Text

Environ Radiation Monitoring Program Rept 17,1984
	ML20113E180
Person / Time
Site:	Pilgrim
Issue date:	12/31/1984
From:	Bowman C, Harrington W, Sowdon T; BOSTON EDISON CO.
To:	Murley T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	17, BECO-85-65, NUDOCS 8504160206
	Download: ML20113E180 (134)
	v • d • e

I l PILGRIM NUCLEAR ' POWER STATION I

I ENVIRONMENTAL RADIATION MONITORING PROGRAM l REPORT NO.17 I

~

l I JANUARY 1 THROUGH DECEMBER 31,1984 l I

I ISSUED: APRIL 1985 I

BY: NUCLEAR MANAGEMENT SERVICES DEPARTMENT I ENVIRONMENTAL AND RADIOLOGICAL HEALTH AND SAFETY GROUP I

I BOSTON EDISON COMPANY I

I sosrom I # EDISON 800 Boylston 5t. Boston, MA 02199 I '

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I I BOSTON EDISON COMPAMY

' PILGRIM NUCLEAR POWER STATION Environmental Radiation Monitoring Program REPORT NO. 17 January 1, 1984 through December 31, 1984 I

I Prepared by: == : e - ~

Christine E./ Bowman Senior Radiological Engineer I s I

I Approved by: g--r1% ; z ps Thomas L. Sowdon I Environmental and Radiological Health and Safety Group Leader

.I Date of Submittal: April 1, 1985 II I

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I TABLE OF CONTENTS Section Page, I Introduction and Summary 1-1 II Description of Monitoring Program 2-1 III Results of Analyses 3-1

' 3-5 A. Air Particulates B. Iodine 3-12 C. Soil 3-15 D. Direct Radiation 3-17 E. Waterborne 3-28 F. Shellfish 3-32 G. Algae (Irish Moss) 3-35 H. Lobster (Arthropods) 3-39 I. Fish 3-42 J. Sediments 3-46 K. Milk 3-52 L. Cranberries 3-59 M. Vegetation 3-62 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 i I Appendix D Radiological Environmental Monitoring Program D-1 l Appendix E 1984 Garden and Milk Animal Survey E-1

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I f ST OF TABLES Table Number Page 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 Filters 3-13 III-D-1 Thermoluminescent Dosimeter Locations 3-21 III-D-2 Results of TLD Measurements - Quarter #1

3-22 III-D-3 Results of TLD Measurements - Ouarter #2 3-23 III-D-4 Results of TLD Measurements - Quarter #3 3-24 III-D-5 Results of TLD Measurements - Quarter #4 3-25 III-D-6 Quarterly Average Exposure Rates 3-26 III-D-7 Field Survey Exposure Rates 3-27 III-E-1 ERMAP Results - Waterborne 3-29 III-F-1 ERFAP Results - Shellfish 3-33 III-G-1 ERMAP Results - Algae 3-37 III-F-1 ERMAP Results - Lobster 3-40 III-I-l ERMAP Results - Fish 3-44 III-J-l ERMAP Results - Sediment 3-49 III-J-2 Results of Sediment Analysis for Plutonium 3-51 III-K-1 ERMAP Results - Milk 3-54 III-L-1 ERMAP Results - Cranberries 3-60 III-M-1 ERMAP Results - Vegetation 3-63 I III-N-1 ERMAP Results - Forage 3-62 I -

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LIST OF FIGURES Figure Number Page III-A-1 Gross Beta Activity - Air Particulates - 3-10 Indicator Stations III-A-2 Gross Beta Activity - Air Particulates - 3-11 Control Station s.

III-B-1 Concentrations of I-131 - Charcoal Filter - 3-14 Indicator Stations III-B-2 Concentrations of I-131 - Charcoal Filter - 3-15 Control Station III-K-1 Concentrations of Cs-137 in Milk 3-57 III-K-2 Concentrations of Sr-90 in Milk 3-58 l

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I Introduction and Summary I.

This report presents a summary of the results of measurement of direct I radiation and radioactivity in environmental media in the vicinity of the Pilgrim Nuclear Power Station - Unit 1 (PNPS-1) and at selected control I

locations for the period January 1 - December 31, 1984. The results of this Program indicate that PNPS-1 has had a negligible and most often

.s 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.

PNPS-1 was in an outage during 1984. PNPS-1 shutdown on December 10, 1983 for a refueling and recirculation pipe replacement, outage and startup commenced on December 30, 1984.

I In general, there were a greater number of positive measurements of nuclides specific to reactor operation observed during 1984 versus 1983, due to the extensive outage.

A tabulation of radicactive effluents from the PNPS-1 is provided in Appendix B for the 1984 calendar year.

There were no Anomalous Measurement Reports made for the calendar year of 1984.

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1-1 i _- _ - _ _ _ _ _ _ _ _ _ _

.-__.a- ... .. ...

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, two milk samples, one air particulate sample, one charcoal filter sample, plus occasional failures of the air samplers, one 6ay sample due to unavailability, and three fish samples and one lobster sample due to unavailability. In addition, a total of three TLDs we're found to be missing from their field locations during 1984.

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 1984. 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 1984. During 1984, two milk samples were not collected from the Plymouth County Farm and the Whitman Farm during week number 32 (early August) due to the fault of Boston Edison.

1-2

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 i.ncorporates Asupplemental provision as specified in the Set:lement Agreement between the Massachusetts Wildlife Federation and Boston Edison Company, June 9, 1977 The exceptions to the program are as follows:

1) There is no TLD station at Saquish Neck since the Mass Wildlife Federation has not yet provided a means for placement and retrievel 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 W and ESE site boundaries.

The 1984 site Census conducted according to Technical Specification requirements determined that there are several vegetable gardens near the site boundary in the W-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 cabbage was collected on 9/26/84. In the west direction, the location of the nearest observed garden of approximately 500 square feet was at the Malmagren residence (1.0 miles W). During the nearest observed garden in the west direction was the Evan's residence (0.7 miles W). This location did not have a garden in 1984.

Another sample of rhubbarb was collected on 9/26/84 from the Jenkins residence (1 mile SE).

2-1

A sample of rhubbarb was collected from this location on 9/26/84. In addition to the above, a sample of beet leaves was obtained from the Whipple Farm (1.5 miles SSW) on 9/26/84.

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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III. Results and Analyses This section summarizes the results of the analyses of environmental media samples in compliance with the monitoring program descr'ibed in Appendix D. The section is divided into sub-sections, each of which 5 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 i of the sample variance);

3) the lowest and highest calculated concentrations;

4) the number of positive measurements divided by the total number of measurements.

3-1

Entries listed under the heading LLD* are the required LLDs that are to be met per PNPS-1 Technical Specification requirements.

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

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

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

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Lower Limit of Detection I

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TABLE III-A-1 Sample Station Identification Codes Media Station Code Station Location Number Air Particulate 00 Harehouse (0.03 mi-SSE) and 01 Rocky Hill Road (0.8 mi-SE)

Iodine Filters 03 Rocky Hill Road (0.3 mi-HNH) 06 Property Line (0.34 mi-NH) 07 Pedestrian Bridge (0.14 mi-N) 08 Overlook Area (0.03 mi-H) 09 East Breakwater (0.35 mi-ESE) 10 Cleft Roak (0.9 mi-S)

$ 15 Plymouth Center (4.0 mi-H-HNH) 17 Manomet Substation (2.5 mi-SSE) 21 East Heymouth (control-21 mi-NH)

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

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

Algae (Irish Moss) 11 Discharge Canal Outfall 15 Manomet Point 22 E111sville (Control 8 mi-SSE))

34 Brant Rock (Control, 12 mi-NNN)

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

Fish 2 Round Hill Point-Offshore-(Control) 11 Vicinity of Discharge Canal 12 Harren Cove 13 Duxbury Bay (Control) 14 Vicinity of Plymouth Beach 19 White Horse Beach 21 Auto Trawl Station-Offshore-(Control) 22 Offshore-(Control) 28 Cataumet, Bourne-(Control) 29 Priest Cove-Offshore-(Control) 96 Houth of North River-Hanover (Control) 97 Nantucket Sound (Control) 99 Provincetown-Offshore (Control)

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

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

Cranberries 13 Manomet Point Bog (2.5 mi-SE) 14 Bartlett Road Bog (2.8 mi-SSE/S) 23 Pine St. Bog (Control-17 mi-HNH) u Vegetation 11 Plymouth County Farm (3.5 mi-H) 16 Work Residence (0.6 mi-ESE) 17 Evans Garden (0.7 mi-H) 27 Bridgewater Farm (Control-20 mi-H) 43 Whipple Farm (1.5 mi-SSH)

Malmgren Residence (1.0 mi-H)

I 75 76 Jenkins Residence (1.0 mi-SE)

Beef Forage 11 Plymouth County Farm (3.5 mi-H)

I 21 27*

Whitman Farm (Control-21 mi-H)

Bridgewater Farm (Control-20 mi-H) l l

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Unavailable during 1984.

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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 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).

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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.

The air particulate filter at Station #00 (Warehouse) for wJek number 51 was not analyzed as the filter was lost by Boston Edison during sample preparation.

During 1984, there were several instances of low sample volume due to a variety of causes, such as power failures, motor failures, broken fittings, and crimped sample lines. Of these, there were two instances which resulted in the MDC not being met. The MDC was not met for Station #07 (Pedestrian Bridge) collected on 5/29/84 due to a low sample volume which was the result of a motor failure of the air sampler. In addition, the MDC was not met for Station #00 (Warehouse) l collected on 10/1/84 due to a low sample volume which was the result of lumber leaning on the line, thus blocking the flow.

3-5 l . _ _ _ .

Positive measurements of a specific nuclide characteristic of reactor operation (C0-60) were observed in five quarterly composite samples.

The following stations had positive measurements of Co-60: Warehouse (Station #00-0.03 mi-SSE), second and third quarter composites; Pedestrian Bridge (Station #07-0.14 mi-N), third and fourth quarter composites; and, Overlook (Station #08-0.03 mi-H), third quarter composite. These three stations are the closest stations to PNPS. The 6

highest mean concentration of Co-60 was observed in the Overlook third quarter composite sample. The positive indications of Co-60 were due to the effluents of PNPS-1. The only other positive measurements observed in the quarterly composite samples were due to naturally occurring nuclides (Be-7, AcTh-228 and K-40).

However, even if an individual were to breathe air with the Co-60 concentration (589+-53)E-5 pC1/m', the maximum exposed individual would receive an annual dose of about 0.00008 mrem to the total body and about 0.031 mrem to the maximum exposed organ (Teen-Lung).

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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TABLE III-A-2 ERMAP RESULTS-AIR PARTICULATE FILTERS EDIUM: AIR PARTICtLATE LNITS: PCI/CU. M INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS ennennunute **uentunenseennen e n **ut**** u et RADIONJCLIDES EAN EAN EAN (NO. ANALYSES) RE(XIIRED RANGE STA. RANGE RANGE (he-ROUTIE)e LLD NO. DETECTED *e NO. NO. DETECTEDet NO. DETECTED **

GR-B (570) .01 ( 2.3 t .1)E -2 07 ( 2.7 i .3)E -2 ( 2.4 i .2)E -2

( 0) ( 4.7 - 1490.0)E -4 ( 5.6 - 1490.0)E -4 ( 5.5 - 65.1)E -3

(510/518)* *( 50/ 52)* *( 51/ 52)*

BE-7 i 43) ( 3.6 2 .1)E -2 06 ( 3.8 i .1)E -2 ( 0.7 i .4)E -2

( C) ( 2.7 - 4.9)E -2 ( 3.6 - 4.2)E -2 ( 2.7 - 4.6)E -2

( 40/ 40)* *( 4/ 4)e *( 4/ 4)*

K-40 ( 44) ( 6.3 t .7)E -3 06 ( 9.2 1 1.6)E -3 ( 4.9 1 1.2)E -3

( 0) (-1.9 - 14.0)E -3 ( 6.9 - 14.0)E -3 ( 2.0 - 8.0)E -3

( 5/ 40)* *( 0/ 4)e *( 1/ 4)*

CR-51 ~( 44) ( 4.2 i 3.4)E -4 01 ( !.9 t 1.1)E -3 ( !.7 i .7)E -3

( 0) (-4.8 - 4.8)E -3 (-5.5 - 45.4)E -4 ( 4.2 - 35.0)E -4

( 0/ 40)* *( 0/ 4)* e( 0/ 4)*

PN-54 ( 44) ( 4.9 1 3.0)E -5 00 ( 2.1 i 1.0)E -4 ( 4.8 i !!.1)E -5

( 0) (-4.5 - 4.4)E -4 ( 2.0 - 42.1)E -5 (-2.0 - 3.2)E -4

( 0/ 40)e *( 0/ 4)* *( 0/ 4)*

CO-53 ( 44) .02 (-3.3 2 3.4)E -5 OS ( 9.2 i 13.9)E -5 (-1.1 1 100.5)E -6

( 0) (-4.2 - 3.5)E -4 (-2.9 - 3.5)E -4 (-2.3 - 2.4)E -4 l

( 0/ 40)* *( 0/ 4)* et 0/ 4)e jg FE-59 ( 44) ( !.5 1 .9)E -4 17 ( 7.0 t 3.3)E -4 ( 6.0 1 12.3)E -5 l3 ( 0) (-1.1 -

( 0/ 40)*

1.4)E -3 (-1.6 - 13.9)E -4

( 0/ 4)*

(-1.5 - 4.1)E -4 et 0/ 4)*

CO-60 ( 44) .02 ( 4.1 i 1.6)E -4 08 ( 1.7 t 1.4)E -3 (-1.4 i 53.5)E -6

( 0) (-5.3 - 58.9)E -4 ( 8.4 - 589.0)E -5 (-1.2 - 1.3)E -4

( 5/ 40)* *( 1/ 4)* *( 0/ 4)*

I ZN-65 ( 44) ( 2.1 i 7.4)E -5 07 ( 4.9 i 3.2)E -4 (-1.4 1 2.9)E -4

( 0) (-1.0 - 1.4)E -3 (-1.3 - 13.9)E -4 (-6.2 - 7.2)E -4

( 0/ 40)* ef 0/ 4)* *( 0/ 4)*

l l e NON-ROUTIE REFERS TO TE NLPBER OF SEPARATE EASUREENTS WHICH WERE GREATER I THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

e THE FRACTION OF SAMPLE ANALYSES YIELDIt0 DETECTABLE EASLFIENTS

! (I.E. >3 STD ICVIATION3) IS INDICATED WI"' *( )*.

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I TABLE III-A-2 (CONTINUED)

EDILM: AIR PARTICtLATE UNITS: PCI/CU. f(

INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS fiffffffffffffffff fifffffffffffffffffffffff fiffffffffffffff RADIOMJCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (WIN-ROUTIE)e LLD NO. DETECTED 45 NO. NO. ETECTEDIi NO. DETECTEDIe ZR-95 ( 44) (-1.0 t .8)E -4 15 ( 4.4 1 2.1)E -4 (-5.4 1 37.6)E -5

( 0) (-1.5 - .9)E -3 (-1.1 - 8.7)E -4 (-1.1 - .5)E -3 f( 0/ 4015 f( 0/ 415 f( 0/ 4)f I f@-95 ( 44)

( 0)

(-9.0 1 40.3)E -6

(-4.4 -

f( 0/ 40)f 7.3)E -4 08 ( 2.5 i

(-2.7 -

f( 0/ 4)f 2.1)E -4 7.3)E -4

( 1.1 i f( 0/ 4)f

.8)E -4

(-6.6 - 31.0)E -5 RU-103 ( 44) (-1.4 1 4.1)E -5 15 ( !.2 i .9)E -4 ( !.1 i .5)E -4

( 0) (-5.6 - 6.7)E -4 (-8.2 - 33.6)E -5 ( 2.1 - 23.9)E -5 f( 0/ 40)f f( 0/ 4)f f( 0/ 415 RU-106 ( 44) ( !.91 2.6)E -4 06 ( !.2 t 1.1)E -3 (-7.6 1 7.9)E -4

( 0) (-4.2 - 3.5)E -3 (-1.5 - 3.5)E -3 (-2.6 - .7)E -3 f( 0/ 4015 f( 0/ 4)f f( 0/ 4)f I-131 ( 44) ( !.7 t 2.0)E -4 10 ( 1.7 i .5)E -3 (-8.0 t 25.2)E -5

.(-2.8 - 3.0)E -3 ( !.0 - 3.0)E -3 (-6.7 - 3.9)E -4 I

( 0) f( 0/ 40)f f( 0/ 4)f f( 0/ 4)f CS-134 ( 44) .01 (-9.0 1 3.4)E -5 10 ( !.6 t 1.3)E -4 (-1.2 2 1.4)E -4 I ( 0) (-7.5 -

f( 0/ 40)f 4.9)E -4 (-1.7 -

f( 0/ 4)f 4.9)E -4 (-3.5 -

f( 0/ 4)f 2.8)E -4 CS-137 ( 44) .01 ( !.5 t 3.1)E -5 00 ( 1.8 i .7)E -4 (-1.3 t 6.0)E -5

( 0) (-5.1 - 3.5)E -4 ( 2.8 - 34.9)E -5 (-1.4 - 1.3)E -4 f( 0/ 40)f f( 0/ 4)f f( 0/ 415 BA-140 ( 44) (-1.9 1 1.3)E -4 21 ( 7.0 t 4.4)E -4 ( 7.0 t 4.4)E -4

( 0) (-1.9 - 2.2)E -3 (-3.6 - 14.3)E -4 (-3.6 - 14.3)E -4 f( 0/ 4019 f( 0/ 414 f( 0/ 4)f CE-141 ( 44) ( 5.3 1 3.7)E -5 03 ( 2.3 1 1.7)E -4 ( !.4 t 1.1)E -4

( 0) (-3.6'- 6.6)E -4 (-7.1 - 66.3)E -5 (-7.1 - 36.7)E -5 f( 0/ 4015 f( 0/ 4)f f( 0/ 4)f CE-144 ( 44) (-9.6 2 12.0)E -5 07 ( 6.2 t 2.3)E -4 ( 4.9 t 34.7)E -5

( 0) (-1.7 - 1.5)E -3 (-5.1 - 96.4)E -5 (-6.1 - 10.1)E -4 f( 0/ 40)f f( 0/ 4)f f( 0/ 4)f f NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREMENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR THE PERIOD OF TE REPORT.

ff TE FRACTION OF SAWLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (I.E. >3 STD EVIATIONS) IS INDICATED WITH f( 15

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TABLE III-A-2 (CONTINUED)

I EDIUM: AIR PARTICULATE UNITS: PCI/CU. H INDICATOR STATIONS STATION WITH HIGEST M CONTROL STATIONS fiffffffffffffffff fifffffffffffffffffffffff fiffffffffffffff RADIOWCLIDES M EAN M (NO. ANALYSES) EQUIRED RANGE STA. RAEE RANGE (IdN-ROUTIElf LLD NO. DETECTEDif NO. NO. DETECTED *f NO. DETECTEDff AC-228 ( 44) ( 2.4 i 1.3)E -4 8.5)E -4 ( 4.5 1 2.3)E -4 I

09 ( 7.8 i

( 0) (-1.0 - 3.2)E -3 (-6.2 - 32.2)E -4 ( 5.8 - !!!.0)E -5 f( 1/ 40)f f( 1/ 4)f f( 0/ 4)f f NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES TE AVERAGE BACKGROLND FOR THE PERIOD OF TE REPORT.

ff THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (I.E. >3 STD THATIONS) IS INDICATED WITH f( )f.

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

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i III.B. Iodine The same sample collection systems used to collect airborne particulates are used to collect gaseous lodine 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

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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.

One charcoal filter sample was not analyzed due to the fault of Boston Edison. The charcoal filter sample for Station #17 (Manomet) was not analyzed for week number 18 as a blank filter was mistakenly submitted for analysis. In addition, the charcoal filter was then placed in the field at Station #17 for week #20.

The MDC for iodine analysis was not met for two samples at two different stations. The MDC was not met for Station #07 (Pedestrian Bridge) collected on 5/29/84 due to a low sample volume which was the result of a motor failure of the air sampler. In addition, the MDC was not met for Station #00 (Warehouse) collected on 10/1/84 due to a low sample volume which was the result of lumber leaning on the sample line, thus blocking the flow.

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

3-12

-...-..... - .- = _.--.___ ___- _--.~.. .. .. -- . .--- ... ..

TABLE III-B-1 ERMAP RESULTS-CHARCOAL FILTERS EDILM: CHARC0AL FILTER LNITS: PCI/CU. if I

INDICATOR STATIONS STATION WITH HIGEST H CONTROL STATIONS )

enutennunen u n ne nte ne n n u n ne eenetetestuen i RADIOMJCLIDES M M M I (NO. ANALYSES) M IRED RANGE STA. RANGE RANCE )

(NON-ROUTIEle LLD NO. DETECTEDee NO. NO. DETECTEDee NO. MTECTEDee I-131 (572) .07 (-3.0 i .5)E -3 06 (-3.4 i 12.2)E -4 (-2.6 i 1.3)E -3

( 0) (-9.4 - 2.8)E -2 (-2.0 -. 1.4)E -2 (-3.4 - 1.5)E -2 I

( 0/520)e *( 0/ 52), *( 0/ 52)e e NON-ROUTIE REFERS TO TE NLMDER OF SEPARATE EASLEEENTS WHICH ERE mEATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SMPLE ANALYSES YIELDING DETECTABLE EASLFEMENTS (I.E. >3 STD DEVIAT!0NS) IS INDICATED WITH *( )*.

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. .___..._-i __ .____ _ , _____._.______ -._._ ..._. __-

g FIGURE III-B-1

' E CONCENTRATIONS OF I-131 CHARC0AL FILTERS INDICATOR STATIONS l

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CONCENTRATIONS OF I-131 CHARCOAL FILTERS I CONTROL STATION I

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TII.C. Soil Soll surveys at eleven locations are required once every three years in

, compliance with the revtsed Technical Specifications which went into effect on April 19, 1977. These in-situ surveys were conducted during May,.0ctober and December of 1982. The results of these surveys are i included in /.ppendix C of this report.

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III.D. Direct Radiation

1. Continuous Thermoluminescent Dosimetry Thermoluminescent dosimeters (TLD) of the CaSO.(Dy) type are used to record direct gamma radiation from all sources including l

direct and scattered radiation from Nitrogen-16 in the turbine building, and cosmic and other natural and artificial gamma radiation. TLD's are installed at the locations identified in Table III-D-1.

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

In addition to average doses for each TLD for each readout period, geographic regional average doses for sectors of different nearness are computed; viz, in immediate proximity to .

PNPS, more distant but near the site boundary, up to several miles away " neighborhood", and far away (background). Each set of data show consistent trends; the near plant dosimeters (orimarily OA, PB, and WS) stand out among all readings and have an average above the dose rates further away. The next region has a lower average dose rate, and beyond 0.7 miles (distant neighborhood and background) the dose rates are statistically consistent. In all cases, the near plant levels are distinctly higher than those off-site and off-site dose rates are not significantly sensitive to distance variations beyond the site itself. Thus, beyond the " exclusion area" (for this purpose, the 0.25-0.7 mile region), dose rates show no significant plant 3-17

.-~-...-_a-. - - . ~ . . . . . . . . - . - . . . -

l I effect; populated areas are therefore beyond the limits of elevated dose rates.

i l

2. Field Survey !

l A gamma exposure survey of Plymouth Beach and Priscilla/ White 4

Horse Beach was conducted during July of 1984. The results of I .

this most recent survey are in agreement with the last seven beach surveys conducted for 1977 through 1983. In addition, a comprehensive soll survey of 11 locations was conducted during the spring and fall of 1982. This study included both gamma exposure rate measurements and in-situ gamma spectrometry analysis for each 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-111 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 1

l (Plymouth and Priscilla/ White Horse) and a control location (Duxbury). The detector's calibration was checked before each measurement. The data (Table III-D-7) indicate that the exposure rates at Plymouth Beach (behind Berts Restaurant) and Priscilla/ White Horse Beach are not significantly greater than the exposure rates measured at the control station in Duxbury, i

l l 3-18 l

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The small differences are likely due to the presence of granite beach stones which are essentially absent at the Duxbury location. Plymouth Beach (Outer) showed a slightly elevated exposure rate most likely due to a different beach sand composition at the 1984 measurement site of course sand and small stones. It has been demonstrated that proximity to beach stones results in higher exposure rates than in sandy ar.eas (see Annual Report No. 10).

This survey indicates that the natural background exposure rate at beaches near Pilgrim Station is probably 6-11 UR/hr. These results are in complete agreement with similar measurements performed in Maine', where the natural background exposure rate at shoreline locations was found to vary between 6.6 and 14.5 uR/hr. These exposure rates were also found to vary directly with the size and proximity of granite outcroppings5 .

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 9.3 to 10.5 uR/hr with an average of 9.7 uR/hr.

