B13206, Point Site Radiological Environ Monitoring Program,Annual Radiological Environ Operating Rept 1988
| ML20245E849 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/31/1988 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES, NORTHEAST UTILITIES SERVICE CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B13206, NUDOCS 8905020166 | |
| Download: ML20245E849 (131) | |
Text
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, (203) 665-5000 April 25, 1989 Docket Nos. 50-245 50-331 50-423 B13206 P.e: 10CFR50.4(b)(1)
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen: Millstone Nuclear Power Station, Unit Nos.1, 2, and 3 Annual Radiological Environmental Operatina Report In accordance with the requirements of the Millstone Nuclear Power Station Radiological Effluent Monitoring Manual, an implementing document of the Millstone Unit 11os.1, 2 and 3 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, , NORTHEAST NUCLEAR ENERGY COMPANY M e E. f. tWofzRa # ~ Se'nior Vice President cc: W. T. Russell, Region I Administrator M. L. Boyle, NRC Project Manager, Millstone Unit No. 1 G. S. Vissing, NRC Project Manager, Millstone Unit No.2 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 1 \ l
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. (203) 665-5000 April 25, 1989 I Docket Nos. 50-245 l-M 1H 50-423 813206 Re: 10CFR50.4(b)(1)
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen: Millstone Nuclear Power Station, Unit Nos.1, 2, and 3 Annual Radiological Environmental Ooeratina Reoort In accordance with the requirements of the Millstone Nuclear Power Station Radiological Effluent Monitoring Manual, an implementing document of the Millstone Unit Nos.1, 2 and 3 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, NORTHEAST NUCLEAR ENERGY COMPANY H 4A/ E.f. Hro6zlia f Sehior Vice President cc: W. T. Russell, Region I Administrator M. L. Boyle, NRC Project Manager, Millstone Unit No. 1 G. S. Vissing, NRC Project Manager, Millstone Unit No.2 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 l
, 1 MILLSTONE POINT SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERA'ii JG REPORT PERIOD JANUARY 1,1988 - DECEMBER 31,1983 MILLSTONE UNIT 1, DOCKET NO.,50-245 MILLSTONE UNIT 2, DOCKET NO. 50 336 ,
MILLSTONE UNIT 3, DOCKET NO. 50-423 PREPARtQ FOR THE NORTHEAST NUCLEAR ENERGY COMPANY l HARTFORD, CONNECTICUT I BY THE NORTHEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT
.- .A
.T. ABLE OF CONTENTS Paae No..
1.0 S u m m a ry . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . ................. 1-1 l 1 2.0 Prog ram Description . . . . . . . . . . . . . . . . . . . . . ...... . ..... . 2-1 l 2.1 Sampling Schedule and Locations . . . . . . . . . . . . . . . . . . . . . . ....... 2-1 2.2 Samples Collected During Report Period . . . . . . . . . . . . . . . . . . . . . . . 2-8 3.0 Radiochemical Results . . . . . . . . . . . . . . . . . . . . . . . .... .. ... ..... 3-1 3.1 Summary Table ...................... ......... . ........ .... 3-1 3.2 D a ta Ta b l es . . . . . . . . . . . . . . . . . . . . . . . ....... . .. . ...... 3-19 4.0 Discussion of Results . . . . . . . . . . . . . . . . .. .. . .......... .. 4-1 S.0 Offsite Dose Equivalent Commitments . .. ........... .. .... 5-1 60 Discussion .. ... ................ .. . .. . . .... ... 6-1 Appendix A - Cow and Goat Census for 1988 ... ...... .. ...... ...... A-1 Appendix B - QA Program . .. .. ... .. . .. . . ... . ..... ..... B-1 Appendix C-Summary of EPA hterlaboratory Comparisons . . . . ... . . C-1 Appendix D - Skyshine Surveys . . . . . . . . . . . . . . . . . . . . . . .... ......... D-1 4 9 z=_--___-__-______- _ _ _ _ _ _ .
, a 1.0
SUMMARY
The radiological environmental monitoring program for the Millstone Nuclear Power Station was continued for the period January through December 1988, in compliance with the Radiological Effluent Monitoring and Offsite Dose Calculation Manual. This annual report was prepared for the Northeast Nuclear Energy Company (NNECO) by the Radiological Assessment Branch of the Northeast Utilities Service Company (NUSCO). Gamma exposure measurements were performed by NUSCO and tritium analyses were performed by Teledyne isotopes, Inc. All the remaining analyses were performed by Clean Harbors, Inc. Teledyne isotopes, Inc. was used as an independent check on the primary cc atractor's laboratory as part of the overall quality assurance program. Sampling and radiological analyses were performed with gamma exposure measuring devices and on air particulate and iodine, milk, pasture grass, broad leaf vegetation, fruits, vegetables, seawater, bottom sediment, aquatic flora, finfish, mussels, oysters, clams, scallops, lobsters, and crabs. In evaluating the results of these analyses it is necessary to consider the variability of radionuclides uptake in environmental media. This variability is dependent on many factors, including plant release rates, seasonal variability of fallout, locational 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,except for oyster results, was that from nonplant (not Millstone) sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. In the case of the terrestrial media, the effect from Unit 1 via the direct dose pathway (i.e., scattered radiation, "skyshine', from nitrogen-16 in the turbine building; unique to Boiling Water Reactors) exists in the gamma exposure measurements at some of the onsite locations. Based upon past years, this effect can normally be seen by a decrease in the thermoluminescent dosimeter (TLD) values during months when Unit 1 is shutdown for refueling. Skyshine's direct dose pathway decreases rapidly with distance, to levels that are undetectable at the offsite locations. The gaseous releases have been reduced such that they are no longer detectable by TLD's at any onsite or offsite location. Gaseous releases of iodine were also very low, such that it was not detectable in milk at the nearest offsite goat location. Monitoring of the aquatic environment in the area of the discharge indicated the < presence of the following plant related radionuclides: manganese-54, cobalt-58 and cobalt-60 in aquatic flora; manganese-54, cobalt-58, iron-59, cobalt-60, zinc-65, ruthenium-106, and silver-110m in fish; manganese-54, cobalt-58 and cobalt-60 in mussels; manganese-54, cobalt-58, cobalt-60, zinc-65, ruthenium-106, and silver-110m in oysters; cobalt-58, cobalt-60, zinc-65, and silver-110m in clams; manganese-54, cobalt-58, cobalt-60, and silver-110m in scallops; and manganese-54, cobalt-58, cobalt-60 and silver-110m in lobsters. The levels of these radionuclides are comparable to last year's levels but are higher than the levels observed for the previous seven years. Generally, releases were greater in 1987 and 1988. However, doses from the measured levels are still well below those required by each Unit's Safety Technical Specifications (10CFR50 Appendix 7, Design Guidelines). All activity levels were below those of the higher discharge period of 1974-1975 (before the Unit 1 augmented liquid radwaste treatment system). 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 l 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 l 11 l l
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 and strontium-90 were detected prior to initial plant operation. The radiation dose (dose equivalent commitment) to the general public from the plant's discharges has been evaluated by two methods. One method utilizes the measured station's dkharges and conservative transport models and the other 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 3.4 millirem and the average dose to a member of thG public residing within 50 miles of the plant is 0.00034 millirem. These doses are 13.6 percent and 0.0014 percent of the standards as set by the Environmental Protection Agency on the maximum allowable dose to an individual of the general public. These standards are a small fraction (less than 70 percent) of the 280 mrem per year normal background radiation and are designed to be inconsequential in 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 1-2 < l
- a. .. ,.
