ML20003F730
| ML20003F730 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/01/1981 |
| From: | Sowdon T BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20003F728 | List: |
| References | |
| NUDOCS 8104230487 | |
| Download: ML20003F730 (100) | |
Text
{{#Wiki_filter:___ _ _ _ _ - . __ I I* I ' PILGRIM NUCLEAR POWER STATION I I Environmental Radiation Monitoring Program REPORT NO.13 g I . I I JANUARY 1 THROUGH DECEMBER 31,1980 I I ISSUED: APRIL 1981 ENVI O MENT L A D RAD 0 CL HEALTH AND SAFETY GROUP I I BOSTON EDISON COMPANY I I vov2596VU
I : E l I ! I I l I ! BOSTON EDIS0N COMPANY PILGRIM NUCLEAR POWER STATION Environmental Radiation Monitoring Program l REPORT NO. 13 January 1, 1980 through December 31, 1980 I I I I I Prepared by: /An Tliomas L. Sowdon 4 Environmental and Radiological Health and Safety Group Leader I ; I o' ' s"' 1't ': ^r<*' ' ' I I
I I TABLE OF CONTENTS Section Page I Introduction and Summary I II Description of Monitoring Program 1-1 2-1 III Results of Analyses 3-1 A. Air Particulate 3-5 B. Iodine 3-12 C. Soil 3-16 D. Direct Radiation 3-17 E. Waterborne 3-31 F. Shellfish 3-35 G. Algae (Irish Moss) 3-39 H. Lobster (Arthropods) 3-43 I. Fish 3-47 J. Sediments 3-51 K. Milk 3-56 I L. M. Cranberries Vegetation 3-63 3-67 N. Forage 3-71 I IV References 4-1 Appendix A Anomalous Measurements A-1 Appendix B Radioactive Effluents B-1 Appendix C Soil Survey C-1 Appendix D Radiological Environmental Monitoring Program D-1 Appendix E 1980 Garden and Milk Animal Survey E-1 I I I I I
I I LIST OF TABLES Table Number Page I I-1 PNPS-1 Capacity Factors 1-2 I III-A-1 III-A-2 Sample Station Identification Codes ERMAP Results - Air Particulate Filters 3-3 3-7 III-B-1 ERMAP Results - Charcoal Cartridges 3-13 III-D-1 Thermoluminescent Dosimeter Locations 3-20 III-D-2 Results of TLD Measurements - January 3-23 III-D-3 Results of TLD Measurements - February 3-24 III-D-4 Results of TLD Measurements - March 3-25 III-D-5 Results of TLD Measurements - Quarter 2 3-26 I' III-D-6 Results of TLD Measurements - Quarter 3 3-27 III-D-7 Results of TLD Measurements - Quarter 4 3-28 I III-D-8 III-D-9 Quarterly Average Exposure Rates Field Survey Exposure Rates 3-29 3-30 III-E-1 ERMAP Results - Waterborne 3-32 III-F-1 ERMAP Results - Shellfish 3-36 III-G-1 ERMAP Results - Algae 3-40 III-H-1 ERMAP Results - Lobster 3-44 ERMAP Results - Fish 3-48 I III-I-1 III-J-1 ERMAP Results - Sediments 3-52 III-J-2 Results of Sediment Analysis for Plutonium 3-55 III-K-1 ERMAP Results - Milk 3-58 III-L-1 ERMAP Results - Cranberries 3-64 III-M-1 ERMAP Results - Vegetation 3-68 l III-N-1 ERMAP Results - Forage 3-72 1 1I I II I I ii
I I LIST OF FIGURES Figure Number M III-A-1 Gross Beta Activity - Air Particulates - I III-A-2 Indicator Stations Gross Beta Activity - Air Particulates - 3-10 Contro'. Station 3-11 III-B-1 Concentration of I-131 - Charcoal Filter - Indicator Stations 3-14 III-B-2 Concentration of I-131 - Charcoal Filter - Contre.1 Station 3-15 III-D-1 Location of Offsite Monitoring Stations 3-21 III-D-2 Location of Onsite Monitoring Stations 3-22 III-K-1 Concentrations of Cs-137 in Milk - All Stations 3-61 I III-K-2 Concentrations of Sr-90 in Milk - All Stations 3-62 E I I I I l I I 111 l I
I I I. Introduction and Summary This report presents a summary of the results of measurements of direct radiation and radioactivity in environmental media in the vicinity of the Pilgrim Nuclear Power Station - Unit 1 (PNPS-1) and at selected control locations for the period January 1 - December 31, 1980. I The results of this Program indicate that PNPS-1 has had a negligible and most often immeasurably small impact on the environment in the vicinity of the plant. Conservatively estimated doses resulting from the measured highest station mean concentrations are typically less than 1% of the doses resulting from naturally occurring radionuclides and residual fallout from atmospheric nuclear weapons testing. I Estimates of concentrations of radionuclides in vegetation and milk and estimates of dose to man, as quoted in this report, were made using methods similar to those described in Regulatory Guide 1.109 and 1.111. The performance record of the PNPS-1 for the calendar year of 1980 reflects an average capacity factor of 52.7%. Monthly capacity factors are given in Table I-1.
-I A tabulation of radioactive effluents from the PNPS-1 is provided in Ap-per Jix B for the 1980 calendar year.
There were seven Anomalous Measurement Reports made during 1980. The media involved were mussels and algae from the discharge canal and on two occa-sions, milk from the Plimoth Plantation. I It should be strongly emphasized that the measured concentrations in milk were characteristic of fallout nuclides. These measured anomalous concen-trations were 10,000 to 1,000,000 times in excess of the concentrations expected to be present in milk as a result of effluents from PNPS-1. In other words, PNPS-1 probably contributed much less than 1% of the measured concentrations of Sr-90 and Cs-137 in ailk at the Plimoth Plantation. The remainder of the measured radioactivity is unquestionably due to atmos-I pheric fallout from weapons tests, not PNPS-1. 1-1
I I The measured concentrations of Co-60, Cr-51 and Mn-54 in the discharge canal samples are unquestionably. due to liquid effluents from PNPS-1. However, the maximum dose due to consumption of either algae or mussels with the peak concentrations would result in less than 0.01 mrem to the total body and 0.05 mrem to any organ. Clearly, this dose is not signi-I ficant when compared to the natural background dose rate of 80 to 100 mrem / year as it is much less than 1% of background. Essentially, all samples required by the PNPS-1 Technical Specifications were collected on schedule. The only exceptions were occasional failures of the air samplers and/or site inaccessability and occasional unavail-ability of milk samples from the Plimoth Plantation. Such incidents af-I fected only about 5% of the total number of samples scheduled Jor col-lection. The only other deviation from the technical specification was that on one occasion a measurement of Sr-90 in a sample of milk taken from the Plimoth Plantation on 1/28/80 was high enough to warrent an Anomalous Measurement Report which was not submitted due to an administrative error. This mea-I surement of Sr-90 was 1,000,000 times in excess of the concentration ex-pected to be present as a result of effluents from PNPS-1. In other words, there is no question that this measurement was the result of a source other than PNPS-1. This source was undoubtly, atmospheric fallout due to atmos-pheric weapons tests. l I All other required Anosialous Measurement Reports were made in a timely manner. I lI 1 lI 1 I 1-2
I l I TABLE I-1 PNPS-1 CAPACITY FACTORS 1980 (Based on 670 MWe)
, Month Percent Capacity January ' 12.08 February 0 March 0 April 0 May 21.32
-June 85.05 July 89.73 August 80.54 i September 95.57 October 76.64 November 70.02 December 101.88 I ^-- 3
I I I I 1-3 I
I I II. Description of the Monitoring Program The Radiological Monitoring Program conducted in accordance with the PNPS-1 Technical Specification is included as Appendix D. The program is essen-tially identical to that conducted during the latter half of 1977 and I incorporates supplemental provisions as specified in the Settlement Agree-ment between the Massachusetts Wildlife Federation and Boston Edison Com-pany, June 9, 1972 . The exceptions to the program are as follows: I 1) There is no TLD station at Saquish neck since the Mass Wildlife Fed-eration has not yet provided a means for placement and retrival of the TLD as prescribed by the agreement noted above. I 2) There is no longer a milk producing cow at the Plymouth County Farm. The location of the nearest cow is now at the Plimoth Plantation (2.2 miles W). Samples have been collected from this new location since 1979. I 3) There is no longer a Karbott Farm. Vegetable samples are now col-lected at the two nearest gardens near the WNW and SE site boundaries. I The 1980 site Census conducted according to Technical Specification re-quirements determined that there are several vegetable gardens near the site boundary in the W-WNW and SE-ESE sectors (see Appendix E). In the ESE sector, i.he nearest garden is at the Shakalis residence (0.6 miles ESE). A sample of squash sprouts was collected from a nearby garden on 9/10/80 (the actual garden was at the resident of Mr. J. B. Work due to the unavailabi-lity of appropriate samples from the Shakalis residence). In the west direction the location of the nearest observed garden of approximately 500 I square feet was at the residence of Mary Lloyd Evans (0.7 miles W). A sample of Chinese Cabbage was collected from this location on 9/11/80. The i location of the nearest animal which produces milk for human consumption is still at the Plimoth Plantation (2.2 miles W). Samples of ailk have been collected from this location since May of 1979. I 2-1 I
)
l During the 1980 year milk was not always available in sufficient quantity from the Plimoth Plantation to allow sample analyses. However, every reasonable effort was made to collect samples on the frequency specified in the technical specifications. I I I I I I I I I ' I I I I I , 22
I I III. Results of Analyses This section summarizes the results of the analyses of environmental media samples in compliance with the monitoring program described in Appendix C. The section is divided into sub-sections, each of which describes a parti-cular media or potential exposure pathway. I The results of analyses conducted on environmental media are maintained in a computerized data file which constitutes a data base used for statistical analyses by a computer code entitled ERMAP3 . I ERMAP calculates a set of statistical parameters for each radionuclide I whose concentration is reported in a given environmental medium. This set of statistical parameters includes separate analyses for (1) the indicator stations, (2) the control stations, and (3) the station having the highest annual mean concentration. For each of these three groups of data, ERMAP calculates:
- 1) the mean value of all measured concentrations; I 2) the square root of the mean square deviation (this is an estimate of the sample variance);
I 3) the lowest and highest calculated concentrations;
- 4) the number of positive measurements divied by the total number of measurements; Entries listed under the heading LLD* are the mean of all LLD values, where I '
each LLD equals 4.67 times the standard error of the associated background measurement. I .s e I
- Lower Limit of Detection '.
3-1
I The results of ERMAP are provided in each subsection for the appropriate media. In addition, plots of measured concentration as a function of sampling time are included for certain isotopes in certain media in an effort to simplify interpretation of the results. Sample station identification numbers used by the ERMAP program are provided I in Table III-A-1. I I I I I I I I I I I I 32 I
I I TABLE III-A-1 Sample Station Identification Codes Station Code Media Number Station Location I Air Particulate and Iodine Filters 00 01 03 Warehouse (0.03 mi-SSE) Rocky Hill Road (0.8 mi-SE) Rocky Hill Road (0.3 mi-WNW) I 06 07 08 Property Line (0.34 mi-NW) Pedestrian Bridge (0.14 mi-N) Overlook Area (0.03 mi-W) 09 East Breakwater (J.35 mi-ESE) 10 Cleft Rock (0.9 mi-S) 15 Plymouth Center (4.5 mi-W-WNW) 17 Manomet Substation (2.5 mi-SSE) 21 East Weymouth (control - 23 mi-NW) Waterborne 11 Discharge Canal Bartlett Pond (1.7 mi-SE) I 17 25 Power Point (control 7.8 mi-NNW) Shellfish 11 Discharge Canal Outfall I 12 13 15 Plymouth Harbor Duxbury Bay Manomet Point I h.gn iS Moss) 24 11 Marshfield (Control) Discharge Canal Outfall 15 Manomet Point 22 Ellisville (Control) Lobster (Arthropods) 11 Vicinity of Discharge Canal Offshore I 15/99 25 Offshore (Control) Scituate (Control) Fish 2 Round Hill Point - Offshore - (Control) l I 11 21 22 Vicinity of Discharge Canal Auto Trawl Station - Offshore - (Control) Offshore - (Control) l Priest Cove - Offshore - (Control) 99 Se.iment 11 Rocky Point 12 Plycouth Harbor 13 Duxoury Bay 'I 14 Plymouth Beach 15 Manomet Point 24 Marshfield (Control) ll l 3-3 I l
I I I TABLE III-A-1 (Continued) Station Code I Media Number Station Location l Milk 11 Plymouth County Farm (3.5 mi-W) , 15 Plimoth Plantation (2.2 mi-W) 21 Whitman Farm (control-21 mi-NW) 22 King Residence (control-12 mi-W) Cranberries 13 Manomet Point Bog (2.5 mi-SE) 14 Bartlett Road Bog (2.8 mi-SSE/S) 23 Pine Street Bog (Control-17 mi-WNW) l Vegetation 11 Plymouth County Farm (3.5 mi-W) I 15 Greenwood Garden (0.5 mi-SE) ( 3 16 Work Residence (0.7 mi-ESE) g 17 Evans Garden (0.7 mi-W) 22 Bridgewater Farm (Control-20 mi-W) I Beef Forage 11 15 21 Plymouth County Farm (3.5 mi-W) Plimoth Plantation (2.2 mi-W) Whitman Farm (Control-21 mi-NW) 22 Bridgewater Farm (Control-20 mi-W) 'I lI lI I I I 3-4 lI
I I III. A. Air Particulate Filters I Sample collection systems consisting of a cellulose disc particulate filter and a charcoal filter cartridge are used to collect particulate matter and iodine isotopes respectively. Analyses of the particulate filters for beta radiation is performed weekly. In addition, quar-terly composite particulate samples are analysed for gamma emitting isotopes. Table III-A-2 presents the results of the ERMAP for air particulate analyses. (The station identification numbers correspond to the locations identified in Table III-A-1.) I For ease of interpretation of these measurements, a plot of gross beta activity vs. time for all indicator stations is provided in Figure I III-A-1 and for the control station in Figure III-A-2. Positive measurements of specific isotopes characteristic of reactor operation (i.e. , Co-60, Zr-95, Nb-95, Ru-103, Cs-137 and Ce-141) were observed at the Warehouse (Station 00 - 0.3 mi - SSE) and on Rocky Hill Road (Station 03 - 0.3 mi - WW and Station 01 - 0.8 mi - SE). I All of the positive measurements on Rocky Hill Road were seen in composite samples for the fourth quarter. As can be seen from Figures III-A-1 and III-A-2 there were peaks in the gross beta activity during the fourth quarter (early October) at the control station in East Weymouth (Station 21 - 23 mi - NW) and at Cleft Rock (Station 10 - 0.9 mi - S). The presence of an elevated gross beta activity at the control station is indication of a contribution of radioactivity from fallout which could also have influenced the measurements made on l Rocky Hill Road during that same period. - l The positive measurements of Co-60 and Cs-137 made at the Warehouse are certainly due to effluents from PNPS-1. However, even if a person
were to breathe air with the highest concentrations measured at the l station with one or more positive measurements, they would receive an antiual dose of less than 0.0003 mrem to the total body and 0.02 mrem to the maximum exposed organ (teen - lung). I 3-5
l
I In consideration of the natural background dose rate of 80 to 100 mrem / year, there was clearly no significant environmental effect observed in the air particulate media as a result of the operation of PNPS-1. I I I I I I I I
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I I III. B. Iodine The same sample collection systems used to collect airborne par-ticulates are used to collect gaseous iodine on a charcoal filter cartridge. The cartridge is removed and analyzed for I-131 weekly. The results of the ERMA? program for this media are provided in Table III-B-1. It is apparent from this table that the mean value of the calculated concentrations for the indicator stations is less than the mean value for the control station. The calculated mean value for the highest indicator station (Station 07 - Pedestrian Bridge - 0.14 mi - N) is significantly higher than I the calculated mean of the control station. This a:sasured mean con-centration la the result of only one positive measurement (week ending 2/11/80) and is probably the result of gaseous effluents from PNPS-1. However, even if a person were to breathe air with the highest mea-sured mean concentration they would receive an annual dose of less than 0.04 mrem to the thyroid and less than 0.0001 mrem to the total body. The results of these analyses are presented graphically in Figure III-B-1 for the indicator stations and Figure III-B-2 for the control station. There was clearly no significant environmental effect observed in the l airborne gaseous iodine collection media as a result of operation of PNPS-1. l l l I I I 3-12
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III. C. Soil Soil surveys at eleven locations are required once every three years in compliance with the revised Technical Specifications which went into effect on April 19, 1977. These in-situ surveys were conducted during July of 1979. The results of these surveys are included in Appendix C of this report for reference information only. They do not constitute measurements made during the 1980 calendar year. I I I .I l I l l 3-16
i I I Direct Radiation III. D. l
- 1. Continuous Thermoluminescent Dosimetry I Thermoluminescent dosimeters (TLD) of the CaSO4 (Dy) type are used I
to record direct gamma radiation from all sources including direct and scattered radiation from Nitrogen-16 in the turbine building, and cosmic and other natural and artificial gamma radiation. TLD's are installed at the locations identified in Table III-D-1 and on Figures-III-D-1 and III-D-2. I Tables III-D-2 through III-D-8 show monthly and quarterly average doses from direct gamma radiation in uR/hr at these stations. Prior to 1980, TLD's were read out monthly although the Technical Specification indicated that a quarterly read out. frequency was adequate. In an effort to improve the statistics associated with tne measurement of extremely low radiation levels around PNPS-1, the frequency of read out was decreased to quarterly at the end l of the first quarter of 1980. l g As a result, data is available for January, February and March on E a monthly basis and for the rest of the year on a quarterly basis. l In addition to average doses for each TLD for each read out per-iod, geographic regional average doses for sectors of different nearness are computed; viz, in immediate proximity to PNPS, more distant but near the site boundary, up to several miles away - l
" neighborhood", and far away (background). Each set of data show consistent trends; the near plant dosimeters (OA, PB, PA, WS) stand out among all readings and have an average above the dose l
rates further away. The next region has a lower average dose 1 l rate, and beyond 0.7 mile (distant neighborhood and background) l l the dose rates are statistically consistent. 3-17 I
I , In all cases, the near plant levels are distinctly higher than those off-site and off-site dose rates are not significantly sensitive to distance variations beyond the site itself. Thus beyond the " exclusion area" (for this purpose, the 0.2'.,-0.7 mile region), dose rates show no significant plant effect; pcpulated areas are therefore beyond the limits of elevated dose rates.
- 2. Field Survey A gamma exposure survey of Plymouth Beach and Priscilla/ White Horse Beach was conducted during May of 1980. The results of this most recent. survey are in agreement with the last three I beach surveys conducted for 1979, 1978 and 1977. In addition, a comprehensive soil survey of 11 locations was conducted during the spring of 1979. This study included both gamma exposure rate I measurements and in-situ gamma spectrometry analysis for each location. Laboratory soil analyses were also conducted for selected locations. The results of this study are presented in Appendix C. The latest gamma exposure survey was conducted using a high pressure ion chamber (HPIC) Model MDL260, Serial Number 007 . The design and calibration of this instrument were de-scribed in the report of the survey of June 1976 ,5 The present survey was designed to detect differences in the external exposure rate encountered at beaches near the ;.lant (Plymouth and Priscilla/ White Horse) and a control location (Duxbury). The detector's calibration was checked before each measurement.
The data (Table III-D-9) indicate that the exposure rates at Plymouth Inner Beach and Priscilla/ White Horse Beach are not significantly greater than the exposure rates measured at the control station in Duxbury. The small differences are likely due to the presence of granite beach stones which are essentially absent at the Duxbury location. I l 3-18 1 I
I I It has been demonstrated that proximity to beach stones results in higher exposure rates than in sandy areas (see Annual Report No. 10). I This survey indicates that the natural background exposure rate These I at beaches near Pilgrim Station is probably 7-9 uR/hr. results are in complete agreement with similar measurements 6 performed in Maine , where the natural background exposure rate at shoreliae locations was found to vary between 6.6 and 14.5 uR/hr. These exposure rates were also found to vary directly 6 with the size and proximity of granite outcroppings , I These latest measurements are also in agreement with the soil survey mentioned earlier. The results of that survey indicate that off-site dose rates have a range of 8.0 to 8.5 uR/hr with an average of 8.2 uR/hr. I I I I I I I I 3-19 I
O E Susveillance Stationan Station Specification Near Plant EaClusion Area 826 s t an t Ne t shtaks hood backg r ound Statton Sua item ttsastance (0-0.16 miles) (0.25-0.7) (0.96-6.5 miles) (e-23 miles) Code Fig. No. (miles) Direct &on Overlook Area OA II-2 9 0.09 W-WSW ,_g
*Werehouse WS II-2 23 0.10 5-SSE I-
*Pedantrian IT) bridge PB II-2 0 0.15 HNW PD Public Pasksng 'E PA Il-2 7 0.86 NW-NNW C3 Area F '
A II-2 5 0.25 W-WSW C
- Property Line ~S
- Property Line l' II-2 2 0.21 WNW-NW
- East Breakw.ter Property Line EB B
II-2 II-2 10 13 0.31 0.32 ESE SSE
]gg p Property Line H Il-2 6 0.33 SW m in (SW) gg Psopesty Line ! Il-2 3 0.33 W WNW (n m
*Progwaty Line PL 11-2 24 0.34 WNW-NW 2 e--
- Property Line D 18-2 1 0.37 NW-NNW --( e -e
- Property Line L II-2 22 0.40 ESE-SE 8
- Property Lina HB II-2 12 9.43 SE O C:1 C II-2 !! 0.44 ESE-SE O I hs *Psoporty Line M H j, 'Psogerty Line G Il-2 4 0.44 W stocky ullt no44 (West)
Wu Il-2 le 0.51 WNW
}
gg (West) g Nicsowave tower HT Il-2 le 0.55 S-SSW rn Cleft Hock Area CR II-! 1 0.63 S-SSW ,o Hocky H6!! Hoad ER II-2 21 0.6 al SE (East) r
- hay Shore Drive BD II-l 6 0.70 W-WNW O O
- Emerson Road EM II-2 15 0.97 SSE >
*Proposty Line J II-2 19 1.21 S-SSE "'I
*Psoporty Line (Sout hl E Il-2 17 1.23 8
- White Nosse Road
- Property Line WH at 11-2 Il-2 16 20 1.31 1.32 SSE S-SSE g h
Hanomet Point MP II-l 8 2.25 E-ESE Nanomiet Elem. School MP. II-I 9 2.50 SE Manomat substation MS II-l 10 2.50 SSE South Plymouth SP II-! 5 3.00 WSW
- Mahomet Beach MS Il-1 11 3.50 SE-SSE Plymouth Center PC 35-8 4 4.50 W-WNW Notth Plymoulit MP II-1 3 5.50 WNW
- Standish Shores SS 15-1 1 6.25 NW (puul ,
- College rond CP Il-1 . 12 6.50 SW Shesmasa Airport (Fly) SA II-I 14 S.00 WSW cedarville Sub. (Sag) CS II-I !) 10.00 S-SSE atingston Substation KS II-! 2 10.00 WNW 6:ast Weymouth LW II-! 15 23.00 MW
- Nut scegut s eil t,y opuratin9 license. '
4-pastence= mudmured trom Unit I smactur building.
TABLE III-D-2 GAMMA EXPOSURE (TLD) DATA FOR JANUARY 1980 TLD MICROR/ NO. STATION HOUR +- 2 SIGMA 50 CP 6.44 +- 1.89 51 4.30 +- 0.87 I CR 52 CS 5.35 +- 1.32 53 ER 5.33 +- 1.11 55 EW 6.04 +- 1.41 I 3003 57 3013 KS MB ME 5.00 6.06 5.32
+-
+-
+-
0.91 1.61 1.16 4.23 +- 0.89 I 59 60 61 MP MS NP 8.32 5.69
+-
+-
1.40 1.25 62 PC 6.14
+- 1.40 I 63 3010 65 SA SP SS 3.77 6.38 6.88
+-
+-
+-
0.56 1.01 1.75 66 WR 7.79 +- 1.98 67 BD 9.88 +- 1.79 68 EB 8.29 +- 1.81 69 EM 4.42 +- 1.01 70 MT 3.75 +- 0.69 71 OA 6.84 +- 2.71 72 PA 4.96 +- 1.39 73 PB 9.56 +- 1.70 74 WH 6.58 +- 1.75 75 A 6.49 +- 1.53 76 B 8.13 +- 1.59 I 77 78 79 C D E 6.12 8.52 4.75
+-
+-
+-
2.16 1.12 1.02 l 80 F 4.41 +- 1.07 3005 G 8.31 +- 1.94 82 H 5.52 +- 1.91 83 I 5.50 +- 1.80 84 J 8.46 +- 2.07 85 K 8.75 +- 1.89 86 L 8.88 +- 1.86 87 PL 3.99 +- 1.06 88 WS 6.92 +- 2.49 92 HP 5.98 +- 1.66 ! 3046 RL 3.32 +- 0.51 37 RL 3.24 +- 0.51 l Geographic Regional Averages this period are: Near Plant (0 .16 mi) 7.07 +- 1.43 Exclusion Area (.25 .68 mi) 6.36 +- 0.45 Distant Neighborhood (.7-6.5 mi) 6.52 +- 0.40 Background (8-23 mi) 5.04 +- 0.74 3-23 I
I TABLE III-D-3 GAMMA EXPOSURE (TLD) DATA FOR FEBURARY 1980 TLD MICR0R/ NO. STATION HOUR +- 2 SIGMA 1 CP 37.01 +7 24.79 23.06 +- I 4.96 31 CR 32 CS 31.22 +- 8.41 33 ER 13.44 +- 2.48 34 EW 16.56 +- 3.98 35 KS 21.24 +- 6.16 36 MB 27.05 +- 6.01 38 ME 16.54 +- 3.15
+-
I 39 40 41 MP MS NP 16.42 10.73 13.81
+-
+-
3.57 4.17 2.97 42 PC 10.30 +- 2.52 43 SA 16.85 +- 4.35 45 SP 19.60 +- 4.34 46 SS 15.89 +- 3.44 I 47 48 3 WR BD EB 18.30 17.24 33.12
+-
+-
+-
7.14 3.68 7.60 90 EM 22.56 +- 6.72 I 91 94 95 MT OA PA 15.86 12.74 12.60
+-
+-
+-
4.73 2.66 2.44 I 96 97 98 PB WH A 27.84 15.15 85.42
+-
+-
+-
6.04 3.04 42.99 99 B 20.33 +- 6.84 I 3033 3001 3042 C D E 15.27 5.09 12.78
+-
+-
+-
3.44 2.43 4.89 3043 F 0.00 +- 0.00 3044 G 13.11 +- 3.18 3045 H 9.60 +- 3.35 20 11.82 +- 3.85 I I 3048 J 8.64 +- 2.15 23 K 11.97 +- 2.45 1008 L 8.46 +- 2.54 I 1009 1011 2011 PL WS HB 15.01 13.67 19.63
+-
+-
+-
5.05 3.17 5.67 37 RL 7.57 +- 0.95 3046 RL 10.02 +- 3.12 I Geographic Regional Averages this period are: Near Plant (0 .16 mi) Exclusion Area (.25 .68 mi) 16.71 20.50
+-
+-
2.57 3.33 Distant Neighborhood (.7-6.5 mi) +- 2.07 I Background (8-23 mi) 3-24 17.05 21.47 +- 3.99
- -- ~ ~ '
W I I I TABLE III-D-4 GAMMA EXPOSURE (TLD) DATA FOR MARCH 1980 I TLD NO. STATION MICR0R/ HOUR +- 2 SIGMA 50 CP 14.55 +- 2.86 I 51 52 53 CR CS ER 20.09 24.32 17.17
+-
+-
+-
4.53 5.25 3.90 I 55 3003 57 EW KS MB 18.52 27.28 17.33
+-
+-
+-
4.47 10.65 3.90 3013 12.67 +- 3.07 I ME 59 MP 17.71 +- 8.42 60 MS 12.59 +- 3.64 61 NP 11.75 +- 2.90 62 PC 10.26 +- 3.43 63 SA 11.14 +- 3.15 3010 SP 16.30 +- 5.34 65 SS 12.19 +- 3.66 66 WR 14.39 +- 4.53 67 BD 19.13 +- 6.03 68 EB 12.89 +- 2.58 I 69 70 71 EM MT 0A 9.01 14.64 16.22
+-
+-
+-
1.67 3.78 4.59 72 PA 17.19 +- 3.26 73 PB 73.39 +- 20.44 74 WH 14.55 +- 5.77 75 A 10.50 +- 2.66 I 76 77 78 B C D 14.49 17.15 14.55
+-
+-
+-
3.23 4.31 6.78 l3 79 E 15.22 34.60
+-
+-
3.65 8.36 3 80 F
+-
