CY-99-058, Annual Radiological Environ Operating Repts for Jan-Dec 1998. with
| ML20206D058 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/31/1998 |
| From: | Mellor R CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CY-99-058, CY-99-58, NUDOCS 9905030287 | |
| Download: ML20206D058 (250) | |
Text
l CONNECTICUT YANKEE ATO MIC POWER COMPANY l HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 l
l i'
April 30,1999 Docket No. 50-213 CY-99-058 U. S. Nuclear Regulatory Commission I Attention: Document Control Desk Washington, DC 20555 Haddam Neck Plant Annual Radioloaical Environmental Operatina Report In accordance with the requirements of the Haddam Neck Technical Specifications, Section 6.9.1.6 and the Radiological Effluent Monitoring and Off-Site Dose Calculation !
Manual, an implementing document of the Haddam Neck Technical Specifications, l
two (2) copies of the Annual Radiological Environmental Operating Report are herewith '
submitted.
If you should have any questions, please contact Mr. G. P. van Noordennen at (860) 267-3938.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER CO.'AP ANY
\l b01lw A K4 MIL I Rdssell A. Mellor U Vice President - Operations and Decommissioning
/_.ool cc: H. J. Miller, NRC Region i Administrator T. L. Fredrichs, NRC Project Manager, Haddam Neck Plant R. R. Bellamy, Chief, Decommissioning and Laboratory Branch, NRC Region i E. L. Wilds, Jr., Director, CT DEP Monitoring and Radiation Division
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT I
HADDAM NECK STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1,1998 - DECEMBER 31,1998 DOCKET NO. 50-213 LICENSE NO. DPR-61 l
Prepared for the CONNECTICUT YANKEE ATOMIC POWER COMPANY Haddam, Connecticut By the NORTHEAST NUCLEAR ENERGY COMPANY Waterford, Connecticut a
Haddam Neck Station Annuil Radiological Environmental Operating Report 1998 i
TABLE OF CONTENTS l
- 1.
SUMMARY
1-1
- 2. PROGRAM DESCRIPTION 2-1 ,
2.1. Sampling Schedule, Types, and Locations 21 2.2. Samples Collected During Rep in Period 2-6
- 3. RADIOCHEMICAL RESULTS 3-1 3.1. Summary Table 31 I 3.2. Data Tables 3-14 l
- 4. DISCUSSION OF RESULTS 4-1 l 4.1. Gamma Exposure Rate (Table 1) 4-1 4.2. Air Particulate Gross Bets Radioactivity (Table 2) 41 4.3. Airborne lodine (Table 3) 4-2 4.4. Air Particulate Gamma (Table 4A-D) 42 ;
4.5. Air Particulate Strontium (Table 5) 4-2 4.6. Soil (Table 6) 4-2 4.7. Cow Milk (Table 7) 4-2 4.8. Goat Milk (Table 8) 4-3 l 4.9. Pasture Grass (Table 9) 4-3 )
4.10. Well Water (Table 10) 4-3 4.11. Reservoir Water (Table 11) 4-4 4.12. Fruits and Vegetables (Table 12) 4-4 4.13. Broad Leaf Vegetation (Table 13) 4-4 4.14. River Water (Table 14) 4-5 4.15. Bottom Sediment (Table 15) 4-5 4.16. Shellfish (Table 16) 4-5 4.17. Fish (Tables 17A and 17B) 4-5
- 5. OFF-SITE DOSE EQUIVALENT COMMITMENTS 5-1
SUMMARY
OF INTERLABORATORY COMPARISONS C-1 y -
Haddam Neck Station Annual Radiological Environmrntal Operating Report 1998 "1.
SUMMARY
The radiologictl environmental monitoring program for the Haddam Neck Station was continued for the period January through Dr.cwnber 1998, in compliance with the Technical Specificatiem and the Radiological Effluent Monitoring and Off Site Dose Calculation Manual (RFMODCM). His annual report was prepared for the Connecticut Yankee Atomic Power Company (CYAPCth by the Safety Analysis Branch of the Naclear Engineering Depenment of Northeast Nuclear Energy Company (NNECO). Sample collection and preparation
- and gamma exposurs me measurements were performed by the Production Operations Services Laboratory (POSL). Laboratory c ,alyses were performed by Duke Engineering and Services Environraental Laboratory j (DESEL). l normoluminescent dosimeters (TLDs) were used to measure direct gamma exposure in the vicinity of the station and as far away as 12.5 miles. Radiochemical and radiological counting analyses of samples were perfonned to detect the presence of any station related radioactivity. Samples included air paniculates collected j on filters, milk, cow and goat feed (hay), broad leaf vegetation, well water, fruits, vegetables, river water, bottom j sediment sMfish, and fish. In evaluating the res alts of these analyses it is necessary to consider the variability
_ of natur6 at 6 man-made sources of radioactivity, distribution in the environment and uptake in environmental media. This variability is doendent on many factors incheding station release rates, past spatial variability of radioactive fal' at from nuclear weapons tests and on-gokw edistribution of the fallout, contribution from cosmically prowced radioactivity, ground water dynamics, soil characteristics, farming practices, and feed type.
Significant variations in measured levels of radioactivity cold be caused by any one of these factors.
Therefore, these factors need to be considered in order to properly explain any variations in radiation detected and to distinguish between natural and station related radioactivity.
Hadder. Neck is permanemly shutdown Primary activities at the Haddam Neck station are now focused on decommissioning. Even though the station is no longer generating power, decommissioning activities included procusing and discharging ofliquids containing radioactivity and releasing of airborne radioactivity. However, the kvels of radioactivity released are significantly lower than releases during plant operation. De radiological monitoring of the environment through this program will continue to assure the health and safety of the public and workers are maintained at all times.
De predominant radioactivity detected by the monitoring program was that from outside sources, such as fallout fmm nuclear weapons tests and naturally occurnng radionuclides. As typical of previous years, station related radioactivity was observed at some of ti,e on site gamma monitoring locations. The only other observation of ,
sianon effects was tritium in well water at the on-site location. ' ;
As usual, Cesium 137 and Strontium-90 were measured in both cow and goat mill . These levels are a result of nuclear weapons testing in the 1960s and not the result of station decommissioning operations. His can be concluded because insufficient quantities of these isotopes have been released by the station to account for the measured concentrations. Higher levels of Cesium-137 and Strontium-90 were detected prior to initial plant operation and have been declining since the ban on nuclear weapons testing in the 1960s.
De radiasion dose (dose equivalent commitment) to the general public from the station's discharges has been l evaluated by two methods. One method utilizes measurements of station's discharges and conservative transport l models and the other tailizes 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 was calculated to be 0.2 millirem. De averso dose to a member of the public residing within 50 miles of the station ;
is 0.00065 milliarm. These doses are 0.8 percent and 0.0026 percent of the standard as set by the Environmental Protection Agency on the maximum allowable dose to an individual of the general public. The sumdards of the Environmental Protecten Agency me a small fractkn (less than 10 percent) of the 284 mrem per year normal Connecticut resident background r=lww=i (NCRP94) and are designed to be inconsequential in regard to public health and safety. Station related doses are a small fraction of these standards and of the variation in natural background in Connecticut. ney pose insignificant public health consequences. )
1-1
r i Haddam Neck Station Annual Radiological Environmental Operating Report 1998
- 2. PROGRAM DESCRIPTION 2.1. Sampling Schedule, Types, and Locations The sample locations and the sample types and frequency of analysis are given in Tables 2 1 and 2-2 and Figures 2.1 and 2.2. The program as described here includes both required samples as specified in the Radiological Effluent Monitoring and Off Site Dose Calculation Manual and any extra samples.
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2*I
Haddam Neck Station Anmcl Radiological Environmsntal Operating Report 1998 i
Table 2-1 Environmental Monitorine Pronram Sampline TYDes add Locations N i.11 '* h e J l f;f .-
I1 On-site Mouth of Discharge Canal 1.1 Mi, ESE TLD 1 21 Haddam-Park Rd. 0.8 Mi, S TLD l 3-1 Haddam4 ail Hill Rd. 0.8 Mi, WSW TLD 4-1 Haddam-Ranger Rd. l.8 Mi, SW TLD, Air Particulate 5-1 On-site lqiun Hollow Rd. 0.4 Mi, NW TLD, Air Particulate 6-1 On-site Substation 0.5 Mi, NE TLD, Air Paniculate, Vegetation 7-1 Haddam 1.8 Mi, SE TLD, Air Particulate 8-1 East Haddam 3.1 Mi, ESE TLD, Air Particulate 9-1 Higganum 4.3 Mi, WNW TLD, Air Paniculate 1 10-1 Hurd Park Rd. 2.8 Mi, NNW TLD l 11 C Middletown 9.0 Mi, NW TLD j 12-C Deep River 7.1 Mi, SSE TLD ;
13-C North Madison 12.5 Mi, SW TLD, Air Particulate '
14-C Colchester 10.5 Mi, NE TLD l 15-1 On-site Wells 0.5 Mi, ESE" Well Water !
16-C Well State Highway Dept. E. Haddam 2.8 Mi, SE Well Water i 17-C Beyond 10 Miles Beyond 10 Miles Fruits & Vegetables I 18-I Site Boundary 0.4 Mi, NW Vegetation l 19-1 Cow Location #1 6.5 Mi, ENE Milk ;
20-1 Cow Location #2 8.0 Mi, NE Milk 21 1 Cow Location #3 11.0 Mi, SE Milk 22-C Cow Location #4 11.0 Mi, ENE Milk 23-C Goat Location #1 16.0 Mi, NNE Milk
- 24-1 Goat Location #2 3.6 Mi, SSE Milk i 25-1 Within 10 Miles Within 10 Miles fruits & Vegetables l 26 1 CT River Near intake 1.0 Mi, WNW Fish 27-C CT River-Higganum Light 4.0 Mi, WNW Shellfish 28-I CT River-E. Haddam Bridge 1.8 Mi, SE Bottom Sediment, River Water 28 X CT River-E. Haddam Bridge 1.8 Mi, SE She!! fish ;
29-1 Vicinity of Dis harge Within 0.3 Miles Bottom Sediment, Fish l
30-C CT River- Middletown 9.0 Mi, NW River Water, Bottom Sediment i 7.6 Mi, NW Fish I 31 1 Mouth of Salmon River 0.8 Mi, ESE Shellfish 40 X Near Intake Structure 0.1 Mi, SSW TLD 41 X Picnic Area 0.3 Mi, WNW TLD 42 X Environmental Trail 0.1 Mi, NW TLD 43 X Moodus Rts 149 & 151 2.5 Mi, ENE TLD 44-X Shailerville, Horton Rd. I.0 Mi, SE TLD 45-X Old Waste Gas Sphere Fence 0.1 Mi, E TLD 46-X Discharge Canal Fence 0.2 Mi, SE TLD 47 X Info Center 0.1 Mi WNW TLD
- Key: I Indicator C Control X - Extra sample not required tihe release points are the stack for terrestrial locations and the end of the discharge canal for aquatic locations.
" New wells at 0.4 miles SE may be used as a replacement for this location.
2-2
l k
Haddam Neck Station Annual Radiologic 1 Environm:ntal Operating Report 1998 Table 2-2 Technical Specification Sampline Freauenev & Tyne of Annivsis l .
la. Gamma Exposure - 14 Monthly Gamma Dose - Monthly EnvironmentalTLD 1b. Gamma Exposure- 25 Quanerly: N/A Accident TLD
- 2. Airbome Particulate Gross Beta - Weekly 7 Continuous sampler - weekly filter change Gamma Spectrum - Quarterly on composite (by location), and on individual filter if gross beta is greater than 10 times the mean of the weekly control station's gross beta results
- 3. Vegetation 4 One sample near middle & Gamma Isotopic on each sample one near end of growing season
- 4. Milk 6 Monthly Gamma Isotopic on each sample - Monthly Sr-89 and Sr Quarterly
- 42. Pasture Grass 6 Sample as necessary to Gamma Isotopic substitute for unavailable milk
- 5. Well Water 2 Quarterly Gamma Isotopic and Tritium on each composite
- 6. Bottom Sediment 3 Semiannually Gamma Isotopic
- 7. River Water 2 Quarterly Sample -Indicator Quarterly - Gamma Isotopic and Tritium is continuous composite; Background is composite of six weekly grab samples i g, Fish (edible portion)- 3 Quarterly Gamma Isotopic - Quanerly bullheads and, when available, perch or other edible fish l
- 9. Shellfish 2 Quarterly Gamma Isotopic - Quarterly
- Accident monitoring TLDs to be dedosed at least quarterly l l
l 2-3 j
i l
Haddam Neck Station Annual R diological Environmental Operating Report 1998
- j Figure 2.1 Haddam Neck Station Sample Stations
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i Haddim Neck Station Annual Radiological Environmental Operating Report 1998 l
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l Haddam Neck Station Annual R-diological EnvironmIntal Operating Report 1998 i 2.2. Samples Collected During Report Period The following table summarizes the number of samples of each type collected during the present reporting period:
I kNN N N hk$ib .. E l 4 58
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!@lmM #$$N[$MNM, 1 hk NElil!Eb 4 N Gamma Exposure- 168 168 96 Environmental TLD Air Particulates 364 364 0 )
Dairy Milk 48 44' 0 Goat Milk 24 18' O Pasture Grass " 0* 3"*
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Well Water 8 8 8 Fruit & Vegetables 8 8 0 Broad Leaf Vegetation 4 4 9 River Water 8 8 0 Bottom Sediment 6 6 0 l Fish 24 24 0 Shellfish 8 8 4 Total AllTypes 670 660 120 Due to sample unavailability, less than required number of samples were obtained.
