ML20247E215
| ML20247E215 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/31/1997 |
| From: | NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO) |
| To: | |
| Shared Package | |
| ML20247E191 | List: |
| References | |
| NUDOCS 9805180252 | |
| Download: ML20247E215 (84) | |
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i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT HADDAM NECK STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM JANUARY 1,1997 - DECEMBER 31,1997 1
i DOCKET NO. 50-213 LICENSE NO. DPR-61 Prepared for the CONNECTICUT YANKEE ATOMIC POWER COMPANY l Haddam, Connecticut By the NORTHEAST UTILITIES SERVICE COMPANY New Britain, Connecticut '
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lladdam Neck Station Annual' Radiological Environmental Operating Report 1997 TABLE OF CONTENTS
- 1.
SUMMARY
1-1
- 2. PROGRAM DESCRIPTION 2-1 2.1. Sampling Schedule, Types,and Locations 2-1 2.2. Samples Collected During Report Period 2-6
- 3. RADIOCHEMICAL RESULTS 3-1 3.1. Sum mary Table 3-1 3.2. Data Tables 3-15
- 4. DISCUSSION OF RESULTS 4-1 4.1. Gamma Exposure Rate (Table 1) 4-1 4.2. Air Particulate Gross Beta Radioactivity (Table 2) 4-2 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) 4-3 4.6. Soil (Table 6) 4-3 4.7. Cow Milk (Table 7) 4-3 4.8. Goat Milk (Table 8) 4-3 4.9. Pasture Grass (Table 9) 4-4 4.10. Well Water (Table 10) 4-4 4.11. Reservoir Water (Table 11) 4-4 4.12. Fruits and Vegetables (Table 12) 4-4 4.13. Broad Leaf Vegetation (Table 13) 4-5 4.14. River Water (Table 14) 4-5 4.15. Bottom Sediment (Table 15) 4-6 4.16. Shellfish (Table 16) 4-6 4.17. Fish (Tables 17A and 17B) 4-6
- 5. OFF-SITE DOSE EQUIVALENT COMMITMENTS 5-1
- 6. DISCUSSION 6-1 APPENDIX A COW AND GOAT CENSUS FOR 1997 A-1 APPENDIX B NORTHEAST UTILITIES QA PROGRAM B-1 APPENDIX C
SUMMARY
OF INTERLABORATORY COMPARISONS C-1 l
r lhddim Neck Station Annual' Radiological Environment:1 Operating Report 1997 1,_
SUMMARY
The radiological- environmental monitoring program for the Haddam Neck Plant was continued for the period January through December 1997, in compliance with the
' Radiological Effluent Monitoring and Off-Site Dose Calculation Manual (REMODCM). This I-annual report was prepared for the Connecticut Yankee Atomic Power Company (CYAPCO) t by the Radiological . Assessment Branch of the Northeast Utilities Service Company (NUSCO). All sample collections and preparations are performed by the Production'-
Operations Services Laboratory. Gamma exposure rate measurements were performed by the Production Operations Services Laboratory. All remaining laboratory analyses -were performed by Duke Engineering and Services Environmental Laboratory, formerly Yankee Atomic Environmental Laboratory.
Radiological. analyses were performed with gamma exposure measuring devices and on samples of air particulate, milk, pasture grass, broad leaf vegetation, well water, fruits, vegetables, river water, bottom sediment, shellfish, and fish. In evaluating the results of these analyses it is necessary to consider the variability of natural sources of radioactivity and radionuclides uptake in environmental media. This variability is dependent on many factors, including plant release rates, seasonal variability of fallout, locational variability of fallout, i
soil characteristics, farming practices, and feed type. Significant variations in measured levels of radioactivity could be caused by any one of these factors. Therefore, these factors need to be considered in order to properly explain any variations in radiation detected and to distinguish between natural and nuclear plant related radioactivity.
Haddam Neck shutdown on July 22,1996. On Dec. 4,1996 the Board of Trustees of the Haddam Neck plant decided to permanently shutdown the plant due to economic reasons. The monitoring of radioactivity in the environment around the site has changed slightly due to this decision. Since iodine has decayed away, the sampling for and analysis of iodine was discontinued in March of 1997. Primary activities at the Haddam Neck site are now focused on
. decommissioning. Even though the plant is no longer generating power, normal operational evolutions require the processing of liquids which are radioactive. Some of these liquids produce discharges which enter into the environment. The radiological monitoring of the environment through this program will continue to assure the health and safety of the public and workers are maintainedat all times.
The predominant radioactivity, indicated by the results in 1997, was that from nonplant (not Haddam Neck) sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. As typical of previous years, plant related radioactivity was observed at some of .
the on-site gamma monitoring locations. The only other observation of plant effects was tritium in well water at the on-site location and a conservative assumption that cesium-137 in fish was }
the result ofplant operation.
l:
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 plant operation.
This can be concluded based on the facts that: insufficient quantities of these isotopes have i
1-1 l
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lladdam Neck Station Annual Radiological Environmental Operating Report 1997 been released by the plant to account for the measured concentrations and higher levels of cesium-137 and strontium-90 were detected prior to initial plant operation.
The radiation dose (dose equivalent commitment) to the general public from the plant's discharges has been evaluated by two methods. One method utilizes the measured station's discharges and conservative transport models and the other utilizes the measured concentrations of radioactivity in the environmental media.
The maximum whole body dose (station boundary) that could occur to a member of the general public was calculated to be 0.059 millirem. The average dose to a member of the public residing within 50 miles of the plant is 0.000027 millirem. These doses are 0.24 percent and 0.00011 percent of the standard as set by the Environmental Protection Agency on the maximum allowable dose to an individual of the general public. The 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 health and safety. Plant related doses are a small fraction of these standards and of the variation in natural background in Connecticut. Plant related doses pose insignificant public health consequences.
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1-ladd:m Nick St: tion Annual'Ridiologicil Environmental Operating Report 1997 I
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 are Off-Site Dose Calculation Manual and any extra samples.
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.. 1 Haddim Ncck Station Annual Radiological Environmental Operating Report 1997 Table 2-1 Environmental Monitorine Program Sampline Types and Locations y m.,.; r. y . - - pr ,
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l-1 On-site - Mouth of Discharge Canal 1.1 Mi, ESE TLD i 2-1 Iladdam-Park Fd. 0.8 Mi, S TLD j 3-1 Iladdam-Jail flill Rd. 0.8 Mi, WSW TLD 4-I Iladdam-Ranger Rd. 1.8 Mi, SW TLD, Air Particulate, lodine' 5-I On-site-Injun iloilow Rd. 0.4 Mi, NW TLD, Air Particulate, lodine' 6-1 On-site-Substation 0.5 Mi, NE TLD, Air Particulate, lodine', Veg.
