ML20150E919
| ML20150E919 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/30/1973 |
| From: | BOSTON EDISON CO. |
| To: | |
| References | |
| NUDOCS 8804040179 | |
| Download: ML20150E919 (115) | |
Text
. . . ._- .. . . . - - - . - _ - -
REGULATORY"DOCKET FILE COPY !
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SEMIANNUAL REPORT NO 2 JANUARY I,1973 THROUGH JUNE 30,1973 DATE OF ISSUE: AUGUST 29,1973 J
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REGULATORY DCCEF.T FILE COPY idu P4SJ3 8B8*
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.f_s CONTENTS
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Secticy Page, I ABSTRACT 1 II Ih"IR0 DUCTION 2 III DESCRIPTION OF MONITORING PROCRAM 4 A. Air Sampling 4 B. External Gamma Exposure Rates 4 C. Milk Samples 8 D. Precipitation 10 E. Cranberries and Crops 10 F. Domestic and Recreational Water 10 G. Seawater 10 H. Marine Life 10 I. Bottom Sediments 14 J. Radioactivity Analyses 14 IV MONITORING DATA AND RESULTS 16 A. Air Surveillance 16 B. Gamma' Exposure Rates 22 C. Milk Surveillance 30
( D. Crops 30 ;
E. Domestic and Recreational Water. 30 F. Precipitation 34 G. Seawater 34 H. Marine Life 39 I. Bottom Sediments 39 V CONCLUSIONS 43 APPENDIX A: Results of Incomplete Analyses '
in Previous Semiannual Report 44 APPENDIX B: Method for Evaluating TLD Measurements 55 APPENDIX C: Results of Pressurized Ion Chamber Surveys 62 APPENDIX D: Tabulated Summary of Radioactive Effluents 79 I
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1 I. ABSTRACT
() The operational environmental radiation surveillance program continues to be conducted in accordance with ,the specifications in the Pilgrim Station operating license. Reactor operation during the reporting period averaged 85% of full power. Integrated radionuclide discharges in the gaseous effluent increased over the first semi-annual period due to the increased plant capacity factor. Liquid effluents were maintained at low levels by minimum liquid releases and improved radwaste treatment. A detailed post-operational radi-ation survey was made in January 1973 using a pressurized ion chamber and NaI spectrometer for comparison to a similar preoperational survey conducted in July 1972.
No significant increases in environmental radiation and radio-activity icvels beyond the station property were cvident in the O monitoring data.
Onsite radiation levels increased in areas close to the turbine building. The increases were attributed to direct radiation from the N-16 present in the turbine steam. The largest increase of any consequence (about 12 uR/h above background) occurred at the over-t look area, a visitors' area controlled by Boston Edison Company.
The average increased dose to the visitor population at this area over natural background is estimated to be 0.08 man-rem during this reporting period. The dose accumulated by all of the visitor population to the Pilgrim Station (22,000 persons) is estimated at 0.1 man-rem during the reporting period. The guard at the public parking area, the two attendants employed there and at the overlook i
, area, and the four groundskeepers cach received an estimated 0.6 mrem over the reporting period. The natural background exposure )
2 over this period was about 50 mrem.
() The Cs-137 concentration in the seawater in'the discharge canal was slightly higher than that of the intake canal although other reactor produced nuclides such as Mn-54, Co-58, 60 and Zn-65 were not detectable. The discharge icvels of Cs-137 into the canal has been similarly as low as these other nuclides so that the slightly higher Cs-137 concentration may or may not be due to reactor operation.
The bottom sediment in the discharge canal outfall has been sampled extensively and showed no significant radioactivity, in particular no Co-58, 60 activity, as found in the discharge canal and reported in the previous report.
II. INTRODUCTION
() This is the second semiennual report of the Pilgrim Nuclear Power Station operational environmental radioactivity monitoring program, covering the period from January 1, 1973 through June 30, 1973. The monitoring data are reported in accordance with the operational environmental monitoring and reporting requirements 'of Appendix A to the Pilgrim Facility Operating License DPR-35, Technical Specifica-tions and Bases.
Pilgrim Station began initial start-up operations in June 1972; however, approximately full power operation was not attained until November 1972. During the current reporting period, gross thermal power generation averaged approximately 85 percent of full power operation. The radionuclide emissions in the gaseous effluents increased above those reported during the previous 6-month period
( due to increased power generation, however, the emissions remained
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very low and were only a small fraction of the permissible limits.
( A summary of plant releases over the reporting' period is included here as Appendix D. More detailed operating information is reported in a separate semiannual report entitled, "Operating and Maintenance Report."
The monitoring program has been execut(d by Boston Edison Company with analyticai services provided by Interex Corporation and data evaluation by Environmental Analysts, Incorporated. Boston Edison per-sonnel collected most of the environmental samples, and delivered them to Interex. Sampics of some marine life were collected by the Massa-chusetts Division of Marine Fisheries. Lobsters were obtained from local fishermen. The thermoluminescent dosimeters (TLD) were changed monthly by Boston Edison Company personnel and read by Interex Corporation.
O f V In addition to the monitoring program specified in the operating license technical specifications, Boston Edison operated 4 additional air sampling stations and 20 additional TLD monitoring locations j during this reporting period. Additional environmental samples not required by the operating license were collected. These include an additional milk source, recreational water source, a precipitation station, and bottom sediments in the outfall'of the discharge canal.
A survey of the nonplume direct radiation fields was performed by Environmental Analysts, Incorporated, during January 1973. This semiannual report includes the results obtained in the specified I
monitoring program and from the supplemencary locations, as well as a brief summary of the measurement of the direct radiation fields.
The results are reported in Section IV of this report, and the results for incomplete analyses will be provided in a later report.
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The results of analyses listed as incomplete in the previous semi-l annual report are provided as Appendix A to th'is report.
III. DESCRIPTION OF MONITORING PROGRAM The environmental radiation surveillance program is being per-formed in accordance with the requirements specified in the operatin; license. A summary of the sampling media, locations, frequency of collections, and analyses is given in Tables 1 through 4. Additional )
details of the program are provided below.
A. Air Sampling Eleven air sampling stations were operated during this reporting periol. These stations include the seven locations specified in Table 4.8.1A of the operating license technical specifications and four additional onsiie air samplers. The air sampling locations are listed in Table 1, and their locations within the site environs are shown in Figures 1 and
- 2. Sampics are collected on glass fiber filters for airborne radioactive particulates and barium-impregnated felt filters (positioned behind the glass fiber filters) for gaseous radioiodine, at a sampling rate of approximately one cubic foot per minute. The filters and cartridges were collected weekly, and the flow rates and total volmac of the samples were recorded. The totc1 volume of the air collected on each sample is <etermined by reading the cumulative air volume recorded by a dry gas meter positioned in each sampling train.
B. External Gamma Exposure Rates.
Environmental monitoring of gamma exposure rates was per-formed using EG&G Model TL-15 thermoluminescent dosimeters.
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5 Table 1
- Air Particulates and Gaseous Radiciodine Surveillance Stations Oistance and Sampling Location Direction from Station Offsite Stations EastWeymouth(EW) 23 miles NW Plymouth Center (PC) 4.5 miles W-WNW Manomet Substation (MS) 2.5 miles SE Cleft Rock Area (CR) 0.9 miles S O
Onsite Stations Rocky Hill Road (ER) 0.8 miles SE Rocky Hill Road (WR) 0.3 miles W-WNW Overlook Area (0A) 0.03 miles S )
i Onsite Stations tiot Required by Operating License Property Line (PL) 0.34 miles NW Pedestrian Bridge (PB) 0.14 miles N l
EastBreakwater(EB) 0.35 miles ESE Warehouse (WS) 0.03 miles SSE I O ,
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- Pilgrim Site O Dosimeter (TLD) y Air Sampler and Dosfrreter (TLD)
IO miles Cape Cod Bay N
ovxbers 4 O Kingston(KS)
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Plymouth Center (PC)-
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O Figure 1. Locations of Offsite Exposure and Air Particulate Monitoring Stations.
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These dosimeters use calcium sulfate as the phosphor and are encapsula ted in glass with an aluminum cover. The dosimeters are changed monthly by Boston Edison personnel. The dosime-ters were annealed at Boston Edison's laboratory, placed in a lead-shielded container, and transported by car to the site.
The exposed dosimeters are placed in the shicided container and transported by car to be read out at Interex Corporation.
During this reporting period, 39 TLD monitoring stations were operated. In addition to the 19 locations specified in Table 4.8.1B of the operating license technical specifications, exposure rates are measured at 20 other locations as indicated in Table 2. Seventeen of the monitoring stations are offsite, with the remaining 22 stations located within the site bound-aries. The locations of the offsite and onsite monitoring stations are shown in Figures 1 and 2. A pair of dosimeters is used for each location so that continuity in monthly measurements is assured.
C. Milk Samples During this reporting period, one-quart milk samples were collected weekly from a dairy in Plymouth, a dairy in Bridge-water, and a grocery store in Plymouth. The veckly samples are composited into a monthly sample for radionuclide analyses.
Beginning in May, a separate two-quart sample was collected at i cach location for immediate radiciodine analysis.
The locations of the two dairies with respect to the plant are shown in Figure 3. The Bridgewater dairy, which is approx-l imately 20 miles west of the plant, serves as a control or !
O background station.
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Table 2 i
External Carra Exposure Surveillarce Stations (TLD) l I Distance and I l
- Dosireter location Direction from Statien l
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- Offsite Stations '
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EastWepouth(EW) 23 miles IN Kingston (KS) 10 miles W!N i Sagamcre(CS) 10 miles SSE S i
Plyrouth Airport (SA) 8 miles WSW North Plymouth (tiP) 5.5 miles WW PlymouthCenter(PC) 4.5 miles W-WW South P1 outh(SP) 3. miles WSW Manomet MS 2.5 miles SSE Manomet ME 2.5 miles SE Manomet l'P 2.25 miles ESE-S Cleft Rock Area (CR) 0.9 miles S l
Offsite Stations i;ot Required, by Operating License Bayshore Drive (BD) 0.8 miles WW Emerson P. cad (Eli) 0.96 miles SSE Whitehorse Read (WH) 1.28 miles SSE Manomet Beach (t'3) 3.5 miles SSE College Fend (CP) 6.5 miles SW StandishShores(SS) 5.9 miles IN Onsite Stations
! Rocky Hill Road (ER 0.8 miles SE Microwave Tower (MT 0.38 miles S Rocky Hill F.ead (WR 0.3 miles W WW Rocky Hill Road (B) 0.26 miles $$E PropertyLire(H) 0.21 miles SSW Property Line (1) 0.14 miles W PublicParkingArea(PA) 0.07 miles N NNE Overlook Area (OA) 0.03 miles S Onsite Stations Not Required by Operating License 1
0.03 miles SSE i Warehouse Property (Lir.e (WS)(FL) 0.34 miles tN I
Station F) 0.25 miles tu Station (0) 0.37 miles h w l PedestrianBridge(PB) 0.14 miles N i l
Station (A) 0.24 miles WSW Station 0.4 miles W Station 1.6 miles S :
I Station 1.6 miles 5-SSE Station K) 1.7 miles S-SSE EastBreakwater(EB) 0.35 miles ESE Station (L) 0.35 miles ESE-SE Station (C) 0.35 miles SE
- Hall'sBog(HB) 0.35 miles SE-SSE.
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10 D. Precipitation Monthly precipitation sampics collec'ted in Plymouth have b(~N been analyzed for radioactivity concentrations. This sampling ,
is not specified in the operating license.
E. Cranberries and Crops Cranberries and other crops--including potatoes, cabbage, lettuce, corn, and hay--are collected during. annual harvests at nearby farms in Plymouth, Manomet, and Bridgewater. Figure 3 indicates the approximate sampling locations. During this reporting period, only samples of hay and cabbage were availabic.
F. Domestic and Recreational Water Water samples have been collected monthly at the locations listed in Table 3. The sampling locations included the four O
\ _/ specified in the operating license plus one additional station at College Pond, G. Seawater During this reporting period, composite seawater samples were collected at the Pilgrim Station intake and discharge channels, and as shown in Figure 3. The monthly sampics and quarterly composite samples are analyzed as specified in Table 4.
H. Marine Life Various sampics of marine life indigenous to the area of the site are collected during commercial harvesting seasons.
These samples include rock weed, Irish moss, lobsters, flounder, pollack, crabs, clams, and other marine life when O availabic. Marine life samples from the vicinity of the
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Pilgrim Station O Domestic and Recreational Water
@ Seawater '
O Crops 9 South Weymouth e Milk g Prnrir4 tat 4-- 15 mi;e, 10 m ,
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OO Bridgewater Plymout -
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- 0) Onsite yrisc111a Coach White l')rse Beach i 0 0 Manome O j College i Pond l
O Figure 3. Aquatic and Terrestrial Surveillance Stations.
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U Table 3 Terrestrial and Aquatic Surveillance Stations Distance and Direction Sample Type Sample Location From Station Milk Plymouth 3.5 miles W Local Store (a) ...
Bridgewater 20 miles W Cranberries Manomet(BogF) 2 miles S Manomet(BogC) 2 miles SSE Manomet(BogE) 2.4 miles SE Panomet (Bog D) 2.75 miles SSE-S Crops (potatoes, cabbage, Plymouth 3.5 miles W 1ettuce and hay) Manomet 2 miles SSE Bridgewater 20 miles W Precipitation SouthPlymouth(a) 4.75 miles W Domestic and recrea- Deep Water Pumping Station 4.75 miles W ticnal water (Lout Pond Well and Little .
South Pond)--Plymouth Warner's Pond Pumping Station 2.75 miles SSE (ManometWell)--Manomet 24 miles WNW-NW GreatPondPumpingStation(b)]
[ Great Pond--South Weymouth College Pond (3) 6.5 miles SW Seawater Discharge channel Onsite Cooling water intake Onsite Priscilla Eeach 0.8 to 1.6 miles ESE-SE I i
White Horse Beach 1.6 to 2.7 miles ESE-SE !
Partne life Area surrounding the station Sampling ranges from l (lobster, fish) 2.4 miles W-WNW to l 2.9 miles ESE-SE i Bottom sediment Area in vicinity of discharge channel outfall
- a. Additional stations operated during reporting period although not required by operating license ,
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- b. Control station.
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Table 4 '
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Types ard Frecceccies of Analyses Planned Sample Type Frequency of Collection and me,Ser Anasysis Analysis Type ,
Air particulates (11) Gross beta Weekly Continuous Gross gama on filter corposites frce each station Monthly Gama spectrum (a)
I-131 Weekly Gaseous iodine (11) I-131 Wecil'y Continuous Garms exposure (39) Dosimeter reading Monthly Continuous Domestic water (5) Gross tieta and gross garna Ponthly Grab Gama spectrun (a)
I-131, Sr-90, H-3 Ponthly Precipitation (1) Grcss beta and gross gama Monthly Continuous Gaw.a spectrum (a)
I-131, Sr-93 H-3 Monthly Seawater (3) Fractior.al gross beta and gross gam.a Monthly Continuous (DC)*
Gama spectrum I-131 Monthly Grab (others)
Sr-90 Cs-137. H-3, Mn-54, In-65, Co-58, and Co-60 Quarterly ,
Marine life (c) Gross beta and gross gama Each sahple Gama spectrum (b)
I-131, Sr-93, Cs-137, Mn-54, Zn-65, Co-58, and Co-60 Each sample Bottom sediment (2) Gross beta, gross gama, and gam.a spectrum semiannually Grab .
Milk (3) I-131, Sr-90, Cs-137, Ba/La-140 Monthly Crops Gross beta, gross gam.a, and gama spectrum Annually Sr-90, Cs-137 Annually
- a. Selective gama analysis will be rade based on gross gama results, with at least one ga na spectrum analysis made each quarter.
- b. A gama spectrum analysis will be r.ade at least ance during each sa=pling period.
- c. Sacales will be collected durir.g their comercial harvesting season. ,_.
DC = discharge channel. w
14 station are collected by the Massechusetts Division of Marine Fisheries, Battelle Clapp Laboratories,' and by local fishermen.
I. Bottom Sediments Bottom sediment samples from the vicinity of the discharge outfall are being analyzed semiannually as specified in the operating license. During this reporting period, samples were co11cceed by Battelle Clapp Laboratories at 12 locations ,
in the discharge outfall, as shown in Figure 11. At each ,
location, a diver collected surface sediment (approximately one inch in depth) within a circular area approximately 10 feet in diameter. Prior to this, bottom sediment was obtained from the discharge canal. However, the swift current of the discharge water has washed all the sediment out and sediment sampics can now be obtained only in the outfall.
J. Radioactivity Analyses The analyses of radioactivity in environmental samples are being performed by Interex Corporation. The types of sample analyses and frequency of collection are summarized in Table 4 Table 5 lists the sample type, analyses performed, approx-imate sample sire, detection limits, and the estimated errors for the analyses performed by Interex Corporation.
Interex Corporation utilizes several programs to assure
- quality in the radioanalysis of environmental sampics. They are, The Environmental Protection Agency (EPA) Standards Program for counting equipment calibration, The EPA Quality Assurance Program for milk and water counting..and the Interex Quality Assurance Program. The later consists of running D
sampics, spiked by the department manager, through radiochemical 4
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- Table 5 t J
' Envirerrental Sarole Analysis Parameters (a)
Sample Type Analysis. Detection Limit Aliquot 1 Error Air particulate Gross beta 4 x 10*3 pC1/m l 10,200 ft3 110 !
