ML20211B442
| ML20211B442 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/31/1985 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20211B410 | List: |
| References | |
| TAC-64735, NUDOCS 8606110653 | |
| Download: ML20211B442 (268) | |
Text
{{#Wiki_filter:._... _. _ _ _ _ _ _. _ _ _.. _... _ -. _. . ~ _ _ _ _ _ _. _... _ _ _. _ _. _ _ _ _.. _. _ _ _ _.. _. - _ - _. _ _ _ x 3 ii l l@ i \\^ i I L i a ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING' REPORT l L as required by: l I Rancho Seco Technical Specification 6.9.2.2 j >i i t 8606110653 860527 PDR ADOCK 05000312 R PDR. 1 r I P
1985 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT k RANCHO SECO NUCLEAR GENERATING STATION EXECUTIVE
SUMMARY
i The Rancho Seco Nuclear Generating Station Unit No. 1 is located approximately 26 miles north-northeast from Stockton and 25 miles southeast from Sacramento in Sacramento County, California. Rancho Seco Unit No. I began commercial operation on April 17, 1975. The single unit on the Rancho 3eco site is a pressurized water reactor supplied by Babcock & Wilcox. The rated capacity is 2,772 megawatts thermal and 963 gross megawatts electrical. This report has been prepared by the Sacramento Municipal Utility District to meet the reporting requirements of Technical Specification 6.9.2.2, Operating l License No. DPR-54. It is transmitted to the U. S. Nuclear Regulatory l Commission Region V Office of Inspection and Enforcement. Copies are provided to the California Department of Public Health, Sacramento County Health r Department, California State University at Sacramento, Central Valley Regional Water Quality Control Board, local libraries, and District offices as a pubile document. This report is a diverse document which assembles several related items as required by the Technical Specification. The document includes: l Summaries, interpretations, and statistical evaluations of the results of O the radiological environmental surveillance for the calendar year 1985. Comparisons with preoperational and previous years data. Descriptions of the elements of the radiological environmental monitoring program. Haps of sampilng locations keyed to tables which give distance and direction from the containment building. J Results of the land use census. Results of the interlaboratory comparison program for the District's environmental monitoring contractor. Assessment of the radiological impact based on environmental sample and l land use versus information. Also included is the complete text of the report of special environmental monitoring studies performed by the Lawrence Livermore National Laboratory during 1985. O I i
Data and information were obtained from several sources: Controls for Environmental Pollution, the District's routine environmental monitoring program centractor. Lawrence Livermore National Laboratory, the District's contractor for special environmental monitoring studies. District staff investigations. The State of California Department of Health Services, Radiological Health Branch. Factors outside the control of the District have delayed completion of the land use survey of nearby residents who use the liquid effluent pathway for food and recreational purposes. The Land Use Census as required by Technical Specifications 3.23 was completed. In brief, the results of the 1935 radiological environmental operating program indicate the following: Land use in the gaseous pathway is essentially unchanged. Residents who regularly used the liquid effluent pathway for food or recreational purposes stopped using the stream system in late 1984. Normal usage of Laguna Creek and Folsom South Canal water for irrigation continued. Radiation exposures in the region are unrelated to plant gaseous effluent releases and appear to be due to local geology. Air sampling data were all negative with respect to contribution by the plant. Radioactivity persists in streambed sediments and aquatic flora and fauna in the Clay-Hadselville-Laguna Creek systems. The radioactivity is principally Cs-134 and Cs-137. No radioactivity in any environmental samples could be attributed to releases in the gaseous pathway. Radiation doses which were calculated for various uses of the liquid pathway totaled approximately two milltrem for 1985. The interlaboratory comparison is satisfactory. O ii
RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS I. EXECUTIVE
SUMMARY
1 II. DATA INTERPRETATION,
SUMMARY
OF ACTIVITIES, AND CONCLUSIONS 1 Air Particulate 1 - Gross Beta - Radiolodine - Gross Alpha - Gamma Spectroscopy TLD 21 - Quarterly Results - Log normal representation - Log normal procedure and interpretation Algae 39 Animal Vegetation 44 Edible Aquatic Fauna 46 Milk 50 Mud and Silt 54 Rabbits 56 Hater 58 - Runoff - Surface - Well Water - Drinking Hater Human Vegetation 65 Beef Tissue 67 Cow Thyroid 69 Honey 71 111 l
IV. ASSESSMENT OF IMPACT ON THE ENVIRONMENT 73 Radiological Impact - Gaseous Effluents 74 Radiological impact - Liquid Effluents 75 Summary 90 Appendices A Land Use Census A-1 B Program Summary Description and Maps B-1 C Environmental Radiological Studies Downstream from the Rancho Seco Nuclear Power Generating Station-1985 LLNL UCID-20641 C-1 D Interlaboratory Comparison Program Results 0-1 E Missing Samples E-1 List of Tables Particulates Released into Sectors with Air Monitors 19 Air Samples Results - Quarterly Arithmetic Mean Gross Beta 20 Environmental Air Sampling Correlations 17 Thermoluminescent Dosimeter Results 25 1985 Correlation TLD vs Noble Gas Release 36 O Noble Gases Released into Sectors 37 TLD Measurements Since Last Atmospheric Heapons Tests 38 Hater Sample Matrix 64 Stream Usage Factors 78 Source Terms 79 Calculated Doses (mrem) for 1985 80 Results of 1985 Gaseous Pathway Census A-3 Galt Irrigation District Water Usage A-4 Detection Limits by Gamma Spectrometry B-7 Radiological Environmental Reporting Levels B-8 List of Figures Air Sample Data Pre-Operational Period 9 Air Sample Data Response Time Following Nuclear Test 10 Air Sampling Quarterly Arithmetic Mean Particulate 11 Site A (RAAO) Quarterly Means 1976-1985 12 Air Particulate Analysis 1985 Q3 13 Air Particulate Comparison Data 14 Air Particulate Levels 15 Air Particulate Analysis 1974 Quarter (1) 16 iv
List of Figures (cont.) Sample 16 TLD Data (Chronological Plot) 29 v Sample 16 TLD Data (Lognormal Plot) 30 i Mean Quarterly TLD Results 1980-86 31 Micro R/ Hour Based on 50th Percentile 32 TLD Group Data (Lognormal Plot) 33 TLD Log Probability Distributions 34 i Algae Samples 1985 K-40 42 Pre-Operational Algae Samples 43 Milk Cow Distribution / Farm 53 Cs 137 Concentrations in Fish at 0.5 KM 81 Cs 137 Concentrations in Fish at 7.5 KM 82 Catfish Flesh 1985 83 Bluegill Flesh 1985 84 Bass Flesh 1985 85 j Cs 137 Concentrations in Frog Legs 86 l Stream Bed Sediment Concentrations 1985 87 Water Concentrations 1985 88 Environmental TLD Locations (20 Mlle Radius) B-9 Environmental TLD Locations (5 Mlle Radius) B-10 j Environmental Sample Locations B-11 l EPA Interlab Comparison D-3 v
O AIR PARTICULATE O O 1
DATA INTERPRETATIONS AND CONCLUSIONS / AIR PARTICULATE \\ OATA SL'MMARY GENERAL Air particulate samples are collected on a weekly basis from eight fixed Sample Volume Range: 8K-24K ft3 monitor locations. Test volumes range 3 from 8000 to 24000 ft. The air 3 Samp'e Flow Rates: 0.8-2.4 ft / min flow is directed through a glass fiber filter followed by a radiolodine Number of Sampler Locations: 8 cartridge (activated charcoal). The purpose of these samples is to monitor the lodine and air particulate pathways.
===__
_==--- GROSS BETA Gross Beta activities for the year 1985 ranged from 0 to 0.059 pC1/m3 Filter type: 900 AF, Reeve Angel for the weekly samples. Mean 0.3 9 glass fiber quarterly averages ranged from 0.013 filter. to 0.029 pC1/m3, Planchette: 50 mm stainless Gross Beta activities for the previous steel year (1984) ranged from.000.037 pC1/m3 This is consistent with the Counting current year. Instrument: Beckman Wide Beta II Internal Flow Proportional Countar Calibration l Source: Cs-137 Efficiency 43% Count Time: 100 min. Sample Period: Weekly (168 hrs.) LLO: 0.002 pCl/m3 Reportable Level:
- 2.0 pC1/m3
- Reportable levels are levels which the NRC requires notification and which CEP is required to notify SMUD.
O 2
f DATA INTERPRETATIONS AND CONCLUSIONS I AIR PARTICULATE V DATA
SUMMARY
RADI0 IODINE No radiolodine was detected during 1985. The lower limit of detection Method 1 being 0.01 to 0.02 pCl/m3 If the alkaline leach method is used, the t Filter type: Activated lower limit of detection is Charcoal (CP-100) 0.004 pCl/m3 Counting Instrument: Intrinsic Radiolodine activity ranged from 0.004 Germanium to 0.234 pC1/m3 during 1984 Only one reading (the highest) was Spectroscopy System: Northern different in magnttude from the Scientific current year. This occurred during TN 4500 the period 8/14-8/21. This wac probably due to a release from the Calibration Source: I-131, first 5 reactor building wnich started on mm of charcoal August 15, 1984. The sample was changed out later the same day. Count Time: 8 hours Sample Period: Weekly q)LLD: 0:01gC1/m3-0.02 pCl/m
- Reportable Level:
0.9 pC1/m3 Method 2 (Alkaline Leach Concentration) Filter type: Same as above (Method 1) Counting Instrument: Beckman Low Beta II Thin window flow counter c Calibration Source: Iodine-131 as ( AgI impregnated in the first 5 mm of charcoal (NBS Traceable) Count Time: 100 min. i Sample Period: Weekly Analysis l only if method 1 analysis reaches (O the reportable V) level of 0.9 pC1/m3 l 3
DATA INTERPRETATIONS AND CONCLUSIONS AIR PARTICULATE OATA
SUMMARY
i LLO: 0.004 pC1/m3 ] r \\
- 0.01 pC1/m3 if analysis is performed within 24 to 48 hrs.
( 0.02 pCl/m3 if analysis is performed i 48 hrs, to 120 hrs. ( s i No gross alpha activities were GROSS ALPHA detected during the year 1985. In Filter type: 900 AF, Reeve addition, no gross alpha activities Angel 0.3F, ,' have been found in the air glass fiber particulates since the date of initial = l
- filter, criticality except for one sample in the 4th quarter of 1984 which read Planchette:
50 mm stainless 0.005 pC1/m3 steel. Counting Instrument: Beckman Wide Beta II or a t l Tennelec LB 5100 low background simultaneous '( counter. s Calibration Source: Pu-239. Beckman efficiency 73% Tennelec efficiency 21% I 3 LLD: 0.005 pC1/m3, t l l f I + 1 8 e i-I s l l i
DATA INTERPRETATIONS AND CCHCLUSIONS 1 AIR PARTICULATE j DATA
SUMMARY
GAMMA SPECTROSCOPY No activities of gamma emitting radionuclides of interest (i.e., Filter type: 900 AF, Reeve fission or activation products) were Angel 0.3F, detected above the respective LLD's glass fiber for each radionuclide of interest
- filter, during 1985.
