B13205, Annual Radiological Environ Operating Rept,1988
| ML20245F272 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/31/1988 |
| From: | Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B13205, NUDOCS 8905020316 | |
| Download: ML20245F272 (108) | |
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e HADDAM NECK STATION . RADIOLOGICAL ENVIRONM ENTAL MONITORING : PROGRAM: , ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 9 PERIOD JANUARY 1,'1.988.- DECEMBER.31,.1988: DOCKET NO. 50-2131 LICENSE NO. DPR-61
' PREPARED FOR THE -
CONNECTICUT YANKEE ATOMIC POWER COMPANY - HADDAM, CONNECTICUT - BY THE NORTHEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT t( .
L NORTHEAST IfTILITIES o.n r.i Ome.. . s.ia.n sir t. s.run, Conn.cticut ARTFORD. CONNECTICUT 06141-0270 l k k iJ ((,((,",[ (203) 665-5000 i l April 25, 1989 Docket No. 50-213 B13205 Re: 10CFR50.4(b)(1) U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen: Haddam Neck Plant Annual Radiological Environmental Operatina Report In accordance with the requirements of the Haddam Neck Radiological Effluent Monitoring Manual, an implementing document of the Haddam Neck Technical Specifications, two (2) copies of the Annual Radiological Environmental Operating Report are herewith submitted. Copies of this report are being distributed in accordance with 10CFR50.4(b)(1). Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY
/ % W E.4 / Mfo~czka //
Senior Vice President cc: W. T. Russell, Region I Administrator l j l A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant l t l 1
. _ _ _ _ _ _ - _ _ . l
HADDAM NECK STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT , PERIOD JANUARY 1,1988 - DECEMBER 31,1988 1 l l DOCKET NO. 50-213 LICENSE NO. DPR-61 PREPARED FOR THE CONNECTICUT YANKEE ATOMIC POWER COMPANY H ADDAM, CONNECTICUT BY THE l l NORTHEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT L _ _ __ _ _._____ _ _ . . _ . _ 3
o TABLE OF CONTENTS Page No. 1.0 S u m m a ry . . . . . . . . . . . . . . . . . . . . . .. ... .. .. . ...... .. 1-1 2.0 '. Program Description . ............ . ..... .. . ...... ... .. 2-1 2.1. Sampling Schedule and Locations . . . . . . . . . . . . . . . . . . . . . ...... 2-1 1
- 2.2 Samples Collected During Report Period . . . . . . . . . . . . . . . . . . . . . 2-7 3.0 Radiochemical Results . .. .... ...... .... . ... ... . . 3-1 3.1 Summary Table . . ......... .. .......... .. . . . . . . . . . . . . 3-1
~ 3.2 Data Ta bles . . . . . . . . . . . . . . . . . . . . . .. . ........... ... ... 3-15
~4 0. . Discussion of Results . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . ..... 4-1 5.0 ' Offsite Dose Equivalent Commitments . . . . . . . .. .... ..... 5-1 6.0 Discussion . .... .. .... ... .. . . ..... . . .... 6-1 Appendix A - Cow and Goat Cnsus for 1988 . . . . . . ... .. . .. . .... A-1 Appendix B - Northeast Utilities QA Program . . . . . . . . . . . ..... . .... . B-1 Appendix C - Summary of EPA Interlaboratory Comparisons . . . . . . .. .. C-1 I
------__.-__._-_._L.____---._ _ . _ - _ _ . _ _ _ _ . _ . _ . _ _ _ , _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ 3
1.0
SUMMARY
The radiological environmental monitoring program for the Haddam Neck Plant was continued for the period January throug 1 December 1988, in compliance with the Radiological Effluent Monitoring and Offsite Dose Calculation Manual. This annual report was prepared for the Connecticut Yankee Atomic Power Company (CYAPCO) by the Radiological Assessment Branch of the Northeast Utilities Service Company (NUSCO). Gamma exposure measurements were performed by NUSCO l and tritium analyses were performed by Teledyne isotopes, Inc. All the remaining analyses were performed by Clean Harbors,Inc. Teledyne Isotopes,Inc.was used to independently check on the primary contractor's laboratory as part of the overall quality assurance program. Radiological analyses were performed with gamma exposure measuring devices and on samples of air particulate and iodine, milk, broad leaf vegetation, well water, fruits, vegetables, river water, bottom sediment, shellfish, and fish. In evaluating the results of these analyses it is necessary to consider the variability of radionuchde uptake in environmental media. This variability is dependent on many factors, including plant release rates, meteorology, number and size of nuclear weapon tests, seasonal variability of fallout, soil characteristics, farming practices, and feed type. Significant variations in measured levels of radioactivity could be caused by any one of these factors. Therefore, these factors need to be considered in order to properly explain any variations. The predominant radioactivity, indicated by the results, was that from nonplant (not Haddam Neck) sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. Plant related radioactivity was observed at some of the onsite gamma monitoring locations and in several other environmental samples. These include tritium m well water at the on-site location, tritium in river water near the East Haddam Bridge, cobalt-60, cesium-134 and cesium-137 in bottom sediment from near the end of the canal, and cesium-137 in fish caught in the discharge canal. As usual, cesium-137 and strontium-90 were measured in both cow and goat milk. These levels are a result of nuclear weapons testing in the 1960's and not the result of plant operation. This can be concluded based on the facts that: insufficient quantities (at least 1000 times less) of these isotopes have been released by the plant to account for the measured concentrations, chemically similar and plant related cesium-134 and strontium-89 which are released in about equal or larger quantities from the plant can not be detected and comparable levels of cesium-137 l and strontium-90 were detected prior to initial plant operation. l The radiation dose (dose equivalent commitment) to the genera! public from the plant's discharges has been evaluated by two methods. One method utilizes the measured station's discharges and conservative transport models and the other i" utilizes the measured concentrations of radioactivity in the environmental media. The maximum whole body dose (station boundary) that could occur to a member of the general public as a result of the plant's discharges was 0.8 millirem and the average dose to a member nf the public residing within 50 miles of the plant is 0.00028 millirem. These doses are 3.2 percent and 0.0011 percent of the standards as set by the Environmental Protection Agency cm the maximum a!!owable dose to an individual of the general public. These standards are a small fraction (less than I 10 percent) of the 280 mrem per year normal background radiation and are designed to be inconsequentialin regard to public health and safety. Plant related doses are even a smaller fraction of the natural background; they are less than 10 percent of the variation in natural background in Connecticut. Therefore, for the above stated reasons the plant related doses have insignificant public health consequences. l 1-1
2.0 PROGRAM DESCRIPTION 2.1 Sa'mplina Schedule and Locations The sample locations and the sample types and frequency of analysis are given in Table 21 and 2-2 and figures 2.I and 2.2. The program as described
' here includes both required samples as specified in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual and any extra samples.
I 2-1
TABLE 2-1 l ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS
.The following lists the environmental sampling locations and the types of samples obtained at each location'. .
i i ahn Direction & Distance From Number Name Release Point ** Sample Types 1 -l
- On-site - Mouth of Discharge Canal 1.1 Mi, ESE TLD 2-1 Haddam-Park Rd. 0.8 Mi,5 TLD 3-1 Haddam-Jail Hill Rd. 0.8 Mi, W5W .TLD 4-1 Haddam-Ranger Rd. 1.8 Mi, SW TLD, Air Particulate, lodine 5-l On-site-Injun Hollow Rd. 0.4 Mi, NW TLD, Air Particulate, lodine 6-l On-site-Substation 0.5 Mi, NE TLD, Air Particulate, lodine 7-l Haddam 1.C Mi, SE TLD, Air Particulate, lodine 8-1 East Haddam 3.1 Mi, ESE TLD, Air Particulate, lodine 9-l Higganum 3.2 Mi, WNW TLD, Air Particulate, lodine 10-1 Hurd Park Rd. 2.8 Mi, NNW TLD 11-C Middletown 9.0 Mi, NW TLD 12-C Deep River 7.1 Mi, SSE TLD 13-C North Madison 12.5 Mi, SW TLD, Air Particulate, lodine 14-C Colchester 10.5 Mi, NE TLD 15-1 On-site Wells 0.8 Mi, ESE Well Water j 16-C Well-State Highway Dept. E. Haddam 2.8 Mi, SE Well Water 17-C Fruits & Vegetables Beyond 10 Miles Vegetation !