Gross gama 2 x 10*3 cpm /rn3 (b) 10,000 f t3 110 3 10,800 f t3 110 lodine-131 1 pC1/m Nonsalir.e water Gross beta 1 pCi/1 1,000 ml 110 Gross gama 5 cpm /1 ICI 4,000 m1 110 Gama spectrun (d) 4,000 ml- l Strontium 90 0.5 pC1/1 1,000 ml 115 i;
Tritium 2.5 pCi/ml 4 ml 110 Crops and Gross beta 0 2 pC1/g 20 g t10 I
- ' I "' " I' Gross gama 0.01 cpm /g ICI 1,000 g 110 Gama spectrum (d) 1,000 g ,
0.005 pCi/g 100 g 110 l Cesium-134.-107 0.1 pC1/g 100 g 120 Manganese 54 0.1 pC1/g 100 g 120 :
Cobalt-58 0.1 pC1/g 100 g 120 i Cobalt 60 0.1 pCi/g 100 g 120 ,
Zinc.65 0.1 pC1/9 100 g *20 l Seawater . Gross beta 60 pC1/1 30 g 120 !
1 Fractional gross beta 5 pC1/1 500 m1 120 I Gross sama 5 cpm /1 IC) 4,C00 m1 110 f I Cama spectrum (d) 4,000 ml ;
a Tritium 2.5 pCi/m1 4 m1 110 Strontium-90 0.5 pCi/1 15,000 mi t15 i j Cesium-137 0.05 pC1/1 15,000 ml 115 I Manganese-54 5 pC1/1 1,000 m1 120 Cobalt 58 5 pC1/1 1,000 ml !20 Cobalt-60 $ pCi/1 1,000 m1 220 I 2ir.c 65 5 pCi/1 1,000 m1 120 I
lodine-131 5 pC1/1 1,000 ml 115 Milk Strontium-90 0.5 pC1/1 1,000 ml- 115 Cesium-137 1 pC1/1 1,000 mi t15 j# Barium-140 $ pC1/1 1,000 m1 115 i lodipe-131 5 pC1/1 1,000 m1 t15
) Bottom sediment Cross teta 2 pC1/g 1g 115 h Gross gama 0.02 epm /g 1,000 g !10 strontium-90 0.005 pct /g 100 g 120 Background Gama eroosure 1-month radiation rate (c) 1 >R/hr exposure 110 Ct !
. a. Provided by Interex Corp. 65 Woerd Avenue, Haltham, Mass. (formerly ICN/Tracerlab).
i b. In the counter used. I com corresrcres to 2.2 pCi of cesiv> 137. .
1 c. In the counter used. I com corres;cnds to 9 pCi of cesium 137. !
- d. Sensitivity cerencs on tne specific nuclide and the presence of interfering nuclides.
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A typicel sensitivity is 30 pC1/sarple ccunted.
- t. F.easured with thernoluminescent dosimeter.
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- procedures, unknown to the analysts involved. Also, sole '.ed
,O field sampics are analyzed in duplicate'to check precision.
%J IV. MONITORING DATA AND RESULTS The results of environmental radioactivity measurements performed during the semiannual reporting period (January 1,1973-June 30,1973) are presented in Tables 6 through 16 according to sampling media and analyses performed. Although samples of various media have been routinely collected, radioactivity analyses were not complete for all samples for inclusion in this report. All sample analyses indicated to be incomplete will be reported in a later report.
Figures 4, 5, 6, 7, 9, 10 show the measured environmenta". radioactivity levels in selected media from 1970 through the present reporting period. These graphs facilitate comparisons of radioactivity Icvels during plant operation with the levels measured prior to plant start-up and also show some seasonal trends associat.ed with f allout from nuclear weapons testing.
The sample results listed as incomplete in the previous semiannual report are provided in Appendix A. For the sake of continuity, the complete tables of sampling results have been included.
A. Air Surveillance The gross beta and gross gamma concentrations measured in weekly air particulate samples for this reporting period are presented in Tables 6 and 7, and the iodine-131 concentrations are presented in Tabic 8.
Figures 4 and 5 show the average monthly gross beta and gross gamma radioactivity concentrations in air particulates
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( at East Weymouth and at the overlook area. The trends shown
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Table 7 ,,
Air Particulates--Gioss Gama Concer.trations in Monthly Composites (c;n x 10-3)(a)
Collection Control Offsite Onsite Feriod East Plpouth Lieft F.anonet Rocky tiill Property
- Overlook Pedestrian
- East
- Rocky hill (1973) Werouth Center Rock Area Substation Road (est) Lir.e Area Eridge Breakwater Rcad (East) Warehouse
- January 7 7 7 5 9 7 5 8 9 10 13 February 2 9 2 7 6 5 6 6 17 12 6
- r. arch 5 9 8 5 4 <2 4 4 7 8 <2 Apr11 4 8 <2 8 5 <2 3 11 <2 6 6 t'.ay <2 <2 <2 <2 <2 <2 <2 <2 <2 <2 <2 June 4 3 3 3 2 <2 <2 3 5 <2 <2
- a. Error is i 2 or 10 percent, whichever is larger.
- ?:st required by operating license.
~
O O O Table 8 Caseous and Particulate Iodir.e-13' in Air Sa ples (pC1/m3 )(a)
Collection Control Offsite Onsite Peried East Plymouth Cleft Vano.et T Rocky Hill Property
- Overloot Pedestrian
- East
- P.ocky Hill (1973) Wercuth Center Rock Area substa tien Road ('.'est) Lire Area j ridae Breakwater Road (East) Warehouse
- Jan. 3-Jan. 11 <1 <1 <1 <1 <1 <1 <1 <1 <1 <1 <1 Jan. 11-Jen. 18 " * * * " " " * * *
- Jan.18-Ja n. 25 " " *
- Jan. 25-Jan. 31 " " "
" " " " " " " =
Jan. 31-ftb. 8 Feb. 8-reb. 15 Teb.15-Feb. 22 * " * * * *
- Feb. 22-ftb. 23 " " " " " * " * * " "
Feb. 26-ftar. 8 ita r . 8-ibr. 15 (b) *
- Var. 15-rar. 22 * * * * " * * *
<1
- " =
Ysr. 22-rar. 28 " " " " " " " " " "
thr. 23-Apr. 5 (b) *
- A pr. 5-tpe. 12 (b) <1 A p r. 12-/ p r. 19 (b) -
Apr. 19-1.;r. 25 <1 A;.r. 25-:by 3 r.ay 3-fby 10 (b) thy 10-r.iy 16 <1 t'a y 16-?%y 24 "
Fay 24-t'ay 31 May 31-Jur.e 7 * " * * * " " "
June 7-June 14 " " " " " " " " * " "
J. re 14-Jane 21 " "
June 21-Jure 28 a.1-131 concentrations were less than the detection limit in all sar"ples.
- b. f:o sample.
Not required by operating license.
o
O I O
I Imonthlyhigh---
monthly average mor.thly low _ (pct /m3 )
l
' g 1.0~ o gross gaw.a (cpm /m3 ) -
g
_ & less than 0.01 (cpm /m3) ..
Preoperationalg Operational 4- less than 0.02 (cpm /m3 ) a ~
l
. o I
~
' ~
o . . I l -
o - o o ..
l
.. o o I
~
b . . . G
\ g .
--g -.
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o l4>
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I A a a I a 1973
- 0. C
I ^ ^ N
- ^ ^ ^ ^^ ^^^ "
- l A l a l J i a l a fii o l u l D JlrinlAlnIJIJiAlSl0!NlD Jl Fl MI Al Mi J Jl Al 510l NlD J l F I MI Al Ml J Figure 4 Radioactivity in Air Particulates (East Weymouth).
O O O i
e renthly bish -
I
. rentnly average Ceta I conthly low - (pC1/m3 )
1.0_ a sross sa.ra (cp=/m3) 3
. Preoperational g Opera tional t
{ A less than C.C1 (c;r/m )
~~
4 g y
- 4. less than 0.C2 (cps /m3 ) <, ,3 g
, .. l o o - - ..
l 1
[ ,,
o .
3 o o 4,
-- ~
l g
g ,
g o o i " o ' a ,,
1.
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3 a o o g 0.1-
~
o 3 u
o . -
L "*
4> .= < 4> =
E -- --
.. a o >I .. -
- 6
~
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y - A a l .
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l 1
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19 0 1913 u 0.0' 1971 s ,19 a72 , , , , , s,,, a ~
MI Al Ml Jl Jl Al $10l Nl D Jl Fl Mj Al Ml Ji Jl Al 5101 WI D Jj Fj N) Al M[ J, Jl A[ 5l 0l H j D J IF lM l A jMlJ Figure 5. Radioactivity in Air Particulates (Overlook Area). .
_- s
I '
22 in these figures are representative of those observed at the
() other stations. In general, the gross beta and gross gamma concentrations continuad to decrease in 1973. The character-istic seasonal increase in airborne particulate radioactivity during the late spring, due to increased fallout from early nucicar weapons testing, was not evident in the samples collected through June. Both particulate and gaseous iodine-131 concentrations were less than 1 picoeurie per cubic meter.
The measured airborne radioactivity concentrations from onsite and nearby sampling locations were coc. pared with the concentrations measured at more distant or control locations.
There was no significant difference in the measured concentra-tions for these two groups of monitoring locations.
B. Cnmma Exposure Rates The environmental gamma exposure rate measurements at TLD stations from January through June 1973 are presented in J
Table 9. The reported exposure rates include contributions due to self-irradiation inherent in this type of dosimeter.
Absolute determinations of self-irradiation contributions for i
cach individual dosimeter have not been made. However, a j set of three or four dosimeters has been designated for exclusive ,
use at each monitoring location, and the relative self-irradia-I tion of the dosimeters in each set has been measured, i t Exposure rate measurements at each location have been normal-ized for relative self-irradiation ef fects to provide continuity of measurements. Information provided by the dosimeter manuf ac-4 turer indicates that typical scif-irradiation rates for these 1
dosimeters are 6 to 8 microroentgenr4 per hour (uR/h). l
23 O
V Table 9 External Gvra Exposure Rates January June 1973 (uR/tr)(8)
Onsite Monitoring January February _ _ March _ April. May June locatiens Over1cokAres(OA) 32.8 27.8 31.6 24.8 27.8 28.2 ,
Public Parking Area (PA) 15.4 17.4 16.4 14.8 16.2
- Pedestrian Bridge (FB) 17.1 19.2 (b) 19.8 (c) 20.0 (c) 19.5
- Rocky Hill Road (A) 15.2 14.1 16.0 15.9 13.0 (t:)
Rocky Hill Road (B) 18.2 16.4 18.5 17.2 14.9 16.0
- East Breakwater (EB) 17.1 16.4 16.3 16.9 14.5 15.6 Micrcwave Tower (MT) 16.9 15.7 17.6 16.3 14.8 15.1
- Property Line (C) 15.5 14.4 16.3 15.0 14.0 14.2
- Property Lire (HB) 17.4 16.1 17.4 16.5 14.6 15.2
- Property Lire WH) 14.9 14.6 15.4 15.2 12.5 13.7
- Property Lire EM) 16.6 15.5 (c) 15.3 (c) 14.6
- Property Line E) 14.4 13.5 15.1 13.8 12.3 12.6 Property Lirc Hs 18.5 17.0 19.0 17.6 13.9 16.6
- Prcperty Lire GL 13.6 13.2 14.1 14.2 11.0 13.3 Property Lire 1) 16.3 15.5 17.5 16.5 14.0 15.5
- Prcperty Line (F 16.8 15.5 17.9 17.6 14.3 16.2
- Prcperty Line D 16.2 15.0 (c) 15.8 13.7 15.0
- Preperty Line J 15.7 13.7 16.7 14.0 12.7 13.6
- Property Lir,e K) 15.6 13.7 16.5 (c) 12.3 13.5
- Property Line PL) 17.3 17.3 17.3 15.3 14.9 14.9
- Warehouse (WS) 15.8 14.4 18.6 14.7 14.3 16.1 Average onsite exposure rate per renth 17.2 16.0 17.7 16.4 14.4 15.8 w
Offsite Penitcrin9 Locations January February Parch April K9y June East Weymouth (EW) 15.9 14.9 16.6 15.5 13.5 14.1 Kingston (KS) 15.9 15.1 16.6 15.6 14.7 14.2 ;
Sagarcre (CS) 17.0 15.5 8.2 15.8 13.6 14.5 PlynouthAirport(SA) 12.9 13.0 13.2 13.1 10.9 11.7
- 0uxbury (55) 14.7 13.4 15.4 14.0 13.0 12.7
- Plyrouth(CP) (11.8)(d) 14.7 16.3 15,3 14.0 13.7 ,
horth P1Fouth (f P) 16.7 16.6 '45.8 15.6 14.4 l Plynauth Center (FC) 12.3 15.2(*)
4.3 12.5 12.0 10.7 10:5 South Plyrcuth (SP) 16.0 14.5 16.3 15.6 14.3 13.9
- Manccet (l'3 15.1 14.2 16.0 14.2 13.3 12.9 Panoret (l's 16.9 15.5 17.0 16.1 14.4 14.8 l Manoret (l'.E 18.7 16.6 18.7 17.3 14.7 15.6 Manotet (t:P) 15.4 14,8 16.3 15.0 14.0 13.4 Clef t Reck Area (CR) (12.3)(d) 15.2 17.0 15.5 14.8 14.8 ,
Rocky Hill Fead (ER) 17.7 16.4 (c) 16.9 15.7 15.2 l
- B4yshore Drive (ED) (13.5)(d) 16.4 (c) 14.7 15.7 15.5 i Rocky Hill Road (LR) 16.1 22.3 17.1 15.4 13.5 14.1 i Average offsite exposure rate per ranth 15.8 15.5 15.6 15.2 13.9 13.9 1
- a. Gross exposure rates which include inherent dosimeter background exposure rates,
- b. No backgroand adjust. ent. new dositeter is used.
- c. Reading lost dse to p:or contacts.
. d. lepreper reader setting..value not included in averages.
- e. Abnen al reading d.e to condensatien.
w,/
- hot required by cperating license.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _
24 l A detailed evaluation of the dosimeter results was made to determine if increased exposure rates were detectable at the monitoring stations. A description of the methods used in evaluating the data is provided in Appendix B. The measured exposure rate at some onsite locations appeared to have increased due to plant operation. Except for the overlook area, the exposure rate increases, were very small and were near the detection limit. Figures 6 and 7 show the measured exposure rates at two offsite and two onsite locations, respectively, including the overlook area. From October 1972 through June 1973, the measured exposure rate at the overlook area averaged approximately 12 uR/h above background due to plant operation. The average measured exposure rates at the public parking lot (PA), Rocky 11111 Road (B), and Location 11 (Re f. Fig. 2) appear to have increased approximately 1 uR/h above background levels when evaluated by the methods outlined in Appendix B. The increased exposure rates at other onsite stations averaged less than 1 uR/h. Figure 8 shows the esti-mated average increase in exposure rates during October 1972 through June 1973. Based on the indicated exposure rate changes, isoexposure rate contours are suggested. The esti-mated isoexposure rate contours should not be construed as exact, but are only approximate indications based on the interpretation of the exposure rate data. The increased exposure rates measured at the public parking area, overlook area, and Rocky 11111 Road with the TLD monitors are consistent with the results of the pressurized ion chamber survey con-O ducted in the early part of the reporting period and summarized
25 25-l PreoperationalIOperational I
l f)
V I I
20- 1 I
I h
e o ol o O
- g ooo lo o n n p 15- o -
l
& I o T 0 l
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l I 7.,
l C
! l l l 1971 19 72 1973
$l 0 lN l 0 JlFlMlAlMlJ JlAl5l0lNlD East Keynouth J lF lM l A (H lJ A
'y 25 ;
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i 20 - 1 I
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- I o o o b o oo lo o 0 o 0
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l Sl0lNIDIT}rlHlAlH kMAj5(0lNl0 JlFlM(AlHlJ 1 South Plyeouth figure 6. Offsite C ms Exposure Rates (East Weynouth and South Plyrouth).
35 26 Preoperational 't Operational 1 0 (M
l o t) l 30 - 1 -
1 i l 6 l c i y o o l o 25 - o l . l t
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, 1: 1971 19 72 l 1973 6 0[NID J [F lH I A IM I[ J I A IS l0 lN ID IJ IF lH I A lH lJ l Overlook Area O 'o -
Preoperational IOperational I
l l
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1
$ lU N I D [dl[f5I A l H (J l J'[ A l $ } O } N l D l J l F l H ( A l H lJ j Pedestrian Eridge l Figure 7. Onsite Gar.ma Exposure Rates (Overlook Area and Pedestrian Eridge). l l
i
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- N o 63 us
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]
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' l_ ~!-
- 28 in Appendix C.
j) The overlook area was reopened for v'isitors in April. Two attendants, who began working the last half of June, ~ spend 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week at the overlook area and the public parking area. The dose to these two workers during'the last_two weeks of June has been estimated. The net exposure rate, above background, at the overlook , area for June 1973 is estimated to be 14.7 uR/h. The not exposure rate at the_public parking area was estimated to be 1.3 uR/h. Each worker spends approx-imately one-half of his work week at the overlook area and_the remaining time at the public parking area. The dose-to these two attendants from plant operation during the last two weeks of June is calculated to be approximately 0.6 millirem.- For dosimetric calculations, it is assumed that an air exposure of 1 roentgen is equivalent to a whole body dose of 1 rem.
A guard worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week at the public parking area during April, May, and June. The net exposure rate at this area is estimated to be 1.3 uR/h. The guard is, therefore, '
estimated to have received a dose of 0.2 pillirem per month.
Two workers from the Manomet Bird Observatory involved in a study spent from 6 to 73 hours8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br /> per month on the site.from February to June. It is c'stimated that one of these workers accumulated approximately 0.2 mrem and the other, approximately l 0.1 mrem during this period.
The net exposure rates at the overlook area and in the i r
public parking area result in only a small dose increase'to [
visitors. Dose estimates to the public have been made assuming that each visitor at the overlook area remains for an average T
i i !