Examples of lower limits of detection for the primary gumma Sample Period: Quarterly emitting-radionuclides of interest composites of (other than radiolodine) are given in I weekly air the adjacent data column. l particulate filters in a i Marinelli beaker. l . Ceunting Instrument: Intrinsic l Germanium l Counting System: Northern l Scientific l TN-4500 l LLD: Cs-137 - 0.001 l pC)/m3 l Reportable Levels: Cs-137 - 20 901/m3 Cs-134 - 10 pC1/ra3 l t 4, 5 n., ,c..--
~ y r a.. j DATA INTERPRETATIONS AND CONCLUSIONS ~ [ AIR PARTICULATE 6
SUMMARY
\\ 5 ' DATA
SUMMARY
l ma Air Sample Pathway Summary. Gross beta activities durina 1985 ranged from 0 to 0.59 pC1/m3 for Gross Seta: weekly samples. Mean quarterly averages ranged from 0.013 to 0.029 pC1/m3, This is consistent with measured i activities during 19Q4 which ranged from 0 to 0.37 pCl/mJ. Pre-Operational data ranged from 0.031 .to 0.228 pCi/m3 due to tr:e effects 'of fallout due to nuclear weapons tests. Proportional data during quiescent periods showed values in the 0.030 pC1/m3 range. ~ Figure I showt a presentation of quarterly averages for all stations l l during 1971. This shows consistency for all Tracking Stations during the I [J] periods of preoperation. l _ Figure 2 shows a presentation of the effects of weapons test fallout. The gross numbers indicate that bulk effects of testing typically require two to three weeks for levels to subside to normal for the area. Inspection of the graph show that testing during this period can raise the measured / levels to a factor of 50 or more higher than normal. Figure 3 shows a time period variation decline in gross beta values from 1976 i l through 1982. Since 1982, the values I have been relatively steady in the l range of 10-20 femtocuries/m3, i Figure 4 shows a log normal presentation of data for one site (RAAO) quarterly means for the period 1976 through 1985. Deviations from the log normal tendency are investigated and typically have shown either a proximate release of activity ) shortly before collection and/or l / fallout from weapons testing. l \\ l 6
DATA INTERPRETATIONS AND CONCLUSIONS O AIR PARTICULATE
SUMMARY
DATA
SUMMARY
Gross Beta (Cont.) The averages of all stations for the third quarter of 1985 were examined statistically as a sample to show the consistency of the whole program. Figure 5 presents this analysis as a log probability graph. The close fit of the points to the regression line indicates that the overall program is working well. Environmental samples of all kinds historically fit into a log normal distribution if sufficient data are available. The detection limit for the system is added to provide a convenient reference point. i Figure 6 shows log normal presentation of identical locations monitored by the state of California and by the Rancho Seco program. Notice that both systems were consistent, but that the difference between systems is O, approximately a factor of five. We are currently investigating this i difference. Figure 7 shows a presentation of significant activity levels in terms of detection and response. Based upon the ranges of the actual data, the Olstrict is investigating lowering the i notification levels. I l Figure 8 shows a presentation of weekly mean gross beta values for the first quarter of 1984 air particulate results. The log normal plot allows a visual picture of the data distribution. The consistency of the measurement procedure can be seen by the degree of conformity to the straight line drawn as a best fit. Figure 9 shows a present'ation of I proportiunal data from 1974 as sample data set. I [ l ( I 7 H l
DATA INTERPRETATIONS AND CONCLUSIONS t AIR PARTICULATE
SUMMARY
DATA
SUMMARY
Radiolodine: No radiolodine was detected in air samplers during 1985. Values observed in 1934 were non-detectable except for one sample during the period 8/14 - 8/21. It was determined that this high sample (0.234 pCl/m3) was due to pulling the sample the same day as a reactor building release occurred. Preoperational data for radiolodine were based on gamma spectroscopy instead of beta measurement of AgI precipitate. No measureable activity for radiolodine was found. Gross alpha: No gross alpha activity was detected during the year 1985. No gross alpha activity has been found in any samples taken since the initial criticality except for one sample which read 0.005 pC1/m3 in the fourth quarter of 1984. Gamma Spectroscopy: No gamma activities were detected above the respective LLD's for each nuclide (i.e., fission or activation products) of interest during 1985. This is consistent with no activities found during 1984. Preoperational data showed no gamma activity of interest except when directly associated with nuclear weapons testi.19 a 8
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6. .6 g-g-S.:. ~ .5 I 5 u l = W==- 4= #=-i= t== f Pitm:- 1--E=t=1 =T#ss= :==-i=Mm=4Y4=t E :=R== '.~~M==^-~===--- E 2 4 _ W-E--M -=== =V4= Y=i=- 2541~ ~B #M--M "EE=u~ 4?MG=W 2==tE'~= 1&L = *^~'*?=* -~ _s E __sEs.2 :-R-W".5= :==~==@-EE :- =k'-LElt.P-E-iE-fi'-- 1" " "'-l= I==-5
=== =:- C= E- ~ Lf ;iE =" :: = .-..==n ___==_m===_=.::_==u._:.=.=.-.r==__....____- = = - - _. _3 3_- 1 s: = _ _ _ _ _ _. _ =._. .0 3 8 -~.g~= ~p-- l =r__ =:= - -- u _. -- = 0_ _0 7. _2 - _= = :=--- '.., =____a===.:==_====-- -...r. -_- _ _~ -h. .-.=u=*_.----e = .m..._.'. I -4~ y b_ _- _ _._ _.1-- C_U M U L-ATIV E1 PE R.C E N T.-t-- , Figure ~.6. l l \\ .0 01. - .i I \\. ..30 35 40 45 50 5.5 6.0 6.5 70 i
- CEiTS 14
=_==----==_==.===---.===..m=-=-
=====--- AIR PARTICUlfATEkEV_Et.5 ~~ 2 = 2- - - - - - - - - - - - - - - - - 2.G: pCl/m3 -- F-REPORTABLE liEVEL7S- ~ ~ \\- i2 2 U*
- 1. 0.=_
=. - _.. _... _.. - _ - -. _ _. _. _ _ _ _= __.__ T' (' 6: S'?NAEETECTED EEVEE DURING PREP PROGRAM = Air pCIT*M ~ a. pCi/m3 ~' 3 i 1; l \\ z ,1 c 4 i j 01 Lar-- :_c; _rr-VAtt!ESrDU RING -urrnz--- --- -Ex-- x_sl RANGE-OF-ME ASURED l iiC xxxx- - _ _ _. ~ ~--- - = ~=' PREMPdPROGRA"r Ei 7 c-5GGGr s1Ei-._._ _r3 ei / =EECRTASt E tEYEM ') _,/ BASEEEON=37 _ _ ___. ___ _. S_ r g yo ro4FrHRU M 75'id o VARIXTIOfEOF TIM 4VERAGE ~ -seuumwemitgymnausqpuu_m9 = l 2i 5 tE i c 2 i h 2 U i l =5e l I I 2[*b I gg5 Ei! ' MI N.-D ETECT E D-L EV Elk-DU RINGf R E-O P-P R O G R A Nh 010-pC l/ m M .01 .==-.- : = =. : - : T _==== - ' . r z.: :- - - - - z. ;_q = 2 ; --- - 3 j e ,5-
- 3 m e - __ __
l
- 5 2
l $ 0 e-4 S i i MINIMUM DETECTABEE~CEVEL5002EpCI/m3 1 2 q LJ i Eigure 7d .001
n i 9 1,.,, 5 4 3 2 i 9 t 1 6 5 4 3 t ._ 9 n ^ 9 o O' o 9 u 9 s o 9 a 9 S Af 9 o _ 8 2 I r-r e 9 9 o _. S E,,, _ 1 . Y $s.g 5 L 0 is 1 $lg s a 9 g lI. 9 i a_ T R a _ _ 'g - E M ATp t 3 l 9 2 _ Ml3m_ A i A M L I 1 5 G _ _. - p Og /; _ 9 5 O N _ I T 3 I I T 40 4p. l 7, l E C 8 E 0 9N h o 9 D T 6 t 4 i i E 0 I d i D i g 08 2 w e 0 o g 7 a L 0 6 4 ,I L 4 l 0 . Oo O i 0 6 4 s i.I1, p, I. m 1 j 04 .W "s, l 0 o 3 / l 6 ? .2 T 1 l 0 a, 5 5 3 o 3 1 3 2hn.,'i 2 t j$ j I 0, ". ,n , J U, _0 7 0 i : 1 4 r 1 9 i. 1 /, P l I 2 i i 6 P pH 1 7. _4 5 I 2-2 B 2 i 5 7 9 _ 1_ CU .~ y_ { 4' _j4br 7 7 7 7 7 E 2 + 8 ? b l [ ( 9 I 8 1 U 1 w 1 .2-5 5 1 5 0 l - 4h'f )l; 1 0 0 O 1 1 l _'j 1 1 i 1 1 1 . F F l .H l 2 a l t _0 % f A A A M.. I e _1 9 1 R R-R R R 0 w i' I
- "-y 5
0 0 Ow.._ f 9 1 9 s. 0 0 3 9 t 1 6 5 4 3 3 1 i 0 9 a /,, 5 4 3 2 m 0 1 1 2 0 0 / lC 0 p lfl I ll
CORRELATION OF AIR SAMPLER RESULTS WITH [mT PARTICULATE RELEASES An attempt was made to correlate environmental air sampler results with particulate releases from Rancho Seco. Time periods were chosen to exclude periods which indicated effects from atmospheric weapons tests. The year 1983 was also excluded because default meteorology was used. The releases were adjusted for sector by multiplying the relative wind frequency by distribution. Except for RAHO, the sector values were correlated to the gross beta air sample results. RAHO was correlated to the total release, due to its proximity to the site. The releases into the sectors are shown in Table 1 attached. Sampler gross beta results are shown in Table II attached. The correlation coefficients were obtained from the standard deviations of the popluations with respect to the linear regression line. The equation for the correlation coefficient, r, is as follows: nlXjYj - IXjlYj r-1-(IXj)2gnIYf-(lYj)2 2 nlX l Table III summarizes the results obtained. ' V TABLE III ENVIRONMENTAL AIR SAMPLING CORRELATIONS CORRELATION LOCATION DISTANCE AND DIRECTION l SAMPLE COEFFICIENT NAME FROM SITE RAA0 -0.227 7 miles Northwest RAB0 -0.137 SMUD Headquarters 23 miles Northwest RACO -0.207 Lodi ~18 miles South-Southwest RADO -0.163 Tokay Substation 1 mile South-Southwest l RAE0 -0.191 Ione 9 miles East l RAF0 -0.217 Carbondale 8 miles Northeast RAGO -0.247 Fish Hatchery 11 miles South-Southeast RAHO -0.220 Rancho Seco On Site l 17
{g'} The lack of correlation is not unexpected. The minimum detectable concentration (MDC) is 0.002 pCl/m3 for a one week sampling period. Table IV lliustrates the required emission rate at a few average concentration / emission factors (X/Q). TABLE IV X/Q FCI/HEEK FCI/ QUARTER 10-4 12 147 10-5 120 1570 10-6 1200 15700 A detectable concentration thus implies an elevated X/Q and/or release ratio for an extended period. Table IV indicates that the required total release rate for a X/Q of 10-5 was exceeded only twice in the period of consideration. During the highest period (fourth quarter 1982), not only were the quarterly averages lower than normal, but no station had any reading higher than 25 fC1/m3, The conclusion reached is that plant releases have little, if any, measurable effect at the air sampler locations. The average values for 1985 and the period of consideration are approximately the same as pre-operational data taken in 1973 when atmospheric weapons testing apparently was not a factor. l l i 18
4 s. TABLE 1 l PARTICULATES RELEASED INTO SECTORS WITH AIR PONIIQRS FOR PERIODS UNAFFECTED BY WEAPONS TESTING AFTER 1/79 (1/79-9/80, 7/81-12/82.
- 1/84-4/85)
(Microcuries) 1979 1980 1981 1982 1984 1985 1 2 3 4 1 2 3 3 4 1 2 3 4 1 2 3 4 1 2 3 4 NE I.43 21.5 110.7 2.51 76.1 35.0 0 2.09 4.47 2.52 2.63 0.94 208.4 1.04 1.34 2.41 6.77 13.9 12.01 1.81 27.6 E 1.66 9.72 26.3 2.52 123.0 3.36 0 8.78 1.06 0.80 0.71 0.74 120.6 0.36 0.50 1.44 2.0 4.75 9.99 1.12 43.7 SSE 1.07 2.52 11.3 2.25 76.0 2.50 0 1.39 3.33 0.76 7.85 11.9 239.5 0.3 4.40 21.0 2.74 3.76 65.52 16.5 30.0 SSW 1.48 2.02 6.58 2.82 136.9 3.09 0 0.47 1.70 0.73 4.5 3.58 796.9 0.45 2.30 4.92 2.51 26.3 33. 5.08 9.64 NW 3.1 6.32 31.8 3.07 226.0 17.6 0 0.71 1.73 0.48 1.97 1.44 272.1 0.85 2.27 4.91 10.8 9.6 34.9 1.89 89.1
- 1983 data not used because of default meteorology.
l m
(w~ ( ) m v TABLE II AIR SAMPLER RESULTS - QUARTERLY ABITietETIC MEAM carKC RETA (Femto Curles per Cubic Meter) 1979 1980 1981 1982 1984 1985 1 2 3 4 1 2 3 3 4 1 2 3 4 1 2 3 4 1 2 3 4 RAA0 23 24 21 33 17 14 17 44 22 7 10 4 9 16 10 15 18 23 13 15 25 RABO 7 7 5 19 16 11 12 39 24 13 14 3-10 15 10 15 19 26 14 15 26 RAC0 19 15 11 21 25 8 13 3 18 9 14 4 6 17 8 14 15 26 14 14 23 RADO 23 28 16 27 28 15 17 57 26 20 10 7 12 17 10 16 20 27 14 16 27 RAE0 20 27 26 48 21 16 21 68 27 11 8 5 9 16 9 20 12 26 15 18 27 i RAF0 24 26 24 28 19 17 24 61 28 15 14 8 11 18 11 17 17 29 15 18 26 RJ.GO 22 23 19 28 17 14 18 49 16 10 10 11 10 16 11 13 16 22 14 16 26 RAHO 22 14 17 27 20 15 14 55 28 20 12 6 10 18 13 11 18 27 14 16 27 l l i + a
m I l l l l THERM 0 LUMINESCENT 00SIMETRY l l I l l 21 l l
DATA INTERPRETATIONS AND CONCLUSIONS '3 TLD ] DATA
SUMMARY
TLD (Thermoluminescent Dosimeters) During the preoperational period, the 19 TLD monitors showed an average Number of Locations: 63 value of 7.61 micro R/hr. The high value was 10.1, the low value was System: Matsushita 5.1. [1973(1) - 1974(2)]. Electric Industrial During the operational period Company [1974(3)-1985(2)], the 20 TLD (Panasonic locations averaged 8.43 micro R/hr in Distributor) each quarter. The high average value was 11.2, the low average value was System Model: UD-7020 6.8. Dosimeter Model: 804 The 1985 quarter summaries showed the following data: Phosphor: CaSO :Tm 4 Quarter 1 and 4 7.97 Phosphors / Dosimeter: 3 Quarter 2 8.95 Quarter 3 8.83 l Dosimeters / Location: 2 l These readings could reflect the j Readout Period: Quarterly 26 decrease of air particulates and radon / l / days thoron effects on the TLD's due to the G i rainy season in quarters 1 and 4. \\ Calibration Source: Cs-137 NBS Traceable The TLD system operation shows a fairly good precision for results from Contractor: SMUD "Inhouse" the system as a whole. Figure 2 presents a sample set of data for the l Statistical Precision: 220 period 1981 through 1985 for one TLD location. (Sample 16, map location Outlier Rejection: "R" Ratio 11, west of site near Clay at 2.5 Technique miles from the site). The data are plotted on cumulative log probability l paper. If the data are truly log i normal (as natural radiation levels are), the data if precise will fail close to a straight line. The degree of fit to the line will indicate the overall performance of the system. Deviations from the line should be examined including changes in shape. The log probability plots show data values on the vertical scale and cumulative percent on the horizontal scale. The percent is calculated by dividing the number of the data point O i ()* Note: 1973(1) represents the year 1973 and Quarter 1. l 22 l l l
DATA INTERPRETATIONS AND CONCLUSIONS /7 TLD DATA
SUMMARY
(in ascending value order) divided by the number of data points. The last point is not used since it would yleid 100% and would be off scale on the l probability paper. The term " probit" refers to one geometric standard deviation (GSD) on the graph. This corresponds to the 16th and 84th j percentiles respectively as
- 1 GSD l
from the geometric mean (or 50th percentile). Figure 6 shows a cut and pasted series of TLD log probability plots for a sample period of 1981 through 1983. The normally sloped curves have been turned to present flat data for l viewing ease. At the extreme left end l of the curves, one can see the data shape changing (i.e., dropping off). Shape changes like this can indicate system problems. At the extreme right, one can see data rising above l 3 the line. Examination of these points j t showed a few locations being affected by radiological storage and others due to naturally high environmental levels. Figure 1 Indicates the data precision for the same location as described in Figure 6 in the above discussion. As I can be seen, the levels of the data show consistency. Deviations such as in the third quarter of 1985 should be investigated. Figure 5 presents two curves (dotted and solid) which show the historical range of TLD data since the inception of the program. The dotted line indicates the range of data since the expansion of the TLD location number l from the original 19 to the current 59 (through the 2nd quarter of 1985). Future quarterly log probability plots can be examined on a clear acetate overlay (from which this was made) as s a very convenient QA check. 23
DATA INTERPRETATIONS AND CONCLUSIONS O TLD DATA
SUMMARY
Figure 3 shows the graphic plot of mean quarterly TLD doses for the t period 1980-86 on log probability paper. The higher dotted line is the l reference line based on the group TLD average of all TLD's for the period. l The lower line is the dose line based l on a ratemeter results of 7 micro R/hr l as an average over a large section of l the site. This graph shows the overall agreement of the TLD dose distribution with average dose and rate meter results. t i Figure 4 provides a long-term trending line from 1973 (the operational period) through 1985. This graph is provided only as a usual reference to see the range and variations over the system record period. Continued studies and trending of data [ on the TLD system will ensure the \\, accuracy and precision of the reported results. An example of attempts at data correlation between TLD results i and noble gas releases is described in a later section. Certain locations recurrently appear above the 95th percentile. Locations l 3 and 4 are due to storage of radwaste l in the vicinity. Locations 10, 52, l and 53 appear to be in high background areas. Their distance from the plant precludes the increase in dose being i due to operations. In addition, the l subsequent analysis indicates that TLD results do not correlate with plant releases. 24
/% O l b \\ / ~ TABLE I Paee 1 of 4 IHEgtgLLMINESCENT 00SIMETER RESULTS 1985 FIRST QUARTER SECONO 00ARTEt THIRO QUARTER FOURTH OuARTER LOCA-Total Exposure Total Ex posure Total Exposure Total Exposure TIC 3 DISTANCE Exposure Rate
- Exposure Rate
- Exposure Rate
- Exposure Rate
- J0.
