ML19309B853
| ML19309B853 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/31/1980 |
| From: | Bartal L, Rafi A, Reichert E BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19309B852 | List: |
| References | |
| NUDOCS 8004070276 | |
| Download: ML19309B853 (50) | |
Text
G RADIOLOGICAL EIIVIRO?iMEIITAL I40fiITORItiG PROGRAM ANIiUAL REPORT FOR THE CALVERT CLIFFS NUCLEAR PLAfiT UtlITS 1 AND 2 JANUARY 1 - DECEMBER 31, 1979 L. J. Bartal A. Rafi E. C. Reichert J. 'd. Stcut , Jr.
BALTIMORE CAS AIID ELECTRIC COMPAITY
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March 1980 Dh3 13k
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I January 1 - Dece=ber 31, 1979 Docket Nos. 50-317/318 TABLE OF CONTENTS PAGE LIST OF FIGURES --- - -- - - - - - - - --- 1i LIST OF TABLES ----------------------- ii A.
SUMMARY
- - - - - - - - - -- -- 1 B. INTRODUCTION-- -- - - - - - - - - - - - - - 3 C. PROGRAM------ - - - - - - - - - - - - - - - - - - - -
3 C. 1 Obj ectives---- - - - -- - - - - - - - 3 C. 2 Sa=ple Collection- --- --- 4 C. 3 Data Interpretation-- ---- - -- h C. h Program Exceptions- - - - - - - h D. RESULTS AND DISCUSSIONS-- -- --- -
5 D. 1 Aquatic Environment--- - - - --- -
5 D. 2 At=ospheric Environ =ent-- - - --- 7 D. 3 Terrestrial Environ =ent - - -
9 D. L External Radiation--- -
10 E. CONCLUSION----- - - - - - - - - - - - - - --
11 F. REFERENCES------ -- - --- 20 APPENDIX A - Environmental Sa=pling Location--- 22 APPENDI'( B - Analytical Data Tables----- 26 i
s January 1 - Dscs=bar 31, 1979
- Dockst Nos. 50-317/318 1
LIST OF FIGUPIS FIGURE TITLZ PAGE A-1 Map of Southern Maryland and Chesapeake Bay Showing Location of Calvert Cliffs Nuclear Power Plant - --- 24 A-2 Radiological Inviron= ental Monitoring Stations in the Vicinity of the Calvert Cliffs Nuclear Pcver Plant-------- - - ---
25 LIST OF TABLES TABLE TITLE PAGE 1' Synopsis of the 1979 Calvert Cliffs Nuclear Power Plant Radiological Environ = ental !!cnitoring Pro gram--- - -- 12 2 Annual S m ry of Radioactivity in the Environs of the Calvert Cliffs Nuclear Power Plant Units 1 and 2 ---
15 A-1 Locations of Environ = ental Sa:pling Stations for the Calvert Cliffs Nuclear Power Plant--- --
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n' January 1 - December 31, 1979 Docket Mos. 50-317/318 A.
SUMMARY
During this operating period for Calvert Cliffs Unit 1 and Unit 2 Radiation Management Corporation (RMC) and Baltimore Gas and Electric Company (BGaE) analyzed. samples from the aquatic, atmospheric,'and terrestrial environments.
Baltimore Gas and Electric Company made measurements of external radiation.
A total of 1,044 analyses were performed on 746 environmental samples during the pericd covered by this report. In addition, BC&E personnel analyzed 612 thermoluminescent dosimeters (TLD's) for ambient radiation dose rates.
Samples of. the aquatic environment included bay water, fish, shellfish
-(oysters, crabs) and sediment. Bay water was analyzed for tritium, Sr-89 and Sr-90 and gamma emitting nuclides. Fish, shellfish and sediment were analyzed for gamma emitting nuclides. Fish bones and sediment were also analyzed for Sr-89 and Sr-90.
Samples from the atmospheric environment included air and precipitation. Air particulates and gaseous iodine were collected on glass fiber filters and-silver' zeolite molecular sieve cartridges, respectively. The particulate filters were analyzed for gross beta activity and for gamma emitting nuclides while the molecular sieve cartridges were analyzed for I-131. Cuarterly composite analyses for Sr-89 and Sr-90 on air particulate filters are reported. Precipitation was analyzed for gross beta, H-3, Sr-89, Sr-90 and gamma emitting nuclides.
Monitoring of the terrestrial environment included vegetation, soil, and ground
' water samples. The vegetation and soil samples were analyzed for gamma emitters and Sr-89 and Sr-90. The ground water samples were analyzed for H-3 and gamma emitting nuclides.
Measurements of external radiation were performed by analyzing thermoluminescent dosimeters from 13 locations surrounding the plant.
Low levels of-various radionuclides were occasionally observed in the environment surrounding the plant during 1979. Most of these observations were attributed to the fallout from recent and past atmospheric nuclear bomb testing. A few of these observations, however, may be directly related to the operation of the plant. Tritium was observed in three samples taken from the discharge area in concentrations greater than that generally observed in previous years. Silver-llCm was observed in oyster samples from Camp Coney in concentrations comparable to previous years. And Co-58 and Co-60 appeared in sediment samples taken fecm the-intake area where.they had only sporadically appeared in the past. In all of these cases, the activity was low and consequently would have had little impact on the surrounding environment.
The results of the dose calculaticns perferned by using the plant effluent release data, on site meteorological data and appropriate pathways indicate: (a) thyroid inhalation maximum doseoof 0.133 mrem (at the On Site location 18 about 2000 feet southeast from the plant vent) which is less than 1% of the pernissible limit of 15 mrem / reactor-year specified in Appendix I 10 CFR 50, and less than 0.2% of the 1
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January 1 - December 31, 1979 Decket Nos.-50-317/318 acceptable limit of 75 mrem / year specified in 40 CFR 190 Environmental Radiation Protection Standards For Nuclear Power Operations; (b) thyroid dose (maxinum via
. inhalation and milk pathway) of 0.24 mrem (at the farm location 16) which is less than 2% of the permissible-limit of 15 mrem / reactor-yr (Appendix I 10 CFR 50) and less than 0.4% of the acceptable limit of 75 mrem / year specified in 40 CFR 190; (c) a total body gamma immersion maximum dose of 0.026 mrem (at the On Site location 18) which is less than 1% of the permissible dose of_5 nrem/ reactor-year specified in-Appendix I 10 CFR 50, and less than 0.2% of the acceptable dose of 25 mrem / year specified in 40 CFR 190; (d) a total body dose (maximum.
via all liquid pathways) of 0.015 mrem which is less than 1% of the permissible limit of 3 mrem / reactor-year (Appendix I 10 CFR 50) and less.than 0.1% of the acceptable limit of 25 mrem /yr specified in 40 CFR 190.
Thus it is concluded, based upon the levels of radioactivity observed and the various dose calculations, that the operation of the Calvert Cliffs Nuclear Power Plant Units 1 and 2 did not cause any significant changes in the observed concertrations of environmental radicactivity or anbient radiation levels.
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January 1 - December 31, 1979 -
Docket Nos. 50-317-318
- 3. INTRODUCTION Baltimore Gas and Electric Company (3G&E) has been conducting a radiological environmental monitoring program in the envirens of the Calvert Cliffs -
Nuclear Power Plant since the summer of 1970. Results of the analyses of environmental samples for the preoperational and operational periods through 4 December 31, 1978 have been reported in a series of documents (1-15).
This report presents the type and uuaber of samples analyzed, the knalyses i performed (see Table 1 for a sumary of the surveillance program) and the data generated during 1979 Interpretation of the data and conclusions are presented.,
Appendix A summarizes the sample media and relative sampling l'ocations .vith respect'to the Calvert Cliffs Nuclear Power Plant (Table A-1 and Figure A-1).
Figure A-2 shows the location of the Calvert Cliffs Nuclear Site in relation to the Chesapeake Bay and Southern Maryland. The Calvert Cliffs site is an operating nuclear generating station consisting of two PWR Units. Unit 1 achieved criticality on October 7,197k, and comenced co==ercial operation
. in May 1975 Unit 2 achieved criticality on November 30, 1976, and vent into ec uercial cpers. tion April 1, 1977. Since July 29, 1977,.we have been operating under combined Environmental Technical Specifications for Units 1 and 2 (16).
Prior to this date, separate Environ = ental Technical Specifications (17, 18).
- were in effect for each unit.
C. PROGRAM The environmental surveillance data collected during this reporting period were ec= pared with that generated in previous periods to assess the environ-mental radiological impact of the operation of Calvert Cliffs Nuclear Power Plant Units 1 and 2.
C.1 Objectives The objectives of the operational radiological envircemental program are:
- a. To deter =ine whether any statistically significant increase cccurs in the concentration of radionuclides in important pathways,
- b. ' To detect any possible buildup of long-lived radienuclides in the environ =ent.
- c. To =cnitor and evaluate ambient radiation levels.
- d. To verify that radioactivity and. ambient radiation levels attributable to the plant are within the limits specified in the Technical Specifications (16).
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w January 1 - rece=ber 31, 1979 Docket Nos. 50-317/318 j i
C.2 Sa=ple Collection The locations of the individual sa:pling stations are listed in Table A-1 and shown in Figure A-2. All sa=ples were collected by consultants to, or personnel of, Balti= ore Gas and Electric Co=pany according to BG&E operating proceduras-(19). Radioche=ical analyses were performed by RMC and BG&E.
Ambient radiation measure =ents were =ade by Balti= ore Gas and Electric Cc=pany personnel in accordance with an operating procedure (22). These measure =ents were made with ther=clu=inescent dosi=eters as previously described (10).
C.3 Data Interpretation ;
Analytical data generated during the progra= are routinely evaluated. In the interpretation of the data several factors are i=portant and are discussed here to avoid repetition in the sections that follow.
It is characteristic of environ = ental =enitoring data that =any results occur at or below the minimu= detectable level (MDL). In this report, all results occurring at or below the relevant MDL are reported as being "less than" the MDL value.
Annual =eans, range and typical MDL's are presented for each type of analysis for every sa=ple.=edia. Results of individual analyses are also presented with applicable standard deviations.
In the case of gar =a spectrc=etry, if no activity of a particular nuclide was found, no average was calculated for that nuclide.
C.h Program Exceptions Surveys conducted in April and October 1979 deter =ined that there was a milk cov vithin five =iles of the plant, but the ovner was unwilling to provide = ilk samples. Therefore, no = ilk samples were analyzed during this reporting period.
