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Environ Radiation Monitoring Program Semiannual Rept 5, 740701-1231
	ML20150E916
Person / Time
Site:	Pilgrim
Issue date:	12/31/1974
From:	Cehn J, Gina Davis; BOSTON EDISON CO.
To:	;
References
	2792, NUDOCS 8804040173
	Download: ML20150E916 (70)
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'I'N PILGRIM NUCLEAR GENERATING STATION g

ND' Environmental Radiation Monitoring Program 50-293 SEMIANNUAL REPORT NO. 5 JULY 1, 1974 THROUGH DECEMBER 31, 1974

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Environmental Sciences Group Nuclear Engineering Department March 1974 Approved By:

f Envi@ yds Davis, Manager G. Jar nmental Sciences Group 2792 i

l TABLE OF CONTENTS Section Page I.

INTRODUCTION AND

SUMMARY

)

1 II.

DESCRIPTION OF MONITORING PROGRAM 3

9 III.

MONITORING DATA AND RESULTS 4

I A.

Air Surveillance.........................

4 B.

External Gamma Exposure Rates 4

)

C.

Milk.....................................

5 h

D.

Crops 5

E.

Domestic and Recreational Water..........

5 i

F.

Precipitation 5

G.

Seawater.................................

5 H.

Marine Life 6

I.

Bottom Sediment 7

IV.

POTENTIAL CONSEQUENCES OF DETECTED RADIATION LEVELS 8

APPENDIX A

SUMMARY

OF RADIOACTIVE EFFLUENTS A-1

(

APPENDIX B RESULTS OF INTEREST ANALYSES OF ENVIRON-I MENTAL PROTECTION AGENCY SAMPLES B-1 APPENDIX C A COMPUTER PROGRAM TO CALCULATE PILGRIM UNIT 1 OPERATING DOSES TO THE PUBLIC C-1 11

LIST OF ILLUSTRATIONS Figure Page 1.

Location of Offsite Radiological Monitoring Stations 9

2.

Location of Onsite Radiological Monitoring Stations 10 3.

Aquatic and Terrestrial Surveillance Stations 11 4.

Radioactivity in Air Particulates - East

)

Weymouth (EW) 12 5.

Radioactivity in Air Particulates - Overlook

)

Area (OA) 13 6.

Offsite Gamma Exposure Rates - East Weymouth (EW)

?

and South Plymouth (SP) 14 7.

Onsite Gamma Exposure Rates - Overlook Area (OA) and Public Parking Area (PA) 15 8.

Concentrations of Strontium-90 and Cesium-137 in Milk (Plymouth) 16 9.

Gross Beta Concentrations in Monthly Water Samples from Little South Pond 17

)

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LIST OF TABLES Table Page 1

AIR PARTICULATES AND GASEOUS RADIOIODINE SURVEILLANCE STATIONS 18 2

EXTERNAL GAMMA EXPOSURE SURVEILLANCE STATIONS (TLD) 19 3

TERRESTRIAL AND AQUATIC SURVEILLANCE STATIONS 20 4

TYPES AND FREQUENCIES OF ANALYSES 21 5

ENVIRONMENTAL SAMPLE ANALYSIS PARAMETERS 22

?

6 AIR PARTICULATES - GROSS BETA CONCENTRATIONS 3

IN WEEKLY SAMPLES (pci/m )

23

)

7 AIR PARTICULATES - GROSS GAMMA CONCENTRATION IN MONTHLY COMPOSITES (cpm /m3 x 10-3) 24 7A AIR PARTICULATES - GAMMA ISOTOPE CONCENTRATION IN MONTHLY COMPOSITES (pCi/m3) 25 7B AIR PARTICULATES - STRONT10M-90 CONCENTRATION IN QUARTERLY COMPOSITES (pCi/m3 x 10-4) 26 8

PARTICULATE IODINE-131 IN AIR SAMPLES (pCi/m3) 27 i

3 8A GASEOUS IODINE-131 IN AIR _ SAMPLES (pCi/m )

28 9

EXTERNAL GAMMA EXPOSURE RATES, JULY-DECEMBER 1974 ( R/hr) 29 10 RADIONUCLIDE CONCENTRATIONS IN MILK (pCi/1) 30 11 RADIOACTIVITY IN CROPS 31 1

12 RADIOACTIVITY IN DOMESTIC AND RECREATIONAL WATER...........................................

32 13 RADIOACTIVITY IN PRECIPITATION - PLYMOUTH

)

' MASSACHUSETTS 33 14 RADIOACTIVITY IN SEAWATER - July - December

)

1974 34 14A RADIOACTIVITY IN SEAWATER - January - June 1974 35 15 RADIOACTIVITY IN MARINE LIFE - June - December 1974 36 iv

LIST OF TABLES - Continued Table Page 15A RADIOACTIVITY IN MARINE LIFE - January - June 1974 38 16 RADIONUCLIDES IN BOTTOM SEDIMENT 40 16A DISTRIBUTION OF RADIOACTIVITY IN BOTTOM SEDIMENT 41 17 DOSE CALCULATIONS RELATED TO PLANT DISCHARGES -

July 1 - December 1974 42 18 DOSE CALCULATIONS RELATED TO CONSUMPTION OF MARINE LIFE - July 1 Through December 31, 1974 43 B-1 INTEREX ANALYSES OF ENVIRONMENTAL PROTECTION AGENCY SAMPLES B-2

)

4 V

I.

INTRODUCTION AND

SUMMARY

f This report describes the data accumulated in the Environmental Radiation Surveillance Program during the semiannual period July l-through-December 31, 1974.

After a seven-month outage for refueling, maintenance, and contested licensing proceedings, the unit came up to full power on August 16.

Plant capacity factors (a measure of electrical output) during the reporting period were:

July, 5 percent; August, 84 percent; September, 73 percent; October, 83 percent; November, 82 percent; arm December, 75 percent.*

t On December 17, an augmented off-gas treatment system was put into service.

This system will effectively eliminate iodines, and greatly reduce the amount of radiogases released from the I

main stack.

Also put into service was a liquid waste solidification system, which is expected to have the effect of significantly reducing the quantity of liquid wastes discharged to the bay.

A summary of radioactive effluents released during the reporting l

period is presented in Appendix A.

d The liquid releases associated with and occuring during the l

seven-month outage (prior to completion of the solidification system) are evident in the program data reported in Section III I

of this report.

Media in the vicinity of the station found with trace amounts of radioactivity from the station were Irish moss, bottom sediment, mussels, lobster (1 individual), cod (2),

herring (2), bluefish (2) and cunner.

A potential radiation dose p

to humans consuming these media was calculated using "worst case" assumptions.

This dose was calculated to be 0.26 millirem per year resulting from station produced radioactivity and 6.7

Details of plant operation can be found in a separate report entitled, "Operating and Maintenance Semiannual Report #5."

1

millirem from nuclear weapons test fallout radioactivity.

These results may be compared to the natural background radiation levels of approximately 100 millirem per year.

No radioactivity attributable to station operation was detected in any terrestrial media.

)

2

II.

DESCRIPTION OF MONITORING PROGRAM The Environmental Radiation and Radioactivity Surveillance Program is being performed in accordance with the requirements specified in the Pilgrim Facility Operating License (DPR-3 5).

Summaries of the sampling media, locations, frequencies of collection and analyses are given in Tables 1 through 4.

Details of the sampling program are given in Semiannual Report #2.*

Sampling locations are shown in Figures 1, 2,

and 3.

The radio-analysis of the majority of the environmental samples is being performed by Interex Corporation.

The li'.its of detection associated with their analytical procedures are given in Table 5.

Samples of bottom sediment and selected marine life were analyzed by Teledyne Isotopes using Ge(Li) gamma spectrometry.

The sensitivities of their analyses are given with the results in the appropriate tables.

The Interex Corporation routinely participates in the EPA Radionuclide Crosscheck Program as part of their quality assurance effort.

The EPA Program consists of distributing media with known radionuclide concentrations to participating laboratories for analysis (the known concentrations are not revealed to the participating laboratories prior to completion of the laboratory reports).

The results of Interex's analyses for 1972 and 1973 are reported in Appendix B.

The results show Intere.x to be consistently performing accurate analyses.

1

)

Pilgrim Nuclear Generating Station, Environmental Radiation Monitoring Program, Semiannual Report #2, August 29, 1973.

t 3

III.

MONITORING DATA AND RESULTS The results of environmental radiation and radioactivity measurements performed during the semiannual reporting period (July 1 to December 31, 1974) are presented in Tables 6 through 16A according to sampling media and analyses performed.

Results for each sampling media are discussed below.

Results of sample analyses indicated as incomplete will be reported in a later report.

A.

Air Surveillance Gross beta radioactivity in air particulates decreased during the reporting period, which is consistent with the seasonal variation of weapons test fallout (Table 6).

These seasonal variations are evident in Figures 4 and 5, which include preoperational data on air particulate radioactivity.

