-M-1 ERMAP RESULTS-VEGETATION I

EDIUM: FOOD CROP UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS eteneee***,seeeten e**estese****iseeeeeeeee,

      • ete**********

RADIONUCL! DES MEAN MEAN EAN (NO. A % LYSES) REQUIRED RANCE STA.

RANCE RANCE (NON-ROUTINEle LLD NO. E TECTEDee NO.

NO. DETECTED **

NO. DETECTEDee BE-7 ( 4)

( -6.4i

.9)E 1 27

(-4.3 i 8.3)E 1

(-4.3 i 8.3)E 1 I

( 0)

(-7.3 -

-5.5)E 1

(-1.3 -

.4)E 2

(-1.3 -

.4)E 2

  • (

0/ 2)*

  • (

0/ 2)*

  • (

0/ 2)e K-40

( 4)

(

1.6i

.3)E 3 27

( 2.3 i

.2)E 3

( 2.3 i

.2)E 3

( 0)

( 1.3 -

2.0)E 3

( 2.0 -

2.5)E 3

( 2.0 -

2.5)E 3

  • (

2/ 2)*

  • (

2/ 2),

  • (

2/ 2),

MN-54 ( 4) 130.

( -4.81 2.3)E O 27

( 4.3 i 3.5)E O

( 4.3 i 3.5)E O

( 0)

(-7.1 -

-2.4)E O

( 7.8 - 77.5)E -1

( 7.8 - 77.5)E -1 J

  • (

0/ 2)e

  • (

0/ 2),

  • (

0/ 21e CO-58 ( 41 130.

(

5.3i 9.6)E O 11

( 5.3 i 9.6)E O

(-2.2 i 3.4)E O

( 0)

(-4.3 - 14.9)E O

(-4.3 - 14.9)E O

(-5.6 -

1.2)E O

  • (

0/ 2)*

  • (

0/ 21e

  • ( 0/ 2)*

FE-59 ( 4) 260.

(

2.0i 1.5)E 1 11

( 2.0 i 1.5)E 1

(-5.6 i 8.6)E O

( 0)

( 5.5 - 35.2)E O

( 5.5 - 35.2)E O

(-1.4 -

.3)E 1

  • (

0/ 2)*

  • (

0/ 2)*

  • ( 0/ 2)*

C0-60 ( 4) 130.

(

2.Si 8.0)E O 11

( 2.8 i 8.0)E O

( 1.2 i 1.8)E O

( 0)

(-5.2 - 10.8)E O

(-5.2 - 10.8)E O

(-6.7 - 30.0)E -1

  • (

0/ 21e

  • (

0/ 2)*

  • (

0/ 2)*

ZN-65 ( 4) 260.

( -2.11 2.4)E 1 27

(-2.0 1 13.0)E O

(-2.0 t 13.0)E O

( 0)

(-4.5 -

.3)E 1

(-1.5 -

1.1)E 1

(-1.5 -

1.1)E 1

  • (

0/ 2)*

  • (

0/ 2)*

  • (

0/ 2)+

ZR-95 ( 4)

(

7.52 5.4)E O 11

( 7.5 i 5.4)E O

(-1.6 i 1.0)E 1

( 0)

( 2.2 - 12.9)E O

( 2.2 - 12.9)E O

(-2.6 -

.6)E 1

  • (

0/ 2)*

  • (

0/ 2)*

  • (

0/ 2)*

RU-103 ( 4)

( -4.21 6.2)E O 11

(-4.2 i 6.2)E O

(-1.5 i

.2)E 1

( 0)

(-1.0 -

.2)E 1

(-1.0 -

.2)E 1

(-1.7 -

-1.3)E 1

  • (

0/ 2)*

  • (

0/ 2)*

  • ( 0/ 2)*
  • NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE EASUREMENTS WHICH WERE GREATER TMN TEN (10) TIMES THE AVERAGE BACKC#END FOR THE PERIOD OF THE REPORT.
    • THE FRACTION CF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*,

E,-

3-61

TABLE III-M-1 (CONTINUED)

EDIUM: FOOD CR0P UNITS: PCI/KG WET INDICATOR STATIMS STATI@' WITH HIGHEST EAN CONTROL STATIONS (lffffffffffffffff Iffffffffffffffffffff4fff efffffffffffffff RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-RLUTINE)f LLD NO. DETECTEDif NO.

NO. DETECTEDff NO. DETECTEDff R'J-106 ( 4)

( -8.51 124.5)E O 27 ( 2.0 t 3.2)E 1

( 2.0 i 3.2)E 1

( 0)

(-1.3 -

1.2)E 2

(-1.3 -

5.2)E 1

(-1.3 -

5.2)E 1 e( 0/ 214

  • (

0/ 21e f( 0/ 21f I-131 ( 4) 80.

( -2.3t 1.1)E 1 27 ( 3.8 i 2.9)E O

( 3.8 i 2.9)E O

( 0)

(-3.3 -

-1.2)E 1

( 8.9 - 67.4)E -1

( 8.9 - 67.4)E -1

  • (

0/ 2)f

  • (

0/ 2)*

  • (

0/ 2)f CS-134 ( 4) 80.

( -S.it 8.8)E O 27

(-5.8 4.0)E O

(-5.8 i 4.0)E O

( 0)

(-1.7 -

.1)E 1

(-9.8 -

-1.7)E O

(-9.8 -

-1.7)E O

  • (

0/ 2)f

  • (

0/ 2)e f( 0/ 2)f CS-137 ( 4) 80.

( -1.5t 2.6)E O 27 ( 7.5 i 5.0)E O

( 7.5 i 5.0)E O

( 0)

(-4.1 -

1.1)E O

( 2.6 - 12.5)E O

( 2.6 - 12.5)E O

  • (

0/ 2:e

  • (

0/ 2)*

  • (

0/ 215 BA-140 ( 4)

( -2.31 1.8)E 1 27 ( 6.1 *

.4)E O

( 6.1 f

.4)E O

( 0)

(-4.1 -

.6)E 1

( 5.7 -

6.5)E O

( 5.7 -

6.5)E 0 f( 0/ 215

  • (

0/ 2)f f( 0/ 214 CE-141 ( 4)

(

9.0f 7.2)E O 27 ( 1.5 i 1.5)E 1

( 1.5 t 1.5)E 1

( 0)

( 1.8 - 16.2)E O

( 5.5 - 297.0)E -1

( 5.5 - 297.0)E -1 f( 0/ 2)f

  • (

0/ 2)*

  • (

0/ 2)e CE-144 ( 4)

(

3.01 5.3)E 1 27 ( 3.1 i 4.4)E 1

( 3.1 i 4.4)E 1

( 0)

(-2.3 -

8.3)E 1

(-1.3 -

7.5)E 1

(-1.3 -

7.5)E 1

  • (

0/ 214

  • (

0/ 21e

  • (

0/ 2)*

TH-232 ( 4)

(

1.it 2.3)E 1 27 ( 3.4 i 3.0)E 1

( 3.4 t 3.0)E 1

( 0)

(-1.2 -

3.4)E 1

( 3.2 - 64.0)E O

( 3.2 - 64.0)E O

  • (

0/ 215

  • (

0/ 215 f( 0/ 2)f I

  • NON-ROUTIE REFERS TO THE iMBER OF SEPARATE EASUREENTS WHICH WERE CREATER THAN TEN (10) TIMES THE AVERACE BACKGROUND FOR THE PERIOD OF TE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YIELD!t0 DETECTABLE MEASUREENTS (I.E. >3 STD DEVIATI0r! IS INDICATED WITH *(

)f.

I k

3-62

I TABLE III-M-1 (CONTINUED)

EDILM: OREEN LEAFY VEGETABLE LNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTRJ. STATIONS eeeeeteteeseeee***

eteeeeeeee************ eve ettee***eette***

RADIONLCt.!EES EAN EAN EAN (NO. ANALYSES) REQUIRED RANCE STA.

RANGE RANGE (NON-ROUTINE)*

LLD NO. DETECTED **

NO.

NO. DETECTEDet NO. DETECTEDee RU-106 ( 6)

( -1.4i 2.9)E 1 16 ( 9.6 i 5.6)E 1

(-9.7 i 49.5)E O I

( 0)

(-7.1 -

9.6)E 1

  • (

0/ 5)e

  • (

0/ 11e e( 0/ 1)*

I-131 ( 6) 80.

( -1.81 5.0)E O 16

( 1.6 i 1.2)E 1

(-1.7 f 1.9)E 1

( 0)

(-1.3 -

1.6)E 1 ei 0/ 5)*

  • (

0/ 1)e

  • (

0/ 1)*

I CS-134 ( 61 80.

( -2.4t 3.0)E O 11

( 7.0 i 5.5)E O

(-4.8 i 7.8)E O

( 0)

(-1.1 -

.7)E 1

?

  • (

0/ 5)*

  • (

0/ 1)*

  • (

0/ lie CS-137 ( 6) 80.

(

2.?f

.9)E 1 16 ( 5.7 i

.8)E 1

( 8.0 t 6.7)E O

( 0)

( 3.8 - 56.6)E 0

  • (

2/ 5),

  • (

1/ 1)e

  • (

0/ 1)*

BA-140 ( 6)

( -1.71

.4)E 1 27

( 1.9 i 13.9)E O

( !.9 i 13.9)E O

( 01

(-2.7 -

.5)E 1

  • (

0/ 5)*

  • (

0/ 1)*

  • (

0/ 1),

CE-141 ( 6)

(

1.li

.7)E 1 16 ( 2.8 i 1.0)E 1

(-1.5 i 1.1)E 1

( 0)

(-1.0 -

2.8)E 1

  • (

0/ 5)e et 0/ 1)*

e( 0/ 1)e CE-144 ( 6)

( -8.31 12.9)E O 76

( 2.7 i 3.2)E 1

(-8.7 i 37.3)E O

( 0)

(-4.0 -

2.7)E 1

  • (

0/ 5)e

  • (

0/ 1)e e( 0/ lie TH-232 ( 6)

(

2.01 1.3)E 1 43

( 6.9 i 2.8)E 1

( 5.7 i 3.5)E 1

( 0)

(-2.6 - 69.5)E O

  • (

0/ 5)*

e( 0/ 1)e

  • (

0/ 1)*

I e NCtJ-ROUTINE REFERS TO TE NLMBER OF SEPARATE EASURETNTS WHICH WERE GREATER THAN TEN (10) TIMES THE A'FAGE BACK0ROUND FOR THE PERIOD OF THE REPORT.

en THE FRACTION OF SA"PLE ANtLYSES YIELDINO DETECTABLE MEASUREENTS I

(I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

~

+-

3-63

l TABLE III-M-1 B

(CONTINUED)

EDIUM: (EEEN LEAFY VEGETABLE UNITS: PCI/KG WET INDICATOR STATICNS STATION WITH HIGHEST MEAN CONTROL STATIONS

                  • ee++e****
            • es***ee*****et<4ent e***eese********

RADIONUCLIDES EAN MEAN MEAN (NO ANALYSES) RE M RED RANGE STA.

RANGE RANCE (NON-ROUTINE)*

LLD NO DETECTED **

NO.

NO. DETECTED **

NO. DETECTED **

BE-7 ( 6)

(

4.1*

1.2)E 2 75 ( 6.1 i

.8)E 2

( 2.5 i

.7)E 2

( 0)

(-3.0 - 61.1)E 1 e( 4/ 5)*

  • (

1/ 1)*

  • (

1/ 1)*

K-40

( 6)

(

2.71

.3)E 3 16 ( 3.4 i

.2)E 3

( 2.0 i

.2)E 3

( 0)

( !.6 -

3.4)E 3

  • (

5/ 5)*

  • (

1/ 1)*

a( 1/ 1)*

PN-54 ( 6) 130.

( 9.91 31.6)E -1 16 ( 9.8 1 7.3)E O

( 4.0 t 6.7)E O

( 0)

(-6.2 -

9.8)E O J

a( 0/ 5)*

  • (

0/ 1)*

et 0/ 1)*

CO-58 ( 6) 130.

(

2.71 3.5)E O 43 ( 9.8 i 6.9)E O

(-6.9 i 7.2:E O

( 0)

(-1.0 -

1.0)E 1

  • (

0/ 5)*

  • (

0/ 1)*

  • ( 0/ 1)*

FE-59 ( 6) 260.

(

2. 6i 3.9)E O 76 ( 1.5 t 1.512 1

( 5.8 i 16.6)E O

( 0)

(-5.1 - 15.5)E O

  • (

0/ 5)e

  • (

0/ 1)*

  • ( 0/ 1)*

CO-60 ( 6) 130.

(

!.91 1.2)E 1 43 ( 5.1 i

.9)E 1

( 3.0 i 10.6)E O

( 0)

(-1.6 -

5.1)E 1 e( 2/ 5)e

  • (

1/ 1)*

  • (

0/ 1)*

ZN-65 ( 6) 260.

( -2.5i 10.01E O 11

( 2.0 f 1.2)E 1

(-1.5 1.7)E 1

( 0)

(-2.5 -

2.1)E 1

  • (

0/ Sie

  • (

0/ 1)*

  • (

0/ 1).

I ZR-95 ( 6)

(

3.61 5.9)E O 16 ( 2.4 i 1.3)E I

( !.2 i 1.4)E 1

( 0)

(-9.1 - 24.5)E 0

  • (

0/ 5)*

  • (

0/ 1)*

  • ( 0/ 1)*

RU-103 ( 6)

( -3.6t 25.1)E -1 16 ( 5.8 i 6.8)E O

(-1.5 i

.7)E 1

( 0)

(-8.4 -

5.8)E 0

  • ( 0/ 5)*
  • (

0/ 1)*

  • ( 0/ 1)*

e NON-ROUTINE REFERS TO THE NltfBER OF SEPARATE MEASLREMENTS WHICH WERE CftEATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

    • THE FRACTION OF SAMPLE ANALYSES YIELDING [ETECTABLE MEASUREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH a(

le.