7-1 Iladdam 1.8 Mi, SE TLD, Air Particulate, lodine' 8-1 East fladdam 3.1 Mi, ESE TLD, Air Particulate, lodine' 9-I liigganum 4.3 Mi, WNW TLD, Air Particulate, lodine' 10-1 Iturd Park Rd. 2.8 Mi, NNW TLD ll C Middletown 9.0 Mi, NW TLD 12-C Deep River 7.1 Mi, SSE TLD 13-C North Madison 12.5 Mi, SW TLD, Air Particulate, lodine' 14-C Co!-hester IP 5 Mi, NE TLD 15-l' On-site Wells 0.5 Mi, ESE Well Water {
16-C Well-State liighway Dept. E. Iladdam 2.8 Mi, SE Well Water 17-C Fruits & Vegetables Beyond 10 Miles Vegetation 18-I Site Boundary 0.4 Mi, NW Vegetation 19-! Cow Location #I 6.5 Mi, ENE Milk 20-1 Cow Location #2 6.0 Mi, NW (<4/97) Milk 8.0 Mi, NE Q5/97) 21-1 Cow Location #3 8.0 Mi, WNW (<4/97) Milk I 1.0 Mi, SE Q5/97) 22-C Cow Location #4 I1.0 Mi, ENE Milk 23-C Goat Location #1 17.0 Mi, NE (_<2/97) Milk 11.5 Mi, S (<4/97) 16.0 Mi, NNE Q5/97) 24-1 Goat Location #2 3.6 Mi, SSE Milk 25-1 Fruits & Vegetables Within 10 Miles Vegetation 26-1 CT River-Near intake 1.0 Mi, WNW Fish 27-C CT River-liigganum Light 4.0 Mi, WNW Shellfish 28-1 CT River-E. Iladdam Bridge 1.8 Mi, SE Bottom Sediment, River Water 28-X CT River-E. Iladdam Bridge 1.8 Mi, SE Shellfish 29-1 Vicinity of Discharge -
Bottom Sediment Fish 30-C CTRiver 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, llorton Rd. 1.0 Mi, SE TLD i 45-X Old Waste Gas Sphere Fence 0.1 Mi, E TLD l
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
'The release points are the stack for terrestrial locations and the end of the discharge canal for aquatic locations.
' lodine analyses and samples were discontinued in March.
2-2 L __ _ - - _ _ _ - - _ - - - - _ - - - - - - _ - _ _ _ _ _ _ - - - - - - _ - - - - - _ - - - - - - - - - - - - - - - - -- - -- - --
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Iladdam Neck Station Annuat Radiological Environmental Operating Report 1997 Table 2-2 Technical Specification Sampline Frequency & Type of Analysis l
!a. Gamma Exposure - 14 Monthly Gamma Dose Environmental TLD lb. Gamma Exposure - 27 Quarterly N/A8 Accident TLD
- 2. Airborne Particulate 7 Continuous sampler - weekly Gross Beta - Weekly filter change Gamma Spectrum - Quarterly on composite (by location), & on individual sample if gross beta is greater than 10 times the mean of the weekly control stations gross beta results
- 3. Airborne lodine' 7 Continuous sampler - weekly 1-131' canister change
- 4. Vegetation 4 One sample near middle & Gamma Isotopic on each sample one near end ofgrowing season
- 5. Milk 6 Monthly Gamma Isotopic and 1-131" on each sample, Sr-89 & Sr-90 on quarterly composites
- 52. Pasture Grass 6 Sample as necessary to Gamma Isotopic substitute for unavailable milk
- 6. Well Water 2 Quarterly Gamma Isotopic & Tritium on each sample
- 7. Bottom Sediment 3 Semiannually Gamma Isotopic
- 8. Ri er Water 2 Quarterly Sample -Indicator Gamma Isotopic & Tritium is Continuous Composite; Background is composite of ,
Six weekly Grab Samples !
Fish - Bullheads &,
- 9. 3 Quarterly Gamma Isotopic when available, Perch or other edible fish
- 10. Shellfish 2 Quarterly Gamma Isotopic 8
Accident monitoring TLDs to be dedesed at least quarterly
- Since lodine no longer exists, iodine sampling and analysis was discontinued in March 1997 2-3
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- - 'lladdam Neck Station Annual Radiological Environmental Report 1997 Fieure 2.1 IInddam Neck Plant Sample Stations
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Itddam Neck Station Annual Radiological Environmental Operating Report 1997 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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.;.........v...,.::. ,...- .... w . ... a. x _ s . A.m A wmm Gamma Exposure (TLD) 168 168 96 Air Particulate 364 364 0 Air lodine" 63 63 0 Dairy Milk 48 45' 0 Goat Milk 24 17' 0 3
Pasture Grass 3 0 Well Water 8 8 0 Fruit & Vegetables 8 8 0 Broad Leaf Vegetation 4 4 8 River Water 8 8 0 Bottom Sediment 6 6 0 Fish 24 23' 0 Shellfish 8 8 4 Total AllTypes 733 725 108 i
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8 Sample as necessary to substitute for unavailable milk.
' Air Iodine samples were required for the first 9 weeks of 1997 before being removed as a required sample from the REMODCM.
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Ihdd:m Neck Station AnnudRadiological Environmental Oper ting Report 1997 3m RADIOCHEMICAL RESULTS 3.1. Summary Table In accordance with the Radiological Effluent Monitoring Manual (IEMM), Section F.1, a summary table of the radiochemical results has been prepared and is presented in Table 3-1.
In the determination of the mean, the data was handled as recommended by tl.e 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 data summaries.
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- H ddim Ncck Station Annut! Radiological Environmental Operating Report 1997 NOTES FOP TABLE 3-1 A. For gamma measurements the (Minimum Detectable Leve_l) 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 of large' amounts of interfering 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 (-kat) 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 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 picoeurie Y is the fractional radiochemical yield (when applicable)
~
A is the radioactive decay constant for the particular radionuclides At is the elapsed time between sample collection (or end of the sample collection period) and time of counting
- It should be recognized that LLD is a defined a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these a priori LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
B.. Analytical results are handled as recommended by HASL (" Reporting of Analytical Resultsfrom HASL," letter by Leo B. Higginbotham) and NUREG/CR-4007 (Sept.1984).
- Negative values were used in the determination of mean.
l C. Nonroutine reported measurements (NRM's). These are results of samples that exceed the repost levels of Table E-2 of the Radiological Effluent Monitoring Afanual.
3-13
firddam Neck Station Annual Radiological Environmental Operating Report 1997 D. First number is the number ofindicator measurements, the second is the number of control measurements.