3005 G 11.27 3.15 82 H 18.60 +- 4.17 83 I 16.39 +- 6.01 84 J 9.98 +- ~2.53 i 85 K 13.94 +- 3.82 l 86 L 13.14 +- 2.41 87 PL 29.40 +- 6.09 88 WS 44.61 +- 13.30 92 28.48 +- 5.60 I HB 37 RL 5.21 +- 1.02 ! 3046 RL 5.86 +- 1.13 I Geographic Regional Averages this period are: Near Plant (0 .16 mi) 37.85 +- 8.34 Exclusion Area (.25 .68 mi) 17.98 +- 1.28 l I Distant Neighborhood (.7-6.5 mi) Background (8-23 mi) 13.81 20.31
+-
+-
1.21 4.36 3-25 ll
I I TABLE III-D-5 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #2 1980 I TLD NO. STATION MICR0R/ HOUR t 2 SIGMA I 40.96 26.38 1 CP +- 31 CR 23.80 +- 5.97 32 CS 23.77 +- 5.65 33 ER 16.53 +- 3.38 I 34 35 36 EW KS MB 20.44 17.21 17.35
+-
+-
+-
4.44 4.41 5.21 I 38 39 40 ME MP MS 21.82 17.43 20.12
+-
+-
+-
8.68 3.32 5.94 41 NP 16.44 +- 3.33 I 42 43 45 PC SA SP 14.14 18.40 17.56
+-
+-
+-
3.38 4.65 3.87 I 46 47 48 SS WR BD 16.83 29.28 26.47
+-
+-
+-
3.65 6.50 5.62 3 EB 27.13 +- 10.42 90 EM 23.19 +- 5.75 91 MT 0.00 +- 0.00 94 OA 24.24 +- 7.86 95 PA 17.26 +- 3.64 96 PB 25.45 +- 5.96 97 WH 20.54 +- 6.01 98 A 47.66 +- 22.25 99 B 18.81 +- 5.63 3033 C 17.68 +- 3.25 t 3001 D 15.38 +- 2.78 3042 E 14.87 +- 3.86 3006 F 8.86 +- 1.59 3044 G 17.35 +- 5.14 . g 3045 H 0.00 +- 0.00 l g 20 I 16.04 +- 2.96 3048 J 11.28 +- 1.91 23 K 13.48 +- 2.42 1008 L 12.60 +- 9.77 1009 PL 18.05 +- 3.95 1011 WS 42.40 +- 8.62 2011 HB 17.81 +- 4.17 37 RL 1.92 +- 0.29 3046 RL 2.03 +- 0.53 I Geographic Regional Averages this period are: 27.34 +- 4.53 Near Plant (0 .16 mi) Exclusion Area (.25 .68 mi) 20.50 +- 2.32 l g Distant Neighborhood (.7-6.5 mi) 19.50 +- 2.28 Background (8-23 mi) 19.96 +- 3.21 3-26
I TABLE III-D-6 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #3 1980 I TLD NO. STATION MICR0R/ HOUR t 2 SIGMA 50 19.74 +- 5.92 I CP 51 CR 20.23 +- 7.61 52 CS 26.22 +- 8.76 53 ER 20.23 +- 6.29 I 55 3003 57 EW KS MB 24.37 22.06 14.98
+-
+-
+-
12.96 12.20 4.70 3013 19.94 +- 6.99 I ME 59 MP 19.37 +- 6.08 60 MS 18.27 +- 5.83 61 NP 18.36 +- 6.86 I 62 63 3010 PC SA SP 12 98 12.70 11.75
+-
+-
+-
5.23 5.45 5.58 5.07 I 16.75 65 SS +- 66 WR 16.84 +- 4.99 67 BD 23.25 +- 8.06 68 EB 16.03 +- 4.75 I 69 70 71 EM MT OA 12.57 27.25 29.17
+-
+-
+-
3.77 11.60 12.65
+-
I 72 73 74 PA PB WH 19.11 63.47 16.99
+-
+-
5.83 23.24 5.14 75 A 19.93 +- 6.95 I 76 77 78 B C D 21.75 13.82 18.39 v-
+-
+-
8.48 4.23 6.41 I 79 80 3005 E F G 18.21 25.09 14.23
+-
+-
+-
5.34 7.41 5.31 82 H 19.10 +- 7.22 83 I 17.34 +- 7.78 84 J 11.78 +- 3.45 85 K 18.55 +- 5.46 l l 86 L 16.56 +- 4.89 l 5 87 PL 22.87 +- 8.30 88 WS 0.00 +- 0.00 92 23.48 +- 7.37 I HB 3014 RL 2.10 +- 0.79 93 RL 1.85 +- 0.68 Geographic Regional Averages this period are: ' Near Plant (0 .16 mi) '7.25 J +- 13.59 1.89 I Exclusion Area ('.25 .68 mi) 19.57 +- Distant Neighborhood (.7-6.5 mi) 16.90 +- 1.57 Background (8-23 mi) 21.34 +- 6.86 3--27
I I l I l TABLE III-D-7 GAMMA EXPOSURE (TLD) DATA FOR QUARTER #4 1980 TLD MICR0R/ NO. STATION HOUR r- 2 SIGMA 34.97 +- 22.76 I 1 CP 31 CR 35.18 +- 8.23 32 CS 26.73 +- 7.32 33 ER 17.29 +- 4.92 I 34 35 36 EW KS MB 26.64 21.66 25.30
+-
+-
+-
5.76 4.59 6.48
+-
I 38 39 40 ME MP MS 27.53 19.09 23.79
+-
+-
5.87 5.34 7.59 41 NP 17.90 +- 4.50 I 42 43 45 PC SA SP 24.35 18.31 22.40
+-
+-
+-
8.20 5.15 7.48
+-
I 46 47 48 SS WR BD 17.55 29.77 16.95
+-
+-
4.48 10.13 4.22 3 EB 27.12 +- 5.50 I 90 213 94 EM MT OA 21.94 0.00 43.15
+-
+-
+-
5.23 0.00 9.90 1 95 PA 18.60 +- 6.47 96 PB 82.66 +- 8.26 97 WH 23.99 +- 5.88 98 A 48.89 +- 25.42 99 B 0.00 +- 0.00 3033 C 21.91 +- 7.17 3001 D 14.56 +- 3.26 l l I 3042 3006 3044 E F G 23.10 22.15 18.97
+-
+-
+-
7.90 4.71 4.43 ( 214 H 11.20 +- 2.11 20 I 18.45 +- 3.76 3048 J 17.12 +- 3.95 23 K 18.49 +- 4.90 1008 L 15.93 +- 5.41 l 1009 PL 20.76 +- 5.21 l 1011 WS 32.23 +- 6.55 l 2011 HB 21.92 +- 6.25
+-
44 RL 2.17 0.45 54 RL 2.69 +- 0.72 Geographic Regional Averages this period are: Near Plant (0 .16 mii 30.66 +- 5.28 Exclusion Area (.25 .63 mi) 23.15 +- 2.54 Distant Neighborhood (.7-6.5 mi) 22.30 +- 2.29 Background (8-23 mi) 23.34 +- 3.86 3-28
I TABLE III-D-8 QUARTERLY AVERAGE EXPOSURE RATES 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Sta. Micror/Hr Micror/Hr Micror/Hr Micror/Hr CP 18.86 +- 8.16 40.96 +- 26.38 19.74 +- 5.92 34.97 +- 22.76 CR 15.21 +- 2.15 23.80 +- 5.97 20.23 +- 7.61 35.18 +- 8.23 19.54 +- 3.21 23.77 +- 5.65 26.22 +- 8.76 26.73 +- 7.32 ICSER 11.57 +- 1.49 16.43 +- 3.38 20.23 +- 6.29 17.29 +- 4.92 EW 13.25 +- 1.95 20.44 +- 4.44 24.37 +- 12.96 26.64 +- 5.76 KS 17.05 +- 3.82 17.21 +- 4.41 22.06 +- 12.20 21.66 +- 4.59 IMB 16.32 +- 2.36 17.35 +- 5.21 14.98 +- 4.70 25.30 +- 6.48 ME 11.20 +- 1.45 21.82 +- 8.68 19.94 +- 6.99 27.53 +- 5.87 MP 12.29 +- 2.82 17.43 +- 3.32 19.37 +- 6.08 19.09 +- 5.34 10.40 +- 1.83 20.12 +- 5.94 18.27 +- 5.83 23.79 +- 7.59 IMS NP 10.17 +- 1.39 16.44 +- 3.33 18.36 +- 6.86 17.90 +- 4.50 PC 8.75 +- 1.42 14.14 +- 3.38 12.98 +- 5.23 24.35 +- 8.20 10.27 +- 1.72 18.40 +- 4.65 12.70 +- 5.45 18.31 +- 5.15 ISASP SS 13.70 11.43
+-
+-
2.18 1.71 17.56 +- 16.83 +- 3.87 3.65 11.75 16.75
+-
+-
5.58 5.07 22.40 17.55
+-
+-
7.48 4.48 i WR 13.22 +- 2.80 29.28 +- 6.50 16.84 +- 4.99 29.77 +- 10.13 BD 15.09 +- 2.29 26.47 +- 5.62 23.25 +- 8.06 16.95 +- 4.22 EB 17.78 +- 2.68 27.13 +- 10.42 16.03 +- 4.75 27.12 +- 5.50 EM 11.72 +- 2.28 23.19 +- 5.75 12.57 +- 3.77 21.94 t- 5.23 l 3 MT 11.00 +- 1.94 0.00 +- 0.00 27.25 +- 11.60 0.00 +- 0.00 l 5 OA 11.61 +- 1.93 24.24 +- 7.86 29.17 +- 12.65 43.15 +- 9.90 PA 11.16 +- 1.37 17.26 +- 3.64 19.11 +- 5.83 18.60 +- 6.47 PB 34.88 +- 6.54 25.45 +- 5.96 63.47 +- 23.24 28.66 +- 8.26 11.79 +- 2.11 20.54 +- 6.01 16.99 +- 5.14 23.99 +- 5.88 IWHA 33.43 +- 14.04 47.66 +- 22.?5 19.93 +- 6.95 48.89 +- 25.42 B 14.03 +- 2.50 18.81 +- 5.63 21.75 +- 8.48 0.00 +- 0.00 g C 12.44 +- 1.90 17.68 +- 3.25 13.82 +- 4.23 21.91 +- 7.17 l g D 9.23 +- 2.24 15.38 +- 2.78 18.39 +- 6.41 14.56 +- 3.26 l E 10.54 +- 1.98 14.87 +- 3.86 18.21 +- 5.34 23.10 +- 7.90 l F 18.00 +- 3.81 8.86 +- 1.59 25.09 +- 7.41 22.15 +- 4.71 l G 10.77 +- 1.58 17.35 +- 5.14 14.23 +- 5.31 18.97 +- 4.43 H 10.82 +- 1.82 0.00 +- 0.00 19.10 +- 7.22 11.20 +- 2.11 I 10.86 +- 2.31 16.04 +- 2.96 17.34 +- 7.78 18.45 +- 3.76 l J 8.98 +- 1.29 11.28 +- 1.91 11.78 +- 3.45 17.12 +- 3.95
- E K 11.38 +- 1.57 13.48 +- 2.42 18.55 +- 5.46 18.49 +- 4.90 L 10.03 +- 1.30 12.60 +- 9.77 16.56 +- 4.89 15.93 +- 5.41 PL 15.29 +- 2.51 18.05 +- 3.95 22.87 +- 8.30 20.76 +- 5.21 WS 20.55 +- 4.27 42.40 +- 8.62 0.00 +- 0.00 32.23 +- 6.55 HB 17.25 +- 2.58 17.81 +- 4.17 23.48 +- 7.37 21.92 +- 6.25 RL 5.28 +- 0.48 1.92 +- 0.29 2.10 +- 0.79 2.17 +- 0.45 RL 6.24 +- 1.09 2.03 +- 0.53 1.85 +- 0.6d 2.69 +- 0.72 l
lI 3-29 I
I TABLE III-D-9 I Location Exposure Rate (uR/Hr) Beach Terrain I khite Horse Beach 6.1 1 0.3 Sandy, granite (near Hill P Avenue) boulders on beach bhite Horse Beach 5.3 1 0.3 Sandy (in back of Blue Sail Bar) I Plymouth Beach (outer beach) 4.6 0.3 Sandy Plymouth Beach 4.7 1 0.3 Sandy (inner beach) I Plymouth Beach 7.1 t 0.2 Sandy, granite (behind Berts Restaurant) boulder on beach Duxbury Beach (Control) 5.1 0.4 Sandy with small I (ocean side) amounts of gravel I I I , 3-30
I I III. E. Waterborne Samples of seawater are collected at three locations, the Station Discharge Canal, (Station 11), Bartlett Pond (Station 17 - 1.7 mi - SE) and Powder Point (Station 25 - 7.8 mi - NNW). The discharge canal I sample is collected by a continuously compositing sampler which extracts a sample of about 20 ml of water from the canal every one-half hour. Grab samples are taken weekly from each of the other two locations. The results of the ERMAP program for seawater samples are presented in Table III-E-1. I The only positive measurement in this media was Cs-137 in the dis-charge canal on one occasion (monthly composite for May). No other isotopes characteristic of reactor operation were observed at this station and the mean value of the Cs-137 concentration is well within one standard deviation of the mean value at the control station. Therefore, it is not clear that PNPS-1 is responsible for this obser-vation. There were no positive measurements at the other indicator station (Bartlett Pond - 1.7 mi - SE) and therefore there was clearly no significant environmental effect observed in the seawater media as a result of the operation of PNPS-1. I I i i I I 3-31
Pitrop!M I s.F F M I T F FNVIGespat NT at k a n int ilL I C a t *Of I Todit.G MS/D7/?T. 90mmany FnW THF WEulpo 17/11/79 = 17/98/en MEDluMt Waff W . SFa t'NI T $ e Pf l /L T T F h - R ADIONiiCl inF A ThnfraTOD 9 f a T IO..n wf GMF 97 STATinN C HN i k nq teraftndi (NO. ANatvsFs) No=INat wra,N,wannf.ahn ,
*FaNeGaNGF,arn =Faw.paNGF,aNo (NDN ROUTINF)* h0 DFTFrTFDee ht . hFTFCTFDee LLn 9fa. NO. DFTFCTEnee BE.7 ( 36) 8.otect ( Pf3 A t.5)E o 11 ( 3.9 A l.71E o (.3.7 A 19.alF 1
( on (.7.0 1.31E I (.l.7 71F 1 et n/ 241e e( 0/ l?le et 4/ 121e n 40 ( 36) 2.orear ( i;na 1)F 7 li ( 3.1 i 11r a ( 3.o a .iir 2 ( 0) (=2.0 . 3a.71E I ( 2.4 3.5tf 7 ( 2.e
- 3.6)F 2 et 17/ 24)e e( 12/ 12)e el 12/ 121e CR=51 ( 36) 1.7Eeot (.1{2 a 1.s)F o it ( 6.6 4 Po.'7iE .I (=l.6 & l.9)F n
( 01 (.l.5 l. elf 1 (.t.4 . ,9)F l et c/ 2mie et o/ IP). et n/ 121. MNe54 ( 36) 8 (.5E7 A 17.3)F 7 11 (=6.9 A 93.81F 3 f 7.2 & 19.11F 2 ( 0) (.t.6 = 1.n)t n (.8.8 = 15.2)E .I et o/ 24). *( 0/ 12)e et n/ 121e F1 -4 m m 2=
. . 3= 2 CD C0 58 ( 36) 8 f.5de a 11.41F 7 11 ( t.5 A 2.01E 1 (.l.k & 2.8)F 1 -4 >> r-I" ( 0) (.t.5 1.71F o (.2.A = 8)F 0 hg T(rn gl *( 0/ 24)e et 0/ 171* of 0/ 121e gjpgll
- o v1 -
( o. FE.59 ( 36) 1.oEeot (.lg .3g 4.9)t 1 25 ( 8.4 g 7.81F .1 g 7.8)E .1 gj pg 4 ( 0) (=#.l . 4.0)E o (.3.a . 6.3)F o -4 e US *" of o/ Pale et n/ IPle et 0/ 121e CD.60 ( 361 A .' (.2g h A 7.11F =1 29 (.l.2 h P.3)E .1 (.l.2 & P.3)F .I ( 0) (.2.2 et n/ 241e 2.0)E n et o/ 121e (-1.5 et n/ 12)e 1.7)F o g ZN.65 ( 16) 4 (.2l0 a. 7.9)F 1 11 ( 7.6 A 44.31F .7 (=N.1 & 4.1)F 1 ( 0) (.P.9 3.1)E o (.2.9 . 1.n)F o et n/ Pale et o/ 12)e et 0/ 121e py[$) , ( a. 2n.95 ( 36) i.oreni -4;i i 3.aie i 7s ( .. 1 5.3iF .. i s.33r -i ( oi f.3.2 a.=ie n (.i.e . . 7iF ..
- .( .. i 7.,e .( oi ,71 .( .. i ,ne (plll)
II { C -ls e NON.Rouff>E HrFFwe f.e THF wo.ss u fiF %FpakafF *f a %e ed F PF t.T A >HirH *Fws GwFaTER TwaN TFN (to) TlHF9 TMF SVFuaGF RaCaGWnHNn F ald fwF PFd!Hn DF TMF WFPowT em THF FWaCTinN OF sappe F anatvsre vfFintr.G nFTFrianeF HFasueFPF*iS a (f.F. 33 SIGMA) TA lanica1FD withlN e( ).,
E E E E E E E
PILGulM I liF F S I T F F%vikoN*twTel santninGTCat .nNi ink i
- G *t/07/27 MHaMapy FDA T*F F F R i nfi 12/31/79 . t?/4t/ha i
MEDIUMt M ATE R = Sta l'NTTS: prt/l.ITFW R ADIONUCLinE S Ihotrafnk MTattons HIGwFmi STafinn C ON T wist locafinns (NO. ANALV8F8) NOM { N a t. NFAN,WahGF,aND p{AN,RahGFe an n "Eah,pakGF,akn (NON.ROUTINFla LLD Nn.' nETFrTFnee STA. Nn. nFTECTEDee hD. OFIFCTEDee NO.95 ( 36) 2 (.5(0 & tt.A)F .? 29 ( 3.7 A 1.41E 1 ( 3.7 & t.4)F 1 ( 01 (=t.o . l.3)E o (.t.9 - to.3)F . et 0/ 24)e e( 0/ 121e et o / 121 e ! 4G=lloM( 36) 1.4 Ecol (.6g 5a to.7)F 1 25 ( t.e A 2.siE o ( l.A & 7.8)E O ! ( n) (.t.a . 0)E I (.I.3 l.8)F 1 ef of 241e *( 0/ 17)e of 0/ 12)e i RU=103 ( 36) 8 (=4(2 & t.A)E .I 29 (=6.2 & t.71E =t f.6.2 & t.7)F 1 ( 0) (=2.6 . . 8)E o (=t.7 3)F o of 0/ 24)e e( 0/ 12)* et 0/ 121e i
! RU.306 ( 36) 8.0 Foot (*1(7A t.11% o 24 ( 5.4 A tl.a)E 1 ( 5.e & lt.0)F =t
( 0) (.l.a - 3.n)E 1 (-4.7 to 0)E o of O/ Pole *( 0/ 121e of 0/ 121e ,,3j n to I co I.131 ( 36) 0 ( Ift & 31.7)E .2 2% ( t.8 A 6.'8)F .1 ( l.P A 6.8)E .I @ [f l e ( 0) (-2.7 - 1.7)E o (.3.4 . 5.9)F 0 rt [j ef 0/ 24)e e( 0/ IP)e of 0/ 121e gf[[ ]' c ** CS.134 ( 36) 9 .' (.5(2 & l.A)E .1 11 f.4.8 A 2.45E .I (=6.6 & 3.u)F 1
@[ /n
( el (.l.a . 3.4)E o (.l.9 . 3.0)F 0 %- e i et 0/ 24)e *( 0/ t?)* ef 0/ 121e C8=137 ( 36) 9 .' ( 3l9 A 7.n)F 1 11 ( 6.6 A 3.SiF =t ( 4.7 & P.3)F -I ( 0) (.t.3 2.6)E o (-1.3 = 2.6)E o (.6.7 18.9)F -l
;
ef t/ pe). og t/ 12). et 0/ 121e mags) I SA=l40 ( 36) 1.5 Ecol f 5ft A 2.0)E .t it (.a.a i 4.ait . (.t.3 A 7)E o ([ I ( 0) (.2.5 7.9)E o (.5.e - 3.23F n of 0/ Pole of 0/ 12)e et 0/ 12)e i ,5 CE=141 ( 36) 2.0Ecot (=3.7 A a.1)E t 17 ( 2.7 A 7.8)E I (**** & 7.4)E 1
$$E
. ( 0) (.3.. . s..)E 2 (. .. . ..iE 2 e( 0/ 24)e et 0/ 321e et 0/ 121e ([[I
~
CE=144 ( 36) 8.0 Ecol ( 6(7 &. 9.6)E .t 17 ( i t.2if n (=2.3 A 1.3)F n l. i 1 ( 0) (.t.1 1.1)E I (.9.2 = 6.3)E o
! ef 0/ 2 ele e( 0/ 123e e( 0/ 121e {[[$h --
- s=-
gemas e NON.ROUTIHE RFFFRS Yn THE NtlanFR nF MFPapa(F MFASilWFMENTM .HICH bFEF GREATER ] THAN TFN (10) TIMFS Tar avFwaGE maCNGunuNn FnD THE PERInn OF THE AFPORT ee THF FNACTink nr 34 Mpt.F ANALv5FS V TEL DING nE TFC TaRL F ME A SilREHENTS
} (I.E. 33 SIGMA) IS INDTCaTFD =ITHIN *( 1e.
i [ a
M M M M M ll 4 i d PILGRIM I OFFSITF FNvf RONMENTat RADInt0GTCAL MUNITnRtwG nt/u2/21
SUMMARY
FOR THF PERinn 12/3t/19 . 92/31/en i MEDIUMS WATER = SFA 88N1T3: PCI/LITFN RADIONUCLinFS INDIC&YOR STATInNS HIGMFST STATION C ON T Nf el ififATION9 (NO. AN AL Y SE S) NOMINAL ME AN,R A NGE', A ND MEAN,RANGF,AND MFAN, RANGE,4Nn { (NON.ROUTTNEin Lt.n NO.' 0FTECTFDee S T A .' No. OFTECTEDee NO. OFTFCTE0** _4 l RA.226 ( 36) 6.0F+01 ( Ife A 1.9)E o 11 ( 2.e a 6.'nir n (.t.1 g a,1)F o ^Q Qr w ( 0) (.2.4 . 5.1)E (.2.% . 1.1)F t ::s rn i 6 et at Pale et n/ l?)e *( n/ 121e [m ! A :s - TH.228 ( 36) ( n) 1.cE+0t ( If 3 A= (.T.n
.A)F 6.4)E o
o 29 f.T.2 A t o.'3 i E 1 f.T.2 & (.6.8 . to.3)F a.21F 1 u
$7 ou rn of 0/ 24)e *( 0/ 123e et 0/ 121e %
! :43 ( 12) 9.0 Feet ( el1 a. 9.7)E 1 11 ( 5.5 A 9.7)F t (.4.3 g e.6)F ( 0) (.l.9 2.a)E 2 (.l.4 . 61F 2
*( 0/ Als e( 0/ 4)e e( p/ 4)e c::P I
9 , e NON.R0llTINE RFFFRS TO TNF NilMRE R OF SFPARATF > F A S81RF 4E N T S **4IC H >FRF GREATER THAN TFN (to) TimFS TMF AVFRAGF mACMGROUND FOR THE PENIOD OF THE REPnRT
** TMF FRACTION OF SAMPLF ANALYSFS YTELnTNG 0FTECTARLE MEASU#EMFNTS (1.E. >3 SIGMA) T8 INDTCATED WITHIN *( 1e.
s l W9 f
I III. F. Shellfish I Shellfish are normally sampled quarterly from 5 locations, the Station Discharge Canal, Duxbury Bay, Manomet Point, Plymouth Harbor and Marshfield. The results of the ERMAP program for shellfish are pre-It is clear from this table that there have I sented in Table III-F-1. been positive measurements of many isotopes (Cr-51, Mn-54, Co-58, Co-60, Nb-95, Cs-137) in the discharge canal. In addition there have been pos:itive measurements of Co-60 and Ce-141 at Manomet Point (3 miles - SE). I These observed concentrations are most probably the result of PNPS-1 liquid releases. However, even if a person were to consume the maximum annual quantity of seafood (5 kilograms / year) with the highest mean concentrations of these isotopes they would receive a dose of less than 0.004 mrem to the total body and about 0.02 mrem to the most restrictive organ (adult GI-LLI). I When compared to the natural background dose rate of 80-100 mrem / year, there was clearly no significant environmental impact observed in I shellfish as a result of the operation of PNPS-1. Mussel shells collected from the discharge canal exhibited a mean con-centration of 29 pCi/kg of Co-60. No other isotope was detected. These measurements are undoubtly due to liquid effluents from PNPS-1. However, since shells are not consumed by man there is no potential ic: pact on man from this media. E I 3-35
S W/ S S S & & M a
**
- R k I M ! DFF AT TF FNVIGHbMFNTag Dant ng AGir g{ NON!TdQIbC Ml/07/?T.
9HMMaWV Fnp THF PEston gp/gt/T9 . gp/)l/en j mediums SHFLLFISH UNITS: PCI/ar. mff Ran!ONUCLInfM INnirafnp STaffnN9 HIGHT 97 ST6 TION Contwon tr. CATIONS (NO. AN AL YSF S) knMINat MFAN.WANGF. ann MFAN,saNGF.shn eFah,nakGF,64n (NON.R0uYINE)* Li n NO] 0FTFrTFOn e Sta[ NO. OFTFCTEDee 40 nFTFCTEnme
............. ........ ........c.......... .... ..................... ...................
SE=7 ( 24) 7 ( 2(2 & .o)E 1 13 ( 2.5 1 3.0)E i ( 9.1 & 4.03E o ( %) (.a.o . 12.1)E I (.t.9 . In.2)E o et 5/ Pole *( 0/ ele et 0/ 4)e N.40 ( 74) 5 ( 1(6 &. 1)E 3 19 ( t.A a l35E 3 ( t.8 & 8)E 3 ( 0) ( t.t 2.7)E 3 ( t.t . 2.7)F 3 ( l.2 = 1.7)F 3 et 20/ Pole e( e/ ele et e/ a)e CR=51 ( 24) ( 01 1.7E+07 ((.9.1 t(54. 1.9)E 13.9)t I I 11 ( 8.3 h f l.a . A g e1F 1 33.9)F t (.O.6 g (.l.5 = a.p)F 7)F t G of i/ 20ie et i/ .)e et o/ .ie aw.5a ( Pai 2.nr.07 ( 2;9 4 6.n)E .i it ( 2.7 4 s.e)E o (.l.n g 5.3)F .
-4
( i) (.7.i . _ 7.9)E o ( 6.3 793.0)F 2 (.t.7 .A)E o et 2e Paie et 2/ .)e et 0/ .se g;jE@$ g; u> n, ,2 j, C0=58 ( 2a3 2.cf.07 ( 4,3 & 95.7)E 2 It ( 3.1 1 2 d'j F A (=1.2 & a 9)F el [2 7, [[ os ( il (.i.3 .o)E i (.i.3 ega.a)E .2 (.i.7 33r n ,,rn --
*( 1/ Pole et t/ ele et u/ ele {;jg4, 3: r :
FE=59 ( 24) 1.0E*01 ( I *3 g a 3.2)E o 37 ( 2.9 i 3.'5 5 E D (.t.a g .e)g a gj e" ( 0) (.4.3 = 3.1)E I (.2.3 o 01F o et 0/ 20)e et 0/ 8)* et 0/ ele Co.60 ( 2s1 2.oE.o? ( 222 & l.01F 1 It ( 9.8 + 2.'6iF 1 1 ( 9.7 & 84.6)F .2 ( A) (.9.t . th7.0)E o ( a.8 - 16.7)E I (.l.6 = 2.2)E o ""TEh et ./ 20)e et ./ a)* *( a/ .)* g3 IN=65 ( 24) 6.7E+nt ( 2de a P.n)F o si ( 7.o i 9l3iF n ( l.9 A 9)F o g**") l t 0) (.2.5 7.9)E I ( l.9 34.01F -l et 2/ Poie et n/ ele et 4/ ele I zR.95 ( 2a) ..oE.or (. ;3 a i.5)F o i9 ( n.: 4 a .' 2 ) F .i (.8.s a it.9)F .a ( 0) (.l.9 . t,a)F (.3.t . 1.8)F 1 et n/ Poie et n/ ele et n/ 4)e py(*) en**** e NnN.ROHTiteF RFFFW4 70 THF Nisan d teF SFpakaTF ~F A SitwF-F 4 7 % THAN TF N flo) Tf=F9 TwF a v F u a r.s p a f m cpnist's, F Hw TMF PE1 Tim nF THF WFPOWT HICH
- F .a t nuFaTEP 7 es THF FRACTTom nF SaMDIF aNatVSFS Y TFi n1NG DF TE r f aMt.E "E a Sisne we nt s (T.F. 31SfGwa) IS INDICATFD ALTHIN *( 1a.
W1 & & M ' S M M W ' S M' ' S & l PILGolm I nFFATTF FevtWite.Mt.NTat RaniqinG1 Cat POs t f ribisG 41/d2/27 silmm a e f Flip TMF P E 8d I DD 12/11/70 . 12/11/en MEDIUMg SMFLIFIRM 8 'P.1 T S g PC1/mG *ET 9 RADIONilCLinES I Nn t e 3 trW si a T Iisw s >IGnEnf sfaTIDs C ON T w e at t f ar a fine.g i MEAN.uaHGE. ann =Faw eaNGF,a.n (NO. AN AL YSE S) NO41 N a t at aw.re anGF, arin (NON.RnuTINE)e LLD No.' DETFrTFnee Sfa. NO. OF TF C TFne e NH. nF TEC TEnee
; ............. ........ ................... .... ..................... ...................
j NO.95 ( 24) 3.*EeSt (.5(* & 7.71E 1 11 ( t.3 A 1.[l ) F n (.7.M g 22.3)F 2 ( 0) (.A.e . 1.A)E o (.t.e . 3.7 t er n (.5.5 3.9)F 1 et 1/ 2n)* et 1/ ele et of e). AG.ll0Mt 2a) 2.5E+02 ( sin a o 17 ( 9.5 A to.3)E o ( 2.n & e.3)E o 4 ( 01 f.l.1 . . 2 (.5.5 13.1)E e ' I ef 1/ 20)e et 0/ Ale e( 0/ ele RU=103 ( 24) 2.0E.32 ( tlc g 1.7)E D 11 ( 8.1 A 7.9)E D (.l.7 & 4.n)F =t ( n) (.5.4 . 31.a)E o (.t.e . 2.7)F o
*( 0/ Pole et 0/ ele et 0/ ele RU.106 ( 24) 2 (.2 g'e & In.11F o It ( 8.5 A 2.' 3 t E o (.6.e & 4.1)F 1
( n) (.l.1 . 1.2)E 2 (=1.5 2)E 6 ef 0/ 20)e of 0/ 4)e et 0/ ele q
!=l31 ( 2a) n.
( 3,9 A 1.e)E n 13 ( l.5 A 1.11E I ( . a! . tl & 262.61F 2
^@
Qr w ( 0) (.2.A = e.9)E I (.7.5 - 1.91F n sm y et n/ 20)e et of ele et of 4)e 1-m 3m CS=134 ( 24) 2.nE.02 f.t.9 A t.3)E o it ( 2.4 A 3.71E .5 (.8.7 A 5.71E . C7
,3 i ( 0) (.2.1
*( n/ 20)e 4)E 1 e( 0/ Ele
(.l.7 et 0/ ele 7)E o y f ' CS.137 ( 24) 2.0E.n2 ( 3.'a A st.11E .I 19 ( 3.2 A 41F o ( S.o & 3.21E =t ( 3) (.l.5 71E t i 1.4 . 5.81E O (.3.9 . In.h1F .I et 3/ Pole et 3/ 4). et o/ ele l BA.te0 ( 24) 8.0E=02 (.4E3 a 2.2)E n 24 f 1.6 A 3.'2 ) E D ( t.6 A 3.2)F n ( 0) (.3.3 1.2)E (.e.e . In.7)E n l *( 0/ 2 ole et 0/ 4)e et 0/ ele @ CE.141 ( 24) ( 2) 4.0E.02 ( 7.o a (.t.9 - 1.41E 5.2)E o t 13 ( l.1 A 7)E I ( l.1 & (.l.0 . 22.01F 51F o 1 et 2/ 20)e *( 0/ ele et 0/ e)e CE.14e ( 24) 2 (.l n a 43E t 24 ( t.o A 1.'8 ) E O ( l.0 & S.A)F 0 ( 01 f.5.1 a 4.3}E t (.l.l . 6.3)E n et 0/ 20)* e( 0/ ele et 0/ ele . e NON.R04sT!hE RFFFN8 70 THF NilMafe CF SFPaid 4 TE *E4 5tIRFHEN T S wMICH eFAF Gi= EATER THAN TEN (to) TIMES TMF avFua4F a4CKGentspn FOR THE PERInn nF Twg uEPowf
** THE FRACTION OF SAMPLF ANat.YSFS VTELnING DETECTAttiE MEAStsREMENTS (f.E. 33 SIGMA) IS int 3ftaTED MITHIN e( }e,
^
M M M M q, 1 I l l l PILGRIM ! nFFSITF FNVIRuh"ENYat #anInt nGIcel MONf fh4TNG Ml/42/27 SummakV FOR TMF Pregno 12/31/T9 . 12/3ttan mediums SnELLFISw UNITS: PCI/aC *ET { Ra0IONUCLIDES {NntCaTn4 STATIONS H{ GHE 97 Sfaffnw CuNidnt LOCATInks 1 (NO. aNALVSES) NOMINAL MFaN,nanGF.ahn wean,RANGF,arn ufaw,sahGF, ann {- (NON.ROUTIhE)* LLO hD.' nFTECTFDee STt. NO. DETECTEnee ha. DFTFCTEne* i I
, R4=226 ( 2e) .k ( 2(4& 2.n)t t 13 ( t.2 a 8)E 2 ( d.1 & t. elf t a I ( 0) (.e.e . 30.a)E t (.l.6 . T.5)E t Q 4( c/ 20)e et of ele et it 4)* o r-ca :s rn b
TH.228 ( 2e) 2.oE 02 ( Ida & 416 t 12 ( 2.6 a :,o)E I ( t.7 & t.81E n E .-. ( 2) (.2.s . an.n)E a ( g.2 Apo.oTE .I (.2.2 e.5)E a g ~m et 2/ 20)e et 1/ A)e et 0/ 41e m O[ ~ e NON. ROUTINE R[FFRS TO THE NHPDFW nF SFPaR&TE .Fashkf*ENTS melCM *FRE GwfaTER THaN TFh (30) flaES THE a VFH GF maCnGanuwe Fna THE PFWInn nF THE REPnpf , se THE FeacTinN nr SamptF aNaLv8Fs viELnthG DFTECTamLE MEaSURFmENTS (I.E. 33SIGua) IS ThDICATFn =TTv?N *( 1a. W&- y , f
I I III. G. Algae (Irish Moss) I Algae, referred to as Irish Moss or Chondrus Chrispus, is sampled I quarterly at three locations, the Station Discharge Canal, Manomet Point and Ellisville. The results of the ERMAP program for Algae are presented in Table III-G-1. It is clear from this table that there have been positive measurements of Co-60, Mn-54 and Cs-137 in the discharge canal. In addition there was one positive measurement of Co-60 at Manomet Point (Station 15 - 3 miles - SE) during the first quarter of 1980. There was also one positive measurement of Co-60 at the control station in Marshfield, ten miles away. This suggests the presence of a source other than PNPS in the case of the measurements beyond the discharge canal. In any event, the measured concentrations in the discharge canal are certainly due to liquid effluents from PNPS-1. I It is important to note that due to processing and market dilution, I the presence of these concentrations do not represent a significant potential source of dose to the general public. In fact, even direct human consumption of Algae (which to our knowledge, does not occur) would result in a dose rate of less than 0.01 mrem /yr to the total f body and 0.0t, mrem /yr to the most sensitive organ (Adult - GI-LLI, using the models presented in Regulatory Guide 1.109) and assuming consumption of 5 kg/ year of unprocessed material. 1
- I l
When compared with the natural background dose rate of 80-100 mrem /yr I there was clearly no significant environmental impact observed in lg l3 Algae as a result of the operation of PNPS-1. !1 lI l I 3-39 1 l ,I 1
S ' S) Y ' 1 l l PILGNIm ! DFF9tTF F>vikowwFutal maninLOGirst =0NTTowt%G 41/02/27, 9HMMARY fob TMF PFotnD 12/11/Te . 17/11/Pa j MEDIUMg VFGFTaTION . acuaTTC omffSt 8CI/uG *ET
) Ran!0NUCL!nES TNDICATHG STATIONS HIGMFMT STATION CONTD0s 80raftONS (NO. aNatVSES) NOMfhat NF a,N , R a NG F . a hn wean, RANGE,aNo "EaN,na=GF,amn 4
(NON.enuffNFlo LLn NH. OffFrTFD** 574 NO. OFTECTEnee NO. OFTFCTEDee j ............. ........ ................... .... ..................... ................... 1 i BE=7 ( 11) 2 ( 7(7a. 2.s1E t 27 ( 7.7 a afniF tI 16.51E ( T7g a.ntF 16.5)F t j ( 0) (.9.1 12.1)E t (.1.0 = (.3.0 t et it 9). et 3/ als et 3/ a)e N 40 ( 11) 5 ( 5(I a. 1)E 3 11 ( 5.2 A 4)F 1 ( 5.1 a 2)E 3 ( 0) ( 3.9 6.5)E 3 , ( 3.9 . 6.11F 3 ( 4.7 5.7)E 1 et 9/ 9). et 5/ 5)* et d# ele CR=51 ( 13) .I.O.100 f.t(2 a 1.7)E 1 27 ( 5.6 A 2 0.'81 E O ( 5.6 & 2n.8)F 6 1 ( 0) (.l.1 . 9)E 2 (.e 4 . 5.n)E 3 et et Ole e( 0/ ele e( 0/ ele c 2.6 i
^
i kN.se ( ti) 2.of.o2 ( i;6 a 5)E i it 5sF t ( a.5 a 2.2)r a n, -4 i ( 11 f.5.6 = 10.4)F o ( 8.5 19;5iE o (=5.1 . 93.7)E .I 22@j et 1/ ele et 3/ 5)e e( 0/ ele 2= ,5. r-o rn ca
- 1. CD.5. ( is) 2.aE..? ( 5;aa s.7)e a is t 7.e a 5;2if a (.i.i a i.93r . E; 2o -.
c) ( oi (.i.2 2.siE i (.6.. . 2..)r o pg[g:: et 0/ 9)e *( 0/ Ale et 0/ ele c: s r c2 i FE.59 ( i3 3.0E.0 ( 5; i . 6iE - is c 6.7 i s;eif 0 (.. 6 i 5.iir o D! J-( 0) (.i.a = s.,ir i (.i.9 . 63r i et o/ 9)e et 0/ 5)e et 0/ ele
. **l$h CD.60 2.6E.02 ( t,2 a . elf 2 11 f 2.0 a (siE 22 (.8.0 a on.6)F 8
($h ( 13) 1 ( 61 ( 9.1 . 127.01E o e 1.1 = 3.2)E (.l.7 1.21F 1 of 6/ 91* et 5/ 5)e e( t/ 41e Z~.65 ( is) . .o.10. . . , .5a ..,)E o ,, ,..a 5;i)F o ( s.. a 5.tiF o ( 03 (.. 5 2.93E i (.5. . is.5)r o et n/ 9)e et 0/ ele et 0/ ele (lll) ZA=95 ( 13) a.0E.02 (.3{t a 1.1)F 0 11 (.5.9 h 40;4iE .t (e3. a 7.2)F 0 ( 0) (.2.1 9)E (.1.P . 1.3)E I et op 9). og 0/ 5). et 0/ ele "g"["""$)
- P' a NON.ROUTINF RFFFRS TO THE NHumER OF REPaRaTF *FaMU4FMENTS *MTCM >FRF GeFaTER r--"
TMaN TEN (80) Tf"Es TMF avERaCF macuCROUND FOR TMF PERIOn OF THE dF80af ee THE FRACTION OF SaMPLF ANaLYSFS VTELDING DETECTaHLE ME ASueEMENTS (I.E. 33StGMa) TS INDICATFD *ITHIN a( )e, i
5 - U S & plLGuig I 0FFSITF F N v t Wn' *F N T r e k a t. g otnG ir s t *0ht fewir G M1/12/77 go.maev Fne THF preton 97/51/79 . 37/31#em MEDIuwt VE GE T & T 10's . aquatic uv iisi pr t /ali .FT Rah!ONUClinFS INntraTOR 9Taffnug wtGwtgi 57aflow rs hipos toraTInhi (NO. ANatYSE3) NodINat *EaN.AaNGF.aNO MEaN.GaHGE. abo *Een.cekGr.amn (NON.ROUTINF)e LLn 40
- OkTFrfFnee sfa. =0 OF TF CTf Dee A0 OFIFCTFree N5 95 ( til 1.0 100 ( 7.'a A 1.a)F e it (.5.7 A I M .' 21 F 1 (.6.H & 37.n)F 1
( 0) (.t.t . .a)E t (.8.4 = 7.3)F n et n/ 4)* et 0/ %)* a( ot 4)* AG.110M( 13) 0)
.t.o.100 ( if5 & 9)E t 11 ( 3.3 A 7)F 1 t.3.M & t.7)F t
( (.3.0 . 9.e)E t (.6.n . p.o)F et 0/ 9)e et 0/ Sie et 0/ ele RU.103 ( til 2.0E.02 ( 3[2 &. t.7)E O t% ( 5.6 A 2.91E n ( 5.5 g in.2)E 1 ( 0) ( 2.4 IG.A)F 0 (.2.M = 2.11F 4
*( 0/ 9)e e( 0/ 4)e et 0/ ale RU.106 ( 11) 2 (.4[4 & 1.4)E 1 27 ( 2.5 A .SiF 1 ( 2.5 & 8)F 1
( 01 (.t.3 .t)E 2 ( t.5 1.4)F 1 l et 0/ 9)e et o/ ele et o/ ele ,, 3d < n r-u3 !=t31 ( 13) n. (=2 g o A 1.A)F t 19 ( 3.8 A 20.A1E o (.3.n a 4.7)F o O $$ e ( 0) (.t.e . 9)F 2 (.t.1 . 1.21E 1 et d3 at 0/ 9)e et 0/ ele of o/ ele $* [[ C >* C8=134 ( 11) 2.0E.02 (.5f8 4 20.o)E 1 t% ( t.1 & 3.aiE n t 9.3 g aan.2)F 2 Eld 3 ( 0) (.9.a . to.1)E n (.6.h . 7.1)E n -- s, et 0/ 9)e e( O/ 4)e e( 0/ 4)e C8 137 ( 131 2.0E.07 ( 9g 7& e.9)E n it ( t.4 h ,M)E t { 5.4 g a.1)E o ( 0) ( t.n . es.1)E o ( t.e . es.3)E n (~3.9 . Imp.01F .I e( ?/ ele *( 2/ Sie *( t/ ele 84 1a0 ( 11) A.0E.02 ( . R .' A & IP.7)E O 27 (.5.3 A 2.3)E o (.5.3 A 2.3)F n "#ES ( 01 (.7,0 . 7.8)E (=9.5 o.0)F o
*( 0/ 9)e e( 0/ ele e( 0/ gie CE.tal ( til a,oF.n2 ( 4.5 A 31.4)f .t 1% ( 7.7 A 3.3)F o (.9.0 g nl.n)F 1
( 1) (.l.9 . t.%)t I (.t.9 . 1.n}F t et t/ 9)e e( 0/ 4)e et 0/ 41. CE.i.. ( 13) ., ( .,. i 1,.,1E o .. ( t.9 . i.,)F t (. .. i 1.3)F , ( 0) (.6.% . 4.4)E : (=3.4 = 1.4)F 1 e( p/ 9). et n/ 4)e et o/ sa l e ,wp** W e Now.RnuTINF wrFFR1 To twF hel**N S W tiF MFPakaTF M asseWF>FNT% .ptrn e r '4 F siGF e TFd P TwaN TFN (ID) T 1 ='F 9 THF a v F p a s;F HaCeGwnleNn Fed teF PF6 I8 0 f)F THE W Pv6T em THF FRacitow tir gn= ps t aNatVSFA v1FLnING Of TF r f ahl F MEARuwfMFNI9 (f.F. 31 SIGMA) 13 t t80f C4TFn alTH1h et le.
