ML19350C507

Radiological Environ Monitoring Program,Annual Rept,1980

ML19350C507
Person / Time
Site:	Calvert Cliffs
Issue date:	03/31/1981
From:	Bartal L, Rafi A, Reichert E BALTIMORE GAS & ELECTRIC CO.
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ML19350C506	List: ML19350C505 ML19350C507
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NUDOCS 8104030466
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{{#Wiki_filter:. ~ RADIOLOGICAL ENVIR0h7ETAL MONITORING PROGRAM ANNUAL REPORT FDR.THE CALVERT CLIFFS 'KUCLEAR PLANT UNITS 1 AND 2 JANUARY 1 - DECEMER 31, 1980 L. J. Bartal A. Rafi E. C. Reichert J. W. Stout, Jr. BALTIMORE GAS AND ELECTRIC COMPANI ? f h

j. Jariuary 1 - Decer-ber 31, 1980 Docket Nos. 50-317/310 N TABLE OF CONTENTS PAGE LI ST O F E GU RES ----- ---- --------- --- ------- ---- - -- - ---- ii LIST O F TABLES-------- --- - ----- -- -- - - - - --- --- -- -------- ii 1 A. SUIMRY= B. INTRODUCTION--------------------------------------- 3 C. PROG RAM --- -- - - - -------- - - - ------ -- - -- -- - --- - - ----- - 3 C.1 Objectivos-------------------------------------- 3 C. 2 Sanple Collection------------------------------- h C. 3 Data I nte rpre tation----------------------------- b C. L Progran Exceptions------------------------------ L D. -RSSULTS AUD DISCUSS 10hS---------------------------- 5 D. 1 Aquatic Environnent----------------------------- 5 D. 2 Atmospheric Envircraent------------------------- 7 D. 3 Terrestrial Environment-----------. ------------ 9 D. h External Radiation------------------------------ 10 E. CON CLUSI ON -------------- --------------------- ------ 11 F. REFEREECES.---------------------------------------- 21 APPENDIX A - Environmental Sargling Location-- 23 APPENDIX B - Analytical Data Tables----------- 27 ) 4 ____..---____m-___m-m_

r-January 1 - December 31, 1960 Docket Nos. 50-317/318 d LIST OF FIGURES FIGURE TITLE PAGE A-1 Map of Southern Maryland and Chesapeake Bay Showing Location of Calvert Cliffs Nuclear Power Plant---------------------------------------- 25 A-2 Radiological Envirorcental Monitoring Stations in the Vicinity of the Calvert Cliffs Nuclear Power Plant---------------------------------------- 26 LIST OF TABLES TABLE TITLE PAGE 1 Synopsis of the.1980 Calvert Cliffs Nuclear Power l Plant Radiological Environmental Monitoring Program-------------------------------------------- 12 2 Annual Surnary of Radioactivity in the Environs of the Calvert Cliffs Nuclear Power Plant Units 1 and 2-------------------------------------- 15 A-1 Locations of Environmental Sampling Stations for the Calvert Cliffs Kuclear Power Plant------------ 2h f 11-i_ -

1 January 1 - Lecenber 31, 1960 Docket I.os. 50-317/318 A. SUWARY During this operating period for Calvert Cliffs Unit 1 and Unit 2, Radiation ManaFement Corporation (RhC) and Baltimore Gas and Electric Conpany (BG&E) analyzed sannles from the aquatic, atmospheric, and terrestrial environments. Baltimore Oas and Electric Company made nessurements of external radiation. ' A total of 1,03$ analyses were perforned on 735 envircnnental sanples during the period covered by this report. In addition, BGLE personnel analyzed 600 them.oluminescent dosimeters (TLD's) for ambient radiation dose rates. Samples of the aquatic environnent included bay water, fish, shellfish (oysters, crabs) and sediment. Bay water was anclyzed for tritium, Sr-69 and Sr-90 and gama emitting nuclides. Fish, shellfish and sedirent were analyzed for gamma eritting nuclides. Fish bones and sediment were also analyzed for Sr-89 and Sr-90. Samples fran the atnospheric environnent included air and precipitation. Air particulates and gaseous iodine were collected on glass fiber filters and silver zeolite nolecular sieve cartridges, respectively. The particulate filters were analyzed for gross beta activity and for garna enitting nuclides while the molecular sieve cartridras were analyzed for I-131. Quarterly composite analyses for Sr-69 and Sr-90 on air particulate filters are reported. Precipitation was analyzed for gross beta, H-3, Sr-89, Sr-90 and s gar:ma eritting nuclides. Monitoring of the terrestrial environment included vegetation, soil, and ground water sanples. The vegetation and soil sanples were anal; zed for gama eritters and Sr-69 and Sr-90. Tne ground water sanples were analyzed for H-3 and gama emitting nuclides. Measurements of external radiation were performed by analyzing thernolurinescent dosimeters from 13 locations surrounding the plant. Low levels of various radionuclides were occasionally observed in the environment surrounding the plant during 1980. Most of these observations were attributed to - the fallcut fron recent and past atmostheric nuclear bonb testing. A few of these observations, however, may be directly related to the operation of the plant. Tritiun,.Sr-69, and Cs-137 were observed in a f.ew samples taken from the discharge area in concentrations greater than that generally observed in previous years. Cobalt-58, Zn-65, and Ag-110m were observec in oyster sanples fron Carp Conoy at relatively low levels. Mangenese-$h, Co-$6, Sr-h9, a.7d Co-60 appeared in sediment sanples taken fred the intake aret where they had sporadically appeared in the past. Strontium-89 was observed in a few vegetation samples taken fren farms near'cy the plant. In all of these cases, the activity was low -and, consequently, would have very little impact on tne surrcunding environment. The results of the dose calculations perferned by using the plant effluent release data, on site neteorological data and appropriate pathways indicate: (a) thyroid inhalation enr h m dose of 0.021 nrem (at the On Site lecction 18 about 2000 feet ? 1 )

January 1 - Dacenter 31, 1980 Locket Kos. 50-317/318 southeast from the plant vent) which is less than 1% of the permissible limit of g 15 mru/ reactor / year specified in Appendix I 10 CFR 50, and less than 0.1% of the acceptable linit of 75 nrer/ year specified in LO CFR 190 Environt ental Radiatior Protection Standards For Nuclear Power Operations; (b) thyroid dose (maximan via inhalation and nilk pathway) of 0.17 mrem (at the farm location 16) which is less than 2% of the pernissible linit of 15 mrem / reactor / year (Appendix I 10 Cia 50) and less than 0.3% of %e acceptable limit of 75 rret/ year specifiec in h0 CFR 190; (c) a total body ganr.a ir:tersion maximum dose of 0.009 mrer. (at 'he On Site location 18) which is less than 1% of the permissible dose of 5 rrer,rreactor/ year specified in Appendix I.; CFR 50, and less than 0.1% of the acceptable dese of 25 nrem/ year specified in 50 CFR 190; (d) a total body dose (naxir.um via all liquid pathways) of 0.010 nrem which is less.than 1% of the permissible limit of 3 mren/ reactor / year ( Appendix I 10 CFR 50) and less than 0.1% of the acceptable linit of 25 mren/yr specified in h0 CFR 190. Thus it is concluded, based upon the levels of radioactivity observed and the various dosa calculations, that the operation of the Calvert Cliffs liuclear Power Plant Units 1 and 2 did not cause any significant changs in the observed concentrations of environmental radioactivity or ambient radiat.an levels. ol 1 e a 2

