Text

Environ Radiation Monitoring Program,Rept 13 for 1980
	ML20003F730
Person / Time
Site:	Pilgrim
Issue date:	04/01/1981
From:	Sowdon T; BOSTON EDISON CO.
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I I*

I PILGRIM NUCLEAR POWER STATION I

I Environmental Radiation Monitoring Program REPORT NO.13 g

I I

I JANUARY 1 THROUGH DECEMBER 31,1980 I

I ISSUED: APRIL 1981 ENVI O MENT L A D RAD 0 CL HEALTH AND SAFETY GROUP I

I BOSTON EDISON COMPANY I

I 6VU vov259

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BOSTON EDIS0N COMPANY PILGRIM NUCLEAR POWER STATION Environmental Radiation Monitoring Program REPORT NO. 13 January 1, 1980 through December 31, 1980 I

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Prepared by:

Tliomas L. Sowdon Environmental and Radiological Health and Safety Group Leader I

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TABLE OF CONTENTS Section Page I

Introduction and Summary 1-1 I

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

Air Particulate 3-5 B.

Iodine 3-12 C.

Soil 3-16 D.

Direct Radiation 3-17 E.

Waterborne 3-31 F.

Shellfish 3-35 G.

Algae (Irish Moss) 3-39 H.

Lobster (Arthropods) 3-43 I.

Fish 3-47 J.

Sediments 3-51 K.

Milk 3-56 I

L.

Cranberries 3-63 M.

Vegetation 3-67 N.

Forage 3-71 I

IV References 4-1 Appendix A Anomalous Measurements A-1 Appendix B Radioactive Effluents B-1 Appendix C Soil Survey C-1 Appendix D Radiological Environmental Monitoring Program D-1 Appendix E 1980 Garden and Milk Animal Survey E-1 I

I I

LIST OF TABLES Table Number Page I

I-1 PNPS-1 Capacity Factors 1-2 III-A-1 Sample Station Identification Codes 3-3 I

III-A-2 ERMAP Results - Air Particulate Filters 3-7 III-B-1 ERMAP Results - Charcoal Cartridges 3-13 III-D-1 Thermoluminescent Dosimeter Locations 3-20 III-D-2 Results of TLD Measurements - January 3-23 III-D-3 Results of TLD Measurements - February 3-24 III-D-4 Results of TLD Measurements - March 3-25 III-D-5 Results of TLD Measurements - Quarter 2 3-26 I'

III-D-6 Results of TLD Measurements - Quarter 3 3-27 III-D-7 Results of TLD Measurements - Quarter 4 3-28 I

III-D-8 Quarterly Average Exposure Rates 3-29 III-D-9 Field Survey Exposure Rates 3-30 III-E-1 ERMAP Results - Waterborne 3-32 III-F-1 ERMAP Results - Shellfish 3-36 III-G-1 ERMAP Results - Algae 3-40 III-H-1 ERMAP Results - Lobster 3-44 III-I-1 ERMAP Results - Fish 3-48 I

III-J-1 ERMAP Results - Sediments 3-52 III-J-2 Results of Sediment Analysis for Plutonium 3-55 III-K-1 ERMAP Results - Milk 3-58 III-L-1 ERMAP Results - Cranberries 3-64 III-M-1 ERMAP Results - Vegetation 3-68 l

III-N-1 ERMAP Results - Forage 3-72 1

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LIST OF FIGURES Figure Number M

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

Indicator Stations 3-10 I

III-A-2 Gross Beta Activity - Air Particulates -

Contro'. Station 3-11 III-B-1 Concentration of I-131 - Charcoal Filter -

Indicator Stations 3-14 III-B-2 Concentration of I-131 - Charcoal Filter -

Contre.1 Station 3-15 III-D-1 Location of Offsite Monitoring Stations 3-21 III-D-2 Location of Onsite Monitoring Stations 3-22 III-K-1 Concentrations of Cs-137 in Milk -

All Stations 3-61 I

III-K-2 Concentrations of Sr-90 in Milk -

All Stations 3-62 E

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I.

Introduction and Summary This report presents a summary of the results of measurements of direct radiation and radioactivity in environmental media in the vicinity of the Pilgrim Nuclear Power Station - Unit 1 (PNPS-1) and at selected control locations for the period January 1 - December 31, 1980.

The results of I

this Program indicate that PNPS-1 has had a negligible and most often immeasurably small impact on the environment in the vicinity of the plant.

Conservatively estimated doses resulting from the measured highest station mean concentrations are typically less than 1% of the doses resulting from naturally occurring radionuclides and residual fallout from atmospheric nuclear weapons testing.

I Estimates of concentrations of radionuclides in vegetation and milk and estimates of dose to man, as quoted in this report, were made using methods similar to those described in Regulatory Guide 1.109 and 1.111.

The performance record of the PNPS-1 for the calendar year of 1980 reflects an average capacity factor of 52.7%. Monthly capacity factors are given in

- I Table I-1.

A tabulation of radioactive effluents from the PNPS-1 is provided in Ap-per Jix B for the 1980 calendar year.

There were seven Anomalous Measurement Reports made during 1980. The media involved were mussels and algae from the discharge canal and on two occa-sions, milk from the Plimoth Plantation.

It should be strongly emphasized that the measured concentrations in milk I

were characteristic of fallout nuclides.

These measured anomalous concen-trations were 10,000 to 1,000,000 times in excess of the concentrations expected to be present in milk as a result of effluents from PNPS-1.

In other words, PNPS-1 probably contributed much less than 1% of the measured concentrations of Sr-90 and Cs-137 in ailk at the Plimoth Plantation. The remainder of the measured radioactivity is unquestionably due to atmos-pheric fallout from weapons tests, not PNPS-1.

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The measured concentrations of Co-60, Cr-51 and Mn-54 in the discharge canal samples are unquestionably. due to liquid effluents from PNPS-1.

However, the maximum dose due to consumption of either algae or mussels with the peak concentrations would result in less than 0.01 mrem to the total body and 0.05 mrem to any organ.

Clearly, this dose is not signi-ficant when compared to the natural background dose rate of 80 to 100 I

mrem / year as it is much less than 1% of background.

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

The only exceptions were occasional failures of the air samplers and/or site inaccessability and occasional unavail-ability of milk samples from the Plimoth Plantation.

Such incidents af-fected only about 5% of the total number of samples scheduled Jor col-I lection.

The only other deviation from the technical specification was that on one occasion a measurement of Sr-90 in a sample of milk taken from the Plimoth Plantation on 1/28/80 was high enough to warrent an Anomalous Measurement Report which was not submitted due to an administrative error.

This mea-surement of Sr-90 was 1,000,000 times in excess of the concentration ex-I pected to be present as a result of effluents from PNPS-1.

In other words, there is no question that this measurement was the result of a source other than PNPS-1.

This source was undoubtly, atmospheric fallout due to atmos-pheric weapons tests.

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All other required Anosialous Measurement Reports were made in a timely manner.

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l TABLE I-1 PNPS-1 CAPACITY FACTORS 1980 (Based on 670 MWe)

Month Percent Capacity January '

12.08 February 0

March 0

April 0

May 21.32

-June 85.05 July 89.73 August 80.54 i

September 95.57 October 76.64 November 70.02 December 101.88 I

^--

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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 essen-tially identical to that conducted during the latter half of 1977 and incorporates supplemental provisions as specified in the Settlement Agree-I ment between the Massachusetts Wildlife Federation and Boston Edison Com-2 pany, June 9, 197. The exceptions to the program are as follows:

I 1)

There is no TLD station at Saquish neck since the Mass Wildlife Fed-eration has not yet provided a means for placement and retrival of the TLD as prescribed by the agreement noted above.

I 2)

There is no longer a milk producing cow at the Plymouth County Farm.

The location of the nearest cow is now at the Plimoth Plantation (2.2 miles W).

Samples have been collected from this new location since 1979.

I 3)

There is no longer a Karbott Farm.

Vegetable samples are now col-lected at the two nearest gardens near the WNW and SE site boundaries.

The 1980 site Census conducted according to Technical Specification re-I quirements 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, i.he nearest garden is at the Shakalis residence (0.6 miles ESE). A sample of squash sprouts was collected from a nearby garden on 9/10/80 (the actual garden was at the resident of Mr. J. B. Work due to the unavailabi-lity of appropriate samples from the Shakalis residence).

In the west direction the location of the nearest observed garden of approximately 500 I

square feet was at the residence of Mary Lloyd Evans (0.7 miles W).

A sample of Chinese Cabbage was collected from this location on 9/11/80. The location of the nearest animal which produces milk for human consumption is i

still at the Plimoth Plantation (2.2 miles W).

Samples of ailk have been collected from this location since May of 1979.

I 2-1 I

)

During the 1980 year milk was not always available in sufficient quantity from the Plimoth Plantation to allow sample analyses.

However, every reasonable effort was made to collect samples on the frequency specified in the technical specifications.

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

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

I The results of analyses conducted on environmental media are maintained in a computerized data file which constitutes a data base used for statistical 3

analyses by a computer code entitled ERMAP.

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

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; I

2) the square root of the mean square deviation (this is an estimate of the sample variance);

I 3) the lowest and highest calculated concentrations; 4) the number of positive measurements divied by the total number of measurements; Entries listed under the heading LLD* are the mean of all LLD values, where I

each LLD equals 4.67 times the standard error of the associated background measurement.

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Lower Limit of Detection I

3-1

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

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

Sample station identification numbers used by the ERMAP program are provided I

in Table III-A-1.

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TABLE III-A-1 Sample Station Identification Codes Station Code Media Number Station Location I

Air Particulate 00 Warehouse (0.03 mi-SSE) and 01 Rocky Hill Road (0.8 mi-SE)

Iodine Filters 03 Rocky Hill Road (0.3 mi-WNW)

I 06 Property Line (0.34 mi-NW) 07 Pedestrian Bridge (0.14 mi-N) 08 Overlook Area (0.03 mi-W) 09 East Breakwater (J.35 mi-ESE) 10 Cleft Rock (0.9 mi-S) 15 Plymouth Center (4.5 mi-W-WNW) 17 Manomet Substation (2.5 mi-SSE) 21 East Weymouth (control - 23 mi-NW)

Waterborne 11 Discharge Canal 17 Bartlett Pond (1.7 mi-SE)

I 25 Power Point (control 7.8 mi-NNW)

Shellfish 11 Discharge Canal Outfall I

12 Plymouth Harbor 13 Duxbury Bay 15 Manomet Point 24 Marshfield (Control)

I h.gn iS Moss) 11 Discharge Canal Outfall 15 Manomet Point 22 Ellisville (Control)

Lobster (Arthropods) 11 Vicinity of Discharge Canal Offshore 15/99 Offshore (Control)

I 25 Scituate (Control)

Fish 2

Round Hill Point - Offshore - (Control)

I 11 Vicinity of Discharge Canal l

21 Auto Trawl Station - Offshore - (Control) l 22 Offshore - (Control) 99 Priest Cove - Offshore - (Control)

Se.iment 11 Rocky Point 12 Plycouth Harbor

'I 13 Duxoury Bay 14 Plymouth Beach 15 Manomet Point 24 Marshfield (Control) ll l

3-3 I

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I TABLE III-A-1 (Continued)

Station Code I

Media Number Station Location l

Milk 11 Plymouth County Farm (3.5 mi-W) 15 Plimoth Plantation (2.2 mi-W) 21 Whitman Farm (control-21 mi-NW) 22 King Residence (control-12 mi-W)

Cranberries 13 Manomet Point Bog (2.5 mi-SE) 14 Bartlett Road Bog (2.8 mi-SSE/S) 23 Pine Street Bog (Control-17 mi-WNW) l Vegetation 11 Plymouth County Farm (3.5 mi-W)

I 15 Greenwood Garden (0.5 mi-SE)

( 3 16 Work Residence (0.7 mi-ESE) g 17 Evans Garden (0.7 mi-W) 22 Bridgewater Farm (Control-20 mi-W)

I Beef Forage 11 Plymouth County Farm (3.5 mi-W) 15 Plimoth Plantation (2.2 mi-W) 21 Whitman Farm (Control-21 mi-NW) 22 Bridgewater Farm (Control-20 mi-W)

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III. A.

Air Particulate Filters I

Sample collection systems consisting of a cellulose disc particulate filter and a charcoal filter cartridge are used to collect particulate matter and iodine isotopes respectively.

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

In addition, quar-terly composite particulate samples are analysed for gamma emitting isotopes.

Table III-A-2 presents the results of the ERMAP for air particulate analyses.

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

I For ease of interpretation of these measurements, a plot of gross beta activity vs. time for all indicator stations is provided in Figure I

III-A-1 and for the control station in Figure III-A-2.

Positive measurements of specific isotopes characteristic of reactor operation (i.e., Co-60, Zr-95, Nb-95, Ru-103, Cs-137 and Ce-141) were 0.3 mi - SSE) and on Rocky observed at the Warehouse (Station 00 Hill Road (Station 03 - 0.3 mi - WW and Station 01 - 0.8 mi - SE).

All of the positive measurements on Rocky Hill Road were seen in I

composite samples for the fourth quarter. As can be seen from Figures III-A-1 and III-A-2 there were peaks in the gross beta activity during the fourth quarter (early October) at the control station in East Weymouth (Station 21 - 23 mi - NW) and at Cleft Rock (Station 10 - 0.9 mi - S).

The presence of an elevated gross beta activity at the control station is indication of a contribution of radioactivity from fallout which could also have influenced the measurements made on l

Rocky Hill Road during that same period.

l The positive measurements of Co-60 and Cs-137 made at the Warehouse are certainly due to effluents from PNPS-1. However, even if a person were to breathe air with the highest concentrations measured at the l

station with one or more positive measurements, they would receive an antiual dose of less than 0.0003 mrem to the total body and 0.02 mrem to the maximum exposed organ (teen - lung).