' 2.0 ~ PROGRAM DESCRIPTION
- -- 2.1 Samplina Schedule and Locations The sample locations and the sample types and frequency of analysis are given in Table 2-1 and 2-2 and figures 2.1 and 2.2. The pregram as described here includes both required samples as specified in the Radiological Effluent
' Monitoring and Offsite Dose Calculation Manual and any extra samples, 2-1
TABLE 2-1 1 ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS The following lists the environmental sampling locations and the types of samples obtained at each location. Location Direction & Distance From Release Point" Number Name Sample Types 1 -l
- On-site- Old Millstone Rd. 0.6 Mi, NNW TLD, Air Particulate, lodine, Vegetation 2-1 On-site - Weather Shack 0.3 Mi,5 TLD, Air Particulate, lodine 3-1 On-site- Bird Sanctuary 0.3 Mi, NE TLD, Air Particulate, lodine 4-1 On-site- Albacore Drive 1.0 Mi, N TLD, Air Particulate, lodine 5-l Floating Barge 0.2 Mi, SSE TLD l 6-1 Quarry Discharge 0.3 Mi, SSE TLD 7-l Fox island 0.3 Mi, SE TLD 8-l Environmental Lab 0.3 Mi, SE TLD 9-1 Bay Point Beach 0.4 Mi, W TLD 10 1 Pleasure Beach 1.2 Mi, E TLD, Air Particulate, lodine 11-l New London Country 1.6 Mi, ENE TLD, Air P rticulate, lodine Club 12-C Fisher's Island, NY 8.7 Mi, ESE TLD, Air Particulate 12-X Fisher's Island, NY 8.7 Mi, ESE Aquatic Species 13-C Mystic, CT 11.5 Mi, ENE TLD 14-C Ledyard, CT 12.0 Mi, NE TLD 15-C Montville, CT 14.0 Mi, N TLD, Air Particulate, lodine 16-C Old Lyme, CT 8.8 Mi, W TLD 17-l Site Boundary 0.5 Mi, N E Vegetation 18-l New London Country 1.6 Mi, ENE Vegetation Club 19-1 Cow Location #1 6.0 Mi, N Milk (7.0 Mi, N) 20-1 Cow Location #2 9.5 Mi, WNW Milk 21-1 Cow Location #3 13.0 Mi,ENE Milk 22-C Cow Location #4 16.0 Mi, NNW Milk 23-l Goat Location #1 2.0 Mi, ENE Milk 24-C Goat Location #2 14.0 Mi, NE Milk 25-1 Fruits & Vegetables Within 10 Miles Vegetation 26-C Fruits & Vegetables Beyond 10 Miles Vegetation 27-1 Niantic 1.7 Mi, WNW TLD, Air Particulate, lodine 28-l Two Tree Island 0.8 Mi, SSE Mussels 29-l West Jordan Cove 0.4 Mi, NNE Clams 29-X West Jordan Cove O A Mi, NNb Fucus 30-C Golden Spur 4.7 Mi, NNW Bottom Sediment 31-l Niantic Shoals 1.8 Mi, NW Bottom Sediment. Oysters, Scallops 1.5 Mi, NNW Mussels 2-2
.- 3 TABLE 2-1 (Cont'd) l Direction & Distance From -
Number Name Release Point" Sample Types p 31-X Niant ic Shoals 1.8 Mi, NW Fucus L 32-l Vicinity of Discharge Bottom Sediment, Oysters, Lobster, Fish, Seawater i 32-X Vicinityof Discharge Fucus, Mussels 33-1 Seaside Point 1.8 Mi, ESE Bottom Sediment l 33-X- Seaside Point 1.8 Mi, ESE Fucus ) 34-1 Thaws River Yacht Club 4.0 Mi, ENE Bottom Sediment 1- 34-X Thames River Yacht Club 4.0 Mi, ENE Oysters 35-1 Niantic Bay 0.3 Mi, WNW Lobster, Fish 36-1 Black Point 3.0 Mi, WSW Bottom Sediment, Oysters 36-X Black Point 3.0 Mi, WSW Fucus 37-C Giant's Neck 3.5 Mi, WSW Bottom Sediment, Oysters, Lobster, Seawater 37 X Giant's Neck 3.5 Mi, WSW Fucus 38-l Waterford Shellfish Bed #1 1 Mi, NW Clams 39-X Jordon Cove Bar 0.B Mi, NE Clams 40-X Quarry Fish, Oysters, Crabs, Seawater 41-X Upper Jordon Cove 1.2 Mi, NE Mussels 50-X Myrock Avenue 3.2 Mi, ENE TLD 54-X Billow Road 2.4 Mi, WSW TLD 55-X Black Point 2.6 Mi, SW TLD