18-l Site Boundary 0.4 Mi, NW Vegetation 19-1 Cow Location #1 1.5 Mi, NNW Milk. 20-1 Cow Location #2 6.0 Mi, NW Milk 21-1 Cow Location #3 4.5 Mi, NE Milk 22-C Cow Location #4 11.0 Mi, EN E Milk 23-C Goat Location #1 16.0 Mi, N E Milk 24-1 Goat Location #2 4.5 Mi, N Milk 25-l Fruits & Vegetables Within 10 Miles Vegetation f 26-1 Conn. River-Near :ntake 1.0 Mi, WNW Fish ! 27-C Conn. River-Higganum Light 4.0 Mi, WNW Pottora Seoiment, She!! fish 28-l Conn. River-E. Haddam Bric'ge 1.8 Mi, SE Bottom 54uiment, River Water i 28-X Conn. River-E. Haddam Bridge 1.8 Mi, SE Shellfish 29-1 Vicinity of Discharge - - - - - - - - - - - Br tte,n Sediment, Fish 30-C Conn. River-Middletown 7.6 Mi, NW River Water, Fish 31-1 Mouth of Salmon River 0.8 Mi, ESE Shellfish 40-X Near intake Structure 0.1 Mi, SSW TLD l 41-X Picnic Area 0.3 M.i, WNW TLD ! 42-X Boron Waste Storage Tank Fence 0.1 Mi, NW TLD ! 43-X Moodus Ris 149 & 151 2.5 Mi, ENE TLD
'44-X Shailerville - Horton Rd. 1.0 Mi, SE TLD l 2-2 !
TABLE 2-1 (Cont'd) Direction & Distance From
. Number '- Name Release Point ** ' Sample Types 45-X Waste Gas Sphere Fence 0.1 Mi, E TLD 46-X Discharge Canal Fence 0.2 Mi, SE TLD 47-X Guard House Fence 0.1 Mi, WNW TLD ,
*l = Indicator C - Control X - Extra - nonrequired sample
**The release points are the stack for terrestiallocations and the end of the discharge L .- ' canal for aquatic locations.
l l I l l 1 i 1 l i 2-3 '
TABLE 2-2 HADDAM NECK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling & Exposure Pathway Number of Collection and/or Sample Locations Freauency Type & Freauency of Analysis 1a. Gamma Dose- 14 . Monthly Gamma Dose - Monthly Environmental TLD 1b. Gamma Dose- 27 Quarterly (a) N/A(a) Accident TLD
- 2. Airborne Particulate 7 Continuous sampler - Gross Beta - Weekly weekly filterchange Gamma Spectrum - Monthly on composite (by location), & on individual sample if gross beta is greater than 10 times the mean of the weeky control stations gross beta results
- 3. Airborne lodine 7 Continuous sampler -
I 131 - Weekly weekly canisterchange
- 4. Vegetation -3 One sample near middle Gamma Isotopic on each sample
& one near end of growing season
- 5. Milk 6 Monthly Gamma Isotopic,1-131, Sr-89 & Sr 90 on each sample
- 6. Well Water 2 Monthly at Indicator Gross Beta, Gamma isotopic, & Tritium on Quarterly at Background each sample
- 7. Bottom Sediment 3 Quarterly Gamma Isotopic
- 8. River Water 2 Quarterly Sample - Quarterly - Gross Beta, Gamma isotopic &
Indicator is Continuous Tritium Composite; Background is composite of Six weeky Grab Samples
- 9. Fish - Bullheads 8, 3 Quarterly Gamma Isotopic - Quarterly when available, Perch or ofher edible fish
- 10. Shellfish 2 Quarterly Gamma Isotopic - Quarterly (a) Accident monitoring TLDs to be dedosed at least quarterly 2-4
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FIGURE 2.2 j Inner Terrestrial Monitoring Stations j Haddam Neck Plant ! 26
2.2 Samples Cellectr.d Durina Repart P3riod The following table summarizes the number of samples of each type collected dunng the present reporting period: Sample Type Number of Number of Reauired Samples Extra Samples Gamma Exposure (TLD) 168 96 Air Particulate 370 0 Air lodine 370 0 Dairy Milk 48 0 Goat Milk 21 0
'Well Water 16 0 Fruit & Vegetables 8 0 Broad Leaf Vegetation 2 0 River Water 8 0 Bottom Sediment 12 0 Fish 24 0 Shellfish 12 0 Total AllTypes 1,059 96 l
l 1 i l 1-1 i l 2-7 U L _- _-
3.0 RADIOCHEMICAL RESULTS 3.1 Summary Table i in accordance with the Radiological Effluent Monitorinc Manual (REMM), Section F.7, a summary table of the radiochemical results las been prepared I and is presented in Table 3-7. In the determination of the mean, the data was handled as recommended by 3 Health and Safety Laboratory, Idaho: all valid data, including negative values 1 and zeroes were used in the determination of the mean (see Part3.2). i A more detailed analysis of the data is given in Section 4.0 where a discussion l of the variations in the data explains many aspects that are not evident in the 1 Sum' mary Table because of the basiclimitation of such an approach. II i i l 3-1 ;
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FOOTNOTES A. For Ge(Li) measurements the MDL's == LLD / 2.33. For all others, MDL = 2 x o background. These MDL's are based on the absence of lar interfering activity (excluding natura'v occurring radionuclides).ge Deviationsamounts by of 3 about factors of 3 to 4 can occur. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with a 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): 4.66 sb LLD = E
- V
- 2.22
- Y
- exp (-A A t) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation) V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable) A is the radioactive decay constant for the particular radionuclides At is the elapsed time between sample collection (or end of the sample collection period) and time of counting it should be recognized that LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these a priori LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological EnvironmentalOperating Report. B. Analytical results are handled as recommended by HASL (" Reporting of Analytical Results from HASL," letter by Leo B. Higginbotham). Negative values were used in the determination of mean. C. Nonroutine reported measurements (NRM's). These are results of samples that exceed the report levels of Table E-2 of the Radiological Effluent Monitoring Manual. I 3-13
r fI-FOOTNOTES (Cont'd) l- D. First number is the number of indicawr measurements, the second is the number of control measurements. E. Assuming 270 m 3/ paper
- F. Assuming 1080 m 3 G. LLD for leafy vegetables.
H. Reduce LLD by a factor of two if the fractional beta for the sample' exceeds 15 pCi/l. l.~ LLD from the end of the sample period. i e 1 3-14
3.2 DOto TeblQs The data reported in this section are strictly counting statistics. The reported error is two times the standard deviation of the net activity. Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.) is estimated to be 2 to 5 times that listed. Because of counting statistics, negative values, zeroes and numbers below the Minimum Detectable Level (MDL) are statistically valid pieces of data. For the purposes of this report,in order to indicate any backcground biases, all the valid data are presented, in instances where zeroes are listed after significant digits, this is an artifact of the computer data handling program. Data are given according to sample type as indictated below.
- 1. Gamma Exposure Rate
- 2. Air Particulate, Gross Beta Radioactivity
- 3. Air Particulate, Weekly I-131
- 4. Air Particulate, Monthly Quantitative Gamma Spectra
- 5. Air Particulate, Quarterly Strontium
- 6. Soil *
- 7. Milk - Dairy Farms
- 8. Milk - Goat Farms
- 9. Pasture Grass *
- 10. Well Water l
- 11. Reservoir Water *
- 12. Fruits & Vegetables I
- 13. Broad Leaf Vegetation ,
- 14. RiverWater l
.l
- 15. Bottom 5ediment
- 16. Shellfish
- 17. Fish l ,
I
*None of these samples were collected, therefore there are no tables for them.