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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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III. C.
Soil Soil surveys at eleven locations are required once every three years in compliance with the revised Technical Specifications which went into effect on April 19, 1977.
These in-situ surveys were conducted during July of 1979.
The results of these surveys are included in Appendix C of this report for reference information only. They do not constitute measurements made during the 1980 calendar year.
I I
I
. I l
' I l
l 3-16
i I
I III. D.
Direct Radiation 1.
Continuous Thermoluminescent Dosimetry I
Thermoluminescent dosimeters (TLD) of the CaSO (Dy) type are used 4
to record direct gamma radiation from all sources including I
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 and on Figures-III-D-1 and III-D-2.
I Tables III-D-2 through III-D-8 show monthly and quarterly average doses from direct gamma radiation in uR/hr at these stations.
Prior to 1980, TLD's were read out monthly although the Technical Specification indicated that a quarterly read out. frequency was adequate.
In an effort to improve the statistics associated with tne measurement of extremely low radiation levels around PNPS-1, the frequency of read out was decreased to quarterly at the end l
of the first quarter of 1980.
l As a result, data is available for January, February and March on g
E a monthly basis and for the rest of the year on a quarterly basis.
l In addition to average doses for each TLD for each read out per-iod, 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 -
l
" neighborhood", and far away (background). Each set of data show consistent trends; the near plant dosimeters (OA, PB, PA, WS) l stand out among all readings and have an average above the dose rates further away.
The next region has a lower average dose 1
l rate, and beyond 0.7 mile (distant neighborhood and background) l l
the dose rates are statistically consistent.
3-17 I
I 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 0.2'.,-0.7 mile region), dose rates show no significant plant effect; pcpulated areas are therefore beyond the limits of elevated dose rates.
2.
Field Survey A gamma exposure survey of Plymouth Beach and Priscilla/ White Horse Beach was conducted during May of 1980.
The results of this most recent. survey are in agreement with the last three I
beach surveys conducted for 1979, 1978 and 1977.
In addition, a comprehensive soil survey of 11 locations was conducted during the spring of 1979. This study included both gamma exposure rate I
measurements and in-situ gamma spectrometry analysis for each location.
Laboratory soil analyses were also conducted for selected locations.
The results of this study are presented in Appendix C.
The latest gamma exposure survey was conducted using high pressure ion chamber (HPIC) Model MDL260, Serial Number a
007.
The design and calibration of this instrument were de-5 scribed in the report of the survey of June 1976,
The present survey was designed to detect differences in the external exposure rate encountered at beaches near the ;.lant (Plymouth and Priscilla/ White Horse) and a control location (Duxbury).
The detector's calibration was checked before each measurement.
The data (Table III-D-9) indicate that the exposure rates at Plymouth Inner Beach and Priscilla/ White Horse Beach are not significantly greater than the exposure rates measured at the control station in Duxbury. The small differences are likely due to the presence of granite beach stones which are essentially absent at the Duxbury location.
I 3-18 1
I I
It has been demonstrated that proximity to beach stones results in higher exposure rates than in sandy areas (see Annual Report No. 10).
I This survey indicates that the natural background exposure rate at beaches near Pilgrim Station is probably 7-9 uR/hr.
These I
results are in complete agreement with similar measurements 6
performed in Maine, where the natural background exposure rate at shoreliae locations was found to vary between 6.6 and 14.5 uR/hr.
These exposure rates were also found to vary directly 6
with the size and proximity of granite outcroppings,
These latest measurements are also in agreement with the soil I
survey mentioned earlier.
The results of that survey indicate that off-site dose rates have a range of 8.0 to 8.5 uR/hr with an average of 8.2 uR/hr.
I I
I I
I I
I I
3-19 I
O E
Susveillance Stationan Station Specification Near Plant EaClusion Area 826 s t an t Ne t shtaks hood backg r ound Statton Sua item ttsastance (0-0.16 miles)
(0.25-0.7)
(0.96-6.5 miles)
(e-23 miles)
Code Fig.
No.
(miles)
Direct &on Overlook Area OA II-2 9
0.09 W-WSW
,_g
Werehouse WS II-2 23 0.10 5-SSE I-
Pedantrian IT) bridge PB II-2 0
0.15 HNW PD
'E Public Pasksng Area PA Il-2 7
0.86 NW-NNW C3 FC
Property Line A
II-2 5
0.25 W-WSW
~S
Property Line l'
II-2 2
0.21 WNW-NW
East Breakw.ter EB II-2 10 0.31 ESE
]
Property Line B
II-2 13 0.32 SSE gg p
Property Line H
Il-2 6
0.33 SW m
in (SW) gg Psopesty Line Il-2 3
0.33 W WNW (n
m
Progwaty Line PL 11-2 24 0.34 WNW-NW 2
e--
Property Line D
18-2 1
0.37 NW-NNW
--(
e -e
Property Line L
II-2 22 0.40 ESE-SE 8
Property Lina HB II-2 12 9.43 SE O
C:1 hs
Psoporty Line C
II-2 0.44 ESE-SE O
I M
H j,
'Psogerty Line G
Il-2 4
0.44 W
(West)
}
stocky ullt no44 Wu Il-2 le 0.51 WNW gg (West) g Nicsowave tower HT Il-2 le 0.55 S-SSW rn Cleft Hock Area CR II-!
1 0.63 S-SSW
,o Hocky H6!! Hoad ER II-2 21 0.6 al SE (East) r
hay Shore Drive BD II-l 6
0.70 W-WNW O
O
Emerson Road EM II-2 15 0.97 SSE
Proposty Line J
II-2 19 1.21 S-SSE
"'I
Psoporty Line (Sout hl E
Il-2 17 1.23 8
h
White Nosse Road WH 11-2 16 1.31 SSE
Property Line at Il-2 20 1.32 S-SSE g
Hanomet Point MP II-l 8
2.25 E-ESE Nanomiet Elem. School MP.
II-I 9
2.50 SE Manomat substation MS II-l 10 2.50 SSE South Plymouth SP II-!
5 3.00 WSW
Mahomet Beach MS Il-1 11 3.50 SE-SSE Plymouth Center PC 35-8 4
4.50 W-WNW Notth Plymoulit MP II-1 3
5.50 WNW
Standish Shores SS 15-1 1
6.25 NW (puul
College rond CP Il-1.
12 6.50 SW Shesmasa Airport (Fly)
SA II-I 14 S.00 WSW cedarville Sub. (Sag)
CS II-I
!)
10.00 S-SSE atingston Substation KS II-!
2 10.00 WNW 6:ast Weymouth LW II-!
15 23.00 MW
Nut scegut s eil t,y opuratin9 license.
4-pastence= mudmured trom Unit I smactur building.
TABLE III-D-2 GAMMA EXPOSURE (TLD) DATA FOR JANUARY 1980 TLD MICROR/
NO.
STATION HOUR
+-
2 SIGMA 50 CP 6.44
+-
1.89 51 CR 4.30
+-
0.87 I
52 CS 5.35
+-
1.32 53 ER 5.33
+-
1.11 55 EW 6.04
+-
1.41 I
3003 KS 5.00
+-
0.91 57 MB 6.06
+-
1.61 3013 ME 5.32
+-
1.16 59 MP 4.23
+-
0.89 I
60 MS 8.32
+-
1.40 61 NP 5.69
+-
1.25 62 PC 6.14
+-
1.40 I
63 SA 3.77
+-
0.56 3010 SP 6.38
+-
1.01 65 SS 6.88
+-
1.75 66 WR 7.79
+-
1.98 67 BD 9.88
+-
1.79 68 EB 8.29
+-
1.81 69 EM 4.42
+-
1.01 70 MT 3.75
+-
0.69 71 OA 6.84
+-
2.71 72 PA 4.96
+-
1.39 73 PB 9.56
+-
1.70 74 WH 6.58
+-
1.75 75 A
6.49
+-
1.53 76 B
8.13
+-
1.59 I
77 C
6.12
+-
2.16 78 D
8.52
+-
1.12 79 E
4.75
+-
1.02 l
80 F
4.41
+-
1.07 3005 G
8.31
+-
1.94 82 H
5.52
+-
1.91 83 I
5.50
+-
1.80 84 J
8.46
+-
2.07 85 K
8.75
+-
1.89 86 L
8.88
+-
1.86 87 PL 3.99
+-
1.06 88 WS 6.92
+-
2.49 92 HP 5.98
+-
1.66 3046 RL 3.32
+-
0.51 37 RL 3.24
+-
0.51 l
Geographic Regional Averages this period are:
Near Plant (0.16 mi) 7.07
+-
1.43 Exclusion Area (.25.68 mi) 6.36
+-
0.45 Distant Neighborhood (.7-6.5 mi) 6.52
+-
0.40 Background (8-23 mi) 5.04
+-
0.74 3-23 I
I TABLE III-D-3 GAMMA EXPOSURE (TLD) DATA FOR FEBURARY 1980 TLD MICR0R/
NO.
STATION HOUR
+-
2 SIGMA 1
CP 37.01
+7 24.79 31 CR 23.06
+-
4.96 I
32 CS 31.22
+-
8.41 33 ER 13.44
+-
2.48 34 EW 16.56
+-
3.98 35 KS 21.24
+-
6.16 36 MB 27.05
+-
6.01 38 ME 16.54
+-
3.15 39 MP 16.42
+-
3.57 I
40 MS 10.73
+-
4.17 41 NP 13.81
+-
2.97 42 PC 10.30
+-
2.52 43 SA 16.85
+-
4.35 45 SP 19.60
+-
4.34 46 SS 15.89
+-
3.44 47 WR 18.30
+-
7.14 I
48 BD 17.24
+-
3.68 3
EB 33.12
+-
7.60 90 EM 22.56
+-
6.72 I
91 MT 15.86
+-
4.73 94 OA 12.74
+-
2.66 95 PA 12.60
+-
2.44 96 PB 27.84
+-
6.04 I
97 WH 15.15
+-
3.04 98 A
85.42
+-
42.99 99 B
20.33
+-
6.84 I
3033 C
15.27
+-
3.44 3001 D
5.09
+-
2.43 3042 E
12.78
+-
4.89 3043 F
0.00
+-
0.00 3044 G
13.11
+-
3.18 3045 H
9.60
+-
3.35 20 I
11.82
+-
3.85 I
3048 J
8.64
+-
2.15 23 K
11.97
+-
2.45 1008 L
8.46
+-
2.54 I
1009 PL 15.01
+-
5.05 1011 WS 13.67
+-
3.17 2011 HB 19.63
+-
5.67 37 RL 7.57
+-
0.95 3046 RL 10.02
+-
3.12 I
Geographic Regional Averages this period are:
Near Plant (0.16 mi) 16.71
+-
2.57 Exclusion Area (.25.68 mi) 20.50
+-
3.33 Distant Neighborhood (.7-6.5 mi) 17.05
+-
2.07 I
Background (8-23 mi) 21.47
+-
3.99 3-24
W
-- ~ ~ '
I I
I TABLE III-D-4 GAMMA EXPOSURE (TLD) DATA FOR MARCH 1980 TLD MICR0R/
I NO.
STATION HOUR
+-
2 SIGMA 50 CP 14.55
+-
2.86 I
51 CR 20.09
+-
4.53 52 CS 24.32
+-
5.25 53 ER 17.17
+-
3.90 I
55 EW 18.52
+-
4.47 3003 KS 27.28
+-
10.65 57 MB 17.33
+-
3.90 3013 ME 12.67
+-
3.07 I
59 MP 17.71
+-
8.42 60 MS 12.59
+-
3.64 61 NP 11.75
+-
2.90 62 PC 10.26
+-
3.43 63 SA 11.14
+-
3.15 3010 SP 16.30
+-
5.34 65 SS 12.19
+-
3.66 66 WR 14.39
+-
4.53 67 BD 19.13
+-
6.03 68 EB 12.89
+-
2.58 I
69 EM 9.01
+-
1.67 70 MT 14.64
+-
3.78 71 0A 16.22
+-
4.59 72 PA 17.19
+-
3.26 73 PB 73.39
+-
20.44 74 WH 14.55
+-
5.77 75 A
10.50
+-
2.66 I
76 B
14.49
+-
3.23 77 C
17.15
+-
4.31 78 D
14.55
+-
6.78 l 3 79 E
15.22
+-
3.65 3
80 F
34.60
+-
8.36 3005 G
11.27
+-
3.15 82 H
18.60
+-
4.17 83 I
16.39
+-
6.01 84 J
9.98
+-
~2.53 i
85 K
13.94
+-
3.82 l
86 L
13.14
+-
2.41 87 PL 29.40
+-
6.09 88 WS 44.61
+-
13.30 92 HB 28.48
+-
5.60 I
37 RL 5.21
+-
1.02 3046 RL 5.86
+-
1.13 I
Geographic Regional Averages this period are:
Near Plant (0.16 mi) 37.85
+-
8.34 Exclusion Area (.25.68 mi) 17.98
+-
1.28 I
Distant Neighborhood (.7-6.5 mi) 13.81
+-
1.21 l
Background (8-23 mi) 20.31
+-
4.36 3-25 ll
I I
TABLE III-D-5 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #2 1980 I
TLD MICR0R/
NO.
STATION HOUR t
2 SIGMA 1
CP 40.96
+-
26.38 I
31 CR 23.80
+-
5.97 32 CS 23.77
+-
5.65 33 ER 16.53
+-
3.38 I
34 EW 20.44
+-
4.44 35 KS 17.21
+-
4.41 36 MB 17.35
+-
5.21 38 ME 21.82
+-
8.68 I
39 MP 17.43
+-
3.32 40 MS 20.12
+-
5.94 41 NP 16.44
+-
3.33 I
42 PC 14.14
+-
3.38 43 SA 18.40
+-
4.65 45 SP 17.56
+-
3.87 46 SS 16.83
+-
3.65 I
47 WR 29.28
+-
6.50 48 BD 26.47
+-
5.62 3
EB 27.13
+-
10.42 90 EM 23.19
+-
5.75 91 MT 0.00
+-
0.00 94 OA 24.24
+-
7.86 95 PA 17.26
+-
3.64 96 PB 25.45
+-
5.96 97 WH 20.54
+-
6.01 98 A
47.66
+-
22.25 99 B
18.81
+-
5.63 3033 C
17.68
+-
3.25 3001 D
15.38
+-
2.78 t
3042 E
14.87
+-
3.86 3006 F
8.86
+-
1.59 3044 G
17.35
+-
5.14
. g 3045 H
0.00
+-
0.00 l g 20 I
16.04
+-
2.96 3048 J
11.28
+-
1.91 23 K
13.48
+-
2.42 1008 L
12.60
+-
9.77 1009 PL 18.05
+-
3.95 1011 WS 42.40
+-
8.62 2011 HB 17.81
+-
4.17 37 RL 1.92
+-
0.29 3046 RL 2.03
+-
0.53 I
Geographic Regional Averages this period are:
Near Plant (0.16 mi) 27.34
+-
4.53 l
Exclusion Area (.25.68 mi) 20.50
+-
2.32 g
Distant Neighborhood (.7-6.5 mi) 19.50
+-
2.28 Background (8-23 mi) 19.96
+-
3.21 3-26
I TABLE III-D-6 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #3 1980 I
TLD MICR0R/
NO.
STATION HOUR t
2 SIGMA 50 CP 19.74
+-
5.92 I
51 CR 20.23
+-
7.61 52 CS 26.22
+-
8.76 53 ER 20.23
+-
6.29 I
55 EW 24.37
+-
12.96 3003 KS 22.06
+-
12.20 57 MB 14.98
+-
4.70 3013 ME 19.94
+-
6.99 I
59 MP 19.37
+-
6.08 60 MS 18.27
+-
5.83 61 NP 18.36
+-
6.86 I
62 PC 12 98
+-
5.23 63 SA 12.70
+-
5.45 3010 SP 11.75
+-
5.58 65 SS 16.75
+-
5.07 I
66 WR 16.84
+-
4.99 67 BD 23.25
+-
8.06 68 EB 16.03
+-
4.75 I
69 EM 12.57
+-
3.77 70 MT 27.25
+-
11.60 71 OA 29.17
+-
12.65 72 PA 19.11
+-
5.83 I
73 PB 63.47
+-
23.24 74 WH 16.99
+-
5.14 75 A
19.93
+-
6.95 I
8.48 76 B
21.75 v-77 C
13.82
+-
4.23 78 D
18.39
+-
6.41 79 E
18.21
+-
5.34 I
80 F
25.09
+-
7.41 3005 G
14.23
+-
5.31 82 H
19.10
+-
7.22 83 I
17.34
+-
7.78 84 J
11.78
+-
3.45 85 K
18.55
+-
5.46 l l 86 L
16.56
+-
4.89 l 5 87 PL 22.87
+-
8.30 88 WS 0.00
+-
0.00 92 HB 23.48
+-
7.37 I
3014 RL 2.10
+-
0.79 93 RL 1.85
+-
0.68 Geographic Regional Averages this period are: '
'7.25
+-
13.59 Near Plant (0.16 mi)
J Exclusion Area ('.25.68 mi) 19.57
+-
1.89 I
Distant Neighborhood (.7-6.5 mi) 16.90
+-
1.57 Background (8-23 mi) 21.34
+-
6.86 3--27
I TABLE III-D-7 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #4 1980 TLD MICR0R/
NO.
STATION HOUR r-2 SIGMA 1
CP 34.97
+-
22.76 I
31 CR 35.18
+-
8.23 32 CS 26.73
+-
7.32 33 ER 17.29
+-
4.92 I
34 EW 26.64
+-
5.76 35 KS 21.66
+-
4.59 36 MB 25.30
+-
6.48 38 ME 27.53
+-
5.87 I
39 MP 19.09
+-
5.34 40 MS 23.79
+-
7.59 41 NP 17.90
+-
4.50 I
42 PC 24.35
+-
8.20 43 SA 18.31
+-
5.15 45 SP 22.40
+-
7.48 46 SS 17.55
+-
4.48 I
47 WR 29.77
+-
10.13 48 BD 16.95
+-
4.22 3
EB 27.12
+-
5.50 I
90 EM 21.94
+-
5.23 213 MT 0.00
+-
0.00 94 OA 43.15
+-
9.90 1
95 PA 18.60
+-
6.47 96 PB 82.66
+-
8.26 97 WH 23.99
+-
5.88 98 A
48.89
+-
25.42 99 B
0.00
+-
0.00 3033 C
21.91
+-
7.17 3001 D
14.56
+-
3.26 I
3042 E
23.10
+-
7.90 l
3006 F
22.15
+-
4.71 l
3044 G
18.97
+-
4.43
(
214 H
11.20
+-
2.11 20 I
18.45
+-
3.76 3048 J
17.12
+-
3.95 23 K
18.49
+-
4.90 1008 L
15.93
+-
5.41 l
1009 PL 20.76
+-
5.21 l
1011 WS 32.23
+-
6.55 l
2011 HB 21.92
+-
6.25 44 RL 2.17
+-
0.45 54 RL 2.69
+-
0.72 Geographic Regional Averages this period are:
Near Plant (0.16 mii 30.66
+-
5.28 Exclusion Area (.25.63 mi) 23.15
+-
2.54 Distant Neighborhood (.7-6.5 mi) 22.30
+-
2.29 Background (8-23 mi) 23.34
+-
3.86 3-28
I TABLE III-D-8 QUARTERLY AVERAGE EXPOSURE RATES 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Sta.
Micror/Hr Micror/Hr Micror/Hr Micror/Hr CP 18.86 +-
8.16 40.96 +- 26.38 19.74 +-
5.92 34.97 +- 22.76 CR 15.21 +-
2.15 23.80 +-
5.97 20.23 +-
7.61 35.18 +-
8.23 ICS 19.54 +-
3.21 23.77 +-
5.65 26.22 +-
8.76 26.73 +-
7.32 ER 11.57 +-
1.49 16.43 +-
3.38 20.23 +-
6.29 17.29 +-
4.92 EW 13.25 +-
1.95 20.44 +-
4.44 24.37 +- 12.96 26.64 +-
5.76 KS 17.05 +-
3.82 17.21 +-
4.41 22.06 +- 12.20 21.66 +-
4.59 IMB 16.32 +-
2.36 17.35 +-
5.21 14.98 +-
4.70 25.30 +-
6.48 ME 11.20 +-
1.45 21.82 +-
8.68 19.94 +-
6.99 27.53 +-
5.87 MP 12.29 +-
2.82 17.43 +-
3.32 19.37 +-
6.08 19.09 +-
5.34 IMS 10.40 +-
1.83 20.12 +-
5.94 18.27 +-
5.83 23.79 +-
7.59 NP 10.17 +-
1.39 16.44 +-
3.33 18.36 +-
6.86 17.90 +-
4.50 PC 8.75 +-
1.42 14.14 +-
3.38 12.98 +-
5.23 24.35 +-
8.20 ISA 10.27 +-
1.72 18.40 +-
4.65 12.70 +-
5.45 18.31 +-
5.15 SP 13.70 +-
2.18 17.56 +-
3.87 11.75 +-
5.58 22.40 +-
7.48 SS 11.43 +-
1.71 16.83 +-
3.65 16.75 +-
5.07 17.55 +-
4.48 i
WR 13.22 +-
2.80 29.28 +-
6.50 16.84 +-
4.99 29.77 +- 10.13 BD 15.09 +-
2.29 26.47 +-
5.62 23.25 +-
8.06 16.95 +-
4.22 EB 17.78 +-
2.68 27.13 +- 10.42 16.03 +-
4.75 27.12 +-
5.50 EM 11.72 +-
2.28 23.19 +-
5.75 12.57 +-
3.77 21.94 5.23 t-l 3 MT 11.00 +-
1.94 0.00 +-
0.00 27.25 +- 11.60 0.00 +-
0.00 l
5 OA 11.61 +-
1.93 24.24 +-
7.86 29.17 +- 12.65 43.15 +-
9.90 PA 11.16 +-
1.37 17.26 +-
3.64 19.11 +-
5.83 18.60 +-
6.47 PB 34.88 +-
6.54 25.45 +-
5.96 63.47 +- 23.24 28.66 +-
8.26 IWH 11.79 +-
2.11 20.54 +-
6.01 16.99 +-
5.14 23.99 +-
5.88 A
33.43 +- 14.04 47.66 +- 22.?5 19.93 +-
6.95 48.89 +- 25.42 B
14.03 +-
2.50 18.81 +-
5.63 21.75 +-
8.48 0.00 +-
0.00 g
C 12.44 +-
1.90 17.68 +-
3.25 13.82 +-
4.23 21.91 +-
7.17 l g D
9.23 +-
2.24 15.38 +-
2.78 18.39 +-
6.41 14.56 +-
3.26 l
E 10.54 +-
1.98 14.87 +-
3.86 18.21 +-
5.34 23.10 +-
7.90 l
F 18.00 +-
3.81 8.86 +-
1.59 25.09 +-
7.41 22.15 +-
4.71 l
G 10.77 +-
1.58 17.35 +-
5.14 14.23 +-
5.31 18.97 +-
4.43 H
10.82 +-
1.82 0.00 +-
0.00 19.10 +-
7.22 11.20 +-
2.11 I
10.86 +-
2.31 16.04 +-
2.96 17.34 +-
7.78 18.45 +-
3.76 l
J 8.98 +-
1.29 11.28 +-
1.91 11.78 +-
3.45 17.12 +-
3.95
E K
11.38 +-
1.57 13.48 +-
2.42 18.55 +-
5.46 18.49 +-
4.90 L
10.03 +-
1.30 12.60 +-
9.77 16.56 +-
4.89 15.93 +-
5.41 PL 15.29 +-
2.51 18.05 +-
3.95 22.87 +-
8.30 20.76 +-
5.21 WS 20.55 +-
4.27 42.40 +-
8.62 0.00 +-
0.00 32.23 +-
6.55 HB 17.25 +-
2.58 17.81 +-
4.17 23.48 +-
7.37 21.92 +-
6.25 RL 5.28 +-
0.48 1.92 +-
0.29 2.10 +-
0.79 2.17 +-
0.45 RL 6.24 +-
1.09 2.03 +-
0.53 1.85 +-
0.6d 2.69 +-
0.72 l
lI 3-29 I
I TABLE III-D-9 I
Location Exposure Rate (uR/Hr)
Beach Terrain I
khite Horse Beach 6.1 1 0.3 Sandy, granite (near Hill P Avenue) boulders on beach bhite Horse Beach 5.3 1 0.3 Sandy (in back of Blue Sail Bar)
Plymouth Beach 4.6 0.3 Sandy I
(outer beach)
Plymouth Beach 4.7 1 0.3 Sandy (inner beach)
I Plymouth Beach 7.1 t 0.2 Sandy, granite (behind Berts Restaurant) boulder on beach Duxbury Beach (Control) 5.1 0.4 Sandy with small I
(ocean side) amounts of gravel I
I I
3-30
I I
III. E.
Waterborne Samples of seawater are collected at three locations, the Station Discharge Canal, (Station 11), Bartlett Pond (Station 17 - 1.7 mi -
SE) and Powder Point (Station 25 - 7.8 mi - NNW). The discharge canal sample is collected by a continuously compositing sampler which I
extracts a sample of about 20 ml of water from the 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 The only positive measurement in this media was Cs-137 in the dis-charge canal on one occasion (monthly composite for May).
No other isotopes characteristic of reactor operation were observed at this station and the mean value of the Cs-137 concentration is well within one standard deviation of the mean value at the control station.
Therefore, it is not clear that PNPS-1 is responsible for this obser-vation.
There were no positive measurements at the other indicator station (Bartlett Pond - 1.7 mi - SE) and therefore there was clearly no significant environmental effect observed in the seawater media as a result of the operation of PNPS-1.
I I
i i
I I
3-31
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I III. F.
Shellfish I
Shellfish are normally sampled quarterly from 5 locations, the Station Discharge Canal, Duxbury Bay, Manomet Point, Plymouth Harbor and Marshfield.
The results of the ERMAP program for shellfish are pre-sented in Table III-F-1.
It is clear from this table that there have I
been positive measurements of many isotopes (Cr-51, Mn-54, Co-58, Co-60, Nb-95, Cs-137) in the discharge canal.
In addition there have been pos:itive measurements of Co-60 and Ce-141 at Manomet Point (3 miles - SE).
I These observed concentrations are most probably the result of PNPS-1 liquid releases.
However, even if a person were to consume the maximum annual quantity of seafood (5 kilograms / year) with the highest mean concentrations of these isotopes they would receive a dose of less than 0.004 mrem to the total body and about 0.02 mrem to the most restrictive organ (adult GI-LLI).
I When compared to the natural background dose rate of 80-100 mrem / year, there was clearly no significant environmental impact observed in I
shellfish as a result of the operation of PNPS-1.
Mussel shells collected from the discharge canal exhibited a mean con-centration of 29 pCi/kg of Co-60.
No other isotope was detected.
These measurements are undoubtly due to liquid effluents from PNPS-1.
However, since shells are not consumed by man there is no potential ic: pact on man from this media.
E I
3-35
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I I
III. G.
Algae (Irish Moss)
I Algae, referred to as Irish Moss or Chondrus Chrispus, is sampled quarterly at three locations, the Station Discharge Canal, Manomet I
Point and Ellisville.
The results of the ERMAP program for Algae are presented in Table III-G-1.
It is clear from this table that there have been positive measurements of Co-60, Mn-54 and Cs-137 in the discharge canal.
In addition there was one positive measurement of Co-60 at Manomet Point (Station 15 -
3 miles - SE) during the first quarter of 1980.
There was also one positive measurement of Co-60 at the control station in Marshfield, ten miles away.
This suggests the presence of a source other than PNPS in the case of the measurements beyond the discharge canal.
In any event, the measured concentrations in the discharge canal are certainly due to liquid effluents from PNPS-1.
I It is important to note that due to processing and market dilution, the presence of these concentrations do not represent a significant I
potential source of dose to the general public.
In fact, even direct human consumption of Algae (which to our knowledge, does not occur) would result in a dose rate of less than 0.01 mrem /yr to the total f
body and 0.0t, 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.
1
I l
When compared with the natural background dose rate of 80-100 mrem /yr I