" Sample as necessary, during the months of April through December, to substitute for unavailable milk.
- " Three of ten unavailable milk samples occurred during the months when a pasture grass ;
sample is required as a substitute. Hay was collected in lieu of pasture grass due to l unavailability of grass.
2-6
Haddam Neck Station Anaual Radi: logical Environmental Oper: ting Report 1998
. l
- 3. RADIOCHEMICAL RESULTS l 3.1. Summary Table in accordance with the Radiological Effluent Monitoring Manual (REMM), Section F.1, a summary table of the radiochemical and radiological analyses results has been prepared and is presented in Table 3 1. All analysis results are summarized including analysis results of extra, non-required samples.
In the determination of the mean, the data was handled as recommended by the Health and Safety L aboratory, Idaho and NUREG/CR-4007 (Sept.1984): all valid data, including negative values and zeros were used in the determination of the mean (see Part 3.2).
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 data summaries.
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Haddam Neck Station Annual Radiological Environmental Operating Repott 1998 NOTES FOR TABLE 3-1 -
A. For gamma measurements the (Minimum Detectable Level) MDL's :: LLD + 2.33. For all others, MDL = 2 x (the standard deviation of the background). These MDL's are based on the absence oflarge amounts ofinterfering activity (excluding naturally occurring radionuclides). Deviations by about factors of 3 to 4 can occur.
- The LLD at a confidence level of 95% is the smallest concentration of radioactive material in a sample that will be detected 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):
LLD =
E
- V
- 2.22
- Y
- exp (-Aht) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)
S, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropnate (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) 2 is the radioactive decay constant for the particular radionuclide 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 a defined apriorl(before the fact) limit representing the capability of a measurement system and not an aposteriori(after the fact) limit for a panicular 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 AnnualRadiological EnvironmentalOperating Report. I B. Analytical results are handled as recommended by HASL (" Reporting ofAnalyticalResultsfom NASL,"
letter by Leo B. Higginbotham) and NUREG/CR 4007 (Sept.1984). Negative values were used in the determination ofmean.
C. Nonroutine reported measurements (NRM's). These are results of samples that exceed the report levels of Table E 2 of the RadiologicalEj1uent Monitoring Manual.
D. First number is the number ofindicator measurements, the second is the number of control measurements. I E. Assuming 270 m' F. Assuming 1080 m' G. LLD for leafy vegetables.
H. LLD from the end of the sample period.
3-13
Haddam Neck Station Annual Radiol gictl Environmental Operating Report 1998 1
l 3.2. Data Tables
'Ihe data reported in this section are strictly counting statistics. The reported error is two times the standard deviation (20) of the net activity. Unless otherwise noted, the overall error (counting. sample J size, chemistry, errors, etc.)is estimated to be 2 to 5 times that listed. Results arc considered positive l when the measured value exceeds 1.5 times the listed 2a error (i.e., the measured value exceeds 30).
l Because of counting statistics, negative values, zeros 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 background biases, all the valid data are presented. In instances where zeros are listed after significant digits, this is an artifact of the computer data handling program.
Data are given according to sample type as indicated below.
- 1. Gamma Exposure Rate i
- 2. Air Particulates, Gross Beta Radioactivity J
- 3. Air Particulates, Weekly 1-131* j
- 4. Air Particulates, Gamma Isotopic
- 5. Air Particulates, Quarterly Strontium * -
- 6. Soi!*
- 7. Milk - DairyFarms ,
- 8. Milk - Goat Farms
- 9. Pasture Grass"
- 10. Well Water
- 11. Reservoir Water *
- 12. Fruits & Vegetables
- 13. Broad Leaf Vegetation
- 14. River Water
- 15. Bottom Sediment
- 16. Shellfish
- 17. Fish
- This type of sampling or analysis was not performed, therefore there is no table.
- Pasture grass was not available, therefore feed (hay) was collected as a substitute 3-14
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L Haddam Neck Station Annual Radi: logical Environmental Operating Report 1998
- 4. DISCUSSION OF RESULTS I
This section summarizes the results of the analyses of environmental media sampled. NNECO has carefully examined the data throughout the year and has presented in this section all cases where station related radioactivity could be detected and compared the results with previous environmental surveillance data. The only impact observed from the station was tritium detected in on-site wells during 1998. Subsections describe each particular media or potential exposure pathway. Any dose commitments from station-related exposures is insignificant as explained in Section 5.
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 airbome and vegetation samples.
Ra-226 and Th 228 results were variable and were observed in broadleaf vegetation, river water (one barely positive Ra 226), river bottom sediment, shellfish, and fish (one barely positive Ra-226).
Cs-137 and Sr-90, present because of atmospheric nuclear weapons testing of years past, were observed at levels similar to those of past years.
4.1. Gamma Exposure Rate (Table 1)
Gamma exposure from all sources of radioactivity is measured over periods of approximately one month using CaF (Mn) thermoluminescent dosimeters (TLDs). These dosimeters are strategically placed at a i number of on-site locations, as well as at inner and outer off-site locations. Glass bulb type TLDs such as I these, are subject to inherent self irradiation which has been experimentally measured for each dosimeter.
The results, shown in Table I have been adjusted for this effect. The range of this correction for field dosimeters is 0.4 pR/hr to 2.8 pR/hr, with a mean of approximately 1 pR/hr.
No indications of plant related exposure were observed. The exposure rate measurements exhibit the same trends as those of past years. These measurements demonstrate the general variations in background radiation between the various on-site and off-site locations and include gamma exposure from all sources ofradioactivity. )
1 4.2. Air Particulate Gross Beta Radioactivity (Table 2)
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 41 and Table 2.
Gross beta activity remained at levels similar to that seen over the last decade. Inner and outer ring monitoring locations showed no significant variation in measured activities. This indicates that any station contribution is not measurable.
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4-1
1 Haddam N ck Stati:n Annu:1 Radiological Environmental Operating Report 1998 Figure 4-1 CY AIR PARTICULATE pcums 1998 Gross Beta Radioactivity 0.036
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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 4.3. Airbornelodine (Table 3)
Because the station permanently shutdown in 1996 all radioactive iodines, which have shon half-lives, have decayed away. Therefore the requirement to sample airbome iodine has been removed from the Radiological Efiluent Monitoring Manual (REMM) and no samples were collected in 1998.
l 4.4. AirParticulate Gamma (Table 4A D) )
The weekly air paniculate filters are composited quanerly for gamma spectral analyses. The results, as shown in Tables 4 A-4D, indicate the presence of naturally occurring Be 7, which is produced by cosmic j processes. No positive results were observed for all the other isotopes. These analyses indicate the lack {
of station effects.
l 4.5. AirParticulate Strontium (Table 5) )
Table 5 in past years was used to repon the measurement of Sr 89 and Sr-90 in quarterly composited air paniculate filters. These measurements are not required by the REMM and have been discontinued.
Previous data has shown the lack of detectable station activity in this media. This fact, and the fact that milk samples are a much more sensitive indicator of fission product existence in the environment, l prompted the decision for discontinuation.
4.6. Soll (Toble 6)
Soil samples are not required by the REMM.
l l
4-2
Haddam Neck Station Annual Radi: logical Environm:ntal Operating Report 1998 l
4.7. CowMilk (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, resuhs in this pathway usually being the most critical from the station release viewpoint. This pathway also shows measurable amounts of nuclear weapons testing fallout. Derefore, this media needs to be evaluated very carefully when trying to determine if there are any station effects.
Previous data over many years has shown the lack of station related strontium activity in this media. t Derefore, the strontium analysis frequency is quarterly, rather than monthly. The monthly samples collected within each quarter from each sample location are composited and analyzed at the end of each quarter. Sr 90 was observed in nearly one half of all samples; the highest value observed was 4.8 pCi/1.
Detailed analysis of previous data has concluded that these levels of Sr-90 are from weapons testing and are not station related (see Section 6.0 for details to this argument).
Cs-137 usually shows the same tendencies as Sr 90. Results for 1998 are similar to those seen for nearly the past two decades. Detailed analysis has concluded that these concentrations are most likely the resuh of fallout from previous nuclear weapons testing (see Section 6.0 for details).
Although not listed on Table 7, the only other nuclide detected by gamma spectrometry was naturally occurring K-40.
4.0. GoatMilk (Table 8)
Depending on the feeding habits, goat milk can be a more sensitive indicator than cow milk of fission products in the environment. His is due to the metabolism of these animals. Similar to the results of the cow milk samples, these show measurable amounts of nuclear weapons testing fallout.
Sr 90 and Cs 137 were observed in most samples, ne levels observed are due to residual radioactivity in the environment from nuclear weapons testings in the 1960s. The variabili ty in the results this year as well as in past years is caused by many factors, including feeding habits (amount of stored feed, etc.), soil characteristics, farmina practices (tillage and quality of fertilization and land management), and feed type.
For a complete discussion of the problem see Section 6.0.
4.9. Pasture Greas (Table 9)
When the routine milk samples are unavailable, samples of pasture grass are required as a replacement during the months of April through December. Dese samples may also be taken to further investigate the levels of radioactivity in milk. Directives since mid-year have been to sample feed (e.g., hay) if pasture grass is also unavailable. During the winter months and early spring, insufficient growth prohibits sampling of pasture grass as a replacement sample. Because of unavailability of pasture grass during November and December, feed (hay) was collected as a substitute for the pasture grass. No station effects were seen in the feed.
4.10. . WnliWater (Table 10)
Activity in this media results from either soluble station effluents permeating through the ground or the leaching of naturally occurring nuclides from the soil and rock. In 1998, samples of well water from the onsite stations (location 15) were taken monthly even though the requirements per the REMODCM are to sample quarterly. Because H 3 instation liquid effluents is the predominant radionuclide present, the higher sampling frequency was implemented to enhance program monitoring effectiveness. On-site wells (location 15) exhibited station related H 3 above background levels. His station effect results from the wells being located within an area influenced by the water in the discharge canal and H 3 having the ;
ability to readily follow the flow of ground water. Off-site concentrations are much lower. This pathway i does not result in any dose consequence since the water from these wells is used only in process streams at the station.
4-3 1
r Haddam Neck Station Annual Radiological Environmental Operating Report 1998 On-site H 3 levels detected in 1998 sampics show a decrease compared to prior years. This is a trend that started back in cycle 17 (1992) due to replacing stainless steel clad fuel with zircaloy clad fuel. The levels of H-3 observed since permanent shutdown in July 1996 represent residual levels of tritium that remain in station process liquids and/or groundwater from beneath the site that are gradually dropping to natural background levels. Figure 4-2 shows the trend of H-3 measured in CY on site wells since 1988. Of note in the figure is the highs and lows observed in measured levels of H 3. Dese swings are coincident with station operations. Higher H 3 levels are observed during periods when increased volumes ofliquid processing occurred in preparation for station outages.
Figure 4-2 H 3 Levels in On-site Wells g.r
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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 station effluents in this media has resulted in discontinuing these samples.
4.12. Fruits and Vegetables (Table 12)
His media did not show any station effects. Naturally occurring K-40 was detected in all samples and cosmically produced Be-7 was detected in one sample. Since there was no fresh fallout, no other nuclides were detected.
4.13. Broad Leaf Vegetation (Table 13)
Concentrations of Cs-137 seen in several of these samples are at levels comparable to past years and are due to fallout. To enhance program monitoring effectiveness, samples of broadleaf vegetation are collected monthly during the growing season, May - October, even though requirements are to collect twice a year. No station effects were observed in broadleaf samples.
4-4
Haddam Neck Station Annual Radiologic:1 Environm:ntal Operating Ripon 1998 4.14. River Water (Table 14)
These samples are collected on a quanerly basis; the sampling procedure is different at the control and indicator locations. Six weekly grab samples are taken within each quarter and composited for the control j station (Middletown - location 30C). Continuous sampling, an automatic process of compositing a small volume of sample periodically over an entire quaner, is utilized at the indicator r,tation (East Heddam Bridge - location 28).
Examination of the data shows there were no H-3 measurements that exceed 1.5 times the listed 2a error.
Even though H 3 measurements at the indicator location (Loc. 28) appear significantly higher than the control location (Loc. 30C), the values reported are the effect of counting statistics. Although measurable levels of tritium above background have been detected in the past; there have been no positive indications of tritium in this media since 1994.
4.16. Bottom Sediment (Table 16)
There were positive indications of Cs-137 in several samples, including the control location. Because the indicator and control samples show similar levels, the source of this Cs-137 is from weapons fallout deposited in woodlands and washed out into water bodies. No indications of station related activity were ,
observed in this sample media.
4.16. SheIlfish (Table 16)
As in previous years, no station related activity was observed. This media is not a source of consumption.
4.17. Fish (Tables 17A and 178) 4.17.1. Bullheads (Table 17A)
No station related activity was observed.
4.17.2. Perch and Other Types (Table 178)
As observed in the past, there was no positive indication of radioactivity in this media from the station, including Cs 137. Even though the measured values at the indicator locations do not exceed 1.5 times the listed 2a error and are the effect of counting statistics, the results will be conrrrvatively treated as a pysible positive results in order to perform a dose consequence analysis in Section 5.0.
]
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m Haddam Neck Station Annual Radiological Environm::ntal Operating Rcport 1998
- 6. OFF-SITE DOSE EQUIVALENT COMMITMENTS De off site dose consequences (dose equivalent commitments) of the stations' radioactive liquid and airbome effluents have been evaluated using two methods. De first method utilizes the stations' measured radioactive discharges as input parameters into conservative models to simulate the transport mechanism through the environment to man. His results in the computation of the maximum doses to individuals and the O to 50 mile population dose. De resuhs of these computations are submitted to the NRC in the Annual Radioactive Effluent Report written in accordance with the Radiological Effluent Monitoring Manual, Section F.2. He second method utilizes the actual measurements of the concentrations of radioactivity in various environmental media (e.g., milk, fish) r.nd then computes the dose consequences resulting from the consumption of these foods.