l 3 15
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4.0 DISCUSSION OF RESULTS This section summarizes the results of the analyses of environmental media sampled. Northeast Utilities has carefully examined the data throughout the year and has presented in this section all cases where plant related radioactivity could be detected and compared the results with previous environmental surveillance data. Few impacts of the plant operation on the environment were observed. Sub-sections contained describe each particular media or potential exposure pathway. Naturally occurring nuclides such as Be-7, K-40, Ra-226 and Th-228 were detected in numerous samples. Be-7 which is produced by cosmic processes was observed predominantly in airborne and vegetation samples. Ra-226 and Th-228 results were variable and are generally at levels higher than plant related radionuclides. ; Cs-137 and Sr-90 were observed at levels similar to those of past years. In general, the detectable levels of Cs-137 and Sr-90 were the result of atmospheric nuclear weapons testing of years past. Gamma Exposure Rate (Table 1) Gamma exposure from all sources including cosmic and other natural and artificial radioactivity is measured over periods of approximately one month using CaF,(Mn) thermoluminescent dosimeters (TLDs). These dosimeters are strategically placed at a number of on-site locations, as well as at inner and outer l off-site locations. Glass bulb type TLDs such as these, are subject to inherent self- I irradiation which has been experimentally measured for each dosimeter. The results, shown in Table 7 have been adjusted for this effect. The range of this correction is 0.4 uR/hr to 2.0 uR/hr, with a mean of approximately 1 uR/hr. The data for 1988 exhibits the same trends as that of previous years, gamma exposure rates did not differ significantly for the off-site inner and outer ring locations. The on-site locations at the boron waste storage tank (location 42X) and the waste gas surge sphere (location 45X) were the only locations showing any plant effects. Increases up to 3 UR/hr due to direct radiation from the plant are observed. These locations are within the plant's restricted area and, as such, are l away from areas where members of the general public are usually allowed. Dosimeters located at areas which are accessible to the public, ' h as the picnic area (location 41X) and the mouth of the discharge canal (locanon 01), did not i indicate any increase in exposure rate due to the plant. l Air Particulate and lodine (Table 2,3,4 A-L and S) Air is continuously sampled at six inner ring and one outer ring location by passing it through glass fiber particulate filters. These are collected weekly and analyzed for gross beta radioactivity. Results are shown on Figure 4-1 and Table 2. } Gross beta' activity remained at levels similar to that seen over the last six years. Inner and outer ring monitoring locations showed no significant variation in measured activities. This indicates that any plant contribution is not measurable. Charcoal cartridges are included at all of the air particulate locations for the collection ofiodine. No detectable levels of I-131 were seen in the 1988 charcoal samples. This is confirmed by the absence of I-131 in any of the milk samples. Milk from cows and goats is a much more sensitive indicator of I-131 presence in the environment. l 4-1
)
The weekly air particulate filters are composited monthly for gamma spectral analyses. The results, as shown in Tables 44-4L, indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. Positive results for all the other isoto ses are attributable to statistical fluctuations in counting. These analyses inc icate the lack of plant effects. For the measurement of Sr-89 and Sr-90, the air particulate filters are composited quarterly and analyzed by radiochemical separation and appropriate counting techniques. The results presented in Table 5 are much more sensitive indicators of environmental radioactivity than gamma spectrum analyses, because of the larger sample volume as a result of compositing and the higher efficiency of beta l counting. The Sr-90 results show the same trend as the gross beta analyses. Levels l continued to remain at the fairly constant low values as observed in 1982-1985. There was no detectable Sr-89 in any of these samples. Since there was no difference in measured levels of Sr-90 between indicator and control locations and no measurable Sr-89, there are no indications of any plant effects. Soil (Table 6) Soil samples are special samples not required by the Radiological Effluent Monitoring Manual (REMM). Previous data has shown the lack of detectable station activity in this media resulting in discontinuing these samples. In the event of widespread plant contamination or special studies, these sample would be collected. Cow Milk (Table 7) Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. This, in combination with the fact that consumption of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint. This pathway also shows significant amounts of nuclear weapons testing fallout. Therefore this media needs to be evaluated very carefully when trying to determine if there are any plant effects. Sr-90 was observed in all samples; all results were below 8 pCi/1. Detailed analysis of previous data has concluded that these levels of Sr-90 are from weapons testing and are not alant related (see Section 6.0 for details to this argument). Sr-89 was not detectec in any of the samples above its MDL This isotope is usually released from the plant in quantities equal to or greater than those of Sr-90, indicating that Sr-90 is the result of weapons testing and not from the plant. Sr-89 is only detected in these samples during episodes of fresh fallout from weapons testing. Cs-137 usually shows the same tendencies as Sr-90. Results for 1988 are similar to those of the past ten years. Detailed analysis has concluded that these concentrations are most likely the result of fallout from previous weapons testing (see Section 6.0 for details). Cs-134 was not observed above detectable levels in any of the samples, further confirming the absence of plant effects. Although not listed on Table 7, the only other nuclide detected by gamma spectrometry was natually occurring K-40. All samples showed a lack of I-131 detectable above the MDL of 0.5 pCi/l. These results are consistent with previous years' results. The only occasions when this nuclide has been detected are those immediately following atmospheric testing of nuclear weapons and the Chernobyl accident. 1 4-2
Goat MiIk (Table 8) Depending on the feeding habits, goat milk can be a more sensitive indicator than cow milk of fission products in the environment. This is due to the metabolism of these animals. Similar to the results of the cow milk samples, these show significant amounts of nuclear weaponstesting fallout. Sr-90 and Cs-137 were observed in all samples, with values similar at both locations. In previous years (1977 - 1983) the control location had significantly higher values than the indicator location. This difference in results between locations decreased substantially with a change in farms in 1983. The difference in results demonstrate the variability is caused in the by many uptake factors, of fallout including levels feeding among habits (various amount farms. of stored This feed, variability etc.), soil characteristics, farming practices (tillage and quality of fertilization and land management), and feed type. For a complete discussion of the problem see Section 6.0. As typical of periods lacking fresh fallout, no detectable Sr-89 was seen in these samples. The absence of Sr-89 and Cs-134 confirm that the levels of Sr-90 and Cs-137 are caused by previous weapons fallout. In August, one sample suffered contamination with I-131. Glassware in the laboratory was not sufficiently cleaned after processing control samples of milk spiked with I-131. All other samples showed a lack of I-131 detectable above the MDL of 0.5 pCi/l. These results are consistent with previous years' results. The only I occasions when this nuclide has been detected are those immediately following atmospheric testing of nuclear weapons and the Chernobyl accident. Pasture Grass (Table 9) ! When the routine milk samples are unavailable, samples of pasture grass are required as a replacement. These samples may also be taken to further investigate the levels of radioactivity in milk. During January -late March, these samples were s not available as a replacement at goat location #1. Pasture grass was again
\ unavailable in December at this location. In samples of past years, no plant effects were seen in this media.
Well Water (Table 10) Activity in this media results from either soluble plant effluents permeating through the ground or the leaching of naturally occurring nuclides from the soil and rock. H-3 and Gross Beta were detected in these samples, at levels similar to previous years. Co-60 was observed in one sample and Nb-95 in a few other i samples. These values could possibly be plant related; however, in years past, similar values have been observed in both indicator and control locations, meaning they are probably due to counting statistics. Bi 214 is a daughter product of naturally occurring Ra-226. In wellwater suppliesit may not necessarily be in equilibrium with its long lived precursor. Therefore it is not indicative of the Ra-226 concentrations. This effect has been discussed in previous reports. As usual the on-site wells (location 75) exhibited plant related H-3 significantly above background levels. This plant effect results from the wells { being located within an area influenced by the water in the discharge canal and j H-3 having the ability to readily follow the flow of ground water. Off-site I concentrations are much lower. This pathway does not result in any dose consequence since the water from these wells is used only in process streams at the station. Also consistent with previous years, the gross beta values for the control location at the State Highway Department (location 76C) were higherthan the values for 4-3