.3 e2 + ,.:s n >?>. . > n v.; <-..er.y n c January 1 - Decenter 31, 1960 Locket Los. 50-317/316 t-3. ILTROLUCTICK Baltinere Gas and Slectric Corpany ( BG'8) has been conducting t radiological environnental nonitoring progran in the environs of the Calvert Cliffs huelear Power Plant since the sunmer of 1970. Results of the analyses of environnental saroles for the preoperatienal and operational periods througn December 31, 1979, have been reported in a series of docunents (1-16). This report presents the type and number of sanples analyzed, the analyses perforned (see Table 1 for a sunnary of the surveillance progran) and the data generated during 1980. Interpretation of the data and conclusions are prese 'ed. Appendix A sunnarizes the sanple redia and relative sanpling locations with respect to the Calvert Cliffs Kuclear Power Plant (Table A-1 and Figure A-1). Figure A-2 shows the location of the Calvert Cliffs Euclear Site in relatien to the Chesapeake Bay and Southern F.aryland. The Calvert Cliffs site is an operating nuclear generating rtation consisting of two P4R Units. Unit 1 achieved criticality on October 7,197L, and connenced cor.aercial operatien in May 1973. Unit 2 achieved criticality on November 30, 1976, and went into connercial operation Apri] 1, 1977. Since July 29, 1977, we have been operating under combined Environnental Technical Specificatiens for Units 1 and 2 (17). Prior to this date, separate Environn. ental Technical Specifications (18,19) were in effect for each unit. C. PROGRAM The environnental surveillance data collected during this reporting period were conpared with that generated in previous periods to assess the environ-nental radiological inpact of the operation of Calvert Cliffs huclear Power Plant Units 1 and 2. C.1 Objectives The objectives of the operatienal radiclogical environnental progran are: a. To deternine wnether any statistically significent increase occurs in the concentration of radionuclides in inportant pathways, b. To detect any possible buildup of long-lived radionuclides in tne environnent. c. To nonitor and evaluate anbient radiation levels. d. To verify that radioactivity and ambient radiation levels attributable to the plant are within the linits specified in the Technical Specifications (17). 5 3 ]

January 1 - Decenber 31, 1980 Docket Nos. 50-317/315 ,l C.2 Sa: ole Collection 't The locat'sns of the individual sanpling statiens are listed in Table A-1 and shown in Figure A-2. All samples were collected by consultants to, or personnel of, Baltimore Gas and Electric Company according to BGLE operating procedures (20). Radiochemical analyses were performed by EMC and BG&E. Ambient radiation measurements were made by Baltimore Gas and Electric Company personnel in accordance with an operating precedure (23). These measurements were made 4th thernoluminescent dosimeters as previously described (10). C.3 Data Interpretation Analytical data generated during the program are routinely evaluated. In the interpretation of the data several factors are imp ~ tant and are discussed here to avoid repetitien in the sections that folh w. It is characteristic of environmental.cnitoring data that many results occur at or below the minimum detectable level (MDL). In this report, all results occurring at er belo ' the relevant MDL are reported as beinC "less than" the MDL value. Annual means, range and typical MDL's are presented for each type of analysis for every sample media. Results of individual analyses are also presented with applicable standard deviations. e In the case of ganna spectrometry, if no activity of a particular nuclide was found, no average was calculated for that nuclide. C.h Procran Exceptions There were no milk samples, from cows within five miles of the plant, available. No rooted aquatic plants uere found during 1980. Sanples of crabs were unavailable during the first quarter of 1980. Edible fish sanples were unatainable during the first quarter, because the comrarcial pcund nets south of Cove Point were not deployed during that period. h

January 1 - Eecenber 31, lib 0 Dceket hes. 50-317/31c D. .ESUI.TS A!:D EISCUSSICSS All the envircre. ental samples were either analyzed by PEC laboratory crecedures (21) or BGE laboratory procedures (22). The analytical results fcr this reporting period, presented in Appendix 3 and also surz.arized en an annual basis in Table 2, have been divided into four categories--aquatic, ainospheric, and terrestrial environment, and external radiation. D.1 Acuatic i.nvirere.ent The aquatic environ.ent surrounding the plant was nenitored by analyzing samples of bay water, aquatic erranists, and botten sediment. These sarples were obtained fren various sar.pling locatiens en the Chesapeake Bay near the plant. D.l.a Bay Water lienthly bay water sanples were taken fren two locations; the Plant Intake area (location 8) and the Plant Outfall area (locatien 7). These sarples were $lyzed fer H-3, ga=na emitters, and Sr-S9 and Sr-90. Monthly analyses for H-3 in these saneles exhibited concentrations ranging fron '12h to 1166*117 p01/1 for location 7 and fren 121til7 to 20Gt122 pC1/1 for location 6. With the exceptien of the single January result of 1166*117 pCi/1 fron location 7, all the results were well within the ranges observed in both the preeperational (6) and previous operational (16) periods. This single outlying result is probably related to routine releases of tritiun fren the plant. Monthly analyses fer ganna enitters in these sarples showed detectable cen-centratiens of Cs-137 at 2.310.9 pCi/1 in the Fecruary sarple fren locatien 7 and of Ce-lb1 at 2.712.7 pC1/1 in the hove-ber sanple fren locatien 6. Tne presence of Cs-137 is probably related to reutine plant releases. The presence of Ce-lb1 is most probably related to the atnespheric nuclear bonb testing carried out by the People's Republic of China during the preceding ncnth of October. Quarterly analyses for radiestrentiun in these sanples shewed one detectable cencentratien of Sr-89 (viz.,1.53tl.20 pCi/l in thirc quarter sanple fren locatien 8), and a single detectable concentratien of Sr-90 (viz., 0.77*0.L3 pC1/1 in secenc quarter sanple fron location 7). The detectable cencentration of Sr-59 is probably related to plant operatien. The Sr-90 concentration is conparable to the concentrations observed in the preeperational (6) and previous operational (16) periods. D.l.b Acuatic Creanisns Quarterly saneles of acuatic orranisns were taken fror five locatiens; the pound nets south ef Cove Pcint (location 1), Kenwood Beach (location 3), 5