E. Assuming 270 m 3 F. Assuming 1080 m' G. LLD for leafy vegetables.
H. LLD from the end of the sample period.
a l
l 3-14 L _-_____ __-_-__ - _ ___ __ _____ _ __ _ -
Hadd:m Neck St: tion Annual Radiological Environmental Operating Report 1997 3.2. Data Tables The data reported in this section are strictly counting statistics. The reported error is two times the standard deviation (2a) 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 2a error (i.e., the measured value exceeds 3o).
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. GammaExposureRate
- 2. Air Particulate, Gross Beta Radioactivity
- 3. AirParticulates,WeeklyI-131'
- 4. AirParticulates,QuantitativeGammaSpectra
- 5. Air Particulate, Quarterly Strontium *
- 6. Soil'
- 7. Milk - DairyFarms
- 8. Milk - GoatFarms
- 9. Pasture Grass
- 10. Well Wster
- 11. Resen oir Water *
- 12. Fruits & Vegetables
- 13. Broad Leaf Vegetation
- 14. River Water
- 15. Bottom Sediment
- 16. Shellfish
- 17. Fish
- I-131 analysis requirementswere removed from the REMODCM on 2/28/97.
- This type of sampling or analysis was not performed, therefore there is no table.
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Haddim N:ck Station . Annu:1 Radiological Environmental Operating Report 1997
_4._ DISCUSSION OF RESULTS
. This section summarizes the results of the analyses of environmental media sampled.
. NUSCO has carefully examined the data throughout the year and has presented in this section all cases where plant related radioactivity could be detected and compared the results with previous environmental surveillance data. Few impacts of plant operation were observed in environmental media during 1997. Subsections contained describe each particular media or potential exposure pathway. The dose' commitments from these plant-related exposures is
' insignificant and is 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 airborne and vegetation samples. Ra-226 and Th-228 results were variable and are generally at levels higher than plant related radionuclides.
' Cs-137 and Sr-90 were observed at levels similar to those of past years. In general, the detectable levels of Cs-137 and Sr-90 were the result of atmospheric nuclear weapons testing ofyears past.
i 4.1. Gamma Exposure Rate (Table 1)
Gamma exposure from all sources including cosmic and other natural and anificial radioactivity is measured over periods of approximately one month using CaF 2 (Mn) thermoluminescent dosimeters (TLDs). These dosimeters are strategically placed at a l 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 I have been adjusted for this effect. The range of this correction for field dosimeters is 0.4 R/hr to 2.8 R/hr, with a mean of approximately 1 R/hr.
The exposure rate measurements exhibit the same trends as those of past years. These measurements demonstrate the general variations in natural background radiation between the various on-site and off-site locations and include gamma exposure from all sources including cosmic, terrestrial, and artificial radioactivity.
The location near the intake structure (location 40X) shows a noticeable increase in I exposure during the month of March. During this month the station was performing radiography tests in a remote area near the intake structure. The increase in gamma ;
exposure during March is attributable to this activity. Exposure due to radiography 1 testing is very localized. Location 40X where an increase in exposure was observed is on-site. Nearby TLD locations outside of the plant protected area fence show no {
noticeable increase in exposure. Therefore, it is concluded that the dose commitment j to the public is negligible from the radiography tests. j 4-1 l
L_ -____ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _
l lliddam Nick Stition Annual Radiological Environm:ntal Operating Report 1997 l .
- 4. 2. Air Particulate Gross Beta Radioactivity (Table 2)
Air is continuously sampled at seven inner ring and two outer ring locations by passing l it through glass fiber particulate filters. These are collected weekly and analyzed for gross beta radioactivity. Results are shown on Figure 4-1 and Table 2.
Gross beta activity remained at levels similar to that seen over the last decade. Inner and outer ring monitoring locations showed no significant variation in measured activities. This indicates that any plant contribution is not measurable.
, l 1
Figure 4-1 CY AIR PARTICULATE PCUrn 3 1997 Gross Beta Radioactivity 0.03
+lndicators l
--G-Controls 0.025 -
l l '
I
_ A 0.02 _ Y" 0.015 _
0.01 ,
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 4.3. Airbornelodine (Table 3)
Through the beginning of March of 1997 charcoal cartridges were included at all of the air particulate locations for the collection ofiodine. As would be expected since short-lived iodint has decayed away since the shutdown of the plant, no detectable levels of I-131 were seen in the charcoal samples taken. The requirement to sample air iodine has been removed from the REMODCM. i 4.4. Air Particulate Gamma (Table 4A-D) l The weekly air particulate filters are composited quarterly for gamma spectral l analyses. The results, as shown in Tables 4A-4D, indicate the presence 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 plant effects.
4-2
_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -)
o Itddam Neck Station Annual Radiological Environmental Operating Report 1997 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 particulate filters. These measurements are not required by the Radiological Effluent Monitoring Manual (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 mere sensitive indicator of fission product existence in the environment, prompted the decision for discontinuation.
- 4. 6. Soil (Tabic 6) l Soil samples are not required by the REMM. '
- 4. 7. Cow Milk (Table 7)
Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. This, in combination with the fact that consumption of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint. This pathway also shows measurable amounts of nuclear weapons testing fallout. Therefore, this media needs to be evaluated very carefully when trying to determine if there are any plant effects.
Previous data over many years has shown the lack of station related strontium activity
)
in this media. Therefore, the strontiurr analysis frequency has been reduced from monthly to quarterly. 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 a quarter of all samples; the highest value observed was 4.0 pCi/1. Detailed analysis of previous data has concluded that these levels of Sr-90 are from weapons testing and are not plant related (see Section 6.0 for details to this argument).
Cs-137 usually shows the same tendencies as Sr-90. Results for 1997 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 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.
i
- 4. 8. Goat Milk (Table 8)
! Depending on the feeding habits, goat milk can be a more sensitive indicator than cow l milk of fission products in the environment. This is due to the metabolism of these animals. Similar to the results of the cow milk samples, these show measurable amounts of nuclear weapons testing fallout.
Sr-90 and Cs-137 were observed in most samples. In samples taken between 1977 -
1983 the control location had significantly higher values than the indicator location.
This difference decreased substantially with a change in farms in 1983. Variability is caused by many factors, including feeding habits (amount of stored feed, etc.), soil 4-3
Haddam Neck Station Annual Radiological Environmental Operating Report 1997 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. These samples may also be taken to further investigate the levels of radioactivity in milk. During the winter months and early spring, insufficient growth prohibits sampling of pasture grass as a replacement sample. This condition is also true late in the year. In this year's samples as in those of past years, no plant effects were seen in this media.