I the indicator location. This activity is due to the leaching of naturally occurring i nuclides. Variations can be caused by different flow patterns of the ground water, l variable permeability of the different soil and rock formations, and the usage pattern of the wells. Therefore, the results of this type of analysis are not very indicative of plant effects. ReservoirWater (Table 11) Reservoir water samples are special samples not required by the REMM. Previous data has shown the lack of detectable station activity in this media. This fact and 1 the extremely unlikely possibility of observing routine plant effluents in this media I has resulted in discontinuing these samples. In the event of widespread plant i contamination, these samples would be collected. J Fruits and Veaetables (Table 12) i Similar to past years,this media did not show any plant effects. Concentrations of Sr-90 in these samples existed at levels comparable to past years and is due to fallout. Naturally occurring K-40 was detected in all samples. Since there was no fresh fallout, no other nuclides were detected. Broad Leaf Veaetation (Table 13) Concentrations of Sr-90 and Cs-137 in these samples are at levels comparable to past years and are due to fallout. River Water (Table 14) These samples are collected on a quarterly basis; the sampling procedure is different at the control and indicator locations. Weekly grab samples of the first six weeks of each quarter are composited at the control station (Middletown-Iocation 30C). Continuous samples are utilized at the indicator station (East Haddam Bridge -location 28). Some indicator samples showed tritium (H-3) concentrations above the backgrour.J levels seen at the control location. These elevated levels are attributab;e to plant operation. They show the effect of plant releases being diluted by the Connecticut River. Because this nuclide only emits low energy beta particles and river water is not a source of drinking water, the dose consequence resulting from these levels is insignificant.- Fish consumption is the only media through which the population encounters dose from H-3 in liquid effluents. The dose consequence of the H-3, although not routinely measured in fish,is calculated based upon the measured effluents and appropriate dispersion models (NRC { l approved computer code -LADTAP). In order to verify these calculations, a special program of measuring H-3 in fish samples had been performed. The results of these analyses indicated that the effluent calculations are conservative. The dose consequences, discussed in Section 5.0, are insignificant. Gross beta was the only other activity that was consistently seen in these samples. The gross beta activities are similar to past data. These results are a gross type measurement and are, therefore, not very indicative of plant effects; they are masked by background activities. Bottom Sediment (Table 15) Plant related levels of Co-60, Cs-134 and Cs-137 were observed at one indicator location (Area of Plant Discharge -location 29). Cs-137 was also observed at the other indicator and the control locations. The Cs-137 levels at the control location are due to fallout activity. 44
h j l l Shellfish (Table 16) < 1 No detectable activity was observed in this media except for the naturally occurring radionuclides. Fish-Bullheads (Table 17A) Cs-137 was observed in both the indicator and the control locations at levels similar to past years. Even though Cs-134 was not observed, a portion of the Cs-137 in these samples could be due to 31 ant operation. Dose consequences were calculated assuming background (fallout) corrected concentrations resulted from plant effluents. The results of the calculations are shown in Section 5.0. Fish-Perch and other Types (Table 178) These fish samples exhibit the same results as the bullhead samples. ,Cs-137 was detectable at higher levels in samples from the indicator locations. These elevated levels may be plant related and as sud., the dose consequence, though very minimal, is discussed in Section 5.0. 1 4-5
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5.0 OFFSITE DOSE EOUlVALENT COMMITMENTS I The off-site dose consequences (dose equivalent commitments) of the station's radioactive liquid and airborne effluents have been evaluated using two methods. i The first method utilizes the station's measured radioactive discharges as input ! parameters to conservative models that simulate the transport mechanism through the environment to man. This results in the computation of the maximum doses to individucts and the 0 to 50 mile population dose. The results of these computations have been submitted to the NRC in the Annual Radioactive Effluents Dose Report written in accordance with the Radiological Effluent Monitoring Manual, Section F.2. The second method utilizes the actual results of the concentrations of radioactivity in various environmental media (e.g., milk, fish) { and then computes the dose consequences from the consumption of these foods. l The first method, which is usually conservative (i.e., computes higher doses than that which actually occur), has the advantage of approximating an upper limit to the dose consequences. This is important in those cases where the actual dose cannot be measured because they are so small as to be well below the capabilities of conventional monitoring techniques. The results of both methods are compared in Table 5.1. For gaseous releases, no plant related detectable activity was observed in any sampling media. The less-than values given for the second method are the doses which would be calculated if the annual average activity was equal to the minimum detectable level. Although the liquid releases are also low, traces of plant related activity were detected in, fish (caught in the discharge canal), bottom sediment and river water samples. The doses presented in Table 5.1 are the maximum doses to an individual for ' specific pathways to man. That is, the dose is calculated at the location of maximum effect from the slant effluents for that pathway and for the critical age group. For example, the c ose via the fish pathway is calculated for fish caught in the discharge canal and the external gamma dose is calculated at the site boundary which has the least meteorological dispersion. The calculations result in maximum total doses to an individual of: 0.8 mrem whole body to an adult, 0.17 mrem to a child's thyroid, and 0.41 mrem to a teen's liver. The calculated doses for all other locations and other age groups will be less than those shown on Table 5.1. The average dose to an individual within 50 miles from the site cannot be i calculated using the second method. However, Method 1 yields the following results for the period January -December 1988 for the average individual: ANNUAL AVERAGE WHOLE BODY DOSE : DUE TO AIRBORNE EFFLUENTS = 0.00023 mrem DUE TO LIQUID EFFLUENTS = 0.00005 mrem Thus,it can be seen that the average whole body dose to an individual is much less than the maximum whole body dose to an individual as shown in Table 5. 7. In order to provide perspective on the doses in Table 5.1, the standards for 1988 on the allowable maximum dose to an individual of the general public are given in 40CFR190 as 25 mrem whole body,75 mrem thyroid, and 25 mrem any other organ. These standards are a fraction of the normal background radiation of 280 : mrem per year and are designed to be inconsequential in regard to public health ! and safety. Since plant related doses are even a smaller fraction of natural background, they have insignificant public health consequences. In fact, the plant related doses to the maximum individual are less than 10% of the variation in natural background in Connecticut. 5-1
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6.0 DISCUSSION The evaluation of the effects of station operation on the environment requires the careful consideration of many factors. Those factors depend upon the media being effected. They include station release rates, effluent dispersion, occurrence of nuclear weapons tests, seasonal variability of fallout, local environment, and locational variability of fallout. Additional factors affecting the uptake of radionuclides in milk include soil conditions (mineral content, pH, etc.), quality of fertilization, quality of land management (e.g., irrigation), pasturing habits of , animals, and type of pasturage. Any of these factors could cause significant variations in the measured radioactivity. A failure to consider these factors could cause erroneous conclusions. Consider, for example, the problem of deciphering the effect of station releases on the radioactivity measured in milk samples. This is an important problem because this product is widely consumed and fission products readily concentrate in this media. Some of these fission products, such as 1-131 and Sr-89 are relatively short-lived. Therefore they result from either plant effluents, recent nuclear weapons tests or recent nuclear incidents (e.g. Chernobyl). Sr-89's lifetime is longer than l-131's, therefore it must be remembered that it will remain around for much longer periods of time. Problems are caused by the long-lived fission products, Sr-90 and Cs-137.These isotopes are still remaining from the high weapons testing era of the 1960's. This results in significant amounts of Sr-90 and Cs-137 appearing in milk samples. Distinguishing between this " background" of fallout activity and plant effects is a difficult problem, in reviewing the Sr-90 and Cs-137 measured in cow and goat milk in the areas around the Millstone and Haddam Neck stations, a casual observer could notice that in some car the levels of these isotopes are higher at farms closer to the station than at those further away from the stations. The stations effluents might at first appear to be responsible. However, the investigation of the following facts prove this conclusion wrong.
- 1. The stations accurately measure many fission products, including Sr-90 and Cs-137 in their releases. Based on these measurements and proven models developed by the Nuclear Regulatory Commission, concentrations in the environment can be calculated. These calculations (generally conservative, see Section 5.0) show that insufficient quantities (by more than a factor of 1000) of Sr-90 and Cs-137 have been released from the stations to yield the measured concentrations in milk.
- 2. Based on the ratio of Sr-89 to Sr-90 in the measured releases from the stations and on the similar chemical properties of the two nuclides, plant-related Sr-90 cannot be detected in milk without also detecting plant related Sr-89.
During 1981 (and a few other occassions), Sr-89 has been detected in many of the milk samples. To investigate the source of St-89, air particulate data has been evaluated. Evaluation shows that airborne Sr-89 is generally uniform at all the indicator and control locations for both the Millstone and Haddam Neck stations. Therefore it can be concluded that the Sr-89 seen in milk is from recent fallout. Similarly, the levels of airborne Sr-90 (and total Cesium) are also generally uniform at all the air sampling locations. However, with the longer half lives of these isotopes, the same conclusion cannot be made. But, plant related Sr-89 has never been detected in milk, therefore levels of Sr-90 observed must be attributable to nuclear weapon's testing. 6-1
- 3. Similar to Sr-89, Cs-134 can be used as an indication of plant related Cs-137.
Although not as conclusive as Sr-89, the lack of any measurable Cs-134 in any of the milk samples suggests that the Cs-137 is not plant related. This is further confirmed by the evaluation of the air particulate data. The only occurrences of detectable Cs-134 in milk resulted from the Chernobyl incident.
- 4. Since dairy milk sampling began in the 1960's, years prior to plant operation, the immediate station areas have always shown higher levels of weapons fallout related Sr-90 and Cs-137 (see Figures 6-1 and 6-2). The ratio of activity between the locations has not changed with plant operation. All areas show the same significant decrease in radioactivity since the 1964 Nuclear Test Ban Treaty.
- 5. Local variability of Sr-90 and Cs-137 in milk is common through-out the United States. Due to the variability in soil conditions, pasturing methods, rainfall, etc., it is the rule rather than the exception. Therefore, it is not surprising that certain farms have higher levels of radioactivity than other farms. In fact, there are some cases where the farms further from the station have higher Sr-90 and Cs-137 values than the farms that are closer to the station (e.g., see pre-1984 Haddam Neck Goat Milk data.)
- 6. The Millstone goat farm with the highest levels of Sr-90 and Cs-137 has also experienced the highest levels of short-lived activity from the 1976 and 1977 Chinese Tests and the 1986 Chernobyl accident. This indicates that for some unknown reason this farm has the ability for higher reconcentration. Special studies performed at this and other farms failed to find any link to the plant.