.,-m. ew-- - ++ -
e-- -+s--vr+ene-
- 5pw = e -- n w eHr 4 e- - - -
e- s-m a----r- w-rv w -y+'s= -
v-
29 of 15 minutes. The average increased dose to an individual visitor at the overlook area during Apr'il, May, and June is (b'
estimated to be 0.003 millirem in April and 0.004 millirem during May and June. The estimated numbers of visitors at the overlook area during April, Fby, and June were 1,000, 3,000, and 18,000, respectively. Accordingly, the estimated population doses at this location from plant ; operation during April, May, and. June are 0.003 man-rem in April, 0.01 man-rem in May, and 0.07 man-rem in June..
The dose to visitors at the public parking area was calcu-lated assuming that individuals remain there an average of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during each visit. The_ increased dose during each 1-hour period would be approximately 0.001 millirem. It is conceiv-able that some individuals might visit this area (e.g. , to fish
(h
(/ _
from shore) for 20 to 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in.a month. An individual remaining at that location for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per month during this period is estimated to have received a dose of approximately 0.05 millirem each month. The estimated number of visitors at the public parhing area during April, May, and June was 1,000, 3,000, and 18,000, respectively. Accordingly, the es:imated population doses at this area due to plant operation are 0.001 man-rem for April, 0.003 man-rem for May, and 0.02 man-rem for June.
The estimaced doses to individuals and the general popula-tion are considered quite small compared even to variations in normal background levels. The range of monthly exposure rates measured at East Weymouth (20 miles from the station)
\_ ,/ '
has varied over 3 uR/h. Therefore, the monthly dose to
30 residents from background radiation has varied by over 2
3 millirems per month. '
(O C. Milk Surveillance Table 10 lists results of radiochemical analyses for cesium-137, strontium-90, iodine-131, and barium / lanthanum-140 in milk sampics from January through June 1973. Figure 9 shows the concentrations of strontium-90 and cesium-137 in milk samples from Plymouth from June 1970 through June 1973.
The seasonal trends described in detail in the previous semi-annual report are evident. The concentrations of iodine-131 and barium / lanthanum-140 in milk samples for this reporting period were less than the minimum detectabic concentrations listed in Table 5.
Increased concentrations of these fallout radionuclides (em,) may occur in subsequent reporting periods as a result of recent atmospheric nuclear weapons testing by France and China.
D. Crops The radioactivity 1cvels in crop samples collected during this reporting period are presented in Table 11. During this winter and spring period, only sampics of hay and cabbage were collected late in the month of June. The majority of the crop sampics are collected during the summer growing season and will be reported in the next semiannual report. The gross beta and gamma concentrations in the hay sampics are essen-tially the same as during the previous reporting period and prior to plant operation. -
E. Domestic and Recreational Water
(^T
\- # Monthly grab samples were collected from Great Pond, Little
31
[)
'u J Table 10 Radionuclide Concentrations in itilk (pCi/1) l Collection Plymouth Bridgewater Period (County (Bridgewater Local Analysis (1973) Farm) Farm) Store 4 Cs-137 January 14 1 9 1 15 1 February 11 1 10 1 11 1 March 14 1 10 1 6 1 April 20 2 14 1 7 1 May '
- 14 1 20 2 5 1 June 19 2 15 2 9 il -
Sr-90 January 9 1 8 il 10 1 February 16 2 10 1 7 1 March 5 1 7 1 6 1 April 7 1 6 1 5 1 liay 10 1 7 1 8 1 June 15 1 9 1 11 1 r3 1-1 31 January <5 <5 <5 k/ February <5 <5 <5 March <5 <5 <5 April <5 <5 <5 May <5 <5 <5 June <5 <5 <5 Ba/La-140 January <5 <5 <5 February <5 <5 <5 March <5 <5 <5 April <5 <5 <5 May <5 <5 <5 )
June <5 <5 <5 l
t 0
L)
32 20
+1 standard deviation f
[ renthly average 1 standard deviation l,
I g
15- o -
g ~
5 l.
s l E
10-f i -
b f i 1
l l f
-L a
r, 1
I 1 ,E {
E f{ . >
Preoperational Operational
l
1970 1971 1972 1973 0
J lJ j Al Sl 0ll1l0 J lF lMl A jl1lJlJ lA IS l0l Nl D J lF jlll Alltl J J l AlSl0l ftlD J lF lM lA lH lJ Strontium-90 ,
\
+1 standard deviation I conthly average l
-1 standard deviation o 8
30- . l I
b o I I
b I !
h20- - I h
{,
I
} (( l hh k I h r
s I y
- I
-} 1 i
II g l
10- I Preoperational Operational g, 0
1970 1971 1972l M73 Jl JI AlSl0h l0 JIF I:4 lA IMldlJl AIS l0 lN l3 JlF l:il A l!!lJ lJI AlS l0 lNID J lF lM lA lH ld l Cesium-137 Figure 9. Concentrations of Strontium-90 and Cesium-137 in Hilk (Plymouth).
O g O **M *Y* 1* M N " .h '9
a
('>')
- s. s_- p/
s.
Table 11 Radioactivity in Crops (a)
Collection Gross Gamma Gross Beta Radionuclides (pCi/g)
Sample Type Location Date (1973) (cpm /g) (pCi/g) Sr-90 Cs-134 Cs-137 I-131 Hay Bridge.ater June 21 0.11 10.01(b) 22 2 .53 .05 <0.1 <0.1 <0.5 Plymouth June 28 0.21 0.02(b) 18 2 .49 .05 <0.1 <0.1 < 0. 5.
Cabbage Plymouth June 28 <0.01 2.3 0.2 I (c) I I <0.5
- a. Concentrations are expressed with one standard deviation counting error.
- b. Gamma spectrum indicates ruthenium-106 and potassium-40.
- c. I indicates incomplete analysis.
=am 4
34 South Pond, College Pond, Lout Pond well, and Manomet well.
1 1
() Table 12 lists the measured radioactivi'ty concentrations in
%s l water samples collected during this reporting period.
Figure 10 shows graphically the gross beta concentrations in water samples from Little South Pond. The concentrations in the water samples appear to be slightly lower than in earlier years.
F. Precipitation Monthly precipitation samples collected in Plymouth were analyzed for radioactivity concentrations. The results of the analyses are presented in Table 13. The deposition rates of gross beta radioactivity are within the range measured througtout the United States.
G. Seawater (A_/ ,
Composite seawater samples were collected monthly from the Pilgrim Station cooling water discharge channel and intake.
Grab samples were also collected in June at White llorse and Priscilla Beaches. The results of the radioactivity analyses are presented in Table 14. The radioactivity concentrations were generally less than the detection limit for the analyses performed monthly. The quarterly sampics are analyzed for specific radionuclides, and analyses of cesium-137 and strontium-90 indicate higher concentrations of cesium-137 in the discharge channel than in the intake during the first quarter. The discharge canal level of 0.57 pCi/1 is essen-tially equal to the 0.63 pCi/1 background level in the July -
,-s September 1972 intake canal composite. The increased cesium-137
'# concentration measured in the discharge may be due to station
r l er O
Os Us Table 12 Radioactivity in Donestic and Recreation k'ater Collection Great Little College Lout Pond Mancret Analysis Period Pond (>o"th Pond Por.d Well __ Uell Gross Beta January 4.2 1.0 '. . ) 1,0 2.0 1.0 <l .0 <l.0 (pCi/1) Februa ry 4.7 1.0 2.2 1.0 2.6 1.0 1.6 11.0 1.0 Furch 3.7 1.0 v.6 1.3 2.3 1.0 <l.0 <l.0 April 3.9 1.0 1.4 tl.0 2.6 1.0 3.4 21.0 7.3 1.0 May 3.6 1.0 3.1 +1.0 2.7 1.0 <l.0 <l.0 June 4.8 21.0 2.1 21.0 2.3 1.0 2.1 11.0 2.0 11.0
<5 <5 <5 <5 <5 Gross Gamma (a) January ~
<5 (cpm /1) Februa ry <5 s, <5 <5 March <5 - <5 <5 14 5 9 5 April <5 <5 <5 6 5 8 5 May -
<5 <3 <5 <5 <5 June <5 <5 <5 13 15 <5 January 1.3 0.5 1.4 20.5 0.9 0.5 <0.5 <0.5 Strontium-90 <0.5 (pCf/1) February 1.4 20.5 1.1 0.5 0.7 20.5 <0.5 March 0.6 0.5 <0.5 <0.5 <0.5 <0.5 April 0.6 0.5 <0.5 0.6 0.5 <0.5 <0.5 ody 0.5 *1.5 0.7 0.5 0.6 10.5 <0.5 <0.5 0.8 . 5 <0.5 <0.5 <0.5 June 0.5 20.5 ,
<2.5 <2.5 <2.5 <2.5 <2.5
- Tritium January
<2.5 <2.5 (pC1/ml) February <2.5 <2.5 <2.5 March <2.5 <2.5 <2.5 <2.5 <2.5 April- <2.5 <2.5 <2.5 <2.5 <2.5 May <2.5 <2.5 <2.5 <2.5 <2.5 June <2.5 <2.5 <2.5 <2.5 -
<2.5 January <5 <5 <5 <5 <5 Iodine-131 s5 <5 (pCf/1) February <5 <5 <5
<5 <5 <5 <5 <5 March April <5 <5 <5 <5 <5
<5- <5 <5 <5 <5 May
<5 <5 <5 <5 <5 June U
- a. 1 cpm corresponds to 9 pCi of cesium-137.
l O O 15 1
14- +1 standard deviation l -
o monthly average
- I3- g s
-1 standard deviation -
~~
12__ Preoperational l Operational _
l T --
% l m 10- ' o -
g o --
O s- 9- .- _
o .. o L
l 3 8- o -i --
3 __
c, 7- -- --
oI -
- u. --
n -
. _ _- ~~
_ o
.2 6- o y g ,-
o o -- --
o .. o __
o o __-- l 3
~~
5- --
__ 6 o o -
g o ,, ,,
__ o ,,
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o l--
o o o __ ..
4- g o ..
-- ._ o __
I o
o .. --
3- __
lo o _
0 --o 2- o -.
-- g __
18 (4 1- .
n 1969 1970 1971 1972 E7Y AlSl0lNlD JlFlMl Alt 4l JlJl Al Sl0lNlD Jl Fl Ml AlMlJlJlAlSl0lt4l0 JlFlMlA lMlJ Jl AlSl0lNlD. JlF lMI A!M lJ; Figure 10. Gross Beta Concentrations in Monthly Water Samples fro:n Little South Pond.
N l
/
37
(~N3 .
L/ Table 13 Radioactivity in Precipitation--Plymouth, Massachusetts Collection Gross Bqta Gross Gamma Sr-90 H-3 Period (1973)_ (pCi/md ) (cpm /m2) (pCi/m2 ) (nCi/m2 )
January 190 121 <120 <40 <170 February <l60 <120 <40 <230 March 2,419 307 <120 <50 <390 April <225 <120 I* <330 May 800 200 <120 I I June ' 340 170 <120 I I
- I indicates incomplete analysis.
1 l
l I
(
C)' :
O O O Table 14 Radicactivity in Seawater Monthly Analysis Collection Gross Lccation Fractional Gross Beta (cCi/1) Gamma Concentration Da te(1973) Frac. I f rac. II Frac. III Frac. IV (com/1) H-3( pci /cl ) I-131(pCi/1)
Intake Janua ry <5 <5 <5 <5 <5 <2.5 <5 Channel February <5 <5 <5 <5 <5 <2.5 <5 March <5 <5 <5 <5 <5 <2.5 <5 April <5 6 5 .<5 l 9 25 <5 <2.5 <5 May <5 <5 <5 <5 <5 <2.5 < 5' Jur.e <5 <5 <5 <5 <5 I(a)
<5 Discharge January <5 <S <5 <5 <5 Channel February <5
<2.5 <5 10 5 <5 <5 <5 <2.5 Ma rch <5 <5
<5 <5 <5 <5 April <5 <2.5 <5
<5 <5 21 5 tby <5
<S <2.5 <5
<5 <5 <5 <5 June <2.5 <5
<S <5 <5 <5 <5 I <5
' 5:hite Horse Beach June <5 <5 <5 ' <5 *
<5 <2.5 I each June <5 <5 <5 <5 <5 <2.5 I Quarterly Analysis of Radienuclides (cCi/1) .
~
Collection Location Date (1973) Cesium-137 Mancanese-54 Cobalt-58 Cobal t-60 Zinc-65 Iron-59 Strontium-90 Intake First Quarter Composite 0.24 0.03 <5 <5 Channel <5 <5 <5 0.17 20.01 Second Quarter Composite 0.32 0.03 I I I I I I Discharge First Quarter Composite 0.57 0.06 <5 <5 <5 Channel <5 <5 0.20 0.01 l
Second Quarter comp. 0.34 0.04 I I l I I I I 1
i.a co
- a. I indicates incomplete analysis; value to be reported in a supplemental report.
39 releases during the first quarter, however, Fraction II gross (3
() beta and gross gamma, which would indic'te a Cr-51, showed no measurable increases as did the analyses of other isotopes (Mn-54, Zn-65, and Co-58, 60) released in the liquid effluent (Ref. Appendix D). Nevertheless, radiocesium levels in the environment will be followed more closely.
H. Marine Life A variety of marine life samples were collected in the vicinity of the station, and the results of radioactivity analyses are presented in Table 15. Specific analyses for radionuclides indicate that the concentrations were less than the minimum detectable icvel, except for strontium-90. The measured radioactivity concentrations are approximately equal to those reported in the previous semiannual report.
\/ Radionuclide releases in the Pilgrim Station liquid effluents during this reporting period did not produce detect-able increases in radionuclide concentrations in marine life samples collected in the vicinity of the station.
I. Bottom Sediments In the previous report, it was indicated that Co-58, 60 were barely detected in the bottom sediment of the discharge canal and that the frequency and extent of surveillance would be increased. Since the discharge current has swept away the remaining sediment in the discharge canal, sediment sampling has been started in the outfall of the canal as indicated in Figure 11. -
, Sediment sampics for the extensive survey of Figure 11 were l
collected in March 1973 by a scuba diver-from the Battelle i
l
O O O 1 Table 15 Radioactivity in Marine Life Collection Gross Gama Concentrations (pC1/g; dry weight)
Sample Type Location Date (1973) (cpm /c) Gross Bets Cs-134 Cs-137 I-131 t:n-54 Co-53 Co-50 Zn-65 Sr-90 Fe-59 Pollack Rocky Point April 20 0.02 20.01 5.1 20.5 <0.1 <0.1 <0.5 <0.1 <0.1 <0.1 <0.1 <0.005 <0.1' !
Pollack Rocky Point May 15 0.03 0.01 4.9 10.5 <0.1 <0.1 <0.5 <0.1 <0.1 <0.1 <0.1 0.008 0.005 .<0.1 ;
Pollack Rocky Point June 15 0.04 0.01 4.9 10.5 I(a) I I <0.1 I I I I I l t
Atlantic Cod Rocky Point April 20 0.02 20.01 3.3 20.3 <0.1 <0.1 <0.5 <0.1- <0.1 <0.1 <0.1 <0.005 <0.1 Atlantic Cod Rocky Point May 15 0.02 20.01 4.2 20.4 . <0.1 <0.1 <0.5 <0.1 <0.' <0.1 <0.1 <0.005 <0.1 Atlantic Cod Rocky Point June 15 0.03 20.01 5.5 10.6 I I <0.5 <0.1 I I I I I Flounder Rocky Point April 20 0.01 20.01 2.0 0.2 <0.1 <0.1 <0.5 <0.1 <0.1 <0.1 <0.1 <0.005 I Flounder Rocky Point May 31 0.03 20.01 5.0 10.5 I I <0.5 <0.1 I I I I I Winter Flcunder Rocky Point March 30 0.01 0.01 3.6 0.4 I I <0.5 <0.1 <0.1 <0.1 <0.1 I <0.1 Winter Flounder Rocky Point May 1 0.02 0.01 5.0 20.5 <0.1 <0.1 <0.5 <0.1 <0.1 <0.1 <0.1 <0.005 <0.1 Striped Bass Rocky Point May 15 0.03 20.01 5.0 20.5 <0.1 <0.1 <0.5 I-
<0.1 <0.1 <0.1 0.019 20.005 <0.1 Rockweed Discharge Canal May 15 0.16 0.02(b) 11 il <0.1 <0.1 <0.5 I <0.1 <0.1 <0.1 0.012 10.005 I Irish Moss Discharge Canal May 15 0.14 10.01(C) 8.5 10.8 <0.1 <0.1 <0.5 I <0.1 0.1 20.1 <0.1 0.014 10.005 I .
Lobster Rocky Point June 1 0.02 20.01 I I I I I I I. I I I Clams Marshfield June 14 <0.01 I I I <0.C5 I <0.1 <0.1 I I I Alewife Rocky Point June 15 0.02 20.01 5.1 10.5 I I <0.05 I I I I I .I Mackerel Rocky Point June 15 ~0.03 0.01' 6.7 10.7 I I <0.05 I I I I I I
- a. Indicates incortplete analysis.
- b. Garca spectrum indicates lead-212 and pctassium-40.
- c. Garna spectrum indicates potassium-40,.
~$-t t
L_- . _ _ . - . - -- -.-_-____----__.-.---------___-__--_-___._____ve- -- __- - - - - - a - -- - -.~r - -- - - ~s.
41
/~~' s
~~.
O O O G @ O
@ @ O o
J M$.T
--w
/ ' 8 IM 200 i
Flli ex Figure 11. Sampling Locations for Bottom Sediment Collected on March 9, 1973.
V The encircled numbers refer to the sample numbers listed in Table 16.
L
42 l gs
() Table 16 .