ftHLIS) DIRECTION LOCATION DESCRIEIJON isram) fur /hr) faram) fur /hrt faram) frr/hr) foram1 fur /hr) 1 N Perimeter Fence 17.58 7.78 24.53 11.28 18.3 8.3 21.9 8.9 2 E Perimeter Fence 15.95 7.13 18.97 8.28 12.3 5.6 17.0 6.9 3 W Perimeter Fence 34.78 15.58 47.58 21.78 38.2 17.3 46.6 19.0 4 SW Periseter fence 20.13 8.90 22.28 10.20 25.5 11.6 24.4 10.0 5 SE Perimeter Fence 16.32 7.22 18.78 8.60 14.0 6.4 17.2 7.0 6 Visitors Center 15.75 7.04 15.98 7.31 11.8 5.3 13.8 5.9 7 Route 104 Entrance 14.10 6.37 Missing 13.6 6.2 11 4.6 8 6 NW 15.35 6.94 17.37 7.87 12.9 5.8 11.9 5.0 9 22 NE SMUD Headquarters 14.93 6.74 15.83 7.17 13.5 6.1 11.5 4.8 10 17 SW Lodi 18.78 8.77 21.18 9.39 16.8 7.6 16.3 6.7 11 0.25 S 15.63 7.06 17.95 8.04 11.9 5.4 12.9 5.4 12 Il ( Ione f5.14 7.46 16.55 7.34 13.0 5.9 11.2 4.6 13 10 W West Hilk Station 14.05 5.56 18.88 8.37 10.6 4.8 13.4 5.4 14 11 SW Galt 15.73 7.35 18.04 8.08 14.1 6.4 16.0 6.4 15 11 SW Camanche Reservoir 14.08 6.57 15.90 7.05 12.2 5.6 15.0 6.2 16 0.65 W Clay 13.20 5.97 15.30 6.85 13.0 5.9 12.8 5.4 17 9 SW Southwest Hilk Station 14.68 6.49 18.38 8.41 14.9 6.8 17.9 7.5 18 8 NE 13.93 6.29 14.6 6.61 10.3 4.6 15.8 6.3 i t l ~ Ln
N i A TABLE I Page 2 of 4 THERMDLUHINESCENT D0iltEIllLRiiULIS 1985 1 FIRST QUARTER SECONO QUARTER THIRD QUARTER FOURTM QUARTER LOCA-Total Exposure Total Exposure Total Exposure Total Exposure TION DISTANCE Exposure Rate
- Exposure Rate
- Exposure Rate
- Exposure Rate
- _hQ.
fdILE11_ DIRECTION LOCATIDILDESCRIPTIDM fareal fur /hr) forem) fur /hr) fareal fur /hr) forem) fur /hrl 19 1 SE 14.60 6.53 14.45 6.61 11.6 5.3 12.6 5.3 20 1.5 WSW 15.20 6.80 14.73 6.67 11.2 5.1 10.6 4.5 21 1.7 SW 15.00 6.71 15.76 7.13 14.8 6.7 11.6 4.9 22 1.8 S 14.93 6.74 15.40 7.05 12.6 5.7 13.5 5.4 23 1.8 SSW 14.55 6.50 16.43 7.52 19.2 8.7 11.2 4.7 24 1.8 SSE 13.30 6.01 14.45 6.62 10.5 4.8 14.0 5.7 14.5 6.6 12.2 5.1 25 3.8 SW 14.15 6.26 16.39 26 3.9 SSW 14.0 6.19 14.3 6.66 13.2 6.0 13.2 5.6 27 3.6 S 14.13 6.25 ,.30 6.62 10.8 4.9 10.6 4.5 l 28 3.7 SSE 15.03 6.65 16.28 7.53 12.2 5.5 Missing 29 4.2 S 15.43 6.82 14.23 6.59 10.2 4.6 11.0 4.6 30 7.4 WSW Herald Fire Station 15.15 6.85 19.08 8.46 13.3 6.0 18.3 7.6 31 3.7 W 16.37 7.65 Missing 14.8 6.7 Missing 32 4.8 WNW 15.03 7.02 17.63 7.81 12.9 5.8 12.0 5.0 33 3.8 WSW 14.83 6.92 18.2 8.07 12.8 5.8 Hissing 34 3.8 NW 16.45 7.43 18.05 8.17 12.4 5.6 11.9 4.9 35 1.9 W 16.10 7.28 18.43 8.26 14.1 8.7 14.4 6.2 36 1.6 WNW 16.60 7.50 16.28 7.29 13.5 6.1 11.6 5.0 N Ch
N m --.s \\ \\ TABLE I Page 3 of 4 THE8fGLIDtINESCENT DGSIMETER RESULTS 1985 FIRST QUARTER SECONO QUARTER THIRD QUARTER FOURTH QUARTER LOCA-Total. Exposure Total Exposure Total Exposure Total Exposure TION DISTANCE Exposure Rate
- Exposure Rate" Exposure Rate
- Exposure Rate"
_NO. (MILES) DIRECIION LOCATICN DESCRIPTION imrem) fur /hr) Imram) fur /hr) farent fur /hr) fareni fur /hrt 37 1.9 NW 15.38 6.95 20.85 9.34 15.2 6.9 15.7 6.4 38 1.6 NNW 15.50 7.00 18.82 8.43 13.5 6.1 17.4 7.2 39 1.5 NME 15.65 7.07 15.48 6.93 13.0 5.9 15.5 6.3 40 1.5 N 13.95 6.30 17.48 7.83 12.9 5.8 13.8 5.6 41 2.0 NE 19.83 8.96 21.65 9.70 18.5 8.4 25.6 10.3 42 4.4 SE 14.65 6.77 17.05 7.72 13.4 6.1 12.6 5.3 43 1.6 SE 14.58 6.59 15.33 7.02 10.0 4.5 9.4 4.0 44 1.4 E 13.38 5.98 14.60 6.69 9.6 4.4 12.1 5.1 45 1.4 ESE 14.18 6.34 15.13 6.93 10.8 4.9 11.2 4.7 46 1.3 ENE 16.68 7.71 18.70 8.29 16.3 7.4 15.9 6.7 47 3 NE 15.10 6.98 15.93 7.06 13.6 6.1 15.4 6.3 48 3.5 ENE 15.83 7.07 17.70 8.10 14.6 6.6 15.9 6.5 49 3.1 E 15.93 7.12 17.00 7.78 12.7 5.7 15.1 6.2 50 3.5 ESE 16.13 7.21 17.95 8.22 14.9 6.8 17.5 7.2 51 11 E Preston School of Industry 14.53 6.71 16.05 7.11 11.6 5.3 11.1 4.6 4 52 19 E Jackson Civic Center 18.65 8.62 23.95 10.62 27.1 12.3 21.2 8.8 53 11 SE Camanche Reservoir 19.73 9.21 20.35 9.02 19.3 8.7 17.3 7.1 { 54 10 S Clements 18.73 8.75 19.65 8.71 16.4 7.4 19.4 8.0 ~ N
v IABLE I Page 4 of 4 THERM)LLMINESCENT DOSIMETER RESULTS 1985 i FIRST QUARTER SECONO QUARTER THIRO QUARTER F00RTH QUARTER LCCA-Total Exposure Total Exposure Total Exposure Total Expcsure TION DISTANCE Exposure Rate" Exposure Rate
- Exposure Rate" Exposure Rate
- J0..
(MRS1 DIRECTION LOCATION DESCRIPTION faremi fur /hr) fareal fur /hrt farmal fur /hri faram) fur /hrl 55 8 WNW Dillard School Missing Missing Missing 14.4 5.8 $6 4.6 NNW 16.73 7.56 16.94 7.67 12.8 5.8 13.9 5.7 57 7.6 N 14.70 6.64 17.80 8.06 12.1 5.5 11.8 4.9 58 6.6 NME 16.53 7.47 17.95 8.13 Missing 12.8 5.3 59 11.3 NNW Sloughhouse Post Office 15.45 6.98 17.33 7.85 12.8 5.8 14.6 6.0 60 10.6 N Rancho Murieta 15.68 7.08 17.90 8.11 12.6 5.7 13.2 5.4 61 13 WNW Elk Grove Cemetery 15.90 7.03 16.58 7.51 5.4 12.5 5.3 62 11 SW Galt 15.23 7.11 17.05 7.56 5.9 Missing 63 1 E 13.28 6.13 16.98 7.69 5.3 16.6 7.0 l m 0)
1 ~ SAMPLE 16 TLD DATA 23 - i 22 - SAMPLE 16 21 - MAP LOCATION 11 20 - +3 a WEST OF SITE 19 - 18 - 3 +2a CLAY, 2.5 MILES j o 17 - u.. o 16 - +1a -- - - o- - - - - ------ M E AN ~I- -- - -- ~ ~ ~ ~ 15 - " ' - ~ - - o 1 o ,z _ -1a 13 -
- g. r _
MEAN = 15.3 n___.-____ " -2a MREM 18 " 17 i i 12 - ________________ l QTR. -3a 2 a = 3.4 11 -- 30 = 5.1 10 - 9-8- 7-6- 5-4- 3-2- 1-i i i i i i i i i i i i i i i i i i i i i i i i i i 1 2 3 4 1 2 3 4 1 23 4 1 2 3 4 1 2 34 1 23 4 81 82 83 84 85 YEAR (QUARTER). Figure 1. ~ 3 6
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- 6jl, t
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- ESCENTi GE 2S 5
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- -- - ' g _ = = -. = -.-._-_ y. ..t .._. 6 s 3 ' ~ ~ ~ w p.= = = m.:==+==:+
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- I 3.0 3.5 40 45 5.0 5.2 o0 5.5 70 PGCElT5 31
O O O L I MICRO R/ HOUR B ASED ON 50th PERCENTILE OF ALL DOSIMETERS FOR EACH QUARTER Eo Ea E 122 ORIGINAL 19 43 POST TMt ADDITIONS 1s i - - -. INITIAL CRITICALITY I 14 13 I I - HIG H DOSE l l 10 l 5 5 8 _l_ j 6 l l 5 --- - - LOWIDOSE I l l 4 I I 2 i i i 1973 1974 1975 1978 1977 1978 ' 1979 1980 ' 1981 1982 1983 1984 1985 M Figure 4. ---m
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I JQ d 3 to ' I [3 I i i g (r. ) 3 i i .it t i - t, M . Q. o .!,t 4 ya ii. i i 6. i ,i i l. i i.3-C (\\ <pu mjui: . it i i i. . pi i =i I: ei i i t ! i f, i i l.l't. b 'lhlll lt!ij.II, IIll' t l4, 1'l lli!' 'l!l'l l'i I i W !! 1.l t i i a f 4 1 I 1 I I 6 i ; i i i S I I I I 1 O O j i f 9 I 9 l l 4 l 1 t t l s l l 6 e I l l t e N } e .= 6 i i . ~ i, s ! i l l l_ t I I - l l ? i ! I i l l t. ! I i o g 8 O 1 I 1 1 i I t 3 l i l I ! I I e l l I i i ! I l! l' ' l I ~ l l' i l l C i l k l = s m i i, s a a ~ .,. ~. a ~ . ~ i o e, v= C 33 i-
t t l TLD LOG PROB ABILITY DISTRIBUTIONS i 1981(4) THRU 1983(2) i 2
- 19 81 Q 4
==-.m...-... i ... ___19_8 2 Q 1 l ..-. 2224 u..................,,,_,_,_. 198 2 Q 2 ......s.+**..........**+............gv.= = 1982 Q 3 ............. e..........'u... ~ ~. -- 198 2 Q 4 .....................2,i._... g .9 3 Q1 .. -e*'............................+-..... 1983 Q 2 . ~.... -.................. ... ~ = - - Figure 6. LAJ*
~ CORRELATION OF ENVIRONMENTAL TLD'S (n) WITH NOBLE GAS RELEASES Q.) As a hypothests, suppose that the noble gas releases from Rancho Seco are measurable in the environment on a long-term basis by means of TL dostmeters. If this hypothesis were true, then TLD results in any given sector should correlate well with the quantity of noble gases released into that sector during the same time period. Lack of correlation would mean that the releases have no effect on the radiological environment or that the TLD is insufficiently sensitive. The TLD's chosen to test the hypothesis are located, one per sector, in the one to two mile annulus surrounding Rancho Seco. There are two reasons for choosing these locations. One, these are the only locations where the TLD's are approximately equidistant from the reactor in all sectors. Two, the TLD's are sufficiently distant as to be unlikely to be affected by direct radiation. Thus, they are close enough to possibly measure gaseous effluent effects. The time period for the correlations includes the fourth quarter of 1981 through the fourth quarter of 1985 and the first quarter of 1984 through the last quarter of 1985. This period postdates any observable effects from the most recent atmospheric nuclear weapons testing. Also, the ring of TLD's was not installed until 1981. ( The four quarters of the years were separated, then combined so that one y/ correlation represents all first quarter readings, another correlation represents all second quarter observations, and so forth. This was done to I reflect the quarterly changes in prevailing winds. The observed fraction of winds blowing into each sector for the entire quarter was obtained by summing values for all stability classes. The quantity of effluent released in the quarter was multiplied by these functions to obtain the quantity released into each sector. 1983 data were not used because default meteorology was used. l Both batch and continuous meteorological data were used. 1 Four correlation cases resulted:
- First quarters of 1982, 1984 and 1985.