*l = Indicator C - Control X - Extra - nonrequired sample
**For terrestial locations, this is the MP1 stack, for aquatic it is the quarry cut.
2-3
TABLE 2-2 MILLSTONE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling & Exposure Pathway Number of Collection and/or Sample Locations Frecuency Tyc>e & Frecuency of Analysis
- 10. Gamma Dose- Gamma Dose - Month /y i 17 Monthly Environmental TLD b 1b. Gamma Dose- 22 Quarterly (a) N/A(a)
Accident TLD
- 2. Airborne Particulate 8 Continuous sampler - Gross Beta Weekly weekly filterchange Gamma Spectrum - Monthly on composite (by location), & on individucI sample if gross beta is greater than 10 times the mean of the weeky control stations gross beta results
- 3. Airborne lodine 8 Continuous sampler -
1-131 - WeeHy weekly canistarchange
- 4. Vegetation S One s9mple near middle Gamma Isotopic on each sample
& one near end of "owing season S. Milk 6 Monthly for all animals Gamma Isotopic,1-131, Sr-89 & Sr-90 on each except semimonthly for sample goats when on pasture
- 6. Sea Water 2 Quarterly Composite Quarterly - Fractional Beta, Gamma Isotopic, of 6 ~ Weekly Grab Tritium on each composite samples
- 7. Bottom Sediment 7 Semiannual Gamma Isotopic on each sample
- 8. Fin Fish-Flounder and 2 Quarterly Gamma Isotopic on each sample one other type of edible fin fish
- 9. Mussels 2 Quarterly Gamma Isotopic on each sample
- 10. Oysters 4 Quarterly Gamma Isotopic on each sample
- 11. Clams 2 Quarterly Gamma Isotopic on each sample i
- 12. Lobster 3 Quarterly Gamma Isotopic on each sample
. (a) Accident monitoring TLDs to be dedosed at least quarterly 2-4
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i 2.2 Samples Collected Durina Report Period The following table summarizes the number of samples of each type collected dunng the present reporting period: Sample Type Number of Number of Required Samples Extra Samples Gamma Exposure (TLD) 204 36 Air Particulate 424 46 Air lodine 424 0 Dairy Milk 48 0 Goat Milk 27 0 Fruit & Vegetables 8 0 Broad Leaf Vegetation 6 0 Seawater 8 0 . Bottom Sediment 14 0 Aquatic Flora 0 14 Fish 16 6 Mussels 8 6 Oysters 16 8 Clams 8 4 Scallops 0 4 Lobster 12 2 Crab 0 2 Total All Types 1,223 128 l 2-8
' 3.0 RADIOCHEMICAL RESULTS '
3.1 Summary Table in accordance with the Radiological Effluent Monitoring Manual (REMM), Section F.1, a summary table of the radiochemical results las been prepared and is presented in Table 3-f. In the determination of the mean,the data was handled as recommended by .; Health and Safety Laboratory, Idaho: all valid data, including negative values and zeroes were used in the determination of the mean (see Part3.2). A more detailed analysis of the data is given in Section 4.0 where a discussion of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of such an approach. 1 i
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I FOOTNOTES l , A. For Ge(Li) measurements the MDL's = LLD/2.33. For all others, MDL = 2 x a background. These MDL's are based on the absence of large arnounts of interfering activity (excluding naturaly occurring radionuclides). Deviations by 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 J 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 (4 A t) where LLD is the lower limit of detectior as defined above (as pCi per unit mass or volume) sb is the standard deviation of the background counting rate or of I 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 poster!ori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routiae 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 identifieci and described in the Annual Radiological EnvironmentalOperating Report. l 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. 3-17 L____________________________
. . , / .e .
FOOTNOTES (Cont'd) ' f D: First number is the number of indicator measurements, the second is the number
, ' of control measurements.-
E. -~ Assuming 270 m3/ paper -
. F. Assuming 1080 m 3
" G. LLD for leafy vegetables.
H. Reduce LLO by a factor of two if the fractional beta for the sample exceeds 15 pCi/l. I. LLD from the end of the sample period. l
.j s
3-18
3.2 DStm Tcbits The data reported in this section are stricti counting statistics. The reported error is two times the standard deviation o. 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 (N,DL) are statistically valid pieces of data. For the purposes of this report,in order to indicate any background 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 1-131
- 4. Air Particulate, Monthly Quantitative Gamma Spectra
- 5. Air Particulate, Quarterly Strontium -
- 6. Scil *
- 7. Milk - Dairy Farms
- 8. Milk - Goat Fanns
- 9. Pasture Grass *
- 10. Well Water *
- 11. Reservoir Water *
- 12. Fruits & Vegetables
- 13. Broad Leaf Vegetation
- 14. Seawater
- 15. Bottom 5ediment
- 16. Aquatic Flora
- 17. Fin Fish
- 18. Mussels
- 19. Oysters
- 20. Clams
- 21. Scallops
- 22. Lobster (and Crabs) l l *Since there were no samples taken for these types there are no tables for them.
3 19
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a . 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 contain a description of 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 7) The gamma exposure rate is determined from the integrated exposure measured over a time period of approximately one month using CaF2 (Mn) thermolumines-cent dosimeters. These glass bulb dosimeters are subject to inherent self-irradiation which has been experimentally measured for each dosimeter. Consequently, the results, shown in Table 1 have been adjusted for self-irradiation effects. The range of this correction is 0.4 uR/hr to 2.0 uR/hr, with a mean of approximately 1 uR/hr. The exposure rate measurements exhibit the same trends as those of past years. These measurements demonstrate the general variations in natural background radiation between the various on-site and off-site locations and include gamma exposure from all sources including cosmic, terrestrial, and artificial radioactivity. In particular, the Weather Shack (location 02) experiences higher exposure rates due to its proximity to granite beds while the Ledyard location (location 14C) experiences relatively higher background exposure rates than the other control locations at Mystic, Montville, and Old Lyme (locations 13C, f SC, and 16C). During Unit 1 operation, a small increase in exposure rates is caused by the direct exposure pathway of "skyshine" (i.e., scattered radiation from nitrogen-16 decay in the turbine; this pathway is unique to boiling water reactors). This direct exposure pathway decreases rapidly with distance from the turbine building, to levels that are virtually undetectable at the off-site locations. Special surveys performed with a high pressure ion chamber support this premise and are discussed in Appendix D. As a result of these surveys, two on-site locations were , repositioned to better evaluate the skyshine effect around Millstone. Evaluation of the monthly data indicates a noticeable decrease at Fox Island (07) and a significant increase at Bay Point Beach (09) due to these location moves. The decrease is due to the new position being more distant from granite beds and being located over water on the dock. The lower background will make TLDs at this location more sensitive to the slight increases caused by skyshine near the Fox island area. The increase at Bay Point Beach is caused by the new position being closer to the Unit 1 turbine buildina. The elevated readings will make the effect of skyshine more easily discernable. buring any Unit 1 shutdown, a small decrease in exposure levels is normally observed at the locations mentioned above and other j on-site locations (Weather Shack (02), Navy Laboratory (05), and Millstone Environmental Laboratory (08)). However, Unit 1 operated at a capacity factor of 95.5% in 1988. The only apparent decrease in exposure can be seen in November at Bay Point Beach (09), the most sensitive skyshine indicator location. Unit 1 1 4-1