January 1 - Dacenber 31, 1960 Docket hos. 50-317/316 Rceky Point (location h), Camp Conoy (location 5) and Plant Intake area (location 8). The edible portions of these samples were analyzec for gama emitters, and sanples of fish bones were analyzed for Sr-69 and Sr-90. Quarterly analyses of fish samples collected during the second and third quarters from location 1 showed detectable concentrations of Cs-137 ranging from 11111 to 22+10 pCi/kg, while those collected during the fourth quarter from the same location revealed no detectable concentrations of any fission or activation by-products relatable to plant operation. The presence of Cs-137 in these sanples nay be related to either the radioactive discharges of the plant or to past nuclear bomb te:..ing, or to a cenbination of both of these sources. However, it should be noted that the sa: ples in question were generally those of large, mature representatives of the species collected, and thus the observed concentrations of Cs-137 are probably the result of a long process of bicaccumulation of this typical fallout radionuclide. Quarterly analyses for gama emitters in the c:ab samples from all locations and in the oyster samples from location 3 revea.ed that no detectable con-centrations of fission or activation products were present in the nuscle tissue. However, the analyses of the oyster sanples fron location 5 showed detectable concentrations of Ag-110m ranging from 5829 to 128:10 pCi/kg in all sanples, and the presence of Co-58 at a concentration of 2216 pC1/kg and of Zn-65 at a concentration of 3211h pCi/kg in only the first quarter sample. The presence of these three radionuclides is probably plant related, though it should be noted that in the cases of Co-58 and Zn-65 both concentrations border the minimum detectable limits of this analysis as typified in Table B-lh and are the result of large sample size; and in the case of Ag-110m the range q of results are much lower than those observed in previous years (15, 16) and the trend of the results shows that the concentration is decreasing with each succeeding quarter. Quarterly radiostrontium analyses of the bones from the fish samples showed only one detectable concentration of Sr-89 (3381190 pCi/kg in the second quarter weak fish sample) and showed detectable concentrations of Sr-90, ranging from 16110 to 102:58 pCi/kg, in most of the samples analyzed. Though the single Sr-89 result may be related to plant operation, it is also possible -that this positive value is a spurious statistical result of the radiochemical procedure for deternining strontium (This effect has been noticed previously (16)). Tne Sr-90 results on the other hand, seem to fall into the same general patterns observed in both the preoperational (6) and previous operational periods (16). 'D.1.c Sediment t Quarterly sediment samples were taken from four locations; Camp Conoy (location 5), Long Beach (location 6), Plant Intake. area (location 8), and Plant Outfall area'(location 7). These samples were analyzed for gan=a emitters and Sr-89 and Sr-90. ( 6

Januar Lecember 31, 1980 Locket hos. 50-317/31o Quarterly analyses for ganna enitters in these sanples revealed the presence of the following radionuclides: Cs-137 in all sanples fren all locations, ranging from 87tL6 to 987tl3h pCi/kg; Co-60 in rest of the sanples fror all locations, ranging fren 75t75 to 920292 pCi/kg; Ce-lh1 and Cc-lhh sporadically present in samples taken from the centrol locatien and tne other indicator locatiens; and Mn-5h and Co-58 sporadically present in sanples taken fron locations in the irrediate vicinity of the plant. The ranges of the Cs-137 concentrations exhibited are typical of the ranges observed in the preoperaticnal (6) and previous operational (16) periods. In addition,the presence of Ce-lhl and Ce-lhh in sanples fec= control and indiccter stations is probably related to past nuclear testing, since these radionuclides are typical of the " main fallout nuclides" of recent nuclear bomb testing. On the other hand, the presence of Mn-Sh, Co-58, and Co-60 is probably plant related, since they are typical of the activatien products released in routine radioactive discharges and since they show up only in the environs nearest the plant. Quarterly radiostrentium analyses showed detectable concentrations of Sr-69 in three sanples (viz., 255t110 pCi/kg in the third quarter sample from locatien 5, 5Lt31 pCi/kg in the fourth quarter sanple fron location 7 and hh01160 pCi/kg in the third quarter sanole fren location 8). These results are prQ soly plant related. The radiostrontiur analyses showed only a single detectable concen-tration of Sr-90 in the first quarter sanple from location 6 with a value of 22122 pCi/kg, which is within the ranges observed in the preoperational (6) 5 and previcus operational (16) periods. D.1.d Dose Assessment Lose calculations, utilizing the plant's effluent release data (2h) and the appropriate regulatory guide (25), were nade to assess the plant's radiological dose inpact on the surrounding aquatic environrent. The calculations included dose estinates received fror the liquid pathways of fish and invertebrate ingestion and from shore line exporares. The results are: (a) a total body dose of about 0.01 nren which is less than 1% of the permissible total bocy dose of 3 nren/ reactor / year (Appendix I to 10 CFR Part 50) and less than 0.1% of the whole body dose of 25 nren/ year as specified in h0 CFR Part 190 Environ-nental Radiation Protection Standards For Nuclear Power Operatiens; and (b) a thyroid dose of about 0.012 nren which is less than 1% of the permissiele dose of 10 nren/ reactor / year to any crgan (Appendix I to 10 CPR Part 50) and less than 0.1% of the thyrcid dose of 75 nren/ year as specified in LO CFR Part 190 Environnental Radiatien Protection Standards For Nuclear Power Operations. D.2 Atmosnheric Environment The atmospheric enviren.ent was nonitored by analyzing samples of air particulate filters, silver zeolite cartridges, and precipitation sanples. These sa.ples were collected fron various locations surrounding the plant. D.2.a Air Particulate Filters Weekly composite air filters were collected from seven locstions; On Site (location 17), On Site (location 16), Knotty Pine (location 19), Lusby 7 \\

January 1 - Lacember 31, 1950 Locket hos. 50-317/316 (locatien 20), long Seach (location 21), Cove Point (locatien 22), and Taylors Island (location 23). These sanples were analyzeo for beta activity, ga na enitters, and Sr-69 and Sr-90. Weekly analyses for beta activity in air particulate filters revealed that the range of data for each site followed a si-ilar trend. The ranges remain fairly censistent during the first ten conths of the year, reflecting a static con-dition with regard to the a.bient atnespheric radicactivity. During the next two ncnths the ranges rise steadily to naxiruns on two occasions (i.e., the weeks of 11/3-10/80 and 12/8-15/80), then generally decrease in the direction of the previous static cenditien. The cause of these sudden increases in ambient radioactivity is the fallout from the mid-October detonatien of a nuclear bonb by the People's Republic of China. Sinilar trends have been observed following weapons testing in the past (15,16). Monthly analyses for ganna e-itters showed the presence of the fission by-products Nb-95, Zr-95, Ru-lO3, Ce-lbl, and Ce-lhh in cencesite sanplec for the ncnths of November and December. These by-products are typical of the radio-nuclides observed in previous fallout patterns (15,16) and are attributable to the nid-October detonation. Quarterly radiostrentiun analyses shewed two detectable concentratiens of Sr-S9 (vic., (0 9*0.7)xlO-3 pCi/n3 in the second cuarter connosite sanple fren location 19 and (1.611.5)x10-3 pCi/n3 in the first quarter sa=ple frc. locatien 22) and I showed the sporadic presence of detectable cencentrations of Sr-90 at all sites, ranging frc= (0.27t0.2h)x10-3 to (0 58t0.27)xlo-> pCi/n3 The positive Sr-69 j results may be related to plant operation; hewever, the relatively large errors associated with these results and the fact that these results occur exclusively at sites relatively rencte in relation to the plant, suggests that a statistical fluctuation of the radiochenical procedure for strontium deternination ray have been responsible for sone spuricus results. The Sr-90 results are nest probably related to past nuclear weapons testing, since the cencentration ranges are typical of previous years (1h, 15, 16). D.2.b Air Iodine deekly co posite radiciocine sa ples were cellected fren five locatiens; On Site (location 17), On Site (location 18), Lusby (locatien 20), Cove Pcint (location 22), and Taylors Island (location 23). Radiciodine analyses perfor ed on the sa: oles frcn all locatiens exnibited no detectable concentrations of I-131. D.2.c Precioitation Monthly conposite precipitation sarples were collected fren one site, On Site (location 'IS), and were analyzed for gross beta, H-3, garr.a enitters, and Sr-59 and Sr-90. d The results of tne renthly analyses 'of the precipitation sa:tples for beta a activity and the quarterly ~ analyses for Sr-c9 seen to fall into tne same 6