A shore line. search for rooted aquatics is conducted at the Flag Ponds area every month. Additionally, the area of shallow vater at Flag Ponds is swept by shore seine every =onth. For 1979 there were no rooted aquatic plants obtained.
The co==ercial pound nets south of. Cove Point were not successfully deployed during 1979 and the coc=ercial fisherman, therefore, eculd not =ake any catch during the year. Sa=ples of edible fish vere, however, obtained during August and October frc= our =enthly benthic travi surveys. The fish collected vere obtained fro: sa:pling locations in the vicinity of the Plant.
Sa:ples of crabs were not available during the first quarter of 1979 for reasons previously described (10).
January 1 - December 31, 1979 Docket Nos. 50-317/318
, D. RESULTS AND DISCUSSIONS All the environ = ental samples were either analyzed by EMC laboratory procedures
-(20) or EG&E laborato y procedures (21). The analytical results for this reporting period, presented in Appendix 3 and also s m arized on an annual basis in Table 2, have been divided into four categories-aquatic, at=ospheric, and terrestrial environment, and external radiation.
D.1- Aquatic' Environ =ent The aquatic environment surrounding the plant was monitored by analyzing samples of bay water, aquatic organis=s, and bottom sediment. These sa=ples were obtained from various sampling locations on the Chesapeake Ba'/ near the plant.
D.l.a Bay Water Monthly bay water sa=ples were taken from two locations; the Plant Intake area (location 8) and the Plant Outfall area (location 7). These samples were analyzed for H-3, ga==a emitters, sud Sr-89 and Sr-90.
Monthly analyses for E-3 in these sa=ples exhibited concentrations ranging from(108 to 13282133 pCi/l for locatien 7 and from 4.108 to 206i97 pCi/1 for location 8. Most of the results were vell within the ranges observed in both the'precperational (6) and previous operation (15) periods; however three results, all from location 7, vere outside these ranges (viz., 1106*111 pCi/l in February, 8752137 pCi/1 in June, and 13281133 pCi/l in September). These -
outlying results are probably related to routine releases of tritium from the plant.
Monthly analyses for ga==a emitters in these sa=ples revealed that no detectable concentrations of activation or fission products vere present.
Quarterly analyses for radiostrontium in these samples showed no detectable concentrations 1
of Sr-89 and two detectable concentrations of Sr-90 (viz. ,
0.50 0 37 pCi/1 in the second quarter frem location 8 and 0.70t0 .67 pCi/l in the third quarter sample from location 7). Both of these detectable concentrations of Sr-90 are ec= parable to the concentrations observed in the preoperational (6) and previous operational periods (15).
D.1.b Ac_uatic Organis=s Quarterly samples of aquatic organisms were taken from five locations; the vicinity of the power plant - from Kenwood Beach to Rocky Point, Kenvood Beach
-(locatica 3), Rocky Point (location h), Camp Coney (location 5) and Plant Intake area (location 8). The edible portions of these samples were analyzed for ga-a emitters, and samples of fish bones were analyzed for Sr-89 and Sr-90.
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$ . January 1 - D;cembIr 31, 1979 Docket Nos. 50-317/318 Quarterly analyses for ge==a e=1tters in all the fish and crab sa=ples,_and the cyster sa=ples from location 3 revealed that no detectable eencentrations of fission and activation products were present. However, the analyses of the oyster sa=ples from location 5 showed detectable concentrations of. Ag-llCm ranging from 8814 to 266 11 pCi/kg. The presence of Ag-llCm in these sa=ples is =ost probably due to a bioaccu=ulation of this nuclide, present in routine releases from the plant.
Quarterly radiostrontium analyses of the bones from the fish sa=ples showed only one detectable concentration of Sr-89 (26! 9 pCi/l in the fourth quarter spot sa=ple) and shoved detectable concentrations of Sr-90, ranging from 16*3
~
to. 37tl4 pCi/kg, in all the sa=ples analyzed. The single positive Sr-89 result
=ay be related to plant operation. It is also possible that this positive value is a spurious statistical result of the radiochemical procedure for deter =ining strontiun. The Sr-90 results, on the other hand, fall into the same general
, patterns observed in both the preoperational (6) and previous operational periods (15).
D.l.c Sediment Quarterly sediment sa=ples were taken from four locations; Ca=p Coney (location 5), long Beach (location 6), Plant Intake area (location 8), and Plant Outfall area (location 7). These samples were analyzed for ga==a emitters and Sr-89 and,Sr-90.
Quarterly analyses for ga==a emitters in these samples revealed the presence of Cs-137 in all sa=ples from all locatiens (ranging frem 191f21 pCi/kg to 1163 77 pCi/kg); the presence of Co-58 in all sa=ples from Iccation 8 (ranging from 5h 19 pCi/kg to 553 76 pCi/kg); the presence of Cc-60 in all sa=ples fres ,
location 8 (ranging frem 23*23 pC1/kg to 701 115 pCi/kg); and the presence ~
)
of Ce-lhh in the sa=ples frc= locations 6 and 8 (ranging from 398 92 pCi/kg !
to 1225*192 pCi/kg). The ranges of Cs-137 exhibited are typical of the ranges !
observed in the preoperational (6) and previous operational periods (15) and are probably related to past nuclear be=b testing. In addition, the presence :
of Ce-lkk at location 8 and at the centrol location 6 are also cost probably I related to past. atmospheric testing, since 'this nuclide was one of the "=ain fa11 cut nuclides" of the nuclear bomb testing conducted in 1977 ani l978 (lk, 15), and it has long enough half-life to still linger in the environ =ent. On the other hand, the presence of Co-58' and Co-60 exclusively in *he vicinity I of the plant suggests that they are plant-related. l Quarterly radiostrontium analyses shoved no detectable concentrations of Sr-89 in any of these sa=ples and only the sporadic presence of Sr-90 in the sa=ples tdcen from all locations. - The Sr-90 results ranged frem 25 23 pC1/kg to I 103*79 pCi/kg, and they are typical of the ranges observed in the precperational (6) and previous operational (15). periods, i
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e-January 1 - December 31, 1979 Docket Nos. 50-317/318 D.1.d Discussion-
-Dose calculations, utilizing the plant's effluent release data (23) and the appropriate regulatory guide (2h), were made to assess the plant's radiological impact-on the surrounding aquatic environ =ent. The calculations included dose esti=ates received frem the liquid pathways of fish and invertebrate ingestion and from shore line exposures. The results are: (a) a total body dose of about 0.015 m rem which is less than 1% of the permissible total body dose of 3 = rem / reactor / year ( Appendix I to 10 CFR Part 50) and less than 0.1% of the whole body dose of 25 mrem / year as specified in ho CFR Part 190 Environ = ental Radiation Protection Standards for Nuclear' Power Operations; and (b) a thyroid dose of about 0.05 m rem which is less than 1% of the permissible dose of 10 = rem / reactor / year to any organ (Appendix I to 10 CFR Part 50) and less than O.1% of the thyroid dose of 75 =re=/ year as specified in h0 CFR Part 190 Environ =2ntal Radiation Protection Standards for Nuclear Power Operations.
Thus, it is apparent, based upon the results of the =enitoring program and the dose calculations performed, that the plant's contribution to the radio-activity of the surrounding aquatic environment was insignificant during the year 1979 D.2 Atmospherie Environment The atmospheric enviren=ent was =onitored by analyzing sa=ples of air particulate filters, silver zeolite cartridges, and precipitation sa=ples. These sa=ples vere collected from various locations surrounding the plant.
D.2.a Air Particulate Filters Weekly composite air filters were collected frem seten locations; On' Site i
(location 17), On Site (location 18), Knotty Pine (location 19), Lusby (location 20), Long Beach (location 21), Cove Point (locatica 22), and Taylors Island (location 23). These sa=ples were analyzed for beta activity, ga==a emitters, and Sr-89 and Sr-90.
Weekly analyses for beta activity in air filters revealed that the range of data for each site followed similar trends. The ranges started with a =axi=um value at the beginning of the year, then diminished gradvally and consistently throughout .the succeeding weeks until a minimen value was reached at the end of the year. These trends are' probably due to the decay and "vashout" of residual activity from the atmospheric nuclear testing carried out during 1977 and 1978.
Menthly analyses for ga==a emitters showed only the sporadic presence of the fission by-products Cs-137 and Ce-1kh, both of which appeared exclusively in the first part of the year. These two radienuclides were typica]ly present in.the fallout patterns observed after the nuclear be=b testing of the preceding year (lk,15), and both have half-lives sufficiently long enough to reappear in sa=ples al= cst a year later.
T
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4 January 1 ' December.31, 1979 Docket Nos. 50-317/318 Quarterly radiostrontium analyses ~showed detectable' concentrations of Sr-89 at four locations during the third cuarter [viz., (1.75, 0.79)x10-3 at location- 17,'(0.91+0.78)x10-3 pci/n3 at location 19, (0788+0.32)x10-3 pCi/m3
~
at location 20 and (1.10 0.84)x10-3 1 pCi/m3 at location 21 ] nnd detectable
. concentrations of Sr-90 at all sites during the first and second quarters,
. ranging from'(0.22:0.21)x10-3pci/m3 to (0.75 0.31)x10-3 pCi/m3 . In view 3
-of the short half-life of Sr-89, its presence is due to a source recent in
. origin, and probably related to the releases from the plant. The Sr-90 con-centrations in large part, are most probably related to past nuclear weapons testing, since the concentration ranges are typical of previous years (14,15),
and the trend of data exhibited (frcm maximum at the beginning of-the year to the minimum at the end) mirror the trend in beta activity.
D.2.b Air Iodine .
Weekly composite radiciodine samples were collected from five locations; On Site (location 17), on Site (location 18), Lusby (location 20), Cove Point (location 22), and Taylors Island (location 23).
Radioiodine analyses performed on the samples from all locations exhibited no detectable concentrations of I-131.
D.2.c Precioitation Monthly composite preceiptation samples were collected from one site, On Site (location IS), and were analyzed for gross beta, H-3, gamma emitters, and Sr-89 and Sr-90.
The results of the monthly analyses of the precipitation samples for beta activity, and the quarterly analyses.for tritium and Sr-89 seem to fall into the'same general pattern as the results of air particulate filters for beta activity and Sr-90 (i.e., a maximum at'the geginning of the year, decreasing to minimum at year's end). This pattern, as discussed previously, indicates that the observed activity is probably due to past nuclear testing. The analyses for gamma emitters and Sr-90 revealed that no detectable concentra-tions of either were observed in any of the precipitation samples.