1 Radioactivity in Bottom Sediment Gross Beta Gross Ganma Location Collection Date (pCi/g) (cpm /g) 0F-1 March 9, 1973 21 2 0.71 0.07 0F-2 ,
19 1 0.64 0.06 0F-13 25 2(a) 0.62 0.06 0F-3 "
21 2 0.49 0.05 0F-5 "
17 il 0.32 0.03 0F-6 "
22 2 0.45 0.04 0F-7 "
21 2 0.33 0.03 0F-8 "
15 2 0.33 0.03 0F-9 "
19il(b) 0.33 10.03 0F-10 "
15 2 0.32 0.03 0F-ll "
19 il 0.45 0.04 0F-12 "
16 i2 0.66 0.06 600 feet from Discharge May 15, 1973 16 1 0.36 0.04 Channel (on axis) 300 feet from Discharge "
20 2 0.56 0.06(c)
Channel (on axis) 1
- a. Strontium-90 less than 0.01 pCi/g. !
- b. Strontium-90 less than 0.02 pCi/g.
- c. Gamma spectrum indicates nuclides: Lead-212, lead-214,
, bismuth-214, actinium-228, and potassium-40 ;
O l l
l l
u_ ~ --
43 Clapp Laboratories. In May 1973, two more sediment samples
() were obtained on the axis of the canal,'300' and 600' from s_/
the end of the canal. ,
The results of the radioactivity analyses of the sediment sampics collected in March and May 1973 are shown in Table 16.
There is a tendency for the gross gamma results to be higher nearer the discharge point. No such tendency is evident for the gross beta results. Gamma spectral analysis did not indicate any significant peaks, especially none of Co-58, 60.
The botto.a sediment collection frequency will continue on a quarterly basis over the next reportinc period.
V. CONCLUSIONS The results of the environmental radiation monitoring program for
/ this 6-month period and the special survey indicate that increased V) gamma exposure rates are present in the vicinity of the turbine building; however, the dose to the general public visiting the site and transient workers not in the controlled security areas is not significant. The resul 1 indicate that the radionuclide releases from Pilgrim Station have not resulted in significant increases in offsite radioactivity levels.
O h
44 a
APPENDIX A RESULTS OF INCOMPLETE ANALYSES IN PREVIOUS SEMIANNUAL REPORT In the prev,ious semiannual report, some radionuclide analyses were incomplete at the time of report preparation. All analyses for that period have been completed and Tables 6-A through 15-A of the previous report are reproduced in this appendix with all of the results. The -
additional analyses did not alter the conclusions in the previous semi-annual report.
.u.
O V
s 1
1 -
O O O 1972 Table A-6 y Air Particulates--Gross Beta Concentrations in Weekly Samples (pC1/m3 )(a)
Control Offsite Onsite Collection Period East Ply:nouth ?!ancmet Cleft Rocky Hill Rocky Hill Overlook (1972) Wey.outh Center Substation Rock Road (West) Road (East) Area July 6-July 13 0.23 0.26 0.18 0.18 0.22 0.18 0.16 July 13-July 21 0.C6 0.04 0.04 0.04 0.C4 0.04 0.Q4 July 21-July 27 0.11 0.14 0.12 C.13 0.13- 0.11 0.10 July 27-Aug. 3 0.11 0.11 0.11 0.10 0.11 0.11 0.13 Aug. 3-Aug. 10 0.11 0.09 0.09 0.09 0.09 0.10 0.12 Aug. 10-Aug. 17 0.10 0.09 0.03 0.09 0.07 0.10 0.08 Aug. 17-Aug. 24 0.10 0.09 0.14 0.08 0.08 0.11 0.07 Aug. 24-Aug. 30 0.07 0.06 0.03 0.13 0.04 0.02 0.05 Aug. 30-Sept. 7 0.07 0.07 (b) 0.06 0.07 0.08 0.05 Sept. 7-Sept. 14 0.08 0.07 0.08 0.08 0.07 0.08 0.07 Sept. 14-Sept. 21 0.06 0.04 0.04 0.05 0.05 0.04 0.05 Sept. 21-Sept. 28 0.05 0.06 0.05 0.05 0.05 0.04 0.04 Sept. 28-Oct. 5 0.04 0.04 0.25 0.02 0.03 0.03 0.03 -
Oct. 5-Oct. 12 0.03 0.03 0.03 0.03 0.04 0.03 0.02 Oct. 12-Oct. 19 0.04 0.04 0.03 0.03 0.05 0.03 0.04 Oct. 19-Oct. 26 0.06 0.04 J .04 0.03 0.04 0.04 0.04 Oct. 26-Nov. 2 0.02 0.04 0.03- 0.03 0.03 0.02 0.04 Nov. 2-Nov. 10 (b) 0.01 0.03 0.02 0.03 (b) 0.02 f:ov. 10-Nov. 16 0.03 0.03 0.01 0.02 0.02 0.01 0.03 flov. 16-Nov. 22 0.03 0.04 0.02 0.04 0.03 0.05 0.04 Nov. 22-Nov. 30 'O.04 0.04 0.04 0.03 0.03 0.03 0.03 Nov. 30-Dec. 7 0.03 0.03 0.02 0.03 0.03 0.02 0.03 Dec. 7-Dec. 15 0.05 0.05 0.04 0.04 0.03 0.03 (b)
Dec. 15-Dec. 21 0.04 0.04 0.03 0.05 (b) 0.04 0.08 Dec. 21-Dec. 28 0.02 0.03 0.02 0.02 (b) 0.02 0.03 Dec. 28-Jan. 4 0.03 0.03 0.03 0.04 0.04 0.03 0.03
- a. Error is 10 percent or 0.01, whichever is larger,
- b. Instrument malfunction--no data available.
D b _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ _ . _ _ _ _ _ _ _ . - _ _ _ _ -__ _ _ _ _ - _ _ _ - _ _ _ _ _
O O O 1972 Table A-7 Air Particulates--Gross Gamma Concentrations in Monthly Composites (cpm /m )(#' }
l Control Offsite Onsite Collection Period East Plymouth Manomet Cleft Rocky Hill Rocky Hill Overlook (1972) Weymouth Center Substation Rock Road (West) Road (East) Area July 24(c) 31 (c,d ) 28(c,d ) 27 (c ,d ) 36(c) 27(c ) 28(c,d )
August 17 11 17 14 13 10 9 September 13 15 22 14 11 14 16 October 5 1(e) 7(e) 5 6(e) 5(e) 5(e) .
November 2 <2 <2 <2 4 3 5 December 5 8 4 7 2 7 4
- a. All values are to be multiplied by 10-3 ,
- b. Error is 2a or 10 percent.
- c. Ru-103, Ru-106, Zr-95, and Nb-95 detected by gamma spectrum analysis.
- d. Ce-141 and Ce-144 detected by gamma spectrum analysis.
- e. Ru-103 and Ru-106 detected by gamma spectrum analysis.
b
O o 1972 o
Table A-8 Gaseous and Particulate Iodine-131 in Air Samples (pCi/m3 )(a) e Control Offsite Onsite Collection Period East Plymouth Mancmet Cleft Rocky Hill Rocky Hill Overlook (1972) Wey:r.outh Center Substation Rock Road (West) Road (East) Area July 6-July 13 <1
<1
<1
<1 a
<1
<1 a
<1 a
July 13-July 21
" " " " " a a July 21-July 27
" " " " " a #
July 27-Aug. 3 .
" " " " a a a Aug. 3-Aug. 10
" " " " a a a Aug. 10-Aug. 17
" " " " a " a Aug. 17-Aug. 24
" " " " " a Aug. 24-Sept. 7 (b) l
" " " a a Sept. 7-Sept. 14 "
<1
" " " " " a a Sept.14-Sept. 21
" " " " a a a Sept. 21-Sept. 28
" " " " = a a Sept. 28-Oct. 5
" " " " a a a Oct. S-Oct. 12 '
" " " " " a a Oct. 12-Oct. 19
" " " a a a a Oct. 19-Oct. 26
" " " a a Oct. 26-flov. 2
" " " " a a flov. 2-f;ov. 10 (b) " " " a a a flov. IC-Hov. 16 <1
" " " " " a a Nov. 16-Nov. 22
" " " " " a a flov. 22-Nov. 30 " " " " " " "
Nov. 30-Dec. 7 Dec. 7-Dec. 15 (b)
Dec. 15-Dec. 21 (b) <1 Dec. 21-Dec. 228 (b)
Dec. 28-Jan. 4 <1 l'
- a. Both particulate iodine-131 concentrations on filters and gaseous iodine-131 concentrations on impregnated filters were less than minimum detectable concentrations in all samples.
. b. Instrument malfunction--no data available.
o o O
1972 Table A-9 External Gamca Exposure Rates, June-December 1972 (pR/hr)(a) ,.
i Offsite Monitorina Locations June July Aug. Sept. Oct. Nov. Dec.
East Weymouth (EW) 17.0 16.2 17.0 16.2 16.5 16.4 15.6 Kingston (KS) 17.0 16.2 17.6 16.2 17.0 16.4 15.8 Sagamore (CS) 17.5 16.7 18.1 16.8 17.1 17.1 16.3 Plymouth Airport (SA) 14.1 13.3 14.0 13.1 14.0 13.0 13.3 North Plymouth (NP) 17.8 16.7 17.5 16.6 16.9 17.0 - 15.8 Plymouth Center (PC) 13.1 12.3 13.1 12.1 13.1 12.6 12.3 South Plymouth (SP) 16.4 15.9- 16.7 16.0 16.5 16.1 15.4 Manomet (MS) 17.3 16.6 17.5 16.6 17.3 16.9 16.4 -
Manomet(ME) 18.6 17.9 19.4 17.6 18.2 18.2 17.4 Manomet (MP) 16.1 15.1 16.3 15.5 15.3 15.8 14.8 Cleft Rock Area (CR) 16.7 16.1 17.3 16.4 16.4 16.5 16.0 Onsite Monitoring Locations June July Aug. Sept. Oct. Nov. Dec. -
Rocky Hill Road (ER) 17.9 17.4 18.3 17.1 17.8 17.4 17.0 Microwave Tower (MT) 17.0 18.1 16.9 16.2 16.7 16.9 16.4 Rocky Hill Road (WR) 16.6 16.2 16.7 16.0 16.6 16.4 15.8 Rocky Hill Road.(B) ' _17.1 16.7 17.7 16.7 17.2 17.7 17.2 Property Line (H) 17.6 17.0 17.9 16.9 18.2 18.4 17.7 Property Line (I) 16.6 15.9 17.1 16.3 16.7 16.4 16.3 Public Parking Area (PA) 16.9 15.7 16.6 15.7 16.3 16.7 16.1 Overlock Area (CA) 16.0 16.9 16.4 16.2 18.5 25.7 22.1 i
- a. Gross exposure rates which include inherent self-irradiation rates.
c _ _ _____-__ _____ _ _ _ _ __-____ _ ._ . - - . - _ _ . - __ ... - .
49
(
\ 1972
-Table A-10 Radionuclide Concentrations in Milk (pCi/1) s p Collection Plymouth Bridgewater Radionuclide Period (1972) (County Farm) (Bridgewater Fann)
Cesium-137 July 12 1 17 2 Au9ust 15 1 10 il September 15 12 12 il i October 12 1 8 1 16 1 November 9 il December 24 1 9 il Strontium-90 July 15 2 9 1 August 17 i2 11 il -
September 7 il 10 11 i October 10 il 10 1-November 11 il 9 1 December 7 1 9 il Iodine-131 July <5 <5 !
Au9ust <5 <5 September <5 <5 October <5 <5 flovember <5 <5 December <5 <5 l
Barium / Lanthanum-140 July <5 <5 '
August <5 <5 September <S <5 October <5 <5 flovember <5 <5 December <5 <5 O
- -_ n
v m 1972 Table Asll Radioactivity in Crcps Collection Gross Gama Gross Egtg Radionuclides (pCi/g)(a)
Sa ple Type Location Date (1972) (cpm /g)(a) (pCi/g)tal Sr-90 Cs-134 Cs-137 1-131 Hay Plymouth (CF) July 5 0.40 0.04(b) 21 2 0.80 10.08 <0.1 <0.1 <0.5 Pip cuth (CF) June 27 0.56 10.06(b) 24 2 0.61 0.06 <0.1 <0.1 <0.5 Plytcuth (CF) July 26 0.04 0.01(c) 13 il 1.1 10.1 <0.1 0.13 0.1 <0.5 Cabbage Plyrouth (CF) July 17 0.04 20.01 2.9 0.3 0.042 0.005 <0.1 <0.1 <0.5 Cranberries t'anomet (Bog F) Sept. 13 0.04 0.01(d) 8.3 0.8 0.075 0.005 <0.1 0.1 20.1 <0.5 Mar.omet (Bog E) Sept.16 0.C6 0.01 (d ) 2.0 0.2 0.065 0.005 <0.1 0.6 0.1 <0.5 Mar.oict (Bog C) Sept. 26 0.03 0.01(d) 0.8 0.2 0.050 10.005 <0.1 <0.1 +0.5 Manocet (Bog D) Oct. 7 0.04 0.01(d) 1.6 20.2 0.022 20.005 <0.1 <0.1 <0.5
. Corn Kernels Plymouth (CF) Aug. 21 0.03 20.01 1.1 0.2 0.0132 0.005 <0.1 <0.1 <0.5 Plyr.outh (CF) Sept. 8 0.01 0.01 (e) (e) <0.1 <0.1 <0.5 Potatoes Plymouth (CF) Oct. 5 0.03 0.01 6.8 0.7 0.011 20.005 <0.1 <0.1 <0.5
- a. one standard deviation.
- b. Zr-95 and i:b-95 detected by ga=a spectrum analysis. ,
- c. Zr-95, ;b-95, Ru-103, and Ru-106 detected by gama spectrum analysis,
- d. Cs-137 detected by gama spectrua analysis,
- e. Aliquot lost.
_ _ _ . _ _ _ _ . _ __.__._____..__m ___
51 o 1972 Table A-12 Radioactivity in Domestic and P.ecreation Water Collection Period Great Little Lout Pond Manomet Analysis (1972) Pond South Pond Well Well Gross Bgta July 7.0 1.0 3.1 11.0 <1.0 <1.0 (pCi/1)ta) Aug. 7.3 11.0 8.7 1.0 2.5 t'. 0 <1.0 Sept. 11.0 1.1 9.8 11.0 <1.0 1 21.0 Oct. 4.7 11.0 1.8 *1.0 <1.0 <1.0 Nov. 4.6 11.0 3.2 ii.0 <1.0 <1.0 ,
Dec. 4.1 11.0 3.0 1.0 <1.0 <1.0 l July <5 <5 <5 <5 i GrossGac=a)
(cpm /1)(a,b Aug. 9 15 <5 6 15 <5 i Sept. <5(c) <5 6 5 <5 Oct. <5 <5 9 15 15 5 ,
Nov. <5 <5 20 15 12 15 )
Dec. <5 <5 <5 <5 !
l July 1.0 10.5 1.0 10.5 <0,5 <0,5 C Strontiym-)90 (pCi/1)ta Aug. 1.1 10.5 0.9 i0.5 <0.5 <0.5 Sept. 1.4 0. 5 - 1.3 10.5 <0.5 <0.5 Oct. 0.9 10.5 0.9 !0.5 <0.5 <0.5 Nov. 1.1 10.5 0.7 10.5 <0.5 <0.5 Dec. 1.5 10.5 0.8 20.5 <0.5 <0.5 Tritium July <2.5 <2.5 <2.5 <2.5 (PCi/ml) Aug. <2.5 <2.5 <2.5 <2.5 Sept. <2.5 <2.5 <2.5 <2.5 Oct. <2.5 <2.5 <2.5 <2.5 l Nov. <2.5 <2.5 <2.5 <2.5 i Dec. <2.5 <2.5 <2.5 <2.5 lodine-131 July <5 <5 <5 <5 (pCi/1) Aug. <5 <5 <5 <5 Sept. <5 <S <5 <5 Oct. <5 <5 <5 <5 Nov. <5 <5 <5 <5 Dac. <5 <5 <5 <5 1
- a. Error va?ue is 1 counting standard deviation,
- b. I cpm corresponds to 9 pC1 of cesium-137. ;
- c. Indication of Zr-95 and Nb-95 in composite for quarter by gate.a spectrum analysis. i V
d M -* We e == ep we g ., 3w,
O O O
- 1972 Table A-13 Radioactivity in Seawater i
Monthly Analysis Concentrations Collection Fractional Gross Beta (pCl/1)- Gross Ga ma Tritium lodine-131 Frac. 11 Frac. III Frac. IV (cpc/l) (pCi/ml) (pCi/1)
Location Date (1972) Frac. I July <5 <5 <5 <5 <5 <2.5 <5 Intake Channel <2.5 <5 August <5 <5 <5 <S <5 Intake Channel <5 <2.5 <5 September <5 <5 <5 <5 Intake Channel <5 <2.5 <5 October <5 <5 <S <5 Intake Channel <2.5 <5 November <5 <5 <5 <5 <5 Intake Channel <5 <2.5 <5 December <5 6 5 <5 <5 Intake Channel .
<5 <5 <5 <5 <5 <2.5 <5 Discharge Channel July Discharge Channel August <5 <5 <5 <5 <5 <2.5 <5 Discharge Channel September <5 <5 <5 <5 <5 <2.5 <5 Discharge Channel October <5 <5 <5 <5 <5 <2.5 <5 Discharge Channel November <5 <5' <5 <5 <5 <2.5 <5 6 15 <5 <5 <5 <2.5 <5 Discharge Channel December <5 July 27 <5 <5 <5 <5' <5 <2.5 <5 Priscilla Beach <5 <2.5 <5 August 24 <5 <5 <5 <5 Priscilla Beach July 26 <5 <5 <5 <5 <5 <2.5 <5 White Horse Beach <2.5 <5 August 24 <5 <5 <5 <5 <5 White Horse Leach Quarterly Analysis of Radionuclides (pCi/1)
Collection Date Location (197?) Cesium-137 Manganese-54 Cobalt-58 Cobalt-60 Enc-65 Iron-59 Strontium-90 Intake Channel July-Sept. Composite 0.63 0.06 <5 <5 <5 <5 <5 0.21 20.05 Discharge Ch.miel July-Sept. Cog osite a) <5 <5 <5 <5 <5 0.20 20.05 Intake Channel Oct.-Dec. Composite a) <5 <5 <5 <5 <5 0.17 20.05 Discharge Channel Oct.-Dec. Composite a) <5 <5 <5 <5 c5 0.17 20.05 U
- a. Aliquot lost.