Results of gross gamma, gamma isotopic, and strontium-90 analyses are shown in Tables 7, 7A and 7B, respectively.

Radiciodine levels 3

remained less than tne detection limits of 1 pCi/M (Tables 8 and 8A).

B.

External Gamma Exposure Rates The environmental gamma exposure rate measurements from July through December 1974 are given in Table 9.

The reported rates include the inherent dosimeter self-irradiation which is typically 6 to 8 microroentgens per hour ( R/hr).

Figures 6 and 7 present measured exposure rates over 34 months at two offsite and two onsite locations, respectively.

The relatively high exposure rate at the overlook area V in November was due to a combination of turoine shine and relatively high stack release rates during that month (see Appendix A).

Potential radiation doses to area visitors are discussed in Section IV.

4

C.

Milk Milk was sampled from three locations and was analyzed monthly for Cs-137, Sr-90, Ba/La-140 and I-131.

The results obtained during the reporting period are presented in Table 10.

The levels of strontium and cesium measured in Plymouth milk do not exceed the levels measured prior to station operation, as shown in Figure 8.

D.

Crops Cranberries and produce were sampled in the Plymouth area and at control sites during the reporting period.

Ge(Li) gamma spectrometry indicated no unusual isotopes in cranberries.

Other analyses showed only background levels of activity.

These data are reported in Table ll.

E.

Domestic and Recreational Water i

Monthly composites of weekly water samples were analyzed for gross radioactivity and the isotopes H-3, Sr-90 and I-131.

Results are shown in Table 12 and in Figure 9, which shows a decrease in gross beta activity during the reporting period.

This is consistent with the decrease in radioactivity in air particulates.

F.

Precipitation i

A precipitation collection station in Plymouth was sampled during the reporting period.

The radioactivity found in the monthly I

samples are reported in Table 13.

G.

Seawater Monthly samples were taken from the intake channel, discharge channel, and a control location 7.5 miles NNW of the station.

These were analyzed for fractional gross beta (explained in

I Table 14), gross gamma, tritium and iodine-131.

The results of these analyses and of quarterly composites from the intake and

}

discharge channels are given in Table 14.

The values which are j

greater than the detection limit are within the range of preoperational values.

Table 14A presents data listed as incomplete in the previous report.

H.

Marine Life Initiated this reporting period were Ge(Li) isotopic analyses of marine life samples.

Results obtained by this method exhibited an increased sensitivity of about a factor of 5 (relative to results obtained by chemical separation techniques).

As a result, trace amounts of radionuclides were able to be detected.

As discussed in Section IV, the potential dose consequences of these amounts are negligible.

The highest levels of radioactivity were detected in mussels taken from the end of the discharge canal, where they grew for a brief period during the six-month station shutdown.

These mussels were too small to be edible and were not harvestable, since the canal is in a controlled access location.

The Co-60 level decreased by a factor of 40 by the time the mussels were last sampled from the canal (in August).

No mussels were available in the canal during subsequent sampling periods.

Edible species (soft shelled clams) showed no elevated activity during the reporting period.

The radioactivity detected in marine life was a result of the higher than normal liquid releases during the recent refueling and maintenance outage (January to July 1974).

A liquid radwaste solidification system was put into service subsequent to this outage, enabling most liquid wastes to be solidified rather than discharged to the bay.

Tables 15 and 15A present the marine sampling data for 1974.

It can be seen that nearly all samples taken at the end of the l

6

____ _ I

reporting period showed only background levels of activity.

Sampling of selected media (lobster, shellfish, Irish moss, cod) will continue at an accelerated rate through 1975.

I.

Bottom Sediment Sediment in the discharge canal reached peak activity levels prior to startup of the station in July.

Sediment at Plymouth Beach (3.5 miles WNW) shcwed trace amounts of station produced nuclides.

These levels are far below that of naturally occurring potassium-40 and do not constitute a radiological hazard.

A special particle size analysis was performed on discharge canal sediment.

The results showed insignificant differences in the radioactivity levels for each particle size group.

Results of the sediment analyses are given in Tables 16 and 16A.

c I

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f

IV.

POTENTIAL CONSEQUENCES OF DETECTED RADIATION LEVELS Using the radiation dose model described in Appendix C, a potential dose to public individuals was calculated.

Inputs used with the model wer2 actual releases in the liquid and gaseous effluents, solid waste shipments, measured radioactivity in discharge canal sediment and plant capacity factors.

The doses calculated are summarized in Table 17.

Also calculated were "worst case" potential doses associated with consumption'of marine life found to contain nuclides attributable to station operation.

The "worst case" assumptions used, and the results, are presented in Table 18.

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Concentrations of Strontium-90 and Cesium-137 in Milk (Plymouth)

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v-~, ,,y,.7,, y y n ,m-,,, ,.,.y .y. m -e ---ew----+e' m- 'T'T'- -v--w* - - - - * - ~ - - - v- TABLE 1 AIR PARTICULATES AND GASEOUS RADIOIOlsINE SURVEILLANCE STATIONS Surveillance Stations Station Incation Rela ve to Pilgrim Station) Req'd by Operating License Not Reg'd by Operating License g g Onsite Offsite Onsite Offsite Code Fig. No. Direction Distance Rocky Hill Road ER 2 21 SE 0.8 m Overlook Area OA 2 9 W 0.03 m Rocky Hill Road WR 2 18 W-WNW 0.3 m Cleft Rock Area CR 1 7 S 0.9 m l East Weymouth EW l 15 NW 23 m Manomet MS 1 10 SE 2.5 m Plymouth Center PC 1 14 W-WNW 4.5 m East Breakwater EB 2 10 ESE 0.35 m Pedestrian Bridge PB 2 -8 N 0.14 m l 6' Property Line PL 2 24 NW 0.34 m l Warehouse WS 2 23 SSE 0.03 m 0 1 c__ TABLE 2 EXTERNAL GAMMP. EXPOSURE SURVEILLANCE STATIONS (TLD) Surveillance Stations Station Location Reg'd by Operating License Not Reg'd by Operating License Station Onsite Offsite Onsite Offsite Code Fig. No. Direction Distance Microwave Tower MT 2 14 S 0.38 m Overlook Area OA 2 9 W 0.03 m Property Line 11 2 6 SSW 0.21 m Property Line I 2 3 W 0.14 m Public Parting Area PA 2 7 W-NNE 0.07 m Rocky 11111 Road B 2 13 SSE 0.26 m Rocky Hill Road ER 2 21 SE 0.8 m Rocky flill Road WR 2 18 W-WNW 0.3 m l Cleft Rock Area CR 1 7 S 0.9 m East Weymouth EW 1 15 NW 23 m Kingston KS 1 2 WNW 10 m Manomet ME 1 9 SE 2.5 m Manomet MP 1 8 ESE-S 2.25 m Manomet MS 1 10 SSE 2.5 m North Plymouth NP 1 3 WNW 5.5 m Plymouth Airport SA I 14 WSW 8 m Plymouth Center PC 1 4 W-WNW 4.5 m Sagamore CS 1 13 SSE-S 10 m South Plymouth SP 1 5 WSW 3 m East Breakwater EB 2 10 ESE 0.35 m Pedestrian Bridge PB 2 8 N 0.14 m Property Line C 2 11 SL 0.35 m Property Line D 2 1 NFN 0.37 m Property Line E 2 17 1.6 m Property Line F 2 2 NW 0.25 m Property Line G 2 4 W 0.4 m Property Line IIB 2 12 SE-SSE 0.35 m Property Line J 2 19 S-SSE 1.6 m Property Line K 2 20 S-SSE 1.7 m Property Line L 2 22 ESE-SE 0.35 m Property Line PL 2 24 NW 0.34 m Warehouse WS 2 23 SSE 0.03 m Bayshore Drive BD 1 C WNW 0.8 m College Pond CP 1 12 SW 6.5 m Duxbury SS 1 1 NW 5.9 m Emerson Road EM 2 15 SSE 0.96 m Manomet MB 1 11 SSE 3.5 m TABLE 3 TERRESTRIAL AND AQUATIC SURVEILLANCE STATIONS Refer to Distance and Direction tig. 3, Sarple Type Sarple Location From Station Item No, Milk Plymouth County Farm (CF) 3.5 miles W 13 Lccal store (a) Bridgewater State Farm (BF) 20 miles W 16 Crenberries Beaver Dam Road Bog 2 miles S 7 Robbins Bog (RB) 2 miles SSE 8 Bartlett Road Bog (BR) 2.75 miles SSE-S 10

lymouth County Farm (CF) 3.5 miles W 13 crops (potatoes, r

a cabbage, lettuce Ma nome t (RF) 2 miles SSE 9 and hay) Bridgewater State Farm (BF) 20 miles W 16 I Precipitation South Plymouth *I 4.75 miles WSW-W 14 Domestic and Deep Water Pumping Station 4.75 miles W 12 recreational water (Lout Pond Well and Little South Pond)--Plymouth (LW) Warner's Pond Pumping Station 2.75 miles SSE 11 Manomet Well (MW) Creat Pcnd Pumping Station 24 miles WNW-NW 17 CollegePondjggtb; South Weymo (cp) (CP) 6.5 miles SW 15 Seawater Discharge channel (DC) Onsite 1 Cooling water. intake (IC) Onsite 2 Priscilla Beach (PRE) 0.8 to 1.6 miles ESE-SE 5 White Horse beach (WHB) 1.6 to 2.7 miles ESE-SE 6 Plymouth Beach (PLB) 3.5 niles WNW 4 Powder Toint - Duxbury (PP) 7.5 miles NNW 3 turine life Marine waters in station Sampling ranges from (lobster, fish, vicinity

2. 4 miles W-Mai to mollusks) 2.9 miles ESE-SE Bottom sediment Area in vicinity of discharge channel outfall (a) Additional stations operated during reporting period although not required by cperating license.