De 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. His 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. For gaseous releases, extremely low concentrations of Cs-137 were released in 1998 for a short period of time. De only other station related activity observed in 1998 was H 3 in on-site well water. On-site well water is used for station processing and services, it is not a pathway for human consumption. Levels of Cs-137 observed in fish, although not plant related, were used to conservatively predict dose consequences as if the radioactivity were the result of station decommissioning operations.
Summarizing the data presented in Table 5.1:
MAXIMUM TOTALINDIVIDUAL DOSES:
%710LE BODY = 0.2 mrem (Adult)
LIVE 3t = 0.27 mrem (Teen) ne average dose to an individual within 50 miles from the site using method 1 yields the following results for the period January - December 1998 for the average individual:
ANNUAL AVERAGE %110LE BODY DOSE :
DUE TO AIRBORNE EFFLUENTS = 0.00002 mrem DUE TO LlQUID EFFLUENTS = 0.00063 mrem Dus, 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 5.1. J In order to provide perspective on the doses in Table 5.1, the standards for 1998 on the allowable maximum dose to an individual of the genecal 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 dose of 284 mrem per year and are designed to be inconsequentialin regard to public health and safety. Station related doses are a small fraction of the standard as set by the Envirors.cntal Protection Agency and of the variation in natural background in Connecticut. Station related doses pose insignificant public heahh consequences.
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Haddam Neck Station Annual Radiological Environmental Operating Report 1998 TABLE 5.1 - COMPARISON OF DOSE CALCULATION METHODS HADDAM NECK STATION 1998 Annual Dose (millirem) hM[r{pitifyy, jgggggfdkh.Ni]$UlfEn'R Q M M d'1$ish .hMethod 2$.:
Airbonne Egluena 1
- 1. Extemal Gamma Dose Max. Ind.m Whole Body 0.00015 ND'*
i
- 2. Inhalation Teen Whole Body 0.051'M NAD*
Liver 0.051(*
LiquidEDluena
- 1. Fish Pathway onlym
- Adult Whole Body 0.15m <0.042'"
Teen 0.082 <0.023 Child 0.032 <0.009
- Adult GI(LLI)'4 0.0078 <0.0012 Teen 0.0058 (0.0009 Child 0.0025 <0.0004 Adult Liver 0.22 <0.064
- Teen 0.22 <0.066 Child 0.20 <0.060 Notes:
(1) Method I uses measured station discharges and meteorological data as input parameters to conservative transport to man models. mwd 2 uses actual measured concentrations in environmental media.
(3) Maximum individual The maximum individual dose is the dose to the most critical age group at the location of maximum concentration of station related activity. The dose to the average individual is much less than the maximum individual dose. The doses for inhalation and vegetable consumption assume that the individual resides at the point of maximum quanctly dose. Therefore, his residence is sub. ject to variation for conservatism.
(3) NAD - No activity detected above the minimum detectable level.
(4) ND Not Detectable - The station effects at all off-site locations were so small that they could not be distinguished from fluctuations in natural background.
(5) Gl(LLI)- Gastrointestinal Tract - Lower Large Intestine.
(6) Dose is primarily due to the release of tritium (H 3)in airborne effluents. Since tritium effects nearly all organs equally, the resulting dose to the whole body from inhaling tritium is the same.
(7) The dose values listed for the fish pathway represent the liquid dose pathway to man that is calculated using Method I conservative computer models.
(8) The dose values represent the dose consequences for eating fish with Cs 137 present from weapons fallout.
52
Haddam Neck Station Annual Radiological Environmental Operating Report 1998
- 6. DISCUSSION De evaluation of the effects of station operation on the environment requires the careful consideration of many factors, nose factors depend upon the media being affected. They include station release rates, effluent dispersion, fallout distribution from past nuclear weapons tests, redistribution of tallout dut to weathering and biotic activity, soil conditions (mineral content, pH, etc.), quality of fertilization, quality of land management (e.g., irrigation), peduring 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 mik samples. Dis is an important problem because this product is widely consumed and flasion products readily concentrate in this media. Some of these fission products, such as Sr 89 are relatively short-lived. Derefore they result from either station effluents, nuclear weapons tests or nuclear incidents (e.g. Chernobyl). The long-lived radionuclides of Sr 90 and Cs-137 are still remaining from the weapons testing era of the 1960's resuking in measurable amounts in milk samples. Distinguishing between this " background" of fallout activity and station effects is a difficult problem.
In reviewing the Sr-90 and Cs-137 measured in cow and goat mik in the areas around the Haddam Neck station, 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 station's effluents might at first appear to be responsible. However, the following facts prove this conclusion wrong.
(1) De station accurately measures the long-lived fission products 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, show that insufficient quantities of Sr 90 and Cs-137 have been released from the -
stations to yield the measured concentrations in milk.
(2) Although the shorter half life isotopes of Sr-89 and Cs-134 have decayed away, their general absence in environmental samples in the past suggest that the isotopes of Sr-90 and Cs 137, presently seen in the environment, are not station related. Over the many years of station operation, Sr-89 has often been released in comparable quantity to Sr-90, as well as Cs 134 to Cs-137. Since the pairs ofisotopes are chemically similar according to their elemental forms, comparable levels should have been detected in milk if Sr 90 and Cs-137 were station related. No station related Sr 89 or Cs 134 have ever been detected in milk samples, or in any other media.
The only occunences of detectable Cs-134 in milk resulted from the Chernobyl incident.
(3) Since dairy milk sampling began in the 1960's, several years prior to station operation, the immediate station areas have always shown higher levels of weapons fallout related St-90 and Co-137 (see Figures 61 and 6-2). De ratio of activity between the locations has not changed with station operation All areas show the same significant decrease in radioactivity since the 1964 Nuclear Test Ban Treaty.
(4) Local variability of Sr-90 and Cs-137 in milk is common throughout the United States. Due to the variability in soil conditions, pasturing methods, rainfall, etc., it is the rule rather than the
- exception. Derefore, 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.)
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)
Haddam Neck Station Annual Radi: logical Environmental Operating R port 1998 Based on these facts, it is concluded that station effluents are not responsible for variations of Sr 90 and Cs 137 in environmental samples. The cause must be one or more of the other variables.
Northeast Nuclear Energy Company has carefully examined the data throughout the year and has presented j in this report all cases where station related radioactivity can be detected. An analysis of the potential exposure to the population from any station related activity has been performed and shows that in all cases the exposureis insignificant.
As in previous years, this data is being submitted to, and will be reviewed by the sppropriate regulatory I bodies such as the Nuclear Regulatory Commission, Environmental Protection Agency and Connecticut I Department of Environmental Protection.
)
l 6-2
Haddam Neck Station Annual Radiologicd Environm:ntal Operating Report 1998 Firure 6-1 Strontium-90 in Milk j
pCMder 25
+CT Pooled Mik
{
20 -G-Haddam area Mik . I
.g. Millstone area Mik 15 5 l i
to ,
AA a a r.
J 6 - -
, u A m.a 0 . ... . . . . . . . . . . . . . . ... . ~~Y ,
61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 91 93 95 97 l Year Firure 6-2 Cesium-137 in Milk gmner 140 a
120
}] +CT Pooled Mik Haddam area Mik
' 4 Millstone area Milk 100 ,
80
\
\
60 i l j
'"/ h i o
mn+ A
,,,,....."..... h.. -e,95t -----
61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 91 93 95 97 Year Dain milk is no longer available in the Millstone area and CT Pooled milk has not been collected by the State of CT since 1994.
CY Start-up occurred: July 24, IM7 MPI Stan-up occurred: October 26,1970 MP2 Stan-up occurred October 17,1975 MP3 Stan-upoccurred: January 23,1986 6-3
HaddamNeck Station Annual Radiological Environmental Operating Report 1998 APPENDIX A LAND USE CENSUS FOR 1998 )
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A-1
HaddamNeck Station Annual Radiological Environm:ntal Operating R: port 1998 TABLE A-1 (name 1 of 2) -
Dairy Cows Within 15 Miles of Conneetleut Yankee -December 1221 i
Direction plaingst Name and Address # of Cows NNE 14 M Allen Hills Hills Farm 185 527 Gilead Street Hebron,CT 06248 NNE 14 M Edward Ellis 176 Mapleleaf Farm,Inc.
768 Gilead Street Hebron,CT 06248 NNE 14 M Gordon N. Rathburn 36 Manin Road Hebron,CT 06248 NNE 14.5 M Douglas i'oner 140 14 Poner Rd.
Hebron,CT 06248 NE 8M Elizabeth Gilman 32 178 Cato Comer Rd.
Colchester,CT 06415 NE 14 M Victor Botticello 40 302 Levita Road Lebanon,CT 06249 ENE 6.5 M Roben Cone 60 Grandpa Hill Farm Box 251 318 Old Colchester Tpke >
East Haddam,CT 06423 ENE I1 M Richard Swider 46 475 New London Rd.
Colchester,CT 06415 j E 11.5 M Eugene Wilczewski 45 Salem Valley Farm Dairy 200 Darling Road i Salem,CT 06415 l E 14 M Stuan Gadbois 225 40 Old Colchester Rd.
Salem,CT 06415 j SE II M John Tiffany til 85 Tiffany Farms 156 Sterling City Road Old Lyme, CT 06371 A-2 1
HaddamNeck Station Annual Radiological Environmental Operating Report 1998 TABLE A-1 (cane 2 of 2)
Dairy Cows Within 15 Miles of Connecticut Yankee - December 1998 l
Direction Distance Name and Address # of Cows WSW 8M Michael Dwyer 30 1 63 Grieb Rd.
Wallingford,CT 06492 WSW 8M Roben Raudat 44 909 Durham Road Killingworth,CT 06417 WSW II M Raymond Wimler 190 533 Guilford Road Durham,CT 06422 WSW 14 M John & Edward Cella 150 Cella Brothers Farm 2 No. Brandford Street Wallingford,CT 06492 WSW 15 M David & Kirsten Footit 140 D & K Fann 81 School St.
Wallingford, CT 06492 W 11.5 M Tony Caltabiano 45 Friendly Acres Dairy Farm 145 Parmalee Hill Road Durham,CT 06422 W 14 M Walte- Werbiski 21 North Farms 1069 Farms Road Wallingford,CT 06492 W 14.5 M Charles Greenback & Sons,Inc. 170 182 Wallingford Rd.
Durham,CT 06422 NW 13 M Higgins Farm,Inc. 79 837 Ridgewood Road Middletown,CT 06457 NW 15 M Joan Bryck or Jean Backiel 51 Riverside Farm i160 France St.
Rocky Hill, CT 06067 A-3
Haddam Neck Station Annual Radiological Environm:ntal Operating Report 1998 l l
TABLE A-2 (page 1 of1) l Dairy Goats Within 20 Miles of Connecticut Yankee - December 1998 Direction Distance Name and Address Total Goats NNE 12 M Louise Sage 4 155 Reidy Hill Road Hebron, CT 06248 NNE 16 M Joan Bowers 2 350 Wall Street Hebron, CT 06248 NNE 16 M Kathy Waters 70 i Bumt Hill Road l Hebron, CT 06248
{
SSE 3.6 M Virginia Marshall 6 Old County Road Haddam, CT 06438 SE 19.5 M Mrs. John Mingo 7 69 Spithead Road Waterford, CT 06385 SE 15.8 M George Scacciafeno 2 338 Boston Post Road East Lyme, CT 06333 S 11.5 M Victor Trudeau 5 174 Horse Hill Road Westbrook,CT 06498 W 15.3 M Jim & Mary Hall Petlack 12 1000 North Farms Road Wallingford,CT 06492 WNW 19 M Daniel Nitkowski 4 46 Firch Avenue Meriden, CT 06450 NNW 14 M Dorothy Joba 10 171 Ferry Lane S. Glastonbury, CT 06073 NNW 15 M Donald Reid
- 1654 Main Street Glastonbury, CT 06033
- UNABLE TO CONTACTAS OF THIS TIME.
A-4
HaddamNeck Station Annual Radiological Environmental Operat tag Report 1998 TABLE A-3 (page 1 of1) -
1998 Resident Survey conducted August 1998 Downwind Distance Sector Direction (Meters)
A N 1150 B NNE 1780 C NE 1265 D ENE 1710 E E 1955 F ESE 2740 G SE 1410 H SSE 940 J S 980 K SSW 860 L SW N0 M WSW 1140 N W 1360 P WNW 660 Q NW 750 R .N N W 1495 l
A-5 I b
)
HaddamNeck Station- Annual Radiolog ical Environmental Operating Rrport 1998 4
APPENDIX B 1
NNECO OA PROGRAM 1
i i
B-1 j
n HaddamNeck Station ' Annual Radiological Environmental Operating Report 1998 i
INTRODUCHON -
Northeast Nuclear Energy Company (NNECO) acting as the agent for the Connecticut Yankee
~ Atomic Power Company (CYAPCO), maintains a quality assurance (QA) program as part of the radiological environmental monitoring program (REMP). The QA program consists of contractor appraisals, quality control samples, and quality control testing of environmental TLDs.
NNECO QA PROGRAM Appraisals are conducted of the primary (Duke) radioanalysis contractor, of the Production j Operations Support Laboratory (POSL), and of the NNECO Radiological Engineering Section (RES). A REMP evaluation form is completed for each appraisal and discrepancies are tracked on a separate form until corrective action is taken. De primary contractor, POSL, and RES are also audited by other organizations; the contractor by other customers, and POSL and RES by Northeast Utilities Nuclear Oversight Department.