D.2.d Discussion
'4 hole body and thyroid dese calculations were performed for various receptor stations surrounding the plant, utilizing the plant's effluent release data (23),
the prevailing. meteorological conditions, and the appropriate regulatory guides (24,25).- The results are: (a) that en site location 18 was the recepotr station with the highest overall doses; (b) a total body doe of about 0.026 mrem which is-less than l% of ty.c permissible total body dose of 5 mrem / reactor / year
.( Appendix I to 10 CRF Part 50) and less than 0.2% of'the whole body dose of 25 mrem / year as specified in 40 CRF Part 190 Environmental Radiation Protection Standards for Nuclear Power Operations; and (c) a thyroid dose of 0.133 mrem which is less than 1% of the permissible thyroid dose of 15 mren/ reactor /
year (Appendix ~I to 10 CFR 50) and less than 0.2% of. the thyroid dose of. 75 Emrem/ year as specified in 40'CFR Part 190 Environmental Radiation Protection Standards.for Nuclear Power-Operation.
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January 1 - December 31, 1979'
. Docket Nos. 50-317/318
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Again it. is apparent, based upon the results of the monitoring program and the idose calculations performed,' that the plant's contribution to the radioactivity of the surrounding atmospheric environment was insignificant during the year
- 1979 D.3 Terrestrial Environment The terrestrial environment was monitored by analyzing sa=ples of vegetation.
soil,.and well. vater. These samples were collected from various sampling locations near the plant.
D.3.a. Vegetation Vegetation samples were collected from three locations; On Site (location 14),
a nearby farm (location 15), and another nearby farm (location 16). These samples included cabbage, corn, radishes, sunflever, and tobacco. They were analyzed for gacma emitters and Sr-89 and Si-90.
Analyses for gamma emitters in these samples revealed that only naturally occurring radionuclides were present in detectable concentrations.
Radiostrontium sanalyses of these samples showed only one detectable concentra-tion of Sr-89 (viz. , 2Th*190 pci/kg in the October sunflower sa=ples frem location ik) and showed detectable concentrations of Sr-90, ranging frem 291 26 pci/kg .to 18ho!280 pci/kg, in al=ost all of the samples analyzed.
The single positive Sr-89 result may have been plant related, though the rest of the vegetation sample results do not readily support this. It is also ,
pos'sible that this positive value is a spurious statistical result of the radiochemical precedure for deter =ining strontium. The Sr-90 results, on l the other hand, fall into the same general pattern observed in the preceding l years when there vere nuclear weapons testing (lk, 15). In addition to this, ;
the half-life of Sr-90 is 1cng enough to linger in the environment for extended 1 periods. Thus, these Sr-90 results are most probably attributable to the i fallout from the' past at=ospheric testing. l l
D.3.b -Soil Se=iannual soil samples were taken from three On Site locations; 11,12, and 13 These samples were analyzed for ga=ma emitters and Sr-89 and Sr-90. j Analyses for ga==a e=itters in these samples revealed a single detectable concentration of Ce-lkh (VIZ. , 289!s9 pci/kg in the March sample from location 13) and revealed detectable concentrations of Cs-137, ranging ,
frc= 6h 26 pCi/kg to 293 35 pci/kg, in five out of the six sa=ples analyzed. !
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January 1 - December 31, 1979 Docket Nos. 50-317/318
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As cited earlier, both of these radionuclides were observed in air particulate filter samples during the year, and it was suggested then that.these two 5dionuclides were related to past ' nuclear testing. In conjunction with this, the appearance of these nuclides in soil samples and sediment samples, taken during the year, would reflect an atmospheric "vashout" phenomenon of the long-lived by-products from previous nuclear bomb tests.
Radiostrontium' analyses of these samples exhibited no detectable concentra-tions of Sr-89 and only the sporadic presence of Sr-90 in the sa=ples analyzed, ranging from 36223 pCi/kg to 8k235 pCi/kg. This range of Sr-90 results is comparable to the ranges observed'in the preceding years of 1977 and 1978, and it is most probably the result of past nuclear weapons testing (6, 15).
D.3.c Well Water Quarterly well vater samples were collected from five locations; Che.sapeake County Club (location 2), On Site (location 10), Long Beach (location 21),
and White Sands Club (locations 25A and 253). These sa=ples were analyzed for H-3 and ga=ma emitters.
Both the quarterly analyses for tritium and the quarterly analyses for gamma emitters in these samples revealed that no detectable concentration of any fission or activation by-products were present.
D.3.d Discussion i
As with the aquatic and at=ospheric environment, the analytical results suggest- )
that the plant's contribution to the natural and man-made radionuclide inventory I of the terrestrial environ =ent was minimal . There were a few fission by-products, namely Sr-89, Sr-90, Cs-137, and Ce-1kh, which could be attributable to either plant operation or past nuclear testing. Regardless of which of these was the source of the nuclides in question, dose calculations were performed for pathways of interest to assess the plant's radiological i= pact on the surrounding terrestrial environment. Plant effluent release data for batch and continuous releases (23) and en site meteorological data were utilized in confor=ance with appropriate regulatory guides (2h, 25). The result of these calculations was an estimated thyroid dose of 0.2h c rem which is less than 2% of the allevable dose of 15 mres/ reactor /yr to any organ as specified in Appendix I to 10 CFR Part 50, and less than 0.k% of the permissible thyroid dose of 75 mres/yr (h0 CFR Part 190 Environmental Radiation Protection Standards for Nuclear Power Operations).
Thus it is apparent frem the above discussion that the plant operatica during 1979 did not =ake any significant contribution to radioactivity in the surrounding terrestrial environment.
D.h External Radiation l
Monthly ther=oluminescent dosimeters were taken from 13 locations surrounding l the plant, namely: Plant Outfall (location T), On Site (location 17), On Site l (location 18), Knotty Pine (location 19), Lusby (location 20), Long Beach j 9
10
January 1 - December 31, 1979 Docket dos. 50-317/318 (location 21), Cove Point.(location 22), Taylors Island (location 23), Cn Site (location 2h), White Sands Club Sign (location 25), St. Leonard (location 26), Solomons (location 27), and Bertha (location 28). The dosimeters were read for =re=s of external radiation dose.
The TLD data for each site are co= piled in Table 3-15 and are presented on an annual basis in Table 2. The means and ranges expressed in Table 2 vere ec= pared with the means and ranges for the previous years of 1977 and 1978.
This comparison revealed that =eans and ranges for 1979 vere less than those observed in the two preceding years.
In order to assess the contribution of the plant to ambient radiation levels, ga==a i=mersion dose calculation, utilizing the plant's gaseous release data
.(23) and on site meteorological data, were made. The =aximum plant contribution is esti=ated to have been 0.026 = rem at locatien 18 vhich is less than 15 of the allevable whole-body dose of 5 mre=/ reactor / year as specified in Appendix I to 10 CFR Part 50, and less than 0.2% of the whole-body dose of 25 =re=/yr (h0 CFR ;
Part 190 Environ = ental Radiation Protection Standards for Nuclear Power Operaticus). i It is apparent from the above discussion that the plant operation during 1979 did not =ake any significant contribution to a=bient radiation levels.
E. Cenelusion l Detectable levels of radicactivity were observed occasionally in sa=ples frem various locations during the year. The =ajority of these observations are attributable to the at=cspheric nuclear bomb testing conducted in 1977 and 1978. However, a few of these observations =ay be directly related to -
the operation of the plant (e.g., H-3 in bay water, Co-58 and Co-60 in sediment, and Ag-llom in oysters).
The results of the dose calculations perfor=ed by using the plant effluent release data, on site =eteorological data and appropriate pathways indicate: (a) thyroid
-inhalation =ax1=um dose of 0.133 = rem (at the on Site -location 18 about 2000 feet southeast from the plant vent) which is less than 1% of the per=issible li=it of 15 = rem / reactor-year specified in Appendix I 10 CFR 50, and less than 0.2% of the acceptable li=it of 75 =re=/ year specified in h0 CFR 190 Environ = ental Radiation Protection Standards For Nuclear Power Operations; (b) thyroid dose (- w h via I inhalation and = ilk pathway) of 0.2h = rem (at the farm location 16) which is less than 25 of the per=issible limit of 15 =re=/ reactor-yr (Appendix I 10 CFR 50) and less than 0.h% of the acceptable limit of 75 =re=/ year specified in k0 CFR 190, (c) a' total body ga==a i==ersion maximum dose of 0.026 m rem (at the Cn Site loca-tien 18) which is less than 15 of the per=issible dose of 5 =res/reacter-year specified in Appendix I 10-CFR 50, and less than 0.2% of the acceptable dese of 25 = rem / year specified in ho CFR 190; (d) a total body dose (=aximum via all liquid pathways) of 0.015 m re= vhich is less than 15 of the per=1ssible limit of 3 =re=/ reactor-year (Appendix I 10 CFR 50) and less than 0.1% of the accept-able 11=1t of 25 =re=/yr specified in LO CFR 190.
Thus it 'can be concluded that the observed activities, coupled with appropriate l dose calculations, indicate that plant operation during 1979 had no significant !
radiological i= pact on the environ =ent.
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TABLE 1 . .. -
SYNOPSIS OF TIIE 1979 CALVERT CLIFFS NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Docket Nos. 50-317/318
' SAMPLE SAMPLING" NUMBER OF NUMBER ANALYSIS
- NUMBER TYPE -FREQUENCY LOCATIONS COLLECTED ANALYSIS FREQUENCY PERFORMED-AQUATIC ENVIRONMENT Bay Water M 2 2h 11 - 3 M 2h Gamma (GeLi) M- 24 Sr-89 -QC 8 Sr-90 QC 8 Fish Q 1 6 Flesh Gamma (GeLi) Q _6' Bones
" Sr-89 4 6 Sr-90 Q 6 Shell Fish (2) Q -h 17 Flesh (Crabs, Oysters) Canana (GeLi) Q 17 Bottom Sediments Q h 16 Gamma (GeLi) Q 16
- Sr-89 -Q 16 Sr-90 Q 16 Rooted Aquatic (3)
Spring & 1 -
Gamma (GeLi) 2/A -
Plant Fall Sr-89 2/A -
Sr-90 2/A -
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TABLE 1 (CONT.)