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

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TABLE II;.-D-2 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #1 T984 I Station Micor/

Hour - 2 Sigma CP 5.87 +- 1.36 CR 7.92 +- 1.62 CS 1.77 +- 0.28 ER 5.60 +- 2.30 EH 6.95 +- 1.10 KS 7.27 +- 3.11 HB 8.58 +- 2.66 ME 1.35 +- 0.51 MP 9.57 +- 3.04 MS 10.95 +- 2.56 NP 6.36 +- 1.73 PC 5.43 +- 2.24 SA 14.50 +- 3.05 SP 7.31 +- 1.50 SS 7.07 +- 2.49 HR 9.01 +- 1.64 BD 5.66 +- 0.98 EB 8.07 +- 1.53 EM 9.10 +- 2.45 MT 5.78 +- 1.42 OA 18.44 +- 3.95 PA 7.68 +- 2.04 PB 17.47 +- 2.86 WH 5.37 +- 1.21 A 6.02 +- 2.33 8 9.15 +- 2.88 C 7.67 +- 2.77 D 6.15 +- 2.37 E 6.62 +- 2.20 F 5.00 +- 1.11 G 8.21 +- 1.97 H 10.78 +- 1.65 I 5.30 +- 1.49 J 4.43 +- 1.54 K 6.73 +- 1.02 L 11.87 +- 3.20 I PL HS HB 7.95 20.48 7.78

+-

1.74 2.96 1.81 RL 0.90 +- 0.40 RL 9.73 +- 2.19 Geographical Regional Averages for this period are:

Near Plant (0 .16 mi.) 16.02 +- 3.50 Exclusion Area (.25 .68 mi.) 7.36 +- 2.04 Distant Nbrhood (.7-6.5 mi.) 6.90 +- 2.16 Background (8-21 mi.) 7.62 +- 2.60 3-22

TABLE III-D-3 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #2 1984 Micror/

Station Hour 1- 2 Sigma CP 15.20 +- 6.08 CR 3.52 +- 1.26 CS 2.34 +- 0.84 ER 1.78 +- 0.67 I EW KS MB 2.08 16.17 2.12

+-

0.69 3.45 0.72

- ME 6.50 +- 3.26 MP 3.87 +- 2.35 MS 4.04 +- 2.44 NP 3.97 +- ,

1.95 PC 0.16 +- 0.06 SA 2.86 +- 1.86 SP 2.22 +- 0.74 I SS WR BD 1.32 3.29 2.09

+-

0.66 1.08 0.67 EB 3.84 +- 2.11 EM 1.52 +- 0.48 HT 1.73 +- 0.78 OA 18.55 +- 3.90 PA 10.60 +- 5.61 PB 18.59 +- 2.13 WH 2.57 +- 1.19 A 1.77 +- 0.74 B 2.75 +- 0.38 C 3.65 +- 0.65 0 1.81 +- 0.82 E 2.86 +- 1.15 F 3.27 +- 0.29 G 2.83 +- 0.56 H 4.74 +- 0.64 I 8.28 +- 7.58 J 14.13 +- 3.68 K 21.63 +- 2.17 L 17.31 +- 4.41 PL 5.05 +- 1.81 HS 12.24 +- 3.94 HB 4.08 +- 1.77 RL 2.61 +- 1.19 RL 3.94 +- 0.47 Geographical Regional Averages for this period are:

Near Plant (0 .16 mi.) 14.99 +- 4.72 Exclusion Area (.25 .68 mi.). 3.49- +- 2.31 Distant Nbrhood (.7-6.5 mi.) 6.69 +- 3.36 Background (8-21 mi.) 5.86 +- 2.35 3-23

TABLE III-D-4 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #3 1984 Micror/

Station Hour i- 2 Sigma CP 6.24 +- 1.55 CR 7.71 +- 2.15 CS 1.84 +- -

.38 7.16 1.83 I

ER +-

EH 9.37 +- 2.21 KS 8.89 +- 4.00 MB 8.54 +- 3.01 ME 1.77 +- .62 MP 9.83 +- 3.35 MS 14.67 +- 6.12 NP 6.16 +- 1.44 PC 6.90 +- 2.27 SA 15.52 +- 3.44 SP 7.92 +- 1.80 SS 7.47 +- 2.50 WR 9.82 +- 1.56 BD 6.98 +- 1.54 EB 9.25 +- 3.05 EM 7.85 +- 4.22 MT 6.46 +- 1.72 OA 19.70 +- 5.08 PA 11.08 +- 2.01 PB 20.47 +- 4.94 NH 7.81 +- 2.55 A 8.88 +- 3.31 8 9.22 +- 4.60 C 8.39 +- 2.51 0 7.58 +- 2.43 E 7.70 +- 2.24 F 6.49 +- 2.51 G 10.93 +- 2.52 H 10.35 +- 4.22 I 6.77 +- 3.43 J 5.77 +- 1.97 K 7.28 +- 1.58 L 11.69 +- 4.21 PL 7.84 +- 2.42 I WS HB RL 20.85 8.24 1.39

+-

7.67 2.64

.11 RL 1.79 +- .68 I Geographical Regional Averages for this period are:

I Near Plant (0 .16 mi.)

Exclusion Area (.25 68 mi.)

Distant Nbrhood (.7-6.5 mi.)

18.03 8.34 7.58

+-

6.14 2.95 3.01 Background (8-21 mi.) 8.90 +- 3.31 3-24

TABLE III-D-5 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #4 1984 Micror/

Station Hour +- 2 Sigma CP 13.08 +- 3.17 CR 2.27 +- 1.01 CS 1.84 +- 1.04 ER 3.96 +- 1.67 EH 3.68 +- 1.14 KS 10.53 +- 5.39 MB 3.20 +- 1.08 ME 3.78 +- 1.42 MP 3.71 +- 1.52 MS 2.66 +- .97 NP 3.42 +- 1.19 PC 1.55 +- .67 SA 2.64 +- 1.08 SP 5.82 +- 1.02 SS 3.26 +- .67 WR 1.44 +- .53 BD .64 +- .37 EB ND* +- ND EM 1.80 +- .58 MT 2.12 +- 1.23 0A 6.28 +- 1.75 PA .98 +- .69 PB 10.38 +- 3.39 WH 4.75 +- 1.81 A 2.12 +- .68 B 4.08 +- 1.00 C 2.25 +- .68 D ND +- ND E 2.40 +- .44 F 2.83 +- .50 G 3.63 +- .83 H 2.70 +- 1.02 I 8.97 +- 4.46 J ND +- ND K 9.77 +- 4.79 L 5.33 +- 1.98 PL 3.13 +- 2.03 WS 6.76 +- 3.59 HB 3.78 +- 1.21 RL 2.01 +- .97 RL 1.93 +- .95

ND - No data due to missing TLD. Geographical Regional Averages for this period are:

Near Plant (0 .16 mi.) 6.10 +- 3.05 Exclusion Area (.25 .68 mi.) 3.46 +- 1.64 Distant Nbrhood (.7-6.5 mi.) 4.82 +- 2.57 Background (8-21 mi.) 4.67 +- 3.30 3-25 3

M M . M M M M M

@ARTERLY AVERAGES FOR GMNA EXPOSURE RATES IST @ARTER 2ND @ARTER 3RD @ARTER 4TH @ARTER ,

STATION MICR0R/HR MICR0R/HR MICR0R/HR MICR0R/HR i i

5.87 15.20 6.08 6.24 1.55 13.08 3.17 f CP .. 1.36 ,. ,.

2.15 CR 7.92 .. 1.62 3.52 ,.

1.26 7.71 ,, 2.27 ,. 1.01 1 77 2.34 0.84 1.84 .38 1.84 1.04 CS +- 0.28 .. ,. ,.

5.60 e. 1.78 0.67 7.16 ,. 1.83 3.96 ,- 1.67 ER 2.30 ,.

2.21 EW 6.95 ,. 1.10 2.08 ..

0.69 9.37 ,, 3.68 p. 1.14 7.27 16.17 3.45 8.89 ,. 4.00 10.53 +. 5.39 KS .. 3.11 ..

8.58 2.12 0.72 8.54 ,. 3.01 3.20 1.08 I" MB .. 2.66 ,.

.62

+.

HE 1.35 *- 0.51 6.50 , 3.26 1.77 .. 3.78 e. l.42 9.57 +- 3.87 2.35 9.83 .. 3.35 3.71 +- 1.52 MP 3.04 ..

6.12 MS 10.95 .- 2.56 4.04 ..

2.44 14.67 .. 2.66 +-

6.36 e- 3.97 l.95 6.16 .. I.44 3.42 e- 1'9719 NP 1.73 ,.

2.27 l PC 5.43 +- 2.24 0.16 ,. 0.06 6.90 .. 1.55 +- 67 14.50 +- 2.86 1.86 15.52 .. 3.44 2.64 e- 1.'08 SA 3.05 ,.

SP 7.31 e- 1.50 2.22 ..

0.74 0.66 7.92 7.47

,. 1.80 2.50 5.82 3.26 e.

+-

1.02 S 7.07 +- 2.49 1.32 .. .. *67 SS WR 9.01 +

.- 1.64 3.29 ..

1.08 0.67 9.82 6.98

.. 1.56 1.54 g,44 ,.

+-

,53 Q>YN 3 m ao

5.66 e- 0.98 2.09 ,. .. .64 '

w BD EB 8.07 +- 1.53 3.84 ,. 2.11 9.25 .. 3.05 ND* +- ND'37 j5 4

m EM MT 9.10 5.78

+-

2.45 1.42 1.52 1.73 e.

e.

0.48 0.78 7.85 6.46 4.22 I.72 1.80 2.12

+-

58 1.'23 e""U C D OA 18.44 e- 3.95 18.55 e- 3.90 19.70 ,- 5.08 2.01 6.28 *- 1.75 5N PA 7.68 e- 2.04 10.60 ,. 5.61 2.13 11.08 20.47

+- 4.94

.98 +- ~69 -i g O PB 17.47 '- 2.86 18.59 .. 10.38 +- 3.39 5 cn /n 5.37 +- 2.57 +- 1.19 7.81 .. 2.55 4.75 +- 1.81 m WH 1.21 3.31 6.02 +- 1.77 e. 0.74 8.88 e- 2.12 +- 68 A 2.33 0.38 9.22 e. 4.60 +-

B 9.15 '- 2.88 2.75 ,. 4.08 1'00 '

i 7.67 >- 3.65 0.65 8.39 .. 2.51 2.25 *- 68 C 2.77 e.

7.58 2.43 +-

D 6.15 ** 2.37 1.81 .. 0.82 +- ND Nh 2.86 e- 1.15 7.70 e. 2.24 2.40 +- .44 E 6.62 *-

2.20

+- 3.27 +- 0.29 6.49 .. 2.51 2.83 *- 50 F 5.00 1.11 2.52 8.21 *- 2.83 ,. 0.56 10.93 e- 3.63 +- .' 8 3 G 1.97 4.22 +-

10.78 *- 4.74 .. 0.64 10.35 ,- 2.70 I.02 H 1.65 6.77 +- 3.43 5.30 *- 8.28 +. 7.58 8.97 *- 4.46 I 1.49 3.68 5.77 e- 1.97 +-

J 4.43 +- 1.54 14.13 .. ND ND

- 21.63 2.17 7.28 +- 1.58 9,77 .- 4,79 K 6.73 1.02 e.

11.87 +- 17.31 e- 4.41 11.69 +- 4.21 5.33 +- I.98

t. 3.20 2.42

7.95 +- 5.05 ,. 1.81 7.84 ,- 3.13 '-

2.03 PL 1.74 7.67 +-

20.48 12.24 ,. 3.94 20.85 +. 6.76 3.59 WS 2.96 e- 2.64 7.78 '-

1.81 4.08 +- 1.77 8.24 3.78 '- 1.21 H8 +-

RL 0.90 '-

0.40 2.61 +- I 19 1.39 '- Il 2.01 97

- 3.94 e- 0.4., 1.79 e- .68 1.93 '-

95 RL 9.73 2.19

ND - No data due to missing TLD.

TABLE III-D-7 1983 DIRECT RADIATION SURVEY RESULTS Exposure Rate Location (uR/hr+-1 sigma) Beach Terrain White Horse Beach 6.8+-0.5 Sand with large amount of (near Hill P. Avenue) course gravel, granite boulders near beach area (within thirty feet).

hihite Horse Beach 7.2+-0.4 Sandy with small amounts (in back of Blue Sail Bar) of gravel.

Plymouth Beach 10.2+-0.4 Sandy with small amounts (outer beach) of gravel.

Plymouth Beach 7.4+-0.6 Sandy.

(inner beach)

Plymouth Beach 6.8+-0.4 Sandy.

(behind Berts Restaurant)

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

(ocean side) l l

3-27 i

i

III.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 mi - NNH). The Discharge Canal sample is collected by a continuously compositing sampler which extracts a sam le of about 20 ml of water from the Discharge Canal every one-half hour.

Grab samples are taken weekly from each of the other two locations.

~

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

i There were positive measurements of nuclides characteristic of reactor operation observed at the Discharge Canal in five samples during the second and third quarters of 1984. There were positive measurements of Cs-137, Co-60 and K-40 in these five samples from the Discharge Canal.

The other samples from the Discharge Canal, and the majority of samples from Bartlett Pond and Powder Point resulted in positive measurements of only K-40.

The observed concentrations of Cs-137 and Co-60 were the result of PNPS-1 11guld releases. However, the observed concentrations of K-40 were due to the natural occurrence of this nuclide.

In addition, there were indications of the presence of H-3 (activity greater than three times the standard deviation) in the second quarter

composite sample for the Discharge Canal and Bartlett Pond. The highest mean concentration occurred at the Dischtrge Canal.

It is important to note that since seawater is r.ot potable, the presence of the Cs-137 and Co-60 concentrations do not represent a significant potential source of dose to the general public.

Therefore, there was clearly no significant environmental effect l

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

3-28

TABLE III-E-1 ERMAP RESULTS-WATERBORNE EDIUM: SEAWATER WITS: PCI/XG INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS eteeeeeeeeeeeeeeee seeeeeeeeeeeeeeeeeeeeeeee seeeeeeeeeeeeees RADIONUCLIDES EAN EAN EAN (N0. ANALYSER) REQUIRED RANGE STA. RANCE RANGE (NON-ROUTIE)* LLD NO. DETECTED ** NO. NO. DETECTED #e NO. DETECTED #e g IE-7 ( 36) ( 1.5 2 1.8)E O 11 ( 5.2 t 2.0)E O ( !.3 i 1.4)E O E ' 0) (-1.8 - 1.8)E 1 (-6.4 - 15.5)E O (-8.4 - 7.3)E O

( 0/ 24)* *( 0/ 12)* e( 0/ 12)e I K-40 ( 36)

( 0)

( !.6 i

(-1.3 - 32.5)E 1 f( 13/ 24)e

.3)E 2 !!, ( 3.0 i

( 2.5 -

( 12/ 12)*

.1)E 2 3.3)E 2

( 2.7 t .3)E 2

( 6.9 - 359.0)E 0

( 11/ 12)*

CR-51 ( 36) ( 6.4 1 16.9)E -1 17 ( 1.2 1 2.2)E O (-1.4 t 1.7)E O

( 0) (-1 3 - 1.8)E 1 (-7.0 - 18.0)E O (-1.1 - .5)E 1 ei 0/ 24)* et 0/ 12)* *( 0/ 12)*

ffi-54 ( 36) 15. ( 9.6 i 15.2)E -2 17 ( 2.7 1 2.1)E -1 ( 2.2 t 16.5)E -2

( 0) (-1.6 - 1.2)E O (-1.1 - 1.2)E O (-1.1 - .7)E O e( 0/ 24)e *( 0/ 12)e *( 0/ 12)*

CD-53 ( 36) 15. (-6.1 t 15.6)E -2 17 ( 5.7 1 16.3)E -2 (-8.7 i 3.3)E -1

( 0) (-1.5 - 2.4)E u (-6.6 - !!.1)E -1 (-2.5 - 1.0)E O

( 0/ 24)e e( 0/ 12)e e( 0/ 12),

FE-59 ( 36) 30. ( 2.4 2 4.6)E -! 17 ( 7.3 2 6.4)E -1 ( 6.4 t 6.8)E -1

( 0) (-2.7 - 5.5)E O (-2.2 - 5.0)E O (-2.1 - 6.6)E O

( 0/ 24)e e( 0/ 12)r *( 0/ 12)*

I C0-60 ( 36)

( 0)

15. ( 2.6 1

(-1.5 - 23.3)E O

( 5/ 24)#

1.2)E O 11 ( 5.2 2 2.1)E O

(-5.3 - 233.0)E -1 e( 5/ 12)*

(-8.4 1

(-4.0 -

( 0/ 12)e 3.6)E -1

.5)E O IN-65 ( 36) 30. (-2.3 2 4.5)E -1 17 (-1.5 t 6.6)E -1 (-4.6 t 5.3)E -1

( 0) (-3.9 - 3.3)E 0 (-3.4 - 3.0)E O (-4.1 - 1.8)E O

( 0/ 24)e #( 0/ 12)e et 0/ 12)*

ZR-95 ( 36) 10. ( 3.7 t 3.1)E -1 17 ( 4.9 t 4.4)E -1 (-2.5 1 5.8)E -1

( 0) (-2.3 - 3.7)E O (-1.6 - 3.7)E O (-4.2 - 3.7)E O

( 0/ 24)e *( 0/ 12)e f( 0/ 12)e a NON-ROUTINE REFERS TO TE NUr$ER OF SEPARATE EASWEENTS WHICH ERE CEATER THAN TEN (10) TIES TE AVERAGE BACK0ROWD FOR TE PERIOD OF TE REPORT.

e TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTABLE EASUREENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH f( le.

3-29

. - . . - . . - ~ ~ - - - . - - - . - - - . . . . - - - . . ~ . . . . . .

TABLE III-E-1 (CONTINUED)

EDILE: SEAWATER LNITS: PCI/KG INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS neuenneneseen eteenunneenneennes eenteesenesen IMDION.lCLIDES EAN MAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (IOi-R0tlT! Ele LLD NO. E TECTEDee NO. NO. DETECTEDee NO. DETECTED **

NB-95 ( 36) ( 2.0 t 2.1)E -1 17 ( 3.6 i 2.6)E -1 ( !.5 t 2.7)E -1

( 0) (-2.0 - 1.6)E O (-9.5 - 16.4)E -1 (-7.5 - 19.3)E -1

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

Rll-103 ( 36) (-7.8 1 2.0)E -1 17 (-5.5 i 3.2)E -1 (-8.0 t 2.7)E -1

( 0) (-2.5 - 2.1)E 0 (-2.3 - 2.1)E O (-2.2 - .4)E O at 0/ 24)* *( 0/ 12)* *( 0/ 12)*

Rll-106 ( 36) (-2.8 i 1.4)E O 23 ( 3.5 t 2.1)E O ( 3.5 t 2.1)E 0

( 0) (-2.7 - .5)E 1 (-5.4 - 14.7)E O (-5.4 - 14.7)E 0

( 0/ 24)# *( 0/ 12)* e( 0/ 12)*

I-131 ( 36) (-3.0 t 5.6)E -1 23 ( 2.8 i 5.4)E -1 ( 2.8 i 5.4)E -1

( 0) (-5.6 - 7.5)E O (-3.8 - 3.5)E O (-3.8 - 3.5)E O

( 0/ 24)e *( 0/ 12)e *( 0/ 12)e CS-134 ( 36) 15. (-5.7 t 2.1)E -1 !! (-2.0 t 3.4)E -1 (-9.5 i 1.9)E -1

( 0) (-2.6 - 2.3)E O (-1.9 - 2.3)E O (-2.0 - .0)E O

( 0/ 24)e f( 0/ 12)e *( 0/ 12)*

CS-137 ( 36) 15. ( 8.1 i 4.1)E -1 !! ( 1.7 i .7)E O (-2.5 1 2.2)E -1

( 0) (-1.3 - 7.1)E O (-2.0 - 70.7)E -! (-1.0 - .6)E O

( 4/ 24)e *( 4/ 12)* *( 0/ 12)e I BA-140 ( 36)

( 0)

15. (-5.7 i

(-3.3 -

( 0/ 24)e 2.2)E -1 1.3)E O 17 (-5.2 1

(-1.5 -

e( 0/ 12)*

1.8)E -1

.4)E O

(-7.9 i

(-3.0 -

( 0/ 12)*

4.2)E -1 1.5)E O CE-141 ( 36) ( !.4 1 3.7)E -1 17 ( 4.2 i 5.5)E -1 (-2.0 t 4.2)E -1

( 0) (-3.8 - 3.8)E 0 (-2.9 - 3.8)E O (-2.3 - 3.2)E O

( 0/ 24)e e( 0/ 12)* *( 0/ 12)e CE-144 ( 36) (-5.0 t 9.9)E -1 23 ( !.5 t 1.7)E O ( 1.5 t 1.7)E O

( 0) (-8.2 - 9.0)E 0 (-7.0 - 9.4)E O (-7.0 - 9.4)E 0

( 0/ 24)* el 0/ 12)* *( 0/ 12)*

AC-228 ( 36) ( !.7 t .6)E O !! ( 2.8 i 1.1)E 0 ( 8.5 t 9.1)E -1

( 0) (-3.5 - 10.4)E O (-3.5 - 10.4)E O (-3.3 - 5.8)E O I *( 0/ 24)* *( 0/ 12)* *( 0/ 12)e 1

NON-ROUTINE REFERS TO TE NUMICR OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE FERIOD OF THE REPORT.

se TE FRACTION OF SAMPLE ANALYSES YIELDING [ETECTABLE EASUREENTS (I.E. >3 STD DEV!ATIONS) IS INDICATED WITH *( )#. ,

1 j

m

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

I TABLE III-E-1 (CONTINUED)

I EDILM: SEAWATER UNITS: PCI/KG INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS nunnuenenn enneennununnun eenunenenn RADIONUCLIDES EAN EAN EAN (N0. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTIEle LLD NO. DETECTEDet NO. NO. DETECTEDu NO. DETECTEDee H-3 ( 12) 330. ( 8.9 t 5.5)E 1 11 ( !.3 t .8)E 2 ( !.4 i 32.9)E O

( 0) (-1.2 - 3.6)E 2 ( !.0 - 35.5)E 1 (-8.0 - 7.0)E 1 f( 2/ 8)e *( 1/ 4)e f( 0/ 4)*

NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREENTS WHICH ERE GREATER TMl TEN (10) TIES TE AVERAGE BACKGROLND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAtPLE ANALYSES YIELDING DETECTABLE EASUf&iNTS

(!.E. >3 STD DEVIATIONS) IS INDICATED WITH et le.

I i

3-31

III.F. Shellfish Shellfish are normally sampled quarterly from 5 locations: the Station Discharge Canal, Duxbury Bay, Manomet Point, Harren Cove and Marshfield. The results of the ERMAP program for shellfish are presented in Table III-F-1. It is clear from this table that there have been positive measurements of Be-7, Ce-141, Co-58, Mn-54 (peak),

~

Zn-65, Co-60, AcTh-228 and K-40 in samples from the Discharge Canal.

In addition there have been positive measurements of Be-7, Mn-54, Co-60, AcTh-228 (peak) and K-40 at Manomet Point; Be-7, AcTh-228 (peak) and K-40 at Warren Cove; AcTh-228 and K-40 at Duxbury Bay; and, Be-7, AcTh-228 and K-40 at the control station in Marshfield.

The observed concentrations of Ce-141, Mn-54 (peak) Co-58, Co-60, and Zn-65 were the result of PNPS-1 liquid releases. However, the observed concentrations of Be-7, AcTh-228 and K-40 are due to the natural occurrence of these nuclides.

However, even if a person were to consume the maximum annual quantity of seafood (5 kilograms / year) with the highest mean concentrations of the above nuclides, they would receive a dose of less than 0.003 mrem to the total body and less than 0.02 mrem to the most restrictive organ (Adult, GI-LLI).

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

3-32

TABLE III-F-1 ERMAP RESULTS-SHELLFISH EDILM: SELLFISH LMITS: PCI/K0 ET I

INDICATOR STATICNS STATION WITH HIGEST EAN CONTROL STATIONS seseeeeeeeeeeeeeee eseesseeeeeeeeeeeeeeeeeee seeeeeeeeeeeeeee MDI0M.lCLIDES EAN EAN EAN (NO. AMLYSES) REQll! RED RANGE STA. RANGE RAf0E (NDN-R0llTIEle LLD NO. DETECTEDet NO. NO. DETECTEDee NO. DETECTEDee I BE-7 ( 40)

( 0)

( 2.1 *

(-8.0 - 15.9)E 1 el 10/ 32)*

.9)E 1 15 ( 3.3 *

( 1.7 -

et 3/ 4)*

.8)E 1 5.4)E I

( 3.3 * .7)E 1

( 5.8 - 61.2)E O e( 5/ 8)e K-40 ( 40) ( 1.0 : .1)E 3 15 ( 1.5 * .2)E 3 ( 7.7 i 2.1)E 2

( 0) ( 1.2 - 21.1)E 2 ( !.2 - 1.9)E 3 ( !.9 - 15.7)E 2

( 29/ 32)e *( 4/ 4)e *( 8/ 8)e CR-51 ( 40) ( 2.8 A 7.9)E O 11 ( 7.5 t 8.1)E 0 (-1.3 * .7)E 1

( 0) (-1.3 - 1.1)E 2 (-1.1 - 6.2)E 1 (-5.8 - .0)E 1 e( 0/ 32), e( 0/ 8)* *( 0/ Ble NN-54 ( 40) 130. I 2.2 i 1.4)E O !! ( 9.1 i 1.8)E O ( !.61 4.5)E -1

( 0) f-1.8 - 1.6)E 1 ( 3.2 - 16.0)E O (-1.7 - 2.6)E O

( 8/ 32)* et 7/ 8)e et 0/ 8)*

CO-53 ( 40) 130. (-9.0 t 83.0)E -2 !! ( 2.9 t 1.1)E O ( 4.6 1 463.0)E -3

( 0) (-1.3 - .8)E 1 (-1.4 - 8.0)E O (-2.2 - 1.8)E O

( 2/ 32)* *( 2/ 8), *( 0/ Sie FE-59 ( 40) (-3.0 t 2.3)E O 15 ( 3.3 i 1.0)E O ( 9.2 2 9.3)E -1 I

260.

( 0) (-5.3 - 2.0)E 1 ( 8.3 - 54.6)E -1 (-3.0 - 4.7)E O et 0/ 12)e *( 0/ 4)* *( 0/ 8)e CD-60 ( 40) 130. ( 9.2 t 3.6)E 1 11 ( 3.6 i .9)E 2 (-3.6 i 4.3)E -1

( 8) (-9. -) - 851.0)E O ( 8.9 - 85.1)E ! (-2.7 - 1.0)E O

( 12/ 32)* *( 8/ 8)e *( 0/ 8),

ZN-65 ( 40) 260. ( 4.3

3.1)E O !! ( !.8 t .7)E 1 ( 3.7 t 1.8)E O

( 2) (-5.7 - 5.2)E 1 (-2.5 - 52.0)E O (-1.2 - 14.5)E O et 5/ 32)e *( 5/ 8)* *( 0/ 8)e ZR-95 ( 40) ( 2.3 t 1.3)E 0 13 ( 7.2 t 2.0)E O ( 3.5 t 9.3)E -1

( 0) (-1.9 - 1.8)E 1 ( 1.1 - 16.2)E O (-4.1 - 3.4)E O

( 0/ 32)e *( 0/ Ble et 0/ 8)e e NON-FGJT!?E REFERS TO THE NLMBER OF SEPARATE EASLFItDTS WHICH WERE GREATER THAN TEN (10) TIE S THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

- TE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE EA$lFIMENTS

(!.E. >3 STD DEVIATIONS) IS INDICATEE WITH e( )e.