There are two types of NNECO QA Program quality control samples - spikes and duplicates.
Sample spikes are a check on the accuracy of results of the contractor's radionnalyses. Duplicate J samples are a check of the contractor's precision or reprcducibility of results. De number and type of NNECO QA Program quality control samples are given in Table 1. De results of the contractor's analyses of NNECO quality control samples must satisfy acceptance criteria in Procedure RAB B-3, " Quality Control of Radiological Environmental Monitoring Program Sample Analyses." An investigation is conducted of any result or trend which does not satisfy acceptance criteria. , i There are two types QA Program tests of environmental TLDs - spikes and field comparisons. l Spike testing involves the exposure of four TLDs each month. POSL readouts of the spiked TLDs are compared to the known radiation exposure. For field comparisons, QA TLDs of a different design from the REMP TLDs, are co-located with REMP TLDs at eight locations and processed at the Nontheast Utilities Dosimetry Laboratory. Readings of the QA TLDs are compared to POSL's REMP TLD readings. De comparison results must satisfy =cca;*= ace criteria in NNECO Radiological Assessment Branch Procedure RAB B-2," Quality Control of the Environmental TLD Monitoring Program." An investigation is conducted on any result or trend which does not satisfy acceptance criteria.
OTHER QA PROGRAMS l The NNECO QA Program is not the only QA Program which monitors REMP radionnalyses performance. Other prograras include:
- 1. Duke's internal QA program. In addition to the NNECO quality control samples the radioanalysis contractor has it's own quality control samples. In total, at least five percent of the contractor's sample analyses include quality control samples. j
- 2. Duke's interldcnn.iy compari' on s program with an independent third party, Analytics, Inc.
Results of the Analytics intercomparison are contained in Appendix C. Primary contractor
- participation in an interlabortary comparison program is required by station Technical !
I Specifications. De Analytics comparison satisfies this requirement and is supplemented by the EPA Intercomparison Studies Program.
)
B-2
. l
HaddamNeck Station Annual Radiological EnvironmIntal Operating Repon 1998
- 3. Duke's participation in EPA's Environmental Radioactivity Laboratory Intercomparison Studies Program. Duke participates in EPA's program because of their analyses of drinking water, not because of nuclear power station environmental sample analyses. However, some of the EPA intercomparison samples are also applicable to nuclear power environmental samples. Results of the EPA Intercomparison Studies Program are contained in Appendix C.
RFRULTS OF NNECO OA PROGRAM FOR CONTRACTOR RADIOANALYSES The NNECO QA Program indicated that Duke's environmental radiological analysis program was adequate in 1998. Of 103 analysis results on QA samples,99 passed criteria, a 96% success rate.
There were two air particulate gamma analyses which exceeded the criterion of being within 20% of the spiked value - both I-131 sample spikes, one at minus 23% and one at minus 30%.
Although three other I-131 spikes on filter passed criteria in 1998, an negative bias for results of I-131 on filter analyses has been noted. This bias is currently under investigation.
' There was one gross beta air paniculate analysis which exceeded the criterion of being within 20% of the spiked value at minus 27%. The failure occurred because of a change in the method of preparing the QC sample. This was corrected by reverting back to the previous method and four subsequent QC samples in 1998 were within the criterion.
There was one strontium in milk QC sample which exceeded the criterion of being within 30%
of the spiked value at plus 58%. The cause of the failure was that the source was expired. It was discarded and a new source was ordered.
RESULTS OF NUSCO OA PROGRAM FOR ENVIRONMENTAL TLDS Eleven of the monthly TLD spike tests satisfied procedural criteria. One TLD spike test failed low because of a personnel error in spiking the test TLDs. A corrective action was identified for preventing a repeat of the spike test personnel error, The corrective action was implemented effective with the November test.
All twelve of the field comparisons satisfied procedural criteria.
B-3
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 TABLE B 1 (page I of1)
NUMBER OF QUALITY CONTROL SAMPLES 1998
$ N[ b f . - .
TLDs - Field Comparison 12
- 528
- Spike 12 m 528 Milk - Strontium SW 32")
Milk - Gamma 60 m 800 Water Gamma 60 576 Water Tritium 3 32 Fish / Invertebrate Gamma 3 2004 Fruits & Vegetation & Sediment Gamma 0 2079 Air Particulate -
Gross Beta 7 832
- Gamma 25 740 FOOTNOTES (1) Includes both Millstone and Haddam Neck (2) Each TLD field comparison sample is comprised of a set of 8 TLDs.
(3) Each TLD spike sample is comprised of a set of 4 TLDs.
(4) Sr-89 and St-90.
(5) Gamma in water QA spikes are treated as milk sunogates.
B-4 l
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 TABLE B 2 (page 1 of1)
RESULTS OF QUALITY CONTROL SAMPLE ANALYSES #
1998
'. '. .?ll!W.? *; -
.. p k,l $ I &*Yb:y ; p . ( G ' I'$IN ;$.g
.... ,q s :r.4 i , + - .+ggit , ; 3.s a ; ,- .
TLDs -
Field Comparison 12 0 Spke 11 1 Milk - Strontium 4m 1 Water - Gammam 60 0 Water - Tritium 3 0 Oysters - Gamma
- 3 0 Air Particulate '- Gross Beta 6 1 GammaM 23 2 TOTALS TLDs: 23 TLDs: 1 Samples: 99 Samples: 4 FOOTNOTES (1) Sr 89 or Sr-90. ,
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Haddam Neck S'.ation Annual Radiological Environmental Operating Report 1998 l
APPENDIX C
SUMMARY
OF INTERLABORATORY COMPARISONS i
I C-1
Haddam Neck Station Annual Radiolrgical Environmental Operating Report 1998 INTRODUCTION This appendix covers the Intercomparison Program of the Duke Engineering and Services Environmental Laboratory (DESEL) as required by technical specifications for each Millstone unit.
DESEL uses QA/QC samples provided by Analytics, Inc to monitor the quality of analytical processing associated with the Radiological Environmental Monitoring Program (REMP). The suite of Analytics QA/QC samples are designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program. It was modified to more closely match the media mix presently being processed by DESEL. All intercomparison results received by DESEL on or before January 31,1999 are included. Late results for 1998 will be reported in the annual report for 1999.
DESEL also receives intercomparison samples from the US EPA because of their drinking water analysis program. Results from analyses of these samples are included where they are applicable to I
the REMP.
ACCEPTANCE CRITERIA Intercomparison Program results are evaluated using two separate DESEL internal acceptance criteria. The first criterion concerns bias, which is defined as the deviation of any one result from the assumed known value. The second criterion concerns precision, which deals with the ability of the measurement to be faithfully replicated by comparison of an individual result with the mean of all results for a given sample set. A sample set is created by taking three aliquots from the same sample and submitting each as a blind replicate.
4 The bias criterion is defined as within 25% of the known value for Sr-89 or Sr 90 and within 15%
of the known value for other radionuclides, or within two sigma of the known value. This bias criterion is applied to both the Analytics and the US EPA intercomparison sample results.
For Analytics intercomparison sample results, the precision criterion is defined as an overlap of the two sigma ranges for the three replicate analyses. US EPA samples have EPA supplied criteria of lower and upper control level within which the average of the three replicate samples must occur.
R MULTS (All results are everacted from References 1 and 2.)
For 1998, bias testing results for 72 individual environmental analyses of seven Analytics intercomparison samples are listed in the table on the following two pages. All of the analyses passed the bias criteria. Replicate sample results are not reported in References 1 and 2; however the references do report that, of the 72 environmental analyses for the seven samples there was only one result which failed the precision criterion. "Ihis was the low-level (LL) 1-131 analysis for the third quarter water sample. DESEL issued CR 98-009 to investigate the failed precision test. The result of this investigation is not yet available.
Results of bias and precision testing on the US EPA intercomparison samples are contained in the table on Pages C-5 and C-6. Of 42 individual analyses of EPA samples,40 passed the bias criteria, a 95% success rate. There were no failures of precision criteria for the EPA samples.
REFERENCES
- 1. DESEL Analytical Services Semi-Annual Quality Assurance Status Report, January-June 1998
- 2. DESEL Analytical Services Semi-Annual Quality Assurance Status Report, July-December 1998 C-2
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Haddam Neck Station Annual Radi: logical Environm:ntal Operating R: port 1998 TABLE C-1 (page 1 of 3)
ANALYTICS INTERCOMPARISON PROGRAM 1998 BIAS TESTING d?TM. D. w e;e t R1,e F I,$. - IAM:ety' '
- 1r,0,N . X 21 #"w ist Milk Sr 89 53 pCi/L 55 pCi/L 1.04 Sr-90 44 45 1.02 Cr 51 201 204 1.01 Mn-54 133 139 1.05 Co-60 85 86 1.01 Fe-59 95 100 1.05 Zn-65 142 147 1.04 1 131 82 84 1.02 1-131 (LL) 82 83 1.01 Cs-134 84 83 0.99 Cs-137 161 171 1.06 Ce-141 70 73 1.04 Ist Water Beta 269 pCi/L 308 pCi/L 1.14 Cr-51 167 171 1.02 Mn-54 111 111 1.00 Co-60 71 70 0.99 Fe-59 79 82 1.04 Zn-65 118 120 1.02 l-131 90 90 1.00 1-131 (LL) 90' 92 1.02 J
Cs-134 70 68 1.01 Cs-137 134 136 1.02 Cc-141 58 59 1.06 Ra 226 53 56 1.02 Ra-228 46 47 2nd Air Filter Beta 212 pCi/ filter 220 pCi/ filter 1.04 Sr-89 142 140 0.99 i Sr-90 51 49 0.96 Cr-51 113 111 0.98 Mn-54 91 96 1.05 Co-60 124 116 0.94 Fe-59 39 43 1.10 l Zn-65 105 114 1.09 i Cs-134 82 84 1.02 Cs-137 61 62 1.02 Ce-141 85 80 0.94 l 2nd Water H-3 6007 pCi/L 5697 pCi/L 0.95 i
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Haddam Neck Station Annual Radiological Environm:ntal Operating Rrport 1998 TABLE C-1 (page 2 of 3)
ANALYTICS INTERCOMPARISON PROGRAM 1998 hk.Ur:i.!,%Cf.VN?6t<- .* AR n . ' . XOWW 3.3 W
- 2nd Milk Cr-51 132 pCi/L 128 pCi/L 0.97 Mn-54 106 111 1.05 Co-60 143 144 1.01 Fe-59 45 46 1.02 Zn-65 122 124 1.02 1-131 67 71 1.06 1 131 (LL) 67 67 1.00 Cs 134 95 97 1.02 Cs-137 70 74 1.06 Ce-141 99 102 1.03 3rd Milk Sr-89 51 pCi/L 62 pCi/L 1.22 Sr 90 81 72 0.89 Cr-51 186 180 0.97 Mn-54 74 77 1.04 Co-60 148 146 0.99 Fe-59 63 66 1.05 Zn-65 195 201 1.03 1 131 90 96 1.07 1-131 (LL) 90 87 0.97 Cs-134 82 80 0.98 Cs-137 134 134 1.00 Cc-141 146 145 0.99 1
l 3rd Water Sr 89 84 pCi/L 83 pCi/L 0.99 Sr-90 51 47 0.92 Beta 198 190 0.96 Cr-51 165 172 1.04 l Mn 54 66 66 1.00 l Co-60 131 129 0.98 Fe-59 55 59 1.07 Zn-65 173 175 1.01 1-131 79 82 1.04 1-131 (LL) 79 78 0.99 i Cs-134 73 71 0.97 Cs-137 119 117 0.98 Cc-141 129 129 1.00 l
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i Haddam Neck Station Annual Radiological Environmental Operating Report 1998 TABLE C-1 (page 3 of 3)
ANALYTICS INTERCOMPARISON PROGRAM 1998 x,,.a,L x a.c w x x ee.1:m y '.u w a : a...,,. w l
4th Milk Cr 51 195 pCi/L 205 pCi/L 1.05 Mn-54 80 83 1.04 l
Co-58 52 56 1.08 Co-60 94 96 1.02 !
Fe-59 57 62 1.09
{
Zn-65 141 144 1.02 l-131 39 42 1.08 l-131 (LL) 39 38 0.97 Cs-134 100 102 1.02 Cs-137 103 109 1.06 Ce-141 98 103 1.05 '
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- - _ _ _ _ _____o
Haddam Neck Station Annual Radiological Environmental Operating Repon 1998 TABLE C-2 (page 1 of 2) i U.S. EPA INTERLABORATORY COMPARISON STUDIES PROGRAM 1998 (all values in pCi/L) w, , . - "rg @ D 'i h d h .c -gj.n.-s,. m 6 $ T
,,m, , J^ ; .
1/16/98 Water Sr 90 32.0 23.3 40.7 28.42 29.26 27.50 2/6/98 Watu I-131LL 104.9 86.7 123.1 109.7 106.8 110.2 3/13/98 Water H3 2155 1551 2759 2147 2095 2044 4/21/98 Water Sr-89 9.3 5.3 13.3 7.8 8.81 10.3 4/21/98 Water Co-60 50.0 41.3 58.7 47.7 48.4 48.5 4/21/98 Water Cs-134 22.0 13.3 30.7 21.3 21.7 20.6 4/21/98 Water Cs-137 10.0 1.3 18.7 8.6 9.6 9.1 6/5/98 Water Co-60 12.0 3.3 20.7 11.5 12.6 11.4 6/5/98 Water Zn-65 104.0 86.7 121.3 105.3 106.6 99.9 6/5/99 Water Cs-134 31.0 22.3 39.7 28.9 27.8 26.9 6/5/98 Water Cs-137 35.0 26.3 43.7 34.9 36.3 34.1 C-6
HaddamNeck Station Annual Radiological Environmental Operating Report 1998 TABLE C-2 (page 2 of 2)
U.S. EPA INTERLABORATORY COMPARISON STUDIES PROGRAM 1998 (all values in pCi/L) e.~ ! .