SYNOPSIS OF TifE 1979 CALVERT CLIFFS NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL MONI'IORING PROGRAM Docket Nos. 50-317/318 SAMPLE SAMPLING" NUMBER OF NUMBER ANALYSIS
- NUMBER TYPE . FREQUENCY LOCATIONS COLLECTED ANALYSIS FREQUENCY PERFORMED ~
ATMOSPIIERIC ENVIRONMENT Air Iodine (l) i W 14 265 I-131 W 265-Air Particulates(5) W 7 371 Gross Beta W 371 -
Gamma (GeLi) MQ 81:
Sr-89 QC 28 Sr-90 QC 28 g Precipitation (6) Continuous 1 12 11 - 3 QC. h w Gross Beta M 12 Gamma (GeLi) M 12 Sr QC 4 Sr-90 QC la TERRESTRIAL ENVIRONMENT Vegetation II) .At Ilarvest 3 9 Gamma.(NaI) A '9 i Sr-89 A '9 Sr-90 A 9 Soil SA 3 6 Gamma (GeLi) SA 6 Sr-89 SA 6 Sr-90 SA 6
TABLE 1 (CONT.)
SYNOPSIS OF THE 1979 CALVERT CLIFFS NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONMENTAL' MONI'IORING PROGRAM Docket Nos. 50-317/318 SAMPLE SAMPLING
- NUMBER OF NUMBER ANALYSIS
- NUMBER .
TYPE FREQUENCY . LOCATIONS COLLECTED ANALYSIS FREQUENCY' PERFORMED TERRESTRIAL ENVIR0!iMENT (CONT. ) .
Ground Water Q 5 20 H-3 4 20 Gamma (GeLi) Q' 20 External Radiation M 13 612 TLD M 612
.g
- W - weekly, M - monthly, Q - quarterly, SA - semi-annual, A -- annual, C - composite.
(1) Edible species are. sampled when available.
(2) The location of crab samples may vary depending upon their availability.
.(3) Sampling may be interrupted when no rooted aquatic plants are available.
(la) The collection devices contain silver zeolite.
(5) After a minimum decay period of 72 hrs, beta counts are performed. Gamma spectrometry is performed on monthly composites of weekly samples. Strontium-89 and -90 analyses are performed on quarterly. composites of weekly samples.
(6) All analyses subject to sufficient sample collection.
(7) Predominant food crops (corn & small grains) are sampled when available.
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s TABLE 2 ANNUAL
SUMMARY
OF RADIOACTIVITY IN TIIE ENVIRONS OF Ti!E CALVERT CLIFFS NUCLEAR POWER PIANT UNITS 1 AND 2 (Jan.-Dec. 1979)
Docket Nos. 50-317/318 Annual Results Sample Radioactivity Typical Type Site MDL's Mean (f)# Range ###
Aquatic Environment
' Bay Water pCi/1 7 Plant H-3 114 517 (8/12) (<108-1328)
Outra11 Sr-90 0.80 0.70 (1/1) 4 (<0.56-0.70) 8 Plant II-3 119 177 (5/12) (<108-206)
Intake Sr-90 0.90 0.50 (1/4) --
Fish' pCi/Kg (Wet) g Flounder . Plant Sito Sr-90 -
22 (2/2) -
Spot. Plant Site Sr-90 -
31 (2/2) -
Shell Fish ' pCi/Kg (Wet)
Oysters 5 Camp Conoy Ag-110m- 7 195 (1/1) 4 4 (<7-266)-
Bottom Sediment -pCi/Kg (Dry) 5 Camp Conoy Co 60 85 58 (1/1) 4 -
Sr-90 144 hk (1/h) ( <33 17) 8 Cs-137 -
633 (4/4) -
Ce-111 4 240 513 (1/1) 4 6 ( <210-513 4 )
6 Long Beach"* Sr-90 51 25 (1/h) -
Cs-137 -
757 ()/h). -
Ce-11.4 240 589 (4/h) ( <21:0-7616 )
7 Plant Outra11 Co-58 69 26 (1/h) -
Sr-90 79 ble (1/h) -
Cs-137 -
602 (la/h) -
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TABLE 2 (CONTINUED)
Annual Results
^ Sample Radioactivity Typical Type Site MDL's Mean'(f)# Range ##'
Bottom Sediment (Continued) pCi/Kg (Dry)_
8 Plant Intake Co-58 69 382 (h/4) (<69-553) co-60 85 376 (4/4) (<85-701)
Sr-90 hk 72 (2/h) (<hh-103) es-137 -
, 618 (h/h) -
Ce-lhh 2h0 1011 (3/4) (<240-1110)
Atmospheric Environment
. Air Particulates- 10-2 pC1/m3 17 on Site Gross Beta 0.2 1.8 (52/53) (<0.2-6.5)
Sr-89 0.07 0.18 (1/h) (<0.05-0.18)
Sr-90 0.03 0.05 (2/4) (<0.03-0.05) 18 on Site Gross Beta 0.2 1.5 (50/53)' (<0.2-3.4)
Sr-90 0.03 0.03 (2/h) (<0.03-0.03)
~ es-137 0.07 0.08 (1/12) (<0.07-0.08) o>
19 Knotty Pine Gross Beta 0.2 ~2.0 (53/53) (<0.2-4.0)
Sr-89 0.07 0.09 (1/4) (<0.05-0.09)-
Sr-90 0.03 0.04 (2/h) (<0.03-0.06) 20 Lusby Gross Beta 0.2 2.0 (53/53) (<0.2-h.6) ,
Sr-89 0.10 0.09 (1/h) (<0.06-0.09)
Sr-90 0.04 0.05 (1/h) (<0.04-0.08) ce-141 -
0.23 (1/12) -
ce-lhh 0.21 0.39 (1/12) (<0.21-0.39) 21 Long Beach Gross Beta 0.2 1.7 (53/53) (<0.2-3.5)
Sr-89 0.07 0.11 (1/h) (<0.05-0.11)
Sr-90 0.03 0.04 (2/h) (<0.03-0.04)
Ce-lhh -
0.21 0.39 (1/12) (<0.21-0.39)
TABLE 2 (CONTINUED)
Annual Results .
Sample Radioactivity Typical 7ype Site MDL's Mean (f)* Range ***
Air Particulates (Continued) 10-2 pCi/m3 22 Cove Point Gross Beta o.2 1 9 (53/53)- (<0.2-3.7)
Sr-90 0.04 0.06 (2/4) ( < 0. Ole-0. 07 )
23 Taylors Island ** Gross Beta 0.2 1.4 (53/53) (<0.2-3.0)-
Sr-90 0.04 0.03 (2/h) -
Precipitation pC1/1 IS On Site Gross Beta 0.2 5.4 (12/12) (<0.2-13)
H-3 133 194 (1/h) (<130-194)
Sr-89 2.1 0.9 (1/h) -
Terrestrial Environment Vegetation. pCi/Kg (Wet)
Catbage lh Old Bay Farm Sr-90 32 153 (1/1) -
Hadish 1h Old Bay Farm Sr-90 32 64 (1/1) -
U Corn '1h Old Bay Farm Sr-90 32 80 (1/1) -
Tbbacco 14 Old Bay Farm Sr-90 32 18h0 (1/1) -
Tobacco 15 Farm Sr-90 32 444 (1/1) -
Corn .16 Parren Farm 'Sr-90 32 29 (1/1) -
Tobacco 16 Parren Farm Sr-90 32 363 (1/1) (<32-363)
Sun flower lh Old Bay Farm Sr-90 32 1050 (1/1) -(<32-1050)
Soil pCi/Kg (Dry) -
78 (1/2) 11 on site Sr-90 33 (<33-78)
Cs-137 20 179 (2/2) , (<20-293) t
TABLE 2 (CONTINUED)
L -Annual Results D ' Sample Radioactivity , Typical Type Site MDL's Mean (f)* Range ###
Terrestrial Environment Soil (Continued)- pCi/Kg (Dry) 12 on Site -Sr-90 35 60 (2/2) (<35-8h) '
Cs-137 20 166 (1/2) (<20-166)'
13 On Site Cs-137 20 201 (2/2). (<20-201)
Ce-lhh 106 289 (1/2) (<106-289) mR/30 Days ****
External Radiation 7 Plant Outfall 3.14 (12/12) (2.96-3.23) 17 On Site 5.23 (12/12) (4.8h-5.54) 18 On Site h.57 (12/12) (h.1h-5.12) r 19 K'otty n Pine 4.09 (12/12) (3.91-4.31) ca 20 Lusby 4.36 (12/12) (3.80 4.75) 21 Flag Harbor 3.73 (12/12) (3.hh-3 99) 22 Cove Point 4,.00 (11/12) (3.71-4.26) 23 Taylors Island 5.62 (12/12) (5.00 6.16) 24 On Site 5.29 (12/12) (4.85-5.75) 25 White Sands Club Sign h.81 (12/12) (4.66-5.01) 26 St., Leonard h.09 (12/12) (3.69-4.42)
TABLE 2 (CONTINUED)
. Annual Results Sample Radioactivity Typical.
Type Site MDL's- Mean (f)* ' Range ***
mR/30 Days ****
External Radiation (Continued). .
27 Solomons 3 98 (10/12) (3.57-4.25)-
28 Bertha 4.63 (12/12) (4.29-4.96)
"Mean encompasses only detectable quantities; fractions in parenthesis represent the' proportion'of detectable quantities to total quantities in a data set. For External Radiat. ion, the fractions represent the proportion of TLDs recovered to the total placed in the field.
- Control 1coations.
""* Minimum observable to maximum observed.
- Minimum to maximum observed.
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January 1 - Dictmbar 31, 1979
' Docket Nos. 50-317/318 F .. REFERENCES (1) Cohen, L,K., "Preoperational Environmental Radioactivity Monitoring Program at Calvert Cliffs Units 1 and 2", NUS No;. 882 Semi-Annual Report January-June 1971, December 1971; NUS No,.- 1025 Annual Report 1971, March 1973.
(2) . Cohen, L.K., "Preoperational Environmental Radioactivity Monitoring Program at Calvert Cliffs Units 1 and 2" NUS Nct. 1137, Annual Report 1972, December 1973.
(3) Cohen, L.K. and Malmberg, M.S. , "Preoperational Environmental' Radioactivity Monitoring Program at Calvert Cliffs Units 1 and 2",
,NUS No. 1188, Annual Report 1973, October 1974 (4) Radiation Management Corporation, Calvert Cliffs Nuclear Power Plant Radiological Environmental Analyses, December 1971 - December 1973 RMC-TR-74-13, August 1974 (5)- Malmberg, M.S., " Environmental Radioactivity Monitoring Program at Calvert Cliffs Nuclear Power' Plant", NUS No. 1332 Annual Report 1974 February 1975.