there was clearly no significant environmental impact observed in lg l3 Algae as a result of the operation of PNPS-1.
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I 3-39
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III. H.
Lobster (Arthropods)
I Lobster samples are collected four times rer season at two locations, the vicinity of the discharge outfall rea and at a distant point off-shore.
The results of the ERMAP / ogram for Lobsters are pre-sented in Table III-H-1.
These results are unremarkable in that there I
were no positive measurements of any isotopes other than K-40 in either the indicator or the control samples.
Therefore, there is no evidence of any environmental impact on this media as a result of the operation of PNPS-1.
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ThaN TFN (to) TimFA THE avFRaGF R4Cucer'UNn FnR THF PEhinn nF THE HFPnRT
e THE FRactinN nF sa mpt F awatYSFS VIELnTNG DETEcTARLF MEASURE"ENTS (f.F. >3SfGMai TS INnfCATFn wf7HIN et le.
M M
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PILGHIH I OFFSTTF E *.v i nnN M E N T a l. RanInLnGTCat. HONITORfmG 8t/02/27 SUMMaWV FnD THF PERInn 12/3t/79 12/31/8n l
MEDIUMS ARTHenPnnS IINTTSt PCI/aC *ET fla DIONUCL inE S INnicafpR ifaTInNs HIGHEAT StafinN CONTROL i fic a f inn S (NO. aNaLTSES) NnMINAL MFaN, RANGE, ann MEaNeRANGF,ahn
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4)
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a NON.ROOTINE RFFFR9 in THE N ti"R F R OF 9FPaRATF "F a SilRF"ENTS WHICH *EWF GREATER THAN TFN (101 TIME 9 THF AVFpaGF RACetGRnyHn FOR THE PERInn nF THE RFPnRT i
se THE FRaf. finn nF SaMPLF ANatVMFS YTEtnTNG OFTECTaMLE "EASifRF"ENTS (T.E. >3 SIGMA) TS INnTCATFD af7HIN et je, i
c#:P c:p 9&h 7f
I I
III. I.
Fish I
Fish samples of Bottom Oriented (Group I) and Near Bottom (Group II)
I species are collected quarterly in the vicinity of the discharge outfall.
In addition, samples of Anadromous (Group III) and Coastal Migratory (Group IV) species are collected when in season, in this same area.
Lastly, a sample from each group is collected once per year at a distant location offshore.
I The results of the ERMAP program for fish are presented in Table III-I-1.
There were no positive measurements of any isotope (other than naturally occuring K-40) at the indicator station (discharge canal - Station 11).
Therefore, there is no evidence of any environ-I mental impact on this media as a result of the operation of PNPS-1.
I l
I I
I I
I I
I I
3-47 I
m W
W M.
W W
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PILGRip !
elf F ST TF F N W I RONdt ni al a n n i nt or. T C a t, howfinufh4 hl/np/77 SUMaaRY Fne TMF P F W I nli 12/31/T9 47/11/>n MEnltlMe FI9H UNITSg PCI/EG MET RanIONUCLInEm INnicainu MTaTIHNS MIGHE9T SfaTInw C a in T W.)I t ur a T 10., 4 (NO. ANALVSES) NnM]Nat ufaN.R4HGF.AND MEAN.RaHGF,4An "Eah.DANGF.&hn (NON.ROUffNFla LLn Nnl nETFrTFOee 974 Nn. DETFCTEDee NO. nFT(CTEnee t.n1E 77
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n)
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NnN. ROUT!hr RFFFRS fn THF Numarp nF SEP AR&TE *F astsRE*ENTS wH{CH nFNF GREAT [R 88)
THAN TFN (101 TTMFS THE avrPaGF RACwCRollNn FnR THE PENInn nF THE RFPORT
THE FRACTinN nF SAMPLF abaLYSFm YtELnTNG DETFCT4 HIE MEASUREMENTS (f.E. >3 SIGMA) IS IN0fCATF0 h! THIN *(
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E PitGp!M i nFFSTTF FeeviknopfHTat paplot pr.iC at a0MT104THA et/42/27 MHMMapy Fhe THF PENInn 12/31/79 12/11/*n MED!tiMs FISH HNITS: *tI/=G 'ET RADIONHCLIDFS Thniraind AfaffnNA MTGMFAT S t a T I O's Ci h T W41 tora *THNS (NO. ANALyMF9) NOMINat MFAN,paNGFeahn MEAN,RANGFeakn MEaN.WabGF,a40
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1e.
M M
M M
M M
M M
M M
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M M
M M
PILGRIM I OFFSif" FNVIRnNMENTal pantntnGICAL "!!NTTOpfNG 41/02/27 SUMMANY FON TMF PFRIOD 12/11/T9 12/11/P4 MEDIUMS FISH amITS: Oct/mG =F.T RADIONUCLinES TNofcaT04 STaftnNS HIGHFat STATinN CON T Wiel 16taTInh5 (NO. ANALYSF8) NOMTNAL NEAN, RANGE. ann MEAN,paNGFeakn MFAN,eANGE,aND (NON.ROUTINEle LLO NO.' nFTFr TFne e STA.
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je.
&###/69Y
I III. J.
Sediments Sediment samples are taken semi-annually at five indicator stations including Rocky Point, Plymouth Harbor, Duxbury Bay, Plymouth Beach and Manomet Point and a control sample is taken from Marshfield.
There is a detailed subdivision of individual sample cores in which samples are sectioned into 2 cm increments (this applies to all loca-I tions except Plymouth Beach).
The surface and alternate sections are analyzed for gamma emitting isotopes.
In addition, the surface section from each core and a mid-depth section from Rocky Point and Plymouth Harbor are analyzed for Pu-238 and Pu-239, 240.
The results of the ERMAP program for sediments are presented in Table III-J-1.
It is clear from this table that Co-60 was observed in sediment samples taken from Rocky Point (Station 11) whi:h is near the discharge canal outfall.
These samples were collected on 6/9/80.
Subsequent samples collected from the same location on 10/22/80 showed no evidence of any isotopes characteristic of reactor operation.
Therefore, the observations of Co-60 are most probably a transient effect.
The only other noteworthy values are the measured concen-trations of Cs-137 and Ce-144 in Duxbury Bay samples.
This may be I
explained by the fact that the sediment samples taken at Duxbury have a ailty character not common to the other samples.
It may be that the nature of the Duxbury sediment is such that certain materials are re-tained more strongly than others.
This theory is supported by the fact that the Duxbury indicator station also had the highest mean concentration of K-40, an isotope which is chemically similar to l
Cs-137.
Analyses for plutonium isotopes in sediment samples were performed by the LFE Environmental Analyses Laboratories in Richmond, California.
The results of these anlayses are presented in Table III-J-2.
There I
is no apparent trend in these data to indicate that the PNPS-1 is contributing measurably to levels of Pu-238 or Pu-239, 240 in the environment since levels of Plutonium at Rocky Point are among the l
lowest measured at any location.
l 3-51 l
W W
W W
W W
W W
M M
M W
M M
M DILCRIM I OFF5tTF FhwfuttektHTat wantrLontral mauffnwt%G 68/np/py.
SurMARY FHb THF PFRIOn 92/4t/T9 17/11/pn N[O [ljM g SFnIDFNT/S]LT HNITS: PC 1/a n r*V RaDIONOCL IDF S TNDiraTHE RT4IIONS HIGMF9T STaffnN CHNTwns IsTaT10mm (NO. ANat VMF S) N0=INal MFAN,WaNCF. ann
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31
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e).
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t 1.0 A 616 e 11
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NON. ROUTINE RFFFRS Tai TME NUMAFA DF MFPaRaTF HFasudFMENTs =HICH eFGE GNEaTER THaN TEN (30) TIMES THE avrpanF matuGROUND Fne THE pgRton OF THE REPORT
THE FRarTION OF SAMPLE ANALYSFS YTELn!NG nF TECTanL E "EaSHREMENTS (f.E. >3SIGua) TS INnicaTFD MITHIH *(
3e.
I TABLE III-J-1 1
l (continued) pBBR B 3
I O
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W PILGRIM 1 0FFSTTF FNVIRtlNMENTAL RantnLnGICAL MONITnRTNG Al/02/27
~~SUMMARY~~
FOR THF PERInD 12/31/19 12/31/80 MEDIUMI SEnIMENT/STLT u=ITS: PCI/mG DRV RADIONUCLIDES INDICATOR sf ailstNS HIGHEST STAT!nN CnNTROI LnCATIn%S (NO. ANALYSES) NnMJNaL MF aN,N ANGF.sNn MEANsRANGFeahn MEAN.RaNGF,aNO (NON.ROUTINEIe LLO Nn.' DE TEr TFile e S T A.'
Nn. DETECTEne,e NO. DFTFCTEDee
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NnN.Rnl8 TINE RFFFR9 Til TMF NilMRFR OF SFPARATF MFaslanFMENTS hMICH >FRF GRFATER THAN TEN (10) TIMFS THE AVFRaGF paCwGenUND FnR THE PERInn nF THE REPORT ee THE FRACTION nr SAMRLF iN01 CAT,LYSFS YTELnTNG DFTECTARLE MEasuRFMENTS awa (i.E.
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I I
I TABLE III-J-2 RESULTS OF SEDIMENT ANALYSES FOR PLUT0NIUM I
Results pCi/Kg (/,cy) 1 % Error (Ir ) (a)
I Location Depth (cm) 238 239,240 p
p Duxbury 0-2 1.15 1 21%
42.9 3%
Duxbury 16-18 0.27 1 32%
9.82 5%
Plymouth Harbor 0-2 0.22 54%
7.72 1 5%
Rocky Point 0-2 0
1 0.07 3.35 10%
Rocky Point 16-18 0
t 0.12 2.32 1 11%.
Manomet Point 0-2 0.09 1 80%
2.16 1 10%
I (a) If the result is zero, the error is in pCi/Kg.
(b) Sample analyses for control station in Marshfield and mid-depth sample at Plymouth Harbor not available as of this date.
I I
I I
I I
I I
3-55 I
I III-K Milk I
Milk samples were collected at three locations, Plimouth Plantation (station 15-2.2 mi-W), Plymouth County Farm (Station 11-3.5 mi-W) and the King Residence (Station 22-12 mi-W) during 1980.
The Plimouth Plantation is a substitute indicator station added to replace the Whitman Farm in 1979.
The 1980 milk animal and garden census (see Appendix E) confirmed this location as the nearest location of a milk producing animal within 5 miles.
As stated in Section I of this report, milk samples were not always available in sufficient quantity for analyses from this location, how-ever, every reasonable effort was made to collect samples from this location whenever they were available.
I When available, samples were collected semi-monthly when animals are on pas-ture and monthly at other times.
The results of the ERMAP program for the milk media are presented in Table III-K-1.
The results of analyses for Cs-137, and Sr-90 are presented graph-ically in Figures III-K-1 and III-K-2 respectively.
There were positive I
measurements of these isotopes at the indicator and control stations.
In the case of Sr-90, I-131 and Cs-137, the highest mean values of concent'ra-1 l
tion occurred at the Plimouth Plantation.
Station releases for this period exhibited a Sr-89/Sr-90 ratio of greater than 100/1 and therefore it is un-likely that the PNPS-1 is the major source of the indicator station activity since the measured Sr-89/Sr-90 ratio was at most 1/2.
l In addition, the measured average concentration of both Cs-137 and Sr-90 were g
E respectively 10,000 and 1,000,000 times in excess of the concentrations ex-pected to be present based on measured releases from PNPS-1 and the conserva-tive dose estimation methodology described in Regulatory Guide 1.109 and l
1.111.
In other words, PNPS-1 probably contributed much less than 0.01% of
(
the measured concentrations of Sr-90 and Cs-137 in milk at the Plimouth Plan-tation.
The remainder of the measured cesium and strontium radioactivity is unquestionably due to atmospheric fallout resulting from atmospheric weapons j
testing.
3-56
I I
In the case of I-131 the only two positive measurements at the Plimouth Plan-tation occurred during October and November (0.52 and 1.7 pCi/ liter respec-tively).
I There was a Chinese atmospheric weapons test which occurred on 10/17/80 which undoubtly contributed most or all of the measured I-131 activity at this loca-I tion.
However, even if a person were to consume milk with the highest mean concen-tration of I-131 for a full year they would receive less than 1 mrem / year to the most restrictive organ (infant thyroid).
When compared with the natural background dose rate of 80 to 100 c_a/ year, I
there was clearly no significant environmental impact on the milk media as a result of operation of PNPS-1.
I I
I l
I I
I 3-57
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3-62 I
III. L.
Cranberries Cranberries are collected from three locations, the Manoment Point Bog (2.6 mi - SE - location 13), the Bartlett Road Bog (2.8 mi - SSE/S -
I location 14) and the Pine Street Bog (17 mi - kW - location 23) at the time of harvest.
The results of the ERMAP program for this media I
are presented in Table III-L-1.
The only man-made radionuclide detected in any sample was Cs-137 which appeared in a?1 samples collected.
A comprehensi re study of cesium uptake in cranberries was performed during 1978. The results of this study are published in the 1978 Environmental Radiation Monitoring Program Report No. 11.
The results of this study and the fact that no other reactor related isotopes were measured above LLD in cranberry samples makes it ex-tremely unlikely that there was any environmental impact on cran-berries due to operation of PNPS-1.
I I
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3-63
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e NON-RnuTINE RFFFRS Tai THE NUahFR OF SFPaHaTF *EaSI'RE*ENTS HICH WFWF GREATFH THaN TEN (10) TI*ES THE a vFWacF maCugenUND Frie TNF PEston nF THE RFPn9T se THE FRacit0N nr samptr aNatYSF A YTELnING DETERTaRLE "EasuMFwENTS (f.E. >1 SIGMA) TS INDIC&TFD mITHIN et le.
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I III. M.
Vegetation Samples of tuberous and green leafy vegetables are collected at the I
time of harvest at four locations, Plymouth County Farm (3.5 mi - W),
Bridgewater Farm (2n mi - W), the Evans Residence (0.7 mi - W) and the Work Residence (0.6 mi - ESE).
The results of the ERMAP program for this media are presented in Table III-M-1.
The only man-made isotope observed was Cs-137 at the Evans Residence.
The absence of Cs-134 at this location and the fact that the measured Cs-137 concentration (40 pCi/Kg) is about 8000 times what would be expected at this location based on releases froci PNPS-1, strongly indicates that fallout, not PNPS-1, is the primary source of this I
Cesium-137.
Therefore, it is extremely unlikely that there was any environmental impact on vegetation due to operation of PNPS-1.
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3-67
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I I
III. N.
Forage Beef Forage is collected from three locations annually, the Plymouth County Farm (3.5 mi - W - Station Number 11), Whitman Farm (21 mi -
NW - Station Number 21) and Plimoth Plantation (2.2 mi - W - Station Number 15).
The results of the ERMAP program for the media are pre-sented in Table III-N-1.
The only man-made isotope detected was Cs-137 which was detected in all samples.
There were no other reactor-related isotopes detected above LLD in any sample.
The highest mean concentration of Cs-137 occurred at the Plimoth Plantation.
However, the absence of Cs-134 and the fact that the measured mean Cs-137 concentration (120 pCi/Kg) is in excess of 100,000 times what would be expected based on releases from PNPS-1, strongly indicates that fallout, not PNPS-1, is the primary source of I
this Cesium-137.
Therefore, it is extremely unlikely that there was any environmental impact on forage due to operation of PNPS-1.
I I
I I
I I
I I
3-71 I
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.$9 f
I I
IV.
References I
1.
Regulatory Guide 1.109 - CALCULATION OF ANNUAL DOSES TO MAN FROM ROUTINE RELEASES OF REACTOR EFFLUENTS FOR THE PURPOSE OF EVALUATING COMPLIANCE WITH 10 CFR PART 50, APPENDIX I -Revision 1, October 1977 2.
SETTLEMENT AGREEMENT BETWEEN MASSACHUSETTS WILDLIFE FEDERATION AND BOSTON EDISON COMPANY RELATING TO OFFSITE RADIOLOGICAL MONITORING
- June 9, 1977 Program "ERMAP", Version 3.1 -
3.
Yankee Atomic Electric Company January 9, 1979, Author - J. E. Vossahlik I
4.
Memorandum, Yankee Atomic Electric Company, Reg 94/77, A. E. Desrosiers 5.
Direct Radiation Survey, June 1976, S. A. Farber, Yankee Atomic Elec-tric Company l
6.
Memorandum, Yankee Atomic Electric Company, Reg 211/76, A. E. Desrosiers i
l 7.
Report on Accumulation of Cesium-137 in Cranberries, March, 1979 Yankee Atomic Electric Company, M. Strum I
I
' I I
I 4-1
I I
Appendix A - Anomalous Measurement Reports I
I I
i I
I
~~g l~~
I I
I
.I I
I I
I l
A-1
~~g'..~~
S.
g '.' s 4
t g.:
s
...s f.,'
,""" Erbsqn n-.d
.I.
d PILGRIM NUCLEAR POWER ST/ ~i0N
! ['
RFD
~~1 ROCKY H LL RoAo g~~
PLYMOUTH. MAS,5ACMUSETT5 00363
~
February 6, 1980 I
BEco Ltr. #80-23 Director, Region'I -
Office of Inspection' and Enforcement l
I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 I
Licensee Event Report 80-005/01T-0 Docket Number 50-293 License DPR-35 Gentlemen:
The attached Licensee Event Report 80-005/01T-0, " Anomalous Measurement.
Report" is hereby submitted in accordance with the requirements of Pilgri~.
Nuclear Powet Station Technical Specification 6.9.C.2.b.
If there are any questions on this subject, please contact us.
I Resp ctfully submitted, d
1 e
P.
. McGuire I
Nuclear Operations Station Manager I
MIM:ap
~~Enclosures:~~
(3 copies)
LER 80-005/01T-O Director (40 copies)
I cc:
Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.C.
20555 l 5 bec: Messrs. C. C. Andognini R. Sevigny E. L. Cobb W. M. Sides
. P. A. Foulsham(2)
D. C. Stoodley I
M. C. Hensch C. K. Vantresse C. J. Mathis C. G. Whitney M. T. McLoughlin 3,Mt" K. Calderone J. W. Nicholson NOD Licensing W. 7. Olsen PNPS Records Center J. A. Seery P.J.M.(LB)
~'
l -
~
l
\\
~~L j~~
u r
\\
LICENSEE EVENT REPORT.'r.,. -
~~E *f,.,.~~
g $iRO! SLOcK: l
.h -
'C f 'l*
l l
l l
IPLEASE PRINT CR TYPE ALL REEUIRED INF3".MATIONI o
i lM l A lP IP lS l1 lh bl' O! 'l Ol 0l01010]
l'OIOl@as l I l II 1l 1l@e, CAT se @.
l l
4 uCaust tvrt ao o
ucansEE Coof is w-uClast Num ER as SuYet [.Lj@l0 l5 lCf l-10121913 h 01 11 il 11 al ol@l 0121 OI 6I 810 l@
so el
$oCKET NuueEm 88 SS EVENT oATE 7.
75 REPORT DATE So EVENT DESCRIPTION AND PROSABLE CONSEQUENCES h i
i On January 1,1980. BECo was notified by Yankee Atomic Elecerte T mh thee
.mur.A 1
f concentrations of Sr-90 in a milk sample taken fron'an indicator station was greater i than 10 times the concentration in the control station sample,18 pei/kg to 1.6 pei/kg
, repectively. The indicator station is 2.2 miles west of the reactor site. There is i g no detectable Sr-89 or I-131 in the indicator sample; therefore, it is not likely l
thet Pilgrim Station is the source of the measured concentrations.
i
, g l
. l
'II II l@ Lxj@ Lz_l@ 12 I z I z I z I z I z I@ suTeL J.1@
sI$bYcoE
'cNo E YoE sNCooE czapoNENT CooE ot s
io n
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a i
SEcuaNTIAL OCCURRENCE REPORT.
REVIStoN I @,a,LER/Ro EVENTYEAR ASPoRT 8eo.
Coot TYPE 18 0.
g la101
[-_l loloisi V_.]
10111 p
[--:l 101
,_ a i za sa m
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CAUSE DE 4RIPTION AND CORRECTIVE ACTIONS 27 lNo corrective action is contemolated. It ann nem thee them. 1 v.1= mr. An. en I
I
~~g l local meteorological conditions which resulted in the deposition of old fallout.~~
I I
~
i l
I 80 s e gT
% POWER oTHER STATi2 D1 R
discovery DESCRIFfloN W @ l01010l@l 1
l
(,p,J@lNotificationbyEnvironmental1mb.
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Auouwt or ACTiv TY h l LOCATION OF RELEASE ELEAsto oP REtaAsE l
N.A.
I
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w a
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PEftSoNNEL EXPOSURES
] 010 l O j@W@DESCRIPTloN NumeER TYPE l
N.A.
I IES PERSONNEL put oEs:RiPT1oN@
NuueER
.J
' '8'
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. so --
s of oR D AuACE To FACluTY 43
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~~5 l~~
W @l N. A.'
so e
to NRC USE ONLY l
PusLICITY
.N:i.
i iiiiiiiiiiiiil ggrac -a~
se se so s io M. Thomas McLoughlin
~~61. 7. 74 6.7900.~~
o
t=
~~.t.: :- :: I---~~
t re - :::.
I
. :. :. a :- r : : : r -
March lE, 1980 bECo Ltr.#80-43 I Director, Region 1 I r.fice of Ir.spection and Enforcement Cf E. Su:*. tar Kegula tc ry Cer=ission f31 ? ark.;ven.se ring of Trussia., PA 19406 I_izenssaIvan:Report 80-009/04T-0 Docket Nt=,ber 50-293 License D?R-35 Gentlemen:
T.,e a:: ached Licensee Event Report 80-009/047-0 "Anomelous ::e:r rerent Reper:
is '. ereby suitir:ed in accordance -ith the requirements of Pi grin Nu:; ear
-:. er I:a:1:n ~echnica; Specifi:ation 6.9.C.2.b.
f there are any questions on this subject, please centact us.
Esspectfully suiritted, I
t P.
. McGuire Sta f en 2: nezer Nu:Itar 0; ars i:ns -
I 3.T.':e; Enclesures:
(2 copies)
LIR S0-009/ 04T-0 cc: Director (40 copies)
Office ef Mrnagement Infor ation and Pregra: Control T. 5. Nuclear Regulatory Co:=ission I
".0:.shing tcn, D.C.
20555 bec:
Messrs. G. C. Andognini R. Sevigny E. L. Cobb W. M. Sides
' I l
P. A. Foulsham(2)
D. G. Stoodley M. G. Hensch C. K. Vantrease J. E. Howard G. G. Whitney C. J. Mathis Ms. K. Calderone M. T. McLoughlin NOD Licensing J. W. Nicholson PNPS Records Center I
W. F. Olsen P.J.M. (LB)
J. A. Seery I
1
LICENSEE EVENT REPORT