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- 1972 Table A-15 Radioactivity in Bottom Sediment Collection Gross Beta Gross Gama Strontium-90 Location Data (pCi/g; wet wt.) (cpm /g; wet wt.) (pCi/g; wet wt.)
White Horse Beach July 17 15 2 0.29 0.03 <0.005 Plymouth Beach July 17 15 2 0.38 20.04 <0.005 Priscilla Beach July 17 14 1 0.29 0.03 <0.005 Discharge Channel December 4 20 2 0.75 20.08(a) 0.042 0.005 4.. Co-58 and Co-60 detected by gamma spectr m analysis.
/
v~
55 APPENDIX B D METHOD FOR EVALUATING TLD MEASUREMENTS The EG&G Model TL-15 thermoluminescent dosimeters used at Pilgrim Station have a significant inherent background of "self-irradiation."
This inherent background is on the order of 6 to 9 microroentgens per hour and, when added to the natural background exposure rates of ap .
proximately 7 to 11 microroentgens per hour, the total measured back-ground exposure rate ranges from approximately 14 to 19 microroentgens per hour. The absolute "self-irradiation" rate has not been determined for each dosimeter; however , sets of dosimeters used at each location have been normalized by placing the set of dosimeters in a shielded con-tainer and measuring the relative self-irradiation rates. The "self-irradiation" factor has been normalized for the month-to-month measure-ments at individual locations, but not for one location relative to an-other location.
The monthly variations in measured background exposure rates are significant when attempting to distinguish net increases of 0.5 to 1 microroentgen per hour. In evaluating the measurements at various onsite l
and nearby locations, the monthly variations in background exposure rates were considered. The difference in the monthly measured exposure rate at an onsite location--e.g. , Rocky Hill Road (B)--and at a more distant con-I trol s tation--e.g. , Eas t Weymouth-< was calculated for the period December i
1971 through June 1973. The average dif ference and s tandard deviation l for the period prior to station operation--December 1971 through September !
1972--was calculated. The average difference af-er the station began significant reactor operation (October 1972 through June 1973) was cal-O culated and compared with the preoperational period. The means were U
56 tested to determine if there had been a statistically significant in-
[) crease--assuming that the preoperational differences'were normally v
distributed.
To illustrate this method, Figure B-1 shows the measured exposure rates at East Weymouth (control) and at Rocky Hill Road (B) . The differ-ences in the exposure rates and the average values are shown in Table B-1.
To minimize the effects of varying local conditions, the measurements at each station were compared with control stations at East Weymouth, Duxbury, and Plymouth Center. The results were generally quite consistent for the three comparisons.
As a further check, the TLD results were compared with the finding of a direct radiation survey (reported in Appendix C) . The estimated not exposure rates at the monitoring stations were consistent with the measure-ments made in the direct radiation study (recognizing that the results in A
(_,) the study were for full power operation and the monthly TLD measurements are generally for less than continuous full power operation) .
The estimated net exposure rates from TLD's were compared with the plant operating his tory. Increased exposure rates at the overlook area, the Rocky Hill Road (B), the public parking area, and possibly the prop-erty line (H) stations would be expected to result from direct radiation (nonplume) as documented in the direct radiation study. Net exposure rates, above background, due to direct radiation in turn would be expected to vary with the operating power level or the total monthly power genera-tion. Graphs of the estimated net exposure rates as a function of monthly power generation are shown in Figures B-2 and B-3 for the over-look area, the Rocky Hill Road (B), and the property line (R) stations.
There is a definite correlation at the overlook area, and there appears n/
\- to be a correlation at the two more distant locations.
57 c 's
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0- 1973 l S l Olti 10 J lF lM lA lMlJ J I A IS 0 Iti 10 J lF IM IA lM ld Figure B-1, Monthly Exposure Rates Measured with TLD's at Rocky Hill Road (B) and at East 'rleymouth (Con-trol). Solid lines show the differences in the ;
i teasured exposure rates at the two statiens.
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_ _ _ _ e% -.A._ _ . _ . _.i__ _-.A .m .A _ _ E _ _ . , . . .
O o o Table B-1 Exacole of Net Exposure Rate Estimtion for Rocky Hill Road'(B) Station Measured Exposure Rate (vR/hr) Difference Month Rocky Hill Road (B) East k'cycouth (EW) (B-EW)
Dec. 1971 17.8 17.3 +0.5 Jan. 1972 16.5 16.2 +0.3 Feb. 1972 16.7 16.0 +0.7 Parch 1972 16.6 16.2 +0.4 April 1972 17.1 16.7 +0.4 May 1972 16.8 16.7 +0.1 June 1972 17.1 17.0 +0.1 July 1972 16.7 16.2 +0.5 Aug. 1971 17.7 17.0 +0.7 Sept. 1972 16.7 16.2 +0.5 Average Difference "Preoperational" +0.4 20.2 vR/hr i Estimated Net Exposure Power Generation Rate for Month 10 5 t'!-hr
~
Oct. 1972 17.2 16.5 +0.7 +0.3 1.34 Nov. 1972 17.7 16.4 +1.3 - +0.9 3.95 Dec. 1972 17.2 15.9 +1.3 +0.9 3.04 Jan. 1973 18.2 15.9 +2.3 +1.9 4.57 Feb. 1973 16.4 14.9 +1.5 +1.1 4.19 March 1973 18.5 16.6 +1.9 +1.5 ~
4.18 April 1973 17.2 15.5 +1.7 +1.3 3.65 May 1973 14.9 13.5 +1.4 +l.0 4.60 June 1973 16.0 14.1 +1.9 +1.5 Average Difference "Postoperational" +1.6 10.4 vR/hr Esticated Net Increase +1.2 20.4 vR/hr Note: The variability in the net exposure rates during October 1972 to June 1973 appears to be related to plant operation levels and not randomly distributed.
59 I The method outlined above was used to estimate the increased ex-posure rates measured at the TLD stations shown in higure 8, 1
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-/
62 APPENDIX C RESULTS OF PRESSURIZED ION CHAMBER SURVEYS An operational environmental radiation survey1was perfonned at the Pilgrim Nuclear Station on December 18-19, 1972, and January 18-19, 1973, while the plant was operating at thermal power levels greater than 1,800 megawatts. An evaluation of direct gamma radiation in the immediate-plant environs and an estimation of nonplume site boundary exposure rates were made by comparing measured exposure rates and gamma ray spectral data obtained with similar measurements made during a preoperational sur-vey in July 1972.
Measurements during both surveys were made using a pressurized ioni- ,
zation chamber and a 4-by-4-inch sodium iodide gamma spectrometer. The ionization chamber was calibrated before and after the survey using a radium-226 source certified by the National Bureau of Standards while the t
O gamma spectrometer was calibrated to span the energy range of zero to 7.7 million electron volts, which encompasses all the high energy gamma emis-sions of nitrogen-16. The detectors were supported at one meter above .
the ground on aluminum tripods for measurements. [
The direct radiation contribution of nitrogen-16'high energy gamma rays in the plant environs was evaluated during this survey. Nitrogen-16 exposure rates were calculated using a proportionality factor published by Lowder et al.3 which is used to convert the energy deposition rate in a 4-by-4-inch sodium iodide crystal detector in the energy range of 3.4 to 6.5 million electron volts to a dose rate in microroentgens per hour.
Exposure rate measurements were made during the survey with the ion chamber at 90 locations while gamma ray energy spectra vere obtained at 39 of these sites. Nine sets of related measurements were made near the plant. The first series of measurements was made inside the security 1
1 s
l
63 fence to determine the areas of highest radiation intensitv (shown in
()
V Figure C-1). In the other remaining sets, measurements were made along seven radials in different directions f rom the plant (as illustrated in Figure C-2) to determine the radiation levels as a function of distance from the turbine building. Measurement locations were chosen to avoid plume radiation when possible and were limited by topographic as well 1 as man-made features, such as hills, woods, and various butidings onsite.
The highest measured exposure rates occurred inside the security fence just across from the southern side of the turbine building, where the exposure rates exceeded the range of the ion chamber, indicating an i
exposure rate of greater than 189 microroentgens per hour. Spectra j obtained in this area revealed the presence of high-energy radiation from i
Additional measurements made in a southerly direction at increasing
) dis tances f rom the turbine building also indicated elevated exposure ;
rates. Radiation from nitrogen-16 was detected at all the locations on 1
this southern radial, and on Rocky Hill Road, a net exposure rate of 2 to 3 microroentgens per hour was measured. This increase over *vackground was primarily due to the penetrating gamma radiation of nitrogen-16 since the estimated exposure rate from primary nitrogen-16 gamma radiation was 2.7 microroentgens per hour.
Two measurements made at the Rocky Hill Road TLD Station B also ;
i indicated increased exposure rates due to plant operation and high-energy nitrogen-16 radiation. In the vicinity of this TLD station, the increase over background was 1 to 2 uR/h (which was also the upper limit of the nitrogen-16 exposure rate) . Radiation from nitrogen-16 was not detected
~
in four other measurements made at dif ferent locations along Rocky Hill 1
Road.
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I ws m,-~nn, -r,,-,--w----,,-,. --n.,,-.,,-.-.,m,-,,,-------n,--. - - - , - , - -,-er -----~.~w-, - , -- - r-.,-.. - -------,a- - - , . - -- -- -
66 Measurements made at the overlook area indicated an increase in h
G exposure rate over that previously measured during the preoperational survey. At the northeast edge, a not exposure rate of 26.8 microroentgens per hour was measured when the plant was at full power. This value must also be considered as an upper bound for the nitrogen-16 exposure rate at this location, since significant nitrogen-16 radiation was detected in the gamma spectrum. Not exposure rates decreased in a southwesterly direction at the overlook (along the parking lot), partially due to shielding af forded by a hill between the plant and the overlook parking area.
Other measurements made for the purpose of investigating the magni-tude of exposure rates with distance did not indicate significant increases over background except along the northeast breakwater where penetrating radiation from gaseous radionuclides released from the stack probably V elevated the exposure rates in the general area of the breakwater and shorefront. The radial through the shorefront area did indicate measure-abic net radiation levels, but this area was in a general downw%d direc-tion from the stack.
Figure C-3 is a direct radiation exposure rate contour map of the Pilgrim site, based on the not exposure rates (background subtracted from total exposure rates) measured during the survey. The locations and shapes of the net exposure rate contours should be considered only as rough approximations for the power levels and meteorological condi-tions existing during the survey. The figure, however, is instructive in showing variations in direct radiation in the plant environs. The most prominent feature is the area of higher gamma exposure rates emanat-ing from the south side of the turbine butiding. The exposure rate at ,
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68 l this location decreases rapidly with distance; however, increased exposure rates (measured at 1 meter above t'he ground) were detected in the southerly direction extending to Rocky 11111 Road, At the more distant measurement locations in this direction, gamma spectra indicated that the major com-1 ponent of the net exposure rate was unscattered or primary nitrogen-16 l gamma rays.
{
The topography in the southern section of the site probably inf1'u-enced the net exposure rates. As shown in the figure, a ridge extends in the southerly direction and provides "shielding" for the areas west of the ridge along Rocky Hill Road.
The elevated exposure rates along the northear,t breakwater were probably influenced by gaseous radionuclide discharges from the stack during the measurement period. The wind generally blew in that direction and increased exposure rates at these locations are consistent with general plume effects. Direct radiation levels measured on the inner plant road northeast of the plant were significantly lower than on the turbine side, and direct radiation from the reactor or turbine building would not be expected to produce the observed increase along the breakwater.
It should be recognized that direct radiation levels from nitrogen-16 will vary with the operating power levels, and plume effects will vary with gaseous radionuclide release rates and meteorological conditions.
Consequently, the net exposure rate contour map should be considered as indicating only relative levels around the station.
The total exposure rates reported in Tables C-1 through C-9 were measured with the pressurized ion chamber. The net ion chamber exposure rates are the difference between the total exposure rates and the natural j background exposure rates, the latter of which were measured during a O previous survey before the Pilgrim Station became operational. These
69 background radiation levels vary according to location. Also presented
() in the tables are the estimated nitrogen-16 exposure' rates which were calculated f rom the gamma spectra using the method. of Lowder et al. .
References I
- 1. Environmental Analysts Incorporated, "An Operational Environmental Radiation Survey of the Pilgrim Nuclear Power Plant," March 1973, prepared for the Boston Edison Company.
- 2. Environmental Analysts Incorporated, "Preoperational Environmental Radiation Survey of the Pilgrim Nuclear Power Plant," August 1972, prepared for the Boston Edison Company. ,
- 3. Lowder, Wayne M. , Peter D. Ra f t , and Carl V. Gogolak, Environmental Gamma Radiation from Nitrogen-16 Decay in the Turbine of a Large Boiling Water Reactor, USAEC llASL-271, January 1973.
1 I
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O O Table C-1 Results of f*casure: rents Inside Security Fence Near Plant Buildings Thermal power Distance (a) S ectrun Total Exposure NetExposure(b) Nal. N-16 Expos
> !.ocation Rate (pR/ hour) th-ber_ Date Time Levels ( '.*t) (Feet) l:Mer Rate (vR/bcur) Rate (uR/heur) 1 18 Cec. 1972 14C5 1934 260 1 23.4 20.6 16.1 1.0 0.5 2 18 Cec. 1972 1433 1984 370 2 17.1 20.4 9.8 21.0 0.3 3
1504 1977 270 3 27.6 10.5 20.3 11.0 2.3 4
1525 1977 225 4 >189 >l82 20 5
1547 1977 300 5 33.0 20.5 25.7 1.0 8.4 6
IC07 1973 165 6 18.5 to.6 11.2 11.0 0.1 7
1642 1973 230 7 12.8 20.5 5.5 1.0 0.2 8
1659 1973 220 8 13.8 20.4 6.5 21.0 0.3 9
1727 1971 320 9 11.3 20.8 4.0 21.2 (d) 10 1748 1971 320 10 13.4 !0.5 6.0 1.0 (d) 47 18 Jan. 1973 1039 1988 260 (c) 70.7 20.9 63.4 11.2 (e) .
48 18 Jan. 1973 1048 1938 240 e) 111 tl.3 104 21.6 (e) 49 18 Jan." 1973 1104 1990 230 c) 139 21.3 132 1.6 (e) 50 1115 1990 225 e) >189 >182 (e)~
51 1117 1990 225 (e) >189 >182 (e) 52 1123 1993 230 (e) 137 21.0 130 1.3 (e) 53 1133 1990 235 (e) 44.1 0.8 36.8 11.2 (e) 54 1145 1990 240 (e) 37.8 10.6 30.5 !1.1 (c) 55 1155 1990 250 (e) 34.0 0.6 26.7 11.1 (c) 56 1209 1990 150 (c) 81.2 2.0 (f) (e)
- a. Approrimate distance to center of turbine building.
- b. Obtained by subtracting a back9round exposure rate of 7.3 0.9 pR/ hour from the total exposure rates.
- c. Estimated exposure rate due to primary N-16 '
gaar.a rays--may underestimate M-16 exposure rate if significant fraction of ga=ta rays are cultiply scattered.
- d. fc ful. H-16 exposure rate.
- e. No gs=ca spectrum obtained at this locction.
- f. No net exposure rate calculated due to lack of background date.
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O O o Tabic C-3 Results of Measure ents en Southern Radial -
Location Thermal Power Distance (a) Spectrum Total Exposure Net Ext.osure(b) rial. N-16 Expos Tfee (Feet) ?;u-ber Rate (uR/bcur) Rate (vR/ hour) Rate (pR/ hour) f;u-ber Cate Levels (fc.st)__
225 4 >189 -- 20 4 18 Cec. 1972 1504 1977 340 128 11.4 119 1.5 31 57 18 Jan. 1973 1416 1993 23 58 18 Jan 1973 1440 1993 410 (d) 85.3 1.1 76.8 21.2 (d)
- 59 1448 1993 490 (d) 50.2 20.8 41.7 10.9 (d) 60 1503 1991 570 (d) 31.6 11.0 23.1 21.1 (d) 61 1510 1991 655 (d) 22.5 0.5 14.0 10.6 (d) 62 1530 1991 730 24 18.3 0.7 9.8 0.8 7.5 63 15*0 1991 810 (d) 19.2 0.6 10.7 0.7 (d) 64 1550 1991 895 25 16.1 10.5 7.6 20.6 6.1 65 1605 1991 9?O (d) 13.2 20.5 4.7 0.6 (d) 65 1620 1991 1060 26 11.8 10.4 3.3 0.6 2.8
- a. Approximate distance to center of turbine building.
- b. Obtained by subtracting a background exposure rate of 8.5 20.4 uPJhour from total exposure rates except for location 4 where 7.3 !0.9 t /Rhour was subtracted.
- c. Estimated exposure rate due to primary fi-16 ga=.a rayt--may underestimate N-16 exposure rate if significant fraction of ga:rna rays are cultiply scattered. . -
- d. No gama spectrum chtained at this location.