- Second quarters of 1982, 1984 and 1985.
I
- Third quarters of 1982, 1984 and 1985.
l
- Fourth quarters of 1981, 1982, 1984 and 1985.
l [ The correlation coefficient was obtained from the standard deviations of the populations with respect to the linear regression line. The equation for correlation coefficient, r, is as follows: nlXgYj - IX IYi t r-nlX[-(IX)E nlYf-(lYj)2 t The resulting correlation coefficients were obtained: [m\\ (,/ First Quarters -0.556 Second Quarters 0.376 Third Quarters 0.247 Fourth Quarters -0.352 35
The correlation process was repeated for the four quarters of 1985. The results as presented in the table below indicate even less correlation. 1985 Correlation Quarter TLD vs. Noble Gas Release 1 -0.065 2 -0.001 3 -0.31 4 -0.038 The third quarter values are suspect since the releases were less than 5 millicuries into any sector. No measurable effect would have been expected from these releases. These results indicate that the hypothesis is not sound. Since the suitability for the TLD's in use for this type of measurement is accepted by regulatory agencies, the conclusion is that the noble gas releases have no measurable impact on the environment beyond a radius of about one mile. .O 1 I 36 i l
O O O NOBLE GASES RELEASED INTO SECTORS AFTER MOST RECENT HEAPONS TESTING (4/81-12/85)* (CURIES) 1981 1982 1984 1985 4 1 2 3 3 1 2 3 4 1 2 3 4 N 5.21 12.5 1.21 18.1 72.9 86.1 58.9 70.5 53.0 354.7 1.0 0.0016 96.3 NNE 2.46 11.2 1.40 18.81 43.1 57.3 67.6 80.4 28.7 236.3 1.31 0.0022 39.6 NE 2.01 12.3 2.06 23.21 28 53.9 71.0 84.1 21.4 185.3 1.36 0.0024 16.7 ENE 2.52 7.55 2.98 32.1 30.4 49.2 98.1 113.2 23.4 198.6 2.49 0.0035 21.4 E 3.49 14.6 3.56 73.4 56.3 39.2 131.2 366 20.9 116.3 277 0.0076 34.8 ESE 2.62 22.2 1.92 34.2 32.8 37.2 36.0 146 22.8 150.6 0.85 0.0031 34.0 SE 2.42 17.4 1.24 16.3 48.5 74.2 68.7 74.7 32.2 276.3 1.08 0.0008 64.7 SSE 2.14 10.3 0.90 17.4 72.7 106.4 71.8 83.7 55.7 321.6 1.13 0.0006 84.9 S 1.91 7.3 0.42 9.08 63.7 74.8 18.2 46.1 27.2 197.1 0.46 0.0008 68.3 SSH 1.33 14.1 0.32 7.29 30.0 43.2 15.4 24.8 13.7 155.2 0.33 0.0006 40.9 SH 1.87 17.2 0.21 8.60 39.9 42.0 17.9 42.2 22.0 152.6 0.35 0.0006 49.3 HSH 1.54 ~13.9 0.28 6.59 47.8 61,4 13.2 28.9 30.1 220.2 0.41 0.0003 32.7 H 2.08 23.7 0.45 2.70 44.1 73.8 9.26 12.2 20.5 156.3 0.17 0.0003 29.7 HNH 3.74 40.0 0.57 5.09 47.8 90.4 16.5 21.5 43.2 254.4 0.30 0.0003 39.2 NH 5.55 42.0 1.03 8.59 83.8 125.4 39.3 42.3 62.6 410.9 0.45 0.0003 34.2 NNH 5.78 22.8 1.17 16.6 127.0 145.6 67.0 60.0 95.6 453.6 1.26 0.0016 138.4
- 1983 data not used due to default meteorology.
g; I
'\\ t v V l TLD MEASUREMENTS SINCE L AST ATMDSPNERIC WEAPools TESTS l (MILLIREM) f TLD 1981 1982 1983 1984 1985 l n 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 l N 40 8.08 8.53 8.54 8.46 NS* 7.78 9.06 7.72 7.00 8.42 8.87 8.85 9.20 6.30 7.83 5.83 5.59 UNE 39 8.33 9.41 8.99 NS NS 7.61 9.76 8.63 7.41 8.12 9.13 9.75 8.75 7.07 6.93 5.86 6.28 l NE 41 10.6 10.94 10.79 11.49 NS 9.43 11.48 10.71 9.26 9.32 12.61 13.27 11.98~ S.% 9.78 8.38 10.34 ENE 46 9.67 9.81 3.09 10.46 6.88 8.84 7.72 8.24 7.70 7.43 8.24 9.56 8.75 7.71 8.29 7.36 6.68 E 44 8.16 8.26 6.49 7.72 4.85 6.02 7.95 6.58 6.65 6.72 NS 8.27 7.26 5.98 6.69 4.37 5.10 ESE 45 7.92 8.62 8.41 6.72 7.03 5.96 7.50 7.62 6.52 6.66 7.49 8.76 8.05 6.34 6.93 4.91 4.73 SE 19 7.84 9.5'2 7.72 7.25 6.73 8.44 NS 7.66-6.60 7.10 8.55 8.88 8.13 6.53 6.61 5.26 5.29 SSE 24 7.84 8.27 8.23 8.82 NS 7.73 7.64 6.10 6.13 8.98 7.54 7.68 7.68 6.01 6.62 4.76 6.0 5 22 8.19 8.46 8.99 9.02 MS 6.85 7.99 7.39 6.33 7.95 8.74 9.19 7.83 6.74 7.05 5.68 5.44 SSW 23 8.15 8.43 8.18 8.82 4.76 7.88 7.58 7.75 6.60 7.65 8.41 8.48 9.08 6.50 7.52 8.70 4.72 SW 21 7.45 8.06 6.38 7.99 6.32 7.40 7.87 6.91 6.01 7.03 7.42 7.89 8.43 6.71 7.13 6.70 4.87 WSW 20 7.66 8.04 6.93 8.76 5.92 NS 7.44 6.75 5.19 7.47 7.36 7.50 7.86 6.80 6.67 5.07 4.47 W 35 8.23 9.31 7.68 10.42 8.24 7.37 9.10 8.71 7.04 8.31 9.03 9.29 10.66 7.28 8.26 8.66 6.18 WNW 36 8.76 9.38 8.56 9.99 5.51 ,8.17 8.54 8.44 7.42 8.32 9.09 9.19 8.30 7.50 7.29 6.12 4.97 NW 37 NS 9.51 NS 9.37 7.18 7.69 9.14 8.85 7.95 9.77 NS 9.76 9.05 6.95 9.34 6.90 6.40 NNW 38 8.14 8.58 8.45 10.59 7.29 6.79 8.12 7.40 7.22 8.77 9.77 8.61 8.42 7.00 8.43 6.10 7.17
- No sample
] r.a 03
p_ a A> _m. -a 2 -._a m. a a b I i i l ALGAE i 1 l [ 1 1 t l [ 39 l t
DATA INTERPRETATIONS AND CONCLUSIONS ALGAE [] V DATA
SUMMARY
~ AQAE Algae samples are obtained because they concentrate activities such as Type of Algae Sr-90, Cs-137, Cs-134. Although they are not part of the direct food chain, Grab samples of algae are a mixture of they are sensitive indicators of algaes including but not limited to stream effluent activities in the the following: environment by virtue of their ability to concentrate radionuclides. This is Diatoma, Gort'oenema, Nitzschia, also true of water hyacinths to an Spirogyra, Spedra, Fragelaria, even greater degree as indicated in Navicula, Microspora, Chlorococeum, the Lawrence Livermore National Urethrix, Zygnema, and Tabillarla Laboratory (LLNL) special studies Varias. appendixed to this report. Direct correlations between radionuclides Sample Locations released and uptakes in these indicator plants has not been possible Algae samples are taken from two either in time or distance. locations chosen to reflect effluent releases in the envircnment. The first is at the effluent out-fall at the site boundary west of the plant, the second from the Hadselville Creek p near the Folsom South Canal. \\V/ Sample Frequency Samples are scheduled on a quarterly basis but are obtained on an as available basis. Gross Beta Gross beta less K-40 values for 1985 ranged from 0 to 25 pC1/g (dry). Method: Dry ash sample at Gross beta values were similar in the 100*C for 24 hours. fourth quarter of 1984 (20-30 pC1/g) and were decreasing from the rise seen Counting System: Beckman Hide Beta II over the first three quarters of 1984 Low background gas due to steam generator leaks. Values flow proportional during the first three months of 1984 counter reached as h'gh as 125 pCl/g. Values during 1982 and 1983 were similar to LLD: 0.02 pCl/g (dry) 1985 ranging from 0 - 30 pC1/g. (Based on 100g dry sample). O 40
DATA INTERPRETATIONS AND CONCLUSIONS O ALGAE "V DATA
SUMMARY
K-40 K-40 values ranged from 1 to 8 pC1/g during 1985. 1984 and 1983 had Method: Potassium similar values ranging from 0 to 60 concentration, pC1/g. atomic i absorption, (K-40 fraction taken to be 1.7 dpm K-40/mg K). LLD: 0.001 pC1/g (dry) Sr-90 Sr-90 was non-detectable during 1985. This has been true during all periods Method: Dry Ash at 110*C of operation except after nuclear for 24 hrs, weapons testing (i.e., after 1981.) dissolved in dilute HC1, Y-90 extraction after j
- ingrowth, precipitate as oxalate.
Counting System: Beckman Low Beta II Internal Flow Proportional Counter Calibration Source: Backcalculated Sr-90 Efficiency - 601.. l LLD: 0.03 pCl/g (dry) (Based on 100g dry sample). Gamma Spectroscopy Gamma spectroscopy of algae samples resulted in identifying the following i Method: Het sample, gamma emitters: Cs-137, Cs-134, f Marinelli Beaker Co-60, Mn-54, Co-58, Ag-110m, Cr-51, and Be-7. Cs-137 levels ranged from Counting Instrument: Intrinsic 10.6 pC1/g (dry) to 136 pC1/g (dry). Germanium. Gamma Spectroscopy of algae samples Counting System: Northern during 1984 in the first three Scientific TN quarter 2 showed isotopes similar to 4500 Multi-above. The Cs-137 levels in 1984 channel analyzer. ranged from 0 to 281 pC1/g. The fourth quarter of 1984 showed ,( decreases with ranges from 27 to 72 pC1/g of Cs-137. 1983 showed ranges of Cs-137 from 0 to 50 pC1/g. 41
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e, eger: ;.2 1000n 5 M 15 20 e c E 40 73 50 as 90 95 ss'., ; .=<=ri w i. =_ -ir-.. =-.i-- _- =i =-- i- := p: - 2==i.=g y -= =- = y __ _. = = -.- 3 9 .==--=--,.r ( g *
- .-j =- = =-.--== m _ _ : = = = -- = - + p=_=..===_i:;=t =_u==
= ==== = _ =.+ g : - =-- :-- ; 1 "~ g y ) -. =. _. 5 _. ......: =.55._g:-3 3. =.... = 5. _.5 - - - _.5 g -- --- - .:_===- - " * " _ %J r__----=-----._:===~.2==.-:-- 5. 197.2(2T 1*7*~4*v '1 5 _= =1 -.Z-_ _ '.= E-Ei.-i-ia;-i=h_n _... --RD =_ ;' W'- Q1'_T '- =f=_;aiae: Z ~ izi=2 --- f_;=,WZ+g g d - -- .--'^T_--..~'-~~Z ____~ - _.:. _ ~ _ Z Z_^Z Z_ -L-' -'Z_ r ~ 1-~ _...Z.. .~~.~~T~ '~_^^____Z'h[ i- _:~ ~'~2 4 y - =. / 3 3.._ _ s'--' .. 2 2.... 4_ _s ', e P4 I t t w' i i COo F i i i i i i co e .100 y . p., et==_ _ c=----t-.==, __ y 9 _ = _ = = z=-- _ -- :==--t=
- = ==== = ===-tac - - -
- - = - - = = = - a+y: 22- :22:: _ _2 :: : t_::T. ::_ :__:.:.__ _ _. :.- -- S
- T.