January 1 - recerber 31, 1960 Locket hos. 50-317/318 / general pattern as the results of the air particulate filters (i.e., a generally static conditien during the first three quarters of the year with a sudcen increase occurring at the end of the last quarter). This pattern as discussed provicusly, is nost probably the result of nuclear testing. The analyses for ganma enitters, H-3, and Sr-90 revealed that no detectable concentrations of these radionuclides were observed in any of the precipitation samples. D.2.d Dose Assessnent Whcle body and thyroid dose calculations were performed for various receptor stations surrounding the plant. utilizing the plant's effluent release data (2h), the prevailing neteorological ocnditions, and the appropriate regulato,ry guides -(25,26). Tne results are: (a) that en site location 18 was the recepter station with the highest overall doses; (b) a tctal body dose of about C.009 mren which is less than 1% of the pernissible total body dose of 5 nren/ reactor / year (Appendix 1 to 10 CFR Part 50) and less than 0.1% of the whole bcdy dose of 2S nren/ year as specified in LO CFR Part 190 Environnental Radiation Protecticn Standards For Euclear Power Operations; and (c) a thyrcid dose of 0.C21 mren which is less than 1f, of the pernissible thyroid dose of 15 nren/reacter/ year (Appendix I to 10 CFR 50) and less than 0.1% of the thyrcid dose of /5 nrer/ year as specified in h0 CFR Part 190 Environnental Radiation Protection Standards For Nuclear Power Operation. D.3 Terrestrial Environment f The terrestrial environment was nonitored by analyzing sanples of vegetation, scil, and well wcter. These sanples were collected fron various sampling i locations near the plant. L D.3.a VePetation Vegetation samples were' collected from three locaticns; Cn Site (location lb), a nearby farm (location 15), and another nearby fern (location 16). These sanples included corn, hay, tebacco, and wheat. They were analyzed for gama enitters and Sr-89 and Sr-90. Analyses fcr ga=na eritters revealec the presence of the following fission by-products: Cs-137 in the October 15 hay and tebacco samples from locations 15 and 16; and Ru-103, Cs-137, Ba-lho, La-lh0, and ce-lhi in the Ecvember 3 hay sanple fron location 15. The presence of Cs-137 in all of these sarples ir probably due to fallout from nuclear bonb testing. T1.e other radionuclides observed in the Noverber hay sanple are probably the fallout from the recent nuclear borb detonation of October 16. Radiostrontiun analyses of these samples showed three detectable concentrations of Sr-89 (viz., 39132 pCi/kg in the September tobacco sample fecn' location lb, 3.913.5 pC1/kg in the Cetober corn sample from location 1b, and 60th8 pCi/kg in the October tobacco sanple fren location 16) and showed detectable concentrations of Sr-90, ranging fron h.112.h to 8812.7 pCi/kg, in nest of the samples analyzed. The positive. Sr-69 results are probably plant related, while the Sr-90 results . seer.to fall within sane general patterns observed in the preceding yetrs when nuclear weapons testing was conducted (1k,15,16) and these results are mest probably attributable to fallout fror, this testing. 9 o

Jarcary 1 - Decenber 31, 1960 Cccket Kos. 50-317/316 D.3.b Soil Soil sanples were taken seri-annually fron three On Site locatiens; 11,12 and

13. These sanples were analyzed for Eanna enitters and Sr-69 and Sr-90.

l.nalyses for ganna eritters in these semples revealed detectable concentratiens of Cs-137 in all sanples, ranging fron 57:2L to 199:26 pCi/kg. This range of values is sinilar to these observed in preoperational (6) and previous cperational (16) periods. Radicstrontiun analyses of these sanples exhibited no detectable concentratiens of Sr-69 and the presence of Sr-90 in five of the six senples analyzed, ranging fron h522L to 67231 pCi/kg. This range of Sr-90 results is cenparable to the ranges observed in the preceding years of 1977, 1976, and 1979, and it is nest probably the result of past nuclear weapons testing (1L-16). D.3.c Well Water Quarterly well water sanples were collected from five 1e:atiens; Chesapeake Country Club (location 2), On Site (location 10), Long Beech (locatien 21), and dnite Sands Club (locations 25A and 253). These sanples were analyzed for H-3 and garna enitters. 1 Both the quarterly analyses for tritiun and the quarterly analyses for ga:ma g enitters in these samples revealed that no cetectable concentration of any fission or_ activaticn by-products were present. -D.3.d Dese Assessnent Dose calculations were perferned for all pathways of interest at location 16 (an off-site fann) to assess the plant's radiclogical inpact en the surrounding terrestrial envircreient. Plant effluent release data for batch and centinuous releases (2h) and on site neteorological data were utilized in confornance with apprcpriate_ regulatory guides (25, 26). The results of these calculatiens was an estinated-thyroid dose of 0.17 nren which is less than 25 of the allowable dose of 15 nren/reacter/ year to any organ as specified in Appendix I to CFR Part 50 and less.than 0.3% of the pernissible thyrcid dose of 75 nren/ year -(LO Ca Part 190 Envirorr ental Radiatien Protecticn Standards For Euclear Power Operatiens). D.h. External Radiation Monthly thernolu~inescent desineters were taken fron 13 locations surrounding the plant, namely: Plant Outfall (location 7), On Site (location 17), On Site (location 18), Kn: tty Pine (locatien 19), Lusby (location 20), Long Beach ~ (location 21), Cove Point (location 22), Taylors Island (locaticn 23), On Site (location 2h), White Sands Club Sign (location 25), St. Leonard (location 26), Solenens (location 27), and Bertha (locatien 26). The dosineters were read for nrens of external radiation dese. ~ -The:TLD data'for each site are compiled in Table 3-15 and are presented en an i annual basis in Table 2. The neans and ranges expressed in Table 2 were conpared ~10 l