(6) Malmberg, M.S., "Preoperational Environmental Radioactivity-Monitoring Program at Calvert Cliffs Units 1 and 2", NUS No. 1333, Data Summary Report, September 1970 to September 1974, July 1975.
(7) Radiation Management Corporation, Calvert Cliffs Nuclear Power Plant -
Radiological Environmental Surveillance Program, January 1 to June 30, 1974 December 1974 (8) Baltimore Gas and Electric Company, Calvert C1'iffs Nuclear Power Plant -~
Semi-Annual Operating Renort, Julv - December 1974, March 1975.
(9) Radiation Management Corporation, Radiological Environmental Monitoring Program - Semi-Annual Report for Calvert Cliffs Nuclear Power Plant, July 1 through December 31, 1974, RMC-TR-75-08, August 1975.
(10) Baltimore Gas and Electric Company and Radiation Management Corporation.
Calvert Cliffs Nuclear Power Plant Radiological Environmental Moritoring Program Semi-Annual-Renort, January 1 - June 30, 1975 RMC-TR-75-11, September 1975.
l (11) Baltimore Gas and Electric Company and Radiation Management Corporation, Calvert Cliffs Nuclear Pcwer Plant Radiological Environmental Monitoring Program Semi-Annual Renort, Julv 1 - December 31, 1975, RMC-TR-76-02, March 1976.
(12) Baltimore Ga.s and Electric Company and Radiation Management Corporation, Calvert Cliffs Muclear Power Plant Radiolorical Environmental Monitoring Program Semi-Annual Renort, January 1 - June 30, 1976, RMC-TR-76-08, September 1976.
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January 1 - December 31, 1979 Docket Nos. 50-317/318 F. References (13) Baltimore Gas and Electric Company and Radiation Management Corporation, Calvert Cliffs Nuclear Power Plant Radiological Environmental Monitoring Program Semi-Annual Report, July 1 - December 31, 1976, RMC-TR-77-07,
- March 1977.
(14) Baltimore Gas and Electric Company,'Calvert Cliffs Nuclear Power Plant Radiological Environmental Monitoring Program Annual Report. January 1-December 31, 1977, March 1978.
(15) Baltimore Gas and Electric Company, Calvert Cliffs Nuclear Power Plant Radiological' Environmental Monitoring Program Annual Report, Januarv 1 -
December 31, 1978. March 1979.
(16) Calvert_ Cliffs Nuclear Power Plant, Unit Mos. I and 2, License Nos.
DPR-53 and DPR-69, Amendment No. 23 for Unit No. 1 Amendment No. 7 for Unit No. 2, Appendix A Technical Specifications; Appendix B, Environmental Technical Specifications.
-(17) Calvert Cliffs Nuclear Power Plant, Unit Number 1, License No.
DPR-53, Appendix A, Technical Specifications; Appendix B, Environmental Technical Specifications.
(18) Calvert Cliffs Nuclear Power Plant, Unit Number 2, License No. DPR-69, l Appendix A, Technical Specifications; Appendix B, Environmental Technical Specifications.
(19)- Baltimore Gas and Electric Company, Operating Procedures for Environ-mental Monitoring Activities at Calvert Cliffs Nuclear Power Plant, OP-2, OP-4, OP-5, October 1974
-(20) Radiation Manag'ement Corporation, Analvtien1 and Cuality Control Program, RMC-TM-75-3, July 1976.
(21) Baltimore Gas and Electric Company, Lab Manual Chemical Ennineerina & Tests. l l
(22) Baltimore Gas and Electric. Company, Operating Procedure for External l Radiation Dose Rate Measurements, OP-6, 1975. l (23) Calvert Cliffs Nuclear Power Plant, Docket Nos. 50-317/318, Semi-Annual Effluent Release Reoorts; Januarv - June 1979, and Julv - December 1979.
(24) U.S. NRC 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", March 1976.
(25) U.S. NRC-Regulatory Guide 1.111,." Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Rcutine Releases from Light-Water-Cooled Reactors for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", March 1976.
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' January 1 - December 31, 1979 Docket tios. 50-317/318-1 APPEIIDIX A Appendix A contains.information concerning the environmental samples which were collected during'the' period January 1, 1979-December 31', 1979.
Samples-locations and specific information about the individual locations are-given in Table A-1. ' Figure A-2 shows the locations of sampling stations with respect to the plant site. Figure A-1 shows the location of the Calvert Cliffs Nuclear-. Power Plant with respect to Southern
- Maryland and the Chesapeake Bay.
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4 TABLE A-1 LOCATIONS OF EUVIF. OMENTAL SA>PLING STATIONS FOR THE CALVERT CLIFFS NUCLEAR POWER PLANT Docket Nos. 50-317/318 DISTANCE
- DIRECTION STATION DESCRIPTIOM-- (FEET) (SECTOR)._ _ . _ _ .
1 Pound Nets Soutk'af Cove Point - 38 ,0 0 0- SE - - -
2 Chesapeake Country Club 20,000 SSE 3 Kenwood Beach -35,000 NNW 4 Rocky Point 10,000 NNW 5 Camp Conoy 3,000 SE 6 Long Beach 15,000 NNW 7 Plant Outfall Area 2,500 NE 8 Plant Intake Area 5,000 E 10 Onsite Well 600 SE 11 On Site 1,300 WNW 12 On Site 1,600 WSW 13 On Site 2,400 SSE Cultivated Field on Site 14 1,200 W 15 Farm 24,000 WSW 16 Farm 22,000 SW 17 On Site 1,200 NW 18 On Site 2,000 SE 19 Knotty Pine 8,900 WSW .
20 Lusby 9.900 SSW 21 Long Beach 14,000 NW 22 Cove Point 24,000 SE 23 Taylor's Island 40,000 ENE 24 On Site 1,800 NW 2S White Sands. Club Sign 7'300
, WSW 26 St. Leonard 27,000 NW 27 Solanons 42,000 S 28 Bertha 17,000 S 29 Flag Ponds 7,500 NW 30 Store (Lusby) 9,900 SSW IS On Site 1.400 SSW PS Plant Site 4,600 NNW Distance measured from plant vent. ,
23
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, Location of Calvert Cliffs Nuclear Power Plant
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APPEllDIX B, l
Data Tables-Appendix B is a presentation of the analytical results of the 1979 Calvert Cliffs Nuclear Power Plant Radiological Environmental
' Monitoring Program.
TABLE NO. TABLE TITLE PAGE B-1 Concentrations of Tritium, Gamma Emitters, and Strontium-89 and -90 in Bay Water 27 B-2 Concentrations of Gamma Emitters and Strontium-89 and -90 in Flesh and Bones of Edible Fish 28 B-3 Concentrations of Gamma Emitters in Shellfish Samples - 29 B-4 Concentrations of Gamma Emitters and Strontium-89 and -90'in Bottom Sediment 30 B-5 Concentrations of Iodine-131 in Filtered Air 31, 32 B-6 Concentrations of Beta Emitters in Air Particulates 33, 34 B-7 Concentrations of Gamma Emitters and Strontium-89 and'-90 in Air Particulates 35 B-8 Concentrations of Beta and Gamma Emitters and Strontium-89 and -90 in Precipitation - Station IS (On Site) 36 B-9 Deposition of Beta and Gamma Emitters and Strontium-89 .
and -90 in Precipitation - Station IS (On Site) 37 B-10 Concentrations of Gamma Emitters and Strontium-89 and -90 in Vegetation 38 B-ll Concentrations of Gamma Emitters and Strontium-89 and -90 in Soil 39 B-12 Deposition of Gamma Emitters and Strontium-89 and
-90 in Soil 40 B-13 Concentrations of Tritium and Gamma Emitters in Ground Water 41 B-14 Typical MDL's for Gamma Spectrometry 42, 43 B-15' External Radiation 44, 45 26
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TABLE B-1 CONCENTRATIONS OF TRITIUM, gal &A EMITEFS, AND STRONTIUM-89 AND -90 IN BAY WATER
- .(Results in Units of pCi/1 2 a) 9 Station Ga:m:ut Date No. H-3 Emitters Sr-89** Sr-90**
1/16/79 7 29ht115 8 177! ns 2/28/79 7 nc6 tin * <2.57 <0.96 8 <109 * <2.ho <0.88 3/16/79 7 1h7 106 8 <ni
<110
- h/05/79 7 8 1881105
- <0.56 5/10/79 7 <108 <3.39 8 nht103 * <2.10 0.50!0.37 6/06/79 7 87h 135 8 <139 7/n/79 7 1h8-121
- 8 <129 8/15/79 7 12T198 * <3.47 0.70!0.67 8 200!98 <2.h7 <0.78 9/12/79 7 13282133 8
- 206197 10/08/79 7 <130 ~
8 <131 11/07/79 7 1101101 * <2.1h <0.87 8 <109 * <2.37 <1.01
<108 *
-12/07/79 7 8 <108 *
'* Naturally occurring K h0 was observed in all samples. All other germa emitters not cited were <MDL; typical MDL's-are given in Table B-lh.
- Analyses _done on quarterly co=posites of monthly samples.
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TABLE B-2.
CONCENTRATIONS OF GAMMA EMITTEPS AND STRONTIUM-89 AND -90 IN FLESH AND BONES OF EDIBLE FISH (Results in Units of PCi/Kg'* 2 a)
Station ' Sampling- Sample Gamma No. Date Type Emitters Sr-89 ~Sr-90 1 First (Pound Nets ' Quarter South of Cove Point) 1 Second Quarter
~9/21/79 Flounder ** .<39 27!11
. Plant Siten*
Spot ** <57 37-th Flounder ** 16 3 Plant Site *** 11/6/79 <10 Spot ** 26 9 32th c
- Samples unavailable
- Naturally occurring K-h0 was observed in all samples. All other garna ;
emitters were <MDL; typical MDL's are given in Table B-lh.
- Samples were obtained from monthly benthic travi surveys of locations !
in the vicinity of the power plant from Kenwood Beach to Rocky Point.
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TABLE B-3 CONCENTRATIONS OF GAMMA DfITTERS* ~IN .
SHELLFISH SAMPLES.