- = -~ -------:.
d -- __.._____.___-._.r_.__-_ _ _ _ _ _ _ _ _._ _,7 _1 7. e pCi/g s. (DRY) 5 5. _,._.Z :-iz_s = = i+= x ao== . s =t= =-f =,== : =_= u - sM = _.:__=55g_ _. _..,r _- -_-__ _ __.-u_.__. dh,py __ e=-=-----==i-+=_-..= .._.__._____.=_-_=.,-__--y.. _... _ _.. _ .4 ._z 4, nP.f_. ____ __ __ __m 7-- o3 J.3 3,,-___ f.__. s q ) gj ..~q j 2... 7 .2 i r-r i g- - i i ti r i I / __ $3 e== =-e.=. u.__s te-m= a =*ar+=-; =_' =.w =.:.u_im ae-x = _ : ,.1 to. l q 3 t==n=- Q g, t==-- = =C. _.~ 4==E .1 l' ! "-~~ i=_=Edi:-ii -~ I" - ~--l- - ~ ~ ~ ~~~ 1_- =. ~ _ -._ i=~=f-. ~. __1 # "X. _. 3 .. =, - - - _ ,f,, ___.._.f_+- ..~ __ 7 7,
- ~
-6 x; 6 -.a, H s_y 5 6 v==1== = ---.,=s = =i. - 8 m -.;wii=M-..%:.x-ut = _ ww= cmam.== - *- m 4%+:n [: 55~ ~~* M f '[ -~~- E NI !WS-- -lI --' _rY-- 5EE-F".2id=- -5fiI5EE5_N~5'~ rN525--'-'-Yrij,4 E A j 4 r UE==^=2 =EE- -2.~.=n==i=~t- ?%=d=r-E' i.L =kMGriM=iM' E +=--- ~ -~-:=ET=i = = 4 k ( E 3.----==-~~~--~f--'.=___..___..-..-..:--=-c.-.___.--~*-- ~~ ~^; 3
- == -
_ - - - = = = = - = = = =
--~-------.i--" l G ~ ~ ~ ' ' - _._T._4 _ _ = =.x=_:== _ :== = r_- __..2 _t e_ .J i LEIGURE:2, . _ __~ _____ C U M U LATIV E?. P ER C E N T_ _v_.. ~ .n, f, l. 1 x / i 30 3.5 40 45 5.0 55 i0 6.5 70 PRCST5 43 l l \\ l
A A m. a g a e J i l i ANIMAL VEGETATION l I l I 44
DATA INTERPRETATIONS AND CONCLUSIONS ANIMAL VEGETATION \\ ") DATA
SUMMARY
Sample Number: 15 Sample Frequency: Quarterly Gross Beta The samples activities for gross beta less K-40 activities ranged from 0 to Samples are dried at Il0*C for 24 6.40 pC1/g (dry). This compares with hours, ashed, and dissolved in dilute a range of 0 to 2.0 pC1/g in 1984. acid. Counting Instrument: Internal. Gas Flow Proportional Counter Model: Beckman Wide Beta II Gamma h ectrometry Gamma activities ranged from.06 to 5.6 pCl/g (dry) in the fourth quarter 3 ample Type: Marinelli Beaker 1985. Gamma analyses were not made in prior quarters. The isotopes Detector: Intrinsic Germanium indicated and their maximum values \\ were as follows: Analyzer: TN 4500, Northern Scientific Cs-137 5.60 pC1/g (dry) Cs-134 1.32 Co-60 1.79 Mn-54 .06 These analyses were performed only on samples taken near Clay Creek. These samples in the fourth quarter 1985 included roots and soll. The activity may have been associated with the roots and soll. Strontium-90 No Strontium activities were found except one sample at a value of 0.11 Samples are dried at IIO*C for 24 pC1/g (dry). hours, ashed, and dissolved in HC1. The Yttrium is backextracted after ingrowth, and precipitated as an oxalate. Counting Instrument: Internal Gas Flow Proportional Counter (V Model: Beckman Wide Beta II Efficiency: 607. (Sr-Y) 45
1 + s E 1 I I l E I i l i EDIBLE' AQUATIC FAUNA O b .I l o l i k 1 8 g I t t I I O + t 46 t m +
DATA INTERPRETATIONS AND CONCLUSIONS EDIBLE AQUATIC FAUNA DATA
SUMMARY
FISH - ROUTINE PROGRAM FISH - ROUTINE PROGRAM In the routine program, fish samples The routine collection of fish from are taken at three locations: the Clay Creek effluent stream was initiated in 1985. In the routine
- 1. Site reservoir program, gross beta less K-40
- 2. Clay Creek - site boundary concentrations ranged from
- 3. Hadselville Creek near Folsom South non-detectable to 2.49 pC1/gm. Since
- Canal, no samples reached the gamma spectroscopy trigger of 10 pC1/gm, no Samples were collected by net at isotopic identification is available.
quarterly intervals. Samples are No Sr-90 was detected in any samples analyzed routinely for gross beta, in the effluent streams. potassium-40 and strontium-90. Gamma spectroscopy is performed only when Sr-90 was seen in one site reservoir gross beta exceeds 10 pC1/gm. sample at 0.5 pC1/gm. Gross beta less K-40 was also seen at concentrations Gross Beta up to 0.9 pC1/gm. Sample Preparation: Dried at 110*C These concentrations are consistent for 24 hours, with the previous few years. ashed, dissolved in dilute acid. Pre-operational data are too heavily O influenced by atmospheric weapons i Counting Instrument Type: Internal Gas testing to allow meaningful comparison. Flow, Proportional Counter. The routine program doesn't sample frog legs or crayfish. Counting Instrument Model: Beckman Wide Beta II. l LLD: 0.02 pC1/gm. K-40 is subtracted. Potassium-40 Sample Preparation: Dried at 110*C for 24 hours, ashed, dissolved in dilute HNO - 3 Analyzed by atomic absorption, K-40 taken as 1.7 dpm K-40 per mg K. 1 LLD: 0.001 pC1/gm. O I 47 ~
DATA INTERPRETATIONS AND CONCLUSIONS () EDIBLE AQUATIC FAUNA V DATA
SUMMARY
Strontium-90 Sample Preparation: Dried at 110*C for 24 hours, ashed, dissolved in dilute hcl, Y90 extracted, and precipitated. Counting Instrument Type: Internal Gas Flow Proportional Counter. I Counting Instrument Model: Beckman Wide Beta II. LLD: 0.03 pC1/gm. FISH - SPECIAL STUDIES FISH - SPECIAL STUDIES The special studies of the 11guld Details of the special studies are / effluent pathways continued through presented in Appendix C, UCID-20641. (, 1985. Locations for fish samples were The nucIldes of primary dose at 0.5, 3.0, 4.6, 6.0, 7.5, 10.2, significance were determined to be 12.6, 17.2 and 19.5 km downstream from Cs-137 and Cs-134. Cs-137 the plant effluent outfall. concentrations ranged from less than detectable to 13.6 pCl/gm of edible Samples were collected by rod and reel flesh as functions of time and during each calendar quarter. dcwnstream distance. Cs-134 Radionuclides were quantitated by concentrations averaged about 35% of gamma spectrometry. Edible flesh was the Cs-137. separated from the gastrointestinal tract and contents. Concentrations of nuclides were reduced as compared with 1984. This Samples were dried at 90*C to constant is consistent with the reductions in dry weight, homogenized, and placed in radioactivity releases starting in containers for analysis. October 1984. Detection limits: (pC1/ sample) Cs-137 1 Cs-134 1 48 i _~_
DATA INTERPRETATIONS AND CONCLUSIONS O EDIBLE AQUATIC FAUNA V DATA
SUMMARY
FROG LEGS - ROUTINE PROGRAM Frog legs are not collected in the routine program. FROG LEGS - SPECIAL STUDIES FROG LEGS - SPECIAL STUDIES Frogs are collected by spearing at Details of the special studies are downstream distances of 0.5, 1.0, 4.6, presented in Appendix C, UCID-20641. 7.5 and 12.6 km. Flesh is dissected from the legs to represent the edible The collection and analysis of frog portions. Samples were dried at 90*C, legs was initiated as a result of homogentzed and placed in containers identifying frog legs as a major dose for analysis by gamma spectrometry. pathway during the 1984 land use survey. Detection limits (pC1/ sample): Thirty-two samples were collected Cs-137 1 outside the site boundary. Cs-134 and Cs-134 1 Cs-137 were the only dose-significant nuclides identified. Cs-137 Instrumentation: concentrations ranged from less than (' O detectable to 5.2 pC1/gm. Cs-134 ) Ge (Ll) spectrometry systems concentrations averaged about 35% of Cs-137. CRAYFISH - ROUTINE PROGRAM Crayfish are not collected in the routine program. CRAYFISH - SPECIAL STUDIES CRAYFISH - SPECIAL STUDIES Crayfish were collected by trapping at Details of the special studies are distances of 0.5, 4.6, 7.5, and 12.6 presented in Appendix C, UCID-20641. km. downstream. Crayfish were added to the sampling The edible portions were separated, schedule after the 1984 land use dried at 90*C, hemogentzed, combined survey identified a significant dose and packaged in standard containers pathway. Nine samples were analyzed for analysis, during 1985. Results ranged from less than detectable to 1.78 pci/gm of Analysis Instrumentation: Ge (L1) Cs-137. Cs-134 averaged about 37% of spectrometry Cs-137. No other nuclides of significance to dose were found. Detection Limits (pC1/ sample): Cs-134 1 Cs-137 1 ,v 49
4 .a a __w - E a ..c i I e l l l MILK I i 50 -ew,- ,,n,___,_,,,.._
DATA INTERPRETATIONS AND CONCLUSIONS MILK DATA
SUMMARY
MILK ANALYSIS Weekly samples are taken from four dairles and analyzed for gross beta Sample Volume: 2 liters less K-40 on a weekly basis. If the Number of Sample 5: 4 activity exceeds 3 pC1/1, a gamma scan Collection Period: Weekly is performed. No radiolodine was Dairy Locations: Madeiros, Angelo, found in any milk samples during Warmerdam, 1985. One sample in the second Marciel. quarter of 1985 showed a Sr-90 level of 0.75 pCl/1. All other samples IODINE ANALYSIS Indicated non-detectable. These are the only two activities looked for in Analysis Period: Weekly (within 48 milk samples on a routine basis. The hrs. of Sr-90 sample analysis is done monthly collection) on a composite of the weekly samples. Samples during 1984 showed a high of Method: Anton Exchange, 2.2 pC1/1 for Sr-90, and a low of Count AgI beta non-detectable. Historical data 1974-1983 indicate a quarterly average Carrier: Standardized maximum of 6 pC1/11ter. Data taken lodine during pre-operational monitoring were i reported as pC1/gm Ca, thus are not Resin: Amberlite directly comparable to operational (IRA-400) Anton data. Exchange Time: I hr It is interesting to note that a survey of the number of cows on each Counting System: Beckman Low Beta farm in the vicinity of Rancho Seco II Thin window are log normally distributed. See proportional Figure 1. Such data is useful to determine the contribution of local Efficiency: 417. Beta herds to the overall milk supply and to project likely future herd sizes. LLD: 0.5 pC1/1 (Beta) Notification Level: 2.4 pC1/1 (Beta less K-40) STRONTIUM-90 Analysis Period: Monthly Method: Cation exchange Count Yttrium 0xalate for Y-90 Carrier: Standardized Yttrium Q Restn: Dowex (50H-V8) Cation 51
DATA INTERPRETATIONS AND CONCLUSIONS MILK OATA
SUMMARY
j. Exchange Time: 30 min l Counting System: Beckman Low Beta l II Thin window i proportiona1 I Efficiency: 60% Beta (Sr-Y) 1 i i l l f i i i I l.. I 1 1 1 i I i 1 l } 52 4 i
,o >- a 7 a s 4 3 i .H 1 6 4 3 2 I ._ 9 i 9 o \\ 9 o_ 9 's. d, g 1 / n i i 9 n l;
- n 9
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- nLl, p
4 08 l 0 a 9 6 l 4 s. g -/ I l, q / j 0 0 8 A' 2 A L / U 07 i q U 0 06 4 /, l r 6 0 ) B/ W E 0 g/, a f( C 4 H / 0 u E 3 / l g' I M P e - 'J 0 P
- I IJ
- A g/
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- r,O 0
i J ?_ f,C ? 1 7 _. iE p B,S / 'I l 1 5 1 . EO p_ 5 _ T i Sl I E _~ l D.C V 2 ( i b j WiA e, .1 sR ? l;Q / C g .5 _. 0 / K j _2 8 L I _H M / 8 ? tl i ,l til i I li
- /i
,l } i10 / 5 _0 / _0 L. .1 ) 9 . / _0 )? 0 0 ( S o H 7 .) 4 3 2 I t 0 n >- n 7 o s 4 3 gW i 1 OC m" ,i l
a -a m. s. .m..m. _m .+ e i 1 1 MUD AND SILT i I I i i 1 54 i ---,--,..,--_..-.,,_--,.-..,,..,,,,,_,,,,,n_._-,,,
DATA INTERPRETATIONS AND CONCLUSIONS / MUD AND SILT DATA
SUMMARY
-MUD AND SILT Samples are routinely taken at the Site Reservoir and at the Site Sample Preparation: Samples are Boundary mixed effluent stream. dried and During the third quarter of 1985, an leached with additional routine sample was taken in nitric acid, Hadselville Creek near Folsom South then ashed and Canal. Thirteen special samples were placed in a 2" taken in 1985 to obtain more data on stainless steel effluent releases via the liquid planchet for pathway. counting. Gross Beta values at the Site Counting Instrument: Thin Window, Gas Reservoir ranged from 0.09 to 2.08 Flow pC1/ gram (dry). Only Cs-137 activity Proportional was observed in the range 0.03 to 0.08 Counter. pC1/g (dry). Instrument Model: Beckman Wide Gross Beta at the mixed effluent site Beta II or a boundary ranged from 1.49 to 11.92 Tennelec LB 5100 pCi/g (dry). Gamma activities low background observed included Cs-137, Cs-134, l simultaneous Co-58, Co-60, and Mn-54. Cs-137 counter. activities (the primary gamma emitter) ranged from 5 to 11 pC1/g (dry). Efficiency: 60% Beta, Sr - Special samples indicated the same Y-90 (Beckman) gamma activities as above with Cs-137 51% Beta, Sr - ranges of 0.165 to 15.6 pC1/g (dry). Y-90 (Tennelec) Levels during 1985 were lower than samples from 1983 and 1984. The low levels combined with scanty preoperational data make a comparison i unmeaningful. This is especially true since the preoperational data had high Sr-90 level due to nuclear weapons testing. I-131, Nb-95, Cr-51, Ag-110m, Zn-65, Rh-106, Be-7, Zr-95 levels which were observed in the 1984 data were absent during 1985. O 55
2.Ae _a m.4_ A.--_. a .m___ _am_a-ale 2m. A ..A,__ --.m a.__ s-am- _*a= a-a.__sa.. -a_ 2 -y-k f i 'I k l 4 i l l I l l t e I t l 1 1 I i RABBITS I J l 1 a I l 4 I 5 Y 2 9 ) i J ? i 4 3 ) 56 l l i
DATA INTERPRETATIONS AND CONCLUSIONS O) RABBITS i V DATA
SUMMARY