4.10. Well Water (Table 10)
Activity in this media results from either soluble plant effluena permeating through the ground or the leaching of naturally occurring nuclides from the soil and rock. In the first quarter of 1997, on-site wells (location 15) exhibited plant related H-3 above background levels. This plant 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 does not result in any dose consequence since the water from these wells is used only in process streams at the station.
H-3 levels detected in 1997 samples show a substantial decrease. This is a trend that started back in cycle 17 (1992) due to the process of 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 plant process liquids and/or groundwater from beneath the site that are gradually dropping to natural background levels. Figure 10-1 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 plant operations. Higher H-3 levels are observed during periods when increased volumes ofliquid processing occurred in preparation for plant outages.
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 plant effluents in this media has resulted in discontinuing these samples.
4.12. Fruits and Vegetables (Table 12)
This media did not show any plant effects. Concentrations of Sr-90 in these samples existed at levels comparable to past years and is due to fallout. Naturally occurring K-4-4
Haddom Ncck Station Annual Radiological Environmental Operating Report 1997 i
40 was detected in all samples. Since there was no fresh fallout, no other nuclides were detected.
Figure 10-1 II-3 Levels in On-site Wells me,
_ A r 4000 I\ r1 I
_ \' lL / \ l ,
_ T/ \ / \/ /\ .
V \/ \l J v\ A.
0 .,... . . . . .
1Q88 1Q89 1Q90 1Q91 1Q92 1Q93 1Q94 1Q95 1Q96 1Q97 Year 4.13. BroadLeaf Vegetation (Table 13)
Concentrations of Cs-137 in 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 plant effects were observed in broadleafsamples.
Starting in 1997 the analysis of this media for strontium was discontinued. Data from past years has shown the lack of station related strontium activity in this media.
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).
In past years, measurable levels of H-3 were detected in this sample media. In 1997 no measurable levels above background were detected. Because tritium only emits low energy beta particles and river water is not a source of drinking water, the dose consequence resulting from tritium is insignificant. Fish consumption is the only 4-5
fladdam Neck St: tion Annuil Radiological Environmental Operating Report 1997 media through which the population encounters dose from tritium in liquid effluents. !
The dose consequence of the tritium, although not routinely measured in fish, is I calculated based upon the measured emuents and appropriate dispersion models (NRC approved computer code LADTAP). In order to verify these calculations, a special program of measuring tritium in fish samples had been perfonned. The result of these analyses indicated that the effluent calculations are conservative.
4.15. Bottom Sediment (Table 15)
No indications of plant related activity were observed in this sampling media.
4.16. Shellfish (Table 16)
No activity was observed except for the naturally occurring radionuclides. This media is not a source of consumption.
4.17. Fish (Tables 17A and 17B) !
4.17.1. Bullheads (Table 17A)
No activity was observed except for the naturally occurring radionuclides. The dose consequences ofplant related activity when detected are discussed and the results are shown in Section 5.0.
4.17.2. Perch and Other Types (Table 178)
Positive indication of Cs-137 was observed in the first quarter sample taken .
from the vicinity of discharge (location 29). Even though the measured value !
does not exceed 1.5 times the listed 2a error, the results from location 29 for I the third quarter sample are also ing conservatively treated as a possible positive result. Conservatively eating the Cs-137 activity observed in both ,
samples as . plant rgeand not the result of weapons testing residual )
radioactivity {4d!eTose consequences are discu.csed and the results are sh Section 5.0. fhese fish samples exhibit similar results as samples taken in previous years at the control location.
l i
4-6
Haddam Neck Station Annual Radiological Environmental Operating Report 1997 5 OFF-SITE DOSE EQUIVALENT COMMITMENTS The off-site dose consequences (dose equivalent commitments)of the stations' radioactive liquid and airborne effluents have been evaluated using two methods. The 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 results 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 Effluent Monitoring Manual, Section F.2.
The second method utilizes the actual measurements of the concentrations of radioactivity in various environmental media (e.g., milk, fish) and then computes the dose consequences resulting from the consumption of these foods.
The 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, no plant related detectable activity was observed in any sampling media. The only plant related activity observed in 1997 was H-3 in on-site well water and possibly Cs-137 in fish.
MS On-site well water is used for plant processing and services,it is not a pathway for human consumption.
The doses presented in Table 5.1 are the maximum doses to an individual for specific pathways to man. The calculations result in maximum total doses to an individual of: 0.059 mrem whole body to an adult and 0.07 mrem to a teen's liver. The calculated doses for all other locations and other age groups will be less than those shown.
The average dose to an individual within 50 miles from the site using method 1 yields the following results for the period January - December 1997 for the average individua i:
ANNUAL AVERAGE WHOLE BODY DOSE :
DUE TO AIRBORNE EFFLUENTS = 0.00002 mrem DUE TO LIQUID EFFLUENTS = 0.0000065 mrem Thus,it can be seen that the average whole body dose to an individuals much less than the maximum whole body dose to an individual as shown in Table 5.1.
In order to provide perspective on the doses in Table 5.1, the standards for 1997 on the allowable maximum dose to an individual of the general public are given in 40CFR190 as 25 mrem whole body,75 mrem thyroid, and 25 mrem any other organ. These standards are a fraction of the normal background radiation dose of 284 mrem per year and are designed to be inconsequential in regard to public health and safety. Plant 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. Plant related doses pose insignificant public health consequences.
5-1
i c
l Ilidd:m Neck Stttion Annual Radiological Environmental Operating Report 1997 TABLE 5.1 COMPARISON OF DOSE CALCULATION METilODS IIADDAM NECK STATION 1997 Annual Dose (millirem)
]. lfff h)& h -Qfpf Airborne Effluents
- 1. External Gamma Dose Max. Ind.
- Whole Body 0.017 ND*
- 2. a. Inhalation Max. Ind. Thyroid 0.022 W NADW LiquidEffluents
- 1. Fish Pathway onlyM * . Adult Whole Body 0.007M 0.042 Teen 0.004 0.023 Child 0.002 0.009
- Adult GI(LLI)* 0.0003 0.0012 Teen 0.0002 0.0009 Child 0.0001 0.0004 Adult Liver 0.010 0.064
- Teen "
0.011 0.066 Child 0.010 0.060 Notes:
(1) Method I uses measured station discharges and meteorological data as input parameters to conservative transport to man models. Method 2 uses actual measured concentrations in environmental media.
(2) Maximum individual - The maximum individual dose is the dose to the most critical age group at the location of maximum concentration of plant 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 quarterly dose. Therefore, his residence is subject to variation for conservatism.
(3) NAD - No activity detected above the minimum detectable level.
(4) ND - Not Detectable - The plant effects at all off-site locations were so small that they could not be distinguished from fluctuations in natural background.