~~CONTROL BLOCK: l l~~
l l
l l lh
~
(PLEASE PHINT CR TYPE ALL RECUlRED INFO 2MATION) i 8
.jl xl A l P l P l S I 1 l@l 0 l 0 l - l 0 l 0 l 0 l 010 l-l 0 l 0 @l 4 l 1 l 1 l 1 l 1 l@l l
lg 8
L6CENSEE Coot to 16 LICENSE NUMSER 2h 25 LICENSE TYPE J0 57 CAT SS Ev","c' Ql 0 l 5 l 0 l - l 0 l 2 l 9 l 3 l@l 01311 l 018 l 0 l@l 0 l 3 l 1 l 8 l 810 l@
1 SO St DOCKET NUMSER SS SS EVENT oATE 74 75 REPoRToATE 80 EVENT DESCRIPTION AND PRO 8ABLE CONSEQUENCES h 2 I On March 10, 1980, Boston Edison receivad an analyses report from the Yankee l
l Atomic Electric Laboratory which indicated that reportable concentrations of Cr-51 l l
(339
~~14 pCi/kg) and Co-60 (167~~
~~25 pCi/kg) existed in a n:ussel sample taken l~~
5 l from the Pilgrim Station Discharge Canal on January 10, 1980.
l l
These concentrations are in excess of 10 times the Lower Limit of Detection at l
7 l the Control Station in Marshfield (LLD for Cr-51 was 31.pci/kg and' for Co-60 l
8 I was 4.7 pCi/kg).
-l Yo'E
$5E SN$$E COMPONENT CODE SUS oE S C E l Il Ilh h
h lZ lZ lZ lZ lZ lZ lh h
h 9
8 8
io ii n
n it it 20 I@,g'Ro LER EVENT YEAR EP TN TV N.
g 1810 l
[:__j 101019 l d
10 14 l T
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_ 21 22 23 24 26 27 at 28 31 32 KN ACT o P
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24 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 l
The maximum dose to an individual consumit.g seafood with these concentrations for l
l] I a full year would be only 4 x 10-3 mrem to the total body and 2.4 x 10-3 mram to I
l the most restrictive organ. Therefore, it is concluded that there is no risk to l
l the health and safety of the public.
l t
t I
I AE
% POWER oTHER STATUS oi5 R
DISCOVERY otSCRIPTioN 32
[H_J@ l0l0l0l@l N.A.
l
(,D_J@l Notification,byEnvircamentalLab.
l s
AbivtTV Co TENT AMOUNT or ACTiv:TY @ l Lo:ATioN or R'4 LEASE
[ Zj @o or RELEAsEy@l LEAst N.A.
l N.A.
l 8
10 11 44 46 80 FER$oNNEL EXPOSURES NvMSER TYPE oESCRIPTioN i ji 0l 010l@LZJ@l 8 A-I rEnsoNNE'L iNav' lits oEsCRiPTioN@
NvMSER N.A.
I I0l0l0l@l S
11 12 80
~~S or oR oAM PACILITY W @l N.A.~~
l 8
10 80 oESCRiPTioN @
NRC WE ONW issut hl N.A.
l lllllllllllll$
o 8
10 GB SS 30 E
~
NAMF OF PRFPARFB PHONE:
t
I g.
~~. t.~~
t ca Edison cam' PsLGRiM NucLcAR Powcn STAviDN RF*D =1 ROCKY Mibt ROAD l
ALvuouTM MassacMusCTTE O2360 I
April 2, 1980 I
BECo Ltr.f 80-53 IDirector,RegionI Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Licensee Event Report 80-009/04T-1 l
I Docket Number 50-293 i
License DPR-35 l
Gentlemen:
The attached, revised Licensee Event Report 80-009/04T-1, "Anomolous Measurement Report" is hereby submitted in secordance with the requirements of Pilgrim Nuclear Power Station Technical Specification 6.9.C.2.b.
This revision is b2ing issued to correct a calculation error. The correction does not alter previous conclusions.
If there are any questions on this subject, please contact us.
Respectfully submitted, c
me P.
. McGuire Sta on Manager Nuclear Operations E
MIM:ep W
~~Enclosures:~~
(3 copies)
LER 80-009/04T-1 I
cc:
Director (40 copies)
Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Iec:
b Messrs. G. C. Andognini R. Sevigny E. L.'Cobb W. M. Sides I
P. A. Foulsham(2)
P. D. Smith M. G. Hensch D. G. Stoodley J. E. Howard G. G. Whitney C. J. Mathis Ms. K. Calderone I
M. T. McLoughlin NOD Licensing J. W. Nicholson PNPS Records Center W. F. Olsen P.J.M.(LB)
J. A. Seery lI I
'"g,-
LICENSEE EVENT REPORT Ce WTRO. B LOCK: l
}
l l
l l lh (PLEASE PRINT CQ TYPE ALL REtUIRED INFtRMATitNI 1
6 l Ml A lP lP lS l1 lg0 l 0l -l 0l 0l 0l 0l 0l -l 0l 0l@264 l 1l 1[ 1l 1l@l l
lg
~~i 9~~
LICENSEE Coog to 16 LICENSE NUMSER 2S LICENSE TYPE JO 57 GAT SS y',$ l L l@l0 15 l0 l-l0 l 21 91 3 @l 01 31 11 Ol 81 0 l@l 0l 3 l 1l 8 l 8 l 0 l@
1 60 Si ooCKET NUMBER es Se EvgNT oATE 74 76 REPORT oATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l
On March 10, 1980, Boston Edison received an analyses report from the Yankee Atomic ;
l Electric Laboratory which indicated that reportable concentrations of Cr-51 (339
~~l l~~
14 pCi/kg) and Co-60 (167 t 25 pCi/kg) existed in a mussel sample taken from the l
g; Pilgrim Station Discharge Canal on January 10, 1980.
l l
l These concentrations are in excess of 10 times the Lower Limit of Detection at
, l the Control Station in Marshfield (LLD for Cr-51 was 31.pci/kg and for Co-60 was 4.7 pCi/kg).
I SoI:'E
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47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l Ths maximum dose to an individual consuming seafood with these concentrations for a I l full year would be only 4.4 x 10-3 mrem to the total body (child) and 3.5 x 10-2 mremI i
l to the most restrictive organ (adult G1-LL1). Therefore, it is concluded that there l 3 l is no risk to the health and safety of the public.
1 l
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~~'T!sY oTwER STATUS @ciEoNEY oisCovERY oEscMirTioN @~~
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NAME OF PREPARER PHONE:
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P.vmoch. M AEE A:e.;;t**
~~"5C1 April 28, 1980 Director, Region I Office of Inspection and Enforcement I~~
U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Licensee Event Report 80-014/04T-0 Docket Number 50-293 License DPR-35 Centlemen:
The attached Licensee Event Report 80-014/04T-0, "Anomolous Measurement Report",'is hereby submitted in accordance with the requirements of Pilgrim I
Nuclear Power Station Technical Specification 6.9.C.2.b.
If there are any questions on this subject, please contact us.
I Respectfully submitted, P. J. Mc ire I
Station Manager l
Nuclear Operations MIM:ep Enc 2csures:
(3 copies)
LER 80-014/04T-0 l
cc: Director (40 copies)
Office of Management Informatios and Program Control U. S. Nuclear Regulatory Cor::nission Washington, D.C.
20555 bec: Messrs.
G. C. Andognini R. Sevigny E. L. Cobb W. M. Sides P. A. Foulsham (2)
P. D. Smith M. G. Hensch D. G. Stoodley J. E. Howard G. G. Whitney I
C. J. Mathis Ms. K. Calderone M. T. McLoughlin NOD Licensing l
J. W. Nicholson PNPS Records Center E
W. F. Olsen P.J.M.(LB) g J. A. Seery lI l I
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LICENSEE EVENT REPORT CONT RO' B LOCA-l l
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60 St DOCILET NUMagR 68 59 EVENT DATg 74 76 REPORT oATE to I! VENT DESCRIPTION AND PROBABLE CONSEQUENCES h l
On April 18, 1980, Boston Edison Company received information from the Yankee l
o is] l Atomic Environmental Laboratory that indicated that a sample of milk collected from l l
an indicator station (Plimouth Plantation - 2.2 miles vest of the plant) contained I c,
3; ;
a concentration of Cs-137 of 24.7 pCi/ kilogram. This concentration was ten (10) l e l times the measured control station concentration of 2.45 pCi/kg (Whitman Farm - 21 l 7
l miles NW).
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Mr. M. Thomas McLoughlin m-%N
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O BOST05 EDISON CO:PANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Attachment to LER 80-014/047-0 On April 18, 1980, Boston Edison Company received information from ' ankee Y
Atomic Environmental Laboratory that indicated that a Sample of milk collected f rom an indicator station contained a concentration which was ten (10) times I
the measured control station concentration. It is very unlikely that this measurement is the result of plant effluents since the measured releases for the prior six months would have resulted in a calculated concentration of Cs-137 in milk that would be 5 orders of magnitude lower than the measured concentration (using the models presented in Regulatory Guide 1.109). The calculated dose due to consumption of milk containing the measured concentra-tion for a full year would be 5.0 millirem to the most restrictive organ.
(inf ant-liver) and 0.55 millirem to the total body (adult).
I I
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June 25, 1980 BEco Ltr #80-113 Director, Region I Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission I
631 Park Avenue King of Prussia, PA 19406 I
Licensee Event Report 80-021/04T-0 Docket Number 50-293
_ License DPR-35 Gentlemen:
The attached Licensee Event Repcrt 80-021/04T-0, "Anomolous Measurement Report", is hereby submitted in accordance with the requireannts of Pilgrim Nuclear Power Station Technical Specification 6.9.C.2.b.
I If there are any questions on this subjact, please contact us.
I Raspectfully submitted, P.
McGuire Sta on Manager Nuclear Operations I
MDi:ep Enclorures:
(3 copies)
LER 80-021/04T-0 cc: Director (40 copies)
Office of Management information and Program Control
. g U. S. Nuclear Regulatory Commission E
Washington, D.C.
20555 bec: Messrs. G. C. Andognini R. Sevigny E. L. Cobb W. M. Sides I
P. A. Foulsham (2)
P. D. Smith M. G. Hensch D. G. Stoodley i
J. E. Howard G. G. Whitney I
C. J. Mathis
-Ms. K. Calderone
~~M. T. McLoughlin NOD Licensing J. W. Nicholson PNPS Records Center~~
,l g W. F. Esen P.J.M. (LB) 3 J. A. Seery I
LICENSEE EVENT REPORT
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CONTROL BLOCK: l l
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(PLEASE PRINT OR TYPE ALL RECUIRED INFCRMATION)
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GO St DOCKET NUMBER 88 89 EVENT oATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I on 6/16/80 PNPS received an analyses report from the Tankee Environmental Laboratory l l that indicated than an algae sample collected on 5/8/80 contained a reportable l
l concentration of Co-60.
l
, c,, l REFER TO ATTACHMENT FOR FURTHER INFORMATION.
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Mr. M. T. McLoughlin 617-746-7900
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BOSTON EDISON COMPANT PILGRIM NUCLEAR POWER STATION DOCKET No. 50-293 Attachment to LER 80-021/04T-0 on 6/16/80 Boston Edison received an analyses report from the Tankee Atomic I
Electric Laboratory which indicated that a reportable concentration of Co-60 (262 i 8.7 p01/kg) existed in an Irish Moss sample taken from the Pilgrim Station discharge canal outfall area on 5/8/80.
This concentration is in excess of 10 times the measured concentration at the control station in E111sv111e (11.7 + 2.7 pCi/kg).
Due to process 1 rig and market dilution it is extremely unliksly that any indi-vidual would consume sny material with the measured concentration of Co-60.
However, even if a person were to directly consume this algae at seafood I
consumption rates given in Regulatory Guide 1.109, the annual dose to that person would be about 0.01 arem to the total body and 0.05 arem to the marimum exposed organ (GI-LLI).
As a result of these extremely small calculated doses.(as compared to the natural background dose rate of about 100 arem/yr) we have concluded that
('
there is no risk to public health and safety.
I I
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~
PILGRIM NUCLEAR POWER STA~iCN RFD *1 Rocacy HILL RcAo PLvMouTM. MassAcMusETTs C2360 July 30,1980 BEco Ltr. #80-158 Director, Region I Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission I
631 Park Avenue King of Prussia, PA 19406 Licensee Event Report 80-031/04T-0 I
Docket Number 50-293
' License ~DPR-35 Gentlemen:
The attached Licensee Event Report 80-031/04T-0, "Anomolous Measurement", is hereby submitted in accordance with the requirements of Pilgrim Nuclear Power Station Technical Specification 6.9.C.2.b.
If there are any questions on this subject, please contact us.
Respectfully submitted, jffe N ->'
ev P.
McGuire I
Station Manager Nuclear Operations MDi:ep
~~Enclosures:~~
(3 copies)
I LER 80-031/04T-0 cc: Director (40 copies)
Office of Management Information and Program Control I
U. S. Nuclear Regulatory Commission Washington, D.C.
20555 I
bec:
Messrs.
G. C. Andognini R. Sevigny E. L. Cobb W. M. Sides P. A. Foulsham (2)
P. D. Smith P. F. Giardiello D. G. Stoodley M. G. Hensch
. G. Whitney J. E. Howard K. Calderone C. J. Mathis NOD Licensing l
M. T. McLoughlin PNPS Rectrds Center l
=
J. W. Nicholson P.J.M. (LB)
W. 7. Olsen J. A. Seery I
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JRC FORM 366 U.S. NUCLEA'1 AEGULAToRY COMMISSION LICENSEE EVENT REPORT NO 80' f yJ, CONTROL BLOCK: l l
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lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATitN) l MI Al Pl Pl Sl 1l@l O l 0 l -l 0 l 0 l O l 0 l 0 l - l 010 l@264l1l1l1l1l@l l
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8 60 61 DOCKET NUMBER e8 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l
On July 21, 1980 Boston Edison received an analyses report from the Yankee Atomic l
o a l Electric Laboratory which indicated that a reportable concentration of Co-60 l
o l
(48.3 t 1.4 pCi/kg) existed in a mussel sample taken from the Pilgrim Station l
f o
I discharge canal outfall area on 4/8/80. This concentration is in excess of 10 times l o
l the lower limit of detection at the control station in Marshfield (4.7 pCi/kg).
l l
This insignificant concentration represents no risk to the public health and l
o1s 1 I safety.
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The presence of Co-60 in this discharge samole is due to coeration of the Pilerim l
l Station. However, even if a person ware 1o directly consume mussels at the rate l
l given in Regulatory Guide 1.109, thE annual dose to that person would only be l
l l
about 1.3 x 10-3 mrem to the total Et dv cnd 9.7 x 10-3 mrem to the maximum exposed I i i 14 i l organ (GE-LLI).
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August 26, 1980 BEco Ltr. #80-199 Director, Region I I
Office of Inspection and Enfonement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Docket Number 50-293 License DPR-35 Gentlemen:
The attached Licensee Event Report 80-042/04T-0,"Anomolous Measurement", is hereby submitted in accordance with the requirements of Pilgrim Nuclear Power Station Technical Specification 6.9.C.2.b.
If there are any questions on this subject, please contact us.
Respectfully submitted, AM P.J. McGu re Station Manager Nuclear Operations i
i
~~Enclosures:~~
(3 copies)
LER 80-042/04T-0 cc: Director (40 copies)
I Office of Management Information and Frogram Control i
U. S. Nuclear Regulatory Commission l
Washington, D.C. 20555 bec: Messrs.
R. Sevigny E.L. Cobb W.M. Sides P.A. Foulsham (2)
P.D. Smith
{
]
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P.F. Giardiello D.G. Stoodley M.G. Hensch G.G. Whitney J.E. Howard Ms. K. Calderene SEP 2 G80 C.J. Mathis NOD Licensing M.T. McLoughlin PNPS Records Center J.W. Nicholson P.J.M.
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8 60 61 DOCKET NUM8ER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l On August 20, 1980, Boston Edison Company received an analyses report from the Yankee l
~~o ;3; l Atomic Electric Laboratory which indicated that a repn. table concentration of Co-60 l~~
~~[ (102.4+2.7 pCi/kg) existed in a mussel sample taken from the Pilgrim Station discharge l~~
~~canal outfall area on July 14, 1980. This concentration is in excess of 10 times the l~~
- 3
[ lower limit of detection at the control station in Marshfield (5.9 pCi/kg).
l iu a l
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=n-,la 4= Aa en nna*n*4nn ns -ka l
l Pilgrim Station.
However, even if a person were to directiv consume mussels a*
I ii i i
1 the rate given in Regulatory Guide 1.109, the annual dose to that person would only l
2 l be about 2.8x10-3 mrem to the total body and 2.1x10-2 mrem to the maximum exposed I
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I 80 8 9 AN
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lllIIlIIIlI!!I 68 69 80 3 8 9 10 617-746-7900
{
Mr. M. Thomas McLoughlin PHONE:
NAME OF PaEPARER
l
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Ed"ison ca.....
ECS10N PILGRIM NUCLEAR POWER SrATICN RfD **1 Rocsty HILL RoAo PLvuouTH. Mass ACMuscTTs 02360 December 19, 1980 R. D. Macwom BECo Ltr. #80-313 Director, Region I Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Licensee Event Report 80-090/04T-0 Docket Number 50-293 License DPR-35 Gentlemen:
The attached Licensee Event Report 80-090/04T-0, entitled "Anomolous Measure-I ments", is hereby submitted in accordance with the requirements of Pilgri=
Nuclear Power Station Technical Specification 6.9.C.2.b.
If there are any questions on this subject, please contact us.
Respectfully submitted, RA M I
R. D. M chon Nuclear Operations Manager Pilgrim Station I
MIM:ep
~~Enclosures:~~
(3 copies)
LER 80-090/04T-0 cc: Director (40 copies)
Office of Management Infor=ation and Program Control U. S. Nuclear Regulatn y Cor=:ission Washington, D.C.
20555 bec: Messrs. J. E. Howard K. P. Roberts W. J. Ar= strong J. A. Seery I
H. F. Brannan P. D. S=ith E. L. Cobb A. R. Trudeau P. A. Foulsham(2)
G. G. Whitney P. F. Giardiello Ms.
K. Calderone M. T. McLoughlin NOD Licensing
(]
C. J. Mathis PNPS Records Center A. V. Morisi PRC Resident Inspector I
J. W. Nicholson E. J. Ziemianski W. F. Olsen m
LICENSEE EVENT REPORT C:'NTROL BLOCK: l 1
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3 60 61 DOCKET NUMG ER 68 69 EVENT QATE 74 75. REPOR* c) ATE 80 EVENT DESCRIPTICN AND PROBABLE CONSEQUENCES h
~~l On Decenber 10, 1980. Boston Edison Co. received an analysts reoort from the Yankee l~~
.Tl Ato=1c Electric Laboratory which iM2.cated that a reportable concentration of Co-60 l (73.7-
.6 pC1/kg) existed in a mussel sa=ple taken fro = the P11gri= Station discharge
canal outfall area on October 1, 1980. This concentration is in excess of 10 ti=es yl