RAB8ITS During 1985, the only positive sample activities were rabbit flesh in Sample Preparation: Quarters 2 and 3. These samples showed gross beta less K-40 activities Samples are prepared to analyze: of 2.7 and 2.9 pC1/g in Quarter 2, and 0.18 pC1/g in Quarter 3. These values Femur - Sr-90, Stable Calcium were similar in magnitude to data Thyroid - I-131 accumulated in 1984 which showed flesh Flesu - Gross Beta less K-40 activities of 2.1 and 6.7 pC1/g gross beta less K-40 in Quarter 4. Flesh: Samples are dried at 110*C for 24 hrs., No lodine activity was found in 1985 ashed, and dissolved thyroid samples. This was true of in dilute acid, 1984 also. Pre-operational samples followed by counting. showed no thyroid lodine. No Sr-90 activities were found in the 1985 Gross Beta: K-40 femur samples. Tnts contrasts to activities found in 1984 1st and 2nd i Counting System: Beckman Wide Beta II Quarter of 1.77 and 0.44, 1.28 pCl/g, respectively. Counter Type: Internal Flow Proportional Counter. The samples for 1985 compare with [] pre-operational samples except for the (-) K-40: Potassium content pre-operational samples containing determined by atomic higher Sr-90 activities due to fallout i l absorption and the from nuclear weapons testing. ratto of 1.7 dpm l K-40/mg K. Equipment Type: Perkin Elmer Atomic Absorption Models 306 and 560. 1 l m 57
_.,a a l WATER I l l l l l l 1 0 58
DATA INTERPRETATIONS AND CONCLUSIONS WATER DATA
SUMMARY
Hater samples are collected both on site and in areas north, east, south, and west of the site. Sample types include surface and runoff, well, and drinking water. All samples except effluent stream are monthly, with the effluent stream fortnightly. Runoff water is analyzed for gamma and l gross beta both dissolved and suspended, plus Tritium and Iodine-131. Surface water is analyzed for gross beta dissolved and suspended, plus Tritium and Iodine-131. Well and drinking water is analyzed for dissolved gross beta, Tritium, and Iodine-131. A matrix follows this section for convenience. Run-Off Water V One liter samples are counted in a Marinelli Beaker. The sample is then put through a millipore filter. The filtrate is then counted again to determine dissolved gamma. The suspended gamma activity is determined by subtraction of the dissolved from the total. The millipore filter is then counted for gross beta. The gamma filtrate is evaporated and counted for dissolved gross beta. Triticin is determined by liquid scintillation counting of 3 ml of water. Iodine is determined by carbon tetrachloride extract in using i standardized lodine carrier. The iodine is then back extracted using hydrazine. A precipitate is then formed of AgI and counted. v 59
DATA INTERPRETATIONS AND CONCLUSIONS ['T WATER DATA
SUMMARY
Gamma Spectroscopy Gamma activities were not detected at the plant LLD. Additional studies by Sample Type: 1 liter Lawrence Livermore National Laboratory Marinelli Beaker. are summarized in their attached report UCID-20641. This report uses Sample Period: Monthly (except environmental LLDs lower than the site Fortnightly for or CEP. mixed effluent) Counting Instrument: Intrinsic Germanium Counting System: Northern Scientific TN 4500 LLO: Cs-137 - 11 pC1/1 Reportable Levels: 50 pC1/1. Radiolodine 131 Runoff water during 1985 showed no levels cf iodine. This compares with Sample Type: 1 liter water trace I-131 during 1984 which peaked \\- processed to at 111 pCl/1. create AgI precipitate. Sample Period: See above. Counting Instrument: Thin window Gas Flow Proportional Counter. Model: Beckman Low Beta II Counting Time: 100 minutes LLD: 0.5 pC1/1 Reportable Level: 2.0 pCl/1. Gross Beta Suspended gross beta and dissolved gross beta ranged from 0-4.5 pC1/1. Sample Type: 1 liter sample This compares with 1984 range of 0-22 Os filtered on pC1/1. stainless steel t planchette 60 i i
DATA INTERPRETATIONS AND CONCLUSIONS HATER DATA
SUMMARY
I Sample Period: See above Counting Instrument: Thin Window Flow Proportional Counter or Tennelec LBN 5100 l Model: Beckman Wide Beta II LLD: 0.5 pCl/l Reportable Level: 40 pC1/1 Counting Time: 100 minutes Beckman efficiency: 60% (Sr-Y) Tennelec efficiency: 51% (Sr-Y) t 4 j Tritium \\ Sample Volume: 3 ml Counting Instrument: Liquid Scintillation l Model: Beckman LS100 Cocktail: Aquasol NEF 934 (New England Nuclear) Efficiency: 30% Calibration: NBS Set of 6 standards. Surface Water Surface water is counted for gross Surface water samples during 1985 beta, dissolved and suspended, H-3, ranged from 0 to 2.8 pC1/1 gross ( and I-131 as specified above in runoff beta. This compares well with 1984 water. data of 0 to 2.3 pC1/1. No H-3 or I-131 were detected. This is a reduction from the small amounts seen in 1984 of 1.9 pC1/1 1-131 and 54.3 pC1/1 H-3. 61 t
DATA INTERPRETATIONS AND CONCLUSIONS DATA
SUMMARY
Comparisons of water samples during 1985 with pre-operational levels indicate relatively similar values during normal environmental sampling. Occasionally, samples were inadvertently taken during operational releases. Under these conditions, positive values were obtained, but not used for routine environmental considerations. Well Water Well water is counted for dissolved Well water samples during 1985 ranged gross beta, H-3, and I-131 as from 0 to 3.5 pC1/1 as compared to specified in runoff water. 1984 levels of 0.5 to 3.7 pC1/1 gross beta. No I-131 or H-3 were detected. Drinking Water Drinking water is counted for Drinking water samples ranged from 0 p dissolved gross beta, H-3, and I-13'l to 3.9 pcl/l as compared to the 1984 ( as specified in runoff water. gross beta levels of 0-4.1. Again, no I-131 or H-3 were detected. The Lawrence Livermore National Laboratory Study was performed to provide a detailed analysis of the liquid pathway for radionuclide movement from Rancho Seco. The study points out the following:
- No activities have been found in ground water (well water).
. Heavy rains move cesium concentrations further downstream than under normal conditions. . All downstream concentrations in the Clay, Laguna, and Hadselville Creeks were above global fallout levels as represented by measurements in the Rancho Seco Reservoir and the Mokelumne river, which ranged from 0.112 to 0.008 pCl/1 Cs-137. J 62
DATA INTERPRETATIONS AND CONCLUSIONS WATER DATA
SUMMARY
. Although the study attempted to explain sources and movements of stream activities, the models used were subject to the vagarles of an "open" ecological system and contri-butions of Cs-137 and Cs-134 from the I plant (even after 1984) which often confused measurements. . The use of plant indicators such as water hyacinth couldn't be i quantitated due to the lack of i uptake and retention data as a function of stream concentrations. The Lawrence Livermore National Laboratory will continue this year to provide more data concerning the i liquid pathway. i d i 63
I \\ ] WATER SAMPLE MATRIX \\ j Total Dissolved Suspended Dissolved Suspended Tritium Iodine 131 j ANALYSIS TYPE + Y Y Y Gross Beta Gross Beta pC)/1 pC1/1 pC1/1 pC1/1 pC1/1 pC1/1 pCl/1 l SAMPLE VOLUME -* 1 liter i liter 1 liter i liter 1 liter 3ml 1 liter i LLD 11.0 0.5 0.5 250 0.5 i (Cs-137) { l I SAMPLE TYPE (Frequency) l Runoff Water (H) = = = Surface Water j (M. F)* Hell Water (Q) F Drinking Hater (H) i j
- Effluent samples taken fortnightly.
t i i + i l S i I t
a .a, a .m2. ..s.. -.w.. ._a , _..-.. a m l i 4 I l l { l HUMAN VEGETATION l l b \\ r 65 -=.-..-..-
DATA INTERPRETATIONS AND CONCLUSIONS CN HUMAN VEGETATION DATA
SUMMARY
I Four samples are routinely obtained during the 2nd and 3rd quarters while available. They are routinely counted for gross beta less K-40. l Gross Beta less K-40 No activities were observed on the samples counted for gross beta less Samples are dried at 110*C for 24 K-40. This is consistent with data hours, ashed, and dissolved with taken in 1984. dilute acid. Counting Instrument: Internal Gas Flow Proportional Counter Model: Beckman Wide Beta II Gamma Spectrometry i Sample Type: Marinelli Beaker Detector: Intrinsic Germanium l Analyzer: TN 4500 Northern Scientific Strontium-90 l Samples are dried at 110*C for 24 hours, ashed, and dissolved in HC1. l The Yttrium is backextracted after ingrowth and precipitated as an ( oxalate. Counting Instrument: Internal Flow Proportional Counter Model: Beckman Wide Beta II e lo l es i t
.A maxA w+e- - --e3 2 aau --4A----a----- -M LAM- ~mmm E A" WAM-AMkwc-- d-w" --m----- -""4m BL AA-ma-aAma--- t i A 'l, i 4 I i + i i i i T p i 1 5 .i l BEEF TISSUE I l. 1 4 i i I 67 t -~ ~ -
DATA INTERPRETATIONS AND CONCLUSIONS 'O SPECIAL SAMPLES BEEF TISSUE DATA
SUMMARY
Routine Program Routine Program A sample of beef tissue was obtained No radiolodine activity was observed in the second quarter of 1985. In the sample. No samples were taken in 1984 or during the pre-operational period. Gamma Spectrometry Sample is dried at 110*C for 24 hours, the sample is then reweighed and ground and blended into powder for analysis. Samples prepared.are then reweighed. Sample Type: Marine 111 Beaker Detector: Intrinsic Germanium Analyzer: TN 4500 Northern O Scientific , b Special Studies Special Studies Special beef samples were obtained Details of the special studies are i from 3 sources: presented in Appendix C, UCID-20641. l Detectable radionuclides were Cs-134
- samples from 2 head on feed lot and Cs-137. Values found were as near Ranch Seco follows: pC1/Kg net
- steaks from 3 local major markets Description Cs-134 Cs-137
- samples from 2 head pastured on Feed lot nd 5.0 Clay Creek Feed lot nd 2.3 Market nd 5.0 Samples were dried at 90*C to constant Clay Creek 14 69 dry weight, homogenized and placed Clay Creek 17 56 into containers for analysis by gamma spectrometry. Detection limits:
nd - nondetectable (pCl/ sample) Cs 134 1 Cs 137 1 l O l 68
,_,s4a4,,-w- - - --- m--m.n -,,-4m-a a aa ___gu_,mam a.r---e ,,me.--m -- s aw.- r-,,,,,,,,,, a,-wa,,_ a,._,,,,-_ ,_.m.,,,, -,,,- - 1 i a i l 1 i I 1 i i l i i I l l 1 i ]
- l l
l j i i COW THYROID l l i l' I t r i i l f 1 t 69 l r i 1 1 I l
DATA INTERPRETATIONS AND CONCLUSIONS I O SPECIAL SAMPLES CON THYROIO j DATA
SUMMARY
Cow Thyroid One cow thyroid (beef) was obtained in the second quarter. i Iodine 131 No Iodine-131 activity was observed in the sample. This is consistent with r The sample is dried at 110*C for 24 the samples obtained in the second hours, ashed, and diluted with acid. quarter of 1984. This is also consistent with samples taken in the ,l Sample Type: Marinelli Beaker pre-operational years of 1971 and 1973. l Detector: Intrinsic Germanium Analyzer: TN 4500 l Northern Scientific l Sensitivity: 0.025 pCl/g 4 I i h + i l i l l i I 70 i
i I f, i i I I I I i l 4 I I l I. 3 i I i l h i l I l HONEY l l l 4 I l 71 1 i 1 1 1
DATA INTERPRETATIONS AND CONCLUSIONS SPECIAL SAMPLES ( HONEY DATA
SUMMARY
A honey sample was obtained in the second and third quarter of 1985. The sample was counted by gamma spectrometry. Gamma Spectrometry No gamma activities were observed in the samples obtained. No honey Sample Type: Marinelli Beaker samples were obtained either in 1984 or during the pre-operational period. Detector: Intrinsic Germanium I Analyzer: TN 4500 l Northern Scientific t. i i t i l 1 i i l i I l r 7E I
i i 2 i i i ASSESSMENT OF RADIOLOGICAL IMPACT l ON THE ENVIRONS i l I i l 73
l Radiological Assessment of Impact on The Environs Ob Radioloalcal Impact - Gaseous Effluents No measurable activities due to the routine operation of the Rancho Seco Nuclear Generating Station has been observed by the air sampling program during 1985. As a result, no radiological impact can be inferred from the measurements. This is supported by the following: 1. No directly detectable activities above background have been correlated with plant operation. All measurements for gross beta, gross alpha, radiolodine, and gamma spectroscopy have not been able to detect quantitles above normal background. 2. Correlation attempts between plant activity released into sector weighted air sample locations have been negative. The use of sector weighted averages should have maximized possible correlation. 3. Actual plant release data indicate on a calculational basis (i.e., X/0 calculations) that current plant releases are unlikely to be detected with the current X/0 values, plant releases, and system sensitivities for lower limits of detection. 4. Measurements below system detectabilities have been consistent with plant history. Positive levels of radionucildes associated with nuclear weapons testing have been observed shortly after the testing and for a period of several weeks after the test. 5. The proper operation and detectability for the air sampling systems can be inferred from the good agreement of natural background measurements with log normality in the environment and the sensitivity of sample measurements which are analyzed too soon after a short-term plant release. l l 74 i
Radiological Impact - Liquid Effluents O(v) The radiological impact of the liquid effluents from Rancho Seco is traced to 4 paths:
- consumption of aquatic foods
- swimming and shoreline usage of the streams
- 1rrigation of crops and subsequent ingestion by humans
- 1rrigation of food crops or pasture with subsequent ingestion of meat by humans.