~

3-64

III.N. Forage Beef forage is collected from three locations annually: the Plymouth County Farm (3.5 ml - H - Station Number 11), Whitman Farm (21 mi - NH

- Station 21) and Bridgewater Farm (20 mi - H - Station 27)._

The beef forage sample from Station #27 was unavailable during 1985.

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

The following positive measurements were made:

Be-7, Cs-137, AcTh-228 (peak) and K-40 at the Plymouth County Farm; and, Be-7, AcTh-228 (peak) and K-40 at the Whitman Farm.

The only positive measurement of Cs-137 occurred at the Plymouth County Farm.

The Plymouth County Farm is an indicator station and is located 3.5 miles - H from PNPS-1.

The absence of Cs-134 at this location and the fact that the measured Cs-137 concentration is about 10,000 times what would be expected at this location based on releases from PNPS-1.

This strongly indicates that fallout from previous atmospheric weapons testing, not PNPS-1, is the primary source of this Cs-137 Therefore, it is extremely unlikely that there was any environmental i

impact on forage due to the operation of PNPS-1.

3-65 I

TABLE III-N-1 ERMAP RESULTS-FOPAGE I

EDIUM: CATTLE FEED UNITS: PCI/KG WCT INDICATOR STATIONS STATION WITH HIGFEST EAN CONTROL STATIONS e************e**ee seeeeeeeeeeeeeeeeeeeeeene ee***eeee***eene RADICNJCLIDES EAN MEAN EAN (N0. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTINE),

LLD NO. DETECTED ++

N0.

NO. DETECTEDee NO. DETECTEDee I

BE-7 ( 2)

(

!.it

.1)E 3 11

( 1.1 i

.1)E 3

( 8.2 i 1.1)E 2 I

( 0)

  • (

1/ 1)*

  • (

1/ 1),

  • (

1/ 1)*

K-40 ( 2)

(

9.2f

.4)E 3 21

( 1.4 i

.0)E 4

( 1.4 i

.0)E 4 I

( 0)

  • (

1/ 1)e

  • (

1/ 1)*

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

( -2.4t 1.2)E 1 21

( 8.0 i 11.9)E O

( 8.0 t 11.9)E O

( 0)

  • (

0/ 1).

  • (

0/ 1)e

  • (

0/ 1)*

CO-58 ( 2) 130.

(

9.61 13.5)E O 11

( 9.6 i 13.5)E O

( 7.0 i 10.7)E O

( 0)

  • (

0/ 11e

  • (

0/ 1)*

  • (

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

( -2.!t 32.4)E 0 11

(-2.1 i 32.4)E O

(-3.1 i 3.2)E 1

( 0)

  • (

0/ 1)e

  • (

0/ 1)*

  • (

0/ Ile C0-60 ( 2) 130.

( -8.6t 19.4)E O 11

(-8.6 i 19.4)E O

(-1.7 t 1.8)E 1

( 0)

  • (

0/ 11e

  • ( 0/ 1)*

et 0/ 1)*

ZN-65 ( 2) 260.

( 6.31 33.4)E O 21

( 2.0 t 3.4)E 1

( 2.0 t 3.4)E 1 I

( 0)

  • (

0/ Ile

  • (

0/ 1),

  • ( 0/ 1)*

IR-95 ( 2)

(

4.0i 2.6)E 1 21

( 4.3 i 2.4)E 1

( 4.3 t 2.4)E 1

( 0)

  • (

0/ 1)*

  • (

0/ 1)*

  • (

0/ 1),

RLh103 ( 21

(

2.!t 14.0)E O 21

( 2.0 i 1.4)E 1

( 2.0 i 1.4)E 1

( 0)

  • ( 0/ 1)*
  • (

0/ 1)e

  • (

0/ 1)e

  • NON-R1)TIfE REFERS TO THE NJMBER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGRCOND FC6 THE PERIOD OF THE REPORT.

en THE FRACTICN OF SAMPLE ELYSES YIELDING DETECTABLE MEASUREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

3-66

l5 TABLE III-N-1 (CONTINUED)

EDIlN: CATTLE FEED UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS memememm

    • m *** m e m *** m m e
    • m m
  • m e m RADIONUCLIDES EM MEAN EAN (N0. ANALYSES) REQUIRED RAN3E STA.

RANGE RANGE (NON-ROUTINE)*

LLD NO. DETECTED **

h9.

NO. DETECTED **

NO. DETECTED **

I RU-106 ( 2)

(

!.11 1.0)E 2 11

( 1.1 i 1.0)E 2

(-1.0 f 1.1)E 2 I

( 0)

  • ( 0/ 1)*
  • (

0/ 1)*

  • ( 0/ 1)*

j I-131 ( 2) 80.

( -5.6i 6.2)E 1 21

(-1.4 i 5.8)E 1

(-1.4 t 5.8)E 1 E

( 0)

  • (

0/ 1)*

  • (

0/ 1)*

  • (

0/ 1)*

CS-134 ( 2) 80.

(

4.0t 1.5)E 1 11

( 4.0 t 1.5)E 1

(-3.1 i 12.3)E O

( 0)

  • (

0/ 1)*

  • ( 0/ 1)*
  • ( 0/ 1)*

CS-137 ( 2) 80.

( 6.3t 1.3)E 1 11

( 6.3 i 1.3)E 1

( 1.5 i 1.2)E 1

( 1)

  • (

1/ 1)*

  • (

1/ 1)*

  • (

0/ 1)*

BA-140 ( 2)

(

3.5t 3.7)E 1 11

( 3.5 t 3.7)E 1

(-3.5 i 3.8)E 1

  • ( 0/ 1)*
  • (

0/ 1)*

  • ( 0/ 1)*

M-141 ( 2) i 2.61 2.4)E 1 21

( 4.7

  • 2.0)E 1

( 4.7 i 2.0)E 1 I

( 0)

  • (

0/ 1)*

  • (

0/ 1)*

  • (

0/ 1)*

CE-144 ( 2)

(

2.31 6.6)E 1 21

( 7.0 i 5.7)E 1

( 7.0 i 5.7)E 1 I

( 0)

  • (

0/ 1)*

  • (

0/ 1)*

  • (

0/ 1)*

I TH-232 ( 2)

(

!.01 1.0)E 2 21

( 1.2 i

.5)E 2

( !.2 i

.5)E 2

( 0)

  • ( 0/ 1)*
  • ( 0/ 1)*
  • (

0/ 1)*

I

  • NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES THE AVERACE BACKGROUND FOR THE PERIOD OF THE REPORT.
    • THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE EASUREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

I 3-67

IV.

References I

1.

Regulatory Guide 1.109 - CALCULATION OF ANNUAL DOSES TO MAN FROM ROUTINE RELEASES OF REACTOR EFFLUENTS FOR THE PURPOSE OF EVALUATING COMPLIANCE WITH 10 CFR PART 50, APPENDIX _I -

Revision 1, October 1977.

I 2.

SETTLEMENT AGREEMENT BETWEEN MASSACHUSETTS WILDLIFE FEDERATION AND BOSTON EDISON COMPANY RELATING TO 0FFSITE RADIOLOGICAL MONITORING - June 9, 1977.

I 3.

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

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

I 4.

Memorandum, Yankee Atomic Electric Company, 1985 Annual Direct Radiation Survey, REG 146/85, July 1985, E. R. Cumming.

I 5.

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

I 6.

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

I I

I 4-1

~

__.m I

I I

I I

i APPENDIX A - ANOMALOUS MEASUREMENT REPORTS I

.I I

I I

I

' I I

I I

g lI l

I I

I I

' I I

I J

There were no Anomalous Measurement Reports I

for the year 1985.

I

. I I

I I

1 I

A-2

I I

I I

I I

I APPENDIX B - Radioactive Effluents I

I E-

'I I

4I

,I

,g I

B-1 I

l I

I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I

Supplemental information JANUARY - JUNE 1985 l

Facilits Pilgrim Nuclear Power Station Ucensee DPR 35 I

1.

Regulatory Umsts Qs

+ Qv a.

Fission and activation gases 0.25/E 0.10/E d-1 I

Particulates. half-lives >N da>s-13(Qs x1.8E4+Qv x 1.8E5) g 1 b.

iodines 2 Ci/ Quarter s.

d.

L; quid ellluents I.

2.

Masimum Permissible Concentration Provide the MPCs u>ed m determining allowable relea>c raies or son 6entrainins.

Fissam and astivatmn gases to CFR 20 2.

h.

lodines.

Appendit B c.

Partisulaies. half.hves >A day s Table II d.

Liquid etiltenis H - 3 = 1 X I0-5 pCi/mt:att rest,10 CFR 20, Appendix B. Table II a

3.

Average Energv Provide the average enerFy (U o: he radionuchde siiisitise in selease os tissioni and activation gases. it appin:able E = i Me, 2

1st Quarter, Qs = 0.75 7 & Q v = 0.420 2nd Quarter Qs = 0.323 & Qv = 0.536 4.

Measurements and Approsimations of Total Radioactivit)

Proside the methods u>ed in measure or appiosimaic the total radioactivii) in elfluents and the me h 45 used to deternune radenushde somposition.

a.

Fission and a iivation gases-c,ti I^

h.

lodines g

c.

Particulater J.

Liquid et11uents.

Analysis 5.

Batch Releases Pmude the sollowing information relating to hatsh relea>c3 us radioa.tive materials in hquid and gaseou> eitluent>.

a.

Uquid 1.

Number of batch releases:

186 2.

Total time period for hatch releases 293.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> I

.t. himum time peinid for a baich release - 8.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> 4 Average time period for batch seicases 1.5 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 5.

Minimum time penod los a hatch release -.33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> 6.

Average stream flow dunng penods of release of efiluent into a flommg stream. 2.81E5 GPM b.

Gaseous (Not Applicable) 6.

Abnormal Releases I

'{

None i

I E

k

[

2

I I

I TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I

GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES JANUARY - JUNE, 1985 I

Quarter Quarter Est. Total Unit Error. %

A. Fission and activation gases

1. Total release Ci 1.87E+3 8.22E+2 1 35.0 l
2. Average release rate for period gCi/sec 7397+7 3,nsp+7 I'
3. Percent of Technical Specification limit

?o 1.11E-1 4.34E-2 B. Iodines I

1. Totaliodine-131 Ci 43.03E-2 4 2. 77E-3 1 33.4 l
2. Average release rate for period gCi/sec 43.85E-3 4.3.52E-4
3. Percent of Technical Specification limit To 41.52

<0.139 C. Particulates

1. Particulates with half-lives > 8 days Ci 41.61E-3 41.49E-3 i 30.1 l

1

2. Average release rate for period gCi/sec 42.04E-4 41.90E-4
3. Percent of Technical Specification limit

?o 42.50E-2 4 2.71E-2

4. Gross alpha radioactivity Ci 6.48E-7 3.87E-7 D. Tritium
1. Total release Ci 9.65E-1 1.70E0 t 43.2 l
2. Average release rate for period pCi/sec 1.23E-1 2.16E-1 5
3. Percent of Technical Specification limit

?o I

I I

g 3

TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985 )

GASEOUS EFFLUENTS - ELEVATED RELEASE I

JANUARY - JUNE 1985 CONTINUOUS MODE BATCH MODE l Nuclides Released l

Unit l

Quarter l

Quarter l

Quarter l

Quarter l

1 2

1. Fission gases krypton-85 Ci 4.12E-3 1.?OF-2 krypton-85m Ci 3.02E+2 1.33E+2 krypton-87 Ci 1.56E+2 1.46E+1

l krypton-88 Ci 4.75E+2 1.24E+2 5 W xenon-133 Ci 5.56E+2 5.08E+2 I o xenon-135 Ci 1.47E+2 1.97E+1 xenon-135m Ci s_n7Fn xenon-138 C;

2.64E+1 u.

xenon-131m Ci xenon-137 Ci yi e renon-133m Ci 7.61E0 2.12E0 Total for period Ci 1.68E3 8.01F2 r'

2. Iodines

-ll 3

iodine-131 Ci 41.33E-3

41. 74E-3 iodine-133 Ci 47.10E-3 9.81E-3 6

iodine-135 Ci 41,56E-2 1.14E-2 fg Total for period Ci

42. 41E-2 4 2.33E-2
3. Particulates 2

strontium-89 Ci 2.44E-4 8.79E-5 strontium-90 Ci 1.11E-6 7.48E-7 cesium-134 Ci 2.29E-7 I

cesium-137 Ci 46.01E-5 42.40E-5 barium-lanthanum-140 Ci 4t_nny_t 2 g,r-s chromium-51 Ci 1.07E-6 I

manganese-54 Ci 3.40E-6 cobalt-58 Ci iron 59 Ci cobalt-60 Ci

41. 3 6E-4 4 1. 55E-4 zinc-65 Ci zirconium-niobium-95 Ci I

cerium.141 Ci cerium-144 Ci ruthenium 103 Ci g

3 ruthenium-106 Ci 4

I TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ( 1984 GASEOUS EFFLUENTS - GROUND LEVEL RELEASE-JANUARY - JUNE, 1985 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission gases i

krypton 85 Ci krypton-85m Ci 43.83E0 4 8.7E-1 krypton-87 Ci 4 7.99E0 41.82E0 krypton-88 Ci 41.22E+1 4 2.69E0 t'

xenon-133 Ci 49.27E0 43.14E0 xenon-135 Ci

41. 64E+2 41.21E+1 l

zenon-135m Ci t

zenon-138 Ci Total for period Ci 4 1. 9 7E+2 42.06E+1

2. Iodines iodine-131 Ci 4 2.90E-2

'1.03E-3 iodine-133 Ci 4 9.62E-2 48.58E-3 iodine-135 Ci 4 3.18E-3 46.83E-3 Total for period Ci 4 4. 43E-3

41. 64E-2 l
3. Particulates

)

strontium 89 Ci 2.93E-4 1.llE-4 I

strontium-90 Ci 6.28E-7 5.84E-7 cesium 134 Ci 2.65E-6 3.28E-6 cesium-137 Ci 4 1.37E-4 1.35E-4 barium-lanthanum-140 Ci 41.88E-4 3.79E-4 manganese 54 Ci cobalt-58 Ci iron-59 Ci cobalt-60 Ci 4 1.3 6E-4 4 2.15E-4 l

zinc-65 Ci zirconium-niobium-95 Ci I

cerium-141 Ci 6.37E-6 ruthenium-103 Ci ruthenium-106 Ci I

s

I I

I TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ([985 )

l LIQUID EFFLUENTS SUMMATION OF ALL RELEASES JANUARY - JUhT 1985 h

I.