I E E E O E- E E E O E E S M E E E E E l l l PfLCRIM ! nFFSTTF F NvipisNME N T al pa nintnGIC a t MONTTnRTAG dt/02/27 Stim'e a R Y Fne ThF PERInD 12/31/T9 . 32/31/an MEDIUMI VEGET& TION 40UsufC t eN I T S : prItan -t? A ADION'4L IDE S INnICa Ina ATaTInNS HIGHE9T STAfino CnN T Hos 4nraTInus (NO. ANALYSES) NOMINAL MLkN,RANCE.'AND MEaN,RANGF,aNO MEaN,haNGF, ann (NON. ROUTINE)* LLn Nn." 3FTEPTFnee A f a .* NO. OFTECTEnee an. nFTFCTEnee
--e RA.226 ( 13) .I (toln A %.7)E t it ( 3.7 A .'8 ) E 2 ( l.2 & .*)F 2 7M i 0) (.6.2 46.2)E t ( 2.9 = 31.3)E t o r-w L
at n/ ele et 0/ 5)e et 0/ ele $A to TM.228 ( 13) 2.0E.02 ( 2(a A= .o)E 27 ( 5.s a 2. TIE I ( 5.A & 7.7)E 1 e ( 0) (.5.R Mo.2)E o (.t.6 . ft.51E I (.l.6 . II.51F t m 8 et 0/ 9)e et 2/ ele *( 2/ =)e OT
- l
, e NON.RnUTINE RFFF99 TO THE NHMRER nF SFPaWaTF MFa$tlRFMEta(S hMICH >FEF GREATER TMAN TEN (80) TIMFS THF avFRacF patacanuNn Fna THE PFRInn nF THE RFPORT
** THF FRaCTinN nF sam 8tF A N a t. V SF S YTELnTNG nFTFCia#LE MEASuRFMENTS (f.F. >1STGMa) TS TNOTCATED eTTMIN et le.
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w I
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I I III. H. Lobster (Arthropods) I Lobster samples are collected four times rer season at two locations, the vicinity of the discharge outfall rea and at a distant point off-shore. The results of the ERMAP / ogram for Lobsters are pre-sented in Table III-H-1. These results are unremarkable in that there I were no positive measurements of any isotopes other than K-40 in either the indicator or the control samples. Therefore, there is no evidence of any environmental impact on this media as a result of the operation of PNPS-1. I I I I I I I I I I I I 3.e 3
i W W W W M M W W M M M W W W W W W W m PILGRIM i nFFSITF Fhw gelmut NT ag Ran[nLOGiCal HnNTTDGl%G Ml/07/77 Summary FOR Tar progno 12/31/70 37/3t/Pn j o.E D I U* t aRTMROPOns 0%tTSg PCI /a G
- E t
! RACIONUCLinES thnitaine stafin%S HIGMFtf STafinw C n* T Het I s er a f ine, S (NO. ANALYSFS) komtNat .F a h. W A NGF .' a hn MEAN,eaNGF.ahn "E 4 h.s a *>GF , a mo (NON. ROUTINE 1e LLn 6.O] DF TFC TF0e e 574 Nn. nFTFCTEnee 60 DF3FCTE0**
BE.7 ( 6) 7 f.td9 1 79.1)E a 99 ( 7.5 A 1.2)E 2 ( l.a & t.4)E 2
; ( n) (.e.5 6 a)E t ( 6.2 = 25.5)F 1
*( 0/ ele et 0/ lie a( 4/ 2)*
K.ao ( 61 5 ( 2(3&. 7)F 3 11 ( 2.3 i .'7)E 3 ( l.* & 7)F 3 ( n) ( t.A 2.7)E 3 ( t.A . 2.7)E 3 ( l.7 - 2.11F 3 et at nye et at a)e et 2/ 21e CR=51 ( 61 3.7E*07 ( 4(I $. 1.
- i f 3 99 ( 4.7 h 13I25F t ( 9.5 & 32.1)F n
( n) (.t.4 ta.o)E I (.2.9 . a.7)F t et n/ nie et 0/ 13e et n/ 21e NN.54 ( 63 ( c) 2.0E.07 ((.4.4 f(2& . 3.71E to.7)F o o 99 ( 4.3 a 15.71E o ( e.1 & ( 4.3 2.01F A.3)E a o -a et or ele et o/ 11e et 0/ 21e > r a r-( l.7 1 @7 w C0=58 ( 61 7.0F.07 ( 3d9 &. 747.7)E =7 99 16.35E O (.o.M & A.9)F o e ( c) (.7.6 9.7)E o (.t.5 = 7)F l m -
$ *f 0/ 4)e et 0/ 1)* et of 21e My[
- o m e FE.59 ( 61 3.0F+01 ( 5(9 A= A.7)E o it ( 5.9 A A.2)E o (.2.3 & 7)F 1
( 0) (.l.6 7.s)E t (.s.9 . n,n)F 3 "% -4 .f. et of 41 et of sie et 0/ 21e ) Co.60 ( 61 2.0F.07 ( 9g ea 1.4)F o it ( 5.0 i 1.'a i E o (.2.5 & 5.5)F o i ( 0) ( 1.A = 7.8)E te (.7.0 . 3.n)E o et 0/ 4)e et 0/ ele et 0/ 21e zu. 5 ( 6) 6.vt.0i ( 2 ;., . .,)E i ii ( ,.. i .vif i f.2.. . .. m i ( e) ( 794.4)E .1 (.5.1,. 0.01F 1 et e.3,.
. .)e .( ., .). *( o 21e c::2 z.. 5 ( 61
( 0)
. 0E.., ( 6,
(.t.5
. 59..)E ..
1.1)E t ii ( 6.0 i 59;.sF .i (.i.i . (.l.M =
.alr 0.0)F i
1 W
., o, .)e .( o, .). .( ., 21e p
- -ll8::8 e eenN.ROU T ! h F RFFFRS TO THE hila #FR OF SFP4WaTF *FaSHRFhFNTS adICH mFRE GeFaTER Y-THAN TEN (10) TIMES TMF aVFpaGF RACetGEnuNn Fue TME PENinn nF THE REPnRT em THF FRACTTnes OF SamptF akaLYSFS VTElef wG nFTECTaRL E "E ASueFmFNTS 7 (I.E. 33 SIGMA) TS INDICATFn *ITHIN *( 1e.
E E O E pfLCRIM [ OF F MI T F F k v l uo%=t 4T al R a n f Hi na f r s t *nuf filWINC 41/s'7/77
- StlMM a R Y FOG TwF PFRInn 17/30/70 = 17/31/60 MEDIHus ARTMunPong teNITS pc l /a G *ET RA0!nNUClinfm TNntrainu 9faTIONS MIGHE97 staffnN co Twol eoraTinem (NO. ANat v4F m) NOMimal M E a,N, R a m 4E . a hn ,
-EAN,RaNGF, awn MFah, war 4F.AND (NON.ROUTINF)e (Ln Nn, nFTFrfanee Afa. No. OFTFCTEDee Nn. OFTFCTEDee Ns. 5 (
(
.)
c) 3..E.ni ( .;i4 s. air a o 9 ( 2.5 i i..if i ( i. i i..)r i (.t.7 = tt.n)E (=2.9 - 25.8)F s' et n/ a)e et n/ l)e et o/ 21e AE.110Mt 6) 7.5F+07 (.4;5 a 19.7)E o it (.4.5 A 19.7)F o (.9.5 A 2.5)F t ( 0) (=5.A . 3.11F 1 (.l.7 - 0.n)F 2 et 0/ ele et n/ ele of S4 21e RU.103 ( al 7.0E.o? (.lle A 3.0)E o 9e ( t.7 i tl55E I (=l.4 & t*.2)F 0 ( n) (.A.l . e.A)E o (.2.0 . 1.7)F t
*( op als et 0/ 1)* *( 0/ 21e Ru.in ( si . (..;. 4 i.s)E i ao ( 2.5 4 i;33r 2 ( .a 1.iir 2
( 01 f.t.2 4)E 7 ( 2.3 = 25.01F i _a et p/ 41e of 0/ 1)e *( 0/ 2)* ,, @@ n r-00
!=131 ( 6) n. ( 1;3 A in.7)F a 11 ( t.3 A 20J7ir n (.t.5 A .e)F t Q F1
( 0) (.3.A . 9.8)E i (.t.9 . 0.0)E 1 et ><
- 1. et 0/ ele et 0/ 4)e et 0/ 2)e gf7' us c e Ca.i3. (
( oi
.) 1.aF.or ( i;r a
(-i.3 3.,=>e
)E i a .. ( i.24 i.5iE i ( 3.i a a..)r o gti:
. (.5.2 u..)r 0 -- -
.( as e). .( os s). .( Gi 2,.
es.i37 ( .) 2.0E.ar ( 2;3 i s.siE O ii ( 2.s i 3;5sE a (.i.* * ..)E a ( ni (...: . is.i)E o (.2.2 a.n)E .
.( as .). .( os a)e .( os 2).
sA i.. ( .) A.0E.0, ( 3;5 . 1)E o ii ( 3.5 4 9.i)E o (.2.. . ..)F i **([$ ( 0) (.t.e . t. ele 1 0.8)F i et ./ .ie of o/ .)e (.3.7 (*# ) et 0/ 21e
;,,,
CE=141 ( 6) a.0E 07 ( 7;4 A 7.4)F 7 1% ( 2.5 i tiliE 1 ( 7.3 & 17.3)F G ( 0) (.9.. . .t)E 2 (.t.0 . 2.5)F 1 et n/ ale et 0/ lie et 0/ 21e CE tes ( 6) 2 ( 6g ng 31.6)E o 99 ( 3.7 1 7.5iE 1 ( 2.9 & .A)F l c::::) ( 0) (.l.2 = 3.0)E ( 2.1 . 3.7)F 1
*( 0/ 4)e *( 0/ l)e et 0/ 21e w*##*
.* NON.Rnt4 TINE RFFFRS in THF NiiwpFR OF SFPARaTF "FAS41RFMENTS mMICH hFRF GREATER
.P I
ThaN TFN (to) TimFA THE avFRaGF R4Cucer'UNn FnR THF PEhinn nF THE HFPnRT
*e THE FRactinN nF sa mpt F awatYSFS VIELnTNG DETEcTARLF MEASURE"ENTS (f.F. >3SfGMai TS INnfCATFn wf7HIN et le.
i M M M M M M W W W W W W m PILGHIH I OFFSTTF E *.v i nnN M E N T a l. RanInLnGTCat. HONITORfmG 8t/02/27 SUMMaWV FnD THF PERInn 12/3t/79 . 12/31/8n l MEDIUMS ARTHenPnnS IINTTSt PCI/aC *ET fla DIONUCL inE S INnicafpR ifaTInNs HIGHEAT StafinN CONTROL i fic a f inn S (NO. aNaLTSES) NnMINAL MFaN, RANGE, ann MEaNeRANGF,ahn *Fah, RANGE,aNO t (NON. ROUTINE)* LL p Nn.' nETFrTFnee S f a .' No. DFTECTEnse an. OFTFCTEnee
............. ........ ................... .... ..................... ................... -4 TH.228 ( 61 2.0E.07 ( a(5 A. e.e)E o 19 ( 2.7 i 2.'95E I (.T.9 & 39.n)F n A
nr l ( 4) (.5.4 et 4/ 4)e IT.n)E o (=e.3 2.7)E 1 gm
, et 0/ 11e et 0/ 2)e rt "*
A I ! m YC c e 1 ' to :r S .' I f a NON.ROOTINE RFFFR9 in THE N ti"R F R OF 9FPaRATF "F a SilRF"ENTS WHICH *EWF GREATER
THAN TFN (101 TIME 9 THF AVFpaGF RACetGRnyHn FOR THE PERInn nF THE RFPnRT i se THE FRaf. finn nF SaMPLF ANatVMFS YTEtnTNG OFTECTaMLE "EASifRF"ENTS (T.E. >3 SIGMA) TS INnTCATFD af7HIN et je, i
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I I III. I. Fish I Fish samples of Bottom Oriented (Group I) and Near Bottom (Group II) I species are collected quarterly in the vicinity of the discharge outfall. In addition, samples of Anadromous (Group III) and Coastal Migratory (Group IV) species are collected when in season, in this same area. Lastly, a sample from each group is collected once per year at a distant location offshore. I The results of the ERMAP program for fish are presented in Table III-I-1. There were no positive measurements of any isotope (other than naturally occuring K-40) at the indicator station (discharge canal - Station 11). Therefore, there is no evidence of any environ-I mental impact on this media as a result of the operation of PNPS-1. I l . I I I I I I I I 3-47 I
m W W M. W W M W M W W m PILGRip ! elf F ST TF F N W I RONdt ni al a n n i nt or. T C a t, howfinufh4 hl/np/77 SUMaaRY Fne TMF P F W I nli 12/31/T9 . 47/11/>n MEnltlMe FI9H UNITSg PCI/EG MET RanIONUCLInEm INnicainu MTaTIHNS MIGHE9T SfaTInw C a in T W.)I t ur a T 10., 4 (NO. ANALVSES) NnM]Nat ufaN.R4HGF.AND MEAN.RaHGF,4An "Eah.DANGF.&hn (NON.ROUffNFla LLn Nnl nETFrTFOee 974 Nn. DETFCTEDee NO. nFT(CTEnee SE.7 ( 3a1 7 ( t.l t.n1E 77 ( a.s 4 7. tie I ( 2.3 g t.7)F t ( 01 (.9.3 9.9)E t (.a.6 . M.n)F t et c/ 25)e et 0/ I)* et 0/ 9)e K a0 ( 3a1 5 ( 3(6 A. .t)E 1 21 ( 3.7 a .'7 5 F 3 ( 3.5 g 31F 3
- ( 01 ( 7.9 a.6)E 3 ( 3.4 . 1.9)E 3 ( 3.n = 3.9)E 3 et 75/ 75)e et 2/ 7)e et 9/ ele C9=51 ( 3a) 3.2Ee02 ( 1(1 a 19.a)E O 99 ( 7.6 1 2 7.' t ) E o ( 2.6 & la?.7)F 1
( c) (.P.3 7.5)E 7 (.7.1 . 8.A)E t et 0/ 25)e *( 0/ ele et 0/ 9)e MN.5e ( 3a1 7.nE=o7 ( 1(aA 15.n)E .3 31 ( t.e a 'ig.nir .3 (.a.o & P.7)F n ( 4) (.l.3 1.9)F t (.l.6 . 71E 1 rn -4
! et A/ 75)e et 0/ 75)e et 0/ 9)e 22 S r$$
ca CO.58 ( 3a) 2.0E.n? ( 2(5 &. 15.7)E 1 27 ( 7.a i 9.7iE o ( l.7 & l.8)F 0 n s ( 0) (=2.1 l.61E I (mees = 7.4)E o -* 30 ><
$$ et 4/ 25)* et 0/ 1)e et 0/ 9)e $$[2[[
C: 8 FE.59 ( 34) 3.0Eeot i 2.1 & 10.5)F 1 , . , [lT* LA 99 ( t.3 a 3)E 1 ( a.6 & 9.9)F n >d I ( 0) ( . 2 .' a . 7.m)E I (.3.0 7.2)E t et n/ 25)e *( n/ 6)e et n/ ele CD.64 ( 34) ( 0) 2.0F 07 ((.l.A t(3A. 17.8)E 1.6)E 1 I 99 ( 5.7 A 5.3sf G ( 2.3 & (=7.2 3.A)F 28.1)E q n et 0/ 251 e( 0/ 6)e et 0/ 9)e l IN=65 ( 34) 6.7Eent ( 2(7g a1.5)E . 77 ( t.7 1 2.'oiE i (.3.7 & 6.31F n
- ( n) (.e.0 . 4.7)F t ( 3.2 7.8)F 1 et 0/ 25)e of 0/ 13e e( O/ 9)e IR=95 ( 3a) a.0E=07 ( 3.7 a 1.1)E o 27 ( 1.5 i 1.'9 ) E t 3 1.8 & 69 a)E 1 C
( 0) ( = 4 .' 5 = 2.9)E t (=2.1 . 3.5)F 1([ph et ut 25)e e( 0/ l)e et 0/ 9)e agg)
, C e NnN. ROUT!hr RFFFRS fn THF Numarp nF SEP AR&TE *F astsRE*ENTS wH{CH nFNF GREAT [R
#- 88)
THAN TFN (101 TTMFS THE avrPaGF RACwCRollNn FnR THE PENInn nF THE RFPORT ,,,,.
** THE FRACTinN nF SAMPLF abaLYSFm YtELnTNG DETFCT4 HIE MEASUREMENTS (f.E. >3 SIGMA) IS IN0fCATF0 h! THIN *( 1e.
r
E O E E O E E O E E E E E N E E E PitGp!M i nFFSTTF FeeviknopfHTat paplot pr.iC at a0MT104THA et/42/27 MHMMapy Fhe THF PENInn 12/31/79 . 12/11/*n MED!tiMs FISH HNITS: *tI/=G 'ET-RADIONHCLIDFS Thniraind AfaffnNA MTGMFAT S t a T I O's Ci h T W41 tora *THNS (NO. ANALyMF9) NOMINat MFAN,paNGFeahn
- MEAN,RANGFeakn MEaN.WabGF,a40
( NON.R0tJ T I N F )
- LLO NO2 0FTFCTFHe e STA. NO. nFTFCTEne,e NO. DFTFCTEnee N8 95 ( 3a) 3.9 Feet (.2(na 1. ale o 21 ( 3.5 a 320if o ( 3.9 & 29.91E .I
( n) (.l.5 1.a)E I (.l.6 . 1.31E I
*( 0/ 25)e et 0/ 2)e et 0/ 9)*
AGell0M( 3a) 2.5Fe02 (.a(9 a 13.4)E o 21 ( 9.2 A 2.pif 1 ( l.0 1 2.n)F t ( 0) ( l.a = l.3)E 2 (.T.3 ll.7)F t et n/ 25)* et o/ 23e et n/ 93 RU=103 ( 3a) 2.0E 02 ( 2(24 2.n)F o 11 ( 2.2 a 2.cif* o (.a.a a 3.5)F o ( 0) (.2.6 , 2.a)E 1 (.l.6 . 1.5)F 1
*( 0/ 25)e et 0/ 25)* et 0/ 9)*
RU.106 ( 3a3 2 (.l(2& t.6)E l 23 ( t.5 1 2.'a i r I (.3.5 g 3.1)F 1 ( 0) (.l.5 = 2.a)E 2 (.2.5 t.n)F 2 _4 et 0/ 25)* *( 0/ Ele et 0/ 9le -~>= n 03
. . . O r"
!=l31 ( 3a) c. (.3,a g a.1)f n 27 f.3.2 a 19.6)F 0 (.2.3 A 9)F l 3 P1 I' ( c) (.3,6 . a.5)E I (.8.6 . 6)E [[ ,,
j; et n/ 25)e et n/ lie et 0/ 9)e g ;; m a C8=l34 ( 3a) 2.0F.02 (.5d6 & l.1)E n 27 f l.A A 9.51E o (.7.1 & 2.61F n cL -* ( 0) (.l.a . .a)E I (.2.3 8)E 1 dL
*( 0/ 25)e of D/ 1)e et 0/ 9)*
C8-137 ( 3a) 2.or.02 ( Ad2 4 2.11t 0 99 ( 1. 6 A d5)F 1 ( l.l & .a)F l ( 0) !atee- e.A)E I ( 5.5 33.a)E o ( 2.1 . 3.3lt l at 0/ 25)e et 1/ 6)e et 2/ 9). 84 140 ( 3a) ( 0) A.0E.02 f.l(5& (.a.7 3.4)E 2.9)E O I 11 (=1.5 i 3.5)E o t.6.6 g (.2.3 a.7)F 1.a)F n,,qa) 1 et of 25). .( of 2gje et c/ 93 ([[[I l CE.ias ( 3a) 2 (.i;i . ..)E i ii (.i., , ;6ir i (.2.2 i ..i>F i t c:::) l ( c) (.A.8 . 3.A)E I (ae.0 . 1.7)F ! et 0/ 2%)e o( 4/ 29)e e( 9/ 9te RA.226 ( 3a) ( n)
.I f.9(7 1.
(.2.3 22.4)F 2.9)E o 2 27 ( 2.9 A 2.' M ) F 2 ( 2.7 & (.3.5 7P.71F 7.9)F o 2 ([[) et n/ 2%). et n/ 1)e et n/ 9)e a wo%.hHHTINF PFFFP9 Til TMF NurkFp siF SF P aw a'* .f a FtfkFFFHIh kHICM .FPF GGEaTF8 g TwaH TF N (to) TT.F9 TPF aVFwacF maCunsnutn Flip twF PFWI8r' nF THF 8FPHkT
** TMF F R AC TlalN OF 84Mos t ANatYSFs ytFinTNG nFTFriablF FFASHWFdFHIS (f.F. >131GMA) T9 ThotC4TFn .ITHIN *( 1e.
M M M M M M M M M M M M M M M M M M PILGRIM I OFFSif" FNVIRnNMENTal pantntnGICAL "!!NTTOpfNG 41/02/27 SUMMANY FON TMF PFRIOD 12/11/T9 . 12/11/P4 MEDIUMS FISH amITS: Oct/mG =F.T RADIONUCLinES TNofcaT04 STaftnNS HIGHFat STATinN CON T Wiel 16taTInh5 (NO. ANALYSF8) NOMTNAL NEAN, RANGE. ann MEAN,paNGFeakn MFAN,eANGE,aND (NON.ROUTINEle LLO NO.' nFTFr TFne e STA. Nil. PFTFCTEDee NO. DFTFCTEhes q
............. ........ ................... .... ..................... ................... _g
. n r-TM-22e ( 3a) 6.n)f om 2.nE.n2 ( aoa g n 21 ( 2.1 A .n1E i ( 5.9 & T.u1E o y ( 0) (.5.4 . 9.6)E (.a.: .
2.9)F l 5-m et 0/ 25)e e( 0/ 2)e *( 4/ 9)e -* M O 5Y m-O. I vW e NON= ROUTINE RFFFRS TO THE NH"PFR OF SFPARATF "EASURFMENTS mMICH >FAF GefaTER TH&N TEN (10) TTWFS THF AVFRACF RACMCanuNn Faiw THE PERInn nF THE WFPnpf
** THF FRacTinN OF saMPLF ANaLYSF S VTELnTNG DFTFCTARLE MEasueFMENis (f.E. >3STGMA) TS IN0TeaTEn wfTHIN *( je.
#/
69 Y
I III. J. Sediments Sediment samples are taken semi-annually at five indicator stations including Rocky Point, Plymouth Harbor, Duxbury Bay, Plymouth Beach and Manomet Point and a control sample is taken from Marshfield. There is a detailed subdivision of individual sample cores in which samples are sectioned into 2 cm increments (this applies to all loca-I tions except Plymouth Beach). The surface and alternate sections are analyzed for gamma emitting isotopes. In addition, the surface section from each core and a mid-depth section from Rocky Point and Plymouth Harbor are analyzed for Pu-238 and Pu-239, 240. The results of the ERMAP program for sediments are presented in Table III-J-1. It is clear from this table that Co-60 was observed in sediment samples taken from Rocky Point (Station 11) whi:h is near the discharge canal outfall. These samples were collected on 6/9/80. Subsequent samples collected from the same location on 10/22/80 showed no evidence of any isotopes characteristic of reactor operation. Therefore, the observations of Co-60 are most probably a transient effect. The only other noteworthy values are the measured concen-trations of Cs-137 and Ce-144 in Duxbury Bay samples. This may be I explained by the fact that the sediment samples taken at Duxbury have a ailty character not common to the other samples. It may be that the nature of the Duxbury sediment is such that certain materials are re-tained more strongly than others. This theory is supported by the fact that the Duxbury indicator station also had the highest mean concentration of K-40, an isotope which is chemically similar to l Cs-137. Analyses for plutonium isotopes in sediment samples were performed by the LFE Environmental Analyses Laboratories in Richmond, California. The results of these anlayses are presented in Table III-J-2. There I is no apparent trend in these data to indicate that the PNPS-1 is contributing measurably to levels of Pu-238 or Pu-239, 240 in the environment since levels of Plutonium at Rocky Point are among the l lowest measured at any location. l 3-51 l
W W W W W W W W M M M W M M M DILCRIM I OFF5tTF FhwfuttektHTat wantrLontral mauffnwt%G 68/np/py. SurMARY FHb THF PFRIOn 92/4t/T9 . 17/11/pn N[O [ljM g SFnIDFNT/S]LT HNITS: PC 1/a n r*V RaDIONOCL IDF S TNDiraTHE RT4IIONS HIGMF9T STaffnN CHNTwns IsTaT10mm (NO. ANat VMF S) N0=INal MFAN,WaNCF. ann " fan,WANGF.atn MEah,WaNGFes%P (N04.a00 TINT}e LLp No,' nFTFrTFnae S f a .' No, nFTFCTEnee NO. OFTFCTEnse SE=7 ( en) 7 ( 72A A 2.elt i 11 ( l.2 A t .sq F 2 ( 7.a & t.7)E I ( 31 (.l.9 . 9.7)E 7 f.t.9 . 9.2)E 7 ( l.4 = 0 9)F l et 3/ aale et 2/ Inle et 4/ e). N=40
~
( 4A1 5 t 1.0 A 616 e 11 ( t.4 A .l)E 4 (10.o & 7)F 3 ( 01 ( 7.8 . th.n)E 3 ( 9.1 16.6)E 3 ( 9.3 In.s)E 3 et as/ sale et tot inle et s/ a). CR-li ( .a) s.,Fe 2 ( 9;5 i i6. iE a is ( 9.5 i 2.nvE i ( 2.. t i. ir i ( ol (.3.2 , 7.71E 7 (.9.4 . 5.5)F l e( n/ es)e e( of tale et 0/ ale MN.54 ( 4A) 2.0E=o2 ((.t.2 ift A l.236 o It ( 6.7 a 2.01E o (=5.0 a es.5)F .: ( 0) l.9)E I ( i.2 7)F t rn -1 et 0/ 44)e a( o/ I0le e( 0/ ele U! b us S r$ Co.54 ( aa) 2.0E=02 f.5;e a 1.11t o 15 f.3.1 a 2.11E D (.M.4 & t.7)F o ES I# ( c) (.3.1 . 1.1)E : (.t.3 - 1.0)E g* fj l[ (n et 0/ aa?e h) et n/ tale et n/ ele rn v> =*
- c: e PE=59 ( an) 5.oEe01
(.3,6 a e.n)E O ll ( f.3 & 7)E 1 ( 7.2 & %.3)F o
--4 r- G Lo -4 e
( 0) (.6.9 . e.4)E "" (.e.6 . IA.5)E d et o/ as)e et o/ tale et 0/ e). CD.60 ( 48) 2.oE.o? ( 5;7 & 2.6)E O 11 ( l.6 A 291E I (=9.9 & #7.01F 1 ( 2) (=2.1 -
*( 2/ aale 9.8)E 1 ( m.1 =
et 2/ lo)e 90.01E o (.l.2 et 0/ d). 9)E i ,([gagI ! zN. 5 ( .ai ...Eeoi (.3;a a i.73E o 2 ( 2.3 .; pie o ( 2.3 ..aie . ( 0) (.5.6 . 4.1)k 1 (.6.0 = 12.n)F o et 0/ 44)e a( 0/ 4)e et 0/ a)e IR=95 ( en) s.cf.02 ( 7;5 a 2.5)t o 31 ( .6 a 27)E I ( t.5 & .P)E I omm** ( .) (-2.5 . 5)E i 35.ile o
*( 0/ 44)e e( 3/ leje f.2.5 e( 4/ 4)e ggr >
,,,a P*"
r" e NON. ROUTINE RFFFRS Tai TME NUMAFA DF MFPaRaTF HFasudFMENTs =HICH eFGE GNEaTER THaN TEN (30) TIMES THE avrpanF matuGROUND Fne THE pgRton OF THE REPORT
** THE FRarTION OF SAMPLE ANALYSFS YTELn!NG nF TECTanL E "EaSHREMENTS (f.E. >3SIGua) TS INnicaTFD MITHIH *( 3e.
I TABLE III-J-1 1 l (continued) 3 " pBBR B I e5 F O 0 9
=4 ==== 3C C .= C == 3 == ee .e = == C ** NN
;
l I CC e 0 h ,b. WE 4 las W tan b in w b, bb em ;= a 3 en m ,= ,= em a= , lad
= ,b=, Ins
= ,=e= m ,= e ,k= e= an , Ins
=e taa
*=
- C 4 eC e e eC o e e2 44 4& M .=
o e
#8' W e e fe O Ce er 1 4 ew 0 e e e e e e e e e e o e i uh> 0 e == C OC >N 4 == m N C E Oeu8 m ,a= == a ,e= ,e= ,e= ,a= e .e= As ,e ,e=
n= .E 8 .e= e s= = 2 e s= 0 e -0 e e e e e e e e I > e G
'J e
se L. O =0 22 J h 9 w e e 0 2wO 8 OI 2 3 u 0 e e de m s8" C ee e e tw 40
=8*
#e e e e 3 0 9 **
49 e&C e o
== a 9 me 40
>==O e e
== is 0 0 *=
48 eeO o e e its 0 9 ** 40 foO e o e == 9 0 ** de E .= m e o
*===
==
48
>eO e e N to 0 9 *e 48 NeO e e to m 0 0 ==
de CCe e e e ip me a wwe w me e I
% n 0 en aw e so me e me me e =* w e me se e w on e sa w e m= =e e san M == e 3 W lad > % > 22 .= == a .= .- C = N ** = = . = == e= 848 m As OC
- 2 e 8 eL 8 W4 I O W 6 ',a. b Ind laJ is led taJ InJ thf las taa 2W e- C C e. 0 *= e e .e -*= e ==== *= e.*= -e .o= w I d%
a-C *= 4 e B w=s e. C We 0
'ee e
.=
o N e -ee
== m
*e
'e e
e *seeeN
== m e
>M
*ee mN
*== e' 4e E taJ 1>>
K&
** m s= w > e e e e e e e == a e ,a= C.=e u 2 2 % eoue == a == *= *= e a a a= e= 16 In.
o o I
- A i is e e e e C O O O e= == e= 4 > e o. . em . w - ee == IE C 2, la e=
- 2 16 e . 40 4 40 40 40 40 . et e 46 . 48 0 48 0 Ca z w C 0 % % % % % % % % % % ec3 0 0 I2 6 m O e C 4 0 4 O M O 4 C O C m 786 m As == 0 > a= m 7 oe e 0 e e e e e e eos80 e.O. e e e e e se 2me so w C 0 ee as s** == to e >N as N == a= 4 laa las ma
_e ZZ Z 9 %e me w me == 6 *e se 9 ** 0 == te & e5 K I <a > e e =* e e e e se em e e e 0 me se =* se to me to ew e e==* is u% 8 E W taJ
*=== 0 Iw e* e; e= z O% *e4 e e .% e 6 wE>
0- > 0 e W af s* s** N s8* s8* 1 Cu t.r. .e. I e= e3 0 N e. = == == == .= g6 m o C te. >e e > c, w a= 2 42C C E
.= C eCo as *= e* S c .= cN c, == cN NN c == == O == N cN sts as a2 2 e= S T S 46 @ o=
I 2E
=E y
im
- I 2 >
OCe 9
== 2 e 8 e= e C 0 e e 16 0
> b s=
e" @ b e == sr rW G 9 laJ e 9 en em sa C e e e and aa a= s= W> o e G ==
== e bw e===
tr N e e
== N e
laJ laJ ei= a= 8 % 88* e e C *= e tal laa c= an
.= e e o
.= to f% e laJ 1aa em a=
.= c e o
*===
e w tad e= a= rC e e N se e
' a saa d
an e s86 E NN e e 5 las and a= a= f= 986 eN e o e tad nad s= a= 4> e e E
== e e"
- C ==
u .A e 16 as lae C E e= 2 2b b @ e3 >
> em 3
I 3 Q 3 e> 6 mm . e= a= s= em a= e= en a= *= am E e w em 2' O O 2 las 9 e e e e e e e e e e I 2E E eb & e= =C 0 e 40 e e e at e e e e O lad > e2 e g6 0 46 0 40 0 40 0 40 4 40 0 40 40 8 40 0 il 0 ZDJC m 3= o as
- e 0 % % % % % % % % % % e e te.