Based on these facts, the observation that the station effluents are responsible is obviously false. The cause must be one or more of the other variables. Northeast Utilities has carefully examined the data throughout the year and has presented in this report all cases where plant related radioactivity can be detected. An analysis of the potential exposure to the population from any plant related activity has been performed and shows that in all cases the exposure is insignificant. As in previous years, this data is being submitted to, and will be reviewed by the appropriate regulatory bodies such as the Nuclear Regulatory Commission, Environmental Protection Agency and Connecticut Department of Environmental l Protection. 1 l f i l I 6-2
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hmm_... l 1 1 i APPENDIX A COW AND GOAT CENSUS FOR 1988 l l l l l l A-1
4 DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1988 DIRECTION DISTANCE NAME AND ADDRESS NO. OF C0WS N 14 M. Arthur Lord 26 180 Jones Hellow Rd. Marlborough, CT 06447 N 15 M. Foot Hills Farm 35-Edward Foote 1126 Gilead Street RFD #2 Hebron, CT 06248 NNE 14 M. Robert K. Gasper 80 694 Gilead St. Hebron, CT 06248 NNE 14 M. Hills Farm 72 527 Gilead St. Hebron, CT 06248 NNE 14 M. Mapleleaf Farm, Inc. 185 750 Gilead St. Hebron, CT 06248 NNE 14 M. Gordon N. Rathburn 41 Martin Rd. Hebron, CT 06248 NNE 14.5 M. Douglas Porter 151 RFD #1 Hebron, CT 06248 NE 4.5 M. John Dill 23 Waterhole Rd. Colchester, CT 06415
- East Hampton -
NE 14 M. Victor Botticello 26 Levita Rd. Lebanon, CT 06249 NE 14 M. Grabbgr Brothers 48 I RFD #1-Lebanon, CT 06249 1 j ENE 6 M. Doris or Oscar Dill 48 l Beebe Rd. , East Haddam, CT 06423 l l 1 i
l; DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF AFRIL 1988 NO. OF COWS I DIRECTION )ISTANCE NAME AND ADDRESS ENE 6.5 M. Grandpa Hill Farm 54 R. S. Cone Box 251 East Haddam, CT 06423 ENE 8.1 M. William Smith 58 Town Road. Colchester,oCT 06415
- East Haddam -
ENE 11 M. Walter Swider 50 Route 85 Colchester, CT 06415 ENE 14 M. Robert Avery 30 Rathburn Hill Rd. Colchester, CT 06415
- Salem -
ENE 14.5 M. Walter Makarevich 14 Geer Rd. Lebanon, CT 06249 E 11.5 M. Wysteria Farm 45 Eugene Wilczewski Darling Rd. Salem, CT 06415 E 13 M. Anne B. Henrici 3 Catawampus Darry Round Hill Rd. Salem, CT 06415 E 13 M. Garry Vaill 45 Forsythe Rd. Salem, CT 06415 E 14 M. Stuart Gadbois 222 Route 82 Salem, CT 06415 ESE 14.5 M. Raymodd Muschinsky 25 Grassy Hill Rd. East Lyme, CT 06333 l l
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DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1988 DIRECTION . DISTANCE NAME AND ADDRESS NO. OF COWS SE 11 M. Tiffany Farms .80 Sterling City Rd. Old Lyme, CT 06371
- Lyme -
SE 12 M. J. Ely Harding 60 Ashlawn Farm Old Lyme, CT 06371
- Lyme -
SW 13 M. Thomas Haggarty 41 Hoophole Rd. Guilford, CT 06437 SW .14.5 M. Sugarloaf Fars 26 154 Beaver Head Rd. North Gu.ilford, CT 06437 WSW 8 M. Michael Dwyer 15 Route 17 Durham, CT 06492
- Wallingford -
WSW 8 M. Robert Raudat 40 Old.Durham Rd. Killingworth, CT 06417 WSW 11 M. Raymond Wimler 174 4 Guilford Rd. Durham, CT 06422 WSW 14 M. Cella Brothers 130 Whirlwind Hill 2 No. Brandford St. Wallingford, CT 06492 WSW 14 M. John Kranyak 49 1349 Whirlwind Rd. Wallingford, CT 06492 WSW 15 M. Co Ag Farm, Inc. 220 Walter. Augur & George Cooke 180 Northford Rd. Wallingford, CT 06492 l 1
.. _ - _ _ _ _ _ _ _ _ _ _ _ a
i-DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1988 DIRECTION DISTANCE NAME Af ADDRESS NO. OF COWS W 8.5 M. Richard Rowe 25 Box 4, Higganum Rd. Durham, CT 06422 I W 11.5 M. Friendly Acres Dairy Farm 29 Tony Caltabiano Parmalee Hill.Rd. Durham, CT 06422 W 12.2 M. Powder Hill Dairy Farm 189 Henry Bugai Powder Hill Rd. Durham, CT 06422 W 12.5 M. Linus Sanstrom, Jr. 32 Strickland Rd. Middlefield, CT 06455 W 14 M. North Farms 22 Walter Werbiski 1069 Farms Rd. Wallingford, CT 06492 W 14.5 M. Charles Greenback & Sons, Inc. 162 Box 451 Route 68 Durham, CT 06422 WNW 7 M. Calvin Harvey 24 55'Tryon St. Middletown, CT 06457 WNW 8 M. Richar. Brock 27 787 RI.ge Rd. Middletown, CT 06457 WNW 8 M. George Seifert 29 Kelsey St. Middletown, CT 06457 a
DAIRY COPS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1988 DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS WNW 12 M. John Kolman 40 Meriden Rd. Middletown, CT 06457 WNW 12 M. Walnut Hill Farm- 123 William & Thomas Mintz Jackson Hill Rd. Middlefield, CT 06455 WNW 15 M. Bilger Brothers 25 Hickory Grove Farr 705 Westfield Rd. Meriden, CT 06450 NW 6 M. Edward Hills 30 Brooks Rd. Middletown, CT 06457 NW 13 h. Higgins Farm, Inc. 58 837 Ridgewood Rd-Middletown, CT L,1457 NW 15 M. Wenceslaus & Jean Backiel 32 Riverside Farm RFD #2 Berlin, C5 06037
- Rocky Hill -
NW 15 M. John W. Meisterling 50 Box 385 France St. Rocky Hill, CT 060',7 NNW 1.5 M. John Kruger 25 Quarry Hill Rd. Haddam, CT 06438 NNW 13 M. Charles Matway, Est. 14 Brook St. Rocky Hill, CT 060s' NNW 14 M. Roaring Brook Farm 24 Henry'.Killam 77 Tryon St. So. Glastonbury, CT 0607.i
^
- G3artonbury -
DAIRY GOATS VITHIN 20 MILES OF CONNECTICUT YANK 3E-AS OF JUNE 1988 DIRECTION DISTANCE NAME AND ADDRESS NO. OF G04TS N 4.5 M. Philip Bourdon 6 164 Young Street East Hampton, CT 06424 N 6 M. Jackie Reardon 4 55 So. Main Street East Hampton, CT 06424 N 15 M. Joan & Thomas Kemble - 3 581 Thompson Street Glastonbury, CT 06033 NNE 12 M. Louise Sage 1 155 Reidy Hill Road Hebron, CT 06248 NNE 16 M. Joan Bowers 1 350 Vall Street Hebron, CT 06248 NNE 16 M. Kathy Waters 13 Burnt Hill Road Hebron, CT 06248 NE 16 M. Barbara Nadeau 3 Clubhouse Road Lebanon, CT 06249 NE 17 M. Lynn Miller 9 Goshen Hill Road Lebanon, CT 06249
l DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF JUNE 1988 ) l DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS NE 17 H. Sharon Sage 2 54 A Kick Hill Road Lebanon, CT I i E 12 H. Anne B. Henrici 5 Round Hill Road Salem, CT 06415 ESE 16 H.
- Ron Birchall 8 339 Boston Post Road East Lyme, CT 06333 SE 13 M. Peter LaPolla 2 Town Woods Road Old Lyme, CT 06371 S 11.5 H. Victor Trudeau 9 174 Horse Hill Road Westbrook, CT 06498 V 4.8 H. Pat Hannetho 2 Jacoby Road Higganum, CT 06441 V 14.5 H. Robert Pogomore 1 177 Villiams Road Wallingford, CT 06492 V 15.3 H. Jim & Mary Hall Petlack 11 1000 North Farms Road Vallingford, CT 06492
DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF JUNE 1988 DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS VNV 10.5 M. Roger Kinderman 2 721 Vadsworth Road Middlefield, CT 06082 VNV 19L M. Daniel Nitkowski 46 Firch Avenue Meriden, CT 06450 NW 13.2 M. Harry & Dilys McIntyre 8 104 Court Street Cromwell, CT 06416 - NW 13.5 M. The LaRoche Family 3 South Road Portland, CT 06480 NW 13.5 M. Melvin Granger 1 140 Coles Road Cromwell, CT 60106 NNU 14 M. Dorothy Joba 16 171 Ferry Lane S. Glastonbury, CT 06073 NNW 15 M. Donald Reid 10 1654 Ma'.n Street Glastonbury, CT 06033
- Unable to contact m__ ___._____-_____-m.__.m_____ __ _ _ _ _ . _ _. _ _ _ , _ . __
APPENDIX B NORTHEAST UTILITIES OA PROGRAM 1 l l i l B-1 j
Northsast Utilitiss 53rvice Company (NUSCO), acting as the agent for both the Northeast Nuclear Energy Company (NNECO) and the Connecticut Yankee Atomic Power Company (CYAPCO), maintains a quality assurance (QA) program of its primary contractor of radiological analyses, Clean Harbors, Inc., (Teledyne for H 3 in water samples). This is accomplished by the use of the three quality control methods that are specified in Radioassay Procedures for Environmental Samples, U.S. Department of Health, Education, and Welfare (January 1967). These three quality control methods are: a) Duplicate analyses of actual surveillance samples with one laboratory. This type of quality control allows an evaluation of the contractor's precision or reproducibility of results. b) Cross-check analyses of actual surveillance samples with more than one laboratory. This intercomparison allows the determination of what agreement the primary contractor has with another laboratory. c) Analyses of " spiked" samples. This type of quality control allows a check on the contractor's accuracy of results. Additional QA programs are performed, these include: 1) Clean Harbor's internal QA program,2) Clean Harbor's participation in EPA's Environmental Radioactivity Laboratory Intercomparison Studies Program, and 3) Nuclear Regulatory Commission - State of Connecticut independent Venfication Program. The number and type of QA samples are given in Table 1. In general, the objective was to obtain between 10 and 20 percent of the samples as QA samples. The results should satisfy acceptance criteria as defined in Radioassay Procedures for Environmental Samples,U.S. Department of Health, Education and Welfare (Jan.1967) and the Handbook for Analytical Quality Control in Radioanalytical Laboratories, EPA 600/7 088 (Aug.1977). Comparisons of the results to the acceptance criteria are tracked on control charts to make apparent radioanalytical trends, biases or other problem areas. During 1988, the quality control methods (b) and (c), along with participation in the EPA's intercomparison Program, indicated a problem with the primary contractor's GeLi analyses of liquid geometry samples. An accuracy review of the contractor's results to
" spiked" samples and an evaluation of their GeLi instrument calibration indicated a trend of analyses low by approximately 20%. The calibration problem was ultimately corrected and past data affected was recalculated with the new calibration data.