Quarter Quarter Est. Total Unit 1

2 Error, %

4 A. Fission and activation products

1. Total release (not including tritium, Ci 3.76E-1 6.19E-1

+ 30.0 noble gases, or alpha)

2. Average diluted concentration gCi/ml L'

3.33E-8 8.39E-8 during period

3. Percent of applicable limit 0.376 0.619 O

B. Tritium

1. Total release Ci 1.75E0 2.61E0 I 32.5
2. Average diluted concentration yCi/ml during period 1.55E-7 3.25E-7
3. Percent of applicable limit 1.55 3.25 C. Dissolved and entrained gases 3
1. Total release Ci 5.07E-2 1.09E-2
  • 35.0
2. Average diluted concentration gCi/mi 4.49E-9 1.54E-9 Ls during period
3. Percent of applicable limit I

D. Gross alpha radioactivity l

1. Total release l

Ci l 4?.ov-4 l41.sar-4 l I 40.0 l

E. Volume of waste released (prior liters 4.69E6 2.95E6 I 20.0

(

to dilution)

F. Volume of dilution water used liters I 20.0 1.13E10 7.38E7 during period I

I g

6

JANUARY - JUNE 1985 I

TABLE 28 EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT (1985)

I LIQUID EFFLUENTS JANUARY - JUNE, 1985 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter i

Quarter 2 strontium-89 Ci 41.72E-4 41.17E-4 strontium-90 Ci 41.12E-4 4 4.09E-5 cesium-134 Ci 9.94E-3

2. 89E-4 I-cesium-137 Ci 1.68E-1 1.20E-4 iodine-131 Ci 4.73E-4 6.30E-4 cobalt 58 Ci 33tp_3 c, q a p_g, I

cobalt-60 Ci 1.16E-1 5.81E-1 iron-59 Ci l

zinc 65 Ci 8.23E-5 manganese-54 Ci 6.88E-3 2.74E-4 c.

chromium 51 Ci 2.51E-5 2.82E-4 zirconimum niobium-95 Ci 1.56E-6 molybdenum 99-technetium 99m Ci 1.83E-4 barium lanthanum-140 Ci 8.45E-5 cerium 141 Ci G

iodine-133 Ci 4.50E-3 2.31E-3 cerium-144 Ci 1.85E-5 silver 110m Ci iron-55 Ci 41.3 7E-2 4 4.07E-3 I

l unidentified l

Ci 5.48E-2 2.04E-2 Total for period (above)

Ci 3.78E-1 6.19E-1 xenon 133 Ci 1.39E-2 1.05E-3 xenon-135 Ci 3.68E-2 9.89E-3 g

l

I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information July - December 1985 Facihty Pdgrim Nuclear Power Station Ucenwe DPR.35 1.

Regulaton Umits

~

Os

+

Q Fission and activation pses. 25/g 0.lb/g

- I t

a.

8.

h>Jines 2Ci/Qtr

<. Parneuiaies. hair hses x Jas s 13(Qs x 1.8E4 + Qv x 1.8E5) T 1 J.

bquid elnuents 10Ci/Qtr 2.

Masimum Permissible Concentration Piovide the MPCs used m deiernunmg allowable release rates or uincentrations F ssam and activation pses 10 CFR 20 a.

b.

lodmes Appendix B Particulates. half-hves > JaD Table II v.

J.

Liquid et flueni s H. 3 = 1 X 101 pCi/ml; all rest,10 CFR 20 Appendix B, Table 11 3.

Average Energs Proude the average enerF) (U on the radninu,hde nustme m icleases of lission and activation pses. il appheable E = 3 Mew 4.

Measurements and Approsimations of Total Radmactmt3 Pronde lhe methods used to measure or approsnnate the total radniactiuty m etduents and the methods used to deternune radainu,hde composition a.

Fissam and a,tivation pses a,t; b.

lodines I P '

i L.

Parti ulaies d.

Liquid et nucm s:

Ana!> m 5.

Batch Releases PiouJe the following mformanon relating io hai h releases os raJina,ine material,in hquid and Faseous ei duents a.

Uquid I.

Number of batch releases 109 2 Toial time period for hatch releases 108 hrs.

A Maumum tm e pernid for a baich release - 3 17 hrs.

4.

Aserage time permd for hati.h icicases 0.99 firs.

5.

Minimum time penod foi a baich release -0.17 hrs.

6 Aserage stream now durmg periods of release of ef0uent mto a nowmg stream 3.14E5gpm i

b.

Gawous (Not Applicable) 6 6.

Abnormal Releases None s.

b.

N0ne e

2

I I

TABLE 1 A l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES I

July - December 1985 Quarter Quarter Est. Total i

Unit 3

4 Em, %

f A. Fission and activation gases

1. Total release Ci 3.29E2 2.38E2 35 l
2. Average release rate for period pCi/sec 4.18E1 3.03E1
3. Percent of Technical Specification limit 1.84E-2 1.37E-2 B. Iodines
1. Total iodine-131 Ci

<8.98E-3

< 6.00E-3 30 l

2. Average release rate for period uCi/sec

<1.14E-3

<7.62E-4

3. Percent of Technical Specification limit

<.449

<.300 I

C. Particulates

1. Particulates with half-lives > 8 days Ci 3.13E-3

<.2.55E-3 30 l

2. Average release rate for period gCi/sec 3.98E-4

<,3.24E-4

3. Percent of Technical Specification limit 7.10E-2

<. 6.39E-2

4. Gross alpha radioactivity Ci

<5.49E-7

< 4.67E-7 D. Tritium

1. Total release Ci 2.15E0 1.68E0 42 l
2. Average release rate for period pCi/sec 2.73E-1 2.13E-1
3. Percent of Technical Specification limit I

I I

I I

TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985 )

GASEOUS EFFLUENTS - ELEVATED RELEASE July - December 1985 I

CONTINUOUS MODE BATCH MODE l Nuclides Released l

Unit l

Quarter l

Quarter l

Quarter l

Quarter l

3 4

1. Fission gases krypton 85 Ci 7.66E-3 5.86E-3 krypton-85m Ci 4.52E1 2.29El krypton 87 Ci 1.23E0 krypton 88 Ci 2.46El 9.53E0 I

xenon-133 Ci 2.31E2 1.84E2 xenon 135 Ci 4.70E0 7.50E-1 I

xenon-135m Ci 2.36E-1 xenon-138 Ci 9.10E-1 xenon-131m Ci xenon-137 Ci xenon 133m Ci Total for period Ci 3.08E2 2.17E2

2. Iodines I~

iodine-131 Ci 43.31E-3

< 1.65E-3 iodine-133 Ci 1.70E-2 1.04E-2 iodine 135 Ci 1.78E-2 1.23E-2 Total for period Ci

< 3.81E-2 4 2.43E-2

3. Particulates strontium-89 Ci 1.3/t-4 5.40E-5 I

strontium-90 Ci 1.04E-6 4.25E-7 cesium-134 Ci 8.24E-7 cesium-137 Ci 3.78E-5 1.76E-5 barium-lanthanum-140 Ci 5.34E-4 2.49E-4 chromium-51 Ci manganese-54 Ci 3.11F-6 4.70F-6 cobalt 58 Ci iron-59 Ci I

cobalt-60 Ci 1.15E-4 1.21E-4 zine-65 Ci l

zirconium niobium 95 Ci l

cerium 141 Ci 2.11E-6 cerium 144 Ci ruthenio:r.103 Ci l

ruthenium-10G Ci 4

I I

TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT E985 )

GASEOUS EFFLUENTS - GROUND LEVEL RELEASE -

July - December 1985 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 3

4

1. Fission gases krypton-85 Ci krypton-85m Ci 9.50E-1 9.79E-1 krypton-87 Ci 2.11E0 2.30E0 krypton-88 Ci 2.82E0 3.03E0 xenon-133 Ci 2.45E0 4.32E0 I

xenon 135 Ci 1.31El 1.07El xenon-135m Ci xenon-138 Ci Total for period Ci 2.14E1 2.13E1

2. Iodines iodine-131 Ci R 67F 1

< d 1RF.1 iodine-133 Ci 5.00E-2 3.35E-2 I

iodine-135 Ci 6.31E-2 4 5.73E-2 Total for period Ci 1.19E-1

< 9.52E-2

3. Particulates strontium 89 Ci 1.95E-4 1.71E-4 strontium 90 Ci 1.29E-6 1.09E-6 cesium.134 Ci cesium 137 Ci 1.46E-4 41.07E-4 I

barium lanthanum-140 Ci 1.60E-3 1.39E-3 manganese-54 Ci 2.66E-5 1.30E-5 cobalt-58 Ci I

iron-59 Ci cobalt-60 Ci 2.80E-4 4.16E-4 zine-65 Ci zirconium-niobium 95 Ci cerium 141 Ci 5.15E-5 2.13E-6 ruthenium-103 Ci ruthenium 106 Ci I

s

I' TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

LIQUID EFFLUENTS SUMMATION OF ALL RELEASES July - December 1985 I

Quarter Quarter Est. Total Unit 3

4 Error, %

I A. Fission and activation products

1. Total release (not including tritium, Ci 1.20E-2 5.50E-2 30 noble gases. or alpha)
2. Average diluted concentration pCi/ml 3.88E-9 1.19E-8 during period
3. Percent of applicable limit 1.20E-1 5.50E-1 B. Tritium
1. Total release Ci 1.20E0 2.25E0 30
2. Average diluted concentration pCi/ml during period 3.88E-7 4.88E-7
3. Percent of applicable limit 3.88 4.88 C. Dissolved and entrained gases
1. Total release Ci 2.49E-3 3.54E-4 40 l
2. Average diluted concentration pCi/ml during period 8.06E-10 7.68E-11
3. Percent of applicable limit D. Gross alpha radioactivity I

l

1. Total release l

Ci l 5.23E-5 l<. 6,05 E-5 l

40 l

E. Volume of waste released (prior liters I

9.57E5 1.86E6 20 to dilution)

F. Volume of dilution water used liters during period 3.09E9 4.61E9 20 I

I e

TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

LIQUID EFFLUENTS July - December 1985 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter 3 Quarter 4 strontium 89 Ci 4 3.30E-5 4.2.33E-5 strontium 90 Ci 41.82E-5

< 2. 36E-4 cesium-134 Ci 1.07E-5 8.53E-4 cesium-137 Ci 1.44E-3 2 29E-2 iodine-131 Ci 5.14E-4 cobalt 58 Ci 2.46E-4 5.02E-7 cobalt-60 Ci 4.15E-3 2.05E-2 iron 5' Ci zine-65 Ci manganese-54 Ci 1.55E-4 3.33E-5 chromium-51 Ci 1.05E-5 3.85E-4 zirconimum niobium-95 Ci 1.34E-5 molybdenum 99-technetium 99m Ci I

barium-lanthanum.140 Ci 2.52E-4 5.30E-7 cerium 141 Ci 8.27E-4 iodine-133 Ci cerium-144 Ci silver 110m Ci iron 55 Ci 1.33E-3 l

unidentified l

Ci l

l 4.310 ~

8.70E-3 Total for period (above)

Ci 1.20E-2 5.50E-2 xenon 133 Ci 8.66E-4 xenon-135 Ci 1.62E-3 3.54E-4 l

l 7

a 1.mm..u_

.w.....m,~

m a

A

._--_m. - -

--.a-a-.

4.--

1 i

i l

l

'l iI 1

1 1,

~

l

'l I

I I

APPENDIX C - S0IL SURVEY I

l I e.

I I

I
I
I

.I

'I a

l l

.I 4

l l

1 l

4

.e-l I

i i

'ph o"c (* ' ') * ' 8 ' 00

';,1NKEE ATOMIC ELECTRIC COMPANY TWX 710-380-7619 07 ^

, s9

'Sg3

\\

1671 Worcester Road, Framingham, Massachusetts 01701 I

A kE E I

I I

February 6, 1986 EL 043/86 Christine Bowman Boston Edison Company 25 Braintree Hill Of fice 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,

% Au

b. C. Murray Environmental Laboratory cc:

B. Lunn (BECo)

I E. Cununing j

0. E. McCurdy C. L. Harrington E. L. Laurenzo I

I

INTRODUCTION I

In compliance with Boston Edison's Technical Specifications for Radiological Monitoring of the environment, M-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 M-situ analysis at that station.

METHODOLOGY h-situ gama spectrometry analysis is used to evaluate the presence of radionuclides in soil.

Using assumptions concerning the soil composition and 7

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 I'

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, a/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 surf ace, such as those f rom.

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

I (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 surface deposition, and laboratory analysis usually confirms that these radionuclides lI

are present throughout the first six inches of soil, implying a period of migration.

This procedure of h-situ gamma spectrometry is explained in detail in References 1 ar.d 2.

I 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 M-situ results.

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

When warranted, soil core samples were also taken and analyzed at the YAEL to confirm the presence of radionuclides in the soil which have been identified in the M-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.

.J RESULTS Tables 1-11 contain the results f rom the M-situ gama 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)

I 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 M-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 h-situ analysis and confirmed by Laboratory soil analy' sis.