U
O -
o o Table C-4 Results of Measure ents on Plant Access Road Location Thernal Power Distance f8) Spectrum Total Exposure Net Exposure (b) Na1. N-16 Expos e f:rber Date Tine Levels (ft-t) (Feet) M=be r__ Rate (uR/ hour) Rate (vR/ hour) Rate (vR/ hour) )
69 19 Jan.1973 0745 1990 340 28 16.0 0.4 7.5 10.6 0.8 70 19 Jan.1973 0800 1930 530 (d) 13.0 0.5 4.5 0.6 (d) 79(e) 11 July 1973 0335 530 --
7.3 20.3 -- --
71 19 Jan.1973 0815 1939 600 (d) 10.7 20.4 2.2 0.6 (d) 72 0325 1939 830 29 9.7 20.3 1.2 20.5 0.9 73 0340 1939 930 (d) 9.4 10.3 0.9 20.5 (d) 74 0850 1989 1160 {d) 8.9 0.4 0.4 20.6 ; (d) 75 0910 1990 1350 30 8.7 20.4 0.2 20.6 0.3 76 0920 1990 1500 (d) 8.2 20.3 (none) (d) 77 0940 1990 1660 (d) 8.4 20.4 (none) (d) 78 0955 1990 '2050 31 8.8 !0.3 0.3 10.5 (f) .
!I ki
- a. Approxicate distance to the center of the turbine building.
- b. Obtained by subtracting a background exposure rate of 8.510.4 vR/ hour frcm the total exposure rates,
- c. Estimated exposare rate due to pri.tary N-16 gama rays--may underesticate fl-16 exposure rate if significant fraction of gama rays are cultiply scattered.
- d. !;a ga ra spectrum obtained at this location.
- e. T;o Na!. N-16 exposure rate obtained at this location.
- f. F.easurement esde during preoperational radiation survey.
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. Table C-5
~
Results of Measur'e-ents on t:orthwest Radial Location Therrai power Distance (a) Spectrum Total Exposure NetExposure(b) tial, N-16 Expos Pu-ber Date Tiec' Levels (raft) (Feet} f:v-ber Rate (uR/ hour) Rate (uR/huur) Rate (pF/ hour) 2 18 Dec. 1972 1433 1934 370 2 17.1 20.4 9.8 20.5 0.3 11 19 Dec.1972 0747 1810 490 (d) 15.3 0.4 7.0 10.6 (d) 12 0800 1810 610 11 14.7 10.4 6.4 10.6 0.1 13 C315 1810 700 (d) 13.7 0.4 5.4 10.5 (d) 14 0325 1810 810 12 12.8 10.4 4.5 0.6 0.1 15 0844 1810 915 (d) 12.3 20.4 4.0 20.5 (d) 16 0856 1810 990 (d) 10.7 0.4 2.4 20.6 (d) 17 0913 1813 1070 (d) 10.6 10.3 2.3 10.5 (d) 18 0925 1813 1200 13 10.2 0.3 1.9 10.5 (e) 19 0958 1813 850 14 12.9 20.5 '4.6 0.6 0.3 36 1204 1814 900 15 12.7 !0.5 4.4 0.6 0.2 67 18 Jan.1973 1700 1995 1100 (d) 10.0 20.5 1.7 10.6 (d) 67 III 12 July 1972 0728 1100 --
8.3 10.3 - --
- a. Approxir. ate distance from center of turbine building.
- b. Obtained by subtracting a background exposure rate of 8.310.3 pR/ hour from the total exposure rates except for Location 2 where 7.3 0.9 SR/hcar was subtracted.
- c. Estir.ated exposure rate due to primary ti-16 gama rays--may underesticate N-16 exposure rate if significant fraction of ga ca rays are multiply scattered.
- d. t:0 ga:=a spectrum chtained at this location.
- e. Tio :al. G-16 exposure rate for this spectrum. u
- f. Measurement made during precperational radiation survey.
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O O o~
Table C-6 Results of Measurerents on Tbrtheast Breakwater Location Thermal Power Distance (a) Total Exposure flet Exposur fiumber Date Time Levels (f".it) (Feet) Rate (uR/ hour) Rate (uR/ hour) b,c) 20 19 Dec.1972 1020 1813 425 17.8 0.4 5.7 0.6 21 19 Dec.1972 1026 1813 565 17.9 10.5 5.8 20.7 22 19 Dec.1972 1030 1813 700 18.4 0.6~ 6.3 0.8 23 19 Dec. 1972 1036 1813 820 18.4 0.5 6.3 20.7 24 19 Dec. 1972 1042 1813 910 18.6 0.7 6.6 10.9 24(d) 10 July 1972 1103 910 12.1 0.5 --
25 19 Dec.1972 1047 1813 920 17.3 1.2 5.2 21.3 26 19 Dec.1972 1052 1813 930 16.7 0.7 4.6 0.9 27 1057 1813 935 15.3 1.0 3.2 1.1 28 1103 1804 950 13.5 i0.4 1.4 0.7 29 1107 1804 975 14.6 0.4 2.5 20.6 30 1115 1804 1020 12.7 0.6 0.6 0.8 ~
31 1122 1804 1055 22.4 0.3 10.3 10.6 32 1127 1804 1125 17.7 20.3' 5.6 20.6 33 1134 1804 1195 22.0 i0.5 9.9 0.6 34 1138 1804 1300 21.9 0.5 9.8 0.7 35 1144 1804 1400 24.9 0.4 12.8 0.6
- a. Approximate distance to center of turbine building.
- b. Obtained by subtracting a background exposure rate of 12.1 0.5 pR/bour from the total exposure rates.
- c. Estimated exposure rate due to primary fi-16 9 arm:a rays--may underestimate N-16 exposure rate if signi-ficant fraction of gama rays are cultiply scattered.
- d. Measurement made during preoperational radiation survey.
U
O U O o~ .
Table C-7 Results of MeasurmEts en k'est-!;orthwest Radial Distance (a) Spectrt., Total Exposure r;etExposure(b) t;al,74-16 Expos Location Therral Pcwcr Rate (pR/hcur)
Cate Time Levels (L*t) (Feet) f6ber Rate (t:R/heur) Rate (uR/ hour) tiu .be r__
635 16 16.7 0.5 8.9 !0.6 2.0 37 19 Dec.1972 1235 1814
- 910 17 12.6 20.3 4.8 10.4 2.8 38 1445 1816
" 1050 18 10.4 20.3 2.6 20.4 0.2 39 1513 1818 1526 1818 1250 (d) 9.5 10.4 1.7 20.5 (d) 40 1540 1818 1500 19 8.8 0.3 1.0 10.4 (e) 41 63 19 Jan.1973 1715 1995 1600 27 8.3 10.4 0.5 0.5 (e) 68If} 10 July 1972 1134 1600 -- 7.3 20.3 --
- a. Approximate distance to center of turbine building.
- b. Obtained by suotracting a background exposure rate of 7.810.3 SR/ hour fro:a the total exposure rates.
- c. Estir:ated exposure rate due to primary fi-16 ga=aa rays--=ay underesticate f4-16 exposure rate if significant fraction of ga:ra rays are cultiply scattered. -
- d. t;o gara spectrum obtained at this location.
- e. 74o ;;al fi-16 exposure rate at this location.
- f. Measurc=ent cade during preoperational radiation survey.
s
o O O Table C-8 Results of !'easure ents at Cverlock Area Location Thermal Power Distance (a) Spectrum Total Exposure feet Exposurc{b) f:al,ti-16 Expcs Number Date Time Levels (%'t) (Feet) f;u-ber Rate (vR/ hour) Rate (pR/ hour) Rate (pR/hcur) 42 19 Dec.1972 1610 1E09 410 20 30.9 0.5 23.3 10.6 15.1 42 19 Jan. 1973 1200 1990 450 (d) 34.4 10.8 26.8 10.8 (d) 85 19 Jan.1973 1215 1990 450 (d) 28.6 it.4 21.0 21.4 (d) 855 ' 11 July 1972 1110 450 --
7.6 !0.3 -- --
43 19 Dec. 1972 1621 1809 480 (d) 14.8 10.5 7.2 10.6 (d) 44 19 Cec. 1972 1645 1809 530 21 14.4 10.6 6.8 0.6 0.6 45 1700 1805 560 (d) 13.5 20.5 5.9 20.6' (d) 45 1713 1803 600 22 14.5 0.4 6.9 10.5 10.4
- a. Approximate distance fro::: center of turbine building.
- b. Obtained by subtracting a backgrt;:ind exposure rate of 7.6 !0.3 pR/ hour from the total exposure rates.
- c. Estimated exposure rate dea to primary f;-16 gama rays--may underestimate ti-16 exposure rate if significant fraction of gama rays are cultiply scattered.
- d. No ga :.a spectrum obtained at this location.
- e. Measurcetnt made durir.g preoperatfor.a1 radiation survey.
U
._ .~ .__ _- .
O O O Table C-9 Results of Feasure-ents on Ecst-Southeast Radial Location Therral Fewer Distance (a) Spectrum Total Exposure NetExposure(D) NaI, N-16 Expos re 1:u-ber Date Tire Levels (;Ct) (Feet) Nr&r Rate (uR/ hour) Rate (uR/bcur) Rate (yR/ hour) Cl 86 19 Jan.1973 1345 1983 430 36 11.9 0.5 3.2 20.6 0.4 87 19 Jan. 1973 1400 1987 615 (d) 10.0 20.5 1.3 0.6 (d) 88 19 Jan.1973 1415 1937 780 (d) 9.5 0.2 0.8 0.4 (d) 89 1430 1987 955 37 8.9 0.4 0.2 20.5 0.4 90 1510 1903 1085 (d) 9 0 10.5 0.3 0.6 (d) 91 1530 1933 13*0 38 8.2 !0.5 (nene) (e) 92 1545 1938 1515 39 9.2 20.4 0.5 10.5 0.2 92 II) 11 July 1972 1545 1515 ,
P 7 10.3 - -- -
- a. Approxicate distance to the center of the turbine building.
- b. Obtained by subtracting a background exposure rate of 8.7 0.3 uR/ hour from the total exposure rates.
- c. Estimated exposure rate due to primary N-16 garna rays--cay underestimate N-16 exposure rete if significant fraction of ga::na rays are multiply scattered.
- d. No garma spectrua, obtained at this locatien,
- e. No Kal. N-16 exposure rate obtained at this location.
- f. P,easurement made during preoperational radiation survey. .
- y
_.. . . . -..._ .-..~ . . - --.. ._ . .- -. . . . . - .. _- = . .
- 79 APPENDIF. D l
TABUIATED SU: NARY OF RADIOACTIVE EFF*LUENTS j The liquid and gaseous radioactive effluents of Pilgrim Station are
, summarized in Tables D-1 and D-2 respectively for the reporting period.
These tables were obtained from the Pilgrim Station "Operating and Maintenance Semiannual Report Number 2." .
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TABLE D-1 SIMI-ANNUAL StMMARY OF RADIOACTIVE LIQUID ETTLITtRIS - ;
JANt'ARY - J1TE. 1973 '
JAN, FEB. MAR. APRIL MAY JUNE Crose Radioactivity Total Released (Curies) 6.55 E-1 1.04 E-3 1.22 E-1 1.91 E-3 4.59 E-2 1.17 E-3 i t
Avs. Cone. Released (uCi/al) 1.04 E-7 4.21 E-9 6.42 E-8 3.29 E-91 2.78 E-9 2.38 E-9 l
Naz. Conc. Released (uC1/al) 1.76 E-7 4.91 E-91 2.49 E-7 1.19 E-8 9.15 E-8 4.65 E-9 Tritim Total Released (Curies) 3.95 E-2 1.31 E-4 2.40 E-2 2.21 E-4 5.95 E-2 4.51.E-4 Avg. Conc. Released (uci/al) 6.27 E-9 3.30 E-10 1.47 E-8 3.81 E-10 3.61 E-8 9.17 E-10 '
Dissolved Noble Cases Total Released (Curies) (a) (a) (a) (a) (a) (a)
Avg. Conc. Released (uct/al) (a) (a) (a) (e) (a) (a)
Cross Alpha Radioactivity Total Released (Curies) (b) (b) (b) (b) (b) (b)
Avg. Conc. Released (uCi/ml) (b) (b) (b) (b) (b) (b)
Volume of Liquid Vaste to Discharge Canal (Liters) 5.81 E55 6.91 E3 3.00 E4 8.49 E3 7.77 E4 5.37 E3 i
volume of Dilation Vater (Liters) 6.30 E9 2.47 E8 1.90 E9 5.80 E8 1.65 E9 4.92 18 Isotopes Released (Curies)
Strontium-89 9.88 E-4 1.8Ph-7 2.25 E-3 6.79 E-7 1.84 E-6 3.11 E-6 Strontium-90 2.21 E-3 5.60 E-s 1.80 E-6 5.43 E-8 5.25 E-7 2.15 E-7 l Cerium-144 2.71 E-5 4 Cesim-137 -
1.63 E-3 2.83 E-6 9.00 E-4 7.22 E-6 6.92 E-4 1.56 E-5 l Chromium-51 1.29 E-1 4.35 E-4 9.20 E-2 8.96 E-4 2.J3 E-2 4.94 E-4 !
Cobalt-58 3.99 E-2 1.46 E-4 2.69 E-3 4.77 E-4 3.8s E-3 3.07 E-4 Cobalt-60 3.07 E-5 1.23 E-3 1.51 E-4 1.20 E-3 1.03 E-4 Iodine-131 3.00 E-1 1.17 E-4 2.04 E-2 2.97 E-5 7.60 E-3 2.78 E-3 todine-133 5.02 E-2 3.25 E-3 8.52 E-41 Iron-59 2.89 E-5 Manganese-54 2.49 E-4 1.83 E-4 1.40 E-4 Neptunium-239 7.51 E-2 l
Unidentified 5.75 E-2 5.92 E-3 1,51 E-3 1.36 E-4 8.37 E*3 5.21 E-3 Forcent of Tech. Spec. Limit Total Activity Released (c)
- - 7.78 - -- 0.49 (a) EDA = No detectable activity (b) Not sessured eine3 no alpha activity was found in reactor coolant ]
(c) Based on 10 C1/ quarter limit )
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41 i I
l TABLE D-2 '
SIMI-ANNUAL SUMMART OF RADIOACTIVE 'CASEQUS ETTLUENTS I J ant'ARY - JUNE . 19 7 3 )
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JAN. yEB. MAR. APRIL E JUNE Total Noble Cases (Curies)
(a) h in Stack 1.65 E4 1.10 E4 1.52 E4 2.02 E4 2.44 E4 1.96 E4 }
(b) Reactor Building vent 1.49 E2 1.37 E2 1.47 E2 7.30 El 5.39 E2 .3.05 E2 Total Malongens (*-1) (Curies) l ,
(a) h in Stack 1.02 E-2 9.89 E-3 1.46 E-2 1.00 E-2 1.43 E-1 2.01 E-2 l (b) Reactor Butiding vent 1.23 E-3 9.72 E-4 2.09 E-3 1.24 E-2 4.18 E-2 5.32 E-3 !
Total Particulate Cross tota-Camma !
Fadioactivity (*-1) (Curies) l (a) m in Stack 1.20 E-4 8.26 E-5 8.98 E-4 1.07 E-3 8.12 E-4 1.31 E-3 (b) Reactor Building vent 1.19 E-4 1.01 E-4 2.68 E-4 6.57 E-4 1.72 E-4 1.63 E-4 !
Total Particulate Groes Alpha
- Radioactivity (Curies) (*-2) (*-2) (*-2) (*-2) (a.2) (*-2) i Total Tritium (Curies) '
(a) hin Stack 1.25 E-1 1.52 E-1 2.19 E-1 1.37 E-1 2.14 E-1 1.94 E-1 r (b) Reactor Building Vent 1.39 EO 8.20 E-2 1.07 E0 1.81 E0 1.67 E0 1.26 E0 ;
mainum 24-Hr. Noble cas 1-17 2-8 3-12 4-30 5-27 6-29 Release (Curies) 7.67 E2 6.48 E2 8.45 E2 1.03 E3 1.56 E3 1.09 E3 Force.st of Applicable Limit for Noble Cases 2.50 1.87 2.33 3.15 4.44 3.14 4 Forcent of Applicable Limit for I Ralogens & Particulates 1.15 1.06 1.45 4.73 30.07 4.14 J
!sotopes Released (Curies) i A. Malogens
- Iodine-131 (- 1.14 E-2 1.09 E-2 1,67 E-2 2.24 E-2 1.85 E-1 2.54 E-2 1 Iodine-133 (*-3) (*-8) ~ 3.92 T-2 ( *- 3) 5.41 E-2 (a.3)
Iodine-135 (*-3) (a.3) (NDA*-4) (*-3) (NDA*-4) (*-3) ,
- 8. Particulates l Barium /Lanthanue-140 2.21 E-5 3.51 E-5 4.66 E-4 1.10 E-4 3.87 E-4 4.79 E-4 Beryllium-7 1.53 E-5 5.42 E-6 i
Cesium 134 5.67 E-7 1.87 E-6 O Cesium-137 Chroetum-51 Cobalt-58 4.26 E-7 1.49 E-5 3.49 E-6 8.20 E-6 1.73 E-4 3.82 E-3 7.49 E-6 3.07 E-4 3.78 E-5 8.56 E-6 1.63 E-3 9.62 E-5 2.97 E-4 4.72 E-6 2.65 E-5 8.16 E-6 1.49 E-4 1.18 E-4 i
i i
Cobalt-60 2.99 E-6 1.99 E-6 1.06 E-5 3.22 E-6 !
Iron-59 3.56 E-6 1.89 E-6 :
Mangane se-54 2.32 E-6 1.96 E-3 6.21 E-6 Zine-65 1.91 E-6 1.30 E-6 i Eirevnium-95 4.52 E-7 '
Niobium-95 1.g2 E-7 C. Cases (*-5) l Ienon-138 4.27 E2 3.84 E2 4.73 E2 6.48 E2 8.12 E2 6.25 E2 l Krypton-87 1.72 E3 1.57 E3 1.88 E3 3.25 E3 4.17 E3 2.39 E3 Krypton-88 2.48 E3 1.77 E3 2.26 E3 3.57 E3 4.61 EJ 2.96 E3 l Krypton-853 1.05 23 7.34 E2 1.19 E3 1.56 E3 2.01 E3 1.37 E3 Ienon-135 4.09 E3 2.50 E3 3.88 E3 6.12 E3 8.81 E3 5.43 E3 l Eenon-133 2.72 E3 ' 2.63 E3 4.16 E3 4.29 E3 6.34 E3 3.03 E3 S e of Remainder 4.02 E3 1.10 E3 1.36 E3 7.62 E2 1.64 E3 1.81 E3 l t
(*-1) With half-lives greater than 8 days '
(*-2) Not seasured since no alpha found in reactor coolant !