January 1 - Decenber 31, 1950 Docket I,os. $C-317/316 with the neans and ranges for the previous years of 1978 and 1979 This conparisen revealed that neans and rances for 1960 were generally less than those observed in the two preceding years. In order to assess the centribution of the plant to anbient radiction levels, garra immersion dose cale'tlation, utilizing the plent's gaseous release data (2h) and on site neteorolc gical data, were rade. Tne maximum plant contribution is esticated to have beeh 0.009 nrem at locetion 16 whien is less than 1% of the allewable whole-body dose of 5 mrem / reactor / year as specified in Apperdix I to 10 CFR Part 50, and less than 0.1% of the whole-body dose of 25 mrer/ year (h0 CFR Part 190 Environmental Radiation Protection Standards For Nuclear Power Operations ). E. Conclusion T Detectable levels of radioactivity were observed occasionally in sanales from various locations during the year. The rajority of these observatiens are attributable to the atmospheric nuclear bonb testing conducted in October,1980, and in previous years. However, a few of these observations ray be directly related to the operation of the clant (e.g., H-3 in bay water, Co-58, Kn-5h, Sr-69, and Co-60 in sedinent, and Ag-110m, Co-58, zn-65 in oysters). In all cases the concentration levels for these radionuclides are very low. The results of the dose calculations performed by using the plant effluent release data, on site neteorological data and appropriate pathways indicate: ( (a) thyrcid inhalation maximum dose of 0.021 nren (at the On Site locaticn 16 about 2000 feet southeast from the plant vent) which is less than 1% of the 5 permissible limit of 15 mren/ reactor / year specified in Appendix I 10 CFR 50, and less than 0.1% of the acceptable limit of 75 tren/ year specified in 60 CFR 190 Environmentc1 Radiation Protection Standards For Nuclear Power Operations; (b) thyroid dose (maxinum via inhalation and milk pathway) of 0.17 mren (at the farm location 16) which ie less than 1% of the permissible limit of 15 nren/ reactor / year ( Appendix I 10 CFR 50) and less than 0.3% of the accept-able lir.it of 75 mren/ year specified in h0 CFR 190, (c) a total body garna irr.ersion maximun dose of 0.009 mren (at the On Site locatien 16) which is less - than 1% of the permissible dose of 5 mrem / reactor / year specified in Appendix I 10 CFR 50, and less than 0.1% of the acceptable dcse of 25 nren/ year specified in h0 CFR 190; (d) a tots 1 bcdy dose (maxinum via all liquid pathways) of 0.010 mren which is less than 1% of the permissible li :it of 3 rren/reacter/ year ( Appendix I 10 CFR 50) and less than 0.1% of the acceptable linit of 25 nren/ year - specified in h0 CFR 190. Thus it can be concluded that the observed activities, coupled with appropriate dose calculations, indicate that plant operation durinF 1980 had no significant - radiolocical impact on the environment. 11 ~- ,. -.. ~

..y .c t' u, Lg _ TABLFo 1 .t SYNOPSIS OF. THE 1980 CALVERT CLIFFS EUCLEAR POWER PLANT RAD 10 LOG 3 CAL EllV3RONNE! ITAL EONITodl1,0 P10GRAli, Docket 1.os. '50-317/318 s s 4 SAMPLM. - SA!!PLINGk' .KUttBER OF' N'U}IBSR - AllALYSI Sn. hUliBER f ' TYPE-FR!NUEllCY . LOCAT3 Ct:S COLLECTED ANALYSIS FRILU6hCY . PERR)ll!4ED l AQdATI'C ENVIRON}iENT t-Bay Water-M 2 2h-11 - 3 M 2h L lT Gama (GeLi) M 2h Sr-89 QC 8 Jr-90 QC 8 IFish(1) .q-1 8 Flesh. . p Garnna (GeLi) Q 8 Dones dr-89 Q 8 Sr-90 Q 8 'Shell ?ish(2)'. q .g-- 17 Flesh -(Crabs,'. 0ys ters). Ganan (GeLi) Q 17 Bottom Sedinanits. Q-h 16 Gansna (CoLi) Q 16 I Sr-89 Q 16 Sr-90' Q 16 Rooted Aquatic (3) [ ~ Plant Spring & 1. Gar:ma (GeLi) ?/I. Fall Sr-69 2/A Sr-90 2/A 4 t- ~ L

, g, e -TABLE 1-('CONTIhUED)l J SYNOPSIS'0F THE 1980 CALVERT CLIFFS NUCLEAR. POWER PLANT RADIOLOGICAL ENVIllOlaIENTAL MON 110R110 PROGRAM Dockst Nos. 50-317/318 l SANPLE . SAMPL11!G* NUMBER'OF NUMIER ANALYSIS

• NUliBER

' TYPE F)UN'JE!!CY - LOCATIONS COLLECTED ANALYSIS FREQUEl.CY ' PERFUle'ED ATMOSPHERlC ENVIRONFENT-- Air Iodine (b) 'W h 260 1-131 W 260 Air Particulates( ~ W 7-36h Gross Beta W 36h Gamma (GeLi) MQ 8h Sr-89 QC 28 Sr-90 QC 28 w Precipitation (6) Continuous 1 12 H-3 QC h Gross Beta H 12 Ganna (GeLi) M 12 Sr-89 QC h E Sr-90 QC h ~ TERRSSTRIAL ENVIRONNEllT' Vegetation ( At liarvest 3 8 Garrna (Nal) A 8 Sr-89 A 8 Sr-90 A 8 Soil SA 3 6 Gamma (GeLi) SA 6 Sr-89 SA 6 Sr-90 SA 6 l-

1 TABLE _1 (C0!!TINUED) SYNOPSIS OF TIE 1980 CALVERT CLIFFS NUCLEAR POWER PLANT RADIOIDGICAL ENVIRONME!JTAL MON 1f0 RING PROGRAM Docket Nos. 50-317/318 l SAMPLE SAMPLING

• NUMBER OF NUllBER ANALYSIS
• NUMBER TYPE FREQUENCY LOCATIONS COLLECTED ANALYSIS FREQUENCY PERR)R12D TEIUESTR] AL ENVIRONMENT (CONT.)

Ground Water Q 5 20 11 - 3 4 20 Gamma (GeLi) Q 20 External Radiation M 13 600 TLD M 600

• 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 dependine u,on their availability. (3) Sampling may be interrupted when no rooted aquatic plants are available. (h) The collection devices contain silver zeolite. ($) 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. i I

TABLE 2 ANNUAL

SUMMARY

OF HAIGOACTIV]TY -3N-THE &lIRONS OF THE CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND 2 (JAN.-DEC.,1980) Docket Nos. 50-317/318 Annual Results Cample Hadioactivity Typical M Site MDL's Mean (f)* Range *** iAquatic Environment Bay Water-PCi/1 7 Plant H-3 127 530 (3/12) (412h-1106) Outfall Sr-90 0.72 0.77 (1/h) (4.0.hh-C.77) Cs-137 1.1 2.3 (1/12) (41.1-2.3) 8 Plant. H-3 127 157 (h/h) (412h-200) Intake Sr-89 1.37 1.53 (1/h) 141.37-1.53) Ce-lhh 7.h 2.7 (1/12) P* Fish pCi/kg (Wet) Blue Fish 1 Cove Point Os-137 13 11 (1/3) Flounder 1 Cove Point Sr-90 69 59 (2/2) (469-102) Cs-137 13 18 (1/3) (e13-18 ) Spot 1 Cove Point Sr-90 69 61 (1/1) Weak 1 Cove Point Sr-90 69 53 Cs-137 13 13 Shellfish pC3/kg (n'et) Oysters 5 Carp Co,noy Co-58 17 22 (1/h) (417-22) Zn-65 3h 32 (1/h) Ag 'J10m 12 86 (h/h) (412-128) Bottom Sedinent pCi/kg (Dry) 5 Camp Conoy Sr-89 18h 255 (1/h) (z1bh-255) Co-58 hh 206 (1/h) (<hh-206) 5 4 P

4 TABI.E '2l (CONTINUED) Annual Results Sample Radioactivity-Typical Type Site ItDL's Mean (f)* Range ***

Bottom Sediment (Continued) pCi/kg (LYy)