(b) Contral station. 20 TABLE 4 TYPES AND FREQUENCIES OF ANALYSES Planned Sample Type Frequency of and Number Analysis Analysis Collection Type Air Particulates (11) Gross beta Weekly Continuous Gross gama on filter composites from each station Monthly Gama spectrum (a) I-131 Weekly Gaseous iodine (11) I-131 Weekly Continuous Gama exposure (39) Dosimeter reading Monthly Continuous Domestic water (5) Cross beta and gross gama Monthly Grab Gama spectrum (a) I-131, Sr-90, H-3 Monthly Precipitation (1) Gross beta and gross gama Monthly Continuous Gama spectrum (a) I-131, sr-90, H-3 Monthly Seawater (3) Fractional gross beta and gross gama Monthly Continuous (DC)* Gamma spectrum I-131 Monthly Grab (others) Sr-90, Cs-137, H-3, Mn-54, 2n-65, Co-58, and Co-60 Quarterly Marine life (c) Gross beta and gross gama Each sample Gamma spectrum (b) I-131, Sr-90, Cs-137, Mn-54, 2n-65, Co-58, and Co-60 Each sample Bottom sediment (2) Gross beta, gross gama, and gama spectrum Semiannually Grab Milk (3) I-131, Sr-90, Cs-137 Ba/La-140 Monthly Crops Gross beta, gross gams, and gamma spectrum Annually Sr-90, Cs-137 Annually (a) Selective gama analysis will be made based on gross gamma results, with at least one gama spectrum analysis made each quarter. (b) A gamma spectrum analysis will be made at least once during each sampling period. (c) Samples will be collected during their comercial harvesting season. DC = discharge channel. l 21 TABLE 5 ENVIRONMENTAL SAMPLE ANALYSIS PARAMETERS Sample Type Analysis Detection Limit Aliquot t Error Air Particulate Gross beta 4 x 10'3 pC1/m 10,080 ft 110 3 3 Gross gama 2 x 10'3 cpm /m 10,080 ft 110 3 I*I 3 131 3 3 I 1 pC1/m 10,080 ft 110 Nonsaline Water Gross beta 1 pCi/ liter 1,000 ml 110 ICI Gross gama 5 cpm / liter 4,000 ml 110 Gama spectrum (d) 4,000 ml 90Sr 0.5 pCi/ liter 1,000 ml 115 3H 2.5 pCi/ml 4 ml 110 Crops and . Gross beta 0.2 pCi/g 20 9 110 Marine Life ICI Gross gama 0.01 cpm /g 1,000 g 110 Gama spectrum (d) 1,000 g 90Sr 0.005 pCi/g 100 g 110 134Cs' 137Cs 0.1 pC1/g 100 g 120 54Mn 0.1 pCi/g 100 9 120 58Co 0.1 pCi/g 100 g 120 60Co 0.1 pC1/g 100 g 120 65 2n 0.1 pC1/g 100 g 120 Seawater Gross beta 60 pCi/ liter 30 g 120 Fractional gross beta 5 pCi/ liter 500 ml 120 Gross gamma 5 cpm / liter (c) 4,000 ml 110 Gamma spectrum (d) 4,000 ml 3 H 2.5 pCi/ml 4 ml 110 90 Sr 0.5 pCi/ liter 15,000 ml 115 137Cs 0.05 pC1/ liter 15,000 ml 115 54 Mn 5 pCi/ liter 1,000 ml 120 58Co 5 pCi/ liter 1,000 ml 120 60Co 5 pCi/ liter 1,000 ml 120 6 In 5 pCi/ liter 1,000 ml 120 131 I 5 pC1/ liter 1,000 ml 115 Milk 90 Sr 0.5 pci/ liter 1,000 ml 115 137 Cs 1 pCi/ liter 1,000 ml 115 1O Ba 5 pct / liter 1,000 ml 115 1I I 2 pCi/ liter 2,000 ml 125 octtom Sediment Gross beta 2 pCi/g 1g 115 Gamma Spectrum (d) 1,000 g 90Sr 0.005 pC1/g 100 9 120

Background

Cama exposure 1 #R/hr 1-month 110 Radiation rate (a) exposure NOTE: Provided by Interex Corp., Natick, Massachusetts (a) Measured with thermoluminescent dosimeter.

337 (b) In the counter used, 1 cpm corresponds to 2.2 pCi of Co.

(c) In the counter used, 1 epm corresponds to 9 pCi of 137 s.

C (d) Ge(L1) detection sensitivities are given in Table 16, 22 1

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TABLE 7 AIR PARTICULATES - GROSS GAMMA CONCENTRATION IN MONTHLY COMPOSITES (cpm /m3 x 10-3) (a)

Control Offsite Onsite Collection East Plyscuth Cleft Manoamet Rocky Hill Property Overlook Pedestrian East Rocky Hill Period (1974)

Weymouth Center Rock Area Substation Road (West)

Line Area Bridge Breakwater Road (East) Warehouse Jan 6(b) 11 7

10 9

15 25 12 14 11 12 Feb 14 14 18 18 14 18 14 4

18 18 14 Mar 15 11 12 12 18 16 13 12 21 13 16 Apr 11 19 20 19 22 26 23 22 24 21 12 May 9

to 18 11 10 11 11 13 8

15 7

June 19 15 8

11 11 9

8 18 16 11 11 July 9

14 12 8

12 14 6

10 1d) 10 13 Aug 10 10 6

5 9

9 8

13 9

6 7

Sept 6

7 7

7 5

3 6

9 1

8 7

Oct 9

16 Il 7

5 6

to 7

7 5

9 nov 7

9 3

4 13 9

10 4

8 6

10 Dec 5

7 12 8

7 6

12 9

8 5

13 (a) Error is +2 or lot, whichever is larger.

3 (b) Comma spectrum indicates no nuclides identified greater than 0.05 pCi/m -

(c) I indicates incomplete analysis results will be reported in next semiannual report.

(d) No sample.

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TABLE 7B l

AIR PARTICULATES - STRONTIUM-90 CONCENTRATION IN QUARTERLY COMPOSITES (pCi/m3 x 10-4) (a) (b)

Cont rol Of f aite Oneito Collection East Plymouth Cleft Manomet Rocky Hill Preperty Overlook Pedestrian East Rocky Mill Period (1974) Wymt h Jenter Rock Area Substation Road (West)

Line Area Bradje Breakwater Road (East) Warehouse Jan - Mar 2 +1 6 +1 4 +1 2 +1 1 +1 4 +1 41 2 +1

$ +4 42 3 +1 Apr - Jun 4 +1 7 +2 5 +1 2 +1 4 +2 6 +1 6 +1 6 +1 3 +1 5 +1 3 +1 1

July - Sept (c) 7 +1 43 S +1 8 +1 3 +1 6 +1 5 +1 3 +1 3 +1 3 +1

.l i

Ort - Dec 4 +1 2 +1 (el 3 +1 5 +1 4 +1 1 +1 2 +1

) +1 2 +1 2 +1 l

3 ta) 3.0 in table means 3 x 10-4 pC1/m (b) These resulta are reported with an error corresponding to two standard deviatione in t.he counting error. At the low count l

M rates encountered, it is difficult to verify the half-life of Y-90 and the actual error could be larger than that reported.

Ch (c) Sample lost in analysis.

i 1

TABLE 8 PARTIC"LATE IODINE-131 IN AIR SAMPLES (pCi/m )

Control Offsite Ons it e East Plymouth Cleft Manomet Rocky Hill Property Overlook Petes t r ian East.