2-D

TABLE III-F-1 (CONTINUED)

EDilff: SELLFISH UNITS: PCI/KG ET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIOPS esseeeeeeeeeeeeeen eesseeeeeeeeeeeeeeeeeeeen eeeeeeeeeeeeeeee RADIONUCL! DES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NCH E UTINEle LLD NO. DETECTEDee NO. NO. ETECTEDee NO. DETECTEE4e NB-95 ( 40) ( 5.8 i 9.6)E -1 24 ( !.6 i .8)E O ( !.6 t .8)E O

( 0) (-1.1 - 2.0)E 1 ( 6.3 - 713.0)E -2 ( 6.3 - 713.0)E -2 e( 0/ 32)e *( 0/ 8)* *( 0/ 8)e RU-103 ( 40) ( 6.6 2 10.3)E -1 13 ( 3.3 i 1.5)E O ( !.4 25.3)E -2

( 0) (-1.3 - 2.0)E ! (-1.1 - 9.4)E O (-1.4 - .8)E O

( 0/ 32)e *( 0/ Ble *( 0/ 8),

RU-106 ( 40) ( 9.7 t 12.5)E O 13 ( 4.1 t 2.6)E 1 (-1.2 t 4.1)E O

( 0) (-2.4 - 1.7)E 2 (-2.8 - 16.9)E I (-2.8 - 1.0)E 1 et 0/ 32)* e( 0/ 8)* ef 0/ 8)*

I-131 ( 40) 80. (-1.3 i 3.5)E O !! ( 2.6 t 6.5)E O (-1.9 2 1.4)E !

( 0) (-6.8 - 4.6)E 1 (-1.3 - 4.6)E 1 (-1.1 - .0)E 2 e( 0/ 32)* *( 0/ Ble *( 0/ Ble CS-134 ( 40) 80. (-1.3 t .9)E O !! ( 1.1 i .6)E O (-5.4 t 5.1)E -1

( 0) (-1.5 - .8)E 1 (-1.4 - 4.2)E 0 (-2.2 - 1.3)E O

( 1/ 32)* e( 1/ 8)* f( 0/ 8)e CS-137 ( 40) 80. ( 3.2 t 1.1)E O !! ( 6.6 t 2.6)E O (-2.5 t 6.0)E -1

( 0) (-1.2 - 2.4)E 1 ( 2.6 - 235.0)E -1 (-5.2 - 2.4)E O f( 4/ 32)e *( 4/ Sie e( 0/ Ble I BA-140 ( 40)

( 0)

(-7.6 t

(-2.4 -

( 0/ 32)e 1.6)E O 1.6)E 1 13 (-7.0 t

(-1.9 -

( 0/ 8)*

2.0)E O

.4)E 1

(-8.4 t

(-2.0 -

I 0/ 8)*

2.5)E O

.1)E 1 CE-141 ( 40) ( 3.3 2 2.1)E O 12 ( 5.5 t 4.0)E O ( !.0 2 1.6)E O

( 0) (-3.3 - 2.6)E 1 (-2.1 - 2.6)E 1 (-7.2 - 8.4)E O e( 2/ 32)e *( 0/ 12)e ef 0/ 8)e CE-144 ( 40) ( 3.8 t 4.0)E 0 12 ( !.21 .9)E 1 (-2.6 i 2.3)E O

( 0) (-3.4 - 6.5)E 1 (-3.4 - 6.5)E 1 (-1.8 - .3)E 1 e( 0/ 32)e e( 0/ 12)e et 0/ 8)*

AC-228 ( 40) ( 3.9 i .8)E 1 13 ( 7.4 t 1.4)E 1 ( !.! t .4)E 1

( 0) (-1.7 - 12.3)E 1 ( 7.3 - !!7.0)E O ( 4.2 - 287.0)E -!

a( 7/ 32)* *( 4/ 8)e e( 3/ 8)e I e NON-ROUTINE REFERS TO TE NtGER OF SEPARATE EASLFIMENTS WHICH WERE GREATER THAN TEN (10) T!r'ES THE AVERAGE BACKGROUND FOR THE PERIOD LT THE REPORT.

I se THE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE EASLEEMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH et Je.

w

III.G. Algae (Irish Moss)

Algae, referred to as Irish Moss or Chondrus Chrispus, is sampled 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.

l .

It is clear from this table that there have been positive measurements of Be-7, Mn-54, Co-58, Co-60, Zn-65, Cs-137, AcTh-228 a,nd K-40 at the Discharge Canal. In addition, there have been positive measurements of Be-7, Mn-54, Co-60, AcTh-228 and K-40 at Manomet Point (Station 15 - 3 miles - SE); and Be-7, Mn-54, Co-60, AcTh-228 and K-40 at the control station of Ellisville (Station 22 - 8 mi - SSE). Due to the positive measurements of reactor related nuclides at Station #22, samples were collected from another control station for the second, third and fourth quarters of 1984. This control station was established at Brant Rock (Station 34-12 mi-NNW). The only observed positive measurements of Brant Rock samples were Be-7, AcTh-228 (peak) and K-40.

The measured concentrations of Co-58 Mn-54, Zn-65, Cs-137, and Co-60 at the Discharge Canal are certainly due to 11guld effluents from PNPS-1.

The observed concentrations of Mn-54 and Co-60 at Manomet Point and Ellisville were the result of PNPS-1 liquid releases. 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 miles away the NNH sector.

3-35 I

. . . . . . . . = ~ . -- - . .- - .._ -. . . - . -

It is important to note that due to processing and market dilution, the presence of the Mn-54, Cs-137, Zn-65, Co-58 and Co-60 concentrations do not represent a significant potential source of dose to the general public. In fact, even direct human consumption of Algae (which to our knowledge, does not occur) with the highest mean concentrations would result in a dose rate of about 0.05 mrem /yr to the total body and less than 0.03 mrem /yr to the most sensitive organ (Adult-GI-LLI, using the models presented in Regulatory Guide 1.109) and assuming consumption of 5 kg/ year of unprocessed material. When compared with the natural background dose rate of 80-100 mrem /yr, there was clearly no significant environmental impact observed in Algae as a result of the operation of PNPS-1, 1

{

l i

3-36 lll l

TABLE III-G-1 ERMAP RESULTS-ALGAE EDIW: IRISHfl0SS WITS: PCI/XG ET INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS ununenunen enounnuneenesune e***ue4*eeeene RADIOMJCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANCE (NDN-ROUTIE)* LLD NO. DETECTED ** NO. NO. DETECTEDet NO. DETECTEDee BE-7 ( 16) ( !.4 i .2)E 2 22 ( 2.1 i .7)E 2 ( 1.6 i .5)E 2

( 0) ( 6.4 - 25.2)E 1 ( 8.3 - 45.4)E 1 ( 8.2 - 454.0)E O el 7/ 8)* *( 5/ 5)e *( 6/ 8)*

X-40 ( 16) ( 6.3 1 .7)E 3 11 ( 7.9 i .7)E 3 ( 6.4 1 1.8)E 3

( 0) ( 4.3 - 9.3)E 3 ( 6.1 - 9.3)E 3 ( 4.0 - 19.1)E 3

( 8/ 8)* *( 4/ 4)* *( 8/ 8)e CR-51 ( 16) ( !.4 1 2.1)E 1 22 ( 5.7 i 4.6)E 1 ( 3.3 1 3.0)E 1

( 0) (-7.3 - 13.1)E 1 ( 2.8 - 242.0)E O (-2.0 - 24.2)E 1 sf 0/ 8)* #( 0/ 5)* *( 0/ 8)e 794- 54 ( 16) 130. ( 9.1 i 3.4)E 1 11 ( !.7 t .3)E 2 ( 3.4 i 1.6)E O

( 4) ( 1.1 - 208.0)E 0 ( 9.9 - 20.8)E 1 (-1.7 - 12.0)E O

( 5/ 8)e *( 4/ 4)e *( 1/ 8)*

CO-58 ( 16) 130. ( 9.6 1 3.7)E O 11 ( !.8 .3)E 1 ( 4.4 1 13.4)E -1 I ( 2) (-2.8 - 27.5)E O

( 2/ 8)e

( !.2 -

( 2/ 4)*

2.8)E 1 (-4.6 -

( 0/ 8)*

7.2)E O FE-59 ( 16) 260. ( 1.4 1 6.1)E O !! ( 8.1 i !!.3)E O (-5.8 i 42.1)E -1

( 0) (-2.3 - 2.7)E 1 (-2.3 - 2.7)E 1 (-2.0 - 1.8)E 1

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

CO-60 ( 16) 130. ( 7.2 t 3.0)E 2 11 ( !.4 i .4)E 3 ( 3.6 1 2.4)E 1

( 4) ( 2.2 - 212.0)E 1 ( 4.8 - 21.2)E 2 (-1.5 - 202.0)E O

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

IN-65 ( 16) 260. ( 3.4 1 1.6)E 1 !! ( 6.7 i 1.9)E 1 (-3.7 1 6.7)E O

( 2) (-1.1 - 11.01E 1 ( !.6 - 11.0)E 1 (-4.6 - 2.1)E 1 e( 2/ 8)e *( 2/ 4)* *( 0/ 8)e ZR-95 ( 16) ( 4.9 i 2.7)E O !! ( 6.7 i 3.2)E O (-1.5 t 24.9)E -1

( 0) (-7.3 - 16.2)E 0 ( 2.5 - 16.2)E 0 (-9.0 - 14.0)E O

( 0/ 8)* *( 0/ 4)e e( 0/ 8)e I e ICN-ROUTINE REFERS TO TE NUMPER Cf SEPARATE EASURESTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

- TE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE EASUREENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH e( le.

3- 7 I - -

l TABLE III-C-1 (CONTINUED)

EDIUM: IRISH MOSS UNITS: PCI/KG ET INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS e**:eveneee**eteen eseeeeeee**eeeeeeeeeeeeee eteeeeee***eneee -

RADIOPOCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTIE)# LLD NO. DETECTED ** NO. NO. DETECTEDee NO. DETECTED *e NB-95 ( 16) ( 2.2 i 2.7)E 0 15 ( 5.2 i 3.7)E 0 (-6.6 i 157.6)E -2

( 0) (-8.1 - 11.7)E O (-2.8 - !!.7)E O (-6.1 - 4.8)E O et 0/ 8)* *( 0/ 4)* *( 0/ 8)*

I RU-103 ( 16)

( 0)

(-1.8 1

(-7.4 -

f( 0/ 8)*

1.1)E O 2.7)E O 34 ( 3.6 t 2.8)E O

(-3.5 - 89.6)E -1 e( 0/ 3)e

( 2.2 1 2.6)E O

(-5.6 - 17.0)E O et 0/ 8)*

RU-106 ( 16) ( !.4 i .8)E 1 15 ( 2.0 t 1.5)E 1 (-8.3 i 7.4)E O

( 0) (-2.3 - 4.3)E 1 (-2.3 - 4.3)E 1 (-4.8 - 2.3)E 1

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

I-131 ( 16) 80. ( 9.3 1 5.3)E O 22 ( !.! t 1.0)E 1 ( 2.5 i 9.0)E O

( 0) (-1.2 - 2.6)E 1 (-6.0 - 50.3)E O (-3.8 - 5.0)E 1

( 0/ 8)* *( 0/ 5), *( 0/ 8)*

CS-134 ( 16) 80. (-6.0 t 15.7)E -1 11 ( 3.3 t 22.4)E -1 (-2.0 t 1.7)E O

( 0) (-7.3 - 4.8)E O (-3.6 - 4.8)E O (-8.7 - 5.7)E O I CS-137 ( 16) 80.

( 0/ 8)e

( 1.0 t .4)E 1 11

( 0/ die

( !.6 t .7)E 1

( 0/ 8)e

( 2.9 i 1.1)E O

( 2) ( 1.6 - 31.2)E O ( 4.6 - 31.2)E O (-1.5 - 8.9)E O el 2/ Ble *( 2/ 4)* *( 0/ 8)#

BA-140 ( 16) (-3.7 1 1.7)E O 11 (-4.9 t 20.7)E -1 (-7.0 1 2.4)E O

( 0) (-1.0 - .4)E 1 (-5.9 - 3.8)E O (-1.5 - .2)E 1

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

CE-141 ( 16) ( 3.6 i 18.4)E -1 22 ( 7.! t 7.0)E O ( 5.0 4.3)E O

( 0) (-1.0 - .5)E 1 (-6.4 - 33.8)E 0 (-6.4 - 33.8)E O

( 0/ 8)e *( 0/ 5)* *( 0/ Ble CE-144 ( 16) ( 1.6 1 5.8)E O 34 ( 6.1 1 7.2)E O (-3.1 i 7.8)E O

( 0) (-2.4 - 2.9)E 1 (-8.2 - 14.2)E O (-4.3 - 1.8)E 1 el 0/ 8)* *( 0/ 3), el 0/ 8)e AC-228 ( 16) ( 9.8

10.5)E O 22 ( 4.5 i 1.0)E 1 ( 3.3 i .8)E 1

( 0) (-2.9 - 5.5)E ! ( 1.7 - 7.8)E 1 ( 5.2 - 77.7)E O

( 1/ 8)e *( 2/ 5)e *( 2/ 8),

l i

e NON-ROUTINE REFERS TO TE NJMBER OF SEPARATE EASLEEMENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKm0lND FOR TE PERIOD OF TE REPORT.

e TE FRACTION OF SAtFLE ANALYSES YIELDING DETECTABLE MEASUREENTS (I.E. 23 STD DEVIATIONS) IS INDICATED WITH *( )*.

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. Only one of the required samples from the Discharge Canal Outfall area was not obtained due to unavailability in the first quarter of the year. The results of the ERMAP program for Lobsters are presented in Table III-H-1. These results are unremarkable in that there were no positive measurements of any isotopes other than K-40 in either the indicator or the control samples (K-40 is a naturally occurring nuclide). Therefore, there is no evidence of any environmental impact on this media as a result of the operation of PNPS-1.

I I

I l1 s.

3-39

--...---- --~~.--.. ~ ..--. .

TABLE III-H-1 ERMAP RESULTS-LOBSTER EDIUM: LOBSTER LNITS: PCI/KG ET INDICATOR STATIONS STATICN WITH HIGEST EAN CONTROL STATIONS eteesseeeeeeeeeee, eeeeeeeeeeeeeeeeeeeeeeeee eseeeeeeeeeee**e RADIONJCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE)* LLD NO. DETECTED *e NO. N0. DETECTED *e NO. DETECTEDee BE-7 ( 4) (-2.4 1 4.6)E ! 19 ( 4.3 i 6.4)E 1 ( 4.3 1 6.4)E I

( 0) (-1.1 - .4)E 2

( 0/ 3)* *( 0/ !)* *( 0/ 1)*

I K-40 ( 4)

( 01

( 2.2 i . .2)E 3

( !.7 -

( 3/ 3)*

2.5)E 3 19 ( 2.7 i

( 1/ 1),

.2)E 3 ( 2.7 i a( 1/ !),

.2)E 3 CR-51 ( 4) (-4.0 1 3.9)E ! 19 ( 4.0 t 8.3)E ! ( 4.0 1 8.3)E 1

( 0) (-1.2 - .1)E 2 e( 0/ 3), *( 0/ !)e *( 0/ 1)e 194- 54 ( 4) 130. (-1.31 3.6)E 0 19 ( 4.9 i 7.9)E O ( 4.9 t 7.9)E O

( 0) (-8.5 - 2.6)E O a( 0/ 3)* *( 0/ 1)* *( 0/ !)*

CO-59 ( 4) 130. ( !.3 37.1)E -1 11 ( !.3 2 37.1)E -1 (-8.3 i 8.9)E O

( 0) (-7.1 - 5.2)E O (-7.1 - 5.2)E O

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

FE-59 ( 4) 260. ( !.71 1.0)E 1 !! ( 1.7 t 1.0)E 1 (-5.1 2 2.1)E !

( 0) (-2.7 - 28.1)E O (-2.7 - 28.1)E O el 0/ 3)* *( 0/ 3)* *( 0/ 1)e CO-60 ( 4) 130. (-4.3 t 57.0)E -1 !! (-4.3 t 57.0)E -1 (-1.4 i 1.1)E !

( 0) (-1.2 - .6)E 1 (-1.2 - .6)E 1

( 0/ 3)e *( 0/ 3), et 0/ !)*

IN-65 ( 4) 260. (-1.1 t 1.7)E 1 19 ( 8.6 i 18.2)E O ( 8.6 t 18.2)E O

( 0) (-4.2 - 1.5)E !

( 0/ 3)+ e( 0/ !)* e( 0/ 1),

ZR-95 ( 4) (-5.9 t 125.0)E -1 19 (-4.1 2 158.0)E -1 (-4.1 i 158.0)E -1

( 0) (-2.1 - 2.2)E !

a( 0/ 3)e e( 0/ 1)* e( 0/ 1)e e EN-ROUTINE REFERS TO THE NUMBER OF SEPARATE E ASUREMENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACK0ROLND FOR THE PERIOD OF TE REPORT.

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

I 3-40

_ ._. .._ _ _ - ~ _ _ _ . . . _ . . . . . . _ _ _ . I I TABLE III-H-1 (CONTINUED)

EDIUM: LOBSTER LNITS: PCI/KG ET INDICATOR STATIONS STATION WITH HIGHEST H CONTROL STATIONS eeeeeeeeeeeeeeeees eeeee***eeeeeeeeeeeee++,e eeneseeeeeeeeee RADIONUCt.! DES S EAN M (N0. ANALYSES) M IRED RANGE STA. RANGE RANGE I (PON-ROUT!PEle LLD NO. DETECTEDet NO. NO. DETECTEDen NO. DETECTE0ee NB-95 ( 4) ( 8.8 2 4.3)E O !! ( B.8 2 4.3)E O (-2.3 $ 82.1)E -!

( 0) ( 9.1 - 157.0)E -1 ( 9.1 - 157.0)E -1 et 0/ 3)* *( 0/ 3)e *( 0/ 1)*

RU-103 ( 4) ( 5.5 t 1.5)E O !! ( 5.5 i 1.5)E O ( !.6 2 8.7)E 0

( 0) ( 3.6 - 8.3)E O ( 3.6 - 8.3)E O

( 0/ 3)* et 0/ 31, *( 0/ 1)e RU-106 ( 4) (-7.3 1 2.7)E 1 !! (-7.3 i 2.7)E 1 (-9.4 2 6.7)E 1

( 0) (-1.2 - .3)E 2 (-1.2 - .3)E 2 ,

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

I-131 ( 4) 80. ( 2.8 t 1.5)E 1 11 ( 2.8 2 1.5)E 1 ( !.5 t 2.7)E !

( 0) (-1.5 - 50.7)E O (-1.3 - 50.7)E O

( 0/ 3), *( 0/ 3)* e( 0/ !)*

CS-134 ( 4) 80. (-1.1 t .6)E 1 19 (-3.6 . 7.1)E O (-3.4 i 7.1)E O

( 0) (-2.3 - .3)E 1

- et 0/ 3), of 0/ 1)* *( 0/ 1)e CS-!37 ( 4) 80. ( 8.4 t 2.8)E O !! ( 8.4 t 2.8)E O ( !.2 2 8.6)E O

( 0) ( 3.5 - 13.2)E O ( 3.5 - 13.2)E O et 0/ 3), *( 0/ 3)* *( 0/ 1)e SA-140 ( 4) ( 5.7 1 17.5)E O 11 ( 5.7 i 17.5)E 0 (-1.1 2 2.1)E !

( 0) (-2.9 - 2.7)E ! (-2.9 - 2.7)E 1

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

CE-141 ( 4) (-1.8 t 8.3)E O 19 (-7.1 2 139.01E -! (-7.1 t 139.0)E -1

( 0) (-1.8 - .8)E 1 et 0/ 3)* *( 0/ 1)* e( 0/ !),

CE-144 ( 4) ( 6.2 t 2.1)E 1 !! ( 6.2 t 2.1)E 1 (-8.9 2 44.3)E O

( 0) ( 2.9 - 10.2)E 1 ( 2.9 - 10.2)E 1

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

AC-228 ( 4) ( 3.6 t 1.5)E 1 !! ( 3.6 t 1.5)E I ( 3.5 t 3.4)E 1

( 0) ( !.2 - 6.4)E I ( !.2 - 6.4)E 1

( 0/ 3)e et 0/ 3)e *( 0/ 1)e e NON-ROUTINE REFERS TO THE NUMEER OF SEPARATE EASUREMENTS WHICH 6FJE GREATER THAN TEN (10) TIMES THE AVERACE BACKGROUND FOR THE PERIOD OF THE REPORT.

se THE FRACTION OC SAMPLE ANALYSES Y!ELDING DETECTAPLE MEASUREMENTS (f.E. >3 STD DEVIATION $) IS !NDICATED WITH *( le.

&Mt

~. _ ._._ _ _ __ _ _ ___ _ _ __ . ~.

I l

III.I. Fish Fish samples of Bottom Oriented (Group I) and Near Bottom (Group II) species are collected quarterly in the vicintiy of the Dis' charge Canal Outfall. In addition, samples of Anadromous (Group III) and Coastal Migratory (GroupIV)speciesarecollectedwheninseason,inthis same area. Lastly, a sample from each group is collected once per year at a distant location offshore. During 1984, one Group II sample was unavailable in the first quarter, and two Group III samples were un-available in the third and fourth quarters respectively.

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

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

An Atlantic cod sample collected on 11/15/84 at the Discharge Canal Out-fall Area indicated a positive measurement of Cs-137. The Atlantic cod is in the Group II category (Near Bottom). Although the collection of salmon is not required per Technical Specifications, salmon is collected and analyzed when available. A salmon sample collected on 11/21/84 at the Mouth of the North River (Hanover) indicated a positive measurement' of Cs-137. The salmon is in the Group III category (Anadromous). The highest mean concentration of Cs-137 was observed in the Atlantic cod sample. 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 0.03 mrem to the total body and less than 0.04 mrem to the most restrictive organ (Adult - Liver). There-fore, there is little evidence of any environmental impact on this media as a result of the operation of PNPS-1.

3-42

._~

.- ..- _f.....~1 .'sm. _ - m. _A_e.~.4-.. - * -. .

i i

J

?

6 i

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1 3-43 i

TABLE III-I-1 ERMAP RESULTS-FISH ED!lft: FIFISH LNITS: PCI/KG ET 1

INDICATOR ST FIONS STATION WITH HIGEST EAN CONTROL STATIONS eteeseeeeeeeeeeeee 44eeeeeeeeeeeeeeeeeeeeee, eeeeeeeeeeeeeeee RADIOPAJCI.! DES MAN EAN EAN (NO. AMLi'SES) REQUIRED RANGE STA. RANGE RANGE (NON-R0llTIE)* LLD NO. DETECTED ** M). NO. DETECTEDet NO. DETECTEDee BE-7 ( 28) ( 1.2 i 1.4)E 1 97 ( !.0 1 1.0)E 2 ( 3.7 i 2.5)E 1

( 0) (-1.2 - 1.0)E 2 (-2.6 - 10.4)E 1 of 0/ 22)e *( 0/ 1)e e( 0/ 61e K-40 ( 28) ( 3.3 1 .1)E 3 97 ( 3.8 i .3)E 3 ( 3.1 i .2)E 3

( 0) ( 2.2 - 4.9)E 3 ( 2.5 - 3.8)E 3 a( 22/ 22)e *( 1/ 1)e *( 6/ 6)*

CR-51 ( 28) ( 4.4 i 1.9)E ! 13 ( 2.4 1 1.7)E 2 ( 3.0 t 5.6)E 1

( 0) (-1.2 - 2.0)E 2 (-1.8 - 2.5)E 2 a( 0/ 22)e *( 0/ 1)* *( 0/ 6)*

MN-54 ( 28) 130. ( 5.4 t 18.2)E -1 14 ( 1.3 i 1.0)E 1 (-6.0 1 35.1)E -1

( 0) (-1.2 - 1.6)E 1 (-1.3 - 1.3)E 1 e( 0/ 22)e *( 0/ De *( O! 6)*

CO-58 ( 28) 130. (-8.1 t 13.6)E -1 96 ( !.1 i .5)E I ( 9.8 i 32.8)E -1

( 0) (-1.7 - .91E l ' (-1.3 - 1.1)E 1

( 0/ 22); i *( 0/ 1)* el 0/ 6)e FE-59 ( 28) 260. ( 4.9 i 4.4)E O 12 ( 2.3 t 2.6)E 1 (-1.1 1.1)E 1

( 0) (-3.9 - 4.1)E 1 (-5.9 - 1.8)E !

( 0/ 22)e *( 0/ 1)e *( 0/ 6)e CD-60 ( 28) 130. ( 1.5 t 2.0)E O 29 ( 8.3 t 11.4)E 0 (-4.5 1 4.7)E O

( 0) (-1.7 - 1.5)E 1 (-2.5 - .8)E !

( 0/ 22)e el 0/ 1)e el 0/ 6)*

ZN-65 ( 28) 260. (-5.0 1 6.2)E O 19 ( !.5 1 2.3)E 1 (-3.5 t 7.2)E O

( 0) (-7.3 - 5.9)E 1 (-3.0 - 1.2)E 1

( 0/ 22)* et 0/ 1)* e! 0/ 6)*

ZR-95 ( 28) (-2.1 1 4.5)E O 29 ( !.3 t 1.8)E 1 (-1.2 i .7)E 1

( 0) (-5.0 - 3.0)E 1 (-3.4 - 1.3)E 1 et 0/ 22)+ e( 0/ 1)e *( 0/ 6)*

e NON-ROUTINE REFERS TO TE NUMBER OF SEFARATE EASUREMENTS WHICH ERE GREATER TMN TEN (10) TIMES TT AVERAGE BACKGROUND FOR THE PERIOD OF TE REPCRT.

I ** TE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASLEEMENTS (I.E. >3 STD DEV!ATIONS) IS INDICATED WITH e( le.