(5) GI(LLI)- Gastrointestinal Tract - Lower Large Intestine.
(6) Thyroid dose is primarily due to the release of tritium (11-3) in airborne effluents. There is essentially no iodine available for release from the station.
l (7) The dose values listed for the fish pathway represent only one of the liquid dose pathways to man that are calculated f when computing the total dose due to liquid effluent releases using Method I conservative computer i models. Other pathways such as boating, swimming and shoreline recreation account for a total whole body dose to the maximum individual in 1997 of 0.032 millirem from liquid effluents.
l 5-2
Hrddim Neck St; tion Annual Radiological Environmental Operating Report 1997
$m DISCUSSION 1
1 The evaluation of the effects of station operation on the environment requires the careful
{
consideration of many factors. Those factors depend upon the media being affected.
They include station release rates, effluent dispersion, occurrence of nuclear weapons tests,' seasonal variability of fallout, local environment, and locational variability of fallout. Additional factors affecting the uptake of radionuclides'in milk include soil conditions (mineral content, pH, etc.), quality of fertilization, quality ofland management (e.g., irrigation), pasturing habits of animals, and type of pasturage. Any of these factors could cause significant variations in the measured radioactivity. A failure to consider these factors could cause erroneous conclusions.
Consider, for example, the problem of deciphering the effect of station releases on the radioactivity measured in milk samples. This is an important problem because this product is widely consumed and fission products readily concentrate in this media. Some of these fission products, such as Sr-89 are relatively sitort-liyed. Therefore they result from either plant effluents, nuclear weapons tests or nuclear incidents (e.g. Chernobyl).
Problems are caused by the long-lived fission products, Sr-90 and Cs-137. These isotopes are still remaining from the high weapons testing era of the 1960's. This results in (
measurable amounts of Sr-90 and Cs-137 appearing in milk samples. Distinguishing between this " background" of fallout activity and plant effects is a diflicult problem.
In reviewing the Sr-90 and Cs-137 measured in cow and goat milk in the areas around the Millstone and Haddam Neck stations, a casual observer could notice that in some cases the levels of these isotopes are higher at farms closer to the station than at those further away from the stations. The stations effluents might at first appear to be responsible.
However, the investigation of the following facts proves this' conclusion wrong.
(1) The stations accurately measure many fission products, including Sr-90 and ~
Cs-137 in their releases. Based on these measurements and pmven models ll developed by the Nuclear Regulatory Commission, concentrations irr the l
lL environment can be calculated. These calculations (generally conservative, see Section 5.0) show that insufficient quantities of Sr-90 and Cs-137 have been released from the stations to yield the measured concentrations in milk.
(2) Over the many years of plant operation, Sr-89 has often been released in
. comparable quantity to Sr-90. Since they are chemically similar, comparable
! levels should have been detected in milk if the Sr-90 was plant related. No
! plant related Sr-89 has ever been detected in milk samples.
(3) Similar to Sr-89, Cs-134 can be used as an indication of plant related Cs-137. I Although not as conclusive as Sr-89, the lack of any measurable Cs-134 in any of the milk samples collected from the past suggests that the Cs-137 is not plant related. This is further confirmed bv 4.e evaluation of the air particulate data. The only occurrences of detectabw Cs-134 in milk resulted from the Chemobyl incident.
(
6-1 L -- _ _ _ _ _ _ _ _ _ _ _ - - - - - _ _ _ _ _ _ _ - . - - . . -- - - _ _ - - - - - - - _ _ _ _ _ _ _ - . - _ _______ -----_ ___ _ __ _ __ _ ____ - .
l Haddun Nrck Station Annual Radiological Environmental Operating Report 1997 (4) Since dairy milk sampling began in the 1960's, years prior to plant operation, the immediate station areas have always. shown higher levels of weapons fallout related Sr-90 and Cs-137 (see Figures 6-1 and 6-2). The ratio of activity between the locations has not changed with plant operation. All areas show the same significant decrease in radioactivity since the 1964 Nuclear Test Ban Treaty.
(5) Local variability of Sr-90 and Cs-137 in milk is common throughout the United States. Due.to the variability in soil conditions, pasturing methods, rainfall, etc., it is the rule rather than the exception. Therefore, it is not surprising that certain farms have higher levels of radioactivity than other-farms. In fact, there are some cases where the farms further from the station have higher Sr-90 and Cs-137 values than the farms that are closer to the
! station (e.g., see pre-1984 Haddam Neck Goat Milk data.)
(6) The Millstone goat farm with the highest levels of Sr-90 and Cs-137 has also experienced the highest levels of short-lived activity from the 1976 and 1977 Chinese Tests and the 1986 Chernobyl accident. This indicates that for some
- unknown reason this farm has the ability for higher reconcentration. Special studies performed at this and other farms failed to find any link to the plant.
l Based on these facts, the observation that the station effluents are responsible is obviously false. The cause must be one or more of the other variables.
Northeast Utilities has carefully examined the data throughout the year and has presented in this report all cases where plant related radioactivity'can be detected. An analysis of the potential exposure to the population from any plant related activity has been performed and shows that in all cases the exposure is insignificant.
l Throughout the year, the Connecticut Department of Environmental Protection performs a parallel environmental program under contract with the Nuclear Regulatory Commission. On a regular basis, the results of their analyses are compared to the results from this program's analyses. The comparisons are tracked and used as a cross-reference to verify measured plant activity. During 1997, both programs showed similar results.
As in previous years, this data is being submitted to, and will be reviewed by the I appropriate regulatory. bodies such as the Nuclear Regulatory Commission, Environmental Protection Agency and Connecticut Department of Environmental Protection.
I L
6-2 L
i
Hadd:.m Ncck Station Annual Radiological Environmental Operating Report 1997 Fieure 6-1 Strontium-90 in Milk pCi/hter 25
- +--CT Pooled Milk 20 "* * " * ' * * -
- -Millstone area Milk 15 l '
~
\
10 ^
- \ / ', / '
/ '-'
\ , .-
5 . .. .
\.-
3 A
0 . . , , , , , . , , , , , , . . , , , . . .
61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 91 93 95 97 Year Fieure 6-2 Cesium-137 in Milk pCi/ liter 160 l
40
-+-CT Pooled Milk 120 - g-- Haddam area Milk f\ --Millstone area Milk 80 I \
60 40
/ %u O , .
7 D ",* N 'N, N 61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 93 95 91 97 Year Dairy milk is no longer available in the Millstonearea and CT Pooled milk has not been collected by the State of CT since 1994.