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7/17/98 Water Sr-89 21.0 12.3 29.7 20.1 20.3 22.0 7/17/98 Water Sr-90 7.00 0 15.7 9.80 7.40 7.11 8/7/98 Water H3 17996 14873 21119 17656 17550 17446 9/11/98 Water I-131 6.10 2.60 9.60 6.04 5.95 4.85
- Same sample analyzed three times.
C-7
,A Northeast -
f Utilities
'\ *~.. c ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT {
{
l HADDAM NECK STATION l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i JANUARY 1,1998 - DECEMBER 31,1998 DOCKET NO. 50-213 LICENSE NO. DPR-61 l l
I Prepared for the CONNECTICUT YANKEE ATOMIC POWER COMPANY Haddam, Connecticut By the NORTHEAST NUCLEAR ENERGY COMPANY Waterford, Connecticut
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 <
TABLE OF CONTENTS
- 1.
SUMMARY
1-1
- 2. PROGRAM DESCRIPTION 2-1 2.1. Sampling Schedule, Types, and 14 cations 21 2.2. Samples Collected During Report Period 2-6
- 3. RADIOCHEMICAL RESULTS 3-1 3.1. Summary Table 3-1 3.2. Data Tables 3 14
- 4. DISCUSSION OF RESULTS 4-1 4.1. Gamma Exposure Rate (Table 1) 4-1 4.2. Air Particulate Gross Beta Radioactivity (Table 2) 41 4.3, Airborne lodine (Table 3) 4-2 4.4. Air Particulate Gamma (Table 4A-D) 4-2 4.5. Air Particulate Strontium (Table 5) 4-2 4.6. Soll (Table 6) 4-2 4.7. Cow Milk (Table 7) 4-2 4.8. Goat Milk (Table 8) 4-3 4.9. Pasture Grass (Table 9) 4-3 4.10. Well Water (Table 10) 4-3 4.11. Reservoir Water (Table II) 4-4 4.12. Fruits and Vegetables (Table 12) ,.
4-4 4.13. Broad Leaf Vegetation (Table 13) 4-4 4.14. River Water (Table 14) 4-5 4.15. Bottom Sediment (Table 15) 4-5 4.16. Shellfish (Table 16) 4-5 4.17. Fish (Tables 17A and 178) 4-5
- 5. OFF-SITE DOSE EQUIVALENT COMMITMENTS 5-1
SUMMARY
OF INTERLABORATORY COMPARISONS C-1 l
I l
Haddam Neck Station Annual Radiologicci Environmental Operating Report 1998 l
- 1.
SUMMARY
I De radiological environmental monitoring program for the Haddam Neck Station was continued for the period January through December 1998, in compliance with the Technical Specirmations and the Radiological Effluent
. Monitoring and Off Site Dose Calculation Manual (REMODCM). His annual report was prepared for the Connecticut Yankee Atomic Power Company (CYAPCO) by the Safety Analysis Branch of the Nuclear Engineering Department of Northeast Nuclear Energy Company (NNECO). Sample collection and preparation and gamma exposure rate measurements were performed by the Production Operations Services Laboratory i
- (POSL). Laboratory analyses were performed by Duke Engineering and Services Environmental Laboratory (DESEL).
Dermoluminescent dosimeters (TLDs) were used to measure direct gamma exposure in the vicinity of the station and as far away as 12.5 miles. Radiochemical and radiological counting analyses of samples were performed to detect the presence of any station related radioactivity. Samples included air particulates collected on flhers, milk, cow and goat feed (hay) broad leaf vegetation, well water, fruits, vegetables, river water, bottom sediment, shellfish, and fish. In evaluating the resuhs of these analyses it is necessary to consider the variability of natural and man-made sources of radioactivity, distribution in the environment and uptake in environmental media. His variability is dependent on many factors including station release rates, past spatial variability of radioactive fallout from nuclear weapons tests and on-going redistribution of the fallout, contribution from 1
. cosmically produced radioactivity, ground water dynamics, soil characteristics, farming practices, and feed type, i Significant variations in measured levels of radioactivity could be caused by any one of these factors.
Derefore, these factors need to be considered in order to properly explain any variations in radiation detected and to distinguish between natural and station related radioactivity.
Haddam Neck is permanently shutdown Primary activities at the Haddam Neck station are now focused on decommissioning.- Even though the station is no longer generating power, decommissioning activities included processing and discharging ofliquids containing radioactivity and releasing of airborne radioactivity. However, the levels of radioactivity released are significantly lower than releases during plant operation. De radiological
. monitoring of the environment through this program will continue to assure the heahh and safety of the public and workers are maintained at alltimes.
. De predominant radioactivity detected by the monitoring program was that from outside sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. As typical of previous years, station related
. radioactivity was observed at some of the on-site gamma monitoring locations. De only other observation of station effects was tritium in well water at the on-site location.
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 1960s and not the result of station decommissioning operations. This can be concluded because insufficient quantities of these isotopes have been released by the station to account for the -
measured concentrations. Higher levels of Cesium 137 and Strontium-90 were detected prior to initial plant operation and have been declining since the ban on nuclear weapons testing in the 1960s.
De radiation dose (dose equivalent commitment) to the general public from the station's discharges has been evaluated by two methods. One method utilizes measurements of station's discharges and conservative transport models and the other utilizes the measured concentrations of radioactivity in the environmental media.
De maximum whole body dose (station boundary) that could occur to a member of the general public was calculated to be 0.2 millirem. De average dose to a member of the public residing within 50 miles of the station is 0.00065 millirem. Dese doses are 0.8 percent and 0.0026 percent of the standard as set by the Environmental Protection Agency on the maximum allowable dose to an individual of the general public. De standards of the Environmental Protection Agency are a small fraction (less than 10 percent) of the 284 mrem per year normal
- Connecticut resident background radiation (NCRP94) and are designed to be inconsequential in regard to public hoekh and safety.. Station related doses are a small fraction of these standards and of the variation in natural background in Connecticut. Dey pose insignificant public health consequences.
k 1
r i Haddam Neck Station Annual Radiological EnvironmGntal Operating Report 1998 l
- 2. PROGRAM DESCRIPTION i
2.1. Sampilng Schedule, Types, and Locations The sample locations and the sample types and frequency of analysis are given in Tables 2-1 and 2 2 and Figures 2.1 and 2.2. The program as described here includes both required samples as specified in j the Radiological Emuent Monitoring and Off Site Dose Calculation Manual and any extra samples.
1 l
l I
4 S
l l
I 2-1
Haddam Neck Station Annual Radiological Environmontal Operating Report 1998 Table 2-1 Environmental Monitorine Pronram SamDIlnt Troes and Locations h
- . % N fh .
0 11 On-site - Mouth of Discharge Canal 1.1 Mi, ESE TLD 21 Haddam-Park Rd. 0.8 Mi, S TLD 31 Haddam4 ail Hill Rd. 0.8 Mi, WSW TLD 41 Haddam-Ranger Rd. I.8 Mi, SW TLD, Air Particulate 5-1 On-site-In,jun Hollow Rd. 0.4 Mi, NW TLD, Air Particulate 6-1 On site Substation 0.5 Mi, NE TLD, Air Particulate, Vegetation 71 Haddam I.8 Mi, SE TLD, AirParticulate 8-I East Haddam 3.1 Mi, ESE TLD, Air Particulate 9-1 Higganum 4.3 Mi, WNW TLD, Air Particulate 10 I Hurd Park Rd. 2.8 Mi, NNW TLD 11 C Middletown 9.0 Mi, NW n.D 12-C Deep River 7.1 Mi, SSE TLD 13-C North Madison 12.5 Mi, SW TLD, Air Particulate 14-C Colchester 10.5 Mi, NE TLD 15 1 On-site Wells 0.5 Mi, ESE" Well Water 16-C Well State Highway Dept. E. Haddam 2.8 Mi, SE Well Water 17-C Beyond 10 Miles Beyond 10 Miles Fruits & Vegetables 18-I Site Boundary 0.4 Mi, NW Vegetation 19-1 Cow Location #1 6.5 Mi, ENE Milk 20-1 Cow Location #2 8.0 Mi, NE Milk 21-1 Cow Location #3 11.0 Mi, SE Milk 22-C Cow Location #4 11.0 Mi, ENE Milk 23-C Goat Location #1 16.0 Mi, NNE Milk 24-1 Goat Location #2 3.6 Mi, SSE Milk 25 1 Within 10 Miles Within 10 Miles Fruits & Vegetables 26-1 CT River Near intake 1.0 Mi, WNW Fish 27 C CT River-Higganum Light 4.0 Mi, WNW Shellfish 28 I CT River-E. Haddam Bridge 1.8 Mi, SE Bottom Sediment, River Water 28-X CT River-E. Haddam Bridge 1.8 Mi, SE Shellfish 29-I Vicinity of Discharge Within 0.3 Miles Bottom Sediment, Fish 30-C CT River- Middletown 9.0 Mi, NW River Water, Bottom Sediment 7.6 Mi, NW Fish 31 1 Mouth of Salmon River 0.8 Mi, ESE Shellfish 40-X Near intake Structure 0.1 Mi, SSW TLD 41 X Picnic Area 0.3 Mi, WNW TLD 42 X Environmental Trail 0.1 Mi,NW TLD 43-X Moodus Rts 149 & 151 2.5 Mi, ENE TLD 44 X Shailerville, Horton Rd. 1.0 Mi, SE TLD 45-X Old Waste Gas Sphere Fen;e 0.1 Mi, E TLD 46-X Discharge Canal Fence 0.2 Mi, SE TLD 47 X Info Center 0.1 Mi, WNW TLD
- Key: I Indicator C - Control X - Extra sample not required tThe release points are the stack for terrestrial locations and the end of the discharge canal for aquatic locations.
" New wells at 0.4 miles SE may be used as a replacement for this location.
2-2
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 Table 2-2 Techalcal Snecification Samnline Freauency & Tyne of Analysis 1..')
- 13. Gamma Exposure - 14 Monthly Gamma Dose - Monthly Envirr.v~al TLD lb. Gamma Exposure - 25 Quanerly8 N/A Accident TLD
- 2. Airbome Particulate Gross Beta - Weekly 7 Continuous sampler - weekly filter change Gamma Spectrum - Quanerly on composite (by location), and on individual filter if gross beta is greater than 10 times the mean of the weekly cccol station's gross beta results l
- 3. Vegetation 4 One sample near midd.e & Gamma Isotopic on each sampla one near end of growing season
- 4. Milk 6 Monthly Gamma Isotopic on each sample - Monthly Sr 89 and Sr Quanerly
- 43. Pasture Grass 6 Sample as neces:.ary to Gamma Isotopic substitute for unavailable milk
- 5. Well Water 2 Quarterly Gamma Isotopic and Tritium on each composite
- 6. Bottom Sediment 3 Semiannually Gamma Isotopic
- 7. River Water 2 Quanerly Sample -Indicator Quanerly - Gamma Isotopic and Tritium is continuous composite; Backgroand is composite of
{
r six weekly a,rab samples )
g, Fish (edible portion)- 3 Quanerly Gamma Isotopic - Quarterly bullheads and, when available, perch or iI other edible fish g 9. Shellfish 2 Qt:rterly Gamma Im{pic -Quarterly
)
l 8 Accident monitoring TLDs to be dedosed at least quanerly 2-3 .
Haddam Nrck St: tion Annual Radiological Environment:1 Opersting Report 1998 Firure 2.1 Haddain Neck Station Sample Stations p o 1
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Haddam Neck Station Annual R-diological Environmental Operating Report 1998 2.2. Samples Collected During Report Period The following table summarizes the number of samples of each type collected during the present reporting period:
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Gamma Exposure- 168 168 96 Environmental TLD Air Particulates 364 364 0 Dairy Milk 48 44' 0 Goat Milk 24 18' 0 Pasture Grass " 0* 3"*
Well Water 8 8 8 Fruit & Vegetables 8 8 0 Broad Leaf Vegetation 4 4 9 River Water 8 8 0 Bottom Sediment 6 6 0 Fish 24 24 0 Shellfish 8 8 4 Total All Types 670 660 120
- Dae to sample unavailability, less than required number of samples were obtained.
" Sample as necessary, during the months of April through December, to substitute for ]
unavailable milk. I
"* Three of ten unavailable milk samples occurred during the months when a pasture grass sample is required as a substitute. Hay was collected in lieu of pasture grass due to unavailability of grass.
l l
2-6
Haddam Neck Station Annual Radiol:gical Environm:ntal Operating Report 1998
- 3. RADIOCHEMICAL RESULTS 3.1. Summary Table in accordance with the Radiological Effluent Monitoring Manual (REMM), Section F.1, a summary table of the radiochemical and radiological analyses results has been prepared and is presented in Table 3-1. All analysis results are summarized including analysis results of extra, non-required samples.
In the determination of the mean, the data was handled as recommended by the Health and Safety Laboratory, Idaho and NUREG/CR-4007 (Sept.1984): all valid data, including negative values and zeros were used in the determination of the mean (see Part 3.2).
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 i data summaries.