3-44

TABLE 111-1-1 (CONTINUED)

E DILE: FI EISH LNITS: PCI/KG ET t

INDICATOR STATIONS STATION WITH HIGHEST E AN CONTROL STATIONS eeeeeeeeeeeeeeeeee seeeeeeeeeeeeeeeeeeeeeeee seeeeeeeeeeeeeee RADIONUCLIDES EAN EAN EAN (ND. AMLYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTIE)* LLD PC. DETECTED ** NO. NO. DETECTEDu NO. DETECTEDee

( 6.2 i 17.9)E -1 ( 1.5 t 1.0)E 1 ( 5.3 3.9)E O I NB-95 ( 28) 14

( 0) (-1.6 - 1.8)E 1 (-8.7 - 15.2)E O

( 0/ 22)* f( 0/ 1)e e( 0/ 6)e RU-103 ( 28) ( 2.1 t 31.1)E -1 12 ( !.! t 1.1)E 1 (-7.3 i 2.6)E O

( 0) (-3.2 - 2.7)E 1 (-1.4 - .3)E 1 et 0/ 221e *( 0/ 1)e et 0/ 6),

RU-106 ( 28) ( 2.9 t 1.8)E 1 19 ( 8.9 1 6.7)E 1 (-6.2 t 21.4)E O

( 0) (-1.1 - 2.1)E 2 (-7.5 - 4.3)E 1 e( 0/ 22)* *( 0/ 1)e e( 0/ 6)*

N 31 ( 28) 80. ( !.5 t .9)E 1 19 ( !.2 1 .81E 2 (-7.0 2 22.6)E O

( 0) (-5.5 - 12.3)E 1 (-7.7 - 9.2)E 1

( 0/ 22)* e( 0/ 1)e *( 0/ 6)e CS-134 ( 28) 80. (-5.1 t 1.9)E 0 12 ( !.4 i 1.2)E 1 (-7.1 1 4.2)E O

( 2.3 - 1.4)E 1 (-2.2 - .7)E 1 I ( 0)

( 0/ 22)* *( 0/ 1)e *( 0/ 6)e CS-137 ( 28) 80. ( 4.4 i 1.8)E 0 13 ( 2.6 2 1.2)E 1 ( 1.2 i .4)E 1

( 0) (-8.7 - 18.7)E O ( 2.1 - 25.8)E O e( 1/ 22)e *( 0/ 1)e *( 1/ 6)e BA-140 ( 28) (-1.4 i .7)E 1 13 ( 4.2 t 5.6)E 1 (-1.3 t 14.0)E O

( 0) (-7.8 - 3.6)E 1 (-5.0 - 4.2)E 1 f( 0/ 221e et 0/ 1)* e( 0/ 6)e CE-141 ( 28) ( 7.5 i 3.5)E O 19 ( 2.3 k 2.1)E 1 (-3.2 t 6.3)E 0

( 0) (-2.2 - 3.8)E 1 (-2.1 - 1.5)E 1 e( 0/ 22)e *( 0/ 1)e *( 0/ 6)*

CE-144 ( 28) ( 9.9 i 91.8)E -1 99 ( 4.6 t 3.7)E 1 ( 3.0 t 14.6)E O

( 0) (-7.9 - 8.7)E 1 (-5.7 - 4.6)E 1 et 0/ 22)* *( 0/ 1)* e( 0/ 6)*

AC-228 ( 28) ( 9.6 1 5.9)E O 97 ( !.1 i .5)E 2 ( 2.9 i 2.3)E 1

( 0) (-5.0 - 5.4)E 1 (-3.5 - !!.5)E 1 e( 0/ 22)e *( 0/ 1)e et 0/ 6)e I e NON-ROUTIE REFERS TO TE NLMBER OF SEPARATE EASLREENTS WHICH WERE GREATER THAN TEN (10) TIES THE AVERAGE BACKGR0lta FOR THE PERIOD OF TE REPORT.

ee TE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE EASUREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *( le.

% 93

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

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

One sediment sample segment was not analyzed during 1984 due to the fault of Boston Edison. This was the 5-10 cm segment collected at Plymouth Beach on 5/17/84.

The results of the ERMAP program for cediments are presented in Table III-J-1. It is clear from this table that the highest mean concentra-tion 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 12-14 cm segment. This sample was collected on 5/16/84. In addition, Cs-137 was observed in the majority of the sediment segments (0-26 cm) obtained from Duxbury Bay on 5/16/84, and was observed in all of the I sediment segments (0-15 cm) collected on 10/19/84. The observation of Cs-137 was also made in the majority of the sediment segments (0-18 cm) at Warren Cove and in all of the sediment segments (0-15 cm) collected 3-46

on 10/15/84. There was one observation of Cs-137 at Plymouth Beach in the 10-15 cm sediment segment collected on 5/17/84. The majority of sediment segments (4-30 cm) collected on 5/17/84 for the control station at Marshfield had positive measurements of Cs-137, and there was only one observation of Cs-137 in the sediment samples collected on 10/16/84 at the 10-15cm segment. The concentrations of Cs-137 at Duxbury Bay may be explained by the fact that the sediment samples have a silty character not connon to the other samples. The Warren Cove 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 con-centrations of Be-7, and to some extent Cs-137, at Duxbury Bay, Warren Cove and Marshfield, are attributable to the fission products related to fallout from previous weapons testing.

In addition to the above, there were four positive measurements of Co-60 observed. The highest mean concentration of Co-60 was observed at Rocky Point. All three sediment segments (0-15 cm) collected at Rocky Point on 10/11/84 indicated the presence of Co-60. Onesedimentsegment(5-10 cm) collected at Manomet Point on 10/18/84 also indicated the presence of Co-60. The measured concentrations of Co-60 are due to the liquid effluents cf PNPS-1.

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 are unavailable at 3-47

( this writing, but are usually presented in Table III-J-2. In the past, and as is expected for the 1984 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.

[ l

[

[-

[

3-48

TABLE III-J-l ERMAP RESULTS SEDIMENT EDILM: SEDIENT UNITS: PCI/KG DRY INDICATOR STATIONS STATION WITH HIGHEST E AN CONTROL STATIONS eteeeeeeeeeeeeeeee eeseeeeeeeeeeeeeeeeeeeeve seeeeeee*,eeeeee RADIONUCLIDES TAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RA%E (10N-ROUTINE)* LLD NO. ETECTEDe, NO. NO. DETECTEDet NO. DETECTEDn BE-7 ( 60) ( 4.7 2 2.0)F ! 13 ( !.! t .6)E 2 ( 4.5 1 4.8)E !

I ( 2) (-1.7 -

( 3/ 49),

6.8)E 2 (-5.5 - 67.5)E 1

( 2/ !!)*

(-1.5 -

( 1/ !!)*

4.7)E 2 K-40 ( 60) ( 1.0 t .0)E 4 13 ( 1.4 i .0)E 4 ( !.0 t .0)E 4

( 0) ( 6.3 - 15.9)E 3 ( 1.0 - 1.6)E 4 ( 9.1 - !!.6)E 3

( 49/ 49)e *( 11/ 11)# *( 11/ !!)*

CR-51 ( 60) (-1.1 13.1]E O !! ( 3.0 t 1.8)E 1 (-2.2 2 2.5)E 1

( 0) (-3.3 - 1.7)E 2 (-6.3 - 17.3)E I' (-1.6 - .8)E 2

( 0/ 49), e( 0/ !!)* ef 0/ 11),

MN-54 ( 60) 60. (-8.3 i 1.4)E O !! (-3.2 2 2.1)E O (-1.0 t .3)E 1

( 0) (-3.1 - .9)E 1 (-1.9 - .8)E 1 (-2.4 - 1.1)E 1 e( 0/ 49), e( 0/ !!), *( 0/ !!)e CD-58 ( 60) 60. (-1.6 t 1.2)E O 12 ( 6.8 2 23.7)E -1 (-6.6 1 2.4)E O

( 0) (-2.2 - 1.9)E I (-9.2 - 15.3)E O (-2.4 - .5)E 1

( 0/ 49)* *( 0/ 11)* *( 0/ 11)*

FE-59 ( 60) 120. (-7.0 t 3.2)E O 13 ( 3.5 t 8.9)E O (-!.! t 7.7)E O

( 0) (-4.8 - 5.4)E ! (-3.3 - 5.4)E 1 (-5.0 - 3.4)E 1 e( 0/ 49), ei 0/ !!), e( 0/ !!)e CO-60 ( 60) 50. ( 5.9 2 3.1)E 0 11 ( 2.1 1 1.2)E 1 (-1.6 i 2.3)E O

( 4) (-1.9 - 10.3)E 1 (-1.8 - 10.3)E 1 (-!.3 - 1.0)E 1 e( 4/ 49), e( 3/ !!)e *( 0/ 11)*

ZN-65 ( 60) 50. ( 3.9 t 29.6)E -! 11 ( 5.4 i 4.7)E O (-1.3 * .6)E !

( 0) (-5.6 - 4.6)E 1 (-2.6 - 3.0)E ! (-4.1 - 1.4)E 1 e( 0/ 49)e *( 0/ 11), et 0/ !!)*

ZR-95 ( 60) 50. ( 9.5 t 2.7]E O 13 ( 2.7 i .5)E 1 ( 1.1 i .5)E 1

( 0) (-2.7 - 5.8)E 1 ( 3.6 - 58.4)E C (-1.6 - 3.1)E 1

( 0/ 49)e *( 0/ 11), *( 0/ !!)*

NON-RCUTINE REFERS TO THE NUMEER OF SEPARATE EASUREMENTS WHICH WET <E GREATER THAN TEN (10) TIMES THE AVERAGE BACKGR'JND J FOR THE PERIOD OF THE REPORT.

e THE FRACTICN OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS

(!.E. >3 STD K VIATIONS) IS INDICATED WITH *( le.

3-49

TABLE III-J-1 I

(CONTINUED)

EDIlm SEDIENT UNITS: PCI/KG DRY INDICATOR STATIONS STATIM WITH HIGEST EAN CONTROL STATIONS eseeeeeeeeeentenee seeeeeeeeeeeeeeeeeeeeeeen seeeeeeeeeeeee*,

RADIOMJCLIDES EAN MAN EAN (NO. ANALYSES) REQUIRED RANCE STA. RANGE RANGE (NON-ROUTINE)e LLD NO. DETECTEDee NO. NO. DETECTEDee NO. IETECTEDee NB-95 ( 60) ( 4.6 1 1.5)E O 11 ( 7.0 t 1.8)E 0 ( 4.5 t 3.8)E O

( 0) (-1.9 - 2.9)E 1 (-5.5 - 15.5)E O (~-1.5 - 2.4)E 1

( 0/ 49)e el 0/ 11), *( 0/ !!)*

( !.81 15 ( 3.8 i 3.0)E O ( !.4 i 1.5)E O I RU-103 ( 60)

( 0) (-1.8 -

( 0/ 49)*

1.2)E O 2.3sE 1 (-1.1 -

( 0/ !!)*

2.3)E 1 (-8.4 -

( 0/ !!)*

8.3)E O RU-106 ( 60) (-1.8 i .9)E 1 24 ( 5.2 i 1.8)E 1 ( 5.2 i 1.8)E 1

( 0) (-2.0 - 1.5)E 2 (-4.5 - 12.9)E I (-4.5 - 12.9)E 1 e( 0/ 49)e e( 0/ !!)* *( 0/ !!),

I-131 ( 60) (-2.0 t 6.6)E O 15 ( 1.4 i 1.3)E 1 (-1.1 i 18.7)E O

( 0) (-1.3 - 1.1)E 2 (-5.2 - 9.7)E 1 (-1.0 - .9)E 2 e( 0/ 49)* *( 0/ 11)* *( 0/ !!)e CS-134 ( 60) 50. (-2.2 1 1.0)E O 14 ( 2.4 1 4.4)E O (-1.1 i 2.5)E O

( 0) (-1.5 - 1.9)E 1 (-5.5 - 18.7)E O (-2.0 - .9)E 1

( 0/ 49), *( 0/ 5)* e( 0/ !!)*

CS-137 ( 60) 50. ( 2.1 i .4)E 1 13 ( 6.7 i .9)E 1 ( 2.4 t .6)E 1

( 0) (-1.1 - !!.4)E 1 ( 1.9 - !!.4)E 1 ( !.1 - 736.0)E -1

( 19/ 49)e *( 10/ !!)* et 6/ !!),

BA-140 ( 60) (-2.7 i .5)E 1 11 (-1.4 i .9)E 1 (-2.6 t .8)E 1 I ( 0) (-1.2 -

et 0/ 49),

.3)E 2 (-5.6 -

( 0/ lile 3.3)E 1 (-7.3 -

( 0/ 11),

.2)E 1 CE-141 ( 60) ( !.! t .2)E 1 13 ( 2.3 i .7)E 1 ( 7.4 i 5.0)E O

( 0) (-2.3 - 5.6)E 1 (-2.3 - 5.6)E 1 (-1.9 - 3.5)E 1

( 0/ 49)* *( 0/ 11), *( 0/ 11),

CE-144 ( 60) 150. (-2.7 i .6)E 1 14 (-1.2 i 1.7)E 1 (-1.6 t 1.5)E 1

( 0) (-1.2 - .6)E 2 (-5.1 - 2.9)E .1 (-1.1 - .4)E 2

( 0/ 49)e e( 0/ 5)* *( 0/ lile AC-228 ( 60) ( 3.9 i .2)E 2 13 ( 6.4 i .3)E 2 ( 3.5 i .2)E 2

( 0) ( !.6 - 7.4)E 2 ( 3.8 - 7.4)E 2 ( 2.8 - 4.9)E 2

( 49/ 49)* *( !!/ !!)* *( 11/ !!)*

NON-ROUTIE REFERS TO TE NLMBER OF SEPARATE EASLREENTS IMICH WERE @ EATER T)MN TEN (10) T!ES TE A'KRAGE BACK0R0lND FOR TE PERIOD OF TT REPORT.

- THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE EASUREENTS (I.E. )3 STD DEVIATIONS) IS INDICATED WITH e( )*.

3-50

. ....._____.__.m_____.

TABLE III-J-2 RESULTS OF SEDlHENT ANALYSES FOR PLUTONIUM l

Location Depth (cm) Results !

pC1/Kg (dry) +- % Error (1 ) (a) l 238 239,240 Pu Pu

.Duxbury 0-2 Plymouth Harbor 0-2 Plymouth Harbor 16-18 Rocky Point 0-2 Unavailable at this time Rocky Point 12-14 Manomet Point 0-2 Harshfield-Control 0-2 (a) If the result is zero, the error is in pC1/Kg 3-51 I

1 l

III.K. Milk I

Milk samples were collected primarily at two locations during 1984, the Plymouth County Farm (Station 11 - 3.5 mi - H) and the Whitman Farm )

(Station 21 - 21 mi - NN). As stated in Section II, Boston Edison is l

aware of a milk-producing cow located at Beaver Dam Road (Station 28 -

2.5 mi - S). Unfor tunately, samples were unavailable from Beaver Dam Road during 1984. This, the only dependable indicator station (within 5 miles) for milk near PNPS-1 during 1984 was from the Plymouth Country Farm. This was confirmed in the 1984 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.

During 1984, milk samples were not collected frc,m either station during week number 32 in early August due to the fault of Boston Edison.

The results of ERMAP program for the milk media are presented in Table III-K-1. The results of analyses for Cs-137 and Sr-90 are presented 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.

The highest mean concentration of Sr-90 occurred at Plymouth County Farm (collected on 5/17/84) and the highest mean concentration of Sr-89 occurred at the Plymouth County Farm (collected on 4/19/84). 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 3-52

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

period exhibited a Sr-89/Sr-90 ratio of about 1/80 and therefore it is unlikely that PNPS-1 is the major source of the indicator staticn activity since the measured Sr-89/Sr-90 was about 2/5.

l l

l In the case of.Cs-137, the highest mean value of concentration occurred I

at Plymouth County Farm (3.5 mi - H). The Cs-137 highest mean I concentration for Plymouth County Farm occurred in mid-April (collected on 4/19/84). The absence of Cs-134 at this location would indicate that the primary source of Cs-137 is other than PNPS-1, and was most likely due to fallout from previous atmospheric weapons testing.

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

3-53

,__.._...-_.c_. __. _.___._ _______. ..._ ___ - ..__.... __

TABLE III-K-1 ERMAP RESULTS-MIIX EDIUM: MILK LNITS: PCI/KG INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIOP6 eeeeeeeeeeeeeessee eeeeeeeeeeeeeeeeeeeeeeeen see**eeeeeeeeeee PADIOPAJCLIDES EAN EAN EAN (NO. AMLYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE)e LLD NO. DETECTEDee NO. NO. IETECTEDee NO. IETECTEDee SR-89 ( 34) 10. ( 3.2 1 1.8)E -1 !! ( 3.2 i 1.8)E -1 (-2.8 1 1.4)E -1

( 0) (-5.8 - 20.6)E -1 (-5.8 - 20.6)E -1 (-!.! - 1.7)E O

( 0/ 17)e *( 0/ 17)e of 0/ 17)e I SR-90 ( 34)

( 0)

2. ( 3.8 i

( 2.7 -

( 17/ 17)e

.2)E O 5.3)E O 11 ( 3.8 i

( 2.7 -

( 17/ 17)*

.2)E O 5.3)E O

( 2.1 i .2)E O

( 9.5 - 36.4)E -1

( 15/ 17)*

BE-7 ( 34) ( !.4 1 16.6)E -1 21 ( 9.5 i 17.7)E -1 ( 9.5 t 17.7)E -1

( 0) (-1.4 - 1.3)E 1 (-1.2 - 1.4)E 1 (-1.2 - 1.4)E 1

( 0/ 17)e *( 0/ 17)* *( 0/ 17)*

K-40 ( 34) ( !.4 * .0]E 3 11 ( !.4 i .0)E 3 ( 1.4 i .0)E 3

( 0) ( 1.4 - 1.5)E 3 ( 1.4 - 1.5)E 3 ( !.3 - 1.5)E 3

( 17/ 17)* e( 17/ 17)* *( 17/ 171*

CR-51 ( 34) (-1.8 i 1.8)E 0 21 (-1.7 i 2.8)E O (-1.7 t 2.8)E O

( 0) (-1.6 - 2.0)E 1 (-2.9 - 1.5)E I (-2.9 - 1.5)E 1

( 0/ 17)* e( 0/ 17)* *( 0/ 17),

PN-54 ( 34) (5.61 33.5)E -2 21 ( !.6 f 2.4)E -1 ( 1.6 1 2.4)E -1

( 0) (-1.9 - 3.2)E O (-1.8 - 1.7)E O (-1.8 - 1.7)E O

( 0/ 17)e *( 0/ 17)* *( 0/ 17)*

CO-58 ( 34) (-3.7 1 1.8)E -1 21 (-3.5

2.3)E -1 (-3.5 1 2.3)E -!

( 0) (-1.8 - 1.1)E O (-1.9 - 1.6)E O (-1.9 - 1.6)E O e( 0/ 17)e *( 0/ 17)e et 0/ 17)#

FE-59 ( 34) ( 8.9 i 5.8)E -1 !! ( 8.9 i 5.8)E -1 ( 5.8 t 5.8)E -1

( 0) (-2.5 - 6.1)E O (-2.5 - 6.1)E O (-3.9 - 4.4)E O

( 0/ 17)* *( 0/ 17)# *( 0/ 17)e CD-60 ( 34) (-7.8 i 39.7)E -2 !! (-7.8 t 39.7)E -2 (-6.9 i 3.3)E -1

( 0) (-4.4 - 2.2)E O (-4.4 - 2.2)E O (-3.3 - 2.5)E O

( 0/ 17)* *( 0/ 17)* *( 0/ 17),

a I

NON-ROUTINE REFERS TO THE NLfGER OF SEPARATE EASUREMENTS WHICH WERE (EEATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF THE REP 3RT.

j ** TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTABLE EASUREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *( le. .

3-54

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

TABLE III-K-1 (CONTINUED)

EDIUM: MILK LNITS: PCI/KG INDICATOR STATIONS STATION WITH HIGEST M CONTR0[. STATIONS

.................. e........................ een. ..........

RADIONJCLIDES EAN EAN M (NO. AMLYSES) M IRED RANGE STA. RANGE RANGE (NON-ROUTIE). LLD NO. DETECTED., NO. NO. DETECTED., NO. DETECTED..

ZN-65 ( 34) (-9.5 2 6.8)E -1 21 (-3.5 t 6.7)E -1 (-3.5 1 6.7)E -1

( 0) (-6.6 - 5.6)E O (-6.5 - 3.7)E O (-6.5 - 3.7)E O et 0/ 17)* *( 0/ 17)* a( 0/ 17)*

2R-95 ( 34) ( 2.5 t 3.2)E -1 11 ( 2.5 i 3.2)E -1 (-5.2 i 5.1)E -1

( 0) (-3.2 - 1.7)E O (-3.2 - 1.7)E O (-4.3 - 3.5)E O

.( 0/ 17)* a( 0/ 17). *( 0/ 17).

NB-95 ( 34) ( 3.1 1 2.9)E -1 !! ( 3.1 1 2.9)E -1 (-3.6 t 21.2)E -2

( 0) (-2.0 - 2.2)E O (-2.0 - 2.2)E O (-1.1 - 1.8)E O

( 0/ 17). *( 0/ 17)e *( 0/ 17).

RU-103 ( 34) (-1.0 t .3)E O 21 (-1.0 i .3)E O (-1.0 t .3)E O

( 0) (-2.5 - 1.5)E O (-3.1 - .8)E O (-3.1 - .8)E O

.( 0/ 17). *( 0/ 17). *( 0/ 17).

RU-106 ( 34) (-1.9 2 2.2)E O 21 (-5.8 2 22.1)E -1 (-5.8 1 22.1)E -1

( 0) (-1.4 - 2.1)E 1 (-1.3 - 1.6)E 1 (-1.3 - 1.6)E 1

.( 0/ 17). .( 0/ 17). .( 0/ 17).

1-131 ( 34) 2. ( 4.6 i 6.4)E -3 !! ( 4.6 t 6.4)E -3 (-2.4 t 7.4)E -3

( 0) (-2.7 - 5.2)E -2 (-2.7 - 5.2)E -2 (-7.0 - 4.5)E -2

.( 0/ 17). .( 0/ 17). .( 0/ 17).

CS-134 ( 34) 15. (-5.2 t 2.1)E -1 11 (-5.2 i 2.1)E -1 (-6.3 1 2.2)E -1

( 0) (-2.1 - .9)E O (-2.1 - .9)E O (-2.2 - .6)E O

.( 0/ 17). .( 0/ 17). .( 0/ 17).

CS-137 ( 34) 15. ( 4.1 i .5)E O 11 ( 4.1 i .5)E 0 ( 2.5 t .5)E O

( 0) (-1.2 - 8.9)E O (-1.2 - 8.9)E O (-9.1 - 650.0)E -2

.( 13/ 17). *( 13/ 17)* *( 6/ 17).

BA-140 ( 34) 15. (-3.7 1 3.7)E -1 11 (-3.7 i 3.7)E -1 (-4.9 t 3.6)E -1

( 0) (-3.5 - 2.2)E O (-3.5 - 2.2)E O (-2.3 - 4.1)E O

.( 0/ 17). *( 0/ 17). *( 0/ 17).

CE-141 ( 34) ( !.! t .4)E O 11 ( !.1 i .4)E O ( 1.0 t .5)E O

( 0) (-2.7 - 4.6)E O (-2.7 - 4.6)E O (-3.1 - 4.3)E O

.( 0/ 17). .( 0/ 17). *( 0/ 17)e e NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREMENTS WHICH WERE GREATER TMN TEN (10) TIES TE AVERAGE BACKGROLND FOR TE PERIOD OF THE REPORT.

.. TE FRACTION CF SAMPLE AM.YSES YIELDING ETECTAEtE EASLREMENTS (I.E. 23 STD DEVIATIONS) IS INDICATED WITH .( )..

- %w

^

1

~

. _ _ . _ . . . . . . _ . . . _ _ _ _ . . . I TABLE III-K-1 (CONTINUED)

EDILM: MILK LNITS: PCI/KG I l

I INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANCE (NON-ROUTIE). LLD NO. DETECTED., NO. NO. DETECTED.. NO. IETECTED.,

CE-144 ( 34) (-1.2 1 1.61E O 21 ( 9.7 1 12.5)E -1 ( 9.7 1 12.5)E -1 i

( 0) (-1.6 - 1.2)E 1 (-9.6 - 8.4)E O (-9.6 - 8.4)E O

.( 0/ 17). .( 0/ 17). .( 0/ 17).

AC-228 ( 34) (-6.7 t 10.3)E -1 21 ( 2.3 i 10.7)E -1 ( 2.3 i 10.7)E -1

( 0) (-9.4 - 5.6)E O (-7.2 - 7.5)E O (-7.2 - 7.5)E O

.( 0/ 17). .( 0/ 17). .( 0/ 17).

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

.. TE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASLEEMENTS (I.E. 23 STD DEVIATIONS) IS INDICATED WITH ( )..

3 56

l FIGURE III-K-1 CONCENTRATIONS OF Cs-137 IN MILK l .

l

u 8

F l i 8

l . -

- 0

~

9 M

l C.D

_J l 8 b

Y ,

d r

i b CM e

.l i

55 cc b

bb @

p ..

00 b

[ N

~

2 e e e a .

l I

WW890~11X / S3180303Id l . . . _ . _ _ . _..,_ _, ,

l 3-57

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

.I

'I ::

lI I

l '

I s

I i E

k I i 8

I EN

=,

C i

a -

M d

E

=a i n

i I 00 b

I , . . . . .

14AIEKrl!N / S31W10(X)Id I -

I , . - . _ . . _ . . , _ ,

'I 3 -58

~

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

SSE/S - Station 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 9/18/84). 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 Prograr Report No. 11. This report identi-fled 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 3-59

. _m.-__....-_-__ ... _ _. . . .. . . . .