Rocky H111 collect ion Per ial weymouth center pock Area substatinn Po=1 (west)

,Line'

_ Area Bridge

Breakwater

Road (East) Warehouse

June il - June 20

<1

<1 J une 20 - June 27

<1 51

<1

<1 (a)

(1

<1 June 27 - July 4

<1

1

<1

<1 (a)

<1

<1 July 4 - July 11 41

<1

<1 (I

<1

<1 (a)

<1

<1 July 11 - July 13 41

<1

<1 l

July 18 - July 25

<1

<1 July 25 - Aug 1

<1

<1 Awg 1 - A eg 8

<1

<3

<1

<1 Aug 8 - Aug 1%

<1

<1 Aug 15 - Aug 22

<1 (a)

<1

<1 s1

<1

<3

<1

<1 i

Aug 22 - Aug 29

()

(a)

<1

<1 Awa 29 - Sept 5

<1 (a)

<1

<1 Sept 5 - Sept 12

<3

<1

<t

<1

<1 Sept 12 - Sept 19

<1

<1 (1

(1

<1

<a

<1

<1 Sept 19 - Sept 26

<1 (a)

<1

<1 Sept 26 - Oct 3

<1

<1 g

Oct 1 - Oct to

<1

<3

<1

<1 (a)

<1

<1 y

Oct to - Oct 17

<1

<1 Oct 17 - Oct 24

<1

<1 (1

<1

<1 Oct 24 - Oct 11

<1

<1 (a)

<1

<1 Oct 31 - Nov 7

<1 Al

<1

<3

<1

<1 Nov 7 - mw 14

<1

<3

<1

<1 Nov 14 - Nov 21

<1

<1 (1

<1

<g Nov 21 - Nov 2B

<1

<1 (a)

<1

<1 (1

<1

<1 Nov 28 - Dec 5

<1

<1 (a)

<1

<1 Dec 5 - Dec 12

<1

<1 Dec 12 - Dec 19

<1

<3

<1

<1 Dec 19 - Dec 26

<1

<1 Dec 26 - Jan 2

<1

<3

<1

<3

<1

<1 (1

(a)

No san te.

Station not required by operating license.

l

TABLE 8A i

GASEOUS IODINE-131 IN AIR SAMPLES (pCi/m )

l l

Control Offsite Onsite East Plymouth Cleft Manomet Rocky Mill

?roperty Overlook Pedestrian L.st Pocky Hill Collection Period Weymouth center Roc % Area Substation Road (West)

1. _i ne

Area Bridge

Breakwater

Road (East) Warehouse

June 20 - June 27

<1

<1 June 27 - July 4

<1

<1 July 4 - July 11

<1

<1 (a)

<1

<1 J

July 11 - July 18

<1

<1 (1

(a)

<1

<1 l

July 18 - July 25

<1

'l

<1 ta)

<1

<1 July 25 - Aug 1

<1

<1 Aug 1 - Au 3 a

<1

<3

<1

<1 Aug 8 - Aug 15

<1

<3

<1

<1 Aug 15 - Aug 22

<1 (a)

<1

<1 Aug 22 - Aug 29

<1 (a)

<1

<1 i

Aug 29 - Sept 5

<1 (a)

<1

<1 i

Sept 5 - Sept 12

<1

<1 1

Sept 12 - Sept 19

<1

<1 Sept 19 - Sept 26

<1 (a)

<1

<1 Sept 26 - Oct 3

<1

<1-

<1

<1 Oct 3 - Det 10

<1

<3

<1 (1

<1

<1 (a)

<1

<1 Oct 10 - Oct 17

<1

<1 N

Oct 17 - Oct 24

<1

<1 CD oct 24 - Oct 31

<1

<1 (a)

<1

<1 Oct 31 - Nov 7

<1

<1 Nov 7 - Nov 14

<1

<1 Nov 14 - Nov 21 (1

<1

<1 Nov 21 - Nov 29

<1

<1 (a)

<1

<1 Nov 28 - Dec 5

<1

<1 (a)

<1

<1 Dec 5 - Dec 11

<1

<1 Dec 12 - Dec 19

<1

<g Dec 19 - Dec 24

<1

<1 Dec 26 - Jan 2

<1

<1 (a) No emple.

(b) Sample lost (Gecang laboratory move.

Station not required by operating license.

TABLE 9 EXTERNAL GAMMA EXPOSURE RATES, JULY-DECEMBER 1974 ( R/hr)I"I Onsite Monitoring Locatione July August September October November December Average Overlook Area (OA) 18.8 24.1 32.6 35.2 47.3 24.7 30.4 Public Parking Area (PA) 16.8 18.8 21.6 21.9 26.5 16.1 20.3 Pedestrian Bridge (PS) 17.2 22.0 (b) 19.7 27.0 (b) 31.0 20.3 (b) 22.9 Rocky Hill Road (A)

(c) 17.8 (c) 20.4 (c) 16.5 18.2 Rocky Hill Road (8) 18.1 17.6 18.8 17.7 22.8 15.7 18.4 East Breakwater (ES) 17.5 22.3 21.2 18.9 23.5 17.3 20.1 Microwave Tower (MT) 17.7 17.8 17.7 18.7 23.0 15.9 18.5 Property Line (C)

(c) 16.6 (c) 16.7 (c) 16.1 16.4 Property Line (HB) 18.0 17.5 18.5 18.1 22.4 16.9 18.6 Property Line (WH) 16.5 14.5 15.1 15.5 16.7 15.6 16.0 Property Line (EN) 17.3 19.2 17.2 15.9 20.4 (d) 18.0 Property Line (E)

(c) 15.9 (c) 14.1 (c) 12.0 14.0 Property Line (H) 17.9 20.6 20.0 21.5 21.0 18.3 19.9 Property Line (G) 13.1 16.7 13.4 16.7 14.7 14.3 14.8 Property Line (1) 17.7 19.2 18.4 19.9 20.9 17.3 19.9 Property Line (F) 17.4 19.1 18.7 19.2 20.7 16.5 15.6 Property Line (D) 15.6 17.5 15.9 16.2 25.0 15.9 17.7 Property Line (J) 17.2 16.1 15.8 14.6 16.6 15.0 15.9 Property Line (K)

(dl 15.7 15.4 14.4 15.9 14.6 15.2 Property Line (PL) 17.3 (d) 21.4 17.4 (b) 19.9 15.9 (b) 18.4 Warehouse (WS) 16.0 17.7 (b) 18.5 19.6 (b) 26.4 16.0 (b) 19.0 l

l Average Onsite Dose Rates per Month 17.1 18.4 18.9 19.0 23.0 16.5 Offsite Monitoring Locations East Weymouth (rW) 17.9 16.2 13.0 15.2 11.6 16.1 15.0 Kingston (KS) 17.4 16.2 (c) 15.2 (c) 14.9 15.9 Sagamore (CS) 19.4 17.0 16.4 16.1 15.3 16.6 16.8 Plymouth Airport (SA) 13.9 14.4 12.6 12.3 12.5 13.7 13.2 a

Duxbury (SS) 15.6 15.3 13.9 13.4 13.5 14.8 14.4 Plymouth (CP)

(c) 14.8 (c) 15.5 (c) 15.5 15.3 North Plymouth (NP) 17.4 16.4 16.2 15.3 15.7 16.1 16.2 Plymouth center (PC) 13.5 13.2 12.4 11.3 (d) 12.6 12.6 South Plymouth (SP) 16.5 16.4 15.5 14.7 16.1 15.7 15.8 Manomet (Ma) 16.1 15.5 15.2 14.5 17.2 14.7 15.5 Manomet (MS) 17.2 17.1 16.8 16.4 16.8 16.6 16.8 Ma noma t (ME) 19.9 17.9 18.0 17.2 19.5 17.6 18.4 Ma nome t (MP) 13.5 15.9 13.0 15.4 13.9 15.3 14.5 Clef t Rock Area (CR) 17.2 17.1 17.7 (c) 16.3 (c) 17.1 Rocky Hill Road (ER) 18.1 18.0 19.2 17.5 23.1 17.0 18.8 Bayshore Drive (SD) 18.7 17.0 16.4 18.3 17.5 17.3 17.5 gocky Hill Road (WR)

(c) 17.2 (c) 16.0 (c) 15.9 16.4 Average Of f site Dose Rate l

per Month 16.0 16.2 15.5 15.3 16.1 15.(

l (e) Gross Erposure Rates which include inherent dosimeter background dose rates. Measured with CaF 2

""I I

dosimeters (EG6G TL-13).

(b) New Dosimeter = not normalised.

(c) Dosimeter stolen.

(d) Reading lost in readout.

29 l

i

TABLE 10 RADIONUCLIDE CONCENTRATIONS IN MILK (pCi/l)

Collection Plymouth Analysis Period (County Farm)

Bridgewater Local Store Cs-137 May (a) 16 + 2 10 + 1 14 + 1 June (a) 16 I 2 7I1 22 T 2 July 15 1 2 5+1 19 1 2

~

Aug 6+1 10 + 1 20 + 2 Sept 14 I 2 8T1 15 I 1 Oct 15 I 2 271 3T1 Nov (E) 12 T 1 5T1 Dec (b)

(E) 6[l Sr-90 M a) 9.6 ib 12.4 1 0.9 13.1 1 0.9 May (a) 12.3 + 0.8 9.0 + 0.9 10.5 + 0.9 (a p [h + LO.8,

~+1 13

+1 June 11 Ju-l f

[2 11

+1 17

[2 Aug 5

+ 1 4

+1 (b)

Sept 9

+ 1 6

+1 (b)

Oct (E) 2 I1 2

+ 1 Nov 6

+ 1 (E)

(b)

Dec (E)

(b)

I-131 July

<2

<2 Aug

<2

<2 Sept

<2

<2 Oct

<2

<2 Nov

<2

<2 Dec

<2

<2 Ba/La-140 May (a)

<5

<5 June (a)

<5

<5 July

<5

<5 Aug

<5

<5 Sept

<5

<5 Oct

<5

<5 Nov

<5

<5 Dec

<5

<5 (a) Data listed as incomplete in previous report (b) Indicates incomplete analysis; value to be reported in next semiannual report.