The Co-60 concentration calculated by the M-situ methodology was 122.6 i 6.5 pCi/kg, assuming a value for a/p of 0.206, while laboratory soil analysis I

I

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

The value for a/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 M -situ methodology. Using an a/p of infinity, the M-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 can also be compared to the laboratory soil core analysis. An a/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 addition, the Cs-137 concentration of 154 i 14 pCi/kg calculated by the h situ methodology is in agreement with the top core section result of 200 10 pCi/kg (4).

For comparison purposes, the h 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 M-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 I

exposure rates were likely a result of some source term other than the soil.

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.

lI i

l 3

I

REFERENCES I

1.

YAEL Procedure 510, Rev. 2, "Identificatior, 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 I

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."

I I

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E I

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I TABLE 1 LOCATION:

WAREHOUSE LOCATION 4 00 COUNT TIME:

6000sec COUNT DATE:

002985 I

InSitu COUNTING RESULTS I

NUCLIDE ID EXPOSURE RATE CONCENTRATION J

nicroR/hr picoCi/Kyran 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 I

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 Ru-106

(

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

( 23+- 39) EO 140E O I

n+ 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 130E-1 Co-60

(

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

(

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

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

( 1103+- 26) E1 60E 1 I

0+

( 715+- 32) EO

)

a+ Th-232

( 2016+- 90) E-3

( 638+- 31) EO 0+ U-238

( 1160+- 57) E-3 I

Notes:

K Activity greater than 3* standard deviation I

+

Peak is found LLD is not calculated I

I I

I TABLE 2 LOCATION:

EAST ROCKY HILL ROAD LOCATION 4:

01 I

COUNT TIME:

6000sec 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

.J RATE Ce-144

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

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

(-4+-

11) E-4 41E-4

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

(

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

(

2+- 40) E-1 150E-1 I

Sb-125

(-29+- 95) E-4 340E-4

(-3+- 11) EO 39E O Ru-103

( 64+- 33) E-4 110E-4

( 61+- 31) E-1 110E-1 Ba-140

(

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

(

2+- 11) EO 39E O Ru-106

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

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

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

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

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

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

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

( 53+- 26) E-1 93E-1 I

La-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 58E-3

( 30+- 20) E-1 75E-1 I

0+

K-40

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

( 761+- 20) E1 33E 1

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

( 1737+- 63) E-3

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

( 1063+- 41) E-3 Notes:

Activity greater than 3* standard deviation Ia+

Peak is found LLD is not calculated I

I I

I

i I

I TABLE 3 I

LOCATION:

WEST ROCKY HILL ROAD LOCATION 4:

03 COUNT TIME:

6000sec COUNT DATE:

082885 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION nicroR/hr picoCi/Kgran

.:I NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

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

(-9+- 65) EO 230E O I

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 I

Ru-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 O

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

( 102+- 12) EO 35E O I

n+ Cs-137 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 78E-1 a

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

( 1429+- 27) E1 42E 1 I

u++

K-40 Th-232

( 2504+- 79) E-3

( 888+- 28) EO

( 672+- 26) EO n+ U-238

( 1224+- 48) E-3 Notes:

u-Activity greater than 3xstandard deviation

+

Peak is found I

LLD is not calculated I

I I

I I

TABLE 4 I

LOCATION:

PLYMOUTH CENTER I

LOCATIONS:

04 COUNT TIME:

6000sec COUNT DATE:

082985 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION nicroR/hr picoCi/Kgran I

NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

(

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

( 82+- 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 O i

0+

Cs-137

( 325+- 11) E-3 32E-3

( 591+- 21) EO SOE O Zr-95

(-7+-

11) E-3 42E-3

(-35+- 61) E-1 230E-1 Nb-95

(

60+- 68) E-4 200E-4

( 31+- 35) E-1 130E-1 La-140

(-106+- 74) E-3 280E-3

(-135+- 95) E-1 360E-1 I

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 U+

K-40

( 2685+- 48) E-3 65E-3

( 1500+- 27) E1 36E 1

( 1014+- 29) EO a+ Th-232

( 2860+- 80) E-3

( 1011+- 29) EO 0+

U-238

( 1840+- 52) E-3 I

Notes:

Activity greater than 3* standard deviation

+

Peak is found I

LLD is not calculated I

I l

I

I I

TABLE 5 LOCATION:

PROPERTY LINE LOCATION 4:

06 COUNT TIME:

6000sec COUNT DATE:

082685 InSito COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION microR/hr picoCi/Kgran I

NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE

.:I Ce-144

(-15+- 13) E-4 48E-4

(-67+- 60) EO 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 g

Sb-125

(-39+- 92) E-4 330E-4

(-4+- 10) EO 30E O g

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 I

n+ Cs-137

( 1361+- 72) E-4 190E-4

( 247+- 13) EO 34E O Zr-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 I

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

( 1772+- 39) E-3 55E-3

( 990+- 22) E1 31E 1 I

a+ K-40

( 545+- 22) EO a+ Th-232

( 1536+- 62) E-3

( 451+- 21) ED 0+

U-238

( 821+- 38) E-3 I

Notes:

Activity greater than 3* standard deviation I

+

Peak is found LLD is not calculated I

' I llL I

l

I I

TABLE 6 I

LOCATION:

PEDESTRIAN BRIDGE LOCATIONS:

07 COUNT TIME:

6000sec COUNT DATE:

082785 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION microR/hr picoCi/Kgran

.I NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE Ce-144

( 24+- 22) E-4 80E-4

( 106+- 99) EO 360E O I

Ce-141

( 30+- 19) E-4 69E-4

( 32+- 20) EO 74E D 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 I.

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 58E-3

(

1B+- 34) EO 130E O I

w+ Cs-137

( 848+- 76) E-4 230E-4

( 154+- 14) EO 41E O Zr-95

(-1+- 10) E-3 38E-3

(-5+- 55) E-1 2.10 E-1 Nb-95

(-27+- 61) E-4 230E-4

(-14+- 32) E-1 120E-1 I

~

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 110E-1

( 398+- 21) E-3 100E-3

( 1226+- 65) E-1 310E-1

( 1380+- 36) E-3 61E-3

( 771+- 20) E1 34E 1 I

(.517+- 19) EO

( 145B+- 53) E-3

( 374+- 23) EO

( 681+- 41) E-3 I

Notes:

x Activity greater than 3xstandard deviation 3

+

Peak is found

' E LLD is not calculated I

l(

I

I I

TABLE 7 I

LOCATION:

DVERLOOK

]

LOCATIONS:

08 COUNT TIME:

6000sec I

COUNT DATE -

082785 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION I

nicroR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD 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 I

Ba-140

(-44+- 91) E-4 330E-4

(-10+- 21) EO 77E D Ru-106

(-1+- 24) E-3 90E-3

(-3+- 53) EO 200E O l

u+ Cs-137

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

( 105+- 19) EO 63E O Zr-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 J

La-140

(

9+-

11) E-2 42E-2

( 11+- 15) EO 54E O I

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 u+ K-40

( 1915+- 51) E-3 130E-3

( 1070+- 29) E1 71E 1

( 647+- 47) EO

( 182+- 13) E-2 I

u+ Th-232

( 334+- 26) EO u+ U-238

( 607+- 47) E-3 Notes:

Activity greater than 3xstandard deviation

+

Peak is found LLD is not calculated I

l I

I I

TABLE 8

, LOCATION:

EAST BREAKWATER LOCATION 4:

09 COUNT TIME:

6025sec 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

(

10+- 13) E-4 44E-4

( 45+- 56) EO 200E O Ce-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 I

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 Ba-140

( 57+- 46) E-4 160E-4

(

13+- 11) EO 37E O In+Ru-106

(

0+- 13) E-3 46E-3

(-1+- 28) EO 100E O Cs-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 La-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 88E-1 Co-60

( 39+- 15) E-3 53E-3

( 50+- 19) E-1 68E-1 I

u+ K-40

( 2348+- 44) E-3 53E-3

( 1311+- 25) E1 30E 1 l

u+ Th-232

( 1990+- 69) E-3

( 706+- 25) EO u+ U-238

( 1050+- 41) E-3

( 577+- 23) EO Notes n

Activity greater than 3xstandard deviation I

+-- Peak is found LLD is not calculated I

I I

I I

TABLE 9 I

I LOCAT10h:

CLEFT ROCK LOCATIONS:

20 COUNT TIME:

6000 set COUNT DATE:

00278G InSitu COUNTING RESULYS I

NUCLIDL ID EXPOSURE RATE CONCENTRATION nicroR/hr picoCi/Kgran

.7 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

(-214-13) EO 49E O I

I-131

(

14+- 34) E-4 120E-4

(

19+- 46) E-1 170E-1 Sb-125

(

6+- 11) E-3 30E-3

(

7+- 12) EO 43E O Ru-103

(-27+- 39) E-4 140E-4

(-26+- 37) E-1 140E-1 I ~

Ba-140

(

14+- 57) E-4 200E-4

(

3+- 13) ED 48E O Ru-106

(-24+-

15) E-3 58E-3

(-54+' 34) EO 130E O 0+

Cs-137

( 331+- 11) E-3 28E-3

( 602+- 20) EO 51E O Zr-95

(-2+- 11) E-3 39E-3

(-13+- 57) E-1 210E-1 I

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 80E-3

( 1449+- 28) E1 49E 1

( 744+- 25) EO 0+

Th-232

( 2098+- 71) E-3

( 596+- 25) EO 0+

U-238

( 1085+- 46) E-3 Notes:

O Activity greater than 3* standard deviation

+

Peak is found calculated I

LLD is n o t I

I I

I I

TABLE 10 I

LOCATION:

EAST WEYMOUTH CONTROL LOCATION 4:

15 COUNT TIME:

6000sec COUNT DATE:

083085 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE RATE CONCENTRATION nicroR/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

(-18+- 12) E-4 45E-4

(-19+- 13) EO 40E 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) EO 43E O

~

Ru-103

(-11+- 38) E-4 140E-4

(-10+- 36) E-1 130E-1 Ba-140

(

62+- 54) E-4 190E-4

(

14+- 13) EO 4GE O

~

Ru-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 D Zr-95

(-4+- 11) E-3 40E-3

(-22+- 57) E-1 210E-1 I

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 0+

K-40

( 2582+- 47) E-3 67E-3

( 1442+- 27) E 1.

38E 1 i

( 665+- 20) EO u+ Th-232

( 1874+- 57) E-3

( 1094+- 28) EO n+ U-238

( 1992+- 51) E-3 Notes:

Activity greater than 3* standard deviation

+

Peak is found calculated I

LLD is not I

E I

I TABLE 11 LOCATION:

MANOMET SUBSTATION LOCATION 4:

17 COUNT TIME:

6000sec COUNT DATE:

082985 InSitu COUNTING RESULTS I

NUCLIDE ID EXPOSURE RATE CONCENTRATION nicroR/hr picoCi/Kgran NAME EXPOSURE +-1-SIGMA LLD CONC +- 1-SIGMA LLD RATE l

Ce-144

(-10+- 12) E-4 42E-4

(-44+- 55) EO 190E D Ce-141 21+- 11) E-4 37E-4

( 22+- 11) EO 3YE O s

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 Ba-140

(

44+- 49) E-4 170E-4

( 10+- 11) EO 39E O Ru-106

(

18+- 13) E-3 46E-3

( 40+- 29) EO 100E O

- n+ Cs-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 I

La-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 I

0+

K-40

( 2682+- 49) E-3 76E-3

( 1498+- 27) E1 42E 1 n+ Th-232

( 2300+- 71) E-3

( 816+- 25) EO a+ U-238

( 1083+- 42) E-3

( 595+- 23) EO i I Notes:

Activity greater than 3Kstandard deviation Ie+

Peak is found LLD is not calculated I

i I 4 /

I l

M M

M M

M M

M M

TABLE 12.

1585in-SituResults. Comparison of Germanium System an4 High Pressure Ionization Chamber Results.

Description Positive Germanium Results (uR/h i lo)

Total

  • HPIC Site (Distance in miles No.

from plant)

U-238 Th-232 K-40 Cs-137 Other (uR/h)

(vR/h) 00 Warehouse 1.16 i 0.06 2.02 0.09 1.98 t 0.05 0.10 0.01 8.85 i 0.12 21.9 1 0.91 (0.03 SSW) 01 Rocky Hill Rd. E.

1.06 t 0.04 1.74 0.06 1.36 0.04 0.36 i 0.01 8.12 1 0.08 7.85 0.64 (0.85 E) 03 Rocky Hill Rd. W.

1.22 0.05 2.57 i 0.08 2.56 0.05 0.06 0.01 10.00 0.14 10.09 i 0.64 (0.3 WNW) 04 Plymouth Center 1.84 i 0.05 2.86 i 0.01 2.68 0.05 0.32 0.01 11.31 1 0.12 11.35 0.52 (4.5 WNW) 06 Property Line 0.82 i 0.04 1.54 i 0.06 1.77 0.04 0.14 i 0.01 7.86 1 0.08 8.72 1 0.86 (0.34 NW) 07 Pedestrian Bridge 0.68 0.04 1.50 0.07 1.38 0.04 0.08 i 0.01 0.40 0.02 7.64 t 0.09 11.76 1 0.75 (0.14 N)

(a) 08 Overlook 0.61 0.05 1.82 i 0.13 1.92 i 0.05 0.06 i 0.01 8.00 0.15 47.56 1 0.81 (0.03 W)

(b) 09 East Breakwater 1.05 0.04 1.99 i 0.07 2.35 0.04 0.07 0.01 9.06 1 0.09 9.11 i 0.47 (0.35 ESE) 10 Cleft Rock 1.08 0.04 2.31 i 0.08 2.59 0.05 0.33 0.01 9 92 1 0.11 9.25 1 0.43 (0.9 S) 15

f. Weymouth Cbntrol 1.99 0.05 1.81 0.07 2.58 0.05 0.17 0.01 10.15 t O.10 9.64 0.40

('23 NW) 17 Manonomet substation 1.08 t 0.04 2.30 0.07 2.68 0.05 0.21 i 0.01 9.87 0.10 8.06 i 0.58 (2.5 SE)

~

Total of Germanium System plus 3.6 pR/h cosmic contribution (a) Co-60 found in in-situ and confirmed by Laboratory soil analysis.