*2 es 6C 0 eetC s == 3o eeo *ecO 4eO e == O >>> d s8* c emm > C en w 2>
e= <a f,. I 2 9 *ee *ee
- e= e ee *ae ee
- e' e == *ee *ee *e e s86 I laJ as at e* I 2 8 4 == @ == == As ==== As e e es N> c to e == > Re >I u th 3 e- 0 0 == 0 == 9 9e 0 te 0 %e 0 0 ** 8 me S 9 == 8 8 ** ew > b *=
sO e ==e- e me no e me w a =s== a ===s e ==*w e == w e *we == tw e se w e O .= c
- c*
I *
> s' S 2 4 1 e=
e5 I as R em el el 9 == 8% N N f% 8% b> *= I J 0 O O O O C C 4 Ib
>1 0 em 2 > ef == 2 > tas u m I
T es, a= S 2 > an 4% d 1 et em s= 9 C &
.,a == eaa E ta, 9 s= s= a= s= a=** a=** a=** s= e= a= en * * *
- a= a= ***= 22h e a= C C e? 2 9 eO EC et C EC et O EO EO CO E s9 SO 8 as taa
& w *= > ** 9 e e e W e e e e e W Z Z tas e et a .J > e C > I e=
u en 3 0 mm tw me me se w me me ww me == es w w me te em me em 2 > %e 22CC I
** K I 2eE 9 O M e se > O # 4 3 0 0 0 ep ** O O == m e e fts e es em e2 0 e se se se M == m.
. e= se As e e C CCC 8 0 a e e ao e a S S S ene as 2 2 9 m ta 3 On A ED at e taf *E E E w *= 0 2 as E E pe U U S U E I
g 3-s3 I
m m M M e m m m e m e m W W W PILGRIM 1 0FFSTTF FNVIRtlNMENTAL RantnLnGICAL MONITnRTNG Al/02/27
SUMMARY
FOR THF PERInD 12/31/19 12/31/80 MEDIUMI SEnIMENT/STLT u=ITS: PCI/mG DRV RADIONUCLIDES INDICATOR sf ailstNS HIGHEST STAT!nN CnNTROI LnCATIn%S (NO. ANALYSES) NnMJNaL MF aN,N ANGF .sNn MEANsRANGFeahn MEAN.RaNGF,aNO (NON.ROUTINEIe LLO Nn.' DE TEr TFile e S T A .' Nn. DETECTEne,e NO. DFTFCTEDee
^>
IM.228 ( 48) ( On 2.of.07 ( 3[6 & ( t.2 71E 7 6.9)E 2 13 ( 5.0 & ( 3.0 g aiF 6.9)E 2 2 ( 5.0 & ( 2.1 .
.a1E
, 3.8)F 2
2 gp s p1 Y U1
*( 44/ 441e et 10/ 10)e et 4/ ele r+
4 o- m. c e- e LL
.L e NnN.Rnl8 TINE RFFFR9 Til TMF NilMRFR OF SFPARATF MFaslanFMENTS hMICH >FRF GRFATER THAN TEN (10) TIMFS THE AVFRaGF paCwGenUND FnR THE PERInn nF THE REPORT ee THE FRACTION nr SAMRLF awa (i.E. >>SiGM., 18 iN01 CAT,LYSFS YTELnTNG DFTECTARLE MEasuRFMENTS 0 >TNiN of ie.
p h& Nt v@f f
I I I TABLE III-J-2 RESULTS OF SEDIMENT ANALYSES FOR PLUT0NIUM 1 l I Results I pCi/Kg (/,cy) 1 % Error (Ir ) (a) Location Depth (cm) 238 p 239,240p Duxbury 0-2 1.15 1 21% 42.9 3% Duxbury 16-18 0.27 1 32% 9.82 5% Plymouth Harbor 0-2 0.22 54% 7.72 1 5% Rocky Point 0-2 0 1 0.07 3.35 10% Rocky Point 16-18 0 t 0.12 2.32 1 11%. Manomet Point 0-2 0.09 1 80% 2.16 1 10% I (a) If the result is zero, the error is in pCi/Kg. (b) Sample analyses for control station in Marshfield and mid-depth sample at Plymouth Harbor not available as of this date. I , I I I I I I I 3-55 I
I III-K Milk I Milk samples were collected at three locations, Plimouth Plantation (station 15-2.2 mi-W), Plymouth County Farm (Station 11-3.5 mi-W) and the King Residence (Station 22-12 mi-W) during 1980. The Plimouth Plantation is a substitute indicator station added to replace the Whitman Farm in 1979. The 1980 milk animal and garden census (see Appendix E) confirmed this location as the nearest location of a milk producing animal within 5 miles. As stated in Section I of this report, milk samples were not always available in sufficient quantity for analyses from this location, how-ever, every reasonable effort was made to collect samples from this location whenever they were available. I When available, samples were collected semi-monthly when animals are on pas-ture and monthly at other times. The results of the ERMAP program for the milk media are presented in Table III-K-1. The results of analyses for Cs-137, and Sr-90 are presented graph-I ically in Figures III-K-1 and III-K-2 respectively. There were positive measurements of these isotopes at the indicator and control stations. In the case of Sr-90, I-131 and Cs-137, the highest mean values of concent'ra-1 tion occurred at the Plimouth Plantation. Station releases for this period l exhibited a Sr-89/Sr-90 ratio of greater than 100/1 and therefore it is un-likely that the PNPS-1 is the major source of the indicator station activity since the measured Sr-89/Sr-90 ratio was at most 1/2. In addition, the measured average concentration of both Cs-137 and Sr-90 were l g E respectively 10,000 and 1,000,000 times in excess of the concentrations ex-pected to be present based on measured releases from PNPS-1 and the conserva-tive dose estimation methodology described in Regulatory Guide 1.109 and l 1.111. In other words, PNPS-1 probably contributed much less than 0.01% of ( the measured concentrations of Sr-90 and Cs-137 in milk at the Plimouth Plan-tation. The remainder of the measured cesium and strontium radioactivity is unquestionably due to atmospheric fallout resulting from atmospheric weapons j testing. 3-56
I I In the case of I-131 the only two positive measurements at the Plimouth Plan-tation occurred during October and November (0.52 and 1.7 pCi/ liter respec-tively). I There was a Chinese atmospheric weapons test which occurred on 10/17/80 which undoubtly contributed most or all of the measured I-131 activity at this loca-I tion. However, even if a person were to consume milk with the highest mean concen-tration of I-131 for a full year they would receive less than 1 mrem / year to the most restrictive organ (infant thyroid). When compared with the natural background dose rate of 80 to 100 c_a/ year, I there was clearly no significant environmental impact on the milk media as a result of operation of PNPS-1. I I I l I . I I 3-57
E E E E E E E E E E E E E E PILGRIM I lie F 511F Fwvisis =E bf at k a n g ret nGit a t MONITDwikG altop/77 StiMM a b V Fire TM F PtGinn 12/39/79 = 17/11#66 M E D IllM t Mllh Is g b g PCI /L I TF ot
- RAD 10NUCLInF5 ThntC4 TOP SiafinaS MIGwfit stafinN Ca h T h ut i str aTID* S (NO. aNat vsES) NOMINat mFaN,paNGF,aan *Fam,WaNGF,akn " fan ewa%LfeaND (NON. ROUTINE)* LLn hn.' nETFCTFnes 374.' Nn. nFTFCTfnee men nF TFCTEnee 88=89 ( 1m) 4 ( tde A- 4.6)F .I 27 ( e.9 A 3d21F .I ( e.1 & t 01F .I
( 0) (=2.1 3.9)E o (=4.7 . 17.6)E .I (.l.4 = 7.7)F o et 2/ 13)e e( 1/ Ale et 2/ 75)e 84 90 ( 34) .A ( Ide A 7)I 1 19 ( t.6 A 2)F t ( 2.7 & 3)F 0 ( 11 ( 7.7 la.o)E o ( 7.7 3a.o)E o ( l.2 9.3)E o et 13/ 131e et 13/ 131e et 25/ 751e OE.7 ( 38) A.0E*01 ( .1,'6 & 1.1)k o 22 (.t.5 & 22.5)E -l (.l.a & t.3)F o ( on ( 9.o . a.11F o (.l.5 7)g i et c/ 13)e et 0/ mie et 4/ 7%)e N.40 ( 34) 7.nF+o? i 1[4 A 01E 1 77 ( t.a A dt)E 3 ( l.4 & .o)F 3 ( 4) ( 8.5 - 1%.7)E 7 ( t.2 l.7)F 3 ( l.2 l.71F 1 mH of 13/ 13)e et 8/ 4)e et 25/ 75)e E@ CR=5l ( 14) .t.o.100 ( 1(6A. 7.a)E o 27 ( e.7 A 3.lif a ( 9.6 & IA.7)F .I s ( c) (.7.6 7%.7)E o (.2.7 2.0)E t .=-* :u .-* g et n/ 13)e et 0/ Als et o/ 251e Q cC Z. MN.34 ( 14) 8[ ( 4(.g 3.9)E 1 77 ( 5.5 1 3J5iE .t ( 2.n g s.8)F .: [f ( c) (.l.7 7.A)E o (-2.e . P.8)F o ut *-* et n/ 13). e( 0/ Ale et 0/ 75)e CO 58 ( 34) 4 .' (.3le A 7.9)F .I 21 ( 3.4 & 2.2)E -l ( l.2 & t.9)F .I ( 0) (.l.7 - et o/ 13)e i.vir n et U/ 17)e (.2.= si c/ 75)e
- s. air o@
- n.59 ( 3.) . 0E.o. ( . ;, , ..)F .. t, ( .., A ...iE .. ( t.7 A ...)F .. p i
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( n) (.3.e . 7.7)E a (.4.7 7.3)F n et o/ 131e *( 0/ 13)e et n/ 2%)e Im=95 ( 14) 1.ntent (.6l7 a 4.n1E . 71 (.2.6 A 3.9)F *t (.4.7 & 3.1)F 1 ( n) (.4.3 7.7)E o ( 3.7 . 3.0)F o j e( et 83)e et 0/ t?)e et 0/ 75)e 8d t.95 ( 18) .l.0 100 ( .7,'n A 7.9)E .I 21 ( 2.9 a 2.3)F 1 ( l.a & 7.51F 1 ( 0) (.l.a - 7 a)E o ( l.7 . 4.5)F a of 0/ 13)e et 0/ t?)* el 0/ 25)* AG=lleMt 34) .t.n.100 f7(A a. 7. a. ) F o 27 ( 6.8 A 3.11F o (.l.a & P.n)F o ( n) (.l.w t 9)E I (.l.A = ?.7)F 1 et 4/ 13). *( n/ A)e et 0/ 75)e 2
^ to RU=lel ( 3m) A .' (.t{t a a 27 (.l.0 a 3.etr .I (.e.7 & 7.7)F .I OE y ( 0) (.2.6 . .5
. )E . (.2.i - i .n f .. g sn e( 0/ 13)e et op n)e et at 75)e .
m s-RU.106 ( 34) A.0E*01 (=3EA A 7.7)E o 28 ( 3.8 a I .'5 ) E 9 ( l.1 & l. elf n 5k ( 01 (.2.2 = .n)F t (.l.e - 3.3)E I 8 ,' , et 0/ Ille *( 8/ 171* *( es / Ps). I 1 r.ni ( ia) 5 ( i; . i .u E .i is ( i... i,nF .i ( 3.3 i.9)F . ( 2) (=4.s . )72.4)E 2 f.4.4 = 872.0%E .2 (.7.6 . 3n.7)F a( 2/ 13)e *( 2/ 13)e et et 75)* g
* ~
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FlGURE I!I-K-1 CONCENTRAT10NS OF Cs-137 TN MILK ALL STATIONS I I :"
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FIGURE Ill-K-2 CONCENTRATI0 tis 0F Sr-90 IN MILK I ALL STATIONS i I II
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f u u ~ 4 o suin/m I 3-62 . I
I III. L. Cranberries Cranberries are collected from three locations, the Manoment Point Bog I (2.6 mi - SE - location 13), the Bartlett Road Bog (2.8 mi - SSE/S - location 14) and the Pine Street Bog (17 mi - kW - location 23) at the time of harvest. The results of the ERMAP program for this media I are presented in Table III-L-1. The only man-made radionuclide detected in any sample was Cs-137 which appeared in a?1 samples collected. A comprehensi re study of cesium uptake in cranberries was performed during 1978. The results of this study are published in the 1978 Environmental Radiation Monitoring Program Report No. 11. The results of this study and the fact that no other reactor related isotopes were measured above LLD in cranberry samples makes it ex-tremely unlikely that there was any environmental impact on cran-berries due to operation of PNPS-1. I I I I I I 3-63
l b & M M M M pfLCRIM f 8- flF F SI T F FwviEstN=FHTal WangntnGtcal =0Nff.1dfMG *t/82/77 Selwwahy Fne THF 8 F W i ns) 12/)t/T9 . 12/3tten MEOluMt Fonn CWakHFwatFS omitst et I / a t. .t f RADIONOClinFs t=nicafele ,TaTIOkS HIGMF MT Staffnw c al= T wiis t eic a fit NS MFa,N,R4HCF. ann MF44,eaNGF,46n 9E a me,D a NGF . A ND (NO. ANALVSFS) Nnu]NAL , (NON. ROUTINE)* LLn NO. nFTFrTFnee Sfa. e.n. nFTECTEnee 40 nF IF C T E tt e e BE.7 ( 1) 2 ( 9(l A= 1.4)F t 13 ( t.) a t 'es) E 2 (.3.3 & 3.7)F 1
. ( 0) ( 5.8 12.%)E t (.3.3 0.8)E t j et o/ 21e et 0/ lie et 4/ lie IE.40 ( 3) 9 ( A(oA= .a)E 2 ti ( 8.4 A 2.'e)E 2 ( 7.6 & 9)E 2 i ( 4) ( 7.6 8.a)E 7
*( 2/ 21e e( 1/ 11e et t/ 11e CR.51 ( 31 1.PE*07 ( 7El 4 .s)E 1 14 ( 7.6 1 5.1)E I (.o.3 & a.21F t I ( 01 ( 6.5 = 7.6)E I (=6.3 0.01E 1 f
et 0/ 21e et n/ lie et op 1).
~
MN.54 ( 31 2.0F.o2 (.5.5 a 2.11E o 21 (.2.1 a 4.5)E o (.2.1 g a.5)F o ma ( 0) (.7.9 . 4.01E o (.2.3 . o.o)E o , et 6/ 2)e et 0/ lie et 0/ Ils n N w 5.0iE o a.A)F 0 h C0=54 ( 3) 2.of.02 ( t{n &. .n)E t t te (.2.s a (.3.4 & o.0)E 2 c'n ( 0) (.t.A . 4.01E ( 3.4 . O A et of 2)e og of t)e et 0/ t)e :ra$vi.[-. deb m --e s FE 59 ( 11 3.0F*01 (=tg 3A 9)E t 21 ( t.e a to.3)E o ( t.a a to.1)E o """ ( 0) (.t.e = 0.n)E 3 et 0/ 2)e et n/ t)e et 0/ t)e CO.60 ( 11 2.0F 02 ( a .' 7 a t.4)E o 14 ( 6.5 i 7. Fit 0 ( 3.0 & 6.9)E o ( 0) ( 2.8 = 6.5)E o et op 21e et 0/ 11e et n/ 11e l 2N.65 ( ( 11 0) 6.7Eeot ( t(5 4 (=A.9 . 2.a)E 1A.9)E t o 31 ( 3.9 A 3.5)E I ( l.3 & l.8)E g
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l
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l . [ NSe9% ( 1) 3.9E*01 ( 4,1 & t.n)E O 14 ( 5.3 A 6.81F 4 (=8.0 & e..)F U l ( 0) ( 3.2 = 5.1)E a (-0.0 - 0.n)g o l ** O/ 21e *( 0/ 1)* e( 0/ lie l 4 Gall 0Mt 11 2.4E*02 ( td6 A- 7)E 2 13 ( 2.3 a 1.01E 2 ( 5.4 & 3.918 I l ( 0) ( 9.4 21.%)E t et of 21e et n/ t)e et 0/ 11e EU-103 ( 31 2.0E=42 ( 3,9 & t.a)E o il ( 5.3 A fl.9)E o ( 3.6 & 4.7)E a ( 0) ( 2.5 - 5.1)E O et 0/ 21e et 0/ 13e et 0/ lie
; au iO6 ( 1) 2 ( a;0 a ...)e i il ( i.2 i 1.2it 2 (-s.7 x a.31F :
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!=131 ( 13 0 ( 2.0 a 1.01E O 11 ( 3.0 i 16.91F 0 (-2.3 & 12.01E n g[f a ( 0) ( 9.1 = 10.1)E 1 (-2.3 = 0.8)F 0 rt oj *( 0/ 2)e e( 0/ lie et 0/ 11e Ef [[
C >* Chel34 ( 11 2.0E-02 ( A 0& 7)E O la ( 8.7 1 6."2ig o (=6.6 & s 7)F 0 Q[jk a ( 0) ( 7.3 - 8.7)E o (-6.s . 0.8)F 0 %-- i
*( 0/ 21e et 0/ t)e et 0/ 11e ""
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==C
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..i)E sa
( 3.. - e( 0/ iie 17..)r 0.0iF 2 2 N, CE tes ( 3) 2 ( 6.' t a 4.a)E I 11 ( t.3 A 71E 2 ( 2.4 & 2.11F 1 .ma"" ( 0) (=t.7 = 129.8)E O et 0/ 21e et 0/ 1)e et 0/ lie r e NON-RnuTINE RFFFRS Tai THE NUahFR OF SFPaHaTF *EaSI'RE*ENTS HICH WFWF GREATFH THaN TEN (10) TI*ES THE a vFWacF maCugenUND Frie TNF PEston nF THE RFPn9T se THE FRacit0N nr samptr aNatYSF A YTELnING DETERTaRLE "EasuMFwENTS (f.E. >1 SIGMA) TS INDIC&TFD mITHIN et le.
mM M M M M N M m M mM M M M M M M 1 5 4 I 4 i i
- PILGRIM I 0FFSTTF FNVIRONMINTal RantnLOGICaL MONTTHRikG 90/02/27
, SUMMaRV Fne THF PERIOD 12/31/T9
- 12/31/A4 MEDIUM FOOD CRAN 8FNRIFS tlNIT83 PCI/mG .ET j maDt0NUCLinE8 INDICATnk AfaT!nNS HIGHEST SfafinN CONTWOL LOCAT10wS (NO. ANALYSES) NOMINAL MEaN,paNGE,aND NEaN,RANGFee60 MFaN,RaNGFeaND (NON. ROUTINE)e LLD NO. nFTErTFDee STA.* No. DFTFCTEDe,e NO. DFitCTEnee
............. ........ ................... .... ............... ..>.. ................... H i
M (.5. 3 A ' 22.2ir 0 TH.228 ( 3) ( e) 2.oE.c2 (.4(1& 2.Y)E I 25 (.5.3 & 22.2)F o 85 i' (.T.o . 0.01E 1 ( 5.3 c.p3r o s [ Ch et O/ 21e *( 0/ lle et 0/ 11e [ ~~ ' CD 3M , c a
$E 1
e NnN.RntlTINE RFFFRS Yt) THE Mikat e nF MFPaRa TF MF a 8184f aENTS *HICd =FRF GefaTER THAN TFN (to) T]MES ThF avFRacF maCusunuun FOR THE PERIsm 0F TME RFPORT se THF FRACT!nN OF Samply aMat.YSF A YTELnTNG DETFrT4 HIE MEASilRFMENTS (1.E. >3 SIGMA) TS INDtcaTFD mTTHIN *( 1e. l. P
.F
I III. M. Vegetation Samples of tuberous and green leafy vegetables are collected at the I time of harvest at four locations, Plymouth County Farm (3.5 mi - W), Bridgewater Farm (2n mi - W), the Evans Residence (0.7 mi - W) and the Work Residence (0.6 mi - ESE) . The results of the ERMAP program for this media are presented in Table III-M-1. The only man-made isotope observed was Cs-137 at the Evans Residence. The absence of Cs-134 at this location and the fact that the measured Cs-137 concentration (40 pCi/Kg) is about 8000 times what would be expected at this location based on releases froci PNPS-1, strongly I indicates that fallout, not PNPS-1, is the primary source of this Cesium-137. Therefore, it is extremely unlikely that there was any environmental impact on vegetation due to operation of PNPS-1. I I I g . I I I I I ! 3-67
) E E E E E E N -[ E l
'pfLGRIM I HFF9tTF F Nv iput*F N T at Danintndtral POSITOW1%G 41/np/77 9 tlee M a H Y FhW TMF PFWlon 17/31/79 . IP/31/>A NEDitml Fonn/GawnEN ranp9 nu1TSI pr i ta 4 *ET RADIONUCLIDES TNn1CATHW MTaTIONS HIGNE9T STATinn C uh T N ot inrefinNS (NO. ANAL YSFS) NOMINAL MF a,N ,R aN G E. AN n MFaN,#aNGF,akn *(au,RahGF,aND (NON.ROUTINF)e [[n NO. nFTFCTFnee 974 _ NO. nFTFCTFnee kn. OFTFCTE0e*
i tlE .7 ( Al 7 ( 3f7 & 3.a)E 1 IT ( t.4 A 7)E 7 (.2.7 & 3.3)F 1 ( c) (.3.3 13.4)E I (.6.9 = 4.2)E l et n/ %)e et n/ 13e et o/ 3)e j tr.40 ( A) .5 ( 3(7 A. 9)E 1 16 ( 3.4 A 7)F 3 ( 3.2 & 7)F 3 ( .) ( l.9 e.A)E 3 ( 2.3 e.6)F 3 et 5/ Sie et 1/ I)* *( 1/ 3)* CA=51 ( R1 3.7E+07 ( 6 .' *
- 2 I 17 ( l.7 A 9)E 2 (.9.7 & 6.6)F 1
( 0) ( 6.' o . 17...)E 9)E o (.2.2 0)F 2 at 0/ 5)e et 0/ lie *( 0/ 3)e MN=54 ( m) 2..F.07 (.3l8 a 2.6)E o tA ( 6.0 A 6.5iE D (-2.1 A 5.11F o ( 0) (.9.5 6.0)E o (.7.9 . m.o}E o m -e et 0/ 5)e et 0/ l)e et n/ 3)e m$g a
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cn ( 0) (.l.7 7)E t (.2.1 . lo.01E o E :n .-.
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S & I pitCWIM I fiF F S T IF F D VipHN=t H T at G a ning nr.T C al NON T Tow !bn Ml/02/77 quMMARY FOW Tur PF# inn 12/le/79 . 32/31/Fn MEDIUM: FHun/GaunEN canP9 usiTS: pC I /a G -L1 RADIONHClinF9 INntraTHW 9faTION9 HIGHEST stattnN CON i dnt t oC a t tons (NO. 4 N 4[ V 3E 9) NOM {NAL MFAN.R4hGF.AND .EAN,4&NGF.&hn NFAN,Da%GF,4Nn (NON.R00TINFlo Ll.D NO[ DF TFrTFam e 374.' NO. DFTECTFDee NO. DFTFCTEpee A)
~
l NO.95 ( 3.9Fe01 ( 4,7 g a.a)F n 17 ( t .8 A 9)F 1 ( 4.3 & to.7)F o I ( n) (.8.6 . 17.5)E o (.t.5 2.11F t
- et 0/ Sie et n/ 1)e et 0/ lie AG.st0M( A1 2.9Fe03 ( 3(9 A. 2.%)E I 16 ( t.2 a .'6 ) F 2 (.5.7 A ela.1)F =t
( n) (.2.8 12.1)E I (=#.7 = 8.2)F l
*( 0/ 5)e *( 0/ 1)* et 0/ 3)*
l RU=103 ( n) 2.oF=o2 ( 2d6 A 5.5)E o 17 ( 4.3 A to.4)E a (.4,9 A t.e)E o ( 0) (=9.5 = 21.6)E o (~7.4 . 0.0)F o
*( 0/ 5)e *( 0/ 11e et 0/ 3)e RU=t06 ( Al 2 (= tdt A 2.6)E I 11 ( 5.64 41.9)E O (.3.3 g a.1)E t
( 0) (=7.1 = 7.3)E 3 (.t.1 = 8)F 2 _4
*( 0/ 5)e et 0/ 3)e et n/ 31. ,, @g o r-I.131 A) n. ( lde g .o)F t in ( l.5 A 1.'l i F l (.2.1 & 4.A)E o
@ P1 jd ( 0) (.4.1 . l.9)E 1 (.7.7 7.4)E o o **
os *( 0/ Sie *( 0/ 1)* et 0/ 3)e gf [[ us c , C8=l34 ( A) ( 0) 2.0F.02 (.t[t & 4)F 1 th f 5.9 1 7.3)E O ( 6.e A 2.n)F 0
@[]E
(.2.6 . o.n)E (.l.t . c.n)E 1 %->" et 0/ Sie *( 0/ 11e et o/ lie C5=137 ( ,83 2.0E=02 ( 6,0 A 9.3)F 0 17 ( 4.0 A 8)E I ( 8.1 & 21.5)F .I ( 11 (=t.6 . a.n)E I (-1.5 = 3.4)F o et 1/ Sie *( 1/ 11e et 0/ 3)e 8A=l40 ( F) 8.0E.02 f.4,9 A 3.5)E O 22 ( t.4 a 1.'0 5 E l ( l.4 & t.4)F t ( 0) (=1.4 . 4)E i (.5.2 29.8)F n et 0/ %)e et 0/ 3)e et 0/ 3)e g*[[a)g g CE.141 ( A) 4.0E=02 (=3(6 A 4.n)F 0 22 ( t .2 A [t)E I ( l.2 a 1)F t ( 0) (=t.n . l.2)E t ( l.1 . l.4}F et 0/ Sie of 0/ 3)e et 0/ 3)e CE=les ( A) 2 ( 1(9 A- 7 )'c 1 17 ( 3.1 A 5.8)E 1 (=o.7 & St.1)F 0 ,,wd* ( n) ( 2.9 et n/ Sie 36.9)E o et 0/ lie ( 2.9 . et o/ 3)c 5)F l *j)
-rf e NON.ROHTINE RFFFRS TO THE N18aAFR nF .9FPARATF FFA90HE>ENTS WHICH eFHF GWEaTER THAN TFN (10) 71MFA THF AvFuaGF maCMGROUNn FOR THE PER!nn nF THE RFPnNT
** THE FRACTION nF SAMPtF ANat VSFR VTEL nf NG DETErf aRLE ME ASueFMENTS (f.E. >3 SIGMA) TS INDTCATFD aTTHIH *( )*.
m m m m M m W W m m m m W W W m m PILGRIM I nFFSITF FNVIRON* Ental pantntnt:fcal MnNiinRING nt/pp/pf.