. 5 Camp Conoy Co 69 1h6 (h/6) (<69-209) - (Continued) Cs-137 h33 (h/h) Co-lh1 h35 (1/h) ' 6.Long Beach **- Sr-90 h6 22 (1/h) Co-60 69 103 (2/h) (469-103) 787 (L/h) Cs-137 Ce-lh1 Bh (1/h) i Co-]hh 18h h09 (1/h) (4189-h09) 7 Plant Outra11 Sr-89 167 Sh (1/h) Mn-5h hh L3 (1/h) (4hh-h8) Co-60 69 118 -(3/h) (<.69-118 ) 562 (h/h) Cs-137 - 8 Plant Intake Sr-89 1h2 hhD (J/h) (41h2-Lh0) Mn-$h hh 175 (1/h) (<hh-175) l Co-58 17 213 (3/h) (<17-213) Co-60 69 595 (3/h) (-69-595) Cs-137 h70 (h/h) Co-lhh 18h 355 (2/h) (<16h-5C9) f l Atmospheric Environment l Air Particulates 10-3 pC1/m3 17 On Site ., Beta 0.2 2.h (52/S2) (< 0.2-9 3) Sr-90 0.h9 0.30 (2/h) Nb-95 2.h 15 (2/12) (e.2.h-20) Zr-95 2.9 9.0 (2/12) (<2.9-12) Ru-103 8.5 (2/12) Ce-lh1 11 (2/12) l

,e -TABLE 2 (CONT 3NUED) Annual Results Sample? Radioactivity . Typical . Type Site-MDL's M,ean (f)* Ranceu** Air Particulates '(Continued)' 10-3 pCi/m3 18 On Site _ Oross Ibta 0.2 2.4 ($2/S2). (<0.2-lh.1) Sr-90 0.86 0.32 (2/h) Nb-95-. 2.h 10 (3/12) (42.h-21) Zr-9$ 2.9 15 (1/12) (*2.9-15) Ru-103 12 (2/12) .Ce-lh1 $.5 (3/12) 19 Knotty' Pine Gross Beta 0.2 2.3 (52/52) (<0.2 -22.6 ) Sr-89 1.h 0.9 (1/h) Sr-90 0.h9 0.h6 (1/h) Nb-95. 2.h 33 (2/12) (< 2.5-oJ ) Zr-95 2.9 21 (2/12) (<2.9-38) Ru-]O3 7.6 (2/12) ce-]h1 13 (2/12) tj ce-) hh 6.6 13 (1/12) (< 6.6-13 ) P ' 20 Lusby Gross Beta 0.2 2.1 (52/52) (<0.2-7.1) Nb-9$ 2.h 17 (1/12) (< 2.h-17) Zr-9$ 2.9 8.3 (1/12) (< 2.9-8.3 ) Ru-103 8.3 (2/12) Ce-lhl-6.9 (2/12) 21 Long Beach Gross Beta 0.2 2.2 ($2/52) (40.2-9.2) Sr-90 0.L2 0.h6 (2/h) (< 0.L 2-0.L6 ) Nb-95 4.h 12 (2/12) (<2.h-18) Zr-95 2.9 11 (1/12) (<2 9-11) Ru-lo3 8.5 (2/12) ce-lh1 8.0 (2/12)

,J [ _s l TABLE 2' (CONTINUFD) - s Annual Results ' Sample'- Radioactivity 1 . Typical ~ Type: Site' MDL's Mean (f)* Hange*** ' Air Particulates (Con (inued) 10-3 pCi/m3 22' Cove Point ~ ~ Gross Beta 0.2 2.3 ($2/52) (4 0.2-lh ) Sr-89' 1.2 1.8 (1/h) (<l.2-1.8) Sr-90 0.$6 38 (2/2) Nb-95 '2.h. 22 (2/12) (< 2.L-33 ) Zr-95 2.9 ' 12 (2/12) (4 2.9-17 ). >c Ru-103 1h (2/12) ' Ce-lh1 13 (2/12) - 23 Taylors Island, Gross Deta. O.2 1 9 ($2/$2) (40.2-6.2) Sr-90 0.584 0.50 (1/h) Hb 2.h 16 (2/12) (<2.h-19) Zr-95 2.9 6.3 (1/12) (<2 9-6.3) W Ru-103 8.8 (2/12) 3" Ce-lhl 7.9 (2/12)

oo Precipitttien pCi/l IS On Site Gross' Beta O.? '

7.2 (12/12) (40.2-7.2) Sr-89 h.2 1.5 (1/h) Nb-95 8.0 13 (1/12) (c8.0-13) -Terrestrial: Environment Vegetation. pCi/kg (det) Wheat 1h Old Bay Farm Sr-90 h.0 26 (3/1) (LL.0-26) Tobacco lh Old Bay Farm Sr-89 hl 39 (1/1) Sr-90 h.0 37 (1/1) (ch.0-37) Corn Ih Old Bay Farm Sr-89 h1 3.9 (1/1) i Tobacco 15 Farm Sr-90 h.0 1G (1/1) (h.0-10) Cs-137 2? 16 (1/1) T r S O

p 1 g TABLE 2 (C0t4T]MJED)- Annual-Results Sample' Radioactivity . Typical ])J3 1 Site - }iDL's - Mean ' ( f )* _ Range *** ' Vegetation (Continued) pCi/kg (Wet) ' Hay' IS Parm Sr-90 h.0 h.1 (1/1) 4th.0-h.1) Ru-103 h6 (1/1) Cs-137-22 $1 (1/1). (<27-51) 'Bo-lho. '3h 716 (1/1) (<3h-716) L La-lho '1B 860 (1/1) ((18-868) Co-lhl f 169 (1/1) Hay 16 Parren'Parm Sr-90 h.0. 8.8 (1/1) (< h.0-8.8) Cs-137 22 16 (1/1) Tobacco 16 Parren ' Farm Sr h1 60 (1/1) (<hl-60) 'Sr-90 h.0 8h (1/1) (< h.0-Uh ) Cs-137, 22 5h (1/1) (<22-SL) y ' Soil. pCi/kg (Dry) 11 On Site Sr-90 h1 70 (2/2) (/.hl-72 ) Cs-137 192 (2/2) 12 On Site Sr-90 L1 Sh (2/2) (<hl 6h) Co-137 - 76 (2/2) 13 On Site Sr-90 hl h5 (1/2) (< hl-h5 ) Cs-137 80 (2/2) External Radiation nR/30 Days 7 Plant Outra11 3,06 (11/12) (2.67-3.Lh) 17 On Site 5.0B (12/12) (h.Sh-5.b1) 18 On Site h.39 (12/12) (b 02-h.77)

s TABLE 2 (CONTI}UED) Annual :tesults ~ Sample Radioactivity typical. ' Type' Site '_ -!!DL's Mean-(f)* ___ Range *** -External Radiation;(Continued) mR/30 Days 19 Knotty Pine 3.99 (12/12) (3.58-h.33) 20 Lusby' 3.98-(12/12) (3.51-h.23) 21 Flag Harbor 3.66 (12/12) (3.10-3.90) 22 Cove Point 3.82 (12/12) (3.38-h.06) 23 Taylors 3sland 5.68 (12/12) (S.1h-6.3h) 2h On. Site $.09 (12/12) (h.57-5.h5) i 25 White Sands h.69 (12/12) (h.23-5.0h) g. 26 St. Leonard 3.92 (12/12) (3.h8-h.22) ' 27 Solomons 3.7h (9/12) (3.33-h.17) ' 28 Bertha h.51 (12/12) (3.69-h.90)

• Mean encompasses only detectable quantities; fractions in parenthesis represent the proportion of detectable quantities to total quantities in a data set.