TABLE III-L-1 ERMAP RESULTS-CRANBERRIES EDIUM: CRANBERRIES LNITS: PCI/KG ET INDICATOR STATIONS STATION WITH HIGEST EAN CONTRG. STATIONS fiffffffffffffffff fffffffffffffffffffffffff efffffffffffffff RADIOPtICLIDES EAN EAN EAN (NO. AMLYSES) REQUIRED RANGE STA. RAFI RANGE (NON-ROUTINEli LLD NO. DETECTEDff NO. NO. IETECTEDit NO. DETECTEDif BE-7 ( 3) ( 5.5 i 1.3)E 1 13 ( 6.8 i 9.1)E 1 ( 3.0 1 6.0)E 1

( 0) ( 4.2 - 6.8)E 1 f( 0/ 2)f *( 0/ 115 *( 0/ 119 I K-40 ( 3)

( 0)

( 6.7 i

( 5.6 -

f( 2/ 2)f 1.1)E 2 7.8)E 2 14 ( 7.8 i f( 1/ 119 1.5)E 2 ( 4.9 i 5( 1/ 1)f 1.5)E 2 CR-51 ( 3) ( 2.6 i 11.6)E 1 14 ( !.4 i .8)E 2 (-3.5 i 7.1)E 1

( 0) (-8.9 - 14.2)E 1 f( 0/ 2)f *( 0/ 1)f *( 0/ 115 PN-54 ( 3) (-9.3 t !!.7)E O 23 ( 5.7 i 8.2)E O ( 5.7 i 8.2)E O I 0) (-2.1 - .2)E 1 f( 0/ 2)f f( 0/ 1)* *( 0/ 115 C0-58 ( 3) (-7.0 i 5.8)E O 23 (-9.5 i 70.8)E -! (-9.5 1 70.8)E -1

( 0) (-!.3 - .1)E 1 f( 0/ 214 f( 0/ 114 *( 0/ 1)f FE-59 ( 3) ( !.5 i .0)E 1 14 ( !.5 1 1.6)E 1 ( 1.0 i 1.5)E I

( 0) ( 1.5 - 1.5)E 1 f( 0/ 2)f *( 0/ 1)f *( 0/ 1)f C0-60 ( 3) (-1.1 t .6)E 1 23 ( 1.4 i 1.1)E 1 ( !.4 i 1.1)E 1

( 0) (-1.8 - .5)E 1 f( 0/ 2)f f( 0/ 115 f( 0/ 1)f ZN-65 ( 3) (-1.6 i .3)E 1 23 ( 2.9 i 15.1)E O ( 2.9 i 15.1)E 0

( 0) (-1.9 - -1.3)E 1 f( 0/ 2)f *( 0/ 1)f *( 0/ 114 ZR-95 ( 3) ( 9.3 1 6.1)E 0 13 ( !.5 t 1.7)E 1 (-1.7 i 1.4)E 1

( 0) ( 3.3 - 15.4)E 0 f( 0/ 2)f et 0/ 1)f f( 0/ 114 i NON-ROUTINE REFERS TO THE NUMBER OF SEPARATE EASUREENTS WHICH WERE CREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF THE REPORT.

If it5 FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE EAstREMENTS

(!.?. >3 STD DEVIATIONS) IS INDICATED WITH ft 14 3-60

TABLE III-L-1 (CONTINUED)

EDIUM: CRANBERRIES LNITS: PCI/KG ET INDICATOR STATIONS STATION WITH HIGEST M CONTROL STATIONS eseeeeee****eeeeee ee******eseeeeeeeeeeeeese seeee****et***ee RADIONUCLIDES M EAN M (NO. ANALYSES) M IRED RANGE STA. RANGE RANGE (M)N-ROUTIEle LLD NO. ETECTEDee NO. NO. DETECTEDee N0. DETECTED *e NB-95 ( 3) ( 9.5 t 1.9)E O 13 ( 1.1 i 1.1)E 1 ( 6.6

7.7)E O

( 0) ( 7.6 - 11.4)E O

( 0/ 2)e *( 0/ 1)* e( 0/ 1)e RU-103 ( 3) (-1.6 t .1)E 1 23 (-7.8 i 75.8)E -1 (-7.8 1 75.8)E -1

( 0) (-1.7 - -1.6)E 1

( 0/ 2)* e( 0/ lie *( 0/ 11e RU-106 ( 3) (-2.4

8.6)E 1 13 ( 6.2 i 8.4)E 1 ( 1.4 i 5.5)E 1

( 0) (-1.1 - .6)E 2

( 0/ 2)* *( 0/ 1)* *( 0/ 1)e I-131 ( 3) ( 2.0 t 3.1)E 1 14 ( 5.1 t 2.2)E 1 ( 4.8 t 13.6)E O

( 0) (-1.1 - 5.1)E 1

( 0/ 2)* *( 0/ 1)e *( 0/ 1)*

CS-134 ( 3) (-1.5 i .3)E 1 23 ( 3.7 i 7.2)E O ( 3.7 i 7.2)E O

( 0) (-1.8 - -1.2)E 1 e( 0/ 2)* *( 0/ 1)e *( 0/ 1)*

CS-!37 ( 3) ( !.2 i 1.2)E 2 13 ( 2.5 t .2)E 2 ( 7.7 t 6.9)E O

( 1) (-1.8 - 248.0)E O ef 1/ 2)e *( 1/ 1)* *( 0/ 1)e BA-140 ( 3) (-1.6 f 2.2)E 1 13 ( 6.1 i 18.1)E O (-1.1 i 11.6)E O

( 0) (-3.7 - .6)E 1 et 0/ 2)* *( 0/ 1)e *( 0/ 1),

CE-141 ( 3) ( !.6 i .3)E 1 13 ( 1.9 t 1.9)E 1 ( 8.9 i !!.7)E O

( 0) ( !.3 - 1.9)E 1 e( 0/ 2)* *( 0/ 1)* *( 0/ 1)*

CE-144 ( 3) (-1.3 f 5.9)E 1 13 ( 4.6 i 5.9)E 1 (-6.4 f 41.4)E O

( 0) (-7.2 - 4.6)E 1

( 0/ 2)e *( 0/ 1)* *( 0/ 1)*

AC-228 ( 3) (-5.1 i 21.2)E O 13 ( !.6

5.0)E ! (-1.3 i 35.9)E O

( 0) (-2.6 - 1.6)E 1

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

e NON-ROUTINE REFERS TO TE NUMBER OF SEPARATE EASUREENTS WHICH WERE GREATER Tim TEN (10) TIES TE AVERAGE BACKGR0lND FOR TE PERIOD OF TE REPORT.

I en THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASLREENTS (f.E. 23 STD DEVIATIONS) IS INDICATED WITH *( le.

III.M. Vegetation I Samples of tuberous and green leafy vegetables were collected at the time of harvest at five locations: Plymouth County Farm (3.5 mi - H), Bridgewater Farm (20 mi - H), the Malmgeen Reside.me (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 - SSW).

The only nuclides observed (other than naturally occurring Be-7, AcTh-228 (peak) and K-40) was Cs-137. A positive measurement of Cs-137 was detected in a vegetation sample from the Jenkins Residence (rhubarb, collected 9/26/84). The absence of Cs-134 at this location and the fact that measured Cs-137 concentration is greater than 10,000 times what would be expected at this location based on releases from PNPS-1, strongly indicates that fallout, not PNPS-1, is the primary source of this Cs-137. Therefore, it is extremely unitxaly that there was any environmental impact on vegetation due to the operation of PNPS-1.

3-62

TABLE III-M-1 I ERMAP RESULTS-VEGETATION EDILP!: FOOD CROP UNITS: PCI/KG ET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS eseee**ee**eeeeee, essestee***eesee**esee*** ***e**eeee***ee, RADIONJCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RA%E (NON-ROUTIE)* LLD NO. DETECTED ** NO. NO. DETECTED +e NO. DETECTEDee BE-7 ( 10) ( 4.5 t 1.7)E 2 16 ( !.3 i .!)E 3 ( 2.9 i 2.0)E 1

( 5) t-8.8 - 1300.0)E O (-1.1 - 5.5)E 1

( 5/ 7)* *( 1/ 1)e *( 0/ 3)e K-40 ( 10) ( 2.7 t .3)E 3 43 ( 3.7 i .2)E 3 ( 2.0 t .3)E 3

' ( 0) ( !.3 - 3.7)E 3 ( !.4 - 2.4)E 3

( 7/ 7), *( 1/ 1)e *( 3/ 3),

CR-51 ( 10) (-1.9 t 2.5)E 1 16 ( 9.1 i 8.9)E 1 (-2.1 2 3.4)E 1

( 0) (-9.3 - 9.1)E 1 (-7.! - 4.5)E 1

( 0/ 7)* *( 0/ 1)* et 0/ 3)e MN-54 ( 10) 130. (-3.0 i 1.7)E O 16 ( 4.9 t 83.5)E -1 (-3.8 i 2.9)E O

( 0) (-1.2 - .2)E 1 (-9.4 - .2)E O

( 0/ 7)* *( 0/ 1)* *( 0/ 3)e C0-58 ( 10) 130. (-4.1 i 1.4)E O 76 (-1.9 i 6.4)E O (-4.9 i 6.3)E O I ( 0) (-1.3 -

( 0/ 7)e

.2)E 1

( 0/ 1),

(-1.7 -

( 0/ 3),

.4)E 1 FE-59 ( 10) 260. (-1.1 1 4.4)E O 76 ( 6.6 i 13.4)E O ( 5.2 t 8.5)E O

( 0) (-2.0 - .8)E 1 (-7.2 - 21.4)E O e( 0/ 7)* *( 0/ 1)e *( 0/ 3)e

! CD-60 ( 10) 130. ( 3.5 1 4.4)E 0 16 ( 1.2 i 1.3)E I (-8.1 t 4.5)E O

, ( 0) (-6.9 - 26.5)E O (-1.6 - .0)E 1 l *( 0/ 7)* *( 0/ 1)* *( 0/ 3)*

ZN-65 ( 10) 260. (8.71 47.5)E -1 43 ( 2.0 t' 2.4)E 1 ( 9.4 i 6.3)E O i

( 0) (-1.3 - 2.0)E 1 (-3.1 - 16.7)E O l et 0/ 7)* *( 0/ 1), *( 0/ 3)*

ZR-95 ( 10) (-7.7 i 58.4)E -1 27 ( !.9 i .5)E 1 ( !.9 i .5)E 1 l ( 0) (-2.6 - 1.4)E I ( !.2 - 2.8)E 1 ( !.2 - 2.8)E 1 el 0/ 7)* *( 0/ 3)* *( 0/ 3)e i

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

- TE FRACTION OF SAMPLE ANALYSES Y1ELDING DETECTABLE EASUREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH e( )*.

1 3-63

. .. ...--- . - --=_ - . . - . - . . - . - - . -. .

TABLE III-M-1 (CONTINUED)

EDILM: FOOD CR0P UNITS: PCI/KG ET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS se*****eeeneeeeeee easteeeeeeeeeeeeeeeeeeeen eeeeeeeeeeeeees, RADIOMJCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (EN-ROUTIE)* LLD NO. ETECTEDet NO. NO. DETECTEDet NO. DETECTED *e NB-95 ( 10) ( 2.0 t 2.7)E O 76 ( 9.7 i 6.3)E O ( 2.2 1 4.4)E O

( 0) (-8.2 - 11.2)E O (-3.4 - !!.0)E O

( 0/ 7)e *( 0/ Ile *( 0/ 3)*

RU-103 ( 10) (-3.8 1 2.0)E O 43 ( !.5 x 12.1)E O ( 6.1 1 42.1)E -1

( 0) (-9.6 - 1.5)E O (-5.2 - 8.8)E O

( 0/ 7), *( 0/ 1)* *( 0/ 3),

RU-106 ( 10) (-3.5 1 2.2)E 1 75 ( 3.4 i 41.0)E O (-3.3 1 6.5)E !

( 0) (-1.3 - .3)E 2 (-9.9 - 9.7)E 1

( 0/ 7)* *( 0/ 1)e *( 0/ 3)e I-131 ( 10) 80. ( 2.1 i 72.8)E -1 75 ( 1.1 1 1.6)E 1 (-9.2 1 113.1)E -1

( 0) (-3.5 - 2.7)E 1 (-2.3 - 1.4)E 1 e( 0/ 7)* *( 0/ 1), *( 0/ 3)*

CS-134 ( 10) 80. (-2.1 1 4.3)E O 75 ( 9.2 1 6.8)E O (-1.1 i .1)E 1

( 0) (-1.8 - 1.3)E 1 (-1.3 - -1.0]E 1

( 0/ 7)* *( 0/ 1)* *( 0/ 3),

CS-137 ( 10) 80. ( !.6 i .8)E 1 76 ( 6.0 t .8)E 1 ( 6.6 2 4.2)E O

( 1) (-3.3 - 60.4)E O (-1.8 - 11.7)E O el 1/ 7)* et 1/ 11e *( 0/ 3)e BA-140 ( 10) (-3.2 t 2.8)E O 43 ( 7.0 1 17.5)E 0 (-1.1 t 4.5)E O

( 0) (-1.4 - .7)E 1 (-9.0 - 6.5)E O e( 0/ 7)e *( 0/ 1), *( 0/ 3)e CE-141 ( 10) ( 5.2 1 4.7)E O 16 ( 2.6 t 1.4)E 1 ( 3.5 2 6.8)E O

( 0) (-1.2 - 2.6)E 1 (-7.3 - 16.1)E O

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

CE-144 ( 10) ( 2.9 f 1.7)E 1 !! ( 5.3 t 3.1)E 1 ( 7.1 i 9.8)E O

( 0) (-2.1 - 11.5)E 1 ( !.6 - 11.5)E 1 (-1.2 - 2.1)E 1

( 0/ 7), et 0/ 3)e *( 0/ 3)e AC-228 ( 10) ( 2.3 i .9)E 1 75 ( 4.2 1 2.6)E 1 ( 2.9 i -2.9)E 1

( 0) (-4.1 - 59.9)E O (-2.3 - 7.8)E 1 et 0/ 7)e *( 0/ 1)* *( 0/ 3),

a WN-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF TE PEPORT.

g ** THE FRACTION OF SAtFLE ANALYSES YIELDING DETECTABLE f*EASUREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED LITH *( Je.

III.N Forage Beef forage is collected from three locations annually: the Plymou'h t County Farm (3.5 mi - H - Station Number 11), Whitman Farm (21 mi - NW

- Station 21) and Bridgewater Farm (20 mi - H - Station 27). The beef fo' rage sample from Station #27 was unavailable during 1984. The results of the ERMAP program for the media are presented in Table III-N-1. The following positive measurements were made: Be-7 and Cs-137 at the Plymouth County Farm; and, Be-7 at the Whitman Farm. In addition, all stations had a positive measurement of K-40.

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

l 3-65 l

lI

.. .. ---. - .... . . ----.. .. 1 I TABLE III-N-1 ERMAP RESULTS-FORAGE LNITS: PCI/KO ET I

EDIUM: CATTLE FEED INDICAT0tlSTATIONS STATION WITH HIGEST MAN CONTROL STATIONS I RADIONUCLIDES (NO. ANALYSES) REQUIRED RANGE 4fffffffffffffffff EAN fffffffffffffffffffffffff STA.

EAN RANGE fiffffffffffffff EAN RANGE (NON-ROUTINE)f LLD NO. DETECTED 4i NO. NO. DETECTED 4i NO. DETECTED 4i

( 4.7 1 .3)E 3 ( 4.7 i .3)E 3 ( 2.6 i .2)E 3 I

PE-7 ( 2) 11

( 0) f( 1/ 119 f( 1/ 1)* f( 1/ 1)f I K-40 ( 2)

( 0)

( 4.8 i f( 1/ 1)f

.4)E 3 21 ( !.6 i f( 1/ 1)f

.1)E 4 ( 1.6 i et 1/ 1)f

.1)E 4 CR-51 ( 2) ( 3.3 1 24.2)E 1 11 ( 3.3 1 24.2)E 1 (-8.7 i 17.7)E 1

( 0) l f( 0/ 119 f( 0/ 1)f f( 0/ 1)f

E i MN-54 ( 2) 130. ( 3.6 1 1.9)E 1 !! ( 3.6 i 1.9)E I (-3.7 i 13.7)E O

! ( 0) f( 0/ 1)f f( 0/ 1)f *( 0/ 119 l CO-59 ( 2) 130. ( 7.0 2 19.5)E O 21 ( !.9 t 1.5)E I (1.92 1.5)E 1 I

( 0) fl 0/ 1)f *( 0/ 11f f( 0/ 1)f FE-59 ( 2) 260. ( 6.6 i 50.3)E O 11 ( 6.6 f 50.3)E O (-6.8 2 46.5)E O

( 0) f( 0/ 119 f( 0/ lit f( 0/ 1)f I

l CD-60 ( 2)

( 0) 130. ( 3.4 1 258.0)E -!

f( 0/ 1)f

!! ( 3.4 1 250.0)E -1 f( 0/ !)f

(-!.3 t f( 0/ 1)f 1.9)E 1 ZN-65 ( 2) 260. ( 3.0 i 4.2)E 1 11 ( 3.0 1 4.2)E I (-6.6 i 4.1)E 1

( 0) f( 0/ 1)f f( 0/ !)f f( 0/ 1)f ZR-95 ( 2) (-3.8 i 3.8)E ! 21 ( !.7 2 2.8)E 1 (1.71 2.8)E 1

( ( 0) f( 0/ 1)f f( 0/ 1)f f( 0/ 119 I f NON-ROUTINE REFERS TO THE N'."5ER OF SEPARATE FIASURErINTS WHICH WERE GREATER THAN TEN (10) TIFES THE AVERA0E BACKGROUND F0fi THE FERIOD OF THE Fio0RT.

ff THE FRACTION OF St#LE ANALYSES YIELDING DETECTABLE MAS'.5EPINTS

'I (I.E. >3 STD DEVIATIONS) IS INDICATED WITH f( 19 I

3-66

TABLE III-N-1 (CGITIINUED)

EDIlli: CATTLE FEED LNITS: PCI/KG ET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS ffffffffffffffffff fifffffffffffffffffffffff fiffffffffffffff RADIONUCLIDES EAN EAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE)f LLD NO. DETECTEDff NO. NO. DETECTEDff NO. DETECTEDif NS-95 ( 2) ( 1.4 f 2.3)E 1 21 ( !.5 i 1.9)E 1 ( !.5 t 1.9)E 1

( 0) f( 0/ 1)f f( 0/ 135 f( 0/ 1)f RU-103 ( 2) (-4.4 1 23.4)E O 11 (-4.4 1 23.4)E O (-2.4 1 2.0)E 1

( 0) f( 0/ lit f( 0/ !)f f( 0/ 1)f RU-106 ( 2) (-1.3 i 1.2)E 2 !! (-1.3 t 1.2)E 2 (-1.6 i 1.3)E 2

( 0) f( 0/ 1)f f( 0/ 1)f f( 0/ 1)#

I-131 ( 2) 80. (-1.9 i 2.2)E 2 21 (-1.1 1 1.6)E 2 (-1.1 1 1.6)E 2

( 0) f( 0/ !)f f( 0/ 1)f f( 0/ 116 CS-134 ( 2) 80. ( 3.8 1 2.0)E 1 11 ( 3.8 i 2.0)E 1 (-1.7 f 1.5)E 1

( 0) f( 0/ 1)G f( 0/ 1)# f( 0/ 1)f CS-137 ( 2) 80. ( 9.1 t 1.9)E 1 !! ( 9.1 t 1.9)E 1 ( 3.4 i 137.0)E -1

( !)

f( 1/ 1)f f( 1/ 1)f f( 0/ !)f BA-140 ( 2) (-1.6 i .9)E 2 21 (-5.9 i 8.5)E ! (-5.9 i 8.5)E !

( 0) f( 0/ 119 f( 0/ 1)# ft 0/ 1)f CE-141 ( 2) ( !.2 t 3.6)E 1 !! ( !.2 i 3.6)E 1 (-2.0 t 2.7)E !

( 0) f( 0/ 1)f f( 0/ !)f f( 0/ 1)f CE-144 ( 2) ( 7.8 i 78.8)E O !! ( 7.8 i 78.8)E O (-5.8 i 6.1)E !

( 0) f( 0/ 1)# f( 0/ 1)f f( 0/ 1)f AC-228 ( 2) (-8.6 i 7.0)E 1 21 (-7.6 2 6.!7 1 (-7.6 1 6.6)E I

( 0) f( 0/ 1)f f( 0/ 115 f( 0/ 1)f f 10N-ROUTINE REFERS TO TE NUMBER OF SEPAPATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR THE PERIOD OF TE REPORT.

if TE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE EASUREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH f( 19

_ 3-67_

i IV. References 1

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.

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

I 3. Yankee Atomic Electric Company - Program "ERMAP", Version 3.1

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

4. Memorandum, Yankee Atomic Electric Company,1984 Anrual Direct Radiation Survey, REG 136/84, July 1984, E. R. Cumming.

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

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

4-1 I

APPENDIX A - ANOMALOUS MEASUREMENT REPORTS l

I I

W A-1

l There were no Anomalous Measurement Reports for the year of 1984.

-r I

l a )

e 4 '

S l

l

I A-2

, l

I .

APPENDIX B - Radioactive Effluents t

i a 4 4 s

l3 l 3 ..

A %

1 5 .

I e

f Ib I J

U y

,- - - B , <

4

/

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information I January - June, 1984 Ucensee DPR.33 Facihes imm Nuclear Power Station

1. Regulator > Umits OS + 0

a. Fissen and aanvation pses ,

g

- I 0.25/E 0.10/ 1 h hidines 2Ci

s. Parisculates. half./Qua Ines >> das s rter

d. bquid etiluents 13(1.8E40s+1.8E50Y)51 10Ci/ Quarter

2. Manimum Permissille Concentration Pioude the MPt's used m deternuning all..wable retene rates ur sim enitations

4. Fission and utn inen pses to CFR 20

h. lodines Appendia B

s. Parisculates. half.hveW Jays Table ll J. bquid elsluenos H . 3 = 1 X 10-5 pCi/ml;all rest,10 CFR 20. Appendix B. Table II I 3. Average Energ.s Proside the aveiage enern (El us the raJionu leJe mnruie niiclease on tission and 4 iivassovi pase>. ei appl..am.f. 4 6,,,

N/

4. Measurements and Approsimations of Total Radioactivity Pi.mde the methods used to measure ni ap iinnuate the total radioa.tivity in etilaents and ilie metti. Js used in Jeternune radionu.hJe somposition

a. Fissnin and 4.tivation pses ceu

b. lodines y,,

s. Paris.ulat es

^'"'8 I

d bound e ttluenis-

$. Batch Releases PiouJe the solio.ing information eclating to bat.h releaes vi radioa tive materist in liquid and pscou3 enluent, i

a. Uquad

l. Number ot' bat.h relenes 324 I :. Totaltime penod for baish relenes 1425.55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months 1 Maumum time peinid for a batcle tel'a' - 76. 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months 4 Aserage time peinod for bat.h seleases' 4.40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months

f. M.r.imum time pern J fin a haich telease - 10 inutes

6. Average stream now Junng periods ua release ni elipuem inio. noming stream 5. 27E4GPM b Caseous (Not Applicable)

I 6. Abnormal Releases a.None

b. None I

TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

'IASEOUS EFFLUENTS. SUMMATION OF ALL RELEASES JANUARY - JUNE 1984 .

Quarter Quarter Est. Total Unit 1 2 Error. %

A. Fission and activation gases

1. Total release Ci *

l l

2. Average release rate for period uCi/sec

3. Percent of Technical Specification limit Fo -1 B. Iodines

1. Total iodine 131 Ci <4_74g_g * ;g l

2. Average release rate for period uCi/see < 9.14E-6

3. Percent of Technical Specification limit To < 2.37E-3 C. Particulates

1. Particula:es with half lives > 8 days Ci lc1_1pp 3 1_37p.3 l gn l

2. Average release rate for period uCi/see < 2. 28E-4 5.29E-4

3. Percent of Technical Specification limit Fe < 0.05 <0.05

4. Gross alpha radioactivity Ci 7.15E-7 <1.19E-6 I D. Tritium

1. Total release Ci l 1.28E0 1.89E-1 40 l I 2. Average release rate for period

3. Percent of Technical Specification limit uCi/see 9e 1.63E-1 2.40E-2 I

Plant shutdown on 12/10/83 - no releases 3

I AHLt lb EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT ( 3934 )

GASEOUS EFFLUENTS - ELEVATED RELEASE JAtiUARY - JUtiE 1984 CONTINUOUS MODE BATCH MODE l Nuchdes Released l Umt l Quarter -ll Quarter-2 l Ouarter l Quarter l

1. Fission gases .

I krypton S5 Ci *

krypton 85m C

krypton 87 Ci *

krypton SS *

Ci xenon 133 Ci *

xenon 135 Ci *

xenon 135m Ci *

xenon 13S Ci *

xenon 131m Ci *

xenon 137 Ci *

xenon 133m Ci *

Total for period Ci *

l l

2. Iodines I iodine 131 Ci < 6.19E-6

l iodine 133 Ci l iodine 135 C *

Total for period Ci < 6.19E-6 *

3. Particulates strontium S9 Ci < 1. 52E-4

strontium 90 Ci < 1. 80E-6 lE

,g

'"**4 cesium 137 C'

Ci

<3 9 E-6 3.04E-6 barium lanthanum 140 Ci < 9.60E-6

chromium 51 Ci -

manganese 54 Ci 1.24E-6

cobalt 58 Ci -

iron 59 Ci cobalt 60 Ci 8.13E-6 zine 65 Ci - *

, zirconium niobium 95 Ci _

cerium 141 Ci -

cerium 144 Ci -

ruthenium 103 C -

l ruthenium 106 Ci -

l 4

Piant shutdown on 12/10/83 - no releases

TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1984)

GASEOUS EFFLUENTS GROUND LEVEL RELEASE JANUARY - JUNE 1984 CONTINUOUS MODE BATCH MODE Urut Quarter .2 Quarter Quarter Nochdes Released Quarter.1 l

1. Fission gases krypton 85 Ci *

l krypton 85m Ci l Ci *

krypton 87 l

j krypton SS Ci Ci *

xenon 133 Ci *

xenon 135 xenon.135m Ci Ci *

xenon 138 Total for penod Ci

2. lodines

I iodine 131 Ci <4.12E-5 iodine-133 Ci iodine 135 Ci Total for penod Ci < 4.12E-5 'I l l

3. Particulates strontium 89 Ci < 1.28E-6 < 6.90E-7 strontium 90 Ci < 1. 94E-7 1.23E-6 cesium 134 Ci 1.24E-5 1.02E-5 cesium 137 Ci 1.46E-4 1.17E-4 barium lanthanum-140 Ci < 5.07E-5 -

manganese 54 Ci 2.11E-4 1.73E-4 cobalt 58 Ci 2.84E-5 9.39E-6 iron 59 Ci cobalt 60 Ci 5.54E-4 8.29i.-4 zine 65 Ci - 2.26E-4 zirconium niobium 95 Ci cenum 141 Q _

ruthenium 103 Ci -

ruthenium 106 Ci -

Plant Shutdown on 12/10/83- no releases 5

i

JANUARY - JUNE 1984 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT Q984)

I LIQUID EFFLUENTS. SUMMATION OF ALL RELEASES l

Quarter Quarter Est. T otal Unit ] 2 E rror. %

A. Fission and activation products

1. Total release (not including tritium. Ci noble gases or alpha) 1.61E0 7.01E-2 30

2. Average diluted concentration p Cirml during period 1.05E-7 4.01E-8

3. Percent of applicable limit 9 16.10 0.70 B. Tritium

1. Total release Ci 1.00E1 4.57E-1 h 30 l

2. Average diluted concentration uCi ml during period 6.54E-7 2.61E-7

{ 3. Percent of applicable limit 9 6.54 ?.61 C. Dissolved and entrained gases f 1. Total release Ci (a) (a) l

2. Average diluted concentration uCi ml during period 7

(- 3. Percent of applicable limit te D. Gross alpha radioactivity l 1. Total release l Ci l < 3.60E 4 l<7.54E-5 l 40 I i

E. Volume of waste released sprior liters 7.26E6 9.99E5 20 to dilutioni F. Volume of dilution water used liters 1.75E9 20 1.53E10 during period (a) No measurable releases.

t 4

L 6

TABLE 2B EF F LUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1984)

LIQUID EFFLUENTS JANUARY - JUNE 1984 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter 1 Quarter 2 strontium 89 Ci < 3.08E-4 < 4.50E-5 strontium 90 Ci 1.83E-3 < 9. 6 3E-5 cesium 13 : Ci l 2.80E-3 1.80E-4 cesium 137 Ci l 7.89E-2 7.02E-3~

iodine 131 Ci l 8.20E-7 l -

cobalt 58 Ci l 7 7pr-p l 7.07E-4 cobalt 60 Ci l 8.41E-1 4.19E-2 iron 59 Ci l 5.57E-3 -

zine 65 Ci l l 1.61E-3 3.77E-4 manganese 54 Ci 8.33E-2 3.13E-3 chromium 51 Ci 2.62E-5 1.61E-5 .