he lower li=1e of detection at the control station in Marshfield (4.5 pCi/kg).
I 3"'
I
' li a
Sv5 TEM CAUSE CAUSE COMP.
VALVE COCE 000E SUSCOOE COMPONENT COCE SugOODE SU5000E
-l l x i x i@ l x i@ 12 l@ l zl 21 21 zl 21 zl@ l 21@ l zi @
9 10 11 12 12 is 19 20 SECUENTI AL OCCURRENCE REPCRT REVl5 ION g so EVENTvt4R R EPORT NO.
CODE TYPE No.
@ 'a(rmaTu"55'
_18 10 I l-l 10 I 91 of l/l 10141 i Tl 1-1 1 01 21 2:
~~2 24 a~~
~~22 2s~~
~~s sa si 22 I AC*!ON 8U'vef EF8ECT SMUTDowN A*TACHMENT NP R D-4~~
~~RIME COMe.~~
COM*CNEN?
TAKEN ACT'ON CN 8LANT MET *CQ wouR5
$U8viTTic 8CR M a t.
SUP*u ts M4NU8AC UnEA 12 !@lz l@
lz!@
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l 01 01 01 I
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l NI@
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l 21 91 91 E 1
24
~~s a~~
3_
ao ai 42 42 u
4 CAUSE DESCRtpTION AND CORRECr1VE AC 10NS h
'gi The cresence of Co-60 in this dischar2e cinni sa-le is due to crer*-icn ?? t'e i Pilzrim Station. :owever, even if a eersen were re M ractiv - e - e -- ~==a'e
=*
-ke ra:e given in Regulato y Guide 1.109, the annual dose to that person would only be ml l&
-3 10-acou: 2.0x10 mres :o :ne :=tal body (child) and 1.5x
=re= :o the =axi=um
--, ; excosed organ (adult, GE-LLI).
METWCD C8 s AC:Lt*v eis::vEnv ciscovEnv eE5:RiF' TON l
5 A US secwEa oTwEn57ATUS N.A.
l lD l@l Environmental Lab Notification f"Il l E l@ l1 10 10 l@l 3
to
2
,1 44 45 46 3'
I CTtvi'v OONTENT ELE /.5EC :P mELEASE AMOUNT OF ACTIVITY 36 LoCAT1oN QF mELgA3E N.A.
I I
N.A.
e i I z l @ l zl@l 3
tC 11 44 45 3
~~ER$CNNEL EXPOSURES NUMBER TveE DESOAIP'tcN -~~
ia.101010l@lz!@{
N.A.
l 9
1, u
a stm5CNNEL <NJU AIES Nuv8Em O E 50 RIP'10N 2 lo!0101@l s.A.
s 8 9 11 12 La55 OF CA D AM AGE TO 8A03U*v
~~v*E DESC*irTION l2 l~~
N.A.
I 4 3 to NS U Ctw NRC USE ONLV 4
v55p,E m DE5025*TICN N.A.
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~~4.* con~~
I
'I Accendix B - Radioactive Effluents f I
!I I
I I
I I
l I
1E lI
!I 1
B-1
.I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Inforrnstion January - June, 1980 Facilitv Pilgrun Nuclear Power Station Ucensee DPR 35 1.
Reguistacy Umits I
s W
a.
F:ssam and activatam gases
, 4 g
0.25/E 0.10/E h.
lodmes-2 Ci/ Quarter I
Particulates. half-hves>N davs 13(1.8E4Qs + 1.8E5Qv) e 1 c.
d.
bquid efnuents: 10 C1/ Quarter 1.
Masimum Permissible Concentration Piovide the MPCs used m determinmg allowable release rates or cimcentration>.
a.
Fissnin and activation gases:
10 CFR 20 h.
lodmes:
Appendis B c.
Partsculates, half-isves >K days:
Table !!
d.
Uquid ef0uents H.'3 = 1 X 101 mci /mt; all rest.10 CFR 20. Appendix B. Table !!
3.
Average Energy Provide tie average energy (El of the radamuciale mniure m releases of 6ssam and activauon gases. il appheableJ 1st Quarter, MS = 1.028 & RBV = 0.293: 2nd Quarter, MS = 0.660 & RBV = 0.622 4.
Measurements and Approsimations of Total Radioactivity I
Provide the methods used to measure or approsmiate the total radioxtivity m ef0uents and the nwthmis used to determme radumuchde composinon.
a.
F:ssam and activation gases:
c,ti b.
lodmes-g, c.
Particulat es:
^^*IYSI' d.
Uquid ef0uents:
Batch Releases Provide tie followmg information relatmg to batch releases ot radmiactive maienals m hquid and gaseous ef0uent>.
a.
Uquid I.
Number of batch releases-228 2.
Total time penod for hatch releaus-263.50 hrs.
3.
Maximum tinn gnod for a batch relea<e. - 8.92 hrs.
4.
Average time pe mid for batch releases: 1.16 hr.
I 5.
Mmimum time penod fm a hatch release: - O. 25 hr.
6.
Averace stream now dunns penods of release of ef0ueni mio a nommg stream: 1.SIE + 5 G N b.
Gaseous (Not Applicable) 6.
Abnormal Releases I
a.
b.
None I
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I
i I
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I TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASES January - June, 1980 Quarter Quarter Est. Total Unit i
2 Error. %
I A. Fission and activation gases
~~1. Total release Ci 2.69E+2 4.13E+2 3.00E+1 l~~
~~2. Average release rate for period uCi/sec 3.42E+1 5.25E+1~~
~~3. Percent of Technical Specification limit 1.39E-2 1.73E-2 B. Iodines~~
~~1. Totallodine.131 Ci 4 4.12E-3 3.21E-3 2.50E+1 l~~
~~2. Average release rate for period yCi/sec 4 5.24E-4 4.08E-4~~
~~3. Percent of Technical Specification limit 2.06E-1 1.61E-1 C. Particulates~~
~~1. Particulates with half. lives > 8 days Ci 4 3.23E-3 4.79E-3 3.00E+1 l~~
~~2. Average release rate for period gCi/sec 44.11E-4 6.09E-4~~
~~3. Percent of Technical Specification limit 8.77E-2 2.63E-2~~
~~4. Gross alpha radioactivity Ci 4 7.00E-7 3.90E-7 I~~
~~D. Tritium~~
~~1. Total release Ci 3.65E0 6.75E0 3.00E+1 l~~
~~2. Average release rate for period gCi/sec 4.64E-1 8.59E-1 I~~
~~3. Percent of Technical Specification limit I~~
I
, I I
I lg
_3
TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (.1980)
GASEOUS EFFLUENTS - ELEVATED RELEASE January - June, 1980 CONTINUOUS MODE BATCH MODE l Nuclides Released l
Unit l
Quarter l
Quarter l
Quarter l
Quarter l
~~1. Fission gases l~~
krypton-85 Ci 6.35E-4 2.72E-3 l
krypton-85m Ci 5.70E+1 6.95E+1 krypton-87 Ci 2.95E+1 2.62E+1 krypton-88 Ci 1.IlE+2 1.00E+2 xenon-133 Ci 5.41E+1 5.55E+1 xenon 135 Ci 1,54E0 1.20E+1 xenon-135m Ci 1.20E-1 4.55EO I
xenon 138 Ci 3.41EO 7.14E+1 zenon-131m Ci renon 137 Ci xenon-133m Ci Total for period Ci 2.57E+2 3.39E+2
~~2. Iodines iodine-131 Ci 4.5.26E-4 2.73E-3 l~~
iodine-133 Ci 41.38E-5 2.42E-2 iodine-135 Ci 2.83E-2 I
Total for period Ci 45.40E-4 5.52E-2
~~3. Particulates Ci 3.62E-5 8.16E-4 i~~
strontium-89 strontium-90 Ci 5.50E-6 9.71E-6 cesium-l'4 Ci 4.54E-7 I
cesium-137 Ci 2.16E-5 1.94E-5 I
barium lanthanum 140 Ci 1.98E-4 3.25E-3 chromium 51 Ci manganese-54 Ci 3.82E-6 1.08E-5 I
cobalt-58 Ci iron-59 Ci cobalt-60 Ci 4.23E-5 4.07E-5 zine-65 Ci zirconium-niobium 95 Ci cerium-141 Ci cerium 144 Ci 3.42E-5 ruthenium 103 Ci gW ruthenium-106 Ci 1.61E-4 -.
I I
TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT (1980)
GASEOUS EFFLUENTS - GROUND LEVEL RELEASE I
January - June, 1980 CONTINUOUS MODE BATCH MODE Nuclides Reneesed Unit Quarter Quarter Quarter Quarter
~~1. Fission gases krypton-85 Ci 4 3.87E-8 t4.65E-8 l~~
krypton-85m Ci 9.10E-2 1.10E-1 I
krypton-87 Ci 1.52E-1 1.26E0 krypton-88 Ci 2.83E-1 4.62E0 xenon-133 Ci 3.04E-1 8.11E0 I
xenon.135 Ci 1.11E+1 6'.02E+1 xenon-135m Ci zenon-138 Ci Total for period Ci 1.19E+1 7.43E+1 i
~~2. Iodines iodine-131 Ci t 3.59E-3 1 4.76E-4 iodine-133 Ci 2.99E-3 3.05E-3 I~~
~~iodine-135 Ci 4.61E-3 Total for period Ci 41.12E-2 3.53E-3~~
~~3. Particulates strontium-89 Ci 7.00E-5 6.02E-5 strontium 90 Ci 6.21E-7 1.02E-6 cesium 134 Ci 5.70E-6 8.82E-6 cesium 137 Ci 6.75E-5 4.93E-5 I~~
barium-lanthanum-140 Ci 42.35E-3 1.99E4 manganese-54 Ci 2,92E-5 1.10E-5 cobalt-58 Ci 2.39E-6 I
iron-59 Ci cobalt-60 Ci 3.73E-4 1.17E-4 zine-65 Ci 4.68E-6 zirconium-niobium-95 Ci cerium 141 Ci 1.74E-5 l
ruthenium-103 Ci ruthenium-106 Ci I
I 5
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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I
January - June, 1980 I
Quarter Quarter Est. Total Unit 1
2 Error, %
A. Fission and activation products
~~1. Total release (not includmg mtium, Ci noble gases, or alpha) 8.77E-1 5.65E-1 3.00E+1~~
~~2. Average diluted concentration pCi/ml 1.07E-7 2.17E-7 during period~~
~~3. Percent of applicsble limit 8.77E0 5.65EO B. Tritium~~
~~1. Total release Ci 2.59E+1 9.13E0 3.00E+1~~
~~2. Average diluted concentration yCi/mi I~~
~~3.15E-6 3.51E-6 during period~~
~~3. Percent of applicable limit 3.15E+1 3.51E+1 C. Dissolved and entrained gases~~
~~1. Total release Ci 4.53E-3 1.51E-3 4.00E+1 l~~
~~2. Average diluted concentration gCi/ml 5.54E-10 5.81E-10 during period~~
~~3. Percent of applicable limit D. Gross alpha radioactivity I~~
l
~~1. Total release l~~
Ci l41. 94E-4 l49.17E-5 l 4.00E+1 l
E. Volume of waste released (prior liters 2.59E+6 1.78E+6 2.00E+1 to dilution)
F. Volume of dilution water used liters
.60 M 2.00E+1 during period I
I I.
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I TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
LIQUID EFFLUENTS January - June, 1980 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter strontium-89 Ci 1.84E-3 5.62E 4 strontium 90 Ci 5.26E-4 5.31E-4 I
cesium-134 Ci 6.46E-3 2.81E-2 cesium-137 Ci 3.34E-2 9.17E-2 iodine-131 Ci 1.07E-4 7.92E-5 cobalt-58 Ci 7.51E-3 5.14E-3 cobalt-60 Ci 3.36E-1 1.57E-1 I
iron-59 Ci 4.31E-3 zine-65 Ci 2.20E-3 1.01E-3 manganese-54 Ci 3.41E-2 1.39E-2 chromium 51 Ci 1.61E-2 zirconimum-niobium-95 Ci
~~8. 81E-4 1.78E-5 molybdenum 99-2.08E-3 l~~
technetium 99m C
barium lanthanum 140 Ci 6.36E-3 cerium-141 Ci 4.52E-3 l
l 5 iodine-133 Ci 2.35E-4 l 4.77E-5 cerium 144 Ci 5.62E-4 )
1.35E-4 silver 110m Ci iron 55 Ci 2.12E-1 1.87E-1 1
l unidentified l
Ci l
l l 2.08E-1 l 7.95E-2 l
Total for period (above)
Ci 8.77E-1 5.65E-1 xenon-133 Ci 8.85E-4 3.97E-4 xenon-135 Ci 3.66E-3 1.11Ee3 --.
I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information July - December, 1980 Facility Pilgrim Nuclear Power Station Ucenze DPR 35 I
1.
Regulatory Umits Os Ov 0.25/[
0.10/[ i I a.
Fission and naivation gases:
h.
lodmes 2 Ci/ Quarter I
Particulaies. half-hves >h days 13 (1.8E4Qs + 1.8E5Qv) il c.
d.
bquid efnuents: 10 Ci/ Quarter 2.
Masimum Permissible Concentration I
Psovide the MPCs used in determining allowable release rates or concentrations.
a.
Fission and activatism gases:
10 CTR 20 h.
lodmes:
Appendia B c.
Particulates. half-lives >x days:
Tsble 11 d.
bquid ef0uents: H - 3 = 1 X 101 MC1/ml,all eest,10 CFR 20, Appendix B. Table H 3.
Average Energy Provide the average ene'dy (Fi oi ihe radamuchde mniure in release, or fissum and aciivation ga 3rd Quarter, M = 0.631 &RBV = 0.484; 4th Quarter, MS = 0.507 & RBV = 0.283 4.
Measurernents and Appresimations of Total Radioactivity Provide the methods used io measure or appmsimate the total radioactivity in ef0uents and the methods used to determme radionuchde composition.
a.
Fissum and activation gases-g h.
lodmes:
I 1stopie c.
Particulaies:
Analysis d.
bquid ef0uents:
5.
Batch Releases I
Pmvide Ihe following informanon relating to batch releases of radioactive matenals in hquid and gaseous efnuents.
a.
Uquid I.
Number of batch releases: 84 2.
Total tune penod for hatch releases.109.82 hrs.
3.
Maximum time permd for a baich release: - 10.33 hrs.
4.
Average isme perm >d for batch releases 1.31 hrs.
I 5.
M nimum nme penod for a haich release: - 0.33 hrs.
6.
Average stream now dunng penods of release of ef0uent mio a nowing stream: 2.97E+5GPM b.
Gaseous (Not Applicable) 6.
Abnormal Releases
[
None lI I
-2 I
1
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I TABLE 1 A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES July - December, 1980 Quarter Quwter Est. ' otal Unit 3
4 Err,r, %
I A. Fission and activation gases
~~1. Total release Ci 1.02E+4 1.53E+4 2.50F+1 l~~
~~2. Average release rate for period pCi/sec 1.28E+3 1.92E+3~~
~~3. Percent of Technical Specification limit 3.26E-1 3.91E-1 B. Iodines~~
~~1. Totaliodine-131 Ci 2.19E-2 6.27E-2 2.50E+1 l~~
~~2. Average release rate for period uCi/sec 2.76E-3 7.89E-3~~
~~3. Percent of Technical Specification limit 1.10E0 3.14E0 I~~
~~C. Particulates~~
~~1. Particulates with half. lives > 8 days Ci 5.91E-3 5.75E-3 3.00E+1 l~~
~~2. Average release rate for period gCi/sec 7.43E-4 7.23E-4 I~~
~~3. Percent of Technical Specification limit 7.89E-2 1.18E-1~~
~~4. Gross alpha radioactivity Ci~~
<4.19E-7
< 5.92E-1 D. Tritium
~~1. Total release ci 1.40E+1 1.94E+1 3.25E+1 l~~
~~2. Average release rate for period gCi/see 1,76E0 2.43E0~~
~~3. Percent of Technical Specification limit N/A N/A I~~
I I
I - -
TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (.1980 )
GASEOUS EFFLUENTS - ELEVATED RELEASE July - December, 1980
~
I CONTINUOUS MODE BATCH MODE l Nuclides Released l
Unit l
Quarter l
Quarter l
Quarter l
Quarter l
~~1. Fission gases krypton-85 Ci 3.37E-2 2.74E-2 krypton-85m Ci 1.85E+3 2.55F+3 krypton-87 Ci 4:86E+?~~
8.29E+2 krypton-88 Ci 2.29E+3 3.21E+3 I
xenon-133 Ci 5.24E+3 7.77E+3 xenon 135 Ci 1.33E+2 5.33E+2 I
xenon-135m Ci
<8.00E0
< 6.43E0 zenon-138 Ci
< 1 : 85E+1
<1.49E+1 i
zenon-131m Ci zenon-137 Ci xenon-133m Ci 5.87E+1 1.66E+2 Total for period Ci 1.01E+4 1.51E+4 2 Iodines I
iodine-131 Ci 1.57E-2 4.41F ?
iodine-133 Ci 3.ggg_2 4 n7F 7 I
iodine-135 Ci 4.00E-2 4.61E-2 Total for period Ci
~~9. 56E -2 1.31E-1~~
~~3. Particulates strontium-89 Ci 6.98E-4 4.67E-4 strontium-90 Ci 8.21E-6 6.05E-6 cesium-134 Ci cesium-137 Ci 2.01E-5 2.80E-5 lI barium lanthanum-140 Ci 2.47E-3 1.35E-3 l~~
chromium-51 Ci 3.96E-5 manganese-54 Ci 6.84E-5 1.84E-5 cobalt-58 Ci 5.59E-5 3.71E-6 iron-59 Ci 4.90E-5 3.24E-6 cobalt-60 Ci 1.47p_4 g_ gar _g zine-65 Ci zirconium-niobium-95 Ci 2.23E-6 i
cerium-141 Ci cerium-144 Ci 1.92E-5 ruthenium-103 Ci I
ruthenium 106 Ci 3,ogp_g I
I TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
GASEOUS EFFLUENTS-GROUND LEVEL RELEASE July - December, 1980 CONTINUOUS MODE BATCH MODE I
Nuclides Rolessed Unit Quarter l
Quarter l
Qu e Quarter
~~1. Fission gases krypton-85 Ci~~
< p n7c 7
< 5. 59E-6 I
krypton-85m Ci
< 2.06EO
< 1. 68F+1 krypton-87 Ci
<4.26EO
< 3.72E0 krypton-88 Ci
<7.83E0
<5.79E0 zenon 133 Ci 9.64i-0 7 R3F+1 zenon 135 Ci 6.33E+1 1.13E+2 xenon-135m Ci xenon-138 Ci Total for period Ci
< 8.71E+1
< 1. 68E+2
~~2. Iodines iodine-131 Ci 6.21E-3 1.86E-2 iodine-133 Ci 2.52E-2 2.86E-2 iodine-135 Ci 2.88E-2 3.77E-2 Total for period Ci I 6.02E-2 8.49E-2 I~~
3. Particulates strontium-89 Ci 3.46E 4 1.26E-3 strontium-90 Ci 1.44E-6 4.36E-6 cesium-134 Ci 3.08E-6 1.90E-6 cesium-137 Ci 3.72E-5 2.66F I barium-lanthanum-140 Ci 1.41E-3 2.27E-3 manganese-54 Ci 2.31E-5 2.87E-5 cobalt-58 Ci l 1.71E 4 3.49E-6 I
iron-59 Ci l
cobalt-60 Ci l 2.29E 4 1.09E 4
-ame % Chromium-51 Ci j 8.60E-5 5.29E-5 zirconium-niobium-95 Ci l 3.23E-6 cerium-141 Ci l 1.27E-5 3.64E-5 ruthenium-103 Ci l
ruthenium 106 Ci l
I
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TABLE 2A I
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
LIQUID EFFLUENTS SUMMATION OF ALL RELEASES July - December, 1980 Quarter Quarter Est. Total Unit 3
4 Error, %
I A. Fission and activation products
~~1. Total release (not including tritium, Ci noble gases, or alpha) 8.11E-1 4.78E-1 3.00E+1~~
~~2. Average diluted concentration~~
~~'gCi/ml during period 1.53E-7 2.25E-7~~
~~3. Percent of applicable limit 8.11E0 4.78E0 B. Tritium~~
~~1. Total release Ci 3.81E0 1.12E0 3.00E+1~~
~~2. Average dilutM concentration yCi/ml during period 7.20E-7 5.28E-7 I~~
~~3. Percent of applicable limit 7.20E0 5.28E0 C. Dissolved and entrained gases~~
~~1. Total release Ci 4.98E-4 4.00E+1 l~~
I
~~2. Average diluted concentration gCi/ml 9.41E-11 during period~~
~~3. Percent of applicable limit I~~
~~D. Gross alpha radioactivity l~~
~~1. Total release l~~
Ci k 5.64E-5 l<1.85E-5 l 4.00E+1 l
E. Volume of waste released (prior liters to dilution) 6.80E+5 2.69E+5 2.00E+1 F. Volume of dilution water used liters I
during period 5.29E+9 2.12E+9 2.00E+1 I I
I TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
LIQUID EFFLUENTS July - Decenber, 1980 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter strontium-89 Ci 1.25E-2 1.47E-3 strontium 90 Ci 7.62E-4 2.81E-4 I
cesium-134 Ci 3.88E-2 3.61E-2 cesium-137 Ci 2.08E-1 1.98E-1 iodine-131 Ci 5.04E-3 cobalt-58 l
Ci 1.43E-2 8.79E-3 cobalt-60 Ci 1.89E-1 7.28E-2 iron-59 Ci 6.44E-3 8.01E-4 zine-65 Ci 1.83E-3 5.60E-4 j
mangariese-54 Ci 1.73E-2 7.18E-3 chromium-51 Ci 2.47E-2 4.83E-3 zirconimum-niobium-95 Ci 9.33E-6 7.00E-5 molybdenum 99-1.42E-3 9.79E-5 technetium 99m Ci iI barium-lanthanum-140 Ci 3.82E-3 5.76E-4 cerium-141 Ci 2.60E-4 iodine-133 Ci 1.39E-3 I
cerium-144 Ci 5.71E-5 I
silver-110m Ci iron-55 Ci 7.53E-2 8.71E-2 l
unidentified l
Ci l
l l2.10E-1 l5.98E-2 l
Total for period (above)
Ci 8.11E-1 4.78E-1 xenon-133 Ci 1.23E-4 xenon-135 Ci 3.75E-4 I
Accendix C -1979 Soil Survey
~~I i~~
i 1
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i i I I
I s
i
-=--e..
,-----w.-
-,-------w-.
w.--+----.-
I INTRODUCTION In order to comply with Boston Edison's technical specification 4.8 for environmental monitoring of soil, gammag situ spectrometry analyses were performed at the 11 stations listed on Table A during the period from the 25th to 27th of July, 1979.
The gama g situ spectra analyses were generated using the mobile van equipped with the downlooker Ge(L1) detector, its associated electronic equipment and computer software according to Reference 1.
Icn chamber measurements at the 11 stations I
and core sampling at 3 stations were also performed according to Ref erence 1 to augment the g situ measurements. All spectral data obtained is available and on file at the environmental lab. The final tabulated results of the soil analyses are presented in this report.
l I
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c.2
I 1
l I
~
RESULTS I
Tables 1 to 11 were generated for each soil surveillance station to contain the date, counting time of analysis and both exposure rates (pR/hr) and concentrations (pCi/Kg) for natural, fission, f allout andiplant related activation nuclides.
The exposure rates were derived using the exposure rate method in Reference 1.
For the natural emitters, a unif orm distribution throughout the soil was assumed (a/c = 0).
If a nuclide gamma peak was found for the fission, fallout and plant-related nuclides an exponential depth distribution was assumed (a/o =.'206).
If a nuclide peak was not found f or these manmade nuclides, a planar distribution was assumed (s/c = =) f or the apparent exposure rate calculation. The conversion f ac tors used in *.rans-forming the exposure rates to activity concentrations (pC1/Kg) are listed in Table B.
Table B was generated from Tables 8 and 9 of HASL-258, Reference 5.
The data format', standard deviations and LLDs used in Tables 1 to 11 are
~
quoted based on Reference 4.
Table 12 con. pares the gamma in situ result (p R/hr) with the ion chamber measurement (uR/hr) that was obtained at each of the 11 stations. The positive gamma g situ exposure rates are divided into five categories, the exposure rate for the U-238 series, Th-232 series. Cs-137, K-40 and others.
The "other" category. notes other nt clides found positive by the in situ analyses.
If the source term of the "other" nuclides could not be assumed to be soil, then the detector efficiency is unknown for these nuclides and the exposure rates were not reported or included in the gamma g situ exposure rate subtotal.
A sealevel cosmic exposure rate of 3 6uR/hr was added to the subtotal of the positive nuclide exposure rates in order to facilitate the comparison of the
_in situ results to the ion chamber results.
As s h o'.Ti by inspection of Table 12, the gamma i_n_ situ exposure rates were calculated to be greater than the ion chamber measurements at all eleven sites evaluated at eigtit of the sites not directly adjacent or possibly influenced by j
the plant's operation or rad waste storage f acilities, the _in situ :ceasurements
(
were higher by 0.4 to 3uR/hr (or 5% to 37.5% r,reated t' tan the ion chamber results.
!I 1
-e2
~~g ee-e2 = e x 1e I~~
a
I The other three measurement sites were in close proximity to the plant and, as a consequence of the plant's influence, the ion chamber results at these sites were found to be 1.6 to 5.5 times greater than the calculated g situ results.
Tables 13 - 15 present the results obtained when the gamma field measurement of two on-site stations and the control station were compared to laboratory analyses of core samples obtained from the same station.
Only the naturally-occurring radionuclides were compared.
A comparison for the naturally-occurring radionuclides was made between the g situ result (pCi/Kg) and the average of the laboratory ana ses of the core sections by using Equation 1.
% Difference I-X *100
=
X Equation 1.
I = h situ result (pC1/Kg)
X = A+I (pCi/Kg) 2 A = Average laboratory soil results (pri/Kg)
Equation 1 was Jerived using the assumption that the g situ and the laboratory measurement were duplicate analyses.
I All the calculated percent differences listed in Tables 13 - 15 are less than 157..
1 I
l C-4
DISCUSSION I
Data concerning six of the eleven stations will be commented on in this discussion. These six stations either had a high ion chamber result relative to the g situ result, showed positive Co-60, Mn-54 or Cs-134 in the gamma measurement, or had both a high ion chamber measurement and showed Co-60, Mn-54 or Cs-134.
The stations with the relatively high ionization chamber measurements were the Warehouse, Pedestrian Bridge and Overlook Area.
According to Table A, these stations are the closest to the reactor and therefore, the high ion chamber measurements at these sites were probably due to some source other than the soil.
The g situ gamma results at the Warehouse and Pedestrian Bridge showed positive Co-60, Mn-54 or Cs-134.
For the Warehouse and Pedestrian Bridge the source term for the positive Co-60, Mn-54 or Cs-134 was quoted as unknown. Because of these station's relatively high ion chamber measurement with respect to the g situ result and the stations closeness to the reactor, the source term of the positive plant related nuclides was not assumed to be the soil. Since the source ter= is unknown the exposure rates for these nuclides w m not reported. However, the source term of the positive Co-60 or Mn-54 at the Property Line, East B.renkwater. and Clift Rock Area sites was assumed to be the soil. The soil was assumed to be the source term for these stations because of the agreement of the two independent measurements and the distance the sites were f rom the f acility.
l
[
l i
I r
I I
C-5
Table A Soil Surveillance Stations Distance and Direction Station Number
~~Samoline Location from Reactor 00 Warehouse (WS)~~
.03 miles SSE 01 Rocky Hill Road (ER) 0.8 miles SE 03 Rocky Hill Road (WR) 0.3 miles W-WNW I
06 Property Line (PL) 0.34 miles NW 07 Pedestrian Bridge (PB) 0.14 =iles N 08 Overlook Area (OA) 0.03 =iles W 09 East Breakwater (ES) 0.35 miles ESE 10 Cleft Rock Area (CR) 0.9 =iles S 15 Plymouth Center (PC) 4.5 miles W-WNW 17 Manomet Substation (MS) 2.5 miles SE 21 East Weymouth (EW)**
2.3 miles NW*
=0tiained from the air particulate station codes.
+
=* Control Station.
l I
C-6
I 11 Table B Exposure Rate to Concentration Conversion Values i
Nuclide Energy Conversion Conversion Conversien Name (Kev) c/o=0.206 a/c==
n/c=0 (uR/hr/cCi/gm)
(uR/hr/oCi/gm)
(uR/hr/oCi/gm)
Ce-144 133.50 0.00913 0.02229 Ce-141 145.44 0.03709 0.09291 1-131 364.46 0.29314 0.73085 Sb-125 427.88 0.35482 0.88332 Ru-103 497.09 0.41724 1.05107 Ba-140 537.30 0.17021 0.42963 Rh-106 622.00 0.17813 0.45466 Cs-137 661.61 0.55007 1.35915 Zr-95 756.72 0.'75624 1.85287 I
Nb-95 765.80 0.79129 1.94376 Mn-54 834.84 0.89883 2.20063 Co-60 1332.51 3.24207 7.78098 La-140 1596.20 3.22581 7.83693 0.179 K-40 1460.76 Th-232 Average 2.82 U-238 Average 1.82 lIt ll I
l l
I C-7
1 E
1
-n Su a Coui
~~r. Ri_~~
ts le te oun J7/
)
l Locatlon:
Warehonse Statton Number 00 Counting Time: 6000 (see) l
~~nc 1 isle E: pounro Rate Concentration til.:nt I(icat ion (pn/hr)~~
( pC 1/ E.:)
I a.__.________._.--