30

i TABLE 11 1

RADIOACTIVITY IN CROPS Radionuclide (pCi/g)

Collection Gross Beta Sample Type Location Date (1974)

(pCi/q)

Sr-90 K-40 Cs-137 Cranberries Itall's Bog Sept 24 1.5 +0.2 0.085 +0.006 2.77 +1.05 0.046 +0.054 (SE Site Boundary)

~

Long Pond Rd.

Sept 24 1.2 +0.2 0.039 +0.006

<0.5 0.087 +0.057 (7 miles S)

~

Beaver Dam Rd.

Sept 24 1.3 +0.2 0.089 +0.008 1.61 +0.80 0.054 +0.028 (4 miles S)

~

Manomet Pt. Rd.

Sept 24

1. 6 + 0. 2 0.036 +0.006 2.12 +0.81

<0.02 (3 miles SE)

~

fralifax Sept-25 1.5 10.1 0.025 +0.002

<0.5

<0.02 (16 miles WNW)

W Bartlett Rd.

Sc t 25 1.1 +0.1 0.040 +0.002

<0.5

<0.02 H

~

(3 miles SSE)

Hay County FaYm June 6 8.7 +0.9 0.126 +0.013 (a)

<0.1 (3.5 miles W)

Bridgewater Farm July 18 14 +1 0.234 +0.324 (a) 0.1 +0.1 (20 miles W)

~

Cabbage County Farm July 18 5 + 0. 5 0.078 +0.005 (a)

<0.1 Lettuce County Farm July 18 3.6 +0.4 0.008 +0.005 (a)

<0.1 Kingston July 22 0 52 +0.05

<0.005 (a)

<0.1 (8 miles NW)

County Farm Sept 5 5.2 +0.5 0.028 +0.005 (a)

<0.1 Potatoes County Farm Aug 8 4.0 +0.4 0.011 +0.005 (a)

<0.1 Corn Bridgewater Farm Aug 22 2.6 +0.3 (b)

(a) 0.1 +0.1 County Farm Sept 5 2.6 +0.7 0.007 +0.005 (a)

<0.1 (a) Not analyzed (b) Results are incomplete

TABLE 12 RADIOACTIVITY IN DOMESTIC AND RECREATIONAL WATER Collection Great Little College Lout Pond Manomet Analysis Date (1974)

Pond South Pond Pond Well

_ Well Gross June (a) 8.8 +1.0 5.4 +1.0 3.1 +1.0

<l.0

<l.0 Beta July 3.9 71.0 4.8 T1.0 1.3 71.0

<l.0

<l.0 (pci/1)

Aug 4.0 T1.0 1.0 71.0 2.0 T1.0

<1.0

<l.0 Sept 6.1 T1.0 2.1 71.0 2.9 71.0 11.0

<l.0 Oct 6.1 T1.0 1.6 T1.0 2.1 T1.0

<l.0

<1.0 Nov 5.9 71.0 1.8 71.0

<170 1.8 +1.0 1.1 +1.0 Dec 1.3{l.0

<170

<1.0 1.7 {1.0 1.7 [1.0 Gross July

<5

<5 Gamma Aug

<5

<5 (cpm /1)

Sept

<5

<5 Oct

<5

<5 Nov

<5

<5 9 +5 8 +5 Dec

<5

<5-

<5-Strontium-90 Apr(a) 2.1 +0.5 1.0 +0.5 0.7 +0.5

<0.5

<0.6 (pci/1)

May

<5.5

<075

<0.5

<0.5 June (a)

<0.5

<0.5 0.8 +0.5

<0.5

<0.5 July 0.9 +0.5

<0.9

<075

<0.5

<0.5 Aug

<5.5

<0.7

<0.8

<0.6

<0.5 Sept 2.0 +0.5 0.7 +0.5

<0.5

<0.5 Oct 1.2 +0.5

<0.5 0.7 +0.5

<0.5

<0.7 Nov 0.9 70.5 1.1 +0.5

<075

<0.5

<0.5 Dec

<5.5

<075

<0.5

<0.5 Tritium July

<2.5

<2.5 (pci/ml)

Aug

<2.5

<2.5 Sept

<2.5

<2.5 Oct

<2.5

<2.5 Nov

<2.5

<2.5 Dec

<2.5

+2.5

<2.5

<2.5 Iodine-131 July

<5

<5 (pC1/1)

Aug

<5

<5 Sept

<5

<5 Oct

<5

<5 Nov

<5

<S

<5

<5 Dec

<5

<5 (a) Data listed as incomplete in previous report.

32

P TABLE 13 RADIOACTIVITY IN PRECIPITATION - PLYMOUTil MASSACilUSETTS("}

i Gross Gross 3

Collection Beta Gamma Sr-90 11 2

2 Period (1974)

(pCi/m )

(cpm /m )

(pCi/m2)

(nci/m2)

January 300 1100

<120 50 140

<240 February 160 140 230 1120 40 130

<80 March 1740 170 120 1120 90 f50

<250 April 2010 1200 1900 1190 120 130

<170 May 560 1120 500 1120 140 150

<290 June

<190

<120 110 130

<320 July 390 180 150 1120 (b)

<60 August (c)

(c)

September 50 130

<120

<10

<50 October 70 150 160 1120 (d)

<l50 November 690 170

<120 (d)

<110 t

December 670 1190

<400 (d)

<220 (a)

Analysis not required by operating license (b)

Aliquot lost (c)

Insufficient sample volume (d)

Results are incomplete 4

j 1

33

TABLE 14 RADIOACTIVITY IN SEAWATER July - December 1974 Fractional Cross Beta (pCi/1)(*'

Concentration Collection Gross Camma 3

Location Date Frac I Frac II Frac III. Frac IV (cpm /1)

H (pci/ml)

I-131 (pci/1)

Intake July

<5

<S

<5

<2.5

<5 Channel Aug

<5

<2.5

<5 Sept

<5

<2.5

<S Oct

<5

<2.5

<5 Nov

<5

<2.5

<5 Dee

<5

<2.5

<5 Discharge July

<5

<2.5

<5 Channel Aug

<5

<2.5

<5 Sept

<5

<2.5

<5 Oct

<5

<2.5

<5 Nov

<5

<2.5

<5 Dec

<5

<5'

<5

<2.5

<5 ta Powder July

<5

<S

<5

<2.5

<5 h

Point Aug

<5

<2.5

<5 (Duxbury)

Sept

<5

<2.5

<5 Oct 9 +5

<5

<2.5

<5 Nov

<5

<S

<5 6 +5

<2.5

<5 Dec

<5

<2.5

<5 OUARTERLY ANALYSIS OF RADIONUCLIDES (pCl/l)

Cs-134 Location Collection Date Co-58 Co-60 Zn-65 Mn~54 Sr-90 Cs-137 Intake 3rd quarter composite (1974)

<5

<l5

<5

<0.03 0.47 +0.09 Channel 4th quarter composite (1974)

<14

<l6

<30

<15

<I(b)

(cf Discharge 3rd quarter composite (1974)

<5

<l5

<5

<0.04 0.40 +0.09 Channel 4th quarter composite (1974)

<14

<16

<30

<l5

<I 0.72 +0.27 (a) The four fractions contain essentially:

1.

Insolubles 2.

Ru, Cr, Co, 2n 3.

Ra, Sr, Ba 4.

Cs (b)

I indicates incomplete analysis, value to be reported in next semiannual report.

(c) Aliquot lost in analysis.