=

zirconimum niobium 95 Ci l molybdenum 99- . .

technetium 99m Ci barium lanthanum 140 Ci 1.29E-6 -

cerium 141 Ci 2.23E-3 l -

iodine-133 Ci -

l cerium 144 Ci 2.08E-3 l -

silver 110m Ci -

l iron 55 Ci 4.55E-1 ! 1.24E52 l umdentified l Ci l l l 1.09E-1 l 4.22E-3 l 1

Total for period iabovel C 3 gro l 7 gir-7 '

l xenon 133 Ci -

l xenon 135 Ci -

l -

l 7

E TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1984)

SOLID HASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - JUNE 1984 I A. SOLID HASTE SHIPPED OFF SITE FOR BURIAL OR DISPOSAL. (not irradiated fuel) l

! 1. TYPE OF HASTE UNIT 6 MONTH EST. TOTAL PERIOD ERROR %

a. Spent resins, filter sludges, m' 82.12 evaporator bottoms, etc. C1 311.39830 N/A

b. Dry compressible waste, m' 1241.55 contaminated equipment, etc. C1 29.16550 N/A I c. Irradiated components, m' control rods, etc. Cl N/A N/A

' d. Otner.(Describe) m' miscellaneous low-level waste Cl N/A N/A I' 2; ESTIMATE OF MAJOR NUCLIDE COMPOSITION.

(by type of waste) % E(Curies)

a. Spent Resin, Filter Sludges, Co-60 44.505 138.58645 Evaporator Bottoms, etc. Co-58 2.716 8.4579 H-3 0.046 0.14254 Cs-137 32.869 102.35222 Cs-134 2.549 7.93936 C-14 0.026 0.08098 Fe-59 0.196 0.60939 I-131 0.004 0.01180 I 129 0.010 0.03110 La-140 0.064 0.20060 Nb-95 0.010 0.03181 Zr-95 0.007 0.02066 Sr-90 7.441 23.17074 Ni-63 1.403 4.37051 Tc-99m 0.010 0.03110 Mo-99 - -

Zn-65 1.698 5.28686 Mn-54 3.874 12.06298 Cr-51 2.148 6.68872 Np-239 0.004 0.01180 Pu-241 0.372 1.15971 Ru-103 0.008 0.02609 Cm-242 0.017 0.05187 Sb-124 0.023 0.07307 TOTAL 100.000 311.39830 8A

s

'7ABLE 3 (continued)

7. E(Curies)

b. Dry Compressible Waste Co-60 43.719 12.73023-Contaminated Equipment- Co-58 7.620 2.21676 Cs-137- 7.882 2.29517 Cs-134 0.499 0.14529 Fe-59 1.315 0.38298 I-131 0.021 0.00526 Ba-140 0.506 0.14720 Sr-90 0.167 0.0*859 Tc-99m 0.012 0.00357 Zn-65 4.564 1.32393 Mn-54 5.032 1.46510 No-95 0.058 0.01692 Zr-95 0.027 0.00738-Cr-51 25.950 7.55626 Ce-141 0.149 0.04338 Ru-103 0.036 0.01061 N1-63 0.744 0.21663 Pu-241 0.374 0.10874 Cm-242 0.010 0.00286 I-129 0.010 0.00296

C-14 0.018 0.00532

H-3 1.068 0.35797 g Cs-136 .009 0.00275

[ Sb-124 .128 0.03724 Aq-110 .082 0.02390 TOTAL 100.000 *29.16550 l

c. N/A

d. N/A

(; 3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transoortation Destination b

52 Tractor - Trailer Barnwell, S.C.

h. 4, IRRADIATED FUEL SHIPMENTS (Disposition)

-Number of Shioments Mode of Transportation Destination f~ None- N/A N/a r *C-14 and H-3 activities were not considered as part of the total percent for t the first several shipments of 1984, but were listed separately on shipping documents. These separ&te totals ~have been added to the Curie column for this report.

8B

(

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i Supplemental Information July - December, 1984 Facility Pilgrim Nuclear Power Station Ucensee DPR-35

1. Regulatory Umits Fission and activation gases QS QV

a. 4 4]

0.25/E 0.10/E

b. iodmes 2Ci/ Quarter

(. Particulates. half-lives >K das s 13 (1.8E4Qs + 1.8E5Qv)1 1

d. bquid elliuents: 10Ci/ Quarter

2. Masimum Permissible Conantration Piovide the MPCs used m deternumng allowable release rates or contentrations. <

J. Fassum and activation gases. 10 CFR 20

h. lodmes: Appendix B

e. Partneulates, half.hves >M days: Table !!

d. bquid ettluents. H 3 = 1 X 101 pC1/ml;all rest,10 CFR 20, Appendix B. Table II

3. Average Energv Provide the average energy (U of the radionuslide miitttire sii releases or tissioni and ac'ivation gases. it appheable. XXXaXMM 4.

E for Qs = 0.795 : E for 0v = 0.434 Measurements and Approitima: ions of Total Radioactivity Provide the methods used to measure or approumate the trial radioactivity m cilluents and the methi ds used to determme radionuchde compossinon.

a. Fissam and activation gases: Get.i

b. lodines:

Istopic

c. Particulaies.

Analysis

d. bquid eIfluents:

5. Batch Releases Piovide the followmg information relating to batsh releases ut radioaciise maienals m hquid and easeous efiluents

a. Uquid I. Number of batch releasev 34')

2. Total time penod for hatch releaws. S

3. Maumum time penod for a baich release - 1464.{3b0u[ours

/.43 n

4. Aserage time penod for batch seleases~ 4.20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months

5. Minimum time penod foi a batch release: - 0 25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months

6. Average stream flow dunng penods of release of etiluent mio a llowmg stream- 9.53E + 4 GPM

b. Gaseous (Not Applicable)

6. Abnormal Releases a

[,NONE 2

ha p

l TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES July - December,1984 Quarter - Quarter Est. Total i unit (3) (4) Error, %

A. Fission and activation gases

1. Total release Ci N/A* <1.84E+1 4.30E+1 l

2. Average release rate for period gCi/sec <2.31E0

3. Percent of Technical Specification limit % <7.33E-4 B. Iodines

1. Totaliodine.131 Ci N/A* <3.09E-5 3.50E+1 l

2. Average release rate for period pCi/sec <3.89E-6

3. Percent of Technical Specification limit % <1.55E-3 C. Particulates

1. Particulates with half-lives > 8 days Ci 1.74E-3 (8.03E-4 3.50E+1 l

2. Average release rate for period pCi/sec 2.19E-4 <1.01E-4

3. Percent of Technical Specification limit % 5.12E-2 <1.75E-2

4. Gross alpha radioactivity Ci 3.81E-7 <5.14E-7 D. Tritium

1. Total release ci 2.16E-1 8.28E-2 5.25E+1 l

2. Average release rate for period uCi/sec 2.72E-2 1.04E-2

3. Percent of Technical Specification limit % N/A i N/A

Plant shut down since 12-10-83 5

i 1

1 f

3

TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ( 1984)

GASEOUS EFFLUENTS - ELEVATED RELEASE July - December, 1984 CONTINUOUS MODE BATCH MODE ,

I l Nuclides Released l Unit l ouarter(3)l Quarter (4)l overter l ouarter l

1. Fission aases l

krypton-85 Ci < 1.00E-5 krypton-85m Ci 1.67E0 i krypton-87 Ci 3.1 OE0 krypton-88 Ci 4.27E0 xenon-133 Ci 9.30E-1 xenon-135 Ci 7.18E0 xenon-135m Ci 7.00E-2 xenon-138 Ci 2.90E-1 xenon 131m Ci -

xenon-137 Ci -

xenon-133m Ci -

Total for period Ci 1.75E+1

2. Iodines iodine-131 Ci 2.39E-5 lodine-133 Ci 1.85E-3 iodine-135 Ci 2.84E-3 Total for period Ci 4.71E-3 u

3. Particulates strontium 89 Ci 1.58E-4 I strontium 90 Ci 1.29E-6 cesium-134 Ci -

cesium-137 Ci <1.35E-5 barium-lanthanum 140 Ci 2.21E-5 chromium 51 Ci -

manganese 54 Ci -

cobalt-58 Ci -

iron 59 Ci -

cobalt-60 Ci <3.55E-5 zine-65 Ci -

zirconium niobium-95 Ci -

cerium 141 Ci -

cerium 144 Ci -

ruthenium-103 Ci -

ruthenium 106 Ci -

4

K L

3 TABLE 1C

[

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1984) e

- GASEOUS EFFLUENTS - GROUND LEVEL RELEASE

- July - December, 1984

[ CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter (3) ouarter (4) Quarter Quarter

1. Fission gases krypton-85 Ci < l .00E-6 krypton-85m La < 2.00E-2 o krypton-87 Ci < 6. 00E-2

. krypton-88 Ci < 8.00E-2 3 xenon-133 Ci < 6. 00E-2 xenon 135 Ci 6.80E-1 xenon-135m Ci -

xenon-138 Ci -

h Total for period Ci 9.00E-1

2. Iodines 1 iodine-131 Ci < 7.03E-6

! iodine-133 Ci < 4.32E-5 iodine-135 Ci < 5.59E-4 Total for period Ci < 6.09E-4 f

3. Particulates strontium 89 Ci < 5.79E-7 1.52E-4 .

=

strontium 90 Ci < 1.94E-7 < 4.44E-7 I cesium 134 Ci -

cesium-137 Ci 6.53E-5 < 6.43E-5 barium-lanthanum-140 Ci - <9.00E-6

, manganese-54 Ci 1.19E-4 m cobalt 58 Ci -

iron-59 Ci -

E cobalt 60 Ci 1.55E-3 < 3. 47E-4

= zinc-65 Ci -

E zirconium niobium 95 Ci -

} cerium-141 Ci -

ruthenium 103 Ci -

{

I ruthenium 106 Ci -

T 5

e

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1984)

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES l July - December, 1984 Ouarter Quarter Est. Total :

Unit (3) (4) Error. %

A. Fission and activation products

1. Total release (not including tritium, Ci l noble gases, or alpha) 9.80E-1 2.09E0 3.54E+1

2. Average diluted concentration pCi/ml 7.42E-8 1.13E-7 during period

3. Percent of applicable limit % 9.80E0 2.09E+1 B. Tritium

1. Total release Ci 1.48E0 2.77E0 -

3.55E+1

2. Average diluted concentration pCi/mi during period 1.12E-7 1.50E-7

~

3. Percent of applicable limit % 1.12E0 1.50E0 C. Dissolved and entrained gases

1. Total release ci -

1.72E-3 4.24E+1

2. Average diluted concentration pCi/ml -

9.30E-ll during period

3. Percent of applicable limit % - -

D. Gross alpha radioactivity

1. Total release l Ci l < 1.95E-4 l < 4.09E-4 l 5.00E+1 l E. Volume of waste released (prior liters 2.92E+6 8.86E+6 2.00E+1 to dilution)

F. Volume of dilution water used liters 1.32E+10 1.85E+10 2.00E+1 I during period s

6

k. .. .

TABLE 2B f EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1984) f LIQUID EFFLUENTS l July - December, 1984

( ;

CONTINUOUS MODE BATCH MODE

, Nuclides Released Unit Quarter Quarter Quarter (3) ouarter(4)

I strontium-89 Ci <l.i3E-4 < 3.62E-4 strontium-90 Ci T4.60E-4 5.36E-4 cesium-134 Ci 6.33E-3 9.46E-2 cesium-137 Ci 1.19E-1 1.08E0 iodine-131 Ci - -

cobalt-58 Ci 6.23E-5 4.46E-5 cobalt-60 Ci 5.23E-1 6.62E-1 iron-59 Ci 7.57E-7 -

zine 65 Ci 2.15E-3 8.91E-3 manganese-54 Ci 1.09E-2 1.04E-2 chromium-51 Ci 5.85E-4 -

zirconimum niobium 95 Ci 9.69E-5 3.96E-6 molybdenum 99-technetium 99m C barium-lanthanum-140 Ci - -

cerium-141 Ci - -

iodine-133 Ci -

1.28E-3 cerium 144 Ci 1.27E-4 -

silver-110m Ci - -

iron 55 Ci 1.63E-1 1.61E-1 unidentified l Ci l 1.54E-1 7. l l E-P.

Total for period (above) Ci 9.80E-1 2.09E0 xenon 133 Ci - -

xenon 135 Ci - 1.72E-3 7

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1984)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JULY - DECEMBER 1984 A. SOLID WASTE SHIPPED OFF SITE FOR BURIAL OR DISPOSAL. (not irradiated fuel) t

1. TYPE OF WASTE UNIT 6 MONTH EST. TOTAL PERIOD ERROR %

a. Spent resins, filter sludges, m' 191.54 evaporator bottoms, etc. Cl 1163.75420 N/A i.

b. Dry compressible waste, m' 1601.72 contaminated equipment, etc. C1 35.28364 N/A

c. Irradiated temponents, m' control rods, etc. Cl N/A N/A

d. Other (Describe) m" miscellaneous low-level waste Cl N/A N/A

2. ESTIMATE OF MAJOR NUCLIOE COMPOSITION.

(by type of waste) % E(Curies)

a. Spent Resin. Filter Sludges, Co-60 52.009 605.25724 Evaporator Bottoms, etc. Co-58 .273 3.17331 Cs-137 22.001 256.03506 Cs-134 2.910 33.86401 Fe-55 15.231 177.24940 Fe-59 .005 .06036 Sr-90 .213 2.48022 Tc-99m .004 .04499 Zn-65 .460 5.35956 Mn-54 2.253 26.22129 Nb-95 .004 .04438 Ce-141 .004 .04438 Ce-144 .056 .65540 Ru-103 .044 .04438 Pu-241 .489 5.69442 Cm-242 .010 .11635 C-14 .023 .26446 I-129 .002 .02123 H-3 .012 ~~

.13868 Nt-63 4.024 46.83004 Sb-124 .006 .06776 Co-57 .007 ;08727 TOTALS 100.000 1163.75420 8A l

TABLE 3 (continued)

~

7. E(Curies)

b. Dry Compressible Waste Co-60 67.566 23.83968 Contaminated Equipment Co-58 .071 .02520 Cs-137 25.020 8.82796 Cs-134 1.375 .48508 Sr-90 .373 .13155 Tc-99m .016 .00563 Mn-54 2.099 .74050 Pu-241 1.151 40593 ,

Cm-242 .010 .0035?

C-14 .019 .00683 I-129 .011 .00404 H-3 1.345 .47461 N1-63 .944 .33311 ,

TOTAL 100.00 35.28364

c. N/A

d. N/A

3. SOLIO WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 78 Tractor - Trailer Barnwell, S.C.

2 Tractor - Trailer Richland. WA.

4. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shloments Mode of Transportation Destination None N/A N/a 88

APPENDIX C - 1982 Soil Survey l

C-1

I Results of Boston Edison _In Situ Gamma Spectrometry Soil Analysis for 1982 Introduction In compliance with Boston Edison's Technical Specifications for radiological monitoring of the environment, in situ gamma spectrometry analyses were performed at eleven sites during May, October and December of 1982. In addition to the gamma spectrometry, which employs a Ge(Li) "downlooker" detector in accordance with Reference 1, measurements were taken with a pressurized ion chamber (PIC) to assess the total exposure rates, and soil core samples were taken at five of the stations to confirm the in situ results.

At all elevE stations, by far the major contributors to the exposure rate due to soil were naturally occurring radionuclides and Cs-137, which is a result of fallout from weapons testing. A small amount of Co-60 was present in the soil at one si te. These results are summarized in Tables 1-12, and the original data is on permanent file at the Environmental Laboratory.

Methodology

-In situ gamma spectrometry was performed at each of the eleven locations, along with FIC measurements for comparison. When possible, a soil sample was also taken for laboratory gama analysis.

In situ gama spectrometry is a convenient and efficient technique used to evalWte the radioactive constituents of the soil. Using assumptions concerning the soil composition and distribution of the radionuclide of interest, the exposure rate and activity concentration of that radionuclide can be calculated. This is done using the spectrum obtained with an unshielded Ge(Li) detector placea above the ground, together with detector specific parameters such as efficiency. The radionuclides of interest are fallout and plant related fission and activation products, as well as those which occur naturally. In evaluating the activity concentration and exposure rate for a given radionuclide, a parameter describing depth distribetion, a/p, must be evaluated. For naturally occurring radionuclides a value of zero is assumed, implying no increase < ' decrease in the concentration with soil depth. For radionuclides present only on the surface, such as those frnm

fresh fallout, a value of infinity is used. (This value is also used for calculations of apparent activity concentrations and exposure rates for those radionuclides not found during the peak search.) For man-made radionuclides found in the soil and not believed to be recently deposited, an expotential distribution is assumed with a/o = .206. This value is a good compromise between deep distribution and surface deposition; and laboratory analysis usually confirms that these radionuclides are present througout the first six inches of soil implying a period of migration. This procedure of in situ gamma spectrometry is explained in detail in Reference 2.

The PIC measurement, which includes all components of the exposure rate, not just terrestrial, is used to evaluate how much of the total exposure rate can be explained by the in situ results together with the cosmic contribution. At control statf ors, away friE the plant's influence, the PIC measurement is used to check the in situ results, as one would expect the terrestrial exposure rate, calculated

{ Es'ing the in-situ methodology, together with the cosmic contribution to closely

approxima *.FthTFIC resul ts.

> When possible soil core samples are also taken and analyzed at the laboratory to confirm the presence or absence of radionuclides in the soil which have been identified in the in situ analysis. In this way, the source term is identified as soil or unknown. E the latter case, the in situ calculations are not valid and results are not reported. In addition, anaTysis of the different core sections aids in defining the depth distribution of the radionuclide.

Results Tables 1-11 contain the results from the in situ gamma analysis for the eleven sites. (It should be noted that in August thTGe(Li) detector was repaired to remedy increasingly poor resolution. The poor resolution was not a problem in the measurements conducted during May; and prior to analysis of the remaining three sites, the operating characteristics of the detector were carefully checked with the result that recalibration following the repair was deemed unnecessary for in situ analysis (Reference 3).) 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. LLD values were not calculated for nuclides with more than one peak, as in these cases all of the peaks found were used to calculate the total exposure rate and activ'ty concentration for that nuclide (or series). Table 12 contains all positive in situ results as well -

as PIC measurements for comparison.

With two exceptions, all exposure rates due to activity within the soil are more than 95 percent resul ting from natural radiation. The remiinder is almost entirely due to Cs-137 which is considered to be a result of weapons testing and is found throughout the environment. The first exception is high Cs-137 concentration at site 10, resulting in 17 percent of the total exposure rate due to soil . The activity concentration for Cs-137 at this site is greater than five times the average value for the other stations. The most probable explanation for this is that the detector may have been placed over a local accumulation point of debris, and therefore the fallout related Cs-137 was present in a higher than average concentra tion. It should be noted that sites considerably closer to the plant shwed only typical environmental levels of Cs-137, and the high concentration is therefore not likely to be plant related. The second case in which the exposure rate due to soil was more than 5 percent related to fission or activation products, was at station 7 where Co-60 was identified during in situ an61ysis, and confirmed f by Laboratory soil analysis. The activity concentration was calculated to be 305*7 pCi/kg, assuming a value for a/o equal to .206, while Laboratory analysis resulted in a value of 224*13 pCi/kg. The value for a/o is likely to be greater than .206, i.e. the distribution of Co-60 was more planar, as it was not found in j the 2"-4" core section. This increase in a/r would result in a lower value for activity concentration more in line with the Laboratory results. In any case, the exposure rate due to Co-60 was calculated to be less than 1 uR/hr.

r k

A*_ - . _ _ _ _ _ _ _ - _ - - - . _ . _ _ _ _ . _ _ _ _ - - _ _ . _ - _ _ _ _ _ - _ . _ _ _ _ _ _ _ _

?*

L Cobolt-60 was identified at three additional sites, but could not be confirmed by Laboratory soil analysis (there was no core sample submitted for site 00). As the source term was therefore unknown for these sites, the' exposure rates which were calculated assuming soil to be the source term, are not valid and were not listed in Table 12. It should also be noted that Zr-95 was detected at two sites at levels at or below LLD, but these results could not be confirmed by soil analysis at the Laboratory.

The PIC measurements agreed well with the in situ results, when a cosmic component of 3.6 uR/hr (Reference 4) was added7with a few notable exceptions.

Sites 00, 07 and 08 showed relatively high PIC measurements which could not be explained with the Ge(Li) results. These sites are all within 0.15 miles of the plant so that the higher than background exposure rates were most likely a result of some source term other than soil.

m. +

I:

p References (1) .YAEL Procedure Number 510, Rev.1, " Identification and Quantitative Determination of Radionuclides in Soil by Gamma-Ray 3_ Situ Spectrometry."

I (2) HASL-258, "In-Situ Ge(Li) and Nal(TI) Gamma-Ray Spectrometry," September 1972.

l:

(3) YAEL Memo ELG 265/82 " Intrinsic Efficiency Check on Ge(Li) Detector No.1."

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

i

)

' s- --_--____

TABLE 1 l

L LOCATION: (JAREHOUSE LOCATIONS: 0 ()

COUN1 TIME: 6000 set COUN1 DATE: 05/27/02 InSitu COUNTING RESUL'sS NiJCLIDE 10 EXPOSURE RATE CONCENTR ATION nicroR/hr picoCi/Kgran NAME EX P U:3 UR E + S IGM A LLD CONC t- 1-SIGMA LLD RATE Ce-144 (-22e- Ib) E-4 'J 31 -- 4 ( 1 0(15- 63) EO 240E O Co-141 ( 5 ' - 1.5 ) E -4 47E -4 ( 3+- 14) E O SOE O

.1 131 ( Y+- 34) E--4 120E -4 ( 124 - 46) E-1 160E-1 Ub 12b ( 1 t- 11) E-3 42E-3 ( 18- 13) E O 47E D No 103 ( 4 7 + -- 4 0 ) E-4 140E-4 ( 4 h: - 30) E-1 140L-1 Da -140 ( Rut- 57) E-4 2 0 0 h--4 ( 7 e- - 13) C 0 quE O Ro 106 ( 13) E-- 3 4 71:--3 ( -U t - 20) ED 1 0 01- 0 x: C t, 1.57 ( I S65 t-- Y4) E4 310 L -4 ( 200 t-- 17) E O SSE O Zr --Yb ( 7 4 t -- Ub) E-4 3 0 0 F --4 ( 406- 46) F. - 1 16 0 L-1 Oli ';.

(-Mat-- 5 (1 ) E4 t u til.2 4 ( 11e 26) E1 ,'4:,- !

Mn -54 ( 1185-- 53) E-4 1 Y(ll: 4 ( 54 :- 24) E-1 Obl. - 1 x! 1:o-60 ( 707t- 21) E -- 3 V:!I{ -3 ( 211!24- 64) E -1 'J.0 U E - 1 La'140 ( ;'1 + - 11) E-3 3Yi.-3 ( 27t 14) E-1 4YL 1 xe M -4 0 ( 2714+- .50 ) E- ;i 61 E -3 ( 1516 + - 21) E 1 31C 1

- Ili - 23 2 ( 213U4- 63) E- 3 -

( 7bl ot -- 22) E (1 - - - - -

I l ..I i ' ',

J ( 13t16 4 - 40) EJ ---

( 761: 26) E O - - - -

iJ o t e? :

k th t i v i t y greater titan 3xstandard deviat: ion t l' e a l< in l'ound LLD in not calc ula ted i

I

TABLE 2' LOCATION: ROCKY HILL RD.

LOCATIONS: 01 COUNT TIME: 6000sec COUNT DATE: 05/27/82 InSitu C,ULINTING RESULTS EXPOSURii RARE CONCENTR A FION NUCLIDE ID picoCi/Kyran nicrOR/hr 1.LD CONC +-- 1-SIGMA LLD.