4 g was shutdown for only 5 days in November making the decrease very slight. The maximum off-site direct exposure due to Unit 1 was determined to be 0.1 uR/hr. The dose consequence attributable to this direct dose is discussed in Section 5.0. Further evaluation of the data reveals a decrease in background at most control locations during January. This was most likely caused by the large amount of snowfall during this month. As shown in previous years, snow tends to provide a shielding effect. The control stations are located inland where accumulation of snow was more significant. With the installation of the augmented off-gas treatment system in May of 197.8, the plant gaseous effluents decreased significantly to levels that are essentially undetectable by TLD's, even at the on-site monitoring stations. The only appreciable effect, aside from that of skyshine, seen in the TLD data is that attributable to the variation in the background radiation which has been noted as being consistent with previous years. Air Particulate and lodine (Table 2,3,4 A-L and 5) Air is continuously sampled at seven inner ring and two outer ring locations 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 r levels similar to that seen over the last six years. Inner and outer ring moniton, ' locations showed no significant variation in measured activities. This indicates dat any plant contribution is not measureable. Charcoal cartridges are included at all of the Radiological Effluent Monitoring Manual required air particulate stations for the collection of atmospheric iodine. These cartridges are analyzed on a weeky basis for 1-131. 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. The air particulate samples that are utilized for the weekly gross beta analyses are composited monthly and analyzed for gamma emitting isotopes. The results, as shown in Tables 4A-4L, indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. Positive results for all the other isotopes are attributable to statistical fluctuations in counting. These analyses indicate 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, b.ecause of the larger sample volume as a result of compositing and the higher efficiency of beta counting. The Sr.90 results show the same trend as the gross beta analyses. Levels continued to remain at the fairly constant low values as observed in 1982-1987. 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. 42
e e Cow Milk (Table 7) The most sensitive indicator of fission product existence in the terrestrial environment is usually the analysis of milk samples. This in combination with the fact that milk is a widely consumed food results in this pathway being the most critical. This pathway also shows significant amounts of weapons testing fallout. Therefore, this media should be carefully evaluated when trying to determine what are the actual plant effects. Routine levels of Sr-90 and Cs-137 similar to those of the past were observed. The ) range of results were 1.1 to 7.6 pCi/l and 0 to 10.7 pCi/l for Sr-90 and Cs-137, ! respectively. Detailed analysis of this data has concluded that these levels are from weapons testing fallout and are not plant related (see Section 6.0 for details to this argument). All samples showed a lack of I-131 detectable above the MDL of 0.5 pCill. These I results are consistent with previous years' results. The only occasions when this l nuclide has been detected are those immediately following atmospheric testing of nuclear weapons and the Chernobyi accident. , Goat Milk (Table 8) Goat milk samples can be a more sensitive indicator of fission products in the terrestrial environment than cow milk samples. This is dependent on a number of parameters, including: metabolism of these animals, feeding habits, and feed type. Samples taken during weapons testing periods have demonstrated higher uptake of fresh fallout nuclides (Sr-89 and 1-131) at the indicator goat location. , This trend helps to explain the usual, higher than normal Sr-90 and Cs-137 ' concentrations at the indicator location as compared to the control location. Positive indications of Sr-89 and Cs-134 were not observed. Therefore, as with cow milk, detailed analysis of the data has concluded that the Sr-90 and Cs-137 levels , are from weapons testing fallout (see Section 6.0 for more details). No plant related 1-131 was seen in this media. For the last four years, no detectable levels of I-131 have been seen in goat milk samples except for the period immediately following 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. In the spring, January- March, these samples were not available as a replacement at either goat location. Pasture grass was also unavailab!e in late fall, November - December, to substitute for goat milk not available. Well Water (Table 10) Well water samples are not required by the REMM. Data from 1973-1985 has shown the lack of detectable station activity in this media. Therefore, the sampling of well water has been discontinued. In the event of widespread plant contamination, these samples would be collected. Reservoir Water (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 the extremely unlikely possibility of observing routine plant effluents in this media has resulted in discontinuing these samples. In the event of widespread plant contamination, these samples would be collected. 4-3
Fruits and Vr.antabhs (Tchla 12) Consistent with past years, this media did not show any plant effects. Concentrations of Sr-90 in these samples existed at levels comparable to those observed for the past eleven vears. Naturally occurring K-40 was detected in all samples. Since there was no fr'esh fallout, no other nuclides were detected. Broad Leaf Vecetation (Table 13) Consistent with past years, this media did not show any plant effects. Concentrations of Sr-90 and Cs-137 in these samples existed at levels comparable to past years and is due to fallout. Seawater (Table 14) Except for samples at location (40X) these samples are quarterly composites of weekly grab samples. Three of the four indicator samples show tritium (H-3) concentrations above the background levels seen at the control location. These elevated levels are attributable to plant operation and are similar to those of past years. Due its low energy emission beta particles, the dose consequence of the observed H-3 concentrations is negligible (see Section 5.0 for a discussion of the maximum dose consequences). Station effects are apparent in the first quarter indicator sample. Co-58, Co-60, Cs-137 and Beta Fraction ll were observed at levels higher than any of those seen in years past. The possible explanation for these levels could be the sampling of the sea water within 500 feet of the discharge during an actual plant liquid effluent discharge. The values observed are in the range of what could be expected during a liquid discharge. Because of this inherent problem with grab samples, a continuous sea water sampler in the vicinity of the discharge was installed in the third quarter. Results from the Quarry (location 40X) were obtained with this sampler. Starting in 1989, sea water samples from this continuous sampler (at the Quarry) will replace the grab samples (from the vicinity of discharge). Because sea water is not a direct source of consumption, other media are utilized in the determination of dose consequences (e.g.see Shellfish and Fish results). Bottom Sediment (Table 15) As in the past, this media did not exhibit any plant related activity. Levels are consistent with previous observations. Cs-137 was detected at a control location. However, the absence of Cs-134 in this sample and the relative distance and direction of this sample location indicate that this Cs 137 is not plant related. The levels of Cs-137 at this location are comparable to those observed in river water sediment (See Connecticut Yankee Annual Radiological Environmental Operating Report). Aquatic Flora (Table 16) There were indications of plant effluents in this media. Mn-54, Co-58 and Co-60 were observed at levels similar to those of last year. Sampling of this media provides useful information because it is very sensitive to plant discharges. However, since seaweed in this area is not consumed, other media are utilized in i the determination of dose consequences (e.g., see Shellfish and Fish results). I 1 Fish Flounder (Table 17A) Plant related Co-60 is shown in one sample from Niantic Bay (location 35). The remaining activity in Flounder is the same as that seen for the past twelve years. The plant effects on Fish are discussed in the next section due to the higher levels observed in fish taken at the onsite location. 44