(*-3) Quarterly analysis - Tech. Spee.
(*=4) NDA = No detectable activity l
(*-5) h in stack only l
l O
r
gu Settlement Agreement Between MASSACHUSETTS WILDLIFE FEDERATION and BOSTON EDISON COMPANY Relating to Offsite Radiological Monitoring NOTICE -
THE ATT ACHED FILES ARE OFFICI AL RECORDS OF THE DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE R_ECOR DS F ACILITY BRANCH 010. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE M All REMOVAL OF ANY PAGEIS) FROM DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.
DE ADLINE RETURN DATE RiGll.E0ilY 20 KET1.1CD?Y I
l RECORL4 F ACILITY BRANCH f
l 1
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SETfLEMENT AGREEMENT AGREEMENT (the "Agreement") made as of the 21st day of October, 1976 between the Bost.an Edison Company ("BECo")
and the Massachusetts Wildlife Federation ("MWF") .
WITNESSES:
Til AT ,
- 1. BECo is an Applicant socking a construction permit for a nuclear power reactor in a Nuclear Regulatory Commission ("NRC") proceeding docketed: Boston Edison Company et al. (Pilgrim Nuclear Generating Station, Unit 2) No. 50-471;
- 2. MWF is an Intervenor, in NRC proceedings before an Atomic Safety and Licensing Board (the "Beard". on the Pilgrim Nuclear Generating Station, Unit 2 c on-struction permit application;
- 3. MWF has advanced Contentions (2c), (3) and (5) which, among other MWF contentions have been admitted by the Board as hearing issues in the proceedings before it; fAlOfO
7, .
1
- 4. MWF Contentions (2c), (3) and (5) manifest, inter alia, a concern with the adequacy of: BECo's offsite environmental radiological monitoring program of effluent discharges from the Pilgrim Nuclear Gener-ating Station ("Pilgrim Station"), BEco's admini-stration of its Pilgrim Station offsite radiological monitoring program, and BECo's technical and mana-gerial competency;
- 5. BECo maintains that the allegations as set forth in MWF Contentions (2c), (3) and (5) are unfounded and without substance; and W!iEREAS , BECo and MWF deem it to be in their mutual in-terest and believe it to be in furtherance of NRC policy (10 CFR 2.759) and in the public interest to resolve contested issues in initial licensing proceedings by settlement; and THEREFORE, in consideration of mutual covenants herein contained, the parties agrce, subject to Board allowance of the Motion referenced in paragraph 1.01 of this Agreement, as follows: 1 l
l efl3 i
- r. .
aq 1.00 Withdrawal of MWF Contentions (2c), (3) and Q),
1.01 MWF will withdraw Contentions (2c), (3) and (5) subject to Board approval, as hearing issues, by filing an appropriate Motion with the Board in the form o f Exhibit "A" attached hereto.
1.02 MWF shall file this Agreement with the Board in support of its Motion, but the filing of the Agree-ment in this proceeding and its acceptance by the Board shall not constitute a waiver of any right of the parties to seek administrative and judicial en-forcement of this. Agreement under applicable federal and Massachusetts law.
2.00 Offsite Radiological Monitoring Program 2.01 BECo shall submit to the NRC for approval and issuance proposed revised technical specifications (associated with its Pilgrim Unit 1 operating license) for offsite radiological monitoring of Pilgrim Station effluent releases in the form attached hereto as Exhibit B, and in connection therewith BECo shall carry forward for a period of ten years commencing with the date of this Agreement as a continued part of its offsite radiological monitoring program for c[l3 .
l
{ s
L the Pilgrim Station (the "Program") those pro-visions set forth in Exhibit B which are identified therein as "Supplemental Provisions", irrespective of NRC's initial approval of Exhibit B or any future actions taken by the NRC authorizing less compre-hensive offsite radiological monitoring.unless the Supplemental Provisions or the term of their imple-mentation are otherwise modified by the mutual agreement o'f BECo and MWF.
2.02 In the event BECo seeks NRC approval to change or modify the Program, BECo will not challenge MWF's standing as a party in interest before the NRC to contest the institution of any such proposed changes or modifications for a period of ten years commencing with the date of this Agreement.
2.03 HECo shal1 provide MWF from time to time with a dosimeter to maintain, without interruption for at least a period of ten years commencing two months from the date of this Agreement, an External Gamma Exposure Station (TLD) to be established,by MWF at an offsite location on Saquish Neck (Lot #69, Saquish Beach) 4.6 miles NNW of the Pilgrim Station. {
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BECo and MWF agree that the inclusion of the SN station as a Supplemental Provision of the Pro-gram (See Exhibit B, Table 4.8.3) is subject to the continu.ed availability of the SN location to MWF and to Min?'s continued station maintenance, dosimeter retrieval and transmittal to BECo.
3.00 Offsite Radiological Monitoring Advisory Committee 3.01 BECo shall establish as soon as reasonably practi-cal an Of fsite Radiological Monitoring Advisory Committee ("Committee") to advise BECo as to the implementation and execution of the Program and make recommendations as to the continuity and scope of its provisions.
3.02 A written charter for the Committee consistent with this Agreement shall be prepared and main-tained. This document shall include the Com-mittee's membership, quorum requirements, responsibilities, record keeping and distribution, authority, scheduling of meetings, compensation and tenure.
m epl3 '
I
3.03 The Committee's enabling document shall provide for at least the following:
- a. MWF and BECo shall be entitled to a repre-sentative of their own selection, and may from time to time make substitutions at their discretion,
- b. In addition, the Committee shall include to the extent possible a representative of a Commonwealth of Massachusetts Depart-ment or Agency with radiological responsibilities (to be selected by the Commissioner of Public Health) and a regional representative of the U.S. Department of Health Education and Welfare, Food & Drug Administration having radiological i responsibilities, each of whom shall have relevant scientific or technical expertise, :
and such other persons as BECo and MWF may mutually agree upon.
I
- c. The Committee shall be composed of five to '
seven members and shall be chaired by a chairman and a vice-chairman who shall be I selected by a majority of the members of the Committee.
I 413
- d. Meetings The Committee shall meet on the call, after reasonable notice, of the chairman or vice-chairman at least semi-annually,
- c. Quorum A quorum shall constitute the majority of the current members of the Committee and shall include the chairman or vice-chairman,
- f. Responsibilities The Committee shall have the responsibility:
- 1) To review the implementation, execution and scope of BECo's offsite radiological monitoring; and
- 2) To evaluate the results of such monitoring and report the Committee's recommendations to BECo's Vice President-Nuclear or his designee.
- g. Records
- 1) Minutes shall be recorded for all meetings of the Committee. Copies of the minutes
~$ f)
o .
shall be furnished to BECo's Vice President-Nuclear or his designee, Committee members and to others whom the chairman or the Committee may direct.
- 2) Resunes or curriculum vitae shall be provided by each of the Committee members and kept by the chairman who shall furnish copies to all Committee members.
- 3) BECo shall provide a secretary to the Com-mittee who shall not be entitled te vote.
Said secretary shall maintain and distribute Committee records and minutes and other in-formation, data, correspondence and reports as the chairman may direct.
- h. Authority
- 1) The, Committee'shall be advisory to BECo's Vice President-Nuclear or his designee.
l
- 1. Docume n ta tion
- 1) BECo shall provide the Committee and its members with copies of future Pilgrim 1
of l3
.. . .=.
Station "Environmental Radiation Monitoring Program Reports" or their equivalent or replacement. BECo will provide the Committee with composite reports of monitoring results on at least a quarterly basis, or more fre-quently as the Committee may request fro'm time to time and correspondence with the NRC or other government agencies as to regulation and enforcement of of fsite radiological monitoring of the Pilgrim Station.
- 2) BECo will make available to the Committee, for inspection and copying, all offsite radiological monitoring data compiled in pursuance of the Program in the possession of its contractors, or others in privity therewith. Said data shall be retained for a reasonable period of time, but not less than one year.
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J. Term of the Committee The Committee shall continue in existence for ten years, at which time BECo and the Committee will jointly evaluate the continued role of the Committee with respect to the offsite radiological monitoring programs of Pilgrim Nuclear Generating Stajion. Continuation of the Committee after "en years shall be at the sole discretion of BECo.
- k. Compensation and Expenses
- 1) The scientific and technical specialist members of the Committee who are not in the employ of either BECo or federal or state agencies shall be compensated by BECo on a per diem basis in accordance with consul-tant fees received during.the calendar year previous to appointment to the Committee or in t he absence thereof in accordance with prevailing consultant fees for such specialty in the nuclear industry or scientific community. No j Committee member shall be entitled to 10 - fl3
compensation in excess of $2000 per year or in the case of the chairman $2500 per year, (calcula ted in 1976 dollar values) .
- 2) BECo shall pay reasonable costs incurred by the Committee and its members in meeting its obligations, including travel expenses to attend duly called meetings and Committee related administrative costs such as mailing and phone expenses, provided, however, BECo shall in no event be required to pay any legal costs or expenses.
4.00 Interim Provisions 4.01 In the event that BECo encounters a delay in achieving the minimum membership of the Committee set forth in paragraph 3.03 c. for whatever cause, BECo shall establish an interim Committee consisting of three members two of whom shall be selected in accordance with paragraph 3.03 a. and the third member shall be such other person as BECo and MWF may agree upon. The MWF representative shall serve as chairman pro-tempore of the Interim Committee. The Interim Committee shall cyl3 4
possess all of the powers and authority of the Com-mittee for a period of one year from the date of its formation or until the minimum membership of the Committee is attained, whichever event first takes place.
4.02 In the event the Committee ceases to exist prior to the termination date of the Committee as provided for in paragraph 3.03 j . BECo will provide or make availabic to the MWF representative designated in accordance with paragraph 3.03 a., the reports, information and data referred to in paragraph 3.03 i, for the period specified -in paragraph 3.03 j.
5.00 Miscellaneous 5.01 Corporate Authority The parties warrant that all necessary corporate action has been duly.taken by them, respectively, to authorize the execution hereof by the signatories.
5.02 Farties This Agreement shall be binding on the parties here-to, and their successors and assigns.
12-yl3 y , -- - - - , - . .- , . . - .
5.03 Captions J The captions in this Agreement are for convenience .
of reference only and shall not be used to construe the terms hereof.
5.04 Notice Notice or transmittals required under this Agree-ment shall be addressed to:
Boston Edison Company Attn: G. J. Davis 800 Boylston Street Boston, Mass. 02199 Massachusetts Wildlife Federation Attn: Lester B. Smith P. O. Box 343 Natick, Mass. 01761 unless changes in the above addresses are provided by registered mail.
Witness the execution hereof, under seal, as of the date first set forth above.
BOSTON EDISON COMPANY By . d4hfA -
<- Nam Tit M { h,jp h g MASSACHUSETTS WILDLIF MAS 3ACHUSETTS WILDLIFE FEDE ' ION FEDERATION l2AlJi/ - .> C -
a hame v / / I aw(c Ti e TiticO*A 'n OEcE7 t By M By , o_ o2 "me n ;L ""1 ra4&
13 -
EXHIBIT "A" !
l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Belare the Atomic Safety and Licensing Board
)
In the Matter of )
)
BOSTON EDISON COMPANY, et al. ) Docket No. 50-471
)
(Pilgrim Nuclear Generating )
Station, Unit 2) )
)
MASSACilUSETTS WILDLIFE FEDERATION'S MOTION TO WITHDRAW CONTENTIONS 2(c), 3 and 5 Now comes the Massachusetts Wildlife Federation and moves to withdraw its Contentions 2(c), 3 and 5, previously filed in this proceeding for the reason that it has entered into a Settlement Agreement with respect to the subject of these Contentions as is set forth in a separate document entitled "Settlement Agreement" .
Respectfully submitted, HENRY llERRMANN Attorney for Massachusetts Wildlife Federation, Intervenor 151 Tremont St., 27K Boston, Mass. 02111
, Tel. 617-423-6096 PN
EXHIBIT B 4.8.D Environmental Monitoring Program An environmental monitoring program shall be conducted as follows:
- 1. Environmental sampics shall be selected and analyzed according to Table 4.8.1 at the locations described in Tables 4.8.2 and 4.8.3 and shown in Figures 4.8.1, 4.8.2 and 4.8.3.
- 2. Analytical techniques used shall be such that the detection capabilities in Table 4.8.4 are achieved.
- 3. A census of gardens producing fresh leafy vegetables for human consump-tion (e.g., lettuce, spinach, etc.) shall be conducted near the end of the growing season to determine or verify the location of the garden (available for sampling) yielding the highest calculated thyroid dose.
This census is limited to gardens having an area of 500 square feet or more and shall be conducted under the following conditions as necessary to meet the above requirement:
- a. Within a 1-mile radius of the plant site, enumeration by a door-to-door, or equivalent counting technique.
- b. If no milk-producing animals are located in the vicinity of the site, as determined by item 4 below, the census described in item 3a above shall be extended to a distance of 5 miles from the site.
If the census indicates the existence of a garden at a location yielding a calculated thyroid dose g'reater than that from the previously sampled garden, the new location shall replace the garden previously having the maximum calculated iodine concentration. Also, any location from which ,
fresh leafy vegetables can no longer be obtained may be dropped from the surveillance program as long as the NRC is notified in writing, as soon as possible that r,uch vegetables are no longer grown or no longer available at that location.
- 4. A census of animals producing milk for human consumption shall be conducted at or near the middle of the grazing season to determine or verify the location yielding the highest calculated annual average thyroid dose. ,
The census shall be conducted under the following conditions as necessary :
to meet the above requirement: ,
- a. Within a 1-mile radius from the plant site or within the 15 mrem /yr isodose line, whichever is larger, enumeration by a door-to-door or ,
equivalent, counting technique, j
- b. Within a 3-mile radius for cows and for goats, enumeration derived !
from referenced information from county agricultural agents or other !
reliable sources.
If it is learned f rom this census that animals are present at a location j which yicids a calculated thyroid dose greater than from previously sampled ani ma ls , the new location shall be added to the surveillance program as soon as practicable. The sampling location having the lowest calculated I dose may then be dropped from the surveillance program at the end of the l grazing season during which the census was conducted. Also, any location i from which milk can no longer be obtained may be dropped from the surveil-7 f
lance program as long as the NRC is notified in writing, as soon as practicable, that milk-producing animals are no longer present, or milk samples are no longer available at that location.
- 5. Deviations are permitted from the required sampling schedule if spec-imens are unobtainable due to hazardous conditions, seasonal unavail-ability or to malfunction of automatic sampling equipment. In the event of equipment malfunction, every reasonable effort shall be made to complete corrective action prior to the end of the next sampling period. Any significant deviations from the sampling schedule shall be explained in the annual report.
- 6. Detailed written procedures, including applicable check lists and instructions, shall be prepared and followed for all activities involved in carrying out the environmental monitoring program.
Procedures shall include sampling, data recording and storage, instrument calibration, measurements and analyses, and actions to be taken when anomalous measurements are discovered.
Procedures shall be prepared for insuring the quality of program results, including analytical measurements. These procedures will identify the responsible organizations, include purchased services (e.g., contractual lab), include independent audits, and include systems (such as participation in IAEA and/or NBS intercalibration exercises and submission of "blind" quality control samples for analyses br_the **
1 contr,acrors)ltoidentifyandcorrectdeficiencies, investigate anomalous or suspect results, and review and evaluate program results and reports.
BASES 3.8.D and 4.8.D Environmental Monitoring Program An Environmental radiological monitoring program is conducted to verify the adequacy of in-plant controls on the release of radioactive materials.
The program is designed to detect radioactivity concentrations which could result in radiation doses to individuals not exceeding the levels set forth in 10CFR50 Appendix I.
An example'of this is the detection of I-131 in milk. Calculational Models (Regulatory Guide 1.109 March 1976) have shown that a constant concentration of 3.5 pCi I-131 per liter milk would result in a dose of 15 millirem to the thyroid of an infant consuming that allk for a year. Allowing for an open grazing season of six months, and a maximum of two half-lives between event and sampling, the lower limit of detection at time of sampling must be 2 pCi/1 (3.5 x 12/6 x 1/4 = 1.8).
A supplemental monitoring program for sediments and mussels has been incorporated into the basic program (see notes f and g to Table 4.8.1) as a result of an agreement with the Massachusetts Wildlife Federation. This **
supplemental program is designed to provide information on radioactivity levels at substantially higher sensitivity levels in selected samples to verify the adequacy (or, alternatively, to provide a basis for later modifications) of the long-term marine sampling schedules. As part of the j supplemental program, analysis of mussels for isotopes of plutonium will be I performed if radiocesium activity should exceed 200 pC1/Kgm in the edible l portions. '
- supplemental provision Gl7
The 200 pCi/Kgm radiocesium "action level" is based on calculations which showed that if radiocesium from plant releases reached this level, plutonium could possibly appear at levels of potential interest.* The calculations also showed that the dose delivered from these levels of plutonium would not be a significant portion of the total dose attributable to liquid effluents.
The program was also designed to be consistent, wherever applicable with Regulatory Guide 4.8 (Issued for comment December 1975). The following exceptions to the generic recommendations stated in Regulatory Guide 4.8 are justified due to site specific considerations:
- 1. The required detection capability for I-131 in milk is about twice the value suggested in Regulatory Guide 4.8. The justi-fication for the higher value is presented in the second paragraph of this section. This is a conservative estimate.of the capability of the milk surveillance program to detect concentrations at the appropriate annual dose level since the annual dose is proportional to the annual average concentration in milk. The detection limit for a group of samples is less than that for a single sample and is inversely proportional to the squire root of the number of sampics. The conser-vatism in this case is approximately of3F, or about a factor of 3.