(Results in Units of PCi/kg'(Wet)
- 2 e)
Station Sample-No. Quarter Type Ag-110m 3 1 Oysters <MDL (Kenvoed Crabs **
Beach- -2 Oysters <MDL Control Crabs <MDL Location) 3 Cysters <MDL Crabs <MDL k Oysters <MDL Crabs <MDL-4 1 Crabs **
(Rocky 2 Crabs <MDL Point) 3 Crabs <MDL h Crabs <MDL 5 1 Oysters 8814 (Camp 2 Oysters 172t9 Conoy) 3 Oysters 266*11 h Oysters 253-42 8 1 Crabs **
(Plant 2 Crabs <MDL Intake) 3 Crabs <MDL h Crabs <!G L
" Naturally occurring K ho observed in all samples.
, All other ga=ma e=1tters not cited vere <MDL; typical MDL's are given in Table B-lk.
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- Samples unavailable. I s
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TABLE 3 k CONCENTRATIONS OF GAMMA EMITTERS
- AND STRONTIUM-89 AND -90 In BOTTOM SEDIMENT
~ (Results in Units of PCi/k6 (Dry) 1 2 e)
Station No. Date Sr-89 Sr-90 Co-58 co-60 cs-137 ce-1kh 5 3/22/79- <100 <33 <!GL 58119 3hht21 <MDL (Camp 6/13/79 <151 <k2 <EL <MDL 282 ho <MDL Conoy) 8/27/79 <232 <57~ <EL <EL 913 70 Sh3t186 10/30/79 <179 kT 3h <MDL <EL 993 75 <MDL 6 3/22/79 <107 25t23 <!GL <MDL 660t31 603t101 (Long** 6/13/79 <179 <52 <!EL <EL 272thi 398I92 Beach) 8/27/79 <179 <h3 <MDL <MDL 1163tT7 589 218 10/30/79 <193 <59 <MDL <MDL 993 85 76h 232 7 3/22/79 <155 hht32 <EL <MDL 195121 <MDL (Plant 6/13/79 <365 <102 <MDL <MDL 256 51 <MDL outfall) 8/27/79 <278 <65 < MDL <!GL 11h317h <!GL 10/30/79 <229 <70 ,
<@L <!GL 815 70 <MDL 8 3/27/79 <102 <33 Sh 19 23 23 191118 <MDL (Plant 6/13/79 <193 <55 553t76 7011115 795173 122ht192 Intake) 8/27/79 <527 103179 528-100 350182 818t7h 1110t199 10/30/79 <201 k0137 392 67 h30!83 666177 698t17h
- Naturally _ occurring K h0, Ra-226, and Th232 were observed in all sa=ples. All other ga=a emitters were <MDL; typical MDL's are given in Table 3-lh.
C* Control location.
.. s TABLE B-5
~C ONCENTRATIONS OF IODINE-131 IN FILTERED AIR (Results in Units of 10-3 pCi/=312 o).
Cove Taylors Start Stop On Site On Site Lusby Point Island
- Date Date~ #17- #18 #20 #22 #23 12/26/78 1/02/79 <3.5 <3.0 < 3. h <h.5 <3.1 1/02/T9- 1/08/79- .< h.0 <3.6 <3.2 <2.8 <3.8 1/08/79 1/15/79 <3.5 <3.h <3.7 <h.2 < 3.h '-
1/15/79 1/22/79 <3.5 <3.3 <3.h <h.h <3.h 1/22/79 1/29-79 <3 5 <3.3 <3.h <3 9 <3 5 1/29/T9 2/05/T9 <3.3 <3.3 <3.7 <h.1 <3.h 2/05/79 2/12/T9 <3.5 <3.3 <3 5 <h.2 <3.h 2/12/79 2/21/T9 <2.6 ** <2 9 < 3.1 <2 9 2/21/79 2/26/T9 <5 3. <1.7 <5.h <5.7 <3 9 2/26/79 3/05/T9 <3.3 <3.h <3.6 <h.1 <3.5 3/05/79. 3/12/79 <3.h <3 5 <3.h <h.1 <3.6 3/12/79 3/19/79 <2 9 <3.h <3.5 <h.0 <3.5 3/19/79 3/26/79 <3.8 <3 5 <3.6 <h.0- <h.2 3/26/79 h/02/79 <3.7 <3.h <3.7 <h.2 <3.7 h/02/79 h/09/T9 <3.6 <3.8 <3.6 <h.2 <3.7 h/09/T9 h/16/79 <3.5 <3.h <3.6 <h.0 <3.2 h/16/79 h/23/79 <3.6 <3.h <3.5 <h.1 <3.7 h/23/79 h/30/T9 <2.6 <3.h <3.7 <h.0 <3.7
~
h/30/79 5/07/79 <3.6 <h.1 <3.7 <h.3 <3.h 5/07/79 5/1h/79 <3.6 <3.7 <3 7 <h.2 <h.2 5/1h/79 5/21/79. <3.6 <3.0 <3.5 <h.2 <h.0 5/21/79 5/29/79 <3.1 <2..h <3.h <3.1 <3.5 5/29/79 6/0h/79. <h.1 <3.1 <h.h <h.h <3.6 6/0h/79- 6/11/79 <3.8 <2.9 <3.8 <3.6 <3.3 6/11/79 6/18/79 <6.7 <2.8 <3.5 <h.0 <3.4 6/18/79 6/25/79 <3.2 <2.6 '<3.5 <3.8 <3 5 6/25/79 7/02/79 <3.2 <2.8 <3.6 <3.7 <3.5 T/02/79 7/09/79- <3.3 <3.0 <3.7- <3 9 <3.5 T/09/79 7/16/79 <3.1 <3.0 <3.8 <3 9 <3.2
'T/16/79 T/23/79 <3.3 <2 9 <3.8 <h.0 <3.6 T/23/79 7/30/79 <3.6 <3.1 <h.0 <h.2 <3.7
. '7/30/79 8/06/79 <3.6 <3.1 <3 9 <3.9 <h . 7~.
8/06/79. 8/13/79 <3.5 <3.h <h.0 <h.1 <3.2 8/13/79- 8/20/79 **' <3.7 <h.1 <3 9 <3.1
-8/20/79- 8/27/79- <3.1 <2.5 <h.1 <h.3 <3.5 I
31 l
( l TABLE 3-5~(CONTINUED) j
'CONCENTRA"IONSOFIODINE-1g1INFILTEREDAIR (Results in Units of 10- pCi/m3 2 o)'
Cove Taylors
. Start Stop. On Site On Site. Lusby Point Island
- Date Date #17 #18 #20 #22 '#23 8/2 TIT 9 9/0h/79 <3.2 <3.5 <3.3 <3.6 <3.k
- ** <3.h 9/04/79 9/10/79- <h.3 <h.T 9/10/79 ** <h.1 <3.8 <3 9 9/17/79 <3.6 9/17/79 9/2h/T9 <3.6 <2.8 <h.T <3.9 <3.7 9/2h/79 10/01/79 <h.0 ;<2.8 <h.3 <h.0 <3.h
-10/01/79 10/08/79 <3.7 <2.8 5
<h.h <h.0 <3.T' 10/08/79 10/15/T9 <3.6 <2 9 <h.5 <h.0 <3.3 10/15/79 10/22/79 <3.8 <2 9 <5.6 <3 9- <3.5 10/22/79 10/29/79 <3.7 <2.8 <3 5 <3 9 <3.8 10/29/79 11/05/79 <h.2 <3.0 <h.2 <5.6 <3.7 11/05/T9 11/12/79 <h.0 . <3.2 <3.8 ** <3.h 11/12/79 11/19/T9 <h.h <h.9 <3 5 <h.1 <3.7 11/19/79 11/26/79 <3.0 <3.5 <3.5 <3.7 <3.9 11/26/79 12/03/79 <2.7 <3.5 <3.5 <3.6 <3.1 12/03/79 12/10/79' <2.7 <h.6 <3.6 <3.7 <3.8 12/10/79 12/17/T9 <2 7 <h.1 <3.5 <3 9 <3.h 12/17/79 12/26/79 <2.3 <2.8 <3.0 <2.9 <3.9 12/26/79 12/31/79 <3.9 <5.3 <5 3 <5.5 <3.k
" Control location
- Air sampler =alfunction.
.32
~ .