Fish - Other (Table 178) Except for the quarry location, +.Sese fish samples exhibited data similar to that in previous years. For the off-site samples, the only detectab'e activity seen above the MDL was K-40. However, as in previous years plant relateo activity was detected in the quarry samples (location 40X). Positive values of Mn-54, Co-58, Fe-59, Co-60, Zn-65, Ru-106 and Ag-110m were observed. The quarry location is not accessible to members of the general public and with the dilution of the Long Island Sound, the levels of radioactivity generally become undetectable in these samples outside of the quarry. An exception to this occurred during the first quarter when a flounder showed detectable Co 60 activity, Using the concentrations measured in the quarry and dilut;ng them by the near field dilution factor of 3 determined for quarry discharges into the Sound, doses to the maximum individual can be calculated. See Section 5.0 for these resuits. Mussels (Table 18) GeLi analyses indicated the presence of plant related Co-58 and Co-60 at Two Tree Island (location 28), Niantic Shoals (location 37) and upper Jordan Cove (location 41X) and possible presence of Mn-54 at Niantic Shoals. The only other detectable activity observed in rnusself consisted of naturally occuring K-40. The dose consequence of the plant related radioactivity via this pathway is dicussed in Section 5.0. The levels observed are similar to last year. Oysters (Table 19) Native oysters are sampled at the quarry discharge (location 40X) an extra location. The remaining locations utilize stocked oysters; trays are kept at these sampling areas to guarantee samples and facilitate sample co!!ection. Plant related activity is shown at Niantic Shoals (location 31), Black Point (location 36), and two locations within the plant discharge area - the quarry discharge (location 40X) and the area within 500 feet of the discharge (location 32). The one within 500 feet is actually at the end of the quarry. This activity included Mn-54, Co-58, Co-60, Zn-65, and Ag-110m. Since the two locations near the quarry are on-site and not available for public use, the actual concentration of radionuclides iri oysters available for public consumption is much less. The dose consequence of the plant related radioactivity via this pathway is discussed in Section 5.0. Clams (Table 20) GeLi analyses indicated the presence of plant related Co-58, Co-60 and Zn-65. These levels correspond to the elevated levels seen in oysters for the same period. The dose consequence of radioactivity via this pathway is discussed in Section 5.0. Scalloos (Table 21) Scallops are not required by the REMM. However, this media is sampled to confirm plant effects and because of its consumption popularity. There were indications of plant effluents in this media. Mn-54, Co-58, Co-60 and Ag-110m were observed at concentrations not seen since the late seventies when Millstone had much higher releases. The levels measured are comparable to other levels in shellfish taken near the same area. The dose consequence of radioactivity via this pathway is discussed in Section 5.0. d5 l t
Lobsters (and Crabs) (Table 22) Some samples for location 12X (Fisher's Island) are crabs while all others are lobsters. Plant related activity is shown in lobsters from the area within 500 feet of the discharge (location 32) and Niantic Bay (location 35). The activity included ! Mn-54, Co-58, Co-60, and Ag-110m. The quarry sample is within the plant discharge, and as such, concentrations in food that the public consumes are assumed to be those seen at the Niantic Bay location. See Section 5.0 for a discussion of the dose consequences. 1 46
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5.0 OFFSITE DOSE EQUlVALENT COMMITMENTS 4 The off-site dose consec uences (dose equivalent commitments) of the stations' radioactive liquid and air aorne effluents have been evaluated using two methods. The first method utilizes the stations' measured radioactive discharges as input l parameters into conservative models to simulate the transport mechanism through the environment to man. This results in the calculation of the maximum dose consequences to individuals and the 0 to 50 mile population dose commitment. The results of these computations have been submitted to the NRC in the Annual Radioactive Effluents Dose Report written in accordance with tile Radiological Effluent Monitoring Manual, Section F.2. This method, which is usually conservative (i.e., computes higher doses than that which actually occur) has the advantage of approximating an upper bound to the dose consequences. This is important in those cases where the actual dose consequence cannot be measured because they are so small as to be well below the capabilities of conventional monitoring techniques. The second method utilizes the actual measurements of the concentrations of radioactivity in various environmental media (e.g., milk, fish) and then computes the dose consequences resulting from the consumption of these foods. The results of both methods are compared in Table 5.1 for those pathways where a potential dose consequence exists and a comparison is possible. The doses presented in this table are the maximum doses to an individual. That is, the dose is calculated at the location of maximum effect from the plant effluents for that pathway and for the critical age group. For example, the external gamma dose is calculated for the site boundary location which is not only the nearest but also has the greatest directional wind frequency and fish and shellfish doses are calculated assuming they are from an area within 500 feet of the station discharge. As indicated by Table 5.1, there is also a direct gamma dose attributable to the operation of Unit 1. This direct dose is inherent to BWR's (Boiling Water Reactors). It is due to direct and scattered radiation (skyshine) of the high energy gamma rays from Nitrogen-16 in the radioactive steam which circulates through the turbine. It should be noted that the indicated dose due to direct radiation is to the maximum individual and is corrected for periods when Unit I is not operating (i.e., there is no direct dose when steam is not generated). Summarizing the data in Table 5.1, the maximum total doses to an individual are: 3.4 mrem whole body to an adult,3.2 mrem to a child's thyroid, and 0.44 mrem to an adult's Gl (LU) (gastrointestinal tract-lowerlarge intestine). Since the maximum dose consequence to an individual is at the location of highest dose consequence, doses will be less for all other locations. The average dose to an individual within 50 miles from the site cannot be calculated using the second method. However, the first method yields the following results for the period January-December 1988 for the average individual: ANNUAL A\/ERAGE WHOLE BODY DOSE : : DUE TO AIRBORNE EFFLUENTS = 0.00022 mrem DUE TO LIQUID EFFLUENTS = 0.00012 mrem Thus,it can be seen that the average whole body dose to an individuals much less than the maximum whole body dose to an individual as shown in Table 5. 7. 5-1
l' in order to provide perspective on the doses in Table 5.f, the standards for 1988 on
. the allowable maximum dose to an individual of the general public are given in 40CFRf 90 as 25 mrem whole body,75 mrem thyroid, and 25 mrem any other organ. These standards are a fraction of the normal background radiation dose of 280 mrem per year and are designed to be inconsequentialin 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.