.NAME EXPOSUR E s--l-S IGM A

- R A'l E

c. e,0 L. S ( -134 - 43) EO I b u t. 0-Co-144 (-2us- v6) Lb 3;.' 0 E - 1

( .52+- 06) II--S JUOE-S (-351 V2) E -- I Ce t- 141 - 120E-1

'I"1 31 ( -- 13 -* - 25 ) E-4 DUE-4 ( 174- 34) E-1 32 0 E--4 ( 1 94 - 10) E O 36E D Ub-125 ( 164+- HV) E-4 110E-1 Ru;103 -( I S4 - 31) E-4 110E-4 ( 14+- 2V) E-1 170E 4 ( 78- 11) ED 3VE O

( 31+-'46) E-4 L'a - 14 0 Re-106 ( 64 - 10) E-3 3UL-3 ( 12+ - 23 ) EO 82L 0 230E-4 ( 2 V 6 +-- 14) E O 41E O

t Co-137 ( 1630*- 76) E -' 4 130E-1 Ze -Vb ( 121+- 71) E-4 UbOE-4 ( 654- 30) E-1 1SOE -4 ( -16 +- 22) E-1 7VE-1 Ni, - V r, (-31+- 42) E- 4 6LtC -I

( 704- 43) 11 - 4 l bOE -4 ( 364- IV) E-1

- Mr.' 54 S 2ti- 1 Go-40 ( 30t- 11) E- J 40E 3 ( 3V - 15) E-1 L.i - 14 0 -( S4 - 10) E- 3 3DL -3 ' ( 74 - 13) E-1 ~ 4 Ull- I x4 K-40 ( 2212+~ 34) 15 3 47E-J ( 1236+" 17) E 1 27E 1 x4 Itr;?3M ( 2252+- 50) E-3 - - - - - - ( 7VV4- 21) ED --

Wt U -2,50 ( 1346+- 41) E3 -~~ ( 740+- 23) E 11 - " - - -

I No ten :

l X . At' t i v x t y greater tii.m 3Kut uitlarel st o v s a t i ti n I

-t- P e til t i n l' o u n d I.LD i s no t c a lc u l a t ett

(

l.

l .

i. TABLE 3 Y

LOCATION: ROCKY HILL RD. (IJ )

LOCATION 4: 03 COUNT TIME: 6000sec COUNT DATE: 12/15/02 InCitu COUNTING RESULTU NUCLII)C ID EXPOSURE R A TE CONCENTR ATION nicruR/hr p ic o Ci /K t1 r a n NAME EXPOSUR E l--l - S I GM A LLD CONC s~ 1 -SIGFin LLD RA'IE Co 144 ( - 1 0 4 -- 12) E-4 43E-4 (-434- 53) ED 190E D Ce-141 ( Ot- 11) E-4 30E-4 ( 0 + -- 11) E O 41E O I-1 31 (-24 t - 31) E-4 110E-4 (-334- 42) E-1 lbOE-1 Sb-12S ( 27i- Y4) E-4 340E-4 ( 34- 11 ) E D 3YC 0 R u -103 - ( --55 4 - 33) E-4 120E-4 (-524- 32) E-1 120E 1 Le a -14 0 ( - 4 ? + -- 47) E -4 13 0 E- 4 (-11+- 11) E O 41E D R u -106 (-2+- 11) E-3 40E-3 (~4+- 24) EO HYC 0 O f- Co-137 ( 613 t- SS) E-4 160E 4 ( 1125t- 100) E-1 2YUE-1 Zr-YD ( 424 - 73) E -- 4 2 6 0 F.- 4 ( 23+- 40) E-1 14 0E -1 Nb 75 (-7 8 - 42) E4 120E-4 ( 12+- 53) E-1 1GUE-1 Mn-54 ( 100t- 45) E-4 16PE-4 ( 45+- 20) E-1 7,1 L-1 Co-60 ( 24+- 12) E- 3 44G-3 ( 315- 16) E-1 S6E-1 L.i - 14 0 ( 1Yt-- 11) E-3 30E-3 ( 25*- 14) E-1 4YC-1 0+ K-40 ( 2 4 Y 4 * -- 35) E- 3 4 4E -3 ( 1.1734- 20) E 1 24E 1 04 .Th 232 ( 247(1* - 57) E -3 - ----

( 076 +-- 2 0 ) EO - - - - -

.xt.U-230 ( 11706- 35) E-3 - - - - -

( 643+- l '/ ) E U ----

~Nutes:

0 Activity greater than 3xstandard deviation

+- Peak is found 1.LD is n o t calculated L OS* 8

4 h

TABLE 4 .

1 1

LOCATION: PLY. CENTER LOCATION #: 04 COUN1. TIME: 6000sec j COUN'I DATE: 10/07/82 InGitu COUNTING RESULTS NUCLIDE ID EXi'USUltE It A TE CONCENTHAFION nicrOR/hr picoCi/Kgrato

NAME EXPOSUREi-1 UIGMA LLO CONC +- 1-SIGMA LLD RAIL Cu-144 (-Si- 12) E- 4 43E -4 (-22+- 53) E. 0 1YDE O

-Co-141 ( 17+- 10) ti -4 3?E-4 ( 10+- 11) E D 40E O I-1 31 (-564- 31) E-4 110E-4 (-76+- 43) E-1 160E-1 Gb- 125 ( St- V6) E-4 3SOE-4 ( 1+- 11) EO 37E 0 Ru 103 (-224- 34) E-4 120E-4 (-21+- 32) E-1 120E-1 it.r- 14 0 (-1Yi- 4Y) E-4 10 0 E-4 (-4+- 11) E U 41E D R o -106 (-6+ - 11 ) E-3 40E-3 (--14 +- 24 ) EO UYE O

- Us-137 ,

( 27639- 74) E-4 16 0 E- 4 ( S02*- 14) EO d')E O Zr-YU - -

( 10+ 75) E-4 270E-4 ( 5+- 40) E -1 1 5 0 E -1 Nb-YU (-164t- 46) E- 4 170E-4 ( -0 4 &-- 23) E- I GOE-1 Mn-S4 (-4S+ - 60 ) E-4 21UE-4 (-50+- 67) E -1 240E-1 Co-60 (- 3 8 - 12 T E--3 46E-3 ( - 4 +- 15) E- I SME-1 La -140 (-13+- 14) E -3 52E-3 (-414 - 43) E-1 16 0 E. -1 x+ X 40-

. ( 23020- J4) E -3 4 3 E --3 ( 1331+~ 1Y) E 1 24C 1

- K4 11-232 ( 24144- Sb) E3 - - - - -

( 0564 - 19) EO -----

- U-23U ( 1S718- 3Y) li -d - - - - -

( 0638-* 21) E O - ----

Noten:

E Ac t iv i t y gr'ea t er- than 3X t.t andard deevi a t inn

+ Peak is i'ound LL D i t. not c alc u l a t ed 1

i .. .. .. .

. C>= .

TABLE 5 f.

I LOCATION: PROPERTY LINE LOCATION #: 06 COUNT TIME: 6000sec COUNT DATE: 05/26/82 InSitu COUNTING RESULTS NUCLIDE ID EXPUSURE RATE CONCENTR ATION nic r o R/hr picoCi/Karan NAMr. EXPU3URE+-1-SIGMA LLD CONC i- 1-SIGMA LLD R A'I L.

Ce-144 ( 4+- 12) E-4 43E-4 ( 16+- S4) C 0 190E D C o-- 141 (-U&- 11) E-4 3VE-4 (-Ot- 11 ) E-0 42E D I -1 31 ( 2D+- 31) E-4 110E-4 ( 34-i- 42) E-1 15DE-1 Gb-125 ( 2104- YS) E-4 340E-4 ( *!S4- 11) EO 33E O

(

Ru 103 ( 30+- 32) E-4 1200.-4 ( 364- 31) E -- 1 110E-1 Da-140 (-34+- 47) E-4 170E-4 (-U+- 11) EO 40E O R o -106 ( 15+- 11) E-3 3YE-3 ( 334- 24) EO USE O x+ Cu-137 ( 10V2+- 02) E-4 200E-4 ( 3 4 4 t- IS) E O 46E O Zr --7b ( 140+- 72) E-4 2SOE-4 ( 76t- 3'/ ) E-1 140E-1 Hb-YS ( 33+- 41) E-4 ISUE-4 ( l '/ t - 21) E- I /6E-1 Mn-54 ( 1164- 60) E-4 2101.-4 ( 1278- 67) E-1 230E-1 x Co-60 ( 3?+- 12) E-3 44E-3 ( G0 s - 16) E1 S6E-1 La -- 14 0 ( 35- 11) E-3 41E-3 ( 36- 14) E-- I 52E-1 44 K-40 ( 21038- 34) E-3 S4 E -3 ( 11*/08 17) E 1 30C 1 xt 1h-232 ( 2320+-- 60) E-3 - - - - - -

( !!234 - 21) EO xt U-230 ( 12YU i - 42 ) E-3 - " - - - - ( 7124 23) E O l

l l- Notes:

K Ac tivit y streater than 3xstandard deviation

+ P ea l< in fuund L L D i t. not calculated

.. ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

s s

(

TABLE 6- 'l ,

U l

LOCN.! 10N t. PEDESTRIAN BRIDGE LOCATIONt: 07' C3UN1 TIME: 6000sc4 e y .

COUN1 DATE: 05/26/2?

InSitu COUNTING RESULTS -

s-NUCLIDE ID EXPOSURE R A TE CONCENTR AT Ii]N nictuR/hr picoCi/K.jran '-

s NAME EX P 03UR E +--l -S I GM A LLD CONC <- 1-SI.GMA 'LLD RATE -

Ce -14 4 ( 5+- 15) E-4 52 E--4 -( 234- 67) EO 230E O Cc-141 ( - l u i - 13 ', ' E- 4 46E-4 (-11+- 14) E O - but 0 1~131 ( 40+- 35) E-4 120E-4 ( 65+- 47) E-1 1 6 01:.- 1 Sb-125 ( 20+- 12) E-3 42E-3 ( 32+- 13) E O 43E O R u --10 3 ( 374- 40) E-4 140E-4 ( 35+- 3D) ' E-1 140L-1 It a - 14 0 ( 408- 07) E-4 210E-4 ( 9+- 14) E O ~. 5 0 E ,0

)' '

Ru-106 ( 1 4-t - 13) E-3 47E-3 ( 31+- 29) F. U 1100C 0 K' Cs -137 i 113.5 +-- 3 0 ) C4 25 0 ED. ; ( 206+- 1 * ) E 'O 46E 'O 'd X Zr-Yb . (- '200+- 00) E-4 31f_"4 ( 151 + -- 40) t '. 1701.-1 f J b --75 ( 7:3- 52) E -4 100E-4 ( 43+-- 27) E-1 */ b E - 1 Ma -54 ( [614- 55) E-4 200L-4 ( "'..H - 25 ) E n1 YUL -i

-x i Co-60 '( 'YUVi- 23) E ;3 9'/E- Z ( 3051r- 70) C-1 .5 0 0 E - 1 '

La -14 0 ( - 17 + - 11) E-3 41E-3 's (-214< 14) E-1 S2L-1

-SSE-3 ( 1197+- 17) E 1 x' K-40 ( 2143+- 34) E3 31E 1 x4 T h --232 ( 2211+- 61) E-3 ----

( 7044- 22) E' O - - - - - -

X+ U --2 30 ( 1267*-- 46) E -3 - - - - -

( 696+- 25) E O - - - - -

s ,

No ten :

X Activity gteater than 3x.tandor9 deviation ,

+ Peak is found LLD is not c a l c u l a t ett r

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4 f?!+m,,'k 4 + sp' -

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+.;y, , 5,,, 7 y o)7j %<p+'e x N'h_ .. - - -- - "

A TABLE 7 LOCATION: OVERLOOK LOCATIONS: 00 COUNT TIME: 6000sec COUNT DATE: 05/26/82 InSitu COUNTING RESULTS NUCLIDE ID EXPOGURE R ATE CONCENTRATION nicruR/hr picoCi/Kgran NAME EXi' 0GUR E+-1 -S I GM A LLD CU N C + -- 1-SIGMA LLD RATE Ce-144 (-25+- 21) E-4 70L-4 (-111+- V(. ) E O 3bOE D Ce-141 (-10+- 17) E-4 69E-4 (-20+- 20) E O 74C 0 I--1 31 (-46+- 51) E-4 100E-4 ( -- 6 4 + - 70) E -1 2bOE-1 Sb-125 ( 11+- 15) C -- 3 54E-3 ( 12+ -- 17) E O 61E O 1

Ru -103 (-564- 54) E-4 190E-4 (-53+- 51) E -1 190E-1 Da-140 (-6&- 75) E-4 270E-4 (-1+- 17) E O 6dE O R u --10 6 (-254 - 17) E-3 63E-3 (-55+- 30) E D 140E O x+ Cs-137 ( 10 U l + . U'/ ) E -- 4 200E-4 ( I ??+- 16) E O SIC 0 Zr-95 ( 0+- 11) E--3 41 E--3 ( 434- 61) E-1 220E-1 Nb --75 (-65+- 67) E-4 2 4 0 E--4 ( -3 4 +- 35) E-1 130E-1 Mn-54 ( B0+- YY ) E-4 350E-4 ( 9+- 11) E O 3?E O

+ Co-60 ( 957&- 27) E-3 110 E-3 ( 2759&-- U2) E -I 350E-1 La-140 (-29+- 10) E-3 6YE-3 (-374- 23) E-- I UUE-1 W+ K-40 ( 2607+- 41) E -- 3 Y1E-3 ( 1458+- 23) E 1 01E 1 x+ Th-232 ( 2052+- 73) E-3 -- --

( 720+- 26) EO ----

x+ U-230 ( 1210+- 55) E-3 -- --

( 66S& 30) E O - - -

Notes:

x Activity greater than 3xstandard deviation t + Peak is found LLD is not calculated i

t, TABLE 8 .

LOCATION: EAST DREAKWATER LOCATION #: 0V COUNT TIME: 6000sec COUNT DATE: 05/27/82 .

InSitu COUNTING RESULTS d

NU'JLIDE ID EXPUSURE R ATE CONCENTR A fl0N nicroR/hr picoCi/Kgram NAME EXP OSUR E &--l-U IGM A LLI) CONC +-- 1-SI.GMA LLD R A1 E Ce-144 ( 64 - 12) E-4 4 3 E--4 ( 27+- 54) E O 1YUE O Ce-141 ( 12+- 11) E-4 30E-4 ( 13 F-- 11) E O 41E O I--131 (-17+- 31) E-4 110E-4 (-23+- 42) E-1 150E-1 f Ub-125 (-310- YS) E-4 350E-4 ( -- 3 + - 11) E O 3YE D R u --10 3 ( 3Y4 - 34) E-4 120E-4 ( 37+- 32) E- I 11011-1 It a -14 0 ( 504- 47) E-4 180E-4 ( 1 24-- 11) E D 41E O N " -- 10 6 ( 14- 11) E-3 41E-3 ( 34- 25) ED UYE O X t- Cn-137 ( 10004- 6Y) E-4 210E-4 ( 1024 ~ 13) E O 37E O A Zr-Yb ( 269+- 72) E-4 250E-4 ( 145+- 3Y) E-1 13 0 E-- 1 Nb-Vb ( 7+- 44) E -4 160E-4 ( 4+- 23) E- 1 02C-1 Mn-54 (-144- 46) E-4 170E-4 (-7+- 21) E-1 76E-1 Co-60 ( 330- 13) E -- 3 4?E-3 ( 43+- 17) E -- I 61E-1 L ee -- 14 0 ( U+- 11) E-3 4 0 E--3 ( -- 1 + - 14) E-1 51 L'-1 m& K-40 ( 2766+- 30) E-3 57E-3 ( 13450- 21) E 1 32E 1 xi T h --232 ( 2467+- 63) E-3 -----

( 875+- 22) EO - - - - - -

x+ U-238 ( 1357+- 44) E -3 -----

( 7464- 24) E O - - - - -

Notes:

x Activity greater than 3xstandard deviation t- Peak is found LLD is n ot calculated i

TABLE 9 LOCATION: CLEFT ROCK LOCATION #: 10 COUNT TIME: 6000sec COUNT DATE: 05/20/82 InSitu COUNTING RESULTS NUCLIDE ID EXPOSURE R ATE CONCENTRATION nitr o R /hr picoCi/Kyran NAME EXPOSURE +-1-SIGNA LLD CONC +- 1 -SIGMA LLD RATE Ce-144 ( V54- 99) E-5 340E-5 ( 43+- 44) EO 1SOE D Ce-141 ( 86+- 80) E-S 310E-5 ( 72+- VS) E-1 33 0 E-- 1 1--131 ( 234- 27) E-4 V2E -4 ( 31+- 36) E-1 130E-1 Ub-125 ( 108+- 96) E-4 350E-4 ( 12+- 11) E O 3YE O Ru-103 ( 26+- 33) E-4 120E-4 ( 254- 31) E-1 110E-1 i It a - 14 0 (-S*-- 47) E -4 170E-4 (-1+- 11) E O 40E D N u -1 (16 ( 20+- 11) C-3 37E-3 ( 61+- 23) EO U2C 0

4 Cs-137 ( 7 4 2 *-- 12) E-3 25E-3 ( 1713+- 22) E O 4dE O Zr-Yb ( 1104- 63) E-4 230E-4 ( SY4- 35) E-1 120E-1 Nb-75 ( 25'- 30) E -- 4 140E-4 ( 13+- 20) EI '/UE-1 M n -- 54 ( - 2 7 + -- 41 ) E-4 150E-4 (-124- 1Y) E-1 6YE-1 Co-60 ( 1 Y i-- 11) E -3 41E-3 ( 24t- 15) E--I S.3E - 1

~

La-140 (-S6+- 96) E-4 360E-4 ( 12) E-1 46E-1

0 K -4 0 ( 1677+- 30) E-3 40E-3 ( v37+- 17) E 1 27E 1 xt Th-232 ( 19524- 55) E-3 -----

( 6V24- 20) E O - - - - -

x- + U-233 ( '71 Y & - 37) E-3 -----

( 505+ 21) E O ----

i Notes:

K Activity greater than 3xstandard deviation

+ Pea k i s f' o u n d LLD is not calculated

'^ ----- ----_-____---_____-__________W& ___ _

i TABLE 10 LOCA110N: EAST WEYMOUTH l

LOCATIONt: 15 COUN~1 TIME: 6000sec COUNT DATE: 10/07/82 l InSitu COUNTING RESULTD l

l NUCLIDE ID EXPOSUilE R ATE CrlNCE N TR A l'I U N nicr o R/hr p2 coCt/K<st an NAME EXi'UUllR E &--I -SIGN A LLD CUNC + O 1. G N A LLD RATL Ce-144 (-Y4- 12) E-4 43C-4 ( -- 3 Y 4 - 04) E O 1YUE O Ce -141 ( 00- 11) E-4 3OIE 4 ( 0+- 11) E U 41h 0 I 1 31 ( - 5 l' 4 - 32) E-4 120E-4 (-71t- 43) E- 1 160E 1 Sb-125 ( 274 t-- 76) E-4 340E-4 ( 31+- 11) E O 5?E O R u --10 3 ( 34) E- 4 120E-4 ( 33) E-1 1201.-1 lla - 14 0 (-lui- 4V) IF 4 10 0 L -- 4 ( 4+- 12) C 0 42L 0 Ru 106 ( 0: -- 12) E-3 42L-3 ( li- 25) EO Y2L 0 K+ Cw -137 ( 27261 - U;? ) E-4 220E-4 ( 4Y6 &- 15) E O 'YE O Zr-Yb ( 1704- 74) E-4 260L-4 ( Y2+- 40) E-- 1 1401.41 Nb-76 (-300- 47) E-4 170E-4 ( - 1 9 4 -- 24) E -- I U7L-1 Mn -54 ( 12YF- 46) E-4 160E-4 ( SY4- 21) E- 1 731-1 Co-60 (-uo- 13) E --3 4VE-3 ( - 10 +- 17) E1 (.M - 1 La 140 ( 25-:- 10) E- 3 3 6 t>-3 ( 32+- 13) L- 1 4 61 --I xe K-40 ( 3 0 0 7 t- - d'1 ) E3 40E-3 ( 16004- 22) E 1 ;!7E 1 K+ Th-232 ( 2570&- 60) E -- 3 -----

( V 1 14 -- 21) 1. 0 - - - -

1 U-238 ( 143S+- JU) E -- 3 - ---

( 700+- 21) L U - - -

Notes:

E- Activity greater tisan 3Xstandard deviation 4 P ea l< is found LLD tr. not c a l f. u l a t ed

l . -

l TABLE 11 LOCATION: MANOMET SUB STA.

LOCATION #: 17 COUNT TIME: 6000sec COUNT DATE: 05/20/02 InSitu COUNTING RESULTS NUCLIDE ID EXi'USURE R ATE CONCENTR ATION nicr o N /hr picoCi/Kgran NAME EXi'0GURE 8 -l--GIGMA LLD CONC o-- 1-SIGMA LLD RATE Ce-144 ( 624- '/ 3 ) E-5 320E-5 ( 20+- 42) EO 150L 0 Co -141 ( 136+- 84) E-5 2'/ D E-5 ( 146t- '/ 0 ) EI 310E-1 1-131 ( 14+- 24) E-4 CSE-4 ( l '/ 4 - 33) E-1 120E-1 Sb-125 ( -10 2+ - O'/ ) E-4 320E-4 (-120- 10) E O 37E O Ru-103 ( 10+- 31) E-4 110E-4 ( 104- 2'/ ) E-1 1 10 E--I Lia - 14 0 ( -514 -- 45) E-4 170E-4 (-120- 11) E D N/E O Ru-106 ( 214- 10) E-3 36E-3 ( 45+- 22) EO 75'E O x+ Cs-137 ( 2128+- 64) E-4 43E-4 ( 3 0 7 + -- 12) E O 7.uE O Zr '/5 ( 111+- 67) E-4 240E-4 ( 504- 36) E-1 130E-1 Nb '/5 (-3O+- 40) E-4 140E-4 (-20+- 20) E-1 74E-1 Mn -54 ( 11+- 41) E-4 150E-4 ( 5+- l '/ ) E-1 67C t Co- 60 ( 00- 11) E-3 3'/ E-3 ( 1 0 + -- 14) E-1 51E-1 La-140 ( 704 - '/ 7 ) E -- 4 360E-4 ( S' + - 12) E-1 45E-1 K+ K-40 ( 2033+- 32) E -- 3 4?E-3 ( 1 13 6 + -- 18) E 1 26E 1

4 Th-232 ( 2210+- 50) E-3 - - - - - - -

( 7 tI 4 + - 20) EO - - - - -

x+ U-230 ( 12000- 3'/ ) E-3 - - - - - -

( 703+- 21) E O Notes:

Activity greater than 3xstandard deviation

+ Peak is i'ound LLD is not calculated

TABLE 12 1982 In Situ Results Comparison of Ge(Li) In Situ and Ion Chamber Results Location Positive Ge(Li) In Situ Results (uR/Hr)

(Distance in Miles Ion Chamber Site No. from Plant) U-238 Th-232 K-40 Cs-137 Other Total * (uR/Hr) 00 Warehouse (0.03 SSE) 1.38 2.14 2.71 0.156 (a) 10.7 13.8 01 Rockyhill Rd. (E) (0.8 SE) 1.35 2.25 2.21 0.163 -

9.6 9.4 03 Rockyhill Rd. (W) (0.3 WNW) 1.17 2.47 2.49 0.062 - 9.8 9.8 04 Plymoth Center (4.5 WNW) 1.57 2.41 2.38 0.276 - 10.2 9.9 06 Property Line (0.34 NW) 1.30 2.32 2.11 0.189 (a) 9.5 10.5 07 Pedestrial Bridge (0.14 N) 1.27 2.21 2.14 0.113 .989 (bc) 10.3 13.8 08 Overlook (0.03 W) 1.21 2.05 2.61 0.108 (a) 9.6 37.8 09 East Breakwater (0.35 ESE) 1.36 2.47 2.77 0.100 (c) 10.3 10.4

10 Cleft Rock (0.9 S) 0.92 1.95 1.68 0.942 -

9.1 9.4 15 East Weymoth (23 NW) 1.44 2.57 3.01 0.273 - 10.9 10.5 17 Manomet Substation (2.5 SE) 1.28 2.21 2.03 0.21 3 -

9.3 9.3 o Total Includes 3.6 uR/Hr cosmic contribution. ,

(a) Co-60 found in in situ but not confirmed by lab soil analysis and therefore not included in total.

l (b) Co-60 found in In situ and confirmed by lab soil analysis.

l (c) Zr-95 found in _T6_sig but not confirmed by lab soil analysis and therefore not included in total.

APPENDIX D - Radiological Environmental Monitoring Program l

l l

I D-1

APPENDlX D 4.8.D Environmental Monitorint ?;otras An environmental monitoring program shall be conducted as follove:

1. Invironmental samples shall be selected and analyzed according to Table 4.8.1 at the locations described in Tables 4.8.2 and 4.8.3 and shown in Tigures 4.8.1, 4.8.2 and 4.8.3.

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 consump-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 saurpling) yielding the highest calculated thyroid dose.

This census is limited to gardens having an area of 500 square feet er more and shall be conducted under the following conditions as necessary i

to meet the above requirement:

I Within a 1-uile radius of the plant site, enumeration by a door-to-a.

door, or equivalent counting technique.

b. If no milk-producing animals are located in the vicinity of the sita, as deter =ined by item 4 below, the census described in item 3a above shall be extended to a distance of 5 miles from the site.

If the census indicates the existence of a garden at a location yielding a calculated thyroid dose greater than that from the previously sa= pled garden, the new location shall replace the garden previously having the maximum calculated iodine concentration. Also, any location fros 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 anNis producing zilk for human consumption shall be conducted at or near the middle of the grazing season to deternine 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-mile radius from the plant site or within tre 15 nrem/yr isodose line, whichever is larger, enumeration by a door-to-door or equivalent, counting technique.

b. Within a 5-mile radius for cows and for goats, enumeratien derived from referenced information from county agricultural agents or other reliable sources.

If it is learned from this census that animals are present at a location which yields a calculated thyroid dose greater than from previously sa= pled animals, the new location shall be added to the surveillance progran as soon as practicable. The sampling 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 no longer be obtained may be dropped from the surveil-D-1

Y' lance program as long as the NRC is notified in writing, as soon or as milk - - -

practicable, that.ailk-producing animals are no longer present, samples are no longer available at that location.