TABLE 14A RADIOACTIVITY IN SEAWATER January - June 1974 Fractional Cross Beta (1<i/l)

Concentration Collection Gross Ganna Location Date Frac I Frac II Frac III Frac IV (cpm /1)

H (pCi/ml)

I-131 (pCi/l)

Intake Jan

<5

<2.5

<5 Channel Feb

<5

<2.5

<5 Mar

<5

<5 6 +5

<5

<2.5

<5 Apr

<5

<5 8 [5 7 +5

<2.5

<5 May

<5

<2.5

<5 June

<5

<2.5

<5 Discharge Jan

<5

<2.5

<5 Channel Feb

<5

<5 5+5

<5

<2.5

<5 Mar

<5

<5 9 75

<5

<2.5

<5 Apr

<5

<5 6 IS 8 +5

<2.5

<5 May

<5

<2.5

<5 June

<5

<2.5

<5 Powder Jan

<5

<2.5

<5 Point Feb

<5

<2.5

<5 (Duxbu ry)

Mar

<5

<2.5

<5 Apr

<5 5+5

<5

<2.5

<5 May

<5

<2.5

<5 June

<5

<2.5

<5 QUARTERLY ANALYSIS OF RADIONUCLIDES (pCi/1)

Cs-134 Location Collection Date Co-58 Co-60 Zn-65 Sr-90 Cs-137 Mn-54 Intake 1st quarter composite (1974)

<l5

<5 0.16 +0.02 0.50 +0.05

<5 Channel 2nd quarter composite (1974)

<l5

<15

<l5 0.12 70.02 0.22 TO.05

<5 Discharge 1st quarter composite (1974)

<10

<9

<5 0.15 10.02 0.62 +0.074

<5 Channel 2nd quarter composite (1974)

<6

<5

<20 0.06 +0.02 0.92 +0.09

<5 (a) The four fractions contain essentially:

1.

Insolubles 2.

Ru, Cr, Cv, Zn 3.

Ra, Sr, Da 4.

Cs (b)

Incorporates data listed as incomplete in previous report.

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l TABLE 16A DISTRIBUTION OF RADIOACTIVITY IN BOTTOM SEDIMENT ("} P Particle Size % by Activity (pCi/gm) (Microns) Weight Gross Alpha Gross Beta >590 6.9 8.6 + 4.6 50 + 3 590 - 420 2.5 5.1 7 3.8 43 I 3 420 - 250 12.2 3.7 7 3.5 43 7 3 250 - 177 46.3 8.6 T 4.6 36 I 3 177 - 149 19.8 7.6 7 4.4 36 7 3 <149 12.3 6.0 I 4.0 42 I 3 (a) Results of special investigation of sediment taken from the discharge canal, July 22, 1974. Nuclide activity shown in Table 16. 41

TABLE 17 DOSE CALCULATIONS RELATED TO PLANT DISCifARGES July 1 - December 1974 To be supplied 42

TABLE 18 DOSE CALCULATIONS RELATED TO CONSUMPTION OF MARINE LIFE } July 1 through December 31, 1974 Lobster Activity: RP 9/12 Mn-54 0.13 pCi/g Co-60 0.05 Sr-90 0.024 Dose equivalent, assuming 18.25 kgm/yr consumed (l) : C[ 0.07 mrem /yr to G.I. Tract Sr-90

2. 6 mrem /yr to bone (3)

Mussels Activity: DC 8/12 Mn-54 0.05 pCi/g Co-58 0.07 Zn-65 0.25 Sr-90 0.12 Co-60 0.34 Dose equivalent assuming 4.5 kgm/gr consumed: Co-60 Mn-54 0.06 mrem /yr to G.I. Tract Co-58 Zn-65 0.007 mrem /yr to whole body Sr-90

3. 3 mrem /yr to bone (3)

Cunner Activity: RP 6/10 Mn-54 0.05 pCi/g Dose equivalent assuming 18.25 Kgm/yr consumcd Mn-54 0.015 mrem /yr to G.I. Tract Irish Moss Activity: MP 8/23 Mn-54 2.21 pCi/g Co-58 0.29 Co-60 3.87 Cs-137 0.15 Sr-90 0.18 K-40 0.36(a) 43

TABLE 18 - Continued Dose equivalent assuming 0.73 kgm per year consumed and 1/20 processing dilution: Mn-54 Co-58 0.07 mrem /yr to G.I. Tract Co-60 Cs-137 0.001 mrem /yr to whole body Sr-90 0.8 mrem /yr to bone (no processin dilution) (3) (g) 4 Cod Activity: RP 10/2 Mn-54 0.011 pCi/g Co-60 0.024 K-40 2.3(2) Dose equivalent assuming 18.25 Kgm por year consumed: ~4 0.02 mrem /yr to G.I. Tract Co 0 Herring Activity: RP 12/12 Co-60 0.04 pCi/g K-40 2.01(2) Th-228 0.10(2) Dose equivalent assuming 18.25 Kgm/yr consumed: Co-60 0.03 mrem /yr to G.I. Tract Bluefish Activity: RP 10/2 Cs-137 0.09 pCi/g K-40 1.63(2) Dose equivalent assuming 18.25 kgm/yr consumed: Cs-137 0.05 mrem /yr to whole body Totals 0.2 mrem /yr to G.I. Tract 0.06 mrem /yr to whole body

6. 7 mrem /yr to bone ( 3)

Notes: (1) Dose model used is from "Environmental Radioactivity Surveillance Guide" ORP/SID 72-2, p. 11, June 1972. (2) Isotope occuring naturally in the environment. (3) Strontium-90 is not attributed to plant discharges but rather to weapons test fallout. (4) It is assumed all Irish Moss processed contains Sr-90 at this level. 44

A l P t i l t APPENDIX A

SUMMARY

OF RADIOACTIVE EFFLUENTS i I t i i ) i .i .i f 4 l i 1 1 I I i A-1 _,n,_-..

l l TABLE A-1 f .i I To be supplied A-2

TABLE A-2 To be supplied A-3

APPENDIX B RESULTS OF INTEREX ANALYSES OF ENVIRONMENTAL PROTECTION AGENCY SAMPLES This appendix reports the results of Interex Corporation's participation in the Environmental Protection Agency's Radionuclides Crosscheck Program. These data are presented in Table B-1. Included in the table is sample type,-analyses , performed, results of each analysis and the average, and the grand average of all participating laboratories. Where the grand average is not available, the EPA value is given. i B-1 1

TABLE B-1 INTEREX ANALYSES OF ENVIRONMENTAL PROTECTION AGENCY SAMPLES Sample Nuclide Nuclide Nuclide Nuclide Type 6 Date (pci/1) (pCi/1) (pC1/1) (pci/1) lC# tc) Water Cross e Cross A SR-90 H-3 1/7/72 12.1 + 1.0 47.3 + 1.3 81.1 + 0.5 6.9 + 0.4 14.7 T 1.0 45.4 7 1.3 79.2 7 0.4 7.0 7 0.4 18.0 ['l.0 44.4 [ 1.3 78.8 [ 0.4 6.0 [ 0.4 Eg)l4.9 i - 45.7 i = 79.9 i = 6.6 39.3 +11.3 K= 54.1 + 7.5 K= 77.0 + 4.4 K = 2.1 + 0.9 K = Milk SR-90 I 1/8/72 50.0 + 1.0 *I K= 65.2 + 3.8 Milk CS-137 SR-90(c) IdI 2/9/72 1R 10.4 + 0.7 C2 22 12.9 [ 0.8 l 21 i = 20 i= 11.7 *I I Water SR-89ICI SR-90(c) Gross a Cross p 3/10/72 19.6 + 2 55.5 + 0.9 8.7 + 1.2 43.6 + 1.1 20.3 7 2 53.9 7 0.8 9.5 7 1.2 42.7 7 1.1 24.2 [ 2 55.2 [ 0.9 6.8 [ 1.2 42.5 [ 1.1 Y = 21.4 E = 54.9 i = 8.3 E = 42.9 K= 25 + 6 K = 59.7 + 3.4 K= 38.6 + 11.1 K= 50.0 + 7.5 C Water

H-3 3/10/72 27.0 + 0.4 28.1 + 0.4 26.2 [ 0.4 E = 27.1 K = 28.9 + 3.3 i

Milk I-131 (d) BA-140(d) CS-137 *d) K (gm/l ) (d) 3/3/72 154 <10 22.1 1.62 159 <10 21.3 1.64 148 <10 21.7 1.64 i = 154 E = <10 f = 21.7 E = 1.63 K= 149 + 13 K=0+6

i 3 1 ) ) e) + ( 3 ( 2 d c dl ) 1 i/ c 1 2 ) 3 5 ) l1 ( 2 t t cC 1 +~ 2 / 1 / 1 up 3 m 062 m 133 5 = g 423 = g 645 = N( 1_ 0 ( ( y 2 K K 111 E K 111 i 3 1 7 e) + ) + ) dl d d i/ ) 22 ( 93 ( ) d d l1 ( 12 7 21 7 9 ( ) cC 1 22 3 11 3 2 1 a up 3 1 1 3 ( N( 1 691 = = 134

= 0 1_ 291 S 332 S 782 2 I 212 KK C 111 iK C 223 E r deun i tno 9 C 4 7 e) + dl ) 11 ( ( 655 83 ( 0 ( ) ) + ) ) i/ a5 C d d li c 1 cC ( 94 7 11 0 1 0 3 up 0 +7~ 98 3 +7~ 11 4 4 (8 N( 9 1 1 1 B 80