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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 factorsdepend 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 l cause erroneous conclusions. j Consider, for example, the problem of deciphering the effect of station releases on the radioactivity measured in milk sam ales. 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 ist Soes are still remaining from the high weapons testing era of the 1960's. This resuns in significant amounts of Sr-90 and Cs-137 appearing in milk samples. Distinguishing between this " background" of fallce t 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 cases 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 measurc, 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 Sr-89, air particulate data has been evaluated. Evaluation shows that airborne Sr-89 is generally uniform at all the ,ndicator 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 isoto aes, the same conclusion cannot be made. But, plant related Sr-89 has never aeen detected in milk, therefore levels of Sr-90 observed must be attributable to nuclear weapon's testing. 6-1
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- 3. Similar to Sr-89, Cs-134 can be ustd 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 rampling 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 chan 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 1977-1983 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 al: 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 Protection. 'l 6-2 i
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'l APPENDIX A i
{ 1 COW AND GOAT CENSUS FOR 1988 l j s I A-1 f 4 _ _ _ _ _ _ _________-__D
DAIRY COWS WITHIN 15 MILES OF MILLSTONE POINT AS OF APRIL 1988 DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS N 6 M. S. Douglas Morgan 3 16 Douglas Lane Waterford, CT 06385 N 7 M. Waterford Country School 4 78 Hunts Brook Rd. Quaker Hill, CT 06375
- Waterford -
N 12.5 M. Conrad Nelson 75 486 Fitch Hill Rd. Uncasville, CT 06382
- Montville -
N 14 M. Wauwecus Farm Dairy 40 RFD #2, Wauwecus Hill Rd. Norwich, CT 06360
- Bozrah -
N 15 M. Joseph Lebejko 40 RFD 2 Norwich, CT 06360 NE 12.5 M. Mainwood Farm 32 936 Colonel Ledyard Hwy. Ledyard, CT 06339 c/o Ed Misiaszek 26 Rex Road Lisbon, QT 06351 NE 13.5 M. Richard H. Morgan 60 RFD #7, Box 1114 Ledyard, CT 06339 ENE 13 M. Charles Perkins 32 RFD fl Stonington, CT 06378 WNW 9.5 M. J. Ely Harding 60 Ashlawn Farm Old Lyme, CT 06371
- Lyme -
DAIRY COWS WITHIN 15 MILES OF MILLSTONE POINT AS OF APRIL 1988
' DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS WNW 11 M. Tiff any Farms 80 Sterling City Rd.
Old Lyme, CT 06371
- Lyme -
NNW 8 M. Raymond Muschinsky 25 Grassy Hill Rd. East Lyme, CT 06333 NNW 11.5 M. Wysteria Farm 45 Eugene Wilczewski Darling Rd. Salem, CT 06415 NNW 13 M. Stuart Gadbois 222 , Route 82 Salem, CT 06415 I NNW 13 M. Garry Vaill 45 Forsythe Rd. Salem, CT 06415 l
. _ _ _ _ _ _ - - _ _ _ ~
I 1 IRIRY GCRTS WITHIN 20 MILES OF MILLSTONE POINT AS OF JUNE 1988 l DIRECTICN LISThNCE NMGE AND ADDRESS NO. OF GCETS N 1.8 M. Mrs. John Mingo 2 l 69 Spithead Road Waterford, CT 06385' NNE 5 M. Allen Moran 3 204 Rope Ferry Road Waterford, CT 06385 i NE. 9 M. Tbrtora Family 4
'80 Moxley Hill Road Uncasville, CT 06382 NE 13 M. Alan J. Starke 1 Rt. 12 Norwich,-CT 06360 Near Mohegan Pequot Bridge NE 14 M. Robert Ruest 4 15 Mathewson Mill Road Ledyard, CT 06339 ENE 2 M. Bertram Smith 4 l 9 Braman Road ]
Waterford, CT 06385 W 16.5 M. Victor Trudeau 9 174 Horse Hill Road Westbrook, CT 06498 i l 4
l WW 8 M. Peter LaPolla 2 Town Woods Road old Lyme, CT 06371 WW 10 M. Dave & Pam Richards 1 285 Grassy Hill Road Lyme, CT 06371 W 5 M. Ron Birchall 8 339 Boston Post Roaf East Lyme, CT 06333 W 5 M. George Scacciaferro 28 338 Boston Post Road East Lyme, CT 06333 NW 14 M. Anne B. Henrici 5 Round Hill Road Salem, CT 06415 I i j
- _ _ - _ _ _ _ - - _ _ . - - - - - _ _ _ _ _ _ _ _ _ . _ _ - - _ . - _ _ . . - _ _ - . . _ _ _ _ _ - _ - _ _ _ . _ - - _ _ _ ._ _ _ ._ ._ __ _ ____.__.3
e , l l 1 4 APPENDIX B , 1 j 1 NORTHEAST UTILITIES OA PROGRAM i l l 1 B-1 I 1
Northeast Utilities Service 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 nhat 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 Verification 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 Radicanalytical 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 GeLiinstrument calibration indicated a trend ,
of analyses low by approximately 20E 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 30E I B-2
o
~ '
Table 1 Number of Quality Control
- 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 l
-lodine 12 794
- Geli 24 192
- Strontium 8 64 i
l
- An additional program is performed by the contractor
]
a - Total for both Millstone and Connecticut Yankee b - Depends on availability c - OC oreakdown does not include H-3 analysis; total number of tritium QC samples was 20 l B-3
W'- - - - ~ ~ - - - - - - - - , . _ , , _ _ , _ _ , _ _ _ _ _ _ _ __ --
# e l
l APPENDIX C l 1
SUMMARY
OF EPA INTERLABORATORY COMPARISONS { i l C-1
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: EL.2.0 17 (xx) 16
- 16. ,
CHAS Avg. 17 (1,0) l EPA Known 17 (1.5, 2.6, 3) EPA Gr. 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 1.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 Coritrol 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 deemed 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 valtie is from the grand average.
)
4 : . EPA Intercomparison Samples Gross Alpha and Beta Samnie No. Samnle Date Samnle Tyne Gross Aloha Gross Beta ) 37158 1/22/88 Water (a) 4 10 4 9 A E 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 12 Lab Avg. 6(1) 9(1)
EPA Known 6(5,9,0) 13(5,9,1) i EPA Gr. Avg. 6(2,0) 13(2,-1). i 8803297. 3/25/88 Air Filter (b) 60 65 (Note 1) 58 65 kl kk 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 sE Lab Avg. 47(2) l EPA Known 46(11,19,0) EPA Gr. Avg. 45(12,0) 8804204 4/24/88 Water (a) 65 8804253 59 b.4 Lab Avg. 63(3) EPA Known 57(5,9,2) EPA Gr. Avg. 58(6,2) 8805233 5/20/88 Water (a) 7 13 i 7 12 I
- 1 12 Lab Avg. 7(0) 12(2)
EPA Known 11(5,9,-1) 11(5,9,0) EPA Gr. Avg. 9(3,-1) 12(2,0) .j Y -
I EPA Intercomparison Samples Gross Alpha and Beta (Continued) , Samole No. Samole Date Samole Tvoe Gross Alpha 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 (Note 10) 8 970 2 1Q00 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 10/18/8f Water (a) 43 43 il 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 1 1 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) pCi/l (b) pC1/ filter
.? .