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Haddam Neck Station Annual Radiological Environmental Operating Report 1998 NOTES FOR TABLE 3-1 A. For gamma measurements the (Minimum Detectable Level) MDL's:: LLD + 2.33. For all others, MDL = 2 x (the standard deviation of the background). These MDL's are based on the absence oflarge amounts ofinterfering activity (excluding naturally occurring radionuclides). Deviations by about factors of 3 to 4 can occur.
The LLD at a confidence level of 95% is the smallest concentration of radioactive material in a sample that will be detected 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):
LLD =
E
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- exp (-Aht) where f LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)
S, 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 picoeuric Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide 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 a defined apriort (before the fact) limit representing the capability of a measurement system and not an aposteriorl(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 apriori LLDs unachievable.
In such cases, the contributing factors will be identified and described in the AnnualRadiological EnvironmentalOperating Report. l B. Analyti:al results are handled as recommended by HASL (" Reporting ofAnalyticalResultsfrom HASL,"
letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept.1984). Negative values were used in the determination of mean.
C. Nonroutine reported measurements (NRM's). These are results of samples that exceed the repost levels of Table E-2 oithe Radiological Efluent Monitoring Manual.
D. First number is the number ofindicator measurements, the second is the number of control measurements.
E. Assuming 270 m'. l F. Assuming 1080 m' G. LLD for leafy vegetables.
H. LLD from the end of the sample period.
l 1
1 3-13
Haddam Neck Station Annual R:diological Environm:ntal Operating Report 1998 3.2. Data Tables The data reponed in this section are strictly counting statistics. The reported error is two times the standard deviation (2o) 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. Results are considered positive when the measured value exceeds 1.5 times the listed 2e error (i.e., the measured value exceeds 30).
Because of counting statistics, negative values, zeros and numbers below the Minimum Detectable Level (MDL) are stati:tically 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 zeros are listed after
'significant digits, this is an artifact of the computer data handling program.
Data are given according to sample type as indicated below.
- 1. Gamma Exposure Rate
- 2. Air Particulates, Gross Beta Radioactivity
- 3. Air Particulates, Weekly I-131 *
- 4. Air Particulates, GammaIsotopic I
- 5. Air Particulates, Quarterly Strontium *
- 6. Soil'
- 7. Milk - Dairy Farms
- 8. Milk - Goat Farms
- 9. Pasture Grass"
- 10. Well Water
- 11. Reservoir Water *
- 12. Fruits & Vegetables
- 13. Broad Leaf Vegetation
- 14. River Water
- 15. Bottom Sediment
- 16. Shellfish
- 17. Fish
- This type of sampling or analysis was not performed, therefore there is no table.
" Pasture grass was not available, therefore feed (hay) was collected as a substitute i i
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Haddam Neck Stati:n Annuil Radiol:gical Environmental Operating Rrport 1998
- 4. DISCUSSION OF RESULTS This section summarizes the results of the analyses of environmental media sampled. NNECO has carefully examined the data throughout the year and has presented in this section all cases where station related radioactivity could be detected and compared the results with previous environmental surveillance data. The only impact observed from the station was tritium detected in on-site wells during 1998. Subsections describe each particular media or potential exposure pathway. Any dose commitments from station-related exposures is insignificant as explained in Section 5.
Naturally occurring nuclides such as Be 7. K-40, Ra 226 and Th-223 were detected in numerous samples.
Be-7, which is produced by cosmic proc esses, was observed predominantly in airbome and vegetation samples.
Ra-226 and Th-228 results were variabl. and were observed in broadleaf vegetation, river water (one barely positive Ra-226), river bottom sediment, shellfish, and fish (one barely positive Ra-226).
Cs-137 and St-90, present because of atmospheric nuclear weapons testing of years past, were observed at levels similar to those of past years.
4.1, Gamma Exposure Rate (Table 1)
Gamma exposure from all sources of radioactivity is measured over periods of approximately one month using CaF (Mn) thermoluminescent dosimeters (TLDs). These dosimeters are strategically pir.ced at a number of on-site locations, as well as at inner and outer off-site locations. Glass bulb type TLDs such as these, are subject to inherent self-irradiation which has been experimentally measured for each dosimeter.
The results, shown in Table 1 have been adjusted for this effect. The range of this correction for field dosimeters is 0.4 R/hr to 2.8 pR/hr, with a mean of approximately 1 pR/hr.
No indications of plant related exposure were observed. The exposure rate measurements exhibit the same trends as those of past years. These measurements demonstrate the general variations in background radiation between the various on-site and off-site locations and include gamma exposure from all sources ofradioactivity.
l 4.2. Air Particulate Gross Beta RadioactMty (Table 2) ]
Air is continuously sampled at seven inner ring and two outer ring locations by passing it through glass fiber particulate filters. "Ihese 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 decade. Inner and outer ring monitoring locations showed no significant variation in measured activities. This indicates that any station contribution is not measurable.
4-1
' Haddam Neck Station Annual Radiological Environmental Operating Report 1998 )
l Figure 4-1 CY AIR PARTICULATE P"*3 1998 Gross Beta Radioactivity 0.035
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Jan Feb Mar Apr May Jun Jul Aug sep oct Nov Dec 4.3. Airborne lodine (Table 3)
Because the station permanently shutdown in 1996 all radioactive lodines, which have shon half-lives, have decayed away. Therefore the requirement to sample airborne iodine has been removed from the Radiological Effluent Monitoring Manual (REMM) and no samples were collected in 1998.
4.4. Air Particulate Gamma (Table 4A-D)
The weekly air paniculate filters are composited quanerly for gamma spectral analyses. The results, as shown in Tables 4A-4D, indicate the f.resence of naturally occurring Be-7, which is produced by cosmic processes. No positive results were observed for all the other isotopes. These analyses indicate the lack of station effects.
4.5. Air Particulate Strontium (Table 5)
Table 5 in past years was used to report the measurement of Sr-89 and Sr-90 in quarterly composited air paniculate filters. These measurements are not required by the REMM and have been discontinued.
Previous data has shown the lack of detectable station activity in this media. This fact, and the fact that milk samples are a much more sensitive indicator of fission product existence in the environment, prompted the decision for discontinuation. .
4.6. Soll (Table 6)
Soil samples are not required by the REMM.
l 4-2
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 4.7. CowMilk (Table 7)
Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment, his, in combination with the fact that consumption of milk is significant, results in this pathway usually being the most critical from the station release viewpoint. This pathway also shows measurable amounts ofnuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there are any station effects.
Previous data over many years has shown the lack of station related strontium activity in this media.
Derefore, the strontium analysis frequency is quarterly, rather than monthly. The monthly samples collected within each quarter from each sample location are composited and analyzed at the end of each .
quarter. Sr 90 was observed in nearly one half of all samples; the highest value observed was 4.8 pCi/l.
Detailed analysis of previous data has concluded that these levels of Sr-90 are from weapons testing and are not station related (see Section 6.0 for details to this argument).
Cs-137 usually shows the same tendencies as Sr 90. Results for 1998 are similar to those seen for nearly the past two decades. Detailed analysis has concluded that these concentrations are most likely the result of fallout from previous nuclear weapons testing (see Section 6.0 for details).
Although not listed on Table 7, the only other nuclide detected by gamma spectrometry was naturally occurring K-40.
4.8. Goat Milk (Table 8)
Depending on the feeding habits, goat milk can be a more sensitive indicator than cow milk of fission products in the environment. His is due to the metabolism of these animals. Similar to the results of the cow milk samples, these show measurable amounts of nuclear weapons testing fallout.
Sr 90 and Cs 137 were observed in most samples. The levels observed are due to residual radioactivity in the environment from nuclear weapons testings in the 1960s. The variability in the results this year as well as in past years is caused by many factors, including feeding habits (amount of stored feed, 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.
4.9. Pasture Grass (Table 9)
When the routine milk samples are unavailable, samples of pasture grass are required as a replacement during the months of April through December. Dese samples may also be taken to further investigate the levels of radioactivity in milk. Directives since mid-year have been to sample feed (e.g., hay) if pasture grass is also unavailable. During the winter months and early spring, insufficient growth prohibits sampling of pasture grass as a replacement sample. Because of unavailability of pasture grass during November and December, feed (hay) was collected as a substitute for the pasture grass. No station effects were seen in the feed.
4.10. WellWater (Table 10)
Activity in this media resuhs from either soluble station effluents permeating through the ground or the leaching of naturally occurring nuclides from the soil and rock. In 1998, samples of well water from the onsite stations (location 15) were taken monthly even though the requirements per the REMODCM are to sample quarterly. Because H-3 instation liquid effluents is the predominant radionuclidc present, the higher sampling frequency was implemented to enhance program monitoring effectiveness. On-site wells (location 15) exhibited station related H 3 above background levels. His station effect results from the l wells being located within an area influenced by the water in the discharge canal and H-3 having the ability to readily follow the flow of ground water. Off-site 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.
4-3
Haldam Neck Station Annual Radiological Environmental Operating Report 1998 On-site H-3 levels detected in 1998 sampics show a decrease compared to prior years. This is a trend that started back in cycle 17 (1992) due to replacing stainless steel clad fuel with zircaloy clad fuel. The levels of H-3 observed since permanent shutdown in July 1996 represent residual levels of tritium that remain in ;
station process liquids and/or groundwater from beneath the site that are gradually dropping to natural background levels. Figure 4-2 shows the trend of H-3 measured in CY on-site wells since 1988. Of note in the figure is the highs and lows observed in measured levels of H 3. These swings are coincident with station operations. Higher H 3 levels are observed during periods when increased volumes ofliquid processing occurred in preparation for station outages.
Figure 4 2 H-3 Levels in On-site Wells g.,
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4.11. 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 station effluents in this media has resulted in discontinuing these samples.
4.12. Fruits and Vegetables (Table 12)
This media did not show any station effects. Naturally occuning K-40 was detected in all samples and cosmically produced Be-7 was detected in one sample. Since there was no fresh fallout, no other nuclides were detected.
4.13. BroadLeaf Vegetation (Table 13)
Concentrations of Cs-137 seen in several of these samples are at levels comparable to past years and are due to fallout. To enhance program monitoring effectiveness, samples of broadleaf vegetation are collected monthly during the growing season, May - October, even though requirements are to collect twice a year. No station effects were observed in broadleaf samples.
4-4
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 4.14. River Water (Table 14)
These samples are collected on a quarterly basis; the sampling procedure is different at the control and indicator locations. Six weekly grab samples are taken within each quarter and composited for the control station (Middletown - location 30C). Continuous sampling, an automatic process of compositing a small volume of sample periodically over an entire quarter, is utilized at the indicator station (East Haddam Bridge - location 28).
Examinatior, of the data shows there were no H 3 measurements that exceed 1.5 times the listed 2e error.
Even though H 3 measurements at the indicator location (Loc. 28) appear significantly higher than the control location (Loc. 30C), the values reponed are the effect of counting statistics. Although measurable levels of tritium above background have been detected in the past; there have been no positive indications of tritium in this media since 1994.
4.15. Bottom Sediment (Table 15)
There were positive indications of Cs-137 in several samples, including the control location. Because the indicator and control samples show similar levels, the source cf this Cs-137 is from wespons fallout deposited in woodlands and washed out into water bodies. No indications of station related activity were observed in this sample media.
4.16. Shellfish (Table 16)
As in previous years, no station related activity was observed. This media is not a source of consumption.
4,17. Fish (Tables 17A and 17B) 4.17.1. Bullheads (Table 17A)
No station related activity was observed.
4.17.2. Perch and Other Types (Table 17B)
As observed in the past, there was no positive indication of radioactivity in this media from the station, including Cs 137. Even though the measured values at the indicator locations do not exceed 1.5 times the listed 2e error and are the effect of counting statistics, the results will be conservatively treated as a possible positive results in order to perform a dose consequence analysis in Section 5.0, 4-5
Haddam Neck Station Annual Radiol gical Environmental Operating Report 1998
- 5. OFF-SITE DOSE EQUIVALENT COMMITMENTS ne off-site dose consequences (dose equivalent commitments) of the stations' radioactive liquid and airbome effluents have been evaluated using two methods. He first method utilizes the stations' measured radioactive discharges as input parameters into conservative models to simulate the transport mechanism through the environment to man. This resuhs in the computation of the maximum doses to individuals and the 0 to 50 mile population dose. The results of these computations are submitted to the NRC in the Annual Radioactive Effluent Report written in accordance with the Radiological Efiluent Monitoring Manual, Section F.2. He 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 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. For gaseous releases, extremely low concentrations of Cs-137 were released in 1998 for a short period of time. The only other station related activity observed in 1998 was H 3 in on-site well water. On-site well water is used for station processing and services, it is not a pathway for human consumption. Levels of Cs-137 observed in fish, although not plant related, were used to conservatively predict dose consequences as if the radioactivity were the result of station decommissioning operations.
Summarizing the data presented in Table 5.1:
MAXIMUM TOTALINDIVIDUAL DOSES :
WHOLE BODY = 0.2 mrem (Adult)
LIVER = 0.27 mrem (Teen)
The average dose to an individual within 50 miles from the site using method 1 yields the following results for the period January - December 1998 for the average individuah ANNUAL AVERAGE WHOLE BODY DOSE:
DUE TO AIRBORNE EFFLUENTS = 0.00002 mrem DUE TO LIQUID EFFLUENTS = 0.00063 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 5.1.
In order to provide perspective on the doses in Table 5.1, the standards for 1998 on the allowable maximum dose to an individual of the general public are given in 40CFR190 as 25 mrem whole body,75 mre,n thyroid, and 25 mrem any other organ. These standards are a fraction of the normal background radiation dose of 284 mrem per year and are designed to be inconsequential in regard to public health and safety. Station related doses are a small fraction of the standard as set by the Environmental Protection Agency and of the variation in natural background in Connecticut. Station related doses pose insignificant public health consequences.