(b) Weighted average Th-232 exposure Fate does not include 2614.7 kev gamma for this station only.

I MAILED YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY FEB 10ses Initial Analysis Report I

ENVIRONMENTALLAB.

YAEC Customer : Boston Edison Company Report Date: 09/19/85 MS. CHRISTINE E. BOWMAN Analysis Date: 9 /5 /85 IAttsntion: MR. EDWARD CUMMING Date Received: 9 /3 /85 Reference Date: 8 /27/85 I

Soil 0.32 Kg.

Lab Sample No.:

G54204 ISempleAmount:

Sample Submission Code: PTS 0713585 Elapsed Time : 9.28 days Other Analysis Requested:

None Comment:

0-2 I

Station No.:

07 Pedestrian Bridge (PB)

DECAY ACTIVITY NUCLIDE CONC. +- 1 SIGMA MDC

_$$$ I_ ____ _____

Np-239 6.48E-02

( 149 +- 57 ) E 1 190 E 1 Co-57 9.77E-01

(-2 +- 43 ) E-1 140 E-1 I

Ce-144 9.78E-01

(-3 +- 34 )EO 110 E O Ce-141 8.21E-01

( 45 +- 92 ) E-1 310 E-1 Mo-99 9.90E-02

(-19 +- 74 ) E 1 250 E 1 I

Se-75 9.48E-01

( 67 +- 72 ) E-1 240 E-1 Cr-51 7.93E-01

( 2 +- 54 )EO 180 E O I -131 4.49E-01

( 4 +- 12 ) E O 39 E O Be-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 I

Cs-134 9.91E-01

( 2 8 +- 7 2 ) E-1 240 E-1 Ru-106 9.83E-01

(-5 +- 47 ) E O 160 E 0-

  • +

Cs-137 9.99E-01

( 2 00 +- 10 ) E O 21 E O Ag-110M 9.75E-01

( 39 +- 82 ) E-1 270 E-1 Zr-95 9.06E-01

( 22 +- 11 ) E O 36 E O Co-58 9.13E-01

( 188 +- 64 ) E-1 230 E-1 Mn-54 9.80E-01

(-154 +- 64 ) E-1 220 E-1 c+

AcTh228 1.00E 00

( 447 +- 34 )EO 95 E O TeI-132 1.38E-01

(-4 0 +- 2 6 ) E 1 86 E 1 Fe-59 8.67E-01

( 8 +- 14 )EO 46 E O I

Zn-65 9.74E-01

( 1 +- 15 ) E O 51 E O o+

Co-60 9.97E-01

( 556 +- 91 ) E-1 280 E-1 o+

K -40 1.00E 00

( 658 +- 20 ) E 1 32 E 1 Sb-124 8.99E-01

( 12 +- 12 ) E O 40 E O Notes:Activity greater than 3* standard deviation Approved by I+x Decay correction less than.01 Peak is found "E.'L.

Laurenzo 1I l

I MAILED y,,xzE A. 1C EtECTRIC COMexuv l

FEB 101986 ENVIRONMENTAL LABORATORY Initial Analysis Report g

Customer : 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 Scmple Amount: 0.37 Kg.

Lab Sample No.:

G54205 Sample Submission Code: PTS 0723585 Elepsed 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 6.40E-02

( 128 +- 64 )E1 210 E 1 9.77E-01

(-52 +- 44 ) E-1 150 E-1 I'

Co-57 Ce-144 9.78E-01

(-80 +- 34 ) EO 110 E O Ce-141 8.21E-01

( 85 +- 90 ) E-1 300 E-1 Mo-99 9.90E-02

(-56 +- 75 ) E1 250 E 1 1

Se-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 ) EO 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 I

Cs-134 9.91E-01

(-80 +- 65 ) E-1 220 E-1 Ru-106 9.83E-01

(-90 +- 53 ) EO 170 E O 0+

Cs-137 9.99E-01

( 697 +- 61 ) E-1 140 E-1 Ag-110M 9.75E-01

( 167 +- 72 ) E-1 240 E-1 Zr-95 9.06E-01

( 2 5 +- 10 ) EO 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 0+

AcTh228 1.00E 00

( 575 +- 31 ) EO 76 E O TeI-132 1.38E-01

(-32 +- 28 )E1 94 E 1 Fe-59 8.67E-01

(-17 +- 14 )EO 47 E O I

Zn-65 9.74E-01

(-31 +- 17 ) EO 57 E O Co-60 9.97E-01

( 155 +- 74 ) E-1 270 E-1 o+

K -40 1.00E 00

( 953 +- 21 ) E1 29 E 1

)

Sb-124 8.99E-01

( 14 +- 12 )EO 41 E O Notes:

Activity greater than 3* standard deviation o

+

Peak is found Approved by x

Decay correction less than.01 en, am e.,

E.- L. Laurenzo i

-m

~, - - -

,, ~. - - -, - - -

YANKEE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY FEB 10886 Initial Analysis Report YAEC ENVIRONMENTAL LAB.

Cuatomer : 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 Semple Amount: 0.33 Kg.

Lab Sample No.:

G54206 Sample Submission Code: PTS 0733585 Elepsed 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 ) E1 290 E 1 Co-57 9.77E-01

( 81 +- 61 ) E-1 200 E-1 Ce-144 9.78E-01

( 42 +- 45 ) EO 150 E O Ce-141 8.21E-01

( 10 +- 12 ) EO 41 E O Mo-99 9.90E-02

( 41 +- 100 ) E1 330 E 1 Se-75 9.48E-01

(-9 6 +- 8 6 ) E-1 290 E-1 3

Cr-51 7.93E-01

( 111 +- 61 ) E O 200 E O I -131 4.49E-01

( 7 +- 14 )EO 45 E O Be-7 8.86E-01

(-32 +- 56 ) EO 190 E O I-Ru-103 8.49E-01

(-119 +- 72 ) E-1 24 0 E-1 xI -133 6.44E-04 Ba-140 6.05E-01

(-32 +- 14 ) E O 46 E O I

Cs-134 9.91E-01

(-2 +- 80 ) E-1 270 E-1 Ru-106 9.83E-01

( 85 +- 67 ) EO 220 E O 0+

Cs-137 9.99E-01

( 687 +- 98 ) E-1 280 E-1 Ag-110M 9.75E-01

(-130 +- 100 ) E-1 330 E-1 Zr-95 9.06E-01

(-10 +- 14 ) EO 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 ) EO 110 E O TeI-132 1.38E-01

( 22 +- 30 ) E1 99 E 1 Fe-59 8.67E-01

(-10 +- 16 ) EO 54 E O Zn-65 9.74E-01

( 5 +- 19 ) E O 63 E O Co-60 9.97E-01

(-10 +- 10 ) EO 40 E O C+

K -40 1.00E 00

( 901 +- 25 ) E1 39 E 1 INotes:

Sb-124 8.99E-01

(-10 +- 15 ) E O 49 E O Activity greater than 3* standard deviation Peak is found Approved by I+x Decay correction less than.01 E.' L. Laurenzo I

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 J

YAEC Environmental Laboratory operations. The information presented reaffirms the Laboratory's initial criteria for precision and accuracy when a known amount of a NBS 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 of activity added. For the latter case, the true radionuclide concentration of the sample set is unknown and a simple comparison of the range (to some statistical confidence level, 2o) of concentration of the individual samples can be made. As a final note, although the criteria presented below are only f-applicable 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 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 dacay 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 io'five percent of the analyzed value. With these facts in mind, it can be readily seen that agreement with a known value to within 115 percent may not be achievable if the one sigma uncertainty associated with the measurements approaches or exceeds the preset percentage.

As an example, the triplicate

-p

-vw

I 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 sumarize the quality control criteria which the Laboratory staff find technically acceptable in view of the three quality control programs currently being implemented for the YAEC Environmental Laboratory operations. The information presented reaffirms the Laboratory's initial criteria for precision and accuracy when a known amount of a NBS 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 of activity added. For the latter case, the true radionuclide concentration of the sample set is unknown and a simple comparison of the range (to some statistical confidence level, 2a) of concentration of the individual samples can be made. As a final note, although the criteria presented below are only I~

applicable for small sample sets (2-5 samples), the infonnation gathered could

' be utilized to detect long-term biasing or a procedure giving non-reproducible results.

Discussion i

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 Comittee 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 dacay 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 115 percent may not be achievable if the one sigma uncertainty associated with the measurements approaches or exceeds the preset percentage. As an example, the tripTicate analysis of a sample for strontium-90 (known value = 5pci/kg) yielded values I

of 311, 411 and 511pti/kg with a mean value of 41 pti/kg. Note that the 1

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 2o) 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 order 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, I

ect.

A1. All known values will be utilized without associated statistics.

A2. Wherever possible, individual values will be investigated with J

regard to agreement with the known. However, mean values may be l

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 SilpCi/kg would be 3-7pti/kg).

If the known value falls within the 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 analyzed value.

If the mean value falls within the specified range, the analysis is considered in agreement.

C.

Determination of Precision:

Duplicate or Replicate Analysis of Environmental - Activity Unknown D1. For duplicate or replicate analyses conducted at the same laboratory, neither value can be considered the 'true" value I

regardless of the uncertainties associated with the measu,rements.

9

02. The average value is the best avail:ble 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 duplicates (three sigma range for replicates) for each of the 4

analyses.

If the ranges overlap, the analyses cannot be said to be I

statistically different and agreement is obtained. An example of the use of this criteria is shown below:

Analysis A Analysis B l

31 pci/kg 511pti/kg 1

Average Value 4pCi/kg Percent Deviation from Average = 100x(3-4) = 25 percent 4

No agreement by D3.

2a Range A 2a 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 agreement criteria is susceptible to biasing by analyzing the samples to a high level of I

statistics (i.e. a shorter counting time).

In order to preclude this biasing, all samples will be analyzed for lengths of time approximating that of routine samples of the appropriate media.

I I

I l

10

u -

,--w.-

.s m

w a

I I

I

~

APPENDIX D RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I

l

I 1

i 4.8.D Environmental Menitorine Precram E

An environmental monit--ing program shall be conducted as follows:

1.

Enviren= ental samples shall be selected and analyzed according to I

Table 4.8.1 at the locations described in Tables 4.8.2 and 4.8.3 and shown in Figures 4.8.1, 4.8.2 and 4.8.3.

I 2.

Analytical techniques used shall be such that the detection capabilities in Table 4.8.4 are achieved.

3.

A census of gardens producing fresh leafy vegetables for human consurp-tion (e.g., lettuce, spinach, etc.) shall be conducted near the end of the growing season to determine or verify the location of the garden (available for sa pling) yielding the highest calculated thyroid dose.

I This census is limited to gardens having an area of 500 square feet or more and shall be conducted under the following conditions as necessary to meet the above requirement:

a.

Within a 1-tile radius of the plant site, enumeration by a door-to-door, or ecuivalent counting technique.

b.

If no cilk-producing anicals are located in the vicinity of the 23 site, as determined by ite: 4 below, the census described in item 3a above shall be extended to a distance of 5 miles from the site.

If the census indicate.s-the existence of a ' garden at a location yielding a calculated thyroid dose greater than that from the previously sampled garden, the new location shall replace the Farden previously havinF the caxi=um calculated iodine concentration. Also, any location from which fresh leafy vegetables can no longer be obtained may be dropped from the surveillance program as long as the NRC is notified in writing, as soon as possible that such vegetables are no longer grown or no longer-available at that location.

4 A census of animals producing milk for human consumption shall be conducted at or near the ciddle of the grazing season to determine or verify the location yielding the highest calculated annual average thyroid dose.

The census shall be conducted under the following conditions as necessary to meet the above requirement:

a.

Within a 1-=ile rad.ius from the plant site or within the 15 mrem /yr I

isodose line, whichever is larger, enumeration by a door-to-door or equivalent, counting technique.

I b.

Within a 5-mile radius for cows and for goats, enumeration derived from referenced information from county agricultural agents or other reliable sources.

If it is learned from this census that animals.ae present at a location which yields a calculated thyroid dose greater than from previously sampled ani=als, the new location shall b dced to the surveillance program as soon as -" cticable. The m.ap_ing location having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing season during which the census was conducted. Also, any location from which milk can n'o longer be obtained may be dropped from the surveil-183

I lance program as long as the NRC is notified in writing, as socn as practicable, that milk-producing animals are no longer present, or milk i

samples are no longer available at that loca:icn.

5.

Deviations are per itted free the required sampling schedule if spec-imens are unobtainable due to hazardous conditions, seasonal unavail-ability or to calfunction of automatic sampling equipment.

In the event of ecuipment calfunction, every reasonable effort shall be nade to complete corrective action prior to the end of the next sampling period. Any significant deviations from the sampling schedule shall be explained in the annual report.

6.

Detailed written procedures, including applicable check lists and instructions, shall be prepared and followed for all activities I

involved in carrying out the environmental monitoring program.

Procedures shall include samplinF, data recording and storage, instrument calibration, reasurements and analyses, and actions to be taken when ancmalous measurements are discovered.

Procedures shall be prepared for insuring the quality of progra:

results, including analvtical measurements.

These procedures will I

identify the responsible organizations, include purchased services (e.o..

contractual lab). include indeoendaar audits, and include syster=

J (suen as participation in lA_a anc/or Eb5 interc 1 oration exercises and sub=ission of "bliTd" quality control sanele= for analy=e= ky +ha raat-actors)lto icenti:y anc correct deficiencies, investigate anc:alous or suspect results, and review and evaluate program results and reports.