TABLE 3-6 CONCENTRATIONS OF BETA D!ITTERS IN AIR PARTICULATES (Results in Units of 10-2 pC1/=3 2 e)
Knotty Long Cove- Taylors Start Stop Cn Site On Site Pine Lusby Beach Point ' Island
- D-te Date #17 #18 #19 #20 #21 #22 #23 12/26/78 1/02/79 5.hto.5 3.310.3 3.8!0.h 3.7to.h 2.810.3 3.7to.h 3.010.3 1/02/79 1/08/79 2 520.3 2.9IO.3 3.7 0.h 3.2!0.3 3.220.3 3.0!O.h 1.2*0.3 1/08/79 1/15/79 3.hto.3 2.820.3 3.710.k 3.9 0.h 3 520 .3 3.310.3 1.7!0.2 1/15/79 1/22/79 2.8!0.3 2.010.3 3.h!0.3 h.6!0.5 2.7IO.3 3.lto.h 1.8+-0.3 1/22/79 1/29/79 1.010.2 0.910.2 1 520.2 2.010.3 -1.310.2 1.hto.3 1.310.2
-1/29/79 2/05/79 2 710.3 2.520.3 -3.2*0.3 3.0*0.3 2.hio.2 2.1 0.3 2.110.3 2/05/79 2/12/79 3 7to.h 3.h 0.3 h.010.4 3.Sto.h 3 5to.h 3.210.3 1.810.2 2/12/79 2/21/79 2 910.3 ** 3.3to.3 3.7to.h 2.610.3 2.310.3 0.810 .2 2/21/79 2/26/79 1.1!0.3 2.210.2 1.310.3 1.8to.h 1.810.3 1.5to.h 0 9!0.3 2/26/79 3/05/79 1.110.2 1.2!O.2 1.h!0.3 1.710.3 1.0t0.2 1.1!0.3 1.6!0.3 3/05/79 3/12/79 2.2ic.3 1 920.3 2.210.3 2.hio.3 2.310.2 1.9!0.3 2.310.3 3/12/79 3/19/79 3.6!0.h 2 520.3 3 5!0.3 3.3 0.3 3.2 0.3 2.510.3 1.810 .3 3/19/79 3/26/79 1.110.2 1.120.2 1.510.3 1.710.3 1.hto.2 1.2 0.3 0.710.2 3/26/79 h/02/79 2 5!0.3 2.7!0.3 3.6to.h 3.610 .h 2.8!0.3 3 7to.h 2.3to.3 4/02/79 h/09/79 2.8!0.3 2.7 0.3 3.5to.h 3 910.h 2.610.3 3.hto.h 1.6to.3 h/09/79 h/16/79 1.620 .3 1.01 0.2 1.610 .3 1.lt o.2 1.3!0.2 1.hto.3 1.11 0.2 h/16/79 h/23/79 3.hto.3 2.6*0.3 3.7 0.h 3.6to.h 3.1 0.3 3.0!0.3 2.110.3 h/23/79 h/30/79 1.8to.3 1.hto.2 2.3!0.3 2.5to.3 1 910.2 2.010.3 1 410 .3
~
h/30/79 5/07/79 3.1!0.3 1.8!0.3 3.2 0.3 2.hto.3 2.7t0 3 2.610.'i 2.3*0.3 5/07/79 5/1h/79 1.3to.2 0.920.2 1.610.3 1 310.3 1.110 .2 1.620. s 1.6to.3 5/1h/79 5/21/79 1.010.2 1.0 0.2 170.3 1.h!0.3 1.210 .2 1.7t0.1 1.1t 0.2
$/21/79 's/29/79 1.120.2 0.810 .2 1.6*0.2 1.0t0.3 1.120.2 1. hto . .! 1.110.2 5/29/79 6/0h/79 1.610.3 0.h*0.2 1.5 0.3 1.0to.3 1.110.2 1.7!0.3 1.0 IO.2 6/0h/79 6/11/79 6.5t0.7 2.710.3 3.210.3 1.720 .3 2.810.3 2.810 3 2.hto.3 6/11/79 6/18/79 3.210 5 1.520.2 2.0to.3 1.L 0.3 1.hto.2 2.810.3 2.810.3 6/18/79 6/25/79 2.220.3 1.0f0.2 2.3to.3 2.710.3 0.7t0.2 2.020 3 2.110.3 6/25/79 7/02/79 1 520.3 0.710.2 1.710.2 0.7 0.2 0.810 .2 1 9to.3 0.6to.2 7/02/79 7/09/79 1.5io.3 0 920.2 1.7to.2 2.2 0.3 1.7 0.2 1.5 0.3 1.2to.2 7/09/79 7/16/79 1.3 0.2 0.6to.2 1.7 0 3 1.720.3 1.7to.2 1.5to.3 1.h*-0.2 7/16/79 7/23/79 1.11 0.2 1.0! 0.2 1.6to.3 1 510.3 1.hto.2 1.8tr. 3 1.0t0.3 7/23/79 7/30/79 0.8 0.2 0.5*0.2 1.0! 0.2 0 9 0.3 0 910.2 1.0tc.3 0.hto.2 7/30/79 8/06/79 1.1!O.2 0.6IO.2- 1 920.3 1.320.3 1.8to.2 1.711.3 1.810 .3 8/06/79 8/13/79. 1.hto.2 0.510.2 1.610.3 1.610.3 1 510.2 1.8tl.3 0.810 .2 8/13/79 8/20/79 ** <0.2 1.2to.2 0.8t0.2 1.hto.2 1.713.3 1.hto.3 8/20/79 8/27/79. 1.2*0.2 0.2*0.1 1 5t0 3 1.620.3 0.620.2 .1.210 .3 0.8to.2 33
TABLE B-6 (CCUTINUED)
CONCENTRATIONS OF BETA EMITTERS IN AIR PARTICULATES (Results in Units of 10-d pCi/m3 2 e)
Knotty Long Cove Taylors Start Stop On Site on Site Pine Lusby Beach Point Island
- Date Date #17 #18 #19 #20 #21 #22 #23 8/27/79 9/0h/79 0.810 .2 0.510.2 0.810.2 1.0t0.2 1.110.2 1.310.2 0.BIO.2 9/04/79 9/10/79 1.1 0.3 3.h 1.2 1.010.3 0.810.3 0.610.2 1.2!0.6 1.h 0.3 9/10/79 9/17/79 0.6to.2 ** 0.810.2 0.h 0.2 1.110.2 1.3to.3 0.8to.2 9/17/79 9/2h/79 0.6to.2 1.3to.2 0 910.3 0.510.3 1.110.2 1.lto.3 0.8!0.2 9/2k/79 10/01/79 0.7to.2 1.2to.2 1.210 .2 0 910.3 1.110.2 1.hto.3 1.110 .2 10/01/79 10/08/79 0.820'.2 0 9!0.2 1.310.2 0 710.3 1.310.2 1.310.3 0.910.2 10/08/79 10/15/79 0.hto.2 0.8to.2 1.210 .2 0.510.3 1.0io.2 1.010.3 0.6io.2
-10/15/79 10/22/79 0.520 .2 0.7to.2 0 710.2 0.6!0.3 1.310.2 2.0t0.3 1 7to.3 10/22/79 10/29/79 -0.6!0.2 0.810.2 0.h!O.2 2.h10.3 1.3!0.2 1.h!0.3 1.710.3 10/29/79 11/05/79 0.7!0.3 0.6!0.2 0.6! 0 .3' 2.010.3 1.2 10.2 0 910.3 1.010.2 11/05/79 11/12/79 0.610.2 0.5to.2 0.610.2 2.0t0.3 1.110.2 1 9 0.3 0.510.2 11/12/79 11/19/79 0.710.3 0.hto.2 2.6!0.3 2.6!0.3 1 510.2 1.Sto.3 0.910.2 11/19/79 11/26/79 2.hto.3 h.2to.h h.0to.h 3.6to.h 1.710.2 2.710.3 1.210.2 11/26/79 12/03/79 1 310.2 2.010.3 2.110.2 2.310.3 2.k!0.2 1.7io.3 1.hto.2 12/03/79 12/10/79 1.hto.2 2.2!0.3 2.210.2 2.220.2 1 7to.2 2.110.3 0.6!0.2 12/10/79 12/17/79 1.010.2 1.810 .3 3.hto.3 1 910.3 1.2 10.2 1.810 .3 1.210.2 12/17/79 12/26/79 0.8!0.1 1.h 0.2 1 5 IO.2 1 520.2 1 510.2 1.6to.2 1.2 !0.2 12/26/79 12/31/79 0.6!0.2 1.3!0.3 0 910.2 1.210.3 1 510.3 1.3to.3 1.2 10.2 I
CControl Location COAir Sampler Malfunction i
F 34
TABLE B-T CONCENTRATICNS OF OAMMA EMITTERS
- AND STRONTIUM-89 AND -90 IN AIR PARTICULATES (Results in Units of 10-3 pCi/m312 a)
Station ' Quarter No. Composited Sr-89 Sr-90
- 17. 1 <0.85 0.k2*0.20 (On Site) 2 <0.81 0.5120.2h 3 1 7520.79 <0.37 h <0.h6 <0.28 18 1 <0 90 b.33o.21 t
(on Site) 2 <0.83 0.3h 0.22 3 <1.13 <0.33 h <0.kT <0.29 19 1 <0.81 0.35to.20 (Knotty 2 <0.92 0 5520.26 Pine) 3 0 9110.78 <0.36 h <0.h6 <0.27 20 1 <1.17 0.h7 0.27 (Lusby) 2 <1.22 0.7510.31 3 0.8820.82 <0.38 h <0.56 0.2210.21 21 1 <0.88 0.2h 0.20 (Long 2 <0.Th 0.5hto.21
-Beach) 3 1.10 0.8h ~ <0.37 h <0.h8 <0.29 22 1 <1.20 0.h0t0.27 (Cove 2 -<0.01 0.69!O.27 Point) 3 <1.Th <0.51 h <0.67 <0.39 23** 1 <1.02 0.27to.23 (Taylors 2 <0.89 0.32 0.2h Island) 3 <1.k1 <0.ho k <0 92 <0.53
- Naturally occurring K h0 and Be-T vere observed in =ost sa=ples. Sporadic
-presences.of Cs-137 Ce-lhi and Ce-1kh were s1so observed; viz.,
4 Cs-137 = (0.81-0.37)x10-3 pCi/m3 from location #18 during h/79 Ce-lk1 = (2.3h 0.8h)x10-3 pCi/m3 from location.#20 during 6/79 Ce-lhk = (3.87tl.37)x10-3 pCi/m3 from locatien #20 during h/79-Ce-1kh = (3 90*1.06)x10-3 pCi/=3 from location #21 during h/79 All other gamma emitters not cited vere <MDL; typical NDL's are given in Table'3-1k.
- Centrol location 35
TABLE B-8 CONCENTRATIONS OF BETA AND GAMMA EMITTERS
- AND S*RONTIUM-89' AND -90 IN PRECIPITATION - STATION IS (ON SITE)
. (3esults in Units of PCi/1 t 2 a)
Cate Beta H-3** Sr-89** Sr Co**
1/79 1111 2/79 h.2to.6 19h1105 0.91
. !0.80 <0.ho 3/79 7.0!0.7 h/79 k.oto.6 5/79 2.120 5 <138 - <3.h6 <0 52-6/79 h.2 0.6 7/79 1.8!0.5 8/79 1311 <130 <1 59 <0.5h 9/79 2.hto.5 10/79 6.lto.7 11/79 5 0!O.6 <134 <1.29 <0.h9 12/79 h.h 0.6
- Naturally occurring K ho and Be-7 was observed in most samples. All other gama emitters not cited vere <!GL; typical !CL's are given in Table B-1k.
- Quaterly analyses of composited nonthly samples.
36
s TABLE B-9
.. DEPOSITION OF-BETA AND GAMMA EMII"'EPS AND STRONTIUM-89 AND -90 IN PRECIPITATION - STATION IS (ON SITE)
, (Results in Units of 103 pet /=2 )-
Date Beta H-3 Sr-80.
1/79 1.24 2/79 0.61 6k'.55 0.30
- 3/79 0 52 h/79 0.23 5/79 0.07 - -
6/79 0 57 7/79 0.23 8/79 2.kk - -
9/79 0.k9 10/79 0 52 11/79 .0.60 - -
12/79 0.07 1
37
TABLE 3-10 CONCENTRATIONS OF GAMMA EMITTERS
- AND STRONTIUM-89 AND -90 IN VEGETATION (Results in Units of pCi/%g (Wet) ! 2 e)
Station Sample No. Date T'rpe Sr-89 Sr-90 1h T/16/79 Cabbage <h5 153 21 Radish <121 6h 13 1h 9/17/79 Corn <99 80225
. Tobacco <1020** 18h0*280 15 9/19/79 Corn <83 <32 Tobacco <309 hhh*59 16 9/19/79 Corn <99 29226 Tobacco <390 363 71 1h 10/03/79 Sunflower 27h2190 1050-510 l
l l
- Naturally occurring K h0 was observed in all sa=ples. All cther gam =a emitters were <MDL; typical MDL's are given in Table 3-lh.