Problems with the primary contractor's GeLi analyses of air particulate filters were also noted beginning in February when faulty equipment was replaced. Evaluation of results indicated a trend of analyses high by approximately 30%. i B-2 1
Table 1 Number of Quality ControI* Samples Number of Number of Sample Type OC Samples Routine Samplesa,b TLDs 144 504 Milk 87 144 Well Water' 24 16 Sea Water' 2 8 River Water' 2 8 Bottom Sediment 8 26 Aquatic Flora 4 14 Fish 8 46 Shellfish 4 66 Lobster / Crab 0 16 Fruits and Vegetables 0 16 Air Particulate - Gross Beta 12 840
-lodine 12 794
- Geli 24 192
- Strontium 8 64
- An additional program is performed by the contractor a - Total for both Millstone and Connecticut Yankee b - Depends on availability c - OC breakdown does not include H-3 analysis; total number of tritium QC samples was 20 B3 L_ __
1 APPENDIX C
SUMMARY
OF EPA INTERLABORATORY COMPARISONS l C1 _ _ - __ - w
i i I EPA DATA The EPA section of the quarterly QC report is cumulative for the year. The table submitted with the last report of the year should be complete for results received and will be updated finally for results received later. Results are presented as follows: , S.D99 17 (xx) 16 13. CHAS Avg. 17 (1.0) EPA Known 17 (1.5, 2.6, 3) EPA Cr. Avg. 16 (yy, zz) (xx) - This value will be given when the precision (1 SD) of the CHAS measurement due to counting statistics is significantly different from the expected EPA precision. This should cause different spread in our results. (1.0) - Next to CHAS Avg. - This is the actual SD of the CHAS data i.e. 1 SD, 1 determination. This means that an additional single measurement should yield a result within 1 SD of the mean 66% of the time. , (1.5, 2.6, 3) Next to EPA Known - The first number is the anticipated 1 SD as decreed by the EPA. This value can be compared to the figure above to see that the CHAS precision is as expected. The second number is 3 SD of the mean which is the EPA Control Limit. If the observed mean (i.e. CHAS Avg.) differs from the known by more than this value the result is unacceptable according to the EPA criteria. The third number is the number of standard deviations that the CHAS value is from the EPA's known value. (yy, zz) - The first number is the observed 1 SD, 1 determination for all labs whose results were not decaed outliers. A significant difference between this value and the one above it indicates that the anticipated precision is not being attained by the majority of the laboratories. The second number is the number of standard deviations that the CHAS value is from the grand average. 1 l .
E i h j EPA Intercomparison Samples Gross Alpha and Beta Samnie No. Samnle Date . Sanmle Tyne Gross Aloha Gross Geta 37158 1/22/88 Water (a) 4 10 4 9
, 1 1
. Lab Avg. 4(1) 9(1) .
EPA Known 4(5,9,0) 8(5,9,0) EPA Gr. Avg. 4(2,0) 8(2,0) 8803216 3/18/88 Water (a) 6 8 5 10 i lQ f Lab Avg. 6(1) 9(1) EPA Known 6(5,9,0) 13(5,9,1) EPA Gr. Avg. 6(2,0) 13(2,-1) 8803297 3/25/88 Air Filter (b) 60 65 (Note 1) 58 65 O M Lab Avg. 60(3) 65(1) EPA Known 20(5,9,14) 50(5,9,5) EPA Gr. Avg. 23(5,13) 53(6,4) 8804184 4/24/88 Water (a) 48 8804252 45 62 Lab Avg. 47(2) EPA Known 46(11,19,0) EPA Gr. Avg. 45(12,0) 8804204 4/24/88 Water (a) 65 8804253 59
' kb.
Lab Avg. 63(3) EPA Known 57(5,9,2) EPA Gr. Avg. 58(6,2) 8805233 5/20/88 Water (a) 7 13 7 12 1 19
'ab Avg.
7(0) 12(2) r:fA Known 11(5,9,-1) 11(5,9,0) era Gr. Avg. 9(3,-1) 12(2,0) - _ _ - _ _ _ - _ - _ _ - _ _ _ _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - = _ _ - - _ _ _ _ - _ _ - _ - _ _ _ _ _ _ _ _ - - -_- - _ ___ - - - -__- ____
EPA Intercomparison Samples Gross Alpha and Beta (Continued) Samnle No. Samnle Date Samnle-Tyne Gross Alnha- Gross Beta 8807192 7/22/88 Water (a) 14 5 14 5 11 1 Lab Avg. 13(2) 5(0) EPA Known 15(5,9,-1) 4(5,9,0) EPA Gr. Avg. 12(3,0) 6(2,0) 8808301 8/26/88 Air Filter (b)- 9 1010 (Nota 10) 8 970 1 12Q2 Lab Avg. 9(1) 990(20) EPA Known 8(5,9,0) 29(5,9,334) EPA Gr. Avg. 9(2,0) 29(4,331) 8809241 9/23/88 Water (a) 7 10 9 12 2 12 Lab Avg. 8(1) 11(1) EPA Known 8(5,9,0) 10(5,9,0) EPA Gr. Avg. 8(2,0) 10(2,0) 8810192 10/18/88 Water (a) 43 43 M Lab Avg. 44(2) EPA Known 41(10,17,1) EPA Gr. Avg. 39(9,1) 8810193 10/18/88 Water (a) 54 53 11 Lab Avg. 53(1) EPA Known 54(5,9,0) EPA Gr. Avg. 50(6,1) 8811281 11/25/88 Water (a) 8 7 10 9 l 2 2 Lab Avg. 9(1) 8(1) EPA Known 9(5,9,0) 9(5,9,0) EPA Gr. Avg. 9(2,0) 10(2,0) Note: (a) pGi/1 (b) pCi/ filter
EPA Intercomparison Samples Gamma Samole No. Samole Date Samole Tvoe 8802093 02/05/88 Water (Note 2) Nuclide (pci/1) 72* Nuclide (pCi/1) 60* Cs-137 82 Co-60 64 11 H Lab Avg. 77*(5*) Lab Avg. 60*(4*) EPA Known 94(5,9,-6*) EPA Known 69(5,9,-3*) EPA Gr. Avg. 94(6,-6) EPA Gr. Avg. 69(5,-4) Nuclide (pci/1) 82* Nuclide (pCi/1) 49(50**) Zn-65 88 Ru-106 88(52**) 2). 42(52**) Lab Avg. 81*(8*) Lab Avg. 60(25) EPA Known 94(9,16,-3*) EPA Known 105(11,19,-7) EPA Gr. Avg. 96(7,-4) EPA Gr. Avg. 100(13,-7) Nuclide (pCi/1) 43* Cs-134 60 E Lab Avg. 53*(9*) EPA Known 64(5,9,-4*) EPA Gr. Avg. 61(5,-3) Note: * - These values reflect our recalculated values not our reported values.