~~r----~~

Nuclide Ener; Expo;nio 9t anil t ril S t anita ril l
Na:.o
( E e v '.
R.ir..
D..v i it ton I l.D Conc Deeiation I.I.D
{
SE-0) 4E-03 15E-03 2E602 2Et02 7Et02
+
i:e-l '.t.
131.30 Ce-141 l
143.4' l
9E-03 l
4E-03 l13E-03 9E4 01 i 4E101 l
14Et01 l-13l l
3 6 '.. ' o l
-13E-03 l
7E-03 l26E-03 l
-2E101 IE101 1
4E601
~~b-123 l~~
427.di l
3E-02 l
2E-02 l
8E-02 l
3E401 l 3 E4 01 l
9E601 4 9 7. U'.'
l
-2E-03 l
7E-03 l26E-03 l
-2E60 l
7E+0 l
25Et0 i
l j
Rn-iOI j
B.i-L ' 0 l
5 17. 10 l
-20E-03 l
10E-03 l36E-03 j
l 2E401 l
BE101
-5Etol l
604.70 l
l g
j l
l C o- ! j '.
Rii-lon j
622.10 l
2E-02 2E-02 l
7E-02 4Et01 l 4E101 16E401 g
}
? Ca-t '17 ir l
661. ei l l
76E-03 l
7E-03 l 23E-03 l
14E601 ;
IE101 1
4E101 m
Zr "i l
75n. 2 l
-3E-02 l
IE-02 l 4E-02 l -16Et0 6Et0 l
24E10 7h3.30 l
-0.5E-03 l
7E-03 l 24E-03 l
-0.3E60 j
3Et0 13E'10 i
Nh-91 l
l l
3E10 l
llE10
' !n - 3 '+
8 10. %
l 8E-03 1
7E-03 l24E-03
{
4E40 01- >o +
l t lil. )l g
g
{
l l
l l
-:.0 c I l
l '. no. 7.>
j 226E-02 l
3E-02 l 4E-02 l 126Et02 l 2E102 l
2E+02 l.a- !.0 1
1 >"'i. 20
'l
-3E-02 i.
lE-02 j 4E-02
-3E10 t
IE10 6E10 l
~'
SE-02 57EtOI [
2E101 Th-1 Il-l i
160l:-02 l
--l
-l SE-02 l
T l
l 87E-02 48E601 2E101 l
l L -l ;M '"
- -~'
g
~~c. :.ii.:n l it.nl b.iac.' on...1 : an! haselin. cann t. in t he.ic t o.i! po d f enn.1~~
.i.4 4nn!1, ( if
.204) 1 a
' ^ C.i l e 11.i t. il has.! on. l.:'it eil ave rage ( if, 0) fo r Th-21'l t'- ? )H.in.1 s ine l o pi.it ( /.2 = 0) for K '40
+ Unknown Son rci. Tsrm
m M
M M
M M
-m M
M M
M M
ysa t e o r Conn t :M M
M M
M (e C>/79 in Sitn Coun t ing 'teunit s
~
Table 2 Locatinn:
East Rocky 11111 Station Number 01 Counting Time:
6000 (sec)
~~nc I tile Expo;nre R.it e Concentration I~~
filent i t' ic.it ion (alt /h r )
(pC L /E.t) 1 Nuc I i.le Ener-E:moinre
?; t.u n t.i r.1 S t anit.ir el
.:a-o (Kevn R.i t..
Dev i.it ion llo Conc.
Devi.irion I.I.D l
l 10-01 4E-03 OE101 set 01 lbEt01
.e-lii 131.10
-0E-03 Cc-l '. l l
l '. 3..
l 16E-04 l
9E-04 l 32E-04 2Et01 l
IE+01 3Et0L i
o
~
_0,41,_ 0 3 3E_03 h [_03
-0.6E60 t 4E4 0 13Et0 l-131
~
l 7 0. 3 :~~ l Sb-12>
{
127.94 l
18E-03 l
10E-01 l 34E-01 l
2E601 I
IE+01 i
4EIDI I:n - I t ) '
l 4 'l l. 0')
l 2E-01 l
.lE- 0 3 l 12E-03 l
2Et0 t
3E40 l
IlEt0 B.t-l '.0 l
537.10 l
2E-03 l
SE-03 l 18E-03 l 0.4 E+01 l
lE+01 l
4E+01 C s-13.'.
l 60'. 70 ]
l j
l j
l l
f-0.4Et0L l 2E101 l
9E601 l
f b.'2.10 l
-0.2E-02 Rh-lon j
IE-02 4E-02 C ;-l li e l
6ni.nl l
3630-01
(
HE-03 l 16E-03 l 66E401 IEt01 l
IEt01 e
l26E-03 l 0.5E601 3 4E401 l
IEl0L t
l
/.> >... '
l IE-03
]
to Z r
').;
7E-03 Nh fi 70).30 l
170-03 l
4E-01 l14E-03 91.60 l
2E60
{
7E60
~~'8 n - s '.~~
l 11 1 *. !
lEt0 2E40 l
7E40 3 E--01 SE-01 l16E-03 i
l.,,ia.>l l
3E-02 l
IE-02 l 4E-02 3
4Eto j
2Eto l
SEIO j
.u-na l
]Il6Et02 l
2E602 l
2E102 l
l 'o.0..~ n l
20i_02 l
3E-02 l 3E-02
~.O f-l Lt-lio
{
136".l '
l
-6E-02 l
lE-02 l 4E-02
-7060 i
LEIO l
6Et0 Th-l;l-l l
237E-02 SE-02 l
84E401 l
2E601 i
j i
i l
4E-02 l
14 J2 l 78E+01 l
2E401 l
l
__]_
i i
I 1
'C.ticiel.u
. b i s..'.ia
.c.!i..i:n! b.s w i ino count, in t lio.ic t u t ! ;ri!- t'oom!.aus'c'ite: 8' i/
.206)
=
' v.il c a l.it. I h.is.! oc
.ec i c o t eil ave r.e:. (.'
= 0) for rii-2 r!
r-ll8 ami sin.le ;ic al: ( t/ > = 0) for K '.0.
M M
M M
M M
m.
M m
m mm m
m m
m
_In Situ f.ountiny, Resultd Table 3 uate at Lount:
07 9
Location:
West Rocky 11111 Station !!umbe r 03 Counting Time:
6000 (sec) l Nuc 11.le E:q>o n u re R.it e Concentration g
(o /hr)
( pC l /E v.)
n Identification Nu c l i.le Ene r:;
E:qio su r e 9t anil.ird Stindard Nane
( Kevi Rat..
Deviition 1.1.D Conc.
Deviar ton I.I D l
f4E-03
{
l set 01 16EtOI 4Et01 0.8E-03 IE-03 C 0 - l '..'.
131.30 9E-04 l 33E-04 2Et01 IE401 l
4EIDI l '. 3..
l 23E-04 l
Ce-l 'e l l ~ J h '. '. o l
3E-03 l 10E-03 l
-7f'10
{
14Et0 4E40
-5E-03 l-1 11 l
IEt01 l
4Et01 Sb-123 l
427.35 l
-9E-03 10E-03 l36E-03 l -lEt01 4 9 /. 0 '.'
l 2E-03 3E-03 l12E-03 l
2Et0 g
3E40 l
12E+0 l
Ru-103 IEt01 l
5Etol Ba-liO l
337.30 l
-2E-03 l
SE-03 l19E-03 l
-0.*4E40lj
~
C.;- 1 ; '.
l 60'4. 70 l
l j
j Eh-106 l
422.10 j
0.9E-02 l
IE-02
[ 4E-02 2E601 l
3E4 01 9E101 l
6E-03 l17E-03 l
14E601 l
lEtol i
3E601
{cs-13;&
l 661.41 l
77E-03 O Zr-91 l
159.72 l
6E-03 l
8E-03 l29E-03 l
3Et0 l
4Eto l
15Et0 j
Nb-93 l
7t 3. S0 l
0.3E-03 l
SE-03 l17E-03 l 0.2E10 l
2Et0 j
9E60
~~c-- '.~~
I 8 3 '.. %
l
-5E-01 f
SE-03 l 19E-03
-2Et0 2Et0 l
9Et0
_m
.:0 Mi l
1 l il. 5 i j
IE-02 i
LE-02 l
$E-02 IEt0 2Et0 j
6 E+ 0 l '4 nd.. o l
29,0E-02 i,
4E-02 l 3E-02 162E602 l
2E102 l
2E402 j
~
K *. 0 2 '
l I
1346.20 l
0.9E-02 I
IE-02 l 4E-02 IE40 I
IEt0 S E-4 0 l
]
'.a - l '. o ib-!32-l l
292E-02 i
6E-02 l
104Etol 2E601 l
8 i
._______t_.
l l
146E-02 l
4E-02 l 80Et01 l
2E601 l
'-23M I
I I'
I e
4
~~' a l. 'll it.-i: b ried n; ii..tF am! h.ree !'ine coun ts in t. he ar t.u1! !w t' t'onnd.ruur !:r. ( t/~~
.206)
=
l 4:.i l. n l a t..I b.im.1 on s i.;it t ed ie ra.p. (ct / = 0) tor Th-212.. r-f in and sin::lc pc i!. ( e/ = 0) for K
'.O.
M i S M Coi M g ! M ts M M
M M
M abl g g
g g Da g Cg:_g26_g,_
_g Location:
Property Line Starion Number 06 Counting Time 6000 (see)
Nuc I til.?
Exposure Rate Concentration filent i t icat ton (p I' / h r )
(PC L /Ev',)
Nuc 1 f.!e L. r.: r Exposure S t and.ird Standard Na. 3 8Kevi Rar -
Dmeianion I.I B Cone Dev i.it ion LI.D
' i t:e-l '.J.
133.30 l
0.2E-03 IE n3 l
4E-03 0.7El01 set 01 17Etol Ce-l 'e l l
l '4 3. 4 '.
l 0.lE-04 l
9E-04 l33E-04 0.2E601 IEt01 4Et01 l
l-t31 l
141 '. ' '
l lE-03 l
3E-03 l
9E-03 2Et0 4Et0 13E40 Sb '2i l
427.Si 0.9E-03 l
9E-03 l34E-03 0.lE401 l IE601 4EtOI 4 91..M l
-2E-03 l
3 E-O 'l i 12E-03 l
-2Et0 l
3E40 l
IlE40 Ru-103 l
517 10 l
7E-03 l
SE-03
!17E-03 l
2Et01 l IEtol 4E601 ll a '. '. 0 l
Cs - l 3 '.
l 64'4.' O l
l l
l l
l L
l Rh-i0e>
j 622.10 l
-lE-02 l
IE-02 l 4E-02
-3E601 l 2Et01 9Et0!
I n
f, Cs-1 lir
[
66!.41 l
a 155E-03 l
7E-03 l 16E-03 28EiOI lE401 l
3E601
~~7. r-9 3 l~~
7 5'). 72 l
4E-03 7E-03 l 25E-03 l
2Et0 l
4E60 l
13E40 i
';b-s i 7n3.30 l
4E-03 l
4E-03 l15E-03 l
2Et0 l
2EiO l
8EfD I
- -l
. !n- >.
8,..:-
l SE-03 l
4E-03 l 16E-03 l
2E40 2E40 7E60
+
.:o-ni F ~
~~~U~il. i t IEt0 SE60
' ' ~
l l
0.9E-02
~~
~ LE-02 4E-02 l
lEin g
l l
-: - i. 0 "
l Lino.'>
l 208E-02 3E-02 l 3E-02
' ll6E+02 l 2E102 2Et02 l
+
I.a.- I '. 0 l
1.> 4. 2 0 l
-10E-03 10E-03 1 38E-03
-lE60 i
lE+0 l
SEtO 70E601 !
2E401 l
t l
l 196E-02 T h-212 SE-07 i
l
+
L__
E - 21.i l
l 112E-02 j
3E-02 l
61E601
{
2EiO!
l l
t i
i i
I I
.--l b.i. ' oa p. ih ind liaso t ine coints in the.ic t sa ! pr. i!- fo' nil asturin. ( t/
~~t a l. n l it.~~
.2048
=
AfC.ilculated h.i' d on i t;St ed ave rac.e ( c/ = 0) ior Th - 21.'
F-218.ind s ingl.: peak (a/: = 0) for K
'.O.
~
+ Source Term assumed to be soil.
l
U
//9 In S Cout gR ts le te oun Location:
Pedestrinn Bridge Station Number ___
07 Counting Time:
600(4 (sec)
Nuclide E:cposu re Rate Concentration identttfeation (pl:/hr)
( pC L /K.:)
__ _ w
% c t (d..
Energy E::po su r e Standard Standard Na:,e
( Kev)
Rate O. v i.t r ion I.I.O Conc Deviacion i LI.D l
l13E-03 6Ef02 0.9E+02 2E+02 C e - l '. '..
131.30 2E-03 4E-03 Cc-l 'e l l
14 3. R l
-5E-03 3E-03 lllE-03 l
-5Ef01 3E+01 l
12E+01 j
364.46 l
4E-03 6E-03 l20E-03 l
[
6E+0 j HE+0 l
27E+0 1-111 6E-02 g
2E40l!
2 E+ 01 l
7E+01 Sb-123 j
427.84 l
2E-02 2E-02 l
Ru-101 l
497.09 l
-2E-03 6E-03 l 20E-03 l
-2E40 l 5E+0 l
19E60 i
Ha-t'io l
337.10 l
-2E-03 uE-03 l28E-03 l
-0.4E60ll 2E+01 l
6E601 C.;-13a l
604.70 l
l l
IlEf01l 4E101 13E+0!
Rh-loti l
622.10 l
5E-02 2E-02 l
6E-02 10E-03 l 24E-03 l
58Ef01j 2E+01 j
4Et01 Cs-137v l
661.61 l
319E-03 l
n i
g Zr-95 l
750.72 l
-lE-03 l
10E-03
!36E-03 l
-0.5E+0 l 5E4 0 20E+0 Nb-93 I
7h3.50 l
-4E-03 l
6E-03 l22E-03 l
-2E+0 l 3E10 llE40 in-n +
a lz. aa l
l l
Co-90 +
l ITi2.it l
l l
j i
3E-02 l 4E-02 K
'.0 0 l
L a no. 7')
l 218E-02 j
122Ef02 2E+02 2Et02 l
1.a-l a n 1590.20 l
-2E-02 l
IE-02 l SE-02
-2E60 2E+0 l
6Et0 Th
'32' l
l 243E-02 6E-02 86Et01 2Ef01 l
1
'J - 2 3 3 l
129E-02
[
4E-02 71Ef01 2E+01 t
I
[
______i
~~'.i ! c u l it eil bas.d on peak acd baseline coscit.; in the ar r na l peal f ouni! assur.in - ( /.:~~
. 20's )
=
ACalcu !at. d has J or, w.:[ ;hted ave ra.:e (n/a = 0) t'o r l'h-2t2 - !*-2 3S and s i nal.' peal: (a/.: = 0) for K
'.O.
+ Source Term L:nknown.
l i
M M
M M
M M
M M
M m ' m m
e e,7/p e
e Date of Count:
u//
g Sitti Counting Results
.I'21e 6 Locatlon:
Overlook Area Station Number 08 Counting Time:
6000 (sec)
W Nuc1ide Exposure Rate Conecotra:1on l
Ident i t'leat ion (pil/ h r)
(pCi/Kg1 i
Nuclide Ene r ;y E:< po su r e Standaril S t an d.i ril Nane (Kevi Ra r..
Deviation I.I.')
Con.:.
Deviatiein I.I il C e-1 'i.
131. 3f)
-2E-03 2E-03 7E-03 9Et01 10Et01 34Et01 1
Ce-141 l
143.44 j
3E-03 l
2E-03 l 7E-03 3E401 2E601 7E101 6E10 l
21Et0 1-131 l
367. 4.i l
-0. 7 E-0 3 l
4E-03 l15E-03
-lE+0 g
l Sb-ll5 l
427.Si l
-0.lt-02 l
IE-02 l 5E-02 l-0.lE+01 j 2Ef01 6Et0!
j SE-03 j17E-03
-10E40 l
SE10 l
16E+0 Ru-101 l
497.09 l
-llE-03 l
Ila-t '+ 0 l
537,30 l
0.6E-03 l
7E-03 l24E-03 0.2Et01 l 2E+01 i
SE+01 i
Cs-13 '.
l 60a.70 l
l l
l 4E+01 3E+01 llE101 2E-02 l
IE-02 l 5E-02 g
l Rh-106 l
612.10 3
{Ca-1lin j
661.nl l
79E-03 l
6E-03 l18E-03 14E101 IE+0L 3E+01 l
9E-03 l31E-03 l
7E10 SE40 l
16E+0
" Z r-9 5 l
756.72 l
12E-03 76).S0 l
-llE-03 l
SE-03 l 19E-03
-6Eto 3E40 l
10E+0 l
~~h-9 3 l~~
'In - 5 '.
l 3 3 5. t'.
l 2E-03 l
5E-03 l18E-03 l
1E+0 l
2E+0 l
8E+0 j
co i=0 1312 il j
4E-02 l
IE-02 l 4E-02 SE+0 l
2Et0 l
6E40 1440.76 207E-02 3E-02 l 3E-02 ll6E402 l 2E+02 2E402 j
K '066 l
La-l E 15 %.20 2E-02 1E-02 l 4E-02 3Et0 lE+0 l
SE+0 Th-2321 l
264 E--02 6E-02 l
94E+01 2Et01 l
l E-2 3d l
l 153 E-02 4E-02 84E+01 2E+01 l
i l
6 l
l
Calcul ited bas.-d on p c#..m.I ba ;eline conuts in the.ic t ii;i' pe.i! thonal assunin : ( s /.: =.206's etc.ilcu lated bas. d on sel ;Sted ave rac.e (2/o = 0) t'or Th-212 T. L'-238 and sincie peak (q/o = 0) for K '.0
/2 '> N E
nS Cou g
it s ble te
'o ui 6000 Locatlon:
East lireakwater St,ition Number 09 Counting Time:
(sec)
';isc i ide Exposure Rate Concentration Ident it icat ion (p il/ h r )
(pC i /I: :)
Nuctide Ene r ;:-
Expo;ure S t.'.o. la r d Standard N. i n.'
(Kevi Rato 0.viarion
'e
! I.9 C.*nc.
Devlation I.I.l) l l4F.-03 l
3Et01 5C+01 19E601 Ce-l '. 4 133.50 0.6E-03 IE-03 u
Ce-141 l
143.i'.
l 0.2E-03 IE-03 4E-03 0.2E+01 lE+01 4E+01 l
l 3 6 '+. 4 "
l IE-03 3E-03 l10E-03 2E+0 4Et0 l
14E+0 l-131 Sb-123 l
427.3i l
0.91;- 0 2 l
IE-02 l 4E-02 ll IE101 lEtol 4Ef01 Ru-103 l
497.0" l
-7E-03 l
4E-03 l 13E-03 l
-6E+0 l
3E10 l
13E10 l
tia-l 'i O l
l
-2E-03 l
SE-03 l 19E-03 l -0.5E+0!
l IE601 4Et01 i
337.10 Cs-I]4 l
60'4 70 l
l j
l l
l 622.10 Rh-106 2E-02 l
IE-02 l 4E-02 4Et01 3E+01 9E601 g
ag Cs-137*
l 661.61 l
91E-03 l
SE-03 l 15E-Oi. l 365Ein l
10E+0 l
27EfD
~~7. r-9 5 l~~
750.72 l
-0.7E-03 8E-03
}28E-03 l -0.4E60 4E+0 l
15E60 j
f 7b3. id i
IE-03 l
Nb-93 SE-03 l 16E-03 0.6E+0 2E+0 l
8E+0 l
!n-3i l
8 34. M l
-5E-03 l
SE-03 18E-03
-2Eto l 2 E+ 0 l
8E+0 l
.;0-604 IE-02 l 3E-02 l
10E+0 j 3E60 l
9E+0 l
l 1312.31 l
4E-02 l
i K
'.O n
~
l l
l 287E-02 4E-02 l 3E-02 160Et02 2E+02 l'.eiO. 76 2E+02 La-I '.0 l
1596.20 1
-6 E- 02 IE-02 I SE-02
-7E60 lEfD 8
6E40
~I I
I I
i l
256E-02 6E-02 I
91E+01 l 2E+01 l
~l T h - 2 12 "
l l
140E-02 4E-02 77Etol 2E401 C ' 33 "
i i
e
^Calculered based on p..tk and ba.eline counts in r ise act o.i! pe i!- found a.4nr in : h / - =. 206)
M C.ilentated tw;..ul on.tuhted average (<4 /.s
= 0) for Th-212 0-2 3F. anel sir.;:l e peak (c/,) = 0) for K 'io.
a
~~Source Terra assumed to be soll.~~
I
E E
E E
E E
E E
E E
E E
%te I'
~~nun~~
_I_n_ S i tu Coun t ing Re:. a. t 5 Table 8 Location:
Cleft Rock Station Number 10 Counting Time:
6000 (sac) i 1
Nuc1ide E posure Rate Coneentr.1 tion (u /hr)
(pC t /i:g) l i
n
~~1. lent i t icat ton~~
~
l Nuclide Ene r.;.
Exposure Standaril Standard l
Nane (Kev i Ita t e D.viation I.I D Conc.
Dc:via t ion I.I.P
! 5E-04
-4Etoi 4Et01 15E401 Ce-l '* 4 131.3')
-lOE-04 10E-04 3
Cc-141 l
143.s'.
-6E-04 9E-04 l31E-04
-6E40 9E40 33E40 l
1 l
-3E-03 3E-03 l 9E-03
-4E60 4E10 13E+0 I
1-131 l
364.'."
a Sb-125 j
427.83 22E-03 9E-03 l33E-03 3EtO!
IE+01 l
4E601 Ru-103 497.09 l
-3E-03 3E-03 l 12E-03
-3E40 l
3Eto l
12E60 l
Ba-l'40 517. P1 l
-3E-03 SE-03
!180-03
.7E601 IEt01 l
4E40 i
60'. 70 l
l l
l Cs-134 l
Rh-LO6 j
622.lti
.5E-02 IE-02 l 4E-02 l
IEtol 2Et01 9Etol l
C.;- 13 7
~~j 661.6 I~~
134E-03 l
6E-03
!16E-03 l
24Etol h IE+01 l
3E401 g Zr-95 750.72 l
10E-03 l
7E-03 l 26E-03 l
$E+0 4E+d l
14E60 e
l I
8Et0 765.30 l
7E-03 l
4E-03 l 16E-03 l
4E+0 l
2E+0 N b-T, l
19E-03 1
4E-03 l14E-03 l
21Etn SE40 l
16E10 i
-In-3 '.+
8 l '.. i f-Co-60
[
1112.3!
l
. 3EN12 l
IE-02 l5E-02
.3E+0' l
2E+0 l
6Et0 i
< - 10 ?-
l'h0.76 i
278E-02 l
4E-02 l 3E-02 155E+02 l 2E402 2E602 I
_ I 1.a - l '.0 l
1596.2" l
7E-02 IE-02 I 4E-02 9E40 lEto l
SEIO
{
l 97Et01 2E601 l
j Th-212"^
l 274E-02 l
6E-02 l
l 142E-02 4E-02 78Eini 2E401 l
E-2 Id
i l
i I
~~C.ilcul.it ed bawd on peah ed ba:ieline count; in tho ac to.i! pe it-f oinid..4cunine (al1~~
.206)
=
*Ca lcu l a t..! has d or...e t ;ht eil.1ve rage (o/ - = 0) t'o r Th-212.. t*-2 3S.md s ing l e p.ak (q/a = 0) for K
'.0
+ Source Term assumed to be soil.
1
d""
/*-
in Si Coui dRt ts Tahl Location:
Plymoutti Center Stat ion Numl>er 15 counting Time:
6000
('
\\
Nuc ! tile Exposure Rate Concentratton lilent i f icat loti (pi' / lir )
(PC I /E.:)
'Juct(de E ne r g:.-
E:<posos e S t anit a ril S t.ind a r il N.i:e
( Ke@
Rat.
Deviation 1.1.!i Cone.
D.*vtarion 1.1 D l
4Et01 15E401 i
- SE-0 4 10E-04 34E-04 2E601 l
~~e-lia 131. 0 31E ~ 0~~
'TE-04 12 64---- 7EW --
IDEIO l
t l4 3. a; j
-8E-04 l
Ce-1 '. I J
t - 1 11 l
3 6 i. '. "
l
-lE-03 l
3E-03 l 9E-03
-2E60 1
4E60 l
12E40 l
Sh-123 l
l
-4E-01 9E-03 34E-03 l
.5Et01 lEtol I
4E401 I
427 3' f
p.u-103 l
4 9 7. u _'
l 2E-03 3E-03 12E-03 2E6C l
3E40 l
11E40
-2E401 IE101 4E401 ILi-L
~~0 1~~
537.30 l 03 l
5E-03 f18E-03 60'.
70 l
l l
j Ca-135 l
E'-lOh l
622.10 l
.6E-02 IE-02 l 4E-02 l -10401 l
2Etol 9E101 l
n Cs-l l7 ^
6II.61 l
243E-03 l
IlE-03 l 18E-03 44E601 l
IE401 1
30401 os
~~7. r-9 3 159.72 l~~
3E-03 l
.7E-03 l26E-03 l
2E40 l
4E40 l
14E40 i
l Nb 'r 3 1
763. iC' l
80-03 l
4E-03 i 15E-03 4E60 l
2E+0 l
8E60
" - T*
l 8 l '* l '
l 01 l
SE-03 l17E-03
-3Eto 2E60 l
8Et0 1112.31
.9E-02 l
1E-07 i 4E-02 1
-Itto l
2E40 l
6E60 i
.:0-90 l
< - 4 0 "
l 1440 I" l
194E-02 3E-02
! 3E-02 109E402 l
2E602 l
2E602 i
IE*O l
IEt0 l
SE40
[4E-02 Ea-lin l
13 % 2" l
IE-02
.l IL-02 Ih-I I I" l
l 25HE-02 l
6E-02 I
9tE601 l
2E401 l
-i.
1------
L-233 '
l
~
[
4E-02 84E+ 01 l
2E401 l
l 154E-02
~!
~~t i
i
~~
i i
a i cul tt.. : bavd on ; ah and b.iseline counts in the actu.i! pe il-f ound autir in T" /. =.2046 "Ca lcu !.it.:il has si on. i; it eil.ive ra ;e ' (u/ - - 0) t or Th-2 62 f. L'-2 3 3 anni single peak (u/ = 0) for R
0.
~
L
,P W
W me Mu' m -. m > g _ g _ g e
Slt ount Res s
Counting Time:
6000 (se )
Locatlon: Honomet Substatton Station Number 17 Concentration Erposuro Rate Nuc 1 tile (PC 1/l*:.0 (p P /lj r)
I. lent i f icat ion Standard Standard Conc Deviation I.I D luclide Enerr-Exnosure
!U t e Deviation I.l _D
_ Kevi
(
lE-03 4E-03
-2E401 SE401 16E401 Na n..
CO-1 ** 4 133.50
-0.4E-03 i
143.i1 l
-22E-04 9E-04 l 325-04
-24E+0 10E+0 34E+0
_l I
Ce-l'+ L j
3E-03 l
10E-03
-1E+0 l 4E+0 l
13E40 l-131 l
3 6 '.. '" '
I
-0.7E-03
)
0.6E+01 l IE+01 l
4E+01 8
427.83 l
6E-03 10E-03 l 36E-03 l
Sb-123 l
497.09 l
-0.7E-01 l
3E-03 l 13E-03
-0.7E+0 l
3E+0 l
12E40 Ru-103 l
Ba-t'.0 l
337.30 l
SE-03 SE-03 18E-03 l
IE+0! l IE+01 l
4E401 l
60i. 0 j
l l
l
~
C.;-135 l
Rh-loo g
l__
-0.2E-02 IE-02
]
4E-02
-0.5E+01 l 3E+01 10E+01 l
622.10 BE-03 l 18E-03 61E+011 2E+01 l
3E+01
[
n 661.61 j
336E-03 f
_' Cs-137*
l
~~7. r-9 5 l~~
75n.72 l
SE-03 l
8E-03 l 28E-03 l
3E+0 l 4E+0 l
15Et0 763.3,0 l
7E-03 l
4E-03 l 16E-03 l
4E40 l 2E+0 l
8E+0 l
Nh-93 l
n-31 l
3 3 '*. %
i 14E-03 l
SE-03
! 17E-03 l
6E40 !
2E+0 7E40 Co-ou l
1132.51 l
IE-02 l
1E-02 SE-02 l
IE+0 l 2E+0 l
6E+0 1*.n0.
o l
293E-02 4E-02 l
3E-02 l
164E+02l 2E+02 l
2E402 i
f f
s-404
!.a-140 1596.2')
l 29 E-02 l
10E-03 34E-03 1
_l 1 E+ 0 l
4E40 4E+0 Th-212' l
l 255 E-02 l
6E-02 I
91E+01!
2E401 l
72E+01 2E401 l
l l
131E-02 j
4E-02 C-133 "
i i
~~Ca l. ul at ed t,.i:;ed o:: p..ah and leaseline counti in the artua! p.'at found assuriino (-'~~
=
'06) for K
'0 for Th-212 !. I'-ll3 anil sincic peak (a/a = 0)
'
~~Ca lc u l.i t.:d b.i+ J.m w.; i c t ed a ve rm;e (n/a = 0) l t~~
E E
E E
E We W g
gt go g, g: ' 'g, g,
L
.4 Si out 21 Counting Time:
6000
(.
ci East Weymoutli Stition Number Locatlon:
.(.
Q-I Concent r.it ion 1
E po ;u r.'
!'a t e i
"nc ! i.l.-
(PC i ! E.' )
L i' '!i r 7 f
~~11. it if tcat ion S '..toda r d i~~
I Nuciide Ener;-
E:-:po.u r e St it d ird (Kev' t' i 0.' e t i r i o i 1.I !)
1 Co n..
Dc"i it wn I.l i' SE+01 l
17E+0i i
.i..
IE-03 l 4E-03
-2E+01 i
l
-0.5E-03 l
l 131. G l
Ce - 1 17.
Co - L '.1 l
113. '
l 4E-04 l
9E-04 l33E-04 l 0.5E+01 i
IE+01 l
4E+01 i
1 f
3E-03 1
3E-03 1 10E-03 l
4E60 1
4E+0 j
13E+0!
T-131 l
Jo.
'27 ;'
IE-02 l
IE-02 4E-02 l
IE401 IE+01 i
4E+01 Sb-ili j
+
19. W-I
-0.8E-03 i
4E-03
! 13E-03 l-0. 7 E + 0 1
3E+0 l
12E+0 Ru-Lu3 l
l SE-01 l 19E-03 l
-2E+01 I
IE+01 l
4E+01 h-lio j
517.34 i
_7g_o)
C;-131 l
60 i. its i
l l
l j
j ull.id 3E-02 l
IE-02 l 4E-02 l
7E+01 l
3E+01 l
9E+01 Rii-lou ool.6l i
SLE-02 l
IE-02 2E-02 l 93E+0!
2E+01 i
4E401 C s - l 3.~ ~
l g C r ',' ;
)
759.Il I
-9E-03 i
8E-03
! 29E-03 l