SUMMARY
Flin TMF PERInn 12/14/T9 . 12/31/>n MEDIU4 FOOD /GARnEN CRnPS UNITSt PCI/nG hFT RADIONtfCLTDES INDICainD 9faTinH9 HIGHEST StaffnN CONTNot ItirafinNS (NO. ANALYMFR) NOMfNAL MFAN.Da>GE.4Nn MFAN, RANGE,Akn MFAN,044GF, ann (NDN.ROUTINFlo LLn NO[ DETFrTFnee RTA[ Nn. DFTFCTEnee NO. DFTFCTEDee g RA.aas ( 6) .i ( a.6 a 9. pie i i. ( t.3 4 i.eiF ( e.n a io.nr i gl;; ( 0) (.t.1 . 7.t)E 7 o y of 0/ %)e *( 0/ lie et 0/ 4)* 9 %. "-. a O TH.22A ( A1 7.0E-07 ( F(7 & 1.91E I IT ( h.T i 4.3 % E t ( 2.e a IP.91f n E$ ( 0) (.t.T . 6.71E 1 (-1.2 P.7)F 1 me of 0/ sie et 0/ t)e et 0/ 31e & CD e NON.R0llTINE RFFFRS TO THF HllunF# nF 9FPARATF MFAMilRFMFNTS aMICH *FRF GREATER THAN TFN (101 TIMFS THF AVFRaGF M ACNConifMn Fn# TME PERinn nF THF RFPORT en THY FRACTinN OF RAMPLF ANALYRF9 viELnTNm nFTFCTanL E ME AStinF>ENTS (f.E. >15fGmal TS INDTCaTF0 WITHIN *( 1e. 9WW
-r f
I I III. N. Forage Beef Forage is collected from three locations annually, the Plymouth County Farm (3.5 mi - W - Station Number 11), Whitman Farm (21 mi - NW - Station Number 21) and Plimoth Plantation (2.2 mi - W - Station Number 15). The results of the ERMAP program for the media are pre-sented in Table III-N-1. The only man-made isotope detected was Cs-137 which was detected in all samples. There were no other reactor-related isotopes detected above LLD in any sample. The highest mean concentration of Cs-137 occurred at the Plimoth Plantation. However, the absence of Cs-134 and the fact that the measured mean Cs-137 concentration (120 pCi/Kg) is in excess of 100,000 times what would be expected based on releases from PNPS-1, strongly indicates that fallout, not PNPS-1, is the primary source of I this Cesium-137. Therefore, it is extremely unlikely that there was any environmental impact on forage due to operation of PNPS-1. I I I I I I I I 3-71 I
.I m m' W W W m m m M M m m W m m W m M 1
pttcpiN i OFFSITF F Nv iD'6NMEN T al DanInt nr.tC AL Ml!NiinWi&G Mt/nP/7T. HimM a p V Fnp THF PFeinn 12/11/T9 . 17/tt/en MEDtuMe VFCETafinN . TFRpFSTial TWIT 5: Pet /mG *FT RADIONUCLinE9 TNn{faTHW ifaTIONs HIGMF9T STAI!nN rONTW'H I v.ra f f rom j (NO. ANALV8FS) NOMINAL HFaN,RANGF Ahn MFaN,OANGF,mkn MFAN,DaeGF, ann (NON.ROUTINF)* Li n NO2 nFTFrTFDee stal Nn. nFTFCTEne. No. nF T Ff f Elis e t i RE.7 ( ( 0)
- 4) 7 (( Ift A .%)E Pl.9)E 3 19 f 1. 3 A (9)F 4 71.5)E
( 5.5 & 9.m)r 2 i 4.1 2 ( e.t . 7 (.2.9 . 113.o1F 1 et 7/ 3)e of t/ 2)e *( 1/ 7)* M.40 ( 9) 9 ( 6.4 & .A)E 1 23 ( t .7 A g t)F a ( t.A g 9)F 4 ( n) ( 4.9 . . 7.6)E 1 ( l.0 . 1.7)F 4 ( 1.0 - 1.7)F 4
*( 1/ 3)e *( 1/ 11e et 2/ 21e CR.51 ( 9) =1.n. ton ( Ido a 17.1)E t it ( 2.2 i 3l3iE 7 ( t.1 & 6)F 7
( n) (.2.n . 7.7)E 7 ( 4.? . tA.n}F i of 0/ 3)e e( n/ t)e et 0/ 2)* 1
~d l MN-54 ( 5) 7.nf n? ( 7{t & 9.7)F n 71 ( 7.2 A 1.9iE 1 ( l.m & . elf 1 l ( oi ( t.1 7. n ) F. t ( t.4 . 7.7)E 1 {'b$
i *( 0/ 3)e *( 0/ 1)e et 0/ 7)* khh$ ] n 19l nit n IJ CO.58 ( 9) 7.0F.np (.7l4 g 5.6)F n 71 f 6.2 A ( R.5 & 53.1)F .I C3fE[[
-4 ( c) ( t .1 6)E t (-4.5 6.7)F 0 b Lo *d j
DJ ef 0/ 3)e *( 0/ 11e of 0/ 21e blEE$-
-4 s I "*"'
FE=59 ( 51 3.nE+01 ( P(7 A. 7.7)E 1 11 f 4.3 A 3.75E I ( t.5 A 5)F 1 ( 01 (=7.1 4.%)E i ( t.o . 7.n)F t p-([) et n/ 3)e et n/ f)e et n/ 2)e . CO.60 ( %) 7.nf.07 ( 5dl & II.11F n. It ( t.5 1 2.9%F t ( 5.9 & 30. air .I ( 01 (=t.7 9.m)E I (.l.5 4.5)F o of 0/ 1)* ef 0/ 1)* e( 0/ 214 ZN=65 ( 9) =1.0 100 f t .a)E t 21 ( 5.4 & 5l5)E I ( t.7 A 3.6)F 1 ( Oi ( .E5
.n -A ia..)E a (.i., . 5..)E i
*( 9/ 3)e *( 0/ 1)e et 0/ 2)* C[$
w[ ZR. 5 ( 51 4.or.np f 3;7 i.7)F i 71 f T.a A 3.iie i ( 3.7 A a.5)F i ( ni ( i T. ). i f">g5 - e,i.5 n, - sie s..iF of n, ile (-i.s . of ., / 2ie .- 7,,- e NnN.RnHTINF FFFFW9 T 't THF Newb5p siF SFpakaTF "f A
- HWF HF'4 T S =MITH *Fef f.E F a T F u THAN TEN (In) T!*F9 THF avFusCF 94(mgunnon Frip Tur prugnn nr 1Hg wFpnet se THF FearTION OF mampt r Amat YsF 9 vitt DTN4 nF TFrf aut E apa500F"FwTA (f.F. 33 31 r,M a ) TS 1"DTCsTFn miTHI*, *f ie.
m m m m m m m m W m m M M m PFLGHIM i eFF9ffF FwVTRH6af JTal panintnGTCal MePsiTHnTkG 4t/n3/>F. 9tedwant Fno Twr Pteinn 17/39/79 . 17/tt/en MEDIUMI VFGFTATION = frRDF 9f f el 88hf TSg PC I /n G -F T RADIONUClinF4 TNhicaTHW qTaTIpot MIGMFtf Sfafins CnN Tsus l e taitow9 (NO. A N al_ y SF M ) NOMINat > FAN,WannF, ann MFaH,4ANGF,ahn "EaN,on=Gr, ann (NON.000TTNF)* Ltp N0l nFTFCTFnee 914 NO. OFTFrTEnee NO. nFIECTEhe* NB.95 ( %) .t.n.100 ( 7(1 4 1.11f e 11 ( t.7 A 1.7%E I ( o.o a 37.9)F 7 ( 4) ( l.3 ft.o)E n (.3.2 e,alF .I et n/ 3)e et n/ t)e et o/ 2). AG.it0M( 4) .l.a. tan (.7fm g i n , a ) F. 3 21 ( 3,1 g 3.65F 7 ( t.T g 1.4)F 7 ( n) ( 2.7 t.n)E 7 ( ).5 31.P)F 1 et n/ 3)* et n/ t)e et n/ ?). RU.103 ( 9) 2.0F.n7 ( 7(o& 6.1)F o 19 ( t.9 A 1.a)E 1 ( l.5 A 318 1 ( 0) (.2.7 t#.a)F o ( t.2 1.k)F t et o/ 31 et 0/ t)e *( o/ 21 RU.lo6 ( 5) 7 ( .7.'1 A 7)I 7 21 ( t.4 A 1. PIE 2 ( q.3 & la.71F 1 _4 ( 0) (.3.5 n.n)E 7 (.6.0 . to.5)F 1 2= et n/ 31 et 0/ 13e et 0/ 21e ,, [E nm 2.55E t
!=tSt ( 5) 6 ( 2.t a .m)E t It t 7.9 A (.6.6 & 7.7)E o @ ,,
( 0) ( 5.5 79.7)F o (.t.4 . 9)F t rt >* jd et n/ 3ie et n/ t)e et 0/ 21e Ef l* l , %J C 2 l CS=t34 ( 5) 2.cE.07 (*2g 2 & t.0)F t 77 ( 6.a A 12.7iE n (.t.1 g 1.7)E 1 @[di n.o)E ( 0) (.3.9 . 1 f.2.s . 6)F t -- et 0/ 3ie *( n/ 1)* et n/ 2)e CS.137 ( 5) 2.0E=07 ( Id2& .p)E 2 14 ( t.2 A .' 3 5 E F ( t.5 & P.ajr 1 ( 3) ( 8.7 ,ts.t)E i ( A.7 15.1)E I (.9.1 = 39.8)F n et 3/ 3)e *( 2/ 7)e *( 0/ 2)* OA.le0 ( 9) A.cf.op (.ela g .o1F 1 21 f 5.m a 3,oir 1 ( 2.8 L 1.nir 1 ( n) (.5.5 n.n)F t (.2.1 . 58.01F n et n/ 31 *( 0/ 1)* *( 0/ 2)* gl[[)> CE=let ( %) ( 0) a.nr.np ( tl2 & t.1)E 2 11 ( 3.7 h 7.'7)F 7 (=7.5 & th.9)F 015 0 ( (.7.9 - 47.417 1 ( 2.4 . 1
*( n/ 3)e *( H/ t)* *( 8' / 7t*
CE.taa ( g) ( 0) 7 ( 3;o a ( l.7 t.p)F 141.n)F 1 e 2t t t.n i .P)F 7 ( 1.a A f.6.4 . a.4)F In 8)F t t g[[) et n/ 3)e *( p/ 11e et 4/ 7)e
&M y
e NMN.R0llf!HF DFFFD9 Tse THF vit* pf W nF trpskaTF
- st a ".UW F.F *' T M . Hire >Fer GUFaTF# g TWAN I F ** (10) flub 9 THF avFueCF b a l u r.E.Ot e%f- F f'd Tkf PF W i t 'll f'F ThF WF PI'W T )
ee Twr FeaC Tif m DF 94wps e assty9s9 y t > LpT *'4 nF Trr f aw F > F a situf st A19 (f.F. 14*tcpa) f5 INHira TFD .ftwik *( 1e.
i M M M M M M M M M M M M M M M M M M M 'l PILGRIM I flFFSITF FNVf 9fplMFMf al Rahll' LOGIC al MOH t filWi>G 41/02/77 AUMMAOY Ft10 THF PE R [nts 12/31/T9 . 17/3l/A0 MEDIUdt VEGEfatt04 . TFRRESYtal seNITSg PCI/MG MET l' RADIONUCLInFS TNotraino staTIllNS d{GHEST STaffnN CONTNot stirafftwR (NO ANALYSES) NnMINat *EaN,RaNr,E, ann wEaw, RANGE,ahn "EaN,PaNGE,4Nn j (NON.ROUTINEie LLD Nn.' DFTFrTF0** 574.' wo. nETECTEDee NO. OFTFCTFisee e............ ........ ................... .... ..................... ................... g j TM.228 ( 5) 2.nf.02 ( 4(2 &. 4. Alt I lt ( t.6 h .'9 i E 2 ( 7.8 & 1.3)F 1 mg Q ,--. y ( 0) (.2.0 19.7)F g ( 6.a . o.3)F 1 3m a N et 4/ 3)e et 0/ lie *( 0/ 21e [ b o -< c --e
*o.5:
~ ,L e NON.RntlTTNF RFFFRS TO THF NIIM R F R 11F 9FPARATF WEA91loFuENTS pHTCH >FRF GREATER THaN TEN (101 ftWER THF abFRAGF RACNGRntlNn Ff1R THE PERitim if THE RFPnpf
** THE FeaCTinu Op naupl F AN AL YMFS YTELoTNG DETECTARLF MEASUREwENTS (f.E. >3SIGuai IS IN0ftaTED mITHIN et le.
c::P 9 9.&e- -
.$9f
I : I IV. References I 1. Regulatory Guide 1.109 - CALCULATION OF ANNUAL DOSES TO MAN FROM ROUTINE RELEASES OF REACTOR EFFLUENTS FOR THE PURPOSE OF EVALUATING COMPLIANCE WITH 10 CFR PART 50, APPENDIX I -Revision 1, October 1977
- 2. SETTLEMENT AGREEMENT BETWEEN MASSACHUSETTS WILDLIFE FEDERATION AND BOSTON EDISON COMPANY RELATING TO OFFSITE RADIOLOGICAL MONITORING
- June 9, 1977
- 3. Yankee Atomic Electric Company -
Program "ERMAP", Version 3.1 - January 9, 1979, Author - J. E. Vossahlik I 4. Memorandum, Yankee Atomic Electric Company, Reg 94/77, A. E. Desrosiers
- 5. Direct Radiation Survey, June 1976, S. A. Farber, Yankee Atomic Elec-tric Company l 6. Memorandum, Yankee Atomic Electric Company, Reg 211/76, A. E. Desrosiers i
l
- 7. Report on Accumulation of Cesium-137 in Cranberries, March, 1979 Yankee Atomic Electric Company, M. Strum I
I I I I 4-1
I I Appendix A - Anomalous Measurement Reports I I
. I ,
i I I
- g l
I I I
.I I
I I l I A-1 ..
- g' . . .- .' .. ' . S.
g '.' s . t * ,' g.: s 4
;
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.I.
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*' ', PILGRIM NUCLEAR POWER ST/ ~i0N .. .
! [' RFD
- 1 ROCKY H LL RoAo
- g PLYMOUTH. MAS,5ACMUSETT5 00363 ,
~ "*
February 6, 1980 , BEco Ltr. #80-23 I Director, Region'I - Office of Inspection' and Enforcement l I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
)
I Licensee Event Report 80-005/01T-0 Docket Number 50-293 License DPR-35 Gentlemen: The attached Licensee Event Report 80-005/01T-0, " Anomalous Measurement. .. Report" is hereby submitted in accordance with the requirements of Pilgri~. Nuclear Powet Station Technical Specification 6.9.C.2.b. If there are any questions on this subject, please contact us. I . Resp ctfully submitted, e d 1 P. . McGuire - I . Station Manager Nuclear Operations
)
MIM:ap I
Enclosures:
(3 copies) LER 80-005/01T-O cc: Director (40 copies) - I Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 l 5 bec: Messrs. C. C. Andognini R. Sevigny E. L. Cobb W. M. Sides I . P. A. Foulsham(2) M. C. Hensch C. J. Mathis D. C. Stoodley C. K. Vantresse C. G. Whitney M. T. McLoughlin 3,Mt" K. Calderone - J. W. Nicholson NOD Licensing ' W. 7. Olsen PNPS Records Center
- J. A. Seery P.J.M.(LB) -
' ~'
- . ;. ;
l- '
~ :
\
l , , , _ l
. u .
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\
l
*E
*f,. ." LICENSEE EVENT REPORT .'r. ,. - .'.
g $iRO! SLOcK: l f 'l* l
'C o i . ..
l l
.h -
l IPLEASE PRINT CR TYPE ALL REEUIRED INF3".MATIONI lM l ucansEEA lP Coof IP lS isl1 lh 4 l I l II 1l 1l@e, CATl se l @.
- o w- bl' O! 'l Ol 0l01010]
uClast Num ER l'OIOl@as as uCaust tvrt ao .
' SuYet [.Lj@l0 l5 lCf l- 10121913 88 h 01 11 SS il 11 al ol@l EVENT oATE 7.
0121 75 OI 6I 810Sol@ REPORT DATE so el $oCKET NuueEm i EVENT DESCRIPTION AND PROSABLE CONSEQUENCES h i On January 1,1980. BECo was notified by Yankee Atomic Elecerte T mh thee .mur.A 1 f
;
, concentrations of Sr-90 in a milk sample taken fron'an indicator station was greater i than 10 times the concentration in the control station sample,18 pei/kg to 1.6 pei/kg l
, , repectively. The indicator station is 2.2 miles west of the reactor site. There is i g no detectable Sr-89 or I-131 in the indicator sample; therefore, it is not likely l
, g thet Pilgrim Station is the source of the measured concentrations. i
. l . l l
'cNo E YoE sNCooE czapoNENT CooE ot sI$bYcoE s .
'II II l@ Lxj@ Lz_l@ 12 I z I z I z I z I z I@ suTeL @ J.1@
. . io n u u a i SEcuaNTIAL OCCURRENCE REPORT . REVIStoN EVENTYEAR ASPoRT 8eo. Coot TYPE 18 0 .
I @ ,a,LER/Ro g la101 ,_ a i za sa [-_l loloisi m as V_.] 37 10111 as as p [--:l si 101 B"'-
'/ YAEE 'ETYod cEP E ** u Tt nouns @ #EeTu TTEE coTn sus. "sEuY' asA YN:TuRER
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..J W. @ W@
E ' 2 . - . . . ., CAUSE DE 4RIPTION AND CORRECTIVE ACTIONS 27 . I lNo corrective action is contemolated. It ann nem thee them. 1 v.1= mr. An. en I
- g l local meteorological conditions which resulted in the deposition of old fallout.
I I
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oTHER STATi2 D1 R discovery DESCRIFfloN gT % POWER (,p,J@lNotificationbyEnvironmental1mb. l s W @ l01010l@l 1 l
.s .s so
.sg g u n LOCATION OF RELEASE ELEAsto oP REtaAsE a
[z]@ W@ln Auouwt N.A. or w ACTiv TY l e hN.A.l so I ; i e to PEftSoNNEL EXPOSURES NumeER TYPE
] 010 l O j@W@DESCRIPTloN l N.A. . I PERSONNEL put IES - "
NuueER oEs:RiPT1oN@
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PusLICITY NRC USE ONLY l
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- 61. 7. 74 6.7900. ._ . _ _.
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March lE, 1980 bECo Ltr.#80-43 I Director, Region 1 Cf I r.fice of Ir.spection E. Su:*. tar Kegula tc ry and f31 ? ark .;ven.se Cer=issionEnforcement ring of Trussia., PA 19406 I_izenssaIvan:Report 80-009/04T-0 Docket Nt=,ber 50-293 License D?R-35 Gentlemen: T.,e a:: ached Licensee Event Report 80-009/047-0 "Anomelous ::e:r rerent Reper: is '. ereby suitir:ed in accordance -ith the requirements of Pi grin Nu:; ear
-:. er I:a:1:n ~echnica; Specifi:ation 6.9.C.2.b.
f there are any questions on this subject, please centact us. Esspectfully suiritted, I t P. . McGuire Sta f en 2: nezer Nu:Itar 0; ars i:ns - I 3.T.':e; Enclesures: (2 copies) LIR S0-009/ 04T-0 cc: Director (40 copies) Office ef Mrnagement Infor ation and Pregra: Control I T. 5. Nuclear Regulatory Co:=ission -
".0:.shing tcn, D.C. 20555 bec: Messrs. G. C. Andognini R. Sevigny E. L. Cobb W. M. Sides
'I l P. A. Foulsham(2) M. G. Hensch D. G. Stoodley C. K. Vantrease J. E. Howard G. G. Whitney C. J. Mathis Ms. K. Calderone M. T. McLoughlin NOD Licensing J. W. Nicholson PNPS Records Center I W. F. Olsen J. A. Seery P.J.M. (LB) 1 I -
LICENSEE EVENT REPORT
~
* ,* CONTROL BLOCK: l i
l l l l l lh 8 (PLEASE PHINT CR TYPE ALL RECUlRED INFO 2MATION)
.jl xl A l P l P l S I 1 tol@l160 l 0 l - l 0 lLICENSE 0 l 0NUMSER l 010 l- l 0 l 0 2h @l254 l 1LICENSE l 1 l 1TYPE l 1J0l@l57 CAT l lg SS 8 L6CENSEE Coot ;..
1 Ev","c' Ql 0 l 5 l 0 l - l 0 l 2 l 9 l 3 l@l 01311 l 018 l 0 l@l 74 0 l 3REPoRToATE 75 l 1 l 8 l 81080l@ SO St DOCKET NUMSER SS SS EVENT oATE EVENT DESCRIPTION AND PRO 8ABLE CONSEQUENCES h 2 I On March 10, 1980, Boston Edison receivad an analyses report from the Yankee l l Atomic Electric Laboratory which indicated that reportable concentrations of Cr-51 l l (339
- 14 pCi/kg) and Co-60 (167
- 25 pCi/kg) existed in a n:ussel sample taken l 5 l from the Pilgrim Station Discharge Canal on January 10, 1980. l l These concentrations are in excess of 10 times the Lower Limit of Detection at l 7 l the Control Station in Marshfield (LLD for Cr-51 was 31.pci/kg and' for Co-60 l 8 I was 4.7 pCi/kg) . -l Yo'E $5E SN$$E COMPONENT CODE SUS oE S C E 9
8 l Il Ilh 8 io ii h n h lZn lZ lZ lZ lZ lZ lh it it h 20 h LER EVENT YEAR EP TN TV N. I@ ,g'Ro g 1810 l [:__j 23 101019 l 24 26 d 27 10 14 l at 28 T l- --J 31 y 32 _ 21 22 KN ACT o P T MET HOURS 22 1 PoR US. L MA C RER _ j@l_Z_.1@ 24 LZ_1@ / as. l.Z_JO IoIoIoIoI ao l!Lj@ LN,,,J@ (,Z J@ _ lZ l9 l9 l947l@ a as . si 4i 42 42 4. CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 l The maximum dose to an individual consumit.g seafood with these concentrations for l l] I a full year would be only 4 x 10-3 mrem to the total body and 2.4 x 10-3 mram to I l the most restrictive organ. Therefore, it is concluded that there is no risk to l l the health and safety of the public. l t t I I AE % POWER oTHER STATUS oi5 R DISCOVERY otSCRIPTioN 32 s [H_J@ l0l0l0l@l" N.A. l (,D_J@l Notification,byEnvircamentalLab. l AbivtTV Co TENT LEAst Lo:ATioN or R'4 LEASE [ Zj @o or RELEAsEy@l AMOUNT N.A. or ACTiv:TY l 46
@N.A. l 80 l
8 10 11 44 FER$oNNEL EXPOSURES NvMSER TYPE oESCRIPTioN 8 A- I i ji 0l ' 010l@LZJ@l ' " '" rEnsoNNE'L iNav' lits NvMSER oEsCRiPTioN@ ,
; I0l0l0l@l S 11 12 N.A.
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.. ca Edison cam' PsLGRiM NucLcAR Powcn STAviDN RF*D =1 ROCKY Mibt ROAD l ALvuouTM MassacMusCTTE O2360 I I
April 2, 1980 l BECo Ltr.f 80-53 IDirector,RegionI Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Licensee Event Report 80-009/04T-1 l I Gentlemen: Docket Number 50-293 License DPR-35 i l* The attached, revised Licensee Event Report 80-009/04T-1, "Anomolous Measurement Report" is hereby submitted in secordance with the requirements of Pilgrim Nuclear Power Station Technical Specification 6.9.C.2.b. This revision is b2ing issued to correct a calculation error. The correction does not alter previous conclusions. . If there are any questions on this subject, please contact us. Respectfully submitted, c me P. . McGuire Sta on Manager Nuclear Operations E MIM:ep W
Enclosures:
(3 copies) LER 80-009/04T-1 cc: Director (40 copies) I Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Iec: b Messrs. G. C. Andognini R. Sevigny E. L.'Cobb W. M. Sides I P. A. Foulsham(2) M. G. Hensch J. E. Howard P. D. Smith D. G. Stoodley G. G. Whitney C. J. Mathis Ms. K. Calderone I M. T. McLoughlin NOD Licensing J. W. Nicholson PNPS Records Center , W. F. Olsen P.J.M.(LB) J. A. Seery lI I .
'"g,- Ce WTRO. B LOCK: l } l l l l LICENSEE EVENT REPORT lh (PLEASE PRINT CQ TYPE ALL REtUIRED INFtRMATitNI 1 6
- i l Ml LICENSEE 9
A lP lP Coog lS l1 lg0 l 0l -l 0l LICENSE to 16 0l 0lNUMSER 0l 0l -l 0l 0l@264 l 1l 2S 1[ 1l 1l@l57 GAT LICENSE TYPE JO l lg SS 1 y',$ l L l@l0 15 l0 l- l0 l 21 91 3 @l 01 31 11 Ol 81 0 l@l 0l 3 l 1l 8 l 8 l 0 l@ 60 Si ooCKET NUMBER es Se EvgNT oATE 74 76 REPORT oATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l On March 10, 1980, Boston Edison received an analyses report from the Yankee Atomic ; l Electric Laboratory which indicated that reportable concentrations of Cr-51 (339
- l l
14 pCi/kg) and Co-60 (167 t 25 pCi/kg) existed in a mussel sample taken from the l g; Pilgrim Station Discharge Canal on January 10, 1980. l l l These concentrations are in excess of 10 times the Lower Limit of Detection at
, l the Control Station in Marshfield (LLD for Cr-51 was 31.pci/kg and for Co-60 was ;
, , 4.7 pCi/kg). I SoI:'E #$ oil suCioE COMPONENT CooE suSWo'E '
9 lX l Kl@ (X j@ l Z l@ l Z l Z l Z l Z l Z l Z l@ [Zj@ s"lZj @ s 9 to I1 12 13 18 19 20 gge go IVENT YE AR RE RT o oCE N .
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27 lo l4 l [ _j y _ 28 29 31 32 N AC o O PL NT Mb HoVRs SUS iTT Pom US. L MA FAC RER IZi@ 101010101 li;_l@ I ' 'J@l Z i@ 3sIZi@ 34 26 3> ao Lu.J@ di IJ_J@ 42 A3 IZl919191@ m 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l Ths maximum dose to an individual consuming seafood with these concentrations for a I i l full year would be only 4.4 x 10-3 mrem to the total body (child) and 3.5 x 10-2 mremI l to the most restrictive organ (adult G1-LL1). Therefore, it is concluded that there l 3 l is no risk to the health and safety of the public. 1 l l
*'T!sY A sPowER oTwER STATUS @ ciEoNEY oisCovERY oEscMirTioN @
(H,,,J@ l 0 l 0 l 0 l@l N.A. l [D_,j@l Notification by Environmental Lab. l alTiviTY co'0 TENT FELEasto o8 RELEASE AMOUNT o# ACTIVITY LOCATION op RELEASE 6 lZl@ ' gj N.A l l N.A. l
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RfD ~1R:.43 e .. , P.vmoch. M AEE A:e .;;t** *"5C1 April 28, 1980 Director, Region I . Office of Inspection and Enforcement I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Licensee Event Report 80-014/04T-0 Docket Number 50-293 . License DPR-35 Centlemen: The attached Licensee Event Report 80-014/04T-0, "Anomolous Measurement I Report",'is hereby submitted in accordance with the requirements of Pilgrim
- Nuclear Power Station Technical Specification 6.9.C.2.b.
If there are any questions on this subject, please contact us. I Respectfully submitted, I P. J. Mc ire Station Manager l Nuclear Operations MIM:ep Enc 2csures: (3 copies) LER 80-014/04T-0 l cc: Director (40 copies) Office of Management Informatios and Program Control U. S. Nuclear Regulatory Cor::nission Washington, D.C. 20555 bec: Messrs. G. C. Andognini R. Sevigny E. L. Cobb W. M. Sides P. A. Foulsham (2) P. D. Smith M. G. Hensch D. G. Stoodley J. E. Howard G. G. Whitney l I C. J. Mathis M. T. McLoughlin J. W. Nicholson Ms. K. Calderone NOD Licensing PNPS Records Center E W. F. Olsen P.J.M.(LB) g J. A. Seery lI l . I . .
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CONT RO' . B LOCA- l l l l l l LICENSEE EVENT REPORT lh (PLE ASE PalN1 o3 7YPE ALL REOUIRED INFORMAllOui bbl@ lLICENSE 0 l 0 NuuBEh l 0 l 0 l - l 0 l 02hl@l264 l 11 I l 1 l 1 l@lb) LA1 l f p l MI LsCENLEE Al Pl Pl CODE Sl 1l@l 14 16 0 l 0 l -l LsCEN5E typt Ju o E',,] @ ]O l5 l0 l -l 0l 2l 9 l 3 @l680 l 594 l 1EVENT l 818101@l DATg 74 076l 4 lREPORT 2l 8oATE l 8 l 0tol@ 8 60 St DOCILET NUMagR I! VENT DESCRIPTION AND PROBABLE CONSEQUENCES h l On April 18, 1980, Boston Edison Company received information from the Yankee l o is] l Atomic Environmental Laboratory that indicated that a sample of milk collected from l l an indicator station (Plimouth Plantation - 2.2 miles vest of the plant) contained I c, 3; ; a concentration of Cs-137 of 24.7 pCi/ kilogram. This concentration was ten (10) l e l times the measured control station concentration of 2.45 pCi/kg (Whitman Farm - 21 l 7 l miles NW). 1 0 E l l 80 i g g C E CO E 5 eC E COMPONENT CCDE Sue Odt 5 E c -
'lI l xlO Lx]@ L 2l@
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Mr. M. Thomas McLoughlin ,, ,ggy, m-%N [,
O BOST05 EDISON CO:PANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Attachment to LER 80-014/047-0 On April 18, 1980, Boston Edison Company received information from ' Yankee Atomic Environmental Laboratory that indicated that a Sample of milk collected I f rom an indicator station contained a concentration which was ten (10) times the measured control station concentration. It is very unlikely that this measurement is the result of plant effluents since the measured releases for the prior six months would have resulted in a calculated concentration of Cs-137 in milk that would be 5 orders of magnitude lower than the measured concentration (using the models presented in Regulatory Guide 1.109). The calculated dose due to consumption of milk containing the measured concentra-tion for a full year would be 5.0 millirem to the most restrictive organ. (inf ant-liver) and 0.55 millirem to the total body (adult) . I I I I I I I I I .. . .
E0'.%C D . *, o-t F"_:= .i Nu:. can P=wcq E A :., wr:s+1m::<v ..s:4=
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June 25, 1980 BEco Ltr #80-113 Director, Region I Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission I 631 Park Avenue King of Prussia, PA 19406 I Licensee Event Report 80-021/04T-0 Gentlemen: Docket Number 50-293 _ License DPR-35 The attached Licensee Event Repcrt 80-021/04T-0, "Anomolous Measurement Report", is hereby submitted in accordance with the requireannts of Pilgrim Nuclear Power Station Technical Specification 6.9.C.2.b. I If there are any questions on this subjact, please contact us. I Raspectfully submitted, P. McGuire Sta on Manager Nuclear Operations I MDi:ep Enclorures: (3 copies) LER 80-021/04T-0 cc: Director (40 copies) Office of Management information and Program Control . g U. S. Nuclear Regulatory Commission Washington, D.C. 20555 E bec: Messrs. G. C. Andognini R. Sevigny E. L. Cobb W. M. Sides i I P. A. Foulsham (2) M. G. Hensch P. D. Smith D. G. Stoodley J. E. Howard G. G. Whitney I C. J. Mathis M. T. McLoughlin J. W. Nicholson
-Ms. K. Calderone
- NOD Licensing PNPS Records Center lg W. F. Esen '
P.J.M. (LB) 3 J. A. Seery I
LICENSEE EVENT REPORT
~
CONTROL BLOCK: l l l l l l (PLEASE PRINT OR TYPE ALL RECUIRED INFCRMATION)
}l9 MI AlUCENSEE P I PCODE l S l 1 lg 0 l 0 l - l 010 i4 18 UCENSEl NUMBER 0 l 0 l 0 l- l 0-l 026l@lUCENSE 2S 4 l 1TYPE l 1JOl 1 $7 l
l 1CATl@l lg 68 l s" u% [L_j@l 0l 5 l 0 l - 10 l 2 l 9 ! 3 l@l 015 l 0 l 8 l 8 l 074 l@l0 l 612 l 5 l 8 l 0 l@ GO St DOCKET NUMBER 88 89 EVENT oATE 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I on 6/16/80 PNPS received an analyses report from the Tankee Environmental Laboratory l l that indicated than an algae sample collected on 5/8/80 contained a reportable l l concentration of Co-60. l
, c, , l REFER TO ATTACHMENT FOR FURTHER INFORMATION. l 1 I l
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,,ny , , 617-746-7900
BOSTON EDISON COMPANT PILGRIM NUCLEAR POWER STATION DOCKET No. 50-293 Attachment to LER 80-021/04T-0 on 6/16/80 Boston Edison received an analyses report from the Tankee Atomic I Electric Laboratory which indicated that a reportable concentration of Co-60 (262 i 8.7 p01/kg) existed in an Irish Moss sample taken from the Pilgrim Station discharge canal outfall area on 5/8/80. l This concentration is in excess of 10 times the measured concentration at the control station in E111sv111e (11.7 + 2.7 pCi/kg) . Due to process 1 rig and market dilution it is extremely unliksly that any indi-vidual would consume sny material with the measured concentration of Co-60. However, even if a person were to directly consume this algae at seafood I consumption rates given in Regulatory Guide 1.109, the annual dose to that person would be about 0.01 arem to the total body and 0.05 arem to the marimum exposed organ (GI-LLI). As a result of these extremely small calculated doses .(as compared to the natural background dose rate of about 100 arem/yr) we have concluded that (' there is no risk to public health and safety. I I I I l l I l
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I , <. '.i sos'*" Edison a-'
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PILGRIM NUCLEAR POWER STA~iCN RFD *1 Rocacy HILL RcAo PLvMouTM. MassAcMusETTs C2360 July 30,1980 BEco Ltr. #80-158 Director, Region I Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission I 631 Park Avenue King of Prussia, PA 19406 Licensee Event Report 80-031/04T-0 I - Docket Number 50-293
' License ~DPR-35 Gentlemen:
The attached Licensee Event Report 80-031/04T-0, "Anomolous Measurement", is hereby submitted in accordance with the requirements of Pilgrim Nuclear Power Station Technical Specification 6.9.C.2.b. If there are any questions on this subject, please contact us. Respectfully submitted, jffeevN ->' - P. McGuire I MDi:ep Station Manager Nuclear Operations
Enclosures:
(3 copies) I LER 80-031/04T-0 cc: Director (40 copies) Office of Management Information and Program Control I U. S. Nuclear Regulatory Commission Washington, D.C. 20555 I bec: Messrs. G. C. Andognini E. L. Cobb P. A. Foulsham (2) R. Sevigny W. M. Sides P. D. Smith P. F. Giardiello D. G. Stoodley M. G. Hensch . G. Whitney J. E. Howard . K. Calderone C. J. Mathis NOD Licensing l , M. T. McLoughlin PNPS Rectrds Center l = J. W. Nicholson P.J.M. (LB) W. 7. Olsen J. A. Seery I .
- , - - _ -r---. -
JRC FORM 366 U.S. NUCLEA'1 AEGULAToRY COMMISSION LICENSEE EVENT REPORT NO 80' f - yJ, (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATitN) CONTROL BLOCK: l l l l l 1 lh
'9 l MI LICENSEEAl Pl CODE Pl Sl 1l@l O l 0 l -l 0 14 15 l 0 NUMBER LICENSE l O l 0 l 0 l - l 010 l@264l1l1l1l1l@l 2S LICENSE TYPE Jo l
57 CAT 58 l@ s$"c, IL @l 0l 5 l 0 l - l 0 l 2 l 9 I 3 @l 0 l 7 l 2 l 1 l 8 l 0 74l@l 750 l 7REPORT I 3 l DATE 0 l 8 l 080 l@ l 8 60 61 DOCKET NUMBER e8 69 EVENT DATE l EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l On July 21, 1980 Boston Edison received an analyses report from the Yankee Atomic l o a l Electric Laboratory which indicated that a reportable concentration of Co-60 l o l (48.3 t 1.4 pCi/kg) existed in a mussel sample taken from the Pilgrim Station l f 1 o I discharge canal outfall area on 4/8/80. This concentration is in excess of 10 times l o the lower limit of detection at the control station in Marshfield (4.7 pCi/kg) . l l l This insignificant concentration represents no risk to the public health and l o1s 1 I safety. l
$$o'Ec" "#$E C0 susci$E COMPONENT COOE .SUB O'E S ODE o 9 8
1 xl xl@ l xl@ l z l@ Iz Iz lz Iz Iz 12 l@ l zi@ l zl@ 9 10 11 12 13 18 19 20 SEQUENTIAL OCCUR R E NCE REPORT REVISION _ EVENT YEAR R EPORT NO, CODE TYPE NO. ,
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XN 34 lzl@ 35 l36z l@ l0 l0l0l0 l 37 40 lN l@ el IN 42 l@ l43 zl@ lz l 9] 9l 9l@ 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l The presence of Co-60 in this discharge samole is due to coeration of the Pilerim l l Station. However, even if a person ware 1o directly consume mussels at the rate l l given in Regulatory Guide 1.109, thE annual dose to that person would only be l l l about 1.3 x 10-3 mrem to the total Et dv cnd 9.7 x 10-3 mrem to the maximum exposed I i i 14 i l organ (GE-LLI). ] a0
- 7 s 9 '
'si"2N"is sPowtR OTwERsTATus @$iEONY DISCOVERY DESCRIPTION @
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RTD # *R~:f H i . 4 0 /. ; mv. m. ut m.: .:,;s c--- O t s ; :. August 26, 1980 BEco Ltr. #80-199 Director, Region I I Office of Inspection and Enfonement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Docket Number 50-293 License DPR-35 Gentlemen: The attached Licensee Event Report 80-042/04T-0,"Anomolous Measurement", is hereby submitted in accordance with the requirements of Pilgrim Nuclear Power Station Technical Specification 6.9.C.2.b. If there are any questions on this subject, please contact us.