Consumption of Aquatic Foods and Swimming and Shoreline Usage Estimates of the impact of this path are derived by evaluation of doses for a hypothetical family with freshwater aquatic food intake in the range of previous studies for persons in the Pacific region (Ru80). Results of the liquid effluent land use survey indicate that no Rancho Seco area residents use the Clay and Hadselville stream system. Consequently, It is inappropriate to assess dose for these residents. The stream usage factors for the hypothetical family are presented in Table I. This table uses the 90th percentile for consumption of freshwater fish from Ru80. Crayfish and frog legs were not identified in Ru80, and are consequently not used. Shoreline usage is scaled to fish consumption from 1984 for families in the Rancho Seco area. Swimming time was derived from one family with large 1984 usage. Source terms were derived from data presented in UCID-20641, Appendix C. Q(' These data were extracted and rearranged into probability plots shown in j Figures I through 8. Cs-134 is taken as 357. of Cs-137 for fish analysts. These are shown in Figures I through 3. The source terms for the hypothetical family were obtained by using 50th percentile values for larger sections of the stream system. For aquatic food and shoreline use, the entire system downstream was used. These are shown in Figures 4 through 7. This includes the length less than 4.6 km although it has been posted with "No Hunting, No Fishing, No Trespassing" signs and usage has been significantly reduced since 1984. The source term for swimming is taken as the 50th percentile of observations downstream (Figure 8) from the Folsom South Canal since upstream is not used for swimming. Table II presents source terms for the hypothetical family. Doses were calculated in accordance with the Offsite Dose Calculation Manual. The doses are presented in Table III. Irrigation of Crops with Subsequent Ingestion In the downstream distance beyond 4.6 km, crops are irrigated from the stream system by subscribers of the Galt Irrigation Olstrict. Some crops such as wheat and rice, could be directly ingested by humans. Although it seems unlikely, since the crops are raised for market, the dose to an Individual n v 75
whose grain intake is composed solely of that from these fleids is evaluated. Only grain crops are grown. The Galt Irrigation Olstrict keeps accurate reco.o. ;* water usage and acreage irrigated. The average rate of irrigation in 1985 was i60 liters per square meter per month, assuming six month irrigation. The source term was obtained from the 50th percentile of water concentrations downstream from Folsom South canal (Fig. 8). The source terms were Cs-134 at 0.123 pCl/ liter and Cs-137 at 0.358 pCl/ liter. All other factors are taken from the Offsite Dose Calculations Manual. The resulting dose equivalent estimates are presented in the table below. DOSE (mres) Organ Adult Teen Child Total Body 0.10 0.093 0.068 Bone 0.097 0.16 0.39 Liver 0.15 0.25 0.42 Thyroid 0.0 0.0 0.0 Kidney 0.05 0.082 0.13 Lung 0.017 0.032 0.049 GI-LLI 0.003 0.003 0.003 Irrigation of Pasture With Subsequent Ingestion of Meat Beef cattle are pastured on land Irrigated by Clay Creek between the plant outfall and the site boundary. Two samples were taken from cattle pastured in this area. Radlonucildes were measured as follows: pC1/kg net weight i i Sample Cs-134 Cs-137 i 1 14 69 2 17 56 The usage parameters are taken from the Offsite Dose Calculation Manual for the maximally exposed individual. kg / yr Infant Child Teen Adult Heat 0 41 65 110 l In the unlikely event that this individual were to eat aII meat from these cattle, the body and organ doses which would result are presented in the table below. Nuclide concentrations are taken as the average of the two measurements. l 16 l L
l l l i millirem (1985) i Adult Teen ChiId Total Body 0.70 0.30 0.17 l Bone 0.65 0.54 0.99 Liver 1.00 0.80 1.04 Thyrold 0.0 0.0 0.0 Kldney 0.34 0.27 0.34 Lung 0.11 0.10 0.12 GI-LLI 0.02 0.01 0.01 i l r i I t i f l I i l v i i s i I l i f I i f i i e t O 77 1 l-L e_.
TABLE I STREAM USAGE FACTORS - HYPOTHETICAL FAMILY AQUATIC FOODS (kg/yr) ALL OLSTANCES 4.6 KN ADULT TEEN CHILD TEEN CHILD Bluegill 0.49 0.11 0.24 Bass 0.49 0.11 0.24 Catfish 0.49 0.11 0.24 SHORELINE (hr/yr) Fishing 65 100 100 Swimming O i 1 t I \\ l l 78 l l--.
4 1 4 l I TA8LE II 1 j SOURCE TERMS f AQUATIC FOODS (pCl/gm) HYPOTHETICAL FAMILY (>0.5 KM) l I Cs-134 Cs-137 1 Bluegill 0.23 0.65 i Bass 0.23 0.65 Catfish 0.66 1.9 t Froglegs l Crayfish t SHORELINE USAGE (pC1/m2) (>0.5 KM) 4 \\ i Fishing Cs-134 2.47 E-5 Hunting Cs-137 6.6 E-5 Co-60 3.98 E-4 l ( SWIMMING (pCl/1) (>4.6 KM) Cs-134 0.12 Cs-137 0.36 t l l l i 79
1 i \\ TABLE III 1 i CALCULATED DOSES (MREM) FOR 1985 BASED ON { ENVIRONMENTAL SAMPLES l HYPOTHETICAL FAMILY l ADULT TEEN CHILD } WHOLE BODY ) Aquatic Foods 0.19 0.04 0.05 t Shoreline 0.13 NA NA Swlmming NA 7 E-5 7 E-5 TOTAL 0.32 0.04 0.05 1 MAXIMUM ORGAN (LIVER) I Aquatic Foods 0.25 0.09 0.34 I Shorellne 0.13 NA NA l t 1 l Swimming NA 7 E-5 7 E-5 l l TOTAL 0.38 0.09 0.34 i I t 1 4 l, i I i 1 l l l 80 [ i
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-.. ~.. i j REFERENCES Ru80 Rupp, Elizabeth, M., Forest, L. Miller and C. F. Baes III, "Some Results of Recent Surveys of Fish and Shellfish Consumption by Age and Region of U.S. Residents, i Health Physics, 39:2, August 1980 i G 89 t -. _ -,. _... _.. -, _ _. =
SUMMARY
- RADIOLOGICAL IMPACT I
Gaseous Effluents l l The results from the TLD program indicate that no correlation can be made with respect to sector-weighted releases even at close distances. The conclusions from analysis of the air sample results are similar, although the air sample coverage is much less than the TLD coverage. i Anomalies occur in the TLD readings. At the protected area boundary, these have been traced to storage of radioactive waste in the vicinity. Other anomalles, such as the Jackson and Lodt results, have yet to be resolved. These high readings are very unlikely to be due to Rancho Seco releases because of the large distances and lack of correlation at closer distances. The geology of the area leads to the hypothesis that these distant anomalies are due to naturally-occurring radioactive materials. Liquid Effluents The results of environmental samples taken in this pathway indicate that a dose equivalent of less than 0.5 mrem could be received by a hypothetical individual who occasionally eats aquatic fauna from the stream. A hypothetical traximum individual who obtains all his grain intake from irrigated crops would receive a dose equivalent of less than 0.5 during 1985. An individual whose sole meat intake is from beef with radionuclide l concentrations similar to the samples might receive a dose to the maximum organ of about 1.0 mrem per year. 7 ? I G l 90 1
t l 1 i l l APPENDICES i A Land Use Census B Program Summary Description and Maps C Environmental Radiological Studies Downstream from the Rancho Seco Nuclear Power Generating Station - 1985. LLNL UCID - 20641 D Interlab Comparison Program Results I l I l ( l l l l f 1 i e 4 .--..-,.-,._.e.,-.,m.. _ _ _. _..-..... ,._,___m...
i i APPENDIX A l l LAND USE CENSUS i i 4 f A-1
LAND USE CENSUS x \\) The land use census is currently composed of three elements: Identification of the nearest milk animal, nearest residence and nearest garden of greater than 500 square feet in each of the 16 sectors within a five-mile radius in accordance with technical Specification 3.23. Interviews of residents living near Rancho Seco who use the Clay-Hadselville-Laguna Creek system to determine extent of usage of this stream system. Review of documents to determine items such as irrigation water obtained from the Clay-Hadselville-Laguna Creek system. The results of the first element are presented in Table I. These data indicate that changes during 1985 principally involve the addltion of gardens and new residences which are closer. Interviews to implement the second element are continuing into 1986 to obtain information on the 1985 usage. The delay has been to factors which are beyond the control of the District. Information into May 1986 indicates that residents in the Rancho Seco area stopped using the stream system for fishing, frogging, swimming, and other recreational purposes in November-December 1984. O Hith the cooperation of local landowners, Clay and Hadselville Creeks were l (m posted with "N0 HUNTING, NO FISHING, NO TRESPASSING" signs in December 1984. Access is limited in the areas of downstream distances less than 4.6 km. On 15 July, 1985, the District initiated a program to inspect the Clay /Hadselville Creek areas. The purpose of the inspection is to determine whether persores are trespassing on posted private property, particularly to l fish. Inspections were performed two or three times per day with tha chosen i pseudo-randomly. Weekends were not covered until after 16 S1ptember 1985. After 16 September, inspections were also performed on Saturdays. In all, 261 observations were made. During the period from 15 July to 21 December, 1985, ne englers were observed in the posted area. On one occasion during September, litter was found which indicates anglers may have been in the area. No other evidence of fishing or trespassing in the posted area was observed. The local landowners also remove trespassers from the posted land. From the interviews and inspections, it appears at the time of this report that no regular use is made of the stream system by residents near Rancho Seco. Usage, if any, of the stream system at less than 4.6 km is confined to occasional users who stop at the California State Route 104 bridge. Data were obtained from the Galt Irrigation District for all irrigation users along Laguna Creek. These users, identified by alphabet code, quantities of f water, areas irrigated, and crops are identified in Table II. A-2
LAND USE CENSUS hQ TABLE I Results of 1985 Gaseous Pathway Census Within 5 Miles (All values are distances in meters to nearest subject in sector) NEAREST MILK ANIMAL NEAREST NEAREST NEAREST MEAT ANIMAL SECTOR GOAT CON RESIDENT GARDEN
- BEEF HOG POULTRY SHEEP N
None** None None None 436 None None None NNE None None None None 433 None None None NE None None 1430 4830 433 None None 4830 ENE None 1140 1140 1140 448 None 1140 1140 E None None None None 472 None None None ESE None None None None 668 None None None SE None None 2560 2560 235 None None None SSE None None 7800 None 198 None None None S None None 6490 None 195 None 6490 None SSW None None 2900 5330 198 None 6340 None SW None 3190 1220 3190 237 3190 3190 3190 WSW Nove 3620 1830 2380 405 3230 3620 3230 W 3230 7740 3230 3230 506 None 5820 3230 WNW None None 4390 4390 436 None None None NH None None 5330 6750 491 6750 6750 6750 NNW None None 7250 None 445 None None None
- Defined as greater than 500 square feet with edible green leafy vegetables.
- None within a five mile radius from the Rancho Seco Containment Building.