- Lev chemical yield in analysis.
l 38
e s
TABLE B-11 CONCCITPATICNS OF gal &A EMITTEES* AND STRONTIUM-89 AND -90 IN SOIL
_(Results in pCi/kg (Dry) 2 a)
Date 3/27/79 11/5/79 Station 11 12 13 11 12 13 No. (On Site) (On Site) (On Site) (On Site) (On Site) (On Site)
Sr-89 <9h <101 <100 <1h6 <158 <1hh Sr-90 <33 36!23 <36 78133 Sh 35 <h7 Cs-137 6h126 <MDL 222216 293135 166t35 180131 Ce-1kh <MDL <MDL 289I59 <MDL <MDL <MDL CNaturally occurring Ra-226, Th232, and K k0 were observed in all sa=ples. All other ga=ma emitters not cited were <MDL; typical MDL's are given in Table 3-lh.
l l
39
TABLE B-12 DEPOSITION
- OF GA!G!A E!ETTERS AND STRONTIUM-89 AND -90 IN SOIL (Results in Units of 103 pCi/m2)
Date 3/27/79 11/5/79 Station 11 12 13 11 . 12 13 No. (Cn Site) (On Site) (On Site) (On Site) (Cn Site) (Cn Site)
Sr-89 .
Sr-90 -
0 58 .. 1.2h 1.33 -
Cs-137 1.02 -
3.52 h.65 2.6h 2.86 Ce-lhk - -
k.59 - - -
- Deposition was calculated using a soil density of 1.27 g/cm3 and a soil depth of 1.25 cm.
40
I e -l
~
TABLE B-13 ;
CONCINTRATICNS OF TRITIUM AND G M M EMITTERS
- IN GROUND WATER (Results in pC1/1
- 2 a)
Station Qaarter No. Compositel H-3 camma Emitters
- 2** 1 <112 <MDL
'(Chesapeake 2 <137 <EL Country Club) 3 <128. <MDL h <131 <@L 10 1 <111 <MDL (On Site 2 <138 <@L Well) 3 <126 <MDL h <131 <MDL 21** 1 <112 <MDL (Long 2 <138 <MDL 3each) 3 <128 <MDL h <129 <MDL 25A** 1 <112 <MDL *
(White Sands 2 <139 <MDL Club) 3 <128 <MDL h <130 <MDL 253** 1 <112 <MDL (White Sands 2 <139 <MDL Club) 3 <128 <MDL h <130 - <MDL -
- Naturally occurring K h0 was observed in most sa=ples. All other ga=ma e=itters not cited were <MDL; typical MDL's are given in Table 3-14
- Centrol-locations.
41
- .
TABLE 3-lh TYPICAL MDL'S FOR OAMMA SPECTRCMETRY Selected Bay Water Fish Shellfish Sediment Nuclides pC1/1 pCi/kg (Wet) pCi/kg (Wet) pCi/kg (Drv)
Na-22 17 11 8.2 72 Cr-51 8.5 h1 33 383 Mn-5h 1.h 9 7.0 67 Co-58 1.6 9 6.3 69 Fe-59 2.3 17 16 13h Co-60 15 1h 9.0 85 Zn-65 3.h. 18 16 101 ZrNb-95 2.2 12 10 83 Zr-95 3.2 17 13 109 Mo-99 0.8 3.1 2.5 27 Ru-Rh-106 1.1 57 h5 518 Ag110m 1.3 75 6.7 5h Te-129m 1.0 51 h '. 6 13h I-17,1 1.0 k.9 h.h h7 Te-132 1.6 12 8.9 69 I-133 1.2 8.0. 5.6 57
'Cs-13h- 1.5 10 7.6 sh
~Cs-137 1.h 10 6.8 -
Sala-lho 2.2 12 12 69 Ce-1kh 7.0 25- 18 2h0 42
l
.- l TABLE B-lk (CONTINUED) !
TYPICAL MDL'S FOR GAMMA SPECTRCMETRY Air Seleeted 'Pgiculatgs Precipitation Vecatation Soil Well Water Nuclides 10 pCi/m pC1/1 pCi/kg (Wet) pCi/kg (Dry) pC1/1 Na-22 0.08 3.3 11 23 1.0 Cr-51 0.kh 22 38 1hl~ 6.3 Mn-5h 0.08 h.1 8.3 23 1.0 Co-58 0.08 3.3 8.5 21 1.k Fe-59 0.21 h.2 19 h1 1.0 Co-60 0.12 h.7 13 27 1.1 Zn-65 0.15 7.1 2h h6 1.h ZrNb-95 0.13 5.7 12 35 1.6 Nb-95 0.07 7.8 7.2 22 2.2 Zr-95 0.19 3.6 18 48 1.0 Mo-99 0.03 2.1 2.6 11 0.6 RuRh-106 0.63 25 6h 206 92 ,
Ag110m 0.08 3.2- 6.5 23 2.2 Te-129m 0.0h 2.8 50 17 2.1 I-131 0.05 3.0 55 20 0.9 Te-132 'O.09 k.h 8.T 30 0.8 I-133 0. 0.6 3.7 6.3 21 0.8 Cs-13h 0.09 h.h 9.6 28 l'. 0 Cs-137 0.07 h.2 95 20 1.1 3aLa-lho 0.1h h.5 11 37 17
.Ce-1kh 0.21 192 22 106 5.2 43
.* g
. s TABLE B-15 EXTERNAL RADIATION (Results in Units of =R/30 Days)
Location #7 Jan. 3.19*0.02 Jul. 2 96!0.18 Feb. 3.18 0.14 Aug. 3.23 0.03 Mar. 2 95 0.17 Sep. 3.23 0.18 Apr. 3.1h!0.26 Oct. 2.9810.16 May 3.33 0.07 Nov. 2.97 0.08 Jun. 3.38 0.10 Dec. 3.16to.12 Location #17 Jan. 5.17 !O.36 Jul. 5.07 10.16 Feb. 5 23 !O.06 Aug. 5.5k10.37 Mar. 5.23 0.24 Sep. 5.47*0.03 Apr. 5.10 0.25 Oct. 5.k580.19 May 5.30!0.19 Nov. h.8520.01 Jun. 5.23!O.10 Dec. 5.1h 0.k8 Location #18 Jan. 5.13!0.31 Jul. h.2610.19 Feb. h.k620.15 Aug. h.56 0.2h Mar. h.57!0.30 Sep. h.8520.5h Apr. h.61 0.03 Oct. h.71to.51 May k.61 0.31 Nov. h.15 !O.17 Jun. k.60 0.k2 Dec. h.hk O.30 i Location #19 Jan, k.32!O.36 Jul. 3 92!0.09 Feb. h.1h!O.10 Aug. 4.1kIO.21 Mar. 3.9k!0.09 Sep. h.18!0.17 Apr. h.01!0.1h Oct. h.23 0.20
.May k.18!0.17 Nov. 3.91 0.13 Jun. h.12!O.00 Dec. h.00 0.05 Location #20 Jan. k.63 IO.16 Jul. h.52!0.13 Feb. 4.07 !O.17 Aug. h.72IO.18 Mar. h.2010.10 Sep. h.7510.07 Apr. h.1510.18 Oct. h.60!0.21 May k.28IO.03 Nov. 3.80*0.07 Jun h.57 0.36 Dec. k,0210.28 Location #21 Jan. h.00!O.03 Jul. 3.k8!0.09 Feb. 3.7610.16 Aug. 3.97 0.16 Mar. 3.67 IO.10 Sep. 3.69t o.13' Apr. 3.85!0.19 Oct. 3.78 0.12 May 3.75 0.11 Nov. 3.k5do.02 Jun. 3.8kio.26 Dec. 3.66*0.18 Location #22 Jan. h.27 IO.01 Jul. 3.78 0.22 Feb. 3 93 !O.27 Aug. h.17 IO.10 Mar. 3.97 0.16 Sep. h.13!0.26 Apr. h.021.07 0 Oct. k.1110.31 May Stolen Nov. 3.72to.1k Jun. k.18!O.15 Dec. 3.7k10.23 44
e.
sp#$ ,
% a TABLE'B-15 (CONTINUED)
EXTERNAL RADIATION (Results in Units of mR/30 Days)
Location #23 Jan. 5.7210.h1 Jul. 5.78I O.39 Feb. 5 0110.09 Aug. 5.88!0.27 Mar. 5.55*0.20 .Sep. 5.8720.19 Apr. 5.35 0.13 Oct. 5.71*0.26 May 6.16*0.23 Nov. 5.koio.26 Jun. 5.85 0.01 Dec. 5.2810.3h Location #24 Jan. 5 7610.50 Jul. h.86 0.16 Feb. 5.18to.43 Aug. 5.hk O.13 Mar. 5.1210.20 Sep. 5.1h 0.12 Apr. 5.36IO.25 Oct. 5.38 0.22 May 5.58 0.25 Nov. 5 0610.18 Jun. 5.66fo.55 Dec. 4.98to.23 Location #25 Jan. k.99!0.35 Jul. k .90 0.15 '
Feb. h.6Tto.01 Aug. 5.02 0.12 Mar. h.67 0.39 Sep. 5 02 0.17 Apr. h.67 IO.26 Oct h.8310.31 May h.8h 0.38 Nov. h.66!0.k8 Jun. h.8310.11 Dec, h.69to.30 Location #26 Jan, k.k3 0.1h Jul. h.02 0.11 Feb. h.1210.21 Aug. h.13 0.19 Mar. h.16io.03 Sep. 4.06 0.01 Apr. h.03 0.20 Oct. k.1610.19 May h.32to.20 Nov. 3.70!0.10 Jun. h.1510.37 Dec. 3 9320.0h Location #27 Jan. h.26 0.29 Jul. Stolen Feb. k.26!0.h6 Aug. 3.93 10.07 Mar. 3.91 0.23 Sep. 3.95to.36 Apr. 3.90 20.18 Oct. 3.5710.12 May h.19 IO.13 Nov. Stolen Jun. 4.21IO.21 Dec. 3.68 0.28 Location #28 Jan, h.96 0.09 Jul k.7610.30 Feb. h.3610.10 Aug. h.57 0.11 Mar. h.3020.29 'Sep. 5.72 IO.58 Apr. h.5h 0.15 Oct. h.69to.09 May h.5510.11 Nov. h.32!0.19 Jun. 4.51IO.36 Dec. h.3710.25 45