-5E+0 l
4E+0 j
16E+0 i
~~ib- ! )~~
l 7ui.3d l
8E-03 i
SE-03 l17E-03 l
4E+0 l
2E+0 i
8E+0 8E+0 3 51. !.
IE-03
$E-03
{18E-03 l0.5E+0 2E40 "n-i.
SE-02 1 0.6E+0 2E+0 l
6E+0 e
10-90 l
1i12.ii 0.5E-02 IE-02 i
t he. : :
317E-02 4E-02 l 3E-02 l 177E+02
{
2E+02
}l 2E+02
<- iF g
I OE-02 l
IE-02 i 4E-02 l
OE+0 l
IE+0 i
SE+0 E. - 1 o 13 %. 2 '
1 2E+01 El-I'-
)
j 262E-02 l
6E-02 j 93E+01 79Es01 j
2E+01 i
{
4E-02 143E-02 g
L-I $
l
.~
1 e
l e ;elin - ety n _ i in t in-.ic i e ' m i'- ' 0'i:t I.t i r e-f re - I#
. 2!)6 -
r ii ile-^
b.i is ' i s r.
. 3
' 21 '. and :s in ! s ; sk (s/: = 0) for <
'A.
f C.t ; ::it-?d ii.c: I or. e : t.: :
".: rm'
('
= 0) t'or th-212 I
]
d a
a o
t n
m m
4u m
m N
3o a
a 4
1f g
g 0
m 4
6 1
4 8
0 0
0 0
0 0
0 0
0 0
0 0
se v
v n
u 7
3 5
1 3
1 P
e U s
(e Cm g
Kd T s
s 0
0 0
0 0
0 0
o 0
0 0
0 0
nI a
a 6
0 -
0
~~3 7oEcT 3u 6 -~~
1 1
g n
01 s
0s lrdaE n
d n
e 6ka l
ri i
t a
e gk0uVa n
o t
s ks e
o i
o Ce o
o p
p i
t N
w oe O
td 4d co t r ar 2
4a ah t h 1
5m 6k ri 5 n r
9 2
4 3
8 0
7 0
0 6
7 m
a es u u
t /
2 S/
2 6
6 8
1 3
9 5
r 4
7 1
SR u
9 0
0 6
1 1
0 2
0 5
3 8
8 1
2 0
2 7
3 0 8 na oe ve n o 1
1 1
Hg Cpob r f
{
i u
)
j
)
_a 1
df e
t f
)
)
3 i
g 4
6 1
4 8
4 6 1
4 1
0 0
0, 0
0 8
4 6
1 4
8 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
1 1 o
0 0
0 0
0 0
2 o
0 0
0 0
0 91 g3 0l 0
n n
o n
o i) o i
a r_
t i
t t'
ar ti t
gS/
ar t h S/
th S/
R 3
2 1
7 3
6 4
3 R
7 u
1 7
6 2
8 0
6 u
0 6
9 7
4 4
9 0
9 6
00 4
5 0
8 0
9 6
6 1
4 6
5 R
1 2
0 3
7 3
3 8
D 3
6 3
0 9
3 1
2 0
2 7
3 1E 1
2 0
2 0
1 g
1 b*
e 46 1
4 8
m 4
6 1
3 8
0 0
00 0
0 M
0 0
0 0
0 0
4 5
1 4
7 0
0 0
0 0
0 0
0 0
8o 0
0 0
0 0
1 7
o 1 -
0 0
0 0
0 01 1
e 0l n
M n
o l
n o
i M
o i
t i'
t ar t
ar S f}
t ar th a
t h S/
R h
S/
R e
u 1
5 4
3 3
6 0
7 R
p E.
3 4
8 7
1 1
9 3
5 3
5 6
0 0,
3 6
9 2
H 1
7 6
7 2
1 2
0 2
7 3
g 8 3
0 2
6
~~8. ~8 4~~
3 3
1 2
0 2
6 3
9 6
g 9
1 1
2 0
2 6
3 N
~
i 4
6 1
3 7
4 6
1 3
8 0
0 0
0 0
l i
5 5
1 3
8 0
0 0
0 0
0 0
0 0
0 o
0 -
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 U
o 0
5 l 71 1
t 01 0
n o
n o
n o
1 i'
E o
i t
i t
a r 4
8 4
4 0
1 3 6 9,
1 th 9
3 2
8 2
t h t
ar 5
5 2
4 2
6 8
~~0. S !~~
2 9
ar 3
1 7
0 8
6 1
2 0
2 6
3 9
0 1
1 2
0 1
6 3
' 9 8
R.
4 0 S/
t h 2
c 8
6 a
S/
8 6
0, R
a 3
p Ru 0
1 0
2 4
3 8
6 p
4
~
r r
e r
e b
m 2
e b
l 1
b l
m a
a l
m a
a s
t c
h 2
7 i
l C
8 3
3 r
o i
l C
C h
2 7
s t
c h
a a
t a
3 2
1 0
e t
m a
3 2
1 0
e t
m a
r o I
l C
8 3
3 r
o s,t 2
7 t
n 2
4 h
b s
t n
a 8
3 3
t n
2 4
h h l h
S t
u o
o o
e,ah T
3 2
1 0
u o
o h
S t
u f I_
U T
C K
o S
C T
I o
o i
h 2
4 T
U T
U K O
S
(
h S
t 0
T C
K O sS C
T I
~
nh I
E E
E E
E E
E E
E E
E W
E O
E E
E E
E COMPARISON OF 1.ABORATORY SOIL RESUI.TS vs. IN SITU COUNTING RifSUI.TS Table 13:
Station Number:
n7 1.ocation:
Pedestr ian Bridste Positive Laboratory Soll Results Nuclide (pC1/kg) Wet In-Situ Concentr tion Identification (pCi/kg) y Core Depth
?!uclide Energy Name (kev) 0-2" 2-4" 4-6" Average
~~Difference Ce-144 133.50~~
(-713)Et01
(-517) Et01
(.912) E+02 Cc-141 145.44 (511)Et01
(.215)E401
(-Si3)Ef 01 1-131 346.46
(. 3F2)E+02 (062)El03 (618)E40 Sb-125 427.88
(-li2)Et01 (2+ 3) Et 01 (212) E+01 Ru-103 497.09
(.611)Et01 (413)E601
(-2+5)E+0
~'
Ba-140" 537.30 Cs-134 604.70 Rh-106 622.10
(-4+ 6) E+0i (011) E+ 02 (11+4)Et01 Cs-137 661.61 (320110)E+0 (711) Et01 (5812)E+01 o
Zr-95 756.72 (312)E+01
(-114)E+01
(.515)E+0 Nb-95 765.80 Sin-54 834.84 (6 F 7) E+ 0
(-Itl)E+01 (37+7)E+0*
d Co-60 1332.51 (45 + 8) E+0 (012)Et01
( 316 49)E+ 0 K-40 1460.76 (10912)Et02 (13414) E+02 (122il8)E402 (12212)E+02 0%
La-140a 1596.20 b
b b
Ih-232 (6713) E+0l (94t6)Et01 (81119)E+0l (86t2)E+01
+3%
U-238 (5312) Et01 (5713)E+01c (5513 ) E+01c
( 7112) E+01
+13%
C The laboratory and In-Situ computation analysis are dif ferent for these nuclides (see Ref erence 2).
This calculation is based on the 911 Kev peak area.
~~This calculation is based on the 609 Key peak area.~~
Assuming a planar source the Co-60 concentration = (9913)E+0 pCi/kg.
(11+2)E+0 pC1/kg.
[ Assuming a planar source the Mn-54 concentration =
The laboratory and In Situ computation analysis are different for this nuclide (see Reference 3).
~~The standard deviation is the 1-sigma deviation of the data.~~
l
W W
W W
W W
W W
W
~m W
W W
W W
W W
W W
Table 14:
IN SITU COUidTING RESULTS COMPARISON OF LABORATORY SOIL RI'.SULTS vs.
Station Number:
08 t.oca t ion :._ Overlook Area Laboratory Soil Results In-Situ Conc r ion Nuclide (pC1/kg) Wet (pCi/ks;)
7 Identification Core Gentli Difforence Nuclide Energy 2-4" 4-6" Average
~~0-2" Name (kev)~~
(9110)Et01 Ce-144 133.50 (4t6)Etol
(-2217) E101 (616)Et01 (312)E401 Ce-141 145.44
(-li2) E t01 (414)Et01
( 313) Et01
(-li6)Et0 (514)EiO2
(.812)E102 L-131 346.46 (211)Et02 Sb-125 427.88 (213) E101 (454)E101 (214) Et01
(-0. li2) EOl
(-lo t S) EO (2+2)EiOI Ru-103 497.09
(.412)E401 (712)Et01 na-140^
537.30 Cs-134 604./0 (413) E101 622.10
(.7tt)Et02
(.911) Et 02 (711)Et02
" Cs-137 661.61 (Ili2)E601 (1412)E401 (1212)Et01 (1411)Et01
? Rh-106 ru (214) E601
(-213)Etol (715)Et0 Zr-95 756.72 (312)Et01 Nb-95 765.80 L
Sin-54 834.84 (2il)Et01
(.712)Et01
(-lil)E601 (li2)Et0 (512)Et0 Co-60 1332.51
(.611)Et01
(.412)E401 (012)Et01
+4%
K-40 1460.76 (10713)E402 (10115) E102 (ll214)Et02 (10716)Et02 (11612) E402 b
b
+2%
La-140 1596.20 (9666)E40lb (78t?)Et0lb (10017)E10l (91112)Et01 (9412} E401 U-238 (6613) E t01 (7114)Et01 (10316)E601 (HJ_20)E101 (84 &2) E401
+2%
Th-232 c
c C
C f or these nuclides (see Ref erence 2 and 3).
"The laboratory and in Situ computation analysis are different bThis calculation is based on the 911 key peak area.
cThis calculation is based on the 609 Kev peak area.
for this nuclide (see Reference 3).
f laboratory and in Situ computation analysis are different The
~~The standard deviation is the 1-sigma deviat ion of the data.~~
I
W W
W W
W W
W W
W W
W e
m W
W W
W W
W Table 15:
COMPARISON OF LABORATORY SOIL RI: SUI.TS vs. IN ">ITU ColiNTING REST *LTS Station Number:
21 Location:
East fle_ymontji Positive Nuclide Laboratory Soit Results g,g Identification (pCi/kg) tJet In-Situ Concentration (PCi/LC) a
'!uclide Energy C_o_re Deigh Name (Kev) 0-2" 2-4" 4-6" Average Difference Ce-14 4 133.50 (216)Et01
(-215) Ef 01 Cc-141 145.44
(-444)E101
(.511) E401 t-131 346.46
(-615) E402 (4+4)E40 Sb-125 427.88 (613)Et01 (lil)Et01 Ru-103 497.09
(. 313)Et01
(~. 713) E10 Ba-140 537.30 Cs-134 604.70 Rh-106 622.10
(. 311) E+ 02
( 713) E401 m
Cs-137 661.61 (12713)E101 (9312)Ef 01 Zr-93 756.72 (414) Et01
(-514)E10 Nb-95*
765.80 1
I Mn-54 834.34
(. 811) E+ 01
(.512)E40 Ce-50 1332.51
(.112)Et01
(. 612) E+0 K-40 1460.76
-( 15615) E+ 02 (17712) E402
+ 6 7.
U-140" 1596.20 Th-232
( 704_6) E+ 01 (9312) E101
+14%
h U.'38 (6414)Et01 (7912)EiOI
+10%
C The laboratory and In-Situ computat ion analysis are dif ferent for these nuclides (see ref erences 2 and 3).
a b1his calculation is based on the 911 KcV peak area.
"This calculation is based on the 609 kev peak area.
The laboratory and in Situ computation analysis are different for this nuclide (see Reference 3).
f
E I
Appendix 0 - Radiological Environmental Monitoring Program I
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~ " * " " ~ ' *
~~APPENDIX D I~~
~~t. 8.D Environmental Monitoring Program~~
~
~
~
An environmental monitoring program shall be conducted as follows:
Environmental samples shall be selected and analyzed according to 1.
I Table 4.8.1 at the locations described in Tables 4.8.2 and 4.8.3 and shown in Figures 4.8.1, 4.8.2 and 4.8.3.
2.
Analytical techniques used shall be such that the detection capabilities I
in Table 4.8.4 are achieved.
A census of gardens producing fresh leafy vegetables for human consump-3.
g tion (e.g., lettuce, cpinach, etc.) shall be conducted near the end of g
the growing season to determine or verify the location of the garden (available for sampling) yielding the highest calculated thyroid dose.
This census is limited to gardens having an area of 500 square feet or I
more and shall be conducted under the following conditions as necessary to meet the above requirement:
Within a 1-mile radius of the plant site, enumeration by a door-to-a.
door, or equivalent counting technique.
If no milk-producing animals are located in the vicinity of the I
site, as determined by item 4 below, the census describsd in item b.
3a above shall be extended to a distance of 5 miles from the site.
i If the census indicates the existence of a garden at a location yielding a calculated thyroid dose greater than that from the previously sampled garden, the new location shall replace the garden previously having the Also, any location from which maximum calculated iodine concentration.
I 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 I
available at that location.
A census of animals producing milk for human consumption shall be conducted 4.
at or near the middle of the grazing season to determine or verify the I
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:
Within a 1-mile radius from the plant se e or within the 15 mrem /yr a.
isodose line, whichever is larger, enusc.ation by a door-to-door or
. equivalent, counting technique.
Within a 5-mile radius for cows and for goats, enumeration derived b.
from referenced information from county agricultural agents or other I
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 sampled I
animals, the new location shall be added to the surveillance program 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
,n m
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1 1
lance program as long as the NRC is notified in writing, co coon ca or milk I
practicable, that milk-producing animals are no longer present, that location.
samples are no longer available-at l
Deviations are permitted from the required sampling 5.
i In the ability or to malfunction of automatic sampling equipment.
h ll be made event of equipment malfunction, every reasonable effort s a ampling to complete corrective action prior to' the end of the next sAn I
period.
be explained in the annual report.
Detailed written procedures, including applicable check lists and instructions, shall be prepared and followed for all activities 6.
involved in carrying out the environmental monitoring program.
Procedures shall include sampling, data r'ecording and s I
taken when anomalous measurements are discovered.
Procedures shall be prepared for insuring the quality of programThese' procedures results, including analytical measurements.
identify the responsible organizations, include purchased services include indeoendent audits and include systems I
(e.a., contractual lab),
(such as participation in IAEA and/or NBS intercalibration exercisescont and submission of " blind" cuality contractors)l to identify and correct deficiencies, investigate anomalous I
or suspect results, and review and evaluate program results and reports.
I Environmental Monitoring Proeram BASES 3.8.D and 4.8.D An Environmental radiological monitoring program is conducted to verify i
aterials.
the adequacy of in-plant controls on the release of radioact ve m The program is designed to detect radioactivity concentrations which cou g,
result in radiation doses to individuals not exceeding the levels set g
forth in 10CFR50 Appendix I.
Calculational Models An example of this is the detection of I-131 in milk.(Regul llirem-to of 3.5 pCi I-131 per liter milk would result in a dose of 15 mi
~
Allowing for an the thyroid of an infant consuming that milk for a year.
I between open grazing season of six months, and a maximum of two half-lives I
time of sampling must event and sampling, the lower limit of detection at be 2 pCi/l (3.5 x 12/6 x 1/4 = 1.8).
A supplemental monitoring program for sediments and This a tesult of an agreement with the Massachusetts Wildlife Federation.
. 3 i
supplemental program is designed to provide informat l g later verify the adequacy (or, alternatively, to provide a basis forAs part of the modifications) of the long-term marine sampling schedules.
I ll be supplemental program, analysis of mussels for isotopes of plutonium wi l
dible performed if radiocesium activity should exceed 200 pCi/Kgm in the e I
portions.
~~supplemental provision E _ __-._ _~~
_. - - -. ~
D-2 l
I The 200 pCi/Kgm radiocesium " action leval" is beced on ecleulctions which if radiocesium from plant releases reached this level, I
plutonium could possibly appear at levels of potential interest.*
showed that The calculations also showed that the dose delivered from these levels of plutonium would not be a significant portion of the total dose attributable I
to liquid effluents.
The program was also designed to be consistent, wherever applicable with The following Regulatory Guide 4.8 (Issued for comment December 1975).
I exceptions to the generic recommendations stated in Regulatory Guide 4.8 are justified due to site specific considerations:
The required detection capability for I-131 in milk is 1.
twice the value suggested in Regulatory Guide 4.8.
The justi-ataut fication for the higher value is presented in the second paragraph This is a conservative estimate of the capability I
of the milk surveillance program to detect concentrations at the of this section.
appropriate annual dose level since the annual dose is proportional to the annual average concentration in milk. The detection limit for a I
group of samples is less than that for a single sample and is inversely The conser-proportional to the square root of the number of samples.
vatism in this case is approximately n[ll', or about a factor of 3.
I Air particulates are not analyzed for raiiostrontium.
2.
This is The program instead calls for this analysis in milk samples.
justified because the air-cow-milk exposure pathway can be better mon-I itored at Pilgrim after the very low level releases of radiostrontium are reconcentrated in cow's milk (Ref. 1).
Soils and sediments are not routinely analyzed for Sr-90, but rather 3.
The rationale behind this the analysis is done on a contingency basis.
is that Sr-90 vill not contribute to long-term radionuclide buildup
==til the =or
= bund==t s==== e=1ttins==ctide= =vv==r in r=2=tiv 27
-5 Both Items 2 and 3 reflect the fact that in 3b large concentrations.
years of operation, Pilgrim Station liquid releases of Sr-90 have 5
amounted to only 1/1000 of the Sr-90 inventory in Cape Cod Bay water
.g (fr = weapons testing fallout) and about 4/1000,000 of the direct deposi-Also, gaseous releases of Sr-90 have been only 1/100,000 5
tion on the Bay.
of the terrestrial Sr-90 inventory within five miles of the station (Ref. 1).
Surveys are conducted annually, if necessary, to determine appropriate 4.
locations for sampling of leafy vegetables and milk. The objective of these surveys is to ensure that the environmental samples are represen-l tat!ve of realistic food chain pathways, considering local conditions.
l Results of the monitoring program will be used as " benchmarks" to verify l
calculational models used to predict the consequences of effluent releases The models can then be employed to predict doses from the station.
5 attributable to radiat! ion deposition at any other location of interest.
g The combination of monitoring results and calculations al model predictions is a practical method of demonstrating compliance with 10CFR50 Appendix I.
This approach does not require (nor is it always practical) that environ-I mental media always be sampled from the " worst case" locations: although sensitivity of the monitoring results might be improved by sampling from locations which are reasonably close to " worst case" conditions.
in rcasurable quantities having a potential dose (human food chain)
I
~~significance comparable to other nuclides if present at their detection limits.~~
I
__D-3_.~.
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,y
I Verification of the appropriate milk sampling locations on an annual basis is satisfactory as there are very few locations suitable for the I
grazing of dairy herds in the vicinity of the plant (Ref. 2).
This situation makes it unlikely the location of the nearest dairy herd (3.5 miles-W) will change.
g 5.
Annual sampling of beef forage (in place of beef) is adequate because beef cattle are not raised commercially in the vicinity of tha site.
However, cairy cows from the Plymouth County Farm are periodically sold for beef. Feed (hay) from this location will be sampled to mmitor this f
potential pathway for ingestion of radioactivity. If beef cattle feeding on local forage are found at locations closer to the site, forage samples from the closer location will replace the sample from the County Farm.
6.
Goundwater flow at the plant site is into Cape Cod Bay; there. fore, I
terrestrial monitoring of groundwater is not included in this program.
7.
Poultry sampling is not performed because poultry in Plymouth County I
feed almost exclusively on imported grain and are usually raised under shelter.
8.
Field gamma isotopic surveys are conducted to monitor radioactivity in
, I soil in lieu of laboratory analysis of soil samples. The technique has several advantages over laboratory analysis. First, analysis can be l