EPA Intercomparison Samples Gamma
'Samole No. Samole Date Samole Tyne 8802093 02/05/88 Water (Note 2)
Nuclide (pci/1) 72* Nuclide (pCi/1) 60* Cs-137 82 Co-60 64
- 23. E 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**)
- 23. 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.
l EPA Intercomparison Samples Gamma (Continued) Samole No. Samnie Date Samole Tyne 37164 1/29/88 Food (Note 8) Nuclide (pCi/kg) 91 Nuclide (pCi/kg) 90 I-131 106 Cs-137 103 ,1 122 19Q 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 (mg/kg) 1586 K-40 1563 14._2p 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 - l 20 29 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-50 54 Cs-134 7 l 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-137 7 7 i Lab Avg. 7(1) EPA Known 7(5,9,0) EPA Gr. Avg. 8(2,0) _ _ _ _ _ - _ _ - -- )
s, , ! EPA Intercomparison Samples Gamma (Continued) Samnle No. Samnie Date Samnle Tyne 8806033 Water i 6/3/88 ! (Note 4) ) Nuclide (pCi/1) 294 Nuclide (pCi/1) 15 Or-51 249 Co-60 15 j 22.Q 11 .". l 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-65 97 Ru-106 169
.9.1 114 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) l 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 E .4_Q 1615
- 12. 16.f.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) i _ _ _ _ . . _ _ . _ _ _ 1
1 EPA Intercomparison Samples Gamma (Continued) q Samnie No. Samnie Date Samnle Tyne ! 8808028 7/29/88 Food f
.)
I Nuclide(pCi/kg) 96 Nuclide(pci/kg) 47 ,-l 1-131 S6 Cs-137 45 121 4.2 Lab Avg. 95(9) Lab Avg. 45(3) . EPA Known 107(11,19,-2) EPA Known 49(5,9,-2) ~i EPA Gr. Avg. 108(8,3) EPA Gr. Avg. 48(3,-2) j Nuclide(mg/kg) 1258 h K-40 1267 1 1101 i Lab Avg. 1243(34) EPA Known 1240(62,107,0) EPA Gr. Avg. 1225(50,1) 8808301 8/26/88 Air Filter '! i Nuclide pCi/ filter 16 i Cs-137 19 22 Lab Avg. '19(3) EPA Known 12(5,9,2) i EPA'Gr. Avg. 13(3,2) l 1
),
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1
]
I EPA Intercomparison Samples Gamma (Continued) Samole No. Samule Date Samole h 8810082 10/07/88 Water (Note 11) Nuclide (pCi/1) 186 "Nuclide(pci/l 22 , Cr-51 201 Co-60 22 122 21 Lab Avg. 195(8) Lab Avg. 23(2) EPA Known 251(25,43,-4) EPA Known 25(5,9,-1) EPA Gr. Avg. 249(24,-4) EPA Gr. Avg. 26(2,-1) Nuclide (pci/1) 135 Nuclide (pCi/1) 113 Zn-65 132 Ru-106 104 115. 111 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 2.Q 14.- Lab Avb. 20(0) Lab Avg. '13(1). EPA Known 25(5,9,-2) EPA Known 15(5,9,-1) EPA Cr. Avg. 24(2,-1) EPA Gr. Avg. 16(2,-1)
3 ..a I EPA Intercomparison Samples Gamma (Continued) Sample No. Sample Date Sample Type-8810193 10/18/88 Water Nuclide(pci/1)' 13 Nuclide(pci/1) 13 Cs-134 11 Cs-137 13 12 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) Nuclide(pCi/1) 40 Nuclide(mg/1) 1610 Cs-137 42 4 E ,49, 1510 M IfiQ.Q Lab Avg. 42(2) Lab Avg. 1570(60) EPA Known 50(5,9,-3) EPA Known 1600(80,140,-1) EPA Gr. Avg. 50(4,-3) EPA Gr. Avg. 1620(100,-1) I
L EPA Intercomparison 3amples ! I-131 (pci/1) Samole No. Samnie Date Samole Tyne I-131 8802312 2/26/88 Milk 4 Lab Avg. 4(0) 1 EPA Known 4(0,1,0) EPA Cr. Avg. 4(1,-1) l l 8804070 3/8/88 Water 8 9 2 Lab Avg. 9(1) EPA Known 8(1,2,3) EPA Gr. Avg. 8(1,3) 8806257 6/24/88 Milk 107 (Note 5) 106 1M Lab Avg. 106(1) , EPA Known 94(9,16,2) l EPA Gr. Avg. 96(9,2) l 8808087 8/05/88 Water " 83 (Note 12) 28 M Lab Avg. 8 5(3) EPA Known '76(6,14,2) EPA Gr. Avg. 77(8,2) 8810261 10/28/88 Milk 66 (Note 16) 69 e 52 f Lab Avg. 66(4) i EPA Known 91(9,16,-5) ] EPA Gr. Avg. 90(8,-5) 8812089 12/09/88 Water 97 (Note 17) 91 l E I i Lab Avg. 91(6) EPA Known 115(12,21,-3) i EPA Gr. Avg. 116(14,-3) l
c o, . i Te ' 1 .(- t L ' EPA Intercomparison Samplec-l Ra-226 and Ra 228(pci/1) h l' Ra-228~ !