- Respectfully submitted, AM P.J. McGu re Station Manager Nuclear Operations i
i
Enclosures:
(3 copies) LER 80-042/04T-0 i I cc: Director (40 copies) Office of Management Information and Frogram Control U. S. Nuclear Regulatory Commission l Washington, D.C. 20555 bec: Messrs. , R. Sevigny E.L. Cobb W.M. Sides P.A. Foulsham (2) P.F. Giardiello P.D. Smith D.G. Stoodley { ] {} M.G. Hensch G.G. Whitney J.E. Howard Ms. K. Calderene G80 SEP 2 C.J. Mathis NOD Licensing M.T. McLoughlin PNPS Records Center J.W. Nicholson P.J.M. (LB) Nuclear Operations W.F. Olsen NRC (on-site) J.A. Seery
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NRC FORM 366 v. s. rwucLean ncuuLA:un y cummissium 3 7) g LICENSEE EVENT REPORT CONTROL BLOCK: l l I I l l lh (PLEASE PRINT OR TYPE ALL RECUlRED INFtRMATION) 8 9 lMIAlPlPl I1l@15l0l0l21010l0 IOlOl IolOl@l 4l1l111l11@l 14 LICENSE NUMBER 25 26 LICENSE TYPE J0 l 57 CAT 58 l@ J 7 LICENSEE CODE 3o
,] l L @l 0 ] 510 l- 101219 I 368 @l69 018121018 l O hl 018REPORT 74 75 l 2161810 DATE 80 l@
8 60 61 DOCKET NUM8ER EVENT DATE EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l On August 20, 1980, Boston Edison Company received an analyses report from the Yankee l
;o ;3; l Atomic Electric Laboratory which indicated that a repn. table concentration of Co-60 l
[ (102.4+2.7 pCi/kg) existed in a mussel sample taken from the Pilgrim Station discharge l
- 3 ; canal outfall area on July 14, 1980. This concentration is in excess of 10 times the l iu a [ lower limit of detection at the control station in Marshfield (5.9 pCi/kg). l l l I
10181l 80 B 9 0 E ODE SU8C E COMPONENT CODE SUS COE $ E 7 8 l x ix l@ l xl@ l a l@ la la la I al al al@ la l@ l al@ 9 10 11 12 13 18 19 20 I SEQUENTIAL OCCURRENCE REPORT R EVISION LER
,_ EVENT YEAR REPORT NO. CODE TYPE NO.
@ sg/RO a 18 10 I l-l 10 la 12 I I/I I n i 4_ I L7J I-I LoJ
_ 21 22 23 24 26 27 N .7 30 31 32 K N AC ON ON PL NT ME HOURS S8 i FOR 8. SUPPL MANUFAC RER Ial@lal@ l3l@ 33 34 25 lal@ 36 10101010i 31 40 Lnj@ 41 lNlh Ialh IaI9l9l9lh 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l The presence of Co-60 in this dischnvre ennal =n-,la 4= Aa en nna*n*4nn ns -ka l ii i l Pilgrim Station. However, even if a person were to directiv consume mussels a* I i
,. 2 1 the rate given in Regulatory Guide 1.109, the annual dose to that person would only l l be about 2.8x10-3 mrem to the total body and 2.1x10-2 mrem to the maximum exposed I gii,; l organ (GE-LLI). I 8 9 80 AN % POWER OTHER STATUS 15 RY DISCOVERY DESCRIPTION I . IslIEl@ liIOIOl@l NA I Laj@lunru4 cne4 nn x,,v n ,,4nn,- men, tnw I A[TIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION oF RELEASE e NA I ! M I 7 8 9 Ia I @ LsJ 10
@l 11 44 45 80 PERSONNEL EXPOSURES E NUMBER TYPE DESCRIPTION ni I p' i Ol O l 01@l a l@l
,v$0~~ Ehu'I iES l
NuM8ER DESCRiPTiO~@ na i [ pa 10101 8 9 Ol@l 11 12 80 l LOSS OF OR DAMAGE TO FACILITY TY*E DESCRIPTION 9 8 9 l3l@l to NA 80 PU8LICITV NRC USE ONLY [N_j l ISSUED @ DESCRIPTION NA l lllIIlIIIlI!!I 8 9 10 68 69 80 3 NAME OF PaEPARER Mr. M. Thomas McLoughlin PHONE: 617-746-7900 {
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ECS10N Ed"ison ca..... PILGRIM NUCLEAR POWER SrATICN RfD **1 Rocsty HILL RoAo PLvuouTH. Mass ACMuscTTs 02360 December 19, 1980 ! ! R. D. Macwom BECo Ltr. #80-313 1 Director, Region I Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Licensee Event Report 80-090/04T-0 Docket Number 50-293 License DPR-35 Gentlemen: The attached Licensee Event Report 80-090/04T-0, entitled "Anomolous Measure-I ments", is hereby submitted in accordance with the requirements of Pilgri= Nuclear Power Station Technical Specification 6.9.C.2.b. If there are any questions on this subject, please contact us. Respectfully submitted, RA M I R. D. M chon Nuclear Operations Manager Pilgrim Station I MIM:ep
Enclosures:
(3 copies) LER 80-090/04T-0 cc: Director (40 copies) Office of Management Infor=ation and Program Control U. S. Nuclear Regulatn y Cor=:ission Washington, D.C. 20555 bec: Messrs. J. E. Howard K. P. Roberts W. J. Ar= strong J. A. Seery I H. F. Brannan E. L. Cobb P. A. Foulsham(2) P. A. G. D. R. G. S=ith Trudeau Whitney P. F. Giardiello Ms. K. Calderone M. T. McLoughlin NOD Licensing (] C. J. Mathis PNPS Records Center A. V. Morisi PRC Resident Inspector I J. W. W. F. Nicholson Olsen m E. J. Ziemianski
LICENSEE EVENT REPORT C:'NTROL BLOCK: l 1 I I I I Ih (Pt. EASE PRINT OR TYPE ALL REQUIRED INFORMATioN) Ta 9
.M IA IPlPlSI1l@l010l UCENSEE CODE 14 5 l010l0IOIO!
uCENSE NUMBER 1010l@l4l1lIIil1l@l 25 26 uCENSE Ty*E JC l 57 GAT 58 l@
. _ , 'ju',"J l L l@l 01 S t o l - l o l 219131@l 68 69 112 ! I l s i 81074 l@l EVENT QATE 11211 ! 9181080 l@
75 . REPOR* c) ATE 3 60 61 DOCKET NUMG ER EVENT DESCRIPTICN AND PROBABLE CONSEQUENCES h
- l On Decenber 10, 1980. Boston Edison Co. received an analysts reoort from the Yankee l
.Tl Ato=1c Electric Laboratory which iM2.cated that a reportable concentration of Co-60
- l (73.7- .6 pC1/kg) existed in a mussel sa=ple taken fro = the P11gri= Station discharge
; canal outfall area on October 1, 1980. This concentration is in excess of 10 ti=es yl :he lower li=1e of detection at the control station in Marshfield (4.5 pCi/kg) .
I 3"' I
' li Sv5 TEM COCE CAUSE 000E CAUSE SUSCOOE COMPONENT COCE COMP.
SugOODE VALVE SU5000E a
-l l x i x i@ l x i@ 12 l@ l zl 21 21 zl 21 zl@ l 21@ l zi @
9 10 11 12 12 is 19 20
,,,, SECUENTI AL OCCURRENCE REPCRT REVl5 ION g so EVENTvt4R R EPORT NO. CODE TYPE No.
@ 'a(rmaTu"55' l-l 10 I 91 of l/l 10141 i Tl 1-1 1 01
_18 10 21 2: I :2 24 a 22 2s A*TACHMENT
- s NP R D-4 sa
- RIME COMe.
si 22 COM*CNEN? 8U'vef EF8ECT SMUTDowN I AC*!ON TAKEN ACT'ON CN 8LANT MET *CQ wouR5 l 01 01 01
$U8viTTic 8CR M a t. SUP*u ts M4NU8AC UnEA l 21 91 91 E 1
12 !@lz
- 24 l@ lz!@
- s la 21@ 3_, ao I
INl@ ai l42NI@ Iz l@ 42 u 4 CAUSE DESCRtpTION AND CORRECr1VE AC 10NS h 'gi The cresence of Co-60 in this dischar2e cinni sa-le is due to crer*-icn ?? t'e i Pilzrim Station. :owever, even if a eersen were re M ractiv - e - e -- ~==a'e =* -ke ml ra:e given in Regulato y Guide 1.109, the annual dose to that person would only be l& ! -3 10-
; acou: 2.0x10 mres :o :ne :=tal body (child) and 1.5x =re= :o the =axi=um --, ; excosed organ (adult, GE-LLI).
s AC:Lt*v METWCD C8 l 5 A US secwEa oTwEn57ATUS eis::vEnv ciscovEnv eE5:RiF' TON N.A. f"Il l E l@ l1 10 10 *2l@l ,1 44 l lD 45 l@l46Environmental Lab Notification 3'
- 3 to I
CTtvi'v OONTENT AMOUNT OF ACTIVITY 36 LoCAT1oN QF mELgA3E ELE /.5EC :P mELEASE N.A. I I N.A. e i I z l @ tCl zl@l 3 11 44 45 3
#ER$CNNEL EXPOSURES NUMBER TveE DESOAIP'tcN -
N.A. ia.101010l@lz!@{ l 9 1, stm5CNNEL <NJU AIES u : a Nuv8Em O E 50 RIP'10N 2 8lo!0101@l 9 11 12 s.A. _ s La55 OF CA D AM AGE TO 8A03U*v .
*v*E DESC*irTION l2 l N.A.
I 4 3 to NS U Ctw 4 NRC USE ONLV v55p,E m DE5025*TICN N.A. l l 1ll l ll !Iil fi 68 69 3 e 9 to 4?* **4.* con
I 'I Accendix B - Radioactive Effluents f I , !I I
- I I
I l I I 1E lI !I 1 B-1
.I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Inforrnstion January - June, 1980 Facilitv Pilgrun Nuclear Power Station Ucensee DPR 35
- 1. Reguistacy Umits I a. F:ssam and activatam gases s , 4 0.25/E W ,-
0.10/E g
- h. lodmes- 2 Ci/ Quarter I c.
d. Particulates. half-hves>N davs 13(1.8E4Qs + 1.8E5Qv) e 1 bquid efnuents: 10 C1/ Quarter
- 1. Masimum Permissible Concentration Piovide the MPCs used m determinmg allowable release rates or cimcentration>.
- a. Fissnin and activation gases: 10 CFR 20
- h. lodmes: Appendis B
- c. Partsculates, half-isves >K days: Table !!
- d. Uquid ef0uents H .'3 = 1 X 101 mci /mt; all rest.10 CFR 20. Appendix B. Table !!
- 3. Average Energy Provide tie average energy (El of the radamuciale mniure m releases of 6ssam and activauon gases. il appheableJ 1st Quarter, MS = 1.028 & RBV = 0.293: 2nd Quarter, MS = 0.660 & RBV = 0.622
- 4. Measurements and Approsimations of Total Radioactivity I Provide the methods used to measure or approsmiate the total radioxtivity m ef0uents and the nwthmis used to determme radumuchde composinon.
- a. F:ssam and activation gases: c,ti
- b. lodmes- g, ,
- c. Particulat es:
Uquid ef0uents: ^^*IYSI' d.
$. Batch Releases Provide tie followmg information relatmg to batch releases ot radmiactive maienals m hquid and gaseous ef0uent>.
- a. Uquid I. Number of batch releases- 228
- 2. Total time penod for hatch releaus- 263.50 hrs.
- 3. Maximum tinn gnod for a batch relea<e. - 8.92 hrs .
- 4. Average time pe mid for batch releases: 1.16 hr.
Mmimum time penod fm a hatch release: - O. 25 hr. I 5.
- 6. Averace stream now dunns penods of release of ef0ueni mio a nommg stream: 1.SIE + 5 G N
- b. Gaseous (Not Applicable)
- 6. Abnormal Releases I
a.
- b. None I
I I 1 I
i I I I I i TABLE 1A > EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980) GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASES January - June, 1980 Quarter Quarter Est. Total Unit i 2 Error. % I A. Fission and activation gases Ci 2.69E+2 4.13E+2 3.00E+1 l
- 1. Total release
- 2. Average release rate for period uCi/sec 3.42E+1 5.25E+1
- 3. Percent of Technical Specification limit % 1.39E-2 1.73E-2 B. Iodines '
Ci 4 4.12E-3 3.21E-3 2.50E+1 l
- 1. Totallodine.131
- 2. Average release rate for period yCi/sec 4 5.24E-4 4.08E-4
- 3. Percent of Technical Specification limit % 2.06E-1 1.61E-1 C. Particulates
- 1. Particulates with half. lives > 8 days Ci 4 3.23E-3 4.79E-3 3.00E+1 l
- 2. Average release rate for period gCi/sec 44.11E-4 6.09E-4
- 3. Percent of Technical Specification limit % 8.77E-2 2.63E-2
- 4. Gross alpha radioactivity Ci 4 7.00E-7 3.90E-7 I D. Tritium
- 1. Total release Ci 3.65E0 6.75E0 3.00E+1 l gCi/sec 4.64E-1 8.59E-1 I 2. Average release rate for period
- 3. Percent of Technical Specification limit %
I I I I
- I lg
! _3
TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ( .1980) GASEOUS EFFLUENTS - ELEVATED RELEASE January - June, 1980 CONTINUOUS MODE BATCH MODE Unit Quarter Quarter l Quarter l Quarter l l Nuclides Released l l l
- 1. Fission gases krypton-85 Ci 6.35E-4 2.72E-3 l
krypton-85m Ci 5.70E+1 6.95E+1 l krypton-87 Ci 2.95E+1 2.62E+1 Ci 1.IlE+2 1.00E+2 krypton-88 xenon-133 Ci 5.41E+1 5.55E+1 xenon 135 Ci 1,54E0 1.20E+1 xenon-135m Ci 1.20E-1 4.55EO I xenon 138 zenon-131m Ci Ci 3.41EO 7.14E+1 renon 137 Ci xenon-133m Ci Total for period Ci 2.57E+2 3.39E+2
- 2. Iodines iodine-131 Ci '
4.5.26E-4 2.73E-3 l iodine-133 Ci 41.38E-5 2.42E-2 Ci 2.83E-2 I iodine-135 Total for period Ci 45.40E-4 5.52E-2
- 3. Particulates i strontium-89 '
Ci 3.62E-5 8.16E-4 strontium-90 Ci 5.50E-6 9.71E-6 cesium-l'4 Ci 4.54E-7 I cesium-137 Ci 2.16E-5 1.94E-5 I barium lanthanum 140 chromium 51 Ci Ci 1.98E-4 3.25E-3 3.82E-6 1.08E-5 I manganese-54 cobalt-58 iron-59 Ci Ci Ci cobalt-60 Ci 4.23E-5 4.07E-5 zine-65 Ci zirconium-niobium 95 Ci cerium-141 Ci cerium 144 Ci 3.42E-5 ruthenium 103 Ci g Ci 1.61E-4 W ruthenium-106
1 l I I l TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT (1980) GASEOUS EFFLUENTS - GROUND LEVEL RELEASE I January - June, 1980 CONTINUOUS MODE BATCH MODE Quarter Quarter Quarter Quarter Nuclides Reneesed Unit
- 1. Fission gases krypton-85 Ci 4 3.87E-8 t4.65E-8 .
l krypton-85m Ci 9.10E-2 1.10E-1 I krypton-87 krypton-88 Ci Ci 1.52E-1 2.83E-1 1.26E0 4.62E0 3.04E-1 8.11E0 I xenon-133 xenon.135 xenon-135m Ci Ci Ci 1.11E+1 6'.02E+1 zenon-138 Ci Total for period Ci 1.19E+1 7.43E+1 i
- 2. Iodines iodine-131 Ci t 3.59E-3 1 4.76E-4 Ci 2.99E-3 3.05E-3 I iodine-133 iodine-135 Total for period Ci Ci 4.61E-3 41.12E-2 3.53E-3
- 3. Particulates strontium-89 Ci 7.00E-5 6.02E-5 strontium 90 Ci 6.21E-7 1.02E-6 Ci 5.70E-6 8.82E-6 cesium 134 cesium 137 Ci 6.75E-5 4.93E-5 I barium-lanthanum-140 manganese-54 Ci Ci 42.35E-3 2,92E-5 1.99E4 1.10E-5 2.39E-6 I cobalt-58 Ci iron-59 Ci Ci 3.73E-4 1.17E-4 cobalt-60 Ci 4.68E-6 zine-65 zirconium-niobium-95 Ci cerium 141 Ci 1.74E-5 l ruthenium-103 Ci ruthenium-106 Ci I
I 5 -
1 I TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980) I LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I January - June, 1980 l I Quarter Est. Total Quarter Unit 1 2 Error, % A. Fission and activation products
- 1. Total release (not includmg mtium, Ci noble gases, or alpha) 8.77E-1 5.65E-1 3.00E+1
- 2. Average diluted concentration pCi/ml 1.07E-7 2.17E-7 during period
- 3. Percent of applicsble limit % 8.77E0 5.65EO B. Tritium
- 1. Total release Ci 2.59E+1 9.13E0 3.00E+1
- 2. Average diluted concentration yCi/mi I during period
- 3. Percent of applicable limit %
3.15E-6 3.15E+1 3.51E-6 3.51E+1 C. Dissolved and entrained gases
- 1. Total release Ci 4.53E-3 1.51E-3 4.00E+1 l
- 2. Average diluted concentration gCi/ml 5.54E-10 5.81E-10 during period
- 3. Percent of applicable limit %
D. Gross alpha radioactivity I l 1. Total release E. Volume of waste released (prior l Ci liters l41. 94E-4 l49.17E-5 l 4.00E+1 l 2.59E+6 1.78E+6 2.00E+1 to dilution) F. Volume of dilution water used liters
. .60 M 2.00E+1 during period I
I I
I I I TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980) LIQUID EFFLUENTS January - June, 1980 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter strontium-89 Ci 1.84E-3 5.62E 4 .. strontium 90 Ci 5.26E-4 5.31E-4 I cesium-134 cesium-137 Ci Ci 6.46E-3 3.34E-2 2.81E-2 9.17E-2 iodine-131 Ci 1.07E-4 7.92E-5 cobalt-58 Ci 7.51E-3 5.14E-3 3.36E-1 1.57E-1 I cobalt-60 Ci iron-59 Ci 4.31E-3 zine-65 Ci 2.20E-3 1.01E-3 manganese-54 Ci 3.41E-2 1.39E-2 chromium 51 Ci 1.61E-2 zirconimum-niobium-95 Ci 8. 81E- 4 1.78E-5 molybdenum 99-technetium 99m C 2.08E-3 l barium lanthanum 140 Ci 6.36E-3 cerium-141 Ci 4.52E-3 l l5 iodine-133 ' Ci 2.35E-4 l 4.77E-5 cerium 144 Ci 5.62E-4 ) 1.35E-4 silver 110m Ci iron 55 Ci 2.12E-1 1 1.87E-1 l unidentified l Ci l l l 2.08E-1 l 7.95E-2 l Total for period (above) Ci 8.77E-1 5.65E-1 xenon-133 Ci 8.85E-4 3.97E-4 xenon-135 Ci 3.66E-3 1.11Ee3
I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information July - December, 1980 Facility Pilgrim Nuclear Power Station Ucenze DPR 35 I 1. Regulatory Umits
- a. Fission and naivation gases:
Os 0.25/[ Ov 0.10/[ i I I h. c. d. lodmes 2 Ci/ Quarter Particulaies. half-hves >h days 13 (1.8E4Qs + 1.8E5Qv) bquid efnuents: 10 Ci/ Quarter il I
- 2. Masimum Permissible Concentration Psovide the MPCs used in determining allowable release rates or concentrations.
- a. Fission and activatism gases: 10 CTR 20
- h. lodmes: Appendia B
- c. Particulates. half-lives >x days: Tsble 11
- d. bquid ef0uents: H - 3 = 1 X 101 MC1/ml,all eest,10 CFR 20, Appendix B. Table H
- 3. Average Energy
- Provide 3rd Quarter, the average M = 0.631 ene'dy (Fi oi ihe
&RBV radamuchde
= 0.484; mniure MS 4th Quarter, in release,
= 0.507or&fissum RBV and aciivation gas
= 0.283
- 4. Measurernents and Appresimations of Total Radioactivity Provide the methods used io measure or appmsimate the total radioactivity in ef0uents and the methods used to determme radionuchde composition.
- a. Fissum and activation gases- g I h.
c. d. lodmes: Particulaies: bquid ef0uents: 1stopie Analysis 5. I Batch Releases Pmvide Ihe following informanon relating to batch releases of radioactive matenals in hquid and gaseous efnuents.
- a. Uquid I. Number of batch releases: 84
- 2. Total tune penod for hatch releases.109.82 hrs.
- 3. Maximum time permd for a baich release: - 10.33 hrs.
I 4. 5. 6. Average isme perm >d for batch releases 1.31 hrs. M nimum nme penod for a haich release: - 0.33 hrs. Average stream now dunng penods of release of ef0uent mio a nowing stream: 2.97E+5GPM
- b. Gaseous (Not Applicable)
- 6. Abnormal Releases
[ None lI I
-2 1
I
I I I TABLE 1 A I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES July - December, 1980 Quarter Quwter Est. ' otal Unit 3 4 Err,r, % I A. Fission and activation gases
- 1. Total release Ci 1.02E+4 1.53E+4 2.50F+1 l
- 2. Average release rate for period pCi/sec 1.28E+3 1.92E+3
- 3. Percent of Technical Specification limit % 3.26E-1 3.91E-1 B. Iodines
- 1. Totaliodine-131 Ci 2.19E-2 6.27E-2 2.50E+1 l
- 2. Average release rate for period uCi/sec 2.76E-3 7.89E-3
- 3. Percent of Technical Specification limit % 1.10E0 3.14E0 I C. Particulates
- 1. Particulates with half. lives > 8 days Ci 5.91E-3 5.75E-3 3.00E+1 l I 2. Average release rate for period
- 3. Percent of Technical Specification limit
- 4. Gross alpha radioactivity gCi/sec Ci 7.43E-4 7.89E-2
<4.19E-7 7.23E-4 1.18E-1
< 5.92E-1 D. Tritium
- 1. Total release ci 1.40E+1 1.94E+1 3.25E+1 l
- 2. Average release rate for period gCi/see 1,76E0 2.43E0
, 3. Percent of Technical Specification limit % N/A N/A I . I I I
TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (.1980 ) GASEOUS EFFLUENTS - ELEVATED RELEASE I July - December, 1980 ~ I - CONTINUOUS MODE BATCH MODE l Nuclides Released l Unit l Quarter l Quarter l Quarter l Quarter l
- 1. Fission gases krypton-85 Ci 3.37E-2 2.74E-2 krypton-85m Ci 1.85E+3 2.55F+3 krypton-87 Ci 4:86E+? 8.29E+2 I krypton-88 xenon-133 xenon 135 Ci Ci Ci 2.29E+3 5.24E+3 1.33E+2 3.21E+3 7.77E+3 5.33E+2 i
I xenon-135m zenon-138 Ci Ci
<8.00E0
< 1 : 85E+1
< 6.43E0
<1.49E+1 zenon-131m Ci zenon-137 Ci
, xenon-133m Ci 5.87E+1 1.66E+2 Total for period Ci 1.01E+4 1.51E+4 2 Iodines I iodine-131 iodine-133 Ci Ci 1.57E-2 3.ggg_2 4.41F ? 4 n7F 7 I iodine-135 Total for period Ci Ci 4.00E-2
- 9. 56E -2 4.61E-2 1.31E-1
- 3. Particulates strontium-89 Ci 6.98E-4 4.67E-4 strontium-90 Ci 8.21E-6 6.05E-6 cesium-134 Ci cesium-137 Ci 2.01E-5 2.80E-5 lI barium lanthanum-140 Ci 2.47E-3 1.35E-3 l chromium-51 Ci 3.96E-5 manganese-54 Ci 6.84E-5 1.84E-5 cobalt-58 Ci 5.59E-5 3.71E-6 iron-59 Ci 4.90E-5 3.24E-6 cobalt-60 Ci 1.47p_4 g_ gar _g zine-65 Ci zirconium-niobium-95 Ci 2.23E-6 i
cerium-141 Ci .. cerium-144 Ci 1.92E-5 , I ruthenium-103 ruthenium 106 Ci Ci 3,ogp_g I I TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980) GASEOUS EFFLUENTS- GROUND LEVEL RELEASE July - December, 1980 I CONTINUOUS MODE BATCH MODE Nuclides Rolessed Unit Quarter l Quarter l Qu e Quarter
- 1. Fission gases krypton-85 Ci < p n7c 7 < 5. 59E-6 I krypton-85m krypton-87 krypton-88 Ci Ci Ci
< 2.06EO
<4.26EO
< 1. 68F+1
< 3.72E0
<7.83E0 <5.79E0 zenon 133 Ci 9.64i-0 7 R3F+1 zenon 135 Ci 6.33E+1 1.13E+2 xenon-135m Ci xenon-138 Ci Total for period Ci < 8.71E+1 < 1. 68E+2
- 2. Iodines iodine-131 Ci 6.21E-3 1.86E-2 iodine-133 Ci 2.52E-2 2.86E-2 ,
iodine-135 Ci 2.88E-2 3.77E-2 Total for period Ci I 6.02E-2 8.49E-2 I 3. Particulates strontium-89 Ci 3.46E 4 1.26E-3 strontium-90 Ci 1.44E-6 4.36E-6 cesium-134 Ci 3.08E-6 1.90E-6 I 2.66F cesium-137 Ci 3.72E-5 barium-lanthanum-140 Ci 1.41E-3 2.27E-3 manganese-54 Ci 2.31E-5 2.87E-5 I cobalt-58 iron-59 Ci Ci l 1.71E 4 l 3.49E-6 cobalt-60 Ci l 2.29E 4 1.09E 4
-ame % Chromium-51 Ci j 8.60E-5 5.29E-5 zirconium-niobium-95 Ci l 3.23E-6 cerium-141 Ci l 1.27E-5 3.64E-5 ruthenium-103 Ci l ruthenium 106 Ci l I
I I TABLE 2A I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980) LIQUID EFFLUENTS SUMMATION OF ALL RELEASES July - December, 1980 Quarter Quarter Est. Total Unit 3 4 Error, % I A. Fission and activation products
- 1. Total release (not including tritium, Ci noble gases, or alpha) 8.11E-1 4.78E-1 3.00E+1
- 2. Average diluted concentration 'gCi/ml during period 1.53E-7 2.25E-7
- 3. Percent of applicable limit % 8.11E0 4.78E0 B. Tritium
- 1. Total release Ci 3.81E0 1.12E0 3.00E+1
- 2. Average dilutM concentration yCi/ml during period 7.20E-7 5.28E-7 I 3. Percent of applicable limit C. Dissolved and entrained gases
% 7.20E0 5.28E0
- 1. Total release Ci 4.98E-4 4.00E+1 l I 2. Average diluted concentration during period gCi/ml 9.41E-11
- 3. Percent of applicable limit %
I l D. Gross alpha radioactivity
- 1. Total release l Ci k 5.64E-5 l<1.85E-5 l 4.00E+1 l E. Volume of waste released (prior liters to dilution) 6.80E+5 2.69E+5 2.00E+1 I F. Volume of dilution water used during period liters 5.29E+9 2.12E+9 2.00E+1 I I
I TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980) LIQUID EFFLUENTS July - Decenber, 1980 CONTINUOUS MODE BATCH MODE Unit Quarter Quarter Quarter Quarter Nuclides Released strontium-89 Ci 1.25E-2 1.47E-3 strontium 90 Ci 7.62E-4 2.81E-4 I cesium-134 cesium-137 Ci Ci 3.88E-2 2.08E-1 3.61E-2 1.98E-1 iodine-131 Ci 5.04E-3 cobalt-58 l Ci 1.43E-2 8.79E-3 cobalt-60 Ci 1.89E-1 7.28E-2 iron-59 Ci 6.44E-3 8.01E-4 zine-65 Ci 1.83E-3 5.60E-4 j mangariese-54 Ci 1.73E-2 7.18E-3 chromium-51 Ci 2.47E-2 4.83E-3 zirconimum-niobium-95 Ci 9.33E-6 7.00E-5 molybdenum 99-Ci 1.42E-3 9.79E-5 technetium 99m iI barium-lanthanum-140 Ci 3.82E-3 5.76E-4 cerium-141 Ci 2.60E-4 I iodine-133 Ci 1.39E-3 ! cerium-144 Ci 5.71E-5 I silver-110m Ci iron-55 Ci 7.53E-2 8.71E-2 l unidentified l Ci l l l2.10E-1 l5.98E-2 l Total for period (above) Ci 8.11E-1 4.78E-1 xenon-133 Ci 1.23E-4 xenon-135 Ci 3.75E-4 I
I Accendix C -1979 Soil Survey l
- I .
l i i 1 I I I I I . I i i I I I ; s i
-=--e.. - - - , _
I INTRODUCTION In order to comply with Boston Edison's technical specification . 4.8 for environmental monitoring of soil, gammag situ spectrometry analyses were performed at the 11 stations listed on Table A during the period from the 25th to 27th of July, 1979. The gama g situ spectra analyses were generated using the mobile van equipped with the downlooker Ge(L1) detector, its associated electronic equipment and computer software Icn chamber measurements at the 11 stations I according to Reference 1. and core sampling at 3 stations were also performed according to Ref erence 1 to augment the g situ measurements. All spectral data obtained is available and on file at the environmental lab. The final tabulated results of the soil analyses are presented in this report. l I !I 'I g c.2
I 1 I l
~
RESULTS I Tables 1 to 11 were generated for each soil surveillance station to contain the date, counting time of analysis and both exposure rates (pR/hr) and concentrations (pCi/Kg) for natural, fission, f allout andiplant related activation nuclides. The exposure rates were derived using the exposure rate method in Reference 1. For the natural emitters, a unif orm distribution throughout the soil was assumed (a/c = 0). If a nuclide gamma peak was found for the fission, fallout and plant-related nuclides an exponential depth distribution was assumed (a/o = .'206). If a nuclide peak was not found f or these manmade nuclides, a planar distribution was assumed (s/c = =) f or the apparent exposure rate calculation. The conversion f ac tors used in *.rans-forming the exposure rates to activity concentrations (pC1/Kg) are listed in Table B. Table B was generated from Tables 8 and 9 of HASL-258, Reference 5.
~
The data format', standard deviations and LLDs used in Tables 1 to 11 are quoted based on Reference 4. Table 12 con. pares the gamma in situ result (p R/hr) with the ion chamber measurement (uR/hr) that was obtained at each of the 11 stations. The positive gamma g situ exposure rates are divided into five categories, the exposure rate for the U-238 series, Th-232 series. Cs-137, K-40 and others. The "other" category . notes other nt clides found positive by the in situ analyses. If the source term of the "other" nuclides could not be assumed to be soil, then the detector efficiency is unknown for these nuclides and the exposure rates were not reported or included in the gamma g situ exposure rate subtotal. A sealevel cosmic exposure rate of 3 6uR/hr was added to the subtotal of the positive nuclide exposure rates in order to facilitate the comparison of the _in situ results to the ion chamber results. As s h o'.Ti by inspection of Table 12, the gamma i_n_ situ exposure rates were calculated to be greater than the ion chamber measurements at all eleven sites evaluated at eigtit of the sites not directly adjacent or possibly influenced by j the plant's operation or rad waste storage f acilities, the _in situ :ceasurements ( were higher by 0.4 to 3uR/hr (or 5% to 37.5% r,reated t' tan the ion chamber results. !I
-e2
- g 1 ee-e2 = e x 1e I a
I The other three measurement sites were in close proximity to the plant and, as a consequence of the plant's influence, the ion chamber results at these sites were found to be 1.6 to 5.5 times greater than the calculated g situ results. Tables 13 - 15 present the results obtained when the gamma field measurement of two on-site stations and the control station were compared to laboratory analyses of core samples obtained from the same station. Only the naturally-occurring radionuclides were compared. A comparison for the naturally-occurring radionuclides was made between the g situ result (pCi/Kg) and the average of the laboratory ana ses of the core sections by using Equation 1.