** - Two sigma standard deviations.
i
L EPA Intercomparison Samples i Gamma (Continued) l Samnie No. Samnie Date Samnie Tygg 37164 1/29/88 Food (Note 8) Nuclide (pci/kg) 91 Nuclide (pci/kg) 90 I-131 106 Cs-137 103 . j 122 19Q 1 Lab Avg. 105(15) Lab Avg. 98(7) EPA Known 102(10,17,1) EPA Known 91(5,9,2) EPA Gr. Avg. 99(8,1) EPA Gr. Avg. 91(7,2) Nuclide (ag/kg) 1586 4 K ,4,.2 1563 lila Lab Avg. 1523(90) EPA Known 1230(62,107,8) EPA Gr. Avg. 1218(122,9) 8803297 3/25/88 Air Filter Nuclide (pCi/ filter) , Cs-137 18 20 12 Lab Avg. 19(1) EPA Known 16(5,9,1) EPA Gr. Avg. 18(3,1) 8804204 4/24/88 Water 8804253 Nuclide (pci/1) 52 Nuclide (pCi/1) 6 Co-60 54 Cs-134 7 11 1 Lab Avg. 52(2) Lab Avg. 6(1) EPA Known 50(5,9,1) EPA Known 7(5,9,0) EPA Gr. Avg. 51(4,1) EPA Gr. Avg. 7(2,0) Nuclide (pCi/1) Cs-131 7 7 k Lab Avg. 7(1) EPA Known 7(5,9,0) EPA Gr. Avg. S(2,0)
i.' E l EPA Intercomparison Samples Gamma (Continued) Samnle No. Samnie Date Samnle Tvoe q
?
8806033 6/3/88 Water (Note 4)' Nuclide (pCi/1) 294 Nuclide (pCi/1) 15
.01..11 249 fdt-6.Q 15 22.0 11 .
Lab Avg. 271(23) Lab Avg. 15(0) EPA Known 302(30,52,-2) EPA Known 15(5,9,0) EPA Gr. Avg. 205(32,-2) EPA Gr. Avg. 16(2,0) Nuclide (pCi/1) 92 Nuclide (pci/1) 160 Zn.f.1 97 Ru-106 169 11 lift Lab Avg. 95(3) Lab Avg. 161(8) EPA Known 101(10,17,-1) EPA Known 195(20,35,-3) EPA Gr.' Avg. 103(7,-1) EPA Gr.-Avg. 191(16,-3) Nuclide (pci/1) 15 Nuclide (pci/1) 22 Cs-134 15 Cs-137 25
- 16. 21' Lab Avg. 15(1) Lab Avg. 23(2)
EPA Known 20(5,9,-2) EPA Known '25(5,9,-1) EPA Gr. Avg. 19(2,-1) EPA Gr. Avg. 26(3,-1) 8806257 6/24/88 Milk Nuclide (pci/1) 46 Nuclide (mg/1) 1537 Cs-137 54 ]L-4Q 1615 il 15f.1 Lab Avg. 52(6) Lab Avg. 1606(65) EPA Known 51(5,9,0) EPA Known 1600(80,139,0) EPA Gr. Avg. 52(4,0) EPA Gr. Avg. 1589(138,0) D
i:t EPA Intercomparison Samples Camma (Continued) Samnie No. Samnie Date Samnie Tvoc , 8808028 7/29/88 Food Nuclide(pCi/kg) 96 Nuclide(pci/kg) 47 , I-131 86 Cs-137 45 191 4Z Lab Avg. 95(9) Lab Avg. 45(3) EPA Known 107(11,19.-2) EPA Known 49(5,9,-2) EPA Cr. Avg. 108(8,3) EPA Cr. Avg. 48(3,-2) Nuclide(ag/kg) 1258 K-40 1267 1291 Lab Avg. 1243(34) i EPA Known 1240(62,107,0) EPA Gr. Avg. 1225(50,1) 8808301 8/26/88 Air Filter Nuclide pCi/ filter 16 , Cs-137 19 22 Lab Avg. 19(3) EPA Known 12(5,9,2) EPA Gr. Avg. 13(3,2)
I l l L EPA Intercomparison Samples l Gamma (Continued) 1 Sm-nle No. Sa=nle Date Samnle Tvoe 8810082 10/07/88 Water. (Note 11) Nuclide (pci/1) 186 "Nuclide(pCi/1 22 . Cr-51 201 Co-60 22 M 11 Lab Avg. 195(8) Lab Avg. 23(2) EPA Known 251(25,43,-4) EPA Known z5(5,9,-1) EPA Gr. Avg. 249(24,-4) EPA Gr. Avg. 26(2,-1) Nuclide (pci/1) 135 Nuclide (pci/1) 113 2n-65 132 Ru-106 104 116. 121 Lab Avg. 134(2) Lab Avg. 116(14) EPA Known 151(15,26,-2) EPA Known 152(15,26,-4) EPA Gr. Avg. 152(9,-2) EPA Gr. Avg. 144(18,-3) Nuclide (pci/1) 20 Nuclide (pCi/1) 12 Cs-134 20 Cs-137 13 22 14 Lab Avg. 20(0) Lab Avg. '13(1) EPA Known 25(5,9,-2) EPA Known 15(5,9,-1) EPA Gr. Avg. 24(2,-1) EPA Gr. Avg. 16(2,-1)
s'
,.I'.
EPA Intercomparison Samples Gamma (Continued) Sample No. Sample Data Sample Type 8810193: 10/18/88 Water
- i. .
Nuclide(pci/1)' 13 Nuclide(pci/1) 13 Cs-134 11 Cs-137 13 11 h Lab Avg. 12(1) Lab Avg. 13(1) EPA Known 15(5,9,-1) EPA Known 15(5,9,-1)
' EPA Gr. Avg. 14(2,-1) EPA Gr. Avg. 16(2,-1)
, 8810261 10/28/88 Milk (Note 15)- t, Nuclide(pci/1) 40 Nuclide(mg/1) 1610 Cs-137 42 M 1510
.M ' J.D.
Lab Avg. 42(2) 14b Avg. . '.*(60) EPA Known 50(5,9,-3) EPA Known '80,140,-1) EPA Gr. Avg. 50(4,-3) EPA Gr. Avg. 10 00,-1)
EPA Intercomparison Samples I-131 (pGi/1) Samnle No. Sanmle Date Sanmle Tvoe M 8802312 2/26/88 Milk 4 Lab Avg. -4(0) EPA Known 4(0,1,0) EPA Gr. Avg. 4(1,-1) 8804070 3/8/88 Water 8 9 i Lab Avg. 9(1) EPA Known 8(1,2,3) l EPA Gr. Avg. 8(1,3) 8806257 6/24/88 Milk 107 (Note 5) 106 10.6 Lab Avg. 106(1) EPA Known 94(9,16,2) EPA Gr. Avg. 96(9,2) 8808087 8/05/88 Water
- 83 (Note 12) 88 3.1 Lab Avg. 85(3)
EPA Known 76(8,14,2) EPA Gr. Avg. 77(8,2) , 8810261 10/28/88 Milk 66 (Note 16) 69 bl Lab Avg. 66(4) EPA Known 91(9,16,-5) EPA Gr. Avg. 90(8,-5) 8812089 12/09/88 Water 97 (Note 17) 91 11 Lab Avg. 91(6) EPA Known 115(12,21,-3) EPA Gr. Avg. 116(14,-3) l l
1 l l l i EPA Intercomparison Samples Ra-226 and Ra-228(pGi/1) l Samole No. Samole Date Samole Tvoe Ra-226 Ba-228 l 8803127 3/11/88 Water 6.0 9.6 4.1 7.6 ! M M Lab Avg. 6.1(2.0) 8.5(1.0) EPA Known 7.6(1.1,2.0,2.3) 7.7(1,2,2.0,1.2) EPA Gr. Avg. 7.2(1.1,-1.7) 7.6(1.7,1.4) 8804184 4/24/88 Water 3.0 3.9 8804252 3.9 4.2 (Note 6) L2 M Lab Avg. 3.7(.6) 4.5(.7) EPA Known 6.4(1.0,1.7,-4.9) 5.6( 8,1.5,-2.3) EPA Gr. Avg. 6.0(.9,-4.2) 5.7(1.2,-2.5) 8806194 6/17/88 Water 11.2 14.6 (Note 7) 10.1 17.5 Ll lb.2. Lab Avg. 10.3(.8) 14.7(2.8) EPA Known 10.0(1.5,2.6,.4) 12.4(1.9,3.2,2.1) EPA Gr. Avg. 9.8(1.5,.6) 11.6(2.3,2.9) 8809178 9/16/88 Water 4.5 8.1 (Note 13) 4.5 14.6 L.f. 14J Lab Avg. 4.6(.2) 12.2(3.6) EPA Known 8.4(1.3,2,3,-5.0) 5.4(.8,1.4,14.8) EPA Gr. Avg. 7.8(1.4,-4.2) 5.6(1.2,14.2) 8810192 10/18/88 Water 4.2 2.9 (Note 18) 3.3 2.9 M 2d Lab Avg. 3.8(.5) 2.9(0.0) EPA Known 5.0(.8,1.4,-2.7) 5.2(.8,1.4,-5.0) EPA Gr. Avg. 4.9(.5,-2,4) 5.3(.9,-5.3) 8812143 12/16/88 Water 2.0 13.1 (Note 19) 1.6 14.1
.Ll lL9 Lab Avg. 1.6(.4) 14.4(1.4)
EPA Known 3.5(.9,1.6) 10.3(2.6,4.5) l l l 1 -
EPA Intercomparison Samples Sr-89 and Sr-90 Sm= ale No. Samnle Date Samnle Tyne Sr-89 Er.-1Q 37164 1/29/88 Food (c) 52 53
.(Note 8) 38 60 M E Lab Avg. 45(5) 50(12)-
EPA Known 46(5,9,0) 55(3,5,-3) , EPA Gr. Avg. 42(12,1) 53(6,-2) 8801055 1/8/88 Water (a) 33 13 36 15 12 11 Lab Avg. 36(3) 14(1) EPA Known 30(5,9,2) 15(2,3,-1) EPA Gr. Avg. 28(6,3) 14(2,0) 8803297 3/25/88 Air Filter (b) 23-(Note 9) 16 21 Lab Avg. 21(5) EPA Known 17(2,3,5) EPA Gr. Avg. 17(2,5) 8804204 4/24/88 Water (a) 6 5 8804253 5 6 4 k Lab Avg. 5(1) 6(1) EPA Known 5(5,9,0) 5(2,3,1) EPA Gr. Avg. 6(2,0) 5(1,1) 8805104 5/6/88 Water (a) 30 22 27 21 2.Q 22 Lab Avg. 26(5) 22(1) EPA Known 20(5,9,2) 20(2,3,2) EPA Gr. Avg. 19(6,2) 18(4,4) 8806257 6/24/88 Milk (a) 39 62 (Note 3) M 11 Lab Avg. 44(6) 64(2) EPA Known 40(5,9,-1) 60(3,5,2) EPA Gr. Avg. 34(12) 56(10)
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EPA Intercomparison Samples 1 Sr-89 and Sr-90 (Continued) I Samnle No. Samnie Date Samnie Tyne jr,- $j, gy,-1Q 8808028 7/29/88 Food (c) 45 36 (Note 14) 26 44 l M 42 l Lab Avg. 35(10) 42(6) I d EPA Known 33(5,9,1) 34(2,3,7) EPA Gr. Avg. 26(11,3) 31(6,9) 8808301 8/26/88 Air Filter (b) 7 7 B. Lab Avg. 7(1) EPA Known 8(2,3.-1) EPA Gr. Avg. 8(2,-1) 8810193 10/18/88 Water (a) 14 13 (Note 20) 15 .11 12 12 Lab Avg. 14(2) 12(1) 1 EPA Known 11(5,9,1) 10(2,3,2) EPA Gr. Avg. 10(3,1) 9(1,3) 8810261 10/28/88 Milk (a) 69 '77 (Note 21) 74 66 11 11