performed on the same plot of land from survey to survey, and radio-activity build-up at the location can be accurately determined. Secondly, gamma exposu:'a rate is determined directly from this technique: hence compliance with 10CFR50 Appendix I levels can be investigated directly rather than itdirectly through soil sampling.
I
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~~~
~~References:~~
I, Wrenn, M.E., " Review of Sr-90 Releases from Pilgrim 1 Nuclear Plant and 1.
a Comparison with Extant Environmental Levels", 1976.
2.
Pilgrim Station Unit #2 PSAR, Appendix 11F, pp. 11FC-11 and 11A, amended June 15, 1976.
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I TABLE 4.8.1 1
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM 1
1 1
I 4
Locations i Exposure Pathway (Direction-Distance)
Sampling and Type and frequency i
or Sample Type from Reactor Collection Frequency of Analysis l \\
~~AIRBORNE i~~
i, Particulates 11 (see Table 4.8.2)
Continuous sampling over Gross beta radioactivity at I
one week least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter filter change. (a) Quarterly composite (by location) for gansna isotopic. (b) i i
?
Radiciodine 11 (see Table 4.8.2)
Continuous sampling with Analyzu weekly for 1-131 canister collection weekly i
Soil 11 (see Table 4.8.2)
Once per three years Field ganza isotopic. (c) r 20 (see Table 4.8.3)
Quarterly Gamma exposure quarterly.
1 DIRECT l
Plymouth Beach and Priscilla/ White llorse Beach Annually (Spring)
Ganma exposure survey.
l WATERBORNE Discharge Canal ce tinuous coaposit sample Ganina isotopic (b) monthly; Weekly grab sample and composite for 11-3 j
Bartlett Pond (SE-1.7 mi.)(d) Weekly grab sample analysis quarterly. (c).
Powder Point (NHW-7.8 mi.)
t AQUATIC
,' Shellfish Discharge outfall Quarterly (atapproximate.
Gamma isotopic (b); also see l
Manomet Pt.
-~~3-month intervals) note (f).
~~Duxbury Bay i~~
t Plymouth or Kingston liarbor Harshfield (d)
,i f
Note (f) and beach surveys are supplemental provision.
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TABLE 4.8.1 (Cont'd) locations Exposure Pathway (Direction-Distance)
Sampling and Type and Frequency l
cr Sample Type from Reactor Collection Frequency of Analysis Irish Moss Discharge outfall Semi-annually Gamma isotopic (b)
Hanomet Pt.
t' E111sv111e (d)
Lobster Vicinity of discharge Four times per season Gamma isotopic D) on edible portions.
gointffshore(d)
Once per season i
Vicinity of discharge Quarterly, Groups I and II (e)
Gama isotopic (h) en
{
Fish point In season, Groups III and IV (e) edible portions (t)
Offshore (d)
Annually, each group Sediments Rocky Point Semi-annually Gama isotopic (b) (c),
Plymouth Harbor see also note (g)
~~g Duxbury Bay Plymouth Beach e,~~
4, Manomet Pt.
Marshfield (d)
INGESTION (Terrestrial)
Milk Plymouth County Farm Semi-monthly during periods when Gama isotopic (b)
Sr-89, j
(W-3.5 mi.)(h); Whitman animals 'are on pasture, other-90 monthly; radiofodine Farm (NW-21 mi.) (d) wise monthly analysis all samples.
Cranberries Manomet Pt. Bog At time of harvest Gama isotopic (b) on j
j (SE-2.6 mi.)
edible portions.
Bartlett Rd. Bog (SSE/S-2 8 mi.)
Pine St. Bog (WNW-17 mi.) (d)
' Note (g) is supplemental provision l
e
t l
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g g
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i TABLE 4.8.1 j
(Cont'd) t Locations i
Exposure Pathway (Direction-Distance)
Sampling and Type and Frequency l
or Sample Type from Reactor Collection Frequency of Analysis i
i, 4
i uberous and Karbott Farm (SSE-2.0 mi.)(h) At time of harvest Gama isotopic (b) i T
{
l green leafy Bridgewater Fann on edible portions.
i vegetables (W-20 mi.) (d)
' Bref Forage Plymouth County Fann Annually Gamma isotopic (b) 1 3
j (W-3.5 mi.) (h) l j
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I Notes (a) If gross beta radioactivity is greater than 10 times the control value, gamma isotopic will be performed on the sample.
I (b) Cama isotopic means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
(c) If integrated gamma activity (less K-40) is greater than 10 times the control value (less K-40), strontium-90 analysis vill be performed on the sample.
(d) Indicates control location.
l (e) Fish analyses will be performed on a minimum of 2 sub-samples, consisting of approximately 400 grams each from each of the following groups:
I I.
Bottom Oriented II. NearBottom III. Anadromous IV. Coastal Distribution Migratory Winter flounder Tautog Alevife Bluefish Yellowtail flounder Cunner Rainbow smelt Atlantic herring Atlantic cod Striped bass Atlantic menhaden I
Pollock Atlantic mackerel Hakes I
(f)*
Mussel samples from four locations (immediate vicinity of discharge outfall, Manomet Pr., Plymouth or Kingston Harbor, and Green Harbor in Marshfield)
'will be analyzed quarterly as follows:
One kilogram vet weight of mussel bodies, including fluid within shells vill
~~be collected. Bodies will be reduced in volume by drying at about 1000C.~~
l Sample vill be compacted and analyzed by GE(Li) gama spectrometry or alternate technique, if necessary, to achieve a sensitivity ** of 5 pCi/kg for Cs-134, Cs-137, Co-60, Zn-65 and Zr-95 and 15 pC1/kg for Ce-144.
The mussel shell sample from one location (the location nearest the discharge I
canal unless otherwise specifie.d pursuant to licensee's agreement with Mass.
WildlifeFederation)villbeanalyzedeachquarter. One additional mussel shell sample (from the Green Harbor location, unless otherwise specified I
pursuant to Licensee's agreement with Mass Wildlife Federation) vill be analyzed semi-annually. Unscrubbed shells to be analyzed will be dried, processea, and analyzed similarly to the mussel bodies.
Because of the s=all volume reduction in pre-processing of shells, sensitiv1-ties attained will be less than that for mussel bodies. The equipment and counting times to be employed for analyses of shells will be the same or I
comparable to that er: ployed for mussel bodies so that the reduction in sensitivities (relative to those for mussel bodies) vill be strictly limited to the effects of poorer geometry related to lower sample volume reduction.
Shell samples not scheduled for analysis vill be reserved (unscrubbed) for possible later analysis, depending upon recomendations of the review comittee.
l
~~Supplemental provision.~~
~~All sensitivity values to be determined in accordance with footnote (a) i to Table 4.8.4., viz., LLD a t 95: confidence level on Le ; 50% confidence~~
_ level on p (See HASL-300 for_definicions).
=
E D-9
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I Notes (Cont'd)
If radiocesium (Cs-134 and Cs-137) activity exceeds 200 pCi/kg (vet) in mussel bodies, the.se samples will be analyzed by radiochemical I
spearation, electrodeposition, and alpha spectrometry for radioisotopes of plutonium, with a sensitivity of 0.4 pC1/kg.
(g)* Sediment samples from four locations (Manomet Pt., Rocky Pt., Plymouth Harbor, and head of Duxbury Bay) will be analyzed once per year (preferably early summer) as follows:
Cores will be taken to depths of 30-cm, minimum depth wherever sediment conditions permit by a hand-coring sampling device. If sediment conditions do not permit 30-cm deep cores, the deepest cores achievable with a I
hand-coring device will be taken. In any case, core depths will not be less than.14-em.
Core samples will be sectioned into 2-cm increments, l and surface and alternate increments analyzed, others reserved. Sediment I
' sample volumes (determined by core diameter and/or number of individual cores taken from any single location) and counting technique will be
. sufficient to achieve sensitivities of 50 pCi/kg dry sediment for Cs-134, Cs-137, Co-60, 2n-65, and Zr-95 and 150 pCi/kg for Ce-144.
In any case I
individual core diameters will not be less than 2 inches.
~~The top 2-em section from each core will be analyzed for Pu isotopes J(Pu-238, Pu-239, 240) using radiochemical separations, electrodeposition, I~~
and alpha spectrometry with target sensitivity of 25 pCi/kg dry sediment.
Two additional core slices per year (mid-depth slice from core samples iqtaken at Rocky Point and Plymouth Harbor, unless otherwise specified I
hpursuant to licensee's agreement with Mass Wildlife Federation) will be similarly analyzed.
i j
(h) These locations may be altered in accordance with results of surveys I
discussed in paragraphs 4.8.D-3 and 4.8.D-4.
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~~Supplemental provision D-10~~
E.
I.
TABLE 4.8.2 AIR PARTICULATES. CASEOUS RADIOIODINE AND MTL SUP.VEILLANCE STATIONS I
Sampling Location Distance and Direction from Reactor (Sample Designation)
Offsite Stations East Weymouth (EW)
~~23 miles NW Plymouth Center (PC) 4.5 miles W-WNW Manomet Substation (MS) 2.5 miles SE~~
/
Clef t Rock Area (CR) 0.9 miles S Onsite Stations Rocky Hill Road (ER) 0.8 miles SE Rocky Hill Road (WR) 0.3 miles W-WNW Overlook Area (OA) 0.03 miles W Property Line (PL) 0.34 miles NW Pedestrian Bridge (PB) 0.14 miles N East Breakwater (EB) 0.35 miles ESE Warehouse (WS) 0.03 miles SSE I
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~~Control Station I~~
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TABLE 4.8.3 EXTERNAL CAMMA EXPOSURE SURVEILLANCE STATIONS (TLD)
Distance and Dosimeter Location (Designation 1.
Direction from Station Offsite Stations East Weymouth (EW)
~~23 miles NW~~
Kingston (KS) 10 miles WNW Sagamore (CS) 10 miles SSE-S Plymouth Airport (SA) 8 miles WSW North Plymouth (NP) 5.5 miles WNW Plymouth Center (PC) 4.5 milds W-WNW South Plymouth (SP) 3 miles WSW Manomet (MS) 2.5 miles SSE l
Manomet (ME) 2.5 miles SE Manomet (MP) 2.25 miles ESE-S
,l Cleft Rock Area (CR) 0.9 miles S 5
Saquish Neck (SN)**
4.6 miles NNWl ***
~~
~
Onsite Stations f
Rocky Hill Road (ER) 0.8 miles SE Microwave Tower (MI) 0.38 miles S Rocky Hill Road (WR) 0.3 miles W-WNW Rocky Hill Road (B) 0.26 miles SSE I
Property Line (H) 0.21 miles SSW Property Line (I) 0.14 miles W Public Parking Area (PA) 0.07 miles N-NNE Overlook Area (OA) 0.03 miles W I
I
._ Data from this surveillance station is subject. to -detector maintenance and
Control Station retrieval by a private party not subject to control by the liennsee. Therefore, the requirement to maintain this station is contingent on station availability and maintenance by the outside party.
l
~~Supplemental provision~~
'~
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l TABLE 4.8.4 l
t (d)
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS I
t Lower Limit of Detection (a) i Water Airborne particulate Wet solids Dry solids Milk' I
Analysis pC1/1 or gas - pCL/M3 pC1/Kg pCi/Kg pC1/1 I
Gross beta 2
1 x 10-2 e
l H-3 330 Kn-54 15 130 60 I
Fe-59 30 260 120 Y
i 0
CO-58,60 15 2 x 10-2 130 60 Zn-65 30 260 120 l
Sr-89 10
~~40 10 t~~
Sr-90 2
8
'150 2
Zr/Nb-95 10 1-131 7 x 10-2 80(b) 2 (c) i Cs-134,137 15 1 x 10-2 80 150 15 I
e-Ba/La-140 15 15 i
l I
(a) The nominal lower limits of detection at the 95% confidence level (defined in the ERDA Health and Safety Laboratory procedures manual, HASL-310).
(d) This table applies to all analyses other (b) Applies only to analysis of green leafy vegetables.
than those for which higher sensitivities appt in accordance with Notes (f) and (g) to Table (c) Sensitivity with 257. error at the 95% confidence level.
4.8.1.
I g ____
g-l Green Harbor LvOe l
Cape ' Cod Bay E
O Ouxbury' Bay l
o 1
2 3
a s
Kingston Harbor SCALE IN WLES g,3,
u A
Rocky Point
\\
Warren i
O Cove Q sA I
Manomet andstage U
Points e
I LEGEND 0 lRISH MOSS 5;;;,y;;;e l
O SOFTSHELL CLAMS Harbor e MUSSELS A SEDIMENT E QUAHOGS I
l 1 Figure 4.8-1 Typical Ifo11use, Alsae and Sediment rampling stations
^
l I e-14
I
~ - - ~6.9.C Unique Reporting Requirements 2.
Environ:nental Program Data 4.
Annual Report. A report on the radiological environmental surveillance program for the previous 12 months of operation shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 90 days after January I
1 of each year. The reports shall include sununaries, interpret-ations, and statistical evaluation of the results of the radio-logical enviranaental surveillance activities for tM report period, including a comparison with preoperational studies,'
. operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall I
also include the results of any land use surveys which affect the choice of sample locations. If harmful effects or evidence of irreversible damage are detected by the monitoring, the I
licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem.
Results of 4 1 radiological environmental samples shall be I
summarized and tabulated on an annual basis. In the event that some results are not available within the 90-day period, the report shall be submitted, noting and explaining the reasons I
for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
b.
Anomalous measurement report. If radioactivity in an indicator I
medium from an off-site location is found and confirmed at a level exceeding ten times the control station value, a written report shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 10 days after confirmation.** This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.
I I
A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate. The results of the con-I firmatory analysis shall be completed at the earliest time consistent with the analysis, but in any case within 30 days of receipt of the anomalous result.
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I LEGENO
~~1 PROPERTY LINE tOI~~
~~13 ROCKY HILL ROAO (8) 2 PROPERTY LINE (F)~~
~~14 MICROWAVE TOWER (MT) 3 PROPERTY LINE (1) 15 EMERSON ROAO (EMI~~
~~4 PROPERTY LINE (G)~~
~~16 WHITE HORSE ROAO fwHF 5 ROCKY HILL ROAO (Al~~
17 PROPERTY LINE (EW 6 PROPERTY LINE (H) 18 ROCKY HILL ROAO (WR) 7 PUBLIC PARKING ARE A (PA) 19 PROPERTY LINE Ul*
8 PEDESTRIAN 8 RIDGE (PS) 20 PROPERTY LINE lKP I
9 OVERLOOK AREA ICA) 21 ROCKY HILL ROAO (ER) 10 E AST 8RE AKWATER (ES) 22 PROPERTY LINE (LP 11 PROPERTY LlP'E (C)
~~23 WAREHOUSE IWS) 12 PROPERTY LINE (H8)~~
~~24 PROPERTY LINE (PL)~~
O OOssMETERITLD)
A AIR PARTICULATES AND DOSIMETERS (TLD)
I
~~additional station not required by Specification 4.8.D.1 Figure 4.8.2 Location of Onsite Monitoring Stations I~~
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A A4m PARTICULATES ANO OC$tuETERS (TLDI 13 0 3
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LEGENO 1 Qux80Av(331*
9 MANOMET IMEl 7 KINGSTON IX31 10 MANOMET (MSI 3 NORTH PL YMOUTH (NP) 11 MANOMET (M81
~~4 PLYMOUTH CENTER iPC) 12 COLLEGE PONO ICP)~~
~~5 SOUTH PLYuouTH 15P1 13 SAGAMORE ICSI 6 O AYSHCRE ORIVE 180#~~
14 PLYMOUTH AIAPOmf (34 7 CLIFT ROCK A A E A (C.H 15 EAST WEYMOUTH IEwl I
a u A N O u ET.MP)
~~16. Saquish Neck. (SN)~~
~~additional stations nOC required by Specification 4 8 D 1 Figure 4.8.3 Location of Offsite Monitoring Stations l~~
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APPENDIX E - 1980 GARDEN AND MILK ANIMAL SURVEY (memo on results of survey)
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NOD #80-924 1
OFFICE MEMORANDUM CO370N Eot ON COMPANY ILE vi-...
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v.ameas ur TO...E..L.Ziemianski
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Jn L,...So' '30 D ATr... 91U/.30 Ma:L. -
PHON c...
I 1980 CARDEN & MILK ANIMAL CENSUS As required by PNPS #1 Environmental Technical Specification, on 9/10/80 and 9/H /80 I conducted the 1980 Census.
I confirmed the existance of gardens near the site boundaries 0.7 milcs west and 0.6 miles ESE from which I obtained samples. Thesegardensaretheclosestagd largest in the vicinity of PNPS (although they are problably less than 500 ft ).
I They de represent conservative garden locations for sampling analyses and dose alculation.
1 I
I conducted a street by street search of the area within 1 mile of PNPS to determine the locations of any cows er goats. I found no such animals or struct-ures which would indicate the presence of such animals within 1 mile. In addit-ion, I contacted the Plymouth County Animal Inspector, Ms. Carolyn Daum, (224-2826)
I who gave me the following locations of cows and goats:
Owner Animal Location I
John Davis 3 beef cows Beaver Das Road, Manomet Warren Raymond 2 goats Off White Horce Road, Manomet (224-2398) l John Almeida 2 goats White Oak Drive, Plymouth 046-3896)
Nancy Lloyd 5 goats Lond Pond Road, Plymouth I
(224-8719)
Plymouth Plantation 1 cow Warren Avenue, Plymouth I contacted the owners of the milk producing animals and found the following:
Warren Raymond (Ms. Florence Raymond) - Sold the goats in the spring.
John Almeida - Presently has no milk producing animals.
Nancy Lloyd - Her goats do not presently produce milk, although they have in E
the past. She does not sell the milk, but uses it for personnel W
consumption. When the animals give milk it is normally very little since they are miniature goats (not full size).
I have concluded that our present location for milk sampling (Plymouth Plantation-2.2 miles West) continues to be the best indicator station.
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ML20003F730

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