O A-3
I i 4 TABLE II l GALT IRRIGATION DISTRICT 'l HATER USAGE 1985 l Nator ( Usage Crops (acres) l User (Liters) Corn Rice Clover Sudan Pasture Wheat Total ( A 1.25E9 120 100 220 B 2.04E8 42 18 60 i l-C 2.71E8 50 50 100 D 6.44E7 70 70 i E 9.66E7 30 30 l ) E 6.26E8 190 190 G 1.12E9 88 135 223 H 3.08E8 50 50 ,[ I 3.15E8 150 150 Total 4.26E9 92 288 435 208 70 1093 A-4
l i I l APPENDIX 8 PROGRAM
SUMMARY
DESCRIPTIONS AND MAPS l l l i B-1
N g g b L PROGRAH SUP94ARY DESCRIPTION SAMPLE COLLECTION ANALYSIS ANALYSIS REPORTABLE TYPE
- LOCATION FRE00ENCY ANALYSIS FREOUENCY SENSITIVITY UNITS LEVELS UNITS i
Alc_Earticulate 3 3 RAA0/2 Hiller Residence W Gross Beta W 1X10-2 pC1/m 2 PC1/m RAB0/16 SHUD Headqutrs. Gamma Isotope QC Table I Table II i RACO/14 Lodi Gamma Isotope If gross beta 5X10-2 RAD 0/6 Tokay Substatn. >10 times Ctr1. RAE0/10 Ione Sample for Same RAF0/17 Carbondale Period 3 3 0.9 pC1/m RAG 0/8 Fish Hatchery Iodine 131 W 7X10-3 pCi/m RAH 0/1 Rancho Seco SuEfn e_ Mater Suspended FracLO. RSWAD/8 Camanche Reservr M Gross Beta M 4 pC1/1 40 pCi/1 2 RSWB0/4 Folsom So. Canal Iodine 131 M 1 RSWC0/1 Rancho Seco Site SuEface_ Water Qissalyed Fractn. RSWA0/8 Camanche Reservr M Gross Beta M 4 pC1/1 40 pC1/1 RSWB0/4 Folsom So. Canal Iodine 131 M i 2 3 4 RSWC0/1 Rancho Seco Site Tritium Q 2x10 2x10 as Runoff Water Susnended RkWC0/1 Rancho Seco Site BW Gross Beta BW 4 pCl/l 40 pC1/1 Boundary Iodine 131 BW 1 2 RunoLE_ Water Gamma Isotopic Q Table I Table II QLssolmed Fract. RRWCO/l Rancho Seco Site BW Gross Beta BW 4 pC1/1 40 pC1/1 Boundary Iodine 131 1 2 Gamma Isotopic Q TablgI Table II Tritium Q 2X10 2X10 Cs 134 30 Cs 137 50 Well Water RWWA0/1 Rancho Seco Q Gross Beta Q 4 pC1/1 40 pC1/1 2 = RWWB0/11 Clay Area G Iodine-131 0 1 4 3 RWWD0/1 Reservoir Well 0 Tritium 0 2x10 2X10 RWWE0/6 Clay Cattle Q Q Feedlot Erjakl0g_Witer Rancho Seco H Gross Beta M 4 pC1/1 40 PC1/1 2 RWWCO/1 Drinking Fountain Iodine-131 M i 4 3 2X10 Tritium M 2X10 W = Weekly Q = Quarterly A = Annually C = Composite
- /n = Hap Lccation H = Honthly SA = Semi-Annually 2/H = Twice/Honth BW = Biweekly (Every two weeks)
s PROGRAM SUte4ARY DESCRIPTION SAMPLE COLLECTION ANALYSIS ANtLYSIS REPORTA8tE TYPE
- LOCATION FREQUENCY ANALYSIS FR[QU{3CY SLESITIVITY UN[IS LEVELS UNITS Mud A_ Slit RHSC0/1 Rancho Seco Site Q
Gross Beta 0 2x10-1 pC1/g NA RHSED/1 Res. Rancho Seco Site Gamma Isotopic Table I dry Table II Boun. Mllk RHFA0/3 Hedeiros Dairy W Iodina 131 W l pC1/1 3 pCi/l RHFB0/9 Angelo Diary Gamma Isotopic Table I TB0 (Table II RHFC0/12 Warmerdam Dairy Strontium 90 TBD RHFD0/1 Harciel Ranch Elib RFA0/l Sp-1 Rancho Seco Site Q Gross Beta-K40 Q IXIO-I pC1/g 10 PC1/g RFA0/1 Sp-2 Res. Gamma Isotopic If Gross Beta Table I dry dry RFB0/1 Sp-1 Rancho Seco Site -K40 is M0 Table II RFB0/1 Sp-2 Boun. P C1/g dry RFCD/4 Sp-l Hadselville Creek Strontium 90 0 0.03 pC1/g TBD RFCO/4 Sp-2 dry W t!uma!1_YtgtLAL100 [3 RLVA0/11 Clay Station Area SA Gross Beta-K40 SA 0.02 10 pC1/g RLVB0/10 Ione Area Ganna Isotopic If Gross Beta Table I Table II RLVCO/7 Clements Area >10 pCl/g dry RLVD0/5 Sloughbouse Area &laat RBA0/1 Q Gross Beta-K40 0 0.02 pC1/g RBB0/4 Ganna Isotopic See T8L V CEP dry I Strontium-90 1984 Annual R;t. 0.03 App D l Aflimal_Ven/Past RLVE0/12 Warmerdam cairy H Gross Beta-K40 H 0.02 pCl/g RLVF0/3 Hedeiros datry Strontium 90 0.03 dry l RLVG0/9 Angels dairy RLVH0/1 Marciel Ranch RLVIO/l Pasture irrigated by Clay Creek Cow Thyroid SA for I-131 Spec SA 0.025 pC1/g Honey SA Spec SA Table I Table II I W = Weekly Q = Quarterly A = Annually C = Composite
- /n = Hap Location l
( H: Honthly SA = Semi-Annually 2/H = Twice/Honth BW = B1 weekly (Every two weeks) i
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TABLE I DETECTION LIMITS BY GAMMA SPECTROMETRY /"" Sensitivity Sensitivity Sensitivity pC1/m3** Energy pC1/gm* pC1/1** Air MeV Isotope Algae & Mud Runoff Water Particulate 0.122 Cobalt-57 0.004 2 0.001 0.134 Cerium-144 0.121 24 0.005 0.186 Radium-226 0.200 84 0.073 0.239 Lead-212 0.040 20 0.016 0.295 Lead-214 0.060 38 0.004 0.320 Chromium-51 0.246 49 0.010 0.344 Actinium-228 0.140 50 0.104 0.364 Iodine-131 0.025 5 (a) 0.476 Bery111um-7 0.236 20 0.030 0.537 Barium-140 0.075 15 0.018 0.583 Thallium-208 0.060 16 0.018 0.605 Cesium-134 0.079 16 0.023 0.609 Bismuth-214 0.100 40 0.030 0.622 Ru, Rh-106 0.143 20 0.001 ) x 0.662 Cesium-137 0.056 11 0.001 0.756 Zirconium-95 0.041 8 0.026 0.765 Niobium-95 0.034 7 0.026 l 0.765 Zirconium, Niobium-95 0.066 8 0.026 ( 0.810 Cobalt-58 0.017 3 0.001 i 0.835 Manganese-54 0.021 4 0.001 1.095 Iron-59 0.024 11 0.006 1.115 Zinc-65 0.060 12 0.045 1.173 Cobalt-60 0.058 12 0.019 1.460 Potasium 1.600 662 1.172 1.596 Lanthanum-140 0.465 93 0.030
- Based on 100 grams.
- Based on l' liter.
3
- Based on 265m volume of air.
3 (a)0.01 pC1/m if CEP receives charcoal cartridges within 24 to 48 hours and 3 0.02 pCl/m for cartridges received 48 to 120 hours after collection. Os B-7 L
TABLE II RADIOLOGICAL ENVIRONMENTAL REPORTING LEVELS Airborne Particulate Water or Gases Fish Milk Food Products Analysis (DC1/1) (DCi/m3 (pC1/am dry) (pCl/1) (DCl/am dry) 4 H-3 2x10 Mn-54 1x103 2 Fe-59 4x10 3 Co-58 1x10 2 Co-60 3x10 2 Zn-65 3x10 2 Zr-Nb-95 4x10 l I-131 2 0.9 3* Cs-134 30 10 60 Cs-137 50 20 70 2 Ba-La-140 2x10 300 Gross Beta 40 2 10*** 10**
- Full gamma isotopic analysis if I-131 exceeds reporting level of 3 pC1/1.
- Edible food must have gamma isotopic analysis if Gross Beta minus K-40 exceeds 10
- Fish is required to have full gamma isotopic analysis if the Gross Beta minus K-40 exceeds 10 pC1/g (dry).
- Edible food must have gamma isotopic analysis if Gross Beta minus K-40 exceeds 10
1 B-8 l
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l ( l l l t i l APPENDIX C Environmental Radiological Studies Downstream from the Rancho Seco Nuclear Power Generating Station-l 1985 LLNL UCID-20641 l t l 1 l l i , -.. - - - _. ~ -. -.
m ~s --a as. n-O APPENDIX 0 INTERLABORATORY COMPARISON PROGRAM O O l l 0-1
EPA Interlaboratory Comparison I l The results of CEP's interlaboratory comparison with the Environmental Protection Agency crosscheck programs are attached in both graphic form. This program is under the direction of Mr. Stephen Nelson at Controls for Environmental Pollution Inc. I
SUMMARY
STATISTICS Lowest % of EPA 73% Sr 90 Highest % of EPA 141% Gross 8 j Average of EPA (%) 101 i Standard Deviation (%) i 29 i i i 4 i i l I I i i i i f 0-2 i t 4 -e,-n--.--n,_ -,.--,,,--n,_.
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i I I l Results of the EPA Cross-Check Program 1985
EPA CROSS-CHECK PROGRAM 1985 i Water ( EPA CEP l Known Value Reported Value Date Parameter pC1/1i 1 a pCi/112 a 1/4/85 Strontium-89 3+5 3.0 + 0.5 3.5 2 0.5 3.2 1 0.5 Strontium-90 30 + 1.5 39 + 3 34 - 3 36 - 2 l l I 1 i l
o EPA CROSS-CHECK PROGRAM 1985 Water EPA CEP Known Value Reported Value Date Parameter pCi/111 a pCi/tt 2 a 2/35 Chromium-51 43 + 3.7 33 + 7 46 + 7 32 7 Cobalt-60 20 + 3.7 20 + 3 25 + 3 20_!3 Zinc-65 55 + 3.7 51+3 5073 5523 Cesium-134 35 + 3.7 33 + 2 29 + 2 ~ 32_!2 \\ Cesium-137 25 + 3.7 23 + 3 2573 2353 7/35 Cobalt-60 14.0 + 5.0 19 + 2 1572 16 - 2 Zinc-65 47.0 + 5.0 52 + 5 49 + 5 l 44i4 Ruthenium-106 62.0 + 5.0 73 + 7 74!7 69_77 Cesium-134 35.0 + 5.0 23 + 3 29 + 3 26_!3 Cesium-137 20.0 + 5.0 19 + 2 16 + 2 1422
O l i { EPA CROSS-CHECK PROGRAM 1985 Water EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a pCi/li 2 a 4/85 Low lodine-131 7.5 + 1.3 6+2 672 ~ 5 2 8/35 High Iodine-131 33 1 6 37 3 3 .a 'm [ l l s 4 't w I g j \\y p* i t, ,v =
EPA CROSS-CHECK PROGRAM 1985 Water EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a pCl/112 a 1/11/85 Plutonium 15.7 + 1.6 13.8 + 4.1 l 16.6 + 3.7 ( l5.813.5 7/13/35 10.6 + 1.1 12.7 + 2.3 l 13.9!2.4 1 14.252.3 ) i l I { l t l l I
l i l EPA CROSS-CHECK PROGRAM 1985 Water l EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a pCi/112 a 1/85 Plutonium-239 15.7 27 18.8 + 1 2 16.8 71 15.8 _ 1 l l l I l
D EPA CROSS-CHECK PROGRAM J 1985 Water EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a pCi/112 a 1/85 Gross Alpha 5.0 20 6 3 2 5 7+2 712 Gross Beta 15.0 + 5.0 13 + 2 14_2 16 3 2 5/35 Gross Alpha 12.0 3 5.0 13 3 2 15 + 2 1412 Gross Beta 11.0 + 5.0 12 + 2 1372 16[2 7/35 Gross Alpha 11 3 5 9 3 2 3+2 11-2 1 Gross Beta 3+5 9+2 13 + 2 1252 l l 9/35 Gross Alpha 8+5 10 + 3 l 9+3 11-3 3 Gross Beta 8+5 6+3 5+3 853 l 11/35 Gross Alpha 10 5 9 3 3 8+3 10- 3 1 Gross Beta 13 + 5 14 + 3 13 + 3 15 E 3
EPA CROSS-CHECK PROGRAM 1985 Water EPA CEP Known Value Reported Value Date Parameter pC1/111 a pCi/li 2 a 3/85 Radium-228 9.0 + 1.3 9.1 + 2 8.9 7 2 8.5 - 2 l l
f EPA CROSS-CHECK PROGRAM ( 1985 Water EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a pCl/112 0 2/85 Tritium 3796 + 634 3750 + 600 3610 + 600 35401600 4/85 3559 + 630 3437 + 500 3265 + 500 33012500 6/85 2416 + 351 3260 + 571 3191 + 576 29065405 8/85 4480 + 448 3893 + 485 3944 + 476 3847i477 ..__.,-_y.
EPA CROSS-CHECK PROGRAM 1985 Water EPA CEP l Known Value Reported Value Date Parameter pCi/li I a pCi/112 a 2/22/85 Uranium 12 + 6 10 + 2 1072 l 12_! 2 3/23/85 4+6 4+3 i 4!3 4 L 2 l -- - e,-- e-, g--. --,__._---,,_--,,_,,,,,,--,-_,,_,,_--.----------.--m,.
EPA CROSS-CHECK PROGRAM 1985 Radionuclides in Milk EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a pCi/112 a l 6/35 Strontium-39 11 + 5 10 + 2 11 + 2 12~2 i I Strontium-90 11 + 1.5 3 + 0.7 7i1.2 3 13 0 Iodine-131 11 + 6 15 + 5 14 + 5 1726 Cesium-137 11 + 5 15 + 5 1675 1456 Potassium 1525 + 76 1480 1520 1440 l l
EPA CROSS-CHECK PROGRAM 1985 l Milk l l EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a pCl/112 a 3/35 lodine-131 9 + 0.9 8 + 0.6 7 - 0.9 ~ 1.3 7 l l l
- s l
^ EPA CROSS-CHECK PROGRAM 1985 Radionuclines in Air Filters EPA CEP Known Value Reported Value Date Parameter pCi/filteri Ia pCi/filteri 2 o 3/85 Gross Alpha 10.0 8.7 91 1 3 10+1 12[1 Gross Beta 36.0+8.7 40+4 4174 3914 Strontium-90
- 15. 0+ 2.6 19+2 1872 17E2 l
Cesium-137 6.08.7 72 1 1 6+2 512 8/85 Gross Alpha 13 + 5 11 + 2 1312 12 1 2 Gross Beta 44 + 5 53+4 54 + 4 56 [ $ Strontium-90 18 + 1.5 15 + 2 1773 1422 Cesium-137 8+5 9+2 Il + 2 8 1 2 l l l l l
APPENDIX E 1 HISSING SAMPLES 1 i l l l l I i I l E-1
MISSING SAMPLES 'O' No. 1985 Reason RAF0 02/16 - 02/22 lost during shipment TLD 55 First quarter missing from sample location TLD 6 Second quarter missing from sample location l TLD 31 Second quarter missing from sample location TLD 55 Second quarter missing from sample location RAA0 07/30 - 08/07 lost during shipment i ) TLD 55 Third quarter missing from sample location TLD 58 Third quarter missing from sample location TLD 28 Fourth quarter missing from sample location TLD 31 Fourth quarter missing from sample location TLD 33 Fourth quarter missing from sample location TLD 62 Fourth quarter missing from sample location L f l O E-2 .}}