CY Start-upoccurred: July 24,1967 i
MPI Start-upoccurred: October 26,1970 MP2 Start-upoccurred: October 17,1975 l MP3 Start-upoccurred: January 23,1986 6-3
' Iliddam Neck Station Annua'l Radiological Environmental Operating Report 1997 -
APPENDIX A COW AND GOAT CENSUS FOR 1997 1
i i
i l
l l
l- !
j i
A- 1 1
l e
liiddam Neck Station Annual Radiological Environmental Operating Report 1997 l
I Dairy Cows Within 15 Miles of Connecticut Yankee December 1997 Direction Distance Name and Address # of Cows i
NNE 14 M Robert K. Gasper 0 694 Gilead Street Hebron,CT 06248 NNE 14 M Hills Farm 120 '
527 Gilead Street Hebron,CT 06248 ;
NNE 14 M Mapleleaf Farm, Inc. 160 750 Gilead Street Hebron,CT 06248 I NNE 14 M Gordon N. Rathburn 36 Martin Road Hebron,CT 06248 NNE 14.5 M Douglas Porter 136 RFD #1 l Hebron, CT 06248 NE 8M Flizabeth Gilman 20 178 Cato Comer Rd.
Colchester,CT 06415 NE 14 M Victor Botticello 22 Levita Road Lebanon,CT 06249 ENE 6.5 M Grandpa Hill Farm / R.S. Cone 40 !
Box 251 i 318 Old Colchester Tpke '
East Haddam, CT 06423 ENE 11 M Richard Swider 40 Route 85 Colchester,CT 06415 E 11.5 M Salem Valley Farm Dairy 21 Eugene Wilczewski 200 Darling Road Salem,CT 06415 !
E 14 M Stuart & Judith Gadbois 200 !
RT 82 / 95 Old Colchester Rd.
Salem,CT 06415 A-2 l
~.
- lladdam Neck Station Annual Radiological Environmental Operating Report 1997 Dairy Cows Within 15 Miles of Connecticut Yankee December 1997 Direction Distance Name and Address # of Cows SE 11 M Tiffany Farms 74 Sterling City Road Old Lyme, CT 06371 SW 14.5 M SugarloafFarm 0 154 Beaver IIead Road North Guilford, CT 06437 WSW 8M Michael Dwyer 24 63 Grieb Rd.
Wallingford, CT 06492 WSW 8M Robert Raudat 36 Old Durham Road Killingworth,CT 06417 WSW l1 M Raymond Wimler 160 Guilford Road Durham, CT 06422 WSW 14 M Cella Brothers 120 Whirlwind Ilill 2 No. Brandford Street Wallingford,CT 06492 WSW 15 M David & Kirsten Footit 100 180 Northford Rd.
Wallingford, CT 06492 g/
W l1.5 M Friendly Acres Dairy Farm 25 Tony Caltabiano Parmalee Hill Road Durham,CT 06422 W 14 M North Farms 21 Walter Werbiski 1069 Farms Road Wallingford, CT 06492 W 14.5 M Charles Greenback & Sons, Inc. 120 Box 451, Route 68 Durham,CT 06422 s
A-3
fladdam Neck Station Annual Radiological Environmental Operating Report 1997 Dairy Cows Within 15 Miles of Connecticut Yankee Decemher 1997 Direction Distance Name and Address # of Cows WNW 8M Richard Brock 0 787 Ridge Road Middletown, CT 06457 WNW 12 M Walnut Hill Farm 0 William & Thomas Mintz Jackson Hill Road Middlefield,CT 06455 WNW 15 M Bilger Brothers 0 Hickory Grove Farm 705 Westfield Road Meriden, CT 06450 NW 6M Edward Hills III 0 772 Brooks Road Middletown,CT 06457 NW 13 M Higgins Farm, Inc. 72 837 Ridgewood Road Middletown, CT 06457 NW 15 M Wenceslaus & Jean Backiel 27 Riverside Farm RFD #2 Berlin,CT 06067 A-4
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L Hrddim Neck Station Annual Radiological Environmental Operating Report 1997 l *.
Dairy Goats Within 20 Miles of Connecticut Yankee December 1997
. Direction Distance Name and Address # of Goats NNE 12 M Louise Sage 4 155 Reidy Hill Road Hebron, CT 06248 NNE 16 M Joan Bowers 3 350 Wall Street Hebron, CT 06248 NNE 16 M Kathy Waters 80 Burnt Hill Road Hebron, CT 06248
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NE 8M Johnathan & Elizabeth Gilman 0 178 Cato Corner Road Colchester,CT 06415 SSE 10 M Laura Parker 5 95 Plains Road Essex,CT 06426 SSE 3.6 M Virginia Marshall 6 Old County Road Haddam, CT NE 17 M Sharon Stewart
East Lyme, CT 06333 S 11.5 M Victor Trudeau 0 174 Horse Hill Road Westbrook,CT 06498 UNABLE TO CONTACTAS OF THIS TIME. ,
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IIaddam Neck St: tion Annual Radiological Environm:ntal Operating Report 1997
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Dairy Goats Within 20 Miles of Connecticut Yankee l December 1997 Direction Distance Name and Address # of Goats 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 12 171 Ferry Lane S. Glastonbury, CT 06073
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NNW l5 M Donald Reid 11 1654 Main Street Glastonbury, CT 06033 i
- UNABLE TO CONTACTAS OF THIS TIME.
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' Hiddim Neck Station Annual Radiological Environmental Operating Report 1997 a
' APPENDIX B P
NORTHEAST UTILITIES QA PROGRAM I
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fladdam Neck Station Annual Radiological Environmental Operating Report 1997 INTRODUCTION Northeast Utilities Service Company (NUSCO), acting as the agent for both the Northeast Nuclear Energy Company (NNECO) and the Connecticut Yankee Atomic Power Company (CYAPCO), maintains a quality assurance (QA) program 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.
NUSCO OA PROGRAM Appraisals are conducted of the primary (Duke *) radioanalysis contractor, of the Production Operations Support Laboratory (POSL), and of the NUSCO 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 NUSCO QA Program quality control samples - spikes and duplicates.
Sample spikes are a check on the accuracy of results of the contractor's radioanalyses. Duplicate
. samples are a check of the contractor's precision or reproducibility of results. The number and type of NUSCO QA Program quality control samples are given in Table 1. The results of the contractor's analyses of NUSCO 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 environment! 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 NUSCO 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.
OTiiER OA PROGRAMS The NUSCO 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 NUSCO 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.
- 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 plant Technica!
- Formerly Yankee Atomic
' Formerly Nonheast Utilities Quality Assessment Services B-2
HIdd:m Neck Station Annual Radiological Environmental Operating Report 1997 Specifications. The Analytics comparison satisfies this requirement and is supplemented by the EPA Intercomparison Studies Program.
- 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 plant 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.