I

. 3.E.D and 4.R.D 23 Environnental Men'itoring Program An Environmental radiological conitoring program is conducted to verify I.

the adequacy of in-plant con:rols on the release of radioactive materials.

The program is designed to detect radioactivity concentrations which could result in radiation doses to individuals not exceeding the levels set for:h in 10CFR50 Appendix 1.

An exa:ple of this is the.d,etection of I-131 in milk.

Calculational Models (Regulatory Guide 1.109 have shown a constant consideration of 3.3 pCi I-131 per liter milk would result in a dose of 15 milliree to the thyroid of an infant consu=ing that milk for a year. Allowing for an open grazing season of six months, aind a maximum of two half-lives between event and sa=pling, the lower limit of detection at time of sampling must beIb pC1/1 (3.3 x 12/6 x t a 1.6).

A supplemental monitoring program for sediments and mussels has been I

incorporated into the basic program (see notes f and g to Table 4.8.1) as a result of an agreement with the Massachusetts Wildlife Federation.

This supplemental prograc is designed to provide information on radioactivity levels at substantially higher sensitivity levels in selected sa=ples to verify the adequacy (or, alternatively, to provide a basis for.later modifications) of the long-ler: marine sampling schedules. As part of the supplemen:al program, analy. sis of mussels for isotopes of plutonium will be performed if radiocesium activity should exceed 200 pC1/Kgm in che edible

(

portions.

l v-

  • Supplemental provision 183a

I The 200 pCi/Kgm radiocesium " action level" is based en calculations which showed that if radiocesiu: free plant releases reached this level, plutonium could possibly appear at levels of potential interest.* The calculations also showed that the dose delivered free these levels of pluteniu: would not be a significant por: ion of the total dose a:tributable to licuid effluents.

The program was also designed to be consistent, wherever applicable with Regulatory Guide 4.8 (Issued for cor=ent December 1975).

The following I

exceptions to the generie reco==endations stated in Regulatory Guide 4.8 t

are justified due to site specific considerations:

1.

The required detection capability for I-131 in milk is about twice the value suggested in Regulatory Guide 4.S.

The justi-fica: ion for the higher value is presented in the second paragraph of this section. This is a conservative estimate of the capability I

of the milk surveillance progra: to detect concentrations at the appropriate annual dose level since the annual dose is proportional to the annual averace concentration in milk.

The detection limit for a I

group of saeples is less than that for a single sample and is inversely proportional to the square root of the number of samples. The conser-vatism in this case is approximately ed2', or about a factor of 3.

2.

Air particulates are not analyzed for radiostrontium.

J The progra: instead calls for this analysis in milk sanples.

~his is justified because the air-cow-milk exposure pathway can be better non-I itored at Pilgris after the very low level releases of radies:rontiur are reconcentrated in cow's = ilk (Ref. 1).

3.

Soils and sediments are not routinely analyzed for Sr-90, but rather the analysis is done.on a contingency basis. The rationale behind this is that Sr-90 will not contribute to long-term radionuclide buildup un:il the more abundant ga==a ermi::ing nuclides appear in relatively

~

1arge concentrations.

Both Items 2 and 3 reflect the fact that in 3b years of operation, Pilgrim Station liquid releases of Sr-90 have amounted to only 1/1000 of the Sr-90 inventory in Cape Cod Bay water (from weapons testing fallout) and about 4/100,000 of the direct deposi-tion on the Bay.

Also, gaseous releases of Sr-90 have been only 1/100,000 of the terrestrial Si-90 inventory within five miles of the station (Ref. 1).'

N 4.

Surveys are conducted annually to determine approoriate locations for sa:pling of leafy vegetables and milk.

The objective of these surveys is to ensure that the environmental samples are represen-I tative of realistic food chain pathways, considering local conditions.

Results,of the monitoring program will be used as " benchmarks" to verify calculational models used to predict the consequences of effluent releases from the station. The models can then be employed to predict doses attributable to radiation deposition at any other location of interest.

The combination of monitoring results and calculationt.1 model predictions is a practical. method of demonstrating compliance with 10CTR50 Appendix I.

This approach does not require (nor is it always practical) that environ-mental media always beysampled from the " worst case" locations: although sensitivity of the monitoring results might be improved by sampling from I

locations which are reasonably close to " worst case" conditions.

(

  • in measurable quantities having a potential dose (hu=an food chaln) -

at their detection limits.

significance comparable to other nuclides if present 183b

E Verificatien of the appropriate milk sampling locations on an annual E

basis is satisfactory as there are very few locations suitable for the

(

gra ing of dairy herds in the vicinity of the plant (Ref. 2).

This situation cakes it unlikely the location of the nearest dairy herd I

(3.5 ciles-W) will change.

S.

Annual sampling of beef forage (in place of beef) is adequate because beef cattle are not raised com=ercially in the vicinity of the site.

I However, dairy cows,from the Plymouth County Farm are periodically sold for beef. Feed (ha'y) from this location will be sampled to monitor this potential pathway for ingestion of radioactivity.

If beef cattle feeding on local forage are found at locations closer to the site, forage sa=ples from the closer location will replace the sa=ple from the County Far=.

6.

Goundwater flow at the plant site is into Cape Cod Bay: therefore, terrestrial monitoring of groundwater is not included in this program.

23 7.

Poultry sampling is not performed because poultry in Plymouth County feed almost exclusively.on imported grain and are usually raised under shelter.

.I Field gn==a isotopic surveys are conducted to monitor radioactivity in S.

.7 seil in lieu of laboratory analysis of soil samples.

The technioue has several advantages.over laboratory analysis.

First, analysis can be performed on the same plot of land from survey to survey, and radio-activity build-up at the location can be accurately deter =ined.

Secondly, hence ga==a exposure rate is determined directly from this technique:

co:pliance with 10CFR50 Appendix I levels can be investigated directly rather than indirectly through soil sampling.

O I

I h

I e

ll' e

I 183c

References:

(

l.

'a'renn M.E., " Review of Sr-90 Releases from Pilgrim 1 Nuclear Plant and a Comparison with Extant Environmental, Levels", 1976.

23 2.

Pilgrim Station Unit #2 PSAR, A;,endix 117, pp. 11FC-11 and 11A, amende;l June 15, 1976.

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l 183d

M EM M

M M

M M

TABLE 4.8.1 o

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM locations Exposure Pathway (Directiors-Distance)

Sampling and Type and Frequency or Sample Type from Deactor Collection frequency _

of Analysis AIR 00RNE Particula tes 11 (see Table 4.8.2)

Conti,iuous sampling over Gross beta radioactivity at one week least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter change.

(a) nuarterly composite l r

(by location) for ganina isotopic.

(b) 23 Radiciodine 11 (see Table 4.8.2)

Continuous sampling with Analyze weekly for I-131 w

canister collection weekly Soil 11 (see Table 4.8.2)

Once per three years Field ganina isotopic.

(c)(1)

DIRECT 20 (see Table 4.8.3)

Ouarterly Gamma exposure quarterly. (1)

Plymouth beach and g

Priscilla/ White llorse Beach Annually (sprinn)

Ganrna exposure survey (i)

WATER 00RNE Discharge Canal continuous compositesampic Ganina isotopic (b) monthly; Dartlett Pond (SE-1.7 mi.)

Weekly grah sample and composite for 11-3 Powder Point (NNW-7.8 mi.)(d) Veckly grab sample analysir quarterly, (c).

AQUATIE Shelffish Discharge outfall Guarterly (at approximate Ganina isotopic (b); also see Duxbury Day 3-nonth intervals) note (f).*

Manomet Pt.

Plymouth or Kingston liarbor Marshfield (d)

ONote (f) and beach surveys are supplemental provision

~

t, TABLE 4.8.1

'TCont'd) locations Exposure Path ay (Direction-Distance)

Sampling and Type and frequency or Sample Type __

from Reactor Collection Frequency of Analysis Irish Moss Discharge outfall Semi-annually Gamma isotopic (b)

Manomet Pt.

Ellisville(d)

Lobster Vicinity of discharge Four times per season Gamma isotopic (b) on edible portions.

point gg) of f sliore Once per season Fish Vicinity of discharge Quarterly, Groups I and 11 (e)

Gamma isotopic (b) on po. int in season, Groups ill and IV (c) edible nortions(e)

Of fsliorebI)

Anr,ina l l y, each r,roup Seini-annual ly Gamma isotopic (b) (c),

Rocky P.oint Sediments Plymouth liarbor see also note (n) Y Duxbury Day Plymouth Beach Manomet Pt.

23 O.

Marshfield (d) n INGESTION (Terrestrial)

Milk Plymouth County Farm Semi-monthly during periods when Gamma isotopic (b)

Sr-89, (W-3.5 mi.)(h) blhitman animals are on pasture, other-90 monthly; radiolodine

)

Farm (NW-21 mi.)

(d) wise monthly analysis all samples.

Cranberries Manomet Pt. Bog-At time of harvest Gama isotopic (b) on

)

(SE-2.6 mi.)

edible portions.

l Dartlett Rd. Bog (SSE/S-2.8 mi.)

pine St.' Bog (WilW-17 mi.) (d)

T ONote (gl is supplemental provision mmc I

M M,~M M

M M

M M

M M

M,, M M

M M

M M.M M,

TABLE 4.8.1 lCont'iI)~

Locations Exposure Pathway (Direction-Distance)

Sampling and Type and Frequency or Sample Type from Reactor Collection Frequency of Analysis 23 Tuberous and Karbott Farm (SSE-2.0 mi.)(h) At time of harvest Gamma isotopic (b) green leafy Bridgewater Farm on edible portions, vegetables (W-20 mi.)

(d)

Beef Forage Plymouth County Farm Annually.

Ganuna isotopic (b)

(W-3.5 mi. ) (h) 1 I

.c s.

tm

?

9 N

\\

l l

l

E Notes (a) If gress beta radioactivity is greater than 10 times the centrol value, 4

ga==a isotopic will be perfor ed on the sa=ple.

(b)

Ga=a isotopic means the identification and quantification of gac=a-e:itting radionuclides that may be attributable to the effluents fro the facility.

(c) If integrated ga==a activity (less K-40) is greater than 10 times the control value (less K-40), strontiu=-90 analysis will be perfor=ed on the sample.

(d) Indicates control location.

l 3 (e) Fish analyses will be perfor=ed on a minimum of 2 sub-samples, consisting g

of approxi=ately 400 grams esch from each of the following groups:

I.

Ectto: Oriented II. Near Botto:

III. Anadromous IV. Coastal Distribution Migratory k' inter flounder Tautog Alewife Bluefish Yellowtail flounder Cunner Rainbow smelt Atlantic herring I

Atlantic cod Striped bass Atlantic menhaden Pollock Atlantic mackerel Hakes (f)* Mussel sa=ples f ro four locations (ic=ediate vicinity of discharge outfall, Mano=et Pt., Plymouth or Kingston Harbor, and Green Harbor in Marshfield) 23 will be analyzed quarterly as follows:

One kilogra= vet weight of'=ussel bodies, including fluid within shells will be collected. Bodies will be reduced in volume by drying at about 1000C.

I' Sa=ple will be ec=pacted and. analyzed by Ge(Li) gac=a spectrometry or alternate technique, if necessary, to achieve a sensitivity ** of 5 pCi/kg for Cs-134, Cs-137, Co-60, 2n-65 and Zr-95 and 15 pCi/kg for Ce-144.

The mussel shell sa=ple fr'om one location will be analyzed each quarter.

One additional mussel shell sample will be analyzed semi-annually. Unscrubbed I

shells to be analyzed will be dried, processed, and analyzed similarly to the mussel bodies.

I Because of the small volume reduction in pre-processing of shells, sensitivi-I ties attained will be less than that for mussel bodies. The equipment and counting times to be employed for analyses of shells will be the sa=e or

,ce= parable to that e= ployed for mussel bodies so that the reduction in sensitivities (relative to those for =ussel bod'ies) will be strictly limited I

to the effects of poorer geometry related to lower sample volume reduction.

~Shall_sa=eles not scheduled for analvsis will be reserved (unscrubbed) for

~

oossib1e later analysis

(

  • Supplemental provision
    • Sensitivity values are to.be determined in accordance with a 95*4 confidence level on K.
50*; confidence level on K g (See HASL-300 for definitions).

185c

I Notes (Cont'd) e If radiocesic= (Cs-134 and Cs-137) activity exceeds 200 pCi/kg (wet)

I in mussel bodies, these samples will be analyzed by radiochemical spearation, electrodeposition, and alpha spectrocetry for radioisotopes of plutoniu=, with a sensitivity of 0.4 pCi/kg.

(g)R Sediment sa=ples fro = four locations (Manore: Pt., Rocky Pt., Plymouth Harbor, and head of Duxbury Bay) will be analyzed once per year (preferably early su==er) as follows:

Cores will be taken to depths of 30-c=, mini =ue depth wherever sedi=ent conditions per:1: by a hand-coring sa=pling device.

If sedinent conditions I

do not pe rmit 30-c= deep cores, the deepest cores achievable with a hand-coring device will be tcken.

In any case, core depths will not be less than 14-c=.

Core sa=ples will be sectioned into 2-c= increments, and surf ace and alternate incre=ents analyzed, others reserved.

Sediment I

sa=ple volumes (deter =ined by core diameter and/or number of individual cores taken fro = any single location) and counting technique will be sufficient to achieve sensitivities of 50 pCi/kg dry sediment for Cs-134, I

Cs-137, Co-60, 2n-65, and Zr-95 and 150 pC1/kg for Ce-144.

In any case 23 individual core diameters will not be less than 2 inches.

The top 2-c= section fre: each core will be analyzed for Pu iso:cpes

(?u-235, Pu-239, 240) using radioche=ical separations, electrodeposition, and alpha spectrometry with target sensitivity of 25 pC1/kg dry sedi=ent.