5-1 1
Haddam Neck Station Annu:1 Radiological Environm:nt-1 Operating Report 1998 TABLE 5.1 - COMPARISON OF DOSE CALCULATION METHODS HADDAM NECK STATION 1998 AnnualDose(millirem) kbkNhNkhhhhbb[hk!bbh NNNDN b. $tM2$
AirborneEBluena a 1. Extemal Gamma Dose Max. Ind.m Whole Body 0.00015 ND")
- 2. Inhalation Teen Whole Body 0.051* NADS Liver 0.051
- l LiquidEffluena
- 1. Fi.h Pathway onlym
- Adu:: Whole Bodv 0.15 * <0.042*
Teen 0.082 <0.023 Child 0.032 <0.009
- Adult GI(LLI)* 0.0078 <0.0012 Teen 0.0058 <0.0009 Child 0.0025 <0.0004 Adult Liver 0.22 <0.064
- Teen 0.22 <0.066 Child 0.20 <0.060 Notes:
(1) Method I uses measured Untion discharges and meteorological d ta as input parameters to conservative transport to man models. Method 2 uses actual measured concentrations in environmental media.
(2) Maimum individui. The maximum individual dose is the dose to the mon critical age group at the location of maximum concentration of station related activity. The dose to the average individual is much less than the maximum individual dose. The doses for inhalation and v getable consumption assume that the individual resides at the point of maximum quarterly dote. Therefore, his residence is subject to variation for conservatism.
(3) NAD - No activity detected shve the minim'im detectable level.
(4) ND - Not Detectable - The station effects at all off site locations were so small that they cold not be distinguished from fluctuations in natural background.
(5) Gl(LLI) - Ga.sociatestinal Tract - Lo ver Large Intestbe.
{
(6) Dose is prin arily due to the release of tritit.m (H 3)in airbome effluents. Since tritium effects nearly all organs l equally, the resuhing dose to the whole body from inhaling teitium is the same.
(7) The dose values listed fa the fish pathway represent the liquid dose pathway to man that is calculated using Method I conservative computer models.
(8) The dose values represent the do.se consequences for cating fish with Cs-137 present from weapons fallout.
l l
5-2
Haddam Neck Station Annual Raditlogical Environmental Operating Report 1998
- 6. DISCUSSION ne evaluation of the effects of station operation on the environment requires the careful consideration of many factors. nose factors depend upon the media being anected. ney include station release rates, effluent dispersion, fallout distribution from past nuclear weapons tests, redistribution of fallout dut to weathering and biotic activity, 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. His 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 Sr-89 are relatively short-lived. Herefore they resuh fror': either station effluents, nuclear weapons tests or nuclear incidents (e.g. Chernobyl). He long lived radionuclides of Sr-90 and Cs-137 are still remaining from the weapons testing era of the 1960's resulting in measurable amounts in milk samples. Distinguishing between this " background" of fallout activity and station effects is a difficult problem.
In reviewing the Sr-90 and Cs 1?7 measured in cow and goat milk in the areas around the Haddam Neck station, a casual observer could notice that in some cases the levels of these isotopes are higher at fanns l closer to the station than at those further sway from the stations. De station's effluents might at first j appear to be responsible. However, the following facts prove this conclusion wrong.
q (1) The station accurately measures the long lived fission products Sr-90 and Cs-137 in their releases. I Based on these measurements and proven models developed by the Nuclear Regulatory Commission, concentrations in the environment can be calculated. Dese calculations, generally ;
conservative, show that insufficient quantities of Sr-90 and Cs-137 have been released from the j stations to yield the measured concentrations in milk. l (2) Although the shorter half life isotopes of St-89 and Cs-134 have decayed away, their general absence in environmental samples in the past suggest that the isotopes of Sr-90 and Cs-137, presently seen in the environment, are not station related. Over the many years of station operation, Sr 89 has often been released in comparable quantity to Sr-90, as well as Cr-134 to Cs-137. Since the pairs ofisotopes are chemically similar according to their elemental forms, i comparable levels should have been detected in milk if Sr 90 and Cs-137 were station related. No station related Sr-89 or Cs 134 have ever been detected in milk samples, or in any other media.
De only occurrences of detectable Cs-134 in milk resulted from the Chernobyl incident.
(3) Since dairy milk sampl:ng began in the 1960's, severs! years prior to station operation, the )
immediate station areas have always shown higher levels of weapons fallout related Sr-90 aw j Cs-137 (see Figures 6-1 and 6 2). De ratio of activity between the locatie s has not changed with j station operation. All areas show the same significant decrease in radioactiv2y since the 1964 Nuclear Test Ban Treaty.
(4) Local variability of Sr 90 and Cs 137 h milk is common throughout the United States. Due to the variability in soil cor ditions, pasturmg methods, rainfall, etc., it is the rule rather than the exception. Derefore, 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 St 90 and Cs 137 values than the farms that are closer to the station (e.g., see pre-1984 Haddam Neck Goat Milk data.)
4 6-1 i
L ._ _ .
Haddam Neck Station Atmual Radiologic:1 Environm:ntal Operating Report 1998 Based on these facts, it is concluded that station effluents are not responsible for variations of Sr-90 and Cs-137 in environmental samples. The cause saust be one or more of the other variables.
Northeast Nuclear Energy Company has carefully examined the data throughout the year and has presented in this report all cases where station related radioactivity can be detected. An analysis of the potential exposure to the population from any station 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 res iewed by the appropriate regulatory bodies such as the Nuclear Regulatory Commission, Environmental Protection Agency and Connecticut Department of Environmental Protection.
6-2
l H:ddam Neck Sttion Annual Radiological Environment:1 Operating Report 1998 Firure 6-1 Strontium-90 in Milk pCMiter j 25
--$- CT Pooled Milk 20
- Haddam area Milk ,
+ Millstone area Milk 15 l
so .
~
AA K K
/ 1 6 , .' A 1
a 0 . . . . . . . . . . . . . . . .. . .777T.
61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 91 93 95 97 Year Firure 6-2 Cesium-137 in Milk gMiter
--+-CT Pooled Milk 120 -W- Haddam area Milk
\ Millstone area Milk 80 i \
60 40 20 * -
0 61 63 65 67 69
)
73 75 77 h k9??$iCO"??? '
71 79 81 63 85 87 39 91 93 95 97 Year
]
Dairy milk is no longer available in the Millstone area and CT Pooled mi!L has not been collected by the State of CT since 1994. j CY Start-up occurred: July 24,1%7 MP1 Start-up occurred: October 26,1970 ,
l MP2 Start-up occurred: October 17,1975 MP3 Start-up occurred: January 23,1986 1
i
)
6-3
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 f
APPENDIX A LAND USE CENSUS FOR 1998
~
A-1
r HaddamNeck Station Annual Radi: logical Environment:1 Operating Rtport 1998 TABLE A-1 (name 1 of 2) I Dairy Cows Within 15 Miles of Connecticut Yankee -December 1998 t Direction Distance Name and Address # of Cows NNE 14 M Allen Hills Hills Farm 185 527 Gilead Street Hebron,CT 06248 NNE 14 M Edward Ellis 176 Mapleleaf Farm,Inc.
768 Gilead Street Hebron,CT 06248 NNE 14 M Gordon N. Rathbum 36 Martin Road Hebron,CT 06248 NNE 14.5 M Douglas Porter 140 14 Porter Rd.
Hebron,CT 06248 NE 8M Elizabeth Gilman 32 178 Cato Corner Rd.
Colchester,CT 06415 NE 14 M Victor Botticello 40 302 Levita Road Lebanon,CT 06249 i
ENE 6.5 M Robert Cone 60 )
Grandpa Hill Farm Box 251 318 Old Colchester Tpke East Haddam,CT 06423 ENE 11 M Richard Swider 46 475 New London Rd.
Colchester,CT 06415 E 11.5 M Eugene Wilczewski 45 Salem Valley Farm Dairy 200 Darling Road Salem,CT 06415 E 14 M Stuart Gadbois 225 40 Old Colchester Rd.
Salem,CT 064!5 SE II M John Tiffany 111 85 l
Tiffany Farms 1 156 Sterling City Road Old Lyme,CT 06371 j i
l A2
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 TABLE A-1 (nane 2 of 2)
Dairy Cows Within 15 Miles of Connecticut Yankee - December 1998 Direction Distance Nameand Address y of Cows WSW 8M Michael Dwyer 30 63 Grieb Rd.
Wallingford,CT 06492 WSW 8M Robert Raudat 44 909 Durham Road Killingworth,CT 06417 WSW 11 M Raymond Wimler 190 533 Guilford Road '
Durham,CT 06422 WSW 14 M John & Edward Cella 150 Cella Brothers Farm 2 No. Brandford Street Wallingford,-CT 06492 WSW 15 M David & Kirsten Footit 140 D & K Farm 81 School St.
Wallingford, CT 06492 4
W I1.5 M Tony Caltabiano 45 Friendly Acres Dairy Farm 145 Parmalee Hill Road Durham,CT 06422 W 14 M Walter Werbiski 21 North Farms 1069 Farms Road Wallingford,CT 06492 W 14.5 M Charles Greenback & Sons,Inc. 170 182 Wallingford Rd.
Durham,CT 06422 NW 13 M Higgins Farm,Inc. 79 i 837 Ridgewood Road l Middletown,CT 06457 MW. 15 M Joan Bryck or Jean Backiel 51 Riverside Farm 1160 France St. i Rocky Hill, CT 06067 A-3
g Haddam Neck Station Annual Radi: logical Envir:nm:ntal Operating R: port 1998 TABLE A-2 (page 1 of1)
Dairy Goats Within 20 Miles of Conneetleut Yankee - December 1998 Direction Distance Name and Address Total Goats NNE 12 M Louise Sage 4 155 Reidy Hill Road Hebron, CT 06248 NNE 16 M Joan Bowers 2 350 Wall Street Hebron, CT 06248 I
NNE 16 M Kathy Waters 70 Burnt Hill Road Hebron, CT 06248 SSE 3.6 M Virginia Marshall 6 Old County Road Haddam, CT 06438 SE 19.5 M Mrs. John Mingo 7 69 Spithead Road Waterford, CT 06385 SE 15.8 M George Scacciaferro 2 338 Boston Post Road East Lyrne,CT 06333 S 11.5 M Victor Trudeau 5 174 Horse Hill Road Westbrook,CT 06498 W 15.3 M Jim & Mary Hall Petlack 12 1000 North Farms Road Wallingford,CT 06492 WNW 19 M Daniel Nitkowski 4 46 Firch Avenue Meriden, CT 06450 NNW 14 M Dorothy Joba 10 171 Ferry Lane S. Glastonbury, CT 06073 NNW 15 M Donald Reid
- 1654 Main Street Glastonbury, CT 06033 UNABLE TO CONTACTAS OF THIS TIME A-4
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 TABLE A-3 (page 1 of1) 1998 Resident Survey l conducted August 1998 Downwind Distance i Sector Direction (Meters)
A N 1150 B NNE 1780 C NE 1265 D ENE 1710 E E 1955 F ESE 2740 G SE 1410 H SSE 940 J S 980 K SSW 860 L SW N0 M WSW 1140 N W 1360 P WNW 660 Q NW 750 R NNW 1495 l
i A-5
m HaddamNeck Station Annu:1 Radi:logicd Environmental Operating Report 1998 APPENDIX B 1
)
l
)
I i
HaddamNeck Station Annual Radi: logical Environmental Operating Report 1998 INTRODUCTION -
Northeast Nuclear Energy Company (NNECO) acting as the agent for the Connecticut Yankee Atomic Power Company (CYAPCO), maintains a quality assurance (QA) program as part of the radiological environmental monitoring program (REMP). The QA program consists of contractor appraisals, quality control samples, and quality control testing of environmental TLDs.
NNECO QA PROGRAM Appraisals are conducted of the primary (Duke) radionnalysis contractor, of the Production Operations Support Laboratory (POSL), and of the NNECO Radiological Engineering Section (RES). A REMP evaluation form is completed for each appraisal and discrepancies are tracked on a separate form until corrective action is taken. The primary contractor, POSL, and RES are also audited by other organizations; the contractor by other customers, and POSL and RES by Northeast Utilities Nuclear Oversight Department.
There are two types of NNECO QA Program quality control samples - spikes and duplicates.
Sample spikes are a check on the accuracy ofresults of the contractor's radioanalyses. Duplicate samples are a check of the contractor's precision or reproducibility of results. The number and type of NNECO QA Program quality control samples are given in Table 1. The results of the contractor's analyses of NNECO quality control samples must satisfy acceptance criteria in Procedure RAB B-3," Quality Control of Radiological Environmental Monitoring Program Sample Analyses." An investigation is conducted of any result or trend which does not satisfy acceptance criteria.
There are two types QA Program tests of environmental TLDs - spikes and field comparisons.
Spike testing involves the exposure of four TLDs each month. POSL readouts of the spiked TLDs are compared to the known radiation exposure. For field comparisons, QA TLDs of a different design from the REMP TLDs, are co-located with REMP TLDs at eight locations and processed at the Northeast Utilities Dosimetry Laboratory. Readings of the QA TLDs are compared to POSL's REMP TLD readings. The comparison results must satisfy acceptance criteria in NNECO Radiological Assessment Branch Procedure RAB B 2," Quality Control of the Environmental TLD Monitoring Program." An investigation is conducted on any result or trend which does not satisfy acceptance criteria.