- 4. For REMP TLDs the Nuclear Regulatory Commission-State of Connecticut Independent Verification Program also provides a quality control : check of TLD measurements independent of the NUSCO QA Program.
' RESULTS OF NUSCO OA PROGRAM FOR CONTRACTOR RADIOANALYSES .
The NUSCO QA Program indicated that Duke's environmental radiological analysis program !
- was adequate in 1997. Of 116 analysis results on QA samples,108 passed criteria, a 93% !
success rate.
There were five air particulate gamma analyses which exceeded the criterion of being within 20% of the spiked value - one Mn-54 sample spike at 23%, one Co-60 sample spike at -38%, two I-131 sample spikes at -24% and -33%, and one Ce-144 sample spike at -50%. For the Mn-54 sample spike and the 1-131 sample spike *.vhich failed at -24%, other nuclide spikes in the same filter sample passed criteria and sub.;equent results for Mn-54 and 1-131 passed criteria. The ;
other three failures all occurred in the same filter sample. It was determined that two of the spikes (1-131 and Ce-144) failed due to the age of the source. Corrective actions have been instituted to avoid using sources beyond their expiration date and to provide for a fresh supply of l sources. Cause of the failure of the third spike (Co-60) could not be determined and is presently !
unresolved. However, review of past analyses of Co-60 spiked filters showed no adverse trends.
There was one water gamma analysis which exceeded the criterion of being within 20% of the i spiked value - an 1-131 spiked sample at -25%. Four other nuclide spikes in the same water sample passed criteria and the eleven (11) other I-131 spikes during 1997 passed the criteria.
There was one tritium in water spike which exceeded the criterion of being within 20% of the !
spiked value at -24%. A recount of the sample yielded a satisfactory result of-11% of the spiked value. Seven other tritium spikes in water over a two year period have all satisfied the criterion.
There was one I-131 spike in milk which exceeded the criterion of being within 20% of the spiked value at -67%. The cause of this failure has not yet been resolved. It occurred at a
. relatively low spike level, indicating a possible problem with low level spikes with I-131.
l There were 13 nuclide gamma analyses comparisons among four sets of duplicate oyster samples in 1997. All the duplicate samples results were within the criterion of being within the two sigma error range of the average for the two duplicate samples. This was an improvement over 1996 results when four of 18 gamma analyses results failed the criterion. An increased emphasis on sample mixing may have caused the improvement. '
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l IIaddam N:ck Station Annual Radiological Environmental Operating Report 1997 RESULTS OF NUSCO OA PROGRAM FOR ENVIRONMENTAL TLDS All 12 of the monthly TLD spike tests satisfied procedural criteria. Eight (8) of ten (10) field comparisons satisfied procedural criteria. Two of the field comparison tests could not be completed, once because of a loss of data due_ to a computer problem and once because of a error in processing the TLDs. Two of the completed field comparison tests failed criteria. One failure was due to a delay in reading out the QA TLDs between the preheat treatment and the final readout. To avoid repetition of this failure a note was added to the readout procedure to readout the TLDs immediately after preheat. A second failure of the field comparisons occurred because the same computer problem which caused one test to be missed. The computer problem was reported via the Corrective Action Program at both Millstone and Connecticut Yankee. Corrective actions were taken to restore lost computer files and to avoid a repetition of the failure.
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Iladdam Neck St tion Annual Radiological Environmental Operating Report 1997 l
TABLE 1 NUMBER OF QUALITY CONTROL SAMPLES 1997 an;py :yy. ,1.r m. ... . ..
- : . : 1., . . ~ sm_wp w a,. .. : . ., j
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. ., u . .. ..
TLDs -
Field Comparison 10(2) 500 l
Spike 12 0) 500 l Milk - Strontium 2") 30 Milk - Iodine 6(') 89(7)
Water - Gamma 12 ") 1000)
Water - Tritium 4 20 l
Fish / Invertebrate - Gamma 4 80 Vegetation / Aquatic Flora / Sediment - 0 50 Gamma l Air Particulate -
Gross Beta 6 800 Iodine 4 800 Gamma 4 ") 60 1
FOOTNOTES (1) Approximate total which includes both Millstone and Connecticut Yankee I (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) One milk sample was spiked with both Sr-89 and Sr-90.
(5) Each water and air particulate gamma QC sample includes five nuclides.
(6) Includes gamma in milk analyses. Gamma in water QA spikes are treated as milk surrogates.
(7) Millstone requirement only to analyze for I-131.
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< 1 linddan Neck Station Annual Radiological Environmental Oper ting Report 1997 l 1
TABLE 2 l RESULTS OF QUALITY CONTROL SAMPLE ANALYSES 1997 ny> ~..;n r ,;
. x . a :: ; xn n
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,;;ij.f m.sr o ,t. p:n.~..:;w:m ; :.
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r v.4 m; 0 7 4. ,. $.yj j p:.: dc :w -J..:;. R:,[g.g m y.,. c.. . , ....
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TLDs -
Field Comparison 8 2 l Spike 12 0 l
Milk - Strontium U
- 3) 0 I Milk -Iodine 5 1 Water - Gamma (2) 59 1 Water - Tritium 3 1 j Oysters - Gamma (2) 13 0 l Air Particulate -
Gross Beta 6 0 Iodine 4 0 Gamma A 15 5 TOTALS TLDs: 20 TLDs: 2 Samples: 108 Samples: 8 l FOOTNOTES !
(1) One milk strontium had two associated analyses - Sr-89 and Sr-90. j (2) Each sample has analysis results for 3 to 6 nuclides and each nuclide resu'.t is required to pass criteria. Therefore each sample has 3 to 6 total comparisons passing or failing criteria.