. Lab Avg. 73(3) 67(9)
EPA Known 40(5,9,11) 60(3,5,4) EPA Gr. Avg. 32(12,14) 56(6,7) Note: (a) pCi/1 (b) pCi/ filter (c) pCi/kg l t l
EPA Intercomparison Samples Tritium
. Samnie Nom Samnie Date Samnie Tyne Tritium (nCi/1) 8802152 2/12/88 Water 3430 3540 1ZiQ Lab Avg. 3570(160)
EPA Known 3330(360,630,1) EPA Gr. Avg. 3360(340,1) 8806108 6/10/88 Water 5100 4900 1Q9.Q Lab Avg. 5000(100) EPA Known 5570(560,960,-2) EPA Gr. Avg. 5390(500,1) 8810142 10/14/88 Water 2080 2010 IQ1Q Lab Avg. 2030(40) EPA Known 2320(350,610,-1) EPA Gr. Avg. 2320'(240,-1) l l
._._m_____._ _ _ . _ _ _ _ _
EPA Intercomparison Samples Uranium (pCi/1) Sample No. Sample Date Sample Tvoe Uranium (oCi/1) 8804184 04/24/88 Water 3 8804252 3 1 Lab Avg. 3(0) EPA Known 6(6,10,-1) EPA Gr. Avg. 6(2,-1) 8810192 10/18/88 Water 5 5 1 Lab Avg. 5(0) EPA Known 5(6,10,0) EPA Gr. Avg. 0(2,0) l i i I l l i
NOTES:
- 1. The air filter results were outside the acceptance criteria for alpha and beta. The raw data was checked and recalculated for the alpha and the beta; all input data were correct. The beta rerun shows data concurring with the original data. The-results for alpha and beta were outside the acceptance criteria for no apparent reason.
- 2. .The water GeLi (2/5/88) was outside the acceptance criteria for all the nuclides.
8802093A was recalculated, and Cs-134, Cs-137, and Ru-106 were out of acceptance. The Cs values were out for no apparent reason but the problem is not genenc. Ru-106 was recalculated with the correction factor (see Note 11) with the following results: Nuclide pCi/1 60162** Ru-106 109 1 64** 52164** Lab Avg. 74 131** EPA Known 105(11,19) The recalculated values 125D are within the EPA results. 3 .' Table of Results: Sr-89 Sr-90 EPA 40 ! 5 60 3 CHAS Repoded 103 45 CHAS Reponed 119 50 CHAS Reponed Not Reponed 55 880625701AR 11916 28.6 t .7 880625701B 10314 28.3 1.7 880625701C 21 1 3 29.4 t .8 880625701D 39 11 62 2 Recalculated C 4817 65 2 Sample 8806257-01C recalculated and 880625701D were acceptable results. However, samples AR and B were not acceptable and review of the raw data, calculations, and counting data indicated no problems.
* *Two sigma standard deviations
i s
- 4. Ru 106 was recalculated with the Ru-106 correction factor (See Note 11):
208
. 219 I
200 Lab Avg. 209 1 19** Recalculated results are within two standards deviations of the EPA result. I
- 5. The raw data, calculations and counting data indicated no problems. i
- 6. Ra-226 result was low in compariso'n with the true result. The Ra-226 results will be watched for a trend in low spike recoveries. The new data calculations and counting data for Ra-228 indicated no problems. i 1
- 7. The raw data, calculations and counting data for Ra-228 indicated no problems.
8.' The food results were outside the acceptance criteria for Sr-90 and K-40. Sr-90 had yield problems due to the sample type. K-40 was biased high due to non-homogeneous sample. A letter was sent to the EPA asking how best to deal with . this type of sample.
- 9. Low Sr chemical yields appear to be responsible for reported Sr-90 values which were outside the acceptance criteria. A different type of filter from that used for contract samples was used which may have contributed to the low Sr yield.
- 10. The air filters were out for beta because of a problem with the data flex calculation program. The program converts the aliquot for air particulate from ft3 to m3 which is correct for contract samples. The program was changed so that if the sample type is AP and aliquot = 1, then the aliquot will not be converted. The air filters were recalculated on the old Apple beta program and on the corrected data flex program with the following results:
Apple 28.611.5 IBM 28.611.5 Basic 27.4 1.4 Data flex 27.411.4 28 'i 2 28 12
- 11. The water GeLi' was out for Ru-106 and Cr-51. Because Ru-106 has been consistently low, a Di spiked with Ru-106 was run. From this result and previous EPA results, a correction factor for Ru-106 was calculated. Water -GeLi (10-07-88) was recalculated using the Ru-106 correction factor to give the following results:
Nuclide pCi/1 146 ! 34** Ru-106 134 34** 170 1 35** Avg. 150 37 Cr-51 was recalculated after the GeLi recalibration with the following results: Nuclide pCi/1 244 135** ' Cr-51 229 ! 36** 227 37** Lab Avg. 233 1 10 l The recalculated Cr-51 results are within the EPA limits.
*
- Two sigma standard deviations.
1 l
- 12. 1-131 was checked for error. Results were recalculated with new efficiencies from LLB calibration.- Recalculated results are within two standard deviations of the EPA known.
i Nuclide pCi/1 70 1-131 72 69 4 ' 1 Avg. 75 3**
- 13. The results were outside the acceptance criteria for both Ra-226 and Ra-228.
Review of counting data and calculations indicated no problem. An investigation into possible problems in chemistry is underway.
- 14. Food results were outside the acceptance criteria for'5r-90. A review of the raw data, counting data, and calculations indicated no problems other than possible non-homogeneity of this sample type.
- 15. Cs-137 was checked for error. A review of the counting data and calculations-indicated no problems.
- 16. Low l-131 results are currently under investigation. Calibration for I-131 on the low level beta counters will be rerun.
- 17. Low l-131 results are currently under investigation. The calibration for I-131 on the low level beta counters will be rerun.
- 18. Ra-226 was checked for error. Review of raw data, counting data, and calculations indicated no problems. Ra-228 is outside the acceptance criteria. . Raw data, counting data, and calculations were reviewed and no problems were found. Ra-228's will be counted for 900 minutes to improve the counting statistics.
- 19. Because of computer problems at EPA, statistics for 8812143 are not available at this time.
- 20. Check of raw data, counting data, and calculations indicated no problems.
- 21. Sr-89 and Sr 90 were outside the acceptance limits because of possible problems in chemistry and low Sr yields.
- 22. The GeLi has been recalibrates and new efficiencies have been calculated.
*
- Two sigma standard deviations.
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