- 2. Air particulates are not analyzed for radiostrontium.
The program instead calls for this analysis in milk samples. This is justified because the air-cow-milk exposure pathway can be better mon-itored at Pilgrim after the very low level releases of radiostrontium are reconcentrated in cow's milk (Ref. 1).
- 3. Sails and sediments are not routinely analyzed for Sr-90, but rather the analysis is done on a contingency basis. The rationale behind this is that Sr-90 will not contribute to long-term radionuclide buildup until the more abundant gamma emmitting nuclides appear in relatively large concentrations. Both Items 2 and 3 reflect the fact that in 3h years of operation, Pilgrim Station liquid releases of Sr-90 have amounted to only 1/1000 of the Sr-90 inventory in Cape Cod Bay water (from weapons testing fallout) and about 4/1000,000 of the direct deposi-tion on the Bay. Also, gaseous releases of Sr-90 have been only 1/100,000 of the terrestrial Sr-90 inventory within five miles of the station (Ref. 1).
- 4. Surveys are conducted annually, if necessary, to determine appropriate locations for sampling of leafy vegetables and milk. The objective of these surveys is to ensure that the environmental samples are represen- l tative of realistic food chain pathways, considering local conditions.
Results of the monitoring program will be used as "benchmarks" to verify calculational models used to predict the consequences of effluent releasee from the station. The models can then be employed to predict doses attributable to radiation deposition at any other location of interest.
The combination of monitoring results and 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-mental media always be sampled from the "worst case" locations: although i sensitivity of the monitoring results might be improved by sampling from I locations which are reasonably close to "worst case" conditions.
- in measurable quantities having a potential dose (human food chain) i significance comparable to other nuclides if present at their detection limits.
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i l Verification of the appropriate milk sampling locations on an annual basis is satisfactory as there are very few locations suitable for the grazing of dairy herds in the vicinity of the plant (Ref. 2). This '
9 situation makes it unlikely the location of the nearest dairy herd s (3.5 miles-W) will change.
- 5. Annual sampling of beef forage (in place of beef) is adequate'b'ecause beef cattle are not raised commercially in the vicinity of the site.
However, dairy cows from the Plymouth County Farm are periodically sold for beef. Feed (hay) from this location will be sampled to monitor this potential pathway for ingestion of radioactivity. If beef' cattle feeding on local forage are found at locations closer to the site, forage 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; therefore, terrestrial monitoring of groundwater is not included in this program.
- 7. Poultry sampling is not performed because poultry in Plymouth County feed almost exclusively on imported grain and are usually raised under m shelter.
- 8. Field gamma isotopic surveys are conducted to monitor radi^o$ct'isit '.In;"' s2,i soil in lieu of laboratory analysis of soil samples. The technique has several advantages over laboratory analysis. First, analysis can be performed on the same plot of land from survey to survey, and radio-activity build-up at the location can be accurately determined. Secondly, ganma exposure rate is determined directly from this technique: hence compliance with 10CFR50 Appendix I levels can be investigated directly rather than indirectly through soil sampling.
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References:
- 1. Wrenn, M.E. , "Review of Sr-90 Releases f rom Pilgrim 1 Nuclear Plant and a Comparison with Extant Environmental Levels", 1976.
i
TABLE 4.8.1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Locations Exposure Pathway (Direction-Distance) Sampling and Type and Frequency or Sample Type from Reactor Collection Frequency of Analysis AIRBORNE Particulates 11 (see Table.4.8.2) Continuous sampling over Gross beta radioactivity at one week least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter filter change. (a) Ouarterly composite (by location) for gamma isotopic. (b) h Radiciodine 11 (see Table 4.8.2) Continuous sampling with Analyze weekly for I-131 canister collection weekly 23 Soil 11 (see Table 4.8.2) Once per three years Field gamma isotopic. (c)
DIRECT 20 (see Table 4.8.3) Quarterly Gamma exposure quarterly.
Plymouth Beach and Priscilla/ White Horse Beach Annually (Spring) Gamma exposure survey.
- WATERBORNE Discharge Canal continuous composit sample Gamma isotopic (b) monthly;
- Bartlett Pond (SE-1.7 mi .) Weekly grab sample and compositt for H-3 Powder Point (NNW-7.8 mi.)(d) Veckly grab sample analysis quarterly, (c).
AQUATIC -
Shellfish Discharge outfall Quarterly (at approximate C-amma isotopic (b); also see ,
Duxbury Bay " ~ ~ ~ 3-month intervals) note (f). * ;
Manomet Pt. .
Plymouth or Kingston Harbor Marshfield (d)
- Note (f) and beach surveys are supplemental provision.
TABLE 4.8.1 (Cont'd) locations Exposure Pathway (Direction-Distance) Sampling and Type and Frequency or Sample Type from Reactor Collection Frequency of Analysis Irish Moss Discharge outfall Semi-annually Gance isotopic (b)
Manomet Pt.
Ellisville (d)
Lobster Vicinity of discharge Four times per seasen Gamma isotopic (b) on point edible portions.
Offshore (d) Once per season Fish Vicinity of discharge Quarterly, Groups I and II (c) Gamma isotopic (b) on point In season, Groups III and IV (e) edible portions (e)
Offshoic(d) Annually, each group _ _-. ,
Sediments Rocky Point Semi-annually i Plynouth Harbor Gammaisotopic(b)(c),!
see also note (g)-'*
Duxbury Bay Plymouth Beach
~
Manomet Pt.
Marshfield (d) 4 23 IWGESTION (Terrestrial)
Milk Plymouth County Farm Semi-monthly during periods when Gamma isotopic (b) Sr-89, (W-3.5 mi.)(h)- Whitman animals are on pasture, other- 90 monthly; radiciodine Farm (NW-21 mi.) (d) wise monthly analysis all samples.
Cranberries Manomet Pt. Bog At time of harvest Gamma isotopic (b) on -
(SE-2.6 mi.) edible portions.
Bartlett Rd. Bog (SSE/S-2. 8 mi.)
Pine St. Bog (WNW-17 mi.) (d)
Wote (g) is supplemental provision 3
E - - - _ _ _ _ _ _ . . _ _ _ _ _ _ . . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
TABLE 4.8.1 (Cont'd) locations Exposure Pathway (Di rection-Distance) Sampling and Type and Frequency or Sample Type from Reactor Collection Frequency of Analysis Tuberous and Karbott Farm (SSE-2.0 mi.)(h) At time of harvest Gamma isotopic (b) green leafy Bridgewater Farm on edible portions.
vegetables (W-20 mi.) (d)
Beef Forage Plymouth County Farm Annually Gamma isotopic (b)
(W-3.5 mi . ) (h) 4 3
e y
_ - _ +~ nsi
Notes (a) If gross beta radioactivity is greater than 10 times the control value, gamma isotopic will be performed on the sample.
(b) Gamma 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 will be performed on the sample.
(d) Indicates control locaticn.
(c) 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. Bottom Oriented II. NearBottom III. Anadromous IV. Coastal Distribution Migratory Winter flounder Tautog Alewife Bluefish i Yellowtail flounder Cunner Rainbow smelt Atlantic herring Atlantic cod Striped bass Atlantic menhaden Pollock Atlantic mackerel Hakes (f)* [ Mussel samples from four locations (immediate vicinity of discharge outfall, )
- Manomet Pt., Plymouth or Kingston Harbor, and Green Harbor in Marshfield)
'will be analyzed quarterly as follows:
Lone kilogram wet weight of mussel bodies, including fluid within shells will be collected. Bodies will be reduced in volume by drying at about 100 C.
. Sample will be compacted and analyzed by GE(Li) gamma spectrometry or alternate technique, if neussary, 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 Cc-144.
'The mussel shell sample from one location (the location nearest the discharge canal unless otherwise specified pursuant to licensee's agreement with Mass, WildlifeFederation)willbeanalyzedeachquarter. One additional mussel shell sample (from the Green Harbor location, unless otherwise specified pursuant to Licensee's agreement with Mass Wildlife Federation) will 'eo analyzed semi-annually. Unscrubbed shells to be analys.ed will be dried, processed, and analyzed similarly to the mussel bodies.
Because of the small volume reduction in pre-processing of shells, sensitivi-ties attained will be less than that 1or mussel bodies. The equipment and .
h counting times to be employed for analyses of shells will be the same or comparable to that employed for mussel bodies so that the reduction in sensitivities (relative to those for mussel bodies) will be strictly limited to the effects of pocrer geometry related to lower sample volume redaction.
Shell samples not scheduled for analysis will be reserved (unscrubbed) for '
possible later analysis, depending upon recommendations of the review comittee.
- Supplemental provision.
. **All sensitivity values to be determined in accordance with footnote (a) a to Table 4.8.4., viz., LLD at 95% confidence icvel on % ; 50% confidence '.
level on Vf (See HASL-300 for definitions).
f 7
Notes (Cont'd)
If radiocesium (Cs-134 and Cs-137) activity exceeds 200 pCi/kg (wet) in mussel bodies, these samples.will be analyzed by radiochemical spearation, electrodeposition, and alpha spectrometry for radioisotopes of plutonium, with a sensitivity of 0.4 pCi/kg.
(g)* Sediment samples from four locations (Manomet Pt., Rocky Pt., Plymc uth Harbor, and head of Duxbury Bay) will be analyzed once per year (preferably early summer) as follows:
Cores will be taken to depths of 30-cm, minimum depth wherever sediment conditions permit by a hand-coring sampling device. If sediment conditions do not permit 30-cm deep cores, the deepest cores achievable with a hand-coring device will be taken. In any case, core depths will not be less than 24-cm. Core samples will be sectioned into 2-cm increments, '
[and surface and alternate increments analyzed, others reserved. Sediment sample volumes (determined by core diameter and/or number of individual cores taken from any single location) and counting technique will be i sufficient to achieve sensitivities of 50 pCi/kg dry sediment for Cs-134, Cs-137, Co-60, 2n-o5, and Zr-95 and 150 pCi/kg for Ce-144. In any case .
individual core diameters will not be less than 2 inches. )
i The top 2-cm section fron each core will be analyzed for Pu isotopes
)(Pu-238,Pu-239,240) using radiochemical separations, electrodeposition, l and alpha spectrometry with target sensitivity of 25 pCi/kg dry sediment. !
,7Vo additional core slices per year (mid-depth slice from core samples L taken at Rocky Point and Plymouth Harbor, unless otherwise specified )
Vp ursuant to licensee's agreement with Mass Wildlife Federation) will be Lsimilarly analyzed.
(h) These locations may be altered in accordance with results of surveys )
discussed in paragraphs 4.8.D-3 and 4.8.D-4.
I 1
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- Supplemental provision 4
qf!7 L
l TABLE 4. 8. 2 AIR PARTICULATES, GASEOUS RADI0 IODINE AND FOIL SURVEILLANCE STATIONS Sampling Location Distance and (Sample Designation) Direction from Reactor Offsite Stations 23 miles NW
- East Weymouth (EW)
- l Plymouth Center (PC) 4.5 miles W-WNW Manomet Substation (FG) 2.5 miles SE ,
Cleft Rock Area (CR) 0.9 miles S Onsite Stations Rocky Hill Road (ER) 0.8 miles SE I
Rocky 11111 Road (WR) 0.3 miles W-WNW l
Overlook area (OA) 0.03 miles W Froperty Line (PL) 0.34 miles NW Pedestrian Bridge (PB) 0.14 miles N East Breakwater (EB) 0.35 miles ESE j l
Warehouse (WS) 0.03 elles SSE l
l
- Control Station 1
(17
TABLE 4.8.3 EXTERNAL CAMMA EXPOSURE SURVEILLANCE STATIONS (TLD)
Distance and Dosimeter Location (Designation)_ 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 I'lymouth (NP) 5.5 miles WNW Plymouth Center (PC) 4.5 miles W-WNW South Plymouth (SP) 3 miles WSW Manomet (MS) 2.5 miles SSE Manomet (ME) 2.5 miles SE ;
Manomet (MP) 2.25 miles ESE-S Clef t Rock Area (CR)
~ ~ ~ ~
0.9 miles S
[SaquiihNeck(SN)** 4.6 miles NNWl * **
Onsite Stations >
Rocky Hill Road (ER) 0.8 miles SE tucrowave Tower (HT) 0.38 miles S Rocky Hill Road (WR) 0. 3 miles W-WNW Rocky Hill Road (B) 0.26 miles SSE Property Line (H) 0.21 miles SSW Property Line (I) 0.14 miles W Public Parking Area (PA) 0.07 miles N-NNE I
Overlook Area (OA) 0.03 miles W 1
- Control Station .. ___ . . . . _ . _ . . . . . . . . _ _ . . ._.
- Data f rom this surveillance station is subject to detector maintenance and retrieval by a private party not subject to control by the licensee. Therefore, the requirement to maintain this station is contingent on station availability I l
and maintenance by the outside party.
- Suppleme.tal provision ty517
~
-____2______________-_--__-___'___?__T____~_~__.
l TABLE 4.8.4 l
(d)
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Lower Limit of Detection (a) ,,
Water Airborne particulate Wet solids Dry solids Milk Analysis pCi/1 or gas - pCi/M3 pC1/Kg pCi/Kg pC1/1 Gross beta 2 1 x 10-2 II-3 330 Mn-54 15 130 60
, Fe-59 30 260 120 s
CO-58,60 15 2 x 10-2 130 60 4
g Zn-65 30 260 120 Sr-89 10 40 10 Sr-90 2 8 150 2 Zr/Nb-95 16 I-131 7x 10-2 80(b) 2 (c)
Ce-134,137 15 1 x 10-2 80 150 15 Ba/La-140 15 15 (a) The nominal lower limits of detection at the 95% confidence level (defined in the ERDA Health and Safety Laboratory procedures manual, HASL-300).
(d) This table applies to all analyses other .
(b) Applies only to analysis of green leafy vegetables. than those for which higher sensitivities app 1; (c) Sensitivity with 25*' error at the 95% confidence level- in accordance with Notes (f) and (g) to Table 4.8.1. --
" V ?)
4 Green Harbor a
'Oo Cape Cod
, Bay a
O Duxbury, Bay 0 1 7 3 4 5 Kingston Harbor SCALE IN MILES Plymouth Harbor 6
Rock y Point Warren b b Cove O*
e6 Manomet and Stage O Points
( ,
4 LEGEND O IRISH MOSS O E//isville .
O SOFTSHELL CLAMS Harbor e MUSSE LS A SEDIMENT E QUAHOGS '
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1 i g.
Figure 4.8-1 Typical !!olluac, Algae and Sediment Campling Stations 'k l
_ic_ g n 1 I
. 'or 6.9.C Unique Reporting Requirements
- 2. Environmental Program Data
- a. 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 1 of each year. The reports shall include summaries, internret-ations, and s,4tistical evaluation of the results of the radio-logical environmental surveillance activities for the 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 also include the results of any land use surveys which affect the choice of sample locations. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem.
Results of all radiological environmental samples shall be 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 for the missing results. The missing data shall be submitted ,
as soon as possibic in a supplementary report,
- b. Anot alous measurement report. If radioactivity in an indicator 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, environn.antal factors, or other aspects necessary to explain the anomalous result.
i l
l
=* A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate. The results of the con-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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LEGEND
- 1 PROPERTY LINE (0)
- 13 RCCKY HILL ROAD 18) 2 PROPERTY LINE IF)
- 4 PHOPERTY LINE 1G1
- 16 WHITE HORSE ROAD (WH8
- 17 PROPERTY LINE (E hir 1 6 FROPERTY LINE (H) 18 ROCKY HILL ROAD (WR) 7 PUBLIC PARKING ARE A (PA) 19 PROPERTY LINE (Ji*
8 PEDESTRI AN 6 RIDGE (PB) 20 PROPE R TY LINE IK A .
9 OVERLOOK ARE A tOA) 21 ROCKY HILL HOAD (ER) 1 10 E AST BHE AKWATER lEB) 22 PROPERTY LINE ILW 11 PROPE HTY LINE (C)
- 23 W AREHOUSE (WS) 12 PROPERTY LINE (HB) t 24 PROPERTY LINE (PL)
O DOSIMETER (TLDI A AIR PART!rul ATES AND DOstMETERS (TLD)
- additional station not required by Specification 4.8.D.1 1
Piqure 4.8.2 Location of Onsite Monitoring Stations 16 6
. . h I . .
- _ li l
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l t *
) A 15 .
N l 5kilgg i
e 'OM IL g, Cape Cod 1
Boy n . 1 MIL gg 0
0#
Plymouth 16 Boy 30 4A W
o a 50 8 A I
9O A
0 14 10 0
11 0 12 n .
O DOstMETER (TLDI A AIR PARTICUL ATES AND DOSIME TE RS ITLD) 13 O o S LEGEND
^ 1' O'U h 8 0R Y 1551
- 9 MANOMET WE) 2 KiNGSTON IKS) to M ANOMET (MSI 3 NCHTH PLYMOUTH tNP) 11 M ANOME T (V Bl
- 4 PliMOUTH CE NTE R (PC) 12 COLLEGE POND ICPl
- 5 SOUTH PLYMOUTH ISP) 13 S AG AMORE (CSI l 6 B AYSHORE ORivE IBD;* 14 PLYVOUTH AlHPORT (S A) 7 cLE rT Roc < ARE A scRI 15 E AST WE TMOUTH #E W)
) e M^NoMETmPi 16. Saguish Neck (SN)
- additional stations not required by Specification 4.8.D.1 Figure 4.8.3 Location of Of f site Monitoring Stations l 17yI7
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