For External Radiation, the fractions represent the proportion of TLD's recovered to the total placed in the field.

• • Control locations.
    • Minimun observable to maxirum observed.
      • Minimum to maximum observed.

i. l'

January 1 - Eccenter 31, 1930 Locket !.os. 50-317/316 r* F. REF7.RENCES (1) Cohen, L. K., "Preoperational Environnental P.adioactivity Monitoring Progran at Calvert Cliffs Units 1 and 2", PFJS & 852 Seni-Annual o Report January-Jure 1971, December 1971; NUS No.1025 An::ual Report 1971, March 1973. (2) Cohen, L.K., "Preoperational Environnental Radioactivity Monitoring Progran at Calvert Cliffs Units 1 and 2", h"JS No.1137, Annual deport 1972, Decenber 1973. (3) Cohen, L.K. and Malnberg, M.S., "Preoperational Environnental Radioactivity Menitoring Program at Calvert Cliffs Units 1 and 2", NUS No.1188, Annual Report 1973, October 197h. (h) Radiation Managenent Corporatien, Calvert Cliffs huelear Power Plant Radiolorical Enviren ental Analyses, Lecercer 1971 - Decencer 1973 PJ:C-TR-7h-13, August 197u. (5) Malnberg, M.S., "Enviren ental Racicactivity Monitoring Progran at Calvert Cliffs Nuclear Power Plant", IFJS No.1332 Annual Report 197h February 1975. (6) Malnberg, M.S., "Preoperatienal Envircreantal Radioactivity Monitoring Progran at Calvert Cliffs Ur.its 1 and 2", EJS No.1333, I:ata Sunnary Report, Septenber 1970 to September 197L, July 1975 (7) Radiation Managenent Corperation, Calvert Cliffs Nuclear Power Plant - Radiolocical Envircre. ental Surveillance Procran, January 1 to June 30,197L. Decenber 197h. (6) Baltinore Gas and Electric conpany, Calvert Cliffs Nuclear Power Plant - Seni-Annual Operatine Report, July - Lecencer 197h, Maren 1975. (9) Radiatien Managenent Corporation, Radiological Environrental Menitoring Prorran - Seni-Annual Report fer Calvert Cliffs huelea" Pcwer Plant, July 1 through Decenber 31,1974, PJ:C-TR-75-Oc, August 1975. (10) Saltinere Gas and Electric Conpam; and Radiation Managenent Corporatien, Calvert Cliffs lmelear Power Pla2.t Radiological Env ren. ental Eonitoring Progran Seni-Annual neport, January 1 - Juna 30,1975, RMC-Tn-75-il, Septenber 1975 (11) Baltinore Gas and Electric Conpany and Radiation Management Corporatien, Calvert Cliffs huelear Power Plant Radiological Environ ental Monitoring Prceran Semi-Annual nerort, July 1 - Iecencer 31, 1975, EMC-TR-70-02, March 1975. (12). Baltinore Gas and Electric Conpany and Radiation hanagement Corporation, Calvert Cliffs Nuclear Power Plant Radiological Environ-ental Monitoring Progran Seni-Annial Report, January 1 - June 30,197o, EMC-1R-70-Cc, Septenber 1976. 21

January 1 - Decenber 31, 1960 locket 1;os. 50-317/316 F. REFERENCES (13) Baltimore Gas and Electric Conpany and Radiatien Managenent Corporation, Calvert Cliffs I;uclear Power Plant Radiological Envircrzental Monitoring Progran Semi-Arrual tieport, July 1 - recember 31, 1970, RMC-Tit-77-07, Earch 1977. (1h) Baltimore Gas and Electric Conpany, Calvert Cliffs Nuclear Power Plant Radiological Envircnmental Monitoring Program Arrual iteport, January 1 - December -31,1977, March 1970. (15) Baltimore Gas and Electric Company, Calvert Cliffs Nuchar Power Plant Radiological Environmental Monitoring Procran Arrual heport, January 1 - December 33, 1975, March 1979 (16) Baltimore Gas and Electric Conpany, Calvert Cliffs l'uclear Power Plant Radiological Environmental Monitoring Progran Annual deport,, January 1 - December 31, 1979, March 1960. (17) Calvert Cliffs Nuclear Power Plant, Unit Nos.1 and 2, License fios. DPR-53 and DPR-69, Anendment !so. 23 for Unit No.1, Anendment No. 7 for Unit No. 2, Appendix A Technical Specifications; Appendix B, Envirennental Technical Specifications. (18) Calvert Cliffs !;uclear Power Plant, Unit Nunber 1, License No. DPR-53, Appendix A, Techrdcal Specifications; Appendix B, Environnental Technical Specifications. (19) Calvert Cliffs Nuclear Power Plant, Unit Nunber 2, License No. DPR-69, Appendix A, Technical Specifications; Appendix B, Environmental Technical Specifications. (20) Baltimore Gas and Electric Company, Operating Procedures for Environ, mental Monitcring Activities at Calvert Cliffs I;uclear Power Plant, OP-2, OP-h, OP-5, October 1974. '(21) Radiation Manage :ent Corpc, ration, Analytical and Quality Control Procrat, RMC-2E-75-3, July 1976 (22) Baltinore Gas and Electric Company, Lab !<anual Chemical Engineering & Tests. (23) Baltimore Gas.and Electric Conpany, Operatine Procedure for External Radiation Dose Rate Measurements, OP-6,1975 .(2h) Calvert Cliffs Nuclear Power Plant, rocket Nos. 50-317/318, Semi-Annual -Effluent Release Reports; January -' June 1979, and July - Decenber 1979. (27) U,S. NRC Reguletcry Cuide 1.109, " Calculation of. Annual Ioses to han from Routine Releases of Reactor Effluents for the Purpose of Evaluating-Conpliance-with 10 CFR Part 50,- Appendix I", March 1976. .(26)' -U.S. NRC.Hegulatcry Guide 1.111,." Methods for Estimating Atmospheric ~ Transpert and Dispersien tf Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors for the Purpose of Evaluating Compl$ance with 10 CFR Part 50, Appendix I", riarch 1976. 22

6 January 1 - Lecenter 31, 1930 Docket Kos. 50-317/318 !c APPS DII A Appendix A contains information concerning the environmental sa.:ples which were collected during the period January 1,1960-December 31, 1960. Sanples locations and specific inforr.ation about the individual locations are given in Table A-1. Figure A-2 onows the locations of sa.:pling 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. I I f I F 4 e e a t b . h. 23

p TABLE A-1 UxAnt:5 CT E i:? rz3~.A: 3::n:30 s~1nc25 FOR THE CALVERT CLIFFS NUCLEAR PCWER PLANT Docket Nos. 50-317/318 DISTANCE