OTHER OA PROGRAMS The NNECO QA Program is not the only QA Program which monitors REMP radioanalyses performance. Other programs include:
- 1. Duke's internal QA program. In addition to the NNECO quality control samples the radionnalysis contractor has it's own quality control samples. In total, at least five percent of the contractor's sample analyses include quality control samples.
- 2. Duke's interlaboratary comparison program with an independent third party, Analytics, Inc.
Results of the Analytics intercomparison are contained in Appendix C. Primary contractor participation in an interlabortary comparison program is required by station Technical Specifications. The Analytics comparison satisfies this requirement and is supplemented by the EPA Intercomparison Studies Program.
B-2 f
Haddam Neck Station Annual Radiological Environmental Operating Report 1998
- 3. Duke's participation in EPA's Environmental Radioactivity Laboratory Intercomparison Studies Program. Duke participates in EPA's program because of their analyses of drinking water, not because of nuclear power station environmental sample analyses. However, some of the EPA intercomparison samples are also applicable to nuclear power environmental samples. . Results of the EPA Intercomperison Studies Program are contained in Appendix C.
RFRULTS OF NNECO OA PROGRAM FOR CONTRACTOR RADIOANALYSES The NNECO QA Program indicated that Duke's environmental radiological analysis program was adequate in 1998. Of 103 analysis results on QA samples,99 passed criteria, a 96% success rate.
There were two air particulate gamma analyses which exceeded the criterion of being within 20% of the spiked value - both I-131 sample spikes, one at minus 23% and one at minus 30%.
Although three other 1 131 spikes on filter passed criteria in 1998, an negative bias for results of I 131 on filter analyses has been noted. This bias is currently under investigation.
There was one gross beta air particulate analysis which exceeded the criterion of being within 20% of the spiked value at minus 27%. The failure occurred because of a change in the method of preparing the QC sample. This was corrected by reverting back to the previous method and four subsequent QC samples in 1998 were within the criterion.
There was one strontium in milk QC sample which exceeded the criterion of being within 30%
of the spiked value at plus 58%. The cause of the failure was that the source was expired. It was discarded and a new source was ordered.
RESULTS OF NUSCO OA PROGRAM FOR ENVIRONMENTAL TLDS Eleven of the monthly TLD spike tests satisfied procedural criteria. One TLD spike test failed low because of a personnel error in spiking the test TLDs. A corrective action was identified for preventing a repeat of the spike test personnel error. The corrective action was implemented effective with the November test.
All twelve of the field comparisons satisfied procedural criteria.
l B-3
HaddamNeck Station Annual Radiological Environmental Operating Report 1998 TABLE B-1 (page 1 ofI)
NUMBER OF QUALITY CONTROL SAMPLES 1998 O A:s . us]. /. .
d TLDs -
Field Comparison 12 m 528
- Spike 12 m 528 Milk - Strontium 5") 32"'
Milk - Gamma 60 m goo Water- Gamma 60 576 Water - Tritium 3 32 Fish / invertebrate - Gamma 3 2004 Fruits & Vegetation & Sediment - Gamma 0 2079 Air Particulate - Gross Beta 7 832
- Gamma 25 740 FOOTNOTES (1) Includes both Millstone and Haddam Neck (2) Each TLD field comparison sample is comprised of a set of 8 TLDs.
(3) Each TLD spike sample is comprised of a set of 4 TLDs.
(4) Sr 89 and Sr-90.
(5) Gamma in water QA spikes are treated as milk surrogates.
B-4
Haddam N:ck Sttion Annual Rrdiological Environmental Operating Report 1998 f
TABLE B-2 (page 1 of1)
RESULTS OF QUALITY CONTROL SAMPLE ANALYSES 1998
~.'f f$[3 _ __ y W'
^
? ::' .):Y.v,yy y ;3,. . }g.9,Rs;j
' j.,.} ..
~- .
. e f. .
q;eng aLg 35_ -
TLDs - Field Comparison 12 0
- Spike 11 1 Milk - Strontium 4m i Water - Gamma
- 60 0 Water - Tritium 3 0 Oysters - Gamma
- 3 0 i
Air Particulate -
Gross Beta 6 1 l'
- Gamma ") 23 2 TOTALS TLDs: 23 TLDs: 1 Samples: 99 Samples: 4 FOOTNOTES (1) Sr 89 or Sr-90.
B-S
HaddamNeck Stadon Annual Radiologic:1 EnvironmIntal Operating R: port 1998 APPENDIX C
SUMMARY
OF INTERLABORATORY COMPARISONS l
l C-1 l
HaddamNeck Station Annual Radiological Environmental Operating Report 1998 INTRODUCTIQE nis appendix covers the Intercomparison Program of the Duke Engineering and Services Environmental Laboratory (DESEL) as required by technical specifications for each Millstone unit.
DESEL uses QA/QC samples provided by Analytics, Inc to monitor the quality of analytical processing associated with the Radiological Environmental Monitoring Program (REMP). The suite of Analytics QA/QC samples are designed to be comparable with the pre-1996 US EPA Interlaboratory Cross-Check Program. It was modified to more closely match the media mix presently being processed by DESEL. All intercomparison results received by DESEL on or before January 31,1999 are included. Late results for 1998 will be reported in the annual report for 1999. 4 DESEL also receives intercomparison samples from the US EPA because of their drinking water analysis program. Results from analyses of these samples are included where they are applicable to the REMP. I I
ACCEPTANCE CRITERIA Intercomparison Program results are evaluated using two separate DESEL internal acceptance criteria. The first criterion concerns bias, which is defined as the deviation of any one result from j the assumed known value. The second criterion concerns precision, which deals with the ability of )
the measurement to be faithfully replicated by comparison of an individual result with the mean of I all results for a given sample set. A sample set is created by taking three aliquots from the same sample and submitting each as a blind replicate.
4 The bias criterion is defined as within 25% of the known value for Sr 89 or Sr-90 and within 15%
of the known value for other radionuclides, or within two sigma of the known. value. This bias criterion is applied to both the Analytics and the US EPA intercomparison sample results.
For Analytics intercomparison sample results, the precision criterion is defined as an overlap of the two sigma ranges for the three replicate analyses. US EPA samples have EPA supplied criteria of lower and upper control level within which the average of the three replicate samples must occur.
RMULTS (All resuhs are extracted from References 1 and 23 For 1998, bias testing results for 72 individual environmental analyses of seven Analytics intercomparison samples are listed in the table on the following two pages. All of the analyses passed the bias criteria. Replicate sample results are not reported in References 1 and 2; however the references do report that, of the 72 environmental analyses for the seven samples there was only one result which failed the precision criterion. This was the low-level (LL)1-131 analysis for the third quarter water sample. DESEL issued CR 98-009 to investigate the failed precision test. The result of this investigation is not yet available.
Results of bias and precision testing on the US EPA intercomparison samples are contained in the table on Pages C-5 and C-6. Of 42 individual analyses of EPA samples,40 passed the bias criteria, a 95% success rate. Dere were no failures of precision criteria for the EPA samples.
REFERENCES
- 1. DESEL Analytical Services Semi-Annual Quality Assurance Status Report, January-June 1998
- 2. DESEL Analytical Services Semi-Annual Quality Assurance Status Report, July-December 1998 C-2
l HaddamNeck Station Annu:1 Radiological Environmtntal Operating Report 1998 TABLE C-1 (page 1 of 3)
ANALYTICS INTERCOMPARISON PROGRAM 1998 BIAS TESTING AN$b!k . W,T!(,)@5 Rf$ N ?(.4 hiiG7t v 3 9 n biCS r 1 3JefliVWW lst Milk Sr-89 53 pCi/L 55 pCi/L 1.04 Sr-90 44 45 1.02 Cr-51 201 204 1.01 Mn-54 133 139 1.05 Co-60 85 86 1.01 Fe 59 95 100 1.05 Zn-65 142 147 1.04 I 131 82 84 1.02 1-131 (LL) 82 83 1.01 Cs-134 84 83 0.99 Cs-137 161 171 1.06 j Cc-141 70 73 1.04 ist Water Beta 269 pCi/L 308 pCi/L 1.14 Cr-51 167 171 1.02 Mn 54 111 111 1.00 l
Co-60 71 70 0.99 j Fe-59 79 82 1.04 i Zn-65 118 120 1.02 ,
1-131 90 90 1.00 1-131 (LL) 90 92 1.02 '
Cs-134 70 68 1.01 Cs-137 134 136 1.02 Ce-141 58 59 1.06 Ra-226 53 56 1.02 Ra-228 46 47 2nd Air Filter Beta 212 pCi/ filter 220 pCi/ filter 1.04 Sr-89 142 140 0.99 Sr 90 51 49 0.96 Cr-51 113 111 0.98 Mn-54 91 96 1.05 Co-60 124 116 0.94 Fe 59 39 43 1.10 Zn-65 105 114 1.09 Cs-134 82 84 1.02 Cs-137 61 62 1.02 Ce-141 85 80 0.94 2nd Water H3 6007 pCi/L 5697 pCi/L 0.95 C-3
__o
Haddam Neck Station Annual Radiological Environmental Operating Report 1998 TABLE C-1 (page 2 of 3)
ANALYTICS INTERCOMPARISON PROGRAM 1998 M.Gi:0 . $ C /.y + M i d s b I n - M .'Z h ..': [ >.Qf.V@b' J9.%Ms 2nd Milk Cr 51 132 pCi/L 128 pCi/L 0.97 Mn-54 106 111 1.05 Co-60 143 144 1.01 Fe-59 45 46 1.02 Zn-65 122 124 1.02 1-131 67 71 1.06 1-131 (LL) 67 67 1.00 Cs-134 95 97 1.02 Cs-137 70 74 1.06 Cc-141 99 102 1.03 3rd Milk Sr-89 51 pCi/L 62 pCi/L 1.22 Sr90 81 72 0.89 Cr-51 186 180 0.97 Mn-54 74 77 1.04 Co-60 148 146 0.99 Fe-59 63 66 1.05 Zn 65 195 201 1.03 1-131 90 96 1.07 I-131 (LL) 90 87 0.97 l Cs-134 82 80 0.98 Cs-137 134 134 1.00 Cc-141 146 145 0.99 i
3rd Water Sr-89 84 pCi/L 83 pCi/L 0.99 Sr-90
)
51 47 0.92 Beta 198 190 0.96 Cr 51 165 172 1.04 Mn 54 66 66 1.00 Co-60 131 129 0.98 Fe-59 55 59 1.07 Zn-65 173 175 1.01 1-131 79 82 1.04 I-131 (LL) 79 78 0.99 Cs-134 73 71 0.97 Cs-137 119 117 0.98 Ce-141 129 129 1.00 C-4
Haddam Neck Station Annual Radiological Environm*.ntal Operating Repon 1998 l
TABLE C-1 (page 3 of 3)
ANALYTICS INTERCOMPARISON PROGRAM 1998 bj.)$ii ';- ~ % t,\ ..;f.L 8 M?.' i M}el'jeyl: ,
- 7. 6 @ G ! I .j;..h l i..2 L.
4th Milk Cr-51 195 pCi/L 205 pCi/L 1.05 Mn-54 80 83 1.04 l Co-58 32 56 1.08 l Co-60 94 96 1.02 l Fe 59 57 62 1.09 j Zn-65 141 144 1.02 '
I-131 39 42 1.08 I-131 (LL) 39 38 0.97 Cs-134 100 102 1.02 Cs-137 103 f
109 1.06 l Ce-141 98 103 1.05 4
l C-5
Haddam N;ck Station Annual Radi: logical Environm:ntal Operating Report 1998 TABLE C-2 (page 1 of 2)
U.S. EPA INTERLABORATORY COMPARISON STUDIES TROGRAM 1998 (all values in pCi/L)
,g .,3 - ?yo .. , .
. .p<_.... y
,.:3. g g-Gq & f g g , y ,,_.3 g 1/16/98 Water Sr 90 32.0 23.3 40.7 28.42 29.26 27.50 2/6/98 Water 1-131LL 104.9 86.7 123.1 109.7 106.8 110.2 3/13/98 Water H-3 2155 1551 2759 2147 2095 2044 4/21/98 Water Sr-89 9.3 5.3 13.3 7.8 8.81 10.3 4/21/98 Water Co-60 50.0 41.3 58.7 47.7 48.4 48.5 4/21/98 Water Cs-134 22.0 13.3 30.7 21.3 21.7 20.6 4/21/98 Water Cs-137 10.0 1.3 18.7 8.6 9.6 9.1 6/5/98 Water Co-60 12.0 3.3 20.7 11.5 12.6 11.4 6/5/98 Water Zn 65 104.0 86.7 121.3 105.3 106.6 99.9 6/5/99 Water Cs 134 31.0 22.3 39.7 28.9 27.8 26.9 6/5/98 Water Cs-137 35.0 26.3 43.7 34.9 36.3 34.1 i
i l
C-6
i H:ddamNeck Station Annu 1 Radiological Environm:ntal Operating Report 1998 TABLE C-2 (page 2 of 2)
U.S. EPA INTERLABORATORY COMPARISON STUDIES PROGRAM 1998 (allvalues in pCi/L) s.q . ':
, , ; ; . 8 :. ..., .
o ::ni9.WKi;ksg.::nsyN6Y .L e,' '$fk.)
7/17/98 Water Sr 89 21.0 12.3 29.7 20.1 20.3 22.0 7/17/98 Water Sr-90 7.00 0 15.7 9.80 7.40 7.11 8/7/98 Water H-3 17996 14873 21119 17656 17550 17446 9/11/98 Water 1-131 6.10 2.60 9.60 6.04 5.95 4.85
- Same sample analyzed three times.
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