112

000 = 0 R 09 S 212 A 111 A 2 S 1 EK C 111 KK B B EL BAT 3 8 2 ( 1 e) 6 442 4 d1 ) + 111 ) i/ I 0 + d 111 4 ) 0 000 d li d ( 93 p d 1 ( +~ 2 0 11 +7~+ 7 ( 1 cC ( 7 8 up 9 4 4 22 s 6 1 5 s + ~ + +~ 5 3 5 N( 8 1 1 s 074 3 s 1 = 422 = = o = 1 = o 246 = = R 3 A 122 r 498 282 r S 978 S 4 K B 222 EK G 765 E I 545 E C 545 -X C 555 i e ta eD l 2 2 p s. 2 2 7 2 7 2 m 7 7 r / 7 r/ 7 ae k / k / e0 k / e 2 k / Sp l 6 l 6 t 1 l 8 t 1 l 1 y i/ i / a / i/ a / i / T M 4 M 4 W 5 M 5 W 7 M 9 g5W t l lll ,lli Ill 1i ll

TABLE B Continued Sample Nuclide Nuclide Nuclide Nuclide Type & Date (pC1/1) (pC1/1) (pC1/1) (pCi/1) Milk SR-90(c) I_131 (d) K (mg/ t ) (d) CS-137(d) 11/22/72 21.2 <10 1630 <10 21.3 <10 1433 <10 <10 1362 <10 E = 21.3(a) E = <10 E = 1475 E = <10 GA(e) 1.0 1 0.5 GA = 19.4 1 29.1 GA = 1537 + 129 GA = 4.3 + 4.3 = Milk CS-137(C) 11/22/72 i= 2.2(a) GA = 4.3 t 4.3 Water H-3ICI H-3(c) n.3(c) H-3(c) 2/14/72 (nci/f) (nci/l) (nCi/l) (nCi/t) 4.2 + 0.4 28.0 + 0.5 101.9 + 0.8 48.4 + 0.6 CD 4.6 7 0.4 26.2 7 0.5 101.6 7 0.8 45.7 7 0.6 8 4.9 [ 0.4 26.5 [ 0.5 96.0 [ 0.8 48.2 [ 0.6 E = 4.6 I = 26.9 E = 99.8 E = 47.4 K= 3.0 K = 27.2 K= 100.9 K= 50.2 Milk (#I SR-90(C) I-131(d) K (mg/l ) (d) 1/5/73 1.8 + 1.0 118 1530 2.0 [ 0.5 96 1250 f = 1.9 E = 107 i = 1390 CA = 2.5 1 3.4 GA = 107.6 + 23.0 GA = 1473 + 179 Milk *I CS-137(d) CS-137(c) I 1/5/73 <S 3.0 + 0.4 <5 5.7 [ 0.5 i= <5 in 4.3 GA = 3.6 1 4.4 CA = 3.6 + 4.4 Water H-3(c) 2/14/74 1600 + 400 1800 7 400 1600 [ 400 E = 1667 CA = 1595 + 504

TABLE B Continued s Sample Nuclide Nuclide Nuclide Nuclide Type & Date (pCi/l) (pci/1) (pci/1) (pci/1) Milk SR-90(c) g_g3g(d) g_g3g(c) BA-140(d) 2/8/73 97 + 2 <20 <20 <20 108 I 3 <20 <20 <20 108 [ 2 <20 <20 <20 i = 104 X = <20 K = <20 E = <20 GA = 91.6 1 22.7 GA = 5.0 t 9.6 5.0 + 9.6 GA = 3.5 1 5.5 " = Milk BA-140(c) K(mg/t)Id) CS-137(d) CS-137(C) 2/8/73 <20 1470 124 115 + 6 <20 1510 129 124 I 5 <20 1410 131 130 [ 5 X = <20 X= 1467 X= 128 X= 123 GA = 3.5 1 5.5 GA = 1396 1 149 GA = 123.3 1 21.5 GA = 123.3 + 21.5 Milk I-131(d) gA_14o(d) K (mg/l ) (d) CS-137(d) 3/7/73 <20 <20 1576 119 03 <20 <20 1787 124 <20 <20 1491 122 2 = <20 i = <20 E = 1618 i= 122 CA - 21.7 + 36.0 CA = 13.6 + 28.0 GA = 1419 + 208 GA = 119.7 + 15.9 Milk SR-90(c) 3/7/73 14 2 + 4 135 I 3 140 [ 4 2 = 139 GA = 122 + 34 ICI Water H-3 3/14/73 2600 + 500 3000 I 600 2300 [ 500 R = 2600 GA = 2177 + 591 Milk SR-90(C) I-131(d) BA-140(d) g(mg/g } (d) 4/10/73 136 + 2 149 <20 1456 136 T 2 120 <20 1532 136 [ 2 134 <20 1806 E = 136 5 = 134 i = <20 f = 1598 GA = 119.7 + 12.8 GA = 131.4 1 12.9 GA = 5.6 + 8.5 GA = 1468 + 169

TABLE B Continued Sample Nuclide Nuclide Nuclide Nuclide Type & Date (PCi/1) (pci/1) (pCi/l) (pCi/1) Milk CS-137 (d) CS-137(d) 4/10/73 115 117 + 2(a) 113 111 + 2(8) 112 i= 113 E = 114 GA = 112.7 + 13.9 GA = 112.7 1 13.9 Water H-3(CI 4/19/73 430 + 400(b) <400 <400 i = <410 GA = 1490 + 368 Milk SR-90(CI I-131(d) I-131 BA-140 ;d) 5/14/73 89 + 4 128 122 + 12(a) <20 tg 89 [ 4 127 131 [ 13(a) <20 a 92 + 4 135 <20 i= 90 i= 130 i= 127 i = <20 CA = 82.5 + 11.6 GA = 135.9 + 13.7 CA = 135.9 + 13.7 GA = 2.2 + 4.0 I I Milk K(mg/f)(d) CS-137 5/14/73 1693 148 1680 153 1570 154 i= 1648 X= 152 GA = 1467 + 143 GA = 144.0 + 10.2 ICI Water II-3 5/21/73 1 600M 13870 + 600 10400 [ 600 R = 12130 GA = 2973 1 524 Water II-3 (c) 6/13/73 2200 + 500 2000 7 500 2560 [ 500 E = 2250 GA = 2243 + 479

1 TABLE B Continued Sample Nuclide Nuclide Nuclide Nuclide Type & Date (pci/1) (pci/1) (pci/1) (pci/1) Milk SR-90(c) y_131(d) DA-140(d) K(mg/l)(d) 4/13/73 91 + 1(a) 151 <20 1696 112 7 1(a) 150 <20 1610 ~~ 157 <20 1596 i = 102 i = 153 i = <20 f = 1634 GA = 79.0 + 8.7 GA = 139.5 + 9.9 GA = 5.0 + 6.0 GA = 1540 + 141 Milk c;

.37 (d) 6/13/73 116 121 119 i= 119 GA = 118.4 + 9.4 Air Filter (a)

SR-90(c) 7/16/73 104 + 3 l f 95 { 2 4 i= 99.5 GA = 81 + 14 Milk 1-131(d) BA-140(d) CS-137 (d) 7/18/73 111 134 123 117 133 133 120 138 132 E - 116 i = 135 i= 129 GA = 118 + 13 GA = 153 + 12 GA = 116 + 8 Milk SR-90(d) y_131(d) BA-140(d) CS-137(d) 8/3/73 159 + 6 137 135 132 183 7 6 130 144 119 ~ 168 + 7 128 122 146 i = 170 i= 132 i= 134 i= 132 GA = 153 + 18 GA = 147 + 15 GA = 154 + 11 GA = 119 + 9 e Water wross p i 8/31/73 32.7 + 1.4 27.5 7 1.3 28.0 { 1.3 i = 29.4 GA = 24 + 6 4

2 1 e) 7 838 d1 409 + 785

0. 0 i/

) + ) li c 557 c

4. 2

+7[12 cC ( ( up 7 +7{98 7 21 N( 3 7 3 849 1 1 524 = 1 = = 885 = S 548 A S 220 A C 778 iG C 111 iG 1 9 4 1 e) 2 + dl 634 ) i/ + d 3 li ) 223 ( 53

0. 5 cC c

) 44 +7~+ 57 g 51 up ( N( 0 7 f 1 9 750 = g 510 = = 229 = R 888 A ( 654 A d S 767 iC g 111 iG eun i tno 2 C 2 1 e) 2 d1 + 442 i/ ) ) + li d 9 111 9 d 1 cC ( 03 p ( 01 up 0 41 + T[ 9 0 21 N( 4 1 s 8 4 1 = s 133 1 = L 900 = o = 000 = A 344 A r 108 A 222 A E B 111 iG G 998 i B <<< iG LBAT 2 0 2 3 3 6 1 1 2 e) + d1 + 000 + + 657 i/ 000 4 li ) 1 555 84 2 ) 1 8 111 8 d 40 3 222 21 cC d 42 69 a C +7{42 0 ( 01 ( 41 +T[9 up ( 41 ) 1 1 0 +[+1 s 7 N( 1 1 C 2 s 3 = ( 103 = s 222 3 = 9 = s 726 1 480 = 3 785 = o = 1 44 = 573 = o = 435 A 417 A r 000 00 A R 344 A r 837 I 111 iG H 222 iG G <<< i I 11 iG S 111 EG G 778 i e t ea lD 3 3 3 3 3 p 3 7 7 7 7 7 m6 7 / / / / / a / r 2 r 6 1 1 r 6 Se k 3 e1 e2 k 2 k 2 e 2 p l 1 t / t / l / l / t / y i / a 0 a 0 i 1 i 1 a 1 T M 9 W 1 W 1 M 1 M 1 W 1 Wh j lll ll l ll l:il, lL