Two additional core slices per year (=id-depth slice from two core sa=ples) will be similarly analyzed.

(h) These locations may be altered in accordance with results of surveys discussed in paragraphs 4.8.D-3 and 4.8.D-4.

(i) Mini =u=

sensitivities for ga==a exposure =easure=ents are as follows:

Field ga==a isotopic - 1 uR/hr for K-40, U series, Th series, and CS-137.

I Ga==a exposure

- 1 uR/hr average exposure rate.

Ga==a exposure survey-1 uR/hr exposure ra:e.

s I

  • Supplemental provision I

S W"

a 185d

~

l I 5

l TA3LE 4.8.2 AIR PARTICULATES. CASEOUS RADIOIODINE AND MOIL SURVE!i.IANCE STATIONS, l

Sampling Location Distance and Direction from Reactor (Samole Desienation)

Offsite Stations East Weymouth (EW)

  • 23 miles NW Plymouth Center (PC) 4.5 miles W-WNW I

Manomet Substation (MS) 2.5 miles SE I

Cleft Rock Area (CR) 0.9 miles S 23 Onsite Stations Rocky Hill Road (ER) 0.8 miles SE Rocky Hill Road (WR) 0.3 miles W-VNW I

Overlook Area (CA)

O.03 miles W Property Line (PL) 0.34 miles NW l

}

Pedestrian Bridge (PB) 0.14 miles N i

East Breakwater (ES) 0.35 miles ESE i

Warehouse (WS) 0.03 miles SSE I

I s

l'#

  • Control Station W

l

.186 l

l

I TABLE 4.8.3 I.

EXTERNAL CAMMA EXPOSURE St'RVEILLANCE STATIONS (TLD)

Distance and Dosimeter Location (Designation 1 Direction from Station Offsite Stations I

East Weymouth (EW)*

23 miles IN

  • Kingston (KS) 10 miles MN Sagamore (CS) 10 miles SSE-S Plymcuth Airport (SA) 8 miles WSW

(

North Plymouth (NP) 5.5 miles WN Plymouth Center (PC) 4.5 miles W-MN South Plymouth (SP) 3 miles WSW Manome t (MS) 2.5 miles SSE Manomet (PI) 2.5 miles SE 23 Mano=et (MP) 2.25 miles ESE-S Cleft Rock Area (CR) 0.9 eiles S I-l Secuish Nack (SN)**

l. 6 tniles NNW lD*

Dnsite Stations Rocky Hill Road (ER) 0.2 miles SE Microwave Tower (MT) 0.38 miles S Rocky Hill Road (WR) 0.3 miles W-WNW Rocky Hill Road (B) 0.26 miles SSE Property Line (!!)

O.21 miles SSW Property Line (I) 0.14 miles W Public Parking Area (PA) 0.07 miles N-NNE Overlook Area (OA) 0.03 miles W s

I

  • Control Station
    • T1.D's for this location will be provided to a third party and will

/

be analyzed for ga==a exposure whenever ra-- med to BECo.

      • Supplemental provision S

[

M 4M M

M M

M M

M M

M,, M M

M M

M M.- M M

i TAnl.E 4. 8.4 o

(d)

DETECTION CApARII,ITIES l'OR ENVIRONMI:NTAI, SAHpl.E ANAI,YSIS 1.uwer I,imit of Detection (a)

Water Airborne particulate Wet solids Dry solids Milk Analysis pC1/1 or gas - pct /H3 pCl/Kg pC1/Kg pCi/l Gross beta 2

1x 10-2 11 - 3 330 Mn-54 15 130 60 Fe-59 30 260 120 s-C0-58,60 15 2 x 10-2 130 60 Zn-65 30 260 120 Sr-89 10 40 10 Sr-90 2

8 150 2

Zr/Nb-95 10 1-131 7 x 10-2 80(h) 1.5 (c) 1 Cs-134,137 15 1 x 10-2 80 150 15 I

f..i /I,a-14 0 15 15 (8) The nominal lower limits of deter, tion at the 95% confidence level (defined in the ERDA Ilealth and Safety I,ahorntory procedures manual, IIASI.-300).

(d) This table appiles to all analyses other (b) Applies only to analysis of green leafy vegetables.

than those for which higher sensitivitics npply in accordance wit h Not es (I) and (g) to Table (c) Sensit Ivit y wit h 257 error at the 957. conIldence level.

/. n.1, I

I I

l Green Harbor b

Oe Cape Cod Bay I

O Duxbury l

Bay 1

i

?

i Kings ton Harbor 50 ALE IN MILES Plymouth Harbor b

~

Rocky Point I

Warren b

b Cove D*

I O

Points eA Manomet and Stage I-I t

LEGEND O IRISH MOSS O

I E//isville O SOFTSHELL CLKMS Harbor e MUSSELS I

A SEDIMENT E QUAHOGS j

m,_ e

.e4. m e.1 ma1 _..,.1s....e e.e1..

1.=,11.c sEm10.

g 1m

I Ii g

\\

f p1

o

,/

\\

s.#

241 2

,A8 l3 f,

0 600 1200 10

','O 9 ',

0 SCALE IN FEET 2

04 0

' 'f '.

5 O 2 l-

~% ~ss,"@ g 13,N f+

j

\\

21*

6 2.

' ~\\

[. /

p

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p5

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's. *.. -

16 '

'i.

0' d

17 20I

~

' O. _ b 2-LEGEND 1 PROPERTY LINE (01

  • 13 ROCKY HILL ROAD 181 2 PROPERTY LINE (F4
  • 14 MICROWAVE TOWE R iMil 3 PROPERTY LINE til, 15 EMERSON RO AD (EMt
  • 4 PROPERTY LINE (G)
  • 16 WHITE HORSE RO AO IWM*

5 ROCKY HILL ROAD ( Al

  • 17 PROPERTY LINE (E t*

6' PROPERTY LINE (HI 18 ROCKY HILL ROAD (WR) 7 PUBLIC PARKING ARE A (PA) 19 PROPERTY LINE Ul*

8 PEDESTRI AN BRIDGE iPBI 20 PROPERTY LINE (KW 9 OVERLOOK ARE A (O A*l 21 ROCKY HILL RO AD (ERI to E AST BRE AKWATER (EB) 22 PROPERTY LINE (LW 11 PROPERTY LINE (Cl

  • 23 WAREHOUSE (WSI 12 PROPERTY LINE tHei*

24 PROPERTY LINE (PL1 O DOSIMETER ITLDI A AIR PARTICULATES AND DOslMETERS (TLDI

  • additional station not required by Specification 4.8.D.1

~

l Figure 4.8.2 Location of Onsite Monitoring S# 9ns g

O

c. a I

I

  1. A I

A 15 I

N

"!L tg I

'O MILtg I

Cape Cod Bay

  • **!L ts 1

O ptymourn s1s I

Bay 30 4A W

I o

a 50 6 A 7

so 23 A

I 0 14 10 0

0 12 I

O COSiMETERITLO)

I A AIR PARTICUL ATES ANO.

DOSIMETERS ITLD, 13 O I

S LEGENO I

1 OUx3URY 1551

  • 9 MANOMET eMEl 2 KINGSTON (KS) 10 MANOMET (MSI 3 NORTH PLYMOUTH INPI 11 MANOMET (MBl*

4 PLYMOUTH CENTER tPC 12 COLLEGE PONO ICPl

  • I 5 SOUTM PLYMOUTH (SP1 13 SAGAMORE (CSI 6 B AYSHORE drive (80*

14 PLYMOUTH AIRPORT (SA) 7 CLEFT POCK AREA ICR) 15 E AST WEYMOUTH (EWI s uANourt (MPi

16. Saquish Neck (SN),
  • additional stations not ' required by Specification 4.8.D.1 Figure 4.8.3 Location of Offsite Monitoring Stations 187d l

I I

-. e. :.. e.

y.

t 3.3 and 1.3 Cbjective:

It is expe::ed that releases of radioactive =sterial in effluents vill be kept at small fracti ns of the li its specified in Section 20.106 of 1C CE, Part 2C.

Consisten; vi h inis objective, cperating procedures shall be develeped and used, e.nd' equip en: which has been installed te =aintain centrcl ever radicactive =ateris.ls in gareous and liquid effluents produced dring ner_al reae:cr cperatiens, including expected cperational occu -

rences, shall be =aintained and used, to keep levels er radicactive =ateri-a' ** aluents released in unestricted areas as low as practicable.

I At the sa:e time the licensee is per=itted the flexibility of operatien, cc:patible with consideratiens of health and safety, to assure that the public is pr vided a dependable source of power even under = usual cperr. ting I

conditiens which may te=porarily result in releases higher than such snall fracticns> but still within the limits specified in Secticn 20.106 of 10 C??., Part 20.

It is expected that in using thir. cperational flexibility

= der = usual Operating cenditiens the licensee vill exert his best efferts I

to keep levels of radicactive =aterial in effluents as icw as practicable.

OI I

I I

I I

I I

~

I l

l ISS l

I

I.

BASES:

3.8. A and 4.8. A Licuid Ef fluents Liquid radieactive material is released periodically from the station under The radioactive controlled conditions as part of planned operations.

liquid effluents will be controlled on a batch basis and each istch will be The limits in Specif:. cation 3.S. A I

sanpled and analyzed prior to discharge.

(above background) are defined to 1.eep ratlicactive mcterini concentrations in the dischsrge canal as low as practicable and below the 11=its given in 10 CFR, Part 20.

the concentration of f pecifi cation 3.8. A.1 requires the licensac to limit radioactive materials in liquid effluents from the station to levels

20. Appendix B, for unrestricted areas. This I

specified in 10 CFF. Part specification provides assurance that no oceber of the general public can he exposed to liquids containing radioactive caterials in execss of limits considered permissibla under the Commission's Rules and Regulations.

for the release of radio-Specification 3.8.A.2 establishes an upper 11=1:

active liquid cffluents, excluding tritium and noble gases, of 10 curies durin ; any calendc cuarter without specific Cor::ission approval. The I

of this specificatien is to pernit the licennec the flexibtJity of intent the public is provided a dependable source of operation to assure that power under unusual operating conditions which may te=porarily resuir in releases higher than the levels norcally achievabic when the staticn and the The licensee has liquid radwaste equipment are functioning as designed.,

shown that releases of up to 10 curies during any calendar quarter will in concei.trations cif radicactive caterial in liquid ef fluents at result I

sm.01 percentages of the limits specified in 10 CFR Part 20; i.e.

approximately one percent'on an identified isotope basis.

In addition to the limiting conditions for operatien listed under Speci-I, fiention 3.8.A.2, the reporting requirements of Specification 3.8.A.6. in the licensee shall identify addition to the requirements of Section 6.6, that the enuse whenever the release rate of radioactive ef fluents, er. eluding

,I tritium and noble gases, exceeds 2.5 curies during any calendar cuarter, and describe the proposed program of action to reduce such release rate.

This report must he filed'within 30 days following the calendar quarter in' which the 2.5 curie release occurred.

Specification 3.8.A.3 restricts the release of tritium in radioactive Itquids to less than one percent of the concentration permissible by 10 This release, rate is considered as low as practicable on the I

~

20.

CFR Part basis of operating experience at other similar nuclear power plants.

to dilute and Specification 3.8.A.4 requires that suitable equipment I

monitor the releases of radioactive materials in liquid effluents are operating during any period these releases are taking place.

I Speelfication3.8.A.5reqbiresthat the licensee shall maintain and operate installed in the radvaate system to reduce the release of the equipment I

389 i

4 S<f

l l

BASES:

3.8 A and b 8.A Licuid Effluents (Cent'd) radioactive =aterials in liquid effluents to as lov as practicable consistent with the requirements of 10 CDi Part 50.36a. Nor=al use ll l

and =aintenance of installed ecuipment in the liquid radioactive syste:

lW is expected to result in releases of not'= ore than about 5 curies per year during normal operations. In order to keep releases of radio-active =aterials as lov as practicable, the specification requires, as a =ini=u=, Operation of equip =ent whenever the rate of release exceeds 1.25 curies per quarter.

The surveillance requirements given under Specification 4.8.A provide assurance that liquid wastes a're properly controlled and conitored during any planned release of radioactive =aterials in liquid effluents.

These surveillance requirements provide the data for the licensee and the Cc=ission to evaluate the station's performance relative to radioactive liquid wastes released to the environment. Reports on the quantities of radioactive =aterials released in liquid effluents shall be furnished to the Cc==ission on the basis of Section 6.6 of these Technical Specifications.

On the basis of such reports and any additional information the Co==ission

.J

=ay obtain frc= the licensee or others, the Cc==ission =ay fro = time to I

time require the licensee to take such action as the Co==ission dec=s appropriate.

I e

I I

I

.( ~

f 190

['

% F

l 1

i j

I l

1 i

i

{

1 l

4 i

(This Page Intentionally Left Blank) i i

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4 l

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I 191

$Y e

I

BASES:

3.8.B and I. 8.3 Airberne Effluents

(

Radioactive cases are routinely discharged from the station via the cain stack I

The limits in Specification and potentially fron the building exhaust vent.

3.8.B are derived to keep the off-site doses as lov as practicable and below the limits given in 10 CFR 20.

These specifications apply tc the interi:

period prier to operation of the augmented gaseous heldup system, when appropriate changes vill be made to the specifications.

Detailed dose calculations have been made by the applicant and are contained I

in Appendix E of the PSAR.

Independent dose calculations for several These calculations consider site meteorology and isotopic content of the effluent.

The AEC staff method locations off-site have been made by the AEC staff.

I utilized on-site =eteorological da,ta developed by the applicant.