• DIRECTION STATION DESCRIPTION--

(FEET) (SECTOR) 1 Pound Nets South Of Cove Pcint -38,G00 SE 2 Chesaceake Country Club 20,000 SSE 3 Kenwood Beach 35,000 NNW 4 Rocky Point 10,000 NNW 5 Came Coney 3,0 00 SE 6 Lon9 Seacn 15,000 !UW 7 Plant Outfall Area 2,500 NE 8 Plant Intake Area 5,000 E 10 Onsite Well 500 SE 11 On Site 1.300 WNW 12 On Site 1,500 WSW 13 On Site 2,400 SSE 14 Cultivatad Field on Site 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 S,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 25 White Sands Club Sign 7,300 WSW 26 St. Leonard 27,000 NW 27 Solomons 42,000 5 23 Bertna 17,000 S 29 Flag Ponds 7,500 KW 30 Store (Lusby) 9,900 SSW IS On Site 1,400 SSW PS Plant Site 4,500 NNW Distance measured from plant vent. _ 2h

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.3 Data Tatles Appendix 3 is a presentcticn cf the analytical results of the 19E0 Calvert Cliffs !.uclear Fewer Flant ?.aciclorical Envircr ental Eenitcring Progra. TABLE 1.~0. TA31E TITLE FAGE w B-1 Concentratiens of Tritiu, Ga.-.a E.itters, and Stronti=-6 9 and -9 0 in Eay date r------------------------ 25 3-2 Concer.trctiens of Gar: a Fr.itters and Strenti=-59 3 and -90 in Flesh and 3:nes cf Edible Fish---------------- -7 3-3 Concentratiens of Ga.-.a E.itters in Shellfish Sa. ples---- 30 E-h Ccncentrations cf Ga-.a E-itters and Strentiun-59 and -90 in Ectten Se di ent-------------------- Ji 5-3 Concentrations of Iodine-131 in Filtered Air------------- 32, 33 3-6 Cer.centrcticns of Beta Enitters in Air Particulates-----

c, ;>

3-7 Concentratiens of Ga.:.a Enitters and Strentiun-69 and -90 in Air Particula tes------------------------------ On J7, 30 B-5 Ccncentraticns of Beta and Ga..a Fritters and Strentiur.-59 and -90 in Precic. itatien - Statien IS ( On Si te ) - -- - - --- --- - - - - - - --- --- - - -- - - - -- - -- -- - -- -- ---- -- J7 30 reposition of Beta and Ga.v.a E itters and Strenti=-59 and -90 in Precipitatien - Staticn IS (On Site )---------- LC 3-10 Ccncentraticns of Ga-.a E.itters and Strentiur-69 and -9 0 i n Ve ge ta tien----------- ------------------------- L1 5-11 Cencentraticns of Ga r.a E-ltters and Strontiu.-69 and -9 0 in Sc i l - ---- ----- ---- -- - - -- --- --- -- -------- --- --- L2 3-12 Ierecitien cf Ga.ra E-itters and Strentim-59 and / -y 4n cm.,2---------------------------------------------- 1; 5-13 Cencentratiens cf Triti= and ,a.- a F.itters in Grc=d Water---------------------------------------------------- LL 3-lh Typical v.DL's for Ga.r.a Spectreretry--------------------- L5, L6 3-15 External Radiatien--------------------------------------- L7, LE 27 -____s

TABLE B-1 ~ CCI:CDdRATICIIS OF TRITII.iE, GA!'MA D2TTZaS*, ISD STi:C). TIUM-89 A!;D -90 Ili 3AY ~.lATER (Results in Units of pCi/1 2 d) s Staticn Garc.a Date lio. H-3 Eritters Sr-69** Sr-9CW 1/16/80 7 1166!128 8 200-422 2/n/80 7 (127 <. 3. 72 40.69 8 177:120 < h.5L <0.79 3/2h/60 7 4 126 5 < 128 L/16/80 7 3031121 8 1311121 5/19/80 7 < 129 - <.1. LO 1 C,77 0.L3 8 < 131 <.2.L1 <1.12 6/13/80 -7 < 131 S <130 7/1h/80 7 (129 8 (129 8/15/60_ 7 <128 <1.37 40.LL 8 <127' 1.5311.20 <0.60 i 9/28/80 7 < 126 8 < 125 10/15/80 7 1hc:125 S 412h n/20/80 7 < 12h tl.62 e0.72 8' 121:n? <1.L 2 40.67 12/11/80' 7 '<125 6 < 12h

• Cesiun-137 wcs observed in tne Febr tary scnple fren statien nunbe-7 at a concentretien of 2.310.9 pCi/1. Certun-lll was observed in tne I;overr.ber sanple -

fren station nunber 8 at a cencentrition of 2.7 2.7 pCi/1. 1;aturany occurring K-LO was observed in c11 sanples. All other ga:=a enitters not cited were '<FDL; typical MDL's are given in Table B-1L.

• • Analyses done on quarterly conpesites of nonthly sanples.

28

TABLE B-2 CONCENTRATIONS OF GAKMA EMITTERS

• AUD STR0hTIUM-89 AND -90 IK FLESH AND BOUES OF EDIBLE ESH o

(Results in Units of pCi/kg 12 6) O Station Sanple Sample Ko. Date Tyoe Cs-137 Sr-89 Sr-90 11 First n (Pound Nets Quarter South of Cove Point) 1-6/23/80' Blue Fish <MDL <119 h112b Weak Fish 22110 3361190 48h .1 -8/22/80 Blue Fish 11111 <171 45L Flounder 1819 <276 102158 Spot Fish <FDL 4160 61138 Weak Fish 1317 483 53:18 1 11/21/80 Flounder <MDL e51 16:10 12/11/80 Blue Fish <MDL 4 23 / 6.3

• Naturally occurring K-h0 war observed in all' sar.ples. - All other gamma enitters not cited were eMDL; typical MLL's are given Table B-lh..

• • Sanples unavailable

( s Ji 29' ';.. e t b. -..e = -1 x . = - --.--.t - w.---e

TABLE B-3 CCECE!;TRATIONS OF GPT.A i2GTTE?.S* IN SHELLFlSH SAMFLES (Results in Units of pCi/kg (det) 12 6) Station Sample No. Quarter Type Co-58 2n-65 Ag-110m 3 1 Crabs (Kenwood Oysters 4MDL <MDL dIL Beach 2 Crabs dDL eFDL <MDL Control Oysters <MDL d.DL <MDL Location) 3 Crabs <MDL < IE eMDL Oysters (MDL <MDL <MDL h Crabs <MDL <MDL <MDL Oysters < MDL <MDL xMDL h 1 Crabs (Rocky 2 Crabs <MDL

• MDL

<MDL Point) 3 Crabs <MDL <MDL <MDL h Crabs <MDL <MDL <MDL - 5 1 Oysters 2216 3211b 128-40 (Camp 2 . Oysters <MDL <MDL 7811L Conoy)- 3 Oysters <MDL <I:DL 80112 h Oysters <MDL <MDL $819 . 8 1. Crabs (Plant 2 Crabs <MDL <MDL <MDL Intake) 3 Crabs <MDL 4IDL <MDL 'L-Crabs <MDL <I E <MDL

• Naturally occurring K-hO observed in all sa:tples. All other gaw.a emitters not cited were <MDL; typical MDL's are given in Table B-lh.
  • Samples unavailable.

30. O e 4

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