)Il1Ii 7 8 2 1 e) +_ + dl I 8 C i/ I 20 ) 6 li ) 35 d_ 27 cC up f 51 I 71 N( / 1 1 1 g 150 = 3 = m 450 = 1 339 = 'A 875 5Q ( 555 s. 111 i I 111 e e) 9 d1 +_ i/ ) li c 878 19 cC ( up 7 19 N( 3 +[+ 1 1 = 085 = S 101 A C 111 i C deun i tnoC e) 9 9 d1 345 +_ + i/ ) d 111

2. 3 li

( 49 p cC 1 up 7 19 +7[ 53 N( 3 1 s 2 1 = s 411 = 191 = o = B S 201 A r 357 A C 111 i G G 222 iG EL BA 4 T 2 3 1 9 + 2 )) e) + 6 (aa 7 1 9 ( 1 7 1 dl 000 312 52 000 7 i/ 000 5 + +_ 000 1 + ) 22 444 7

7. 0

3. 5

7. 8 li 555 33 111 c

3 6 = o 101 cC 06 p up +T[ 62 +i{ 23 ( +{ 59 ) +T[7 111 83 N( 2 s 3 0 + 9 c { s 4 = ( 000 s +T[ = 6 1. 1 (' 604 = s 210 = 9 M721 = 3 000 = o = = o = 665 A r 503 A R 641 A 878 A r 204 A 222 iC C 333 i C S 991 EC H 111 i G c545 iG e ta eD 3 3 3 3 l 7 7 7 7 4 p& / / /. / 7 4 r / r / m r 0 r 6 '1 ae e3 e 2 k k 1 e 4 e 5 sp t / t / l / l / t 1 t 1 y a 1 a 2 i 2 i 2 a / a / T W 1 W 1 M 1 M 1 W 1 W 2 me* l ll lrl

(!ll: lllI Il l

TABLE B Continued Sample Nuclide Nuclide Nuclide Nuclide Type & Date (pCi/1) (pC1/1) (PC1/1) (pCi/1) Milk SR-90(c) CS-137(c) CS-137 (d) K-40(d) 2/22/74 192 + 6 207 +5 212 1656 210 7 7 224 7 5 223 1683 204 [ 6 202 [ 3 227 1646 i - 202 i-211 E = 221 E = 1656 CA = 187 1 27 CA = 211 1 14 CA = 211 + 14 GA = 1536 + 128 Water H-3(c) 3/15/74 3200 + 600 4000 + 600 3600 [ 600 E = 3600 GA = 3331 + 332 Milk

SR-90(c)

I-131(d) BA-LA-14 0 (d) K-40(d) 4/5/74 169 5 154 <20 1462 185 3 144 <20 1625 D7 160 5 152 <20 1513 I Fa E = 171 E = 150 X = <20 E = 1533 C3 CA = 167 1 22 GA = 152 i 19 CA = 11 i 14 GA = 1563 + 111 Milk CS-137(c) CS-137(d) 4/5/74 181 + 8 183 167 7 8 173 164 [ 4 189 % = 171 i= 182 GA = 170 + 15 CA = 170 + 15 Water Gross a Cross p 4/19/74 88 + 13 175 + 4 125 i 17 196 7 4 78 [ 12 139 [ 4 i= 97 i = 170 GA = 64 + 28 GA = 199 + 39 Water H-3(c) 5/24/74 2900 + 500 2600 7 500 3000 [ 500 f - 2833 l GA = 2669 + 236

TABLE B Continued Sample Nuclide Nuclide Nuclide Nuclide Type & Date (pCi/1) (pCi/1) (pCi/1) (pci/l) Air Filter Grossa Gross p SR-90(c) CS-137(C) 6/21/74 195 + 7 726 + 13 201 + 4 192 + 4 204 7 7 722 7 13 207 T 14 181 7 5 190 [ 7 705 [ 13 199 [ 5 181 [ 5 i = 196 i = 718 X = 203 E = 184 CA = 177 + 39 GA = 770 + 162 GA = 187 + 16 GA = 199 + 31 Air Filter CS-137Id) 6/21/74 194 202 197 i= 198 CA = 199 + 31 (a) Less than three aliquots completed. (b) Samples run at same time but results suspect since instrument problems (inter:nittent spectrum shif ting) s was evident. (c) Specific Nucfide Analysis: Error indicated in that calculated from counting statistics. The overall procedural error would be 10% or that shown whichever is larger. (d) Gamma Spectrometry: No error is included with values attained since the error varies from sample to sample depending on type and relative quantities of nuclides present. (e) GA is the grand average of all participating laboratories plus or minus the experimental sigma of all labs. (f) K is the EPA known value. l l

APPENDIX C A COMPUTER PROGRAM TO CALCULATE PILGRIM UNIT 1 OPERATING DOSES TO THE PUBLIC by Joel I. Cehn Environmental Sciences Group Nuclear Engineering Department Boston Edison Company s C-1

APPENDIX C A COMPUTER PROGRAM TO CALCULATE PILGRIM UNIT 1 OPERATING DOSES TO THE PUBLIC A computer program was developed using existing codes published in WASH 1258 (Appendix I Rulemaking Hearings), and Regulatory Guide 1.42. These codes were applied to the Pilgrim site to calculate potential and, in some cases, actual radiation doses to the public from radioactive effluent releases over a six month period. Immersion, ingestion and external doses are calculated for a hypothetical individual at the site boundary, the recreational visitor population, a hypothetical milk consuming infant, ar.d the resident population out to fif ty miles. The calculations are of the forms shown below. 1. Gaseous Release Doses e a. Immersion Dose (D7) Q.. C. X/Q. D = I 13 1 3 -s i,j where O is curies released of isotope i from release f3 point 3, C is dose conversion factor for isotope i f (from WASH 1258), and X/Q is the annual average atmospheric dispersion 3 factor from release point j to the receptor. b. Inhalation dose (DN) is calculated in the same form as D except C is the inhalation dose conversion 7 f factor for iodine isotope i, taken from Regulatory Guide 1.42. C-2

c. Milk Ingestion Dose (DM} DM" ij i !j j i,j where Q.. is the curies released of iodine isotope i 13 from release point j during the grazing

season, K

is the dose conversion factor for isotope i 1 (from Regulatory Guide 1.42), X/Q. is the atmospheric dispersion factor from 3 release point j to the nearest dairy farm, and R is the cloud depletion factor for release 3 point j (from Regulatory Guide 1.42), d. Population Dose (Dp) (D7+DN) K D = p p where 55 X/Q. P. 4s 1 1 i K = p X/0 J and X/Q is the atmospheric dispersion factor for i the release point to area i, P is the population of area i, and g X/Q is the factor used in calculating D and D 3 7 N* C-3

2. Liquid Release Doses (DL) L CF Lj= f fj i where DL is skin dose, 1 DL is whole body dose, 2 DL is GI-LLI dose, 3 DL is thyroid dose, 4 DL is bone dose, 5 DL is man-thyroid-rem 6 DL is whole body population dose, 7 L is the curies released of isotope i, and g CF., are conversion factors calculated by the ARRRG 1J Computer Code assuming a 3400 Mwt reactor, once-through cooling, and the parameters shown in Table 6B-8 in WASH 1258. 3. Direct Radiation Doses l a. Turbine Shine (DT) D (.006 +.005) CV T ff i where 0.006 is millirem per visitor at Overlook Area,* 0.005 is millirem per visitor at Shorefront Area,*

Measured with pressurized ion chamber.

See Semi-Annual Report

2, Appendix C.

C-4

C is plant capacity factor for month i, and 1 V is site visitation for month i. i b. Discharge Canal Shine (Dc S c" i (1.6) C V D f i where S. is the maximum concentration of isotope i in 1 discharge canal sediment (pCi/gm), 1.6 is the conversion from grams to square centimeters, C is the shine dose conversion factor for g isotope i (mr/hr per pCi/cm from WASH 1258), and V is the number of visitors spending one hour at the discharge canal during the reporting period. c. Transportation of Solid Wastes (D ) g D =S (1.8E-05) 900 s t where S is the number of solid waste shipments of greater than 0.01 curies, ~ 1.8E-05 is the dose (person-rem) to the public per mile of truck transport,* and OMaximum dose rate derived in, "Environmental Survey of Transportation of Radioactive Materials to and from Nuclear Power Plants" (AEC-DRS). C-5

900 is the mileage from Pilgrim Station to the waste burial site at Morehead, Ky. { C-6

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