% Difference = I-X *100 X
Equation 1. I = h situ result (pC1/Kg) X = A+I (pCi/Kg) 2 A = Average laboratory soil results (pri/Kg) Equation 1 was Jerived using the assumption that the g situ and the laboratory measurement were duplicate analyses. I All the calculated percent differences listed in Tables 13 - 15 are less than 157.. 1 I l C-4
DISCUSSION I , Data concerning six of the eleven stations will be commented on in this discussion. These six stations either had a high ion chamber result relative to the g situ result, showed positive Co-60, Mn-54 or Cs-134 in the gamma measurement, or had both a high ion chamber measurement and showed Co-60, Mn-54 or Cs-134. The stations with the relatively high ionization chamber measurements were the Warehouse, Pedestrian Bridge and Overlook Area. According to Table A, these stations are the closest to the reactor and therefore, the high ion chamber measurements at these sites were probably due to some , source other than the soil. The g situ gamma results at the Warehouse and Pedestrian Bridge showed positive Co-60, Mn-54 or Cs-134. For the Warehouse and Pedestrian Bridge the source term for the positive Co-60, Mn-54 or Cs-134 was quoted as unknown. Because of these station's relatively high ion chamber measurement with respect to the g situ result and the stations closeness to the reactor, the source term of the positive plant related nuclides was not assumed to be the soil. Since the source ter= is unknown the exposure rates for these nuclides w m not reported. However, the source term of the positive Co-60 or Mn-54 at the Property Line, East B.renkwater. and Clift Rock Area sites was assumed to be the soil. The soil was assumed to be the source term for these stations because of the agreement of the two independent measurements and the distance the sites were f rom the f acility. l [ l i I r I I C-5
Table A _ Soil Surveillance Stations Distance and Direction Station Number
- Samoline Location from Reactor 00 Warehouse (WS) .03 miles SSE 01 Rocky Hill Road (ER) 0.8 miles SE 03 0.3 miles W-WNW I
Rocky Hill Road (WR) 06 Property Line (PL) 0.34 miles NW 07 Pedestrian Bridge (PB) 0.14 =iles N 08 Overlook Area (OA) 0.03 =iles W 09 East Breakwater (ES) 0.35 miles ESE 10 Cleft Rock Area (CR) 0.9 =iles S 15 Plymouth Center (PC) 4.5 miles W-WNW 17 Manomet Substation (MS) 2.5 miles SE 21 East Weymouth (EW)** 2.3 miles NW*
=0tiained from the air particulate station codes. + =* Control Station.
l I C-6
I 11 Table B Exposure Rate to Concentration Conversion Values
- i Nuclide Energy Conversion Conversion Conversien Name , (Kev) c/o=0.206 a/c== n/c=0 (uR/hr/cCi/gm) -
(uR/hr/oCi/gm) * (uR/hr/oCi/gm) Ce-144 133.50 . 0.00913 0.02229 Ce-141 145.44 0.03709 0.09291 1-131 364.46 0.29314 0.73085 Sb-125 427.88 0.35482 0.88332 Ru-103 497.09 0.41724 1.05107 Ba-140 537.30 0.17021 0.42963 Rh-106 622.00 0.17813 0.45466 Cs-137 661.61 0.55007 1.35915 Zr-95 756.72 0.'75624 1.85287 . I , Nb-95 Mn-54 Co-60 765.80 834.84 1332.51 0.79129 0.89883 3.24207 1.94376 2.20063 7.78098 La-140 1596.20 3.22581 7.83693 K-40 1460.76 - 0.179 Th-232 Average 2.82 U-238 Average 1.82 l It ll l I l I C-7
1
-n Su a Coui r. Ri_ ts le te oun J7/ ) E 1
l Locatlon: Warehonse Statton Number 00 Counting Time: 6000 (see)
--, ;
l
*nc 1 isle E: pounro Rate Concentration ;
til.:nt I(icat ion (pn/hr) ( pC 1/ E.:) I _ a.__.________._.-- ----r---- - - - - - - - -
- Nuclide Ener; Expo;nio 9t anil t ril S t anita ril l Na: .o ( E e v '. R.ir.. D..v i it ton I l.D Conc Deeiation I.I.D i:e- l '.t. 131.30 SE-0) 4E-03 15E-03 2E602 2Et02 7Et02 +
{ Ce-141 143.4' - l 9E-03 4E-03 9E4 01 i 4E101 14Et01 ; l l l13E-03 l l-13l 3 6 '. . ' o -13E-03 7E-03 -2E101 IE101 1 4E601 l l l l26E-03 l
- b-123 427.di l 3E-02 2E-02 8E-02 3E401 l 3 E4 01 9E601 l l l l l j Rn-iOI 4 9 7 . U'.'
l -2E-03 7E-03 l26E-03 -2E60 7E+0 25Et0 i l l l l l j B.i- L ' 0 l 5 17. 10 l -20E-03 l 10E-03 l36E-03 j -5Etol l 2E401 l BE101 . C o- ! j '. 604.70 - - - - j - - l l l g l l 622.10 4E101 16E401
? Ca- t '17 ir Rii-lon j 661. ei l l 2E-02
} 2E-02 7E-03 l
7E-02 4Et01 l IE101 4E101 g m l l 76E-03 l l 23E-03 l 14E601 ; 1 Zr "i 75n. 2 -3E-02 IE-02 l -16Et0 6Et0 24E10 l l l l 4E-02 l Nh-91 7h3.30 l -0.5E-03 l 7E-03 l 24E-03 l -0.3E60 j 3Et0 ; 13E'10 i l
' !n - 3 '+
8 10. % 8E-03 1 7E-03 4E40 3E10 l llE10 l24E-03 l l l { 01- >o + l t lil. )l g l l g { l l
.0 c I l '. no . 7.> j 226E-02 l 3E-02 l 4E-02 2E102 2E+02 l .
, l 126Et02 l l :
l.a- ! .0 1 1 >"'i . 20 -3E-02 lE-02 j 4E-02 -3E10 t IE10 6E10
; 'l i. .
l
~'
Th- 1 Il- l i 160l:-02 . SE-02 57EtOI [ 2E101 l L -l ;M '" l l 87E-02 SE-02 48E601 2E101
- - - - - - - - - - - -lg - --
l -- l - -~' l
--l , T
- c. :.ii .:n l it .nl b.iac.' on .. 1 .1 : an! haselin. cann t . in t he .ic t o.i! po d f enn.1 .i.4 4nn!1, ( if a .204)
' ^ C.i l e 11.i t . il has .! on . l .:'it eil ave rage ( if , 0) fo r Th-21'l t'- ? )H .in.1 s ine l o pi .it ( /.2 = 0) for K '40
+ Unknown Son rci. Tsrm
m M M M M ~ M -m M M M M M ysa t e oMr Conn t :M (e C>/79 M M M in Sitn Coun t ing 'teunit s Table 2 Locatinn: East Rocky 11111 Station Number 01 Counting Time: 6000 (sec)
- nc I tile Expo;nre R.it e Concentration I filent i t' ic.it ion (alt /h r ) (pC L /E .t) 1 Nuc I i.le Ener- E:moinre ?; t .u n t.i r.1 S t anit.ir el
.:a- o (Kevn R.i t .. Dev i.it ion llo Conc. Devi.irion I.I.D .e-lii 131.10 -0E-03 10-01 4E-03 OE101 set 01 lbEt01 '
l l Cc- l '. l l '. 3 . . 16E-04 9E-04 l 32E-04 2Et01 l IE+01 3Et0L i l l l , o *
~ ~
l-131 l 7 0. 3 :~~ l _0,41,_ 0 3 3E_03 h [_03 -0.6E60 t 4E4 0 ! 13Et0 Sb-12> { 127.94 l 18E-03 l 10E-01 l 34E-01 l 2E601 I IE+01 i 4EIDI I:n - I t ) ' 4 'l l . 0') 2E-01 .lE- 0 3 2Et0 3E40 IlEt0
- l l l l 12E-03 l t l B.t- l '.0 537.10 l 2E-03 SE-03 l 18E-03 l 0.4 E+01 l lE+01 l 4E+01 ;
l l C s- 13.'. l 60'. 70 ] _ l j _ l _ j _ l
- l Rh-lon j b.'2.10 l -0.2E-02 IE-02 4E-02 f-0.4Et0L l 2E101 l 9E601 l f '
C ;-l li e l 6ni.nl l 3630-01 ( HE-03 l 16E-03 l 66E401 ; IEt01 l IEt01 e . to Z r ') .; /.> > . . . ' 7E-03 4E401 IEl0L l l IE-03
] l26E-03 l 0.5E601 3 l t Nh fi 70).30 l 170-03 l 4E-01 l14E-03 91.60 l 2E60 { 7E60 ;
11 1 * . ! ' ' ' 2E40 7E40
- '8 n - s '.
l 3 E--01 SE-01 l16E-03 i lEt0 l .,
.u-na l
l ., ,ia.>l l 3E-02 l IE-02 l 4E-02 3 4Eto j 2Eto l SEIO j
- ~.O f- l 'o .0 . .~ n 20i_02 l 3E-02 l 3E-02 2E602 l 2E102 l l
]Il6Et02 l l Lt-lio
{ 136".l ' l -6E-02 l lE-02 l 4E-02 -7060 i LEIO l 6Et0 Th-l;l- 237E-02 : SE-02 l 84E401 l 2E601 i j l l ' 4E-02 2E401 l i __]_ i 14 J2__ l i l i l 78E+01 I l l
. 1
'C.ticiel.u
. b i s. .' .ia .c .!i . .i:n! b.s w i ino count, in t lio .ic t u t ! ;ri!- t'oom! .aus'c'ite: 8' i/ = .206)
' v.il c a l .it . I h.is .! oc .ec i c o t eil ave r.e:. (.' = 0) for rii- 2 r! r-ll8 ami sin.le ;ic al: ( t/ > = 0) for K '.0.
_In Situ f.ountiny, Resultd M M M M M M m. Table 3 M m m mmuate at Lount: m 07 9 m m , m Location: West Rocky 11111 Station !!umbe r 03 Counting Time: 6000 (sec) l Nuc 11.le E:q>o n u re R.it e Concentration g Identification (on /hr) ( pC l /E v.) ; Nu c l i.le Ene r:; E:qio su r e 9t anil.ird Stindard ; Nane ( Kevi Rat.. Deviition 1.1.D Conc. Deviar ton I.I D 131.30 4Et01 l set 01 16EtOI C 0 - l '. .'. l 0.8E-03 IE-03 f4E-03 { Ce- l 'e l l '. 3 . . 23E-04 9E-04 2Et01 IE401 4EIDI l l l 33E-04 l l- 1 11 ll ~ J h ' . '. o ; -5E-03 { 3E-03 l 10E-03 l
-7f'10 , 4E40 l 14Et0 Sb-123 427.35 -9E-03 10E-03 l -lEt01 IEt01 4Et01 :
l l l36E-03 : l Ru-103 4 9 / . 0 '.' 2E-03 3E-03 2Et0 3E40 12E+0 l l l12E-03 l g l Ba-liO 337.30 l -2E-03 l SE-03 l19E-03 l -0.*4E40lj IEt01 l 5Etol ; l ~ C.;- 1 ; '. 60'4. 70 - _ j _ _ j _ _ l l l Eh-106 422.10 j 0.9E-02 IE-02 2E601 3E4 01 9E101 ; l l [ 4E-02 l 77E-03 6E-03 14E601 lEtol 3E601 {cs-13;& l 661.41 l l l17E-03 l l i O Zr-91 159.72 6E-03 8E-03 3Et0 4Eto 15Et0 j l l l l29E-03 l l l Nb-93 7t 3. S0 0.3E-03 SE-03 l17E-03 2Et0 j 9E60 l l l l 0.2E10 l
' 2Et0 9Et0
**c-- '. I 8 3 '. . %
l -5E-01 f SE-03 l 19E-03 -2Et0 l _m __ '
.:0 Mi l
1 l il . 5 i j IE-02 i LE-02 l
$E-02 IEt0 2Et0 j 6 E+ 0 ,
~
4E-02 162E602 2E102 l 2E402 j K *. 0 2 ' l l '4 nd . . o l 29,0E-02 i, l 3E-02 l I l 1346.20 IE-02 IE40
'.a - l '. o ib-!32-
] l l
0.9E-02 292E-02 I i 6E-02 l 4E-02 l 104Etol I IEt0 2E601 l* S E-4 0 ,
;
l 8 i ._______t_. l 80Et01
'-23M 146E-02 4E-02 2E601 l ;
l l l l I I I' I e
- 4
*' a l. 'll it.-i: b ried n; ii. .tF am! h.ree !'ine coun ts in t. he ar t.u1! !w t' t'onnd .ruur !:r. ( t/ = .206) l 4:.i l . n l a t. .I b.im .1 on s i .;it t ed ie ra.p. (ct / = 0) tor Th-212 .. r-f in and sin::lc pc i!. ( e/ = 0) for K '.O.
M i S M Coi M g ! M ts M M M M M abl g g g g Da g Cg:_g26_g,_ _g Location: Property Line Starion Number 06 Counting Time 6000 (see) Nuc I til.? Exposure Rate Concentration filent i t icat ton (p I' / h r ) (PC L /Ev',) . Nuc 1 f.!e L . r .: r Exposure S t and.ird Standard Na . 3 8Kevi Rar - Dmeianion I.I B Cone Dev i .it ion LI.D
' i t:e- l '.J. 133.30 l 0.2E-03 IE n3 l 4E-03 0.7El01 set 01 17Etol !
Ce- l 'e l l '4 3 . 4 '. 9E-04 0.2E601 4Et01 l l 0.lE-04 l l33E-04 IEt01 l l-t31 141 ' . ' ' l l lE-03 l 3E-03 l 9E-03 2Et0 4Et0 13E40 Sb '2i 427.Si l ! 0.9E-03 l 9E-03 l34E-03 0.lE401 l IE601 ! 4EtOI ' Ru-103 4 91. .M -2E-03 l l l 3 E-O 'l i 12E-03 l -2Et0 l 3E40 l IlE40 , ll a '. '. 0 517 10 7E-03 SE-03 !17E-03 l l l l 2Et01 l IEtol 4E601
- Cs - l 3 '. 64'4 .' O l l l l _
l l l _ Rh-i0e> j 622.10 l IE-02 l 4E-02 2Et01 n l -lE-02 L - -3E601 l l 9Et0! I f, Cs-1 lir 66!.41 155E-03 7E-03 28EiOI lE401 3E601 a [ l
- l l 16E-03 l _ _ . . . - - -
- 7. r-9 3 l 7 5') . 72 4E-03 7E-03 2Et0 l 4E60 13E40 l l 25E-03 l l i 7n3.30
- -l
';b- s i :
l 4E-03 l 4E-03 l15E-03 l 2Et0 l 2EiO l 8EfD 8,. .:- ..
. !n- > . +
l SE-03 4E-03 l 16E-03 2E40 2E40 I
! l l 7E60 ' ' ~
~~
.:o-ni F ~ ~~~U~il. i t 0.9E-02 ~ LE-02 4E-02 lEin g IEt0 SE60 l l l l
-: - i. 0 "
l Lino.'> l 208E-02
+
3E-02 l 3E-02 ' ll6E+02 l 2E102 l 2Et02 l I.a.- I '. 0 l 1.> 4 . 2 0 l
-10E-03 10E-03 1 38E-03 -lE60 i lE+0 l SEtO '
T h- 212 l 196E-02 SE-07 ' 70E601 ! 2E401 l t l i l L__ + - E - 21.i 112E-02 j 3E-02 61E601 2EiO! l l l { l l i _ . . . .--l .- t i i I I
*t a l. n l it . -
b.i . ' oa p. ih ind liaso t ine coints in the .ic t sa ! pr. i!- fo' nil asturin. ( t/ = .2048
~
AfC.ilculated h.i' d on i t;St ed ave rac.e ( c/ = 0) ior Th - 21.' F-218 .ind s ingl .: peak (a/: = 0) for K '.O.
+ Source Term assumed to be soil.
l
Cout gR ts le te oun U //9 In S Pedestrinn Bridge 07 Counting Time: 600(4 (sec) Location: Station Number ___ Nuclide E:cposu re Rate Concentration identttfeation (pl:/hr) ( pC L /K.:) __ _ w -
% c t (d.. Energy E::po su r e Standard Standard Na:,e Rate O. v i.t r ion I.I.O Conc Deviacion i LI.D
( Kev) C e - l '. '.. 131.30 2E-03 4E-03 l13E-03 0.9E+02 2E+02 l 6Ef02 Cc- l 'e l 14 3. R -5E-03 3E-03 -5Ef01 3E+01 12E+01 l l lllE-03 l l j 1-111 364.46 4E-03 6E-03 6E+0 j HE+0 l 27E+0 [ l l20E-03 l Sb-123 j 427.84 l 2E-02 2E-02 6E-02 g 2E40l!' 2 E+ 01 l 7E+01 ; l -' Ru-101 l 497.09 l
-2E-03 6E-03 l 20E-03 l -2E40 l 5E+0 l 19E60 i Ha-t'io 337.10 -2E-03 uE-03 -0.4E60ll 2E+01 6E601 .
l l
, l28E-03 l . l C.;-13a 604.70 - - - - - -
l l l l 622.10 5E-02 2E-02 6E-02 4E101 13E+0! Rh-loti l l l IlEf01l ' Cs-137v 661.61 319E-03 10E-03 l 24E-03 58Ef01j 2E+01 j 4Et01 n l l l l , i g Zr-95 l 750.72 l -lE-03 l 10E-03 !36E-03 l -0.5E+0 l 5E4 0 20E+0 ! Nb-93 I 7h3.50 -4E-03 6E-03 l22E-03 -2E+0 l 3E10 llE40 l l l in- n + ; a lz. aa ; ; ! l l l Co-90 + l ITi2.it l : , l l j i K '.0 0 l L a no . 7') l 218E-02 j 3E-02 l 4E-02 l 122Ef02 2E+02 2Et02 1.a- l a n 1590.20 l -2E-02 IE-02 l SE-02 -2E60 2E+0 l 6Et0 l _. Th '32' l l 243E-02 6E-02 86Et01 2Ef01 l 1
'J - 2 3 3 l 129E-02 [
4E-02 71Ef01 2E+01 , t I ! [ ______i
*' .i ! c u l it eil bas.d on peak acd baseline coscit.; in the ar r na l peal f ouni! assur.in - ( /.: = . 20's )
ACalcu !at. d has J or, w.:[ ;hted ave ra.:e (n/a = 0) t'o r l'h-2t2 - !*-2 3S and s i nal .' peal: (a/.: = 0) for K '.O.
+ Source Term L:nknown.
l i
M g Sitti Counting Results M M M M M M M
.I'21e 6 M m ' mDate m of Count:
e e,7/p u// e e Overlook Area Station Number 08 Counting Time: 6000 (sec) Locatlon: W l Nuc1ide Exposure Rate Conecotra:1on Ident i t'leat ion - (pil/ h r) (pCi/Kg1 i Nuclide Ene r ;y E:< po su r e Standaril S t an d.i ril Nane (Kevi Ra r .. Deviation I.I.') Con.: . Deviatiein I.I il ,
-2E-03 2E-03 7E-03 9Et01 10Et01 34Et01 :
131. 3f) C e- 1 'i . 1 Ce-141 143.44 j 3E-03 2E-03 3E401 2E601 7E101 l l l 7E-03 1-131 367. 4.i -0 . 7 E-0 3 4E-03 -lE+0 g 6E10 l 21Et0 l l l l15E-03 l Sb-ll5 l 427.Si l
-0.lt-02 l
IE-02 l 5E-02 l-0.lE+01 j 2Ef01 6Et0! j Ru-101 497.09 SE-03 -10E40 SE10 16E+0 l l
-llE-03 l j17E-03 l l Ila- t '+ 0 l 537,30 l 0.6E-03 l i
7E-03 l24E-03 0.2Et01 l . 2E+01 i SE+01
;
Cs- 13 '. 60a.70 - - - - l l l l l Rh-106 612.10 2E-02 IE-02 4E+01 3E+01 llE101 g l l l l 5E-02 3 661.nl 79E-03 6E-03 14E101 IE+0L 3E+01 {Ca-1lin j l l l18E-03 ,
" Z r-9 5 l 756.72 l 12E-03 9E-03 l31E-03 l 7E10 SE40 l 16E+0 l
- h-9 3 76).S0 l -llE-03 l SE-03 l 19E-03 -6Eto 3E40 l 10E+0 l l
'In - 5 '. 3 3 5 . t'. 2E-03 l 5E-03 1E+0 2E+0 8E+0 l l l18E-03 l l l co i=0 1312 il j 4E-02 IE-02 l 4E-02 SE+0 l 2Et0 l 6E40 j l
K '066 1440.76 207E-02 3E-02 l 3E-02 ll6E402 l 2E+02 2E402 j l La-l E 15 % .20 2E-02 1E-02 l 4E-02 3Et0 lE+0 l SE+0 Th-2321 264 E--02 6E-02 - 94E+01 2Et01 l l l l , E-2 3d ' 4E-02 84E+01 2E+01 - i l l 153 E-02 - l l 6 l l
*Calcul ited bas.-d on p c#. .m.I ba ;eline conuts in the .ic t ii;i' pe.i! thonal assunin : ( s /.: = .206's etc.ilcu lated bas. d on sel ;Sted ave rac.e (2/o = 0) t'or Th-212 T. L'-238 and sincie peak (q/o = 0) for K '.0
nS Cou g it s ble te 'o ui /2 '> N E East lireakwater 09 6000 Locatlon: St,ition Number Counting Time: (sec)
';isc i ide Exposure Rate Concentration Ident it icat ion (p il/ h r ) (pC i /I: :)
_; Nuctide Ene r ;:- Expo;ure S t .'.o. la r d Standard N. i n.' (Kevi Rato 0.viarion 'e ! I.9 C.*nc . Devlation I.I.l) Ce- l '. 4 133.50 0.6E-03 IE-03 l 3Et01 l 5C+01 19E601 l4F.-03 u Ce-141 l 143.i'. l 0.2E-03 IE-03 4E-03 0.2E+01 lE+01 4E+01 l l-131 3 6 '+ . 4 " 14E+0 l l IE-03 3E-03 l10E-03 2E+0 4Et0 l Sb-123 427.3i IE101 4Ef01 l l 0 .91;- 0 2 l IE-02 l 4E-02 ll lEtol . Ru-103 497.0" -7E-03 4E-03 -6E+0 3E10 13E10 l l l l 13E-03 l l l l tia- l 'i O 337.10 SE-03 IE601 4Et01 l l -2E-03 l l 19E-03 l -0.5E+0! l i Cs-I]4 60'4 70 j l _ _ l l , l _ _ _ Rh- 106 622.10 2E-02 IE-02 l 4E-02 4Et01 3E+01 9E601 g a l l l g Cs-137* 661.61 91E-03 SE-03 10E+0 27EfD l l l l 15E-Oi . l 365Ein l l ,
- 7. r- 9 5 750.72 -0.7E-03 8E-03 4E+0 15E60 j l l }28E-03 l -0.4E60 l Nb-93 7b3. id i IE-03 SE-03 l 16E-03 . 0.6E+0 2E+0 l 8E+0 f l l 8 34. M 18E-03 8E+0
!n-3i l l -5E-03 l SE-03 . l -2Eto l 2 E+ 0 l ,
.;0-604 1312.31 4E-02 IE-02 10E+0 j 3E60 9E+0
~
l
. l l l 3E-02 l
. . l l i
K '.O n l'.eiO . 76 287E-02 4E-02 l 3E-02 160Et02 2E+02 2E+02 l l l ; La- I '.0 l 1596.20 1 -6 E- 02 IE-02 I! SE-02 -7E60 ! lEfD 8 I 6E40 ~Ii I I T h - 2 12 " ' 6E-02 2E+01 256E-02 I l ; 91E+01 l l ~l' C ' 33 " 140E-02 4E-02 77Etol 2E401 l l i , e " i
^Calculered based on p..tk and ba.eline counts in r ise act o.i! pe i!- found a .4nr in : h / - = . 206)
M C.ilentated tw;..ul on .tuhted average (<4 / .s = 0) for Th-212 0-2 3F. anel sir.;:l e peak a(c/,) = 0) for K 'io. '
- Source Terra assumed to be soll.
I
E E E E E E E E E E E E _I_n_ S i tu Coun t ing Re:. a . t 5 Table 8 %te nun I'
- ___
Cleft Rock Station Number 10 Counting Time: 6000 (sac) Location: i 1 Nuc1ide E posure Rate Coneentr.1 tion , i
- 1. lent i t icat ton (un /hr) (pC t /i:g) l
~
l Nuclide Ene r.; . Exposure Standaril Standard l* (Kev i Ita t e D.viation I.I D Conc. Dc:via t ion I.I.P Nane __ Ce- l '* 4 131.3') -lOE-04 10E-04 ! 5E-04 3 -4Etoi 4Et01 15E401 ; Cc-141 143.s'. -6E-04 1 9E-04 -6E40 9E40 33E40
- l l31E-04 l I
1-131 l 364.'." l_ -3E-03 3E-03 l 9E-03 -4E60 4E10 13E+0 a Sb-125 j 427.83 22E-03 9E-03 3EtO! IE+01 l 4E601 . l33E-03 497.09 -3E40 3Eto 12E60 l Ru-103 l -3E-03 3E-03 l 12E-03 l l Ba-l'40 517. P1 -3E-03 ! SE-03 !180-03 .7E601 IEt01 l 4E40 i l Cs-134 60'. 70 l _ l _ _ l _ _ l l Rh-LO6 622.lti IE-02 2Et01 9Etol l j .5E-02 l 4E-02 l IEtol 661.6 C.;- 13 7
- j I 134E-03 l 6E-03 !16E-03 l 24Etol h IE+01 l 3E401 ,
e g Zr-95 750.72 10E-03 7E-03 l 26E-03 l $E+0 4E+d l 14E60 ! l l , N b- T, ' 765.30 l 7E-03 l 4E-03 l 16E-03 l 4E+0 l 2E+0 I 8Et0 l 21Etn SE40 16E10 i
-In- 3 '.+ 8 l '. . i f-l 19E-03 1 4E-03 l14E-03 l l ..
1112.3! IE-02
.3E+0' 2E+0 6Et0 i Co-60 [ l . 3EN12 l l5E-02 l l
< - 10 ?- l'h0.76 278E-02 4E-02 l 3E-02 2E402 2E602 I i l 155E+02 l
_I 1.a - l '.0 l 1596.2" l 7E-02 ; IE-02 I 4E-02 9E40 lEto l SEIO Th-212"^ 274E-02 6E-02 97Et01 2E601 l j l l { l _ E-2 Id " 142E-02 4E-02 78Eini 2E401 l l l i l i I
*C.ilcul .it ed bawd on peah ed ba:ieline count; in tho ac to.i! pe it- f oinid ..4cunine (al1 = .206)
'.0
* *Ca lcu l a t. .! has d or. ..e t ;ht eil .1ve rage (o/ - = 0) t'o r Th-212 .. t*-2 3S .md s ing l e p.ak (q/a = 0) for K
+ Source Term assumed to be soil. .
1
"" d"" /*-
in Si Coui dRt ts Tahl Location: Plymoutti Center Stat ion Numl>er 15 counting Time: 6000 ('
\
Exposure Rate Concentratton Nuc ! tile lilent i f icat loti (pi' / lir ) (PC I /E.:) E ne r g:.- E:<posos e S t anit a ril S t.ind a r il
'Juct(de N.i:e ( Ke@ Rat. Deviation 1.1.!i Cone. D.*vtarion 1.1 D 10E-04 34E-04 2E601 4Et01 15E401 i
- e-lia 131. 0 - SE-0 4 l l 31E ~t 0 Ce- 1 '. I l4 3. a; j -8E-04 ,
'TE-04 12 64---- 7EW -- IDEIO l ,
J l
-2E60 4E60 l 12E40 l t - 1 11 l
3 6 i . '. " l -lE-03 l 3E-03 l 9E-03 1 I 4E401 I Sh-123 427 3' l -4E-01 9E-03 34E-03 l .5Et01 ! lEtol l p.u-103 4 9 7 . u _' l 2E-03 3E-03 12E-03 2E6C l 3E40 l 11E40 f l ILi- L
- 0 537.30 5E-03 -2E401 ! IE101 4E401 1 l 03 l f18E-03 Ca-135 60'. 70 _
l _ _ j l l _ _ l _ E'-lOh 622.10 .6E-02 IE-02 l 4E-02 l -10401 l 2Etol 9E101 l l l ' n Cs-l l7 ^ 6II.61 l 243E-03 l IlE-03 l 18E-03 44E601 l IE401 1 30401 os 7. r-9 3 159.72 2E40 l 4E40 l 14E40 i l 3E-03 l .7E-03 l26E-03 l Nb 'r 3 763. iC' i 15E-03 4E60 l 2E+0 8E60 1 l 80-03 l 4E-03 l l
" - T* 8 l '* l ' l 01 SE-03 l17E-03 -3Eto ! 2E60 l 8Et0 l l i
.:0-90 1112.31 1E-07 i 4E-02 1 -Itto 2E40 l 6E60 l ! .9E-02 l l 1440 I" 109E402 2E602 l 2E602 i
< - 4 0 "
l l 194E-02 3E-02 ! 3E-02 l Ea-lin 13 % 2" IL-02 IE*O IEt0 l SE40 l l IE-02 . l [4E-02 l Ih-I I I" l l 25HE-02 l 6E-02 I 1------ 9tE601 l 2E401 l -i. L-233 ' l 154E-02 4E-02 84E+ 01 l 2E401 l l ~ [ ~~ i ~!
~~t i i - - - - -
i
**:a i cul tt.. : bavd on ; ah and b.iseline counts in the actu.i! pe il- f ound autir in T" / . = .2046 "Ca lcu !.it.:il has si on . i; it eil .ive ra ;e ' (u/ - - 0) t or Th-2 62 f. L'-2 3 3 anni single peak (u/ = 0) for R
~
**0.
L
Res s e ,P W W me Mu' m -. m > g _ g _ g Slt ount Counting Time: 6000 (se ) Station Number 17 Locatlon: Honomet Substatton - Concentration Erposuro Rate Nuc 1 tile (PC 1/l*:.0 (p P /lj r) I. lent i f icat ion Standard Exnosure Standard I.I D luclide Enerr- Deviation I.l _D Conc Deviation ___:
!U t e Na n. . _ Kevi (
16E401 ! 4E-03 -2E401 SE401 CO- 1 ** 4 133.50 -0.4E-03 i lE-03
-24E+0 10E+0 34E+0 _l Ce-l'+ L j 143.i1 l -22E-04 9E-04 l 325-04 I
-1E+0 l 4E+0 l 13E40 _.
3 6 '. . '" ' -0.7E-03 3E-03 l 10E-03 l-131 l I ) 4E+01 8 0.6E+01 l IE+01 l Sb-123 427.83 l 6E-03 10E-03 l 36E-03 l l 3E+0 l 12E40 3E-03 l 13E-03 -0.7E+0 l Ru-103 497.09 l -0.7E-01 l 4E401 l IE+01 l l 337.30 SE-03 SE-03 18E-03 l IE+0! l Ba-t'.0 l l !
~ _
l l C.;-135 60i. 0 j _ l l 10E+01 l n Rh-loo g 622.10 l__ -0.2E-02 IE-02 ] 4E-02 -0.5E+01 l 3E+01 2E+01 l 3E+01 [ 661.61 j BE-03 l 18E-03 61E+011 _' Cs-137* l 336E-03 ; 3E+0 l 4E+0 l 15Et0 f
- 7. r-9 5 l 75n.72 l SE-03 l 8E-03 l 28E-03 l 4E40 l 2E+0 l 8E+0 l Nh-93 763.3,0 l 7E-03 l 4E-03 l 16E-03 l l 6E40 ! 2E+0 ! 7E40 3 3 '* . % i 14E-03 l SE-03 ! 17E-03 l
n- 31 l
IE+0 l 2E+0 l 6E+0 _; 1132.51 IE-02 1E-02 SE-02 l Co-ou l l l i 2E+02 l 2E402 1*.n0. o 4E-02 l 3E-02 l 164E+02l s-404 f l 293E-02 4E+0 1 E+ 0 l 4E40 f
!.a-140 1596.2') l 29 E-02 l 10E-03 34E-03 1 _l I 91E+01! 2E401 l Th-212' l 255 E-02 l 6E-02 l 72E+01 2E401 l C-133 " 131E-02 j 4E-02 -
l l _. i i (-' = '06)
*Ca l . ul at ed t,.i:;ed o:: p..ah and leaseline counti in forthe artua! !.p.'at Th-212 I'-ll3found anil assuriino sincic peak (a/a = 0) for K '0 ,
'
- Ca lc u l .i t.:d b.i+ J .m w.; i c t ed a ve rm;e (n/a = 0) l t .
Si out L .4 E E E E E We W g gt go g, g: ' 'g, Counting Time: 6000 g, (. ci 21 East Weymoutli Stition Number Locatlon: .(. Q-I
- Concent r.it ion 1
E po ;u r.' !'a t e i
"nc ! i.l.- (PC i ! E .' )
- 11. it if tcat ion L i' '!i r 7 .
f S '..toda r d i St it d ird I Ener;- E:-:po .u r e Dc"i it wn I.l i' ! Nuciide 1.I !) Co n . . 0.' e t i r i o i 1 i .i.. (Kev' t' i 17E+0i i
-2E+01 ; SE+01 l 131. G -0.5E-03 IE-03 l 4E-03 l
Ce - 1 17. l l l 4E+01 i l 0.5E+01 i IE+01 l 1
; Co - L '.1 l 113. ' l 4E-04 l 9E-04 l33E-04 4E60 4E+0 j 13E+0!
T-131 Jo . "' f 3E-03 1 3E-03 1 10E-03 l 1 l i 4E+01 4E-02 IE401 ! IE+01 Sb-ili j
'27
+ ;' ! IE-02 l IE-02 l
- 3E+0 l 12E+0 Ru-Lu3 19 . W- I -0.8E-03 i 4E-03 ! 13E-03 l-0. 7 E + 0 1 l 4E+01 l l 19E-03 -2E+01 I IE+01 l h-lio j 517.34 i _7g_o) SE-01 l j j - .
C;-131 l 60 i . its i _ l l l 3E+01 l 9E+01 Rii-lou ; ull.id 3E-02 l IE-02 l 4E-02 l 7E+01 l _
! 4E401 2E-02 2E+01 i C s - l 3.~ ~ ool.6l i SLE-02 l IE-02 l 93E+0! ,
l j 16E+0
-5E+0 l 4E+0 i
) 759.Il -9E-03 i 8E-03 ! 29E-03 l g C r ',' ; I 2E+0 i 8E+0 4E+0 l
- ib- ! ) l 7ui.3d l 8E-03 i SE-03 l17E-03 l 2E40 8E+0 "n-i. ; 3 51. ! . : IE-03
$E-03 {18E-03 l0.5E+0 1 0.6E+0 2E+0 l 6E+0 10-90 1i12.ii 0.5E-02 ; IE-02 i SE-02 e l !
2E+02 2E+02
<- iF g t he. : : ! 317E-02 4E-02 l 3E-02 l 177E+02 { }l OE+0 IE+0 i SE+0 i 4E-02 E. - 1 o 13 % . 2 ' I OE-02 l IE-02 l l j 93E+01 1 2E+01 El-I'- j 262E-02 l 6E-02 ',
)
79Es01 j 2E+01' i* L-I $ ! 143E-02 g 4E-02 { _.: l .~ -- . 1 e l e ;elin - ety n _ i in t in- .ic i e ' m i'- ' 0'i:t I .t i r e- f re - I# r . 2!)6 - ii ile-^ b.i is ' i s r. . 3
' 21 '. and :s in ! s ; sk (s/: = 0) for < 'A.
f C.t ; ::it-?d ii.c: I or. e : t .: : " .: rm' (' = 0) t'or th-212 - I . .