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- lladdam Neck Station Annual Radiological Environmental Operating Report 1997 i
APPENDIX C I
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I
SUMMARY
OF INTE~RLABORATORY l COMPARISONS l
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11 dd m Ncck Stttion Annuil Radiological Environmental Operating Report 1997 i
ANALYTICS INTERCOMPARISON PROGRAM 1996
?!$[} 4;*f #Q?ffl(fyQ,.f:)lQ}yfiffRT[R('}f'}
lst Milk Sr-89 25 pCi/L 24 pCi/L 0.96 Sr-90 19 18 0.95 Cr-51 387 403 1.04 l Mn-54 176 177 1.01 J Co-58 79 80 1.01 Co-60 176 176 1.00 )
Fe-59 144 150 1.04 Zn-65 165 178 1.08 l-131 20 '23 1.15 1-131 (LL) 20 21 1.05 Cs-134 143 143 1.00 Cs-137 114 117 1.03 Ce-141 232 232 1.00 1st Water Beta 144 pCi/L 132 pCi/L 0.92 Cr-51 419 433 1.03 Mn-54 190 193 1.02 Co-58 86 84 0.98 Co-60 190 190 1.00 Fe-59 155 160 1.03 Zn-65 179 185 1.03 1-131 25~ 26 1.04 Cs-134 155 151 0.97 Cs-137 123 124 1.01 Ce-141 251 249 1.01 Ra-226 53 52 0.98 Ra-228 59 60 1.02 2nd Air Filter Beta 135 pCi/ filter 127 pCi/ filter 0.94 Sr-89 94 100 1.06 Sr-90 92 84 0.91 Cr-51 213 208 0.98 Mn-54 91 98 1.08 Co-SP 83 81 0.98 Co-60 121 108 0.89 Fe-59 81 '88 1.09 Zn-65 151 176 1.17 Cs-134 88 84 0.95
- Cs-137 124 137 1.10 Cc-141 142 134 0.94 2nd Water 11-3 1313 pCi/L i197 pCi/L 0.91 l
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-.' ll:ddan Nrck Station Annuil Radiological Environmental Oper.-ting Report 1997 ANALYTICS INTERCOMPARISON PROGRAM 1997
'ill:. l.(?'. l)[,l: -l,;I ,' R[]&{} }'{;flK.)tgQl}}'fl%f 2nd Milk Cr-51 319 pCi/L 325 pCi/L 1.02 Mn-54 137 144 1.05 Co-58 124 127 1.02 Co-60 168 168 1.00 Fe-59 122 130 1.07 ' Zn-65 225 245 1.09 I-131 61 57 0.93 I Cs-134 131 129 0.98 Cs-137 185 200 1.08 i Ce-141 213 214 1.00 3rd Milk Sr-89 15 pCi/L 15 pCi/L 1.00 Sr-90 14 15 1.07 Cr-51 304 313 1.03 Mn-54 88 93 1.06 Co-58 60 64 1.07 Co-60 197 201 1.02 Fe-59 119 126 1.06 Zn-65 196 204 1.04 1-131 87 97 1.11 Cs-134 102 104 1.02 Cs-137 107 110 1.03 Ce-141 77 78 1.01 3rd Water Sr-89 15 pCi/L 17 pCi/L 1.13 Sr-90 15 14 0.93 Beta 291 298 1.02 Cr-51 239 240 1.00 Mn-54 69 72 1.04 Co-58 47 49 1.04 Co- 60 155 155 1.00 Fe-59 94 99 1.05 Zn-65 154 157 1.02 i I-131 94 99 1.05 Cs-134 80 80 1.00 Cs-137 84 84 1.00 Ce-141 60 66 1.10 i \ C-3 L
l
.: llidd:m Neck Station Annual Radiological Environmental Operating Report 1997 ANAINTICS INTERCOMPARISON PROGRAM 1997 hdNYh5[L i:T[ %'L;-[}(($b [ (fAkbbS i 4th Milk Cr-51 195 pCi/L 205 pCi/L 1.05 Mn-54 80 83 1.04 Co-58 52 56 1.08 Co-60 94 96 1.02 i Fe-59 57 62 1.09 l Zn-65 141 144 1.02 1-131 39 42 1.08 1-131 (LL) 39 38 0.97 Cs-134 100 102 1.02 Cs-137 103 109 1.06 Ce-141 98 103 1.05
)
. 4th Air Filter Beta 238 pCi/61ter 245 pCi/61ter 1.03 Sr-89 182 167 0.92 Sr-90 110 101 0.92 !
4th Water H-3 1076 pCi/L 1017 pCi/L 0.95 l r C-4 t.
Iladdrm Neck Station Annual Radiological Environmental Oper: ting Rrport 1997 U.S. EPA INTERLABORATORY COMPARISON STUDIES PROGRAM 1997
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1/17/97 Water Sr-89 12.0 i 2.9 11.5 1.8 Sr-90 25.0 2.9 22.8
- 0.9 3/7/97 Water 11-3 7611
- 460 7611 750 4/15/97 Water Sr-89 24.1 2.9 24.1
- 2.0 Sr-90 13.0
- 2.9 11.0
- 0.3 Co-60 21.0
- 2.9 21.1 0.S Cs-134 31.0
- 2.9 30.0
- 0.6 Cs-137 22.0 2.9 21.2
- 0.1 Ra-226 13.0
- 1.2 13.9*0.3 Ra-228 3.1
- 0.5 4.8
- 1.3 6/6/97 Water Co-60 18.0 i 2.9 18.0
- 0.5 6/13/97 (Ra) Zn-65 100.0 5.8 98.6
- 2.1 Cs-134 22.0
- 2.9 20.4 i 1.8 Cs-137 49.0
- 2.9 48.8 0.5 Ba-133 25.0 2.9 21.5
- 0.4 Ra-226 3.0*0.3 3.4
- 0.2 Ra-228 3.1*0.5 4.6 1.0 1 7/11/97 Water Sr-89 44.0
- 2.9 42.8
- 0.4 Sr-90 16.0
- 2.9 I4.8
- 0.4 7/18/97 Water Beta 15.1*2.9 15.2
- 0.8 8/8/97 Water II-3 11010
- 640 9290
- 470 i
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1 e o- H;dd:m Neck Station Annual Radiological Environmental Operating Report 1997 r, U.S. EPA INTERLABORATORY COMPARISON STUDIES PROGRAM 1997 M IIIZIE5fflif M filisTSPR?ifi E R EdiskTTs W M 10/21/97 Water Sr-89 36.0 2.9 36.7 2.8 i Sr-90 22.0 2.9 20.7 0.9 Co-60 10.0 2.9 9.0 0.2 Cs-134 41.0 2.9 39.6 1.0 Cs-137 34.022.9 33.6 0.8 Ra-226 5.0
- 0.5 5.5
- 0.3 Ra-228 5.0
- 0.8 4.8 1.1 10/31/97 Water Beta 48.9 2.9 47.0 1.6 ,
I I i1/7/97 Water Co-60 27.0
- 2.9 27.7
- 0.2 Zn-65 75.0
- 4.6 75.4
- 1.6 Cs-134 10.0
- 2.9 10.4 0.7 Cs-137 74.0
- 2.9 77.1 i 1.3 I Ba-133 99.0
- 5.8 97.6 2.2 l l
FOOTNOTES Units are pCi/ liter for water and milk. Air particulate filters are in units of total pCi. (a) EP known value normalized standard deviation. Normalized standard deviation is derived by dividing EPA's expected precision by the square root of the number of I analyses to be performed, which is 3. (b) Average of three analyses
- one standard deviation of the three analytical results. If the average value is not within the EPA known value
- three times the normalized standard deviation it is outside of EPA control limits.
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