5. Deviations are permitted from the required In the sampling schedu ability or to salfunction of automatic sampling equipment.

event of equipment selfunction, every reasenable effort shall be ande to complete correctivo action prior to the end of the next sampling period. Any si%nificant deviations from the sampling schedule shall be explained in the annual report. ~

L'

6. Detailed written procedures, including applicable check lists and instructions, shall be prepared and followed for all activities involved in carrying out the environmental monitoring program.

Proceduras shall include sampling, data recording and storage, instrument calibration, measurements and analyses, and actions to be .

taken when anomalous measurements are discovered.

3 '

Procedures shall be prepared for insuring the quality of programThese procedures vill results, including analytical w asurements.

identify the responsible organizacions, include purchased services (e.e., contractus1 Isb). include indeoendent audies. and include svste.s (such as participation in IAs.A and/or N35 intercalibratien exercises **

and submissien of " blind" cualiry control sat:cles for analvses bv the contractors)lto identify and correct deficiencies, investigate anom.alous or suspect results, and review and evaluate program results and reports.

3.5.D and 4.8.D Envirennental Menitorint Prot-as An Environmental radiological menitoring program is conducted to verify the adequacy of in-plant controls 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 forth in 10Cy150 Appendix I.

Calculational Models An exa=ple of this is the detection of I-131 in milk.

(Ragulatory Guide 1.109 March 1976) have shown that a constant cencentratier.

of 3.5 pC1 1-131 per liter milk would result in a dose of A11oving15 milliree-to for an the thyroid of an infant consuming that milk ==vd-"=

for a year.of two half-lives between open grazing season of six months, and a event and sampling, the icver limit of detection at time of sa=pling must be 2 pC1/1 (3.5 x 12/6 x 1/4 = 1.8).

A supplemental acnitoring program for sediments and mussels has been incorporated into the basic program (see notes f and g to Table 4.8.1) *hisas **

a result of an agreement with the Massachusetts Wildlife Tederation.

supplemental program is designed to provide information on radioactivity levels at substantially higher sensitivity levels in selected samples to verify the adequacy (or, alternatively, to provide a basis for laterAs part of the modifications) of the long-term marine sampling schedules.

supplemental program, analysis of mussels for isotopes of plutonium vill be ,

performed if radiocesium activity should exceed 200 pC1/Xgm in the edible _

=

, portions.

L p

- supplemental provision i l

D-2 p

l i

q 4

1 ME The 200 pC1/Kgs radiocesium " action level" is based on calculations which %

showed that if radiocesium from plant releases reached this level. ne 3 plutonium could possibly appear at levels of potential interest.*

g

-i calculations also showed that the dose delivered from these levels of q plutonium would not be a significant portion of the total dose at:ributable 1 co liquid effluents. -au .

g The program was also designed to be consistent, wherever applicable vi:5 G Regulatory Guide 4.8 (Issued for comcwne Cecember 1975). The following exceptions to the generic reccamendations stated in Regulatot7 Cuide 4.8 are justified due to site specific ecusiderations:

1. n e required deceetten capabiliry for I-131 in milk 'is i about twice the value suggested in Regulatory Guide 4.8. The justi- _

fication for the higher value is presented in :he second paragraph of this section. This is a conservative esti= ate of the capabili:7 of thg milk surveillance program to detect concentrations at the "

appropriate annual dose level since the annual dose is proportional to -

! the annual aversee concentration in milk. The detectico limit for a -A group of sa=ples is less than that for a single sa=ple and is inversely a proportional to the square rect of the nusher of samples. The conser-l vatism in this case is appr xi=ately <[iT, or about a fae:or of 3. a i

2. Air particulates are not analyzed for radicstrontin.

The program instead calls for this analysis in milk sa ples. This is ]

,a justified because the air-cev-milk exposure pathway can be be::er men- -

itored at Pilgrim af ter the very lov level releases of radiostren:1u:s --

are reconcentrated in cev's milk (Raf. 1). 1

3. Soils and sediments are not reutinely analyzed for Sr-90, but racer -

the analysis is done on a contingency basis. The rationale behind this is that St-90 vill not centribute to long-term radionuclide buildup '

until the more abundant gan=e er:zitting nuclides appear in rela:ively large contentracions. Both Items 2 and 3 reflect the fac: that in 3h J years of operation. Pilgrim Statien liquid releases of Sr-90 have ,

amounted to enly 1/1000 of the Sr-90 inventory in Cape Cod Bay water (frem weapons testing fallout) and about 4/1000,000 of the direc: de;ost- =

tien en the Bay. Also, gaseous releases of Sr-90 have been only 1/100.000 of the :errestrial St-90 inventer 7 within five miles of the statien (Ref. 1),

i

4. Surveys are conducted annually, if necessary, to deternine appropriate -

locations for sa=pling of leafy vegetables and milk. ne objective of -

these surveys is to ensure that the environmental sa=ples are represen-

' tative of realistic food chain pathways, considering local conditions. 1 Results of the monitoring program vill be used as " benchmarks" to verify calculatienal medals used to predict the consequences of effluent releases 7 from the station. The models can then be employed to predict doses M attributable to radiatilen deposition at any other location of interest. J1 The combination of monitoring results and calculations al sedel predictions is a practical method of demonstrating compliance with 10CTR$0 Appendix I.

This approach does not require (nor is it always practical) that environ-mental media always be sampled from the " worst case" locatiens: althcugh =

sensitivity of the monitoring results might be improved by sa=pling fren locations which are reasonably close to "verst case" conditions. -

4 a -

in measurable quantities having a potential dose (human food chain) N significance ec= parable to other nuclides if present at their detection limits. J

-4 D .3 _i

Verification of the appropriate milk sampling locations on an annual basis is satisfactory as there are very few locations sui:able for the grazing of dairy herds in the vicini:7 of the planc (Raf. 2). This situation makes it unlikely the location of the nearest dairy herd (3.5 miles *d) vill change.

3. Annual sampling of beef forage (in place of beef) is adequate because beef cattle are not raised conumercially in the vicinity of the site.

However, dairy cows from the Plymouth County Farm are periodically sold for beef. Trad (hay) from this location vill be sampled to monitor this potenti.41 pathway for ingestion of radioactivity. If beef ca::le feeding on local forage are found at locations closer to the si:e, forage samples from the closer location vill replace the sample fres :he -

County Tara.

6. Coundwater flow at the plant site is into Cape Cod Bay: therefore, terrestrial moni:oring of groundwater is not included in this progran.

7. Foultry sampling is not perfor:ned because poultry in Plymouth County .

feed almost excluitrely on ingorted grain and are usually raised under shelter.

8. Field gn==a isotopic surveys are conducted to moni:or radioactivi:7 in soil in lieu of laboratory analysis of soil samples. The technique l+

has several advantages over laboratory analysis. Tirst, analysis can be performed on the same pict of land frna survey to survey, and radio-activity build-up at the location can be accurately deterzined. Secondly, ga a exposure rate is deter =ined directly from this technique: hence compliance with 10Cy130 Appendix I levels can be investigated di.rectly rather than indirectly through soil sa=pling.

g .

.. h'

qK L _E [ l'

.r, ,,

%> .y,j D-4 3 v..'-f

^

I

r i

Refereness:

1. Urenn, M.E., " Review of 3r-90 Releases from Filgrim i Nuclear Plant and a Comparison vi:h Ex ant Iwironnantal Levels",1976.

2. Filgris Station Uni: #2 PSAR, Appendix 117, pp. 11TC-11 and 11A, amended June 13, 1976.

D-5

TABLE 4.8.1 GPERATIONAL RADIOLOGICAL ENVIR0l# ENTAL HDMITORING PROGRAM Locations Exposure Pathway (Direction-Distance) Saapilng and Type and Frequency or Sample Type frome Reactor Collection Frequency of Analysis AIRBORNE Particulates II (see Table 4.8.2) Continuous saapilng uer Gross beta radlonctivity at one week least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months af ter filter change. (a) Quarterly composite (by location) for gassua 1sotopic. (b) if Radiolodine 11 (see Table 4.8.2) Continuous sampilng with Analyze weekly for I-131

canister collection weekly Soll 11 (see Table 4.8.2) Once per three years Fleid gassna Isotopic. (c)

DIRECT 20 (see Table 4,R.3) Quarterly Gansna exposure quarterly.

Plymouth Beach and Priscilla/ White llorse Beach Annually (sprias) Gassna exposure survey ,

WATERBORNE Discharge Canal continuous composit sample Gassna isotopic (b) monthly; Bartlett Pond (SE-1.7 ml. Weekly grab sample and composite for 11-3 Powder Point (NNW-7.8 al.?(d) Weekly grab sample l analysis quarterly. (c).

AQUATIC - .. - - - - - . . . . . . . . . . - . . _ . . . . . . - ,

j Shellfish Discharge outfall Quarterly (at approximate. Gassna isotopic (b); also see ihmbury Day ~ ' '3-month Intervals) note (f).

Hanomet Pt.

Plynumth or Kingston llarbor liarshfield (d)

Note (f) and beach surveys are supplemental provision.

l l

_ m

TABtt 4.8 1

~(font'df Locatlons Dposure Pathway (Direction-Distance) Saapilng and Type and Frequency Collection frequency of Analysis or Sample Type from Reactor ;

Irish Moss Discharge outfall Semi-annually Gassna Isotopic (b)

Hanomet Pt.

Ellisvl11e (d)

Lobster Vicinity of discharge Four times per season Gaassa isotopic (b)on edible portions.

goint ffshore gg) Once per season Fish Vicinity of discharge Quarterly, Groups I and II (e? Ganssa isotopic (b) on point in season, Groups III and IV La) edible portions (e) offshore (d) Annually, each group - -

Rocky Point Semi-annually Gassna isotopic (b) (c),

Sodiments Plymouth liarbor see also note (g) e Duxbury Bay Plymouth Beach 7

y Manomet Pt.

Marshfleid (d)

INGESTION (Terrestrial)

Milk Plymouth County Farm Semi-monthly during periods when Gassna isotopic (b) Sr-8g, (W-3.5 mi.)(h); Whitman animals are on pasture, other- 90 ponthly; radiolodine fans (NW-21 mi.) (d) wise monthly analysis all samples.

Cranberries Manomet Pt. Bog At time of harvest Gammaisotopic(b)on (SE-2.6 mi.) edible portions.

Bartlett Rd. Bog

($5E/5-2.8 mi.)

Pine St." Bog (WHW-17 ml.) (d)

' Note (g) is supplemental provision m Am

TABLE 4 8 7CoTD.1 tocations Dposure Pathway (Direction-Distance) Saapilng and Type and Frequency er Saaple Type from Reactor Collection Frequency of Analysis l

Tuberous and Karbott Farm (55E-2.0 mi.)(h) At time of harvest Gaame isotopic (b) green leafy Bridgewater Fans on edible portions. .

vegetables (W-20 mi.) (d)

Beef Forage Plymouth County Fans Annually Gasse isotopic (b)

(W-3.5 mi.) (h)

(

v e

Utes

' (a) If grors beta radioactivity is greater than 10 times the control value.

gasma isott.,pic win be performed on the sample.

(b) Casuna isotopic means the identification and quantification of gamma-emitting radionuclides that may be attributable to the affluents from the facility.

(c) If integrated gamma activtry (less K-40) is g; mater than 10 times the control value (less I-40), strontium-90 analysis win be performed on the samp14.

(d) Isdicates' control location.

(a) Fish analyses vin be performed on a minima of 2 sub-samples, consisting of approximately 400 grams each from each of the folleving groups:

I. Botton Oriented H. Near3ettes HI. Anadromous 17. Coastal Distribution Migratory Vinter flounder Tautog Alevife Bluefish Tenowtail flounder Cunner R.alnbow smel Atlantic herring Atlantic cod Striped bass Atlantic menhaden Fonoch Atlantic mackerel Eakes (f)* Wasel sa=ples from four locatiens (i= mediate vicinity of discharge outfan, Mancmet Pr. , 717 mouth or Kingston Harbor, and Crass Harbor in Marshfield) vill be analyzed quarterly as fenoust one kilogram vet weight of mussel bodies, including fluid within shells vill be conected. Sodies will be reduced in volume by drying at abcut 1CCCC.

Sample vill be cespacted and analyzed by CI(L1) gn=ca spectr: metry or alter-iate technique, if necessary, to achieve a sens1:1vity'* of 5 pC1/kg for Cs-134 Ca-137, co-60, In-45 and 3r-95 and 15 pci/kg for Ca-144 The mussel shell sample from one location (the location nearest the discharge cans 1 unless othervise specified pursuant to licensee's agreement vich Mass,

,Vildlife Tederatien) vill be analyzed each quar.er. One additional mussel shell sampla (from the Creen Eartor location, unless othervise specified pursuant to Licensee's agreement with Mass Wildlife Tederatien) vill be analyzed semi-annually. Unscrubbed sha us to be analyzed win be dried, processed, and analyzed similarly to the mussel bodies.

Because of the emen volume reduction in pre-processing of shens sensitiv1-ties attained wi n be less than that for mussel bodies. The equipment and counting times to be employed for analyses of shaus vill be the same or comparable to that e=picyed for mussel bodies so that the reduction in sensitivities (relative to those for mussel bodies) vin be strictly limited to the effects of poorer gecastry related to lover sample volume reduction.

Shell samples not scheduled for analysis vin be reserved (unscrubbed) for possible later analysis, depending upcn recetsmandaticas of the review c= ittee.

Supplemental provision.

- AU sensitivity values to be determined in accordance with footnote (a) tlevel o Taon bleTj

4. 8. 4. , vt z. , LLD a t 95 : con!!dence level on T.,t 50% confidence (See BASL-300 for definitions).

D-9

E, y:

. ..[. , '.;

,,.v .

h*,

E [;1 ' , .

I Notes (Cont'd) ;/4: 4

.-- . - 9. . . . .;

If radiocesisse (Ca-134 and Cs-137) activity exceeds 200 pC1/kg (vet) -.? ) >

in mussel bodies, these samples will be analyzed by radiochemical b.'

spearation, electrodeposition, and alpha spectrometry for radioisotopes t . . ' j-of plutonium, with a sensitivity of C.4 pC1/kg. . ls

...33-}

l (g)* Sediment samples from four locations (hnomet Ft., Rocky Pt., Flymouth l

Harbor, and head of Duxbury Bay) vi n be analyzed ones per year s.}.3 J; @n (preferably early summer) as fonovs:

l ,f,3,.ygi Cores win be taken to depths of 30-cm, 31M= depth wherever sediment . * : ? 3 .* ~

conditiens permit by a hand-coring sampling device. If sediment conditicus C %)h.

do not permit 30-cm deep cores, the deepest cores achievable with a :..

hand-coring device vin be takan. In any case, core depths viu not be 4-, 'N, N 1%

less than.14-cm. Core samples vill be sectiened into 2-en increments, w'X' and surface and alternate increments analyzed, others reserved. Sediment 4 sample volumes (determined by core diameter and/or nu=ber of individual . .;, '.,/l3 cores taken from any singla locaticu) and counting technique vin be :49d sufficient to achieve sensitivities of 50 pci/kg dry sediment for Ca-134, ~f 5 Cs-137, co-60, In-65, and Ir-95 and 150 pCi/kg for C4-141,. In any case + . dM ,

individual core diameters vill not be less than 2 inchas. ; T . ,.sjyt.Q t

':he top 2-en section from each core vin be analyzed for Fu isotopes ),"' p 2,)l' s.

!(Fu-235, Fu-239, 240) using radioche=1 cal separations, electrodepositics, -)

and a2pha spectronstry with target sensitivity of 25 pC1/kg dry sediment. } 4j po additienal core slices per year (mid-depth slice from core samples -, tg - .q' ltaken at Rocky Point and Flymouth Harbor, unless othetvise specified h 2 .c -' ,';

l purruant to licensee's agreement with has '411d11fa Tederation) vin be qsimilarly analyzed. ;

(h) These locatiens may be altered in accordance with results of surveys ', I j.<

discussed is paragraphs 4.8.D-3 and 4.8.D-4. [ p.;-

j n y l

.)f, QL, c ,

il sy' l ]

\,y

-,a

+['.,g Miv ., p p

% f

., N '. 4 4 41 4 . t ,

. i, f. f 7

Supplemental provision f,.

x. , ...

hr p D-10 .i :'

,g 4_

... v

_ .A

i TABLE 4.8.2 I

AIR PAR *IC*!LATIS, CASICUS RADiCICDIST. AND MT1, %7m'I.I.ANCT. K*A"!ONS l

$stralint Location Distance and (Sample Desitnation) Direction from Reactor offsite Stations East Weymouth (DT)

23 miles NW Plymouth Cantar (?C) 4.5 miles W *W Hancest Substation (MS) 2.5 miles SE Claft Rock Arma (C2) 0.9 miles S Onsite Stations Rocky Hill had (ER) 0.8 miles SE Rocky Hill Road (V1) 0.3 miles M'NW Overlook Area (CA) 0.03 miles W Property 1.ine (FL) ,

0.34 miles NW Pada.strian Bridge (F3) 0.14 miles N East Breakvatar (I3) 0.15 miles ESI Warehouse (WS) 0.03 miles SSI

Contro; Station D-11 l

l

TA5LE 4.8.3 EX !RNAL CAW.A IX?CSURI SURVIILLANCI STATIONS (TLD)

Distance and Desimeter Loestien (Designatietd tirection f rom Station Offsite Stations East Veymouth (IV)* 23 miles Nil

Kingston (KS) 10 miles VNV l Sagamore (cs) 10 miles 53E-5 i

! Flymouth Airport (SA) 8 miles VSV North Flymouth (NF) 5.5 miles kW Flymouth Cancer (FC) 4.5 milais V-kW South Flymouth (SF) 3 miles V5V Manomet (MS) 2.5 miles SSE Manomat (ME) 2.5 miles SE Manomat (MP) 2.25 miles ESE-5 Clef t Rock Area (CR)

~

0.9 miles 5

[Sa,gy5hNec ($N ) ** 4.6 sties ~NNV I***

Onsite 5'tations Rocky Hill Road (ER) 0.8 miles SE Microwave Tower (MT) 0.38 miles 5 Rocky Bill Road (V1) 0.3 miles V-4W Rocky Hill Road (3) 0.26 miles SSE Property Line (H) 0.21 miles SSV Property Line (I) 0.14 miles W Public Parking Area (PA) 0.07 miles N-NNE Overlock Area (CA) 0.03 miles W

, ,* _ control , Station

" Data from this surveillance station is subject to detector maintenance and retrieval by a privats party not subject to control by the licensee. Ther ef o re ,

the requirement to maintain this station is contingent on station availability and maintenance by the outside parry.

- - Supplemental prtwision * ' ' '

D-12

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Rocky Point womn b on C eb u m smistore U po nu I

LEGEND C tRISH MCSS Ettisville

! O SOFTSHELL CLAMS Harcar e MUSSELS A SEDIMENT l 5 QUAHOGS Tigure 4.8-1 Typical Ho11use, Alase and Sediment familinc !:stions l

D-14 I

M

.6 N M 6.9.C tnioue Reeorting Reeuirements e.e 2 M

M

2. Envirec= ental Proeram Data _==

"5

4. Annua.1 Report. A report on the radiological environmencal --

surveillanca program for the previous 12 months of operatten -

i shall be submitted to the Director of the NRC Retto ul Office (with a copy to the Director, Office of Nuclear Asse:or -

Regulation) as a separate doc.unent within 90 days after January 1 of each year. De reports shall include suranaries, interpre:- %

ations, and statistical evaluation of the results of the radio- --

logical environmental surveillance activi:1es for the report, y period, including a con:parison with preoperational studies, q operational controls (as appropriate), and previous environ = ental r surveillance reports, and an assessment of the observed impac:s _-

of the plant. operation on 'the environment. ne reports shall also include the results of any land use surveys which affec: ."

the choice of sa=ple locations. If harmful effects or evidence of irreversible da= age are detected by the monitoring, the j licenses shall provide an analysis of the problem and a proposed g course of actica to alleviate the problem. ys Results of a.11 radiolegical envirenzental samples shall be y sunmaarized and tabulated on an acm.a1 basis. In the event that g some results are not available within the 90-day period, the _

report shall be submitted, noting sad explaining the reasons _

for the missing results. ne alasi.ng data shall be submit:ed as soon sa possible in a supplementary report.

b. Anomalous measurement report. If radioactivity in an indicator medium from an off-si:e location is found and confirned at a -

level exceeding ten times the control station value. a written report shall be submi:ted to the Director of the NRC Regional Office (with a copy to the Director, Office of Huclear Reactor ==

Regulation) within 10 days af ter confirmation.** nia repor:

shall include an evaluation of any release candi:1ons, environmental .

factors, or other aspects necessary to explain the ancme.'.ous resul:. j 7 .

i 4

3 9

J:l

- A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate. n e results of the con- "

firmator7 analysis shall be completed at the earliest time consistent with the analysis, but in any case within 30 days of receipt of the =

ananalous result. -

B q

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1 PacPtMTV LINE (D1 e 12 m0CxY weLL ACAC tel 2 PnC*tRTY UNE (70 # 14 WICmCWAvt TOwim rMT) 2 PSCPERTY UNE 111 11 (MimSCN *C AC ttWI

4 PaCPtRTY UNE (C) 8 16 WMITI MCm31 ac AC NrMP 5 aCCKY HILL PCAD LAI e 17 peCPtmyY LiNE sta 4 PMCPERTY UNE (H) 18 aCCKY Ml(L RCAC fWR1 7 *uSLIC P A AtlNC AREA pal 19 PSO*tMTV LINE 1Ji*

8 PtCt3Tm:AN sRIDCE Pet 20 P*Cetm TY LINE tE m 9 CytmLCCE Amt.A ICAI 21 mCCMY MILL acAo ital to IAST IntAEWATER ttsi 2: **CPtMTV LINE IL7 11 '#CPtmTY UNE fC

22 WA8thCUSE(W51 12 PSCPtRTY UNE IHet a 24 pac'IRTY UNE (PV O CCSsWLTimfTtDI A Aim P AMTICULAf ts ANC CCSiutTERS ffLDI

additional station not required by Specification 4.8.D.1 Tigure 4.8.2 Location of Cnsite MCnitDring Stations D-16

/

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$ SCUfM PtvuCUTM (SPt IJ SACanaCRI Ital 8 Sav$mCat caryg(8078 to PLvuCVfw aimpost 34 7 CL38T aCCE AAtA (CRI 19 BAK? wtYucutm inwi s wanowet wi 16, 54quish Nacir. (EN)

additional sta:1cns =ct required by Spec 181utien 4.8.D.1 Tigure 4.8.3:,ccatien of Cffsite Menitering statiens D-17

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knendnent No. 57 0-18

APPENDIX E - 1984 Garden & Milk-Producing Animal Survey 4

i E-1

suo rw m. OFFICE MEMORANDUM g Rua control No.

Dept Doc. No. -

To Mr. A. V. Morisi From Ms. C. E. Bo n ^ EiiiiS #85-30

} Record Typo Date March 29. 1985 A4.08

O Safety-RMated O Non SafeyRelated

Subject:

1984 GARDEN & MILK-PRODUCING ANIMAL CENSUS

)

As required by PNPS Environmental Technical Specifications, the 1984 Garden and Milk-Producing Census was conducted in September 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 con-firmed. The garden near the site boundary of 0.7 miles W no longer exists; however, a garden 1.0 miles W of the site boundary was identified. 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, vegetation samples were collected from four locations on 9/26/84. Only one location was greater than one mile from PNPS. A sample of cabbage was collected from the J. Work Residence (0.6 miles ESE) on John Alden Road; rhubbarb was obtained from the Malmgren Residence (1.0 miles W) on Rocky Hill Road, and from the Jenkins Residence (1.0 miles SE) on Rocky Hill Road; and, a sample of beet leaves was collected 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 indicating that the only milk-producing animals within five miles of PNPS are located at the Plymouth County Farm. 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 S). This animal is still located on Beaver Dam Road. The owner did not participate in the 1984 Environmental Monitoring Program, but has indicated a renewed interest for participating in the 1985 Environmental Monitoring Program.

In conclusion, the 1984 Census indicates that there are no additional indica-tor stations available for milk sampling.

1sd attachment Distribution: -

m

TOWN OF PLYMOUTH OFFICE OF

'37 BOARD OF HEALTH v

March 114 , 1985 Boston Edison Company 800 Boylston Street Bost m, MA 02199 Attention: Brian P. Lunn .

Dear Mr. Lunn:

Please be advised that the only milk produci that I am aware of within the five mile redius of)1g animals

,the Pilgrim Huclear Powe- Plant are those housed at the Plymouth County farm. As you may know, this is located at the Plymouth County Houae of Correction, Obery Street, Plymouth.

If you have any further questions regarding t31s matter please contact me.

Sincerely, 9

m s w o D OJs w /x b Milton D. Wood Plymouth Animal Inspector

}

f, s

i i,

11 LINCOLN STREET PLYMOUTH, M ASSACHUSETTS 02360 Tel. 7471620 Ext. 33

ECSTON EDISON QOMPANY 800 BOYLSTON STREET BOSTON. M ASEACHUBETTS O219 9 WILLIAM D. HARRINCBTON ctmean wees pasonesss?

NIOLSAR April 1, 1985 BEco 85-65 Dr. Thomas E. Murley_

Regional Administrator Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 License DPR-35 Docket 50-293 Environmental Radiological Monitoring Report No.17 January 1 - December 31, 1984

Dear Sir:

In accordance with the Pilgrim Nuclear Power Station Technical Specification 6.9.C.2, Boston Edison Company hereby submits Environmental Radiological Monitoring Report No. 17. This report applies to the period from January 1, 1984 through December 31, 1984.

Very truly yours, d4 MTL/ns Attachments: (2 copies) cc: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 (18 copies) 1\\

aJ

ML20113E180

Contents

Text

* h6 W w .2 5 0% O O O O O O e == w N e N em um e e .u. .g U es m n *e 4 h A. ed =o 3

e he w

Subject:

Dear Mr. Lunn:

Dear Sir:

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ML20113E180

Text

* h6 W w .2 5 0% O O O O O O e == w N e N em um e e .u. .g U es m n *e 4 h A. ed =o 3

e he w

Subject:

Dear Mr. Lunn:

Dear Sir:

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