- - ]
d a a o _ t n m m 4u m m 3o a " a N 4 1f g ' g 4 6 1 4 8 " m _ 0 - v n u 3 5 1 3 1 7 0 0 0 0 0 0 0 se v
- s 0 0 0 0 0 P e U s 0 0 0 0 g KdnIT s 6 -
0 0 0 0 0 0 0 0 1 1 o 0 0 Cm 6 0s (e g
- 7oEcT 3u a a n
n 01 n s e 6k *3 lrdaE t a e n d
- o t a l ri i s ks e o o Ce p o p i
o i t r t ar 2 N 4a gk0uVa O w oe td 4d co r ah t h 2 4 3 8 0 9 . 5m 6k ri 5 n t / 2 6 6 8 1 2 S/ 4 7 1 7 0 6 7 1 m a es u u SR u 1 9 1 0 0 3 6 9 5 r u 0 7 3 0 8 na oe ve n o Cpob r fi { 1 2 0 2 Hg 1 1 0 2 0 5 3 8 8 1 j ) f
)
_a
)
1 3 df ) i e t g 4 6 1 4 8 4 6 0 1 0 4 0 1 8 0 0 4 0 0 6 1 0, 0 4 8 0 0 0 0 - 0 0 0 0 0 o 0 0 1 1 0 0 0 0 -
- 0 0 0 0 o- 0 0 0 0 - 0 - 2
- 91 g3n 0l 0 n
o n o i) o i t i t a r_ t' ar ti t ar t h S/ gS/ th R D 6 2 8 0 6 3 6 00 S/ R u 40 6 5 9 0 7 8 4 0 7 9 6 6 1 R u 3 4 2 6 1 5 7 1 3 3 7 7 6 3 3 3 4 8 4 9 0 9 _ 6 3 0 9 1 2 0 _ 3 1E 1 2 0 2 0 1 2 0 2 _ 7 3 1 1 b g *
;
e 46 1 4 8 m 1 3 8 0 0 _ 0 7 4 6 - 0 0 00 _ 4 5 1 4 0 0 0 0 0 0 0 0 _ 0 - - 0 0 0 0 _ 0 M 1 - o 0 0 0 0 _ 0 8o 01 0 0 0 0 - 0 7 1 1 e 0l n M n o l n o i _ o i t i' t ar M t ar ar th t S f} a t h S/ R h S/ R e u 1 5 4 3 3 R p 8 7 - 1 3 9 _ 1 6 7 0 3 4 9 2 3 5 , H 7 2 0 - 3 6 _ . 1 7 6 6 3 5 6 0, . . 3 g 8 E. 3 3 0 - 2 - 1 2 0 2 _ 7 4 6 3 9 6 g 1 2 0 2
- 6 3 8.
9 ~8 1 2 0 2 1 N il 8
~ 4 6 1 3 7 0
i 4 6 1 3 0 0 0 0 _ 5 1 3 8 0 0 0 0 _ 5 0 0 0 0 o 0 0 0 0 _ 0 0 0 o 0 0 - 0 0 0 5 l U t o 0 - 01 0 0 0 0 0 0 71 0 n 1 n o n o 1 i' o i t i t a r 4 8 4 4 0 1 ar t h 3 6 9, Ea t 3 2 8 2 5 5 2 9 _ ar th 9 8 . t h 7 0 8 6 c 1 8 6 4 0 S/ 2 4 3 1 2 6 0. S ! 1 6 3 ' 9 8 2 . . a R. 1 2 0 _ S/ 8 6 0, . R 1 2 0 2 6 3 9 0 1 p R 4 3 8 6 p 3 0 1 0 2 u 4
~
r r e
- r e b 2 e b l m 1 b l m a a l m a a 7 s t c h a 2 C a 2 7 s t c h 8 3 3 r o i l a
C h r o i l C 0 e t m a 2 7 3 s,t r o I l C 8 3 3 0 e t m a 3 2 1
- 4 h b s t o
n o 8 3 t *" a 3 2 1 h h l t n 2 S t u o he ,ah T 3 2 1 0 n 2 - - 4 o o - h - C T I 2 - - 4 t o o - h S - t u f( i T I_ U T C K o S
- h S - t u " U T U K O S 0 T C K O sS ,
C T I
~
nh I
E E E E E E E E E E E W E O E E E E E Table 13: COMPARISON OF 1.ABORATORY SOIL RESUI.TS vs. IN SITU COUNTING RifSUI.TS Station Number: n7 1.ocation: Pedestr ian Bridste Positive Laboratory Soll Results Nuclide In-Situ (pC1/kg) Wet Concentr tion Identification (pCi/kg) y Core Depth
?!uclide Energy 4-6" Average
- Difference (kev) 0-2" 2-4" Name Ce- 144 133.50 (-713)Et01 (-517) Et01 ( .912) E+02 Cc-141 145.44 (511)Et01 ( .215)E401 (-Si3)Ef 01 1-131 346.46 ( . 3F2)E+02 (062)El03 (618)E40 Sb-125 427.88 (-li2)Et01 (2+ 3) Et 01 (212) E+01 497.09 (-2+5)E+0 Ru-103 ( .611)Et01 (413)E601
~'
Ba-140" 537.30 Cs-134 604.70 622.10 (-4+ 6) E+0i (011) E+ 02 (11+4)Et01 Rh-106 - o (5812)E+01 Cs-137 661.61 (320110)E+0 (711) Et01 Zr-95 756.72 (312)E+01 (-114)E+01 ( .515)E+0 Nb-95 765.80 834.84 (6 F 7) E+ 0 (-Itl)E+01 (37+7)E+0* Sin-54 d 1332.51 ( 316 49)E+ 0 Co-60 (45 + 8) E+0 (012)Et01 (12212)E+02 0% K-40 1460.76 (10912)Et02 (13414) E+02 (122il8)E402 La-140a 1596.20 Ih-232 (6713) E+0l b (94t6)Et01 b (81119)E+0l b (86t2)E+01 . +3%
+13%
C (5513 ) E+01c ( 7112) E+01 U-238 (5312) Et01 (5713)E+01c The laboratory and In-Situ computation analysis are dif ferent for these nuclides (see Ref erence 2) . This calculation is based on the 911 Kev peak area. This calculation is based on the 609 Key peak area. Assuming a planar source the Co-60 concentration = (9913)E+0 pCi/kg. (11+2)E+0 pC1/kg. [ Assuming a planar source the Mn-54 concentration = The laboratory and In Situ computation analysis are different for this nuclide (see Reference 3). .
*The standard deviation is the 1-sigma deviation of the data.
l
W W W W W W W W W ~m W W W W W W W W W Table 14: IN SITU COUidTING RESULTS COMPARISON OF LABORATORY SOIL RI'.SULTS vs. 08 Station Number: , t.oca t ion :._ Overlook Area Laboratory Soil Results In-Situ Nuclide (pC1/kg) Wet Conc r ion (pCi/ks;) 7 Identification Core Gentli Difforence Energy 4-6" Average
- Nuclide 0-2" 2-4" Name (kev)
(9110)Et01 (4t6)Etol (-2217) E101 (616)Et01 Ce-144 133.50 (312)E401 (414)Et01 ( 313) Et01 145.44 (-li2) E t01 < Ce-141 (514)EiO2 (.812)E102 (-li6)Et0 L-131 346.46 (211)Et02 (454)E101 (214) Et01 (-0. li2) EOl Sb-125 427.88 (213) E101 (-lo t S) EO (2+2)EiOI Ru-103 497.09 ( .412)E401 (712)Et01 na-140^ 537.30 Cs-134 604./0 (413) E101 - ( .7tt)Et02 ( .911) Et 02 (711)Et02
? Rh-106 622.10 '
(1212)Et01 (1411)Et01 ru (1412)E401
" Cs-137 661.61 (Ili2)E601 (715)Et0 (214) E601 (-213)Etol Zr-95 756.72 _
(312)Et01 Nb-95 L 765.80
(-lil)E601 (li2)Et0 834.84 (2il)Et01 ( .712)Et01 Sin-54 (512)Et0 ( .412)E401 (012)Et01 Co-60 1332.51 (.611)Et01 (11612) E402
+4%
(ll214)Et02 (10716)Et02 1460.76 (10713)E402 (10115) E102 K-40 La-140 1596.20 b b (9412} E401
+2%
(78t?)Et0lb (10017)E10l (91112)Et01 Th-232 (9666)E40lb c +2% C c (84 &2) E401 (HJ_20)E101 C (7114)Et01 (10316)E601 U-238 (6613) E t01 f or these nuclides (see Ref erence 2 and 3) .
"The laboratory and in Situ computation analysis are different b
This calculation is based on the 911 key peak area. c This calculation is based on the 609 Kev peak area. f for this nuclide (see Reference 3). The laboratory and in Situ computation analysis are different
*The standard deviation is the 1-sigma deviat ion of the data.
I
W W W W W W W W W W W e m W W W W W W Table 15: COMPARISON OF LABORATORY SOIL RI: SUI.TS vs. IN ">ITU ColiNTING REST *LTS Station Number: 21 Location: East fle_ymontji Positive Nuclide Laboratory Soit Results g,g (pCi/kg) tJet In-Situ Concentration Identification (PCi/LC) a Energy C_o_re Deigh
'!uclide Difference 4-6" 0-2" 2-4" Average Name (Kev)
Ce- 14 4 133.50 (216)Et01 (-215) Ef 01 Cc-141 145.44 (-444)E101 (.511) E401 t-131 346.46 (-615) E402 (4+4)E40 Sb-125 427.88 (613)Et01 (lil)Et01 Ru-103 497.09 ( . 313)Et01 (~ . 713) E10 Ba-140 537.30 Cs-134 604.70 Rh-106 622.10 ( . 311) E+ 02 ( 713) E401 m Cs-137 661.61 (12713)E101 (9312)Ef 01 Zr-93 756.72 (414) Et01 (-514)E10 Nb-95* 765.80 1 I Mn-54 834.34 ( . 811) E+ 01 (.512)E40 Ce- 50 1332.51 (.112)Et01 ( . 612) E+0
+ 6 7.
K-40 1460.76 -( 15615) E+ 02 (17712) E402 U-140" 1596.20 h (9312) E101 +14% Th-232 ( 704_6) E+ 01 C * (7912)EiOI +10% U .'38 (6414)Et01 a The laboratory and In-Situ computat ion analysis are dif ferent for these nuclides (see ref erences 2 and 3) . b 1his calculation is based on the 911 KcV peak area.
"This calculation is based on the 609 kev peak area.
f The laboratory and in Situ computation analysis are different for this nuclide (see Reference 3).
E I Appendix 0 - Radiological Environmental Monitoring Program I . !I I E : E I I lI I ,I l lI 'I I lI .I lI - I
> APPENDIX D I
~
~
~
- t. 8.D Environmental Monitoring Program An environmental monitoring program shall be conducted as follows:
- 1. Environmental samples shall be selected and analyzed according to I -
Table 4.8.1 at the locations described in Tables 4.8.2 and 4.8.3 and shown in Figures 4.8.1, 4.8.2 and 4.8.3. Analytical techniques used shall be such that the detection capabilities I 2. in Table 4.8.4 are achieved.
- 3. A census of gardens producing fresh leafy vegetables for human consump-g tion (e.g., lettuce, cpinach, etc.) shall be conducted near the end of g the growing season to determine or verify the location of the garden (available for sampling) yielding the highest calculated thyroid dose.
This census is limited to gardens having an area of 500 square feet or I more and shall be conducted under the following conditions as necessary to meet the above requirement: __.
- a. Within a 1-mile radius of the plant site, enumeration by a door-to-door, or equivalent counting technique.
If no milk-producing animals are located in the vicinity of the I b. site, as determined by item 4 below, the census describsd in item 3a above shall be extended to a distance of 5 miles from the site. i If the census indicates the existence of a garden at a location yielding , a calculated thyroid dose greater than that from the previously sampled garden, the new location shall replace the garden previously having the Also, any location from which maximum calculated iodine concentration. I fresh leafy vegetables can no longer be obtained may be dropped from the surveillance program as long as the NRC is notified in writing, as soon as possible that such vegetables are no longer grown or no longer I 4. available at that location. 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 I location yielding the highest calculated annual average thyroid dose. The census shall be conducted under the following conditions as necessary to meet the above requirement:
- a. Within a 1-mile radius from the plant se e or within the 15 mrem /yr isodose line, whichever is larger, enusc.ation by a door-to-door or
. equivalent, counting technique.
- b. Within a 5-mile radius for cows and for goats, enumeration derived from referenced information from county agricultural agents or other I reliable sources.
If it is learned from this census that animals are present at a location which yields a calculated thyroid dose greater than from previously sampled I animals, the new location shall be added to the surveillance program as soon as practicable. The sampling location having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing season during which the census was conducted. Also, any location from which milk can no longer be obtained may be dropped from the surveil-
. D-1 _
- ,, ,n m -
- ~ - - - , -,--v
1 1 lance program as long as the NRC is notified in writing, co or milkca coon l I practicable, that milk-producingthat samples are no longer available-at animals are location. no longer present, i
- 5. Deviations are permitted from the required In the sampling ability or to malfunction of automatic sampling equipment.h ll be made event of equipment malfunction, every reasonable effort s a ampling I to complete corrective action prior to' the end of the next sAn period.
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. I Procedures shall include sampling, data r'ecording and s taken when anomalous measurements are discovered. Procedures shall be prepared for insuring the quality of programThese' procedures results, including analytical measurements. identify the responsible include organizations, include purchased services I (e.a., contractual lab), indeoendent audits and include (such as participation in IAEA and/or NBS intercalibration exercisescont and submission of " blind" cuality systems contractors)l to identify and correct deficiencies, investigate anomalous I I or suspect results, and review and evaluate program results and reports. Environmental Monitoring Proeram BASES 3.8.D and 4.8.D - An Environmental radiological monitoring program isiconducted aterials. to verify the adequacy of in-plant controls on the release of radioact ve m g, The program is designed to detect radioactivity concentrations which cou g result in radiation doses to individuals not exceeding the levels set forth in 10CFR50 Appendix I. Calculational Models An example of this is the detection of I-131 in milk.(Regula llirem-to ~ of 3.5 pCi I-131 per liter milk would result in a dose of 15 mi Allowing for an I I the thyroid of an infant consuming that milk for a year. open grazing season of six months, and a maximum event and sampling, the lower limit of detection at time ofofsampling between two half-lives must ' be 2 pCi/l (3.5 x 12/6 x 1/4 = 1.8). A supplemental monitoring program for sediments This ** and . 3 a tesult of an agreement with the Massachusetts Wildlife Federation. i l g supplemental program is designed to provide later informat verify the adequacy (or, alternatively, to provide a basis for As part of the modifications) of the long-term marine sampling schedules. ll be l I supplemental program, analysis of mussels for isotopes of plutonium dible wi performed if radiocesium activity should exceed 200 pCi/Kgm in the e I portions.
** supplemental provision
_. - - - . ~ D-2 _ _ . _ _ _ _ _ l E _ __- . _ _ .
I The 200 pCi/Kgm radiocesium " action leval" is beced on ecleulctions which if radiocesium from plant releases reached this level, I showed that plutonium could possibly appear at levels of potential interest.* calculations also showed that the dose delivered from these levels of The plutonium would not be a significant portion of the total dose attributable I to liquid effluents. The program was also designed to be consistent, wherever applicable with The following I Regulatory Guide 4.8 (Issued for comment December 1975). 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 ataut 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 I 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 I group of samples is less than that for a single sample and The proportional to the square root of the number of samples.
vatism in this case is approximately n[ll', or about a factor of 3. is inversely conser-I 2. Air particulates are not analyzed for raiiostrontium. The program instead calls for this analysis in milk samples. This is justified because the air-cow-milk exposure pathway can be better mon-I itored at Pilgrim after the very low level releases of radiostrontium are reconcentrated in cow's milk (Ref. 1).
- 3. Soils and sediments are not routinely analyzed for Sr-90, but rather the analysis is done on a contingency basis. The rationale behind this is that Sr-90 vill not contribute to long-term radionuclide buildup
==til the =or = bund ==t s==== e=1ttins ==ctide= =vv==r in r=2=tiv 27 -5 large concentrations. Both Items 2 and 3 reflect the fact that in 3b 5 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 .g (fr = weapons testing fallout) and about 4/1000,000 of the direct deposi-5 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 tat!ve of realistic food chain pathways, considering local conditions.
l Results of the monitoring program will be used as " benchmarks" to verify l calculational models used to predict the consequences of effluent releases from the station. The models can then be employed to predict doses 5 g attributable to radiat! ion 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. I This approach does not require (nor is it always practical) that although mental media always be sampled from the " worst case" locations: sensitivity of the monitoring results might be improved by sampling from environ-locations which are reasonably close to " worst case" conditions. in rcasurable quantities having a potential dose (human food chain) I
- significance comparable to other nuclides if present at their detection limits.
I __D-3_.~. -
. - _ . - .,,,_w .
,y , -.
I - - - - - - Verification of the appropriate milk sampling locations on an annual basis is satisfactory as there are very few locations suitable for the I grazing of dairy herds in the vicinity of the plant (Ref. 2). This situation makes it unlikely the location of the nearest dairy herd (3.5 miles-W) will change. g
" 5. Annual sampling of beef forage (in place of beef) is adequate because beef cattle are not raised commercially in the vicinity of tha site.
However, cairy cows from the Plymouth County Farm are periodically sold f for beef. Feed (hay) from this location will be sampled to mmitor 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. Goundwater flow at the plant site is into Cape Cod Bay; there. fore, I 6. terrestrial monitoring of groundwater is not included in this program.
- 7. Poultry sampling is not performed because poultry in Plymouth County I feed almost exclusively on imported grain and are usually raised under shelter.
Field gamma isotopic surveys are conducted to monitor radioactivity in I 8. soil in lieu of laboratory analysis of soil samples. The technique has several advantages over laboratory analysis. First, analysis can be l performed on the same plot of land from survey to survey, and radio-activity build-up at the location can be accurately determined. Secondly, gamma exposu:'a rate is determined directly from this technique: hence compliance with 10CFR50 Appendix I levels can be investigated directly rather than itdirectly through soil sampling. I
- I 1
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References:
~~~
;
I, 1. Wrenn, M.E., " Review of Sr-90 Releases from Pilgrim 1 Nuclear Plant and a Comparison with Extant Environmental Levels", 1976.
- 2. Pilgrim Station Unit #2 PSAR, Appendix 11F, pp. 11FC-11 and 11A, amended June 15, 1976.
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1 TABLE 4.8.1 1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM 1 1
I 4 ! Locations i Exposure Pathway (Direction-Distance) Sampling and Type and frequency or Sample Type from Reactor Collection Frequency of Analysis i l \ ,
; AIRBORNE ,
i i Gross beta radioactivity at
, Particulates 11 (see Table 4.8.2) Continuous sampling over I one week least 24 hours af ter filter
! change. (a) Quarterly composite (by location) for gansna i isotopic. (b) i Radiciodine 11 (see Table 4.8.2) Continuous sampling with Analyzu weekly for 1-131
?
- canister collection weekly
Soil 11 (see Table 4.8.2) Once per three years Field ganza isotopic. (c) i Gamma exposure quarterly. r 1 DIRECT 20 (see Table 4.8.3) Quarterly l Plymouth Beach and
- Priscilla/ White llorse Beach Annually (Spring) Ganma exposure survey.
WATERBORNE Discharge Canal ce tinuous coaposit sample Ganina isotopic (b) monthly; l Weekly grab sample and composite for 11-3 j ; Bartlett Pond(NHW-7.8 (SE-1.7 mi.) mi.)(d) Weekly grab sample analysis quarterly. (c).
! Powder Point
, t AQUATIC .
,' Shellfish Discharge outfall Quarterly (atapproximate. Gamma isotopic (b); also see t
i Duxbury Bay -~~3-month intervals) - - - - - - - - - - - - note (f).
- Manomet Pt.
l Plymouth or Kingston liarbor
; ,i Harshfield (d) f Note (f) and beach surveys are supplemental provision.
l i
W W W W W W W W W W W W W W W W W W W i TABLE 4.8.1 (Cont'd) locations Exposure Pathway (Direction-Distance) Sampling and Type and Frequency ' cr Sample Type from Reactor Collection Frequency of Analysis l Irish Moss Discharge outfall Semi-annually Gamma isotopic (b) Hanomet Pt. t E111sv111e (d) Lobster Vicinity of discharge Four times per season Gamma isotopic D) on edible portions.
- gointffshore(d) Once per season , ,
Fish Vicinity of discharge Quarterly, Groups I and II (e) Gama isotopic (h) en i In season, Groups III and IV (e) edible portions (t) { point Offshore (d) Annually, each group _ . . . ! Sediments Rocky Point Semi-annually Gama isotopic (b) (c), ., Plymouth Harbor see also note (g)
- g Duxbury Bay e, Plymouth Beach 4, Manomet Pt.
Marshfield (d)
- INGESTION (Terrestrial)
Milk Plymouth County Farm Semi-monthly during periods when Gama isotopic (b) Sr-89, j (W-3.5 mi.)(h); Whitman animals 'are on pasture, other- 90 monthly; radiofodine Farm (NW-21 mi.) (d) wise monthly analysis all samples. . At time of harvest Gama isotopic (b) on j j Cranberries Manomet Pt. Bog (SE-2.6 mi.) edible portions. Bartlett Rd. Bog - (SSE/S-2 8 mi.) Pine St. Bog (WNW-17 mi.) (d)
' Note (g) is supplemental provision l
e
t l E E E E E E E 'M E W W W W W W g g g g i . I ! i TABLE 4.8.1 j (Cont'd) t
< Locations i Exposure Pathway (Direction-Distance) Sampling and Type and Frequency or Sample Type from Reactor Collection Frequency of Analysis l
i 4 i, T Karbott Farm (SSE-2.0 mi.)(h) At time of harvest Gama isotopic (b) i i uberous and on edible portions. { l green leafy Bridgewater Fann i vegetables (W-20 mi.) (d)
' Bref Forage Plymouth County Fann Annually Gamma isotopic (b) 1 3
j (W-3.5 mi.) (h) l - 4 j
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I Notes (a) If gross beta radioactivity is greater than 10 times the control value, gamma isotopic will be performed on the sample. , I (b) Cama isotopic means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. (c) If integrated gamma activity (less K-40) is greater than 10 times the control value (less K-40), strontium-90 analysis vill be performed on the sample. l (d) Indicates control location. (e) Fish analyses will be performed on a minimum of 2 sub-samples, consisting I 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 Alevife Bluefish Yellowtail flounder Cunner Rainbow smelt Atlantic herring I Atlantic cod Pollock Hakes Striped bass Atlantic menhaden Atlantic mackerel (f)* Mussel samples from four locations (immediate vicinity of discharge outfall, I Manomet Pr., Plymouth or Kingston Harbor, and Green Harbor in Marshfield)
'will be analyzed quarterly as follows:
One kilogram vet weight of mussel bodies, including fluid within shells vill
- be collected. Bodies will be reduced in volume by drying at about 1000C.
l Sample vill be compacted and analyzed by GE(Li) gama spectrometry or alternate technique, if necessary, to achieve a sensitivity ** of 5 pCi/kg for Cs-134, Cs-137, Co-60, Zn-65 and Zr-95 and 15 pC1/kg for Ce-144. The mussel shell sample from one location (the location nearest the discharge I canal unless otherwise specifie.d pursuant to licensee's agreement with Mass. WildlifeFederation)villbeanalyzedeachquarter. One additional mussel shell sample (from the Green Harbor location, unless otherwise specified I pursuant to Licensee's agreement with Mass Wildlife Federation) vill be analyzed semi-annually. Unscrubbed shells to be analyzed will be dried, processea, and analyzed similarly to the mussel bodies. Because of the s=all volume reduction in pre-processing of shells, sensitiv1-ties attained will be less than that for mussel bodies. The equipment and counting times to be employed for analyses of shells will be the same or I comparable to that er: ployed for mussel bodies so that the reduction in sensitivities (relative to those for mussel bodies) vill be strictly limited to the effects of poorer geometry related to lower sample volume reduction. Shell samples not scheduled for analysis vill be reserved (unscrubbed) for possible later analysis, depending upon recomendations of the review comittee. l
- Supplemental provision.
i
**All sensitivity values to be determined in accordance with footnote (a) to Table 4.8.4. , viz. , LLD a t 95: confidence level on Le ; 50% confidence = _ level on p (See HASL-300 for_definicions).
D-9 -- --
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I _ Notes (Cont'd) _ . - - . - _ . . If radiocesium (Cs-134 and Cs-137) activity exceeds 200 pCi/kg (vet) I in mussel bodies, the.se samples will be analyzed by radiochemical spearation, electrodeposition, and alpha spectrometry for radioisotopes of plutonium, with a sensitivity of 0.4 pC1/kg. (g)* Sediment samples from four locations (Manomet Pt., Rocky Pt., Plymouth Harbor, and head of Duxbury Bay) will be analyzed once per year (preferably early summer) as follows: Cores will be taken to depths of 30-cm, minimum depth wherever sediment conditions permit by a hand-coring sampling device. If sediment conditions do not permit 30-cm deep cores, the deepest cores achievable with a I hand-coring device will be taken. In any case, core depths will not be less than.14-em. Core samples will be sectioned into 2-cm increments, l and surface and alternate increments analyzed, others reserved. Sediment I sample volumes (determined by core diameter and/or number of individual cores taken from any single location) and counting technique will be ,
. sufficient to achieve sensitivities of 50 pCi/kg dry sediment for Cs-134, Cs-137, Co-60, 2n-65, and Zr-95 and 150 pCi/kg for Ce-144. In any case I individual core diameters will not be less than 2 inches.
- The top 2-em section from each core will be analyzed for Pu isotopes I J(Pu-238, Pu-239, 240) using radiochemical separations, electrodeposition, i
and alpha spectrometry with target sensitivity of 25 pCi/kg dry sediment. Two additional core slices per year (mid-depth slice from core samples qtaken at Rocky Point and Plymouth Harbor, unless otherwise specified j I hpursuant to licensee's agreement with Mass Wildlife Federation) will be i similarly analyzed. I (h) These locations may be altered in accordance with results of surveys discussed in paragraphs 4.8.D-3 and 4.8.D-4. l I - lI l I l 1I I I
- Supplemental provision D-10
E. I. - TABLE 4.8.2 AIR PARTICULATES. CASEOUS RADIOIODINE AND MTL SUP.VEILLANCE STATIONS I Sampling Location Distance and (Sample Designation) Direction from Reactor Offsite Stations East Weymouth (EW)
- 23 miles NW Plymouth Center (PC) 4.5 miles W-WNW Manomet Substation (MS) 2.5 miles SE /
Clef t Rock Area (CR) 0.9 miles S Onsite Stations , Rocky Hill Road (ER) 0.8 miles SE Rocky Hill Road (WR) 0.3 miles W-WNW Overlook Area (OA) 0.03 miles W Property Line (PL) 0.34 miles NW Pedestrian Bridge (PB) 0.14 miles N East Breakwater (EB) 0.35 miles ESE Warehouse (WS) 0.03 miles SSE I I
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- Control Station I '
1 I . D-11 ~
I . I . TABLE 4.8.3 EXTERNAL CAMMA EXPOSURE SURVEILLANCE STATIONS (TLD) Distance and Dosimeter Location (Designation 1. Direction from Station Offsite Stations East Weymouth (EW)
- 23 miles NW
- Kingston (KS) 10 miles WNW Sagamore (CS) 10 miles SSE-S Plymouth Airport (SA) 8 miles WSW North Plymouth (NP) 5.5 miles WNW Plymouth Center (PC) 4.5 milds W-WNW South Plymouth (SP) 3 miles WSW Manomet (MS) 2.5 miles SSE l
, Manomet (ME) 2.5 miles SE Manomet (MP) 2.25 miles ESE-S ,l Cleft Rock Area (CR)
- - ~~
0.9 miles S ~ 5 Saquish Neck (SN)** 4.6 miles NNWl *** Onsite Stations f Rocky Hill Road (ER) 0.8 miles SE Microwave Tower (MI) 0.38 miles S Rocky Hill Road (WR) 0.3 miles W-WNW Rocky Hill Road (B) 0.26 miles SSE I Property Line (H) 0.21 miles SSW Property Line (I) 0.14 miles W Public Parking Area (PA) 0.07 miles N-NNE I Overlook Area (OA) 0.03 miles W I
- Control Station Data from this surveillance station is subject. to -detector maintenance and retrieval by a private party not subject to control by the liennsee. Therefore, the requirement to maintain this station is contingent on station availability and maintenance by the outside party. '~
~"
l *** Supplemental provision
'E ' E E E E E E E E E E E E E E E E E ,E i
l TABLE 4.8.4 l t (d) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS I t Lower Limit of Detection (a) .. i Wet solids Dry solids Milk' I Water Airborne particulate ' Analysis pC1/1 or gas - pCL/M3 pC1/Kg pCi/Kg pC1/1 I Gross beta 2 1 x 10-2 e l H-3 330 Kn-54 15 130 60 I Fe-59 30 260 120 , i
, Y '
0 CO-58,60 15 2 x 10-2 130 60 Zn-65 30 260 120 l Sr-89 10
- 40 10 t
Sr-90 2 8 '150 2 Zr/Nb-95 10 1-131 7 x 10-2 80(b) 2 (c) i Cs-134,137 15 1 x 10-2 80 150 15 , , e- I Ba/La-140 15 15 ! i l I (a) The nominal lower limits of detection at the 95% confidence level (defined in the ERDA Health and Safety Laboratory procedures manual, HASL-310). (d) This table applies to all analyses other (b) Applies only to analysis of green leafy vegetables. than those for which higher sensitivities appt in accordance with Notes (f) and (g) to Table (c) Sensitivity with 257. error at the 95% confidence level. 4.8.1. _ _ _ , _ , _ , , , , _ _ .
I g ____ _ g- , l l Lv Green Harbor Oe l Cape ' Cod Bay E ! O Ouxbury' l Kingston Harbor Bay o 1 2 3 a s g ,3 , SCALE IN WLES u . A Rocky Point
\ Warren O Cove Q i
sA I - e U Manomet andstage Points I
- LEGEND ,
0 lRISH MOSS ' 5;;;,y;;;e l O SOFTSHELL CLAMS ' Harbor e MUSSELS A SEDIMENT ; E QUAHOGS , I l1 Figure 4.8-1 Typical Ifo11use, Alsae and Sediment rampling stations
^
l I - e-14 .. . - . . -
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~ - - ~6.9.C Unique Reporting Requirements
- 2. Environ:nental Program Data
- 4. Annual Report. A report on the radiological environmental surveillance program for the previous 12 months of operation shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 90 days after January I 1 of each year. The reports shall include sununaries, interpret-ations, and statistical evaluation of the results of the radio-logical enviranaental surveillance activities for tM report period, including a comparison with preoperational studies,'
. operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall I also include the results of any land use surveys which affect the choice of sample locations. If harmful effects or evidence of irreversible damage are detected by the monitoring, the I ,
licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem. Results of 4 1 radiological environmental samples shall be I summarized and tabulated on an annual basis. In the event that some results are not available within the 90-day period, the report shall be submitted, noting and explaining the reasons I for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. Anomalous measurement report. If radioactivity in an indicator I b. medium from an off-site location is found and confirmed at a level exceeding ten times the control station value, a written report shall be submitted to the Director of the NRC Regional
- Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 10 days after confirmation.** This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.
I . I ** A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate. The results of the con-I firmatory analysis shall be completed at the earliest time consistent with the analysis, but in any case within 30 days of receipt of the anomalous result. I - lI l
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*1 PROPERTY LINE tOI
- 13 ROCKY HILL ROAO (8) 2 PROPERTY LINE (F)
- 14 MICROWAVE TOWER (MT) 3 PROPERTY LINE (1) 15 EMERSON ROAO (EMI
- 4 PROPERTY LINE (G)
- 16 WHITE HORSE ROAO fwHF 5 ROCKY HILL ROAO (Al
- 17 PROPERTY LINE (EW 6 PROPERTY LINE (H) 18 ROCKY HILL ROAO (WR) 7 PUBLIC PARKING ARE A (PA) 19 PROPERTY LINE Ul*
I 8 PEDESTRIAN 8 RIDGE (PS) 20 PROPERTY LINE lKP . 9 OVERLOOK AREA ICA) 21 ROCKY HILL ROAO (ER) 10 E AST 8RE AKWATER (ES) 22 PROPERTY LINE (LP 11 PROPERTY LlP'E (C)
- 23 WAREHOUSE IWS) 12 PROPERTY LINE (H8)
- 24 PROPERTY LINE (PL)
O OOssMETERITLD) A AIR PARTICULATES AND DOSIMETERS (TLD) I
- additional station not required by Specification 4.8.D.1 Figure 4.8.2 Location of Onsite Monitoring Stations I .
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- 4 PLYMOUTH CENTER iPC) 12 COLLEGE PONO ICP)
- 5 SOUTH PLYuouTH 15P1 13 SAGAMORE ICSI 6 O AYSHCRE ORIVE 180# 14 PLYMOUTH AIAPOmf (34 7 CLIFT ROCK A A E A (C.H 15 EAST WEYMOUTH IEwl I a u A N O u ET .MP) 16. Saquish Neck. (SN)
- additional stations nOC required by Specification 4 . 8. .D 1 Figure 4.8.3 Location of Offsite Monitoring Stations l -
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I I I I APPENDIX E - 1980 GARDEN AND MILK ANIMAL SURVEY (memo on results of survey) I l I j I I . I I I , r
;
NOD #80-924 1
,,,,,, OFFICE MEMORANDUM ,_ ,,
CO370N Eot ON COMPANY ILE vi-... ,
)
v.ameas ur TO . ..E. .L .Ziemianski -.EnOM. Jn L,...So' '30 . . D ATr.. . 91U/.30 l Ma:L. - PHON c. .. . l I . 1980 CARDEN & MILK ANIMAL CENSUS , As required by PNPS #1 Environmental Technical Specification, on 9/10/80 and 9/H /80 I conducted the 1980 Census. I confirmed the existance of gardens near the site boundaries 0.7 milcs west and ' 0.6 miles ESE from which I obtained samples. Thesegardensaretheclosestagd largest in the vicinity of PNPS (although they are problably less than 500 ft ). I They de represent conservative garden locations for sampling analyses and dose alculation.
)
1 I I conducted a street by street search of the area within 1 mile of PNPS to determine the locations of any cows er goats. I found no such animals or struct-ures which would indicate the presence of such animals within 1 mile. In addit-ion, I contacted the Plymouth County Animal Inspector, Ms. Carolyn Daum, (224-2826) I who gave me the following locations of cows and goats: Owner Animal Location I John Davis Warren Raymond 3 beef cows 2 goats Beaver Das Road, Manomet Off White Horce Road, Manomet l (224-2398) l John Almeida 2 goats White Oak Drive, Plymouth 046-3896) Nancy Lloyd 5 goats Lond Pond Road, Plymouth I (224-8719) Plymouth Plantation 1 cow Warren Avenue, Plymouth I contacted the owners of the milk producing animals and found the following: Warren Raymond (Ms. Florence Raymond) - Sold the goats in the spring. John Almeida - Presently has no milk producing animals. Nancy Lloyd - Her goats do not presently produce milk, although they have in l E the past. She does not sell the milk, but uses it for personnel W consumption. When the animals give milk it is normally very little since they are miniature goats (not full size). I have concluded that our present location for milk sampling (Plymouth Plantation-2.2 miles West) continues to be the best indicator station. l I /gn t f.
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