The method utilized by the staff is described in Section T-5 2.5 of

" Meteorology and Atomic Energy-1968". The results of these calculations were core censervative than those generated by the applicant and vere thus chosen to be used as the basis of establishment of the limits. The equation given in Specification 3.8.5.1 provides a =ethod to be used in su= ing the airborne I

effluents frem the main stack and the building exhaust vent that vill assure in excess of the limits specified in that total off-site doses are not The centinuous release of radioactive noble gases in airborne 10 CFR 20.

effluents at the rates permissible by Specification 3.8.B.1 are calculated by the Consissien's staff to correspond to an upper limit does of 500 mre= per year at the most restrictive land boundary (SW of the station).

~

The permissible release rate from,the plant stack alone by this specification I

is about 0.36 curies /second based on an average disintegration energy of 0.7 Mev.

The applicaticn of the average disintegration energy for the released radioactive gases cakes the formula appropriate to a vide range of release conditions and extended holdup periods.

The release rate Specifications fer a radiciodine and radioactive material in particulate form with half-lives, greater than eight days are dependent on existing radienuclide pathways to can.

The pathways which vere examined for these Specifications are: 1) Individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent l

consumption by can, and 3) deposition onto grassy areas where milch animals l

Methods for estimating doses to I

graze with consu=ption of the milk by man.

the thyroid via these pathways are described in Draft Regulatory Guide 1.AA.

The offsite location with the highest anticipated thyroid dose rate from radiciodines and radioactive material in particulate form.vith half-lives I

greater than eight days was determined using on-site meteorological data and 12 the expressions described in Draft Regulatory Guide 1.AA.

Specification 3.8.E.2 (a) limits 'the release rate of radiciodines and radioactive material in particulate form with half-lives greater than eight l

days so that the corresponding an'nual thyroid dose via the most restrictive pathway is less than 1500 trem. -

191A

I~

b I,

.B and h.8.3 Airborne Effluents (Cont'd) f For radiciodines and radioactive material in particulate form with half-lives greater than ei6ht days, the cost restrictive location is I a dairy cow located 5600 meters in the west direction (vent X/Q =

2.2 x 10-7 sec/c0; stackX/Q=1.8x10-8sec/m3).

Specification 3.8.3.2(b), (c), (d) and (e) establishes upper offsite I levels for the releases of radiciodines and radioactive material in l

particulate fe= with half-lives greater than eight days at twice the

(

design objective annual quantity during any calendar quarter, or four I times the design objective annual quantity during any period of 12 g

In addition to the~ limiting conditions for consecutive mer.ths.

operation of Specifications 3.8.E.2(a) through (e) the reporting requirements of 3.8.3.2(f) provide that the cause shall be identified I whenever the release of Easeous effluents exceeds one-half the design objective annual quantity during any calendar quarter and that the I proposed prog-am of action to reduce such release rates to objectives shall be described.

.JSpecification 3.8.E.3 establishes as low as practicable limits for the release The values chosen 12 I levels of gaseous effluents for the interi: period.

are consistent with interi: limits used for other BWR's without Under these specifications, the licensee will aug=ented syste=s.

I

' required to take such actions, including reducing station power, other appropriate measures, as may b'e necessary to keep the average radioactive gaseous releases below this level, but afforded the flexibility regarding short-ter= plant operation to caintain station power for public needs.

Specification 3.8.s.6 requires that the primary containment atmosphere receive treatment for the removal of gaseous iodines and particulates I prior to its release whenever the reactor is in the RUN mode.

This specification provides a further reduction from this source of release of iodines and particulates fro = the station.

The surveillance requirements given under Specification 4.8.B provide assurance that radioactive gaseous effluents from the station are properly These surveillance I r:ntrolled and monitored over the life -of the station.quirements provide the d co ovaluate the station's perfor=ance relative to radioactive gaseous vastes Reports on the quantities of radioactive Ireleasedtotheenvironment. materials released in gaseous effluents shall b mission on the basis of Section 6.6 of these Technical Specifications.

On the basis of such reports and any additional information the Commis-sion may obtain fro = the licensee or others, the Cocmission may from time I to time require the licensee to take such action as the Con =ission deems cypropriate.

I

~

'.191B 1

,lI l

.7 BASES :

3.8.D and 4.8.D Environmental Monitoring Program The operational environmental monitering program is based upon a preop-erational program which is described in Section 2.6, Volttme 1 of the

~

FSAR (A=endment 22). The preoperational environ = ental monitoring pro-gram han been gatherinn. data on all ca=ple types described in Specifica-tions 4.8.D since at least September 1970, and in many cases, since August 1969. lience, one to two years of data vill be availabic to draw I

baselines against which to evaluate plant effects.

Evaluations after plant startup will be made on the' basis of these base-lines, considering geography and time of year where these factors are I

applicable, and by comparisons to control stations.

The reference sc=ples provide a running background which will make it possible to distinguish cignificant radioactivity introduced into the I,

environment by the operation of the station.

In those cases where a statistically significant increase may be seen in a particular sa=pling vector but not in the control station, meterology and/or specific nuclide analysis vill be used to identify the source of the increase.

The planned sempling frequencies vill assure that significant changes in the environmental radioactivity can be detected. The materials which first show changes in radioactivity are sc= pled most frequently. Those which are less effected by transient changes but chov long ter= accu =nictiens are sampled less frequently.,,However, the specific cc=pling datcc are not crucial, and adyerse weather conditions or equipment failure may on oc-casion prevent collection of specific samples on the planned frequency.

I.

The progrcm has considered the radiological matters identified by the Fish and Wildlife Service in their correspondence with the AEC.

ll I

II 11 I

192 S

9#

e II

I I

BASES:

t 3.6.E and 1.8.E Mechanical Vacuu: Pump 4

The p.:rpose of isolatire the ecchanical vacuum pa=p line is to licit the release of activity from the :nin condenser. Darir; an accident, fission products vould be transp6rted fro = the reactor throu6h the ccin sten:

lines to the condenser. The fission product radioactivity would be sensed by the enin stec line radiocetivity ::enitors which initiate isolation.

bI

  • 6 O

e I

e O

Ie k

e

'e I

e 193 I

S I

f

I.:;

n I

C.

Unicue Resertiet Recuirements 1.

Radioactive Effluent Release Recort I

A reporr shall be submitted to the Commission within 60 days after January, 1 and July, 1 of each year specifying the quantity of'ench 4

of the principal radionuclides released to unrestricted areas in I

liquid and gaseous affluents during the previous 6 mo'ths.

n The fornat and content of the report shall be in accordance with Regulatory Guide 1.21 (Revision 1) dated June, 1974 2.

Environmental Prostam Data a.

Annual Report. A report on the radiological environmental surveillance program for the previous 12 months of operation I

shall be submitted to the Director of the NRC Regional office (with a copy to the Director, Office of Nuclear Reseter Regulation) as a separate document within 90 days af ter January I.

ations, and statistical evaluation of the results of the radio-1 of each year. The reports shall include summaries, interpret-logical environmental surveillance activities for the report.

period, including a comparison with preoperational studies, I

operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of any land use surveys which affect the choice of sample locations. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the ~ problem and a preposed

,l course of action to alleviate the probles.

Results of all radiological environmental sanples shall be In the event that I..

....,... summarised and tabulated on an annual basis.some results are not av report shall be submitted, noting and explaining the reasons for the missing results. The missing data shall be subsitted 3

E as soon as possible in a supplementary report.

/

~

b.

The following svent shall be the subject of a written report to the

~

Director of the NRC Regional Office (with a copy to the Director.

r Office of Nuclaar Reactor Regulation) within 60 days of the occur-rence of the events measured levels of radioactivity in an environ-mental sampling meditas detarmined to exceed the reporting level I

values of Tab 1h 6.9.C-1 when averaged over any calendar qur.rter

'y sampling periol. When more than one of the radionuclides in Table 6.9.0-1 are detected above lower limits of detection (LLD) in the R

sampling medium, this report shall be submitted if t

.}

I Concentration (1)

  • Concentration (2)

M*

+

+... g 1.0 g,g,gg g,y,y (g)

I.init Level (2)

When radionuclides other than those in Table 6.9.C-1 are detected above LLD and are the result of plant affluents, this report shall N

be submitted if the potential annual does to an individual is l

equal to or greater than quarterly and/or yearly limits of Table Z

6.9.C-2.

Thia: report is not required if the menscred level of I

radioactivity was not the result of plant eR1uents; however, in such an event, the condition shP" P. reported and described in j g the Annual Radiological. Fnvi aantal Monitoring Report.

i l

- 2D-Anendment No. 57 r

l g.

L

M M

M M

l t

. f TABLE 6.9.C-1 k

REPORTING LEVELS FOR RA010 ACTIVITY CONCENTRATIONS IN ENVIROMENTAt SAMPLES a

=

P Reporting Levels m

Water Airborne Particu} ate Fish, Mussels Milk Vegetables Analysis (pC1/1) or Gases (pC1/M )

(pC1/Kg, wet)

(pcl/1)

(pC1/kg, wet) l H-3 2 k 104

'Mn-54 I x.10 3 x 10 3

4 2

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I 3.

Special Reports Special reports shall be submitted as indicated in Table 6.9.1.

I 6.10 RECORD RITENTION A.

The following records shall be retained for at least five years:

1.

Records of facility operation covering time interval at each power level.

2.

Records of prine'ipal maintenance activities, inspections, repair and replacement of principal items of equipment related to

~

nuclear safety.

3.

Reportable Occurrence Kaports.

Records of turve' llance activities, inspections and calibrations i

4.

required by these Technical Specifications.

5.

Records of reactor tests and experiments.

6.

Racords of changes made to Operating Proceduras.

7.

Records of radioactive shipments.

8.

Records of sealed source leak tests and results.

9.

Records of annual physical inventory of all source material of record.

3.

The following records shall be retained for the duration of the Operating License:

1.

Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

2.

Records of new a'ad irradiated fuel inventory, fuel transfers and assembly burnup" histories.

3.

Records of facility radiation and contamination surveys.

4.

Records of radiation exposure for all individuals entering radiation control areas.

5.

Records of the service lives of all hydraulic and mechanical snubbers listed 'on Tables 3.6.I(a) and 3.6.I(b) including the date at which the service life commences and associated installa-tion and maintenance records.

/

Amendment No. N 60 224 l

TABLE 6.9.1 Area Reference Submittal Date a.

Secondary Containment 4.7.C.c Upon completien Leak Rate Testing (1) of each test (2) b.

In-service Inspection 4.6.G.

Five years after Evaluation commercial operation c.

(Deleted) 30 d.

Gross Gaseous Release 4.8.3.

Ten days after the 0.05 C1/ set for 48 release occurs Hours NOTES:

1.

Each integrated leak rate test of the secondary containment shall be the subject of a sa==ary, technical report. This report should include data on 'he wind speed, vind direction, outside and t

inaide te=peratures during the test, concurrent reactor building pressure, and emergency ventilation flow rate. The report shall also include analyses and interpretations of those data which de=enstrate ce=pliance with the specified leak rate limits.

2.

The report shall be submitted within 90 days after completion of each test.

Test periods shall be based on the com=ercial service date as the starting point.

e O

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b

$I S

Y 4

225 I

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lI I

!.l APPENDIX E - 1985 GARDEN & HILK-PRODUCING ANIMAL SURVEY I

l

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OFFZCE MEMORAWDUM Boston Edison Company RMG Control Numoer To: T. L. Sowdon From: C. E. Bowma Record Type A4.08 Date: April 29, 1986 Dept. Doc. ERHS86-116 Non-Safety Related

Subject:

1985 GARDEN & MILK-PRODUCING ANIMAL CENSUS Distribution:

As required by PNPS Environmental Technical Specifications, the 1985 Garden I

and Milk-Producing Census was conducted in October 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 confirmed.

The garden near the site boundary of 0.7 miles W did not exist in 1984 or 1985; however, a garden 1.0 miles W of the site boundary was identified in 1984 and was still available in 1985.

These gardens are the closest and largest in the near vicinity (1 mile) of PNPS, and are less than 500 square feet. They do represent conservative garden locations for sampling analysis and dose calculation.

With the assistance of Mr. Robert Tis, I

vegetation samples were collected from four locations on 10/3/85. Only one location was greater than one mile from PNPS. A sample of lettuce was collected from the J. Work Residence (0.6 miles ESE) on John Alden Road; I

vegetation leaves were obtained from the Malmgren Residence (1.0 miles W) on Rocky Hill Road, from the Jenkins Residence (1.0 miles SE) on Rocky Hill Road, and from the Whipple Farm (1.5 miles SSW) off Doten Road.

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 In-spector forwarded a letter (attached) to Boston Edison in 1984 indicating that the only milk-producing animals within five miles of PNPS are located at the Plymouth County Farm; however, Boston Edison was unable to receive a reply from the Plymouth Animal Inspector for the year of 1985 concerning the same issue.

The Plymouth County Farm is a participant in the Environmental Monitoring Program. During the 1982 Census, a milk-producing cow was located on Beaver Dam Road (2.5 miles 5).

This animal is still located on Beaver Dam Road.

The owner did not participate in the 1985 Environmental Monitoring I

Program, and has not indicated an interest for participating in the 1986 Environmental Monitoring Program.

In conclusion, the 1985 Census indicates that there are no additional indicator stations available for milk sampling.

CEB/dvc I

Attachment I

t

TOWN OF PLYMOUTH omCE OF ijg 3

W BOARD OF HEALTH I

March 1!+, 1985 Boston Edison Company I

800 Boylston Street Bost,n. MA 02199 Attention:

Br.an P. Lunn t

Dear Mr. Lunn:

Please be advised that the only milk producing animals that I a= aware of within the five mile redius of the Pilgrin Nuclear Power Plant are those housed at the Plymouth County farm. As you may know, this is located at the Plymouth Coimty Hou=e of Correction, Obery Street, Plymouth.

If you have any further questions regarding this matter please contact me.

Sincerely, I

tre m o D DJoM /db Milton D. Wood Plymouth Animal Inspector I

11 LINCOLN STREET PLYMOUTH, M ASSACHUSETTS 02360 Tel. 7471620 Ext. 33 l

_

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