.Samole Nq. Samole Date Samole Tvoe Ra-226
- 8803127: 3/11/88 Water 6.0 9.6 4.1 7.6 0 L.1 L.1
; 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) r EPA Gr. Avg. 7.2(1.1.-l.7) 7.6(1.7,1.4)
~8804184 4/24/88 Water 3.0 3.9-8804252 3.9 4.2 (Note 6) '
L.1 LJ. 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 91 lb ?. 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 4.9 14, 2 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 ld L.9 Lab Avg-, 3.8(.5) 2.9(0.0)
EPA Y.covn 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 12/16/83 Water 2.0 13.1 (Note 19) 1.6 14.1 1.1 lb.9. Lab Avg. 1.6(.4) 14.4(1.4) EPA Known 3.5(.9,1.6) 10.3(2.6,4.5) i S
EPA Intercomparison Samples Sr-89 and Sr-90 Samnle No. Samnle Date Samnie Tvoe M M 37164- 1/29/88 Food (c) 52 53-(Note 8) 38 60 M 17. 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 1 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 22 11-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 51 Lab Avg. 44(6) 64(2) EPA Known 40(5,9, 1) 60(3,5,2) , l EPA Gr. Avg. 34(12) 56(10) l 4 i l 1 1
(. ; i EPA Intercomparison Samples
- Sr-89 and Sr-90 (Continued)
Samole No. 3, amole Dete Samole Tvoe Sr-89 Er.-1Q 8808028 7/29/88 Food (c) 45 36
.(Note 14) '26 44 h bl Lab Avg. 35(10) 42(6)
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 ! 1 ( 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 2 2' Lab Avg. 14(2) 12(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 12
. Lab Avg. 73(3) 67(9)
EPA Known '40(5,9,11) 60(3,5,4) l EPA Gr.' Avg. 32(12,14) 56(6,7) l Note: (a) pCi/l l (b) pCi/ filter (c) pCi/kg l l I I _m_ _ _ - __m_______. _ _ _ . _ _ _ _ _ - . _ . _ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ ._ __ _ .
e--_ q f EPA Intercomparison Samples Tritium , i Samnle No. Samnle Date Samnle Tvos, Tritium'(oCi/1) !
.8802152 2/12/88 Water 3430' 3540 ll1Q '
1ab Avg. 3570(160) i EPA Known 3330(360,630,1). EPA Gr. Avg. 3360(340,1) 8806108 6/10/88 Water 5100 4900-1QQ.9 Lab Avg. 5000(100) EPA Known 5570(560,960,-2) EPA Gr. Avg. 5390(500,1) 8810142 10/14/88 Water 2080-2010 2.Ql.Q Lab Avg. 2030(40) EPA Known 2320(350,610,-1) EPA Gr. Avg. 2320'(240,-1) 9 u_._.mm_m_m _ _ . - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . . _ _ , _ _ _ _ . _ _ _ _ _
~l s' p, EPA Intercomparison Samples ,
Uranium (pci/1) Samole No. Samole Date- Samole Tvoe Uranium (oC(Zll 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 h Lab Avg. 5(0) EPA Known 5(6,10,0) EPA Gr. Avg. 6(2,0) l i
)
l-1 1
4 , 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 i 64** ' 52 64** 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 t 3 CHAS Repoded 103 45 CH AS Repoded 119 50 CHAS Reponed Not Repoded 55 880625701AR 119 t 6 28.6 .7 880625701B 103 4 28.3 1.7 880625701C 2113 29.4 i .8 880625701D 39 11 62 2 Recalculated C 48 'l 65 2 Sample 8806257-01C recalculated and 880625701D were acceptable results. However, samples AR and B were not acceptable and review of the raw cata, calculations, and counting data indicated no problems.
*Two sigma standard deviations
l
-G a.
J L
- 4. . Ru-106 was recalculated with the Ru-106 correction factor (See Note 11):
208 219 200 Lab Avg. 209 1 19** l Recalculated results are within two standards deviations of the EP;A result.
- 5. The raw data, calculations and counting data indicated no problems.
- 6. Ra-226 result was low in comparison 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.
- 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 witle 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 28.6 1.5 IBM 28.611.5 Basic 27.411.4 Data flex 27.411.4
-28 12 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 ! 35** l Avg. 150 1 37 i Cr-51 was recalculated after the GeLi recalibration with the following results: Nuclide pCi/1 244 1 35** Cr-51 229 36** 227 37** Lab Avg. 233 1 10 The recalculated Cr-51 results are within the EPA limits.
*
- Two sigma standard deviations. ,
.12. .1-131 was checked for error. Resaits were recalculated with new efficiencies from
. LLB calibration. Recalculated results are within two standard deviations of the EPA known.
Nuclide pCi/1 70 1-131 72 69 . 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 Sr-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. l l
- 17. ~ Low l-131 results are currently under investigation. The calibration for 1-131 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. i
*
- Two sigma standard deviations.
l _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i
s , APPENDIX D SKYSHINE SURVEYS l l I D-1
Northeast Utilities has performed several studies on the effects of skyshine on the immediate vicinity and surroundings of Millstone Unit 1. Unique to boiling water reactors such as Unit 1, skyshine originates from plant equipment transporting the l radioisotope nitrogen-16 (N-16). When N-16 decays,it releases very high energy gammas l of 6.13 and 7.11 MeV. These gammas can escape through the turbine building walls or ; roof, scatter in air, and provide both on-site and off-site dose consequences (see Figure ! D-1). ! I The latest in-depth skyshine study conducted around Unit 1 was performed in October 1987. It consisted of numerous surveys taken with a high pressure ion chamber (HPlC). Some results of these surveys are contained within this section. The results make apparent the rapid decrease in exposure with distance from the source and the effects of shielding from surrounding structures. Figure D-2 illustrates the locations of the measurements and Table D-1 lists the results of the HPIC surveys. Examination of the results (e.g. Point (4) - Fox island and Points (16), (17), and (18)- Bay Point Beach) encouraged the repositioning of some area TLD locations to points of more sensitivity. Northeast Utilities will continue to devote its efforts toward the study and understanding of skyshine effects in the immediate surroundings of Millstone Unit 1. The understanding of these effects and the monitoring of the environment around the Millstone site will help continue Northeast Utilities endeavors to protect the health and safety of its , employees and neighboring communities. l e i i i D-2
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Table D-1 Environmental G mma Msasur.*msnts (Skyshine Effects) uR/hr Backaround Skyshine
, Measurement Point Measurement Effect 1 10.6 0.4 2 11.0 1.2 3 12.0 0.8 4 4.3 0.8 5 15.9 0.9 6 16.0 0.7 7 13.0 0.8 8 9.4 4.6 9 23 11 10 14.0a 16 11 13.2 290 12 10.2 87 13 9.0 9.5 14 7.0 12 15 4.7 4.2 16 13.0 6.0 17 13.0 4.7 18 11.0 3.6 19 11.0 0.8 20 10.6 0.6 l 21 9.5 0.6 22 9.0 03 1 23 11.9 0.1 24 9.7 0.05-0.1 l 25 9.9 0.13 26 8.8 0.2 27 10.4 0.3 :
i a Background variable due to radwaste operations. ) D-5 _ _ _ _ - _ _ _ l}}